IR 05000413/2024011
ML24270A138 | |
Person / Time | |
---|---|
Site: | Catawba |
Issue date: | 10/01/2024 |
From: | Paul Carman Division Reactor Projects II |
To: | Flippin N Duke Energy Carolinas |
References | |
IR 2024011 | |
Download: ML24270A138 (1) | |
Text
SUBJECT:
CATAWBA NUCLEAR STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000413/2024011 AND 05000414/2024011
Dear Nicole Flippin:
On September 19, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Catawba Nuclear Station and 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.
October 1, 2024 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, Paul J. Carman, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 05000413 and 05000414 License Nos. NPF-35 and NPF-52
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000413 and 05000414 License Numbers:
NPF-35 and NPF-52 Report Numbers:
05000413/2024011 and 05000414/2024011 Enterprise Identifier:
I-2024-011-0026 Licensee:
Duke Energy Carolinas, LLC Facility:
Catawba Nuclear Station Location:
York, South Carolina Inspection Dates:
August 26, 2024, to September 19, 2024 Inspectors:
B. Bishop, Senior Project Engineer D. Jackson, Senior Project Engineer J. Quinones-Navarro, Senior Project Engineer A. Wang, Resident Inspector R. Wehrmann, Resident Inspector Approved By:
Paul J. Carman, Chief Reactor Projects Branch 1 Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Catawba 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)
- (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 conducted an in-depth corrective action program review of the following systems or portions thereof: chemical volume and control, component cooling water, control room ventilation, engineered safety features actuation. The inspectors also conducted a five-year review of equipment aging issues. The corrective actions for the following non-cited violations were evaluated as part of the assessment: 05000413/2023003-01, 05000414/2023001-02, 05000413,05000414/ 2022403-01, 05000413,05000414/ 2022403-02, as well as nuclear condition report 2476801 associated with a licensee-identified violation.
- 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 1) Corrective Action Program Effectiveness Problem Identification: Based on a review of the requirements for initiating condition reports as described in licensee procedure AD-PI-ALL-0100, "Corrective Action Program," the inspectors determined that the licensee was effective in identifying problems and entering them into the corrective action program (which includes the work management system), and there was a low threshold for entering issues into the 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 determined 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 to also address the root and contributing causes for significant conditions adverse to quality to preclude repetition. Effectiveness reviews for corrective actions to preclude repetition were sufficient to ensure corrective actions were properly implemented and were effective. The inspectors noted that while issue evaluations were generally sound, there were several examples where additional research was needed to verify that the appropriate corrective actions were taken, primarily due to a lack of clear documentation.
Based on the samples reviewed, the team concluded 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) Use of 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 had been completed consistent with those recommendations.
4) Safety Conscious Work Environment Based on interviews with plant staff and reviews of the latest safety culture survey results, the team found no evidence of challenges to a safety conscious work environment. Employees interviewed appeared willing to raise nuclear safety concerns through at least one of the several means available.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On September 19, 2024, the inspectors presented the biennial problem identification and resolution inspection results to Nicole Flippin and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Action Request
(AR)
1902459, 2281737, 2296571, 2391622, 2438893, 2439553,
2440296, 2440457, 2440648, 2441520, 2441679, 2441710,
2441937, 2441976, 2442060, 2442061, 2442159, 2442816,
2443205, 2443211, 2443392, 2443870, 2444090, 2444181,
2445495, 2445680, 2446319, 2446552, 2446717, 2446718,
2446796, 2447114, 2447910, 2448582, 2448675, 2449252,
2452054, 2452317, 2452423, 2453258, 2453528, 2454309,
2455122, 2455172, 2455719, 2456267, 2457596, 2458114,
2458249, 2458912, 2459010, 2459013, 2459101, 2460422,
2462016, 2464240, 2464718, 2465312, 2466117, 2466279,
2467436, 2468311, 2468403, 2468727, 2468727, 2468778,
2469693, 2469767, 2469852, 2470908, 2471431, 2471639,
2472201, 2472596, 2474120, 2474221, 2474223, 2474846,
2474913, 2475579, 2476801, 2477258, 2477709, 2478808,
2479000, 2480138, 2480525, 2480870, 2481053, 2481289,
2482423, 2482425, 2483565, 2485804, 2486202, 2486204,
2486380, 2488073, 2488277, 2488715, 2490163, 2491222,
2492108, 2492337, 2492911, 2493723, 2494544, 2497918,
2499589, 2500192, 2500443, 2500868, 2501417, 2501666,
2501704, 2502220, 2502629, 2503486, 2504889, 2504914,
2505102, 2508170, 2508336, 2509035, 2509558, 2509870,
2509871, 2510232, 2510429, 2512316, 2512316, 2512318,
2512330, 2513356, 2514044, 2515189, 2515431, 2515667,
2517219, 2518041, 2518184, 2518340, 2518607, 2519533,
21538, 2522709, 2526482, 2526740, 20580204
Nuclear Condition
Report (NCR)
26740, 2529222, 2529224
Corrective Action
Documents
Resulting from
Inspection
Work Request
(WR)
274345, 20274291, 20274292, 20274294, 20274295,
274296, 20274298, 20274299
71152B
Procedures
AD-EG-ALL-1210
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AD-LS-ALL-0018
Evaluating and Reporting of Defects and Noncompliance in
Accordance with 10 CFR 21
AD-MN-ALL-0005
Nuclear Planning
AD-OP-ALL-0105
AD-PI-ALL-0100
Corrective Action Program
AD-SS-ALL-0001
Control of Portable Measuring and Test Equipment and Plant
Tools and Portable Media/Mobile Devices (PMMD)
AD-WC-ALL-0200 On-Line Work Management
AD-WC-ALL-0210 Work Request Initiation, Screening, Prioritization, and
Classification
MP-0-A-7450/031
Obtaining Carbon Filter Test Sample
PT-0-A-4450/020
Ventilation Filter Testing Program (VFTP)
Work Orders
WO/WP
2153233, 2179731, 20081175, 20081200, 20146775
20184662, 20184667, 20184673, 20206273, 20208884,
229096, 20231743, 20233312, 20233673, 20233803,
233881, 20234226, 20236004, 20237379, 20238880,
239713, 20241647, 20243388, 20244004, 20244620,
245012, 20245321, 20246540, 20246699, 20246870,
247464, 20248979, 20250219, 20250895, 20251907,
253051, 20255858, 20259422, 20262532, 20266958,
266968, 20272095, 20272631, 20285831, 20346546,
20409265, 20419205, 20452034, 20461587, 20466299,
20501215, 20504659, 20517632, 20529545, 20553404,
20555765, 20561172, 20567159, 20593769, 20600638,
20620671, 20620906, 20623105, 20632290, 20640031,
20651603