IR 05000321/2025004
| ML26015A128 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/28/2026 |
| From: | Catherine Scott NRC/RGN-II/DORS/PB3 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2025004 | |
| Download: ML26015A128 (0) | |
Text
SUBJECT:
EDWIN I. HATCH - INTEGRATED INSPECTION REPORT 05000321/2025004 AND 05000366/2025004
Dear Jamie Coleman:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch. On January 27, 2026, the NRC inspectors discussed the results of this inspection with Mr. Carl James Collins, Licensing Manager, 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, Christian B. Scott, Acting Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000321 and 05000366
License Numbers:
Report Numbers:
05000321/2025004 and 05000366/2025004
Enterprise Identifier:
I-2025-004-0014
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Edwin I. Hatch
Location:
Baxley, GA
Inspection Dates:
October 1, 2025 to December 31, 2025
Inspectors:
R. Easter, Resident Inspector
D. Hardage, Senior Resident Inspector
K. Kirchbaum, Senior Operations Engineer
T. McGowan, Emergency Preparedness Inspector
M. Rich, Emergency Preparedness Inspector
J. Walker, Sr Emergency Preparedness Inspector
Approved By:
Christian B. Scott, Acting Chief
Reactor Projects Branch 3
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Edwin I. Hatch, 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 05000366/2025-003-00 Unit 2, Manual Reactor SCRAM Due to Trip of Both Reactor Recirculation Pumps 71153 Closed LER 05000321/2025-002-00 Unit 1, Reactor Protection System Instrumentation for Turbine Control Valve Fast Closure Inoperable 71153 Closed
PLANT STATUS
Unit 1 operated at or near rated thermal power (RTP) at the beginning of the inspection period.
On November 26, 2025, power was reduced to approximately 50 percent RTP to remove condenser waterboxes from service and plug leaking condenser tubes. The unit returned to RTP on November 29, 2025. On December 17, power was reduced to approximately 68 percent RTP to support control rod pattern adjustments and turbine valve testing. The unit returned to RTP on December 19, 2025, and remained at or near that level for the remainder of the inspection period.
Unit 2 operated at or near RTP at the beginning of the inspection period. On October 9, 2025, the unit experienced a recirculation pump runback signal, resulting in a power reduction to 78 percent RTP. The unit returned to RTP on October 12, 2025, and remained at or near that level for the remainder of the 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
71111.04 - 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 2 division 1 of residual heat removal (RHR) system on October 21 through 23, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Unit 2 reactor building 185' elevation on October 3, 2025
- (2) Main control room, control building 164' elevation on November 13, 2025
- (3) Unit 1 reactor building 203' elevation on December 9, 2025
- (4) Cable spreading room, control building 147' elevation on December 23, 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 and evaluation of the overall pass/fail results of individual operating examinations, crew simulator operating examinations, and 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 review included licensed operator examination failure rates for the annual requalification operating exam administered on December 3, 2025, and the biennial written examinations completed on December 18, 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 Unit 1 main control room during control rod pattern adjustment on October 26, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated annual requalification simulator exams on October 14, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Reviewed maintenance rule (i.e., 10 CFR 50.65) evaluation for condition monitoring events related to the post accident monitoring system on December 9, 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) Condition Report (CR) 11217771. Station service battery 1A cell 11 missing nut and washer on October 8, 2025.
- (2) CR 11220791. Unit 1 D plant service water (PSW) pump 4160-volt breaker racking issue on October 17, 2025.
- (3) CR 11223929. Local power range monitor (LPRM) current-amperage (I/V) curve 28-13C found outside expected reading on October 29, 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) (6 Samples)
- (1) Procedures 34SV-E11-002-2 and 34SV-E11-001-2, Unit 2 RHR pump and valve operability test after a maintenance outage of the B RHR pump, reviewed on October 25, 2025.
(2)34SV-P41-001-1, Unit 1 PSW pump operability test after replacement of the A PSW pump, reviewed on November 12, 2025.
(3)34SV-P41-001-1, Unit 1 PSW pump operability test after replacement of the B PSW pump on November 22, 2025.
(4)34SO-E51-001-1, Unit 1 reactor core isolation cooling (RCIC) pump room cooler functional test after RCIC A room cooler maintenance on December 4, 2025.
- (5) Leak test of the Unit 1 PSW D173B isolation valve, 1P41-1416B, after disassembly and repair on December 6, 2025.
(6)34SV-R43-005-2, emergency diesel generator 1B fast-start test after replacement of the diesels governor servo booster on December 12, 2025.
Surveillance Testing (IP Section 03.01) (1 Sample)
- (1) Procedure 34SV-C71-005-1, turbine control valve fast-closure instrument functional test on December 17, 2025.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) The inspectors observed and evaluated licensee staff activities at the simulator building and the Joint Information Center (JIC) in Vidalia, GA, during a Hostile Action Base (HAB) evaluated exercise on November 5, 2025.
