IR 05000272/2025002

Integrated Inspection Report 05000272/2025002 and 05000311/2025002

ML25203A002
Person / Time
Site:	Salem
Issue date:	07/22/2025
From:	Nicole Warnek Division of Operating Reactors
To:	Mcfeaters C Public Service Enterprise Group
References
IR 2025002
Download: ML25203A002 (1)

Text

July 22, 2025

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000272/2025002 AND 05000311/2025002

Dear Charles McFeaters:

On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2. On July 9, 2025, the NRC inspectors discussed the results of this inspection with David Sharbaugh, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

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

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:

05000272/2025002 and 05000311/2025002

Licensee:

PSEG Nuclear, LLC

Facility:

Salem Nuclear Generating Station, Units 1 and 2

Location:

Hancocks Bridge, NJ

Inspection Dates:

April 1, 2025 to June 30, 2025

Inspectors:

P. Finney, Senior Resident Inspector

J. Kulp, Senior Reactor Inspector

J. Patel, Senior Resident Inspector

S. Quiroga, Resident Inspector

R. Rolph, Senior Health Physicist

L. Sinclair, Operations Engineer

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.

List of Findings and Violations

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

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at approximately 91 percent rated thermal power in a coastdown in preparation for planned refueling outage 30 (S1R30). The unit shutdown and entered S1R30 on April 13, 2025. On May 30, 2025, operators commenced a reactor startup, and the unit returned to rated thermal power on June 1, 2025. Unit 1 operated at or near rated thermal power for the remainder of the 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

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

(1) Unit 1, 1B vital instrument bus during 1A vital instrument bus powered from a temporary non-safety-related power source, April 18, 2025

(2) Unit 1, 12 service water (SW) train during 11 SW train drained for maintenance, April 18, 2025

(3) Unit 2, component cooling water (CCW) system following in-service testing of 23 CCW pump, May 14, 2025

(4) Unit 1, emergency core cooling subsystems containment sump during outage activities, May 19, 2025

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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, SW intake structure, pre-fire plan FP-SA-2651, April 25, 2025

(2) Unit 1, fuel handling building, pre-fire plan FP-SA-1201, April 29, 2025

(3) Unit 1, 12 residual heat removal pump and heat exchanger room, pre-file plan FP-SA-1511, May 24, 2025

(4) Unit 1, reactor coolant pump oil collection system during refueling outage, May 28, 2025

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated the readiness and performance of:

(1) Unit 1, 11 component cooling heat exchanger, April 18-24, 2025

===71111.08P - Inservice Inspection Activities (PWR)

The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 1 during refueling outage S1R30 from April 14, 2025, to May 29, 2025.

PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Ultrasonic Examination

• Ultrasonic Examination of Residual Heat Removal System Pipe to Elbow Weld 14-RH-1111.10(S1-I-UT-25-004)

• Ultrasonic Examination of Pressurizer Relief System Elbow to Pipe Weld 6-PR-1105-4 (S1-I-UT-25-013)

• Ultrasonic Examination of Pressurizer Relief System Elbow to Pipe Weld 6-PR-1105-5 (S1-I-UT-25-014)

• Phased Array Ultrasonic Examination of Core Barrel Upper Girth Weld (18-9392332-000)

Visual Examination

• Visual Examination (EVT-1) of Upper Core Barrel Girth Weld (S1-I-VE-25-002)

• Post mitigation Visual Exam (VT-1) of Upper Core Barrel Girth Weld (S1-I-VT-25-087)

Condition Previously Accepted by Evaluation

===70223213, Unexpected Protruding Thermal Shield Support Block Bolt

Welding Activities

• Core Barrel Upper Girth Weld Indication Mitigation (80139028)

PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)===

The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

(1) Ultrasonic Examination of Reactor Vessel Head Control Rod Drive Mechanism Penetrations 1, 20, 23, 46, 56, 67, 73 (180-9392333-000)

PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:

(1)

• Boric Acid Corrosion Control - 1PS42 Leak and Corroded Tee (20991725)

• Boric Acid Corrosion Control - Leak: Dry White Med BA 12SJ173PC (20985303)

• Boric Acid Corrosion Control - Leak: Dry Discolor Excess BA Fitting 1LT935C (20985648)

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)

(1) The inspectors observed and evaluated Unit 1 licensed operator performance in the main control room during a plant shutdown for a refueling outage on April 12-13, 2025.

(2) The inspectors observed and evaluated Unit 1 licensed operator performance in the main control room during a plant startup from a refueling outage on May 30, 2025.

