ENS 45964
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ENS Event | |
|---|---|
22:30 May 29, 2010 | |
| Title | Containment Purge Isolation Signal Caused Control Room Isolation System Actuation |
| Event Description | While operating in Mode 1, 100% rated thermal power (RTP), Wolf Creek received a Containment Purge Isolation Signal (CPIS) caused by Containment Purge Exhaust Radiation Monitor GT RE-33 exceeding the high radiation trip setpoint. There was no containment purge in progress at the time of the CPIS so no containment dampers actuated or were required to actuate. Control Room Ventilation Isolation Signal (CRVIS) was also received, as expected, from the actuation of the CPIS. All CRVIS components actuated as required. Review of GT RE-33 identified that the radiation monitor spiked high causing the CPIS then returned to normal values. All other containment radiation monitors are indicating normal values.
The NRC Resident has been notified of this event by the Licensee. GT RE-33 is currently removed from service.
The licensee is retracting this event based on the following: The Containment Purge Exhaust Radiation Monitor GT RE-33 failed due to a corrupted database initiated by a Radiation Monitor System (RMS) communication loop problem. The signal was not initiated by actual plant conditions or parameters, so this was an invalid actuation. This actuation did not involve a critical scram. So it is not reportable per 10 CFR 50.72. The licensee will inform the NRC Resident Inspector. Notified R4DO (Pick). |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.23 h-0.0513 days <br />-0.00732 weeks <br />-0.00168 months <br />) | |
| Opened: | Mark Jenkins 21:16 May 29, 2010 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Jun 21, 2010 |
| 45964 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 560132022-07-23T00:49:00023 July 2022 00:49:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Actuation Signal Received Due to Human Performance Error ENS 560052022-07-18T23:03:00018 July 2022 23:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Steam Generator LOW Level ENS 554162021-08-18T15:36:00018 August 2021 15:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 540872019-05-24T18:10:00024 May 2019 18:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Offsite Power Due to Fire on Startup Transformer ENS 523712016-11-17T03:09:00017 November 2016 03:09:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Started on Valid Undervoltage Signal ENS 510362015-05-03T15:22:0003 May 2015 15:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Feedwater Isolation, Turbine Trip and Manual Reactor Trip During Power Ascension ENS 508552015-02-28T06:00:00028 February 2015 06:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Auxiliary Feedwater Actuation Due to Planned Reactor Trip ENS 493392013-09-11T22:31:00011 September 2013 22:31:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Loss of Cooling to Switchgear Rooms ENS 475902012-01-13T20:03:00013 January 2012 20:03:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Notification of Unusual Event and Reactor Trip Due to Loss of Offsite Power ENS 469902011-06-26T21:09:00026 June 2011 21:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Manual Trip Due to Main Feed Pump Trip ENS 468772011-05-24T16:20:00024 May 2011 16:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Lo-Lo Level in Steam Generator Results in Specified System Actuations ENS 466852011-03-19T09:04:00019 March 2011 09:04:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Safety Injection Discharge to the Reactor ENS 463382010-10-17T14:53:00017 October 2010 14:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip on Low Steam Generator Level During Plant Startup ENS 459642010-05-29T22:30:00029 May 2010 22:30:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Containment Purge Isolation Signal Caused Control Room Isolation System Actuation ENS 457492010-03-08T09:33:0008 March 2010 09:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of All Main Feedwater ENS 457452010-03-05T06:07:0005 March 2010 06:07:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Feedwater Isolation Due to High Steam Generator Water Level ENS 457392010-03-02T20:58:0002 March 2010 20:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Caused by Low Steam Generator Water Level ENS 452812009-08-21T11:48:00021 August 2009 11:48:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Feed Water Isolation Due to High Steam Generator Water Level ENS 452782009-08-19T20:49:00019 August 2009 20:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Caused by Turbine Trip ENS 450272009-04-28T20:27:00028 April 2009 20:27:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Steam Generator Level Due to Feedwater Valve Failure ENS 440722008-03-17T18:00:00017 March 2008 18:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Lowering Steam Generator Level Due to the Loss of 'B' Main Feed Water Pump ENS 411132004-10-11T12:25:00011 October 2004 12:25:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Switchyard West Bus ENS 411002004-10-07T16:48:0007 October 2004 16:48:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Main Turbine Trip ENS 409742004-08-22T15:10:00022 August 2004 15:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip During Surveillance Test ENS 405722004-03-07T03:47:0007 March 2004 03:47:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Plant Had a Loss of Power to the Startup Transformer and the "B" Train 4.16Kv Esfas Bus. ENS 405172004-02-13T14:10:00013 February 2004 14:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation Due to Low Steam Generator Level ENS 400862003-08-18T20:54:00018 August 2003 20:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due Low Low "B" Steam Generator Water Level 2022-07-23T00:49:00 | |
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