ML25112A188

Nuclear Generating Station, Annual Radiological Environmental Operating Report for 2024

ML25112A188
Person / Time
Site:	Oyster Creek
Issue date:	04/22/2025
From:	Noval W Holtec Decommissioning International
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
HDI-OC-25-014
Download: ML25112A188 (1)

Text

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 HDI-OC-25-014 10 CFR 50 Appendix I April 22, 2025 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 Radiological Environmental Operating Report for 2024 Enclosed with this cover letter is the Annual Radiological Environmental Operating Report for the calendar year 2024 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, William Noval Director of Regulatory Affairs Holtec Decommissioning International, LLC

Enclosure:

1) 2024 Annual Radiological Environmental Operating Report for 2024 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 Digitally signed by William Noval DN: cn=William Noval, o=HDI, ou=Regulatory Affairs, email=w.noval@holtec.com Date: 2025.04.22 08:33:07 -04'00' William Noval

Docket No:

50-219 OYSTER CREEK GENERATING STATION UNIT 1 Annual Radiological Environmental Operating Report 1 January through 31 December 2024 to HDI-OC-25-014 Prepared By Teledyne Brown Engineering Environmental Services Oyster Creek Generating Station Forked River, NJ 08731 March 2024

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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............................................................................................. 22 IV. Program Description.................................................................................................... 23 A. Aquatic Environment......................................................................................... 23 B. Atmospheric Environment................................................................................. 26 C. Ambient Gamma Radiation............................................................................... 25 D. 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, 2024 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, 2024 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Oyster Creek Generating Station, 2024 Figures Figure B-1 Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station, 2024 Figure B-2 Locations of REMP Stations within a 1 to 5-mile radius of the Oyster Creek Generating Station, 2024 Figure B-3 Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station, 2024 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, 2024 Table C-I.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-II.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-II.2 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-II.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-III.1 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024

iii Table C-III.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-IV.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-IV.2 Concentrations of Gamma Emitters in Clam and Crab Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 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, 2024 Table C-VI.3 Concentrations of Strontium in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-VI.4 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-VII.1 Concentrations of Strontium and Gamma Emitters in Vegetation Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table C-VIII.1 Quarterly OSLD Results for Oyster Creek Generating Station, 2024 Table C-VIII.2 Mean Quarterly OSLD Results for the Site Boundary, Intermediate, Special Interest, and Control Locations for Oyster Creek Generating Station, 2024 Table C-VIII.3 Summary of the Ambient Dosimetry Program for Oyster Creek Generating Station, 2024 Figures Figure C-1 Mean Cobalt-60 Concentration in Clams Oyster Creek Generating Station, 1983 - 2024 Figure C-2 Mean Cobalt-60 Concentration in Aquatic Sediment Oyster Creek Generating Station, 1984 - 2024 Figure C-3 Mean Cesium-137 Concentration in Aquatic Sediment Oyster Creek Generating Station, 1984 - 2024 Figure C-4 Mean Weekly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station, 2008 - 2024 Figure C-5 Mean Monthly Gross Beta Concentrations in Air Particulates Oyster Creek Generating Station, 1984 - 2024 Figure C-6 Mean Quarterly OSLD Gamma Dose Oyster Creek Generating Station, 2024

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, 2024 Table D-I.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table D-II.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table D-II.2 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table D-II.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table D-III.1 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table D-III.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table D-IV.1 Concentrations of Gamma Emitters in Clam Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Table D-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Oyster Creek Generating Station, 2024 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2024 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2024 Table E-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2024 Table E-4 DOEs Mixed Analyte Performance Evaluation Program (MAPEP),

ATI Environmental, Inc. Midwest Laboratory, 2024 Table E-5 Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) RAD Study, ATI Environmental, Inc.

Midwest Laboratory, 2024 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.

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

4 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 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

5 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 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

6 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 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

7 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.

Radiation Risk

8 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 to radioactivity, 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.

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 2024 through 31 December 2024. During that time period, a total of 579 analyses were performed on 429 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 2024.

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, 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-90 analysis was performed on quarterly composites of air particulate samples and all results were below the Minimum Detection Concentration (MDC).

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 11

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).

As part of the Radioactive Environmental Monitoring Program (REMP),

measurements of direct radiation around the plant are made and analyzed quarterly.

The dosimeter readings were used to calculate dose to a member of the public from direct radiation from the plant. In order to distinguish between radiation from the plant and radiation from background sources, control station (not affected by the plant) readings were subtracted from the dosimeter station (indicator) readings near the plant to get a net dosimeter result. This was then used for dose calculation of direct radiation from the plant. In 2024 the method used to analyze environmental dosimeter results was changed to comply with ANSI N13.37, and net dose was no longer calculated. Each station is compared to a baseline reading for that station.

The baseline is a five-year average dose. To determine if the plant is contributing direct radiation to member(s) of the public, the quarterly dosimeter readings are compared to the baseline reading for each station. If the reading is within a limit, then there is no direct dose detected (ND). For 2024, all REMP dosimeter results were ND, but individual readings are used to assign dose to a member of the public, and these doses are no longer a net value so there is an apparent step change in dose. The doses measured are similar to the results from recent years, but the current methodology does not compare with previous methodology and results in this apparent change.

12

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 Microbac Laboratories Inc. on samples collected during the period 01 January 2024 through 31 December 2024.

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 until the plant has completed decommissioning and the license is terminated.

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 2024. 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 six locations (C, 20, 66, 71, 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 bi-weekly and sent to the laboratory for analysis.

Terrestrial Environment Revision 13 to the Offsite Dose Calculation Manual (ODCM) released in December 2022 removed vegetable samples from the program. These samples are of primary use to monitor radioactive I-131 uptake from plant releases. This radioisotope has a short half-life of 8.3 days and has decayed away completely. Therefore, the analysis of vegetables has no value in monitoring for this uptake any longer.

17 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 20 locations (1, T1, 51, 52, 53, 54, 55, 55A, 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 Microbac Laboratories Inc. to analyze the environmental samples for radioactivity for the OCGS REMP in 2024. The analytical procedures used by the laboratories are listed in Table B-3.

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

18

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

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

4. Concentrations of strontium in air particulates C. Data Interpretation For trending purposes, the radiological and direct radiation data collected during 2024 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.

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 - five nuclides:

Mn-54, Co-60, Zn-65, 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.

19 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.

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 2024, the OCGS REMP had a sample recovery rate in excess of 97.1%.

Exceptions are listed below:

Environmental Dosimetry

1. 07/09/24: All Dosimeters-It has been identified by Pilgrim (PIL-07620) and Indian Point (IP2-01132) that their evaluation of REMP dosimetry may not be aligned with the latest regulatory guidance (ANSI N13.37).

After reviewing this new guidance, the calculation method was changed to align with ANSI N13.37. These changes will not require additional dosimetry in the field or change in dosimetry type, but pertain to how doses are calculated, how extraneous dose is assigned, and account for any other administrative changes. All data for 2024 is compliant. (OYS-03984).

2. 12/03/24: All Dosimeters-ANSI/HPS N13.37-2014 (R2019) required dosimeters used for direct radiation monitoring to be stored in a shielded storage vault when they are not deployed in the field, including control dosimeters. Section 7.2.1 provides requirements for the shielding to be at least 10 cm of lead or 16 cm of steel, The current shielded storage box does not meet this requirement. The site has an abandoned shield cave for gamma spectrometer detectors for a possible solution but would require significant lifting and rigging support to adequately cover the cave floor with lead bricks. Unresolved at this time. (OYS-04197)

Air

1. 01/03/24: Station 72 - The station was removed from the ODCM in 2023, but the box which contained the sample pump was still in the fields and needs to be recovered for use as a possible spare. Equipment was recovered for reuse. (OYS-03679)

2. 01/23/24: Station 73 - During routine air particulate sampling, the sample pump was found to not be running. Pump run time was <90

20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> which may have affected sample recovery and the sample result for Gross Beta was not detected. This sample has been marked as a missed sample. The pump was restarted with the assistance form station electricians. (OYS-03850).

3. 03/19/24: Station 73 - The pump was not running when samples were collected on 03/19/24 at 09:47. The GFCI was tripped. The timer reading indicated ~133 hours of sample collection compared to the ~359 hours for the other stations collected. Gross Beta was not detected due to insufficient sample volume. Once the GFCI was reset, the pump started again. This IR was initiated while reviewing this stations sample recovery. (OYS-03814)

4. 04/01/24: Station 73 - The pump was found not running when sample collection was performed. The GCFI was tripped. This pump was found tripped during previous sample collection (03/19/24). There was insufficient material on the filter for sample analysis. This sample has been documented as a missed sample. After changing the sample head, the GFCI was reset with an acceptable vacuum. (OYS-03832)

5. 04/11/24: Station 73 - The sample pump was not running, and pump run time was <90 hours which may affect sample recovery. The pump was restarted with the assistance from station electricians. Location found to have a negative trend regarding sample collection performance. In 2024, three IRs (OYS-03850 01/9-01/23, OYS-03814 03/05-03/19, and OYS-0382 03/19-04/01) have been initiated when the stations sample pump was not operation at the time of collection. Sample station was refurbished and the power feed from the pole was updated. New electrical outlets (GFCI) were installed inside the box. The box was refitted with new stainless-steel hinges and clasps and repainted. The air inlet for cooling were covered with fine mesh screen inside to prevent insects and debris from entering. (OYS-03851)

6. 06/20/24: Station 73 - The station has had several IRs initiated for missed samples due to pump trips. The condition of the sample box and electrical supply to this station as degraded. The work required for repairs required the station to be removed from service. The sample station was taken out of service 06/19/24 at 08:06 and was restored to service 06/20/24 at 08:20. The typical sample period is ~336 hours (two weeks) and the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> missed will not compromise the sample as there will be sufficient run time to collect sample and meet required limit of detection for sample analysis. (OYS-03956)

7. 07/09/24: Station 71 - After the sample collection on 7/9, it was observed during sample calculation, the station ran ~9 hours less than all the other stations. As the sample period is ~336 hours, this does not impact the sample, and the filter will be sent for analysis. It is possible that there was a brief power outage due to a storm during the sample period. IR initiated for trending of issue. (OYS-03983)

21

8. 09/03/24: Station 71 - During sample collection, the sample pump at the station (AP002) had a low vacuum. Filter loading indicated that adequate sample was collected. The sample result for Gross Beta was normal (positive). A spare pump was put in service (AP006) and the vacuum read 17 Hg (>15 is SAT). (OYS-04065)

9. 06/05/24: Station 66 - The sample pump was found not running when sample collection was performed. Calibration of the flow orifice had been performed during the previous collection period and the switch was inadvertently left off. The timer reading was the same as the previous reading, indicating no sample was collected during this period. The pump restarted once the switch was turned on. (OYS-03965)

10. 08/06/24: Station 66 - During sample collection, it was observed that the sample inlet tubing was bent, creating a flow restriction. While the pump ran for the entire period, the filter was lighter in color than normal. Due to the sample results for Gross Beta coming back as Undetected, this has been counted as a missed sample. (OYS-04027)

11. 11/26/24: Station 66 - During sample collection, the sample volume was calculated to be 76.4 m3, ~23% of the expected volume. The sample pump was running. Per CY-OC-200-101, Collection of Air Particulate Samples, any sample with <100 m3 in the collection period, is not a valid sample. A possible power interruption at the station could have disrupted the sampling. This sample has been marked as a missed sample. (OYS-04190)

12. 02/20/24: Station 20 - The vacuum reading was 14 Hg when the sample was collected. Sample result for Gross Beta was normal (positive). Procedure requires action when the vacuum reading is <15 Hg. A replacement pump was installed and was left with the vacuum reading 17 Hg. (OYS-03775)

13. 10/01/24: Station 20 - During sample collection, the pump was found running quietly and with a 0 vacuum (minimum 15 vacuum required).

The filter was clean, indicating the pump failed early in the sample period (2 weeks). The filter was changed, and the pump was replaced with a spare (AP 002). This was marked as a missed sample. (OYS-04101)

14. 10/15/24: Station 111 - Sample pump AP005 measured vacuum at <15 Hg. Sample loading on filter appeared adequate. Sample result for Gross Beta was normal (positive). Pump was replaced with AP008 and was left with vacuum reading at 20.5 Hg. (OYS-04128)

15. 10/29/24: Stations 111 and 20 - While performing sample collection, the gate to the farm property was found locked with a new lock that was not interlocked with the NJDEP or Security lock. This did not allow for the gate to be opened to perform required sampling. The samples were collected after the lock was cut. There were no missed samples, and no further actions required. IR was initiated for trending. (OYS-04151)

22 Groundwater

1. 10/28/24: Station 3C - While performing sampling, the contract technician reported that Well 3C was not able to be secured because the lid was damaged. The sample was collected as scheduled. There was no effect to the program and a new cover was installed, so the well is secured. (OYS-04146)

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.

2024: Station 1S was not operational for the entire year.

04/23/24: Station 1N -The well was out of service and was not able to be sampled during the April surface/drinking water sample collection. The connection to the Lacey Municipal water system for potable water has ben completed and this well has been removed from the ODCM as a drinking water sample. This sample was a designated QC sample and because the crossover to the municipal water supply occurred before the drinking water collection, there was no QC sample collected for April. Stations 37 and 38 will be used for QC samples going forward. (OYS-03875) 05/21/24: DW QC -The QC sample of drinking water was collected on 5/21/24 was shipped to the lab on the same day. The lab did not receive the sample and reports no data for that month. No sample was returned by the shipping vendor. The sample was lost in shipping. (OYS-04377)

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 Revision 14 of the Offsite Dose Calculation Manual (ODCM) was issued in May of 2024. The Direct Radiation Monitoring Station 55 was removed from the program and replaced by Station 55A. Well 1N was removed from the program as it is no longer a drinking water well. Site drinking water is now supplied from municipal water.

23 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 2024 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

24

(> 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 2024 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 15 of 27 samples and is attributed to natural sources and fallout residual from previous bomb testing. The values ranged from 1.8 to 3.8 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, striped bass, white perch, smooth dogfish) were collected at two locations (33 and 93) semiannually when available. These locations could be affected by Oyster Creeks effluent releases. The following analysis was performed:

Gamma Spectrometry The edible portions of fish samples from two locations were analyzed for gamma emitting nuclides. Naturally occurring K-40 was detected in 11 of

25 11 samples and ranged from 1,802 to 4,608 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 one location (33) 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 1,337 to 2,514 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 met the required Lower Limit of Detection (LLD) and were less than the Minimum Detectable Concentration (MDC).

