IR 05000424/2025002
| ML25190A357 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/09/2025 |
| From: | Alan Blamey NRC/RGN-II/DORS |
| To: | Coleman J Southern Nuclear Operating Co |
| References | |
| IR 2025002 | |
| Download: ML25190A357 (11) | |
Text
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000424/2025002 AND 05000425/2025002
Dear Jamie Coleman:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant, Units 1 and 2. On July 1, 2025, the NRC inspectors discussed the results of this inspection with. Matthew Euten, Regulatory Affairs Manager. 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:
05000424/2025002 and 05000425/2025002
Enterprise Identifier:
I-2025-002-0029
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Vogtle Electric Generating Plant, Units 1 and 2
Location:
Waynesboro, GA
Inspection Dates:
April 01, 2025 to June 30, 2025
Inspectors:
A. Craig, Project Engineer
T. Morrissey, Senior Resident Inspector
B. Truss, 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 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 April 26, 2025, power was reduced to approximately 97.5 percent RTP in order to remove the 6A feedwater heater from service for repair of a steam leak. Power was returned to RTP on April 29, 2025, with the 6A feedwater heater removed. On May 1, 2025, power was reduced to approximately 97.5 percent RTP for several hours in order to place 6A feedwater heater back in service following repair. On May 20, 2025, power was reduced to approximately 92 percent RTP for several hours to perform a planned turbine valve surveillance. On May 28, 2025, the unit was manually tripped due to a loss of one main feedwater (MFW) pump. The MFW pump experienced an automatic trip when operations attempted to swap the feedwater pump's lube oil coolers. The unit restarted May 29, 2025, and returned to RTP on June 1, 2025. The unit was at RTP for the remainder of the inspection period.
Unit 2 began the inspection period shut down for a planned refueling outage (2R24). On April 1, 2025, the unit was restarted and reached RTP on April 6, 2025. On June 2, 2025, power was reduced to approximately 92 percent RTP for several hours to perform a planned turbine valve surveillance. The unit was at RTP 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) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 train "A" emergency diesel generator (EDG) and associated emergency switchgear while train "B" EDG was out of service (OOS) for planned maintenance, on June 2, 2025
- (2) Unit 2 train "A" and "B" auxiliary feedwater (AFW) trains while train "C" AFW was OOS for planned maintenance, on June 16, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 145, 146, 160A, and 160B. Unit 2 train A and B nuclear service cooling water (NSCW) pump rooms and electrical tunnels, on April 4, 2025.
- (2) Fire zones 19, 20, 21 and 14B. Unit 2 centrifugal charging pump (CCP) and normal charging pump rooms and pipe penetration area, on April 25, 2025.
- (3) Fire zones 91, 92, 98, and 103. Unit 1 4.16KV switchgear and remote shutdown rooms, on May 2, 2025.
- (4) Fire zones 530 and 531. North and south fire pump houses, on May 14, 2025.
- (5) Fire zones 54, 55, 147, 148, 172. Unit 2 auxiliary building level 2 component cooling water heat exchanger rooms, switchgear room, and piping penetration filter room, on May 18, 2025.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in unit 2 A and B train safety injection pump rooms.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the main control room during a planned unit 2 startup and power ascension, following refueling outage 2R24, on April 1-2, 2025.
- (2) The inspectors observed and evaluated licensed operator performance in the main control room during startup and power ascension of unit 1 following a manual reactor trip, on May 29, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator continuing training dynamic simulator scenario that included a steam generator tube rupture, a rapid power reduction, a pressure transmitter failure, a reactor coolant pump trip, and a loss of coolant accident on April 30, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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) Unit 1 safety injection system, on April 30, 2025
- (2) Condition report (CR) 11172337. Unit 2 125-Volt DC (direct current) non-1E maintenance preventable functional failure for battery capacity less than 80 percent on May 20, 2025.
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Work orders SNC1182433 and SNC1160363. Unit 2 containment coating inspection and repair during refueling outage, on June 23, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (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:
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) CR 11167986. Unit 2 B train EDG inspection cover jacket water leak, on April 9, 2025.
- (2) CR 11171425. Unit 1 B train battery bus bar #43 corrosion degradation, on April 28, 2025.
- (3) CR 11174946. Unit 1 A train CCP seal leakage, on May 13, 2025.
- (4) CR 11180346. Unit 2 A train EDG inspection cover jacket water leak, on May 21, 2025.
- (5) CR 11177030. Unit 1 B train sequencer processor logic failure, on May 22, 2025.
