IR 05000400/2025011
| ML25239A776 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/27/2025 |
| From: | Louis Mckown NRC/RGN-II/DORS/EB3 |
| To: | Joseph C Duke Energy Progress |
| References | |
| IR 2025011 | |
| Download: ML25239A776 (1) | |
Text
SUBJECT:
SHEARON HARRIS NUCLEAR PLANT - NRC POST APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, PHASE II, INSPECTION REPORT 05000400/2025011
Dear Carloyne Joseph:
On August 21, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed a Post-Approval Site Inspection for License Renewal (Phase II) at 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.
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.
Sincerely, Louis J. McKown, II, Chief Engineering Branch 3 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-2025-011-0025
Licensee:
Duke Energy Progress, LLC
Facility:
Shearon Harris Nuclear Plant
Location:
New Hill, North Carolina
Inspection Dates:
August 04, 2025 to August 21, 2025
Inspectors:
L. Colon Fuentes, Construction Project Inspector
P. Cooper, Senior Reactor Inspector
S. Downey, Senior Reactor Inspector (Lead)
A. Ponko, Senior Construction Project Inspector
D. Strickland, Senior Reactor Inspector
Approved By:
Louis J. McKown, II, Chief
Engineering Branch 3
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Post Approval Site Inspection for License Renewal (Phase II) 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
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===71003 - Post-Approval Site Inspection for License Renewal From August 4, to August 22, 2025, the NRC continued monitoring Duke Energys performance at Shearon Harris Nuclear Power Plant by conducting a Post-Approval Site Inspection for License Renewal (Phase II) in accordance with the license renewal inspection program (LRIP).
This inspection took place prior to the period of extended operation (PEO) for Unit 1, which will begin on October 24, 2026. Per IMC 2516, the LRIP is the process used by NRC staff to verify the adequacy of aging management programs (AMPs), Time Limited Aging Analyses (TLAAs),and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant beyond the initial licensing period under 10 CFR Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.
Post-Approval Site Inspection for License Renewal===
- (1) License Conditions and Commitments for License Renewal, Implementation of Aging Management Programs and Time-Limited Aging Analyses There are 37 regulatory commitments linked to the renewed operating license for Shearon Harris Nuclear Power Plant, Unit 1, issued in December 2008, which include the following: 2 standalone commitments (not associated with an AMP or TLAA); 12 commitments to implement new aging management programs; 21 commitments to enhance existing aging management programs for license renewal, and 2 commitments to perform Time Limited Aging Analyses. During the inspection, the team reviewed a majority sample (greater than 70% as required by IP 71003) of regulatory commitments and associated AMPs and TLAAs in order to assess the adequacy and effectiveness of the license renewal program. For each item selected in the sample, the inspectors also reviewed the applicable license renewal program documents, conducted interviews with licensee staff, and performed system walkdowns as needed to verify that the licensee completed the actions necessary to comply with the conditions listed in the renewed facility operating license. For those license renewal action items that were not completed at the time of this inspection, the team verified that there was reasonable assurance that such action items were on track for completion prior to the PEO or in accordance with an established implementation schedule consistent with the license renewal application (LRA), the NRC safety evaluation report (SER), and the Updated Final Safety Analysis Report (UFSAR) supplement.
The regulatory commitments selected for the inspection sample are listed below along with the completion status of the item at the time of the inspection. The full description of each commitment is available in the UFSAR supplement for license renewal, as revised, and Appendix A of the NRC SER issued as NUREG-1916.
Commitments (by Number):
- Commitment 1: Enhancements to the Reactor Vessel Internals Aging Management Activities Program. Status: Complete.
- Commitment 2: Enhancement to the Primary Water Stress Corrosion Cracking of Nickel Alloys Program. Status: Complete
- Commitment 4: Implement the Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) Program. Status:
Complete
- Commitment 5: Enhancements to the Flow Accelerated Corrosion Program.
Status: Complete.
- Commitment 6: Enhancement to the Bolting Integrity Program to prohibit the use of molybdenum disulfide lubricants. Status: Complete.
- Commitment 7: Enhancements to the Steam Generator Tube Integrity Program. Status: Complete
- Commitment 8: Enhancements to the Boraflex Monitoring Program. Status:
Commitment is no longer applicable. In October 2018, the licensee received NRC approval to amend its renewed operating license to modify the Technical Specifications to no longer credit Boraflex for criticality control in the A and B spent fuel pools (ML18204A28). As a result of the amendment, the Boraflex Monitoring Program is no longer needed and has been removed from the FSAR.
- Commitment 9: Enhancements to the Inspection of Overhead Heavy Load and Light Load Handling Systems Program. Status: Complete.