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Partial Sample)
(1)
(Partial)
The inspectors reviewed and evaluated the proposed scenario for the biennial emergency plan exercise (i.e., HAB) thirty days prior to the exercise scheduled for November 5, 2025.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (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)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2024, through September 30, 2025)
- (2) 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 relay failures associated with safety-related valves that might be indicative of a more significant safety issue.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the licensees response to a degraded reactor protection system condition on Unit 1, in which three turbine control valve pressure switches did not actuate the low electrohydraulic control oil-pressure trip during surveillance testing on April 5, 2025. Per IMC 0309, Reactive Inspection Decision Basis for Power Reactors, the NRC considered whether this inspection sample should be the subject of a reactive inspection and determined that a reactive inspection was not necessary, as documented in ADAMS Accession No. ML25106A142.
Event Report (IP Section 03.02) (2 Samples)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2025-003-00, "Edwin I. Hatch Nuclear Plant Unit 2, Manual Reactor SCRAM dure to Trip of Both Reactor Recirculation Pumps," dated November 11, 2025 (ML25315A010). The inspection conclusions associated with this LER are documented in Inspection Report 05000321/2025003, 05000366/2025003, and 07200036/2024001 (ML25339A066) under Inspection Results Section 71153. This LER is Closed.
- (2) LER 2025-002-00, "Edwin I. Hatch Nuclear Plant Unit 1, Reactor Protection System Instrumentation for Turbine Control Valve Fast Closure Inoperable," dated December 19, 2025 (ML25353A533). The inspection conclusions associated with this LER are documented in Inspection Report 05000321/2025003, 05000366/2025003, and 07200036/2024001 (ML25339A066) under Inspection Results Section 71153. This LER is Closed.
Personnel Performance (IP Section 03.03) (2 Samples)
- (1) The inspectors evaluated licensee personnel performance during a Unit 2 speed limiter #3 recirculation pump runback on October 9, 2025.
- (2) The inspectors evaluated licensee personnel performance during the loss of the Unit 1 B essential and instrument electrical buses on November 2, 2025.
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 27, 2026, the inspectors presented the integrated inspection results to Mr. Carl James Collins, Licensing Manager, and other members of the licensee staff.
THIRD PARTY REVIEWS Inspectors reviewed an Institute of Nuclear Power Operations (INPO) report that was issued during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Residual Heat Removal System
Version 45.9
NMP-ES-035-
019-GL02-F03
Control Building El. 147
Version 2.0
NMP-ES-035-
019-GL02-F04
Control Building El. 164
Version 3.0
NMP-ES-035-
019-GL02-F16
U1 Reactor Building El. 203
Version 3.0
Fire Plans
NMP-ES-035-
019-GL02-F32
U2 Reactor Building El. 185
Version 1.0
H-LTC-SE-00124
Simulator Exam
Version 5.0
Miscellaneous
H-LTC-SE-00151
Simulator Exam
Version 4.0
Version
30.15
Procedures
NMP-RE-008-F02
Simplified Reactivity Management Plan
10/26/2025
Functional failure of Unit 1 Z99-01 PAMs
04/11/2025
CR 11149598
1T48R609 Recorder screen is blank
2/08/2025
CR 11164006
Unit 1 Z99 FF reclassified as CME
03/25/2025
Corrective Action
Documents
TE 1170923
MRE--1T48R609 Recorder screen is blank
03/08/2025
Engineering
Evaluations
EVAL-H-Z99-
06870
Maintenance rule evaluation for Post Accident Monitoring
11/19/2025
Work Orders
SNC2311021
Replace recorder LED screen for 1T48R609
2/09/2025
Corrective Action
Documents
CR 11220791
1D PSW pump 4160v breaker racking issue
10/17/2025
Corrective Action
Documents
CR 11236154
Unit 1 TCV #1 failed to actuate half scram during testing
2/17/2025
Residual Heat Removal Pump Operability
10/25/2025
RHR Valve Operability
10/25/2025
Plant Service Water Pump Operability
11/09/2025
Diesel, Alternator, and Accessories Inspection
Version 33.4
Procedures
NMP-MA-014-001
Post Maintenance Testing Guidance
Version 5.14
Work Orders
SNC1110059
Replace the Governor Servo-Booster 1R43-A778B on 1R43-
S001B
2/12/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC640488
Disassemble and inspect 4 inch Anchor Darling carbon steel
flex wedge gate valve and make necessary repairs
2/06/2025
Miscellaneous
25EX03
Plant Hatch Hostile Action Based Drill 25EX03
25EX03
71151
Miscellaneous
Performance Indication Data Hatch Units 1 & 2 for period
10/1/2024-9/30/2025
Corrective Action
Documents
CR 11185539
2E11-K75A RHR LPCI pump timer found INOP
06/09/2025
Engineering
Evaluations
TE 1179904
Failure Analysis Tracking
6/11/2025
NMP-ES-007-008
Equipment Failure Trending
Version 9.0
NMP-GM-002
Corrective Action Program
Version 20.0
Procedures
NMP-GM-051
Trending, Gap Identification, Analysis, and Closure
Version 2.0
CR 11218881
Unit 2 received #3 Recirc Runback
10/09/2025
Corrective Action
Documents
CR 11224973
Loss of 600-120/208V essential transformer 1C
11/02/2025