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 a concentration of 2,490 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 8 samples ranged from 1,586 to 16,040 pCi/kg dry. Naturally occurring Th-228 was found at all 4 stations and ranged from 153 to 730 pCi/kg wet.

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

The Figure C-3, Appendix C graph shows Cs-137 concentrations in sediment from 1984 through 2024 and Figure C-2, Appendix C graph shows Co-60 concentrations in sediment from 1984 through 2024.

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 1.000E+03 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 2024 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 2024 and no adverse long-term trends are shown in the aquatic monitoring data.

B. Atmospheric Environment Airborne (Air Particulates)

Continuous air particulate samples were collected from six locations on a bi-weekly basis. The six 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 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 7E-03 to 22E-03 pCi/m3 with a mean of 14E-03 pCi/m3. The results from the Intermediate Distance locations (Group II) ranged from 7E-03 to 24E-03 pCi/m3 with a mean of 14E-03 pCi/m3. The results from the Distant locations (Group III) ranged from 9E-03 to 25E-03 pCi/m3 with a mean of 15E-03 pCi/m3. (Table C-VI.1 and C-VI.2, Appendix C)

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

26

27 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 2024 gross beta activity values ranged from <3E-03 to 29E-03 pCi/m3. The 2024 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 24 of 24 samples. The values ranged from 31E-03 to 87E-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.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured using Optically Stimulated Luminescence Dosimeters (OSLD). Forty-five 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. Ambient gamma radiation measurements for 2024 were consistent with data from previous years, however the analysis methodology for these data was changed to align with ANSI N13.37 in 2024.

This analysis method compares each site reading with a 5-year baseline reading from the same site. The baseline data were taken from 2012-2016, the first five years that the program used OSLDs to measure direct radiation, and the measurements for 2024 indicates that there were no readings greater than the baseline. In previous years, the reading for each location was reported as a net dose, with the Control location dose subtracted from the Indicator station.

This difference in reporting creates an apparent shift in dose, when it is due to analysis and the doses are still similar to previous years.

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 2024 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.

28 D. Summary of Results - Inter-laboratory Comparison Program The Teledyne Brown Engineering Environmental Services (TBE-ES) laboratory analyzed Performance Evaluation (PE) samples of air particulate (AP), milk, soil, vegetation, and water matrices that represent test and matrix combinations available for REMP programs. The PE samples supplied by Eckert & Ziegler (E&Z) 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. E&Z Analytics Evaluation Criteria Analytics evaluation report provides a ratio of TBEs result and E&Z Analytics known value. Since flag values are not assigned by E&Z Analytics, TBE evaluates the reported ratios based on internal QC requirements based on the DOE MAPEP criteria.

1. A = Acceptable - reported result falls within ratio limits of 0.80-1.20

2. W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30

3. N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 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 US EPA, National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT) program requirements or ERAs 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.

1. A = Acceptable - Reported value falls within the Acceptance Limits

2. N = Not Acceptable - Reported value falls outside of the Acceptance Limits C. DOE Evaluation Criteria MAPEPs evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

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

2. Acceptable with Warning (flag = W) - result falls in the +/- 20% to +/- 30% of the reference value

3. Not Acceptable (flag = N) - bias is greater than 30% of the reference value

29 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 always resemble typical environmental samples obtained at commercial nuclear power facilities.

The Inter-Laboratory Comparison Program provides evidence of in control counting systems and methods, and that the laboratories are producing accurate and reliable data. For the TBE laboratory, 152 out of 167 analyses performed met the specified acceptance criteria. Fifteen analyses did not meet the specified acceptance criteria and were addressed through the TBE Corrective Action Program. A summary is found below:

A. NCR 24-02: ERA March MRAD-40 study with Air Particulate AM-241 evaluated as Not Acceptable. TBE reported 38.8 pCi/filter and the known value returned at 55.0 pCi/filter (range 39.3-73.3). The root cause investigation determined that the sample was not logged into the system correctly and therefore not prepared with the required tracer. To correct and prevent recurrence, personnel involved are to utilize a template to ensure all analyses are logged as required and the QA Manager will perform sample log review as a back up to ensure accuracy. Acceptable results returned in a later sample study, supporting effectiveness of corrective action.

B. NCR 24-03: ERA March MRAD-40 air particulate study GR-B evaluated as Not Acceptable. TBE reported 42.1 pCi/filter and the known value returned at 22.2 pCi/filter (range 13.5-33.5). The root cause investigation determined that alpha-to-beta crosstalk was more significant than normal which caused the beta activity to report falsely high data. To correct and prevent recurrence, personnel involved are to adjust the alpha-to-beta crosstalk via correction calculation measures when high alpha activities are observed. Acceptable results returned in a later sample study, supporting effectiveness of corrective action.

C. NCR 24-05: ERA April RAD-137 water study GR-A evaluated as Not Acceptable. TBE reported 35.2 pCi/L and the known value returned at 52.6 pCi/L (range 39.6-65.6). The root cause investigation determined that the provided samples contained a solids content that was significantly higher than the typical client samples tested by the laboratory. A set aliquot volume for prior ERA samples was used and not adjusted to account for the sudden increase in solid content. To correct and prevent recurrence, new sample types were ordered from ERA that used Am-241 to better reflect client sample testing and acceptable results were achieved. Acceptable results returned in a later sample study, supporting effectiveness of corrective action.

D. NCR 24-06: E&Z Analytics March E14092 air particulate study Co-60 evaluated as Not Acceptable. TBE reported 168 pCi and the known value returned at 126 pCi. Additionally, March E14093 soil Ce-141 evaluated as Not Acceptable. TBE reported 0.106pCi/g and the known value returned at 0.071pCi/g. The root cause investigation was unable to determine any anomaly

30 thus no proposed corrective action. No recurrence has occurred.

E. CAR 24-02 (CAR 23-31): MAPEP February 24-MaS50 soil study Fe-55 evaluated as Not Acceptable. TBE reported 297 Bg/Kg and the known value returned at 650 Bg/Kb (range 455-845). The root cause investigation suspects that the current analytical procedure is not sufficient to add the interferences added to the sample by MAPEP. This investigation is still ongoing (See NCR 24-16) as the suggested corrective action did not provide desired results.

F. NCR 24-08: MAPEP February 24-MaS50 soil study Ni-63 evaluated as Not Acceptable. TBE reported 1070 Bg/Kg and the known value returned at 1530 Bg/Kb (range 1071-1989). The root cause investigation suspected that the sample contained added interferences that are not typically seen in client samples. All QC efforts associated with the sample were acceptable and no anomalies found, even after reanalysis. To correct and prevent recurrence, samples suspected of additional interferences will include the addition of Ni-59 tracer to determine yield results when calculating results. TBE analytical procedure TBE-2013 was updated to include this change.

G. NCR 24-09: MAPEP February 24-MaSU50 urine study Zn-65 evaluated as Not Acceptable. The root cause investigation determined that the sample was spiked lower than TBEs typical detection limit and client requirements. The report was revised by MAPEP indicating Not Evaluated, resulting in this nuclide to not be considered a failure.

H. NCR 24-10: MAPEP February 24-MaW50 water study Tc-99 evaluated as Not Acceptable. TBE reported 9.95Bg/L and the known value returned 7.47Bg/L (range 5.23-9.71). The root cause investigation suspects Thorium interference that was not removed during the column separation process of the analytical procedure; however, it cannot be confirmed as all QC efforts associated with the sample were acceptable and with no anomalies found. To potentially correct and prevent recurrence, an additional rinse step was added to the procedure. Acceptable results returned in a later sample study, supporting effectiveness of corrective action.

I. NCR 24-11: MAPEP February 24-RdV50 vegetation study Sr-90 evaluated as Not Acceptable. TBE reported 0.276Bg/sample and the known value returned 0.529Bg/sample (range 0.370-0.688). The root cause investigation determined a laboratory accident resulting in a spilled (loss) of sample. No corrective action was performed as the cause was an unintentional sample spill.

J. NCR 24-14: ERA September MRAD-41 air particulate study U-234/238 evaluated as Not Acceptable. TBE reported 14.0/14.2 pCi/filter and the known value returned at 31.1/30.9 pCi/filter (range 23.1-36.9). The root cause investigation determined that the laboratory technician placed double the amount of tracer in the sample by error. To correct and prevent recurrence, samples that have been digested/leached with carrier/tracer added will have a label placed over the cap indicating it has already been added. Additionally, the

31 beaker that aliquot is put in should have markings to indicate carrier/tracer has already been added to the sample.

K. NCR 24-15: ERA September MRAD-41 water study Fe-55 evaluated as Not Acceptable. TBE reported 615 pCi/L and the known value returned at 1230 pCi/L (range 723-1790). The root cause is still under investigation.

L. NCR 24-16: MAPEP August 24-MaS50 soil study Fe-55 evaluated as Not Acceptable. TBE did not report a value and the known value returned 780Bg/Kg (range 546-1014). The root cause is still under investigation.

M. NCR 24-17: MAPEP August 24-RdV51 vegetation study Sr-90 evaluated as Not Acceptable. TBE reported 0.95Bg/sample and the known value returned 2.39Bg/sample (range 1.67-3.11). The root cause is still under investigation.

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 2024.

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

NAME OF FACILITY: OYSTER CREEK GENERATING STATION DOCKET NUMBER:

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

2024 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M)

MEAN (M)

MEAN (M)

STATION #

NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD)

RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER H-3 30 2000

<LLD

<LLD 0

(PCI/LITER)

GAMMA 30 MN-54 15

<LLD

<LLD 0

CO-60 15

<LLD

<LLD 0

ZN-65 30

<LLD

<LLD 0

CS-134 15

<LLD

<LLD 0

CS-137 18

<LLD

<LLD 0

DRINKING WATER H-3 27 2000

<LLD

<LLD 0

(PCI/LITER)

GR-B 27 4

2.5 2.1 2.6 38 INDICATOR 0

(8/15)

(5/12)

(7/12)

RT 532 - OCEAN TOWNSHIP MUA PUMPING (1.8/3.8)

(1.7/2.4)

(1.8/3.8) 1.6 MILES SSW OF SITE GAMMA 27 MN-54 15

<LLD

<LLD 0

CO-60 15

<LLD

<LLD 0

ZN-65 30

<LLD

<LLD 0

CS-134 15

<LLD

<LLD 0

CS-137 18

<LLD

<LLD 0

GROUNDWATER H-3 8

2000

<LLD NA 0

(PCI/LITER)

GAMMA 8

MN-54 15

<LLD NA 0

CO-60 15

<LLD NA 0

ZN-65 30

<LLD NA 0

CS-134 15

<LLD NA 0

CS-137 18

<LLD NA 0

FISH (PREDATOR)

GAMMA 11 (PCI/KG WET)

K-40 NA 3257 NA 3368 33 INDICATOR 0

(11/11)

(6/6)

EAST OF RT 9 BRIDGE IN OCGS DISCHARGE (1802/4608)

(1854/4608) 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

CLAMS GAMMA 7

(PCI/KG WET)

K-40 NA 1708 1975.3 2115 94 CONTROL 0

(4/4)

(3/3)

(2/2)

GREAT BAY/LITTLE EGG HARBOR (1337/2085)

(1696/2514)

(1716/2514) 20.0 MILES SSW 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

LOCATION WITH HIGHEST ANNUAL MEAN (M)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2024 (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:

2024 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M)

MEAN (M)

MEAN (M)

STATION #

NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD)

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE OYSTER CREEK GENERATING STATION, 2024 CRABS GAMMA 2

(PCI/KG WET)

K-40 NA 2312.5 NA 2490 33 INDICATOR 0

(2/2)

(1/1)

EAST OF RT 9 BRIDGE IN OCGS DISCHARGE (2135/2490) 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 3965 11512 15430 94 CONTROL 0

(6/6)

(4/4)

(2/2)

GREAT BAY/LITTLE EGG HARBOR (1586/11910)

(1469/16040)

(14820/16040) 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 1166 1713 1784 QCA CONTROL 0

(3/6)

(2/4)

(1/2)

QC DUPLICATE SAMPLE (610/1584)

(1641/1784)

Th-228 NA 314 534 637 QCA CONTROL (6/6)

(3/4)

(1/2)

QC DUPLICATE SAMPLE 0

(153/730)

(427/637)

AIR PARTICULATE GR-B 158 10 14 15 15 C CONTROL 0

(E-3 PCI/CU.METER)

(127/131)

(27/27)

(27/27)

JCP&L OFFICE - COOKSTOWN NJ (7/24)

(9/25)

(9/25) 24.7 MILES NW OF SITE SR-90 24 10

<LLD

<LLD 0

GAMMA 24 BE-7 NA 47.3 53.2 57.7 20 INDICATOR 0

(20/20)

(4/4)

(4/4)

FINNINGER FARM ON SOUTH SIDE ACCESS ROAD (29.4/86.6)

(37.2/73.6)

(40.6/86.6) 0.7 MILES E 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

DIRECT RADIATION OSLD-QUARTERLY 176 NA 8

7.3 12.5 55 INDICATOR 0

(MILLIREM/STD.MO.)

