ENS 42182
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ENS Event | |
|---|---|
00:30 Dec 2, 2005 | |
| Title | Unanalyzed Condition - Emergency Diesel Capability |
| Event Description | This report addresses a concern with the capability to field flash the diesel generator after the diesel engine has started in response to a fire in the Control Room. Step C9 in procedure OFN RP-017 opens NB0212 to drop power to NB02 and force an automatic start of the 'B' Train emergency diesel engine. Step C10 states to verify that the diesel engine is running and provides an RNO action to start the diesel if it is not running.
Step C10.d in OFN RP-017 has the operator check NB02 voltage on breaker NB0201 NORMAL. There is no RNO action if the voltage is not normal. A fire in control room panel RL015 has the potential to cause a loss of diesel generator field flashing. For example, a short to ground on conductor 51 in cable 14KJK03AH with a simultaneous short to ground on conductor N1 in cable 14NEB11AA could blow the fuse(s) associated with the speed control relays (LSR and HSR). Loss of power to these relays will prevent field flashing, which will prevent voltage generation from the diesel generator, even though the diesel engine may be running. Step C10.b in OFN RP-017 has the operator place the master transfer switch (KJHS0109) in LOC/MAN. Based on drawing E-13KJ03A, this action will isolate the control room start circuit by opening the contact between G7 and H7, and effectively isolate the short circuit potential. However, the fuse may have already blown before this action is taken. The circuit is not provided with redundant fusing, so it may be necessary to replace one or both fuses (FU5 and FU6) in panel KJ122 to re-establish power to the speed relays. Wolf Creek has implemented the following compensatory measures: Staged 4 spare fuses in the emergency locker in the B Train Diesel Generator Room. Revised OFN RP-017, Control Room Evacuation. Continued hourly fire watch in the control room (established due to another concern). 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:+-4.93 h-0.205 days <br />-0.0293 weeks <br />-0.00675 months <br />) | |
| Opened: | David Seeney 19:34 Dec 1, 2005 |
| NRC Officer: | Ronald Harrington |
| Last Updated: | Dec 1, 2005 |
| 42182 - NRC Website
Loading map... | |
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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