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

(1) The inspectors observed and evaluated licensed operator performance in the plants simulator during a licensed operator requalification examination on June 17, 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) Unit 1, 1SW199, 12 charging pump lube oil cooler control valve failed to open during 12 charging pump start, April 12, 2025 (Notification (NOTF) 20991376)

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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, 22 auxiliary feedwater train and protected equipment, April 10, 2025

(2) Unit 1, emergent work, main turbine valve troubleshooting, April 10-11, 2025

(3) Unit 2, fire risk assessment for 13 charging pump out of service, April 21-22, 2025

(4) Unit 1, elevated risk during scheduled refueling outage activities for spent fuel cooling, during the week of May 1, 2025

(5) Unit 1, elevated shutdown risk (Orange) due to lowered reactor coolant system inventory during scheduled reactor coolant system drain down to mid-loop for the fill and vent operation, May 24, 2025

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1) Unit 1, 1A emergency diesel generator due to fuel oil leak on 8R fuel pump, April 2, 2025 (NOTF 20988907)

(2) Unit 2, 23 auxiliary feedwater pump inboard and outboard bearing oil viscosity exceeding fault range, April 11, 2025 (NOTF 20991348)

(3) Unit 2, 21 steam generator level channel II restored to operable, June 14, 2025 (NOTF 20994751)

(4) Unit 1, PT506 turbine 1st stage impulse pressure transmitter out of channel check, April 9, 2025 (NOTF 20991258)

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) Engineering change package 80139028, "Unit 1 Core Barrel Upper Girth Weld Indication Mitigation," week of May 19, 2025

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated Unit 1 refueling outage S1R30 from April 12 to June 30, 2025.

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 1, 1A emergency diesel generator following fuel oil leak repair, April 2, 2025 (Work Orders (WOs) 60163382 and 50246356)

(2) Unit 1, 11SW122, 11 component cooling heat exchanger service water inlet control valve, following internal inspection and repairs, April 30, 2025 (WO 30370485)

(3) Unit 1, 1CV55, centrifugal charging pump flow control valve, following drifting close, on May 13, 2025 (WO 60158118)

(4) Unit 1, 11 charging pump following mechanical seal replacement due to leak, May 20, 2025 (WO 60159663)

(5) Unit 1, 11 auxiliary feedwater pump following motor replacement, May 30, 2025 (WO 60155218)

Surveillance Testing (IP Section 03.01) (2 Samples)

(1) Unit 1, S1.IC-SC.RCP-0020, 0021, and 0022, "Pressurizer Level Protection Channels 1, 2, and 3 Sensors Calibration," April 16, 2025 (WOs 50247123,

===50247017, 50246978)

(2) Unit 1, S1.OP-ST.SS-0004, "SEC Mode Ops Testing 1C Vital Bus," April 28, 2025 (WO 50223753)

Containment Isolation Valve (CIV) Testing (IP Section 03.01)===

(1) Unit 1, S1.OP-LR.VC-0003, "Type C Leak Rate Test 1VC5," April 25, 2025 (WO 30335347)

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels, identifies the concentrations and quantities of radioactive materials, and assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Radiological control technicians and workers transferred make-up pump parts from Salem to Hope Creek. During the transfer, the containment package was torn at Hope Creek and contamination spilled on the floor. After the package was secured inside the contamination area, a survey identified the extent of the contamination spill, and it was cleaned up prior to the work group exiting the Hope Creek area.

(2) Workers exiting the radiologically controlled area and licensee surveys of potentially contaminated material leaving the radiologically controlled area at Unit 1 and 2 control point during a refueling outage in Unit 1.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Work on the Unit 1 reactor head

(2) Work under the Unit 1 reactor head

(3) Fill and vent of the residual heat removal system

(4) Spent fuel pool fuel placement verification

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas (VHRAs):

(1) Entrance to under the reactor vessel while thermocouples were parked under the reactor vessel (VHRA)

(2) Entrance to the fuel transfer tube area (VHRA)

(3) Area under the Unit 1 reactor vessel head, locked high radiation area, posted with red flashing lights

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.07 - Radiological Environmental Monitoring Program

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

(1)

(Partial)

The inspectors evaluated the implementation of the licensees radiological environmental monitoring program. Specifically, the inspectors observed fish and water sampling. The remaining samples will be observed in the third quarter of

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===

(1) Unit 1, April 1, 2024 through March 31, 2025

(2) Unit 2, April 1, 2024 through March 31, 2025

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1, April 1, 2024 through March 31, 2025

(2) Unit 2, April 1, 2024 through March 31, 2025

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1, April 1, 2024 through March 31, 2025

(2) Unit 2, April 1, 2024 through March 31, 2025

===71152S - Semiannual Trend Problem Identification and Resolution

Semiannual Trend Review (Section 03.02)===

(1) The inspectors reviewed the licensee's corrective action program for potential adverse trends that might be indicative of a more significant safety issue.

INSPECTION RESULTS

Observation: Semi-Annual Trend Review 71152S The inspectors performed a semi-annual review of site issues to identify trends that might indicate the existence of more significant safety concerns. As part of this review, the inspectors included repetitive or closely related issues documented by PSEG in their corrective action program database, trend reports, major equipment problem list, system health reports, and maintenance or corrective action program backlog. During the first half of 2025, PSEG documented several cognitive trends that included fire protection program issues (NOTFs 20991410, 20991388), challenges with the generation of notifications and operability screening by licensed operators (NOTFs 20993996, 20994733), and an adverse trend in effluent radiation monitoring system performance (NOTF 20993686).

