IR 05000327/2025004
| ML26033A012 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-077, DPR-079) |
| Issue date: | 02/09/2026 |
| From: | Renee Taylor NRC/RGN-II/DORS/PB5 |
| To: | Erb D Tennessee Valley Authority |
| References | |
| IR 2025004 | |
| Download: ML26033A012 (0) | |
Text
SUBJECT:
SEQUOYAH UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000327/2025004 AND 05000328/2025004
Dear Delson Erb:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah Units 1 and 2. On January 6, 2026, the NRC inspectors discussed the results of this inspection with Ricardo Medina, Site Regulatory Compliance Manager, 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, Ryan C. Taylor, Chief Projects Branch 5 Division of Operating Reactor Safety Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000327 and 05000328
License Numbers:
Report Numbers:
05000327/2025004 and 05000328/2025004
Enterprise Identifier:
I-2025-004-0026
Licensee:
Tennessee Valley Authority
Facility:
Sequoyah Units 1 and 2
Location:
Soddy-Daisy, TN
Inspection Dates:
October 1 to December 31, 2025
Inspectors:
K. Lei, Emergency Preparedness Inspector
P. Meier, Senior Resident Inspector
A. Price, Resident Inspector
M. Rich, Emergency Preparedness Inspector
J. Walker, Senior Emergency Preparedness Inspector
Approved By:
Ryan C. Taylor, Chief
Projects Branch 5
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Sequoyah 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 05000327/2025-001-01 Unit 1, Manual Reactor Trip due to Reboot of the Distributed Control System and Lowering Steam Generator Levels 71153 Closed LER 05000328/2025-002-01 Unit 2, Manual Reactor Trip due to a Failed Closed Main Feedwater Regulating Valve 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at approximately 100 percent rated thermal power (RTP). On October 3, 2025, unit 1 came offline for refueling outage 1R27. Unit 1 was restarted on December 1, 2025, and entered Mode 1. Refueling outage 1R27 ended on December 6, 2025, after synchronizing unit 1 to the grid. Unit 1 achieved approximately 100 percent RTP on December 8, 2025, and remained at or near 100 percent RTP for the remainder of the inspection period.
Unit 2 began the inspection period at approximately 100 percent RTP. On November 1, 2025, unit 2 came offline for a reactor coolant pump seal replacement. The unit returned to 100 percent RTP on November 10, 2025, and remained at or near 100 percent 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 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
71111.01 - 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 during the week of November 10, 2025:
- main steam valve vaults
- refueling water storage tanks
- essential raw cooling water
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 2 A train essential raw cooling water system while B train was inoperable for planned unit 1 essential raw cooling water piping replacement on October 14, 2025 (2)unit 1 auxiliary feedwater system prior to startup following unit 1 refueling outage U1R27 on November 26, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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)unit 1 containment annulus on November 19, 2025 (2)unit 1 upper containment on November 21, 2025 (3)unit 1 lower containment on November 24, 2025
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." The inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, and the crew simulator operating examinations in accordance with IP 71111.11, "Licensed Operator Requalification Program and Licensed Operator Performance." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered in September 2025.
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 unit 1 down power and cool-down for refueling outage 1R27 on October 4, 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 "A" train containment spray heat exchanger on December 23, 2025
Quality Control (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the effectiveness of maintenance and quality control activities during the unit 1 refueling outage, 1R27, (October 2025 through November 2025) to ensure the following components remained capable of performing their intended functions:
- unit 1 loop one cold leg injection check valve (1-VLV-063-0560) overhaul (work order [WO] 122863332)
- unit 1 B train low head safety injection hot leg flow control valve (1-FCV-063-0172-B) overhaul (WO 124420608)
- essential raw cooling water "B" train isolation valve (1-VLV-067-1603B)replacement (WO 125630221)
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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 2 loop two reactor coolant pump seal leakage identified on October 12, 2025 (condition report [CR] 2043734)
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)unit 1 main steam safety valve testing configuration impact to operability on October 1 and 2, 2025 (WO 124490658; procedure 0-SI-SXV-001-859.0)
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)
- (1) The inspectors evaluated refueling outage 1R27 activities from October 4 to December 6, 2025.
