IR 05000261/2025004
| ML26016A662 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/22/2026 |
| From: | Matthew Fannon NRC/RGN-II/DORS/PB2 |
| To: | Basta L Duke Energy Progress |
| References | |
| EPID I-2025-004-0021 IR 2025004 | |
| Download: ML26016A662 (0) | |
Text
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT - INTEGRATED INSPECTION REPORT 05000261/2025004
Dear Laura Basta:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at H. B. Robinson Steam Electric Plant. On January 12, 2026, 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.
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 No. 05000261 License No. DPR-23
Enclosure:
As stated
Inspection Report
Docket Number:
05000261
License Number:
Report Number:
Enterprise Identifier:
I-2025-004-0021
Licensee:
Duke Energy Progress, LLC
Facility:
H. B. Robinson Steam Electric Plant
Location:
Hartsville, SC
Inspection Dates:
October 1, 2025, to December 31, 2025
Inspectors:
C. Dorman, Resident Inspector
J. Zeiler, Senior 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 H. B. Robinson 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 2 operated at or near rated thermal power for the entire duration 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)
'A' and 'B' motor driven auxiliary feedwater pumps while the steam driven auxiliary feedwater pump was out-of-service for planned maintenance on November 3, 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)component cooling water (CCW) pump room (fire zone 5) on October 6, 2025 (2)charging pump room (fire zone 4) on October 28, 2025 (3)
'A' and 'B' vital battery room (fire zone 16) on November 12, 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 administered on March 7, 2025, and the biennial written examinations completed on March 7, 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 the following risk significant activities:
- annual Technical Specification required surveillance testing of the 'A' train reactor protection system logic and reactor trip breaker in accordance with procedure MST-020 on November 18, 2025
- calibration of power range nuclear instruments per process instrument calibration procedure 112 on November 20, 2025
- unexpected high pressure feedwater transient during planned repair of 6A feedwater heater normal drain level control valve LCV-1508A on December 3, 2025
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator as-found simulator exam which included a containment cooling fan failure, a seismic event, high main turbine bearing vibrations, and a faulted steam generator in containment on November 18, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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)
'B' service water booster pump trip on September 17, 2025, due to shorted diodes in motor breaker starter relay coil (Nuclear Condition Report (NCR) 02569145)
(2)loss of turbine electrohydraulic control fluid inventory results in rapid unit downpower and removal of main turbine from service (NCR 02557259), review completed November 28, 2025 (3)exceeded performance criteria for unavailability for 'A' CCW pump during maintenance to replace the inboard pump seal (NCRs 02568758, 02569119,
02569188, and 02566982), review completed December 3, 2025 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)preventive maintenance replacement schedule exceeded for 'A' and 'B' emergency diesel generator dresser couplings for the lube oil and jacket water support systems (NCRs 02555345 and 02502887), review completed November 19, 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 risk (Green) during planned maintenance to replace degrading 'A' reactor coolant system (RCS) loop flow transmitter FT-416 electronics on November 5, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) NCR 02572591, NRC inspector-identified 'A' train 125-volt DC vital battery cells 19 and 46 with cracks or bulging deformation in plastic surrounding positive posts with noticeable battery corrosion emanating from locations, review completed on October 17, 2025
- (2) NCR 02571974, 'B' train 125-volt DC vital battery distribution system spurious ground alarms beginning October 10, 2025, review completed on October 23, 2025
- (3) NCR 02573570, RCS loop 'A' flow transmitter FT-416 output slowly drifting downward due to instrument degradation, review completed on November 3, 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) OST-908-2, Component Cooling Water Pump A Test, following completion of an extended maintenance and unavailability period on October 7, 2025
- (2) OST-101-3, CVCS Component Test Charging Pump C, following replacement of plungers and the primary seal on October 15, 2025
- (3) Work Order (WO) 20755434 PMT instructions for validating proper response output following replacement of 'A' RCS loop flow transmitter FT-416 circuitry board due to degraded output performance on November 5, 2025
- (4) WO 20762980 PMT instructions for validating proper response output following emergent replacement of reactor trip protection system overpower delta-temperature degrading circuitry module NM-422B on December 10-11, 2025
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) MST-020, Reactor Protection Logic Train 'A' At Power, on November 18, 2025
- (2) OST-202, Steam Driven Auxiliary Feedwater System Component Test, on December 3, 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) (1 Sample)
- (1) Unit 2 (October 1, 2024, through September 30, 2025)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) Unit 2 (October 1, 2024, through September 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 to identify potential trends in equipment reliability or human 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.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 12, 2026, the inspectors presented the integrated inspection results to Laura Basta and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Auxiliary Feedwater System
Rev. 125
CSD-RNP-PFP-
AB2-0226-001
Auxiliary Building Elevation 226 Pre-Fire Plan
Rev. 3
Fire Plans
CSD-RNP-PFP-
AB2-0246-001
Auxiliary Building Elev 246 Pre-Fire Plan
Rev. 1
AD-FP-ALL-1520
Transient Combustible Control
Rev. 3
AD-FP-ALL-1522
Duties of a Compensatory Fire Watch
Rev. 4
Fire Protection Systems Minimum Equipment and
Compensatory Actions
Rev. 40
Procedures
OMM-002
Fire Protection Manual
Rev. 59
Procedures
PIC-112
F Delta I Calibration
Rev. 18
AD-EG-ALL-1202
Preventive Maintenance and Surveillance Testing
Administration
Rev. 15
Procedures
AD-EG-ALL-1210
Rev. 5
AD-OP-ALL-0210
Operational Risk Management
Rev. 4
AD-WC-ALL-
200
On-Line Risk Management Process
Rev. 22
AD-WC-ALL-
240
On-Line Risk Management Process
Rev. 6
Procedures
CSD-WC-RNP-
240-00
Rev. 1
Procedures
AD-OP-ALL-0105
Rev. 9
Chemical and Volume Control System Charging Pump C
Operation
Rev. 8
Procedures
PLP-033
Post-Maintenance Testing (PMT) Program
Rev. 70
AD-EG-ALL-1217
Mitigating System Performance Index (MSPI)
Rev. 3
71151
Procedures
AD-PI-ALL-0700
Performance Indicators
Rev. 7