(172/172)

(4/4)

(4/4)

SOUTHERN AREA STORES SECURITY FENCE (2.7/15.4)

(4.8/8.7)

(9/15.4) 0.3 MILES W (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

A-2

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 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

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 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 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 B-2

Sample Medium Station Code Distance (miles)

Azimuth (degrees)

Description 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 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 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 SSE of site, OCGS Discharge Canal between Pump Discharges and Route 9, Forked River, NJ 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 B-3

Sample Medium Station Code Distance (miles)

Azimuth (degrees)

Description 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 former vegetation Station 35, Lacey Township, NJ B-4

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-200-103, REMP sample collection procedure - well water 1 gallon TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Microbac, 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 Microbac, 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 CY-OC-200-103, Collection of water samples for radiological analysis 1 gallon TBE, TBE-2007 Gamma-Emitting Radioisotopes Analysis Microbac, GS-01 Determination of gamma emitters by gamma spectroscopy Surface Water Tritium Grab Sample CY-OC-200-103, Collection of water samples for radiological analysis 1 gallon TBE, TBE-2011 Tritium in Drinking Water by Liquid Scintillation Microbac., 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 Microbac, 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 B-5

Sample Medium Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number 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 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 Microbac, 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 CY-OC-200-101, Collection of 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 CY-OC-200-101, Collection of Air Particulate samples for radiological analysis 13 filters (approximately 4000 cubic meters)

TBE, TBE-2018 Radiostrontium Analysis by Chemical Separation OSLD Optically Stimulated Luminescence Dosimetry Quarterly OSLDs comprised of two Al2O3:C Landauer Incorporated elements.

CY-OC-200-102, Posting and Retrieval of REMP TLDs for Radiological Analysis 2 dosimeters Landauer Incorporated B-6

B-7

B-8

B-9

Intentionally left blank

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank

Table C-I.1 COLLECTION PERIOD 23 24 33 94 1/17/2024

< 197

< 194 2/12/2024

< 191

< 193 3/20/2024

< 501

< 517 4/23/2024

< 503

< 528 5/21/2024

< 483

< 495 6/3/2024

< 530

< 521

< 187

< 194 7/16/2024

< 574

< 575 8/13/2024

< 602

< 603 9/3/2024

< 186

< 195

< 301 10/22/2024

< 568

< 582

< 596 11/19/2024

< 572

< 574 12/17/2024

< 482

< 487 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 C-1

Table C-I.2 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 23 06/03/24

< 6

< 6

< 14

< 7

< 6 10/22/24

< 5

< 6

< 12

< 6

< 5 MEAN 24 06/03/24

< 4

< 5

< 12

< 7

< 6 09/30/24

< 2

< 2

< 4

< 2

< 2 MEAN 33 01/17/24

< 5

< 5

< 11

< 5

< 5 02/12/24

< 8

< 8

< 15

< 8

< 8 03/20/24

< 7

< 7

< 13

< 8

< 5 04/23/24

< 5

< 5

< 11

< 5

< 5 05/21/24

< 5

< 7

< 11

< 7

< 6 06/18/24

< 6

< 7

< 14

< 7

< 6 07/16/24

< 9

< 4

< 15

< 9

< 8 08/13/24

< 7

< 9

< 15

< 8

< 10 09/10/24

< 7

< 8

< 15

< 8

< 6 10/22/24

< 8

< 13

< 24

< 9

< 11 11/19/24

< 6

< 5

< 14

< 9

< 7 12/17/24

< 7

< 10

< 15

< 9

< 7 MEAN 94 01/17/24

< 5

< 5

< 10

< 5

< 5 02/12/24

< 6

< 9

< 19

< 7

< 7 03/20/24

< 7

< 8

< 15

< 6

< 7 04/23/24

< 4

< 4

< 7

< 4

< 4 05/21/24

< 6

< 6

< 13

< 7

< 7 06/18/24

< 4

< 6

< 9

< 7

< 7 07/16/24

< 5

< 6

< 12

< 6

< 7 08/13/24

< 7

< 7

< 13

< 8

< 8 09/10/24

< 5

< 6

< 12

< 6

< 5 10/22/24

< 7

< 7

< 17

< 7

< 8 11/19/24

< 8

< 10

< 17

< 8

< 9 12/17/24

< 6

< 6

< 12

< 5

< 5 MEAN RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 C-2

Table C-II.1 COLLECTION PERIOD 1N 1S 37 38 01/17/24

< 444 (1) 02/12/24

< 188 (1) 03/19/24

< 509 (1) 04/23/24 (1)

(1) 05/21/24 (1)

(1) 06/18/24 (1)

(1) 07/16/24 (1)

(1) 08/13/24 (1)

(1) 09/10/24 (1)

(1) 10/22/24 (1)

(1) 11/19/24 (1)

(1) 12/17/24 (1)

(1)

MEAN Table C-II.2 COLLECTION PERIOD 1N 1S 37 38 01/17/24

< 1.9 (1)

< 1.8 2.5 +/- 1.3 02/12/24 2.1 +/- 1.3 (1)

< 1.8 2.6 +/- 1.4 03/19/24

< 1.8 (1)

< 1.9

< 1.9 04/23/24 (1)

(1) 2.4 +/- 1.2 1.8 +/- 1.1 05/21/24 (1)

(1) 1.7 +/- 1.2 3.1 +/- 1.3 06/18/24 (1)

(1)

< 1.7

< 1.7 07/16/24 (1)

(1)

< 2.4

< 2.4 08/13/24 (1)

(1) 2.2 +/- 1.1 3.8 +/- 1.2 09/10/24 (1)

(1) 2.2 +/- 1.2

< 2.5 10/22/24 (1)

(1)

< 1.8

< 2.0 11/19/24 (1)

(1)

< 1.7 2.0 +/- 1.2 12/17/24 (1)

(1) 1.8 +/- 1.2 2.4 +/- 1.2 MEAN +/- 2 STD DEV 2.1 +/- 0 2.1 +/- 0.6 2.6 +/- 1.4 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION WATER SAMPLES COLLECTED IN THE VICINITY OF WATER SAMPLES COLLECTED IN THE VICINITY OF THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES OYSTER CREEK GENERATING STATION, 2024 CONCENTRATIONS OF GROSS BETA IN DRINKING 177 489 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA 182 481 OYSTER CREEK GENERATING STATION, 2024 304 434 193 584 196 580 190 572 597 297 575 586 511 519 484 CONCENTRATIONS OF TRITIUM IN DRINKING 518 525 488 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA 440 193 C-3

Table C-II.3 SITE Mn-54 Co-60 Zn-65 Cs-134 Cs-137 1N 01/17/24

< 4

< 5

< 8

< 5

< 5 02/12/24

< 7

< 7

< 9

< 8

< 7 03/19/24

< 6

< 5

< 13

< 7

< 6 04/23/24 (1)

(1)

(1)

(1)

(1) 05/21/24 (1)

(1)

(1)

(1)

(1) 06/18/24 (1)

(1)

(1)

(1)

(1) 07/16/24 (1)

(1)

(1)

(1)

(1) 08/13/24 (1)

(1)

(1)

(1)

(1) 09/10/24 (1)

(1)

(1)

(1)

(1) 10/22/24 (1)

(1)

(1)

(1)

(1) 11/19/24 (1)

(1)

(1)

(1)

(1) 12/17/24 (1)

(1)

(1)

(1)

(1)

MEAN 1S (1) 37 01/17/24

< 4

< 5

< 9

< 5

< 5 02/12/24

< 6

< 4

< 10

< 8

< 6 03/20/24

< 5

< 8

< 10

< 6

< 5 04/23/24

< 4

< 4

< 9

< 5

< 5 05/21/24

< 3

< 4

< 12

< 4

< 3 06/18/24

< 5

< 5

< 8

< 6

< 4 07/16/24

< 7

< 6

< 18

< 8

< 7 08/13/24

< 8

< 9

< 19

< 7

< 7 09/10/24

< 3

< 4

< 8

< 4

< 4 10/22/24

< 7

< 11

< 23

< 9

< 8 11/19/24

< 9

< 11

< 20

< 10

< 9 12/17/24

< 8

< 9

< 18

< 9

< 9 MEAN 38 01/17/24

< 5

< 6

< 14

< 5

< 4 02/12/24

< 7

< 5

< 11

< 5

< 6 03/20/24

< 7

< 9

< 14

< 7

< 8 04/23/24

< 3

< 3

< 7

< 4

< 4 05/21/24

< 7

< 8

< 13

< 6

< 5 06/18/24

< 6

< 7

< 14

< 7

< 6 07/16/24

< 6

< 5

< 10

< 6

< 6 08/13/24

< 9

< 8

< 18

< 7

< 8 09/10/24

< 6

< 6

< 13

< 6

< 5 10/22/24

< 7

< 9

< 19

< 9

< 8 11/19/24

< 6

< 7

< 11

< 7

< 5 12/17/24

< 5

< 7

< 12

< 6

< 5 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING C-4

Table C-III.1 COLLECTION PERIOD 02/09/24 -

04/17/24 -

07/01/24 -

10/23/24 -

MEAN Table C-III.2 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 MW-24-3A 02/09/24 - 02/09/24

< 6

< 6

< 11

< 5

< 5 04/17/24 - 04/17/24

< 5

< 7

< 14

< 7

< 6 07/01/24 - 07/01/24

< 8

< 8

< 14

< 7

< 6 10/23/24 - 10/23/24

< 5

< 6

< 10

< 5

< 5 MEAN W-3C 02/09/24 - 02/09/24

< 5

< 5

< 9

< 5

< 5 04/17/24 - 04/17/24

< 4

< 5

< 10

< 4

< 5 07/01/24 - 07/01/24

< 8

< 7

< 13

< 8

< 8 10/23/24 - 10/23/24

< 5

< 5

< 11

< 5

< 6 MEAN CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA MW-24-3A W-3C RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES 02/09/24 04/17/24 07/01/24 10/23/24 189 305 583 190 188 184 307 595 C-5

Table C-IV.1 COLLECTION SITE PERIOD K-40 Mn-54 Co-60 Zn-65 Cs-134 Cs-137 33 06/03/24 2823 +/- 1021

< 49

< 55

< 136

< 59

< 55 06/03/24 4313 +/- 1088

< 65

< 41

< 105

< 57

< 63 06/03/24 2937 +/- 765

< 46

< 57

< 103

< 45

< 44 09/26/24 3675 +/- 1098

< 101

< 94

< 249

< 90

< 100 09/26/24 4608 +/- 1066

< 54

< 76

< 143

< 65

< 50 09/26/24 1854 +/- 1282

< 64

< 73

< 157

< 79

< 84 MEAN +/- 2 STD DEV 3368 +/- 2059 93 06/04/24 2422 +/- 1091

< 53

< 95

< 152

< 62

< 66 06/04/24 3856 +/- 1103

< 67

< 83

< 139

< 77

< 66 06/04/24 1802 +/- 746

< 48

< 58

< 140

< 69

< 66 10/01/24 4539 +/- 1221

< 88

< 80

< 230

< 96

< 86 10/02/24 2997 +/- 1407

< 95

< 86

< 203

< 106

< 82 MEAN +/- 2 STD DEV 3123 +/- 2190 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR OYSTER CREEK GENERATING STATION, 2024 (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 06/03/24 1337 +/- 793

< 52

< 64

< 107

< 67

< 51 10/22/24 1589 +/- 670

< 56

< 60

< 118

< 66

< 50 MEAN +/- 2 STD DEV 1463 +/- 356 24 Clams 06/03/24 1821 +/- 829

< 37

< 66

< 129

< 65

< 54 09/30/24 2085 +/- 938

< 65

< 84

< 161

< 67

< 82 MEAN +/- 2 STD DEV 1953 +/- 373 94 Clams 06/05/24 2514 +/- 1027

< 81

< 79

< 183

< 84

< 73 10/02/24 1716 +/- 854

< 55

< 67

< 134

< 55

< 61 MEAN +/- 2 STD DEV 2115 +/- 1129 33 Crabs 09/26/24 2490 +/- 1089

< 83

< 53

< 169

< 62

< 70 MEAN +/- 2 STD DEV 2490 +/- 0 93 Crabs 09/26/24 2135 +/- 1106

< 67

< 108

< 162

< 124

< 84 MEAN +/- 2 STD DEV 2135 +/- 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, 2024 C-7

Table C-V.1 COLLECTION SITE PERIOD Be-7 Mn-54 Co-60 Cs-134 Cs-137 23 06/03/24

< 633 2316 +/- 875

< 65

< 97

< 62

< 63 1584 +/- 897 153 +/- 81 10/22/24

< 349 3856 +/- 727

< 41

< 46

< 51

< 45

< 982 258 +/- 71 MEAN +/- 2 STD DEV 3086 +/- 2178 1584 +/- 0 206 +/- 149 24 06/03/24

< 425 2055 +/- 783

< 60

< 43

< 57

< 56

< 1175 252 +/- 84 09/30/24

< 465 11910 +/- 1090

< 58

< 64

< 73

< 57

< 1092 730 +/- 116 MEAN +/- 2 STD DEV 6983 +/- 13937 491 +/- 676 33 06/03/24

< 570 1586 +/- 648

< 61

< 65

< 66

< 73 1305 +/- 1061 173 +/- 158 09/30/24

< 283 2069 +/- 485

< 31

< 37

< 41

< 36 610 +/- 542 317 +/- 38 MEAN +/- 2 STD DEV 1828 +/- 683 958 +/- 983 245 +/- 204 94 06/05/24

< 676 14820 +/- 2158

< 99

< 122

< 97

< 79

< 1683 537 +/- 143 10/02/24

< 351 16040 +/- 1035

< 40

< 47

< 52

< 50 1641 +/- 751 427 +/- 66 MEAN +/- 2 STD DEV 15430 +/- 1725 1641 +/- 0 482 +/- 156 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, 2024 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA C-8

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

12/26/23 - 01/09/24 11 +/- 3 12 +/- 3 14 +/- 3 13 +/- 3 14 +/- 3 13 +/- 3 01/09/24 - 01/23/24 18 +/- 3

< 3 16 +/- 3 15 +/- 3

< 12 18 +/- 3 01/23/24 - 02/06/24 9 +/- 2 11 +/- 2 11 +/- 2 12 +/- 3 9 +/- 2 9 +/- 2 02/06/24 - 02/20/24 13 +/- 3 12 +/- 3 14 +/- 3 13 +/- 3 14

+/- 3 14 +/- 3 02/20/24 - 03/04/24 12 +/- 3 12 +/- 3 11 +/- 3 14 +/- 3 9 +/- 3 12 +/- 3 03/04/24 - 03/19/24 14 +/- 3 10 +/- 3 10 +/- 2 10 +/- 3

