ML26022A350
| ML26022A350 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/26/2026 |
| From: | Matthew Fannon NRC/RGN-II/DORS/PB2 |
| To: | Krakuszeski J Duke Energy Progress |
| References | |
| IR 2025004 | |
| Download: ML26022A350 (0) | |
Text
John A. Krakuszeski Site Vice President Duke Energy Progress, LLC 8470 River Road SE Mail Code: BNP04 Southport, NC 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - INTEGRATED INSPECTION REPORT 05000324/2025004 AND 05000325/2025004
Dear John A. Krakuszeski:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant. On January 8, 2026, the NRC inspectors discussed the results of this inspection with Mark DeWire 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, Matthew S. Fannon, Chief Projects Branch 2 Division of Operating Reactor Safety Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71
Enclosure:
As stated cc w/ encl: GovDelivery Subscriber January 26, 2026 Signed by Fannon, Matthew on 01/26/26
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DORS RII/DORS RII/DORS NAME K. Carrington A. Wilson M. Fannon DATE 01/26/2026 01/23/2026 01/26/2026
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000324 and 05000325 License Numbers:
DPR-62 and DPR-71 Report Numbers:
05000324/2025004 and 05000325/2025004 Enterprise Identifier:
I-2025-004-0019 Licensee:
Duke Energy Progress, LLC Facility:
Brunswick Steam Electric Plant Location:
Southport, NC Inspection Dates:
October 1, 2025, to December 31, 2025 Inspectors:
M. Bates, Senior Operations Engineer K. Carrington, Senior Resident Inspector C. Curran, Resident Inspector Approved By:
Matthew S. Fannon, Chief Projects Branch 2 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Brunswick Steam Electric 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.
3 PLANT STATUS Unit 1 began the inspection period operating at 100 percent rated thermal power (RTP) where it remained throughout the entire period with the exception of occasional down powers to perform control rod pattern improvements, rod sequence exchanges, and planned balance-of-plant (secondary) system activities, on the following dates:
October 16, 2025, 73 percent for rod improvement November 14, 2025 - 65 percent for rod sequence exchange and scram time testing November 17, 2025-81 percent for rod improvement December 1, 2025 - 70 percent for rod improvement December 16, 2025 - 87.5 percent for rod improvement December 30, 2025 - 70 percent for rod improvement and condensate demineralizer system maintenance Unit 2 began the inspection period operating at 100 percent RTP where it remained throughout the entire period with the exception of occasional down powers for control rod sequence exchanges, and planned balance-of-plant (secondary) system activities, on the following dates:
December 5, 2025 - 60 percent for rod sequence exchange, reactor feed pump filter swaps, and condensate demineralizer system maintenance December 8, 2025 - 80 percent for rod sequence exchange 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)
Unit 2 train B residual heat removal (RHR) system while Unit 2, train 'A' RHR and RHR service water systems were out-of-service (OOS) for planned maintenance, on October 2, 2025 (2)
No. 3 emergency diesel generator (EDG) system while No. 4 EDG system was OOS for planned maintenance, on December 9, 2025
4 71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations and biennial written examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with IP 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
(1)
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on October 2, 2025, and the biennial written examinations completed on October 8, 2025.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the control room during a Unit 2 down power for a control rod improvement on September 29, 2025; a control rod sequence exchange on October 5, 2025; and troubleshooting and recovery of control rod 34-03, following directional control valve actuator maintenance on October 8, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated requalification scenario exam LORX-004 related to a reactor building ventilation radiation monitor failure, loss of conventional service water, anticipated transient without a scram, and a main steam isolation valve closure, on October 16, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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 reactivity risk during Unit 2 down power for rod sequence exchange and out-of-band chemistry parameters due to condensate demineralizer system issues, the week of December 5, 2025
5 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) (4 Samples)
(1) 2PT-24.1-2, "Service Water Pump and Discharge Valve Operability Test," following replacement of the 2A nuclear service water pump motor under work order (WO) 20751571, on October 10, 2025 (2) 0PT-12.2A, "No. 1 Diesel Generator Monthly Load Test," following 2-DG1-DA and 2-DG1-DB relay replacements under WOs 20286836, 20721049, and 20749084, on October 14, 2025 (3) 0SPP-HYDRO501, "Functional Pressure Testing," following replacement of EDG No.
3 jacket water heater pump under WO 20762100-01, on December 10, 2025 (4)
Post-maintenance checks on the 2E control building heating, ventilation, and air conditioning system (HVAC) following replacement of the 2E HVAC compressor breaker under WO 2075887, on November 21, 2025 Surveillance Testing (IP Section 03.01) (1 Sample)
(1) 0PT-10.1.1, "RCIC System Operability Test," on December 8, 2025 Inservice Testing (IST) (IP Section 03.01) (3 Samples)
(1) 0PT-10.1.8, "RCIC [reactor core isolation cooling] System Valve Operability Test," on October 6, 2025 (2) 0PT-7.2.4B, Core Spray System Operability Test - Loop B, on October 20, 2025 (3) 0PT-09.2, "HPCI [high pressure coolant injection] System Operability Test," on December 9, 2025 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
(1)
Unit 1 (October 1, 2024, through September 30, 2025)
(2)
Unit 2 (October 1, 2024, through September 30, 2025)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
(1)
Unit 1 (October 1, 2024, through September 30, 2025)
(2)
Unit 2 (October 1, 2024, through September 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
(1)
Unit 1 (October 1, 2024, through September 30, 2025)
(2)
Unit 2 (October 1, 2024, through September 30, 2025)
6 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
(1)
Unit 1 (July 1, 2024, through June 30, 2025)
(2)
Unit 2 (July 1, 2024, through June 30, 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
(1)
Unit 1 (July 1, 2024, through June 30, 2025)
(2)
Unit 2 (July 1, 2024, through June 30, 2025) 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program for the period of January 1 to November 17, 2025, for a potential adverse trend in control building HVAC system performance that might be indicative of a more significant safety issue.
The inspectors did not identify a negative trend that could lead to a more significant safety issue since the issue was captured in the licensee's corrective action program, and a success path was developed to resolve ongoing and future operational issues of the system.
INSPECTION RESULTS No findings were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On January 8, 2026, the inspectors presented the integrated inspection results to Mark DeWire and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed the results of the 2025 Institute on Nuclear Power Operations report that was issued during the inspection period.
7 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Drawings D-02273, Sheet 2A Diesel Generator Jacket Water System Piping Diagram 15 71111.04 Procedures 0OP-39 Diesel Generator Operating Procedure 209 Drawings 0-FP-2908 Jacket Water Heater Pump - Curve 04/20/1972 Miscellaneous FP-20322 Diesel Engine Instruction Manual 00T 0PT-09.2 HPCI System Operability Test 10/29/2025 0PT-10.1.1 RCIC System Operability Test 115 Procedures 0PT-10.1.8 RCIC System Valve Operability Test 10/06/2025 71111.24 Work Orders 20762100-01 2-MUD-HTR-CIRC-PUMP-3, Jacket Water Heater Pump Replacement 71152S Corrective Action Documents CR 02540368, CR 02541068, CR 02544987, CR 02553024, CR 02567633, CR 02572905, CR 02575541, CR 02576382, CR 02492699