- Commitment 10: Enhancements to the Fire Protection Program. Status:
Complete
- Commitment 11: Enhancements to the Fire Water System Program. Status Incomplete. The licensee has three remaining activities associated with this commitment. The licensee has an action to initiate an activity via Preventative Maintenance Add (PMAD) 2492895 to replace sprinklers at 50 years or perform testing. Additionally, the licensee has an action to modify Predefined Maintenance ID (PMID) 43477 via Preventative Maintenance Change (PMCH)2492905 to detect fouling and blockage in containment and the waste processing, reactor auxiliary, and fuel handling buildings. Lastly, the licensee has an action to replace discharge piping of the fire jockey pump via work order 20569676. These remaining actions are assigned and tracked via NCR 2563931. Based on review of the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the remaining actions prior to the period of extended operation.
- Commitment 12: Enhancement for Fuel Oil Chemistry Program to monitor and control fuel oil contaminants to prevent significant degradation and ensure components function properly. Status: Incomplete. The licensee has an action to update CRC-001 prior to the PEO via Procedure Review Request (PRR)2555997 to ensure that when monitored parameters are exceeded, these events will be entered into the licensee's Corrective Action Program.
Additionally, it will add particulate sampling for the diesel driven fire pump tank, and the frequency of particulate contamination sampling will be adjusted.
These actions are being tracked via NCR 2563931. Based on the review of licensee actions completed at the time of this inspection, the timeliness of those actions, and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet the commitment.
Therefore, no follow-up inspection is warranted.
- Commitment 13: Enhancements to the Reactor Vessel Surveillance Program.
Status: Complete.
- Commitment 14: Implement the One-Time Inspection Program. Status:
Incomplete. At the time of the inspection, the licensee had completed engineering evaluations for the majority of the one-time inspections associated with the License Renewal Application; however, three inspections remain outstanding:
- (1) one work order (WO 20297633) under the Secondary Water Chemistry Verification set,
- (2) pending ultrasonic thickness measurements requiring engineering evaluation under the Lubricating Oil Analysis Verification set, and
- (3) remaining inspections of the Essential Chilled Water Compressors Lube Oil Cooling System components. The licensee plans to update Engineering Change (EC) 417936 to incorporate the results of these inspections upon completion. The inspection team reviewed the completed inspection documentation and verified that EC 417936 accurately identifies the remaining inspections. The team also confirmed that the licensee has established a program to ensure completion of these inspections prior to the PEO. Based on the review of the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet the commitment. Therefore, no follow-up inspection is warranted.
- Commitment 15: Enhancements to the Selective Leaching of Materials Program. Status: Complete.
- Commitment 16: Implement the Buried Pipes and Tanks Inspection Program. Status: Incomplete. The licensee has an action to update existing PM 3003750 via PMCH 2557721 to create a 10-year inspection to either credit an opportunistic inspection or create a work request for a planned buried pipe inspection to start 5 years into the period of extended operation. The PMCH will also modify the due date to document and resolve results of the 10-year buried pipe program to be started 7 years into the period of extended operation. Both of the PMs will be modified to have a 10-year frequency. These actions are being tracked for completion in NCR 2563931. Based on review of the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the required updates of PM 3003750.
- Commitment 17: Implement the One-Time Inspection of ASME Code Class 1 Small-Bore Program. Status: Incomplete. The licensee has remaining one additional volumetric examination to perform on a class 1 butt weld with NPS less than 4" in order to sample the required population. Additional ultrasonic inspections will be performed via work order 20683559 during refueling outage H1R26 (October 2025) on line 1RC3-28SN. Based on review of the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the remaining ultrasonic exam to meet the commitment.
- Commitment 18: Enhancements to the External Surfaces Monitoring Program.
Status: Complete.
- Commitment 19: Enhancements to the Flux Thimble Tube Inspection Program. Status: Complete.
- Commitment 20: Enhancements to the Inspection of Internal Surfaces of Miscellaneous Piping and Ducting Components Program. Status: Complete.
- Commitment 21: Enhancements to the Lubrication Oil Analysis Program.
Status: Complete.
- Commitment 22: Enhancements to the ASME Section XI, Subsection IWE Program. Status: Complete.
- Commitment 23: Enhancements to the 10 CFR 50, Appendix J Program.
Status: Complete.
- Commitment 24: Enhancements to the Masonry Wall Program. Status:
Complete.
- Commitment 25: Enhancements to the Structures Monitoring Program. Status:
Complete.
- Commitment 26: Enhancements to the RG 1.127 Inspection of Water Control Structures Associated with Nuclear Power Plants Program. Status: Complete.
- Commitment 27: Implement the Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program.
Status: Complete.
- Commitment 28: Implement the Electrical Cables and Connections not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits Program. Status: Complete.
- Commitment 29: Implement the Inaccessible Medium Voltage Cables not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program.
Status: Complete.
