Text

2023 Annual Radiological Environmental Operating Report (AREOR)
	ML24122C680
Person / Time
Site:	Salem, Hope Creek
Issue date:	04/30/2024
From:	Jennings J; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	LR-N24-0035
	Download: ML24122C680 (1)
	v • d • e

Jason Jennings Director - Site Regulatory Compliance, PSEG PO Box236 Hancocks Bridge, New Jersey 08038-0221 856-339-1653 Jason.Jennings@PSEG.com o PSEG I NUCLEAR Technical Specification Section 6.9.1.7(Salem)

Technical Specification Section 6.9.1.6 (Hope Creek)

LR-N24-0035 April 30, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 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:

2023 Annual Radiological Environmental Operating Report (AREOR)

As required in Section 6.9.1. 7 of Appendix A to Renewed Facility Operating License Nos. DPR-70 (Unit 1) and DPR-75 (Unit 2) for Salem Generating Station, and Section 6.9.1.6 of Appendix A to Renewed Facility Operating License NPF-57 for Hope Creek Generating Station, PSEG Nuclear hereby transmits the combined 2023 Annual Radiological Environmental Operating Report (Enclosure). This report contains the results of the radiological environmental surveillance program for the period January 1, 2023 to December 31, 2023 in the vicinity of the Salem and Hope Creek Generating Stations.

There are no regulatory commitments contained in this letter.

If you have any questions or comments on this transmittal, please contact Mr. Rick Heathwaite at Frederick.Heathwaite@PSEG.com.

Sincerely, Jason Jennings Director - Site Regulatory Compliance PSEG Nuclear LLC

April 30, 2024 LR-N24-0035 Page2 Technical Specification Section 6.9.1.7(Salem)

Technical Specification Section 6.9.1.6 (Hope Creek) 023 Annual Radiological Environmental Operating Report for Salem and Hope Creek Generating Stations cc:

Administrator - Region I - USNRC Project Manager - USNRC Salem Senior Resident Inspector - USN RC Hope Creek Senior Resident Inspector - USNRC NRC Inspector (RP) - Region I - USNRC Chief - NJ Bureau of Nuclear Engineering (NJBNE)

Salem and Hope Creek Commitment Tracking Coordinator - w/o attachment

LR-N24-0035 Enclosure 2023 Annual Radiological Environmental Operating Report for Salem and Hope Creek Generating Stations (Total Pages 97)

Salem and Hope Creek Generating Stations 2023 Document Number: SGS-AREOR-72 / HCGS-AREOR-46 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 I YEAR: 2023 I

Page 1 of 96 Company: PSEG Nuclear LLC

!Plant: Salem and Hope Creek Generating Stations AREOR (REMP) Review and Approval Confirmation in SAP (1.A.W. AD-AA-1006 SIGNATURE AUTHORITY)

SAP 80134311 oer.

0021 Stephen Gattuso, 04/22/2024 Salem Chemistry Manager Date 0022 Jason Nordin, 04/18/2024 Hope Creek Chemistry Manager Date 0023 William Gropp, 04/10/2024 Salem Radiation Protection Manager Date 0024 Mariaz Davis, 04/17/2024 Hope Creek Radiation Protection Manager Date 0025 William Muffley, 04/15/2024 Salem Senior Director of Operations Date 0026 Joshua Moss, 04/22/2024 Hope Creek Senior Director of Operations Date 0027 Richard Desanctis, 04/16/2024 Salem Plant Manager Date 0028 Robert McLaughlin, 04/22/2024 Hope Creek Plant Manager Date

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p<r Report Prepared By: ________

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 2 of 96 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.............................................................................................. 20 7.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES................................................................................................. 23 8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTEPRETATION OF RESULTS................................................................................................................................ 24 8.1 Environmental Direct Radiation Dosimetry Results....................................................... 24 8.2 Air Particulate and Radioiodine Sample Results........................................................... 29 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................................................................................... 46 13.0 BIBLIOGRAPHY...................................................................................................................... 47 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................. 16 Table 6, REMP Sampling Locations - Direct Radiation........................................................................ 17 Table 7, Reporting Levels for Radioactivity Concentrations in Environmental Samples....................... 23 Table 8, Maximum Values for the Lower Limit of Detection (LLD)........................................................ 23 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................................................. 61 Table 13, Concentrations of Gamma Emitters in Quarterly Composites of Air Particulates, 2023........ 63 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 3 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Table 14, Concentrations of Gross Beta Emitters in Air Particulates, 2023.......................................... 65 Table 15, Concentrations of Iodine-131 in Filtered Air, 2023................................................................ 67 Table 16, Concentrations of Tritium in Surface Water, 2023................................................................ 69 Table 17, Concentrations of Iodine-131 and Gamma Emitters in Surface Water, 2023........................ 70 Table 18, Concentrations of Gross Alpha and Gross Beta Emitters, and Tritium in Raw and Treated Potable Water, 2023............................................................................................................... 73 Table 19, Concentrations of Iodine-131 and Gamma Emitters in Raw and Treated Potable Water, 2023......................................................................................................................................... 74 Table 20, Concentration of Gross Alpha and Beta Emitters, and Tritium in Well Water, 2023.............. 75 Table 21, Concentrations of Iodine-131 and Gamma Emitters in Well Water, 2023............................. 76 Table 22, Concentrations of Gamma Emitters in Sediment, 2023........................................................ 77 Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2023........................................ 78 Table 24, Concentrations of Gamma Emitters in Edible Fish, 2023...................................................... 81 Table 25, Concentrations of Gamma Emitters in Blue Crabs, 2023...................................................... 82 Table 26, Concentrations of Gamma Emitters in Broadleaf Vegetation (FPL), 2023............................ 83 Table 27, Concentrations of Gamma Emitters in Vegetables (FPV), 2023........................................... 84 Table 28, Concentrations of Gamma Emitters in Fodder Crops, 2023................................................. 85 Table 29, Concentrations of Gamma Emitters in Game, 2023............................................................. 86 Table 30, Concentrations of Gamma Emitters in Soil, 2022................................................................. 87 FIGURES Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations.................... 7 Figure 2, REMP Sample Locations (On-Site Sampling Locations To 1 Mile)........................................ 20 Figure 3, REMP Sample Locations (Off-Site Sampling Locations 1 to 10 Miles).................................. 21 Figure 4, REMP Sample Locations (Off-Site Sampling Locations Greater Than 10 Miles)................... 22 Figure 5, TLD Sample Results............................................................................................................. 27 Figure 6, Air Particulate: Analysis for Gross Beta, Average Mean for All Indicator Vs. Control............. 31 Figure 7, Surface Water Tritium Results.............................................................................................. 32 Figure 8, Cesium-137 Activity in Soil 1974 Through 2022.................................................................... 40 Figure 9, TBE vs GEL Gross Beta....................................................................................................... 93 ATTACHMENTS, Data Table Summary.................................................................................................... 50, Complete Data Table for All Analysis Results Obtained In 2023................................... 60, Cross heck Intercomparison Program........................................................................... 88 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 4 of 96 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: 2023 Page 5 of 96 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: 2023 Page 6 of 96 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, 2023. During that time period 1628 analyses were performed on 1272 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, 2023. Tritium was detected in Surface Water but was below reporting levels (see Figure 7, 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: 2023 Page 7 of 96 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: 2023 Page 8 of 96 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: 2023 Page 9 of 96 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: 2023 Page 10 of 96 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: 2023 Page 11 of 96 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: 2023 Page 12 of 96 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: 2023 Page 13 of 96 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: 2023 Page 14 of 96 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: 2023 Page 15 of 96 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 2023. 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: 2023 Page 16 of 96 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 03E1 4.2 mi. NE; Local Farm 13E3 5.0 mi. W; Local Farm, Odessa, DE Annually Gamma scan 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: 2023 Page 17 of 96 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: 2023 Page 18 of 96 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: 2023 Page 19 of 96 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: 2023 Page 20 of 96 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: 2023 Page 21 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Figure 3, REMP Sample Locations (Off-Site Sampling Locations 1 to 10 Miles) 1§1-.,.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 22 of 96 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

Annual Radiological Environmental Operating Report YEAR: 2023 Page 23 of 96 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: 2023 Page 24 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTEPRETATION 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, 2023, are described below.

In the following sections, results from direct radiation, air, water, and food products analyzed as part of REMP in 2023 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: 2023 Page 25 of 96 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 2023, a total of 238 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.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 26 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Figure 5, TLD Sample Results demonstrates the historical trend of the TLD program.

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

2.

8.

2.

8.

2 2 2 2 3 2

2 2

2 2 8 2 9 2 2 2 2 2 22 2 23 er i g Miles reas o eres opula o Ce ers Ou er i g Miles Co rol oca o s Miles m T 0 -

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Net quarterly dose is the observed field value minus transit and extraneous dose. However, this net dose is not a final net value because the location background has not yet been subtracted. Otherwise this table would largely be non-detect (ND).

1 QTR is a standard quarter, which is normalized over 91 days.

2 Population CenterTLDs: SA-IDM-02F5, 03F3, 13F3, 13F4, 16F2

Annual Radiological Environmental Operating Report YEAR: 2023 Page 27 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Figure 5, TLD Sample Results 8.1.2 Calculated Annual Facility Dose All annual inner ring and outer ring indicator locations (Table 6, REMP Sampling Locations - Direct Radiation) resulted in non-detectable dose.

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

All annual control locations resulted in non-detectable dose.

After reviewing REMP TLD data for the 2022 AREOR, several TLDs had a net Annual Facility Dose (FA) above background despite non-detectable net Quarterly Facility Doses (FQ). Following the guidance in ANSI/HPS N13.37-2014 new quarterly and annual background (BQ and BA) values and Net Differential Dose (NDDQ and NDDA) values were generated (80130946/280). These new values were applied to the 2023 data.

2.

8.

2.

8.

2 2 2 2 3 2

2 2

2 2 8 2 9 2 2 2 2 2 22 2 23 er i g Miles reas o eres opula o Ce ers Ou er i g Miles Co rol oca o s Miles m T 0 -

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Net quarterly dose is the observed field value minus transit and extraneous dose. However, this net dose is not a final net value because the location background has not yet been subtracted. Otherwise this table would largely be non-detect (ND).

1 QTR is a standard quarter, which is normalized over 91 days.

2 Population CenterTLDs: SA-IDM-02F5, 03F3, 13F3, 13F4, 16F2 I

Annual Radiological Environmental Operating Report YEAR: 2023 Page 28 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 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 15.3 to 20.5 mrem/Standard Quarter and annual doses of 78.3 and 64.7 mrem for Locations 01Q1 and 16Q2, respectively.

Dose to the nearest resident due to direct radiation from ISFSI was calculated to be 0.007 mrem/yr, which is a very small fraction (0.03%) 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)

Location R1 (ft)

D1 Annual Net Dose (mrem)

R2 (ft)

OF D2 Annual Net Dose (mrem)

Nearest Resident 203 64.7 19,536 1.0 6.99E-03 8.1.4 TLD anomalies There were two instances of missing TLDs during the reporting period. A description of these deviations is in section 10.0, Sample Deviations, Anomalies and Unavailability.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 29 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 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 2023, 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].

Naturally occurring Be-7, attributed to cosmic ray activity in the atmosphere, was detected in all 28 indicator location composites at concentrations ranging from 35E-03 pCi/m3 to 67E-03 pCi/m3 with an average concentration of 51E-03 pCi/m3, and in the four control location composites ranging in concentration from 45E-03 pCi/m3 to 78E-03 pCi/m3 with an average concentration of 61E-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]).