< 8 10 +/- 2 03/19/24 - 04/01/24 9 +/- 3 11 +/- 3 11 +/- 3 12 +/- 3 (1) 13 +/- 3 04/01/24 - 04/16/24 10 +/- 2 10 +/- 2 11 +/- 2 12 +/- 2 10 +/- 2 11 +/- 2 04/16/24 - 04/30/24 16 +/- 3 8 +/- 2 14 +/- 3 17 +/- 3 15 +/- 3 13 +/- 3 04/30/24 - 05/14/24 8 +/- 2 8 +/- 2 9 +/- 2 8 +/- 2 7 +/- 2 9 +/- 2 05/14/24 - 05/28/24 11 +/- 3 11 +/- 3 10 +/- 2 10 +/- 3 9 +/- 2 12 +/- 3 05/28/24 - 06/11/24 14 +/- 3 14 +/- 3 14 +/- 3 16 +/- 3 11 +/- 3 13 +/- 3 06/11/24 - 06/25/24 13 +/- 3 (1) 11 +/- 2 12 +/- 3 8 +/- 3 16 +/- 3 06/25/24 - 07/09/24 13 +/- 2 11 +/- 2 12 +/- 2 16 +/- 3 12 +/- 3 14 +/- 3 07/09/24 - 07/23/24 15 +/- 3 14 +/- 3 16 +/- 3 15 +/- 3 14 +/- 3 16 +/- 3 07/23/24 - 08/06/24 19 +/- 3

< 3 19 +/- 3 20 +/- 3 14 +/- 3 22 +/- 3 08/06/24 - 08/20/24 16 +/- 3 15 +/- 3 16 +/- 3 16 +/- 3 15 +/- 3 19 +/- 3 08/20/24 - 09/03/24 17 +/- 3 16 +/- 3 15 +/- 3 18 +/- 3 13 +/- 3 17 +/- 3 09/03/24 - 09/17/24 16 +/- 3 17 +/- 3 15 +/- 3 15 +/- 3 16 +/- 3 21 +/- 3 09/17/24 - 10/01/24 (1) 11 +/- 2 7 +/- 2 12 +/- 3 10 +/- 2 14 +/- 3 10/01/24 - 10/15/24 15 +/- 3 14 +/- 3 17 +/- 3 14 +/- 3 15 +/- 3 18 +/- 3 10/15/24 - 10/29/24 20 +/- 3 21 +/- 3 22 +/- 3 21 +/- 3 24 +/- 3 25 +/- 3 10/29/24 - 11/12/24 21 +/- 3 15 +/- 3 15 +/- 3 14 +/- 3 13 +/- 3 14 +/- 3 11/12/24 - 11/26/24 15 +/- 3 (1) 15 +/- 3 18 +/- 3 13 +/- 3 19 +/- 3 11/26/24 - 12/10/24 20 +/- 3 21 +/- 3 21 +/- 3 23 +/- 3 19 +/- 3 22 +/- 3 12/10/24 - 12/23/24 15 +/- 3 14 +/- 3 14 +/- 3 17 +/- 3 12 +/- 3 16 +/- 3 12/23/24 - 01/07/25 15 +/- 3 14 +/- 3 14 +/- 3 17 +/- 3 12 +/-

3 16

+/-

3 MEAN +/- 2 STD DEV 14 +/- 7 13 +/- 7 14 +/- 7 15 +/- 7 13 +/-

7 15 +/-

8 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I GROUP II C-9

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

+/- 2SD PERIOD MIN MAX

+/- 2SD PERIOD MIN MAX

+/- 2SD 12/26/23 - 02/06/24 9

18 13 +/- 6 12/26/23 - 02/06/24 9

15 13 +/- 4 12/26/23 - 02/06/24 9

18 13 +/- 9 02/06/24 - 03/04/24 11 14 12 +/- 2 02/06/24 - 03/04/24 9

14 13 +/- 4 02/06/24 - 03/04/24 12 14 13 +/- 3 03/04/24 - 04/01/24 9

14 11 +/- 3 03/04/24 - 04/01/24 10 12 11 +/- 3 03/04/24 - 04/01/24 10 13 12 +/- 4 04/01/24 - 04/30/24 8

16 12 +/- 6 04/01/24 - 04/30/24 10 17 14 +/- 6 04/01/24 - 04/30/24 11 13 12 +/- 3 04/30/24 - 05/28/24 8

11 10 +/- 2 04/30/24 - 05/28/24 7

10 9 +/- 2 04/30/24 - 05/28/24 9

12 10 +/- 5 05/28/24 - 06/25/24 11 14 13 +/- 3 05/28/24 - 06/25/24 8

16 12 +/- 6 05/28/24 - 06/25/24 13 16 15 +/- 4 06/25/24 - 08/06/24 11 19 15 +/- 6 06/25/24 - 08/06/24 12 20 15 +/- 5 06/25/24 - 08/06/24 14 22 17 +/- 8 08/06/24 - 09/03/24 15 17 16 +/- 2 08/06/24 - 09/03/24 13 18 15 +/- 4 08/06/24 - 09/03/24 17 19 18 +/- 2 09/03/24 - 10/01/24 7

17 13 +/- 8 09/03/24 - 10/01/24 10 16 13 +/- 6 09/03/24 - 10/01/24 14 21 18 +/- 10 10/01/24 - 10/29/24 14 22 18 +/- 7 10/01/24 - 10/29/24 14 24 18 +/- 10 10/01/24 - 10/29/24 18 25 21 +/- 10 10/29/24 - 11/26/24 15 21 16 +/- 5 10/29/24 - 11/26/24 13 18 15 +/- 5 10/29/24 - 11/26/24 14 19 16 +/- 7 11/26/24 - 01/07/25 12 21 16 +/- 7 11/26/24 - 01/07/25 9

23 16 +/- 10 11/26/24 - 01/07/25 16 22 18 +/- 7 12/26/23 - 01/07/25 7

22 14 +/- 7 12/26/23 - 01/07/25 7

24 14 +/- 7 12/26/23 - 01/07/25 9

25 15 +/- 8 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, 2024 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 12/26/23 - 04/01/24

< 5 04/01/24 - 06/25/24

< 5 06/25/24 - 09/17/24

< 6 10/01/24 - 01/07/25

< 4 MEAN 66 12/26/23 - 04/01/24

< 5 04/01/24 - 06/11/24

< 7 06/25/24 - 10/01/24

< 4 10/01/24 - 01/07/25

< 8 MEAN 71 12/26/23 - 04/01/24

< 2 04/01/24 - 06/25/24

< 5 06/25/24 - 10/01/24

< 4 10/01/24 - 01/07/25

< 6 MEAN 73 12/26/23 - 03/19/24

< 8 04/01/24 - 06/25/24

< 6 06/25/24 - 10/01/24

< 4 10/01/24 - 01/07/25

< 6 MEAN 111 12/26/23 - 04/01/24

< 4 04/01/24 - 06/25/24

< 6 06/25/24 - 10/01/24

< 4 10/01/24 - 01/07/25

< 4 MEAN C

12/26/23 - 04/01/24

< 6 04/01/24 - 06/25/24

< 6 06/25/24 - 10/01/24

< 4 10/01/24 - 01/07/25

< 4 MEAN RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 C-11

Table C-VI.4 COLLECTION SITE PERIOD Mn-54 Co-60 Cs-134 Cs-137 20 12/26/23 - 04/01/24 41 +/- 13

< 1

< 2 2

< 1 04/01/24 - 06/25/24 46 +/- 20

< 3

< 3 3

< 3 06/25/24 - 09/17/24 87 +/- 22

< 2

< 4 2

< 2 10/01/24 - 01/07/25 57 +/- 16

< 2

< 2 2

< 2 MEAN +/- 2 STD DEV 58 +/- 41 66 12/26/23 - 04/01/24 31 +/- 19

< 3

< 4 3

< 2 04/01/24 - 06/11/24 38 +/- 24

< 4

< 4 2

< 2 06/25/24 - 10/01/24 29 +/- 13

< 2

< 3 2

< 2 10/01/24 - 01/07/25 33 +/- 18

< 2

< 3 3

< 2 MEAN +/- 2 STD DEV 33 +/- 7 71 12/26/23 - 04/01/24 56 +/- 16

< 2

< 2 2

< 2 04/01/24 - 06/25/24 61 +/- 21

< 3

< 3 3

< 2 06/25/24 - 10/01/24 60 +/- 15

< 2

< 2 2

< 2 10/01/24 - 01/07/25 41 +/- 19

< 3

< 3 3

< 3 MEAN +/- 2 STD DEV 55 +/- 18 73 12/26/23 - 03/19/24 48 +/- 23

< 3

< 4 4

< 3 04/01/24 - 06/25/24 48 +/- 14

< 2

< 3 2

< 2 06/25/24 - 10/01/24 41 +/- 15

< 2

< 3 2

< 2 10/01/24 - 01/07/25 39 +/- 13

< 2

< 3 2

< 2 MEAN +/- 2 STD DEV 44 +/- 9 111 12/26/23 - 04/01/24 50 +/- 13

< 3

< 2 3

< 2 04/01/24 - 06/25/24 58 +/- 17

< 2

< 3 2

< 2 06/25/24 - 10/01/24 36 +/- 23

< 2

< 3 4

< 3 10/01/24 - 01/07/25 47 +/- 15

< 3

< 3 3

< 3 MEAN +/- 2 STD DEV 48 +/- 19 C

12/26/23 - 04/01/24 39 +/- 15

< 2 2

3

< 2 04/01/24 - 06/25/24 63 +/- 24

< 3 2

3

< 3 06/25/24 - 10/01/24 74 +/- 25

< 4 4

4

< 4 10/01/24 - 01/07/25 37 +/- 11

< 2 1

2

< 2 MEAN +/- 2 STD DEV 53 +/- 36 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, 2024 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA C-12

Table C-VII.1 STATION MEAN CODE

+/- 2 S.D.

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

8.2 +/- 4.3 9.8 9.9 5.3 8.0 6

7.9 +/- 2.8 9.3 8.5 6.0 7.9 8

7.1 +/- 4.3 7.3 8.6 3.9 8.4 9

6.3 +/- 3.3 7.3 7.6 4.0 6.3 22 9.7 +/- 3.7 11.6 10.7 7.3 9.3 51 9.7 +/- 3.4 10.0 9.3 7.7 11.7 52 12.1 +/- 2.3 12.7 12.3 10.4 13.0 53 9.5 +/- 5.8 9.6 12.9 5.8 9.6 54 6.9 +/- 4.3 8.4 7.3 3.8 8.2 55 12.5 +/- 5.3 12.2 15.4 9.0 13.2 55A 7.0 +/- 2.9 7.8 6.7 5.0 8.3 56 11.2 +/- 2.1 12.3 11.9 10.1 10.6 57 7.3 +/- 4.6 9.4 7.8 4.0 8.1 58 6.5 +/- 5.0 7.7 7.4 2.8 8.1 59 8.9 +/- 2.5 7.6 9.4 8.1 10.4 61 7.9 +/- 3.2 8.1 9.1 5.6 9.0 62 7.9 +/- 3.3 8.8 8.0 5.5 9.2 63 8.4 +/- 3.2 9.4 9.2 6.0 9.0 64 9.0 +/- 4.4 10.1 10.7 5.8 9.3 65 7.6 +/- 2.5 8.7 7.6 5.8 8.3 66 6.9 +/- 3.6 8.3 7.4 4.2 7.7 68 5.3 +/- 3.5 6.4 5.8 2.7 6.5 71 7.1 +/- 3.5 7.6 8.0 4.5 8.2 72 8.0 +/- 3.8 8.9 9.8 5.4 8.1 73 6.3 +/- 3.8 6.8 7.9 3.6 6.8 74 7.1 +/- 4.3 7.8 8.3 3.9 8.4 75 8.1 +/- 3.9 9.7 8.6 5.3 8.9 78 8.6 +/- 3.1 8.3 10.0 6.5 9.5 79 10.3 +/- 2.9 11.2 11.3 8.2 10.4 81 7.9 +/- 4.8 9.5 9.1 4.3 8.7 98 6.4 +/- 3.4 7.3 7.0 4.2 7.1 99 6.8 +/- 2.4 7.0 7.9 5.1 7.3 T1 8.7 +/- 2.4 9.2 9.8 7.0 8.8 100 7.1 +/- 3.4 7.8 7.6 4.6 8.3 101 7.0 +/- 2.0 6.6 7.8 5.8 7.8 102 7.8 +/- 4.0 8.7 8.0 5.0 9.6 103 7.7 +/- 4.0 8.2 9.4 4.8 8.2 104 7.3 +/- 4.6 8.6 8.0 3.9 8.8 106 5.9 +/- 3.4 6.6 6.6 3.3 7.0 107 6.8 +/- 2.9 7.5 8.0 4.7 7.1 109 7.4 +/- 4.2 8.6 9.0 4.4 7.7 110 6.4 +/- 3.0 7.6 6.7 4.2 7.0 112 8.8 +/- 2.8 10.2 9.5 6.97 8.6 113 8.3 +/- 3.4 8.9 9.8 5.8 8.5 C

7.3 +/- 3.7 8.7 7.0 4.8 8.7 (1) SEE PROGRAM EXCEPTIONS FOR EXPLANTION 2024 REMP Dosimetry Report(1)

RESULTS IN UNITS OF MILLIREM/STD. QUARTER +/- 2 STANDARD DEVIATION

• Results on this table reflect a "Net" result (background subtracted)

C-13

TABLE C-VII.2 SITE BOUNDARY INTERMEDIATE SPECIAL INTEREST

+/- 2 S.D.

+/- 2 S.D.

+/- 2 S.D.

9.5 +/- 5.1 8.1 +/- 2.8 8.7 +/- 1.9 8.7 +/- 0.0 9.1 +/- 4.4 8.3 +/- 2.6 9.0 +/- 1.8 7.0 +/- 0.0 6.2 +/- 4.0 4.8 +/- 2.7 4.7 +/- 1.2 4.8 +/- 0.0 9.4 +/- 3.2 8.0 +/- 2.2 8.3 +/- 0.7 8.7 +/- 0.0 TABLE C-VII.3 PERIOD PERIOD PERIOD MEAN MINIMUM MAXIMUM

+/- 2 S.D.

8.7 +/- 4.6 7.3 +/- 3.8 7.7 +/- 3.8 7.3 +/- 3.7 SITE BOUNDARY STATIONS - 1, 51, 52, 53, 54, 55, 55A, 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 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, 2024 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, 2024 CONTROL

+/- 2 S.D.

