IR 05000400/2024004
| ML25042A136 | |
| Person / Time | |
|---|---|
| Site: | Harris  (NPF-063) |
| Issue date: | 02/11/2025 |
| From: | Katie Mccurry NRC/RGN-II/DORS/PB2 |
| To: | Haaf T Duke Energy Progress |
| References | |
| IR 2024004 | |
| Download: ML25042A136 (1) | |
Text
SUBJECT:
SHEARON HARRIS NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000400/2024004
Dear Thomas Haaf:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Shearon Harris Nuclear Plant. On January 29, 2025, the NRC inspectors discussed the results of this inspection with David Hoffman 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, Katherine H. McCurry, Chief Projects Branch 2 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-2024-004-0016
Licensee:
Duke Energy Progress, LLC
Facility:
Shearon Harris Nuclear Plant
Location:
New Hill, North Carolina
Inspection Dates:
October 01, 2024, to December 31, 2024
Inspectors:
M. Bates, Senior Operations Engineer
D. Jung, Acting Senior Resident Inspector
M. Kay, Resident Inspector
A. Ruh, Acting Senior Resident Inspector
Approved By:
Katherine H. McCurry, 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 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
Type Issue Number Title Report Section Status LER 05000400/2024-001-01 LER 2024-001-01 for Shearon Harris, Unit 1,
Automatic Reactor Trip Due to Main Generator Lock-Out 71153 Closed LER 05000400/2024-001-00 LER 2024-001-00 for Shearon Harris Nuclear Power Plant, Unit 1,
Automatic Reactor Trip Due to Main Generator Lock-Out 71153 Closed
PLANT STATUS
Unit 1 operated at or near rated thermal power for the entire inspection 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the emergency diesel generator system and feedwater system on November 14, 2024.
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)circuits between the offsite transmission network and the onsite Class 1E distribution system on December 23, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the 'A' emergency diesel generator system after semi-annual testing on November 19, 2024.
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)reactor auxiliary building 236' elevation (fire zone 1-A-3-PB and 1-A-3-TA) and 261' elevation (fire zone 1-A-4-CHILR) on October 9, 2024 (2)reactor auxiliary building 305' elevation (fire zone 12-A-6-HV7) on November 15, 2024 (3)reactor auxiliary building 305' elevation (fire zone 12-A-6-CHF1&2) and 324' elevation (fire zone 12-A-7-HV) on November 25, 2024
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 25, 2024, and the biennial written examinations completed on March 8, 2024.
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 4B feedwater heater level perturbation on November 13, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a portion of an annual requalification operating test in the simulator involving reactor coolant pump seal leak and main steam line rupture outside containment on October 16, 2024.
71111.12 - Maintenance Effectiveness
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remained capable of performing its intended function:
(1)emergency diesel generator 1B fuel control shaft lubrication on December 23, 2024
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 due to planned alternate seal injection pump quarterly testing on November 15, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) NCR 2537650, 1MS-231 failed to open and failed stroke time to shut during Operations Surveillance Test (OST)-1038
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) (1 Sample)
- (1) Operations Performance Test (OPT)-1530, "Dedicated Shutdown Diesel Generator (DSDG) Operability Test Monthly," following annual DSDG maintenance on October 22, 2024
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Maintenance Surveillance Test (MST)-I0055, "Reactor Coolant Flow Channel Calibration (F-0414)," on November 13, 2024
- (2) MST-I0122, "Pressurizer Pressure P-0455 Operational Test," on November 18, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) OST-1211, "Auxiliary Feedwater Pump 1A-SA Operability Test," on November 19,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) October 1, 2023, through September 30, 2024
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) October 1, 2023, through September 30, 2024
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)failure to test safe shutdown 6.9 kilovolt (kV) relays (NCR 02519253)
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program and related documents such as trend reports, self-assessments, and quality assurance audits to identify potential trends that might be indicative of a more significant safety issue.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
- (1) Licensee Event Report (LER) 4002024001/2024-001-00, Automatic Reactor Trip due to Main Generator Lock-Out, ADAMS Accession No. ML24204A192. The inspector conclusions associated with this LER are documented in inspection report 05000400/2024003 under the Inspection Results section. This LER is closed.
- (2) LER 4002024001/2024-001-01, Automatic Reactor Trip due to Main Generator Lock-Out, ADAMS Accession No. ML24204A192. The inspector conclusions associated with this LER are documented in inspection report 05000400/2024003 under the Inspection Results section. This LER is closed.
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 29, 2025, the inspectors presented the integrated inspection results to David Hoffman and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
6-G-0038
Turbine Generator Main & Auxiliary Transformer Protective
Relaying Logic Diagram Unit 1
Plant Electrical Distribution System
OPS-1-24-5065-B
UAT ONLINE-
0478(2)
Clearance for B UAT Out of Service
06/19/2024
PRT-1-244-B
UAT-0066(1)
Protected Equipment Scheme for B UAT Out of Service
07/26/2024
Miscellaneous
PSC-1-24-5132-C
XFMR OILSW-
282
Clearance for C Main Transformer Oil Level Cutout Switch
2/05/2024
Engineering
Changes
400765
F, SL, PQL-0,1,2,3, Various, Shelf-Life Requirements,
MJH/TS
Miscellaneous
EPRI TR1019518
Nuclear Maintenance Applications Center: Lubrication Guide
AD-EN-ALL-0045
Nuclear Chemical Control
AD-SC-ALL-0100
Nuclear Procurement Program
IA-SC-ALL-0001
Supply Chain Departmental Interface Agreement
Procedures
MPT-M0013
Emergency Diesel Generator Fuel Control Shaft Lubrication
Work Orders
20697973
B-401-1273
Control Wiring Diagram Main Steam Line 1A Drain isolation
VA 2MS-V59-5AB-1
G-0042
Flow Diagram Main Steam System Unit 1
Drawings
S-0542
Simplified Flow Diagram Main Steam System Unit 1
Procedures
APP-ALB-020
Main Control Board
56