ML24016A304

Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump

ML24016A304
Person / Time
Site:	Browns Ferry
Issue date:	01/16/2024
From:	Sivaraman M Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24016A304 (1)

Text

Post Office Box 2000, Decatur, Alabama 35609-2000

January 16, 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 Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump

References:

1. Letter from TVA to NRC, Interim Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump, dated October 6, 2023 (ML23282A002)

2. Letter from TVA to NRC, Interim Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump, dated November 16, 2023 (ML23320A254)

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

On August 10, 2023, following completion of maintenance on the D1 Residual Heat Removal Service Water (RHRSW) Pump and its check valve 0-CKV-023-0565, the check valve failed post-maintenance testing due to failure of the valve to fully close resulting in backwards rotation of the RHRSW Pump. BFN completed its 10 CFR Part 21 discovery process and determined the need to perform a 10 CFR Part 21 Evaluation. The vendor for testing (Watts Water) was contacted and assumed responsibility for performing the 10 CFR Part 21 Evaluation for the check valve (Reference 1, 2).

The check valves were returned to Watts Water for testing. Following vendor testing and in consultation with Watts Water, an evaluation conducted by TVA 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 January 16, 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 M Si araman Site Vice President

cc (w/ Enclosures):

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