ML25335A037
| ML25335A037 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/04/2025 |
| From: | Matthew Fannon NRC/RGN-II/DORS/PB2 |
| To: | Krakuszeski J Duke Energy Progress |
| References | |
| IR 2025003 | |
| Download: ML25335A037 (0) | |
Text
John A. Krakuszeski Site Vice President Duke Energy Progress, LLC 8470 River Road SE Mail Code: BNP001 Southport, NC 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - INTEGRATED INSPECTION REPORT 05000324/2025003 AND 05000325/2025003
Dear John A. Krakuszeski:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant. On November 20, 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 1, 2025, the NRC began operating under its Office of Management and Budget (OMB)-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 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.
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.
December 4, 2025
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: Distribution via LISTSERV Signed by Fannon, Matthew on 12/04/25
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE PB2/DORS PB2/DORS PB2/DORS NAME A. Wilson K. Carrington M. Fannon DATE 12/3/2025 12/3/2025 12/4/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000324 and 05000325 License Numbers:
DPR-62 and DPR-71 Report Numbers:
05000324/2025003 and 05000325/2025003 Enterprise Identifier:
I-2025-003-0019 Licensee:
Duke Energy Progress, LLC Facility:
Brunswick Steam Electric Plant Location:
Southport, NC Inspection Dates:
July 1, 2025, to September 30, 2025 Inspectors:
S. Battenfield, Operations Engineer B. Bishop, Senior Project Engineer C. Curran, Senior Resident Inspector M. Donithan, Senior Operations Engineer C. Dorman, Resident Inspector J. Hickey, Senior Project Engineer D. Orr, Senior Project Engineer J. Walker, Senior Emergency Preparedness Inspector A. Wilson, Senior Project Engineer 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) and operated there until September 6, 2025, when power was reduced to 70 percent RTP for a control rod pattern adjustment. The unit was restored to 100 percent RTP on September 7, 2025, where it continued to operate for the remainder of the period.
Unit 2 began the inspection period operating at 100 percent RTP and operated there until September 20, 2025, when power was reduced to 70 percent RTP for a control rod pattern adjustment. The unit was restored to 100 percent RTP on September 20, 2025, where it continued to operate for the remainder of the 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) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
Unit 1, 'A' train residual heat removal (RHR) system while train B RHR was out of service for maintenance, on September 10, 2025 Complete Walkdown Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated system configurations during a complete walkdown of the Unit 2 high pressure coolant injection (HPCI) system, on July 17, 2025.
71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
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:
4 (1)
Unit 2, reactor building 98 (RB2-18/18GA/19) and 117 (RB2-01M) elevations, on July 17, 2025 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the onsite fire brigade training and performance during unannounced fire drills, on August 29, 2025 (17-F-TB-02), and September 18, 2025 (15-F-TY-01).
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 1 down power and control rod pattern adjustment, on September 5, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
(1)
The inspectors observed and evaluated a simulator scenario conducted for licensed operator requalification training exam LREG-043, on September 3, 2025. The scenario consisted of a level transmitter failure, condenser air in-leakage, and a reactor core isolation cooling (RCIC) system steam line break and failure to isolate.
(2)
The inspectors observed and evaluated an evaluated simulator scenario conducted for licensed operator annual requalification exam LREG-202, on September 10, 2025.
The scenario consisted of a recirculation loop 'A' flow transmitter failure, followed by a loss of offsite power and a small break loss of coolant accident.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (5 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)
Thermal Overload of Diesel Generator 1 Lube Oil Filter Pump Motor on January 9, 2025 (nuclear condition report (NCR) 02540124)
(2)
Control Building Air Cooled Condenser Unit 1D Loss of Refrigerant on January 16, 2025 (NCR 02541068)
(3)
Unit 1, 1-E11-PDV-F068B, Residual Heat Removal Heat Exchanger Service Water Discharge Valve Breaker Trip while Closing on January 19, 2025 (NCR 02541178)
(4)
Unit 2, 2-E11-F048B, Residual Heat Removal Heat Exchanger Bypass Valve Magnetics Coil Trip while Closing on March 17, 2025 (NCR 02547563)
(5)
Unit 2 2-E51-F026, Reactor Core Isolation Cooling Steam Drain Pot Isolation Valve Porting Excessive Air on March 19, 2025 (NCR 02547937)
5 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)
Emergency diesel generator (EDG) 4 starting air valve replacement U-bolt (2-DG4-SV-6553-4 and 2-DG4-SV-6554-4) torque measurements (work order (WO) 20640325 01)
EDG 4 reassembly verification following electrical breaker replacement (WO 20610935 01)
Aging Management (IP Section 03.03) (1 Sample)
The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:
(1)
Intake Gantry Crane East Rail Studs in Degraded Condition, on July 17, 2025 (NCR 2554976) 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 during the Unit 2 RCIC outage, on July 8 and July 9, 2025 (2)
Elevated risk during Unit 2, 'A' standby liquid control (SLC) outage, on June 23 and June 24, 2025 (3)
