IR 05000390/2025011

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Biennial Problem Identification and Resolution Inspection Report 05000390/2025011 and 05000391/2025011
ML25267A201
Person / Time
Site: Watts Bar  
Issue date: 09/25/2025
From: Renee Taylor
Division of Operating Reactors
To: Erb D
Tennessee Valley Authority
References
IR 2025011
Download: ML25267A201 (1)


Text

SUBJECT:

WATTS BAR NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000390/2025011 AND 05000391/2025011

Dear Delson Erb:

On August 21, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at Watts Bar Nuclear Plant and discussed the results of this inspection with Chris Reneau, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspection team reviewed the stations problem identification and resolution program to confirm that the station was complying with NRC regulations and licensee standards. Based on the samples reviewed, the team determined that the stations program complies with NRC regulations and applicable industry standards such that the Reactor Oversight process can continue to be implemented.

The team also evaluated the stations effectiveness in identifying, prioritizing, evaluating, and correcting problems, reviewed licensee audits and self-assessments, and its use of industry and NRC operating experience information. The results of these evaluations are in the enclosure.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, the team found no evidence of challenges to the organizations safety-conscious work environment. Employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

No findings or violations of more than minor significance were identified during this inspection.

September 25, 2025 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, Branch Chief Projects Branch 5 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:

NPF-90 and NPF-96

Report Numbers:

05000390/2025011 and 05000391/2025011

Enterprise Identifier:

I-2025-011-0026

Licensee:

Tennessee Valley Authority

Facility:

Watts Bar Nuclear Plant

Location:

Spring City, Tennessee

Inspection Dates:

August 4, 2025 to August 21, 2025

Inspectors:

P. Braxton, Reactor Inspector

N. Childs, Senior Project Engineer

A. Price, Resident Inspector (Team Lead)

R. Wehrmann, Resident 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 a biennial problem identification and resolution 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

Type Issue Number Title Report Section Status CAPR 05000391/2025011-01 Watts Bar Unit 2 95001 CAPRs (Unplanned Scrams Performance Indicator)71152B Closed

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.

OTHER ACTIVITIES - BASELINE

71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 03.04)

(1) The inspectors performed a biennial assessment of the effectiveness of the licensees Problem Identification and Resolution program, use of operating experience, self-assessments and audits, and safety conscious work environment.
  • Problem Identification and Resolution Effectiveness: The inspectors assessed the effectiveness of the licensees Problem Identification and Resolution program in identifying, prioritizing, evaluating, and correcting problems, including an in-depth corrective action program review of the following systems or portions thereof: essential raw cooling water, auxiliary feedwater, and 6.9 kV reactor shutdown power. The inspectors also conducted a five-year review of the essential raw cooling water system. The corrective actions for the following violations and findings were evaluated as part of the assessment: non-cited violation (NCV) 2023011-01, 2023010-01, 2023002-01, 2023003-02, 2023003-03, 2023003-04, 2023003-05, 2023004-02, 2023004-03, 2024001-01, 2024001-04, 2024001-05, 2024001-09, 2024002-02, 2024002-03, 2024003-05, 2024003-06, 2024004-01, 2024440-01, 2025001-01, two licensee-identified violations (LIV) from IR 2024004, minor violation (MV) 2023010, 2024002, 2024004.
  • Operating Experience: The inspectors assessed the effectiveness of the licensees processes for use of operating experience.
  • Self-Assessments and Audits: The inspectors assessed the effectiveness of the licensees identification and correction of problems identified through audits and self-assessments.
  • Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
  • The inspectors reviewed the completed corrective actions to prevent recurrence that were not complete at the time of the 95001 Supplemental Inspection (ML25013A198, dated January 16, 2025) associated with a White performance indicator for Unplanned Scrams per 7000 Critical Hours. The inspectors verified these corrective actions had been completed as scheduled.

INSPECTION RESULTS

Assessment 71152B Watts Bar Biennial PI&R Assessment 1) Problem Identification and Resolution Effectiveness Problem Identification: Based on a review of the requirements for initiating condition reports as described in licensee procedure NPG-SPP-22.300 Rev. 26, "Corrective Action Program,"

the inspectors determined that the licensee was effective in identifying problems and entering them into the corrective action program (which includes the work management system), and there was a low threshold for entering issues into the corrective action program. Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.