- (2) The inspectors evaluated the unit 2 forced outage to replace the loop 2 reactor coolant pump seal from November 2 to November 8, 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) (2 Samples)
(1)unit 1 loop one cold leg injection check valve overhaul during refueling outage 1R27 in October and November 2025 (WO 122863332)
(2)unit 1 turbine driven auxiliary feedwater pump governor valve maintenance on November 28, 2025 (WO 124357493)
Surveillance Testing (IP Section 03.01) (2 Samples)
(1)unit 1 turbine driven auxiliary feedwater pump comprehensive testing on October 2, 2025 (WO 124491566)
(2)1A-A emergency diesel generator loss of offsite power with safety injection testing on October 5, 2025 (WO 124490651)
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)containment isolation valve local leak rate test for the unit 1 upper compartment air monitor intake inboard isolation valve, FCV-90-116, on October 27, 2025 (procedure 0-SI-SLT-090-258.1, CR 2046929)
Ice Condenser Testing (IP Section 03.01) (1 Sample)
(1)unit 1 ice condenser as-left ice weighing on October 28, 2025 (0-SI-MIN-061-105.0)
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of December 8, 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 December 8, 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 December 8, 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 December 8, 2025.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) October 1, 2024, through September 30, 2025 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) October 1, 2024, through September 30, 2025 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14) (1 Sample)
- (1) October 1, 2024, through September 30, 2025
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (2 Samples)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000327/2025-001-01, Manual Reactor Trip Due to Reboot of the Distributed Control System and Lowering Steam Generator Levels (ADAMS Accession No.
ML25295A001). The inspectors reviewed the updated LER submittal and did not identify a performance deficiency or violation of NRC requirements. The previous LER submittal was reviewed in integrated inspection report 05000327/2025003 and 05000328/2025003. This LER is closed.
- (2) LER 05000328/2025-002-01, Manual Reactor Trip Due to a Failed Closed Main Feedwater Regulating Valve (ADAMS Accession No. ML25275A002). The inspectors reviewed the updated LER submittal and did not identify a performance deficiency or violation of NRC requirements. The previous LER submittal was reviewed in integrated inspection report 05000327/2025003 and 05000328/2025003. This LER is closed.
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 6, 2026, the inspectors presented the integrated inspection results to Ricardo Medina, Site Regulatory Compliance Manager, and other members of the licensee staff.
- On December 10, 2025, the inspectors presented the emergency preparedness program inspection results to Ricardo Medina, Site Regulatory Compliance Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
0-PI-OPS-000-006.0
Freeze Protection
Revision 78
Procedures
RXB-0-679-01
Fire Protection Pre-Fire Plans: Reactor
Building
Rev 3
Corrective Action
Documents
CR 2050905
1A CS HTX differential pressure
exceeded ACMP values
11/14/2025
Corrective Action
Documents
CR 2051937
Discovered that in 2024 and 2025 the
ERCW fall non-oxidizing biocide
treatments (molluscicide) was not
performed.
11/19/2025
Corrective Action
Documents
CR 2052231
Incorrect DP gauge installed
11/20/2025
Corrective Action
Documents
CR 2052391
Live clams found inside 1A CS HX
11/21/2025
Corrective Action
Documents
CR 2052468
Inlet Flange Bolting Material appears to
be the wrong material
11/22/2025
Work Orders
1A CS HX differential pressure
11/21/2025
Corrective Action
Documents
28235, 1984601, 1979022,
1979096, 2018923, 2003168,
1990953, 1982622, 1978117,
1961523, 1959377
CRs related to ERO, Training, Drills,
and OSC Speakers
Miscellaneous
ERO Augmentation Reports
Miscellaneous
OSSA
On shift staffing analysis in Eplan
Procedures
ERO Training procedures, EPIPs
related to ERO Callout
Miscellaneous
December
11, 2024
Procedures
EPIP-1
Emergency Classification Matrix
Revision 64
Procedures
EPIP-1, Attachment 1
Revision 64
Procedures
NPG-SPP-22.300
CAP Governing Procedures
Rev. 0027
Procedures
REP-Appendix B
Sequoyah Nuclear Plant Radiological
Rev. 111
Procedures
REP-Generic
Radiological Emergency Plan (Generic
Rev. 117
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Part)
Self-Assessments
24 SQN December Exercise
24 SQN December Graded Exercise
QA Record
2/11/2024
Self-Assessments
25 SQN July EMPE
25 SQN July EMPE
07/23/2025
Self-Assessments
25 SQN May Tabletop
25 SQN May Blue Team Tabletop QA
Record
05/21/2025
Self-Assessments
Baseline Assessment
25 SA signed NRC Baseline
assessment full package
8/30/25