IR 05000424/2025001
| ML25128A117 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/13/2025 |
| From: | Alan Blamey NRC/RGN-II/DORS |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2025001 | |
| Download: ML25128A117 (16) | |
Text
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000424/2025001 AND 05000425/2025001
Dear Jamie Coleman:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 and 2. On April 16, 2025, the NRC inspectors discussed the results of this inspection with J. Weissinger, Site Vice President, 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.
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 and 05000425 License Nos. NPF-68 and NPF-81
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000424 and 05000425
License Numbers:
Report Numbers:
05000424/2025001 and 05000425/2025001
Enterprise Identifier:
I-2025-001-0035
Licensee:
Southern Nuclear Operation Company, Inc.
Facility:
Vogtle Electric Generating Plant, Units 1 and 2
Location:
Waynesboro, GA
Inspection Dates:
January 01, 2025 to March 31, 2025
Inspectors:
J. Bell, Senior Health Physicist
A. Craig, Project Engineer
W. Deschaine, Senior Project Engineer
S. Downey, Senior Reactor Inspector
T. Morrissey, Senior Resident Inspector
J. Rivera, Health Physicist
B. Truss, Resident Inspector
J. Walker, Senior Emergency Preparedness 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 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
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power (RTP). On March 2, 2025, power was reduced to approximately 92 percent RTP to perform a planned main generator turbine valve surveillance. The unit was at RTP for the remainder of the inspection period.
Unit 2 began the inspection period at RTP and was shut down for a planned refueling outage (2R24) on March 6, 2025, where it remained shut down for the rest 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following unit 1 and unit 2 systems on January 3, 2025:
- nuclear service cooling water (NSCW)
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of overall preparations to protect risk-significant systems from sub-freezing on January 19-24, 2025.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 train "A" centrifugal charging pump (CCP) while train "B" CCP was out of service (OOS) for planned maintenance on January 8-9, 2025.
- (2) Unit 1 train "B" safety injection (SI) pump while train "A" SI pump was OOS for planned maintenance on January 14-15, 2025.
- (3) Unit 2 train "B" EDG while train "A" EDG was OOS for planned maintenance on February 18-19, 2025.
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the SI system, including the SI accumulators on March 30, 2025.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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) Fire zones 108, 120, and 121, unit 1 upper cable spreading room on January 18, 2025.
- (2) Fire zones 56B, 77B, 78B, 83, unit 2 safety-related battery rooms (trains A, B, C and D)on February 6, 2025.
- (3) Fire zones 19, 20, 21 and 14B, unit 1 CCP rooms and level C pipe penetration area on February 23, 2025.
- (4) Fire zones 165 and 166, unit 1 EDG fuel oil storage tank pump rooms (trains A and B)on March 4, 2025.
- (5) Fire zones 155, 156, 157A, and 157B, unit 2 AFW pumphouse on March 12, 2025.
- (6) Fire zones 140A, 140B, 140C, and 140E, unit 2 containment building on March 18, 2025.
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during live-fire training on January 29-30, 2025.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated the readiness and performance of:
- (1) Unit 1 and unit 2 NSCW systems (i.e., ultimate heat sink) on February 25, 2025.
===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 2 during refueling outage
2R24 from March 17 to March 26, 2025
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
(1)
- Liquid Penetrant Examination o
===21201-B6-002-W25, trunnion to shell weld, ASME Class 2
- Ultrasonic Examination o
21201-029-16-RB, 4-inch pipe to elbow weld, ASME Class 1 o
21201-042-3-RB, 2-inch elbow to pipe, ASME Class 1 o
21204-024-15-RB, 6-inch pipe to valve, ASME Class 1 o
21205-007-11-RHR, 8-inch pipe to tee, ASME Class 2 o
21302-108-17-RB, 6-inch valve to pipe, ASME Class 1
- Visual Examination o
Bare metal visual examination of 21201-V6-001-BMI-BMV, reactor vessel bottom head exterior and bottom-mounted instrumentation nozzles, ASME Class 1.
- Welding Activities o
Gas Tungsten Arc Welding and Shielded Metal Arc Welding SI system piping replacement - Work order (WO) SNC1861090 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)===
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1)
- Bare metal visual examination of 21201-V6-001-CRDM, reactor vessel closure head exterior, ASME Class 1 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, March 18, 2025
- Review of the following boric acid evaluations (by corrosion assessment number):
1208-2023-006 1208-2024-002 1208-2024-003
- Review of the following corrective actions performed for evidence of boric acid leaks that were identified (by condition report [CR] number):
CR11010685 CR11025118 CR11056882 CR11087032 CR11087048 CR11087119 CR11095243 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)
- Steam Generator 1, eddy current testing (ECT) for tubes R1C78, R50C29, R58C63, R58C64
- Steam Generator 3, ECT for tube R45C79
- Steam Generator 4, ECT for tube R46C87, R58C51
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 a planned power reduction, shutdown, and cooldown of unit 2 to support refueling outage 2R24 on March 5-6, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator scenario consisting of an inadvertent turbine runback, loss of a reserve auxiliary transformer, and a large break loss of coolant accident, on January 23, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) Unit 1 and unit 2, system 1807, regulating transformer reliability/unavailability performance criteria not met resulting in maintenance rule (a)(1) determination (i.e.,
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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 1 elevated risk with train "B" CCP, NSCW pump no. 1, and main steam loop 2 atmospheric valve PV-3020 OOS for planned maintenance on Jan 7-8, 2025.
