ML25342A003
| ML25342A003 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/10/2025 |
| From: | Alan Blamey NRC/RGN-II/DORS/PB3 |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2025003 | |
| Download: ML25342A003 (0) | |
Text
Jamie Coleman Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 - INTEGRATED INSPECTION REPORT 05200025/2025003 AND 05200026/2025003
Dear Jamie Coleman:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 3 and 4. On October 29, 2025, the NRC inspectors discussed the results of this inspection with William Garrett, 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 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.
No findings or violations of more than minor significance were identified during this inspection.
December 9, 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. 05200025 and 05200026 License Nos. NPF-91 and NPF-92
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Blamey, Alan on 12/09/25
SUNSI Review x
Non-Sensitive
Sensitive x
Publicly Available
Non-Publicly Available OFFICE RII/DORS RII/DORS RII/DORS NAME T. Fanelli A. Alen Arias A. Blamey DATE 12/08/2025 12/08/2025 12/09/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05200025 and 05200026 License Numbers:
NPF-91 and NPF-92 Report Numbers:
05200025/2025003 and 05200026/2025003 Enterprise Identifier:
I-2025-003-0018 Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Vogtle Electric Generating Plant, Units 3 and 4 Location:
Waynesboro, GA Inspection Dates:
July 01, 2025 to September 30, 2025 Inspectors:
J. Bell, Senior Health Physicist P. Cooper, Senior Reactor Inspector T. Fanelli, Senior Resident Inspector J. Parent, Resident Inspector J. Rivera, Health Physicist J. Vasquez, Construction Project Inspector 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 3 and 4, 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 PLANT STATUS Unit 3 operated at or near rated thermal power (RTP) for the entire inspection period.
Unit 4 began the inspection period at RTP. On August 17, 2025, the Unit entered coastdown in preparation for refueling outage 4R01. The unit was shut down on September 7, 2025, to commence the outage and remained shut down 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 onsite 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 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample [AP1000] (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)
Unit 4 containment building hot work during refueling outage 4R01 on September 17, 2025:
Fire Area: 1000 AF 01, Fire Zone: 1100 AF 11300A: Containment Building Elev. 107'-2", Maintenance Floor Southeast Fire Area: 1000 AF 01, Fire Zone: 1100 AF 11300B: Containment Building Elev. 107'-2", Maintenance Floor North Fire Area: 1000 AF 01, Fire Zone: 1100 AF 11300A: Containment Building Elev. 118'-6", Maintenance Floor Southeast 71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified that the reactor coolant system (RCS) boundary, reactor vessel internals, risk significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 4 during refueling outage 4R01 from September 15 to September 19th, 2025.
4 PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
(1)
Ultrasonic Examination Passive Cooling System, SV4-PXS-PLW-05A-FW1, Core Makeup Tank Nozzle N-1 to Pipe Reactor Cooling System, SV4-RCS-PLW-034-SW2, Elbow to Pipe Dye Penetrant Examination Passive Cooling System, SV4-PXS-PLW-05A-SW10, Core Makeup Tank Pipe-to-Cap Reactor Cooling System, SV4-RCS-PLW-034-SW2, Elbow to Pipe Visual Examination Passive Cooling System, SV4-PXS-PH-11R0044, Rigid Pipe Support Reactor Cooling System, SV4-RCS-PH-11Y0811, Hydraulic Snubber Containment, SV4-P32-I, Containment Shutdown Purge Exhaust Containment, SV4-P13-I, RCS/Containment Air Sample Containment, SV4-P14-I, RCS/PXS/CVS Air Sample Containment, SV4-P15-I, Containment Air Sample Containment, SV4-P16-I, RCS Sample Containment, SV4-P40-I, Spare Penetration Containment, SV4-P41-I, Spare Penetration Containment, SV4-P42-I, Spare Penetration PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
(1)
Boric Acid Walkdown, Tuesday September 16, 2025 Review of the following boric acid evaluation (by technical evaluation (TE) number):
TE 1185437 Review of evidence of boric acid leaks that were identified by condition report (CR) numbers:
CRs 11209626, 11210021, 11210016, 11210014, and 11209492 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
(1)
Eddy current Examination Steam Generator A: Tube at Row 25, Column 15
5 Steam Generator A: Tube at Row 102, Column 106 Steam Generator B: Tube at Row 2, Column 48 Steam Generator B Tube at: Row 96, Column 66 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 main control room during Unit 4 shutdown for refueling outage 4R01 at midnight on September 6, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated Crew 4 on a simulator requalification scenario on July 28, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample [AP1000] (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)
Unit 4 outage risk assessment during refueling outage 4R01 on September 8, 2025.
(2)
Unit 4 drain to mid-loop risk assessment on September 9, 2025.
71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors observed and evaluated the following activities during the Vogtle Unit 4 first refueling outage (4R01) from September 7 to September 30:
Initial Unit 4 containment walkdown/inspection after the unit reached cold shutdown (i.e., Mode 5) on September 7, 2025.
Activities related to RCS drain-down to hot mid-loop conditions to support steam generator nozzle dam installations on September 9 and 10, 2025.
Integrated head package de-tension into Mode 6 (i.e., Refueling mode with fuel in the reactor vessel) and removal as a heavy lift.
Fuel movements for core offload. All fuel was removed on September 14, 2025.
Fuel movements for core reload and entry into Mode 6 on September 19, 2025.
Core fuel load verification on September 20, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk Postmaintenance Testing (PMT) [AP1000] (IP Section 03.01) (2 Samples)
6 (1)
Work order (WO) SNC1855390. Containment recirculation A motor-operated valve 4-PXS-V117A, following diagnostic testing on September 15, 2025.
(2)
WO SNC1855437. Pressurizer spray motor-operated valve 4-RCS-111A, following diagnostic testing on September 12, 2025.
Surveillance Testing [AP1000] (IP Section 03.01) (1 Sample)
(1)
Procedure 3-GEN-OTS-10-001, Division A Quarterly Valve Stroke Test, for containment isolation valves WLS-V055, WLS-V067, VFS-V003, and VFS-V010, on July 17, 2025. WO SNC2247090.
Containment Isolation Valve (CIV) Testing [AP1000] (IP Section 03.01) (1 Sample)
(1)
Containment Penetration 19 local leak rate test (LLRT). Normal residual heat removal (RNS) system suction header valves 4-RNS-V004A, 4-RNS-V004B, 4-RNS-V005A, 4-RNS-V005B, 4-CVS-V079, 4-PXS-V210A, 4-PXS-V209A, and 4-PXS-V208B.
Diverse and Flexible Coping Strategies (FLEX) Testing [AP1000] (IP Section 03.02) (1 Sample)
(1)
This sample is conducted sitewide for Vogtle Units 1-4 per IP 71111.24 and was conducted under the baseline inspection for Vogtle Units 1 and 2 on July 29, 2025.
Inspection sample details and results are documented in Inspection Report 05000424/2025003, 05000425/2025003, and 07201039/2025001 (ADAMS Accession No. ML25321A057) under Section 71111.24 of the report.
RADIATION SAFETY 71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels, identifies the concentrations and quantities of radioactive materials, and assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)
Health physics personnel controlling movement of material across a radiologically controlled area boundary via forklift.
(2)
Workers exiting Unit 4 containment during refueling outage 4R01.
7 Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)
Steam generator diaphragm removal.
(2)
Steam generator nozzle dam installation.
(3)
Scaffold building activities in containment, various.
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
(1)
Areas of Unit 4 being controlled as HRA or locked high radiation areas (LHRA) for crud burst evolution, various buildings.
(2)
Resin transfer pump room LHRA.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1)
The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Dose Calculations (IP Section 03.03) (1 Sample)
The inspectors evaluated the following dose calculations:
(1)
Unit 3 weekly plant vent stack continuous release permit process.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation Radioactive Material Storage (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
(1)
Unit 4 outdoor storage area containing sealands with radioactive material (RAM).
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
(1)
Unit 4 dewatering system for disposal of spent resin in the radwaste building.
8 Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1)
Dry Active Waste (DAW) Part 61 Analysis, December 17, 2024 (2)
Unit 3 Mobile Treatment System Part 61 Analysis, December 17, 2024 Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
(1)
Shipment no. RVRS-25-303, Hi-Rad DAW (2)
Shipment no. RVRS-25-304, 200L-22012 Resin Liner (3)
Shipment no. RVRS-25-306, 200L-22026 Resin Liner OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
OR01: Occupational Exposure Control Effectiveness Sample [AP1000] (IP Section 02.15)
(1 Sample)
(1)
November 8, 2024 through September 12, 2025 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample
[AP1000] (IP Section 02.16) (1 Sample)
(1)
June 14, 2024 through August 3, 2025 INSPECTION RESULTS No findings were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On October 29, 2025, the inspectors presented the integrated inspection results to William Garrett, Licensing Manager, and other members of the licensee staff.
