Text

Submittal of 2024 Annual Radiological Environmental Operating Report (AREOR)
	ML25114A232
Person / Time
Site:	Salem, Hope Creek
Issue date:	04/24/2025
From:	Jennings J; Public Service Enterprise Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LR-N25-0045 SGS-AREOR-73/ HCGS-AREOR-47
	Download: ML25114A232 (1)
	v • d • e

Jason Jennings Director, Site Regulatory Compliance, PSEG Nuclear LLC PO Box 236 Hancocks Bridge, New Jersey 08038-0221 Technical Specification 6.9.1.7 (Salem)

Technical Specification 6.9.1.6 (Hope Creek)

LR-N25-0045 April 24, 2025 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354

Subject:

2024 Annual Radiological Environmental Operating Report (AREOR)

PSEG Nuclear LLC hereby submits the 2024 Annual Radiological Environmental Operating Report (Enclosure) for the period January 1, 2024 to December 31, 2024.

There are no regulatory commitments contained in this letter.

Please contact Rick Heathwaite at Rick.Heathwaite@PSEG.com with questions or comments.

Sincerely, Jason Jennings Director, Site Regulatory Compliance

Enclosure:

2024 Annual Radiological Environmental Operating Report for Salem and Hope Creek Generating Stations o PSEG I NUCLEAR SIGN

Jennings, Jason Digitally signed by Jennings, Jason Date: 2025.04.24 15:51:00

-04'00'

April 28, 2025 Page 2 LR-N25-0045 cc:

USNRC Regional Administrator Region 1 USNRC NRR Project Manager - Salem USNRC Senior Resident Inspector - Salem USNRC NRR Project Manager - Hope Creek USNRC Senior Resident Inspector - Hope Creek NJ Department of Environmental Protection, Bureau of Nuclear Engineering

LR-N25-0045 Enclosure 2024 Annual Radiological Environmental Operating Report for Salem and Hope Creek Generating Stations (Total Pages 101)

Salem and Hope Creek Generating Stations 2024 Document Number: SGS-AREOR-73/ HCGS-AREOR-47 Unit 1 Unit 2 Unit 1 Docket No. 50-272 Docket No. 50-311 Docket No. 50-354 Operating License No. DPR-070 Operating License No. DPR-075 Operating License No. NPF-057 Annual Radiological Environmental Operating Report O PSEG Nuclear LLC

Annual Radiological Environmental Operating Report YEAR: 2024 Page 1 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations AREOR (REMP) Review and Approval Confirmation in SAP (I.A.W. AD-AA-1006 SIGNATURE AUTHORITY)

SAP Order 80136643 Operation 0021 Stephen Gattuso, Salem Chemistry Manager 0022 Jason Nordin, Hope Creek Chemistry Manager 0023 William Gropp, Salem Radiation Protection Manager 0024 Robert Ronan, Hope Creek Radiation Protection Manager 0025 Matthew Mog, Salem Senior Director of Operations 0026 Joshua Moss, Hope Creek Senior Director of Operations 0027 Richard DeSanctis, Salem Plant Manager 0028 Robert McLaughlin, Hope Creek Plant Manager 04/23/2025 04/15/2025 04/13/2025 04/21/2025 04/22/2025 04/20/2025 04/10/2025 04/23/2025 Report Prepared By:__________________________________________

Rick M. Heathwaite (REMP / REC Program Manager)

Date I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 2 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS................................................................................ 4 2.0 EXECUTIVE

SUMMARY

............................................................................................................ 6 2.1 Summary of

Conclusions:

............................................................................................... 6

3.0 INTRODUCTION

........................................................................................................................ 7 4.0 SITE DESCRIPTION AND SAMPLE LOCATIONS..................................................................... 8 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS.............. 10 6.0 MAPS OF COLLECTION SITES.............................................................................................. 21 7.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES................................................................................................. 24 8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTERPRETATION OF RESULTS................................................................................................................................ 25 8.1 Environmental Direct Radiation Dosimetry Results....................................................... 25 8.2 Air Particulate and Radioiodine Sample Results........................................................... 28 8.3 Waterborne Sample Results......................................................................................... 31 8.4 Ingestion Pathway Sample Results............................................................................... 36 8.5 Terrestrial..................................................................................................................... 39 9.0 LAND USE CENSUS............................................................................................................... 42 12.1 NEI 07-07 Onsite Radiological Groundwater Monitoring Program................................. 45 12.2 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program.................... 45 12.3 Hope Creek Technical Specification Limit For Primary Water Iodine Concentration............................................................................................................... 45 12.4 Corrections to Previous Reports................................................................................... 45 13.0 BIBLIOGRAPHY...................................................................................................................... 46 TABLES Table 1, Radiological Environmental Sampling Program - Exposure Pathway - Direct Radiation....... 10 Table 2, Radiological Environmental Sampling Program - Exposure Pathway - Airborne.................... 11 Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne............... 12 Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion................... 14 Table 5, Radiological Environmental Sampling Program - Exposure Pathway - Terrestrial................. 17 Table 6, REMP Sampling Locations - Direct Radiation........................................................................ 18 Table 7, Reporting Levels for Radioactivity Concentrations in Environmental Samples....................... 24 Table 8, Maximum Values for the Lower Limit of Detection (LLD)........................................................ 24 Table 9, Air Particulate and Radioiodine Comparison of Current Year and Historic Data..................... 30 Table 10, Land Use Census - Nearest Pathway within 5 miles............................................................ 42 Table 11, Sample Deviation Summary................................................................................................. 43 Table 12, Environmental Direct Radiation Dosimetry Sample Results................................................. 60 Table 13, Concentrations of Gamma Emitters in Quarterly Composites of Air Particulates, 2024........ 62 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 3 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 14, Concentrations of Gross Beta Emitters in Air Particulates, 2024.......................................... 64 Table 15, Concentrations of Iodine-131 in Filtered Air, 2024................................................................ 66 Table 16, Concentrations of Tritium in Surface Water, 2024................................................................ 68 Table 17, Concentrations of Iodine-131 and Gamma Emitters in Surface Water, 2024........................ 69 Table 18, Concentrations of Gross Alpha and Gross Beta Emitters, and Tritium in Raw and Treated Potable Water, 2024............................................................................................................................ 72 Table 19, Concentrations of Iodine-131 and Gamma Emitters in Raw and Treated Potable Water, 2024

............................................................................................................................................................ 73 Table 20, Concentration of Gross Alpha and Beta Emitters, and Tritium in Well Water, 2024.............. 74 Table 21, Concentrations of Iodine-131 and Gamma Emitters in Well Water, 2024............................. 75 Table 22, Concentrations of Gamma Emitters in Sediment, 2024........................................................ 76 Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2024........................................ 77 Table 24, Concentrations of Gamma Emitters in Edible Fish, 2024...................................................... 80 Table 25, Concentrations of Gamma Emitters in Blue Crabs, 2024...................................................... 81 Table 26, Concentrations of Gamma Emitters in Broadleaf Vegetation (FPL), 2024............................ 82 Table 27, Concentrations of Gamma Emitters in Vegetables (FPV), 2024........................................... 83 Table 28, Concentrations of Gamma Emitters in Fodder Crops, 2024................................................. 84 Table 29, Concentrations of Gamma Emitters in Game, 2024............................................................. 85 Table 30, Concentrations of Gamma Emitters in Soil, 2022**.............................................................. 86 FIGURES Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations [7]............... 7 Figure 2, REMP Sample Locations (On-Site Sampling Locations To 1 Mile)........................................ 21 Figure 3, REMP Sample Locations (Off-Site Sampling Locations 1 to 10 Miles).................................. 22 Figure 4, REMP Sample Locations (Off-Site Sampling Locations Greater Than 10 Miles)................... 23 Figure 5, Air Particulate: Analysis for Gross Beta, Average Mean for All Indicator Vs. Control............. 30 Figure 6, Surface Water Tritium Results.............................................................................................. 32 Figure 7, Cesium-137 Activity in Soil 1974 Through 2022.................................................................... 40 Figure 8, TBE vs GEL Gross Beta....................................................................................................... 93 ATTACHMENTS, Data Table Summary.................................................................................................... 49, Complete Data Table for All Analysis Results Obtained In 2024................................... 59, Cross check Intercomparison Program......................................................................... 87, Errata/Corrections to Previous Reports......................................................................... 97 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 4 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 1.0 LIST OF ACRONYMS AND DEFINITIONS

1.

Airborne Activity Sampling: Continuous sampling of air through the collection of particulates and radionuclides on filter media.

2.

ARERR: Annual Radioactive Effluent Release Report

3.

AREOR: Annual Radiological Environmental Operating Report

4.

BWR: Boiling Water Reactor

5.

Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.

6.

Control: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the station.

7.

Curie (Ci): A measure of radioactivity; equal to 3.7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.

8.

Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using Thermoluminescent Dosimeters (TLD), Optically Stimulated Luminescence Dosimeters (OSLD) and pressurized ionization chambers.

9.

EPA: Environmental Protection Agency

10.

GPI: Groundwater Protection Initiative

11.

Grab Sample: A single discrete sample drawn at one point in time.

12.

Indicator: A sampling location that is likely to be affected by plant effluents due to its proximity and/or direction from the plant.

13.

Ingestion Pathway: The ingestion pathway includes milk, fish, drinking water and garden produce. Also sampled (under special circumstances) are other media such as vegetation or animal products when additional information about particular radionuclides is needed.

14.

ISFSI: Independent Spent Fuel Storage Installation

15.

Lower Limit of Detection (LLD): An a priori measure of the detection capability of a radiochemistry measurement based on instrument setup, calibration, background, decay time, and sample volume. An LLD is expressed as an activity concentration. The MDA is used for reporting results. LLD are specified by a regulator, such as the NRC and are typically listed in the ODCM.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 5 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

16.

MDA: Minimum Detectable Activity. For radiochemistry instruments, the MDA is the a posteriori minimum concentration that a counting system detects. The smallest concentration or activity of radioactive material in a sample that will yield a net count above instrument background and that is detected with 95%

probability, with only five % probability of falsely concluding that a blank observation represents a true signal.

17.

MDC: Minimum Detectable Concentration. Essentially synonymous with MDA for the purposes of radiological monitoring.

18.

Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.

19.

Microcurie: 3.7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.

20.

N/A: Not Applicable

21.

NEI: Nuclear Energy Institute

22.

NIST: National Institute of Standards and Technology.

23.

NRC: Nuclear Regulatory Commission

24.

ODCM: Offsite Dose Calculation Manual

25.

OSLD: Optically Stimulated Luminescence Dosimeter

26.

pCi/L: picocuries / Liter

27.

PWR: Pressurized Water Reactor

28.

REMP: Radiological Environmental Monitoring Program

29.

TLD: Thermoluminescent Dosimeter I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 6 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 2.0 EXECUTIVE

SUMMARY

Salem and Hope Creek Generating Stations Radiological Environmental Monitoring Program (REMP) was established prior to the station becoming operational to provide information on background radiation present in the area. The goal of SGS/HCGS REMP is to evaluate the impact of the station on the environment. Environmental samples from different media are monitored as part of the program in accordance with specifications detailed in the Offsite Dose Calculation Manual Common REMP (ODCM). The program compares data from Indicator locations near the plant, to Control locations farther away from the site to assess operation impacts.

The Annual Radiological Environmental Operating Report (AREOR) provides data obtained through analyses of environmental samples collected at SGS/HCGS for the reporting period of January 1st through December 31st, 2024. During that time period 1636 analyses were performed on 1280 samples and there was no instance of radioactivity from plant effluents observed in the environment that exceeded any Reporting Levels identified in Salem and Hope Creek Common ODCM Table 3.12-2

[23]. Also, in assessing all the data gathered for this report and comparing these results with preoperational data it was concluded that the operation of SGS/HCGS, had no significant radiological impact on the health and safety of the public or on the environment.

2.1 Summary of

Conclusions:

There was one instance of plant related radionuclides above baseline during the reporting period January 1 through December 31, 2024. Tritium was detected in Surface Water but was below reporting levels (see Figure 6, Surface Water Tritium Results). Naturally occurring radionuclides are present in the Earth's crust and atmosphere and exists in detectable quantities throughout the world. It is common to detect naturally occurring radionuclides in many of the samples collected for REMP.

Some examples of naturally occurring radionuclides that are frequently seen in samples are potassium-40, beryllium-7, actinium-228 (present as a decay product of radium-228), and radium-226. Additionally, some relatively long-lived anthropogenic radioisotopes, such as strontium-90 and cesium-137, are also seen in some REMP samples; these radionuclides exist in measurable quantities throughout the world as a result of fallout from historic atmospheric nuclear weapons testing. Detailed information on the exposure of the U.S. population to ionizing radiation can be found in NCRP Report No. 160 [1].

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 7 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

3.0 INTRODUCTION

The Radiological Environmental Monitoring Program (REMP) provides data on measurable levels of radiation and radioactive materials in the environment. This program also evaluates the relationship between quantities of radioactive materials released from the plant and resultant doses to individuals from principal pathways of exposure. In this capacity, REMP provides a check on the effluent release program and dispersion modeling to ensure that concentrations in the environment due to radioactive effluents conform to the As Low as Is Reasonably Achievable (ALARA) design objectives of 10 CFR 50, Appendix I [2], and implements the requirements of Section IV.B.2 and IV.B.3 of Appendix I. REMP is designed to conform to the Nuclear Regulatory Commission (NRC) Regulatory Guide 4.1 [3], NUREG 1301/1302 [4] [5],

and the 1979 NRC Branch Technical Position [6].

Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations [7]

Quality assurance aspects of the sampling program and TLD/OSLD data collection are conducted in accordance with Regulatory Guides 4.15 [8] and 4.13 [9]. REMP also adheres to the requirements of New Jersey, SGS/HCGS Technical Specifications, and Common REMP Offsite Dose Calculation Manual (ODCM). These governing documents dictate the environmental sampling, sample analysis protocols, data reporting and quality assurance requirements for the environmental monitoring program.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 8 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations The Annual Radiological Environmental Operating Report provides summaries of the environmental data from exposure pathways, interpretations of the data, and analyses of trends of the results. Routinely monitored pathways include ingestion, inhalation, and direct radiation. Routes of exposure are based on site specific information such as meteorology, receptor locations, and water usage around the plant.

4.0 SITE DESCRIPTION AND SAMPLE LOCATIONS The Site is located in Lower Alloways Creek Township, Salem County, New Jersey.

SGS consists of two operating pressurized water nuclear power reactors. SGS Unit 1 has an approximate net electrical rating of 1,180 megawatts electric (MWe) and SGS Unit 2 has an approximate net electrical rating of 1,178 MWe. The licensed core thermal power rating for both Units is 3,459 megawatts thermal (MWth). HCGS consists of an operating boiling water nuclear power reactor, which has an approximate net electrical rating of 1,212 MWe. The licensed core thermal power rating is 3,902 MWth.

The Site is located on a man-made peninsula on the east bank of the Delaware River called Artificial Island. The peninsula was created by the deposition of hydraulic fill from dredging operations. The surrounding environment is characterized mainly by the Delaware River Estuary, extensive tidal marshlands, and low-lying meadowlands.

These land types make up a vast majority of the land area within five miles of the Site, with most of the remaining land used for agriculture.

Since 1968, a Radiological Environmental Monitoring Program (REMP) has been conducted at the Site. Starting in December 1972, a more extensive radiological monitoring program was initiated in preparation for the operation of SGS Unit 1. The operational REMP was initiated in December 1976 when SGS Unit 1 achieved criticality.

SGS/HCGS sampling media are selected based on site specific information such as meteorology, receptor locations, and water usage around the plant. Sampling and analysis frequencies are documented in the Offsite Dose Calculation Manual and site procedures. Required sampling, analysis frequencies and location of sample collected are captured in the following tables and figures:

Table 1, Radiological Environmental Sampling Program - Exposure Pathway -

Direct Radiation Table 2, Radiological Environmental Sampling Program - Exposure Pathway -

Airborne Table 3, Radiological Environmental Sampling Program - Exposure Pathway -

Waterborne Table 4, Radiological Environmental Sampling Program - Exposure Pathway -

Ingestion I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 9 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 5, Radiological Environmental Sampling Program - Exposure Pathway -

Terrestrial Table 6, REMP Sampling Locations - Direct Radiation Figure 2, REMP Sample Locations (On-Site Sampling Locations To 1 Mile)

Figure 3, REMP Sample Locations (Off-Site Sampling Locations 1 to 10 Miles)

Figure 4, REMP Sample Locations (Off-Site Sampling Locations Greater Than 10 Miles).

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 10 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS Table 1, Radiological Environmental Sampling Program - Exposure Pathway - Direct Radiation Requirement Sample Location Description, Distance, and Direction Sampling Collection/

Frequency Type of Analyses DIRECT RADIATION

a. Dosimeters (IDM)

Fifty-nine routine monitoring locations with two or more dosimeters placed as follows:

An inner ring of locations, one in each of the land based meteorological sectors in the general area of the SITE BOUNDARY; and An outer ring of locations, one in each of the land based meteorological sector in the 5 to 11 km (3.1 - 6.8 miles) range from the site; and The balance of the locations placed in areas of special interest such as population centers, nearby residences, and schools and in one or two areas to serve as control locations.

See Table 6, REMP Sampling Locations -

Direct Radiation Quarterly Gamma dose I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 11 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 2, Radiological Environmental Sampling Program - Exposure Pathway - Airborne Requirement Sample Location Description, Distance, and Direction Sampling Collection/

Frequency Type and Frequency of Analyses ATMOSPHERIC

a. Air Particulate (APT)

b. Air Iodine (AIO) 3 samples close to the Site Boundary: 05X1, 06S1, 15S2.

One duplicate sample from close to the site boundary: 05S2.

3 samples from different land-based sectors: 01F1, 02F6, 05D1.

One sample from the vicinity of a community having a highest annual average ground level D/Q: 16E1.

One sample from a control location; for example, 15 - 30 km distant (9.3

- 18.6 miles) and in the least prevalent wind direction: 14G1 05X1 0.86 mi. E; site access road 05S2 0.86 mi. E; site access road 06S1 0.19 mi. ESE; station personnel gate 15S1 0.57 mi. NW; near river and HCGS barge slip 15S2 0.59 mi. NW; near river and HCGS barge slip 05D1 3.5 mi. E; local farm along SGS/HCGS access road.

16E1 4.1 mi. NNW; Port Penn, DE 01F1 5.7 mi. N; Fort Elfsborg, NJ 02F6 7.3 mi. NNE; Energy & Envmt Resource Center, Salem NJ 14G1 13.4 mi. WNW; Route 286, Bethel Church Road, DE Particulate:

Continuous sampler operation with sample collection weekly or more frequently if required by dust loading Gross Beta /

weekly Gamma isotopic analysis /

quarterly composite Iodine:

Continuous sampler operation with sample collection weekly or more frequently if required by dust loading Iodine-131 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 12 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne Requirement Sample Location Description, Distance, and Direction Sampling Collection/

Frequency Type of Analyses Surface Water (SWA)

One sample upstream: 01F2.

One sample downstream: 07E1.

One sample outfall: 11A1.

One sample cross-stream (mouth of Appoquinimink River): 12B1.

And an additional location in the Chesapeake & Delaware Canal: 16F1.

11A1 0.22 mi. SW; SGS outfall area 11A1A 0.15 mi. SE; Located in the plant barge slip area 12B1 1.8 mi. WSW; West bank of Delaware River 12B1A 3.7 mi. NW; Tip of Augustine Beach Boat Ramp 07E1 4.4 mi. SE; riverbank 1 mi. W of Mad Horse Creek 07E1A 9.2 mi. SE; Located at the end of Bayside Road, NJ 01F2 7.1 mi. N; midpoint of Delaware River 16F1 6.9 mi. NNW; C&D Canal, DE 16F1A 6.5 mi. NNW; Located at the C&D Canal Tip, DE Semi-Monthly (composited)

Gamma scan Tritium Potable Water (Drinking Water) (PWR, PWT)

Although no potable water samples are required as liquid effluents discharged from SGS/HCGS do not directly affect this pathway and it is not required by SGS/HCGS ODCM, one raw and one treated water sample from a public water supply (City of Salem Water and Sewer Department) are collected: 02F3 as management audit samples.

02F3 8.0 mi. NNE; Salem Water Company Monthly (composited weekly)

Gross alpha Gross beta Tritium Gamma scan Iodine-131 Well Water (Ground) (WWA)

Although wells in the vicinity of SGS/HCGS are not directly affected by plant operations so sampling is not required by SGS/HCGS ODCM, samples of 03E1 farms well are collected as management audit samples.

03E1 4.2 mi. NE; local farm Monthly Gamma scan Gross alpha Gross beta Tritium I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 13 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne Requirement Sample Location Description, Distance, and Direction Sampling Collection/

Frequency Type of Analyses Sediment (ESS)

One sample from downstream area:

07E1.

One sample from cross-stream area and control location: 12B1.

One sample from outfall area: 11A1.

One sample from upstream, the C & D Canal: 16F1.

One sample from shoreline area: 05A1.

One sample from Cooling Tower Blowdown discharge: 15A1.

One sample south storm drain discharge line: 15A2.

05A1 0.89 mi. E, shoreline 07E1 4.4 mi. SE; riverbank 1 mi. W of Mad Horse Creek 11A1 0.22 mi. SW; SGS outfall area 12B1 1.8 mi. WSW; West bank of Delaware River 15A1 0.69 mi. NW; HCGS outfall area 15A2 0.66 mi. NW; South Storm Drain outfall 16F1 6.9 mi. NNW; C&D Canal, DE Semi-Annually Gamma scan I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 14 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion Requirement Sample Location Description, Distance, and Direction Sampling Collection/

Frequency Type of Analyses Milk (MLK)

Samples from milking animals in 3 locations within 5 km distance (3.1 miles) having the highest dose potential. If there are none, then 1 sample from milking animals in each of 3 areas between 5 - 8 km distant (3.1 - 5.0 miles) where doses are calculated to be greater than 1 mrem per yr: 13E3.

1 Sample from milking animals at a control location 15 30 km distant (9.3 - 18.6 miles):

02G3.*

NOTE: Milk animals are not prevalent in the vicinity of the plant. Only one farm met the requiem for milk. In lieu of samples, broad-leaf vegetation sampling is being conducted.

13E3 5.0 mi. W; local farm, DE 02G3 11.8 mi. NNE; Local Milk Farm, Corner of Routes 540 & 45, Mannington, NJ 14F4 7.6 mi. WNW; local farm Semi-monthly (when animals are on pasture)

Gamma scan Iodine-131 Monthly (when animals are not on pasture)

Gamma scan Iodine-131 Edible Fish (ESF)

One sample of each commercially and recreationally important species in vicinity of plant discharge area: 11A1.

One sample of same species in area not influenced by plant discharge: 12B1, and an additional location downstream: 07E1.

07E1 4.4 mi. SE; riverbank 1 mi. W of Mad Horse Creek 11A1 0.22 mi. SW; SGS outfall area 12B1 1.8 mi. WSW; West bank of Delaware River Semi-Annually Gamma scan (flesh)

Listed as 03G1 in ODCM, see Section 11.0 PROGRAM CHANGES.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 15 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion Requirement Sample Location Description, Distance, and Direction Sampling Collection/

Frequency Type of Analyses Blue Crabs (ECH)

One sample of each commercially and recreationally important species in vicinity of plant discharge area 11A1.