- (2) Unit 1 elevated risk with train "A" SI pump and NSCW pump no. 1 OOS for planned maintenance on Jan 14-15, 2025.
- (3) Unit 1 elevated risk with train "A" EDG and NSCW pump no. 1 OOS for planned maintenance on February 11-12, 2025.
- (5) Unit 2, elevated shutdown risk (i.e., Yellow) due to reduced RCS inventory and one DC (direct current) vital bus OOS for planned maintenance on March 10-12, 2025.
- (6) Unit 2 elevated shutdown risk (i.e., Yellow) due to RCS inventory in mid-loop for planned maintenance on March 28, 2025.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) CR11137894, unit 2 reactor coolant pump (RCP) 1 seal no. 1 increased leak-off flow, on January 16, 2025.
- (2) CR11146377, unit 2 train B control room emergency filtration system (CREFS)18-month surveillance halide detector (i.e., measuring and test equipment) found out-of-tolerance after surveillance was completed, on January 30, 2025.
- (3) CR11141778, Unit 1 train A EDG generator trouble alarm during testing, on February 24, 2025.
- (4) CR11155166, Unit 1 train A chiller and CREFS regulating transformer elevated temperatures on March 18, 2025.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 2 reactor core lead test assembly (LTA) loaded during the March 2025 refueling outage (2R24).
- (2) SNC2373434, temporary modification of the polar crane trolley slow-speed motor cable prior to moving the unit 2 reactor upper internals during 2R24 on March 14, 2025.
- (3) SNC1575838, unit 2 RCS head vent controller modification on March 20, 2025.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial) The inspectors evaluated unit 2 cycle 24 refueling outage (2R24) from March 6 to March 31, 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 (IP Section 03.01) (8 Samples)
- (1) Procedures 14825-2, "Quarterly Valve Test, (valve HV8812B, RHR RWST suction valve, only) and 13011-2, "Residual Heat Removal System," after train B RHR pump outage; WOs SNC1408682, SNC1345787 and SNC1162589, on January 28, 2025.
(2)
===14430-2, "NSCW Cooling Tower Fans Monthly Test," (2B NSCW fan no. 4 only), after gearbox replacement: WO SNC1017779, on February 5, 2025.
(3)14980A-1, "Diesel Generator 1A Operability Test," after train "A" EDG system outage; WOs SNC1162598 and SNC1351050, on February 12, 2025.
(4)14372A-2, "Containment Penetration No. 72A RCS Loop no. 1 Accumulator Sample Line Local Leak Rate Test," after replacement of accumulator no. 1 sample valve; WO SNC1483783 on March 25, 2025.
(5)14825-2, "Quarterly Inservice Valve Test," (valve 2HV1668B, NSCW tower A header bypass, only), after performing maintenance on 2HV1668B; WOs SNC1743101 and SNC1743102, on March 26, 2025.
(6)28816-C,"Class 1E Battery Modified Performance Test," (2CD1B battery), after battery replacement; WOs SNC1177350 and SNC1161757, on March 27, 2025.
(7)24817-2, "Head Vent Throttle 2HC-442B Channel Calibration," and 22286-C, "Target Rock Filed Calibration for Modulating Valves," after modification of the head vent controller; WO SNC1578554, on March 28, 2025.
(8)14786-2, "Turbine Driven Auxiliary Feedwater Pump Overspeed Test," and 14810-2, "TDAFW Pump & IST Response Time Test", after preventative maintenance that included replacing the governor; WO SNC1057974, on March 31, 2025.
Surveillance Testing (IP Section 03.01)===
(1)
===14640-1, "SSPS Slave Relay K 640 Train "A" Auxiliary Feedwater, on February 13, 2025.
(2)28210-C, "Main Steam Line Code Safety Valve Setpoint Verification," (Unit 2 loop 3 valves), on March 26, 2025.
(3)84400-2, "Containment Integrated Leak Rate Test," on March 25, 2025.
Inservice Testing (IST) (IP Section 03.01)===
(1)
===14810-2, "TDAFW Pump & Check Valve IST Response Time Test, on January 24, 2025.
Containment Isolation Valve Testing (IP Section 03.01)===
(1)
===14348-2, "Containment Penetration No. 48 CVCS Normal Letdown Local Leak Rate Test," on March 11, 2025.
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04)===
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of February 24, 2025.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of February 24, 2025.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of February 24, 2025. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of February 24, 2025.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator continuing training dynamic simulator scenario that included an inadvertent turbine runback, loss of a reserve auxiliary transformer, a large break loss of coolant accident coincident with containment isolation valves failing to close, resulting in an Alert emergency declaration and notification to the State of Georgia and surrounding counties, on January 23,
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 and the concentrations and quantities of radioactive materials and how the licensee 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) Licensee surveys of potentially contaminated material leaving the radiologically controlled area (RCA).
