IR 05000324/2025004
| 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
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
Inspection Report
Docket Numbers:
05000324 and 05000325
License Numbers:
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
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.
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 DProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 2515,</br></br>Appendix D" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., 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
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
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)
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.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
D-02273, Sheet
2A
Diesel Generator Jacket Water System Piping Diagram
Procedures
Diesel Generator Operating Procedure
209
Drawings
0-FP-2908
Jacket Water Heater Pump - Curve
04/20/1972
Miscellaneous
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
Work Orders
20762100-01
2-MUD-HTR-CIRC-PUMP-3, Jacket Water Heater Pump
Replacement
Corrective Action
Documents
CR 02540368,
CR 02541068,
CR 02544987,
CR 02553024,
CR 02567633,
CR 02572905,
CR 02575541,
CR 02576382,
CR 02492699