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 30 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Gross beta activity was detected in 363 of 364 of indicator location samples at concentrations ranging from 4E-03 pCi/m3 to 34E-03 pCi/m3 with an average concentration of 14E-03 pCi/m3, and in 52 of 52 of the control location samples at concentrations ranging from 7E-03 pCi/m3 to 31E-03 pCi/m3 with an average of 16E-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 6).

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, 2023, 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.

Table 9, Air Particulate and Radioiodine Comparison of Current Year and Historic Data Analysis Preoperational Data (pCi/m3) 2023 Sample Result Average (pCi/m3)

Gamma 109E-03 51E-03 Beta 74E-03 14E-03 Iodine 42E-03

< MDC I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 31 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Figure 6, Air Particulate: Analysis for Gross Beta, Average Mean for All Indicator Vs. Control 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.

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

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2013 2014 201S 2016 control Average

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 32 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 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 do 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 2023, 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 of the 48 indicator location samples at a concentration of 623 pCi/L (80133368-10). 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 7 for graphical presentation.

Figure 7, Surface Water Tritium Results I

I TRITIUM ACTIVITY IN SURFACE WATER - QUARTERLY AVERAGE 2013 THROUGH 2023 I

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

Effluent discharge near lime of fampling 03-05-14 \\

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

Effluent discharge near lime of Effluent discharge near time of sampling: 04-21 -22 1000.00 -----------------------------'sa=m,::pli::,ng,c:_::04_:._-::::20-:..:2::::0c.__---=

--~-::-:-----------_.._------------I Effluent discharge near time of ____..

sampling: 01-17-23 100.00 +--------------------------------------------------------------<

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 1----------------------------------------------------------------------------------------------------------------

Detecta~Trttium(pQ/l) o Lo.ver Limit or Detection (200 ~ill)

Annual Radiological Environmental Operating Report YEAR: 2023 Page 33 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

1.

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 15 of the 48 indicator location samples at concentrations ranging from 59 pCi/L to 131 pCi/L, with an average of 86 pCi/L.

K-40 was detected in 5 of the 12 control location samples at concentrations ranging from 46 pCi/L to 119 pCi/L, with an average concentration of 69 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]).

2.

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).

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 2.2 pCi/L to 9.0 pCi/L, with an average concentration of 6.2 pCi/L. Concentrations for the treated water ranged from 4.3 pCi/L to 9.7 pCi/L, with an average concentration of 6.7 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: 2023 Page 34 of 96 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 detected in 1 of the 12 treated potable water samples at a concentration of 76.3 pCi/L. No preoperational data were 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 10 of the 12 well water samples.

Concentrations ranged from 1.6 pCi/L to 14.7 pCi/L, with an average concentration of 11.6 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]).

5.

Gamma Spectroscopy I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 35 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 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 3,175 pCi/kg (dry) to 16,970 pCi/kg (dry), with an average concentration of 8,029 pCi/kg (dry). Both control locations samples had concentrations ranging from 11,800 pCi/kg (dry) to 13,270 pCi/kg (dry) with an average concentration of 12,535 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 2,644 pCi/kg (dry). Ra-226 was not detected in any of the control location samples. 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]).

Naturally occurring Th-232 was detected in 6 of the 10 indicator location samples at concentrations ranging from 347 pCi/kg (dry) to 989 pCi/kg (dry) with an average concentration of 605 pCi/kg (dry). Th-232 was not detected above MDC in any of the control location samples. 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]).

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 36 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 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, and14F4) 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 PROGRAM CHANGES.

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 1,019 pCi/L to 1,940 pCi/L with an average concentration of 1,368 pCi/L, and the 20 control location sample concentrations ranging from 837 pCi/L to 1,634 pCi/L, with an average concentration of 1,256 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 12 fish and invertebrate samples were analyzed in 2023, 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.

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 2023, were striped bass and white 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.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 37 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations 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 5 indicator location samples at concentrations ranging from 3,272 pCi/kg (wet) to 4,273 pCi/kg (wet) with an average concentration of 3,721 pCi/kg (wet).

The 3 control location samples had concentrations ranging from 2,863 pCi/kg (wet) to 4,195 pCi/kg (wet), with an average of 3,429 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 1,995 pCi/kg (wet) and 3,109 pCi/kg (wet) with an average concentration of 2,552 pCi/kg (wet). The control location samples had concentrations ranging from 2,161 pCi/kg (wet) to 2,896 pCi/kg (wet), with an average concentration of 2,529 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 24 food samples were analyzed in 2023, 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 five locations (02F9, 01G1, 03F8, 15F4 and 03H5); fodder crops (VGT) were sampled at three locations (13E3, 14F4, and 02G3); and broad leaf vegetation (FPL) was sampled at five locations (06S1, 16S1, 10D1, 01G1 and 03H5). 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: 2023 Page 38 of 96 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 3 of the 6 indicator location samples with concentrations ranging from 1,635 pCi/kg (wet) to 2,852 pCi/kg (wet), with an average concentration of 2,127 pCi/kg (wet). Be-7 was detected in 2 of the 2 control location samples, with concentrations ranging from 1,309 pCi/kg (wet) to 2,183 pCi/kg (wet), and an average concentration of 1,746 pCi/kg (wet). No preoperational Be-7 data was available for comparison (Table 26).

Naturally occurring K-40 was detected in all 6 indicator samples, with concentrations ranging from 1,429 pCi/kg (wet) to 11,750 pCi/kg (wet) with an average concentration of 5,427 pCi/kg (wet). K-40 was detected in all of the control location samples, with concentrations ranging from 5,454 pCi/kg (wet) to 8,426 pCi/kg (wet), and an average concentration of 6,940 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 (13 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: 2023 Page 39 of 96 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 13 indicator samples, with concentrations ranging from 1,184 pCi/kg (wet) to 2,857 pCi/kg (wet) with an average concentration of 1,916 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 125 pCi/kg (wet) to 284 pCi/kg (wet) with an average concentration of 205 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 1,834 pCi/kg (wet) to 5,943 pCi/kg (wet) with an average concentration of 3,240 pCi/kg (wet). Preoperational results averaged 7,000 pCi/kg (wet) (Table 28 and RMC-TR-77-03 [11]).

4.

Game Although not required by the Site ODCM, two muskrat samples were collected from two indicator locations. The game samples were collected as Management Audit samples and analyzed for gamma emitters.

No plant related gamma emitters were detected above the MDC in any of the indicator game samples. Naturally occurring K-40 was detected in all 2 samples at concentrations ranging from 2,972 to 3,328 pCi/kg (wet) with an average concentration of 3,150 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. These Management Audit samples were collected in areas that have been relatively undisturbed since the last collection in order to determine any change in the radionuclide inventory of the area.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 40 of 96 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 8 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 the control location. All other gamma emitters were less than the MDC (Table 30).

Figure 8, Cesium-137 Activity in Soil 1974 Through 2022

~

C,

~

u

a.

M -

.;, u 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 Soil is sampled every three years. Last samples were taken in 2019. Annual values are an average of the results from the ten soil sites.

Annual Radiological Environmental Operating Report YEAR: 2023 Page 41 of 96 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: 2023 Page 42 of 96 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, 2023, within the growing season to identify changes in land use, receptor locations, and new exposure pathways. The results for the 2023 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 2023 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: 2023 Page 43 of 96 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 2023, 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 05X1/05S2 5/8/23 - 5/15/23 Power Outage N/A TLD 2 Gamma Dose 13F3 7/1//23 - 9/30/23 TLD Lost Replaced TLD SWA 3 Gamma Dose 11A1 9/20/2023 LLD not met Vendor Tech Coached MLK 3 Gamma Dose 14F4 10/3/2023 LLD not met Vendor Tech Coached APT/AIO4 Gross Iodine 05X1/05S2 11/27/23 - 12/4/23 Power Outage N/A APT/AIO5 Gross Iodine 15S2 11/20/23 - 11/27/23 GFCI Trip Reset GFCI APT/AIO6 Gross Iodine 02F6 11/20/23 - 11/27/23 Power Outage N/A APT/AIO7 Gross Iodine 02F6 11/27/23 - 12/4/23 Power Outage N/A TLD8 Gamma Dose 13F3 10/1/23 - 12/31/23 TLD Missing Replaced TLD in tamper proof housing ESS9 Gamma Emitters 15A2 1/1/23 - 12/31/23 Sample could not be obtained due to construction Required sample was obtained from location 15A1 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 44 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

1.

Sample Deviation (Order 80133368/20): Air samplers 05X1/05S2 lost power during the 5/8/23 to 5/15/23 collection period. The total time the sampler was in operation was 166.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The total outage duration was 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . A total of volume 14,700 (05X1) and 15,260 (05S2) cubic feet were collected for the sample period. Adequate sample volume was achieved during the sample collection period to meet the Gross Beta and I-131 ODCM LLD requirement.

2.

Sample Deviation (Order 80133368/60): TLD at location 13F3 was missing.

The pole appeared to have been struck and a new pole was attached.

Construction was in progress in the area. The TLD was replaced.

3.

Sample Deviation (Order 80133368/70): Vendor that performs duplicate analysis did not count the samples in a timely manner, which resulted in not meeting the sensitivity (LLD) requirements of the ODCM for I-131. The new technician was coached to adhere to the count schedule when counting samples. The ODCM required samples were analyzed by the primary vendor and the ODCM sensitivity requirements were met for these samples.

4.

Sample Deviation (Order 80133368/80): Air samplers 05X1/05S2 power was lost due to maintenance during the 11/27/23 to 12/4/23 collection period. The total time the sampler was in operation was 131.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The total outage duration was 35.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . A total of volume 12,300 (05X1) and 11,850 (05S2) cubic feet were collected for the sample period. Adequate sample volume was achieved during the sample collection period to meet the Gross Beta and I-131 ODCM LLD requirement.

5.

Sample Deviation (Order 80133368/100): Air sampler 15S2 lost power during the 11/20/23 to 11/27/23 collection period. The total time the sampler was in operation was 105.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The total outage duration was 62.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . A total of volume 9,300 cubic feet was collected for the sample period. Adequate sample volume was achieved during the sample collection period to meet the Gross Beta and I-131 ODCM LLD requirement.

6.

Sample Deviation (Order 80133368/100): Air sampler 02F6 power was lost due to GFCI trip on the 11/20/23 to 11/27/23 collection period. The total time the sampler was in operation was 165.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The total outage duration was 2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . A total of volume 14,300 cubic feet was collected for the sample period.

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

7.

Sample Deviation (Order 80133368/110): Air sampler 02F6 lost power during the 11/27/23 to 12/4/23 collection period. The total time the sampler was in operation was 150.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . The total outage duration was 16.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . A total of volume 13,700 cubic feet was collected for the sample period. Adequate sample volume was achieved during the sample collection period to meet the Gross Beta and I-131 ODCM LLD requirement.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 45 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

8.

Sample Deviation (Order 80133368/120): TLD at location 13F3 was missing.

This was the second time the TLD was missing. The TLD is located near a school in a residential neighborhood. The TLD was replaced with a tamper proof container and placed higher on the pole to prevent tampering.

9.

Sample Deviation (Order 80133368/130): Sediment 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. This is not a program deviation.

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).

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.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 46 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations Therefore, HCGS did not exceed the Technical Specifications limit specified in section 3.4.5.

12.4 Corrections to Previous Reports No errata from previous reports I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 47 of 96 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.

[2] "10 CFR 50, "Domestic Licensing of Production and Utilization Facilities"," US Nuclear Regulatory Commission, Washington, DC.

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

Revision 2," Nuclear Regulatory Commission, 2009.

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

[5] "NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors,," Nuclear Regulatory Commission, April 1991.

[6] "Branch Technical Position, Revision 1," NRC000096, Submitted March 30, 2012, November 1979.

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

https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.

[8] "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.

