ENS 49339
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ENS Event | |
|---|---|
22:31 Sep 11, 2013 | |
| Title | Technical Specification Required Shutdown Due to Loss of Cooling to Switchgear Rooms |
| Event Description | Wolf Creek has commenced a plant shutdown in accordance with Technical Specifications. The A Train Class 1E Electrical Equipment Air Conditioning unit was declared non-functional due to a possible failed compressor cylinder, as indicated by increased vibration. This failure could prevent the unit from performing its required function over its required mission time, as required by Technical Specifications 3.8.4, 3.8.7, and 3.8.9. The following safety related electrical equipment was declared inoperable: 4.16KV Bus NB01; 480 Volt AC buses NG01 and NG03; 120 Volt Instrument AC inverters and buses NN11, NN13, NN01 and NN03; 125 VDC chargers and buses NK11, NK13, NN01 and NN03.
Technical Specification 3.0.3 was entered at 1645 CDT on 9/11/2013 from Technical Specification 3.8.7 due to two out of four 120 VAC inverters (NN11 and NN13) being inoperable. Plant shutdown to Mode 5 commenced at 1731 CDT. The unit is currently at approximately 50% power. All electrical systems listed above remain available but are declared inoperable due to inadequate room cooling capability. No major equipment is out of service. The NRC Resident Inspector has been notified. No switchgear room temperature limits were challenged. See EN #49008 (May 6, 2013) and EN #49126 (June 17, 2013) for similar events.
At 00:36 CDT 9/12/13, Wolf Creek had an Auxiliary Feedwater Actuation during a plant shutdown in accordance with Technical Specifications. The plant was in Mode 3, all control rods inserted, with reactor trip breakers closed when low steam generator levels prompted a manual reactor trip. A Valid Auxiliary Feed Actuation signal was received due to low steam generator levels. All Auxiliary Feedwater pumps started and operated as expected. The licensee has informed the NRC Resident Inspector. R4DO (Hay) notified. |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.9 h-0.0792 days <br />-0.0113 weeks <br />-0.0026 months <br />) | |
| Opened: | Marcy Blow 20:37 Sep 11, 2013 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Sep 12, 2013 |
| 49339 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (50 %) |
Wolf Creek with 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
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 545082020-02-02T00:45:0002 February 2020 00:45:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Containment Purge Valve Excessive Leakage 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 522182016-09-02T13:08:0002 September 2016 13:08:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 510742015-05-16T02:48:00016 May 2015 02:48:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to 2 Ac Inverters Inoperable ENS 510712015-05-15T09:36:00015 May 2015 09:36:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to 2 Ac Inverters Inoperable 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 494482013-10-18T17:11:00018 October 2013 17:11:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Loss of Cooling to Switchgear Rooms 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 491262013-06-17T16:11:00017 June 2013 16:11:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Non-Functional Class 1E Electrical A/C Unit ENS 490082013-05-06T22:33:0006 May 2013 22:33:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Required Due to Non-Functional Class 1E Air Conditioning Unit ENS 479982012-06-06T08:27:0006 June 2012 08:27:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Inadequate Cooling Available to Support Electrical Power Systems 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 471542011-08-15T15:55:00015 August 2011 15:55:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown - Contaminated Oil Sample 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 464572010-12-06T10:18:0006 December 2010 10:18:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Exceeding Allowed Outage Time on the 'A' Emergency Diesel Generator 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 463092010-10-05T03:00:0005 October 2010 03:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 461982010-08-23T13:14:00023 August 2010 13:14:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Both Edgs and an Rhr Loop Inoperable ENS 459852010-06-07T23:44:0007 June 2010 23:44:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Voiding in the Component Cooling Water System 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 456632010-01-26T21:25:00026 January 2010 21:25:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Entry Into Technical Specification Required Shutdown 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 439852008-02-14T00:50:00014 February 2008 00:50:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification 3.0.3 Required Shutdown ENS 438952008-01-11T22:22:00011 January 2008 22:22:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech. Spec. Required Shutdown Due to Gas Voiding in Discharge Piping ENS 420042005-09-21T03:40:00021 September 2005 03:40:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Commenced Due to Inoperability of Residual Heat Removal Containment Sump Isolation Valves 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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