ENS 44586
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ENS Event | |
|---|---|
05:00 Oct 21, 2008 | |
| Title | Unanalyzed Condition During Design Basis Fire in Area A-27 of Auxiliary Building |
| Event Description | During a design-basis fire in area A-27 (2026' level Auxiliary Building) actions designated in OFN KC-016, FIRE RESPONSE, remove safety-related 125 VDC Power from the B Train Pressurizer PORV, BB PCV-456A, by opening fused disconnects NK0404 and NK0405. The intent of this action is to remove all power from the affected cable tray. This action removes control power to several safety-related components, which are assumed to remain available to the Control Room since the analyzed fire in area A-27 relies on the B Train to maintain safe-shutdown conditions.
Opening NK0404 and NK0405 and removing control power fm the assumed safe-shutdown train was not fully analyzed as to the impact on Control Room Actions and subsequent affects on availability of the assumed safe-shutdown train. Actions taken or planned: 1) Fire detection and suppression in area A-27 are functional. 2) Established an hourly firewatch in area A-27 per the AP 10-104, Breach Authorizations. 3) Changed OFN KC-016, FIRE RESPONSE, to isolate the specific fused disconnect for BB PCV-456A, NK4421, and added a note to the operator to be aware that the PORV could reopen due to a cable-to-cable hot short. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+18.45 h0.769 days <br />0.11 weeks <br />0.0253 months <br />) | |
| Opened: | Richard Hubbard 23:27 Oct 21, 2008 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Oct 21, 2008 |
| 44586 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 526662017-04-05T19:00:0005 April 2017 19:00:00
[Table view]10 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, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for Both Edg Transfer Line Connections ENS 506282014-11-19T21:37:00019 November 2014 21:37:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 504682014-09-18T16:55:00018 September 2014 16:55:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 494232013-10-09T22:30:0009 October 2013 22:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Hot Short Fire Event That Could Adversely Impact Safe Shutdown Equipment ENS 481342012-07-25T21:02:00025 July 2012 21:02:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Identification of a Degraded or Unanalyzed Condition ENS 474122011-11-03T21:00:0003 November 2011 21:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for a Postulated Control Room Fire ENS 470762011-07-20T18:15:00020 July 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)(ii)(B), Unanalyzed Condition Fire Protection Program Concern 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 464882010-12-17T21:35:00017 December 2010 21:35:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Potential Equipment Actuations Due to Electrical Short Circuits ENS 464282010-11-18T22:26:00018 November 2010 22:26:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Post Fire Safe Shutdown Unanalyzed Condition ENS 461962010-08-21T22:00:00021 August 2010 22:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition One Train Eccs Declared Inoperable Due to Void in "a" Rhr Heat Exchanger 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 458592010-04-20T18:07:00020 April 2010 18:07:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Five Potential Issues Discovered During Post-Fire Safe Shutdown Review ENS 456922010-02-10T00:00:00010 February 2010 00:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Post Fire Safe Shutdown Unanalyzed Condition ENS 452772009-08-19T20:00:00019 August 2009 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Time to Establish Charging Flow Exceeded Thermal Hydraulic Analysis ENS 445862008-10-21T05:00:00021 October 2008 05:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition During Design Basis Fire in Area A-27 of Auxiliary Building ENS 441722008-04-26T18:18:00026 April 2008 18:18:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Discovered Due to Improperly Installed Fuse Wiring in Class 1E Air Conditioning Unit ENS 441312008-04-10T15:15:00010 April 2008 15:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition "Analysis Indicates Containment Coolers May Not Have Automatically Started in Slow Speed Following Postulated Main Steam Line Break ENS 426032006-05-24T15:38:00024 May 2006 15:38:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Discovered During Post-Fire Safe Shutdown Area Review ENS 423272006-02-10T17:00:00010 February 2006 17:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential for Loss of Safe Shutdown Capability ENS 421822005-12-02T00:30:0002 December 2005 00:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Emergency Diesel Capability ENS 421462005-11-16T21:30:00016 November 2005 21:30:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Failure to Meet Required Response Times for Shutdown Outside Control Room 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 417862005-05-10T21:55:00010 May 2005 21:55:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Emergency Safety System Actuation Dampers Inoperable ENS 413272005-01-13T01:45:00013 January 2005 01:45:00 Other Unspec Reqmnt, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 24 Hour Condition of License Report Regarding Halon System- Actuator Connection Error ENS 413172005-01-07T23:00:0007 January 2005 23:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Loss of a Fire Safe Shutdown Success Path 2017-04-05T19:00:00 | |
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