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 Start dateTitleReporting criterion
ENS 5663725 July 2023 13:24:00Control Room Envelope Inoperable10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
ENS 5662012 July 2023 08:49:00ECCS Potentially Inoperable10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat
ENS 548164 August 2020 21:45:0010 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor
ENS 547385 June 2020 07:20:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
ENS 5375225 November 2018 01:15:00En Revision Imported Date 1/22/201910 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
ENS 5118728 June 2015 13:00:00Control Room Environmental Boundary Door Found Unlatched10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
ENS 5116117 June 2015 03:43:00Service Water Effluent Radiation Monitor Out of Service10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness
ENS 507121 January 2015 23:25:00Main Control Room Boundary Door Did Not Properly Latch10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
ENS 4967829 December 2013 12:44:00Switchgear Room Door Discovered Unlatched10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
ENS 4904717 May 2013 08:39:00Unanalyzed Condition for Reactor Coolant System Temperature Below Required Value10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition
ENS 4903916 May 2013 06:56:00Manual Reactor Trip During Control Rod Testing10 CFR 50.72(b)(3)(iv)(A), System Actuation
ENS 4821521 August 2012 04:38:00Both Emergency Diesel Generators Inoperable10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
ENS 4660711 February 2011 13:45:00Tears Discovered in Flexible Pipe Seals10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material
ENS 4272525 July 2006 13:45:00Reactor Trip Breakers Opened During Maintenance on Steam Generator Wide Level Channels10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation