IR 05000390/2026010
| ML26078A364 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  (NPF-090, NPF-096) |
| Issue date: | 03/20/2026 |
| From: | Christopher Even NRC/RGN-II/DORS/EB1 |
| To: | Erb D Tennessee Valley Authority |
| Shared Package | |
| IR 2026010 | List: |
| References | |
| IR 2026010 | |
| Download: ML26078A364 (0) | |
Text
SUBJECT:
WATTS BAR NUCLEAR PLANT - NRC INSPECTION REPORT 05000390/2026010 AND 05000391/2026010
Dear Delson C. Erb:
On February 26, 2026, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar Nuclear Plant and discussed the results of this inspection with William C. Reneau 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, Acting Chief Engineering Branch 1 Division of Operating Reactor Safety Docket Nos.: 05000390 and 05000391 License Nos.: NPF-90 and NPF-96
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000390 and 05000391
License Numbers:
Report Numbers:
05000390/2026010 and 05000391/2026010
Enterprise Identifier:
I-2026-010-0025
Licensee:
Tennessee Valley Authority
Facility:
Watts Bar Nuclear Plant
Location:
Spring City, TN
Inspection Dates:
February 09, 2026 to February 26, 2026
Inspectors:
P. Alier, Reactor Inspector
P. Braaten, Senior Reactor Inspector
P. Braxton, Reactor Inspector
M. Carothers, Reactor Inspector
L. Day, Reactor Inspector
S. Hamilton, Resident Inspector
B. Stuckart, 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 NRC inspection at Watts Bar Nuclear Plant, 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
71111.21M - Comprehensive Engineering Team Inspection The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Structures, Systems, and Components (SSCs) (IP Section 03.01) (5 Samples)
For each component sample, the inspectors reviewed the licensing and design bases including:
- (1) the Updated Final Safety Analysis Report (UFSAR);
- (2) the Technical Specifications (TS); and
- (3) the Technical Requirements Manual (TRM). The inspectors reviewed a sample of operating procedures (including normal, abnormal, and emergency procedures) and overall system/component health (including condition reports and operability evaluations, if any). The inspectors performed visual inspections of the accessible components to identify potential hazards and/or signs of degradation. Additional component specific design attributes reviewed by the inspectors are listed below.
- (1) Control room heating, ventilation, and air conditioning system
- Seismic and Structural Integrity
- (2) Unit 1 480V shutdown board 1A1-A ( 1BD-212-A1-A)
- Protection and coordination
- Protective relays calibrations and breakers maintenance
- (3) Unit 1 6.9kV shutdown board 1A-A ( 1-BD-211-A-A) and breakers
- Protection and coordination
- Protective relays calibrations and breakers maintenance
- (4) Unit 1 safety injection
- Lube oil system
- (5) Chemical volume and control system (high head injection portion)
- Emergency operating procedures and abnormal operating procedures operational implementation
Modifications (IP Section 03.02) (2 Samples)
- (1) WBN-21-074, Main steam dump valve control upgrade
- (2) WBN-21-055-03/04/05/06/09, Pressurizer heater transformer replacements 10 CFR 50.59 Evaluations/Screening (IP Section 03.03) (7 Samples)
- (1) WBN-24-075, Replace main control room A chiller oil pump starter
- (2) WBN-20-1243-03, Emergency diesel generator governor actuators replacement
- (3) WBN-18-255, Intake security upgrade
- (4) WBN-19-759, Replace unit 1 inadequate core cooling monitor
- (5) WBN-22-019-01/2, Replace 500kV feeder differential relay set
- (6) WBN-21-074, Main stem dump valve control upgrade
- (7) WBN-24-077, Main feed pump trip to bypass
Operating Experience Samples (IP Section 03.04) (1 Sample)
- (1) OpE Smart Sample 2023/01 - Digital instrumentation and controls
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 26, 2026, the inspectors presented the NRC inspection results to William C. Reneau and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CDQ0000682022000000
NEDP-2-1
Anchorage Design For Category I Transformers in the
Auxiliary Building
EPMGRS022693
Evaluation of System 63 Safety Injection Pump Suction
Components for Increased System Design Pressure
Rev. 04
EPMIW052490
Air handling units structural integrity
05/31/1990
EPMJKJ013088
SIS Operating Modes
Rev. 10
EPMLCP110689
MCR normal and emergency pressurization equipment
performance adequacy
EPMSNM043092
Failure Modes and Effects Analysis for Safety Injection
System
Rev. 11
MDQ00106320060110
CCP, SIP, CSP, and RHR Pump NPSH Analysis
Rev. 5
NEDP-9-1(1-LUB-
TX17484S)
S/SQ Review/ Approval: Hitachi Energy USA Test Report
for Transformer Seismic Certification.
