IR 05000272/2025010

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Biennial Problem Identification and Resolution Inspection Report 05000272/2025010 and 05000311/2025010
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

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. 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

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:

PSEG Nuclear, LLC

Facility:

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

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.

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) 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.

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.

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 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.

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

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