ENS 52647
ENS Event | |
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19:08 Mar 29, 2017 | |
Title | Discovery of Non-Conforming Conditions During Tornado Hazards Analysis |
Event Description | During an evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, Palisades Nuclear Plant personnel identified conditions in the plant design such that specific TS equipment is considered not adequately protected from tornado missiles.
Specifically, vulnerabilities were identified in the following systems and components: Service Water System - Service water pump discharge header and service water pump cable trays. Fuel Oil Transfer System - Fuel oil transfer piping and transfer pump cable trays. Emergency Diesel Generators - Vent lines on the fuel oil day tanks. Control Room Heating, Ventilation, and Cooling System - Both the normal and emergency intake ducts. Steam Driven Auxiliary Feedwater Pump - Feedwater pump relief valves. Component Cooling Water System - Component cooling water surge tank. The identified vulnerabilities are being addressed in accordance with Enforcement Guidance Memorandum (EGM),15-002, and Interim Staff Guidance, DSS-ISG-2016-01. Initial compensatory measures are in place. The licensee notified the NRC Resident Inspector. |
Where | |
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Palisades Michigan (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+-0.97 h-0.0404 days <br />-0.00577 weeks <br />-0.00133 months <br />) | |
Opened: | Terry Davis 18:10 Mar 29, 2017 |
NRC Officer: | Bethany Cecere |
Last Updated: | Mar 29, 2017 |
52647 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (70 %) |
After | Power Operation (70 %) |
Palisades with 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
WEEKMONTHYEARENS 553112021-06-16T19:50:00016 June 2021 19:50:00
[Table view]10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Atmospheric Steam Dump Valves Inoperable ENS 526472017-03-29T19:08:00029 March 2017 19:08:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Discovery of Non-Conforming Conditions During Tornado Hazards Analysis ENS 518202016-03-24T06:11:00024 March 2016 06:11:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Control Room Ventilation Declared Inoperable ENS 495162013-11-07T20:52:0007 November 2013 20:52:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 492762013-08-13T15:02:00013 August 2013 15:02:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Control Room Ventilation Filtration Trains Declared Inoperable ENS 473222011-09-26T10:02:00026 September 2011 10:02:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Appendix R Equipment May Not Have Been Available ENS 463022010-10-01T17:25:0001 October 2010 17:25:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Appendix R Non-Compliance Issue Identified ENS 462212010-08-24T02:10:00024 August 2010 02:10:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Loss of Load Trip Signal on All Four Channels of Reactor Protection System ENS 446452008-11-07T19:41:0007 November 2008 19:41:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Load Calulations for Edg Were Incorrect ENS 431862007-02-25T18:00:00025 February 2007 18:00:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Degraded Electrical Cables to Ccw System ENS 429632006-11-04T21:30:0004 November 2006 21:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Auxiliary Feedwater Not Aligned Properly in Startup Mode ENS 429592006-11-02T19:36:0002 November 2006 19:36:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition High Pressure Safety Injection (Hpsi) Pumps Alignment Blocks Improperly Installed ENS 423372006-02-14T21:00:00014 February 2006 21:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Appendix "R" Related Unanalyzed Condition 2021-06-16T19:50:00 | |