SAMPLES LOCATION ANALYZED SITE BOUNDARY 80 CONTROL 4

4.8 8.7 15.4 INTERMEDIATE 80 2.7 11.6 SPECIAL INTEREST 12 4.3 9.8 2.8 C-14

FIGURE C-1 MEAN COBALT-60 CONCENTRATION IN CLAMS OYSTER CREEK GENERATING STATION, 1983 - 2024 0

5 10 15 20 1983 1989 1995 2001 2006 2012 2018 2024 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-15

FIGURE C-2 MEAN COBALT-60 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984 - 2024 0

50 100 150 200 250 300 1984 1986 1989 1996 2011 2024 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-16

FIGURE C-3 MEAN CESIUM-137 CONCENTRATION IN AQUATIC SEDIMENT OYSTER CREEK GENERATING STATION, 1984 - 2024 0

200 400 600 1984 1987 1991 2005 2024 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-17

FIGURE C-4 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERATING STATION, 2008 - 2024 0

0.01 0.02 0.03 0.04 0.05 Indicator

Background

picoCuries per cubic meter Date C-18

FIGURE C-5 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATES OYSTER CREEK GENERATING STATION, 1984 - 2024 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-19

FIGURE C-6 MEAN QUARTERLY OSLD GAMMA DOSE OYSTER CREEK GENERATING STATION, 2024 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 1Q24 2Q24 3Q24 4Q24 millirem per Standard Quarter Oyster Creek's dosimetry changed from TLD to OSLD in 2012.

C-20

APPENDIX D DATA TABLES QC COMPARISON SAMPLES

The following section presents the results of data analysis performed by the QC laboratory, Microbac Laboratories - Northbrook (formerly Environmental Inc.). Duplicate samples were obtained from several locations and media and were split with the primary laboratory, Teledyne Brown Engineering (TBE) and the QC Laboratory. Comparison of the results for all media were within expected ranges.

Table D-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA OC-24 COLLECTION PERIOD 06/03/24 09/30/24 24 (TBE)

<521

<186 D-1 QCA (TBE)

<523

<189 (Microbac)

< 185

< 181

Table D-I.2 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 24 06/03/24

< 4

< 5

< 12

< 7

< 6 (TBE) 09/30/24

< 2

< 2

< 4

< 2

< 2 QCA 06/03/24

< 7

< 7

< 15

< 7

< 7 (TBE) 09/30/24

< 2

< 2

< 4

< 2

< 2 OC-24 06/03/24

< 2

< 3

< 4 (1)

< 3 (Microbac) 09/30/24

< 3

< 3

< 7 (1)

< 3

`

(1) Not reported CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA WATER SAMPLES COLLECTED IN THE VICINITY OF D-2

Table D-II.1 COLLECTION PERIOD QC (Microbac) 01/17/24

< 444

< 434

< 440

< 168 02/12/24

< 188

< 193

< 193

< 169 03/19/24

< 509

< 511

< 518

< 174 04/23/24 (1)

< 519

< 525 (1) 05/21/24 (1)

< 484

< 488 (1) 06/18/24 (1)

< 190

< 196

< 185 07/16/24 (1)

< 572

< 580

< 177 08/13/24 (1)

< 597

< 586

< 181 09/10/24 (1)

< 297

< 304

< 183 10/22/24 (1)

< 575

< 584

< 177 11/19/24 (1)

< 182

< 177

< 185 12/17/24 (1)

< 481

< 489

< 182 Table D-II.2 COLLECTION PERIOD QC (Microbac) 01/17/24

< 1.9

< 1.8 2.5 +/- 1.3

< 0.8 02/12/24 2.1

+/- 1.3

< 1.8 2.6 +/- 1.4

< 0.9 03/19/24

< 1.8

< 1.9

< 1.9

< 0.9 04/23/24 (1) 2.4 +/- 1.2 1.8 +/- 1.1 (1) 05/21/24 (1) 1.7 +/- 1.2 3.1 +/- 1.3 (1) 06/18/24 (1)

< 1.7

< 1.7

< 0.9 07/16/24 (1)

< 2.4

< 2.4

< 0.8 08/13/24 (1) 2.2 +/- 1.1 3.8 +/- 1.2

< 1.0 09/10/24 (1) 2.2 +/- 1.2

< 2.5

< 0.7 10/22/24 (1)

< 1.8

< 2.0 (2) 11/19/24 (1)

< 1.7 2.0 +/- 1.2

< 0.4 12/17/24 (1) 1.8 +/- 1.2 2.4 +/- 1.2

< 2.3 (1) SEE PROGRAM EXCEPTIONS FOR EXPLANATION (2) Analysis in process 1N (TBE) 37 (TBE) 38 (TBE)

CONCENTRATIONS OF TRITIUM IN DRINKING WATER WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2023 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA 38 (TBE) 1N (TBE) 37 (TBE)

D-3

Table D-II.3 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 1N 01/17/24

< 4

< 5

< 8

< 5

< 5 (TBE) 02/12/24

< 7

< 7

< 9

< 8

< 7 03/19/24

< 6

< 5

< 13

< 7

< 6 04/23/24 (2)

(2)

(2)

(2)

(2) 05/21/24 (2)

(2)

(2)

(2)

(2) 06/18/24 (2)

(2)

(2)

(2)

(2) 07/16/24 (2)

(2)

(2)

(2)

(2) 08/13/24 (2)

(2)

(2)

(2)

(2) 09/10/24 (2)

(2)

(2)

(2)

(2) 10/22/24 (2)

(2)

(2)

(2)

(2) 11/19/24 (2)

(2)

(2)

(2)

(2) 12/17/24 (2)

(2)

(2)

(2)

(2) 37 01/17/24 4

5 9

5 5

(TBE) 02/12/24 6

4

< 10 8

6 03/19/24 5

8

< 10 6

5 04/23/24 4

4 9

5 5

05/21/24 3

4

< 12 4

3 06/18/24 5

5 8

6 4

07/16/24 7

6

< 18 8

7 08/13/24 8

9

< 19 7

7 09/10/24 3

4 8

4 4

10/22/24 7

< 11

< 23 9

8 11/19/24 9

< 11

< 20

< 10 9

12/17/24 8

9

< 18 9

9 38 01/17/24 5

6

< 14 5

4 (TBE) 02/12/24 7

5

< 11 5

6 03/19/24 7

9

< 14 7

8 04/23/24 3

3 7

4 4

05/21/24 7

8

< 13 6

5 06/18/24 6

7

< 14 7

6 07/16/24 6

5

< 10 6

6 08/13/24 9

8

< 18 7

8 09/10/24 6

6

< 13 6

5 10/22/24 7

9

< 19 9

8 11/19/24 6

7

< 11 7

5 12/17/24 5

7

< 12 6

5 QC 01/17/24

< 4

< 3

< 15 (1)

< 3 (Microbac) 02/12/24

< 1

< 2

< 3 (1)

< 2 03/19/24

< 3

< 4

< 3 (1)

< 3 04/23/24 (2)

(2)

(2)

(2)

(2) 05/21/24 (2)

(2)

(2)

(1)

(2) 06/18/24

< 2

< 3

< 5 (1)

< 3 07/16/24

< 2

< 3

< 3 (1)

< 2 08/13/24

< 2

< 2

< 5 (1)

< 3 09/10/24

< 2

< 4

< 5 (1)

< 3 10/22/24

< 2

< 3

< 6 (1)

< 4 11/19/24

< 2

< 3

< 7 (1)

`

< 4 12/17/24

< 2

< 2

< 5 (1)

< 3 (1) Not reported (2) SEE PROGRAM EXCEPTIONS FOR EXPLANATION CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA D-4

Table D-III.1 W-3C 02/09/24 -

02/09/24

< 169 04/17/24 -

04/17/24

< 170 07/01/24 -

07/01/24

< 183 10/23/24 -

10/23/24

< 185 184 307 595 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA OC-W-3C (Microbac) 188 COLLECTION PERIOD D-5

Table D-III.2 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 W-3C 02/09/24 -

02/09/24

< 5

< 5

< 9

< 5

< 5 04/17/24 -

04/17/24

< 4

< 5

< 10

< 4

< 5 07/01/24 -

07/01/24

< 8

< 7

< 13

< 8

< 8 10/23/24 -

10/23/24

< 5

< 5

< 11

< 5

< 6 OC -W-3C 02/09/24 -

02/09/24

< 1

< 2

< 2 (1)

< 2 (Micobac) 04/17/24 -

04/17/24

< 2

< 3

< 4 (1)

< 3 07/01/24 -

07/01/24

< 1

< 4

< 5 (1)

< 3 10/23/24 -

10/23/24

< 3

< 4

< 6 (1)

< 5

`

(1) Not reported CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA D-6

Table D-IV.1 COLLECTION SITE PERIOD Mn-54 Co-60 Zn-65 Cs-134 Cs-137 24 06/03/24 1821 +/- 829

< 37

< 66

< 129

< 65

< 54 (TBE)

OC-24 06/03/24 1430 +/- 159

< 7

< 8

< 15 (1)

< 10 (Microbac)

`

`

(1) Not reported CONCENTRATIONS OF GAMMA EMITTERS IN CLAM K-40 OYSTER CREEK GENERATING STATION, 2024 SAMPLES COLLECTED IN THE VICINITY OF RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA D-7

Table D-V.1 COLLECTION SITE PERIOD Mn-54 Co-60 Cs-134 Cs-137 24 06/03/24

< 425 2055 +/- 783

< 60

< 43

< 57

< 56 1175 252 +/-

84 (TBE) 09/30/24

< 465 11910 +/- 1090

< 58

< 64

< 73

< 57 1092 730.2 +/-

116 OC-24 06/03/24

< 212 1890 +/- 241

< 9

< 10 (1)

< 11 755 +/- 344 987 +/- 541 (Microbac) 09/30/24

< 367 7290 +/- 392

< 16

< 16 (1)

< 14 1090 +/- 533 1270 +/- 748

`

(1) Not reported CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED Be-7 IN THE VICINITY OF OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA K-40 Ra-226 Th-228 D-8

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 2024 E14089 Milk Sr-89 pCi/L 79.6 78.2 1.02 A

Sr-90 pCi/L 12.6 11.9 1.06 A

E14090 Milk Ce-141 pCi/L 75.6 85.0 0.89 A

Co-58 pCi/L

-0.069 Not Measured Co-60 pCi/L 139 158 0.88 A

Cr-51 pCi/L 212 230 0.92 A

Cs-134 pCi/L 167 198 0.84 A

Cs-137 pCi/L 158 171 0.93 A

Fe-59 pCi/L 81.1 86.5 0.94 A

I-131 pCi/L 80.9 90.8 0.89 A

Mn-54 pCi/L 173 183 0.95 A

Zn-65 pCi/L 165 176 0.93 A

E14091 Charcoal I-131 pCi 90.1 90.3 1.00 A

E14092 AP Ce-141 pCi 68.1 67.5 1.01 A

Co-58 pCi 1.73 Not Measured Co-60 pCi 168 126 1.34 N(1)

Cr-51 pCi 182 183 0.99 A

Cs-134 pCi 157 157 1.00 A

Cs-137 pCi 132 136.0 0.97 A

Fe-59 pCi 70.3 68.6 1.02 A

Mn-54 pCi 144 145 0.99 A

Zn-65 pCi 125 140 0.89 A

E14093 Soil Ce-141 pCi/g 0.106 0.071 1.48 N(1)

Co-58 pCi/g

-0.005 Not Measured Co-60 pCi/g 0.121 0.133 0.91 A

Cr-51 pCi/g 0.198 0.194 1.02 A

Cs-134 pCi/g 0.206 0.166 1.24 W

Cs-137 pCi/g 0.207 0.209 0.99 A

Fe-59 pCi/g 0.063 0.073 0.87 A

Mn-54 pCi/g 0.140 0.153 0.91 A

Zn-65 pCi/g 0.149 0.148 1.01 A

E14094 AP Sr-89 pCi 83.9 90.6 0.93 A

Sr-90 pCi 11.7 13.8 0.85 A

September 2024 E14095 Milk Sr-89 pCi/L 88.0 92.3 0.95 A

Sr-90 pCi/L 12.4 15.2 0.82 A

E14096 Milk Ce-141 pCi/L 124 124 1.00 A

Co-58 pCi/L 154 150 1.03 A

Co-60 pCi/L 232 236 0.98 A

A.1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services E-1

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

Ratio of TBE to Analytics Result Evaluation (b)

A.1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services Cr-51 pCi/L 284 274 1.04 A

Cs-134 pCi/L 180.0 187 0.96 A

Cs-137 pCi/L 126 127 0.99 A

Fe-59 pCi/L 127.0 113 1.12 A

I-131 pCi/L 85.3 89.0 0.96 A

Mn-54 pCi/L 162 162 1.00 A

Zn-65 pCi/L 294 275 1.07 A

E14097 Charcoal I-131 pCi 98.8 92.6 1.07 A

E14098 AP Ce-141 pCi 82.0 76.7 1.07 A

Co-58 pCi 91.0 92.6 0.98 A

Co-60 pCi 180 146 1.23 W

Cr-51 pCi 208 170 1.22 W

Cs-134 pCi 116 116 1.00 A

Cs-137 pCi 83.1 78.9 1.05 A

Fe-59 pCi 75.6 70.2 1.08 A

Mn-54 pCi 101 100 1.01 A

Zn-65 pCi 167 170 0.98 A

E14099 Soil Ce-141 pCi/g 0.224 0.222 1.01 A

Co-58 pCi/g 0.249 0.268 0.93 A

Co-60 pCi/g 0.420 0.423 0.99 A

Cr-51 pCi/g 0.492 0.492 1.00 A

Cs-134 pCi/g 0.278 0.336 0.83 A

Cs-137 pCi/g 0.276 0.295 0.94 A

Fe-59 pCi/g 0.233 0.204 1.14 A

Mn-54 pCi/g 0.279 0.290 0.96 A

Zn-65 pCi/g 0.538 0.494 1.09 A

E14100 AP Sr-89 pCi 79.8 82.7 0.96 A

Sr-90 pCi 12.0 13.6 0.88 A

E14197 Liquid Gr-A (Am241) pCi/L 47.6 50.1 0.95 A

Gr-B (Cs137) pCi/L 248 270 0.92 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 E-2