Problem Prioritization and Evaluation: Based on the review of condition reports, work orders, and work requests, the inspectors determined that problems were prioritized and evaluated in accordance with licensee guidance. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that in general, plant personnel had conducted cause evaluations in compliance with the licensees corrective action program procedures and cause determinations were appropriate, and considered the significance of the issues being evaluated.

Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that generally, corrective actions were timely, commensurate with the safety significance of the issues, and effective, in that conditions adverse to quality were corrected. The team determined that the licensee was generally effective in developing corrective actions that were appropriately focused to also address the root and contributing causes for significant conditions adverse to quality to preclude repetition. Effectiveness reviews for corrective actions to preclude repetition were sufficient to ensure corrective actions were properly implemented and were effective. However, in the area of corrective action, the inspectors documented one observation in the Results section of this report regarding traceability of lubricants used in safety related components. The licensee initiated condition report 2029540 to address this observation.

Based on the samples reviewed, the team concluded that the licensees corrective action program complied with regulatory requirements and self-imposed standards. The licensees implementation of the corrective action program adequately supported nuclear safety.

2) Operating Experience The team determined that the stations processes for the use of industry and NRC operating experience information were effective and complied with regulatory requirements and licensee standards. The implementation of these programs adequately supported nuclear safety. The team concluded that operating experience was adequately evaluated for applicability and that appropriate actions were implemented in accordance with applicable procedures.

3) Self-Assessments and Audits The inspectors determined that the licensee was effective at performing self-assessments and audits to identify issues at a low level, properly evaluated those issues, and resolved them commensurate with their safety significance. The self-assessments and audits were adequately self-critical and performance-related issues were being appropriately identified. The inspectors verified that action requests were created to document areas for improvement and findings and verified that actions had been completed consistent with those recommendations.

4) Safety-Conscious Work Environment Based on interviews with plant staff and reviews of the latest safety culture survey results, the team found no evidence of challenges to a safety conscious work environment. Employees interviewed appeared willing to raise nuclear safety concerns through at least one of the several means available.

Observation: Failure to Maintain Traceability of Lubricants Used in Safety-Related Applications 71152B During a review of corrective action documents associated with a previously documented Minor Violation (ML25043A055), Failure to Maintain Traceability of Lubricants Used in Safety-Related Applications, inspectors reviewed more recent work orders to determine if the corrective actions had addressed the previous non-compliance. Work orders 124923796, 124923301, and 124664943 were reviewed, and none contained the required traceability information to document the lubricants used in the safety related components. The licensee captured this observation in condition report

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On August 21, 2025, the inspectors presented the biennial problem identification and resolution inspection results to Chris Reneau, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

907579; 1522957; 1592395;

1603265; 1647893; 1713247;

1756422; 1838907; 1854299;

1858712; 1869965; 1870216;

1870420; 1872342; 1873023;

1873548; 1875432; 1876645;

1879973; 1884979; 1887083;

1887085; 1890139; 1892182;

1894498; 1902221; 1907126;

1907128; 1914685; 1914803;

1917809; 1920266; 1923202;

23532; 1923548; 1926632;

28330; 1930872; 1931733;

1942040; 1942549; 1947461;

1952237; 1962168; 1970517;

1971248; 1985658; 1992762;

2005430; 2019407; 1892748;

2000227; 1985651; 1887599;

1878981; 1876051; 1865502;

1379214; 1972147; 1989420;

1992767; 1906093; 1848149;

1881873; 1881911; 1881663;

1866399; 1866416; 1866581;

20732; 2020426; 2020324;

1893269; 1982910; 1890684;

1872637; 1928330; 1930872;

21724; 1931797; 1921517;

1959207; 1921259; 1870942;

1887307; 1878981; 1887078;

26163; 1923535; 1923540;

1942542; 1947477; 1961825;

1964436; 1964445; 1992767;