WBNAPS2032
Water Hammer Analysis of SIS Piping due to Check
Valve Closure on Pump Trip
Rev. 5
WBNOSG4095
Selection Criteria for Motor Operated Valves Requiring
Thermal Overload Bypass
Rev. 22
Calculations
WBNOSG4099
MODERATE ENERGY LINE BREAK FLOODING
STUDY (Flood Calculations Including Rooms 782-A1, -
A2, -A3 and -A4)
Corrective Action
Documents
CR 2008999
CR 2009000
CR 2034774
Condition Reports that specifically were a result from the
execution of the WOs for the WBN-21-055 Child Change
Packages.
CR 2066982
26 NRC CETI - Bolt on 1A SI Pump Shaft Shroud
Needs to be Tightened
2/10/2026
CR 2067005
26 CETI Inspection - Potential Leak on Threaded
Connection
2/10/2026
Corrective Action
Documents
Resulting from
Inspection
CR 2067014
26 CETI Inspection - Capillary Tubing Needs Protected 02/10/2026
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 2067180
26 NRC CETI Inspection - Oil Level High on 1A and
1B SI Pumps
2/11/2026
CR 2067263
26 NRC CETI - Vendor Manual WBN-VTD-P318-1430
has incorrect number in header
2/11/2026
CR 2067546
26 NRC CETI - Copper Wire NRC Identified
2/12/2026
CR 2067546 - Copper
Wire
CR 2067568
CR 2067584
Condition Reports for Loose Bolts found on 480 V
Transformers and Extra Pieces of Copper Conduit during
Plant Walkdown in Auxiliary building
CR 2067568
26 NRC CETI - Loose bolt on 2-DXF-68-341H
2/12/2026
CR 2067584
26 NRC CETI - Loose Bolts on 2-DXF-68-341A
2/12/2026
1-45W724-1
Wiring Diagram, 6900 Shutdown Board 1A-A
Rev. 35
1-45W749-1
Wiring Diagram, 480V Shutdown Board 1A1-A Single
Line
Rev. 69
Drawings
WBN-0-47E235-5-CC
006760411
Auxiliary Building Units 1 & 2 Environmental Data EL
2.0
WBN-0-2024-205-001
480 V Turbine Building Lighting Boards Temporary
Power Commercial Change Package.
WBN-055-03
WBN-055-04
WBN-055-05
WBN-055-06
WBN-055-09
Design Equivalent Change Packages: Child Packages for
WBN-21-055 Design Equivalent Change Package for
Replacement of 480 V Transformers (PZR HTR and Turb
Bldg Transformers).
Rev 1
WBN-18-255,
H.5
Intake Pumping Station Upgrades
Rev. 00
WBN-19-759
Design Change Package for Replacement of Unit 1
ICCM and 50.59 Screening.
WBN-20-1243
EDG Governor Annunciator Removal 1BB
Engineering
Changes
WBN-21-055
Design Equivalent Change Package, Parent Package:
Replacement of 480 V Transformers
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
WBN-21-055 10CFR
50.59 Screening
SCREENING REVIEW/50.59 EVALUATION for ECP
WBN-21-055 Parent Package.
