ENS 42004
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ENS Event | |
|---|---|
03:40 Sep 21, 2005 | |
| Title | Technical Specification Required Shutdown Commenced Due to Inoperability of Residual Heat Removal Containment Sump Isolation Valves |
| Event Description | At 2240 09/20/2005 an engineering evaluation concluded that the Residual Heat Removal Containment Sump Isolation Valves were inoperable based on their inability to open against a higher differential pressure than had been previously evaluated. Historically Wolf Creek has operated with the Component Cooling Water isolated to the Residual Heat Removal Heat Exchangers. If the pumps started during accident conditions there is a potential that the pump heat generated could cause system pressure to increase to the suction relief valve setting of 450 psig. Testing of the valves has shown that they are capable of opening with 207 psid across the valve.
Technical Specification 3.0.3 was entered at 2240 9/20/2005 due to the inoperability of both Residual Heat Removal trains. Power reduction was commenced at 2340. Component Cooling Water was aligned to the Residual Heat Removal Heat Exchangers at 0004 9/21/2005 restoring operability of the Residual Heat Removal trains. At 0017 9/21/2005 actions were commenced to restore power to 100%. This event is reportable under 10 CFR50.72(b)(2)(i) Technical Specification required shut down (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and 10 CFR50.72(b)(3)(v)(B) Event or Condition that could have prevented fulfillment of a Safety Function (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). The NRC Resident has been contacted.
Evaluation of the Residual Heat Removal Containment Sump Isolation Valves concluded that the valves were operable and the Residual Heat Removal trains were capable of fulfilling their safety function. Therefore, this event is not reportable under 10 CFR 50.72(b)(3)(v)(B). The licensee notified the NRC Resident Inspector. Notified the R4DO (Whitten). |
| 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)(v)(B), Loss of Safety Function - Remove Residual Heat | |
| Time - Person (Reporting Time:+-1.05 h-0.0438 days <br />-0.00625 weeks <br />-0.00144 months <br />) | |
| Opened: | Dave Dees 02:37 Sep 21, 2005 |
| NRC Officer: | Arlon Costa |
| Last Updated: | Nov 8, 2005 |
| 42004 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Wolf Creek with 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 | |
WEEKMONTHYEARENS 572842024-08-23T13:00:00023 August 2024 13:00:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shutdown Required by Technical Specifications 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 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 507722015-01-28T11:35:00028 January 2015 11:35:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Residual Heat Removal Capability Affected by Valve Clearance 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 481742012-08-09T23:45:0009 August 2012 23:45:00 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)(v)(C), Loss of Safety Function - Release of Radioactive Material Control Building A/C Unit May Not Perform Design Function on Loss of Redundant A/C 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 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 469092011-06-01T18:15:0001 June 2011 18:15:00 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)(ii)(B), Unanalyzed Condition Both Trains of Component Cooling Water Declared Inoperable Due to Voiding 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 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 461362010-07-28T19:22:00028 July 2010 19:22:00 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)(ii)(B), Unanalyzed Condition Three Auxiliary Feedwater (Afw) Trains Declared 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 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 441982008-05-09T19:20:0009 May 2008 19:20:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Both Trains of Rhr Declared Inoperable ENS 441652008-04-25T07:56:00025 April 2008 07:56:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat Both Emergency Diesel Generators Declared Inoperable 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 438922008-01-11T00:12:00011 January 2008 00:12:00 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 Voiding Discovered in High Head and Intermediate Head Si Common Suction ENS 420292005-09-30T14:45:00030 September 2005 14:45:00 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 Potential Vulnerabilities Discovered During Design Basis Fire Review 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 405962004-03-17T20:57:00017 March 2004 20:57:00 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 Switchgear Rooms Flooding Analysis Concerns 2024-08-23T13:00:00 | |
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