IR 05000272/2025003

Integrated Inspection Report 05000272/2025003 and 05000311/2025003

ML25356A001
Person / Time
Site:	Salem
Issue date:	12/22/2025
From:	Nicole Warnek Division of Operating Reactors
To:	Mcfeaters C Public Service Enterprise Group
References
IR 2025003
Download: ML25356A001 (0)

Text

December 22, 2025

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2025003 AND 05000311/2025003

Dear Charles McFeaters:

On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2. On November 18, 2025, the NRC inspectors discussed the results of this inspection with Jason Jennings, Director Regulatory Compliance, and other members of your staff. The results of this inspection are documented in the enclosed report.

Due to the temporary cessation of government operations, which commenced on October 1, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and made progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025, third quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, fourth quarter integrated inspection reports, which will be issued 45 days after the fourth quarter ends on December 31, 2025.

No NRC-identified or self-revealing findings were identified during this inspection.

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Salem Nuclear Generating Station, Units 1 and 2.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Nicole S. Warnek, Chief Projects Branch 3 Division of Operating Reactor Safety

Docket Nos. 05000272 and 05000311 License Nos. DPR-70 and DPR-75

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000272 and 05000311

License Numbers:

DPR-70 and DPR-75

Report Numbers:

05000272/2025003 and 05000311/2025003

Licensee:

PSEG Nuclear, LLC

Facility:

Salem Nuclear Generating Station, Units 1 and 2

Location:

Hancocks Bridge, NJ 08038

Inspection Dates:

July 1, 2025 to September 30, 2025

Inspectors:

J. Patel, Senior Resident Inspector

S. Quiroga, Resident Inspector

R. Rolph, Senior Health Physicist

N. Harmon, Health Physicist

Approved By:

Nicole S. Warnek, Chief

Projects Branch 3

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Salem Nuclear Generating Station,

Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

A licensee-identified non-cited violation is documented in report section: 71111.1

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 operated at or near rated thermal power for the entire inspection period.

Unit 2 operated at or near rated thermal power for the entire inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated the licensees readiness for seasonal extreme hot weather conditions during the week of July 7, 2025.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Units 1 and 2, diesel fuel oil storage and transfer system for underground fuel oil leak, August 7, 2025

(2) Unit 2, 115 volts alternating current system while 2D vital inverter is energized from its alternate power source, September 25 and 26, 2025

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Unit 2, auxiliary feedwater (AFW) pump rooms, pre-fire plan FP-SA-2543, July 7, 2025

(2) Unit 2, 460V switchgear rooms and corridors, pre-fire plan FP-SA-2541, September 12, 2025

(3) Unit 2, relay room, pre-fire plan FP-SA-2551, September 12, 2025

(4) Unit 1, electrical penetration area, pre-fire plan FP-SA-1546, September 18, 2025

(5) Unit 1, 4160 volt switchgear room, pre-fire plan FP-SA-1531, September 29, 2025

(6) Unit 2, charging pump and spray additive tank area, pre-fire plan FP-SA-2544, September 30, 2025

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operators in the plants simulator during a licensed operator requalification examination on July 15, 2025.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Units 1 and 2, containment fan cooling units, multiple failures to start in high speed, September 16, 2025

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 2, elevated risk during emergent work on 24BF19, steam generator feed water control valve leak and packing adjustment, July 22, 2025

(2) Unit 2, elevated risk (Yellow) during emergent work on 2A emergency diesel generator (EDG), July 29, 2025

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 1, predicted versus measured boron concentration input to shutdown margin calculation, July 11, 2025 (notification (NOTF) 20995508)

(2) Unit 1, pressurizer relief tank level rising trend and relief valve tailpipe elevated temperature indicating pressurizer overpressure relief valve seat leakage, July 14, 2025 (NOTF 20994256)

(3) Unit 2, containment air particulate detector radiation monitors loss of communication to main control room, July 16, 2025 (NOTF 20997289)

(4) Unit 1, plant barrier, service water (SW) chlorination pipe penetration degraded, flooding impact assessment in the 11, 12, and 13 SW pump room, July 24, 2025 (NOTF 20997928)