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

[10] "ANSI 13.37, Environmental Dosimetry-Criteria for System Design and Implementation," Health Physics Society (HPS), May, 2019.

[11] "RMC-TR-77-03, 1978, Artificial Island Radiological Environmental Monitoring Program -

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

[12] "4th Quarter 2023 Quality Assurance Report," Teledyne Brown Engineering Environmental Services, 2023.

[13] "Annual Quality Assurance Report For The Radiological Environmental Monitoring Program (REMP)," GEL Laboratories, 2023.

[14] "Annual Quality Assurance Status Report," Environmental Dosimetry Company, 2023.

[15] "NUREG/CR-2919, XOQDOQ Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,," Nuclear Regulatory Commission, September, 1982.

[16] "Measurements of Radionuclides in the environment Sampling and Analysis of plutonium in soil,"

Nuclear Regulatory Commission, 1974.

[17] "Ionizing Radiation Exposure of the Population of the United States," Bethesda, MD, 2009.

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

[19] "ICRP Publication 60, ICRP Publication 60: 1990 Recommendations of the International Commission on Radiological Protection, 60, Annals of the ICRP Volume 21/1-3,," International Commission on Radiation Protection, October, 1991.

[20] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. [Accessed 10 November 2020].

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 48 of 96 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].

[24] "NEI 07-07, Industry Ground Water Protection InitiativeFinal Guidance Document,," Nuclear Energy Institute, Washington, D.C..

[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].

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

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

https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.

[31] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. [Accessed 10 November 2020].

[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: 2023 Page 49 of 96 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: 2023 Page 50 of 96 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: 2023 Page 51 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

I. DIRECT DIRECT RADIATION TLD-QUARTERLY 234 N/A 14.9 (222/224)

SA-IDM-01Q1 33.2 (4/4) 14.5 (12/12) 0 (mR/standard quarter)

(10.9/34.1) 0.58 MILES N (32.5/34.1)

(12.7/16.0)

II. AIRBORNE AIR PARTICULATE Gr-B 416 10 14 (363/364)

SA-APT-14G1 (C) 16 (52/52) 16 (52/52) 0 (E-3 pCi/m3)

(4/34) 13.4 MILES WNW (7/31)

(7/31)

GAMMA 32 Be-7 N/A 51 (28/28)

SA-APT-14G1 (C) 60.5 (4/4) 60.5 (4/4) 0 (34.6/67.2) 13.4 MILES WNW (45/77.6)

(45/77.6)

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 60 200 623 (1/48)

SA-SWA-11A1 623 (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 86 (15/48)

SA-SWA-07E1 113 (5/12) 69 (5/12) 0 (59/131) 4.4 MILES SE (99/131)

(46/119)

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 52 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

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

6.2 (12/12)

SA-PWR-02F3 6.2 (12/12)

N/A 0

(2.2/9) 8.0 MILES NNE (2.2/9)

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: 2023 Page 53 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

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

6.7 (12/12)

SA-PWT-02F3 6.7 (12/12)

N/A 0

(4.3/9.7) 8.0 MILES NNE (4.3/9.7)

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 76.3 (1/12)

SA-PWT-02F3 76.3 (1/12)

N/A 0

8.0 MILES NNE 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: 2023 Page 54 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

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

11.6 (10/12)

SA-WWA-03E1 11.6 (10/12)

N/A 0

(1.6/14.7) 4.1 MILES NE (1.6/14.7)

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: 2023 Page 55 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

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 8029 (10/10)

SA-ESS-12B1 (C) 12535 (2/2) 12535 (2/2) 0 (3175/16970) 1.8 MILES WSW (11800/13270)

(11800/13270)

Cs-134 150

<MDC N/A N/A

<MDC 0

Cs-137 180

<MDC N/A N/A

<MDC 0

Ra-226 N/A 2644 (1/10)

SA-ESS-16F1 2644 (1/2)

<MDC 0

6.9 MILES NNW Th-232 N/A 605 (6/10)

SA-ESS-16F1 743 (2/2)

<MDC 0

(347/989) 6.9 MILES NNW (498/989)

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 56 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

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 1368 (40/40)

SA-MLK-14F4 1376 (20/20) 1256 (20/20) 0 (1019/1940) 8.4 MILES WNW (1051/1940)

(837/1634)

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 8

(pCi/kg wet)

K-40 N/A 3721 (5/5)

SA-ESF-07E1 3793 (3/3) 3429 (3/3) 0 (3272/4273) 4.4 MILES SE (3272/4273)

(2863/4195)

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: 2023 Page 57 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

BLUE CRABS GAMMA 4

(pCi/kg wet)

K-40 N/A 2552 (2/2)

SA-ECH-11A1 2552 (2/2) 2528.5 (2/2) 0 (1995/3109) 0.22 MILES SW (1995/3109)

(2161/2896)

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 8

FPL (pCi/kg wet)

Be-7 N/A 2127.3 (3/6)

SA-FPL-16S1 2373.5 (2/2) 1746 (2/2) 0 (1635/2852) 0.57 MILES NNW (1895/2852)

(1309/2183)

K-40 N/A 5427.3 (6/6)

SA-FPL-16S1 9752.5 (2/2) 6940 (2/2) 0 (1429/11750) 0.57 MILES NNW (7755/11750)

(5454/8426)

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: 2023 Page 58 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

VEGETABLES, FPV GAMMA 13 (pCi/kg wet)

Be-7 N/A

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

K-40 N/A 1916.2 (13/13)

SA-FPV-15F4 2207 (2/2)

N/A 0

(1184/2857) 7.0 MILES NW (1852/2562)

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 204.7 (2/3)

SA-VGT-2G3 284 (1/1)

N/A 0

(125.3/284) 11.8 MILES NNE K-40 N/A 3240 (3/3)

SA-VGT-13E3 5943 (1/1)

N/A 0

(1834/5943) 5.0 MILES W 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: 2023 Page 59 of 96 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, 2023 to December 31, 2023 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 MEASUREMENT S

MEAN (f) **

NAME MEAN (f) **

MEAN (f) **

(RANGE)

DISTANCE AND DIRECTION (RANGE)

(RANGE)

GAME GAMMA 2

(pCi/kg wet)

Be-7 N/A

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

K-40 N/A 3150 (2/2)

SA-GAM-03E1 3328 (1/1)

N/A 0

(2972/3328) 4.1 MILES NE 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: 2023 Page 60 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Complete Data Table for All Analysis Results Obtained In 2023 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 61 of 96 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)

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

Baseline, BA (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 33.3 34.1 33.0 32.5 19.7 20.5 19.5 18.9 54.6 132.9 78.3 16Q2 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 ND ND 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 ND ND ND ND 42.8 49.7 ND 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 ND ND 47.8 52.6 ND 07S1 12.5 13.4 13.0 12.9 13.6 ND ND ND ND 49.9 52.9 ND 08S1 11.0 11.2 11.4 11.3 11.5 ND ND ND ND 44.1 45.4 ND 08S2 11.3 11.4 11.1 10.9 11.6 ND ND ND ND 45.3 45.0 ND 10S1 11.6 12.4 12.3 12.0 13.2 ND ND ND ND 47.3 49.9 ND 11S1 10.7 12.2 11.8 11.3 12.9 ND ND ND ND 43.8 48.3 ND 12S1 14.4 15.1 14.9 14.3 18.4 ND ND ND ND 57.7 62.6 ND 13S1 16.3 17.3 17.1 16.3 17.9 ND ND ND ND 65.2 68.6 ND 15S1 10.8 13.0 12.9 13.4 12.7 ND ND ND ND 43.3 52.0 ND 15S2 13.2 13.9 14.1 13.6 13.8 ND ND ND ND 52.6 55.4 ND 15S3 16.0 18.2 17.4 18.2 17.3 ND ND 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 ND ND ND 52.3 61.7 ND 05D1 13.6 14.3 14.9 14.6 14.3 ND ND ND ND 54.3 58.1 ND 10D1 13.7 14.8 15.6 15.6 15.2 ND ND ND ND 55.2 61.2 ND 14D1 12.0 13.5 13.8 14.1 13.4 ND ND ND ND 48.1 54.8 ND 15D1 13.6 14.5 15.0 15.0 15.0 ND ND ND ND 54.7 59.5 ND 02E1 12.3 13.8 14.3 14.2 14.2 ND ND ND ND 49.5 56.5 ND 03E1 10.4 12.8 12.7 12.4 12.8 ND ND 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 ND ND ND 55.4 63.1 ND 13E1 10.9 12.6 12.6 12.0 13.0 ND ND ND ND 44.0 50.2 ND 16E1 12.8 14.3 14.7 14.0 14.4 ND ND ND ND 51.7 57.4 ND 01F1 17.1 18.6 18.8 18.7 18.8 ND ND ND ND 68.3 74.8 ND 02F2 12.8 13.3 13.5 13.3 13.6 ND ND ND ND 51.2 53.7 ND 02F5 12.8 15.1 14.8 15.3 14.6 ND ND ND ND 51.4 59.7 ND 02F6 11.9 13.6 14.0 13.3 13.9 ND ND ND ND 47.6 54.8 ND 03F2 11.0 13.3 13.2 12.9 13.5 ND ND ND ND 44.4 52.9 ND 03F3 11.0 13.3 13.1 13.3 13.6 ND ND ND ND 44.2 53.3 ND 04F2 10.7 12.4 13.1 12.6 12.8 ND ND ND ND 43.1 51.0 ND 05F1 11.5 13.7 13.3 13.4 13.7 ND ND ND ND 46.1 54.1 ND 06F1 11.3 11.5 11.3 10.9 11.4 ND ND 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 ND ND ND 59.9 54.7 ND 09F2 14.0 15.6 16.6 12.4 16.3 ND ND ND ND 56.3 60.9 ND 10F2 13.2 14.6 15.3 15.1 15.4 ND ND ND ND 52.9 60.5 ND 11F1 13.8 15.7 16.2 16.1 16.1 ND ND ND ND 55.4 64.1 ND 12F1 12.9 14.8 15.4 15.2 15.3 ND ND ND ND 51.7 60.7 ND I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 62 of 96 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)

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

Baseline, BA (mrem)

Annual Monitoring Data, MA (mrem)

Annual Facility

Dose, FA=MA-BA (mrem)

(mrem)

(mrem) 1 2

3 4

1 2

3 4

13F2 12.7 14.7 15.0 15.5 15.1 ND ND ND ND 51.2 60.4 ND 13F3 14.2 15.0 15.6 TNR TNR ND ND TNR TNR 58.0 61.2 ND 13F4 13.0 15.6 16.5 16.1 15.6 ND ND ND ND 59.7 63.8 ND 14F2 14.0 15.5 15.5 16.7 16.5 ND ND ND ND 56.2 64.2 ND 15F3 14.5 15.7 16.3 15.9 16.2 ND ND ND ND 58.2 64.1 ND 16F2 11.7 14.1 14.3 14.2 14.3 ND ND ND ND 47.1 56.9 ND 01G3 14.9 14.3 15.2 14.3 14.7 ND ND ND ND 60.2 58.5 ND 03G1 13.3 15.6 15.6 15.5 15.8 ND ND ND ND 53.4 62.5 ND 10G1 14.7 15.6 15.7 15.5 16.0 ND ND ND ND 58.8 62.8 ND 14G1 13.4 15.2 15.6 15.2 15.7 ND ND ND ND 54.1 61.7 ND 16G1 12.7 13.6 14.0 13.7 14.2 ND ND ND ND 50.1 55.6 ND 03H1 12.6 13.3 13.2 12.7 13.4 ND ND ND ND 50.6 52.6 ND I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 63 of 96 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, 2023 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) 01/03/23 04/03/23 53

