IR 05000269/2025011

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Biennial Problem Identification and Resolution Inspection Report 05000269/2025011 and 05000270/2025011 and 05000287/2025011
ML25157A114
Person / Time
Site: Oconee  
Issue date: 06/11/2025
From: Robert Williams
NRC/RGN-II/DORS
To: Snider S
Duke Energy Carolinas
References
IR 2025011
Download: ML25157A114 (1)
v • d • e


Text

SUBJECT:

OCONEE NUCLEAR STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000269/2025011 AND 05000270/2025011 AND 05000287/2025011

Dear Steven Snider:

On May 1, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Oconee Nuclear Station. On May 1, 2025, the NRC inspectors discussed the results of this inspection with you 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 its 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.

June 11, 2025

Sincerely, Robert E. Williams, Jr., Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000269 and 05000270 and 05000287 License Nos. DPR-38 and DPR-47 and DPR-55

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000269, 05000270 and 05000287

License Numbers:

DPR-38, DPR-47 and DPR-55

Report Numbers:

05000269/2025011, 05000270/2025011 and 05000287/2025011

Enterprise Identifier:

I-2025-011-0019

Licensee:

Duke Energy Carolinas, LLC

Facility:

Oconee Nuclear Station

Location:

Seneca, South Carolina

Inspection Dates:

April 14, 2025 to May 01, 2025

Inspectors:

B. Bishop, Senior Project Engineer

D. Jackson, Technical Assistant

E. Robinson, Senior Project Engineer

J. Seat, Senior Project Engineer

Approved By:

Robert E. Williams, Jr., Chief

Reactor Projects Branch 1

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 Oconee Nuclear Station, 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)

Main article: IP 71152
(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.
  • Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience. The licensees evaluation of NRC generic communications was reviewed as well as other significant industry and fleet operating experience to determine whether the licensee appropriately used operating experience information.
  • Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments. Specifically, nuclear oversight audits and departmental self-assessments were reviewed to determine whether the licensee appropriately assessed performance and identified areas for improvement.
  • Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment. Inspectors reviewed employee concerns program issues, and the latest Nuclear Safety Culture Assessment Report, and conducted interviews with licensee staff from various departments to assess whether issues exist that may represent challenges to the free flow of information, and to determine whether underlying factors exist that would produce a reluctance to raise nuclear safety concerns.

INSPECTION RESULTS

Assessment 71152B Biennial PI&R Assessment 1) Corrective Action Program Effectiveness Problem Identification: The inspectors determined that the licensee was effective in identifying problems and entering them into the corrective action program (which included the work management system), and there was a low threshold for entering issues into the corrective action program. This conclusion was based on a review of the requirements for initiating condition reports as described in licensee procedure AD-PI-ALL-0100, "Corrective Action Program." Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.

Problem Prioritization and Evaluation: Based on the review of condition reports, work orders, and work requests, the inspectors concluded that problems were prioritized and evaluated in accordance with licensee guidance. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that, in general, plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and cause determinations were appropriate, and considered the significance of the issues being evaluated.

Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that, generally, corrective actions were timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. The team determined that the licensee was generally effective in developing corrective actions that were appropriately focused. Effectiveness reviews for corrective actions to preclude repetition were sufficient to ensure corrective actions were properly implemented and were effective. The inspectors found that issue evaluations were generally sound.

Based on the samples reviewed, the team determined that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees implementation of the corrective action program adequately supported nuclear safety.

2) Operating Experience The team determined that the stations processes for the use of industry and NRC operating experience information were effective and complied with regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The team concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented in accordance with applicable procedures.

3) Self-Assessments and Audits The inspectors determined that the licensee was effective at performing self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance. The self-assessments and audits were adequately self-critical and performance-related issues were being appropriately identified. The inspectors verified that action requests were created to document areas for improvement and findings, and verified that actions generally had been completed consistent with those recommendations.

4) Safety-Conscious Work Environment Based on both formal and informal interviews conducted with licensee personnel across several organizations and reviews of the latest safety culture assessment results, the team determined that employees felt free to raise issues without fear of retaliation. Those interviewed were knowledgeable of the different avenues available to raise safety concerns, including through us of the Employee Concerns Program and were familiar with who to contact on site. The team found no evidence of challenges to a safety conscious work environment.

EXIT MEETINGS AND DEBRIEFS

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

  • On May 1, 2025, the inspectors presented the biennial problem identification and resolution inspection results to Steven Snider and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

2315317,

2340231,

2408618,

2415204,

25098,

2466315,

2493205,

2493373,

2493542,

2495862,

2503209,

2504166,

2504916,

2508926,

2509983,

20442,

2510402,

2514735,

2518069,

29103,

2545420,

2546229,

2480047,

2477886,

2455196,

2459548,

2531858,

2457692,

2447897,

2493534,

2546420,

2546421,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2546423,

2546424,

2546425,

2546426,

2546427,

2472973,

2366042,

2481263,

2491967,

2546438,

2535306,

24960,

2516514,

2507689,

2487133,

2517929,

2495192,

2516959,

2518069,

22431,

27884,

2465385,

2463459,

2478813,

2534816,

2534862,

2538175,

2541430,

2496568,

2513562,

2496568,

2467403,

2467434,

2463573,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2464000,

2464021,

2464512,

2467081,

2470733,

2473173,

2474006,

2477233,

2481444,

2481206,

2482730,

2483059,

2483638,

2484068,

2487314,

2546427,

2542013,

2495192,

2533422,

25510,

26380,

2432379,

2433176,

2459110,

2459564,

2468585,

2462145,

2454884,

2471437,

2469531,

2469702,

2473099,

26301,

2464000,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2546427,

2546428,

2449194,

23749,

2477210,

2495280,

2503209,

2477145,

2477210,

2477611,

2489821,

2477145,

26319,

2515442,

2516601,

2475826,

23539,

29614,

28948,

2487362,

25640,

2465514,

2466290,

2481069,

2491254,

2491779,

2492313,

2503508,

2504188,

2504231,

2509639,

2515786,

20747,

29359,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2533213,

2534818,

2540884,

2495135,

2540167,

2481184,

2515028,

2519846,

21150,

2447967,

2534840

OFD-102A-1.2

Flow Diagram of Low Pressure Injection System LPI Pump

Discharge

Rev. 62

OFD-102A-2.2

Flow Diagram of Low Pressure Injection System LPI Pump

Discharge

Rev. 54

Drawings

OFD-104A-3.1

Flow Diagram of Spent Fuel Cooling System

Rev. 61

AD-OP-ALL-0105

Operability Determinations

Rev. 009

AD-OP-ALL-0200

Clearance and Tagging

Rev. 026

OP/2/A/1104/015

Reactor Building Cooling System

Rev. 040

OP/3/A/1104/010

Low Pressure Service Water

Rev. 124

PT/3/A/0150/070

Leak Test of SFP Cooling Purification System Isolation from

BWST

Rev. 005

Procedures

TE-MN-PWR-

0006

Inspection, Assessment, and Cleanup of Boric Acid on Plant

Materials

Rev. 2

Self-Assessments 24892385,

2500645,

2410393,

2419413,

2436557,

2452639,

2493612,

22028,

2448761,

2453099,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2453105,

2453115

Work Orders

20636186,

20670908,

20671100,

20685006,

240737,

20586110,

285643,

253989,

20683468,

20690265,

20690265,

20688230,

20688231,

252945,

257354,

263206,

269302,

270964,

277430,

279429,

280498,

281203,

283199

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