ML25321A057
| ML25321A057 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, 07201039  |
| Issue date: | 11/19/2025 |
| From: | Alan Blamey NRC/RGN-II/DORS |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2025003, IR 2025001 | |
| Download: ML25321A057 (0) | |
Text
Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Company, Inc 3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000424/2025003, 05000425/2025003, AND 07201039/2025001
Dear Jamie Coleman:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 and 2. On October 1, 2025, the NRC inspectors discussed the results of this inspection with Mr. Jason Thomas, Regulatory Affairs 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.
November 19, 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, Alan J. Blamey, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000424, 05000425, and 07201039 License Nos. NPF-68 and NPF-81
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Blamey, Alan on 11/19/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DORS RII/DORS RII/DORS NAME T. Morrissey A. Alen Arias A. Blamey DATE 11/17/2025 11/19/2025 11/19/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000424, 05000425, and 07201039 License Numbers:
NPF-68 and NPF-81 Report Numbers:
05000424/2025003, 05000425/2025003, and 07201039/2025001 Enterprise Identifier:
I-2025-003-0017 and I-2025-001-0091 Licensee:
Southern Nuclear Operating Company, Inc Facility:
Vogtle Electric Generating Plant, Units 1 and 2 Location:
Waynesboro, GA Inspection Dates:
July 01, 2025 to September 30, 2025 Inspectors:
P. Cooper, Senior Reactor Inspector D. Lanyi, Senior Operations Engineer T. Morrissey, Senior Resident Inspector D. Neal, Health Physicist B. Truss, Resident Inspector J. Viera, Senior Operations Engineer Approved By:
Alan J. Blamey, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Vogtle Electric Generating Plant, Units 1 and 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 Type Issue Number Title Report Section Status LER 05000424/2025-001-00 LER 2025-001-00 for Vogtle, Unit 1, Human Performance Error Results in Loss of Main Feedwater Pump and Manual Reactor Trip 71111.53 Closed
3 PLANT STATUS Unit 1 operated at rated thermal power (RTP) at the start of the inspection period. On September 2, 2025, power was reduced to approximately 92 percent RTP for several hours to perform a planned main turbine valve surveillance. Following the surveillance, power was increased to 97 percent RTP to implement new leading edge flow monitor (LEFM) parameters.
Full RTP was restored on September 3, 2025, and the unit remained at RTP for the remainder of the inspection period.
Unit 2 operated at RTP at the start of the inspection period. On September 8, 2025, power was reduced to approximately 92 percent RTP for several hours to perform a planned main turbine valve surveillance. The unit returned to RTP later that day and remained at 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.
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 "B" and "C" auxiliary feedwater (AFW) trains while train "A" AFW pump was out of service (OOS) for planned maintenance, on July 22, 2025.
71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
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)
Fire zones 4, 5, 9 and 10. Unit 1 containment spray and residual heat removal (RHR) pump rooms, on September 14, 2025.
4 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill in the following area:
Unit 1, 1AB05X transformer cubical, on August 11, 2025.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
(1)
Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered in August 2025.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by Title 10 of the Code of Federal Regulations (CFR) 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the facility licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the facility licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46, Simulation Facilities.
5 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
(1)
The inspectors observed and evaluated a licensed operator continuing training dynamic simulator scenario that included an instrument failure, a failure of a nuclear service cooling water (NSCW) pump, a steam line rupture, and a failure of the reactor to trip from the control room, on July 7, 2025.
(2)
The inspectors observed and evaluated a licensed operator simulator annual examination scenario that included a normal charging pump failure, an atmospheric relief valve stuck open, a failed reactor coolant pump seal, a manual reactor trip, a small break loss of coolant accident, and a containment isolation actuation failure, on August 11, 2025.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)
Title 10 CFR 50.65, Requirements for monitoring the effectiveness of maintenance at nuclear power plants, (i.e., Maintenance Rule (MR)) evaluations, EVAL-V-1302-06109 and EVAL-V-1302-06951, for return of the Unit 1 AFW system from MR (a)(1) to MR (a)(2), on July 24, 2025.
(2)
Condition report (CR) 11190594. Unit 1 system 1306 (main feedwater) exceeded its MR performance criteria, on August 4, 2025.
(3)
Units 1 and 2 system 1532 (engineered safety features (ESF) heating, ventilation, and air conditioning (HVAC)) on September 10, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
(1)
Unit 1, elevated risk with train B emergency diesel generator (EDG) building missile shield removed to support maintenance, work order (WO) SNC381092, on July 8 - 9, 2025.
(2)
Unit 2, elevated risk with train "B" NSCW fan no. 3 OOS for emergent maintenance due to an oil leak, WO SNC 2254144, on August 4 - 6, 2025.
(3)
Unit 2, elevated risk due to emergent work on train B EDG, WO SNC2740358, August 10, 2025.
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:
6 (1)
CR 11196867, Unit 1, chemical and volume control system flow control valve 1-FV-121 leakage exceeds 2 gallons per minute (gpm) limit, on July 29, 2025.
(2)
CR 11180182. Unit 1, inboard main steam isolation valve HS3016A not fully open alarm, on July 30, 2025.