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the completion of the unit 2 cycle 24 refueling outage (2R24) from April 1 - 3, 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) Procedure 14430-1, "NSCW Cooling Tower Fans Monthly Test," after replacing unit 2 NSCW train A fan #2 motor; WO SNC 1435270, on April 26, 2025.
(2)
===14980B-2, "Diesel Generator 2B Operability Test," after planned maintenance to repair a jacket water leak on the unit 2 B train EDG; WO SNC2121031, on May 6, 2025.
(3)14632-2, "SSPS Slave Relay K 648 Train A Test Safety Injection," after planned maintenance outage on the unit 2 essential safety features chiller train A: WOs SNC1388126, SNC1388125, and SNC1420196, on June 13, 2025.
Surveillance Testing (IP Section 03.01)===
- (1) Procedure 11882-1/2, "Unit 1/2 Outside Area Rounds" on May 22, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Procedure 14808B-1, "Train B Centrifugal Charging Pump and Check Valve IST and Response Time Test," (IST only) on May 28, 2025
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) On April 15, 2025, the inspectors evaluated an emergency preparedness drill in the simulator and technical support center. The drill involved a reactor coolant pump trip, which led to an automatic reactor trip, and a subsequent loss of coolant accident.
Containment radiation monitors showed an upward trend, indicating core damage.
Also, a simulated release path to the environment was introduced via a failed penetration in the auxiliary building. The drill scenario resulted in the declaration of an
'Alert,' 'Site Area Emergency,' and 'General Emergency,' along with 'Protective Action Recommendations' notifications to the State of Georgia and surrounding counties.
Additional Drill and/or Training Evolution (1 Sample)
- (1) On April 30, 2025, the inspectors observed and evaluated a licensed operator continuing training dynamic simulator scenario that included a steam generator tube leak, a rapid power reduction, a pressure transmitter failure, a reactor coolant pump trip with subsequent automatic reactor trip, and a loss of coolant accident. The training scenario resulted in an 'Alert' emergency declaration and notification to the State of Georgia and surrounding counties.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1, (April 1, 2024, through March 31, 2025)
- (2) Unit 2, (April 1, 2024, through March 31, 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1, (April 1, 2024, through March 31, 2025)
- (2) Unit 2, (April 1, 2024, through March 31, 2025)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) CR 11165734. Unit 2 Technical Specification (TS) Limiting Condition for Operation (LCO) 3.3.4, Remote Shutdown System, was not met when Mode 3 (RCS temperature >350°F) was entered on March 31, 2025.
- (2) Technical evaluation (TE) 1176457. Negative trend in the use of fire doors.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program, maintenance rule database, operator control room logs, and management review committee reports for potential adverse trends in equipment reliability that might be indicative of a more significant safety issue. The licensee as well as the inspectors identified the negative trends listed below.
- CR 11176402. Power supply failures.
- TE 1172561. Negative trend in the use of fire doors.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)
- (1) The inspectors evaluated operator and equipment performance in response to a unit 1 manual reactor trip initiated when a main feedwater pump tripped due to loss of lube oil pressure on May 28,
INSPECTION RESULTS
Minor Violation 71152A Minor Violation: Unit 2 Technical Specification (TS) Limiting Condition for Operation (LCO)3.3.4, Remote Shutdown System, was not met when Mode 3 (RCS temperature >350F)was entered on March 31, 2025. Prior to Mode 3 entry, the licensee removed all cold leg and hot leg wide range temperature instruments from service to support instrument cross-calibrations in accordance with licensee procedure 54015-2, Reactor Coolant System RTD Cross-Calibration. Although TS 3.3.4 allowed these instruments to be removed from service for up to 30 days while in Mode 3, TS LCO 3.0.4 does not allow entry into Mode 3 without these instruments unless certain conditions are met. Technical Specification LCO 3.0.4, LCO Applicability, specifies in part, that when an LCO is not met, entry into a Mode shall only be made if the associated Actions to be entered permit continued operation in that Mode for an unlimited time, a risk assessment has been completed addressing inoperable systems or components, or when an allowance is stated in the specification. None of these conditions were met.
Screening: The inspectors determined the performance deficiency was minor. Although the installed temperature instrumentation was not available, the cold leg and hot leg temperature indications were displayed on a temporary computer in the control room, which was installed for the instrument cross-calibration.
Enforcement:
This failure to comply with TS 3.0.4 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified that no proprietary information was retained or documented in this report.
- On July 1, 2025, the inspectors presented the integrated inspection results to Matthew Euten, Regulatory Affairs Manager.
ADDITIONAL
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
Flooding Analysis-Auxiliary Building Level "B"
09/21/1993
Engineering
Evaluations
DC-1003
Flooding-Interdisciplinary
11