IR 05000400/2025003
| ML25330A005 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/02/2025 |
| From: | Matthew Fannon NRC/RGN-II/DORS/PB2 |
| To: | Joseph C Duke Energy Progress |
| References | |
| IR 2025003 | |
| Download: ML25330A005 (0) | |
Text
SUBJECT:
SHEARON HARRIS NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000400/2025003
Dear Carolyne Joseph:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Shearon Harris Nuclear Plant. On November 19, 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.
Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. Due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.
No findings or violations of more than minor significance were identified during this inspection.
December 2, 2025 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, Matthew S. Fannon, 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-2025-003-0020
Licensee:
Duke Energy Progress, LLC
Facility:
Shearon Harris Nuclear Plant
Location:
New Hill, NC 27562
Inspection Dates:
July 01, 2025 to September 30, 2025
Inspectors:
P. Boguszewski, Senior Resident Inspector
M. Kay, Resident Inspector
Approved By:
Matthew S. Fannon, Chief
Projects Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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.
PLANT STATUS
Unit 1 operated at or near rated thermal power for the entire inspection period.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
'A' emergency service water after maintenance on July 9, 2025
- (2) Spent fuel pool cooling system during spent fuel pool transfer canal work on July 25, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Reactor auxiliary building mechanical penetration room on July 12, 2025
- (2) Fuel handling building 236' elevation on July 12, 2025
- (3) Unit 2 diesel generator building on September 3, 2025
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on August 6, 2025.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated a simulator training scenario involving a main steam line break outside of containment on July 8, 2025.
- (2) The inspectors observed and evaluated classroom and simulator training for the plant shutdown scheduled for the upcoming refueling outage on September 24, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Miscalculation of unavailability hours in maintenance rule tracking software (Nuclear Condition Report (NCR) 2556132) on July 18, 2025
- (2) Medium voltage underground cabling (Work Order (WO) 20605343) on August 26, 2025
- (3) Instrument air system on July 23, 2025 (4)
'C' steam generator power operated relief valve on September 26, 2025
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)
'A' emergency diesel generator maintenance outage on September 18, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Elevated risk due to switchyard circuit breaker 52-2 gearbox replacement on August 4, 2025
- (2) Elevated risk due to 'A' startup transformer inspections and repair on September 8, 2025
- (3) Elevated risk due to 'A' emergency diesel generator planned maintenance on September 18, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
'B' emergency diesel generator jacket water high temperatures (NCR 2561687) on July 18, 2025
- (2) Air leak on 1EA-188, 'B' emergency diesel generator engine control panel pressure regulator (NCR 2560252) on July 8, 2025 (3)
'C' charging/safety injection pump elevated leakage (NCR 2562681) on July 30, 2025 (4)1D2-7B:002 degraded closing coil (WO 20292155) on August 7, 2025
- (5) Emergency service water pipe leaks (NCRs 2563862 and 2564663) on August 15, 2025
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (3 Samples)
- (1) OST-1076, "Auxiliary Feedwater Pump 1B-SB Operability Test," after planned maintenance on July 1, 2025
- (2) OST-1191, "Steam Generator PORV and Block Valve Operability Test," following maintenance on August 1, 2025
- (3) OST-1093, "CVCS/SI System Operability Train B Test," following maintenance on July 24, 2025
Surveillance Testing (IP Section 03.01) (5 Samples)
- (1) LP-T-6903A, "Diesel Generator Room A Temperature," on July 9, 2025
- (2) OPT-1532, "Alternate Seal Injection Squib Valves Fire Test," on September 10, 2025
- (3) TE-NF-PWR-0810, "Moderator Temperature Coefficient - End of Life," on July 30, 2025
- (4) OST-1119, "Containment Spray Operability Train B Quarterly," on July 21, 2025
- (5) MPT-E0008, "Environmentally Qualified 480 VAC Motor Electrical Inspection,"
performed on the 'C' charging/safety injection pump motor on July 23, 2025
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) OST-1215, "Emergency Service Water System Operability Train B Quarterly," on August 8, 2025
- (2) OST-1073, "1B-SB Emergency Diesel Generator Operability Test Monthly," on August 27, 2025
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) The inspectors observed and evaluated the conduct of an emergency preparedness tabletop drill involving a reactor coolant system leak during a refueling outage with containment open on August 11,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) July 1, 2024, to June 30, 2025
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) July 1, 2024, to June 30, 2025
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) July 1, 2024, to June 30,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 19, 2025, the inspectors presented the integrated inspection results to Carolyne Joseph and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5-S-0547
Simplified Flow Diagram Circulating and Service Water
Systems
Revision 68
5-S-0805
Simplified Flow Diagram Fuel Pools Cooling System Unit 1
Revision 14
Drawings
5-S-0807
Simplified Flow Diagram Fuel Pools Cooling System Unit 2
Revision 9
Fuel Pool Cooling System
Revision 50
Procedures
Service Water System
Revision 150
CSD-HNP-PFP-
DGB
Diesel Generator Building Pre-Fire Plan
Revision 2
CSD-HNP-PFP-
FHB
Fuel Handling Building Pre-Fire Plan
Revision 2
CSD-HNP-PFP-
RAB-236
Reactor Auxiliary Building Elevation 236 Pre-Fire Plan
Revision 3
Procedures
Fire Protection Program Manual
Revision 47
GP-006
Normal Plant Shutdown From Power Operation to Hot
Standby (Mode 1 to Mode 3)
Revision 123
Procedures
GP-007
Normal Plant Cooldown Mode 3 to Mode 5
Revision 80
Corrective Action
Documents
2542050
2545717
2550636
2561847
2561971
2505389
2505381
2512233
2512232
2518442
26518
2547223
2557590
2537547
2569938
Procedures
AD-EG-ALL-1103
Procurement Engineering Products
Revision 9
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
20709834-02
AD-OP-ALL-0210
Operational Risk Management
Revision 5
Procedures
AD-WC-ALL-200
Online Work Management
Revision 25
1364-007813
Diesel Generator Starting Air Piping Schematic
Revision 22
Drawings
CPL-2165-S-
633S04
Simplified Flow Diagram Emergency Diesel Generator 1A-
SA & 1B-SB Starting Air System Unit 1
Revision 24