WBN-21-074
Main Steam Dump Valve Controls Upgrade
Rev. 02
WBN-22-019
Design Equivalent Change Package and 50.59
Screening
WBN-24-075
Replace MCR A Chiller Obsolete Oil Pump Motor Starter
PER 02-002116-000
Performance Evaluation Report for Oil Level Identification
and Resolution
2/20/2002
Engineering
Evaluations
Surveillance Test Risk-
Informed Documented
Evaluation (STRIDE)
STRIDE to Extend the Frequency for the Pressurizer
Heater Capacity Check Evaluation
CNL-20-016
LAR Application to Modify WBN Unit 1 Tech Specs 3.3.3
PAMS (WBN-TS-19-23)
FAT-TVA-7495945
Factory Acceptance Test Report for WBN-21-074
Rev. 00
PR-WBN-21-055-01
PR-WBN-21-055-04
Procurement Requests for 480 V Transformers
WB-DC-30-28
Design Criteria Document - LOW AND MEDIUM
VOLTAGE POWER SYSTEMS
WBN-SDD-N3-63-4001
Rev. 41
WBN-VTD-A996-0010
Areva EOI 17, DS Breaker Reconditioning Process
Rev. 2
WBN-VTD-D245-0350
Operating & Maintenance Instructions for Dresser Pump
Division (Formerly Pacific Pumps) Model JHF Safety
Injection Pumps
Rev. 22
Miscellaneous
WBN-VTD-G080-0660
Magne-Blast Circuit Breaker 1200 AND 2000 Ampres
Rev. 8
0-GOI-7
Generic Equipment Operating Guidelines
Rev.16
0-MI-57.036
Electric Motor/Generator Replacement and Bearing
Maintenance
Rev. 06
Procedures
0-MI-57.036
Electric Motor/Generator Replacement and Bearing
Maintenance
Rev. 10
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-MI-57.036
Electric Motor/Generator Replacement and Bearing
Maintenance
Rev. 13
0-PI-OPS-1.0
Operator Aid Review Verification
Rev. 13
0-TI-100.006
Inservice Testing Program
Rev. 13
0-TI-78
Lubrication Program
Rev. 27
0-TI-SFCP-STI-WBN
Surveillance Test Interval (STI) Table
0032
1-AOI-15
Loss of Component Cooling Water
Rev. 09
1-AOI-20
Malfunction of Pressurizer Level Control System
Rev. 13
1-PI-OPS-1-AB_RW
Auxiliary Building / Radwaste AUO Work Station
Responsibilities
Rev. 24
1-SI-68-35 SI 18 /19 / 20 Surveillance Task Sheet (STS) Procedure 2-SI-68-35
PZR HTR Capacity (Surveillances: Completed every 18
months)
2-SI-68-35 SI 17 / 18 /
Surveillance Task Sheet (STS) for Procedure: 2-SI-68-
35, PZR HTR CAPACITY Surveillance (Conducted every
months)
E-0
Reactor Trip or SI
Rev. 35
E-1
Loss of Reactor or Secondary Coolant
Rev. 19
CVCS Emergency Abnormal Operations
Rev. 01
FR-S.1
Response to Nuclear Power Generation ATWS
Rev. 23
N3-30CB-4002
CONTROL BUILDING HEATING, VENTILATING, AIR
CONDITIONING, AND AIR CLEANUP SYSTEM
NEDP-5
Design Document Reviews
Rev. 16
NEPD-22
Operability Determinations and Functional Evaluations
Rev. 25
NISP-IP-ENG-001
Standard Design Process
Rev. 03
NPG-SPP-01.18
Emergent Issue Response and Resolution
Rev. 04
NPG-SPP-09.4
CFR 50.59 Evaluations of Changes, Tests, and
Experiments
Rev. 21
NPG-SPP-09.5
Temporary Modifications Temporary Configuration
Rev. 21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
OPDP-8
Operability Determination Process and Limiting
Conditions for Operation Tracking
Rev. 34
P.S.4.M.1.5
CLASSIFICATION, PROCUREMENT, RECEIPT AND
USE OF LUBRICANTS
Rev. 10
SDD-N3-68-4001 DOC
000050
System Description Document
REACTOR COOLANT SYSTEM: Unit 1 / Unit 2: QA
Record
0050
TVA-NQA-PLN89-A
Quality Assurance Program Description for
TVA Nuclear
Rev. 45
Shipping Records MEL-WBN-21-055-03-R
MEL-WBN-21-055-04-R
MEL-WBN-21-055-05-R
MEL-WBN-21-055-06-R
MEL-WBN-21-055-09-M
Component Update Requests for Transformer
Procurements.
21461932
Diesel generator engine inspection
04/19/2021
24969146
1-SI-63-901-B SAFETY INJECTION PUMP 1B-B
QUARTERLY PERFORMANCE TEST
09/19/2025
24969258
-SI-63-901 -A SAFETY INJECTION PUMP 1A-A
QUARTERLY PERFORMANCE TEST
09/09/2025
25690389
High Vibrations on CCP Room Cooler 2B-B
10/20/2025
Various
2771532, 121491708, 122772792, 121492327,
2772851, 124557984, 125146661, 120291038,
114561749, 120291045, 119825474, 122993817,
23119793, 124400950, 125186181, 121851494,
21659812, 125815273
Work Orders
WBN-21-055 Routine
WO 123852896 WBN-21-055, MOE, PMT TURN BLDG
Lighting BD TRANS 1
WO 123199641 WBN-21-055-06, MOE, PMT, PRESS
HTR, BACKUP GRP TRANS 2C
WO 123199637 WBN-21-055-05, MOE, PMT, PRESS
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
HTR CONT GRP TRANS 2D
WO 123199633 WBN-21-055-04, MOE, PMT, PRESS
HTR BACKUP GRP TRANS 2B-B
WO 123199629 WBN-21-055-03, PMT, PRESS HTR
BACKUP GRP TRANS 2A-A
Site Acceptance Tests for Child Design Change
Packages.