- Commitment 30: Implement the Metal Enclosed Bus Program: Status:
Incomplete. The licensee has one remaining license renewal activity to complete. Specifically, the inspection of the 480V Crosstie connecting Auxiliary Bus 1D1 to Auxiliary Bus 1E1 (1EE-E135) is scheduled to be performed online in May 2026 (PMID 81687-01). Based on the review of the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #30. Therefore, no follow-up inspection is warranted.
- Commitment 31: Implement the Electrical Connections not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program. Status: Complete.
- Commitment 32: Enhancements to the Reactor Coolant Pressure Boundary (RCPB) Fatigue Monitoring Program. Status: Complete.
- Commitment 34: Implementation of the Oil-Filled Cable Testing Program.
Status: Commitment is no longer applicable. After the renewed license was issued, the licensee changed the design of the plant via EC 284155 to remove the oil-filled cables that provided offsite power from the Switchyard to the Start-up Transformers (SUT-1A and SUT-1B) and replace them with 230 kV overhead lines. Upon removing the oil-filled cables from service, the licensee retired the Oil-Filled Cable Test Program and removed it from the FSAR.
- Commitment 36: Standalone commitment to replace elastomeric and thermoplastic components and add them to the Preventative Maintenance Program. Status: Complete.
- Commitment 37: Standalone commitment to update the piping design specification to reflect the current design basis operation transients used in the Time-Limited Aging Analysis for the reactor coolant pressure boundary.
- (2) Changes to license renewal commitments and the UFSAR supplement for license renewal As part of the review of license renewal commitments, AMPs, and TLAAs described in this report, the inspectors reviewed license renewal commitment change documents to verify the licensee followed the guidance in NEI 99-04, Guidelines for Managing NRC Commitment Changes, for any change to the commitments, including their elimination. The team verified that the licensee properly evaluated, reported, and approved where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59.
The team also reviewed the licensees procedures for commitment revision to obtain reasonable assurance that future changes to regulatory commitments would follow the guidance in NEI 99-04, and would properly evaluate, report, and approve changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 21, 2025, the inspectors presented the Post Approval Site Inspection for License Renewal (Phase II) inspection results to Carolyne Joseph, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Editorial Correction Needed for Calculation HNP-P/LR-5501
07/29/2025
License Renewal Administrative Controls
08/05/2025
NCR 2564080
HNP License Renewal Commitment 17 Missing Inspection
08/06/2025
Corrective Action
Documents
Resulting from
Inspection
NCR 2564148
NRC Phase II License Renewal Inspection: Fire Surveillance
Records Not Retained
08/07/2025
CRC-001
HNP Environmental and Chemistry Sampling and Analysis
Program
Revision 45
FPT-3580
Completed 18-Mo Fire Wrap Surveillance
03/30/2021
HNP-LR-001
Reactor Vessel Internals Aging Management Activities
Implementation Plan
Revision 4
HNP-LR-002
Primary Water Stress Corrosion Cracking of Nickel Alloys
and Nickel-Alloy Penetration Nozzles Welded to the Upper
Reactor Vessel Closure Heads of Pressurized Water
Reactors Program Implementation Plan
Revision 2
HNP-LR-004
HNP License Renewal Thermal Aging and Neutron
Irradiation Embrittlement of Cast Austenitic Stainless Steel
(CASS) Program
Revision 2
HNP-LR-009
Inspection of Overhead Heavy Load and Light Load Handling
Systems Program Implementation Plan
Revision 2
HNP-LR-012
HNP License Renewal Fuel Oil Chemistry Control Program
Revision 2
HNP-LR-014
HNP One Time Inspection Program Implementation Plan
Revision 1
HNP-LR-015
HNP License Renewal Selective Leaching of Materials
Program
Rev 1
HNP-LR-019
Flux Thimble Tube Inspection Program Implementation Plan
Revision 2
HNP-LR-021
HNP Lubrication Oil Analysis Program Implementation Plan
Revision 2
HNP-LR-022
ASME Section XI, Subsection IWE Program Implementation
Plan
Revision 2
HNP-LR-023
CFR 50, Appendix J Program Implementation Plan
Revision 1
71003
Procedures
HNP-LR-028
HNP Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
Used in Instrumentation Circuits Program Implementation
Plan
Revision 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
HNP-LR-029
HNP Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
Program Implementation Plan
Revision 4
HNP-LR-030
HNP Metal Enclosed Bus Implementation Plan
Revision 2
HNP-LR-031
HNP Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program
Implementation Plan
Revision 2
HNP-LR-032
HNP Reactor Coolant Pressure Boundary Fatigue Monitoring
Program
Revision 1
HNP-LR-037
HNP Piping Specification Design Update Implementation
Plan
Revision 1
MMM-010
Threaded Fastener Tightening Procedure
Revision 021