IR 05000348/2025003

Integrated Inspection Report 05000348/2025003 and 05000364/2025003

ML25345A121
Person / Time
Site:	Farley
Issue date:	12/11/2025
From:	Alan Blamey NRC/RGN-II/DORS
To:	Coleman J Southern Nuclear Operating Co
References
IR 2025003
Download: ML25345A121 (0)

Text

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000348/2025003 AND 05000364/2025003

Dear Jamie Coleman:

On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant. On December 8, 2025, the NRC inspectors discussed the results of this inspection with Gene Surber, Licensing Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

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, 3rd quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025.The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, 4th quarter integrated inspection reports, which will be issued 45 days after the 4th quarter ends on December 31, 2025.

No findings or violations of more than minor significance were identified during this inspection.

December 11, 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, Alan J. Blamey, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000348 and 05000364 License Nos. NPF-2 and NPF-8

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000348 and 05000364

License Numbers:

NPF-2 and NPF-8

Report Numbers:

05000348/2025003 and 05000364/2025003

Enterprise Identifier:

I-2025-003-0013

Licensee:

Southern Nuclear Operating Company, Inc.

Facility:

Joseph M. Farley Nuclear Plant

Location:

Columbia, AL

Inspection Dates:

July 01, 2025 to September 30, 2025

Inspectors:

B. Bishop, Senior Project Engineer

T. Griffin, Resident Inspector

R. Lewis, Senior Resident Inspector

S. Temple, Senior Resident Inspector

Approved By:

Alan J. Blamey, 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 Joseph M. Farley 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

None.

PLANT STATUS

Unit 1 began the inspection period at full rated thermal power (RTP). On September 9, 2025, the unit entered coastdown in preparation for refueling outage 1R33. The unit was shut down on September 28, 2025, to commence the refueling outage and remained shut down for the remainder of the inspection period.

Unit 2 began the inspection period at approximately 80 percent RTP while increasing power following a unit startup that began on June 30, 2025. The unit returned to full RTP on July 2, 2025, and remained at or near full power 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1 'A' train emergency diesel generators, while 'B' train was out of service for planned maintenance on July 9, 2025.

(2) Unit 1 'A', 'B', and 'C' component cooling water pumps and 'A' and 'C' component cooling water heat exchangers, while the 'B' component cooling water heat exchanger was out of service during the week of July 14, 2025 (Drawing D205002).

(3) Unit 2 'A' motor-driven auxiliary feedwater pump system following quarterly surveillance testing during the week of August 18, 2025 (D205007).

(4) Unit 2 'E' service water system pump, following an equipment outage during the week of August 25, 2025 (D205003).

(5) Unit 2 'A' train residual heat removal system, while the 'B' train residual heat removal pump was out of service during the week of September 1, 2025 (D205041).

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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 1 turbine building (fire area 1-TB) on the week of September 21, 2025 (Procedure FNP-1-FPP-2.0)

(2) Unit 2 turbine building (fire area 2-TB) on the week of September 21, 2025 (FNP-2-FPP-2.0)

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:

1. Unit 2 separation of auxiliary steam from Unit 1 to prevent cross-unit effects

while stabilizing steam generator pressure, on July 11th, 2025.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspector observed and evaluated the operators perform simulated time critical actions on September 9, 2025.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated maintenance activities for the following structures, systems, and components (SSCs) to ensure the licensee appropriately addressed performance and condition problems:

(1) Emergency diesel generator 1C (shared between units 1 and 2) exceeding 75% of the unavailability performance criteria on July 7, 2025 (Condition Report (CR)

===11193314).

(2) Unit 2 steam dump valves monitoring under 10 CFR50.65 a

(1) due to multiple functional failures, including a failure to open when demanded on July 29, 2025 (CR 11191903).

Aging Management (IP Section 03.03)===

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) Units 1 and 2 fire protection header rupture identified on September 9, 2025 (CR 11210121)

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 activity to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 1 outage risk assessment for turbine building direct-current (DC) backup power supply maintenance, prior to the 1R33 refueling outage (Procedure FNP-0-UOP-4.0).

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 2 'B' charging pump partial failure during routine surveillance on July 14, 2025 (CR11195159).

(2) Unit 1 component cooling water relief valve with seat leakage on August 13, 2025 (CR 11203749).

(3) Emergency diesel generator 1C fuel oil leak on August 12, 2025 (CR 11202470).