One sample of same species in area not influenced by plant discharge 12B1.

11A1 0.22 mi. SW; SGS outfall area 12B1 1.8 mi. WSW; West bank of Delaware River Semi-Annually Gamma scan (on edible portions)

Vegetables (FPL, FPV)

Although the Delaware River at the location of SGS/HCGS is a brackish water source and is not used for irrigation of food products and so sampling is not required by SGS/HCGS ODCM, samples of vegetables are collected as management audit samples from various locations during harvest. In addition, broad leaf vegetation is collected from various offsite locations as well as being planted & collected onsite (06S1, 16S1, 10D1). This is in lieu of having a milk farm within 5 km (3.1 miles) of the Site.

Samples were not taken from these locations in 2024. They are Management Audit samples that are not required by the ODCM and may not be sampled every year due to crop rotation.

06S1 0.17 mi. SE 16S1 0.57 mi. NNW 10D1 3.9 mi. SSW; Taylors Bridge Spur 01G1 10.9 mi. NNE; Rte. 49, South Broadway 03H5 25 mi. NE; Farm Market, Rt 77 02F9 7.5 mi. NNE; Local Farm, Tilbury Rd, Salem 02G2*

13.5 mi. NNE; Local Farm; Pointers Auburn Road 01S3*

0.58 mi. N; Garden 15S2*

0.57 mi. NNW 02F10*

9.2 mi. NNE; Local Farm, South Broadway, Pennsville 03F6*

6.5 mi. NE; Local Farm, Salem/Hancocks Bridge Road 03F7*

7.2 mi. NE; Local Farm, Beasley Neck Road, RD#3 03F8*

9.28 mi. NNE Circle M Orchard 14F4*

7.6 mi. WNW; local farm 15F4 7.0 mi. NW; local farm; Port Penn Road; DE 02G4*

11.3 mi. NNE; Rt 45 & Welchville Rd, Mannington, NJ 09G1*

10.3 mi. S; Woodland Beach Rd., Smyrna, DE 09G2*

10.7 mi. S; Woodland Beach Rd, Smyrna, DE Monthly (during growing season)

Gamma scan I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 16 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion Requirement Sample Location Description, Distance, and Direction Sampling Collection/

Frequency Type of Analyses Fodder Crops (VGT)

Although not required by SGS/HCGS ODCM, samples of crops normally used as cattle feed (silage) were collected from milk farms as management audit samples: 14F4, 02G3, 13E3.

13E3 5.0 mi. W; Local Farm, Odessa, DE 14F4 7.6 mi. WNW; local farm 02G3 11.8 mi. NNE; Local Milk Farm Annually (at harvest)

Gamma scan Game (GAM)

Although not required by SGS/HCGS ODCM, game samples were collected as management audit samples from two indicator locations: 03E1 and 13E3

Sample was not taken at this location in 2024 03E1*

4.2 mi. NE; Local Farm 13E3 5.0 mi. W; Local Farm, Odessa, DE Annually Gamma scan I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 17 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 5, Radiological Environmental Sampling Program - Exposure Pathway - Terrestrial Requirement Number of Representative Samples and Sample Locations Sampling Collection/

Frequency Type of Analyses Soil (SOL)

Although not required by SGS/HCGS ODCM, samples of soil are collected as management audit samples.

10D1 3.9 mi. SSW; Taylors Bridge Spur 13E3 5.0 mi. W; Local Farm, Odessa, DE 14F4 7.6 mi. WNW; Local Farm 16E1 4.1 mi. NNW; Port Penn 02F9 7.5 mi. NNE; Local Farm, Tilbury Rd, Salem 02G3 11.8 mi. NNE; Local Milk Farm 03G1 16.5 mi. NE; Milk Farm, Woodstown 05F1 6.5 mi. E; Canton 06S1 0.23 mi. ESE Every 3 years (2016-2019-2022)

Gamma scan I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 18 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 6, REMP Sampling Locations - Direct Radiation Site #

Location Type Sector Distance (miles)

Description 01Q1 Special Interest N

0.58 N side of road near ISFSI pad 02S2a Inner Ring NNE 0.41 Lamp pole 65 near HC switch yard 07S1 Inner Ring SE 0.12 Station personnel gate 08S1 Inner Ring SSE 0.14 Fuel oil storage 08S2 Inner Ring SSE 0.17 Fuel oil storage 10S1 Inner Ring SSW 0.11 Circulating water building 11S1 Inner Ring SW 0.12 Circulating water building 12S1 Inner Ring WSW 0.09 Outside security fence 14S2 Inner Ring WNW 0.12 Outside security fence 15S1 Inner Ring NW 0.57 Near river and HCGS barge slip 15S2 Inner Ring NW 0.59 Near river and HCGS barge slip 15S3 Inner Ring NW 0.17 Outside security fence 16S1 Inner Ring NNW 0.57 On road near fuel oil storage tank 16Q2 Special Interest NNW 0.6 Near security firing range 01X2 Inner Ring (SB)

N 0.6 382 feet from TLD 01Q1 02X4 Inner Ring (SB)

NNE 0.59 In the equipment laydown area 03X1 Inner Ring (SB)

NE 0.58 Behind refrigeration building 04X1 Inner Ring (SB)

ENE 0.6 Access road near intersection to LDC 05X1 Inner Ring (SB)

E 0.86 Site access road 06X2 Inner Ring (SB)

ESE 0.23 Area around helicopter pad 16X3 Inner Ring (SB)

NNW 0.88 Consolidated spoils facility 04D2 Outer Ring ENE 3.9 Alloway Creek Neck Road 05D1 Outer Ring ENE 3.5 Local farm along SGS/HCGS access road.

10D1 Outer Ring SSW 3.9 Taylor's Bridge Spur, DE 14D1 Outer Ring WNW 3.3 Bay View, DE I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 19 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 6, REMP Sampling Locations - Direct Radiation Site #

Location Type Sector Distance (miles)

Description 15D1 Outer Ring NW 3.7 Route 9, Augustine Beach, DE 02E1 Outer Ring NNE 4.4 Local farm, NJ 03E1 Outer Ring NE 4.1 Local farm, NJ 12E1 Outer Ring WSW 4.4 Thomas Landing, DE 13E1 Outer Ring W

4.1 Diehl House Lab, DE 16E1 Outer Ring NNW 4.1 Port Penn, DE 11E2 Outer Ring SW 5

Route 9, DE 01F1 Outer Ring N

5.7 Fort Elfsborg, NJ 02F2 Outer Ring NNE 8.5 Salem Substation, Salem, NJ 02F5 Special Interest NNE 7.3 Salem High School, Salem, NJ 02F6 Outer Ring NNE 7.3 Energy & Envmt Resource Center, Salem, NJ 03F2 Outer Ring NE 5.1 Hancocks Bridge, NJ, Munc Bldg 03F3 Special Interest NE 8.6 Quinton Township Elem. School, NJ 04F2 Outer Ring ENE 6

Mays Lane, Harmersville, NJ 05F1 Outer Ring E

6.4 Canton, NJ 06F1 Outer Ring ESE 6.4 Stow Neck Road, NJ 07F2 Outer Ring SE 9.3 Bayside, NJ 09F1 Outer Ring S

5.3 Off Route #9, DE 09F2 Outer Ring S

5.2 Collins Beach boat ramp.

10F2 Outer Ring SSW 5.7 Route #9, DE 11F1 Outer Ring SW 6

Taylor's Bridge, DE 12F1 Outer Ring WSW 9.4 Townsend Elementary School, DE 13F2 Outer Ring W

6.5 Odessa, DE 13F3 Special Interest W

9.3 Redding Middle School, Middletown, DE 13F4 Special Interest W

9.8 Middletown, DE I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 20 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 6, REMP Sampling Locations - Direct Radiation Site #

Location Type Sector Distance (miles)

Description 14F2 Outer Ring WNW 6.7 Route 13 and Boyds Corner Rd, DE 15F3 Outer Ring NW 5.4 Port Penn Rd. At Pole Bridge Rd., DE 16F2 Special Interest NNW 8.1 Delaware City Public School, DE 01G3 Control N

19 N. Church Street Wilmington, DE 03G1 Outer Ring NE 16.5 Local farm, NJ 10G1 Control SSW 11.6 Smyrna, DE 14G1 Outer Ring WNW 13.4 Route 286, Bethel Church Road, DE 16G1 Outer Ring NNW 15.1 Wilmington Airport, DE 03H1 Control NE 33.1 National Park, NJ I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 21 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 6.0 MAPS OF COLLECTION SITES Figure 2, REMP Sample Locations (On-Site Sampling Locations To 1 Mile)

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 22 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Figure 3, REMP Sample Locations (Off-Site Sampling Locations 1 to 10 Miles)

Annual Radiological Environmental Operating Report YEAR: 2024 Page 23 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Figure 4, REMP Sample Locations (Off-Site Sampling Locations Greater Than 10 Miles) 8 ru H.tl 7 J

Annual Radiological Environmental Operating Report YEAR: 2024 Page 24 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 7.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Table 7, Reporting Levels for Radioactivity Concentrations in Environmental Samples Radionuclide Water (pCi/L)

Air Particulates or Gases (pCi/m3)

Fish (pCi/kg-wet)

Milk (pCi/L)

Food Products (pCi/Kg-wet)

H-3 30,0001 NA NA NA NA Mn-54 1,000 NA 30,000 NA NA Fe-59 400 NA 10,000 NA NA Co-58 1,000 NA 30,000 NA NA Co-60 300 NA 10,000 NA NA Zn-65 300 NA 20,000 NA NA Zr-Nb-95 400 NA NA NA NA I-131 202 0.9 NA 3

100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 NA NA 300 NA Table 8, Maximum Values for the Lower Limit of Detection (LLD)

Radionuclide Water (pCi/L)

Air Particulates or Gases (pCi/m3)

Fish (pCi/kg-wet)

Milk (pCi/L)

Food Products (pCi/Kg-wet)

Sediment (pCi/Kg-dry)

Gross Beta 4

0.01 NA NA NA NA H-3 3,0003 NA NA NA NA NA Mn-54 15 NA 130 NA NA NA Fe-59 30 NA 260 NA NA NA Co-58, Co-60 15 NA 130 NA NA NA Zn-65 30 NA 260 NA NA NA Zr-Nb-95 15 NA NA NA NA NA I-131 154 0.07 NA 1

60 NA Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 NA NA 15 NA NA 1 For surface water samples: If a drinking water pathway exists, a value of 20,000 pCi/L shall be used.

2 For surface water samples: If a drinking water pathway exists, a value of 2 pCi/L shall be used.

3 For surface water samples: If a drinking water pathway exists, a value of 2,000 pCi/L shall be used.

4 For surface water samples: If a drinking water pathway exists, a value of 1 pCi/L shall be used.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 25 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTERPRETATION OF RESULTS At most nuclear stations, data was collected prior to plant operation to determine background radioactivity levels in the environment. Annual data is routinely compared to preoperational and/or 10-year average values to determine if changes in the environs are present. Strict comparison is difficult to make due to fallout from historical nuclear weapon testing. Cesium-137 can be routinely found in environmental samples as a results of above ground nuclear weapons testing. It is important to note, levels of Cs-137 in environment are observed to fluctuate, for example as silt distributions shift due to natural erosion and transport processes, Cs-137 may or may not be observed in sediment samples. Results from samples collected and analyzed during the year, 2024, are described below.

In the following sections, results from direct radiation, air, water, and food products analyzed as part of REMP in 2024 will be discussed. Sampling program descriptions and deviations will also be discussed.

8.1 Environmental Direct Radiation Dosimetry Results Dose is measured as net exposure (field reading less transit reading) normalized to 91-day quarters. Data is treated and analyzed consistent with ANSI/HPS N13.37-2014, which compares the measured dose for each location to the baseline background dose for that location. Environmental dose rates vary by location, depending on geological and land use considerations, and remain relatively constant for any given location (unless land use changes). Some facilities observe seasonal variation in environmental doses. Baseline Background Doses have been determined for both quarterly and annual measurements at each location using historical field measurements. Minimum Differential Doses for Annual and Quarterly periods have been determined based on 3-times the 90th percentile standard deviation for monitoring locations. Doses that exceed the Minimum Differential Dose value above the Baseline Background Dose are considered to indicate Facility-Related Dose; a quality assurance review is performed to verify that any results indicating Facility-Related Dose are accurate.

ANSI/HPS N13.37-2014 uses the concept of minimum differential dose (MDD), which is the minimum facility-related dose that can be detected above the baseline background. Due to natural background variations and measurement sensitivities and uncertainties, minimum differential dose is not zero. MDD is calculated based on performance of the dosimetry system in the environment and is about 5 mrem per quarter and 10 mrem per year. If a dosimeter indicates dose greater than background plus MDD, then the net dose (above background) is reported as Facility Related Dose.

Ambient radiation levels in the environment were monitored at locations on the Site and in the surrounding areas with pairs of passive dosimeters (PD) supplied and analyzed by Stamford Dosimetry/Environmental Dosimetry Co. Packets containing the PDs were placed in the owner-controlled area, around the Site at various distances, and in each land based meteorological sector, Table 6, REMP Sampling Locations - Direct Radiation.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 26 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations The PDs at each location are changed and analyzed quarterly. The laboratory utilizes a Panasonic based system using UD-814 dosimeters that are constructed of three rectangular, lead-shielded (protects against low-energy gamma radiation) Teflon wafers, impregnated with 25% calcium sulfate phosphor (CaSO4:Dy) to monitor gamma radiation. Additionally, each PD has one lithium borate (LiBO:Mn) element to monitor beta radiation (which is not used). Two PDs (Panasonic type UD-814) are placed at each location.

In 2019 PSEG implemented American National Standards Institute (ANSI) N13.37-2014 Environmental Dosimetry - Criteria for System Design and Implementation [10]

for comparing each PD location dose result to its historical background dose. Per the standard a well-functioning dosimetry system should be able to detect a 5 mrem difference in the quarterly data and a 10 mrem difference in the yearly data above background.

8.1.1 Quarterly Facility Dose During this calendar year 2024, a total of 236 samples were collected and analyzed in accordance with the requirements in Table 1, Radiological Environmental Sampling Program - Exposure Pathway - Direct Radiation.

All of the quarterly inner ring and outer ring indicator locations (Table 6, REMP Sampling Locations - Direct Radiation) resulted in non-detectable dose.

All of the quarterly offsite special interest locations resulted in non-detectable dose.

All of the quarterly control locations resulted in non-detectable dose.

The direct radiation sample results are in Table 12, Environmental Direct Radiation Dosimetry Sample Results.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 27 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 8.1.2 Calculated Annual Facility Dose All annual inner ring (Table 6, REMP Sampling Locations - Direct Radiation) resulted in non-detectable dose except for location 16X3 (13.6 mrem annual dose). See section 8.1.4 TLD anomalies.

All annual offsite outer ring locations resulted in non-detectable dose.

All annual offsite special interest locations resulted in non-detectable dose.

The direct radiation sample results are in Table 12, Environmental Direct Radiation Dosimetry Sample Results.

8.1.3 ISFSI Dose Two on site ISFSI locations, in the controlled area, 01Q1 and 16Q2 showed measurable dose rates above background as seen in Table 12. The net dose radiation levels as measured by these special interest locations ranged from 12.4 to 19.0 mrem/Standard Quarter and annual doses of 73.2 and 54.7 mrem for Locations 01Q1 and 16Q2, respectively.

Dose to the nearest resident due to direct radiation from ISFSI was calculated to be 0.006 mrem/yr, which is a very small fraction (0.024%) of the 25 mrem/yr limit per 40 CFR 190 and 10 CFR 72.104. Both regulations limit the dose to a real member of the public to 25 mrem in a year to the total body. The calculation was performed using the formula provided in ANSI/HPS N13.37-2014 as follows:

Where:

D1 = Dose that was measured from TLD Location 16Q2 (1Q1 was also calculated and had a slightly lower dose)

D2 = Dose that will be extrapolated to Nearest Resident R1 = Distance from the source to the location where D1 was obtained. (Distance from ISFSI to TLD at 16Q2)

R2 = Distance from ISFSI to the location that dose will be extrapolated (Nearest Resident)

OF = Occupancy Factor (1 = full time)

(

)

(

)

2 2

2 1

1 2

/

=

D D

R R

OF I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 28 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Location R1 (ft)

D1 Annual Net Dose (mrem)

R2 (ft)

OF D2 Annual Net Dose (mrem)

Nearest Resident 203 54.7 19,536 1.0 5.91E-03 8.1.4 TLD anomalies TLD 16X3 had a net positive annual dose of 13.6 mrem for 2024. The location of 16X3 is near the water in the Windport parcel 1,324 feet from the ISFSI pad. The data is anomalous because other TLDs closer to the source, i.e., ISFSI pad, do not have net positive results. An additional dosimeter will be added to this location to determine if the dose is accurate.

8.2 Air Particulate and Radioiodine Sample Results Air particulate filters and charcoal canisters were collected from locations specified in Table 2, Radiological Environmental Sampling Program - Exposure Pathway -

Airborne. During this calendar year 2024, a total of 832 samples (416 particulate filters and 416 iodine cartridges) were collected and analyzed for gross beta, gamma emitters and Iodine-131. Particulate samplers are used to analyze gross beta activity following filter change out which occurs weekly. Gamma isotopic analysis is performed on composite samples collected at each location and is analyzed quarterly. Radioiodine (I-131) analysis is performed weekly on radioiodine sample cartridges.

APT (Air Particulate) samples were collected on glass fiber filters with low-volume air samplers sampling at approximately 1.5 SCFM. Air sample volumes were measured with calibrated dry-gas meters.

AIO samples (Air Iodine) were collected from the air by adsorption on triethylene-diamine (TEDA) impregnated charcoal cartridges connected in series after the APT filters.

8.2.1 Air Particulates APT samples were collected weekly at seven indicator locations (05X1, 06S1, 15S2, 05D1, 16E1, 01F1, and 02F6), one duplicate location (05S2) and one control location (14G1). Each weekly sample collected was analyzed for gross beta by TBE. Quarterly composites of the weekly samples from each location were analyzed for specific gamma emitters. The duplicate air location sample was shipped to GEL for analysis (Table 13, Table 14, and Table 15).

8.2.2 Gamma Spectroscopy Gamma spectroscopy was performed on each of the 32 quarterly particulate composite samples. Naturally occurring Be-7 was detected, and no other gamma emitters were detected in any of the samples. RMC-TR-77-03 [11].

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 29 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was detected in all 28 indicator location composites at concentrations ranging from 31E-03 pCi/m3 to 71E-03 pCi/m3 with an average concentration of 47E-03 pCi/m3, and in the four control location composites ranging in concentration from 40E-03 pCi/m3 to 63E-03 pCi/m3 with an average concentration of 54E-03 pCi/m3. The maximum preoperational level detected was 330E-03 pCi/m3 with an average concentration of 109E-03 pCi/m3 (Table 9, Table 13 and RMC-TR-77-03 [11]).

Gross beta activity was detected in 361 of 364 of indicator location samples at concentrations ranging from 4E-03 pCi/m3 to 27E-03 pCi/m3 with an average concentration of 13E-03 pCi/m3, and in 51 of 52 of the control location samples at concentrations ranging from 5E-03 pCi/m3 to 29E-03 pCi/m3 with an average of 14E-03 pCi/m3. Gross beta activity was less than ten times the yearly mean of control samples.

Therefore, per the ODCM gamma isotopic analysis was not required to be performed on the individual samples. The maximum preoperational level detected was 920E-03 pCi/m3 with an average concentration of 74E-03 pCi/m3 (Table 9, Table 14, and RMC-TR-77-03 [11]. See Figure 5).

8.2.3 Air Iodine AIO samples were collected weekly at seven indicator locations (05X1, 06S1, 15S2, 05D1, 16E1, 01F1, and 02F6), one duplicate location (05S2) and one control location (14G1). The duplicate air location sample was shipped to GEL for analysis. Each sample was analyzed by TBE for I-131, and all 416 samples were less than the MDC for both indicator and control samples during the Reporting Period. The maximum preoperational level detected was 42E-03 pCi/m3 (Table 9, Table 15 and RMC-TR 03 [11]).

Air particulate and radioiodine results from this monitoring period, 2024, were compared to preoperational data as shown in Table 9, Air Particulate and Radioiodine Comparison of Current Year and Historic Data, and there were no significant changes.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 30 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 9, Air Particulate and Radioiodine Comparison of Current Year and Historic Data Analysis Preoperational Data (pCi/m3) 2024 Sample Result Average (pCi/m3)

Gamma 109E-03 47E-03 Beta 74E-03 13E-03 Iodine 42E-03

< MDC Figure 5, Air Particulate: Analysis for Gross Beta, Average Mean for All Indicator Vs. Control 1

...... u.e

~

u

<(

0...

C, 1.80E-02 1.60E-02 1.40E-02 1.20E-02 1.00E-02 8.00E-03 6.00E-03 4.00E-03 2.00E-03 O.OOE+OO 2014 I

I Air Particulate: Analysis of Gross Beta Activity 2015 (Average mean for all indicator Locations vs. Control)

~

Indicator Average 2016 2017 2018 control Average

~

2019 Year

~

2020

~

2021 I

- ~~

2022 2023 2024

Annual Radiological Environmental Operating Report YEAR: 2024 Page 31 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 8.3 Waterborne Sample Results 8.3.1 Surface Water (i.e., Bay, Lake etc.)

Surface water samples were collected twice a month at four indicator locations and one control location in the Delaware River Estuary. The two samples for the month were combined to create a single monthly composite sample that was then analyzed. One location (11A1) is at the outfall area (which is the area potentially impacted by effluents discharged from the Site into the Delaware River), one location is downstream from the outfall area (07E1), and one location is directly west of the outfall area at the mouth of the Appoquinimink River (12B1). Samples were collected upstream in the Delaware River (01F2) and at the mouth of the Chesapeake and Delaware Canal (16F1), the latter being sampled when the flow was from the Canal into the river.

Surface water samples were collected offshore in new polyethylene containers that were rinsed twice with the sample medium prior to collection. The surface water samples were transported to TBE for analysis.

Location 12B1, located directly west of the Site, at the mouth of the Appoquinimink River, serves as the control. 12B1 was chosen as the control location because the physical characteristics of this location more closely resemble those of the outfall area than those at the farther upstream location (01F2). As discussed in the preoperational summary report, due to its tidal nature, there were flow rate and salinity variations in the Delaware River Estuary. These variations accounted for the differences in K-40 concentrations.

During this calendar year 2024, a total of 60 surface water samples were collected and analyzed in accordance with the requirements of Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne.

1.

