IR 05000272/2026011
| ML26056A050 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-070, DPR-075) |
| Issue date: | 02/25/2026 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Mcfeaters C Public Service Enterprise Group |
| Shared Package | |
| IR 2026011 | List: |
| References | |
| IR 2026011 | |
| Download: ML26056A050 (0) | |
Text
February 25, 2026
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 - AGE-RELATED DEGRADATION INSPECTION REPORT 05000272/2026011 AND 05000311/2026011
Dear Charles McFeaters:
On January 30, 2026, 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 Tom Mulholland, Engineering Director, 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
Inspection Report
Docket Numbers:
05000272 and 05000311
License Numbers:
Report Numbers:
05000272/2026011 and 05000311/2026011
Enterprise Identifier: I-2026-011-0011
Licensee:
Facility:
Salem Nuclear Generating Station, Units 1 and 2
Location:
Hancocks Bridge, NJ
Inspection Dates:
January 12, 2026 to January 30, 2026
Inspectors:
A. Patel, Team Leader
J. Tifft, Senior Reactor Inspector
S. McClay, Reactor Inspector
Approved By:
Erin E. Carfang, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an age-related degradation 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.
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.
REACTOR SAFETY
71111.21N.04 - Age-Related Degradation Age-Related Degradation (8 Samples)
The inspectors selected a sample of components and structures to verify that engineering performance and maintenance activities addressed age-related degradation and that problems were appropriately identified, addressed, and corrected.
Samples were selected considering risk insights and the potential for degradation.
Specifically, the inspectors selected samples that were risk-significant and either had indications of age-related degradation or were exposed to environments that could cause age-related degradation. The inspectors considered site-specific and industry-wide operating experience to identify samples and included both active and passive sub-components within each component or structure.
For each selected sample listed below, the inspectors reviewed the licensees engineering and maintenance activities credited to address age-related degradation to assess whether they were being performed using applicable standards and procedures, evaluated against appropriate acceptance criteria, and that maintenance and condition monitoring was completed at an appropriate interval. The inspectors also assessed whether issues identified during licensee activities were being entered into and addressed by the applicable station processes including the corrective action program, and whether periodic assessments of maintenance effectiveness and operating experience were being completed, including feedback and process adjustments.
(1)2B 125VDC Vital Bus (2)2B Emergency Diesel Generator (3)12SW129, Component Cooling Pump Room Cooler Service Water Containment Valve (4)1SJ31, Refueling Water Storage Tank to Safety Injection Check Valve (5)1RH2, Residual Heat Removal Common Suction Motor Operated Gate Valve (6)2PR2, Pressurizer Power Operated Relief Valve (7)11 Residual Heat Removal Pump (8)21 Component Cooling Heat Exchanger
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On January 30, 2026, the inspectors presented the age-related degradation inspection results to Tom Mulholland, Engineering Director, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.04 Calculations
S-1-RHR-MDC-
0890
MOV Capability Assessment for 1RH2-MTRY
Revision 6
Corrective Action
Documents
20926537
20927161
20999175
Corrective Action
Documents
Resulting from
Inspection
21011582
21011702
21012158
Engineering
Changes
PCR-24-000325
Engineering
Evaluations
70165699
237159
243667
244644
Miscellaneous
2B 125VDC Battery Performance Monitoring Trend Data
Procedures
Bolt Torquing and Bolting Sequence Guidelines
Revision 5
S2.OP-PM.CC-
21(Q)
Component Cooling Heat Exchanger High Flow Flush
and Alignment
Revision 28
S2.OP-ST.PZR-
0003
Inservice Testing Pressurizer PORV and Reactor head Vent
Valves
Revision 11
SC.MD-PM.DG-
0004
Emergency Diesel Generator Preventive Maintenance
Revision 17
Work Orders
279527
30300018
246630
259423
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
259550
80112003