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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 8, 2019 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 NRG Docket No. 50-296
Subject:
Licensee Event Report 50-296/2019-001-01 10 CFR 50.73
Reference:
Letter from TV A to NRG, "Licensee Event Report 50-296/2019-001-00,"
dated May 8, 2019 (ML19128A102)
On May 8, 2019, The Tennessee Valley Authority submitted Revision Oto Licensee Event Report (LER) 50-296/2019-001-00 (Reference) which provided the details of an automatic reactor scram due to a turbine load reject. The enclosed LER has been revised to document the causal analysis.
The Tennessee Valley Authority is submitting this report in accordance with Title 10 of the Code of Federal Regulations 50.73(a)(2)(iv)(A), as any event or condition that resulted in a manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B).
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636.
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D. L. Hughes Site Vice President Enclosure: Licensee Event Report 50-296/2019-001 Automatic Reactor Scram Due to a Turbine Load Reject
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
Estim.red, the NRC may not conduct or sponsor, and a person is not reqlired to respond ID, the infoonalion colection.
YEAR 2019 -
- 3. LER NUMBER SEQUENTIAL NUMBER 001 REV NO.
01 B. Corrective Actions to Prevent Recurrence or to reduce the probability of similar events occurring in the future The corrective action to prevent recurrence is to revise the Operations Excellence Program, BFN-ODM-4.28, to require use of a dynamic learning environment to develop Operations Department Leaders' skills in coaching and reinforcing the use of appropriate HU barriers.
Training will be required prior to assuming shift following initial qualification as Nuclear Unit Senior Operators (NUSO) and Shift Managers (SM). The currently qualified NUSOs and SMs have received training.
VII.
Previous Similar Events at the Same Site
A revi~w of the BFN CAP and Licensee Event Reports for Units 1, 2, and 3 found no instances of reactor SCRAMs similar to this event within the past five years.
VIII. Additional Information
There is no additional information.
IX.
Commitments
There are no new commitments. Page_5_ of _5_
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| 05000260/LER-2019-001-01, Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits | Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2019-001-01, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation | High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000259/LER-2019-001, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation | High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000296/LER-2019-001-01, Automatic Reactor Scram Due to a Turbine Load Reject | Automatic Reactor Scram Due to a Turbine Load Reject | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000259/LER-2019-002, Unanalyzed Condition Due to Inoperable Security Doors Following a Liqhtninq Strike | Unanalyzed Condition Due to Inoperable Security Doors Following a Liqhtninq Strike | | | 05000260/LER-2019-002, 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)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(viii)(A) | | 05000260/LER-2019-003, Automatic Reactor Scram During Startup Due to Intermediate Range Monitor Noise | Automatic Reactor Scram During Startup Due to Intermediate Range Monitor Noise | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
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