- (2) Workers exiting unit 2 containment and the RCA during 2R24 refueling outage.
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) Removal of unit 2 code safety valves.
- (2) Removal of unit 2 RCP no. 4.
- (3) ECT activities on unit 2 steam generators (SGs) nos. 1 through 4.
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) Unit 2 RCP no.4 platform inside containment.
- (2) Unit 2 SGs 1 through 4 platforms inside containment.
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.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) Outage-related components and materials including an RCP motor at the unit 2 equipment hatch during refueling outage 2R24.
- (2) Boxes and containers of radioactive materials stored in various storage locations throughout the protected area, including near the solid building and on the south side of the auxiliary building.
- (3) Shepherd box calibrator in the calibration lab in the auxiliary building.
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Liquid waste processing system at the radwaste processing facility including means for disposing of spent filter and demineralizer media associated with such.
- (2) Abandoned liquid and solid waste processing systems at the alternate radwaste building.
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
- (1) Title 10 CFR Part 61 analysis of dry active waste in 2024.
- (2) Title 10 CFR Part 61 analysis of radioactive primary resin sampled in Sept. 2023.
Shipment Preparation (IP Section 03.04) (1 Sample)
- (1) The inspectors observed the preparation of radioactive shipment #25-03-008 of chemistry samples on 3/19/2025.
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Shipment RVRS-24-008 of radioactive resin on November 21, 2024.
- (2) Shipment RVRS-24-001 of radioactive resin on March 1, 2024.
- (3) Shipment 23-10-004 of surface contaminated objects on October 11, 2023.
- (4) Shipment 24-08-008 of a resin sample on August 23,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1, (January 1, 2024 through December 31, 2024)
- (2) Unit 2, (January 1, 2024 through December 31, 2024)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1, (January 1 through December 31, 2024)
- (2) Unit 2, (January 1 through December 31, 2024)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1, (January 1 through December 31, 2024)
- (2) Unit 2, (January 1 through December 31, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) September 27, 2024 through March 21, 2025 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) June 14, 2024 through March 21, 2025
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) April 1 through December 31, 2024 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1 through December 31, 2024 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14)
This is a new NRC performance indicator, described in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 8 (Agencywide Documents Access and Management System [ADAMS] Accession no. ML24331A114). Licensees began collecting data for this performance indicator on January 1, 2025. Therefore, at the time of inspection there was no quarterly data compiled and submitted to the NRC.
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 April 16, 2025, the inspectors presented the integrated inspection results to J. Weissinger, Site Vice President (SVP), and other members of the licensee staff.
- On March 27, 2025, the inspectors presented the emergency preparedness program inspection results to J. Weissinger, SVP, and other members of the licensee staff.
- On March 26, 2025, the inspectors presented the inservice inspection results to J. Weissinger, SVP, and other members of the licensee staff.
- On March 21, 2025, the inspectors presented the radiation protection inspection results to Robert Norris, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
SG-CDMP-24-24
Vogtle 2R24 Steam Generator Degradation Assessment
Revision 0
S25VNP2P001
Liquid Penetrant Examination of 21201-B6-002-W25
03/20/2025
S25VNP2UT012
Ultrasonic Examination of 21201-042-3-RB
03/20/2025
S25VNP2UT022
Ultrasonic Examination of 21204-024-15-RB
03/21/2025
S25VNP2UT031
Ultrasonic Examination of 21302-108-17-RB
03/20/2025
S25VNP2UT034
Ultrasonic Examination of 21205-007-11-RHR
03/19/2025
S25VNP2UT053
Ultrasonic Examination of 21201-029016-RB
03/21/2025
S25VNP2V001
Visual Examination of 21201-V6-001-BMI-BMV
03/13/2025
NDE Reports
S25VNP2V019
Visual Examination of 21201-V6-001-CRDM(BMV)
03/16/2025
Calculations
CN-GB25-015
Vogtle Unit 2 Cycle 25 LTA Checks
Unit 2 Cycle 25 Core Loading Plan and Loading Pattern Risk
Assessment
09/30/2024
Miscellaneous
170FA LTA Product Release Certificates, 170FA Axiom Fuel
Assemblies, GB7ST1, 2, 3 and 4
01/17/2025
Procedures
NMP-AD-009-F01
Licensee Document Change Request " License Amendment
Request to Allow Use of Lead Test Assemblies for Accident-
Tolerant Fuel
Work Orders
40678351 and
40678352
Final product Release Certificates, 170FA Axiom Fuel Rod
and 170FA Axiom Chrome Coated Fuel Rod
01/17/2025
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
(CRs)
11162522, 11162560, 11162570, 11162650
Corrective Action
Documents
CRs
11159614, 11073225
Corrective Action
Documents
Resulting from
Inspection
CRs
11162867, 11162877, 11162874