+/-

13 29 1

1 04/03/23 07/03/23 78

+/-

15 24 2

1 07/03/23 10/03/23 67

+/-

13 33 1

1 10/03/23 01/02/24 45

+/-

12 23 1

2 AVERAGE*

60

+/-

29 SA-APT-05X1 01/03/23 04/03/23 35

+/-

10 18 1

1 04/03/23 07/03/23 47

+/-

12 25 1

1 07/03/23 10/03/23 51

+/-

11 22 1

1 10/03/23 01/02/24 42

+/-

10 21 1

1 AVERAGE*

44

+/-

14 SA-APT-06S1 01/03/23 04/03/23 67

+/-

18 34 2

2 04/03/23 07/03/23 62

+/-

18 27 2

2 07/03/23 10/03/23 58

+/-

13 21 1

1 10/03/23 01/02/24 40

+/-

13 20 1

2 AVERAGE*

57

+/-

24 SA-APT-15S2 01/03/23 04/03/23 38

+/-

12 25 1

1 04/03/23 07/03/23 50

+/-

13 26 2

1 07/03/23 10/03/23 45

+/-

13 28 1

1 10/03/23 01/02/24 43

+/-

9 21 1

1 AVERAGE*

44

+/-

10 SA-APT-05D1 01/03/23 04/03/23 60

+/-

16 21 1

1 04/03/23 07/03/23 67

+/-

17 20 2

1 07/03/23 10/03/23 38

+/-

13 27 2

1 10/03/23 01/02/24 50

+/-

12 23 1

1 AVERAGE*

54

+/-

25 SA-APT-16E1 01/03/23 04/03/23 50

+/-

13 26 2

1 04/03/23 07/03/23 63

+/-

15 19 1

1 07/03/23 10/03/23 61

+/-

14 27 2

2 10/03/23 01/02/24 51

+/-

12 22 2

1 AVERAGE*

56

+/-

13 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 64 of 96 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, 2023 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 01/03/23 04/03/23 50

+/-

14 33 2

2 04/03/23 07/03/23 52

+/-

15 20 2

1 07/03/23 10/03/23 54

+/-

12 26 2

1 10/03/23 01/02/24 41

+/-

9 21 2

1 AVERAGE*

49

+/-

11 SA-APT-02F6 01/03/23 04/03/23 57

+/-

13 26 1

1 04/03/23 07/03/23 58

+/-

19 31 3

2 07/03/23 10/03/23 56

+/-

11 26 2

1 10/03/23 01/02/24 40

+/-

11 28 2

2 AVERAGE*

53

+/-

17 ALL INDICATOR AVERAGE *.

51

+/-

18 (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: 2023 Page 65 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 14, Concentrations of Gross Beta Emitters in Air Particulates, 2023 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 01/03/23 -

01/09/23 13

+/-

3 17

+/-

3 14

+/-

3 12

+/-

3 16

+/-

3 15

+/-

3 16

+/-

3 15

+/-

3 01/09/23 -

01/17/23 15

+/-

3 15

+/-

3 16

+/-

3 9

+/-

3 16

+/-

3 14

+/-

3 16

+/-

3 13

+/-

3 01/17/23 -

01/23/23 9

+/-

3 7

+/-

3 9

+/-

3 7

+/-

3 8

+/-

3 7

+/-

3 5

+/-

3 9

+/-

3 01/23/23 -

01/30/23 11

+/-

3 12

+/-

3 14

+/-

3 8

+/-

3 15

+/-

3 15

+/-

3 13

+/-

3 15

+/-

3 01/30/23 -

02/06/23 16

+/-

3 15

+/-

3 15

+/-

3 10

+/-

3 14

+/-

3 14

+/-

3 11

+/-

3 13

+/-

3 02/06/23 -

02/13/23 24

+/-

3 26

+/-

3 23

+/-

3 20

+/-

3 23

+/-

3 23

+/-

3 23

+/-

4 24

+/-

4 02/13/23 -

02/21/23 15

+/-

3 11

+/-

3 15

+/-

3 10

+/-

3 13

+/-

3 14

+/-

3 13

+/-

3 13

+/-

3 02/21/23 -

02/27/23 16

+/-

4 17

+/-

3 15

+/-

3 14

+/-

3 13

+/-

3 16

+/-

3 16

+/-

3 16

+/-

3 02/27/23 -

03/06/23 9

+/-

3 11

+/-

3 8

+/-

3 7

+/-

3 9

+/-

3 11

+/-

3 8

+/-

3 10

+/-

3 03/06/23 -

03/13/23 9

+/-

3 8

+/-

3 9

+/-

3 6

+/-

3 9

+/-

3 9

+/-

3 9

+/-

3 10

+/-

3 03/13/23 -

03/20/23 18

+/-

3 16

+/-

3 14

+/-

3 12

+/-

3 26

+/-

4 14

+/-

3 12

+/-

3 16

+/-

3 03/20/23 -

03/28/23 17

+/-

3 16

+/-

3 16

+/-

3 13

+/-

3 18

+/-

3 16

+/-

3 16

+/-

3 15

+/-

3 03/28/23 -

04/03/23 18

+/-

4 19

+/-

4 20

+/-

4 15

+/-

4 18

+/-

4 19

+/-

4 13

+/-

3 18

+/-

4 04/03/23 -

04/10/23 18

+/-

3 17

+/-

3 16

+/-

3 12

+/-

3 19

+/-

3 17

+/-

3 16

+/-

3 16

+/-

3 04/10/23 -

04/17/23 17

+/-

3 13

+/-

3 13

+/-

3 13

+/-

3 15

+/-

3 11

+/-

3 13

+/-

3 13

+/-

3 04/17/23 -

04/24/23 14

+/-

3 13

+/-

3 15

+/-

3 11

+/-

3 13

+/-

3 9

+/-

3 15

+/-

3 13

+/-

3 04/24/23 -

05/01/23 7

+/-

3 8

+/-

3 10

+/-

3 10

+/-

3 8

+/-

3 7

+/-

3 10

+/-

3 10

+/-

3 05/01/23 -

05/08/23 7

+/-

3 5

+/-

2 5

+/-

2 4

+/-

2 7

+/-

2 6

+/-

3 5

+/-

2 4

+/-

2 05/08/23 -

05/15/23 19

+/-

3 13

+/-

3 18

+/-

3 12

+/-

3 17

+/-

3 16

+/-

3 14

+/-

3 14

+/-

3 05/15/23 -

05/22/23 12

+/-

3 10

+/-

3 11

+/-

3 8

+/-

3 9

+/-

3 11

+/-

3 10

+/-

3 12

+/-

3 05/22/23 -

05/30/23 10

+/-

2 11

+/-

3 11

+/-

2 9

+/-

2 9

+/-

2 11

+/-

3 11

+/-

2 8

+/-

2 05/30/23 -

06/05/23 9

+/-

3 6

+/-

3 8

+/-

3 6

+/-

3 6

+/-

3 9

+/-

3 6

+/-

3 7

+/-

3 06/05/23 -

06/12/23 18

+/-

3 16

+/-

3 16

+/-

3 13

+/-

3 17

+/-

3 17

+/-

3 16

+/-

3 15

+/-

3 06/12/23 -

06/20/23 18

+/-

3 12

+/-

3 13

+/-

3 9

+/-

2 12

+/-

3 11

+/-

3 12

+/-

2 15

+/-

3 06/20/23 -

06/26/23 8

+/-

3 7

+/-

3 5

+/-

3 4

7

+/-

3 9

+/-

3 6

+/-

3 7

+/-

3 06/26/23 -

07/03/23 13

+/-

3 15

+/-

3 14

+/-

3 11

+/-

3 12

+/-

3 14

+/-

3 14

+/-

3 15

+/-

3 07/03/23 -

07/10/23 26

+/-

4 17

+/-

3 27

+/-

4 10

+/-

3 15

+/-

3 20

+/-

3 15

+/-

3 15

+/-

3 07/10/23 -

07/17/23 17

+/-

4 15

+/-

3 12

+/-

3 12

+/-

3 17

+/-

3 12

+/-

3 15

+/-

3 14

+/-

3 07/17/23 -

07/24/23 19

+/-

4 13

+/-

3 16

+/-

3 14

+/-

3 12

+/-

3 13

+/-

3 11

+/-

3 13

+/-

3 07/24/23 -

07/31/23 18

+/-

3 14

+/-

3 19

+/-

3 12

+/-

3 16

+/-

3 18

+/-

3 14

+/-

3 14

+/-

3 08/07/23 -

08/14/23 16

+/-

3 15

+/-

3 16

+/-

3 13

+/-

3 14

+/-

3 12

+/-

3 15

+/-

3 14

+/-

3 08/14/23 -

08/21/23 19

+/-

3 16

+/-

3 19

+/-

3 15

+/-

3 17

+/-

3 19

+/-

3 16

+/-

3 18

+/-

3 08/21/23 -

08/28/23 15

+/-

3 13

+/-

3 16

+/-

3 10

+/-

3 13

+/-

3 14

+/-

3 15

+/-

3 15

+/-

3 08/28/23 -

09/05/23 16

+/-

3 13

+/-

3 15

+/-

3 9

+/-

3 15

+/-

3 15

+/-

3 12

+/-

3 17

+/-

3 09/05/23 -

09/11/23 14

+/-

3 15

+/-

3 16

+/-

3 10

+/-

3 14

+/-

3 15

+/-

3 13

+/-

3 17

+/-

3 09/11/23 -

09/18/23 31

+/-

4 31

+/-

4 30

+/-

4 25

+/-

4 34

+/-

4 27

+/-

4 34

+/-

4 28

+/-

4 09/18/23 -

09/25/23 20

+/-

4 15

+/-

3 16

+/-

3 9

+/-

3 14

+/-

3 15

+/-

3 15

+/-

3 14

+/-

3 09/25/23 -

10/03/23 12

+/-

3 8

+/-

3 6

+/-

3 9

+/-

3 9

+/-

3 12

+/-

3 7

+/-

3 8

+/-

3 10/03/23 -

10/09/23 9

+/-

2 10

+/-

3 9

+/-

3 11

+/-

3 8

+/-

2 8

+/-

3 11

+/-

3 13

+/-

3 10/09/23 -

10/16/23 18

+/-

4 16

+/-

4 21

+/-

4 15

+/-

4 18

+/-

4 18

+/-

4 15

+/-

4 15

+/-

4 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 66 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 14, Concentrations of Gross Beta Emitters in Air Particulates, 2023 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 10/16/23 -

10/24/23 15

+/-

3 14

+/-

3 17

+/-

3 15

+/-

3 13

+/-

3 13

+/-

3 17

+/-

3 16

+/-

3 10/24/23 -

10/30/23 10

+/-

3 8

+/-

3 8

+/-

3 9

+/-

2 8

+/-

3 7

+/-

3 7

+/-

2 8

+/-

3 10/30/23 -

11/06/23 22

+/-

4 18

+/-

4 17

+/-

4 15

+/-

3 15

+/-

3 14

+/-

3 15

+/-

3 16

+/-

3 11/06/23 -

11/13/23 17

+/-

3 15

+/-

3 17

+/-

3 16

+/-

3 19

+/-

3 18

+/-

3 15

+/-

3 25

+/-

4 11/13/23 -

11/20/23 22

+/-

4 10

+/-

3 19

+/-

3 23

+/-

3 21

+/-

3 21

+/-

3 21

+/-

3 11

+/-

3 11/20/23 -

11/27/23 22

+/-

3 17

+/-

3 16

+/-

3 18

+/-

3 19

+/-

3 18

+/-

3 16

+/-

3 18

+/-

3 11/27/23 -

12/04/23 13

+/-

3 12

+/-

3 12

+/-

3 16

+/-

5 13

+/-

3 9

+/-

3 10

+/-

3 13

+/-

3 12/04/23 -

12/11/23 20

+/-

4 23

+/-

4 23

+/-

4 21

+/-

4 23

+/-

4 17

+/-

3 20

+/-

4 22

+/-

4 12/11/23 -

12/19/23 16

+/-

3 17

+/-

3 16

+/-

3 19

+/-

3 17

+/-

3 17

+/-

3 17

+/-

3 17

+/-

3 12/19/23 -

12/26/23 14

+/-

3 14

+/-

3 17

+/-

3 18

+/-

3 17

+/-

3 19

+/-

3 17

+/-

3 16

+/-

3 12/26/23 -

01/02/24 14

+/-

3 14

+/-

3 15

+/-

3 15

+/-

3 14

+/-

3 13

+/-

3 13

+/-

3 12

+/-

3 AVERAGE*

12

+/-

3 11

+/-

3 12

+/-

3 10

+/-

3 10

+/-

3 14

+/-

3 10

+/-

3 7

+/-

3 ALL INDICATOR AVERAGE* 14 +/- 9 I

I I

Annual Radiological Environmental Operating Report YEAR: 2023 Page 67 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 15, Concentrations of Iodine-131 in Filtered Air, 2023 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 01/03/23 01/09/23