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

Acceptance Range Evaluation (b)

February 2024 24-MaS50 Soil Fe-55 Bq/kg 297 650 455 - 845 N(3)

Ni-63 Bq/kg 1070 1530 1071 - 1989 N(4)

Tc-99 Bq/kg 325 336 235 - 437 A

Th-228 Bq/kg 34.6 48.8 34.2 - 63.4 W

Th-230 Bq/kg 49.7 54.0 38.0 - 70.0 A

Th-232 Bq/kg 36.4 45.1 31.6 - 58.6 A

24-MaSU50 Urine Cs-134 Bq/L 1.12 1.36 0.95-1.77 A

Cs-137 Bq/L 2.00 2.23 1.56-2.90 A

Co-57 Bq/L 1.06 1.26 0.88 - 1.64 A

Co-60 Bq/L 2.26 2.38 1.67 - 3.09 A

K-40 Bq/L

-1.80 NR Mn-54 Bq/L 1.44 1.51 1.06 - 1.96 A

U-234 Bq/L 0.00101 (1)

A U-238 Bq/L 0.00228 (1)

A Zn-65 Bq/L

-0.42 0.84 0.59-1.09 NE(5) 24-MaW50 Water Ni-63 Bq/L 0.338 0.80 (2)

A Tc-99 Bq/L 9.95 7.47 5.23 - 9.71 N(6) 24-RdV50 Vegetation Cs-134 Bq/sample 2.80 3.67 2.57 - 4.77 W

Cs-137 Bq/sample 2.21 2.57 1.80 - 3.34 A

Co-57 Bq/sample 2.23 2.53 1.77 - 3.29 A

Co-60 Bq/sample 2.42 2.96 2.07 - 3.85 A

Mn-54 Bq/sample 0.033 (1)

A Sr-90 Bq/sample 0.276 0.529 0.370 - 0.688 N(7)

Zn-65 Bq/sample 6.83 8.02 5.61 - 10.43 A

August 2024 24-MaS51 Soil Fe-55 Bq/kg (8) 780 546-1014 N(9)

Ni-63 Bq/kg 1140.00 1450.00 1015 - 1885 W

Tc-99 Bq/kg 155.00 171.00 120 - 222 A

Th-228 Bq/kg 38.00 43.30 30.3 - 56.3 A

Th-230 Bq/kg 46.10 44.00 30.8 - 57.2 A

Th-232 Bq/kg 38.90 42.60 29.8 - 55.4 A

24-MaW51 Water Ni-63 Bq/L 0.60 (1)

A Tc-99 Bq/L 11.90 11.20 7.8 - 14.6 A

24-RdV51 Vegetation Cs-134 Bq/sample 3.12 2.89 2.02 - 3.76 A

Cs-137 Bq/sample 2.18 1.91 1.34 - 2.48 A

Co-57 Bq/sample 0.00 (1)

A Co-60 Bq/sample 2.24 2.01 1.41 - 2.61 A

Mn-54 Bq/sample 3.76 3.53 2.47 - 4.59 A

Sr-90 Bq/sample 0.95 2.39 1.67 - 3.11 N(10)

Zn-65 Bq/sample 10.30 9.13 6.39 - 11.87 A

A.2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering Environmental Services E-3

(a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOE/MAPEP evaluation:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) False positive test (2) Sensitivity evaluation (3) See CAR 23-31 (4) See NCR 24-08 (5) Not Evaluated, re-reported as Falst Pos by MAPEP (6) See NCR 24-10 (7) See NCR 24-11 E-4

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

Acceptance Limits Evaluation (b)

March 2024 MRAD-40 Water Am-241 pCi/L 101 139 95.4 - 178 A

Fe-55 pCi/L 2185 2480 1460- 3610 A

Pu-238 pCi/L 62.0 70.4 42.3 - 91.2 A

Pu-239 pCi/L 61.2 76.5 47.3 - 94.3 A

Soil Am-241 pCi/kg NR 1880 1020 - 2660 Pu-238 pCi/kg 667 512 255 - 778 A

Pu-239 pCi/kg 562 545 297 - 784 A

Sr-90 pCi/kg 4050 3630 1130 - 5650 A

U-234 pCi/kg 3040 4360 2040 - 5710 A

U-238 pCi/kg 3270 4320 2370 - 5800 A

AP Am-241 pCi/filter 38.8 55.0 39.3 - 73.3 N(1)

Fe-55 pCi/filter 387 386 141 - 616 A

Pu-238 pCi/filter 45.9 41.1 31.0 - 50.5 A

Pu-239 pCi/filter 54.9 56.1 41.9 - 67.7 A

U-234 pCi/filter 11.1 11.6 8.60 - 13.6 A

U-238 pCi/filter 12.8 11.5 8.68 - 13.7 A

GR-A pCi/filter 116 95.9 50.1 - 158 A

GR-B pCi/filter 42.1 22.2 13.5 - 33.5 N(2)

April 2024 RAD-137 Water Ba-133 pCi/L 62.8 65.9 50.1 - 81.7 A

Cs-134 pCi/L 51.0 57.8 42.8 - 72.8 A

Cs-137 pCi/L 153 186 149 - 223 A

Co-60 pCi/L 92.1 98.8 79.7 - 118 A

Zn-65 pCi/L 208 240 188 - 292 A

GR-A pCi/L 35.2 52.6 39.6 - 65.6 N(3)

GR-B pCi/L 49 46.5 33.9 - 59.1 A

U-Nat pCi/L 56.0 59.3 52.8-65.8 A

H-3 pCi/L 19,000 21,300 18,200 - 24,400 A

Sr-89 pCi/L 48.9 52.2 37.8 - 66.6 A

Sr-90 pCi/L 32.6 37.6 32.0 - 43.2 A

I-131 pCi/L 21.8 25.1 21.7 - 28.5 A

September 2024 MRAD-41 Water Am-241 pCi/L 108.0 117.0 80.3-150 A

Fe-55 pCi/L 615 1230 723-1790 N(4)

Pu-238 pCi/L 99 103 61.9-133 A

Pu-239 pCi/L 123 133 82.3-164 A

Soil Am-241 pCi/kg 1320 1110 599-1570 A

Pu-238 pCi/kg 1380 1860 928-2830 A

Pu-239 pCi/kg 796 1030 561-1480 A

Sr-90 pCi/kg 3240 4730 1470-7370 A

A.3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services E-5

U-234 pCi/kg 2540 2860 1340-3750 A

U-238 pCi/kg 2390 2840 1560-3810 A

AP Am-241 pCi/filter 27.0 29.1 20.8-38.8 A

Fe-55 pCi/filter 644 800 292-1280 A

Pu-238 pCi/filter 22.3 21.5 16.2-26.4 A

Pu-239 pCi/filter 30.6 32.4 24.2-39.1 A

U-234 pCi/filter 14.0 31.1 23.1-36.4 N(5)

U-238 pCi/filter 14.2 30.9 23.3-36.9 N(5)

GR-A pCi/filter 80.0 72.4 37.8-119 A

GR-B pCi/filter 57.5 47.9 29.0-72.4 A

October 2024 RAD-139 Water Ba-133 pCi/L 30.3 27.4 15.5-39.3 A

Cs-134 pCi/L 73.3 80.2 63.0-97.4 A

Cs-137 pCi/L 46.6 46.3 23.3-69.3 A

Co-60 pCi/L 44.2 45.3 31.6-59.0 A

Zn-65 pCi/L 104 114.0 75.0-153 A

GR-A pCi/L 47.6 51.7 38.9-64.5 A

GR-B pCi/L 44.2 48.1 35.2-61.0 A

U-Nat pCi/L 28.3 26.90 23.6-30.2 A

H-3 pCi/L 4,690 5,320 3870-6770 A

Sr-89 pCi/L 57.5 44.2 30.6-57.8 A

Sr-90 pCi/L 37.3 35.6 30.2-41.0 A

I-131 pCi/L 28.3 26.3 22.7-29.9 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 24-02 (2) See NCR 24-03 (3) See NCR 24-05 (4) See NCR 24-15 E-6

APPENDIX F ERRATA DATA

Intentionally left blank

There was no errata data for 2024.

F-1

Intentionally left blank

APPENDIX G ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Docket No:

50-219 OYSTER CREEK GENERATING STATION UNIT 1 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2024 Prepared By Teledyne Brown Engineering Environmental Services Oyster Creek Generating Station Forked River, NJ 08731 April 2024

Table of Contents I. Summary and Conclusions.............................................................................................. 3 II. Introduction...................................................................................................................... 4 A. Objectives of the RGPP....................................................................................... 5 B. Implementation of the Objectives......................................................................... 6 C. Program Description............................................................................................ 7 D. Characteristics of Tritium (H-3)............................................................................ 7 III. Program Description....................................................................................................... 9 A. Sample Analysis.................................................................................................. 9 B. Data Interpretation............................................................................................... 9 C. Background Analysis....................................................................................... 10 IV. Results and Discussion.............................................................................................. 12 A. Program Exceptions........................................................................................... 12 B. Groundwater Results......................................................................................... 12 C. Surface Water Results....................................................................................... 13 D. Precipitation Water Results............................................................................... 13 E. Summary of Results - Inter-laboratory Comparison Program........................... 14 F. Leaks, Spills, and Releases............................................................................... 14 G. Trends................................................................................................................ 15 H. Ongoing Investigations...................................................................................... 15 I. Remedial Actions Taken.................................................................................... 15 V. References.................................................................................................................... 16

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2024 Figures Figure A-1 RGPP Sample Locations, Surface Water and Cape May Formation, Oyster Creek Generating Station, 2024 Figure A-2 RGPP Sample locations, Cohansey Formation, Oyster Creek Generating Station, 2024 Figure A-3 RGPP Sample locations, Cape May Groundwater Formation, Oyster Creek Generating Station, October 2024 Figure A-4 RGPP Sample locations, Cohansey Groundwater Formation, Oyster Creek Generating Station, October 2024 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, 2024 Table B-I.2 Concentrations of Gamma Emitters in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2024 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, 2024 Table B-II.1 Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2024 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, 2024

I.

Summary and Conclusions A Radiological Groundwater Protection Program (RGPP) was conducted at the Oyster Creek Generating Station (OCGS) by Holtec Decommissioning International (HDI) for the period January1, 2024 through December 31, 2024.

This report includes groundwater and surface water samples collected from the environment in 2024. In 2024, 473 analyses were performed on 56 samples from 23 locations.

No fission or activation gamma emitting radionuclides were detected at any of the 22 groundwater well sample locations or 1 surface water locations analyzed during 2024.

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) (200 pCi/l versus 2,000 pCi/l). Tritium was detected in groundwater samples with concentrations varying from <190 to 694 pCi/L. The well with the highest concentration was W-13.

Surface water samples were collected from 1 onsite monitoring location during 2024.

Tritium was not detected in any of the 3 samples.

Strontium-90 (Sr-90) was not detected in any groundwater samples during 2024.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples in 2024. There were 41 samples taken from 22 groundwater well locations. Gross Alpha (dissolved) was detected at 3 locations and concentrations range 0.6 to 2.0 pCi/L. Gross Alpha (suspended) was detected in 8 samples and concentrations ranged from 1.0 to 17.0 pCi/L. Gross Beta (dissolved) was detected in 37 samples with a range of 1.0 to 8.0 pCi/L. Gross Beta (suspended) was detected in 11 samples and ranged from 2.0 to 85.0 pCi/L.

Hard-To-Detect (HTD) analyses were performed on 27 samples in 2024. These analyses are prompted by procedure EN-AA-408-4000 and include americium-241 (Am-241), cerium-242 (Ce-242), cerium-243/244 (Ce-243/244), plutonium-238 (Pu-238), plutonium-239/240 (Pu-239/240), plutonium-241 (Pu-241), carbon-14 (C-14),

technetium-99 (Tc-99), iron-55 (Fe-55) and nickel-63 (Ni-63). All HTD analyses were less than MDC.

II.

Introduction On July 1st, 2019, Exelon Generation Company sold the Oyster Creek Nuclear Generating Station to Oyster Creek Environmental Protection, LLC (OCEP) 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 rated at 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 was designed to minimize 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 Annual Radiological Groundwater Protection Program report covers those analyses performed by Teledyne Brown Engineering (TBE) and Microbac Laboratories (formerly Environmental Inc. Midwest Labs) on samples collected in 2024.

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 by Normandeau Associates, Inc.

This section describes the general collection methods used to obtain environmental samples for the OCGS RGPP in 2024. Sample locations can be found in Table A-1, Appendix A.

1. Sample Collection Both groundwater and surface water are collected, managed, transported and analyzed in accordance with approved procedures. 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. In addition, Normandeau procedure ER-OGS-18 as well as the New Jersey Field Sampling Procedures Manual are utilized during field collection activities.

2. Sample Analyses Samples are analyzed as specified by approved analytical procedures.

These procedures include industry standards, such as the EPA Procedures for Measuring Radioactivity in Drinking Water, DOEs EML Procedures Manual (HASL 300), or by Teledyne proprietary methods.

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 (Certification ID #RN003).

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. Duplicate samples are provided to and data is shared with the New Jersey Department of Environmental Protection - Bureau of Nuclear Engineering.

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 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 and Fukushima in 2011. 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 emits very weak radiation and the associated dose is generally uniform but 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 order to achieve the stated objectives, the current program includes the following analyses for groundwater and surface water:

1. Gamma emitters

2. Tritium

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

The following parameters are conditionally analyzed in accordance with (Sampling and Analysis Protocols) of procedure EN-AA-408-4000:

1. Strontium-89 and Strontium-90

2. Selected transuranics

3. Iron-55

4. Nickel-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 and Fukushima in 2011.

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 2024. 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 24 locations were analyzed for tritium activity. Tritium was detected in 2 of 49 samples. The values ranged from <LLD to 694 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-90 were not detected in any location sampled in 2024. (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 2024. There were 41 samples taken from 22 groundwater well locations. Gross Alpha (dissolved) was detected at 3 locations and concentrations range 0.6 to 2.0 pCi/L.