Tritium Tritium activity was detected in 1 (sample location 11A1) of the 48 indicator location samples at a concentration of 674 pCi/L (80135746-40). Location 11A1 is at the outfall area that is influenced by permitted plant liquid discharges (see Figure 2). A discharge was in progress at the time of sample. The resulting maximum organ and total body dose to an adult would be 1.84E-03 mrem or

<0.01 percent of the 40 CFR 190 limit. Tritium was not detected in the control location samples. The maximum preoperational level detected was 600 pCi/L, with an average concentration of 210 pCi/L (Table 16 and RMC-TR-77-03 [11]).

See Figure 6, Surface Water Tritium Results.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 32 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Figure 6, Surface Water Tritium Results 2.

Gamma Spectroscopy No plant related gamma emitters were detected above the MDC in any of the indicator or control surface water samples.

Naturally occurring K-40 was detected in 18 of the 48 indicator location samples at concentrations ranging from 53 pCi/L to 171 pCi/L, with an average of 100 pCi/L. K-40 was detected in 5 of the 12 control location samples at concentrations ranging from 49 pCi/L to 144 pCi/L, with an average concentration of 97 pCi/L. The maximum preoperational level detected for K-40 was 200 pCi/L with an average concentration of 48 pCi/L (Table 17 and RMC-TR-77-03 [11]).

3.

I-131Low Level I-131 was not detected above the MDC in any of the 48 indicator samples or in any of the control location samples (Table 17).

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TRITIUM ACTIVITY IN SURFACE WATER - QUARTERLY AVERAGE 2013 THROUGH 2024 I

10000.00 ~---------------------------------------------~

Effluent discharge near time of sampling: 04-21-16 Effluent discharge near time

\\

Effluent discharge near ofsampUoI"'.':,::hase oea, __:.

~:~*~:::~~foi" 3Fo20

>ime ofs*r ;;;;:~~~:,::~;:;,

1000.00 +----t~im=e~o~f~s~a~m.,,,,,

nlin,,,n,,_:~0~SL-~3-~1~6~ ________________

_,,_~---------+-------\\-\\-----,

Effluent discharge near time of sampling: 07-19-1 8and 09-20-18 Effluent discharge near time of ______,.,..

sampling: 01-17-23

\\i

100.00 +---------------------------------------------------<

1 Note: For purposes of this chart. when there was no positive detection in the quarter, the LLD was displayed as an open diamond.

10.00 +-~-~-~~

- -~

--= --= --=-=-=-~-~-~ --=-~-~-~-~-~-=-~-=-~-~-~-~-~-~-=-=-~-~-~- =- =-= --=

--= --~ - -~ --=-~-=-~-~-~-~-~-~-~-~-~-~-~-~-=-=-=-~-~-~~

--~ - -= --= --=-=-=-~--~--=-~-~-~-er--,

Detectable Tritium (pCi/l) o Lower Unit of Detection (200 pO/L)

Annual Radiological Environmental Operating Report YEAR: 2024 Page 33 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 8.3.2 Potable Water (Drinking Water)

Both raw and treated potable water samples were collected and composited at the local water treatment facility. Each sample consisted of weekly aliquots composited into a monthly sample. The raw water source for this plant is a combination of surface water from Laurel Lake and groundwater from its adjacent wells. These are Management Audit samples as no liquid effluents discharged from the Site directly affect this pathway.

1.

Gross Alpha No Gross alpha activity was detected above the MDC in any of the raw or treated water samples. The maximum preoperational level detected was 2.7 pCi/L (Table 18 and RMC-TR-77-03 [11]).

2.

Gross Beta Gross beta activity was detected in 12 of 12 raw water samples and 12 of 12 treated water samples. The concentrations for the raw samples ranged from 5.7 pCi/L to 10.4 pCi/L, with an average concentration of 8.0 pCi/L. Concentrations for the treated water ranged from 6.2 pCi/L to 10.7 pCi/L, with an average concentration of 8.5 pCi/L. The maximum preoperational level detected was 9.0 pCi/L with an average concentration of 4.2 pCi/L (Table 18 and RMC-TR-77-03

[11].

3.

Tritium Tritium activity was not detected above the MDC in any of the 12 raw or 12 treated water samples. The maximum preoperational level detected was 350 pCi/L with an average of 179 pCi/L (Table 18 and RMC-TR-77-03 [11]).

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 34 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

4.

I-131 I-131 activity was not detected above the MDC in any of the 12 raw or 12 treated water samples. No preoperational data were available for comparison, since I-131 was not analyzed as a specific radionuclide prior to 1989. However, I-131 analytical results to date have been below the MDC (Table 19 and RMC-TR 03 [11]).

5.

Gamma Spectroscopy No plant related gamma emitters were detected above the MDC in any of the 12 raw potable water samples. Naturally occurring K-40 was not detected in any raw or treated water samples. No preoperational data was available for comparison. Naturally occurring Ra-226 was not detected in any raw or treated water samples. The maximum preoperational level detected for Ra-226 was 1.4 pCi/L (Table 19 and RMC-TR-77-03 [11]).

8.3.3 Well Water (Ground Water)

Although offsite wells in the vicinity of the Site are not directly affected by plant operations, well water samples were collected monthly from one farm (03E1). Samples from this well are considered Management Audit samples.

1.

Gross Alpha Gross alpha activity was not detected above the MDC in any of the 12 well water samples. The maximum preoperational level detected was 9.6 pCi/L (Table 20 and RMC-TR-77-03 [11]).

2.

Gross Beta Gross beta activity was detected in 1 of the 12 well water samples at a concentration of 3.7 pCi/L. The preoperational results ranged from <2.1 pCi/L to 38 pCi/L, with an average value of 9 pCi/L (Table 20 and RMC-TR-77-03 [11]).

3.

Tritium Tritium activity was not detected above the MDC in any of the 12 well water samples. The maximum preoperational level detected was 380 pCi/L (Table 20 and RMC-TR-77-03 [11]).

4.

I-131 I-131 activity was not detected in any of the 12 well water samples. No preoperational data were available for comparison, since I-131 was not analyzed as a specific radionuclide prior to 1989. However, I-131 analytical results to date have been below the MDC (Table 21 and RMC-TR-77-03 [11]).

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 35 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

5.

Gamma Spectroscopy No plant related gamma emitters were detected above the MDC in any of the indicator or control location well water samples. Naturally occurring K-40 was not detected in any of the well water samples. The maximum preoperational levels detected were 30 pCi/L (Table 21 and RMC-TR-77-03 [11]).

8.3.4 Sediment Sediment samples were collected semi-annually from five indicator locations and one control location. Location 05A1 was the only shoreline sediment sample location that was directly subjected to tidal fluctuations. The remaining locations were located offshore. Location 15A2, South Storm Drain outfall, was not sampled due to the Windport Project. Only one outfall location is required (obtained from 15A1) by ODCM table 3.12-1.

Sediment samples were taken with a bottom grab sampler and frozen in sealed polyethylene containers before being transported in ice chests to TBE. For the river bottom sediment, a marine GPS was used to locate the correct site and the sampling boat was maneuvered over the area until the correct amount of sample was obtained (grabbed) with the sediment dredge.

Location 05A1 shoreline sediment sample (an onsite location) was sampled as follows:

A square area, measuring one meter on each side was staked out and then divided into a grid of nine smaller boxes, three per side. A one inch deep scoop from the center of each of the small grids was taken. All the aliquots were combined and the total sample transported in the ice chest to TBE and analyzed for gamma emitters.

Naturally occurring K-40 was detected in all 10 indicator location samples at concentrations ranging from 2,470 pCi/kg (dry) to 14,340 pCi/kg (dry), with an average concentration of 8,327 pCi/kg (dry). Both control locations samples had concentrations ranging from 14,780 pCi/kg (dry) to 16,000 pCi/kg (dry) with an average concentration of 15,390 pCi/kg (dry). The maximum preoperational level detected was 21,000 pCi/kg (dry) with an average concentration of 15,000 pCi/kg (dry) Table 22 and RMC-TR 03 [11]).

Cs-137 was not detected in any of the indicator or control samples. The maximum preoperational level detected was 400 pCi/kg (dry) with an average concentration of 150 pCi/kg (dry) (Table 22 and RMC-TR-77-03 [11]).

Naturally occurring Ra-226 was detected in 1 of 10 indicator location samples with a concentration of 1,531 pCi/kg (dry). Ra-226 was detected in 1 of the 2 control location samples with a concentration of 1,834 pCi/kg (dry).. The maximum preoperational level detected was 1,200 pCi/kg (dry) with an average concentration of 760 pCi/kg (dry)

(Table 22 and RMC-TR-77-03 [11]).

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 36 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Naturally occurring Th-232 was detected in 5 of the 10 indicator location samples at concentrations ranging from 210 pCi/kg (dry) to 780 pCi/kg (dry) with an average concentration of 499 pCi/kg (dry). Th-232 was detected 2 of 2 control location samples at concentrations ranging from 807 pCi/kg (dry) to 984 pCi/kg (dry) with an average concentration of 895 pCi/kg (dry). The maximum preoperational level detected was 1,300 pCi/kg (dry) with an average concentration of 840 pCi/kg (dry). All other gamma emitters were less than the MDC (Table 22 and RMC-TR-77-03 [11]).

8.4 Ingestion Pathway Sample Results 8.4.1 Milk Milk samples (MLK) were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture, from two indicator locations (13E3, and 14F4) and one control location (02G3). Animals were considered on pasture from April to November of each year. Samples were collected in new polyethylene containers, sodium bisulfite was added as a sample preservative, and then samples were frozen and transported in ice chests to TBE. Each sample was analyzed for I-131 and gamma emitters. Note: Location 03G1 was the previous control location, however, the dairy farm is no longer in business, see section 11.0.

There is no dairy farm within three miles of the Site, and there is only one dairy farm within five miles (13E3). Therefore, broadleaf vegetation is grown, maintained, and harvested monthly during the growing season.

1.

I-131 I-131 was not detected above MDC in any of the 60 samples analyzed. The maximum preoperational level detected was 65 pCi/L, which occurred following a period of atmospheric nuclear weapons (Table 23 and RMC-TR-77-03 [11]).

2.

Gamma Spectroscopy No plant related gamma emitters were detected above the MDC in any of the indicator or control location milk samples.

Naturally occurring K-40 was detected in all 40 indicator samples with concentrations ranging from 995 pCi/L to 1,846 pCi/L with an average concentration of 1,233 pCi/L, and the 20 control location sample concentrations ranging from 1,004 pCi/L to 1,677 pCi/L, with an average concentration of 1,247 pCi/L. The maximum preoperational level detected was 2,000 pCi/L with an average concentration of 1,437 pCi/L (Table 23 and RMC-TR-77-03 [11]).

8.4.2 Fish and Invertebrates A total of 6 fish and invertebrate samples were analyzed in 2024, for gamma emitting radionuclides in accordance with requirements of Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion. These samples are collected from the indicator and control areas as required by the ODCM.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 37 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

1.

Fish Edible species of fish were collected semi-annually at two indicator locations and one control location and analyzed for gamma emitters in edible flesh. Sample species collected in 2024, were striped bass and catfish. Edible fish were collected using gill nets. These samples were processed by separating the flesh from the bone. The flesh was placed in sealed containers and frozen before being transported in ice chests to TBE for analysis.

No plant related gamma emitters were detected above the MDC in any of the indicator or control location fish samples. Naturally occurring K-40 was detected in all 4 indicator location samples at concentrations ranging from 2,872 pCi/kg (wet) to 3,876 pCi/kg (wet) with an average concentration of 3,473 pCi/kg (wet).

The 2 control location samples had concentrations ranging from 2,918 pCi/kg (wet) to 4,062 pCi/kg (wet), with an average of 3,490 pCi/kg (wet). The maximum preoperational detection was 13,000 pCi/kg (wet) with an average concentration of 2,900 pCi/kg (wet) (Table 24 and RMC-TR-77-03 [11]).

2.

Blue Crab Blue crab samples were caught in commercial traps and collected twice during the season at one indicator and one control location. The edible portions were analyzed for gamma emitters. No plant related gamma emitters were detected above the MDC in any of the indicator or control location blue crab samples.

Naturally occurring K-40 was detected in both indicator samples at concentrations of 2,291 pCi/kg (wet) and 2,389 pCi/kg (wet) with an average concentration of 2,340 pCi/kg (wet). The control location samples had concentrations ranging from 2,238 pCi/kg (wet) to 2,864 pCi/kg (wet), with an average concentration of 2,551 pCi/kg (wet). The maximum preoperational level for K-40 detected was 12,000 pCi/kg (wet) with an average concentration of 2,835 pCi/kg (wet). All other gamma emitters were less than the MDC (Table 25 and RMC-TR-77-03 [11]).

8.4.3 Vegetation A total of 33 food samples were analyzed in 2024, for gamma emitting radionuclides in accordance with requirements of Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion.

Locally grown vegetables (FPV) were collected at the time of harvest at four locations (02F9, 01G1, 15F4 and 03H5); fodder crops (VGT) were sampled at three locations (13E3, 14F4, and 02G3); and broad leaf vegetation (FPL) was sampled at six locations (06S1, 16S1, 10D1, 01G1, 03H5, and 15F4). The vegetables and fodder samples are additional samples (Management Audit) taken to enhance the radiological monitoring program.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 38 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

1.

Broadleaf Vegetation (FPL)

Broadleaf vegetation samples were collected since there were no dairy farms operating within the five km (three mile) radius of the Site. The closest dairy farm (13E3) was located in Odessa, DE at 5.0 miles to the West.

All samples were analyzed for gamma emitters and included cabbage and lambs ear. These samples were obtained from four indicator locations and one control locations. The results for these samples are discussed below.

No plant related gamma emitters were detected above the MDC in any of the indicator or control location broadleaf vegetation samples.

Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was detected above the MDC in 4 of the 12 indicator location samples with concentrations ranging from 1,288 pCi/kg (wet) to 2,032 pCi/kg (wet), with an average concentration of 1,534 pCi/kg (wet). Be-7 was detected in 2 of the 4 control location samples, with concentrations ranging from 1,474 pCi/kg (wet) to 2,837 pCi/kg (wet), and an average concentration of 2,156 pCi/kg (wet). No preoperational Be-7 data was available for comparison (Table 26).

Naturally occurring K-40 was detected in all 12 indicator samples, with concentrations ranging from 1,587 pCi/kg (wet) to 11,770 pCi/kg (wet) with an average concentration of 5,299 pCi/kg (wet). K-40 was detected in all of the control location samples, with concentrations ranging from 2,923 pCi/kg (wet) to 7,651 pCi/kg (wet), and an average concentration of 5,289 pCi/kg (wet). The maximum preoperational level detected was 4,800 pCi/kg (wet) with an average concentration of 2,140 pCi/kg (wet) (Table 26 and RMC-TR-77-03 [11]).

Naturally occurring Th-232 was not detected in any of the indicator location samples or control location samples (Table 26).

2.

Vegetables There are no farm products that are irrigated with water in which plant effluents have been discharged. The Delaware River at the location of the Site is brackish and therefore is not used for irrigation.

A variety of food products were sampled on and around the Site; however, the variety was dependent on the farmers preference. These vegetables were collected as Management Audit samples.

All samples were analyzed for gamma emitters and included asparagus, sweet corn, peppers, tomatoes, and peaches. These samples were obtained from five indicator locations (14 samples). The results for these samples are discussed below.

No plant related gamma emitters were detected above the MDC in any of the indicator or control location vegetable samples.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 39 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was not detected above the MDC in any of the vegetable samples.

Naturally occurring K-40 was detected in all 14 indicator samples, with concentrations ranging from 1,147 pCi/kg (wet) to 3,197 pCi/kg (wet) with an average concentration of 1,966 pCi/kg (wet). The maximum preoperational level detected was 4,800 pCi/kg (wet) with an average concentration of 2,140 pCi/kg (wet) (Table 27 and RMC-TR-77-03 [11]).

3.

Fodder Crops Although not required by the Site ODCM, three samples of silage normally used as cattle feed were collected from three indicator locations. It was determined that these products could be an element in the food-chain pathway. These fodder crops were collected as Management Audit samples and analyzed for gamma emitters. All three locations from which samples were collected are milk sampling locations.

No plant related gamma emitters were detected above the MDC in any of the indicator or control location fodder crop samples. Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was detected in 2 of 3 indicator samples with concentrations ranging from 455 pCi/kg (wet) to 491 pCi/kg (wet) with an average concentration of 473 pCi/kg). The maximum preoperational level detected for fodder was 4,700 pCi/kg (wet) with an average concentration of 2,000 pCi/kg (wet) (Table 28 and RMC-TR-77-03 [11]).

Naturally occurring K-40 was detected in all three indicator samples at concentrations ranging from 2,990 pCi/kg (wet) to 6,814 pCi/kg (wet) with an average concentration of 4,499 pCi/kg (wet). Preoperational results averaged 7,000 pCi/kg (wet) (Table 28 and RMC-TR-77-03 [11]).

8.4.4 Game Although not required by the Site ODCM, one muskrat sample was collected from one indicator location. The game sample was collected as a Management Audit sample and analyzed for gamma emitters.

No plant related gamma emitters were detected above the MDC in the indicator game sample. Naturally occurring K-40 was detected with a concentration of 2,167 pCi/kg (wet). No preoperational data was available for comparison (Table 29 and RMC-TR-77-03 [11]).

8.5 Terrestrial 8.5.1 Soil Soil is sampled every three years and analyzed for gamma emitters. Nine locations were sampled in 2022 (next sample is due in 2025). These Management Audit samples were collected in areas that have been relatively undisturbed since the last collection to determine any change in the radionuclide inventory of the area.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 40 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations The 2022 samples had naturally occurring K-40 was detected in all nine indicator samples at concentrations ranging from 5,448 to 13,690 pCi/kg (dry) with an average concentration of 9,315 pCi/kg (dry). The maximum preoperational level detected was 24,000 pCi/kg (dry) with an average of 10,000 pCi/kg (dry) (Table 30).

Cs-137 was detected in 5 of 9 indicator samples at concentrations ranging from 75 to 184 pCi/kg (dry) with an average concentration of 128 pCi/kg (dry). The maximum preoperational level detected was 2,800 pCi/kg (dry) with an average of 800 pCi/kg (dry). See Figure 7 for graphical presentation (Table 30 and RMC-TR-77-03 [11]).

Naturally occurring Ra-226 was detected in 8 of 9 indicator samples at concentrations ranging from 1,398 pCi/kg (dry) to 2,836 pCi/kg (dry) with an average concentration of 1,989 pCi/kg (dry) (Table 30).

Naturally occurring Th-232 was detected in 8 of 9 indicator samples at concentrations ranging from 436 pCi/kg (dry) to 975 pCi/kg (dry) with an average concentration of 742 pCi/kg (dry), Th-232 was not detected in control location. All the other gamma emitters were less than the MDC (Table 30).

Figure 7, Cesium-137 Activity in Soil 1974 Through 2022

~

Cl

,:: r; c..

M

~

0 800 700 600 500 400 300 200 100 0

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CESIUM-137 ACTIVITY IN SOIL 1974 THROUGH 2022 (TRIENNIAL)

I 1971 1974 1977 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 2010 2013 2016 2019 2022 Annual values are an average of the results from the ten soil sites.

Annual Radiological Environmental Operating Report YEAR: 2024 Page 41 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Historically, Cs-137 has been observed in REMP soil samples and attributed to weapons testing. The values observed in these samples are consistent with prior results and are below the NRCs predicted values of Cs-137 for the New Jersey area soils as a result of fallout from atmospheric weapons testing. Furthermore, the analyzed samples were at concentrations many orders of magnitude above the theoretical impact by plant operation given the Cs-137 concentrations in plant effluents back through 2005.

Additionally, soil is not a formal component of the REMP, nor is it required to be collected as part of the REMP in accordance with the ODCM; it is collected as a REMP Management Audit sample. As such, the ODCM specifies no reportability or LLD thresholds for soil samples. PSEG REMP Implementation procedure, Attachment 1 (Analytical Results Investigation Levels) provides an investigation threshold of 1,000 pCi/kg for Cs-137 in soil and sediment, which is based on the expected concentrations for our region from sources other than plant operation as recognized by the NRC in DOCKET NO.50-219, RFTA NO.99-040.

This evaluation validated suppositions and will appropriately characterize positive sample results obtained in future sampling evolutions as related to atmospheric testing, provided that:

Soil concentrations are less than 1,000 pCi/kg Annual gaseous Cs-137 effluents are reviewed and do not show a significant increase Cs-134 is not detected (Cs-134 is plant related and has a much shorter half-life than Cs-137)

D/Q values continue to be routinely evaluated and are updated as necessary For the above reasons, it can be concluded that the samples are primarily the result of atmospheric testing, with negligible contribution from site operations at PSEG Nuclears three reactors.

Although it has been concluded the Cs-137 in the soil is due to fallout from atmospheric weapons testing, there is no radiological impact to the environment or a member of the public with respect to the annual dose. To demonstrate this, a skin dose calculation was performed for a theoretical person who stood on the soil at location 05F1 (184 pCi/kg) for 1,000 hours0 days 0 hours 0 weeks 0 months per year (arbitrary number). This calculation concluded the dose to a member of the public beyond the site boundary would be a mere 2.16E-1 mrem/yr (1.4% of the annual skin dose limit of 15 mrem/yr), which conforms to 10 CFR 50 Appendix I. Since this activity has been determined to be non-site related, a better comparison is the calculated skin dose against background radiation levels (or approximately 0.1% of the 300 mrem/yr background dose).

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 42 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 9.0 LAND USE CENSUS The Land Use Census required by the Offsite Dose Calculation Manual is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and modifications to REMP are made if required by changes in land use. Land use census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50 [2].

NUREG-1301/1302 Control 3.12.2 specifies that "a land use census shall be conducted and shall identify within a distance of 8 km (5 mi.) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation." Note, per NUREG-1301/1302, Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

The Land Use Census was conducted during the calendar year, 2024, within the growing season to identify changes in land use, receptor locations, and new exposure pathways. The results for the 2024 Land Use Census are listed in Table 10, Land Use Census - Nearest Pathway within 5 miles. In summary, the highest D/Q locations for nearest garden, nearest residence and nearest milk animal did not change following the 2024 census.

Table 10, Land Use Census - Nearest Pathway within 5 miles Sector Direction Nearest Residence (Miles)

Nearest Milk Animal (Miles)

Garden (Miles)

Meat Animal Distance (Miles) 1 N

None None None None 2

NNE 5.0 None None None 3

NE 3.9 None None None 4

ENE 3.9 None None None 5

E None None None None 6

ESE None None None None 7

SE None None None None 8

SSE None None None None 9

S None None None None 10 SSW 3.9 None None None 11 SW 4.3 None None None 12 WSW 4.4 None None None 13 W

4.0 5.0 None None 14 WNW 3.4 None None None 15 NW 3.7 None None None 16 NNW 4.2 None None None I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 43 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 10.0 SAMPLE DEVIATIONS, ANOMALIES AND UNAVAILABILITY Sampling and analysis are performed for media types addressed in the Offsite Dose Calculation Manual. Sampling and analysis challenges may be experienced due to a multitude of reasons including environmental factors, loss of TLDs/OSLDs, contamination of samples, etc. To aid classification of sampling and analysis challenges experienced in 2024, the following three terms are used to describe the issues: Sample Anomalies, Sample Deviation, and Unavailable Samples.

