ML25349A704

Nuclear Plant - Fire Protection Team Inspection (FPTI) Report 0500032/2025010 and 05000366/2025010

ML25349A704
Person / Time
Site:	Hatch
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

Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Co., Inc 3535 Colonnade Parkway, N 274.EC Birmingham, AL 35243

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

J. Coleman 2

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 cc w/ encl: Distribution via LISTSERV Signed by Bacon, Daniel on 12/28/25

ML25349A704 X

SUNSI Review X

Non-Sensitive

Sensitive X

Publicly Available

Non-Publicly Available OFFICE R2/DORS/EB2 R2/DORS/EB2 R2/DORS/EB1 R2/DORS/EB1 NAME W. Stuckart W. Monk P. Braaten D. Bacon DATE 12/23/2025 12/15/2025 12/18/2025 12/28/2025

Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:

05000321 and 05000366 License Numbers:

DPR-57 and NPF-5 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

2

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.

3 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) (4 Samples)

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.

(1) SSC #1 (Fire Prevention) - Transient Combustible Controls Program (2) SSC #2 (Detection/Suppression) - U1/U2 Low Pressure CO2 Systems (3) SSC #3 (SSD) - U1/U2 EDG System and 4160V Emergency Distribution (4) SSC #4 (SSD) - U1/U2 Low Pressure Coolant Injection (LPCI) Systems

4 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 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 (2)

FPP Change #2: RER SNC1244102 - Performance Based Evaluation of Fire Damper Configurations 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.

5 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 12/10/2024 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 12/01/1973 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 2025 FPTI - Fire Protection Program References in NMP-ES-063-GL01 Need Updating 09/03/2025 CR 11210429 2025 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 2025 FPTI - Diesel Generator Recovery Procedure Correction 09/10/2025

6 Inspection Procedure Type Designation Description or Title Revision or Date CR 11210943 2025 FPTI - CO2 Nozzle Inspection NPFA 12 09/11/2025 CR 11210952 2025 FPTI - 52SV-FPX-010-0 Procedural Enhancement 09/11/2025 CR 11233548 2025 FPTI - Use of Grace Periods for Fire Protection Surveillances 12/08/2025 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 -

CO2 System P&ID 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-014-002-TCAF201 Operator Response Time Validation Sheet 06/30/2023 31RS-OPS-001-1 Shutdown from Outside Control Room Rev. 6.6 31RS-OPS-002-2 Shutdown from Outside Control Room Rev. 7.5 34AB-X43-001-1 Fire Procedure Rev. 18.9 34AB-X43-001-2 Fire Procedure Rev. 23.9 34SO-E11-010-1 Residual Heat Removal System Rev. 46.9 Procedures 42SV-SUV-007-0 CO2 FIRE SUPPRESSION EQUIPMENT INSPECTION Rev 1.7

7 Inspection Procedure Type Designation Description or Title Revision or Date 52SV-FPX-010-0 LOW PRESSURE CO2 SYSTEM SURVEILLANCE 08/21/2025 NMP-ES-035 Fire Protection Program 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-014-002 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 WO SNC0571621 EDDY CURRENT TEST OF 1E1 1 BOO1B (1B RHR HEAT EXCHANGER) 02/22/2018 WO SNC0662592 LOW PRESSURE CO2 SYS SURVEILLANCE HYDROSTATIC HOSE TEST 01/10/2020 WO SNC0893926 D/G ROOM 1A 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 10/29/2021 WO SNC0963578 52SV-FPX-010-0 CABLE SPREAD & COMPUT ROOM LOW PRESSURE CO2 SYS SURVEILLANCE 06/28/2023 WO SNC1017433 LOW PRESSURE CO2 SYS SURVEILLANCE HYDROSTATIC HOSE TEST 08/18/2025 WO SNC1025311 D/G ROOM 1B 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 10/15/2021 WO SNC1025312 D/G ROOM 1B 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 04/02/2024 WO SNC1025313 D/G ROOM 1C 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 11/01/2021 WO SNC1025314 D/G ROOM 1C 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 04/02/2024 WO SNC1025315 D/G ROOM 2A 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 10/20/2021 Work Orders WO SNC1025316 D/G ROOM 2A 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 04/02/2024

8 Inspection Procedure Type Designation Description or Title Revision or Date WO SNC1025317 D/G ROOM 2C 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 11/01/2021 WO SNC1025318 D/G ROOM 2C 52SV-FPX-010-0 D/G ONLY LOW-PRESSURE CO2 SYS SURVEILLANCE 04/02/2024 WO SNC1037250 52SV-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