IR 05000348/2025003
| 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:
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 DProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 2515,</br></br>Appendix D" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., 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) (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-
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.
2.
Unit 1 reactor shutdown for refueling outage 1R33, on September 28, 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) (1 Sample)
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) (2 Samples)
(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 Sample)
(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 Sample)
(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.
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
869376
1181657
Corrective Action
Documents
CR
11191023, 11191064
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
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
07/21/2022
SNC1581439
Underground Water Leak Near Fire Protection Tank #1
09/27/2023
Work Orders
SNC1725873
Fire protection header break
02/22/2024
Corrective Action
Documents
CRs
11187762, 11189092