< 19

< 27

< 18

< 20

< 27

< 18

< 26

< 27 01/09/23 01/17/23

< 15

< 20

< 14

< 15

< 20

< 7

< 20

< 20 01/17/23 01/23/23

< 25

< 23

< 24

< 25

< 15

< 26

< 24

< 23 01/23/23 01/30/23

< 16

< 21

< 16

< 7

< 22

< 17

< 23

< 22 01/30/23 02/06/23

< 21

< 17

< 21

< 17

< 22

< 18

< 8 02/06/23 02/13/23

< 20

< 21

< 20

< 23

< 8

< 23

< 22 02/13/23 02/21/23

< 15

< 18

< 14

< 7

< 17

< 15

< 17

< 19 02/21/23 02/27/23

< 30

< 19

< 29

< 12

< 28

< 18

< 19 02/27/23 03/06/23

< 13

< 27

< 22

< 21

< 25

< 20

< 25

< 24 03/06/23 03/13/23

< 20

< 10

< 19

< 10

< 19

< 20

< 19

< 20 03/13/23 03/20/23

< 24

< 32

< 23

< 31

< 24

< 31

< 31 03/20/23 03/28/23

< 8

< 13

< 17

< 18

< 17

< 18

< 18 03/28/23 04/03/23

< 40

< 26

< 40

< 39

< 25

< 39

< 25

< 25 04/03/23 04/10/23

< 23

< 16

< 22

< 16

< 22

< 16

< 15 04/10/23 04/17/23

< 23

< 26

< 23

< 22

< 24

< 23

< 24

< 22 04/17/23 04/24/23

< 20

< 21

< 20

< 21

< 18

< 20 04/24/23 05/01/23

< 21

< 31

< 23

< 30

< 22

< 30

< 30 05/01/23 05/08/23

< 24

< 22

< 23

< 24

< 25 05/08/23 05/15/23

< 27

< 32

< 26

< 32

< 27

< 31

< 31 05/15/23 05/22/23

< 24

< 16

< 26

< 25

< 15

< 26

< 15

< 15 05/22/23 05/30/23

< 9

< 26

< 18

< 25

< 19

< 24

< 25 05/30/23 06/05/23

< 38

< 15

< 37

< 39

< 35

< 35 06/05/23 06/12/23

< 24

< 29

< 10

< 23

< 30

< 23

< 31

< 30 06/12/23 06/20/23

< 18

< 24

< 18

< 17

< 25

< 8

< 22

< 25 06/20/23 06/26/23

< 23

< 29

< 24

< 22

< 30

< 21

< 27

< 30 06/26/23 07/03/23

< 28

< 31

< 28

< 27

< 31

< 27

< 30

< 30 07/03/23 07/10/23

< 24

< 26

< 24

< 10

< 27

< 23

< 26

< 27 07/10/23 07/17/23

< 28

< 27

< 11

< 27

< 28

< 28 07/17/23 07/24/23

< 25

< 21

< 25

< 20

< 24

< 20

< 19 07/24/23 07/31/23

< 25

< 20

< 25

< 8

< 25

< 19

< 19 07/31/23 08/07/23

< 27

< 30

< 28

< 27

< 12

< 27

< 29

< 28 08/07/23 08/14/23

< 19

< 18

< 9

< 19

< 20

< 19 I

I I

Annual Radiological Environmental Operating Report YEAR: 2023 Page 68 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 15, Concentrations of Iodine-131 in Filtered Air, 2023 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 08/14/23 08/21/23

< 21

< 24

< 21

< 20

< 24

< 20

< 11

< 25 08/21/23 08/28/23

< 26

< 22

< 24

< 25

< 22

< 24

< 21

< 22 08/28/23 09/05/23

< 14

< 18

< 14

< 17

< 15

< 17

< 18 09/05/23 09/11/23

< 30

< 36

< 30

< 34

< 31

< 35

< 37 09/11/23 09/18/23

< 23

< 9

< 21

< 20

< 21

< 20

< 21 09/18/23 09/25/23

< 11

< 44

< 25

< 27

< 45

< 24

< 44

< 43 09/25/23 10/03/23

< 17

< 19

< 9

< 20

< 16

< 18

< 17

< 20 10/03/23 10/09/23

< 40

< 33

< 34

< 39

< 32

< 35

< 32

< 33 10/09/23 10/16/23

< 29

< 25

< 27

< 24

< 29

< 25

< 24 10/16/23 10/24/23

< 54

< 26

< 54

< 20

< 26

< 56

< 27

< 26 10/24/23 10/30/23

< 21

< 32

< 21

< 14

< 31

< 21

< 31

< 31 10/30/23 11/06/23

< 19

< 24

< 18

< 13

< 24

< 20

< 25

< 24 11/06/23 11/13/23

< 22

< 25

< 21

< 25

< 22

< 25

< 25 11/13/23 11/20/23

< 15

< 33

< 32

< 33

< 34

< 33 11/20/23 11/27/23

< 20

< 23

< 19

< 25

< 23

< 20

< 24

< 25 11/27/23 12/04/23

< 20

< 24

< 20

< 22

< 20

< 15

< 20

< 22 12/04/23 12/11/23

< 26

< 8

< 26

< 25

< 17

< 25

< 18

< 19 12/11/23 12/19/23

< 11

< 14

< 11

< 8

< 15

< 11

< 15

< 15 12/19/23 12/26/23

< 20

< 19

< 20

< 21

< 20

< 19

< 18 12/26/23 01/02/24

< 18

< 19

< 17

< 20

< 19

< 20

< 19 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.

I I

I

Annual Radiological Environmental Operating Report YEAR: 2023 Page 69 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 16, Concentrations of Tritium in Surface Water, 2023 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 01/04/23 01/17/23 181 623 +/-

147 179 181 175 02/07/23 02/20/23 183 181 182 174 180 03/06/23 03/21/23 191 174 179 192 195 04/04/23 04/20/23 183 184 174 184 183 05/08/23 05/16/23 183 179 190 182 184 06/07/23 06/25/23 195 199 197 196 199 07/07/23 07/22/23 193 192 189 194 192 08/09/23 08/23/23 198 197 197 193 193 09/06/23 09/20/23 188 188 187 190 188 10/05/23 10/19/23 196 198 196 196 199 11/08/23 11/25/23 192 194 193 190 197 12/06/23 12/21/23 179 181 181 185 182 AVERAGE*

623 +/-

147 (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: 2023 Page 70 of 96 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, 2023 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) 01/04/23

< 0.9

< 44

< 5

< 6

< 14

< 7

< 12

< 6

< 5

< 11 02/07/23

< 0.6

< 89

< 4

< 5

< 9

< 8

< 11

< 5

< 6

< 5

< 8 03/06/23

< 0.9 68 +/- 27

< 2

< 4

< 2

< 4

< 2

< 4 04/04/23

< 0.9

< 151

< 8

< 11

< 6

< 15

< 6

< 5

< 14 05/08/23

< 0.9

< 48

< 2

< 4

< 2

< 4

< 2

< 3

< 2

< 4 06/07/23

< 0.8

< 102

< 5

< 12

< 5

< 11

< 6

< 10 07/07/23

< 0.9 46 +/- 26

< 1

< 3

< 2

< 3

< 1

< 2 08/09/23

< 0.9

< 21

< 2

< 5

< 3

< 5

< 3

< 2

< 4 09/06/23

< 0.8 47 +/- 31

< 2

< 4

< 2

< 4

< 2

< 5 10/05/23

< 0.9 119 +/- 38

< 3

< 4

< 8

< 4

< 7

< 3

< 4

< 7 11/08/23

< 0.8

< 30

< 3

< 6

< 3

< 5

< 3

< 4 12/06/23

< 0.9 65 +/- 36

< 3

< 6

< 3

< 6

< 3

< 5 AVERAGE*

69 +/- 59 SA-SWA-11A1 01/04/23

< 0.9 98 +/- 48

< 4

< 9

< 5

< 11

< 4

< 5

< 4

< 9 02/07/23

< 0.8

< 58

< 4

< 6

< 10

< 5

< 13

< 6

< 5

< 6

< 7 03/06/23

< 0.8 60 +/- 28

< 2

< 5

< 2

< 4

< 2

< 5 04/04/23

< 0.8

< 61

< 5

< 11

< 5

< 10

< 5

< 6

< 5

< 7 05/08/23

< 0.9

< 78

< 4

< 5

< 9

< 5

< 10

< 5

< 8 06/07/23

< 0.9

< 122

< 5

< 9

< 4

< 10

< 6

< 5

< 6

< 8 07/07/23

< 0.9 72 +/- 17

< 1

< 3

< 1

< 3

< 1

< 2 08/09/23

< 0.8

< 21

< 2

< 5

< 3

< 5

< 2

< 4 09/06/23

< 1.0 61 +/- 35

< 2

< 5

< 2

< 5

< 2

< 4 10/05/23

< 0.9

< 78

< 4

< 9

< 4

< 8

< 4

< 8 11/08/23

< 0.8 105 +/- 32

< 3

< 6

< 3

< 6

< 3

< 4 12/06/23

< 0.9 63 +/- 38

< 4

< 8

< 3

< 8

< 4

< 8 AVERAGE*

76 +/- 40 (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: 2023 Page 71 of 96 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, 2023 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 01/04/23