Elevated risk during the EDG 4 outage, from August 11 through August 15, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (8 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
Unit 2 RCIC System Conditions Unable to be Established for ASME OM Code IST Test (NCR 02557580)
(2)
Multiple Test Failures During 1PT-40.2.9 Turbine Control and Stop Valve Closure Test (NCR 02556510)
(3)
Unable to Meet 0PT-10.1.1 RCIC System Operability Test Required Flow (NCR 02561001)
(4)
EDG 1 Diesel Damper Thermostat Not Controlling Damper (NCR 02559625)
(5) 1A RPS MG Set Voltage Trending Upwards (NCR 02562055)
(6)
Unit 2 RCIC Steam Line Drain Valve, 2-E51-V83, Mechanically Bound (NCR 02560441)
(7)
SLC Continuity Loss Alarm When Swapping Circulation Water Intake Pumps (NCR 02557268)
6 (8)
HPCI Turbine Stop Valve Trip Not Changing State (NCR 02557257) 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) (8 Samples)
(1) 1PT-24.1-1, "Service Water Pump and Discharge Valve Operability Test," Rev. 99 following 1-SW-PV-116, 1A conventional service pump discharge strainer blowdown valve and actuator maintenance in accordance with (IAW) WO 20581750 (2)
Post maintenance checks following 1B conventional service water pump discharge strainer maintenance IAW WO 20724578 (3) 1SP-EC422040-001, "Post-Modification Testing for DG2 Overspeed System Upgrade," Rev. 0 following diesel generator 2 modifications IAW WO 20578745 (4) 1PT-24.1-1, "Service Water Pump and Discharge Valve Operability Test," Rev. 99 following 1B nuclear service water pump discharge strainer rebuilds IAW WO 20419318 (5) 0PT-10.1.1A, RCIC System Component Test, Rev. 24 following valve motor operator rebuild IAW WO 20417942 02 (6) 0PT-06.1, Standby Liquid Control System Operability Test, Rev. 91 following environmentally qualified pump breaker replacement IAW WO 20499815 (7) 0PT-12.3.2D, "No. 4 Diesel Generator (DG) Starting Air Valve Operability Test,"
following DG engine air start and jet assist solenoid valve replacements IAW WO 206440325 (8) 0PT-07.2.4A, Core Spray System Operability Test - Loop A, Rev. 89 following valve motor operator rebuild IAW WO 20716850 Surveillance Testing (IP Section 03.01) (1 Sample)
(1) 1MST-RHR28BR, "RHR B Loop Time Delay Relay Channel Cal," on July 23, 2025 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1)
CSD-BNP-SSD-FLX-003, Triennial Flex Testing, IAW WO 20205214 and WO 20740723 71114.02 - Alert and Notification System Testing Inspection Review (IP Section 02.01-02.04) (1 Sample)
(1)
The inspectors evaluated the maintenance and testing of the alert and notification system during the week of August 11, 2025.
71114.03 - Emergency Response Organization Staffing and Augmentation System Inspection Review (IP Section 02.01-02.02) (1 Sample)
(1)
The inspectors evaluated the readiness of the emergency response organization during the week of August 11, 2025.
7 71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03) (1 Sample)
(1)
The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of August 11, 2025. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
(1)
The inspectors evaluated the maintenance of the emergency preparedness program during the week of August 11, 2025.
OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
(1)
April 1, 2024, through June 30, 2025 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
(1)
April 1, 2024, through June 30, 2025 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14) (1 Sample)
(1)
April 1, 2024, through June 30, 2025 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (3 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
Reactor Water Cleanup Inboard Isolation Valve (1-G31-F001) Closure during Wire Lift (NCR 2528266)
(2)
Investigate Feedwater Heater 1-2A Level High (NCR 02532034)
(3)
Allen-Bradley 700-RTC Relay Failure, specifically 2-DG2-RTR, that Rendered EDG-2 Inoperable and Unavailable (NCR 02537739)
INSPECTION RESULTS No findings were identified.
8 EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On November 20, 2025, the inspectors presented the integrated inspection results to John A. Krakuszeski and other members of the licensee staff.
On August 14, 2025, the inspectors presented the emergency preparedness program inspection results to Mark Dewire and other members of the licensee staff.
9 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date LREG-043 Level transmitter failure, Condenser air in-leakage, RCIC steam line break with a failure to isolate 09/03/2025 71111.11Q Miscellaneous LREG-202 Recirculation Loop A flow transmitter failure, Loss of offsite power, small break loss of coolant accident 09/10/2025 NCR 02547937 2-E51-F026 RCIC Steam Drain Pot Isol Valve Porting Excessive Air 03/19/2025 71111.12 Corrective Action Documents NCR 2540124 Thermal Overload of DG1 Lube Oil Filter Pump Motor 01/09/2025 EC 425109 UNIT 1 Temporary Bypass of 1A Recirc Runback Limiter 1.
Install Jumper to Prevent VFD Runback Limiter #1 Initiation from DFCS Rev 000 71111.18 Engineering Changes EC422063 RHR-SDC HIGH PRESSURE TRIP LOGIC TIME DELAY RELAY REPLACEMENT Rev 005 AR02512787 0PEP-03.6.3 REV 26 CDAM 50.54(Q) Review (Screen and Eval combined) 05/14/2024 71114.04 Miscellaneous AR02547807 50.54(Q) Review AD-EP-BNP-0407 REV 008 05/12/2025 2023-BNP-EMP-01 NUCLEAR OVERSIGHT - AUDIT BRUNSWICK EMERGENCY PREPAREDNESS 11/02/2023 Miscellaneous 2024-BNP-EMP-PR-01 NUCLEAR OVERSIGHT - PERFORMANCE REVIEW BRUNSWICK EMERGENCY PREPAREDNESS 10/03/2024 AD-EP-ALL-0105 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER REVISION 14 AD-EP-BNP-0105 BNP SITE SPECIFIC TSC SUPPORT REVISION 005 AD-EP-BNP-0106 BNP SITE SPECIFIC OSC SUPPORT REVISION 002 EP-ALL-EPLAN DUKE ENERGY COMMON EMERGENCY PLAN REVISION 6 71114.05 Procedures EP-BNP-EPLAN-ANNEX DUKE ENERGY BRUNSWICK EMERGENCY PLAN ANNEX REVISION 3