Latest revision as of 16:18, 2 January 2025

Text

Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010
	ML24067A215
Person / Time
Site:	Watts Bar
Issue date:	03/08/2024
From:	James Baptist; Division of Reactor Safety II
To:	Jim Barstow; Tennessee Valley Authority
References
	IR 2024010
	Download: ML24067A215 (13)
	v • d • e

SUBJECT:

WATTS BAR NUCLEAR PLANT - AGE-RELATED DEGRADATION INSPECTION REPORT 05000390/2024010 AND 05000391/2024010

Dear James Barstow:

On February 8, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar Nuclear Plant and discussed the results of this inspection with Mr. Anthony Williams, Site Vice President, 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, James B. Baptist, Chief Engineering Branch 1 Division of 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:

05000390/2024010 and 05000391/2024010

Enterprise Identifier:

I-2024-010-0021

Licensee:

Tennessee Valley Authority

Facility:

Watts Bar Nuclear Plant

Location:

Spring City, TN

Inspection Dates:

January 22, 2024 to February 08, 2024

Inspectors:

P. Carman, Senior Reactor Inspector

J. Copeland, Reactor Inspector

C. Even, Sr. Reactor Inspector

J. Lizardi-Barreto, Reactor Inspector

Approved By:

James B. Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an age-related degradation 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

71111.21N.04 - Age-Related Degradation Age-Related Degradation

Main article: IP 71111.21

For each sample listed below, inspectors reviewed licensee activities credited to address age-related degradation to assess whether they were being performed using appropriate standards and procedures, assessed against appropriate acceptance criteria, and that maintenance was being performed at an appropriate interval. Inspectors assessed whether issues identified during licensee activities were being appropriately entered into and addressed by the station corrective action program, and whether periodic assessments of maintenance effectiveness and operating experience were being completed.

(1)480 VAC shutdown board breaker (0-BKR-548-131-S)

(2) A-A main control room heating ventilation and air conditioning air handling unit motor (0-MTR-31-12-A)

(3) Auxiliary building gas treatment system containment purge air isolation dampers (1,2-FCO-30-294/295)

(4) Control rod drive mechanism (CRDM) thermal sleeves

(5) Essential raw cooling water (ERCW) discharge piping (C-A)

(6) ERCW motor cooler (pumps A-A, B-A, C-A, D-A, E-B, F-B, G-B, H-B)

(7) Unit 1 and 2 hydrogen igniters

(8) Unit 2 motor driven auxiliary feedwater (MDAFW) pump 2B-B motor oil and bearings

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 8, 2024, the inspectors presented the age-related degradation inspection results to Mr. Anthony Williams, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

v t e Inspection Report - Watts Bar - 2024010
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
2024 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 10(0) 7(0) 40(0) Security 401(0) 402(0) 403(0) 440(0) Operator Exams 301(0) Emergency Planning Other

IR 05000390/2024010: Difference between revisions