Media that experienced downtime (i.e., air samplers or water samplers) during a surveillance period are classified as Sample Deviation. Sample Anomalies are defined as errors that were introduced to a sample once it arrived in the laboratory, errors that prevents the sample from being analyzed as it normally would or may have altered the outcome of the analysis (i.e., cross contamination, human error).

Sample Unavailability is defined as sample collection with no available sample (i.e.,

food crop, TLD).

All required samples were collected and analyzed as scheduled except for the following:

Table 11, Sample Deviation Summary Sample Type and Analysis Analysis Location Collection Date or Period Reason for not conducting REMP sampling as required by ODCM Plans for preventing reoccurrence APT/AIO1 Gross Iodine 14G1 1/16/24 - 1/22/24 GFCI Trip &

Blown Fuse LLD not met Installed new pump APT/AIO 2 Gross Iodine 05D1 2/20//24 - 2/26/24 Power Outage N/A APT/AIO 3 Gross Iodine 15S2 7/1//24 - 7/8/24 Motor Failure Installed new pump APT/AIO4 Gross Iodine 05X1/05S2 9/9/24 - 9/16/24 Power Outage N/A APT/AIO5 Gross Iodine 06S1 11/4/24 - 11/12/24 GFCI Trip Reset GFCI

1.

Sample Deviation (Order 80135746/10): Air sampler 14G1 lost power due to blown fuse and GFCI trip during the 1/16/24 to 1/22/24 collection period. The total time the sampler was in operation was 15.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . The total outage duration was 133.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . A total of volume 1,400 cubic feet was collected for the sample period. Adequate sample volume was not achieved during the sample collection period to meet the ODCM LLD requirements for Gross Beta and I-131.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 44 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

2.

Sample Deviation (Order 80135746/20): Air sampler 05D1 lost power during the 2/20/24 to 2/26/24 collection period. The total time the sampler was in operation was 143.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . The total outage duration was 5.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . A total of volume 12,000 cubic feet was collected for the sample period. Adequate sample volume was achieved during the sample collection period to meet the ODCM LLD requirements for Gross Beta and I-131.

3.

Sample Deviation (Order 80135746/50): Air sampler 15S2 has a motor failure on the 7/1/24 to 7/8/24 collection period. The total time the sampler was in operation was 60.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The total outage duration was 110.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . A total volume of 5,700 cubic feet was collected for the sample period. Adequate sample volume was achieved during the sample collection period to meet the ODCM LLD requirements for Gross Beta and I-131.

4.

Sample Deviation (Order 80135746/60): Air samplers 05X1/05S2 power was lost during the 9/9/24 to 9/16/24 collection period. The total time the sampler was in operation was 128.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The total outage duration was 40.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

A total volume 11,800 (05X1) and 11,530 (05S2) cubic feet were collected for the sample period. Adequate sample volume was achieved during the sample collection period to meet the ODCM LLD requirements for Gross Beta and I-131.

5.

Sample Deviation (Order 80135746/100): Air sampler 06S1 power was lost due to GFCI trip on the 11/4/24 to 11/12/24 collection period. The total time the sampler was in operation was 112.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months . The total outage duration was 80.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . A total volume of 10,100 cubic feet was collected for the sample period.

Adequate sample volume was achieved during the sample collection period to meet the ODCM LLD requirements for Gross Beta and I-131.

6.

Sample Anomaly (Order 80135746/70): Vendor informed station personnel that the gross beta results on air sample 02F6 during the 9/9/24 to 9/16/24 collection period were lower than the other results in the dataset. The reported result was 1.37E-02 pCi/m3. The normal range in this report for the 02F6 sample location is 4.00E-03 to 1.7E-02 pCi/m3. The sampler was inspected, and no anomalies were noted.

11.0 PROGRAM CHANGES The milk farm used as the control (03G1, 16.5 miles, NE) went out of business. The farm located 11.8 miles, NNE, location 02G3 was used as an alternate for the control location within 30 days in accordance with ODCM, Part 1, 3.12.1.c. The location at 03G1 was not removed in the 2021 revision of the ODCM, because it was not determined if the location change was permanent. The next revision of the ODCM will replace location 03G1 with 02G3 (80130863 Operation 20).

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 45 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 12.0 OTHER SUPPLEMENTAL INFORMATION 12.1 NEI 07-07 Onsite Radiological Groundwater Monitoring Program Salem and Hope Creek Generating Stations has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. It is important to note, samples and results taken in support of NEI 07-07 on-site groundwater monitoring program are separate from the Radiological Environmental Monitoring Program (REMP). Results of the NEI 07-07 Radiological Groundwater Monitoring Program for onsite groundwater wells are provided in the ARERR.

12.2 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program ISFSI information is reported in the Salem and Hope Creek Generating Stations ARERR.

12.3 Hope Creek Technical Specification Limit For Primary Water Iodine Concentration The HCGS primary coolant results for Dose Equivalent Iodine-131, Total Gamma, and Total Beta were reviewed. The specific activity of the primary coolant did not exceed 0.2 micro curies per gram Dose Equivalent I-131 (DEI).

The Total Gamma and the Total Beta activity (microcuries per gram) did not exceed the 100/E-Bar limit.

Therefore, HCGS did not exceed the Technical Specifications limit specified in section 3.4.5.

12.4 Corrections to Previous Reports In 2021 the Common REMP ODCM Revision 0 was created and changed the name of location 13S1 to 14S2 to better reflect what sector the sample location was in.

However, in the AREOR for 2021, 2022, and 2023, location 14S2 was reported under the old location name (13S1). This errata corrects the location name from the old to new (Notification 20990610). See Attachment 4, Errata/Corrections to Previous Reports.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 46 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 13.0 BIBLIOGRAPHY

[1]

NCRP, "Report No. 160, Ionizing Radiation Exposure of the Population of the United States,"

National Council on Radiation Protection, Bethesda, 2009.

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"10 CFR 50, "Domestic Licensing of Production and Utilization Facilities"," US Nuclear Regulatory Commission, Washington, DC.

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"Regulatory Guide 4.1, "Radiological Environmental Monitoring for Nuclear Power Plants",

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"NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,.," Nuclear Regulatory Commission, April 1991.

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"Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment,"

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"Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 2," Nuclear Regulatory Commision, June, 2019.

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Reoperation Summary - 1973 through 1976, Radiation Management Corporation.".

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Nuclear Regulatory Commission, 1974.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 47 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

[21] "NUREG-0133, Preparation of Effluent Technical Specifications for Nuclear Power Plants,"

Nuclear Regulatory Commission, 1987.

[22] "Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I,,"

Nuclear Regulatory Commission, Ocotober, 1977.

[23] [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html. [Accessed 2020].

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[25] "40 CFR Part 141, National Primary Drinking Water Regulations,," US Environmental Protection Agency, Washington, DC..

[26] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].

[27] "NEI 07-07, Industry Ground Water Protection InitiativeFinal Guidance Document, Rev. 1,"

Nuclear Energy Institute, Washington, D.C., 2019.

[28] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].

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[30] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:

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[32] "NUREG-0133, Preparation of Effluent Technical Specifications for Nuclear Power Plants,"

Nuclear Regulatory Commission, 1987.

[33] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].

[34] "Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 2," Nuclear Regulatory Commision, June, 2019.

[35] "Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment,"

Nuclear Regulatory Commission, July, 2007.

[36] "10 CFR 50 - Domestic Licensing of Production and Utilization Facilities," US Nuclear Regulatory Commission, Washington, DC.

[37] "40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.

[38] "NUREG-0324 - XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," Nuclear Regulatory Commission, September, 1977.

[39] "NCRP Report No. 160 - Ionizing Radiation Exposure of the Population of the United States,"

National Council on Radiation Protection and Measurements, Bethesda, MD, 2009.

[40] "Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I," Nuclear Regulatory Commission, Ocotober, 1977.

[41] "40 CFR 141 - National Primary Drinking Water Regulations," US Environmental Protection Agency, Washington, DC..

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 48 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

[42] "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 49 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 50 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

I. DIRECT DIRECT RADIATION TLD-QUARTERLY 236 N/A 14.5 (224/224)

SA-IDM-01Q1 32.0 (4/4) 14.0 (12/12) 0 (mR/standard quarter)

(10.5/32.6) 0.58 MILES N (31.5/32.6)

(12.3/15.6)

II. AIRBORNE AIR PARTICULATE Gr-B 416 10 13 (361/364)

SA-APT-14G1 C 14 (51/52) 14 (51/52) 0 (E-3 pCi/m3)

(4/27) 13.4 MILES WNW (5/29)

(5/29)

GAMMA 32 Be-7 N/A 46.9 (28/28)

SA-APT-14G1 C 54 (4/4) 54 (4/4) 0 (30.9/70.9) 13.4 MILES WNW (40.3/62.5)

(40.3/62.5)

K-40 N/A

<MDC N/A N/A

<MDC 0

Cs-134 50

<MDC N/A N/A

<MDC 0

Cs-137 60

<MDC N/A N/A

<MDC 0

AIR IODINE GAMMA 416 (E-3 pCi/m3)

I-131 70

<MDC N/A N/A

<MDC 0

III. WATERBORNE SURFACE WATER H-3 60 200 674 (1/48)

SA-SWA-11A1 674 (1/12)

<MDC 0

(pCi/L) 0.22 MILES SW I-131 (LOW LVL) 60 1

<MDC N/A N/A

<MDC 0

GAMMA 60 K-40 N/A 100 (18/48)

SA-SWA-07E1 116 (7/12) 97 (5/12) 0 (53/171) 4.4 MILES SE (75/171)

(49/144)

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 51 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

SURFACE WATER (CONT.)

Mn-54 15

<MDC N/A N/A

<MDC 0

(pCi/L)

Co-58 15

<MDC N/A N/A

<MDC 0

Fe-59 30

<MDC N/A N/A

<MDC 0

Co-60 15

<MDC N/A N/A

<MDC 0

Zn-65 30

<MDC N/A N/A

<MDC 0

ZrNb-95 15

<MDC N/A N/A

<MDC 0

Cs-134 15

<MDC N/A N/A

<MDC 0

Cs-137 18

<MDC N/A N/A

<MDC 0

BaLa-140 15

<MDC N/A N/A

<MDC 0

POTABLE WATER (RAW)

Gr-A 12 3

<MDC N/A N/A N/A 0

(pCi/L)

Gr-B 12 4

8 (12/12)

SA-PWR-02F3 8 (12/12)

N/A 0

(5.7/10.4) 8.0 MILES NNE (5.7/10.4)

H-3 12 200

<MDC N/A N/A N/A 0

I-131 (LOW LVL) 12 1

<MDC N/A N/A N/A 0

GAMMA 12 K-40 N/A

<MDC N/A N/A N/A 0

Mn-54 15

<MDC N/A N/A N/A 0

Co-58 15

<MDC N/A N/A N/A 0

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 52 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

POTABLE WATER (RAW)

(cont.)

Fe-59 30

<MDC N/A N/A N/A 0

(pCi/L)

Co-60 15

<MDC N/A N/A N/A 0

Zn-65 30

<MDC N/A N/A N/A 0

ZrNb-95 15

<MDC N/A N/A N/A 0

Cs-134 15

<MDC N/A N/A N/A 0

Cs-137 18

<MDC N/A N/A N/A 0

BaLa-140 15

<MDC N/A N/A N/A 0

Ra-226 N/A

<MDC N/A N/A N/A 0

POTABLE WATER (TREATED)

Gr-A 12 3

<MDC N/A N/A N/A 0

(pCi/L)

Gr-B 12 4

8.5 (12/12)

SA-PWT-02F3 8.5 (12/12)

N/A 0

(6.2/10.7) 8.0 MILES NNE (6.2/10.7)

H-3 12 200

<MDC N/A N/A N/A 0

I-131 (LOW LVL) 12 1

<MDC N/A N/A N/A 0

GAMMA 12 K-40 N/A

<MDC N/A N/A N/A 0

Mn-54 15

<MDC N/A N/A N/A 0

Co-58 15

<MDC N/A N/A N/A 0

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 53 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

POTABLE WATER (TREATED) (Cont)

Fe-59 30

<MDC N/A N/A N/A 0

(pCi/L)

Co-60 15

<MDC N/A N/A N/A 0

Zn-65 30

<MDC N/A N/A N/A 0

ZrNb-95 15

<MDC N/A N/A N/A 0

Cs-134 15

<MDC N/A N/A N/A 0

Cs-137 18

<MDC N/A N/A N/A 0

BaLa-140 15

<MDC N/A N/A N/A 0

Ra-226 N/A

<MDC N/A N/A N/A 0

WELL WATER Gr-A 12 3

<MDC N/A N/A N/A 0

(pCi/L)

Gr-B 12 4

3.7 (1/12)

SA-WWA-03E1 3.7 (1/12)

N/A 0

4.2 MILES NE H-3 12 200

<MDC N/A N/A N/A 0

I-131 (LOW LVL) 12 1

<MDC N/A N/A N/A 0

GAMMA 12 K-40 N/A

<MDC N/A N/A N/A 0

Mn-54 15

<MDC N/A N/A N/A 0

Co-58 15

<MDC N/A N/A N/A 0

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 54 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

WELL WATER (cont.)

Fe-59 30

<MDC N/A N/A N/A 0

(pCi/L)

Co-60 15

<MDC N/A N/A N/A 0

Zn-65 30

<MDC N/A N/A N/A 0

ZrNb-95 15

<MDC N/A N/A N/A 0

Cs-134 15

<MDC N/A N/A N/A 0

Cs-137 18

<MDC N/A N/A N/A 0

BaLa-140 15

<MDC N/A N/A N/A 0

Ra-226 N/A

<MDC N/A N/A N/A 0

SEDIMENT GAMMA 12 (pCi/kg dry)

Be-7 N/A

<MDC N/A N/A

<MDC 0

K-40 N/A 8327 (10/10)

SA-ESS-12B1 (C) 15390 (2/2) 15390 (2/2) 0 (2470/14340) 1.8 MILES WSW (14780/16000)

(14780/16000)

Cs-134 150

<MDC N/A N/A

<MDC 0

Cs-137 180

<MDC N/A N/A

<MDC 0

Ra-226 N/A 1531 (1/10)

SA-ESS-12B1 C 1834 (1/2) 1834 (1/2) 0 1.8 MILES WSW Th-232 N/A 499 (5/10)

SA-ESS-12B1 C 895 (2/2) 895 (2/2) 0 (210/780) 1.8 MILES WSW (807/984)

(807/984)

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 55 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

IV. INGESTION MILK I-131 (LOW LVL) 60 1

<MDC N/A N/A

<MDC 0

(pCi/L)

GAMMA 60 K-40 N/A 1233 (40/40)

SA-MLK-02G3 C 1247 (20/20) 1247 (20/20) 0 (995/1846) 11.8 MILES NNE (1004/1677)

(1004/1677)

Cs-134 15

<MDC N/A N/A

<MDC 0

Cs-137 18

<MDC N/A N/A

<MDC 0

BaLa-140 15

<MDC N/A N/A

<MDC 0

Ra-226 N/A

<MDC N/A N/A

<MDC 0

FISH GAMMA 6

(pCi/kg wet)

K-40 N/A 3473 (4/4)

SA-ESF-11A1 3572 (2/2) 3490 (2/2) 0 (2872/3876) 0.22 MILES SW (3407/3736)

(2918/4062)

Mn-54 130

<MDC N/A N/A

<MDC 0

Co-58 130

<MDC N/A N/A

<MDC 0

Fe-59 260

<MDC N/A N/A

<MDC 0

Co-60 130

<MDC N/A N/A

<MDC 0

Zn-65 260

<MDC N/A N/A

<MDC 0

Cs-134 130

<MDC N/A N/A

<MDC 0

Cs-137 150

<MDC N/A N/A

<MDC 0

Ra-226 N/A

<MDC N/A N/A

<MDC 0

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 56 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

BLUE CRABS GAMMA 4

(pCi/kg wet)

K-40 N/A 2340 (2/2)

SA-ECH-12B1 C 2551 (2/2) 2551 (2/2) 0 (2291/2389) 1.8 MILES WSW (2238/2864)

(2238/2864)

Mn-54 130

<MDC N/A N/A

<MDC 0

Co-58 130

<MDC N/A N/A

<MDC 0

Fe-59 260

<MDC N/A N/A

<MDC 0

Co-60 130

<MDC N/A N/A

<MDC 0

Zn-65 260

<MDC N/A N/A

<MDC 0

Cs-134 130

<MDC N/A N/A

<MDC 0

Cs-137 150

<MDC N/A N/A

<MDC 0

Ra-226 N/A

<MDC N/A N/A

<MDC 0

BROAD-LEAF VEGETATION, GAMMA 16 FPL (pCi/kg wet)

Be-7 N/A 1534 (4/12)

SA-FPL-10D1 C 2156 (2/4) 2156 (2/4) 0 (1288/2032) 3.9 MILES SSW (1474/2837)

(1474/2837)

K-40 N/A 5299 (12/12)

SA-FPL-06S1 6734 (4/4) 5289 (4/4) 0 (1587/11770) 0.17 MILES SE (3081/11770)

(2923/7651)

I-131 60

<MDC N/A N/A

<MDC 0

Cs-134 60

<MDC N/A N/A

<MDC 0

Cs-137 80

<MDC N/A N/A

<MDC 0

Ra-226 N/A

<MDC N/A N/A

<MDC 0

Th-232 N/A

<MDC N/A N/A N/A 0

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 57 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

VEGETABLES, FPV GAMMA 14 (pCi/kg wet)

Be-7 N/A

<MDC N/A N/A N/A 0

K-40 N/A 1966 (14/14)

SA-FPV-15F4 2286 (3/3)

N/A 0

(1147/3197) 7.0 MILES NW (2152/2500)

I-131 60

<MDC N/A N/A N/A 0

Cs-134 60

<MDC N/A N/A N/A 0

Cs-137 80

<MDC N/A N/A N/A 0

Ra-226 N/A

<MDC N/A N/A N/A 0

Th-232 N/A

<MDC N/A N/A N/A 0

FODDER CROPS GAMMA 3

(pCi/kg wet)

Be-7 N/A 473 (2/3)

SA-VGT-13E3 491 (1/1)

N/A 0

(455/491) 5.0 MILES W K-40 N/A 4499 (3/3)

SA-VGT-14F4 6814 (1/1)

N/A 0

(2990/6814) 7.6 MILES WNW I-131 60

<MDC N/A N/A N/A 0

FODDER CROPS (cont.)

Cs-134 60

<MDC N/A N/A N/A 0

(pCi/kg wet)

Cs-137 80

<MDC N/A N/A N/A 0

Ra-226 N/A

<MDC N/A N/A N/A 0

Th-232 N/A

<MDC N/A N/A N/A 0

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 58 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Data Table Summary SALEM GENERATING STATION DOCKET NO. 50-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 SALEM COUNTY, NEW JERSEY REPORTING PERIOD: January 1, 2024 to December 31, 2024 MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)

ANALYSIS AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD*)

ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NUMBER OF NONROUTINE REPORTED MEASUREMENTS MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

GAME GAMMA 1

(pCi/kg wet)

Be-7 N/A

<MDC N/A N/A N/A 0

K-40 N/A 2167 (1/1)

SA-GAM-13E3 2167 (1/1)

N/A 0

5.0 MILES W I-131 60

<MDC N/A N/A N/A 0

Cs-134 60

<MDC N/A N/A N/A 0

Cs-137 80

<MDC N/A N/A N/A 0

V. TERRESTRIAL SOIL GAMMA 0

(pCi/kg dry)

Be-7 N/A N/A N/A N/A N/A 0

K-40 N/A N/A N/A N/A N/A 0

Cs-134 150 N/A N/A N/A N/A 0

Cs-137 180 N/A N/A N/A N/A 0

Ra-226 N/A N/A N/A N/A N.A 0

Th-232 N/A N/A N/A N/A N/A 0

The LLD listed is the Lower Limit of Detection, which was requested by PSEG to be achieved.

- Mean was calculated using values above the MDC only. f = the fraction of measurements above the MDC.

