05000296/LER-2022-001, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints

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Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
ML22192A036
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 07/11/2022
From: Rasmussen M
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 2022-001-00
Download: ML22192A036 (9)


LER-2022-001, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2962022001R00 - NRC Website

text

Post Office Box 2000, Decatur, Alabama 35609-2000 July 11, 2022 10 CFR 50.73 10 CFR 50.4(a)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296

Subject:

Licensee Event Report 50-296/2022-001 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints The enclosed Licensee Event Report provides details of the inoperability of Main Steam Relief Valves for longer than allowed by plant Technical Specifications. The Tennessee Valley Authority is submitting this report in accordance with Title 10 of the Code of Federal Regulations 50.73(a)(2)(i)(B), as any operation or condition which was prohibited by the plants Technical Specifications.

There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Chris L. Vaughn, Site Licensing Manager, at (256) 729-2636.

Respectfully, Matthew Rasmussen Site Vice President Enclosure: Licensee Event Report 50-296/2022-001 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints for 1\\14 TENNESSEE VALLEY AUTHORITY

U.S. Nuclear Regulatory Commission Page 2 July 11, 2022

cc (w/ Enclosure):

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

Abstract

On May 10, 2022, the Tennessee Valley Authority was notified of As-Found testing results that four Main Steam Relief Valves (MSRVs) from Browns Ferry Nuclear Pant (BFN), Unit 3 were outside the +/- 3 percent set-point band required for operability.

More than the one allowed MSRV was considered to be inoperable during the entire operating cycle and longer than permitted by Technical Specifications. During this time, BFN Unit 3 made entries into Modes of Operation that were not allowed under this condition. The affected valves remained capable of maintaining reactor pressure within the American Society of Mechanical Engineers code limits.

It was determined that the MSRVs failed due to corrosion bonding to the valve seats and non-quantifiable leakage known as simmering. All thirteen of the MSRV pilot valves were replaced during the Unit 3 spring 2022 refueling outage. The Boiling Water Reactor Owners' Group is continuing to work toward a solution to improve the quality and adhesion of the platinum coating on the discs.

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ID Page 7 of 7 LER 50-260/2021-002-00, for Unit 2 Cycle 21 LER 50-259/2020-003-01, for Unit 1 Cycle 13 LER 50-296/2020-002-00, for Unit 3 Cycle 19 LER 50-260/2019 002 00, for Unit 2 Cycle 20 LER 50-259/2018 007 00, for Unit 1 Cycle 12 LER 50-296/2018 004 00, for Unit 3 Cycle 18 LER 50-260/2017 004 00, for Unit 2 Cycle 19

VIII. Additional Information

There is no additional information.

IX.

Commitments

There are no new commitments.