Gross Alpha (suspended) was detected in 8 samples and concentrations ranged from 1.0 to 17.0 pCi/L. Gross Beta (dissolved) was detected in 37 samples with a range of 1.0 to 8.0 pCi/L. Gross Beta (suspended) was detected in 11 samples and ranged from 2.0 to 85.0 pCi/L. (Table B-I.1, Appendix B)

Gamma Emitters No gamma-emitting nuclides of activation or fission products were detected in

any groundwater sample in 2024. (Table B-I.2, Appendix B).

Hard-To-Detect Hard-To-Detect (HTD) analyses are conditionally analyzed in accordance with Attachment 3 (Sampling and Analysis Protocols) of Procedure EN-AA-408-4000. Hard-To-Detect (HTD) analyses were performed on 27 samples in 2024. All HTD analyses were less than MDC. (Table B-I.3, Appendix B)

C.

Surface Water Results Samples were collected from 1 on-site location in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below:

Tritium Samples from 1 location 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 in the dissolved and suspended fraction were performed on surface water samples in 2024. There were 2 samples taken from 1 surface water location. Gross Alpha (dissolved) was not detected in any sample. Gross Alpha (suspended) was not detected in any sample.

Gross Beta (dissolved) was detected in 2 samples with a range of 79.0 to 101.0 pCi/L. Gross Beta (suspended) was not detected in any sample (Table B-II.1, Appendix B).

Gamma Emitters Naturally occurring K-40 was detected in one sample at a concentration of 96 pCi/L. No other gamma-emitting nuclides were detected in surface water samples during 2024. (Table B-II.2, Appendix B)

Hard-To-Detect Hard-To-Detect (HTD) analyses are conditionally analyzed in accordance with Attachment 3 (Sampling and Analysis Protocols) of Procedure EN-AA-408-4000. Hard-To-Detect (HTD) analyses were performed on 2 samples in 2024. All HTD analyses were less than MDC. (Table B-I.3, Appendix B)

D.

Precipitation Water Results The precipitation recapture study at Oyster Creek was terminated in 2019 based

upon the following criteria:

1) Historic on-site groundwater tritium concentrations do not appear to have been influenced by recapture.

2) During the nine years of sampling precipitation on a quarterly frequency from four (4) indicator and one (1) control location, there was only one (1) detection of tritium greater than the MDA (0.63% detection rate). That detection was close to the detection limit, and it cannot be ruled out that this was a contamination event (no error measurement is provided in this data table).

Although a continuous release of gaseous tritium has continued from tritiated water vapor from evaporation from the refuel floor reactor cavity, the cessation of power generation in September 2018 ended the production of tritium at the site. Since tritium is created by activation of hydrogen in the reactor during fission, the quantity of tritium in the tanks and systems of the plant has only decreased since shutdown in 2018. The addition of demineralized water to the spent fuel pool/reactor cavity during decommissioning activities has diluted the tritium in the plant water. The tritium concentration in the plant-contaminated water systems has dropped by ~ 44% since decommissioning efforts began.

Flow from the main stack has also decreased by ~60% since power operation ceased as ventilation for radwaste, reactor, and turbine buildings are no longer operating and building heat loads have decreased. There is also much less contaminated water in the plant, therefore the ventilation system is transporting far less tritiated water vapor up the stack.

Monthly releases are calculated based on the existing tritium concentration of this water, typical release rates during operation were ~30,000 µCi/day but the current release rate is ~1,600 µCi/day. The combination of factors (lower inventory, reduced concentration, and reduced stack flow) produces approximately 5% of the release as compared to operation.

In summary, with the low detection rate while the plant was operational and the factors reducing detection probability since cessation of operation, it would be improbable to detect tritium in recapture samples collected under current plant conditions.

E.

Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE and Microbac (formerly Environmental Inc. Midwest Labs) are presented in the 2024 Oyster Creek AREOR. This report is part of the AREOR.

F.

Leaks, Spills, and Releases

There were no leaks or spills during 2024.

G.

Trends A groundwater remedial program was initiated in early 2009 due to the discover of leaking underground pipelines associated with the Condensate Storage Tank (CST). The damaged underground piping was replaced in late April 2009 through August 2009. A groundwater extraction well was installed on November 17, 2010, and continued to operate to remove residual tritium concentrations in the area of the CST as well as control the groundwater elevation on the western side of the protected area. Groundwater extraction ceased in October 2019 with NJDEP concurrence. Overall, the station has seen a decreasing trend in tritium values to the point where groundwater tritium is in an order of magnitude below the ODCM LLD (2,000 pCi/L).

H.

Ongoing Investigations To date, GHD completed three (3) five-year hydrogeologic investigation reports for the Station (April 2011, January 2017 and September 2022). The referenced reports summarized station activities since the implementation of the NEI groundwater initiative, including changes at the site as well as RGPP sampling activities and groundwater flow. The results of these assessments can be found in References 1, 2 and 3.

I.

Remedial 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 (Historic)

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 (Historic)

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 was terminated in 2019 with State of New Jersey concurrence.

V.

References

1. GHD, Hydrogeologic Investigation Report, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, September, 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

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2024 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

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

200 pCi/L Cape May MW-15K-1A Roadway -

Intake 357297.90 574469.50 19.0 D

200 pCi/L Cape May SW-2 RT 9 South Bridge N/A N/A SW 200 pCi/L Surface Water W-1B North Yard 358312.80 574685.40 20.0 L

200 pCi/L Cape May W-3 Intake - Access Road 357173.00 574499.10 24.0 D

200 pCi/L Cape May W-4 Intake - Access Road 357176.40 574497.70 55.0 D

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

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

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

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

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

200 pCi/L Cape May W-16 Yard - E of LLRW 357967.26 574933.03 20.0 D

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

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

200 pCi/L Cohansey MW-56I By NaOCl tanks 357305.30 574465.50 52.0 E

200 pCi/L Cohansey MW-57I Near Intake Structure 357343.71 574373.89 50.0 E

200 pCi/L Cohansey MW-59I Intake Roadway

- NW of CST 357422.14 574406.38 44.0 D

200 pCi/L Cohansey MW-64 Near Intake Structure 357343.96 574377.88 25.0 E

200 pCi/L Cape May MW-65 Intake Roadway

- NW of CST 357421.00 574402.55 25.0 D

200 pCi/L Cape May MW-67 West side of Turbine Bldg 357401.99 574540.38 25.0 L

200 pCi/L Cape May

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2024 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-71 S of Reactor Bldg 357365.52 574841.89 25.0 L

200 pCi/L Cape May MW-72 N of Reactor Bldg 357549.87 574788.52 25.0 L

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

Figure A-1 RGPP Sample Locations Surface Water, Cape May, and Cohansey Formation Oyster Creek Generating Station, 2024

Figure A-2a Groundwater Elevation and Groundwater Elevation Contours, Cape May Formation Oyster Creek Generating Station, April 2024

Figure A-2b RGPP Sample Locations Groundwater Elevation and Groundwater Elevation Contours, Cohansey Formation Oyster Creek Generating Station, April 2024

Figure A-3a Groundwater Elevation and Groundwater Elevation Contours, Cape May Formation Oyster Creek Generating Station, October 2024

Figure A-3b Groundwater Elevation and Groundwater Elevation Contours, Cohansey Formation Oyster Creek Generating Station, October 2024

APPENDIX B DATA TABLES

Intentionally left blank

TABLE B-I.1 COLLECTION SITE DATE H-3 MW-15K-1A 04/17/24

< 195 MW-15K-1A 04/17/24 Duplicate

< 0.4

< 1 3 +/- 1

< 2 MW-15K-1A 10/22/24

< 201 MW-15K-1A 10/22/24 Duplicate 2.0 +/- 0.8 7 +/- 2 3 +/- 1 13 +/- 2 MW-1A-2A 04/17/24

< 197 MW-1A-2A 10/23/24

< 200 MW-1A-2A 10/23/24 Duplicate

< 0.3

< 0.8 2 +/- 1

< 2 MW-1I-1A 04/16/24

< 191 MW-1I-1A 04/16/24 Duplicate

< 1.0

< 0.9 4 +/- 1

< 2 MW-1I-1A 10/23/24

< 200 MW-1I-1A 10/23/24 Duplicate

< 1.0 5 +/- 1 3 +/- 1 14 +/- 2 MW-56I 04/16/24

< 194 MW-56I 04/16/24 Duplicate

< 0.4

< 0.7 4 +/- 0.8

< 2 MW-56I 10/22/24

< 199 MW-56I 10/22/24 Duplicate

< 0.3

< 1 2 +/- 0.8

< 2 MW-57I 04/16/24

< 193 MW-57I 04/16/24 Duplicate

< 0.4

< 1 4 +/- 0.8 3 +/- 1 MW-57I 10/22/24

< 201 MW-57I 10/22/24 Duplicate 0.9

+/- 0.5 2 +/- 1 8 +/- 1 2 +/- 1 MW-59I 04/16/24

< 195 MW-59I 04/16/24 Duplicate

< 0.3

< 0.7 2 +/- 0.6

< 2 MW-59I 10/23/24

< 197 MW-59I 10/23/24 Duplicate

< 0.4

< 0.9 2 +/- 0.8

< 2 MW-64 04/16/24

< 197 MW-64 04/16/24 Duplicate

< 0.3 3 +/- 1 2 +/- 0.6 6 +/- 2 MW-64 10/22/24

< 203 MW-64 10/22/24 Duplicate

< 0.4

< 1 4 +/- 1.0

< 2 MW-65 04/16/24

< 193 MW-65 04/16/24 Duplicate

< 1.3

< 0.7 7 +/- 1

< 2 MW-65 10/23/24

< 1.2 1 +/- 1 6 +/- 2

< 2 MW-65 10/23/24 Duplicate

< 201 MW-67 04/16/24 206 +/- 125 MW-67 04/16/24 Duplicate

< 0.4

< 0.7 4 +/- 0.9

< 2 MW-67 10/23/24

< 207 MW-67 10/23/24 Duplicate

< 0.5

< 0.9 6 +/- 1

< 2 MW-71 04/16/24

< 190 MW-71 04/16/24 Duplicate

< 193 MW-71 04/16/24 Duplicate

< 0.4

< 0.7 2 +/- 0.8

< 2 MW-71 04/16/24 Duplicate

< 0.5

< 0.7 2 +/- 0.8

< 2 MW-71 10/23/24

< 209 MW-71 10/23/24 Duplicate

< 0.7

< 1 3 +/- 1 3 +/- 1 MW-72 04/17/24

< 192 MW-72 04/17/24 Duplicate

< 0.4

< 0.7 1 +/- 0.7

< 2 MW-72 10/22/24

< 199 MW-72 10/22/24 Duplicate

< 0.4

< 0.9 2 +/- 0.9

< 2 CONCENTRATIONS OF TRITIUM, GROSS ALPHA, AND GROSS BETA IN PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Gr-B (Sus)

Gr-B (Dis)

Gr-A (Dis)

Gr-A (Sus)

GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER (1) Total Gross Alpha and Beta result reported (not dissolved/suspended)

B-1

TABLE B-I.1 COLLECTION SITE DATE H-3 CONCENTRATIONS OF TRITIUM, GROSS ALPHA, AND GROSS BETA IN PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Gr-B (Sus)

Gr-B (Dis)

Gr-A (Dis)

Gr-A (Sus)

GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER W-10 04/16/24

< 197 W-10 04/16/24 Duplicate

< 199 W-10 04/16/24 Microbac

< 174 W-10 10/23/24

< 197 W-10 10/23/24 Duplicate

< 198 W-10 10/23/24 Duplicate

< 0.4

< 0.8 1 +/- 0.6

< 2 W-10 10/23/24 Duplicate

< 0.4

< 0.9 2 +/- 0.7

< 2 W-10 10/23/24 Microbac

< 185

< 0.7 (1)

< 0.8 (1)

W-12 04/17/24

< 197 W-12 04/17/24 Duplicate

< 0.9

< 0.7 3 +/- 1 3 +/- 1 W-12 10/22/24 W-12 10/22/24 Duplicate

< 198

< 1.1 17 +/- 4

< 3 85 +/- 6 W-13 04/17/24

< 197 W-13 10/22/24 694 +/- 154 W-13 10/22/24 Duplicate

< 0.4

< 1 2 +/- 0.7

< 2 W-15 04/17/24

< 198 W-15 10/22/24

< 200 W-15 10/22/24 Duplicate 0.6

+/- 0.3

< 0.5 3 +/- 0.7

< 2 W-16 04/17/24

< 193 W-16 10/22/24

< 201 W-16 10/22/24 Duplicate

< 0.4

< 1 4 +/- 0.8

< 2 W-1B 04/17/24

< 199 W-1B 04/17/24 Duplicate

< 0.4

< 0.9 2 +/- 0.7

< 2 W-1B 10/23/24

< 197 W-1B 10/23/24 Duplicate

< 0.5

< 0.9 3 +/- 0.7

< 2 W-24 04/17/24

< 198 W-24 10/22/24

< 199 W-24 10/22/24 Duplicate

< 0.5 3 +/- 1 1 +/- 0.7 3 +/- 1 W-3 04/16/24

< 199 W-3 04/16/24 Duplicate

< 0.9

< 0.9 8 +/- 1

< 2 W-3 04/16/24 Duplicate

< 0.5

< 0.9 2 +/- 0.8

< 2 W-3 04/16/24 Duplicate

< 198 W-3 04/16/24 Microbac

< 174

< 0.8 (1)

W-3 10/22/24 2.0

+/- 0.8 3 +/- 1 8 +/- 1 8 +/- 2 W-3 10/22/24 Duplicate

< 200 W-34 04/17/24

< 199 W-34 04/17/24 Duplicate

< 0.4

< 0.7

< 0.9

< 2 W-34 10/22/24

< 199 W-34 10/22/24 Duplicate

< 198 W-34 10/22/24 Duplicate

< 0.4

< 1

< 0.9

< 2 W-34 10/22/24 Duplicate

< 0.4

< 1

< 0.9

< 2 W-34 10/22/24 Microbac

< 186

< 0.6 (1)

< 0.9 (1)