(C) = Control Location N/A = Not Applicable I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 59 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Complete Data Table for All Analysis Results Obtained In 2024 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 60 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 12, Environmental Direct Radiation Dosimetry Sample Results Monitoring Location Quarterly

Baseline, BQ (mrem)

Minimum Differential Dose BQ + 5 (mrem)

Normalized Quarterly Monitoring Data, MQ Quarterly Facility Dose, FQ=MQ-BQ Annual

Baseline, BA (mrem)

Minimum Differential Dose BA + 13 (mrem)

Annual Monitoring Data, MA (mrem)

Annual Facility

Dose, FA=MA-BA (mrem)

(mrem)

(mrem) 1 2

3 4

1 2

3 4

01Q1 13.6 18.6 32.6 31.9 31.5 31.9 19.0 18.3 17.9 18.3 54.6 67.7 127.8 73.2 16Q2 13.6 18.6 28.4 27.5 25.9 27.5 14.9 13.9 12.4 13.9 54.6 67.7 109.3 54.7 01X2 13.0 18.0 14.2 14.6 14.6 15.6 ND ND ND ND 52.1 65.1 59.0 ND 02X4 13.7 18.7 13.6 14.7 14.1 15.0 ND ND ND ND 54.7 67.7 57.3 ND 03X1 12.3 17.3 12.4 12.5 12.6 13.1 ND ND ND ND 49.0 62.1 50.6 ND 04X1 11.9 16.9 12.6 12.6 13.2 13.9 ND ND ND ND 47.8 60.8 52.3 ND 05X1 10.7 15.7 12.7 11.8 12.1 12.8 ND ND ND ND 42.8 55.8 49.4 ND 06X2 15.0 20.0 13.8 13.5 13.6 14.2 ND ND ND ND 60.5 73.5 55.1 ND 16X3 12.2 17.2 14.1 15.7 15.7 16.9 ND ND ND ND 48.8 61.8 62.4 13.6 2S2A 14.6 19.6 15.0 14.3 15.0 15.5 ND ND ND ND 58.4 71.5 59.7 ND 04X1 Dup 11.9 16.9 12.7 12.7 12.9 14.4 ND ND ND ND 47.8 60.8 52.7 ND 07S1 12.5 17.5 12.8 12.7 13.3 13.3 ND ND ND ND 49.9 63.0 52.1 ND 08S1 11.0 16.0 10.9 10.7 11.1 11.8 ND ND ND ND 44.1 57.2 44.5 ND 08S2 11.3 16.3 10.5 10.8 11.0 11.4 ND ND ND ND 45.3 58.3 43.6 ND 10S1 11.6 16.6 12.5 12.2 12.3 13.0 ND ND ND ND 47.3 60.3 49.9 ND 11S1 10.7 15.7 12.1 11.9 12.3 13.0 ND ND ND ND 43.8 56.8 49.4 ND 12S1 14.4 19.4 16.9 15.4 15.6 16.4 ND ND ND ND 57.7 70.7 64.2 ND 14S2 16.3 21.3 16.9 15.4 16.4 18.0 ND ND ND ND 65.2 78.3 66.7 ND 15S1 10.8 15.8 12.3 12.0 12.7 13.0 ND ND ND ND 43.3 56.3 49.9 ND 15S2 13.2 18.2 13.1 13.1 13.5 13.7 ND ND ND ND 52.6 65.7 53.4 ND 15S3 16.0 21.0 16.3 15.3 16.6 17.7 ND ND ND ND 63.9 77.0 65.9 ND 16S1 12.8 17.8 14.3 14.3 14.9 15.2 ND ND ND ND 51.4 64.5 58.7 ND 04D2 13.0 18.0 13.9 14.3 14.7 15.3 ND ND ND ND 52.3 65.3 58.2 ND 05D1 13.6 18.6 13.6 13.3 13.7 14.5 ND ND ND ND 54.3 67.3 55.1 ND 10D1 13.7 18.7 14.3 15.3 15.6 16.1 ND ND ND ND 55.2 68.2 61.3 ND 14D1 12.0 17.0 13.1 13.0 13.4 13.6 ND ND ND ND 48.1 61.2 53.0 ND 15D1 13.6 18.6 13.9 14.6 14.4 14.7 ND ND ND ND 54.7 67.7 57.5 ND 02E1 12.3 17.3 13.3 13.2 13.5 14.1 ND ND ND ND 49.5 62.6 54.1 ND 03E1 10.4 15.4 11.8 12.2 12.3 12.6 ND ND ND ND 42.0 55.0 48.9 ND 11E2 13.6 18.6 14.7 15.5 15.9 16.0 ND ND ND ND 54.7 67.8 62.2 ND 12E1 13.7 18.7 14.4 15.0 15.8 16.4 ND ND ND ND 55.4 68.4 61.5 ND 13E1 10.9 15.9 12.1 12.2 12.2 12.7 ND ND ND ND 44.0 57.0 49.1 ND 16E1 12.8 17.8 13.9 13.4 14.0 14.5 ND ND ND ND 51.7 64.7 55.9 ND I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 61 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 12, Environmental Direct Radiation Dosimetry Sample Results Monitoring Location Quarterly

Baseline, BQ (mrem)

Minimum Differential Dose BQ + 5 (mrem)

Normalized Quarterly Monitoring Data, MQ Quarterly Facility Dose, FQ=MQ-BQ Annual

Baseline, BA (mrem)

Minimum Differential Dose BA + 13 (mrem)

Annual Monitoring Data, MA (mrem)

Annual Facility

Dose, FA=MA-BA (mrem)

(mrem)

(mrem) 1 2

3 4

1 2

3 4

01F1 17.8 22.8 17.7 18.1 18.2 18.9 ND ND ND ND 68.3 81.3 72.8 ND 02F2 12.8 17.8 12.9 12.8 13.1 13.8 ND ND ND ND 51.2 64.2 52.5 ND 02F5 12.8 17.8 14.1 14.0 14.4 14.7 ND ND ND ND 51.4 64.4 57.2 ND 02F6 11.9 16.9 13.8 13.6 13.7 14.6 ND ND ND ND 47.6 60.7 55.7 ND 03F2 11.0 16.0 12.7 12.4 12.9 12.9 ND ND ND ND 44.4 57.5 50.8 ND 03F3 11.0 16.0 13.1 12.8 13.0 13.1 ND ND ND ND 44.2 57.3 51.9 ND 04F2 10.7 15.7 12.3 12.5 12.7 13.0 ND ND ND ND 43.1 56.2 50.4 ND 05F1 11.5 16.5 12.6 13.3 13.4 13.9 ND ND ND ND 46.1 59.2 53.2 ND 06F1 11.0 16.0 10.6 11.0 11.3 11.5 ND ND ND ND 45.1 58.2 44.4 ND 07F2 13.0 18.0 12.5 13.3 13.3 13.5 ND ND ND ND 52.3 65.3 52.6 ND 09F1 14.2 19.2 14.2 15.5 16.1 16.3 ND ND ND ND 59.9 72.9 62.1 ND 09F2 14.1 19.1 12.2 11.9 12.5 12.4 ND ND ND ND 56.3 69.3 48.9 ND 10F2 13.2 18.2 14.1 14.3 14.9 15.4 ND ND ND ND 52.9 66.0 58.7 ND 11F1 13.8 18.8 14.6 15.0 15.5 15.8 ND ND ND ND 55.4 68.4 61.0 ND 12F1 12.9 17.9 14.4 14.6 14.6 15.1 ND ND ND ND 51.7 64.7 58.7 ND 13F2 12.7 17.7 13.7 14.2 14.4 14.6 ND ND ND ND 51.2 64.2 56.9 ND 13F3 14.7 19.7 14.3 14.5 14.8 15.6 ND ND ND ND 58.0 71.0 59.2 ND 13F4 13.0 18.0 14.6 15.1 15.1 16.0 ND ND ND ND 59.7 72.7 60.8 ND 14F2 14.0 19.0 15.3 15.8 15.8 16.4 ND ND ND ND 56.2 69.2 63.3 ND 15F3 14.5 19.5 14.7 15.6 15.7 16.5 ND ND ND ND 58.2 71.2 62.4 ND 16F2 11.7 16.7 13.5 13.4 13.8 14.1 ND ND ND ND 47.1 60.2 54.7 ND 01G3 14.9 19.9 13.8 14.2 14.0 14.8 ND ND ND ND 60.2 73.3 56.7 ND 03G1 13.3 18.3 14.5 15.0 15.4 15.8 ND ND ND ND 53.4 66.5 60.7 ND 10G1 14.8 19.8 14.7 14.8 15.6 15.3 ND ND ND ND 58.8 71.9 60.4 ND 14G1 13.4 18.4 14.6 15.0 14.9 15.2 ND ND ND ND 54.1 67.1 59.6 ND 16G1 12.7 17.7 13.0 13.0 13.3 13.3 ND ND ND ND 50.1 63.2 52.6 ND 03H1 12.6 17.6 12.3 12.6 12.8 13.2 ND ND ND ND 50.6 63.6 51.0 ND MDDQ = Quarterly Minimum Differential Dose = 5 mrem MDDA = Annual Minimum Differential Dose = 13 mrem ND = Not Detected, where MQ (BQ+MDDQ) or MA (BA+MDDA)

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 62 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 13, Concentrations of Gamma Emitters in Quarterly Composites of Air Particulates, 2024 Results in Units of E-03 pCi/m3 +/- 2 STATION ID COLLECTION PERIOD

<------------GAMMA EMITTERS------------>

START STOP Be-7 K-40 Cs-134 Cs-137 SA-APT-14G1 (C) 01/02/24 04/01/24 55 +/- 13

< 31

< 2

< 2 04/01/24 07/01/24 58 +/- 13

< 21

< 1

< 1 07/01/24 09/30/24 62 +/- 13

< 29

< 2

< 1 09/30/24 12/31/24 40 +/- 14

< 32

< 2

< 2 AVERAGE*

54 +/- 19 SA-APT-05X1 01/02/24 04/01/24 42 +/- 13

< 30

< 2

< 2 04/01/24 07/01/24 45 +/- 12

< 25

< 2

< 1 07/01/24 09/30/24 51 +/- 14

< 22

< 2

< 2 09/30/24 12/31/24 35 +/- 15

< 27

< 2

< 2 AVERAGE*

43 +/- 14 SA-APT-06S1 01/02/24 04/01/24 31 +/- 12

< 24

< 2

< 1 04/01/24 07/01/24 52 +/- 15

< 36

< 3

< 2 07/01/24 09/30/24 51 +/- 13

< 24

< 1

< 1 09/30/24 12/31/24 44 +/- 13

< 33

< 1

< 1 AVERAGE*

45 +/- 20 SA-APT-15S2 01/02/24 04/01/24 50 +/- 10

< 21

< 1

< 1 04/01/24 07/01/24 64 +/- 11

< 24

< 1

< 1 07/01/24 09/30/24 52 +/- 15

< 28

< 1

< 1 09/30/24 12/31/24 43 +/- 9

< 21

< 1

< 1 AVERAGE*

52 +/- 18 SA-APT-05D1 01/02/24 04/01/24 46 +/- 9

< 26

< 1

< 1 04/01/24 07/01/24 53 +/- 16

< 27

< 2

< 2 07/01/24 09/30/24 46 +/- 17

< 31

< 2

< 2 09/30/24 12/31/24 41 +/- 11

< 17

< 1

< 1 AVERAGE*

47 +/- 10 SA-APT-16E1 01/02/24 04/01/24 36 +/- 13

< 20

< 2

< 1 04/01/24 07/01/24 55 +/- 15

< 30

< 2

< 1 07/01/24 09/30/24 71 +/- 22

< 39

< 3

< 3 09/30/24 12/31/24 39 +/- 10

< 31

< 1

< 1 AVERAGE*

50 +/- 32 I

I I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 63 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 13, Concentrations of Gamma Emitters in Quarterly Composites of Air Particulates, 2024 Results in Units of E-03 pCi/m3 +/- 2 STATION ID COLLECTION PERIOD

<------------GAMMA EMITTERS------------>

START STOP Be-7 K-40 Cs-134 Cs-137 SA-APT-01F1 01/02/24 04/01/24 42 +/- 19

< 38

< 2

< 2 04/01/24 07/01/24 52 +/- 13

< 21

< 1

< 1 07/01/24 09/30/24 52 +/- 13

< 27

< 1

< 1 09/30/24 12/31/24 40 +/- 10

< 22

< 2

< 1 AVERAGE*

47 +/- 13 SA-APT-02F6 01/02/24 04/01/24 48 +/- 11

< 28

< 1

< 1 04/01/24 07/01/24 51 +/- 12

< 26

< 1

< 1 07/01/24 09/30/24 38 +/- 12

< 23

< 1

< 1 09/30/24 12/31/24 41 +/- 11

< 36

< 2

< 2 AVERAGE*

45 +/- 12 ALL INDICATOR AVERAGE *.

47 +/- 17 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 64 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 14, Concentrations of Gross Beta Emitters in Air Particulates, 2024 Results in Units of E-03 pCi/m3 +/- 2 COLLECTION PERIOD CONTROL INDICATORS START STOP SA-APT-14G1 SA-APT-05X1 SA-APT-06S1 SA-APT-15S2 SA-APT-05D1 SA-APT-16E1 SA-APT-01F1 SA-APT-02F6 01/02/24 -

01/08/24 9 +/- 3 9 +/- 3 13 +/- 3 10

+/-

3 9 +/- 3 6 +/- 3 9 +/- 3 6 +/- 3 01/08/24 -

01/16/24 18 +/- 3 15 +/- 3 16 +/- 3 16

+/-

3 17 +/- 3 17 +/- 3 14 +/- 3 12 +/- 3 01/16/24 -

01/22/24

< 40 E 18 +/- 4 17 +/- 4 18

+/-

4 16 +/- 4 18 +/- 4 16 +/- 4 14 +/- 4 01/22/24 -

01/29/24 9 +/- 3 5 +/- 3 5 +/- 2 9

+/-

3 7 +/- 3 9 +/- 3 9 +/- 3 4 +/- 2 01/29/24 -

02/05/24 10 +/- 3 9 +/- 3 6 +/- 3 8

+/-

3 8 +/- 3 8 +/- 3 7 +/- 3 6 +/- 3 02/05/24 -

02/12/24 17 +/- 3 10 +/- 3 11 +/- 3 11

+/-

3 11 +/- 3 10 +/- 3 9 +/- 3 8 +/- 2 02/12/24 -

02/20/24 12 +/- 3 13 +/- 3 13 +/- 3 13

+/-

3 16 +/- 3 15 +/- 3 14 +/- 3 12 +/- 2 02/20/24 -

02/26/24 10 +/- 3 16 +/- 4 18 +/- 4 17

+/-

4 13 +/- 4 13 +/- 3 14 +/- 3 10 +/- 3 02/26/24 -

03/04/24 17 +/- 3 15 +/- 3 11 +/- 3 15

+/-

3 15 +/- 3 10 +/- 3 12 +/- 3 10 +/- 3 03/04/24 -

03/11/24 6 +/- 2 7 +/- 2 6 +/- 2 7

+/-

2 5 +/- 2 7 +/- 2 5 +/- 2 6 +/- 2 03/11/24 -

03/18/24 19 +/- 3 16 +/- 3 17 +/- 3 16

+/-

3 20 +/- 3 19 +/- 3 17 +/- 3 12 +/- 3 03/18/24 -

03/25/24 10 +/- 3 10 +/- 3 10 +/- 3 7

+/-

3 10 +/- 3 9 +/- 3 7 +/- 3 8 +/- 3 03/25/24 -

04/01/24 11 +/- 3 13 +/- 3 11 +/- 3 14

+/-

3 13 +/- 3 12 +/- 3 9 +/- 3 11 +/- 3 04/01/24 -

04/08/24 6 +/- 2 4 +/- 2 7 +/- 2 6

+/-

2 5 +/- 2 5 +/- 2

< 3 5 +/- 2 04/08/24 -

04/15/24 12 +/- 3 9 +/- 3 8 +/- 3 12

+/-

3 9 +/- 3 11 +/- 3 11 +/- 3 8 +/- 3 04/15/24 -

04/22/24 13 +/- 3 14 +/- 3 14 +/- 3 14

+/-

3 13 +/- 3 11 +/- 3 13 +/- 3 8 +/- 3 04/22/24 -

04/29/24 16 +/- 3 4 +/- 2 14 +/- 3 16

+/-

3 14 +/- 3 12 +/- 3 13 +/- 3 12 +/- 3 04/29/24 -

05/06/24 12 +/- 3 11 +/- 3 10 +/- 3 12

+/-

3 14 +/- 3 14 +/- 3 13 +/- 3 8 +/- 3 05/06/24 -

05/13/24 6 +/- 3 5 +/- 3 7 +/- 3 4

+/-

3 8 +/- 3 6 +/- 3 6 +/- 3 5 +/- 3 05/13/24 -

05/21/24 7 +/- 3 5 +/- 2 6 +/- 2 6

+/-

2 7 +/- 2 8 +/- 2 6 +/- 2 5 +/- 2 05/21/24 -

05/28/24 16 +/- 3 10 +/- 3 13 +/- 3 12

+/-

3 11 +/- 3 14 +/- 3 13 +/- 3 11 +/- 3 05/28/24 -

06/03/24 15 +/- 3 13 +/- 3 14 +/- 3 18

+/-

4 14 +/- 3 15 +/- 3 13 +/- 3 13 +/- 3 06/03/24 -

06/10/24 12 +/- 3 14 +/- 3 11 +/- 3 14

+/-

3 14 +/- 3 12 +/- 3 11 +/- 3 5 +/- 3 06/10/24 -

06/17/24 9 +/- 3 9 +/- 3 10 +/- 3 11

+/-

3 9 +/- 3 11 +/- 3 10 +/- 3 6 +/- 3 06/17/24 -

06/24/24 16 +/- 3 13 +/- 3 11 +/- 3 17

+/-

3 14 +/- 3 13 +/- 3 12 +/- 3 12 +/- 3 06/24/24 -

07/01/24 14 +/- 3 11 +/- 3 9 +/- 3 11

+/-

3 9 +/- 3 12 +/- 3 9 +/- 3 8 +/- 3 07/01/24 -

07/08/24 11 +/- 3 10 +/- 3 10 +/- 3 7

+/-

3 10 +/- 3 11 +/- 3 8 +/- 3 6 +/- 3 07/08/24 -

07/16/24 12 +/- 3 12 +/- 3 12 +/- 3 12

+/-

3 13 +/- 3 10 +/- 3 13 +/- 3 8 +/- 3 07/16/24 -

07/22/24 14 +/- 4 15 +/- 3 17 +/- 4 13

+/-

3 18 +/- 3 15 +/- 4 16 +/- 4 12 +/- 3 07/22/24 -

07/29/24 16 +/- 3 14 +/- 3 11 +/- 3 13

+/-

3 14 +/- 3 13 +/- 3 14 +/- 3 9 +/- 3 07/29/24 -

08/05/24 20 +/- 4 18 +/- 3 19 +/- 3 17

+/-

3 17 +/- 3 16 +/- 3 17 +/- 3 15 +/- 3 08/05/24 -

08/12/24 15 +/- 3 14 +/- 3 14 +/- 3 13

+/-

3 15 +/- 3 11 +/- 3 14 +/- 3 10 +/- 3 08/12/24 -

08/19/24 17 +/- 3 17 +/- 3 17 +/- 3 17

+/-

3 15 +/- 3 17 +/- 3 13 +/- 3 10 +/- 3 08/19/24 -

08/26/24 12 +/- 3 14 +/- 3 14 +/- 3 11

+/-

3 13 +/- 3 13 +/- 3 10 +/- 3 10 +/- 3 08/26/24 -

09/03/24 21 +/- 3 17 +/- 3 17 +/- 3 20

+/-

3 16 +/- 3 19 +/- 3 18 +/- 3 13 +/- 3 09/03/24 -

09/09/24 12 +/- 3 8 +/- 3 11 +/- 3 10

+/-

3 14 +/- 3 12 +/- 3 11 +/- 3 9 +/- 3 09/09/24 -

09/16/24 21 +/- 3 21 +/- 4 18 +/- 3 21

+/-

3 21 +/- 3 20 +/- 3 22 +/- 4 14 +/- 3 09/16/24 -

09/23/24 17 +/- 3 16 +/- 3 15 +/- 3 17

+/-

3 16 +/- 3 17 +/- 3 15 +/- 3 13 +/- 3 09/23/24 -

09/30/24 5 +/- 3 6 +/- 3 4 +/- 3 8

+/-

3

< 4 5 +/- 3 5 +/- 2

< 4 09/30/24 -

10/07/24 14 +/- 3 17 +/- 3 15 +/- 3 16

+/-

3 15 +/- 3 13 +/- 3 11 +/- 3 11 +/- 3 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 65 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 14, Concentrations of Gross Beta Emitters in Air Particulates, 2024 Results in Units of E-03 pCi/m3 +/- 2 COLLECTION PERIOD CONTROL INDICATORS START STOP SA-APT-14G1 SA-APT-05X1 SA-APT-06S1 SA-APT-15S2 SA-APT-05D1 SA-APT-16E1 SA-APT-01F1 SA-APT-02F6 10/07/24 -

10/14/24 23 +/- 4 19 +/- 3 24 +/- 4 18

+/-

3 21 +/- 4 20 +/- 3 17 +/- 3 15 +/- 3 10/14/24 -

10/21/24 13 +/- 3 14 +/- 3 12 +/- 3 11

+/-

3 11 +/- 3 12 +/- 3 12 +/- 3 9 +/- 3 10/21/24 -

10/28/24 29 +/- 4 25 +/- 4 22 +/- 3 23

+/-

3 25 +/- 4 27 +/- 4 23 +/- 3 17 +/- 3 10/28/24 -

11/04/24 16 +/- 3 15 +/- 3 13 +/- 3 17

+/-

3 16 +/- 3 17 +/- 3 13 +/- 3 9 +/- 3 11/04/24 -

11/12/24 14 +/- 3 10 +/- 3 15 +/- 4 11

+/-

3 13 +/- 3 15 +/- 3 11 +/- 3 9 +/- 3 11/12/24 -

11/18/24 13 +/- 3 13 +/- 3 12 +/- 3 11

+/-

3 13 +/- 4 10 +/- 3 13 +/- 4 12 +/- 3 11/18/24 -

11/25/24 21 +/- 3 19 +/- 3 20 +/- 4 20

+/-

3 20 +/- 3 18 +/- 3 13 +/- 3 13 +/- 3 11/25/24 -

12/02/24 21 +/- 3 23 +/- 4 20 +/- 3 22

+/-

4 21 +/- 4 20 +/- 3 19 +/- 3 15 +/- 3 12/02/24 -

12/09/24 17 +/- 3 15 +/- 3 20 +/- 3 16

+/-

3 17 +/- 3 18 +/- 3 17 +/- 3 13 +/- 3 12/09/24 -

12/16/24 17 +/- 3 17 +/- 3 16 +/- 3 17

+/-

3 16 +/- 3 17 +/- 3 19 +/- 3 14 +/- 3 12/16/24 -

12/24/24 12 +/- 3 12 +/- 3 10 +/- 3 11

+/-

3 13 +/- 3 11 +/- 3 8 +/- 3 11 +/- 3 12/24/24 -

12/31/24 15 +/- 3 18 +/- 3 15 +/- 3 17

+/-

3 13 +/- 3 12 +/- 3 12 +/- 3 15 +/- 3 AVERAGE*

14 +/- 10 13 +/- 9 13 +/- 9 13 +/-

9 14 +/- 8 13 +/- 9 12 +/- 8 10 +/- 6 ALL INDICATOR AVERAGE* 13 +/- 9 THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING ONLY THE POSITIVE VALUES. IF THERE IS ONLY 1 POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

E SEE SAMPLE ANOMOLIES AND PROGRAM EXCEPTIONS SECTION OF THIS REPORT I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 66 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 15, Concentrations of Iodine-131 in Filtered Air, 2024 Results in Units of E-03 pCi/m3 +/- 2 COLLECTION PERIOD CONTROL INDICATORS START STOP SA-AIO-14G1 SA-AIO-05X1 SA-AIO-06S1 SA-AIO-15S2 SA-AIO-05D1 SA-AIO-16E1 SA-AIO-01F1 SA-AIO-02F6 01/02/24 01/08/24

< 23

< 30

< 24

< 23

< 31

< 24

< 28

< 29 01/08/24 01/16/24

< 31

< 39

< 31

< 30

< 42

< 33

< 39

< 41 01/16/24 01/22/24

< 106 E

< 23

< 17

< 25

< 18

< 23

< 10 01/22/24 01/29/24

< 9

< 34

< 22

< 34

< 24

< 33

< 33 01/29/24 02/05/24

< 19

< 27

< 21

< 20

< 27

< 20

< 26

< 27 02/05/24 02/12/24

< 24

< 20

< 22

< 21

< 20

< 22

< 19

< 8 02/12/24 02/20/24

< 29

< 15

< 30

< 29

< 15

< 33

< 14

< 13 02/20/24 02/26/24

< 26

< 31

< 24

< 33

< 25

< 30

< 27 02/26/24 03/04/24

< 21

< 22

< 20

< 19

< 22

< 20

< 21

< 23 03/04/24 03/11/24

< 24

< 21

< 23

< 25

< 20

< 24

< 20

< 20 03/11/24 03/18/24

< 27

< 29

< 25

< 26

< 12

< 27

< 29

< 29 03/18/24 03/25/24

< 18

< 27

< 11

< 18

< 26

< 18

< 26

< 26 03/25/24 04/01/24

< 31

< 29

< 30

< 12

< 28

< 28 04/01/24 04/08/24

< 17

< 18

< 17

< 17 04/08/24 04/15/24

< 19

< 24

< 18

< 24

< 18

< 25

< 25 04/15/24 04/22/24

< 16

< 20

< 16

< 17

< 20

< 12

< 21

< 20 04/22/24 04/29/24

< 29

< 33

< 27

< 28

< 13

< 27

< 35

< 35 04/29/24 05/06/24

< 21

< 20

< 21

< 23

< 8

< 21

< 22 05/06/24 05/13/24

< 19

< 23

< 18

< 19

< 22

< 18

< 24

< 26 05/13/24 05/21/24

< 15

< 26

< 14

< 27

< 14

< 28

< 27 05/21/24 05/28/24

< 17

< 27

< 17

< 24

< 16

< 27

< 28 05/28/24 06/03/24

< 20

< 35

< 21

< 20

< 34

< 19

< 33

< 34 06/03/24 06/10/24

< 15

< 18

< 15

< 17

< 14

< 12

< 19 06/10/24 06/17/24

< 27

< 26

< 27

< 24

< 25

< 27 06/17/24 06/24/24

< 42

< 26

< 43

< 46

< 27

< 41

< 26

< 26 06/24/24 07/01/24

< 20

< 19

< 18

< 17

< 20

< 19

< 20

< 20 07/01/24 07/08/24

< 16

< 21

< 15

< 30

< 21

< 15

< 22

< 23 07/08/24 07/16/24

< 16

< 21

< 16

< 17

< 20

< 16

< 21

< 22 07/16/24 07/22/24

< 21

< 22

< 20

< 19

< 20

< 23

< 21 07/22/24 07/29/24

< 17

< 23

< 16

< 22

< 16

< 23

< 22 07/29/24 08/05/24

< 28

< 23

< 26

< 25

< 23

< 26

< 23

< 22 08/05/24 08/12/24

< 23

< 19

< 22

< 19

< 23

< 19

< 20 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 67 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 15, Concentrations of Iodine-131 in Filtered Air, 2024 Results in Units of E-03 pCi/m3 +/- 2 COLLECTION PERIOD CONTROL INDICATORS START STOP SA-AIO-14G1 SA-AIO-05X1 SA-AIO-06S1 SA-AIO-15S2 SA-AIO-05D1 SA-AIO-16E1 SA-AIO-01F1 SA-AIO-02F6 08/12/24 08/19/24

