IR 05000032/2025010
| ML25349A704 | |
| Person / Time | |
|---|---|
| Site: | Hatch, 05000032  |
| Issue date: | 12/28/2025 |
| From: | Daniel Bacon NRC/RGN-II/DORS/EB2 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2025010 | |
| Download: ML25349A704 (0) | |
Text
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT - FIRE PROTECTION TEAM INSPECTION (FPTI) REPORT 05000321/2025010 AND 05000366/2025010
Dear Jamie Coleman:
On December 9, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2. On October 9, 2025, the NRC inspectors discussed the results of this inspection with the Engineering Director, Fleet and Site fire protection personnel, 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.
Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-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.
However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor 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.
December 28, 2025 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, Daniel M. Bacon, Chief Engineering Branch 2 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:
05000321/2025010 and 05000366/2025010
Enterprise Identifier:
I-2025-010-0047
Licensee:
Southern Nuclear Operating Co., Inc
Facility:
EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2
Location:
Baxley, GA
Inspection Dates:
September 08, 2025 to December 09, 2025
Inspectors:
P. Braaten, Senior Reactor Inspector
W. Monk, Senior Reactor Inspector (Lead)
B. Stuckart, Reactor Inspector
I. Wang, Observing Inspector
Approved By:
Daniel M. Bacon, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a fire protection team inspection at EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2, 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.
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 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
71111.21N.05 - Fire Protection Team Inspection (FPTI) Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)
The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).
a. Review deficiencies or open fire protection impairments for the selected system, including any temporary modifications, operator workarounds, or compensatory measures.
b. Verify that operator actions can be accomplished as assumed in the licensees FHA, or as assumed in the licensees fire probabilistic risk assessment (FPRA)analysis and SSA.
c. Review repetitive or similar maintenance work requests which could be an indicator of a design deficiency and could affect the ability of the components to perform their functions, when needed.
d. Ensure that post maintenance and/or surveillance activities are performed as scheduled.
e. Perform a walkdown inspection to identify equipment alignment discrepancies.
Inspect for deficient conditions such as corrosion, missing fasteners, cracks, and degraded insulation.
f. Ensure the selected SSCs that are subject to aging management review (AMR)pursuant to 10 CFR Part 54 are being managed for aging (e.g., loss of material, cracking, reduction of heat transfer) in accordance with appropriate aging management programs. Verify that the licensees aging management program activities (such as, Fuel Oil Analysis or Selective Leaching Aging Management Program) associated with FP equipment are being implemented.
g. If a review of operating experience issues will be completed for the selected inspection sample, verify that the licensee adequately reviewed and dispositioned the operating experience in accordance with their processes.
- (4) SSC #4 (SSD) - U1/U2 Low Pressure Coolant Injection (LPCI) Systems
Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)
The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.
- (1) FP Admin Program #1 - Hot Work Program
- (2) FP Admin Program #2 - Fire Brigade Drills and Training Program
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
The inspectors verified the following:
a. Changes to the approved FPP do not constitute an adverse effect on the ability to safely shutdown.
b. The adequacy of the design modification, if applicable.
c. Assumptions and performance capability stated in the SSA have not been degraded through changes or modifications.
d. The FPP documents, such as the Updated Final Safety Analysis Report, fire protection report, FHA, and SSA were updated consistent with the FPP or design change.
e. Post-fire SSD operating procedures, such as abnormal operating procedures, affected by the modification were updated.
- (1) FPP Change #1: LDCR23-37 - Update to Hatch TRM Appendix B to Align Compensatory Actions to RER SNC1524271 and RER SNC1524271 - Basis for Risk Informed Compensatory Actions for Fire System Impairments in NFPA 805 Licensed Plants
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On December 9, 2025, the inspectors presented the Fire Protection Team Inspection Exit Meeting inspection results to Jeremy Torrez, Engineering Director and other members of the licensee staff.
THIRD PARTY REVIEWS No review of third-party documentation during the inspection period.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
H-RIE-FIREPRA-
U00-012
Hatch Fire PRA Task 12, Human Reliability Analysis
(HRA)
Rev. 6.0
SMNH-05-011
Determine Diesel Generator Building Switchgear Room
heatup due to a loss of cooling transient
Rev. 1.0
SMNH-05-014
Post LOCA Time Elapsed RHR and CN NPSH Margin
Long Term Operation (>600 Sec)
Rev. 2.0
SMNH-05-015
Post LOCA Time Elapsed RHR and CN NPSH Margin
Long Term Operation (>600 Sec)
Rev. 2.0
SMNH-13-005
Hatch Switchgear Room on Control Building Elevation 130
Heatup Evaluation during an Extended Loss of all AC
Power (ELAP)
Rev. 2
SMNH-16-025
NFPA 12 Code Compliance Review
Rev 2.0
2/10/2024
SMNH-16-080
DGB CO2 Suppression System Calculation
Rev. 2
SMNH-16-084
Documents the evaluation of MOV Pressure Boundary
(PB) components to determine the impact of the
Information Notice 92-18 type "hot short" (motor stall)
event.
Rev. 3.0
SMNH-16-085
Documents the evaluation of MOV Operator Manual
Actions (OMA) components to determine impact of the
Information Notice 92-18 "hot short" motor stall event.