W-4 04/16/24

< 196 W-4 10/22/24

< 0.6

< 0.8 4 +/- 0.8

< 2 W-4 10/22/24 Duplicate

< 198 W-9 04/16/24

< 0.5

< 0.9 2 +/- 0.7

< 2 W-9 04/16/24 Duplicate

< 197 W-9 10/23/24

< 1.2

< 1.0 6 +/- 1 3 +/- 1 W-9 10/23/24 Duplicate

< 195 (1) Total Gross Alpha and Beta result reported (not dissolved/suspended)

B-2

TABLE B-I.2 RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING S COLLECTION SITE DATE Nb-94 Sb-125 Cs-134 Cs-137 Eu-152 Eu-154 MW-15K-1A 04/17/24

< 5

< 5

< 5

< 15

< 6

< 4

< 17

< 11 MW-15K-1A 10/22/24

< 4

< 4

< 3

< 8

< 4

< 4

< 10

< 7 MW-1A-2A 04/17/24

< 4

< 5

< 4

< 13

< 5

< 5

< 11

< 9 MW-1A-2A 10/23/24

< 4

< 4

< 4

< 11

< 4

< 4

< 12

< 8 MW-1I-1A 04/16/24

< 4

< 7

< 5

< 13

< 5

< 6

< 17

< 11 MW-1I-1A 10/23/24

< 8

< 6

< 7

< 21

< 8

< 8

< 22

< 16 MW-56I 04/16/24

< 4

< 4

< 2

< 9

< 3

< 3

< 10

< 7 MW-56I 10/22/24

< 7

< 7

< 6

< 19

< 7

< 6

< 19

< 11 MW-57I 04/16/24

< 5

< 6

< 6

< 14

< 6

< 6

< 14

< 9 MW-57I 10/22/24

< 5

< 8

< 5

< 18

< 6

< 7

< 16

< 11 MW-59I 04/16/24

< 5

< 6

< 4

< 14

< 5

< 5

< 16

< 9 MW-59I 10/23/24

< 5

< 6

< 5

< 16

< 5

< 5

< 16

< 12 MW-64 04/16/24

< 5

< 4

< 5

< 12

< 5

< 4

< 13

< 9 MW-64 10/22/24

< 3

< 4

< 4

< 9

< 4

< 4

< 10

< 6 MW-65 04/16/24

< 4

< 5

< 5

< 15

< 6

< 5

< 16

< 11 MW-65 10/23/24

< 6

< 5

< 5

< 15

< 6

< 6

< 15

< 9 MW-67 04/16/24

< 7

< 5

< 7

< 17

< 8

< 6

< 23

< 15 MW-67 10/23/24

< 5

< 5

< 7

< 13

< 6

< 4

< 14

< 9 MW-71 04/16/24

< 6

< 6

< 6

< 16

< 7

< 6

< 17

< 9 MW-71 04/16/24 Duplicate

< 7

< 8

< 7

< 13

< 8

< 6

< 14

< 10 MW-71 10/23/24

< 8

< 11

< 8

< 18

< 8

< 8

< 22

< 15 MW-72 04/17/24

< 8

< 6

< 9

< 17

< 6

< 7

< 19

< 11 MW-72 10/22/24

< 4

< 3

< 3

< 9

< 4

< 3

< 10

< 7 W-10 04/16/24

< 7

< 6

< 6

< 15

< 8

< 6

< 19

< 9 W-10 04/16/24 Duplicate

< 7

< 7

< 8

< 14

< 7

< 7

< 20

< 11 W-10 04/16/24 Microbac

< 3

< 3 (1)

(1)

(1)

< 3 (1)

(1)

W-10 10/23/24

< 4

< 6

< 4

< 13

< 7

< 6

< 15

< 9 W-10 10/23/24 Duplicate

< 7

< 7

< 4

< 18

< 5

< 6

< 18

< 11 W-10 10/23/24 Microbac

< 6

< 4 (1)

(1)

(1)

< 5 (1)

(1)

W-12 04/17/24

< 7

< 6

< 6

< 17

< 11

< 7

< 20

< 10 W-12 10/22/24

< 8

< 6

< 6

< 19

< 7

< 8

< 20

< 12 W-13 04/17/24

< 5

< 7

< 6

< 14

< 6

< 6

< 15

< 10 W-13 10/22/24

< 7

< 6

< 7

< 19

< 7

< 7

< 20

< 19 W-15 04/17/24

< 5

< 4

< 4

< 12

< 5

< 5

< 14

< 9 W-15 10/22/24

< 9

< 8

< 7

< 19

< 8

< 9

< 22

< 14 W-16 04/17/24

< 5

< 6

< 5

< 15

< 6

< 5

< 14

< 9 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Mn-54 Co-60 (1) Nuclide Not Reported B-3

TABLE B-I.2 RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING S COLLECTION SITE DATE Nb-94 Sb-125 Cs-134 Cs-137 Eu-152 Eu-154 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Mn-54 Co-60 W-16 10/22/24

< 6

< 6

< 5

< 13

< 5

< 7

< 18

< 10 W-1B 04/17/24

< 5

< 5

< 5

< 13

< 5

< 5

< 13

< 9 W-1B 10/23/24

< 5

< 6

< 6

< 17

< 6

< 7

< 18

< 12 W-24 04/17/24

< 5

< 5

< 5

< 13

< 5

< 5

< 13

< 8 W-24 10/22/24

< 7

< 8

< 7

< 16

< 7

< 6

< 18

< 12 W-3 04/16/24

< 5

< 6

< 5

< 13

< 5

< 5

< 14

< 8 W-3 04/16/24 Duplicate

< 5

< 6

< 5

< 13

< 5

< 5

< 15

< 10 W-3 04/16/24 Microbac

< 1

< 1 (1)

(1)

(1)

< 1 (1)

(1)

W-3 10/22/24

< 9

< 8

< 8

< 25

< 10

< 8

< 25

< 15 W-34 04/17/24

< 7

< 5

< 6

< 14

< 6

< 5

< 15

< 7 W-34 10/22/24

< 6

< 7

< 6

< 18

< 7

< 7

< 17

< 10 W-34 10/22/24 Duplicate

< 4

< 4

< 4

< 12

< 6

< 4

< 11

< 12 W-34 10/22/24 Microbac

< 2

< 3 (1)

(1)

(1)

< 4 (1)

(1)

W-4 04/16/24

< 6

< 6

< 6

< 12

< 5

< 5

< 14

< 9 W-4 10/22/24

< 7

< 6

< 5

< 22

< 6

< 7

< 21

< 11 W-9 04/16/24

< 5

< 5

< 5

< 11

< 5

< 5

< 13

< 7 W-9 10/23/24

< 8

< 7

< 8

< 20

< 6

< 6

< 17

< 13 (1) Nuclide Not Reported B-4

TABLE B-I.3 COLLECTION SITE DATE Fe-55 Ni-63 MW-15K-1A 04/17/24

< 0.9 MW-15K-1A 10/22/24

< 0.1

< 0.05

< 0.4

< 0.08

< 19

< 0.4

< 31

< 27

< 1.0

< 60

< 31 MW-1A-2A 10/23/24

< 0.2

< 0.1

< 0.4

< 0.1

< 14

< 0.3

< 50

< 27

< 0.7

< 90

< 27 MW-1I-1A 04/16/24 0.6 MW-1I-1A 10/23/24

< 0.6

< 0.3

< 0.4

< 0.2

< 18

< 0.3

< 35

< 27

< 0.8

< 58

< 24 MW-56I 04/16/24

< 0.9 MW-56I 10/22/24

< 0.02

< 0.1

< 0.2

< 0.1

< 16

< 0.2

< 35

< 30

< 0.9

< 148

< 34 MW-57I 04/16/24

< 0.7 MW-57I 10/22/24

< 0.2

< 0.04

< 0.1

< 0.1

< 14

< 0.2

< 37

< 30

< 1.0

< 59

< 28 MW-59I 04/16/24

< 0.8 MW-59I 10/23/24

< 0.4

< 0.3

< 0.2

< 0.2

< 15

< 0.2

< 40

< 30

< 0.8

< 148

< 24 MW-64 04/16/24

< 0.9 MW-64 10/22/24

< 0.3

< 0.2

< 0.1

< 0.03

< 18

< 0.2

< 37

< 30

< 0.9

< 54

< 27 MW-65 04/16/24

< 0.9 MW-65 10/23/24

< 0.1

< 0.2

< 0.02

< 0.05

< 13

< 0.1

< 22

< 30

< 0.8

< 58

< 41 MW-67 04/16/24

< 0.7 MW-67 10/23/24

< 0.3

< 0.04

< 0.1

< 0.1

< 18

< 0.1

< 41

< 30

< 0.8

< 114

< 24 MW-71 04/16/24

< 0.9 Duplicate MW-71 04/16/24

< 0.9 MW-71 10/23/24

< 0.3

< 0.2

< 0.3

< 0.3

< 16

< 0.2

< 37

< 30

< 0.8

< 68

< 29 MW-72 04/17/24

< 0.9 MW-72 10/22/24

< 0.2

< 0.1

< 0.3

< 0.2

< 14

< 0.2

< 39

< 30

< 0.9

< 96

< 34 W-10 10/23/24

< 0.2

< 0.2

< 0.1

< 0.1

< 14

< 0.1

< 24

< 30

< 0.9

< 167

< 23 Duplicate W-10 10/23/24

< 0.2

< 0.08

< 0.1

< 0.1

< 16

< 0.1

< 39

< 30

< 0.7

< 186

< 24 Microbac W-10 10/23/24

< 0.3

< 0.2

< 0.1

< 0.1

< 73 0.2

< 103

< 12

< 0.6

< 443

< 231 W-12 04/17/24

< 0.7 W-12 10/22/24

< 0.1

< 0.3

< 0.3

< 0.04

< 15

< 0.1

< 24

< 30

< 0.9

< 145

< 33 W-13 10/22/24

< 0.1

< 0.03

< 0.3

< 0.1

< 18

< 0.2

< 40

< 30

< 0.9

< 162

< 26 W-15 10/22/24

< 0.03

< 0.2

< 0.2

< 0.03

< 18

< 0.0

< 33

< 30

< 0.9

< 48

< 23 W-16 10/22/24

< 0.1

< 0.2

< 0.1

< 0.1

< 14

< 0.1

< 46

< 30

< 0.8

< 49

< 23 W-1B 04/17/24

< 0.9 W-1B 10/23/24

< 0.3

< 0.07

< 0.2

< 0.1

< 16

< 0.1

< 40

< 27

< 0.9

< 179

< 24 W-24 10/22/24

< 0.1

< 0.1

< 0.1

< 0.2

< 17

< 0.2

< 39

< 30

< 0.9

< 170

< 23 W-3 04/16/24

< 0.9 Duplicate W-3 04/16/24

< 0.8 W-3 10/22/24

< 0.5

< 0.2

< 0.2

< 0.1

< 18

< 0.1

< 23

< 27

< 0.8

< 175

< 26 W-34 04/17/24

< 0.9 W-34 10/22/24

< 0.1

< 0.1

< 0.04

< 0.2

< 14

< 0.1

< 49

< 30

< 0.8

< 43

< 24 Duplicate W-34 10/22/24

< 0.1

< 0.02

< 0.2

< 0.2

< 14

< 0.1

< 44

< 30

< 0.9

< 123

< 23 Microbac W-34 10/22/24

< 0.2

< 0.10

< 0.1

< 0.1

< 72 0.1

< 103

< 12

< 0.6

< 438

< 103 W-4 10/22/24

< 0.4

< 0.09

< 0.2

< 0.1

< 14

< 0.1

< 49

< 30

< 0.8

< 128

< 23 W-9 04/16/24

< 0.9 W-9 10/23/24

< 0.3

< 0.2

< 0.1

< 0.4

< 14

< 0.4

< 36

< 30

< 0.8

< 190

< 32 CONCENTRATIONS OF HARD-TO-DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Pu-239/240 Am-241 Cm-243/244 Pu-238 Np-237 C-14 Tc-99 Sr-90 Pu-241 B-5

TABLE B-II.1 SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER COLLECTION SITE DATE H-3 SW-2 04/15/24

< 190 SW-2 10/23/24

< 200 SW-2 10/23/24 Duplicate

< 201 SW-2 10/23/24 Duplicate

< 13

< 2 101 +/- 18

< 11 SW-2 10/23/24 Duplicate

< 13

< 2 79 +/- 17

< 11 SW-2 10/23/24 Microbac

< 185

< 18 (1)

< 10 (1)

CONCENTRATIONS OF TRITIUM, GROSS ALPHA, AND GROSS BETA IN PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Gr-A (Dis)

Gr-A (Sus)

Gr-B (Dis)

Gr-B (Sus)

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

B-6

TABLE B-II.2 PROTECT COLLECTION SITE DATE Mn-54 Co-60 Nb-94 Sb-125 Cs-134 Cs-137 Eu-152 Eu-154 SW-2 04/15/24

< 4

< 4

< 5

< 12

< 4

< 4

< 11

< 8 SW-2 10/23/24

< 3

< 4

< 3

< 9

< 4

< 4

< 10

< 6 SW-2 10/23/24 Duplicate

< 4

< 5

< 4

< 12

< 5

< 5

< 12

< 8 SW-2 10/23/24 Microbac

< 3

< 2 (1)

(1)

(1)

< 3 (1)

(1)

CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA (1) Nuclide Not Reported B-7

TABLE B-II.3 COLLECTION SITE DATE Pu-239/240 Fe-55 Ni-63 SW-2 10/23/24

< 0.1

< 0.2

< 0.2

< 0.3

< 18

< 0.2

< 39

< 30

< 0.9

< 116

< 27 Duplicate SW-2 10/23/24

< 0.1

< 0.3

< 0.4

< 0.2

< 15

< 0.2

< 34

< 30

< 0.9

< 89

< 27 Microbac SW-2 10/23/24

< 0.2

< 0.01

< 0.2

< 0.2

< 79

< 0.2

< 103

< 12

< 0.5

< 449

< 180 CONCENTRATIONS OF HARD-TO-DETECTS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2024 Am-241 Cm-243/244 Pu-238 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Pu-241 Np-237 C-14 Tc-99 Sr-90 B-8

Intentionally left blank