ENS 47489
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
23:28 Nov 29, 2011 | |
| Title | Unit Experienced an Automatic Reactor Scram During a Planned Shutdown |
| Event Description | During a planned shutdown in preparation for refueling outage C1R13, shortly after tripping the main turbine, an automatic reactor scram occurred due to high reactor steam dome pressure. Preliminarily, per the plant process computer, the reactor pressure was observed to reach approximately 1074 psig approximately 26 seconds after main steam bypass valves unexpectedly closed. An investigation will be conducted to determine the cause of the bypass valve closure and reactor scram. No safety relief valves lifted as a result of the pressure increase.
This event is being reported under 10 CFR 50.72(b)(2)(iv)(B) as an event or condition that results in actuation of the reactor protection system when the reactor was critical. The licensee is manually controlling the steam bypass valves to remove decay heat via the main condenser. All control rods fully inserted. The Unit is in a normal shutdown electrical lineup. The licensee informed the NRC Resident Inspector. |
| Where | |
|---|---|
Clinton  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000461/LER-2011-004 |
| Time - Person (Reporting Time:+-1.68 h-0.07 days <br />-0.01 weeks <br />-0.0023 months <br />) | |
| Opened: | Ken Leffel 21:47 Nov 29, 2011 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Nov 29, 2011 |
| 47489 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (16 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 563282023-02-01T05:43:0001 February 2023 05:43:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Scram Due to Turbine Trip ENS 541972019-08-03T07:26:0003 August 2019 07:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge En Revision Imported Date 8/7/2019 ENS 536982018-10-28T05:00:00028 October 2018 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram During a Reactor Shutdown ENS 531102017-12-09T19:48:0009 December 2017 19:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 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, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Manual Reactor Scram Due to Loss of Division 1 Ac Power to Numerous Components ENS 528002017-06-11T03:56:00011 June 2017 03:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Feedwater Heating ENS 527772017-05-31T01:38:00031 May 2017 01:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram ENS 499582014-03-26T00:42:00026 March 2014 00:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Condenser Vacuum ENS 496322013-12-13T23:57:00013 December 2013 23:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During Feed Pump Swap ENS 496172013-12-09T02:27:0009 December 2013 02:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Manual Scram Due to Loss of Division 1 480 Vac Power Causing Loss of Instrument Air to Containment and Scram Air Header ENS 489742013-04-26T13:55:00026 April 2013 13:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Rapidly Decreasing Level in the Ehc Oil Reservoir ENS 488122013-03-07T13:56:0007 March 2013 13:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram on Generator Trip/Turbine Trip ENS 474892011-11-29T23:28:00029 November 2011 23:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit Experienced an Automatic Reactor Scram During a Planned Shutdown ENS 454332009-10-15T10:37:00015 October 2009 10:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 439762008-02-11T04:07:00011 February 2008 04:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Increasing Reactor Vessel Level ENS 428072006-08-27T22:05:00027 August 2006 22:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Reactor High Water Level ENS 424302006-03-20T10:53:00020 March 2006 10:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Main Turbine Trip Caused Reactor Scram ENS 408682004-07-13T21:10:00013 July 2004 21:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Possible Adverse Weather ENS 406042004-03-23T01:31:00023 March 2004 01:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram from 93% Power Due to Generator Trip ENS 403682003-12-02T22:58:0002 December 2003 22:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Low Reactor Water Feed Pump Suction Pressure 2023-02-01T05:43:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_47489&oldid=424203"