LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator |
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10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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| 2962024002R00 - NRC Website |
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Post Office Box 2000, Decatur, Alabama 35609-2000 April 24, 2024 10 CFR 50.73 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 50-296/2024-002-00 The enclosed Licensee Event Report provides details of a breaker trip which automatically started an Emergency Diesel Generator on Browns Ferry Nuclear Plant, Unit 3. The Tennessee Valley Authority is submitting this report in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.73(a)(2)(iv)(A), as an event or condition that resulted in the unplanned, valid, manual or automatic actuation of emergency AC electrical power systems.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact David J. Renn, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully, Manu Sivaraman Site Vice President Enclosure: Licensee Event Report 50-296/2024-002 Breaker Trip Automatically Started an Emergency Diesel Generator cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant TENNESSEE VALLEY AUTHORITY
ENCLOSURE Browns Ferry Nuclear Plant Unit 3 Licensee Event Report 50-296/2024-002-00 Breaker Trip Automatically Started an Emergency Diesel Generator See Enclosed
Abstract
On February 24, 2024, at approximately 0219 Central Standard Time (CST), the closing 4kV shutdown board (SDBD) breaker (3-BKR-211-03EB/009) caused the 3EB 4kV SBDB normal feeder breaker (3-BKR-211-03EB/014) to unexpectedly trip open. This trip resulted in a valid 4kV bus under-voltage condition, which caused the 3B emergency diesel generator (EDG) to automatically start and tie to the board.
No components failed during this event, which was ultimately attributed to an intermittent loose connection. Corrective measures included additional monitoring during cycling of board loads, trouble shooting and tightening of all accessible connections. The condition was unable to be repeated.
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Commitments
There are no new commitments.
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| 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup | Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure | Inoperability of Unit 3 Diesel Generator Due to Relay Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000260/LER-2024-001-01, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure | Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000259/LER-2024-001, Inoperability of Unit 3 Diesel Generator Due to Relay Failure | Inoperability of Unit 3 Diesel Generator Due to Relay Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure | Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000260/LER-2024-001, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure | Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure | Reactor Scram Due to Generator Step-Up Transformer Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation | High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator | Breaker Trip Automatically Started an Emergency Diesel Generator | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000260/LER-2024-002-01, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation | High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators | Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000296/LER-2024-004, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping | Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000259/LER-2024-004, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000296/LER-2024-004-01, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping | Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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