ML25247A022
| ML25247A022 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/04/2025 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Mcfeaters C Public Service Enterprise Group |
| References | |
| IR 2025011 | |
| Download: ML25247A022 (1) | |
Text
September 4, 2025 Charles McFeaters President and Chief Nuclear Officer PSEG Nuclear, LLC P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - LICENSE RENEWAL PHASE 4 INSPECTION REPORT 05000272/2025011 AND 05000311/2025011
Dear Charles McFeaters:
On August 21, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Salem Nuclear Generating Station, Units 1 and 2 and 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, Erin E. Carfang, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket Nos. 05000272 and 05000311 License Nos. DPR-70 and DPR-75
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV ERIN CARFANG Digitally signed by ERIN CARFANG Date: 2025.09.04 11:40:28 -04'00'
ML25247A022 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS NAME PCataldo ECarfang DATE 9/4/2025 9/3/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000272 and 05000311 License Numbers:
DPR-70 and DPR-75 Report Numbers:
05000272/2025011 and 05000311/2025011 Enterprise Identifier: I-2025-011-0010 Licensee:
Salem Nuclear Generating Station, Units 1 and 2 Location:
Hancocks Bridge, NJ Inspection Dates:
August 11, 2025 to August 21, 2025 Inspectors:
P. Cataldo, Senior Reactor Inspector M. Hardgrove, Senior Project Engineer D. McHugh, Reactor Inspector Approved By:
Erin E. Carfang, Chief Engineering Branch 1 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a License Renewal Phase 4 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.
3 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 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.
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 71003 - Post-Approval Site Inspection for License Renewal The team conducted a Phase 4 license renewal inspection as outlined in NRC IP 71003. The team selected six aging management programs for evaluation based on risk insights and programs that were enhanced or new under the renewed operating license for each unit. The team also considered for selection those programs with monitoring results that were performed for the first time or those that identified examination or test results not experienced in the past.
For the aging management programs selected, the team reviewed records, interviewed plant staff, and conducted plant walk downs to evaluate whether aging management program elements were being implemented in accordance with NRC requirements. The team evaluated the following elements of the aging management programs: scope, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, corrective actions, confirmation process, administrative controls, and operating experience.
The following aging management programs were evaluated by the team:
Post-Approval Site Inspection for License Renewal (6 Samples)
(1)
(B.2.1.22) Buried Piping Program (2)
(B.2.1.24) External Surfaces Monitoring Program (3)
(B.2.1.26) Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program (4)
(B.2.1.28) ASME XI, Subsection IWE (5)
(B.2.1.34) Inspection of Water-Cooled Structures Associated with Nuclear Power Plants (6)
(B.2.1.38) Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program INSPECTION RESULTS No findings were identified.
4 EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On August 21, 2025, the inspectors presented the License Renewal Phase 4 inspection results to David Sharbaugh, Site Vice President, and other members of the licensee staff.
5 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71003 Corrective Action Documents Resulting from Inspection NOTF 20999450 LRP4 NUCMs Do Not Address Notifications NOTF 20999508 LRP4 SSPC-VIS-2 Reference in OU-AA-335-018 NOTF 20999514 LRP2 NRC Ineffective SWIS LR Inspections NOTF 20999519 LRP2 NRC Ineffective Chilled Water System Inspections NOTF 20999599 LRP4 NRC SWYD Vault PCR NOTF 20999601 LR-S 11 SW Pump Bay Pit Concrete Slab Repair NOTF 20999629 Turtle Observed at Salem Circ Water NOTF 20999733 LRP4 NRC SRB Feed Standing Water 1BDE35 NOTF 20999734 LRP4 NRC SRB Feed Standing Water 1BDE36 NOTF 20999735 LRP4 NRC SRB Feed Standing Water 1BDE37 NOTF 20999736 LRP4 NRC SRB Feed Standing Water 1BDE36 NOTF 20999736 LRP4 NRC SRB Feed Standing Water 1BDE38 NOTF 20999737 LRP4 NRC SRB Feed Standing Water 1BDE39 NOTF 20999738 LRP4 NRC SRB Feed Standing Water 1BDE40 NOTF 20999739 LRP4 NRC SRB Feed Standing Water 1BDE41 NOTF 20999740 LRP4 NRC SRB Feed Standing Water 1BDE42 NOTF 20999741 LRP4 NRC SRB Feed Standing Water 1BDE43 NOTF 20999742 LRP4 NRC SRB Feed Standing Water 1BDE42 NOTF 20999743 LRP4 NRC Switchyard Dewatering Evaluation NOTF 21000042 LRP4 NRC IWE Visual Exam Enhancement Miscellaneous SH-PBD-AMP-XI.M36 External Surfaces Monitoring Revision 2 SH-PBD-AMP-XI.E3 Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Revision 2 SH-PBD-AMP-XI.M34 Buried Piping Inspection Revision 3 SH-PBD-AMP-XI.M38 Buried Piping Inspection Revision 3 SH-PBD-AMP-XI.S1 ASME Section XI, Subsection IWE Revision 4 SH-PBD-AMP-RG 1.127, Inspection of Water-Control Structures Revision 2
6 Inspection Procedure Type Designation Description or Title Revision or Date XI.S7 Associated with Nuclear Power Plants NDE Reports S-IR-6S0-0030 (010)
Service Water Intake Structure (2023), Baseline Database for Structures Monitoring Program, Salem Generating Station, Units 1 & 2 Revision 0 Procedures ER-AA-3003 Cable Condition Monitoring and Aging Management Program Revision 4 ER-AA-310-101 Condition Monitoring of Structures Revision 3 ER-AA-5400-100 Underground Piping Examination Guide Revision 5 ER-AA-700-1012 External Surfaces Monitoring Aging Management Program Revision 1 ER-AA-700-1014 Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Aging Management Program Revision 1 MA-AA-716-010-1000 Maintenance Planning Revision 19 MA-AA-724-105 VLF Tan Delta and Withstand Cable Testing Revision 4 SA-AA-117 Excavation, Trenching, and Shoring Revision 16 Work Orders 30349021 60157692