Additionally, the inspectors reviewed the following equipment reliability and human performance trends:

Equipment Reliability Challenges:

1. Containment Fan Cooling Units: Multiple containment fan cooling units failed to start

at high speed due to the tripping of high-speed breakers (NOTFs 20988222, 20988656, 20993194, and 20994305). PSEG documented as an adverse trend in NOTFs 20988660 and 20994317.

2. Auxiliary Building Ventilation (ABV) System: 22 ABV supply fan tripped (NOTF

20995421). In the first quarter of 2025, the inspectors documented observations associated with the 21 ABV supply fan bearing failures (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25118A217).

Additionally, the inspectors noted that 21 ABV exhaust fan had tripped due to belt failure in November 2024 (NOTF 20979639, 20979359). These issues indicate an emerging trend in ABV system performance and challenges system reliability.

3. SW System: In the first quarter of 2025, inspectors observed SW valve failures

affecting emergency diesel generator reliability (ML25118A217). Additional component degradations noted during the first half of 2025 include:

a. 12 charging pump lube oil cooler control valve, 1SW199, failed to open during pump start (NOTF 20991376).

b. 23 SW pump strainer failed to rotate, rendering the pump inoperable (NOTFs 20984913 and 20991397).

c. PSEG identified degraded SW strainer supports (NOTFs 20992163 and 20993011).

d. PSEG identified decreasing biofouling margin on the 12A CCW heat exchanger (NOTF 20993045).

Human Performance Trends:

During the first half of 2025, inspectors observed a continued decline in Human Performance related to procedure use and adherence. This ongoing trend, first identified in the fourth quarter of 2024 (ML25042A384), was further evidenced during the Unit 1 refueling outage.

Specific examples included in NOTF 20994663:

1. Technicians failed to stop work upon encountering an unexpected condition while

performing core plate nozzle checks. This led to damage of a core plate S-pin, requiring its retrieval from the reactor, and the need for engineering justification to support continued operation. The event was attributed to the failure to apply Human Performance Tools as specified in procedure HU-AA-101.

2. During startup, a leak from the 12 reactor coolant pump seal return vent valve was

identified, attributed to an improperly assembled flanged joint caused by inadequate maintenance practices.

3. Pre-and post-weld activities for the 11BF22 main feedwater stop check valve were

not performed in accordance with PSEG standards, requiring additional engineering evaluation to support operability.

Based on the overall results of the semi-annual trend review, the inspectors determined that issues were appropriately evaluated by PSEG for potential trends and actions were taken or planned to address within the scope of the corrective action program.

The inspectors did not identify any findings or violations of more than minor significance.

EXIT MEETINGS AND DEBRIEFS

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

• On July 9, 2025, the inspectors presented the integrated inspection results to David Sharbaugh, Site Vice President, and other members of the licensee staff.

• On April 24, 2025, the inspectors presented the Radiological Hazard Assessment and Exposure Controls Inspection, 71124.01 inspection results to Richard DeSanctis, General Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Corrective Action

Documents

Resulting from

Inspection

20991692

Missed Narrative Entry

20993539

ECCS Sump Inspections

71111.05

Corrective Action

Documents

Resulting from

Inspection

20992476

Extinguisher Not on FP-SA-120-F1

20992639

FHB Area Observations

71111.08P Engineering

Evaluations

80139035-0030

Acceptance of WEC Letter PSE-RV010-TM-CG-000004

Salem Unit 1 Cycle 31 Safety Assessment

Revision 0

PSE-RV010-TM-

CG-000001

Salem Unit 1 Fall 2023 Outage - Disposition of As-Found

Conditions to Thermal Shield Supports and Justification for

Return to Service

Revision 0

PSE-RV010-TM-

CG-000004

Salem Unit 1 Fall 2023 Outage - Disposition of As-Found

Conditions to Thermal Shield Supports and Justification for

operating with open holes over the 1R30-1R31 operating

cycle

Revision 1

R-038-2501-00-

Technical Review Assessing Abnormal Water Chemistry

Conditions Event at Salem Unit 1 in January of 2025

Revision 0

NDE Reports

180-9392332-000

Salem Unit 1, 1R30 Automated Phased Array Core Barrel

Examination

Revision 000

180-9392333-000

Salem Unit 1, 1R30 RVCH Penetration Examination Report

Revision 000

S1-I-UT-25-013

S1-I-UT-25-013

UT Examination Elbow to Pipe (6-PR-1105-4)

S1-I-UT-25-014

UT Examination Elbow to Pipe (6-PR-1105-5)

71111.13

Corrective Action

Documents

Resulting from

Inspection

20992487

Protected Equipment Improvement

71124.01

Corrective Action

Documents

Resulting from

20992008

CFR 20.1101(c) Annual Assessment

04/22/2025

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Inspection