(5) Unit 2, steam generator pressure instrumentation due to degraded instrument line support structures, September 11, 2025 (NOTF 20999643)

(6) Unit 2, 22 SW nuclear header through wall leak, September 15, 2025 (NOTF 21001131)

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 1, review of change to diesel fuel oil transfer pump motor bearing type, July 9, 2025 (70240726)

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)

(1) Unit 2, 2A EDG following repairs to watt indicator circuit, July 30, 2025 (work order (WO) 60164482)

(2) Unit 2, 26 SW train following pump replacement, August 14, 2025 (WO 30385480)

(3) Unit 2, 2A EDG following preventive maintenance, during the week of August 25, 2025 (WOs 50256343, 50258354, 50259773)

(4) Unit 1, 12 AFW train following preventive maintenance, included relays replacement and AF21 valve work, September 3, 2025 (WOs 30303599, 30391575, 30391581)

(5) Unit 2, 2D vital inverter following blown fuse and circuit card replacement, September 23, 2025 (WO 60164866)

Surveillance Testing (IP Section 03.01) (3 Samples)

(1) Unit 1, S1.IC-ST.SSP-0008, "Solid State Protection System Train A Functional Test,"

August 25, 2025 (WO 50257730)

(2) Unit 2, S2.OP-ST.DG-0002, "2B Diesel Generator Surveillance Test," following air start motor solenoid valves replacement, September 3 and 4, 2025 (WO 50259881)

(3) Unit 1, S1.OP-ST.PZR-0002, "Inservice Testing Power Operated Relief Valve Block Valves," and S1.IC-FT.RCP-0019, "1PT457 Pressurizer Pressure Protection Channel III," September 9, 2025 (WOs 50258408 and 50259398)

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Unit 2, S2.OP-ST.AF-0001, "21 AFW pump IST," July 9, 2025 (WO 50257541)

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

The inspectors evaluated:

(1) The inspector evaluated a simulator scenario and the associated emergency classification on July 29,

71124.07 - Radiological Environmental Monitoring Program (REMP)

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program. Partial completed in second quarter and remaining part of sample completed in third quarter.

Groundwater Protection Initiative Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the groundwater protection initiative program to identify incomplete or discontinued program elements.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS07: High Pressure Injection Systems (IP Section 02.06)===

(1) Unit 1, July 1, 2024 through June 30, 2025

(2) Unit 2, July 1, 2024 through June 30, 2025

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1, July 1, 2024 through June 30, 2025

(2) Unit 2, July 1, 2024 through June 30, 2025

MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1, July 1, 2024 through June 30, 2025

(2) Unit 2, July 1, 2024 through June 30, 2025

===71152A - Annual Follow-Up Problem Identification and Resolution

Annual Follow-Up of Selected Issues (Section 03.03)===

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Unit 1, 12 reactor coolant pump #1 seal leak-off line leakage during startup from

1R30 refueling outage (2)

Multiple initial license candidates failed the NRC written exam for Salem initial licensed operator training class 23-01

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71111.15 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Title 10 of the Code of Federal Regulations Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, states, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, and drawings and shall be accomplished with these instructions, procedures, or drawings. PSEG Procedure MA-AA-716-006, Control of Lubricants Program, requires that prior to lubricant application, verify the correct lubricant is specified in the WO. Contrary to these requirements, on October 23, 2024, PSEG performed quality-related maintenance on the 23 AFW pump inboard and outboard bearing oil bubblers using a WO that did not specify appropriate instructions for using the correct type of lubricant. As a result, an incorrect lubricant, Exxon Teresstic 46, with a higher viscosity than the type specified by the original equipment manufacturer and approved under PSEGs lubricant control program, was used to refill the oil bubblers. This introduced potential long-term reliability concerns regarding the performance of the 23 AFW pump. PSEG subsequently performed a "bleed and feed" and flushed the system with the correct oil type, Mobil DTE 732. On April 25, 2025, follow-up oil analysis confirmed that the oil viscosity had returned to the normal range.

Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power.

Using Exhibit 2, Mitigating Systems Screening Questions, the finding screened to very low safety significance (Green), by answering No to all the questions in Exhibit 2A. Specifically, PSEG conducted two in-service tests with Exxon Teresstic 46 oil in the system between November 2024 and April 2025. The results of these tests did not reveal any adverse conditions or degradation in pump performance. Furthermore, oil sample analyses showing elevated viscosity did not detect the presence of wear metal particles, indicating that the pump bearings had not experienced degradation. Based on this information, although the issue had the potential to impact pump performance and long-term reliability, it was reasonable to conclude that the pump had not lost its probabilistic risk assessment functionality.

Corrective Action References: NOTFs 20977868, 20991348, 70240458 Observation: Reactor Coolant Pump (RCP) #1 Seal Leak-Off Line Leakage During Reactor Startup 71152A The inspectors evaluated PSEGs corrective actions associated with Unit 1 #12 reactor coolant pump (RCP), seal #1 leak-off line leakage that occurred during startup following the S1R30 refueling outage (NOTF 20993714). PSEG completed apparent cause evaluation (ACE) 70241210 to assess the failure and to develop corrective actions addressing both the failure and its underlying causes.

PSEG determined that the direct cause of the flange leak was improper gasket installation.

The gasket was not verified to be properly seated in the spigot fit during flange assembly and torquing process. As a result, the gasket shifted and became pinched between the flanges, preventing the gasket seating surfaces from mating correctly. This caused an inadequate internal seal and resulted in the observed leakage. The event occurred during reactor startup while the unit was in Mode 5 (cold shutdown), and leakage remained below 1 gpm, within the technical specification limit for unidentified leakage. PSEGs ACE identified contributing causes attributed to failures to follow existing processes and procedures, including:

1. A human performance issue in which the reactor services supervisor did not meet the

work order walkdown and task-ready requirements in accordance with PSEG procedure MA-AA-1002, Work Management Responsibilities for Maintenance.

2. The seal leak-off line piping interference installation activity was not screened as non-

recoverable in accordance with OP-AA-107, Integrated Risk Management, for risk screening. Proper screening and classification would have designated the task as High Risk and required a Risk Management Plan with associated mitigating actions.

3. Maintenance procedure SC.MD-CM.RC-0001, Reactor Coolant Pump Seal

Disassembly Inspection, Repair and Assembly, did not specify using Silicon 111 or Dow Corning high-vacuum grease during flange assembly to ensure proper gasket seating. Technicians knew this practice from operating experience but did not apply it since it was not in the procedure.

The inspectors reviewed PSEGs evaluation, WO documentation, and both planned and completed corrective actions, as applicable, and did not identify any performance deficiency of more than minor significance. Specifically, the unit was in cold shutdown, and leakage was below the technical specification limit.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified that no proprietary information was retained or documented in this report.

• On November 18, 2025, the inspectors presented the integrated inspection results to Jason Jennings, Director Regulatory Compliance, and other members of the licensee staff.

• On July 17, 2025, the inspectors presented the REMP Exit/Debrief for Hope Creek and Salem inspection results to Eric Larson, Hope Creek Site Vice President, and David Sharbaugh, Salem Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Corrective Action

Documents

20999357

Underground fuel oil leak

21001319

2D VIB fuse F101 Blown

71111.05

Corrective Action

Documents

Resulting from

Inspection

21002694

Revise combustible loading calculation

71111.13

Corrective Action

Documents

Resulting from

Inspection

NOTF 20998612

Incorrect Protected Equipment Posted

71111.18

Corrective Action

Documents

NOTF 20992309

Discrepancies in motors

71152A

Corrective Action

Documents

20987406

Salem ILOT 23-1 NRC Exam Failures

20988020

NRC Exam Failures Salem ILOT 23-1

20993714

1. 1 seal leak off flange leaking PINV

Miscellaneous

ACE 70239625

Salem 23-01 ILOT Class NRC Exam Failure

ACE 70241210

RCP #1 Seal Leak-Off Line Leakage Following S1R30