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1972147; 1989437; 1964405

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 2029540

Traceability of lubricants used in Safety Related

applications

07/31/2025

71152B

Corrective Action

Documents

Resulting from

Inspection

CR 2034566

25 WBN PI&R NRC Comment

08/26/2025

71152B

Drawings

0-15E500-2

Station Aux Power System Units 1 & 2

71152B

Drawings

1-45W724-2

6900V Shutdown Board 1B-B Single Line

Wiring Diagram

71152B

Drawings

1-45W749-2

480V Shutdown Board 1B1-B Single Line

Wiring Diagram

71152B

Drawings

1-45W749-4

480V Shutdown Board 1B2-B Single Line

Wiring Diagram

71152B

Miscellaneous

Health Report Scorecard for Auxiliary

Feedwater (System 003B)

March 20,

25

71152B

Miscellaneous

WBN 200, 201,202,211

System Health Report

04/2025

71152B

Miscellaneous

QA-CH-24-001

Radiological Emergency Preparedness

Performance Assessment, Browns Ferry

Nuclear Plant (BFN), Fleet Center (FC),

Sequoyah Nuclear Plant (SQN), Watts Bar

Nuclear Plant (WBN)

January 8 -

18, 2024

71152B

Miscellaneous

SDD-N3-3B-4002

System Description, Auxiliary Feedwater

System

Revision 34

71152B

Miscellaneous

SSA2303

Audit Report - Chemistry, Effluent, and

Environmental Monitoring Watts Bar Nuclear

Plant (WBN)

September

25, 2023 -

February 1,

24

71152B

Miscellaneous

SSA2501

Audit Report, Radiological Emergency

Preparedness (REP) Watts Bar Nuclear Plant

(WBN)

November

2, 2024 -

February 4,

25

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Procedures

NPG Cause Evaluation Training Manual

Revision 17

71152B

Procedures

0-TI-100.011

IST Program Bases Document

Revision 4

71152B

Procedures

0-TI-119

Maintenance Rule Performance Indicator

Monitoring, Trending, and Reporting -

10CFR50.65

Revision 13

71152B

Procedures

0-TI-66.004

Temporary Dehumidifiers in Upper

Containment

Revision 2

71152B

Procedures

0-TI-78

Lubrication Program

26

71152B

Procedures

MMDP-1

Maintenance Management System

Revisions

43, 48

71152B

Procedures

NPG-SPP-03.5

Regulatory Reporting Requirements

Revision 21

71152B

Procedures

NPG-SPP-04.003

Material Storage and Handling

006

71152B

Procedures

NPG-SPP-06.1

Work Order Process

016

71152B

Procedures

NPG-SPP-06.10

NPG Fix It Now (FIN) Team Process

007

71152B

Procedures

NPG-SPP-06.2

Preventive Maintenance

017

71152B

Procedures

NPG-SPP-09.16.1

System, Component and Program Health

Revision 18

71152B

Procedures

NPG-SPP-22.102

Self-Assessment and Benchmarking Programs

Revision 15

71152B

Procedures

NPG-SPP-22.300

Corrective Action Program

Revision 26

71152B

Procedures

NPG-SPP-22.302

Condition Report Screening

Revision 15

71152B

Procedures

NPG-SPP-22.305

Level 2 Evaluations

Revision 8

71152B

Procedures

NPG-SPP-22.306

Level 1 Evaluations

Revision 8

71152B

Procedures

NPG-SPP-22.500

Operating Experience Program

Revision 18

71152B

Procedures

NPG-SPP-22.600

Issue Resolution

Revision 15

71152B

Procedures

WB-DC-30-28

Low and Medium Voltage Power Unit1/Unit2

Revision 23

71152B

Work Orders

07-820464-011; 119741063;

20523453; 121697642;

21789593; 124422780;

25079884; 115921084;

119342365; 115573591;

2466728; 113916830;

115573592; 116194368;

117128240; 118695785;

119342365; 115921084;

108127150; 121789928;

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

21934731; 123303128;

24179781; 124531769;

24561544; 124571873;

24498845; 124595571;

25402569