IR 05000400/2024010
| ML24339B800 | |
| Person / Time | |
|---|---|
| Site: | Harris  (NPF-063) |
| Issue date: | 12/04/2024 |
| From: | Katie Mccurry NRC/RGN-II/DORS/PB4 |
| To: | Haaf T Duke Energy Progress |
| References | |
| IR 2024010 | |
| Download: ML24339B800 (1) | |
Text
SUBJECT:
SHEARON HARRIS NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000400/2024010
Dear Thomas Haaf:
On October 24, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Shearon Harris Nuclear Plant 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 assessed the licensees 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.
December 4, 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, Katherine McCurry, Chief Projects Branch 2 Division of Operating Reactor Safety Docket No. 05000400 License No. NPF-63
Enclosure:
As stated
Inspection Report
Docket Number:
05000400
License Number:
Report Number:
Enterprise Identifier:
I-2024-010-0038
Licensee:
Duke Energy Progress, LLC
Facility:
Shearon Harris Nuclear Plant
Location:
New Hill, North Carolina
Inspection Dates:
October 7, 2024 to October 24, 2024
Inspectors:
C. Curran, Resident Inspector
M. Kay, Resident Inspector
A. Ponko, Senior Construction Project Inspector
A. Wilson, Senior Project Engineer
Approved By:
Katherine McCurry, Chief
Projects Branch 2
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 Shearon Harris Nuclear Plant, 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 also conducted a five-year review of equipment aging issues. The corrective actions for the following non-cited violations (NCV), minor violations (MV), and findings (FIN) were evaluated as part of the assessment: NCV 2024001-01, NCV 2024011-01, MV 2023-003 (1), MV 2023-003 (2), FIN 2023003-01, FIN 2023003-02, NCV 2023002-01, NCV 2023002-02, NCV 2023404-01, NCV 2023404-02, NCV 2023404-03, MV 2023401, NCV 2023001-01, NCV 2022004-01, LIV 2022003, NCV 2022003-01, NCV 2022003-02, NCV 2022003-03, MV 2022003, LIV 2022002 (1), LIV 2022002 (2), MV 2022011, NCV 2022010-01, NCV 2022010-02, NCV 2022010-03.
- 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 PI&R Assessment 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.
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 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 evaluating those issues, and resolving 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 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 October 24, 2024, the inspectors presented the biennial problem identification and resolution inspection results to Thomas Haaf and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
27397
2384809
2391700
2406337
2409314
2410358
2411360
2418524
23818
23878
24355
25550
25558
26708
28530
28530
2431659
2431919
2432246
2432931
2433436
2433692
2434802
2435548
2435666
2437245
2437865
2438075
2439239
2439654
2440181
2440855
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2441196
2441659
2441880
2443443
2443861
2443892
2444020
2445528
2446358
2447152
2447153
2447356
2447591
2447620
2447620
2447663
2447750
2448544
2448837
2450265
2455923
2456610
2456634
2458170
2460166
2460346
2461030
2461094
2461450
2463970
2464264
2465738
2466193
2466223
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2467256
2467578
2469554
2471032
2471415
2472331
2472408
2473696
2475271
2476027
2476806
2477628
2479412
2479586
2479615
2479803
2479966
2482360
2482558
2482565
2486589
2486781
2486870
2486928
2487036
2487626
2488447
2491068
2491308
2492192
2492485
2493782
2494704
2495281
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2496925
2497919
2498238
2501567
2504066
2504618
2504774
2506097
2507380
2509836
2510442
2513355
2514152
2514815
2515924
2517946
2519253
2519349
2519876
2519994
20157
23456
26786
29800
29801
29889
NCR 02531640
Corrective Action
Documents
Resulting from
Inspection
WRs 20276612,
276622,
276623,
276626,
276633,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
276628,
276629,
276630
Document No.: 5-
S-0547
Simplified Flow Diagram Circulating & Service Water
Systems Sheet 1 - Unit 1,
Revision 067
Drawings
Document No.: 7-
G-2847
Emer Serv Wtr Sys-Mn Rsvr Int Str M Sh-3-Un 1-2
Revision 013
2923
Engineering
Changes
ESW Fine Screens
Revision 2
Harris Nuclear Plant Nuclear Safety Culture Assessment
August 2023
EVAL-2022-HNP-
4010-00002224 -
NCR 2425550
Maintenance Rule Evaluation
EVAL-2022-HNP-
4065-00002240 -
NCR 2444020
Maintenance Rule Evaluation
Miscellaneous
EVAL-2022-HNP-
5165-00002245 -
NCR 2447620
Maintenance Rule Evaluation
AD-EG-ALL-1210
AD-NO-ALL-0202
Employee Concerns Program
AD-OP-ALL-0105
AD-PI-ALL-0100
Corrective Action Program
AD-PI-ALL-0101
Root Cause Evaluation
AD-PI-ALL-0106
Cause Investigation Checklists
AD-PI-ALL-0300
Self-Assessment and Benchmark Programs
AD-PI-ALL-0400
Operating Experience Program
AD-PI-ALL-0401
Significant Operating Experience Program
AD-WC-ALL-0210
Work Request Initiation, Screening, Prioritization and
Classification
Procedures
AD-WC-ALL-0250
Work Implementation and Completion
2410347-05
RP Task to Training Matrix and Training Selection Alignment
2454086-05
Annual Effectiveness Review of the Fatigue Rule (Program)
Self-Assessments
2454087-05
Quality Records - Assessment of Accuracy and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Completeness (Performance)
2454283-05
Assess training impacts related to the Eng Organizational
changes on Eng
2478660-05
2488622-05
Review of AOP actions against critical parameters
2499207-05
HNP 2024 NRC PI&R Readiness Assessment
2508461-05
23 Annual Backlog Review
22-FLEET-
CAP-01
Fleet Performance Improvement and Corrective Action
Program
22-HNP-EMP-
LSA-01
Harris Emergency Preparedness
22-HNP-EMP-
PR-01
Performance Review - Harris Emergency Preparedness
22-HNP-SEC-
Harris Physical Security Audit
23-HNP-MNT-
Harris Maintenance and Special Processes Audit
24-HNP-ENG-
Harris Engineering Audit
Work Orders
256465 (WR),
241314 (WR),
20580373-01
(WO), 20645088-
(WO),
261635 (WR),
241320 (WR),
20580193-01
(WO), 20276633
(WR)