Cancellation of LER 2018-001-00 for Browns Ferry Nuclear Plant, Fire Damage to Cables for Residual Heat Removal Service Water Valves Could Result in Water Hammer and Piping Damage
Person / Time
ML18320A263
Site:	Browns Ferry
Issue date:	11/16/2018
From:	Hughes D Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 2018-001-00
Download: ML18320A263 (2)
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LER-2018-001, Cancellation of LER 2018-001-00 for Browns Ferry Nuclear Plant, Fire Damage to Cables for Residual Heat Removal Service Water Valves Could Result in Water Hammer and Piping Damage

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
2592018001R00 - NRC Website
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text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 November 16, 2018 10 CFR 50.73 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 No. DPR-33, DPR-52, and DPR-68 NRC Docket No. 50-259, 50-260, and 50-296

Subject:

Cancellation of Licensee Event Report 50-259/2018-001-00, Fire Damage to Cables for Residual Heat Removal Service Water Valves Could Result in Water Hammer and Piping Damage

Reference:

Letter from TVA to NRC, Licensee Event Report 50-259/2018-001-00, dated May 15, 2018 (ML18135A247).

Consistent with the guidance in NUREG-1022, Revision 3, Sections 2.8 and 5.1.2, Browns Ferry Nuclear Plant (BFN) is cancelling (formally withdrawing) Licensee Event Report (LER) 50-259/2018-001-00.

The LER was submitted on May 15, 2018, pursuant to Title 10 of the Code of Federal Regulation (10 CFR) 50.73(a)(2)(ii)(B), as an unanalyzed condition involving the Residual Heat Removal Service Water (RHRSW) system with the potential to significantly degrade plant safety. Subsequent to the LER submittal, an independent analysis determined that functionality of the RHRSW system was maintained. Therefore, the condition no longer meets the reporting criteria of 10 CFR 50.73. A supplement to the LER was anticipated. This cancellation eliminates the need for that supplement.

On March 16, 2018, a potential unanalyzed condition was identified which could have affected the Residual Heat Removal (RHR) heat exchangers (HX) in a postulated fire event. It was discovered that the RHRSW HX piping associated with the credited HXs in the National Fire Protection Association 805 Nuclear Safety Capability Analysis could experience water hammer. A legacy condition existed where credited RHR HXs were subject to voiding due to single spurious opening of the RHRSW outlet valve and subsequent manual or spurious start of a pump. Spurious opening of the valves was recognized and addressed for flow diversion, but the potential effects of water hammer were not addressed. While this condition was being evaluated, the LER was submitted with the expectation that a supplement to the report would be submitted following completion of the evaluation.

Licensee Event Report

Browns Ferry

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		Reporting criterion
05000259/LER-2018-001, Cancellation of LER 2018-001-00 for Browns Ferry Nuclear Plant, Fire Damage to Cables for Residual Heat Removal Service Water Valves Could Result in Water Hammer and Piping Damage	Cancellation of LER 2018-001-00 for Browns Ferry Nuclear Plant, Fire Damage to Cables for Residual Heat Removal Service Water Valves Could Result in Water Hammer and Piping Damage	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000259/LER-2018-002-01, Automatic Reactor Scram Due to an Unanticipated Electro-Hydraulic Control Logic Condition	Automatic Reactor Scram Due to an Unanticipated Electro-Hydraulic Control Logic Condition	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000259/LER-2018-002, Automatic Reactor Scram Due to an Unanticipated Electro-Hydraulic Control Logic Condition	Automatic Reactor Scram Due to an Unanticipated Electro-Hydraulic Control Logic Condition	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)(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-2018-002, Inoperable 250V Shutdown Board Battery Charger Results in Condition Prohibited by Technical Specifications	Inoperable 250V Shutdown Board Battery Charger Results in Condition Prohibited by Technical Specifications	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)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000259/LER-2018-003, For Browns Ferry Nuclear Plant, Units 1, 2, and 3, Unanalyzed Condition Due to an Incorrectly Wired Breaker on Emergency Equipment Cooling Water Pump	For Browns Ferry Nuclear Plant, Units 1, 2, and 3, Unanalyzed Condition Due to an Incorrectly Wired Breaker on Emergency Equipment Cooling Water Pump	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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) 10 CFR 50.73(a)(2)(viii)(B)
05000296/LER-2018-003, Misadjusted Switch Results in Condition Prohibited by Technical Specifications	Misadjusted Switch Results in Condition Prohibited by Technical Specifications	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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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-2018-004-01, Hiqh Pressure Coolant Injection Declared Inoperable Due to Steam Supply Valve Isolation	Hiqh Pressure Coolant Injection Declared Inoperable Due to Steam Supply Valve 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-2018-004, 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)(iv)(A), System Actuation 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)(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-2018-005, Inoperability of Unit 1 and 2 Emergency Diesel Generators Results in Condition Prohibited by Technical Specifications	Inoperability of Unit 1 and 2 Emergency Diesel Generators Results in Condition Prohibited by Technical Specifications	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-2018-006, Standby Gas Treatment System Train C Inoperable Longer than Allowed by Tech	Standby Gas Treatment System Train C Inoperable Longer than Allowed by Tech	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-2018-007, 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)(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-2018-001, Cancellation of LER 2018-001-00 for Browns Ferry Nuclear Plant, Fire Damage to Cables for Residual Heat Removal Service Water Valves Could Result in Water Hammer and Piping Damage

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