< 21

< 19

< 21

< 19

< 21

< 19

< 13 08/19/24 08/26/24

< 24

< 17

< 25

< 24

< 18

< 25

< 17

< 16 08/26/24 09/03/24

< 10

< 17

< 22

< 17

< 22

< 17

< 17 09/03/24 09/09/24

< 18

< 22

< 17

< 23

< 17

< 23

< 21 09/09/24 09/16/24

< 27

< 25

< 26

< 27

< 28

< 24 09/16/24 09/23/24

< 23

< 24

< 23

< 10

< 24

< 23

< 21

< 23 09/23/24 09/30/24

< 17

< 27

< 18

< 17

< 27

< 18

< 24

< 29 09/30/24 10/07/24

< 19

< 14

< 19

< 18

< 14

< 15

< 12

< 14 10/07/24 10/14/24

< 23

< 19

< 23

< 22

< 19

< 24

< 19

< 18 10/14/24 10/21/24

< 20

< 14

< 20

< 12

< 14

< 20

< 14

< 12 10/21/24 10/28/24

< 17

< 18

< 17

< 19

< 18

< 16 10/28/24 11/04/24

< 25

< 18

< 26

< 24

< 18

< 26

< 16

< 17 11/04/24 11/12/24

< 26

< 23

< 43

< 24

< 26

< 25

< 23 11/12/24 11/18/24

< 26

< 28

< 27

< 24

< 29

< 27

< 31

< 27 11/18/24 11/25/24

< 18

< 12

< 19

< 13

< 11

< 18

< 12

< 11 11/25/24 12/02/24

< 36

< 23

< 37

< 24

< 37

< 10

< 22 12/02/24 12/09/24

< 21

< 18

< 21

< 17

< 21

< 16

< 17 12/09/24 12/16/24

< 26

< 22

< 25

< 24

< 20

< 27

< 20

< 22 12/16/24 12/24/24

< 19

< 16

< 19

< 18

< 16

< 17

< 9 12/24/24 12/31/24

< 27

< 26

< 27

< 25

< 26

< 30

< 16

< 30 AVERAGE*

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING ONLY THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

E See Section 10.0 for additional detail I

I I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 68 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 16, Concentrations of Tritium in Surface Water, 2024 Results in Units of pCi/L +/- 2 COLLECTION PERIOD CONTROL INDICATORS START STOP SA-SWA-12B1 (C)

SA-SWA-11A1 SA-SWA-07E1 SA-SWA-01F2 SA-SWA-016F1 01/08/24 01/23/24

< 184 185

< 187

< 185

< 185 02/05/24 02/21/24

< 188

< 183

< 186

< 183

< 184 03/04/24 03/26/24

< 189

< 192

< 186

< 188

< 189 04/01/24 04/17/24

< 193

< 185

< 182

< 188 05/07/24 05/23/24

< 197 674 +/- 154

< 195

< 196

< 194 06/03/24 06/20/24

< 189

< 196

< 194

< 195

< 190 07/10/24 07/26/24

< 193

< 191

< 184

< 188

< 187 08/08/24 08/22/24

< 191

< 193

< 195

< 200 09/10/24 09/24/24

< 188

< 187

< 186

< 181

< 185 10/10/24 10/25/24

< 189

< 198

< 189

< 190 11/08/24 11/20/24

< 199

< 195

< 193

< 190

< 190 12/04/24 12/16/24

< 180

< 182

< 178

< 177

< 179 AVERAGE*

674

+/-

154 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES.

IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 69 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 17, Concentrations of Iodine-131 and Gamma Emitters in Surface Water, 2024 Results in Units of pCi/L +/- 2 STATION ID Collection Date

<------------GAMMA EMITTERS------------>

I-131 LL K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 Cs-134 Cs-137 BaLa-140 SA-SWA-12B1 (C) 01/08/24

< 0.9 49 +/- 31

< 2

< 3

< 5

< 3

< 5

< 3

< 2

< 5 02/05/24

< 0.8

< 82

< 4

< 6

< 13

< 5

< 9

< 6

< 7

< 5

< 10 03/04/24

< 0.7

< 98

< 6

< 11

< 8

< 12

< 6

< 6 04/01/24

< 0.8

< 93

< 5

< 11

< 5

< 10

< 5

< 6

< 5

< 7 05/07/24

< 0.7

< 97

< 6

< 4

< 12

< 7

< 9

< 6

< 8 06/03/24

< 0.9

< 47

< 4

< 5

< 11

< 3

< 12

< 5

< 7 07/10/24

< 0.7

< 90

< 4

< 6

< 5

< 8

< 4

< 5

< 3

< 6 08/08/24

< 0.8 115 +/- 38

< 3

< 7

< 4

< 7

< 3

< 4

< 3

< 5 09/10/24

< 0.7 72 +/- 26

< 1

< 2

< 3

< 2

< 3

< 2

< 3 10/10/24

< 0.7

< 92

< 4

< 5

< 9

< 5

< 10

< 6

< 5

< 6

< 8 11/08/24

< 0.8 144 +/- 60

< 4

< 9

< 4

< 7

< 4

< 8 12/04/24

< 0.8 107 +/- 40

< 3

< 7

< 3

< 7

< 3

< 5 AVERAGE*

97 +/- 74 SA-SWA-11A1 01/08/24

< 0.8 53 +/- 35

< 2

< 5

< 3

< 5

< 3

< 2

< 5 02/05/24

< 0.9

< 84

< 5

< 8

< 5

< 11

< 4

< 5

< 9 03/04/24

< 0.5

< 134

< 6

< 7

< 14

< 7

< 16

< 7

< 8

< 7

< 11 04/01/24

< 0.8

< 106

< 5

< 6

< 9

< 7

< 10

< 5

< 5 05/07/24

< 0.8

< 122

< 5

< 3

< 11

< 6

< 14

< 5

< 6

< 5

< 8 06/03/24

< 0.8 98 +/- 61

< 4

< 5

< 11

< 4

< 9

< 5

< 4

< 8 07/10/24

< 0.8

< 152

< 7

< 5

< 16

< 4

< 16

< 6

< 7

< 13 08/08/24

< 0.7 101 +/- 50

< 4

< 7

< 4

< 7

< 4

< 5

< 6 09/10/24

< 0.6 79 +/- 47

< 3

< 4

< 8

< 4

< 7

< 3

< 4

< 9 10/10/24

< 0.7 109 +/- 42

< 3

< 6

< 3

< 6

< 3

< 4 11/08/24

< 0.9 90 +/- 49

< 3

< 8

< 4

< 7

< 4

< 7 12/04/24

< 0.8 87 +/- 45

< 3

< 6

< 3

< 6

< 3

< 4 AVERAGE*

88 +/- 37 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 70 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 17, Concentrations of Iodine-131 and Gamma Emitters in Surface Water, 2024 Results in Units of pCi/L +/- 2 STATION ID Collection Date

<------------GAMMA EMITTERS------------>

I-131 LL K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 Cs-134 Cs-137 BaLa-140 SA-SWA-07E1 01/08/24

< 0.8 75 +/- 31

< 2

< 3

< 5

< 3

< 5

< 3

< 2

< 4 02/05/24

< 0.9 85 +/- 57

< 6

< 10

< 6

< 10

< 6

< 4

< 6

< 10 03/04/24

< 0.4

< 107

< 5

< 6

< 9

< 6

< 13

< 5

< 4

< 5

< 5 04/01/24

< 0.7

< 100

< 5

< 12

< 6

< 9

< 5

< 4

< 8 05/07/24

< 0.8

< 48

< 6

< 10

< 5

< 12

< 6

< 7

< 6

< 13 06/03/24

< 0.9

< 55

< 4

< 5

< 9

< 5

< 11

< 5

< 6

< 6 07/10/24

< 0.9

< 56

< 5

< 6

< 13

< 7

< 10

< 6

< 7

< 6

< 8 08/08/24

< 0.9 137 +/- 48

< 4

< 8

< 4

< 8

< 4

< 6 09/10/24

< 0.7 122 +/- 32

< 2

< 5

< 3

< 5

< 2

< 3

< 4 10/10/24

< 0.7 98 +/- 40

< 3

< 7

< 3

< 7

< 3

< 5 11/08/24

< 0.9 171 +/- 40

< 3

< 8

< 4

< 8

< 4

< 7 12/04/24

< 0.8 123 +/- 43

< 3

< 2

< 5

< 3

< 5

< 2

< 3

< 4 AVERAGE*

116 +/- 66 SA-SWA-01F2 01/08/24

< 0.9

< 18

< 2

< 4

< 2

< 4

< 2

< 4 02/05/24

< 0.8

< 84

< 4

< 11

< 5

< 9

< 4

< 10 03/04/24

< 0.6

< 128

< 2

< 5

< 13

< 7

< 18

< 6

< 8

< 6

< 10 04/01/24

< 0.9

< 75

< 4

< 8

< 5

< 8

< 4

< 5

< 4

< 7 05/07/24

< 0.9

< 135

< 8

< 7

< 13

< 7

< 12

< 7

< 11 06/03/24

< 0.9

< 76

< 5

< 6

< 12

< 5

< 11

< 6

< 5

< 9 07/10/24

< 0.9

< 120

< 5

< 10

< 7

< 11

< 5

< 6

< 5

< 7 08/08/24

< 0.7

< 41

< 4

< 3

< 7

< 4

< 7

< 4

< 3

< 6 09/10/24

< 0.5

< 15

< 2

< 4

< 2

< 4

< 2

< 3 10/10/24

< 0.7 90 +/- 48

< 4

< 3

< 9

< 4

< 10

< 5

< 4

< 6 11/08/24

< 0.9 109 +/- 43

< 4

< 11

< 5

< 8

< 4

< 9 12/04/24

< 0.9

< 26

< 3

< 7

< 4

< 7

< 3

< 4

< 3

< 5 AVERAGE*

101 +/- 23 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 71 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 17, Concentrations of Iodine-131 and Gamma Emitters in Surface Water, 2024 Results in Units of pCi/L +/- 2 STATION ID Collection Date

<------------GAMMA EMITTERS------------>

I-131 LL K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 Cs-134 Cs-137 BaLa-140 SA-SWA-16F1 01/08/24

< 0.8

< 21

< 2

< 5

< 2

< 4

< 3

< 2

< 4 02/05/24

< 0.9

< 90

< 5

< 12

< 7

< 11

< 7

< 5

< 6

< 10 03/04/24

< 0.5

< 122

< 6

< 11

< 6

< 14

< 7

< 6

< 7

< 8 04/01/24

< 0.7

< 100

< 6

< 5

< 9

< 6

< 9

< 6

< 5

< 8 05/07/24

< 0.7

< 74

< 5

< 11

< 6

< 8

< 5

< 6

< 5

< 7 06/03/24

< 0.8

< 44

< 5

< 4

< 11

< 6

< 8

< 4

< 6

< 8 07/10/24

< 0.7

< 94

< 5

< 11

< 5

< 8

< 5

< 6

< 5

< 7 08/08/24

< 0.8

< 27

< 3

< 6

< 4

< 6

< 3

< 4 09/10/24

< 0.6 53 +/- 27

< 2

< 4

< 2

< 3

< 2

< 3 10/10/24

< 0.8

< 37

< 5

< 9

< 4

< 8

< 5

< 4

< 8 11/08/24

< 0.9 114 +/- 48

< 3

< 8

< 4

< 8

< 4

< 8 12/04/24

< 0.8

< 30

< 3

< 2

< 6

< 3

< 6

< 3

< 4 AVERAGE*

84 +/- 87 ALL INDICATOR AVERAGE*

100 +/- 57 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 72 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 18, Concentrations of Gross Alpha and Gross Beta Emitters, and Tritium in Raw and Treated Potable Water, 2024 Results in Units of pCi/L +/- 2 COLLECTION PERIOD STATION ID START STOP Gross Alpha Gross Beta H-3 SA-PWR-02F3**

12/26/23 01/29/24

< 0.9 8.1 +/- 1.6

< 179 01/29/24 02/26/24

< 1.2 5.7 +/- 1.5

< 192 02/26/24 03/25/24

< 1.8 7.9 +/- 1.7

< 184 03/25/24 04/29/24

< 1.7 7.1 +/- 2.1

< 196 04/29/24 05/28/24

< 2.3 6.6 +/- 2.3

< 180 05/28/24 06/25/24

< 2.1 10.4 +/- 2.0

< 198 06/25/24 07/29/24

< 2.1 9.4 +/- 2.1

< 187 07/29/24 08/26/24

< 2.4 7.1 +/- 2.3

< 193 08/26/24 09/30/24

< 2.9 10.0 +/- 2.2

< 174 09/30/24 10/29/24

< 3.0 8.1 +/- 2.1

< 187 10/29/24 11/25/24

< 1.5 8.3 +/- 1.4

< 199 11/25/24 12/31/24

< 1.6 7.6 +/- 1.7

< 180 AVERAGE*

8.0 +/- 2.8 SA-PWT-02F3**

12/26/23 01/29/24

< 0.9 6.2 +/- 1.5

< 182 01/29/24 02/26/24

< 1.3 7.7 +/- 1.7

< 187 02/26/24 03/25/24

< 2.7 9.6 +/- 2.4

< 184 03/25/24 04/29/24

< 3.0 6.4 +/- 2.0

< 197 04/29/24 05/28/24

< 2.3 8.4 +/- 2.4

< 187 05/28/24 06/25/24

< 1.9 8.0 +/- 1.8

< 193 06/25/24 07/29/24

< 2.2 8.4 +/- 2.1

< 188 07/29/24 08/26/24

< 2.5 8.0 +/- 2.4

< 189 08/26/24 09/30/24

< 2.7 10.7 +/- 2.2

< 174 09/30/24 10/29/24

< 2.4 9.4 +/- 1.5

< 182 10/29/24 11/25/24

< 1.5 9.9 +/- 1.5

< 192 11/25/24 12/31/24

< 1.6 8.9 +/- 1.7

< 180 AVERAGE*

8.5 +/- 2.7 THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 73 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 19, Concentrations of Iodine-131 and Gamma Emitters in Raw and Treated Potable Water, 2024 Results in Units of pCi/L +/- 2 COLLECTION PERIOD

< - - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

STATION ID START STOP I-131 LL K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 Cs-134 Cs-137 BaLa-140 Ra-226 SA-PWR-02F3**

12/26/23 01/29/24

< 0.8

< 98

< 5

< 4

< 12

< 5

< 11

< 6

< 5

< 10

< 118 01/29/24 02/26/24

< 0.7

< 113

< 6

< 15

< 6

< 13

< 6

< 7

< 6

< 9

< 176 02/26/24 03/25/24

< 0.5

< 132

< 6

< 8

< 7

< 12

< 7

< 6

< 7

< 11

< 156 03/25/24 04/29/24

< 0.6

< 114

< 8

< 6

< 14

< 8

< 16

< 9

< 7

< 8

< 182 04/29/24 05/28/24

< 0.8

< 121

< 7

< 12

< 2

< 15

< 7

< 194 05/28/24 06/25/24

< 0.8

< 111

< 5

< 13

< 5

< 11

< 6

< 7

< 6

< 145 06/25/24 07/29/24

< 0.7

< 114

< 7

< 14

< 9

< 10

< 9

< 7

< 8

< 170 07/29/24 08/26/24

< 0.8

< 98

< 4

< 5

< 11

< 5

< 9

< 5

< 6

< 5

< 7

< 135 08/26/24 09/30/24

< 0.4

< 114

< 8

< 18

< 7

< 13

< 8

< 7

< 9

< 176 09/30/24 10/29/24

< 0.6

< 109

< 6

< 5

< 11

< 7

< 12

< 6

< 5

< 6

< 8

< 163 10/29/24 11/25/24

< 0.6

< 98

< 6

< 12

< 5

< 11

< 7

< 6

< 10

< 158 11/25/24 12/31/24

< 0.8

< 49

< 3

< 6

< 3

< 6

< 3

< 4

< 3

< 6

< 66 AVERAGE*

SA-PWT-02F3**

12/26/23 01/29/24

< 0.6

< 73

< 5

< 10

< 5

< 11

< 6

< 5

< 10

< 144 01/29/24 02/26/24

< 0.9

< 117

< 7

< 6

< 14

< 7

< 15

< 8

< 7

< 9

< 157 02/26/24 03/25/24

< 0.6

< 92

< 6

< 5

< 10

< 8

< 12

< 5

< 7

< 6

< 7

< 169 03/25/24 04/29/24

< 0.5

< 96

< 6

< 4

< 12

< 7

< 11

< 6

< 8

< 6

< 8

< 170 04/29/24 05/28/24

< 0.8

< 109

< 6

< 8

< 14

< 7

< 16

< 6

< 7

< 9

< 164 05/28/24 06/25/24

< 0.7

< 123

< 7

< 15

< 7

< 18

< 8

< 7

< 168 06/25/24 07/29/24

< 0.7

< 71

< 6

< 5

< 11

< 6

< 14

< 6

< 7

< 6

< 8

< 130 07/29/24 08/26/24

< 0.8

< 86

< 5

< 4

< 12

< 7

< 13

< 5

< 6

< 8

< 154 08/26/24 09/30/24

< 0.7

< 140

< 7

< 6

< 12

< 8

< 10

< 7

< 8

< 6

< 11

< 156 09/30/24 10/29/24

< 0.6

< 83

< 4

< 5

< 8

< 5

< 10

< 5

< 6

< 116 10/29/24 11/25/24

< 0.6

< 101

< 5

< 11

< 6

< 14

< 6

< 7

< 9

< 139 11/25/24 12/31/24

< 0.9

< 26

< 2

< 5

< 2

< 5

< 2

< 3

< 2

< 3

< 62 AVERAGE*

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 74 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 20, Concentration of Gross Alpha and Beta Emitters, and Tritium in Well Water, 2024 Results in Units of pCi/L +/- 2 STATION ID COLLECTION DATE Gross Alpha Gross Beta H-3 SA-WWA-03E1**

01/25/24

< 2.4

< 1.6

< 190 02/21/24

< 1.3

< 2.1

< 192 03/25/24

< 1.5

< 2.0

< 188 04/22/24

< 1.5

< 2.6

< 186 05/22/24

< 1.7

< 2.3

< 189 06/24/24

< 1.5 3.7 +/- 1.4

< 196 07/23/24

< 1.3

< 2.1

< 193 08/19/24

< 1.8

< 2.6

< 194 09/25/24

< 1.8

< 2.6

< 187 10/21/24

< 1.3

< 2.7

< 180 11/18/24

< 1.8

< 2.5

< 192 12/16/24

< 2.1

< 1.6

< 183 AVERAGE*

3.7 +/- 1.4 THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2024 Page 75 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 21, Concentrations of Iodine-131 and Gamma Emitters in Well Water, 2024 Results in Units of pCi/L +/- 2 STATION ID COLLECTION DATE

< - - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

I-131 LL K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 ZrNb-95 Cs-134 Cs-137 BaLa-140 Ra-226 SA-WWA-03E1**

01/25/24

< 0.7

< 138

< 6

< 5

< 14

< 8

< 13

< 9

< 5

< 9

< 187 02/21/24

< 0.8

< 83

< 6

< 12

< 7

< 13

< 7

< 6

< 9

< 162 03/25/24

< 0.5

< 91

< 6

< 5

< 11

< 6

< 10

< 7

< 6

< 5

< 7

< 139 04/22/24

< 0.7

< 95

< 6

< 5

< 11

< 6

< 11

< 7

< 6

< 9

< 151 05/22/24

< 0.9

< 106

< 6

< 5

< 12

< 7

< 13

< 6

< 7

< 6

< 10

< 183 06/24/24

< 0.8

< 82

< 5

< 7

< 5

< 10

< 5

< 7

< 135 07/23/24

< 0.8

< 73

< 7

< 6

< 16

< 10

< 9

< 7

< 10

< 154 08/19/24

< 0.9

< 106

< 9

< 8

< 15

< 7

< 15

< 9

< 7

< 8

< 10

< 187 09/25/24

< 0.7

< 76

< 4

< 8

< 4

< 10

< 5

< 4

< 8

< 114 10/21/24

< 0.8

< 107

< 6

< 13

< 8

< 17

< 8

< 7

< 9

< 173 11/18/24

< 0.9

< 112

< 7

< 9

< 15

< 8

< 17

<9

< 7

< 8

< 12

< 180 12/16/24

< 0.8

< 79

< 6

< 5

< 12

< 9

< 11

< 8

< 6

< 8

< 168 AVERAGE*

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

- MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM.

- INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 76 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 22, Concentrations of Gamma Emitters in Sediment, 2024 Results in Units of pCi/kg (dry) +/- 2 Collection Date

<------------GAMMA EMITTERS------------>

STATION ID Be-7 K-40 Cs-134 Cs-137 Ra-226 Th-232 SA-ESS-12B1 (C) 07/02/24

< 751 14,780 +/- 1,865

< 120

< 89

< 2,113 807 +/- 241 12/04/24

< 351 16,000 +/- 1,160

< 62

< 44 1,834 +/- 820 984 +/- 112 AVERAGE*

15,390 +/- 1,725 1,834 +/- 820 895 +/- 252 SA-ESS-05A1 07/09/24

< 311 4,182 +/- 880

< 57

< 42

< 1,262

< 257 12/05/24

< 406 9,486 +/- 899

< 60

< 55

< 1,090 542

+/- 115 AVERAGE*

6,834 +/- 7,501 542

+/- 115 SA-ESS-11A1 07/02/24

< 295 2,470 +/- 768

< 62

< 55

< 1,149 246

+/- 118 12/04/24

< 350 4,729 +/- 637

< 45

< 37

< 702 210

+/- 90 AVERAGE*

3,600 +/- 3,195 228

+/- 51 SA-ESS-15A1 07/02/24

< 611 3,603 +/- 966

< 76

< 60

< 1,457

< 341 12/04/24

< 458 12,640 +/- 1,082

< 59

< 52 1,531 +/- 963 780 +/- 159 AVERAGE*

8,122 +/- 12,780 1,531 +/- 963 780 +/- 159 SA-ESS-15A2 (a)

(a)

AVERAGE*

SA-ESS-07E1 07/02/24

< 523 9,119 +/- 1,361

< 78

< 69

< 1,377 696 718 +/- 176 12/04/24

< 316 9,692 +/- 937

< 55

< 40

< 275 AVERAGE*

9,406 +/- 810 718 +/- 176 SA-ESS-16F1 07/02/24

< 866 14,340 +/- 2,250

< 139

< 112

< 2,104

< 661 12/04/24

< 680 13,010 +/- 1,635

< 98

< 102

< 1,664

< 483 AVERAGE*

13,675 +/- 1,881 ALL INDICATOR AVERAGE 8,327 +/- 8,622 1,531 +/- 963 499 +/- 526 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

(a)

STATION 15A2 COULD NOT BE COLLECTED DUE TO A WIND PORT PROJECT (TABLE 11).

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 77 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2024 Results in Units of pCi/L +/- 2<

STATION ID COLLECTION PERIOD

- - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

START STOP I-131 LL K-40 Cs-134 Cs-137 BaLa-140 Ra-226 SA-MLK-02G3 (C) 01/01/24 01/02/24

< 0.9 1,125 +/- 190

< 8

< 13

< 162 02/04/24 02/05/24

< 0.8 1,506 +/- 158

< 6

< 10

< 153 03/03/24 03/04/24

< 0.8 1,224 +/- 192

< 8

< 7

< 10

< 163 04/01/24 04/02/24

< 0.9 1,050 +/- 134

< 6

< 5

< 10

< 130 04/14/24 04/15/24

< 0.7 1,163 +/- 136

< 6

< 8

< 143 05/05/24 05/06/24

< 0.7 1,160 +/- 162

< 8

< 9

< 12

< 177 05/20/24 05/21/24

< 0.8 1,141 +/- 167

< 6

< 5

< 9

< 121 06/02/24 06/03/24

< 0.7 1,405 +/- 190

< 8

< 9

< 12

< 163 06/16/24 06/17/24

< 0.7 1,410 +/- 173

< 8

< 10

< 174 07/15/24 07/16/24

< 0.9 1,018 +/- 152

< 7

< 8

< 13

< 217 07/21/24 07/22/24

< 0.9 1,448 +/- 169

< 8

< 9

< 190 08/04/24 08/05/24

< 0.9 1,494 +/- 174

< 8

< 11

< 135 08/18/24 08/19/24

< 1.0 1,677 +/- 175

< 7

< 9

< 132 09/02/24 09/03/24

< 0.9 1,205 +/- 121

< 7

< 8

< 131 09/15/24 09/16/24

< 0.9 1,281 +/- 152

< 8

< 7

< 5

< 176 10/13/24 10/14/24

< 0.8 1,004 +/- 106

< 5

< 4

< 8

< 99 10/20/24 10/21/24

< 0.8 1,188 +/- 116

< 5

< 7

< 115 11/03/24 11/04/24

< 0.8 1,282 +/- 184

< 9

< 7

< 14

< 186 11/17/24 11/18/24

< 0.9 1,027 +/- 162

< 9

< 8

< 6

< 215 12/02/24 12/03/24

< 0.9 1,141 +/- 162

< 9

< 8

< 10

< 158 AVERAGE*

1,247 +/- 374 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 78 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2024 Results in Units of pCi/L +/- 2<

STATION ID COLLECTION PERIOD

- - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

START STOP I-131 LL K-40 Cs-134 Cs-137 BaLa-140 Ra-226 SA-MLK-13E3 01/01/24 01/02/24

< 0.9 1,182 +/- 173

< 8

< 6

< 13

< 162 02/04/24 02/05/24

< 0.9 1,070 +/- 172

< 8

< 14

< 162 03/03/24 03/04/24

< 0.9 1,454 +/- 179

< 8

< 12

< 167 04/01/24 04/02/24

< 0.8 1,277 +/- 151

< 7

< 10

< 138 04/14/24 04/15/24

< 0.8 1,316 +/- 176

< 9

< 7

< 12

< 171 05/05/24 05/06/24

< 0.8 1,069 +/- 175

< 7

< 14

< 167 05/20/24 05/21/24

< 0.8 1,144 +/- 136

< 7

< 10

< 168 06/02/24 06/03/24

< 0.8 1,045 +/- 192

< 7

< 6

< 5

< 107 06/16/24 06/17/24

< 0.9 1,285 +/- 163

< 8

< 7

< 8

< 170 07/15/24 07/16/24

< 0.6 1,300 +/- 165

< 10

< 7

< 12

< 165 07/21/24 07/22/24

< 0.6 1,234 +/- 170

< 9

< 7

< 12

< 201 08/04/24 08/05/24

< 0.9 1,093 +/- 148

< 9

< 7

< 10

< 190 08/18/24 08/19/24

< 1.0 1,846 +/- 161

< 7

< 6

< 7

< 173 09/02/24 09/03/24

< 0.8 1,306 +/- 150

< 9

< 7

< 11

< 137 09/15/24 09/16/24

< 0.8 1,372 +/- 142

< 8

< 7

< 8

< 140 10/13/24 10/14/24

< 0.8 1,079 +/- 160

< 9

< 7

< 13

< 187 10/20/24 10/21/24

< 0.9 1,092 +/- 126

< 6

< 8

< 134 11/03/24 11/04/24

< 0.9 1,119 +/- 168

< 9

< 7

< 10

< 196 11/17/24 11/18/24

< 0.8 1,334 +/- 153

< 8

< 7

< 15

< 164 12/02/24 12/03/24

< 0.8 1,231 +/- 181

< 9

< 8

< 12

< 166 AVERAGE*

1,242 +/- 370 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 79 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2024 Results in Units of pCi/L +/- 2<

STATION ID COLLECTION PERIOD

- - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

START STOP I-131 LL K-40 Cs-134 Cs-137 BaLa-140 Ra-226 SA-MLK-14F4 01/01/24 01/02/24

< 0.9 1,037 +/- 139

< 9

< 8

< 11

< 179 02/05/24 02/06/24

< 0.9 1,392 +/- 171

< 6

< 8

< 11

< 169 03/03/24 03/04/24

< 0.9 1,183 +/- 172

< 9

< 6

< 9

< 158 04/01/24 04/02/24

< 0.7 1,214 +/- 177

< 7

< 6

< 11

< 139 04/14/24 04/15/24

< 0.7 1,356 +/- 159

< 8

< 7

< 8

< 166 05/05/24 05/06/24

< 0.8 995 +/- 180

< 9

< 8

< 10

< 205 05/20/24 05/21/24

< 0.7 1,299 +/- 150

< 5

< 6

< 9

< 130 06/02/24 06/03/24

< 0.8 1,433 +/- 172

< 7

< 8

< 133 06/16/24 06/17/24

< 0.9 1,090 +/- 186

< 8

< 9

< 10

< 145 07/15/24 07/16/24

< 0.8 1,259 +/- 177

< 8

< 7

< 6

< 171 07/21/24 07/22/24

< 0.8 1,098 +/- 193

< 9

< 7

< 12

< 162 08/04/24 08/05/24

< 0.8 1,119 +/- 163

< 8

< 7

< 13

< 190 08/18/24 08/19/24

< 1.0 1,405 +/- 152

< 9

< 7

< 11

< 170 09/02/24 09/03/24

< 0.9 1,119 +/- 156

< 6

< 5

< 8

< 160 09/15/24 09/16/24

< 0.6 1,382 +/- 152

< 6

< 7

< 140 10/13/24 10/14/24

< 0.8 1,266 +/- 175

< 8

< 9

< 14

< 201 10/20/24 10/21/24

< 1.0 1,209 +/- 131

< 6

< 7

< 121 11/03/24 11/04/24

< 0.9 1,134 +/- 169

< 9

< 14

< 204 11/17/24 11/18/24

< 0.8 1,268 +/- 185

< 8

< 7

< 199 12/02/24 12/03/24

< 0.9 1,214 +/- 167

< 10

< 9

< 195 AVERAGE*

1,224 +/- 256 ALL INDICATOR AVERAGE*

1,233 +/- 314 (C) CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

- INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 80 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 24, Concentrations of Gamma Emitters in Edible Fish, 2024 Results in Units of pCi/kg (wet) +/- 2

<------------GAMMA EMITTERS------------>

STATION ID Collection Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 SA-ESF-12B1 (C) 04/29/24 2,918

+/-

900

< 43

< 50

< 120

< 41

< 129

< 58

< 52

< 1,005 11/18/24 4,062

+/-

928

< 70

< 64

< 129

< 54

< 157

< 67

< 61

< 1,111 AVERAGE*

3,490

+/-

1,618 SA-ESF-11A1 04/29/24 3,736

+/-

964

< 69

< 63

< 128

< 76

< 150

< 55

< 62

< 1,714 11/13/24 3,407

+/-

836

< 66

< 65

< 149

< 74

< 129

< 66

< 63

< 1,310 AVERAGE*

3,572

+/-

465 SA-ESF-07E1 04/29/24 3,876

+/-

809

< 47

< 44

< 105

< 70

< 107

< 52

< 51

< 1,175 11/13/24 2,872

+/-

844

< 43

< 56

< 111

< 71

< 108

< 56

< 50

< 1,162 AVERAGE*

3,374

+/-

1,420 ALL INDICATOR AVERAGE*

3,473

+/-

892 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 81 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 25, Concentrations of Gamma Emitters in Blue Crabs, 2024 Results in Units of pCi/kg (wet) +/- 2 Collection Date

<------------GAMMA EMITTERS------------>

STATION ID K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 SA-ECH-12B1 (C) 07/03/24 2,864

+/-

886

< 43

< 65

< 107

< 62

< 134

< 57

< 54

< 1,531 09/24/24 2,238

+/-

687

< 43

< 38

< 89

< 36

< 83

< 44

< 43

< 712 AVERAGE*

2,551

+/-

885 STATION ID Collection Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 SA-ECH-11A1 07/03/24 2,389

+/-

933

< 77

< 68

< 108

< 87

< 138

< 63

< 49

< 1,076 09/24/24 2,291

+/-

551

< 44

< 40

< 92

< 40

< 90

< 43

< 808 AVERAGE*

2,340

+/-

139 (C) CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES. IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

- INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 82 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 26, Concentrations of Gamma Emitters in Broadleaf Vegetation (FPL), 2024 Results in Units of pCi/kg (wet) +/- 2 COLLECT ION DATE SAMPLE TYPE

< - - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

STATION ID Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 Th-232 SA-FPL-01G1 06/28/24 Cabbage

< 110 2,565 +/- 362

< 21

< 12

< 13

< 273

< 60 SA-FPL-01G1 11/25/24 Collards

< 247 3,268 +/- 515

< 42

< 31

< 27

< 590

< 116 SA-FPL-03H5 06/28/24 Cabbage

< 160 2,690 +/- 481

< 42

< 29

< 25

< 485

< 99 SA-FPL-06S1 06/28/24 Cabbage

< 317 5,078 +/- 774

< 36

< 40

< 28

< 708

< 147 SA-FPL-06S1 06/28/24 Lamb's Ear 1,315 +/- 421 11,770 +/- 1,197

< 54

< 44

< 43

< 800

< 183 SA-FPL-06S1 09/04/24 Lamb's Ear 1,288 +/- 191 7,005 +/- 488

< 20

< 19

< 353

< 71 SA-FPL-06S1 12/03/24 Kale

< 246 3,081 +/- 463

< 55

< 32

< 31

< 683

< 109 SA-FPL-15F4**

07/17/24 Cabbage

< 62 1,587 +/- 150

< 11

< 8

< 7

< 151

< 32 SA-FPL-16S1 06/28/24 Cabbage

< 364 4,903 +/- 742

< 46

< 37

< 42

< 830

< 146 SA-FPL-16S1 06/28/24 Lamb's Ear 1,499 +/- 324 9,421 +/- 888

< 49

< 36

< 35

< 766

< 137 SA-FPL-16S1 09/04/24 Lamb's Ear 2,032 +/- 241 8,871 +/- 575

< 20

< 22

< 21

< 439

< 80 SA-FPL-16S1 12/03/24 Kale

< 250 3,349 +/- 726

< 52

< 46

< 35

< 809

< 132 SA-FPL-10D1 (C) 06/28/24 Cabbage

< 310 2,923 +/- 540

< 45

< 38

< 34

< 722

< 131 SA-FPL-10D1 (C) 06/28/24 Lamb's Ear 2,837 +/- 404 7,651 +/- 838

< 35

< 31

< 799

< 138 SA-FPL-10D1 (C) 09/04/24 Lamb's Ear 1,474 +/- 221 7,149 +/- 498

< 25

< 24

< 21

< 498

< 92 SA-FPL-10D1 (C) 12/03/24 Kale

< 278 3,432 +/- 517

< 52

< 37

< 34

< 638

< 113 CONTROL AVERAGE*

2,156 +/- 1,928 5,289 +/- 4,911 ALL INDICATOR AVERAGE*

1,534 +/- 691 5,299 +/- 6,485 (C)

CONTROL LOCATION.

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES.

IF THERE IS ONLY ONE POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 83 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 27, Concentrations of Gamma Emitters in Vegetables (FPV), 2024 Results in Units of pCi/kg (wet) +/- 2 COLLECTION DATE SAMPLE TYPE

< - - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

STATION ID Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 Th-232 SA-FPV-02F9**

04/30/24 Asparagus

< 119 1,567 +/-

258

< 19

< 16

< 14

< 331

< 53 SA-FPV-15F4**

07/17/24 Corn

< 58 2,152 +/-

171

< 11

< 8

< 7

< 179

< 30 SA-FPV-15F4**

07/17/24 Peppers

< 117 2,205 +/-

239

< 21

< 15

< 13

< 356

< 53 SA-FPV-15F4**

07/17/24 Tomatoes

< 67 2,500 +/-

205

< 11

< 9

< 8

< 153

< 33 SA-FPV-01G1 04/30/24 Asparagus

< 120 1,913 +/-

340

< 18

< 19

< 17

< 335

< 58 SA-FPV-01G1 06/28/24 Tomatoes

< 121 1,147 +/- 234

< 24

< 16

< 15

< 357

< 50 SA-FPV-01G1 07/17/24 Corn

< 87 3,197 +/-

240

< 14

< 12

< 11

< 254

< 42 SA-FPV-01G1 07/17/24 Peaches

< 54 1,606 +/-

157

< 9

< 8

< 6

< 141

< 28 SA-FPV-01G1 07/17/24 Peppers

< 72 1,576 +/-

207

< 12

< 10

< 11

< 198

< 41 SA-FPV-03H5 04/30/24 Asparagus

< 125 1,902 +/- 366

< 21

< 16

< 317

< 51 SA-FPV-03H5 06/28/24 Corn

< 138 2,377 +/-

378

< 30

< 19

< 16

< 415

< 71 SA-FPV-03H5 06/28/24 Peaches

< 176 2,285 +/-

412

< 34

< 22

< 18

< 435

< 67 SA-FPV-03H5 06/28/24 Tomatoes

< 88 1,576 +/-

223

< 23

< 15

< 11

< 291

< 47 SA-FPV-03H5 07/17/24 Peppers

< 85 1,514 +/-

206

< 14

< 12

< 10

< 239

< 41 AVERAGE*

1,966 +/-

1,058

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES.

IF THERE IS ONLY ONE POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

- MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM.

- INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 84 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 28, Concentrations of Gamma Emitters in Fodder Crops, 2024 Results in Units of pCi/kg (wet) +/- 2 COLLECTION DATE SAMPLE TYPE

< - - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

STATION ID Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 Th-232 SA-VGT-13E3**

11/04/24 Silage 491 +/- 168 2,990 +/-

565

< 31

< 27

< 584

< 72 SA-VGT-14F4**

11/04/24 Silage

< 249 6,814 +/-

732

< 38

< 35

< 919

< 137 SA-VGT-02G3**

11/04/24 Silage 455 +/- 183 3,693 +/-

465

< 20

< 21

< 398

< 61 AVERAGE*

473 +/- 50 4,499 +/-

4,071

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES.

IF THERE IS ONLY ONE POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

- MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM.

- INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 85 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 29, Concentrations of Gamma Emitters in Game, 2024 Results in Units of pCi/kg (wet) +/- 2 STATION ID COLLECTION DATE SAMPLE TYPE

<------------GAMMA EMITTERS------------>

Be-7 K-40 I-131 Cs-134 Cs-137 SA-GAM-13E3**

02/21/24 Muskrat 87 2,167 +/-

325

< 12

< 16

< 14 ALL INDICATOR AVERAGE*

2,167 +/- 325

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES.

IF THERE IS ONLY ONE POSITIVE VALUE, THE AVERAGE AND THE ERROR ARE DISPLAYED.

- MANAGEMENT AUDIT SAMPLE: NOT REQUIRED BY ODCM.

- INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 86 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 30, Concentrations of Gamma Emitters in Soil, 2022**

Results in Units of pCi/kg (dry) +/- 2 STATION ID COLLECTION DATE

< - - - - - - - - - - - - - - GAMMA EMITTERS - - - - - - - - - - - - - - >

Be-7 K-40 Cs-134 Cs-137 Ra-226 Th-232 SA-SOL-10D1**

3/22/2022

< 344 10,330 +/- 919

< 53 121 +/- 49 1398

+/-

832 608

+/-

121 SA-SOL-13E3**

3/22/2022

< 326 13,690 +/- 996

< 52

< 51 1,799

+/-

817 843

+/-

127 SA-SOL-16E1**

3/22/2022

< 349 9,936 +/- 917

< 49

< 44 1,775

+/-

839 741

+/-

102 SA-SOL-02F9**

3/22/2022

< 421 5,448 +/- 897

< 57 153 +/- 64 1,621

+/-

970 436

+/-

131 SA-SOL-05F1**

3/22/2022

< 394 7,476 +/- 1,193

< 69 184 +/- 58 2,836

+/-

1,359 884

+/-

156 SA-SOL-14F4**

3/22/2022

< 450 11,460 +/- 1,147

< 69

< 71 1,916

+/-

1,126 975

+/-

150 SA-SOL-02G3**

3/22/2022

< 464 7,511 +/- 1,031

< 70 108 +/- 69 2,793

+/-

1,250

< 358 SA-SOL-03G1**

3/22/2022

< 316 8,217 +/- 796

< 46 75 +/- 33 1,774

+/-

909 855

+/-

92 SA-SOL-06S1**

3/22/2022

< 438 9,765 +/- 1,091

< 66

< 71

< 1,262 593

+/-

140 AVERAGE*

9,315 +/- 4,907 128 +/- 84 1,989

+/-

1,064 742

+/-

364

THE AVERAGE AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES, IF THERE IS ONLY 1 POSITIVE VALUE THE AVERAGE AND THE ERROR ARE DISPLAYED.

- MANAGEMENT AUDIT SAMPLES TAKEN EVERY 3 YEARS, NEXT SAMPLE DUE 2025: NOT REQUIRED BY ODCM.

INDICATES AVERAGE WAS NOT CALCULATED DUE TO NO POSITIVE VALUES FOR THE REPORTING PERIOD.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 87 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Cross check Intercomparison Program I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 88 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program Summary of Cross Check Program Participation in cross check intercomparison studies is mandatory for laboratories performing analyses of REMP samples satisfying the requirements in the Offsite Site Dose Calculation Manual. Intercomparison studies provide a consistent and effective means to evaluate the accuracy and precision of analyses performed by a laboratory.

Study results should fall within specified control limits and results that fall outside the control limits are investigated and corrected.

Teledyne Brown Engineering (TBE) and GEL Analytical Services (GEL) participated in the following proficiency testing studies provided by Environmental Resource Associates (ERA), Eckert Ziegler Analytics and DOE Mixed Analyte Performance Evaluation in 2024. The Laboratorys intercomparison program results for 2024 are summarized below.

Teledyne Brown Engineering Summary of Results 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 I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 89 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program 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 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-231 to better reflect client sample testing and acceptable results were achieved. Acceptable results returned in a later sample study, supporting effectiveness of corrective action.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 90 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program 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 0.106 pCi/g and the known value returned at 0.071 pCi/g. The root cause investigation was unable to determine any anomaly 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 Bq/Kg and the known value returned at 650 Bq/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 Bq/Kg and the known value returned at 1530 Bq/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 9.95 Bq/L and the known value returned 7.47 Bq/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 0.276 Bq/sample and the known value returned 0.529 Bq/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.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 91 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program 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 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-MaS51 soil study Fe-55 evaluated as Not Acceptable.

TBE did not report a value and the known value returned 780 Bq/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 0.95 Bq/sample and the known value returned 2.39 Bq/sample (range 1.67-3.11). The root cause is still under investigation.

Additional details can be found in the report, "4th Quarter 2024 Quality Assurance Report," Teledyne Brown Engineering Environmental Services, 2024 [12]

GEL Laboratories Summary of Results During 2024, forty-one (41) radioisotopes associated with six (6) matrix types were analyzed under GELs Performance Evaluation program in participation with ERA, MAPEP, and Eckert & Ziegler Analytics. Matrix types were representative of client analyses performed during 2024. Of the four hundred sixty-three (463) total results, 96.1% (445 of 463) were found to be acceptable within the PT providers three sigma or other statistical criteria. The list below contains the type of matrix evaluated by GEL.

Air Filter

Cartridge

Water

Milk

Soil

Vegetation Summary of Participation in the Eckert & Ziegler Analytics Environmental Cross-Check Program Eckert & Ziegler Analytics provided samples for sixty-nine (69) individual environmental analyses. The accuracy of each result reported to Eckert & Ziegler Analytics, Inc. is measured by the ratio of GELs result to the known value. Of the 69 analyses reported, 97% (67 out of 69) fell within the acceptance criteria.

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 92 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program Summary of Participation in the ERA MRaD PT Program The ERA MRad program provided samples (MRAD-40 and MRAD-41) for one hundred forty-eight (148) individual environmental analyses reported. Of the 148 analyses reported, 97.3% (144 of the 148) fell within the PT providers acceptance criteria.

Summary of Participation in the MAPEP Monitoring Program MAPEP Series 49, Series 50 and Series 51 were analyzed by the laboratory. Of the two hundred five (205) analyses reported, 97.1% (199 out of 205) fell within the PT providers acceptance criteria.

Summary of Participation in the ERA PT Program The ERA program provided samples (RAD-136, RAD-137, RAD-138 and RAD-139) forforty-one (41) individual environmental analyses. Of the 41 analyses reported, 80.5% (33 of 41) fell within the PT providers acceptance criteria.