Rev. 2.0
SX11992
FP-LP CO2-FLOW CALCULATIONS-CABLE
SPREADING ROOM
2/01/1973
Calculations
SX11992
FP-LP CO2 Flow Calculation - Cable Spread Room
Rev. 1
Corrective Action
Documents
CR 11142973
Individual Fire Brigade Member Drill Failures
01/16/2025
CR 11208487
25 FPTI - Fire Protection Program References in NMP-
ES-063-GL01 Need Updating
09/03/2025
CR 11210429
25 FPTI - One Fire Drill in 2024 Did Not Meet Program
Requirements
09/10/2025
71111.21N.05
Corrective Action
Documents
Resulting from
Inspection
CR 11210511
25 FPTI - Diesel Generator Recovery Procedure
Correction
09/10/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 11210943
25 FPTI - CO2 Nozzle Inspection NPFA 12
09/11/2025
CR 11210952
25 FPTI - 52SV-FPX-010-0 Procedural Enhancement
09/11/2025
CR 11233548
25 FPTI - Use of Grace Periods for Fire Protection
Surveillances
2/08/2025
B-11988
E.I. HATCH PLANT UNIT NO.1 FIRE PROTECTION FCD
COMPUTER RM (1/2), (2/2)
Rev. 0
H-41508
U1 Turbine & Control Building - Fire Protection Piping -
Rev. 9
H-41509
U1 & U2 Diesel Generator BLD CO2 System P&ID
Rev. 7
SX11786
Computer Room CO2 Schematic
10/05/1973
Drawings
SX11937
FP-LP CO2-HOSE REEL INFO
Rev. 0
LDCR23-37
Update to Hatch TRM Appendix B, to align Compensatory
Action to RER SNC 1524271
Rev. 1.0
SNC1244102
Performance Based Evaluation of Fire Damper
Configurations
Rev. 1.0
Engineering
Changes
SNC1524271
Basis for Risk Informed Compensatory Actions for Fire
System Impairments in NFPA 805 Licensed Plants
replacing RER SNC1133273
Rev. 2.0
NMP-ES-035-
019-GL02-F03
CONTROL BUILDING EL 147 Pre Fire Plan
Rev. 1
NMP-ES-035-
019-GL02-F06
DIESEL GENERATOR BLDG Pre Fire Plan
Rev. 1
NMP-ES-035-
019-GL02-F12
U1 REACTOR BUILDING EL 130 Pre Fire Plan
Rev. 1
Fire Plans
NMP-ES-035-
019-GL02-F29
U2 REACTOR BUILDING EL 130 Pre Fire Plan
Rev. 1
Miscellaneous
NMP-OS-014-
2-TCAF201
Operator Response Time Validation Sheet
06/30/2023
Shutdown from Outside Control Room
Rev. 6.6
Shutdown from Outside Control Room
Rev. 7.5
Fire Procedure
Rev. 18.9
Fire Procedure
Rev. 23.9
Residual Heat Removal System
Rev. 46.9
Procedures
CO2 FIRE SUPPRESSION EQUIPMENT INSPECTION
Rev 1.7
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LOW PRESSURE CO2 SYSTEM SURVEILLANCE
08/21/2025
NMP-ES-035
Rev. 7
NMP-ES-035-014
Fleet Transient Combustible Controls
Rev. 8
NMP-ES-063-
GL01
Hatch License Renewal Program Manual
Rev. 3
NMP-FLS-017
Compressed Gas Safety
Rev. 2
NMP-OS-007-
001
Conduct of Operations Standards and Expectations
Rev. 19
NMP-OS-014-
2
HNP Time Critical Operator Action Program
Rev. 4.1
NMP-TR-425
Fire Drill Program
Rev. 14
NMP-TR-426
Fire Training Program
Rev. 10
SNC0571621
EDDY CURRENT TEST OF 1E1 1 BOO1B (1B RHR
HEAT EXCHANGER)
2/22/2018
SNC0662592
LOW PRESSURE CO2 SYS SURVEILLANCE
HYDROSTATIC HOSE TEST
01/10/2020
SNC0893926
D/G ROOM 1A 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
10/29/2021
SNC0963578
2SV-FPX-010-0 CABLE SPREAD & COMPUT ROOM
LOW PRESSURE CO2 SYS SURVEILLANCE
06/28/2023
SNC1017433
LOW PRESSURE CO2 SYS SURVEILLANCE
HYDROSTATIC HOSE TEST
08/18/2025
SNC1025311
D/G ROOM 1B 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
10/15/2021
SNC1025312
D/G ROOM 1B 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
04/02/2024
SNC1025313
D/G ROOM 1C 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
11/01/2021
SNC1025314
D/G ROOM 1C 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
04/02/2024
SNC1025315
D/G ROOM 2A 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
10/20/2021
Work Orders
SNC1025316
D/G ROOM 2A 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
04/02/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC1025317
D/G ROOM 2C 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
11/01/2021
SNC1025318
D/G ROOM 2C 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
04/02/2024
SNC1037250
2SV-FPX-010-0 CABLE SPREAD & COMPUT ROOM
LOW PRESSURE CO2 SYS SURVEILLANCE
06/11/2025
WO SNC970250
D/G ROOM 1A 52SV-FPX-010-0 D/G ONLY LOW-
PRESSURE CO2 SYS SURVEILLANCE
03/27/2024