IR 05000369/2024011
| ML24152A316 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 06/04/2024 |
| From: | Eric Stamm NRC/RGN-II/DRP/RPB1 |
| To: | Pigott E Duke Energy Carolinas |
| References | |
| IR 2024011 | |
| Download: ML24152A316 (11) | |
Text
SUBJECT:
MCGUIRE NUCLEAR STATION - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000369/2024011 AND 05000370/2024011
Dear Edward Pigott:
On May 9, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your McGuire 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.
June 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, Eric J. Stamm, Chief Reactor Projects Branch #1 Division of Reactor Projects Docket Nos. 05000369 and 05000370 License Nos. NPF-9 and NPF-17
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000369 and 05000370
License Numbers:
Report Numbers:
05000369/2024011 and 05000370/2024011
Enterprise Identifier:
I-2024-011-0025
Licensee:
Duke Energy Carolinas, LLC
Facility:
McGuire Nuclear Station
Location:
Huntersville, NC
Inspection Dates:
April 22, 2024, to May 9, 2024
Inspectors:
D. Dang, Resident Inspector
W. Deschaine, Senior Resident Inspector
R. Mathis, Senior Construction Inspector
M. Riley, Senior Project Engineer
C. Safouri, Senior Resident Inspector
Approved By:
Eric J. Stamm, 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 McGuire 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 AC power system, auxiliary feedwater system, and component cooling water system. The inspectors also conducted a five-year review of equipment aging issues. The corrective actions for the following non-cited violations and findings were evaluated as part of the assessment: FIN 2023003-01, NCV 2023010-01, NCV 2023401-01, NCV 2022003-01, and NCV 2022002-01.
- 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 McGuire 2024 Problem Identification and Resolution Inspection 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 includes 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 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 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 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. The team noted that most interviewees were not familiar with the employee concerns program (ECP), specifically how to raise issues through the ECP, or who to contact on site. However, most interviewees did not have experience using the ECP because they were comfortable raising issues through other available avenues (e.g., directly to supervisor). The inspectors noted that issues were still being received and evaluated by the ECP.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 9, 2024, the inspectors presented the biennial problem identification and resolution inspection results to Edward Pigott and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Action
Requests/Nuclear
Condition Reports
2430799, 02443279, 02502620, 02456456, 02455474,
2498442, 02486130, 02422881, 02433395, 02464436,
2495229, 02432084, 02432979, 02423333, 02294641,
2380257, 02477945, 02430757, 02430792, 02431023,
2431718, 02431933, 02433471, 02434529, 02435263,
2502662, 02496497, 02493559, 02493561, 02490867,
2486182, 02493670, 02493665, 02455257, 02471242,
2430807, 02432083, 02435677, 02438237, 02447352,
2448603, 02452261, 02448844, 02479420, 02480945,
2432289, 02443184, 02448149, 02323487, 02197462,
2422009, 02424572, 02422865, 02493170, 02498440,
2498442, 02495703, 02502356, 02473453, 02423861,
2468097, 02498008, 02433886, 02438948, 02450117,
2451848, 02456168, 02456176, 02456557, 02463243,
2475832, 02481718, 02487883, 02491350, 02492136
Corrective Action
Documents
Resulting from
Inspection
Nuclear Condition
Report(s)
2513939, 02514108, 02515533
Drawings
MCCD-1702-
01.00
4160V Essential Power System One Line Diagram
Drawings
MCCD-1702-
2.00
4160V Essential Power System One Line Diagram
Drawings
MCCD-1702-
03.00
13800 V Normal Auxiliary Power System One Line Diagram
Drawings
MCEE-0120-
01.01
Diesel Generator 1A Start Circuit Elementary Diagram
Drawings
MCEE-0120-
01.02
Diesel Generator 1A Start Circuit Elementary Diagram
Drawings
Unit 1: MCFD-
1592-01.00,
MCFD-1592-
Flow Diagrams of Auxiliary Feedwater System (CA)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01.01, MCFD-
1592-01.02,
MCFD-1592-
2.00
Unit 2: MCFD-
2592-01.00,
MCFD-2592-
01.01, MCFD-
2592-01.02,
MCFD-2592-
2.00
Engineering
Evaluations
Operating
Experience
Evaluation
OPEX 02455474
Miscellaneous
22 Boric Acid Corrosion Control Program Health Report
05/30/2023
Miscellaneous
LP-SY-MNS 0506
Vehicle Search
Miscellaneous
OP-MC-CF-CA
Operations Training Document - Auxiliary Feedwater System
(CA)
Procedures
AD-EG-ALL-1202
Preventive Maintenance and Surveillance Testing
Administration
Procedures
AD-EG-ALL-1207
PLANT HEALTH PROCESS
Procedures
AD-EG-ALL-1210
Procedures
AD-EG-ALL-1618
Snubber Program Plan
Procedures
AD-EG-ALL-1720
Inservice Testing (IST) Program Implementation
Procedures
AD-EG-PWR-
1611
Boric Acid Corrosion Control Program Implementation
Procedures
AD-LS-ALL-0018
Evaluating and Reporting of Defects and Noncompliance in
Accordance with 10 CFR 21
Procedures
AD-MN-ALL-0005
NUCLEAR PLANNING
Procedures
AD-NO-ALL-0202
Employee Concerns Program
Procedures
AD-PI-ALL-0100
CORRECTIVE ACTION PROGRAM
Procedures
AD-PI-ALL-0106
CAUSE INVESTIGATION CHECKLISTS
Procedures
AD-PI-ALL-0300
SELF-ASSESSMENT AND BENCHMARK PROGRAMS
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
AD-PI-ALL-1000
Conduct of Performance Improvement
Procedures
AD-SY-ALL-0215
Security Search and Entry Processing
Procedures
AD-WC-ALL-0210
Work Request Initiation, Screening, Prioritization and
Classification
Procedures
AD-WC-ALL-0250
WORK IMPLEMENTATION AND COMPLETION
Procedures
CSD-AD-ALL-
0004-01
Corrective Action Program Review Meeting
Procedures
CSD-SY-MNS-
201-01
MNS Security Post Order Handbook
Procedures
MP-0-A-7650-261
Component Status Tracking for Equipment Cleared for Work
Procedures
OP/1/A/6250/002,
OP/2/A/6250/002
Technical Procedures (Operating) - AUXILIARY
FEEDWATER SYSTEM
Self-Assessments
McGuire Nuclear Station Nuclear Safety Culture Assessment
August 2022
Self-Assessments 2020-FLEET-
CAP-01
NUCLEAR OVERSIGHT - AUDIT FLEET PERFORMANCE
IMPROVEMENT AND CORRECTIVE ACTION PROGRAM
Self-Assessments 2022-FLEET-
CAP-01
NUCLEAR OVERSIGHT AUDIT FLEET PERFORMANCE
IMPROVEMENT AND CORRECTIVE ACTION PROGRAM
Self-Assessments MNS-SITE-
1497.02-2023-2
MNS Performance Trending Report 2nd Triannual Period
23, Period Covered: May 2023 through August 2023
Work Orders
WO 20607092, WP 20607704, WO 20608485, WO 20126901, WO 20129602, WO 20179615, WO 20299181,
WO 20343927, WO 20349445, WR 20228184, WR 268594, WO 20646896, WR 20239415, WR 20240696,