Corrective Action Request and Report (CARR)

There are two categories of corrective action at GEL. One is corrective action implemented at the analytical and data review level in accordance with the analytical SOP. The other is formal corrective action documented by the Quality Systems Team in accordance with GL-QS-E-002.

A formal corrective action is initiated when a nonconformance reoccurs or is so significant that permanent elimination or prevention of the problem is required. Formal corrective action investigations include root cause analysis.

GEL includes quality requirements in most analytical standard operating procedures to ensure that data are reported only if the quality control criteria are met or the quality control measures that did not meet the acceptance criteria are documented. A formal corrective action is implemented according to GL-QS-E-002 for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement. Recording and documentation is performed following guidelines stated in GL-QS-E-012 for Client NCR Database Operation.

Any employee at GEL can identify and report a nonconformance and request that corrective action be taken. Any GEL employee can participate on a corrective action team as requested by the QS team or Group Leaders. The steps for conducting corrective action are detailed in GL-QS-E-002. In the event that correctness or validity of the laboratorys test results in doubt, the laboratory will take corrective action. If investigations show that the results have been impacted, affected clients will be informed of the issue in writing within five (5) calendar days of the discovery.

Additional details can be found in the GEL Laboratories, 2024 Annual Quality Assurance Report

[13].

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 93 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program Summary of Results: Split Sample Comparison Program To meet the requirement of ODCM 3/4.12.3, INTERLABORATORY COMPARISON PROGRAM, several duplicate environmental samples each year are sent to a second independent laboratory to compare results. The laboratory chosen for these Quality Control Analyses is General Engineering Laboratories (GEL).

Duplicate samples were obtained for some samples of weekly air iodine and particulates, quarterly air particulate, sediment, broad leaf vegetation, milk, and surface water. These samples were analyzed by GEL as comparison and quality assurance of TBE results. The GEL duplicate analysis results are shown in Figure 8 below.

Agreement between TBE and GEL is based on criteria for accepting measurements in NRC Inspection Procedure 84525.

Air Iodine I-131 was not detected (less than MDC) by both TBE and GEL for all 52 air samples.

Air Particulates Gross beta was detected by GEL and TBE in 52 of the duplicate weekly APT samples.

GEL detects significantly higher gross beta results. The variance between the lab results is due to different calibration energy sources used by each lab.

Figure 8, TBE vs GEL Gross Beta 5.00E-02 4.SOE-02 4.00E-02 3.S0E-02 3.00E-02 2.S0E-02 2.00E-02 1.S0E-02 1.00E-02 5.00E-03 0.0OE+OO 1/ 1/2024 2/20/2024 4/10/2024 I

Gross Beta 5/30/2024 7/19/2024

--TBE Activity -- GEL Activity I

I 9/7/2024 10/27/2024 12/16/2024

Annual Radiological Environmental Operating Report YEAR: 2024 Page 94 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program All duplicate quarterly composite samples analyzed had positive results for Be-7.

Surface Water Naturally occurring K-40 was detected in 3 of the 4 TBE samples. K-40 was detected in all the GEL samples.

Milk Naturally occurring K-40 was detected in all duplicate samples. One of the duplicate samples was not in agreement. Because of the variability in environmental samples, i.e. time of year, food source, etc., one non-agreement does not constitute an issue with the primary laboratory.

CRS #

Collection Date Nuclide Decay Corrected Activity 1 Sigma Error Resolution CRS #

Nuclide Decay Corrected Activity Ratio Agreement L105027-1 4/1/2024 Be-7 4.18E-02 6.58E-03 6

665698 Be-7 4.75E-02 1.14 0.50 2.00 YES L106116-1 7/1/2024 Be-7 4.48E-02 6.03E-03 7

679368 Be-7 6.35E-02 1.42 0.50 2.00 YES L107591-1 9/30/2024 Be-7 5.14E-02 6.89E-03 7

694534 Be-7 5.35E-02 1.04 0.50 2.00 YES L108423-1 1231/2024 Be-7 3.45E-02 7.46E-03 5

705163 Be-7 4.65E-02 1.35 0.50 2.00 YES AIR PARTICULATE COMPOSITES TBE GEL TBE / GEL Comparison Acceptance Critera CRS #

Collection Date Nuclide Decay Corrected Activity 1 Sigma Error Resolution CRS #

Nuclide Decay Corrected Activity Ratio Agreement L104783-2 3/26/24 K-40

<DL N/A N/A 660534 K-40 5.70E+01 L105979-2 6/20/24 K-40 9.75E+01 3.07E+01 3

660534 K-40 5.81E+01 1.68 0.40 2.25 YES L107261-2 9/10/24 K-40 7.85E+01 2.36E+01 3

688718 K-40 8.59E+01 0.91 0.40 2.25 YES L108293-2 12/16/24 K-40 8.70E+01 2.25E+01 4

701797 K-40 1.23E+02 0.71 0.40 2.25 YES SURFACE WATER TBE GEL TBE / GEL Comparison Acceptance Critera No comparison result <MDL CRS #

Collection Date Nuclide Decay Corrected Activity 1 Sigma Error Resolution CRS #

Nuclide Decay Corrected Activity Ratio Agreement L103783-3 1/2/2024 K-40 1.04E+03 6.96E+01 15 650724 K-40 1.69E+03 0.61 0.60 1.66 YES L104258-3 2/6/2024 K-40 1.39E+03 8.54E+01 16 654784 K-40 1.16E+03 1.20 0.75 1.33 YES L104554-3 3/4/2024 K-40 1.18E+03 8.59E+01 14 658049 K-40 2.88E+03 0.41 0.60 1.66 NO L104924-3 4/2/2024 K-40 1.21E+03 8.85E+01 14 661871 K-40 1.33E+03 0.91 0.60 1.66 YES L105417-3 5/6/2024 K-40 9.95E+02 9.00E+01 11 667076 K-40 7.12E+02 1.40 0.60 1.66 YES L105734-3 6/3/2024 K-40 1.43E+03 8.60E+01 17 670549 K-40 1.45E+03 0.99 0.75 1.33 YES L106306-3 7/16/2024 K-40 1.26E+03 8.86E+01 14 676712 K-40 1.05E+03 1.20 0.60 1.66 YES L-106578-3 8/5/2024 K-40 1.12E+03 8.14E+01 14 679899 K-40 1.05E+03 1.07 0.60 1.66 YES L-106916-3 9/2/2024 K-40 1.12E+03 7.80E+01 14 684421 K-40 7.11E+02 1.57 0.60 1.66 YES L107493-3 10/13/2024 K-40 1.27E+03 8.70E+01 15 690798 K-40 1.13E+03 1.12 0.60 1.66 YES L107807-3 11/4/2024 K-40 1.13E+03 8.47E+01 13 694373 K-40 8.41E+02 1.35 0.60 1.66 YES L108132-3 12/3/2024 K-40 1.21E+03 8.33E+01 15 699396 K-40 1.07E+03 1.13 0.60 1.66 YES MILK TBE GEL TBE / GEL Comparison Acceptance Critera I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 95 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program Broad Leaf Vegetation Naturally occurring K-40 was detected by GEL and TBE in all duplicate samples analyzed. Two of the seven duplicates did not agree. Sampling variability in the field is not accounted for when taking vegetation samples and some non-agreements are occasionally expected.

CRS #

Collection Date Nuclide Decay Corrected Activity 1 Sigma Error Resolution CRS #

Nuclide Decay Corrected Activity Ratio Agreement L106053-2 6/28/24 K-40 2.57E+03 1.81E+02 14 674053 K-40 4.70E+03 0.55 0.60 1.66 NO L106053-5 6/28/24 K-40 2.69E+03 2.40E+02 11 674053 K-40 3.24E+03 0.83 0.60 1.66 YES L106305-7 7/17/24 K-40 1.59E+03 7.48E+01 21 676698 K-40 1.69E+03 0.94 0.75 1.33 YES L106921-1 9/4/24 K-40 7.01E+03 2.44E+02 29 684459 K-40 9.99E+03 0.70 0.75 1.33 NO L106921-2 9/4/24 K-40 7.15E+03 2.49E+02 29 684459 K-40 8.86E+03 0.81 0.75 1.33 YES L106921-3 9/4/24 K-40 8.87E+03 2.87E+02 31 684459 K-40 1.01E+04 0.88 0.75 1.33 YES L108033-1 11/25/24 K-40 3.27E+03 2.57E+02 13 698117 K-40 5.17E+03 0.63 0.60 1.66 YES Acceptance Critera VEGETATION TBE GEL TBE / GEL Comparison I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 96 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program TLD Annual QA Status Report EXECUTIVE

SUMMARY

Routine quality control (QC) testing was performed for dosimeters issued by the Environmental Dosimetry Company (EDC).

During this annual period 100% (72/72) of the individual dosimeters, evaluated against the EDC internal performance acceptance criteria (high-energy photons only), met the criterion for accuracy and 100% (72/72) met the criterion for precision. In addition, 100% (12/12) of the dosimeter sets evaluated against the internal tolerance limits met EDC acceptance criteria and 100% of independent testing passed the performance criteria.

One internal assessment was performed in 2024. There were no findings. Additional detail can be found in the Environmental Dosimetry Company, 2024 Annual Quality Assurance Status Report. [14]

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 97 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Errata/Corrections to Previous Reports

, Errata/Corrections to Previous Reports I

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Annual Radiological Environmental Operating Report YEAR: 2024 Page 98 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Errata/Corrections to Previous Reports 1.0 2021 Errata/Corrections In 2021 the Common REMP ODCM Revision 0 was created and changed the name of location 13S1 to 14S2 to better reflect what sector the sample location was in.

However, in the AREOR for 2021, 2022, and 2023, location 14S2 was reported under the old location name (13S1). This errata corrects the location name from the old to new (Notification 20990610).

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I Annual Radiological Environmental Operating Report YEAR: 2021 Page 73 of 141 Com an : PSEG Nuclear Plant: Salem and Ho e Creek Generatin Stations Table 15, Direct and Immersion Radiation Measurements, 2021 (REMP DOSIMETRY RESULTS")

QUARTERLY NET DOSE AND GROSS DOSE STATION ID GROSS (mrem/StandardQuarter)

ANNUAL ANNUAL JAN-MAR APR-JUN JUL -SEP OCT-DEC NET DOSE DOSE (mrem)

(mrem)

Net Gross Net Gross Net Gross Net Gross SA-IDM-01G3 (C)

ND 60.5 ND 16.0 ND 14.1 ND 15.0 ND 15.4 SA-IDM-03G1 (C)

ND 64.6 ND 17.2 ND 14.8 ND 15.6 ND 17.0 SA-IDM-10G1 (C)

ND 63.8 ND 16.9 ND 14.9 ND 15.2 ND 16.8 SA-IDM-14G1 (C)

ND 63.6 ND 17.0 ND 14.6 ND 15.4 ND 16.5 SA-IDM-16G1 (C)

ND 56.9 ND 15.1 ND 13.1 ND 13.9 ND 14.7 SA-IDM-03H1 (C)

ND 54.7 ND 14.9 ND 12.8 ND 13.0 ND 14.0 SA-IDM-0101..

85.9 140.1 22.6 36.2 19.5 33.1 21.0 34.5 22.7 36.3 SA-IDM-01X2 ND 54.9 ND 14.7 ND 12.8 ND 13.1 ND 14.3 SA-IDM-02S2A ND 61.5 ND 16.5 ND 14.2 ND 14.8 ND 16.0 SA-IDM-02X4 ND 58.6 ND 15.3 ND 13.8 ND 14.4 ND 15.0 SA.-IDM-03X1 ND 54.1 ND 14.3 ND 12.6 ND 13.3 ND 13.8 SA-IDM-04X1 ND 54.9 ND 14.7 ND 12.8 ND 13.5 ND 14.0 SA-IDM-05X1 ND 52.5 ND 13.9 ND 12.5 ND 12.8 ND 13.3 SA.-IDM-06X2 ND 60.4 ND 17.4 ND 14.9 ND 15.9 ND 12.2 SA-IDM-07S1 ND 54.0 ND 14.6 ND 12.4 ND 13.3 ND 13.6 SA-IDM-0851 ND 47.4 ND 12.8 ND 10.7 ND 11.5 ND 12.4 SA-IDM-0852 ND 47.0 ND 12.9 ND 10.7 ND 11.2 ND 12.1 SA-IDM-10S1 ND 51.8 ND 14.1 ND 11.9 ND 12.7 ND 13.0 SA-IDM-1 1S1 ND 49.3 ND 13.2 ND 11.3 ND 11.9 ND 12.8 SA-IDM-12S1 ND 60.9 ND 16.3 ND 13.3 ND 15.2 ND 16.1 SA-IDM4a&l-14S2 ND 69.5 ND 17.8 ND 15.2 ND 17.2 ND 19.3 SA-IDM-1553 ND 70.0 ND 18.3 ND 15.7 ND 17.3 ND 18.8

Annual Radiological Environmental Operating Report YEAR: 2024 Page 99 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Errata/Corrections to Previous Reports 2.0 2022 Errata/Corrections In 2021 the Common REMP ODCM Revision 0 was created and changed the name of location 13S1 to 14S2 to better reflect what sector the sample location was in.

However, in the AREOR for 2021, 2022, and 2023, location 14S2 was reported under the old location name (13S1). This errata corrects the location name from the old to new (Notification 20990610).

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I Annual Environmental Operating Report YEAR: 2022 Page 64 of 107 Com an : PSEG Nuclear Plant: Salem and Ho e Creek Generatin Stations Table 12, Environmental Direct Radiation Dosimetry Sample Results Quarterly Normalized Quarterly Monitoring Data, Illa Qu-rly Faclllty Dose, Fa=llla-Ba Annual Annual Annual Monitoring

Basellna, Basellna, Monitoring Faclllty Location Bo (mram)

(mram)

a.

Data, M*

Dose, F.=M*-B*

(mram) 1 2

3 1

2 3

(mram)

(mram) 01Q1 13.6 33.5 32.5 33.9 32.2 20.0 18.9 20.3 18.6 54.6 132.1 77.4 16Q2 13.6 29.3 28.4 29.6 28.9 15.8 14.9 16.1 15.3 54.6 116.3 61.6 01X2 13.6 14.0 13.1 13.9 13.6 ND ND ND ND 54.6 54.6 ND 02X4 11.4 15.3 13.9 14.3 14.5 ND ND ND ND 45.7 58.0 12.2 03X1 10.0 13.4 13.0 12.9 13.2 ND ND ND ND 40.2 52.5 12.4 04X1 11.9 13.9 12.7 13.2 13.2 ND ND ND ND 47.8 52.9 ND 05X1 10.7 13.3 12.6 12.8 12.6 ND ND ND ND 42.8 51.3 ND 06X2 15.0 14.4 13.9 13.8 13.6 ND ND ND ND 60.5 55.7 ND 16X3 11.8 13.3 14.3 13.4 12.8 ND ND ND ND 47.6 53.8 ND 2S2A 16.6 15.7 14.8 15.1 14.6 ND ND ND ND 68.0 60.2 ND 04X1 Dup 11.9 14.0 12.7 13.3 13.1 ND ND ND ND 47.8 53.1 ND 07S1 16.6 13.7 13.1 13.0 12.9 ND ND ND ND 66.9 52.7 ND 08S1 10.5 12.0 11.3 11.4 11.4 ND ND ND ND 43.2 46.2 ND 08S2 10.8 12.1 12.4 12.6 11.3 ND ND ND ND 44.3 48.4 ND 10S1 11.6 12.8 11.3 11.7 12.3 ND ND ND ND 47.3 48.1 ND 11S1 10.7 12.8 12.2 12.8 12.7 ND ND ND ND 43.8 50.5 ND 12S1 13.4 15.5 14.9 15.3 14.7 ND ND ND ND 53.8 60.4 ND 43S-l-14S2 15.9 TNR 17.2 17.3 18.9 TNR ND ND ND 61.7 71.2 ND 15S1 10.8 12.9 12.6 12.4 NR ND ND ND NR 43.3 50.6 ND 15S2 11.8 14.7 13.7 13.6 13.6 ND ND ND ND 53.3 55.6 ND 15S3 15.9 17.8 17.9 17.4 16.7 ND ND ND ND 62.8 69.9 ND 16S1 12.8 14.9 15.0 15.3 14.6 ND ND ND ND 51.4 59.9 ND 04D2 13.0 15.7 15.4 15.3 14.8 ND ND ND ND 52.3 61.1 ND 05D1 11.7 14.9 14.5 13.9 13.9 ND ND ND ND 46.9 57.3 10.4

Annual Radiological Environmental Operating Report YEAR: 2024 Page 100 of 100 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Errata/Corrections to Previous Reports 3.0 2023 Errata/Corrections In 2021 the Common REMP ODCM Revision 0 was created and changed the name of location 13S1 to 14S2 to better reflect what sector the sample location was in.

However, in the AREOR for 2021, 2022, and 2023, location 14S2 was reported under the old location name (13S1). This errata corrects the location name from the old to new (Notification 20990610).

I I

I Annual Radiological Environmental Operating Report YEAR: 2023 I Page 61 of 96 I Company: PSEG Nuclear LLC

!Plant: Salem and Hope Creek Generating Stations I - Data Table Table 12, Environmental Direct Radiation Dosimetry Sample Results Qu.....,.

Qu.....,._ortngO-.llc, au.....,., ac1111y DoN,,a-11o-ea Annual Annual Annual Monllortng

BaNIIM, BaNIIM, llllonltDrtng,~

Locallon Bo (mrwn)

{mnml Dau, MA

DoN, 1

2 3

4 1

2 3

4 (mrwn)

{mrwn)

(mnm) 0101 13.6 33.3 34.1 33.0 32.5 19.7 20.5 19.5 18.9 54.6 132.9 78.3 1602 13.6 28.9 30.4 29.6 30.4 15.3 16.8 16.1 16.9 54.6 119.3 64.7 01X2 13,0 13.6 13.8 13.7 14.7 ND ND ND ND 52.1 55.8 ND 02X4 13,7 15.0 14.3 14.5 14.7 ND NO NO ND 54.7 58.5 ND 03X1 12,3 12.9 12.9 12.6 13.1 ND ND ND ND 49.0 51.5 ND 04X1 11.9 12.9 12.9 13.2 13.7 ND ND ND ND 47.8 52.7 ND 05X1 10,7 12.3 12.3 12.4 12.7 NO NO NO NO 42.8 49.7 NO 06X2 15,0 14.0 14.3 13.9 14.9 ND ND ND ND 60.5 57.1 ND 16X3 12.2 13.1 12.6 12.8 13.5 ND ND ND ND 48.8 52.1 ND 2S2A 14,6 15.1 14.9 15.0 15.3 ND ND ND ND 58.4 60.3 ND 04X1 Dup 11.9 13.1 12.9 13.0 13.6 ND ND NO ND 47.8 52.6 ND 07S1 12.5 13-4 13.0 12.9 13.6 ND NO ND ND 49.9 52.9 ND 08S1 11,0 11.2 11.4 11.3 11.5 ND NO ND ND 44.1 45.4 ND 08S2 11.3 11.4 11.1 10.9 11.6 ND NO ND ND 45.3 45.0 ND 10$1 11.6 12.4 12.3 12.0 13.2 NO NO ND NO 47.3 49.9 NO 11S1 10,7 12.2 11.8 11.3 12.9 ND NO ND ND 43.8 48.3 ND 12S1 14.4 15.1 14.9 14.3 18.4 NO NO ND ND 57.7 62.6 ND

.tlS 14S2 16,3 17.3 17.1 16.3 17.9 ND NO ND ND 65.2 68.6 ND 15S1 10.8 13.0 12,9 13.4 12.7 ND NO NO ND 43.3 52.0 ND 15S2 13.2 13.9 14.1 13.6 13.8 NO NO ND NO 52.6 55.4 NO 15S3 16,0 18.2 17.4 18.2 17.3 ND NO ND ND 63.9 71.1 ND 16S1 12.8 14.8 14.9 15.5 15.0 ND ND ND ND 51.4 60.2 ND 04D2 13.0 15.2 15.4 15.4 15.6 ND NO NO NO 52.3 61.7 NO 05D1 13,6 14.3 14.9 14.6 14.3 ND NO ND ND 54.3 58.1 ND 1001 13.7 14.8 15.6 15.6 15.2 ND NO ND ND 55.2 61.2 ND 1401 12,0 13.5 13.8 14.1 13.4 ND NO ND ND 48.1 54.8 ND 15D1 13.6 14.5 15.0 15.0 15.0 ND NO ND ND 54.7 59.5 ND 02E1 12.3 13.8 14.3 14.2 14.2 ND NO ND ND 49.5 56.5 ND 03E1 10,4 12.8 12.7 12.4 12.8 ND NO ND ND 42.0 50.7 ND 11E2 13.6 15.5 15.8 15.7 15.8 ND ND ND ND 54.7 62.8 ND 12E1 13,7 15.5 15.7 15.7 16.2 ND NO ND ND 55.4 63.1 ND 13E1 10,9 12.6 12.6 12.0 13.0 ND NO ND ND 44.0 50.2 ND 16E1 12.8 14.3 14.7 14.0 14.4 NO NO ND ND 51.7 57.4 ND 01F1 17,1 18.6 18.8 18.7 18.8 ND NO ND NO 68.3 74.8 ND 02F2 12.8 13.3 13.5 13.3 13.6 ND NO ND ND 51.2 53.7 ND 02FS 12.8 15.1 14.8 15.3 14.6 ND NO ND ND 51.4 59.7 ND 02F6 11,9 13.6 14.0 13.3 13.9 ND NO ND ND 47.6 54.8 ND 03F2 11.0 13.3 13.2 12.9 13.5 NO NO NO ND 44.4 52.9 ND 03F3 11,0 13.3 13.1 13.3 13.6 ND NO ND ND 44.2 53.3 ND 04F2 10,7 12.4 13.1 12.6 12.8 ND NO ND ND 43.1 51.0 ND 05F1 11.5 13.7 13.3 13.4 13.7 ND NO ND ND 46.1 54.1 ND 06F1 11,3 11.5 11.3 10.9 11.4 ND NO ND ND 45.1 45.1 ND 07F2 13.1 13.8 13.4 13.7 14.0 ND ND ND ND 52.3 54.9 ND 09F1 15,0 12.8 12.7 16.2 13.0 ND NO NO NO 59.9 54.7 NO 09F2 14,0 15.6 16.6 12.4 16.3 ND NO ND ND 56.3 60.9 ND 10F2 13.2 14.6 15.3 15.1 15.4 ND NO NO ND 52.9 60.5 ND 11F1 13,8 15.7 16.2 16.1 16.1 NO NO NO ND 55.4 64.1 NO 12F1 12,9 14.8 15.4 15.2 15.3 ND NO ND ND 51.7 60.7 ND

v t e Letter Sequence Request
EPID:L-2024-LLA-0100, (Open)
Initiation Request Acceptance Administration Questions 21 November 2024 Answers 15 December 2024 Results Approval Other:
MONTHYEAR2024-12-15 [Table View]

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LR-N25-0045, Submittal of 2024 Annual Radiological Environmental Operating Report (AREOR)

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