(3)
CR 11200230. Unit 2, missing post maintenance test documentation for instrument air containment isolation valve 2HV-9378, on August 5, 2025.
(4)
CR 11206445. Unit 2, train B RHR pump elevated suction pressure and lowering accumulator no. 3 level during in-service test, on August 28, 2025.
(5)
CR 11207100. Excess water observed in unit 2 NSCW pump no. 3 oil samples, on September 12, 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)
Procedures 13610-2, "Auxiliary Feedwater System," and 14825-2, "Quarterly Inservice Valve Test," following Unit 2 train A AFW system outage, WOs SNC1276093, SNC1155502 and SNC1155793, on July 22 - 23, 2025.
(2) 14808B-2, "Train B Centrifugal Charging Pump and Check Valve IST and Response Time Test," following Unit 2 centrifugal charging pump system outage, WO SNC1374611, on August 27, 2025.
(3) 14980B-1, "Diesel Generator 1B Operability Test," (fast start) following a unit 1 train B EDG maintenance outage, WOs SNC1998157 and SNC1170024, on August 29, 2025.
Surveillance Testing (IP Section 03.01) (2 Samples)
(1)
Procedure 14980A-1, "Diesel Generator 1A Operability Test,' (fast start), on July 14, 2025.
(2) 14668B-1, "Train B Diesel Generator Operability Test," (24-hour run), on August 4 and 5, 2025.
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
Procedure 14805A-1, "Train A Residual Heat Removal Pump and Check Valve IST and Response Time Test," on August 11, 2025.
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1)
WOs SNC2095093 and SNC2095096, for steam generator and condensate storage tank make-up FLEX pumps, on July 29 and 30, 2025.
OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
7 MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
(1)
Unit 1 (July 1, 2024 - June 30, 2025)
(2)
Unit 2 (July 1, 2024 - June 30, 2025)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
(1)
Unit 1 (July 1, 2024 - June 30, 2025)
(2)
Unit 2 (July 1, 2024 - June 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
(1)
Unit 1 (July 1, 2024 - June 30, 2025)
(2)
Unit 2 (July 1, 2024 - June 30, 2025) 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program (CAP) related to the following issues:
(1)
CR 11123823, 125-volt DC (direct-current) battery 1BD1B bus bar degradation. The inspectors reviewed corrective actions taken to address degradation of the 1BD1B battery bus bar. As part of the review, the inspectors conducted walkdowns of all Unit 1 and Unit 2 safety-related batteries to verify that deficient conditions were properly identified, documented, and trended in the licensees CAP.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event report (LER) to verify its accuracy and completeness and determine the appropriateness of corrective actions:
(1)
LER 2025-001-00, Human Performance Error Results in Loss of Main Feedwater Pump and Manual Reactor Trip," (ADAMS Accession No. ML25205A149). The inspectors reviewed the LER and associated cause determination in corrective action report (CAR) 863003. The event involved human performance errors during operation of a 3-way lube oil valve, which contributed to the trip of the main feedwater pump.
However, the loss of lube oil (and subsequent pump trip) would not have occurred if the valves stop device had been functional. The licensee identified the direct cause as a broken valve operator stop device, with one stop tab broken and the other tab cracked. Due to the valve design, this condition was not apparent to the operator and could only be identified through partial disassembly. While human performance was a contributing factor, the inspectors concluded that the same outcome could have occurred even without operator error. Therefore, the inspectors determined that it was not reasonable to foresee or correct the direct cause (i.e., broken valve stop device), as discussed in the corrective action report and LER, and no performance deficiency or violation of NRC requirements was identified. This LER is Closed.
8 OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855 - Operation Of An Independent Spent Fuel Storage Installation (ISFSI)
Inspections were conducted using the appropriate portions of the 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) 2690, Inspection Program for Storage of Spent Reactor Fuel and Reactor-Related Greater-than-Class C Waste at Independent Spent Fuel Storage Installations (ISFSI) and for 10 CFR Part 71 Transportation Packagings."
Operation Of An ISFSI (1 Sample)
(1)
From July 7 - 11, 2025, the inspectors performed a review of the licensees ISFSI activities to verify compliance with regulatory requirements. During the on-site inspection, the inspectors observed and reviewed licensee activities in each of the five safety focus areas including occupational exposure, public exposure, fuel damage, confinement, and impact to plant operations.
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. Additionally, the inspectors performed independent walkdowns of the heavy load lifting equipment and the ISFSI haul path. The inspector also performed an independent radiation survey of the ISFSI pad.
INSPECTION RESULTS No findings were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On July 11, 2025, the inspectors presented the ISFSI inspection results to Mr. Matthew Euten, Regulatory Affairs Manager, and other members of the licensee staff.
On August 7, 2025, the inspectors presented the licensed operator requalification program inspection results to Mr. Jason Thomas, Regulatory Affairs Manager, and other members of the licensee staff.
On October 1, 2025, the inspectors presented the integrated inspection results to Mr. Jason Thomas, Regulatory Affairs Manager, and other members of the licensee staff.