< 0.9

< 41

< 4

< 9

< 5

< 8

< 4

< 5

< 7 02/07/23

< 0.6

< 135

< 7

< 8

< 13

< 7

< 10

< 4

< 7

< 9 03/06/23

< 0.8 131 +/- 32

< 2

< 5

< 2

< 4

< 2

< 5 04/04/23

< 0.9

< 160

< 5

< 6

< 17

< 7

< 15

< 7

< 5

< 7

< 12 05/08/23

< 0.9

< 21

< 2

< 5

< 3

< 5

< 2

< 3

< 2

< 4 06/07/23

< 0.8 121 +/- 69

< 7

< 6

< 10

< 6

< 14

< 4

< 6

< 7

< 8 07/07/23

< 0.9 99 +/- 23

< 2

< 3

< 2

< 3

< 2

< 3 08/09/23

< 0.9

< 22

< 2

< 6

< 3

< 5

< 2

< 3

< 2

< 6 09/06/23

< 0.9

< 35

< 3

< 4

< 7

< 3

< 7

< 4

< 3

< 4

< 5 10/05/23

< 1.0 109 +/- 38

< 3

< 6

< 3

< 6

< 3

< 5 11/08/23

< 0.8

< 30

< 3

< 6

< 2

< 5

< 3

< 4 12/06/23

< 0.9 105 +/- 41

< 4

< 5

< 10

< 4

< 8

< 4

< 7 AVERAGE*

113 +/- 25 SA-SWA-01F2 01/04/23

< 0.7

< 41

< 4

< 10

< 5

< 9

< 5

< 4

< 6 02/07/23

< 0.6

< 104

< 6

< 8

< 7

< 9

< 6

< 7 03/06/23

< 0.8

< 17

< 2

< 4

< 2

< 4

< 2

< 5 04/04/23

< 0.7

< 77

< 5

< 4

< 10

< 5

< 11

< 4

< 5

< 9 05/08/23

< 0.8

< 21

< 2

< 5

< 3

< 5

< 2

< 3

< 2

< 4 06/07/23

< 0.9

< 94

< 6

< 5

< 11

< 6

< 11

< 6

< 7

< 11 07/07/23

< 0.9

< 17

< 2

< 4

< 2

< 3

< 2

< 3 08/09/23

< 0.9

< 41

< 2

< 4

< 3

< 5

< 2

< 4 09/06/23

< 0.9

< 19

< 2

< 5

< 2

< 4

< 2

< 4 10/05/23

< 0.9 70 +/- 30

< 2

< 6

< 3

< 5

< 3

< 2

< 5 11/08/23

< 0.7

< 30

< 3

< 6

< 3

< 6

< 3

< 4 12/06/23

< 0.9

< 38

< 4

< 8

< 4

< 8

< 4

< 8 AVERAGE*

70 +/- 30 (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: 2023 Page 72 of 96 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, 2023 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 01/04/23

< 0.8

< 54

< 4

< 5

< 11

< 5

< 10

< 4

< 5

< 8 02/07/23

< 0.5

< 158

< 4

< 5

< 11

< 6

< 13

< 5

< 6

< 7

< 5 03/06/23

< 0.9 59 +/- 28

< 2

< 3

< 6

< 3

< 5

< 3

< 2

< 6 04/04/23

< 0.8

< 98

< 5

< 6

< 8

< 7

< 12

< 5

< 6

< 5

< 9 05/08/23

< 0.9

< 41

< 3

< 5

< 8

< 5

< 9

< 5

< 5 06/07/23

< 0.8

< 103

< 5

< 12

< 5

< 11

< 6

< 10 07/07/23

< 0.8

< 17

< 2

< 4

< 2

< 3

< 2

< 3 08/09/23

< 0.8

< 22

< 2

< 5

< 2

< 4

< 3

< 2

< 6 09/06/23

< 1.0 61 +/- 32

< 2

< 4

< 2

< 4

< 2

< 4 10/05/23

< 0.9

< 38

< 4

< 5

< 8

< 4

< 9

< 4

< 6

< 5

< 9 11/08/23

< 0.8 83 +/- 39

< 3

< 6

< 3

< 6

< 3

< 4 12/06/23

< 0.8

< 73

< 5

< 9

< 6

< 9

< 4

< 5

< 4

< 9 AVERAGE*

68 +/- 26 ALL INDICATOR AVERAGE*

86 +/- 49 (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: 2023 Page 73 of 96 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, 2023 Results in Units of pCi/L +/- 2 COLLECTION PERIOD STATION ID START STOP Gross Alpha Gross Beta H-3 SA-PWR-02F3**

12/27/22 01/30/23 1.4 7.8

+/-

1.7 189 01/30/23 02/27/23 1.0 7.5

+/-

1.6 179 02/27/23 03/28/23 1.1 6.9

+/-

1.6 191 03/28/23 04/24/23 1.6 7.3

+/-

2.1 192 04/24/23 05/30/23 1.4 7.4

+/-

1.7 191 05/30/23 06/26/23 2.4 6.7

+/-

2.2 180 06/26/23 07/31/23 0.6 8.1

+/-

1.7 192 07/31/23 08/28/23 1.8 9.0

+/-

1.7 178 08/28/23 09/25/23 2.9 3.4

+/-

1.7 188 09/25/23 10/30/23 2.3 3.8

+/-

1.2 195 10/30/23 11/27/23 1.7 2.2

+/-

1.1 196 11/27/23 12/26/23 1.0 4.6

+/-

1.4 184 AVERAGE*

6.2

+/-

4.3 SA-PWT-02F3**

12/27/22 01/30/23 1.4 7.4

+/-

1.7 191 01/30/23 02/27/23 0.9 9.7

+/-

1.7 183 02/27/23 03/28/23 1.1 6.8

+/-

1.6 194 03/28/23 04/24/23 1.5 6.1

+/-

2.0 192 04/24/23 05/30/23 1.3 5.8

+/-

1.6 191 05/30/23 06/26/23 2.2 6.1

+/-

2.1 180 06/26/23 07/31/23 0.5 8.0

+/-

1.7 192 07/31/23 08/28/23 1.8 8.6

+/-

1.6 180 08/28/23 09/25/23 2.7 4.3

+/-

1.7 189 09/25/23 10/30/23 2.5 6.6

+/-

1.4 197 10/30/23 11/27/23 1.9 4.6

+/-

1.3 195 11/27/23 12/26/23 1.0 5.9

+/-

1.5 181 AVERAGE*

6.7

+/-

3.2 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: 2023 Page 74 of 96 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, 2023 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**

12/27/22 01/30/23

< 0.8

< 97

< 5

< 11

< 5

< 11

< 5

< 6

< 5

< 6

< 153 01/30/23 02/27/23

< 0.5

< 94

< 6

< 5

< 10

< 5

< 9

< 6

< 5

< 6

< 160 02/27/23 03/28/23

< 0.9

< 133

< 7

< 6

< 13

< 8

< 12

< 6

< 7

< 5

< 8

< 154 03/28/23 04/24/23

< 0.7

< 118

< 7

< 8

< 13

< 9

< 13

< 8

< 9

< 7

< 11

< 165 04/24/23 05/30/23

< 0.8

< 130

< 5

< 7

< 13

< 7

< 10

< 6

< 7

< 8

< 172 05/30/23 06/26/23

< 0.8

< 141

< 7

< 6

< 12

< 9

< 12

< 7

< 6

< 8

< 9

< 186 06/26/23 07/31/23

< 0.8

< 83

< 4

< 11

< 5

< 8

< 5

< 4

< 7

< 135 07/31/23 08/28/23

< 0.8

< 83

< 5

< 13

< 6

< 14

< 6

< 5

< 6

< 9

< 163 08/28/23 09/25/23

< 0.9

< 33

< 4

< 3

< 7

< 3

< 8

< 4

< 3

< 6

< 83 09/25/23 10/30/23

< 0.9

< 58

< 3

< 4

< 6

< 3

< 8

< 4

< 3

< 4

< 98 10/30/23 11/27/23

< 0.8

< 90

< 6

< 13

< 8

< 15

< 7

< 8

< 171 11/27/23 12/26/23

< 0.9

< 96

< 7

< 13

< 7

< 15

< 7

< 8

< 9

< 178 AVERAGE*

SA-PWT-02F3**

12/27/22 01/30/23

< 0.8

< 114

< 4

< 9

< 4

< 10

< 5

< 6

< 120 01/30/23 02/27/23

< 0.9

< 99

< 5

< 6

< 9

< 5

< 11

< 5

< 6

< 5

< 9

< 119 02/27/23 03/28/23

< 0.8

< 122

< 6

< 5

< 11

< 7

< 12

< 7

< 8

< 5

< 9

< 173 03/28/23 04/24/23

< 0.6

< 107

< 7

< 12

< 8

< 16

< 6

< 8

< 9

< 201 04/24/23 05/30/23

< 0.8

< 128

< 7

< 6

< 16

< 8

< 11

< 7

< 8

< 11

< 165 05/30/23 06/26/23

< 0.9

< 110

< 7

< 6

< 15

< 10

< 12

< 6

< 7

< 5

< 9

< 162 06/26/23 07/31/23

< 0.9

< 85

< 6

< 5

< 12

< 6

< 12

< 6

< 5

< 9

< 149 07/31/23 08/28/23

< 0.9

< 93

< 5

< 6

< 9

< 7

< 12

< 6

< 5

< 7

< 147 08/28/23 09/25/23

< 0.9

< 75

< 4

< 5

< 10

< 4

< 8

< 5

< 8

< 117 09/25/23 10/30/23

< 0.8 76 +/- 34

< 3

< 8

< 4

< 8

< 3

< 4

< 5

< 99 10/30/23 11/27/23

< 0.8

< 127

< 7

< 6

< 13

< 8

< 15

< 10

< 7

< 6

< 10

< 191 11/27/23 12/26/23

< 0.8

< 159

< 5

< 7

< 17

< 7

< 14

< 8

< 9

< 7

< 9

< 155 AVERAGE*

76 +/- 34 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: 2023 Page 75 of 96 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, 2023 Results in Units of pCi/L +/- 2 STATION ID COLLECTION DATE Gross Alpha Gross Beta H-3 SA-WWA-03E1**

01/23/23 2.6 14.7

+/-

2.5 182 02/21/23 2.9 14.4

+/-

2.6 165 03/20/23 0.6 12.6

+/-

2.0 199 04/17/23 1.6 13.9

+/-

2.0 185 05/22/23 2.2 13.1

+/-

2.1 182 06/20/23 2.2 9.6

+/-

2.1 196 07/17/23 2.2 12.7

+/-

3.0 187 08/21/23 2.1 14.1

+/-

2.4 191 09/18/23 1.3 8.9

+/-

1.8 195 10/24/23 1.4 1.6

+/-

1.1 195 11/27/23 2.0 1.9 191 12/19/23 2.4 1.7 176 AVERAGE*

11.6

+/-

8.0 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: 2023 Page 76 of 96 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, 2023 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**

01/23/23

< 0.6

< 131

< 6

< 15

< 6

< 14

< 7

< 13

< 163 02/21/23

< 0.8

< 163

< 8

< 7

< 15

< 7

< 13

< 6

< 7

< 8

< 9

< 195 03/20/23

< 0.8

< 78

< 5

< 7

< 5

< 10

< 6

< 5

< 6

< 144 04/17/23

< 0.8

< 105

< 6

< 8

< 11

< 9

< 13

< 7

< 5

< 7

< 11

< 181 05/22/23

< 0.6

< 154

< 4

< 7

< 14

< 8

< 15

< 7

< 8

< 7

< 11

< 161 06/20/23

< 0.8

< 80

< 5

< 4

< 11

< 4

< 13

< 6

< 4

< 8

< 149 07/17/23

< 0.9

< 83

< 6

< 5

< 13

< 7

< 12

< 7

< 6

< 5

< 10

< 180 08/21/23

< 0.8

< 100

< 6

< 9

< 7

< 16

< 7

< 6

< 10

< 195 09/18/23

< 0.9

< 143

< 10

< 9

< 21

< 7

< 16

< 11

< 8

< 14

< 214 10/24/23

< 0.9

< 90

< 6

< 5

< 9

< 6

< 10

< 5

< 6

< 10

< 164 11/27/23

< 0.8

< 76

< 6

< 5

< 10

< 6

< 12

< 6

< 5

< 10

< 163 12/19/23

< 0.8

< 59

< 4

< 8

< 5

< 9

< 4

< 7

< 120 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: 2023 Page 77 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 22, Concentrations of Gamma Emitters in Sediment, 2023 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) 07/28/23

