ML25216A132
| ML25216A132 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/04/2025 |
| From: | Jason Schussler Division of Operating Reactors |
| To: | Mcfeaters C Public Service Enterprise Group |
| References | |
| Download: ML25216A132 (1) | |
Text
August 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 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000272/2025010 AND 05000311/2025010
Dear Charles McFeaters:
On June 25, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your 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.
The NRC inspection team reviewed the stations problem identification and resolution program to confirm that the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that your program complies with NRC regulations and applicable industry standards such that the Reactor Oversight Process can continue to be implemented.
The team also evaluated the stations effectiveness in identifying, prioritizing, evaluating, and correcting problems, reviewed licensee audits and self-assessments, and the stations use of industry and NRC operating experience information. The results of these evaluations are in the enclosure.
Finally, the team reviewed the stations programs to establish and maintain a safety conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found no evidence of challenges to your organizations safety conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
No findings or violations of more than minor significance were identified during this inspection.
C. McFeaters 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, Jason E. Schussler, Team Leader Technical Support and Administrative Team 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 JASON SCHUSSLER Digitally signed by JASON SCHUSSLER Date: 2025.08.04 13:48:51 -04'00'
ML25216A132 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS NAME MHardgrove JSchussler DATE 7/16/2025 8/4/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000272 and 05000311 License Numbers:
DPR-70 and DPR-75 Report Numbers:
05000272/2025010 and 05000311/2025010 Enterprise Identifier: I-2025-010-0002 Licensee:
Salem Nuclear Generating Station, Units 1 and 2 Location:
Hancocks Bridge, NJ Inspection Dates:
June 9, 2025 to June 25, 2025 Inspectors:
M. Hardgrove, Senior Project Engineer D. Orr, Senior Project Engineer S. Quiroga, Resident Inspector K. Smetana, Reactor Engineer Approved By:
Jason E. Schussler, Team Lead Technical Support and Administrative Team Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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 - BASELINE 71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04) (1 Sample)
(1)
The inspectors performed a biennial assessment of the effectiveness of the licensees problem identification and resolution program, use of operating experience, self-assessments and audits, and safety conscious work environment.
Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees problem identification and resolution program in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a five-year review of Unit 1 and Unit 2 emergency diesel generators. The corrective actions for the following non-cited violations (NCVs) and findings were evaluated as part of the assessment: NCV 05000272,05000311/2023402-01; NCV 05000311/2023003-01; NCV 05000272/2023004-01; NCV 05000272/2023004-02; NCV 05000272/2023004-03; NCV 05000272,05000311/2023004-04; NCV 05000272,05000311/2024010-01; and NCV 05000272, 05000311/2024402-
- 01.
Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience.
Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
4 INSPECTION RESULTS Assessment 71152B Problem Identification and Resolution Program Effectiveness:
The inspectors determined that the licensee's problem identification and resolution program for Salem Nuclear Generating Station was generally effective and adequately supported nuclear safety and security.
Identification: The team reviewed a sample of issues that have been processed through the licensee's problem identification and resolution program since the last biennial team inspection, including NCVs of regulatory requirements and other documented findings. The team determined that, in general, the station identified issues and entered them into the corrective action program at a low threshold and timely manner.
Prioritization and Evaluation: Based on the samples reviewed, the team determined the licensee was effective at prioritizing and evaluating issues commensurate with the safety significance of the identified problem. Inspectors observed that at station corrective action program meetings, issues were generally screened and prioritized at the appropriate level and that corrective actions were assigned to address the issues.
Corrective Action: The team reviewed a sample of corrective actions and concluded that the licensee was generally effective in developing corrective actions that were appropriately focused to correct the identified problems.
Assessment 71152B Operating Experience:
The inspectors reviewed a sample of operating experience captured in the corrective action program and sampled operating experience from NRC, industry, vendors, and third-party groups. Overall, for the samples selected, the licensee was generally performing the appropriate assessments for station applicability.
Assessment 71152B Self-Assessments and Audits:
The inspectors determined that the licensee was adequately performing self-assessments and audits in accordance with licensee procedures and implementing corrective actions as needed.
Assessment 71152B Safety Conscious Work Environment:
The team interviewed a total of 40 individuals in one-on-one interviews. The purpose of these interviews was (1) to evaluate the willingness of the licensee staff to raise nuclear safety issues, (2) to evaluate the perceived effectiveness of the corrective action program at resolving identified problems, and (3) to evaluate the licensee's safety conscious work environment. The personnel interviewed were randomly selected by the inspectors from
5 Engineering, Maintenance, Operations, Radiation Protection, Chemistry, Emergency Preparedness, and Security. To supplement these discussions, the team interviewed the Employee Concern Program (ECP) Coordinator to assess their perception of the site employees' willingness to raise nuclear safety concerns. The team also reviewed the ECP case log and select case files.
All individuals interviewed indicated that they would raise safety concerns. Individuals felt that their management was receptive to receiving safety concerns and generally addressed them promptly, commensurate with the significance of the concern. Interviewees indicated that they were adequately trained and proficient on initiating condition reports. Most interviewees were aware of the licensee's ECP, and all stated they would use the program if necessary and expressed confidence that their confidentiality would be maintained if they brought issues to the ECP. When asked whether there have been any instances where individuals experienced retaliation or other negative reaction for raising safety concerns, all individuals interviewed stated that they had neither experienced nor heard of an instance of retaliation at the site.
The team determined that the processes in place to mitigate potential safety culture issues were adequately implemented.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On June 25, 2025, the inspectors presented the biennial problem identification and resolution inspection results to David Sharbaugh, Site Vice President, and other members of the licensee staff.
6 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71152B Corrective Action Documents 70129157 Corrective Action Documents Resulting from Inspection 20994116*
20994117*
20994118*
20994119*
20994120*
20994456*
20994546*
20994549*
20994554*
20994558*
20994560*
20994561*
20994563*
20994564*
20994565*
20994566*
20994567*
20994568*
20994569*
20994597*
20994621*
20994622*
20994848*
20994850*
20994851*
20994852*
20994853*
20994965*
20995129*
Procedures LS-AA-120 Issue Identification and Screening Process Revision 26
7 Inspection Procedure Type Designation Description or Title Revision or Date LS-AA-125 Corrective Action Program Revision 29 LS-AA-125-1001 Cause Analysis Revision 23 LS-AA-125-1002 Common Cause Evaluation Manual Revision 12 LS-AA-125-1004 Effectiveness Review Manual Revision 6 LS-AA-125-1006 Integrated Performance Assessment Revision 14