On September 12, 2025, the inspectors presented the radiation protection inspection results to Steven Leighty, Regulatory Affairs Manager, and other members of the licensee staff.
9 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.05 Fire Plans B-PFP-ENG-001-F4104 Pre-Fire Plan - Containment Building El 107'-2" 2.0 71111.05 Fire Plans B-PFP-ENG-001-F4104 Pre-Fire Plan - Containment Building El 118'-6" 2.0 71111.05 Procedures NMP-ES-035 Fire Protection Program 7.1 71111.05 Procedures NMP-ES-035-003 Fleet Hot Work Instruction 12.0 71111.05 Procedures NMP-ES-035-007 Fleet Fire Watch Instruction 7.0 71111.08P NDE Reports IWE-S25V4V035 RCS/Containment Air Sample SV4-P13-I 9/17/2025 71111.08P NDE Reports IWE-S25V4V048 RCS/PXS/CVS Air Sample SV4-P14-I 9/17/2025 71111.08P NDE Reports IWE-S25V4V049 Containment Air Sample SV4-P15-I 9/17/2025 71111.08P NDE Reports IWE-S25V4V050 RCS Sample Penetration SV4-P16-I 9/17/2025 71111.08P NDE Reports IWE-S25V4V058 Containment Shutdown Purge Exhaust SV4-P32-I 9/17/2025 71111.08P NDE Reports IWE-S25V4V059 Visual Examination of Spare Penetration SV4-P40-I 09/17/2025 71111.08P NDE Reports IWE-S25V4V060 Visual Examination of Spare Penetration SV4-P41-I 9/17/2025 71111.08P NDE Reports IWE-S25V4V061 Visual Examination of Spare Penetration SV4-P42-I 9/17/2025 71111.08P NDE Reports S25V4P006 Liquid Penetrant Examination of RCS Elbow-to-Pipe Weld SV4-RCS-PLW-034-SW2 9/12/2025 71111.08P NDE Reports S25V4P018 Liquid Penetrant Examination of Core Makeup Tank Weld SV4-PXS-PLW-05A-SW10 9/16/2025 71111.08P NDE Reports S25V4U031 Ultrasonic Examination of Elbow to Pipe Weld SV4-RCS-PLW-034-SW2 9/12/2025 71111.08P NDE Reports S25V4U046 Ultrasonic Examination of Core Makeup Tank Nozzle N-1 to Pipe Weld SV4-PXS-PLW-05A-FW1 9/16/2025 71111.08P NDE Reports S25V4V004 Visual Examination of Hydraulic Snubber SV4-RCS-PH-11Y0811 9/09/2025 71111.08P NDE Reports S25V4V007 Visual Examination of Rigid Pipe Support SV4-PXS-PH-11R0044 9/10/2025 71111.13 Procedures B-ADM-OPS-011 Outage Risk Assessment Monitoring 5.0 71111.13 Procedures NMP-OM-002 Shutdown Risk Management 6.1 71124.01 Corrective Action Documents Condition Reports (CRs) 10932098, 11103453, 11136010, 11153686, 11164965, and 11194173 71124.08 Corrective Action Condition Reports 11011118 and 11210379
10 Inspection Procedure Type Designation Description or Title Revision or Date Documents (CRs) 71124.08 Corrective Action Documents Resulting from Inspection CR 11210993 NRC Radiological Protection Inspection Comments on Radwaste Shipping Documentation 09/11/2025 71124.08 Procedures NMP-HP-405 Shipment of Radioactive Waste and Radioactive Material 5.0 71124.08 Procedures NMP-HP-407 Radioactive Materials - Additional Transportation Controls for Category 1 and 2 Quantities of Radioactive Materials 3.6 71124.08 Procedures NMP-HP-408 Solid Radioactive Waste Scaling Factor Determination and Implementation and Waste Classification 3.0 71124.08 Procedures NMP-SE-018 Physical Protection of Category 1 and 2 Quantities of Radioactive Material 6.0