< 615 13,270 +/- 1,573

< 78

< 56

< 1,182

< 475 11/30/23

< 815 11,800 +/- 1,757

< 107

< 82

< 2,313

< 542 AVERAGE*

12,535 +/- 2,079 SA-ESS-05A1 07/31/23

< 518 8,620 +/- 1,225

< 82

< 74

< 1,429

< 354 12/05/23

< 552 9,065 +/- 1,261

< 79

< 72

< 1,639

< 429 AVERAGE*

8,843 +/- 629 SA-ESS-11A1 07/28/23

< 344 3,514 +/- 788

< 59

< 50

< 941 347

+/- 108 11/30/23

< 385 3,175 +/- 729

< 46

< 45

< 970

< 234 AVERAGE*

3,345 +/- 479 347

+/- 108 SA-ESS-15A1 07/28/23

< 387 5,113 +/- 1,032

< 69

< 52

< 1,169 461 +/- 104 11/30/23

< 518 7,702 +/- 1,385

< 89

< 67

< 1,449 643 +/- 174 AVERAGE*

6,408 +/- 3,661 552 +/- 257 SA-ESS-15A2 (a)

(a)

AVERAGE*

SA-ESS-07E1 07/28/23

< 512 8,412 +/- 1,242

< 72

< 67

< 1,512

< 402 11/30/23

< 431 11,540 +/- 1,149

< 67

< 46

< 1,038 690

+/- 133 AVERAGE*

9,976 +/- 4,424 690 +/- 133 SA-ESS-16F1 07/28/23

< 400 6,177 +/- 1,176

< 67

< 58

< 1,182 498 +/- 131 11/30/23

< 744 16,970 +/- 1,806

< 112

< 94 2,644 +/- 1,676 989

+/- 182 AVERAGE*

11,574 +/- 15,264 2,644 +/- 1,676 743 +/- 168 ALL INDICATOR AVERAGE 8,029 +/- 8,160 2,644 +/- 1,676 605 +/- 451 (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: 2023 Page 78 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2023 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) 01/02/23 01/03/23 0.7 993

+/-

180 9

9 11 188 02/05/23 02/06/23 0.4 1,316

+/-

197 9

6 13 156 03/05/23 03/06/23 0.5 1,593

+/-

136 6

4 7

118 04/02/23 04/03/23 0.9 1,202

+/-

168 6

7 9

168 04/16/23 04/17/23 0.8 1,628

+/-

166 9

8 8

206 05/08/23 05/09/23 0.9 837

+/-

123 7

7 12 187 05/21/23 05/22/23 0.9 1,579

+/-

180 6

7 10 188 06/04/23 06/05/23 0.8 1,634

+/-

227 8

7 8

159 06/19/23 06/20/23 0.9 1,391

+/-

155 8

7 10 175 07/02/23 07/03/23 0.9 1,266

+/-

160 6

5 9

153 07/16/23 07/17/23 0.9 1,173

+/-

174 9

8 10 173 08/06/23 08/07/23 0.9 1,055

+/-

121 4

5 9

130 08/20/23 08/21/23 0.9 1,039

+/-

176 8

8 12 192 09/10/23 09/11/23 0.8 1,341

+/-

159 8

8 9

190 09/17/23 09/18/23 0.9 1,257

+/-

165 7

8 8

147 10/02/23 10/03/23 0.8 1,194

+/-

205 7

8 14 155 10/23/23 10/24/23 0.9 916

+/-

132 7

6 8

124 11/05/23 11/06/23 0.7 1,304

+/-

173 9

8 12 221 11/26/23 11/27/23 0.9 935

+/-

153 10 9

11 233 12/10/23 12/11/23 0.9 1,467

+/-

191 10 9

10 166 AVERAGE*

1,256

+/-

490 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 79 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2023 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 01/02/23 01/03/23 0.7 1,220

+/-

150 7

8 9

194 02/05/23 02/06/23 0.6 1,845

+/-

236 9

11 14 175 03/05/23 03/06/23 0.5 1,261

+/-

137 6

6 8

118 04/02/23 04/03/23 0.4 1,151

+/-

191 7

7 9

153 04/16/23 04/17/23 0.9 1,361

+/-

206 8

8 12 180 05/08/23 05/09/23 0.9 1,098

+/-

191 10 9

12 159 05/21/23 05/22/23 1.0 1,552

+/-

196 8

9 9

142 06/04/23 06/05/23 0.8 1,494

+/-

205 6

8 10 170 06/19/23 06/20/23 0.8 1,365

+/-

173 7

7 10 156 07/02/23 07/03/23 0.7 1,511

+/-

166 7

6 12 143 07/16/23 07/17/23 1.0 1,381

+/-

179 5

7 5

150 08/06/23 08/07/23 0.8 1,019

+/-

136 4

8 8

124 08/20/23 08/21/23 0.8 1,354

+/-

182 9

8 12 184 09/10/23 09/11/23 0.9 1,508

+/-

201 9

8 13 166 09/17/23 09/18/23 0.9 1,372

+/-

168 9

7 14 156 10/02/23 10/03/23 0.7 1,494

+/-

214 8

8 12 170 10/23/23 10/24/23 1.0 1,255

+/-

139 7

5 8

153 11/05/23 11/06/23 0.9 1,339

+/-

145 6

6 7

142 11/26/23 11/27/23 0.9 1,414

+/-

209 10 8

11 229 12/10/23 12/11/23 0.8 1,209

+/-

191 10 9

8 169 AVERAGE*

1,360

+/-

370 I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 80 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 23, Concentrations of Iodine-131 and Gamma Emitters in Milk, 2023 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 01/02/23 01/03/23 0.7 1,051

+/-

172 9

8 8

168 02/05/23 02/06/23 0.7 1,552

+/-

203 9

6 8

164 03/05/23 03/06/23 0.6 1,411

+/-

134 6

6 7

107 04/02/23 04/03/23 0.4 1,235

+/-

176 9

9 10 203 04/16/23 04/17/23 0.9 1,762

+/-

207 9

9 10 237 05/08/23 05/09/23 0.9 1,427

+/-

189 6

6 12 186 05/21/23 05/22/23 0.8 1,582

+/-

170 8

6 9

166 06/04/23 06/05/23 0.8 1,940

+/-

230 7

9 6

196 06/19/23 06/20/23 0.8 1,676

+/-

199 8

6 7

142 07/02/23 07/03/23 0.7 1,197

+/-

166 8

6 12 149 07/16/23 07/17/23 0.9 1,285

+/-

175 6

9 6

173 08/06/23 08/07/23 0.9 1,086

+/-

108 5

4 7

116 08/20/23 08/21/23 0.8 1,268

+/-

190 12 8

13 168 09/10/23 09/11/23 0.7 1,279

+/-

190 8

8 14 169 09/17/23 09/18/23 1.0 1,369

+/-

152 7

7 10 165 10/02/23 10/03/23 0.9 1,209

+/-

202 10 9

9 185 10/23/23 10/24/23 0.9 1,086

+/-

127 6

6 6

121 11/05/23 11/06/23 0.6 1,409

+/-

161 7

6 10 183 11/26/23 11/27/23 0.8 1,420

+/-

164 8

8 13 205 12/10/23 12/11/23 0.8 1,273

+/-

184 9

8 9

224 AVERAGE*

1,376

+/-

446 ALL INDICATOR AVERAGE*

1,368

+/-

415 (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: 2023 Page 81 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 24, Concentrations of Gamma Emitters in Edible Fish, 2023 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) 04/20/23 2,863

+/-

1,049

< 41

< 58

< 110

< 64

< 113

< 57

< 46

< 954 04/20/23 3,230

+/-

1,156

< 74

< 66

< 141

< 70

< 141

< 75

< 77

< 1,584 10/02/23 4,195

+/-

1,001

< 78

< 94

< 249

< 69

< 165

< 82

< 79

< 1,396 AVERAGE*

3,429

+/-

1,376 SA-ESF-11A1 04/20/23 3,542

+/-

949

< 58

< 46

< 114

< 62

< 114

< 54

< 57

< 1,059 10/25/23 3,684

+/-

1,164

< 56

< 67

< 150

< 50

< 194

< 73

< 69

< 1,205 AVERAGE*

3,613

+/-

201 SA-ESF-07E1 04/20/23 3,835

+/-

1,219

< 61

< 58

< 102

< 72

< 128

< 68

< 60

< 1,238 04/20/23 3,272

+/-

915

< 60

< 85

< 67

< 123

< 43

< 45

< 1,075 10/25/23 4,273

+/-

1,359

< 92

< 94

< 198

< 80

< 208

< 91

< 98

< 1,938 AVERAGE*

3,793

+/-

1,004 ALL INDICATOR AVERAGE*

3,721

+/-

743 (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: 2023 Page 82 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 25, Concentrations of Gamma Emitters in Blue Crabs, 2023 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) 07/31/23 2,161

+/-

1,187 72 90 152 71 157 74 76 1,981 10/02/23 2,896

+/-

775 49 49 84 64 111 70 55 1,405 AVERAGE*

2,529

+/-

1,039 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 07/31/23 1,995

+/-

776 55 63 149 67 120 39 53 1,199 10/02/23 3,109

+/-

837 54 47 114 60 111 45 46 1,076 AVERAGE*

2,552

+/-

1,575 (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: 2023 Page 83 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 26, Concentrations of Gamma Emitters in Broadleaf Vegetation (FPL), 2023 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 06/29/23 Cabbage 145 1,844

+/-

429 27 19 21 445 67 SA-FPL-03H5 06/29/23 Cabbage 115 1,429

+/-

310 17 15 10 240 64 SA-FPL-06S1 07/31/23 Cabbage 346 3,931

+/-

716 36 39 36 659 123 SA-FPL-06S1 07/31/23 Lamb's Ear 1,635

+/-

412 5,855

+/-

926 44 52 37 771 134 SA-FPL-16S1 07/31/23 Lamb's Ear 1,895

+/-

470 7,755

+/-

1,010 51 41 42 827 148 SA-FPL-16S1 08/31/23 Lamb's Ear 2,852

+/-

298 11,750

+/-

800 40 29 32 626 122 SA-FPL-10D1 (C) 07/27/23 Lamb's Ear 2,183

+/-

397 5,454

+/-

756 42 32 30 626 122 SA-FPL-10D1 (C) 08/31/23 Lamb's Ear 1,309

+/-

277 8,426

+/-

925 42 39 38 899 150 CONTROL AVERAGE*

1,746

+/-

277 6,940

+/-

4,203 ALL INDICATOR AVERAGE*

2,127 +/-

1,282 5,427

+/-

7,830 (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: 2023 Page 84 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 27, Concentrations of Gamma Emitters in Vegetables (FPV), 2023 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**

05/03/23 Asparagus 193 2,141

+/-

384 33 22 20 541 89 SA-FPV-03F8**

06/29/23 Peaches 144 1,184

+/-

278 32 19 15 432 68 SA-FPV-15F4**

07/27/23 Corn 214 2,562

+/-

491 25 18 22 505 103 SA-FPV-15F4**

08/31/23 Tomatoes 72 1,852

+/-

221 11 7

7 145 30 SA-FPV-01G1**

05/03/23 Asparagus 260 2,644

+/-

572 41 32 32 726 118 SA-FPV-01G1**

06/29/23 Tomatoes 125 1,313

+/-

267 22 17 14 342 55 SA-FPV-01G1**

06/29/23 Corn 211 2,857

+/-

574 42 39 26 762 140 SA-FPV-01G1**

07/20/23 Peppers 147 1,614

+/-

324 21 16 20 510 83 SA-FPV-03H5**

05/03/23 Asparagus 166 2,701

+/-

573 36 27 24 541 98 SA-FPV-03H5**

06/29/23 Peaches 224 1,317

+/-

375 42 27 26 572 102 SA-FPV-03H5**

06/29/23 Tomatoes 123 1,422

+/-

262 24 15 17 334 59 SA-FPV-03H5**

06/29/23 Corn 291 1,874

+/-

582 40 34 23 584 111 SA-FPV-03H5**

07/20/23 Peppers 206 1,430

+/-

392 25 26 25 608 92 AVERAGE*

1,916

+/-

1,202

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: 2023 Page 85 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 28, Concentrations of Gamma Emitters in Fodder Crops, 2023 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**

11/27/23 Silage 122 5,943

+/-

410 15 15 14 267 60 SA-VGT-14F4**

11/27/23 Silage 125

+/-

82 1,834

+/-

199 16 13 14 239 48 SA-VGT-02G3**

11/27/23 Silage 284

+/-

66 1,943

+/-

192 10 8

8 214 27 AVERAGE*

205

+/-

224 3,240

+/-

4,683

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: 2023 Page 86 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Data Table Table 29, Concentrations of Gamma Emitters in Game, 2023 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-03E1**

12/20/23 Muskrat 115 3,328

+/-

298 26 16 14 SA-GAM-13E3**

03/04/23 Muskrat 114 2,972

+/-

317 19 15 12 ALL INDICATOR AVERAGE*

3,150

+/-

503

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: 2023 Page 87 of 96 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 20: 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: 2023 Page 88 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

, Cross heck Intercomparison Program I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 89 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- 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 2023. The Laboratorys intercomparison program results for 2023 are summarized below.

