ML24032A476

Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve

ML24032A476
Person / Time
Site:	Browns Ferry
Issue date:	02/01/2024
From:	Sivaraman M Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24032A476 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000 February 1, 2024 10 CFR 21.21 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve

Reference:

Letter from TVA to NRC, Interim Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve, dated December 14, 2023 (ML23348A394)

In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 21.21(a)(2), the Tennessee Valley Authority (TVA) is submitting this report for Browns Ferry Nuclear Plant (BFN).

On October 13, 2023, a new starter contactor was found to be defective during post-maintenance testing on a circuit breaker for the BFN, Unit 1, High Pressure Coolant Injection pump. This issue was promptly entered into the TVA Corrective Action Program as Condition Report (CR) 1886000.

BFN completed its 10 CFR Part 21 discovery process and determined the need to perform a 10 CFR Part 21 Evaluation. This Part 21 Evaluation is being tracked by TVA under CR 1887094. The vendor, GE-Hitachi (GEH), was contacted and assumed responsibility for performing the Part 21 Evaluation for this relay.

The contactor was returned to GEH for testing and evaluation. The vendors evaluation, tracked under CR 1894524, determined that there was no deviation in the basic component.Therefore, this condition is not reportable under 10 CFR Part 21.

U.S. Nuclear Regulatory Commission Page 2 February 1, 2024 There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact David Renn, Site Licensing Manager, at (256) 729-2636.

Respectfully, M. Sivaraman Site Vice President cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant M Si