(4) Unit 1 containment cooler service water inlet flow transmitter found out of calibration and unable to be calibrated on August 28, 2025 (WO SNC1506527, CR 11207521).

(5) Loss of seismic monitoring system on July 2, 2025 (CR11192274).

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 2 reactor coolant system loop 'A' cold leg wide-range temperature instrument detector local (hot shutdown panel) indication input change (Design Equivalent Change Package SNC2596258)

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

(1)

(Partial)

The inspectors evaluated Unit 1 refueling outage 1R33 activities from September 28, 2025, to September 30, 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) (3 Samples)

(1) Unit 1 '1B' emergency diesel generator testing following a planned maintenance outage on July 11, 2025 (Procedure FNP-STP-80.1).

(2) Emergency diesel generator 1C (shared between Units 1 and 2) testing following a failed surveillance test during the week of August 10, 2025 (FNP-0-STP-80.7).

(3) Unit 2 B residual heat removal pump surveillance testing following a planned maintenance outage on September 2, 2025 (WO SNC1377535).

Surveillance Testing (IP Section 03.01) (1 Sample)

(1) Unit 1 'C' component cooling water pump quarterly surveillance on July 16, 2025.

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Unit 2 'B' charging pump on July 14, 2025 (FNP-2-STP-4.2).

Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)

(1) FLEX 'A' and 'B' 600-volt diesel generator operational inspection on July 22, 2025 (WOs SNC2071179, SNC1973168).

71114.06 - Drill Evaluation

Required Emergency Preparedness Drill (1 Sample)

(1) The inspectors observed an emergency response organization drill involving a large-break loss-of-coolant-accident (LOCA) with a failed electrical containment penetration, resulting in a radioactive release and classification of a General Emergency on August 5, 2025 (2025 Off-Year Exercise).

Additional Drill and/or Training Evolution (1 Sample)

(1) The inspectors evaluate licensed operator response during a simulator examination involving a steam generator tube rupture and classification of an Alert on July 28, 2025 (2025 Exam 3). This scenario represented a drill and exercise performance opportunity.

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)===

(1) Unit 1 (July 1, 2024 through June 30, 2025)

(2) Unit 2 (July 1, 2024 through June 30, 2025)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 1 (July 1, 2024 through June 30, 2025)

(2) Unit 2 (July 1, 2024 through June 30, 2025)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (July 1, 2024 through June 30, 2025)

(2) Unit 2 (July 1, 2024 through June 30, 2025)

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program to identify potential trends in non-safety system equipment failures due to outage maintenance work 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) The inspectors evaluated the licensees response to a ruptured fire main at Farley Nuclear Plant on September 9, 2025. The rupture resulted in a temporary loss of the fire suppression water system for both units. Compensatory measures were implemented, and the system was restored later that same day. The inspectors evaluated this event in accordance with NRC Management Directive (MD) 8.3 and determined that no follow-up inspection was necessary (ADAMS Accession No.

ML25258A001).

Event Report (IP Section 03.02) (1 Sample)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000364/2025-003-000, Unit 2 Automatic Reactor Trip Due to Low Steam Generator Level (ADAMS Accession No. ML25230A239). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. 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 December 8, 2025, the inspectors presented the integrated inspection results to Gene Surber, Licensing Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CAR

869376

TE

1181657

Corrective Action

Documents

CR

11191023, 11191064

71111.12

Work Orders

SNC855371

Inspect and Repair Feed Water Turbine and Steam Valves,

to Include Remove and Replace Turbine Oil Hoses

CR

10773474

Corrective Action

Documents

CARs

278955, 647996, 744903 (ERC), 744903 (OPC)

21C067

Metallurgical Report - Investigation of the Failure of a Section

of Fire Protection Piping

03/24/2021

23G305

Metallurgical Report - Evaluation of a Section of Fire

Protection Piping

09/09/2022

23J351

Examination of Cracked Well-Water Supply Pipe

24B079

Examination of a Section of Fire Protection Piping

Engineering

Evaluations

24H315

Examination of One Section of Fire Protection Piping

SNC1173940

PHC Top 10 Fire Protection Pipe Replacement Adjacent to

2A Cooling Tower

07/21/2022

SNC1581439

Underground Water Leak Near Fire Protection Tank #1

09/27/2023

71152A

Work Orders

SNC1725873

Fire protection header break

2/22/2024

71152S

Corrective Action

Documents

CRs

11187762, 11189092