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

A.

Analytics Evaluation Criteria Analytics evaluation report provides a ratio of TBEs result and Analytics known value.

Since flag values are not assigned by Analytics, TBE evaluates the reported ratios based on internal QC requirements based on the DOE MAPEP criteria.

B.

ERA Evaluation Criteria ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. ERAs acceptance limits are established per the 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.

C.

DOE Evaluation Criteria MAPEPs evaluation report provides an acceptance range with associated flag values.

MAPEP defines three levels of performance:

Acceptable (flag = A) - result within +/- 20% of the reference value Acceptable with Warning (flag = W) - result falls in the +/- 20% to +/- 30% of the reference value Not Acceptable (flag = N) - bias is greater than 30% of the reference value Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not always resemble typical environmental samples obtained at commercial nuclear power facilities.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 90 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program For the TBE laboratory, 124 out of 131 analyses performed met the specified acceptance criteria. Seven analyses did not meet the specified acceptance criteria and were addressed through the TBE Corrective Action Program. A summary is found below:

1.

The MAPEP February 2023 Soil Ni-63 result was evaluated as Not Acceptable. TBEs reported value was 294 Bq/kg and the known result was 1130 Bq/kg (range 791 -

1469). The sample was reprepped by a different (senior) lab technician with results of 1120 & 1250 Bq. It was determined that there was a difference between the two techs during the sample prep (technique) and the procedure was revised to reflect these differences including using a specific aliquot amount. (NCR 23-08).

2.

The MAPEP February 2023 vegetation Sr-90 result was evaluated as Not Acceptable.

The reported value was 0.05 Bq (not detected) and the known result was a false positive. This was considered to be a statistical failure because TBEs reported result with 3 times the uncertainty resulted in a slightly positive net result (0.03194 Bq/kg).

The reported result was significantly below TBEs average detection limit for vegetation samples. (NCR 23-09)

3.

The ERA RAD April 2023 water Ba-133 result was evaluated as Not Acceptable. The reported value was 26.0 pCi/L and the known was 22.3 (acceptance range 17.1 - 25.8 pCi) or 117% of the known (acceptable for TBE QC). The sample was used as the workgroup duplicate with a result of 25.4 (114%). The sample had also been counted on a different detector with a result of 21.9 (98%). The was TBEs first failure for Ba-133. (NCR 23-10)

4.

The MAPEP August 2023 soil Fe-55 result was evaluated as Not Acceptable. The reported value was 346 Bq/kg and the known result was 1280 (acceptance range of 896-1664 Bq/kg). This was TBEs initial evaluation for Fe-55 in soils. The result was received at the end of December and the root cause is under investigation. No client samples were associated with this cross-check. (CAR 23-31)

5.

The Analytics September 2023 milk Sr-90 result was evaluated as Not Acceptable.

The reported result was 7.28 pCi/L and the known result was 12.8 (57% of known).

This sample was used as the workgroup duplicate and the carrier yields for both samples were 107% and 75%. The LCS recovery for the workgroup was at 106%.

The ERA drinking water Sr-90 cross check that was analyzed around the same time was acceptable at 108%. There was no explanation for the failure. This is the first low biased failure for Sr-90 milk. The last failure (high) was in 2016. (NCR 23-24)

6.

The ERA RAD October 2023 water Gross Alpha result was evaluated as Not Acceptable. The reported result was 53.2 pCi/L and the known result was 70.6 (acceptable range of 54.0 - 87.2 pCi/L). The reported result was the workgroup duplicate and was within 75% of the known value (within TBE QC range). The original result was 63.3 pCi/L (90% of the known). Because the LCS result was biased slightly high, the decision was made to report the lower value. (NCR 23-20)

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 91 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program

7.

The ERA RAD October 2023 water I-131 result was evaluated as Not Acceptable. The reported value was 23.5 pCi/L and the known result was 29.7 (acceptable range of 25.8 - 33.6). The reported result was 79% of the known, which is within the acceptable TBE QC range. The workgroup was reviewed with no anomalies found. The LCS/LCSD results were 109% and 86.1%. The sample was not processed in a timely manner as per the ERA instructions which stated to analyze shortly after receipt due to the short half-life. Going forward, the QA &/or Lab Mgr. will ensure that this analysis is started sooner. (NCR 23-21)

The Inter-Laboratory Comparison Program provides evidence of in control counting systems and methods, and that the laboratories are producing accurate and reliable data. Additional detail can be found in Teledyne Brown Engineering Environmental Services, 4th Quarter 2023 Quality Assurance Report [12].

GEL Laboratories Summary of Results During 2023, 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 2023. Of the three hundred eight (308) total results, 96.8%

(298 of 308) 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 ninety-two (92) 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 92 analyses reported, 98.9% (91 out of 92) fell within the acceptance criteria.

Summary of Participation in the ERA MRaD PT Program The ERA MRaD program provided samples (MRAD-38 and MRAD-39) for one hundred forty-eight (148) individual environmental analyses reported. Of the 148 analyses reported, 98.6% (146 of the 148) fell within the PT providers acceptance criteria.

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 92 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program Summary of Participation in the MAPEP Monitoring Program MAPEP Series 48 was analyzed by the laboratory. Of the sixty-eight (68) analyses reported, 97.1% (66 out of 68) fell within the PT providers acceptance criteria.

Summary of Participation in the ERA PT Program The ERA program provided samples (RAD-132, RAD-133 and RAD-134) for forty-six (46) individual environmental analyses. Of the 46 analyses reported, 86.9% (38 of 46)

All corrective actions for unacceptable PTs are summarized in Table below.

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 detail can be found in the GEL Laboratories, 2023 Annual Quality Assurance Report

[13].

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 93 of 96 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 9 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 9, TBE vs GEL Gross Beta I

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Gross Beta 7.00E-02 I

I 6.00E-02 I

+

5.00E-02 4.00E-02 3.00E-02 2.00E-02 l.OOE-02 O.OOE+OO 12/25/2022 2/13/2023 4/4/2023 5/24/2023 7/13/2023 9/1/2023 10/21/2023 12/10/2023

--TBE Activity -- GEL Activity

Annual Radiological Environmental Operating Report YEAR: 2023 Page 94 of 96 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 2 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 L100240-1 4/3/2023 Be-7 3.46E-02 4.85E-03 7

620171 Be-7 6.71E-02 1.94 0.50 2.00 YES L101617-1 7/3/2023 Be-7 4.70E-02 5.99E-03 8

631580 Be-7 6.75E-02 1.44 0.50 2.00 YES L102669-1 10/3/2023 Be-7 5.15E-02 5.70E-03 9

643139 Be-7 6.46E-02 1.26 0.60 1.66 YES L-103776-1 1/2/2024 Be-7 4.20E-02 4.94E-03 9

653231 Be-7 5.52E-02 1.31 0.60 1.66 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 L99579-2 3/21/23 K-40

<58.4 3.34E+01 3

616602 K-40 95.1 L101195-2 6/25/23 K-40

<122.1 2.98E+01 4

627642 K-40 105.0 L102566-2 9/20/23 K-40 60.5 1.74E+01 5

639074 K-40 79.0 0.77 0.50 2.00 YES L103704-2 12/21/23 K-40 63.5 1.91E+01 3

650172 K-40 59.2 1.07 0.40 2.25 YES No comparison result <MDL 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 L99027-3 1/3/2023 K-40 1.05E+03 8.60E+01 12 606253 K-40 1.01E+03 1.04 0.60 1.66 YES L99403-3 2/6/2023 K-40 1.55E+03 1.02E+02 15 610332 K-40 2.33E+03 0.67 0.60 1.66 YES L99737-3 3/6/2023 K-40 1.41E+03 6.70E+01 21 613706 K-40 7.83E+02 1.80 0.75 1.33 NO L100064-3 4/3/2023 K-40 1.24E+03 8.82E+01 14 617199 K-40 1.60E+03 0.77 0.60 1.66 YES L100566-3 5/9/2023 K-40 1.43E+03 9.47E+01 15 621965 K-40 1.42E+03 1.00 0.60 1.66 YES L100921-3 6/5/2023 K-40 1.94E+03 1.15E+02 17 625176 K-40 1.51E+03 1.28 0.75 1.33 YES L101275-3 7/3/2023 K-40 1.20E+03 8.30E+01 14 628424 K-40 1.12E+03 1.07 0.60 1.66 YES L101913-3 8/7/2023 K-40 1.09E+03 5.41E+01 20 632846 K-40 1.11E+03 0.98 0.75 1.33 YES L102356-3 9/11/2023 K-40 1.34E+03 7.94E+01 17 637116 K-40 1.40E+03 0.96 0.75 1.33 YES L102687-3 10/3/2023 K-40 1.21E+03 1.01E+02 12 640322 K-40 1.25E+03 0.97 0.60 1.66 YES L103165-3 11/6/2023 K-40 1.41E+03 8.07E+01 17 644898 K-40 1.23E+03 1.15 0.75 1.33 YES L103569-3 12/11/2023 K-40 1.27E+03 9.21E+01 14 648829 K-40 1.37E+03 0.93 0.60 1.66 YES MILK TBE GEL TBE / GEL Comparison Acceptance Critera I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 95 of 96 Company: PSEG Nuclear LLC Plant: Salem and Hope Creek Generating Stations

- Cross Check Program Sediment Naturally occurring K-40 was detected in the sample by both GEL and TBE. All results were in agreement.

Broad Leaf Vegetation Naturally occurring K-40 was detected by GEL and TBE in all duplicate samples analyzed. All results were in agreement.

CRS #

Collection Date Nuclide Decay Corrected Activity 1 Sigma Error Resolution CRS #

Nuclide Decay Corrected Activity Ratio Agreement L101758-1 7/28/23 K-40 3.51E+03 3.94E+02 9

631922 K-40 3.94E+03 0.89 0.60 1.66 YES SEDIMENT 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 L101528-1 7/20/23 K-40 1614 1.62E+02 10 630065 K-40 1.66E+03 0.97 0.60 1.66 YES L101528-2 7/20/23 K-40 1430 1.96E+02 7

630065 K-40 1.55E+03 0.92 0.50 2.00 YES L101654-1 7/27/23 K-40 2562 2.46E+02 10 631226 K-40 1.68E+03 1.53 0.60 1.66 YES Acceptance Critera VEGETATION TBE GEL TBE / GEL Comparison I

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Annual Radiological Environmental Operating Report YEAR: 2023 Page 96 of 96 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 2023. There were no findings. Additional detail can be found in the Environmental Dosimetry Company, 2023 Annual Quality Assurance Status Report. [14]

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LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)

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