IR 05000424/2026010
| ML26057A042 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  (NPF-068, NPF-081) |
| Issue date: | 02/26/2026 |
| From: | Christopher Even NRC/RGN-II/DORS/EB2 |
| To: | Coleman J Southern Nuclear Operating Co |
| Shared Package | |
| IR 2026010 | List: |
| References | |
| IR 2026010 | |
| Download: ML26057A042 (0) | |
Text
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT UNITS 1 & 2 - FOCUS ENGINEERING AGE-RELATED DEGRADATION INSPECTION REPORT 05000424/2026010 AND 05000425/2026010
Dear Jamie M. Coleman:
On January 29, 2026, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Vogtle Electric Generating Plant Units 1 & 2 and discussed the results of this inspection with Jason Thomas 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, Christopher J. Even, Chief Engineering Branch 1 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:
05000424/2026010 and 05000425/2026010
Enterprise Identifier:
I-2026-010-0026
Licensee:
Southern Nuclear Operating Company, Inc
Facility:
Vogtle Electric Generating Plant Units 1 & 2
Location:
Waynesboro, GA
Inspection Dates:
January 12, 2026, to January 29, 2026
Inspectors:
D. Burgess, Reactor Inspector
J. Copeland, Reactor Inspector
T. Su, Senior Reactor Inspector
Approved By:
Christopher J. Even, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Focus Engineering Age-Related Degradation Inspection at Vogtle Electric Generating Plant Units 1 & 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.
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 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
71111.21N.04 - Age-Related Degradation Age-Related Degradation (8 Samples)
(1)21202P4003M01, unit 2 normal service cooling water pump motor 3 (2)1HV9002A, unit 1 containment spray sump suction isolation valve
- (3) Capacitors (various systems)
(4)1BD1I2, unit 1 120 VAC inverter (5)1HV0442A & 1HV0442B, unit 1 reactor coolant system letdown to pressurizer relief tank, 1 Target Rock valve (6)1804A, unit 1 4160 VAC power distribution system (7)1806A, unit 1 125 VDC power distribution system (8)2403, unit 1 emergency diesel generator 1A fuel oil system and oil lube system
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 29, 2026, the inspectors presented the Focus Engineering Age-Related Degradation Inspection results to Jason Thomas and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
260961, CAR
273458, CAR
278328, CAR
498400, CR
263211, CR
273135, CR
273164, CR
273165, CR
10916682, CR
10948016, CR
11102710, CR
207100, CR
10790958
Various
Various
CR 11143744
NRC Identified-Insulation missing from 2A NSCW Pump 3
motor cooler lines
01/19/2026
Corrective Action
Documents
Resulting from
Inspection
CR 11248789
NRC Observation: 2025 Vogtle Unit 1 7 2 Age Related
Degradation Inspection
01/29/2026
1X4DB112
P & I Diagram Reactor Coolant System
44.0
1X4DB119
P&I Diagram Safety Injection System
31.0
1X4DB120
P&I Diagram Safety Injection System
28.0
1X4DB121
P & I Diagram Safety Injection System
2.0
Drawings
1X4DB131
P & I Diagram Containment Spray System
36.0
Engineering
Changes
SNC1575838
Replacement Target Rock controller boards for safety
related solenoid operated valves
2/22/2025
2-VAD014
Equivalency Determination
03/18/2002
SNC 620017
Configuration Change Evaluation (CCE) Contents Form:
NSCW Pump Motor Replacement - Unit 2 Pump 3
7.0
71111.21N.04
Engineering
Evaluations
SNC-1971884-01
Analysis on Encapsulated Valve Leakage Rate for
08/21/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1HV9002A
TE 580473
NSCW NRC issued Information Notice IN12-11, age related
capacitor degradation
1/28/2013
TE 580485
RHR NRC issued Information Notice IN12-11, age related
capacitor degradation.
1/28/2013
TE 580487
CVCS NRC issued Information Notice IN12-11, age related
capacitor degradation.
1/28/2013
1150394, TE
1160737,
TE1186431
Technical Evaluations
AX3AA04A-20006
Vogtle - Unit No. 1&2 BILL OF MATERIAL 15 KVA
ISOLIMITER TRANSFORMER
9.0
DC-1202
Design Bases: Nuclear Service Cooling Water (NSCW)
System
DC-1206
Containment Spray System Design Bases
Ver 8
DC-1804
4160 V AC System
3/31/00
DC-1807
Design Bases: 120-VAC Power System
DC-2403
Design Bases: Emergency Diesel Generator Systems
EOG PMP
Enterprise Owners Group Preventative Maintenance
Program (PMP) for Nuclear Standby Applications
PMCR 100700
50.69 AT for Cont Spray ISI Pressure Test
PMCR 101700
Removal of RISC-3 SSCs from EQ required PMs
TR-112175
Capacitor Application and
Maintenance Guide
08/1999
Miscellaneous
X3AQ03
Specification for Inverters for the Georgia Power Company
Lab No:
2510220027
Oil Sample Analysis
10/22/25
NDE Reports
Lab No:
Oil Sample Analysis
10/22/25
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2510220028
11877-2
Cold Weather Checklist
25.4
27816-C
Ametek SCI Battery Charger Maintenance
4.2
28912B-1
184-Day Unit 1 "B" Train Safety Related Battery and
Charger Inspection and Maintenance
5.1
20
IEEE Recommended Practice for Installation, Inspection,
and Testing for Class 1E Power, Instrumentation, and
Control Equipment at Nuclear Facilities
20
NMP-CH-401
Diesel Fuel Oil Program
7.3
Procedures
NMP-ES-214
Shelf Life Determination
1.2
Work Orders
25932,
1131937, 126071,
21739, 381126,
386055, 394719,
475898, 540747,
595249, 724590,
766484, 806184,
958517, 968492,
1032414,
1159647,
1159679,
1169846,
1177802,
232817,
1348532,
1394018,
23813,
1431523,
1732538,
1878511,
2033148,
2060742,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2109932,
26924,
274468,
2318840,
2351228,
2401062,
2404289,
2408165,
2408212,
2468403,
2552649,
2752025,
2766631,
2784919,
2789054,
2801605, 2801608