ML24023A280: Difference between revisions

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{{#Wiki_filter:TENNESSEE VALLEY 1\\14 AUTHORITY
{{#Wiki_filter:TENNESSEE VALLEY 1\\14 AUTHORITY


Post Office Box 2000, Decatur, Alabama 35609-2000
Post Office Box 2000, Decatur, Alabama 35609-2000


January 23, 2024
January 23, 2024
Line 23: Line 23:
10 CFR 21.21
10 CFR 21.21


ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001


Browns Ferry Nuclear Plant, Units 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260
Browns Ferry Nuclear Plant, Units 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260

Revision as of 19:44, 5 October 2024

Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump
ML24023A280
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 01/23/2024
From: Sivaraman M
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML24023A280 (1)


Text

TENNESSEE VALLEY 1\\14 AUTHORITY

Post Office Box 2000, Decatur, Alabama 35609-2000

January 23, 2024

10 CFR 21.21

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Browns Ferry Nuclear Plant, Units 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260

Subject:

Final Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump

References:

Letter from TVA to NRC, Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump, dated December 1, 2023 (ML23335A072)

On December 1, 2023, the Tennessee Valley Authority (TVA) submitted an interim Part 21 report regarding a defective overload relay at Browns Ferry Nuclear Plant (BFN). On October 2, 2023, a new overload relay was found to be defective during post-maintenance testing on a circuit breaker for the BFN, Unit 2, Reactor Core Isolation Cooling (RCIC) condensate pump. This QA1 part (DBC069X) had previously passed receipt inspection in April 2023 as part of a bulk order of 90 relays of this same type, of which, 82 remained in stock. This issue was promptly entered into the BFN Corrective Action Program (CAP) as Condition Report (CR) 1883872.

The manufacturer, GE-Hitachi (GEH), has inspected and tested the relay. Based upon TVAs evaluation of GEHs report, BFN Engineering had concluded that this is not a Part 21 reportable issue.

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 U.S. Nuclear Regulatory Commission Page 2 January 23, 2024

cc (w/ Enclosures):

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