ENS 50855
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ENS Event | |
|---|---|
06:00 Feb 28, 2015 | |
| Title | Automatic Auxiliary Feedwater Actuation Due to Planned Reactor Trip |
| Event Description | Wolf Creek Generating Station performed a planned shutdown for the start of a refueling outage. As part of the procedure GEN 00-005, Minimum Load to Hot Standby, a planned manual reactor trip was initiated from 25 percent power level with the plant in Mode 1. As part of this planned shut down sequence, an anticipated automatic Auxiliary Feedwater [AFW] actuation signal was generated. This is a non-emergency event notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) due to preplanned manual actuation of the reactor protection system and auto-initiation of auxiliary feed water system.
All systems and components operated as designed with the exception of the main generator output breakers. They did not open as designed. They were manually opened using the main control room hand switches as directed by EMG ES-02, Reactor Trip Response. The plant is stable in Mode 3 with AFW secured, with plans to cool down and enter Mode 5 for the planned refueling outage. The NRC Resident Inspector has been notified.
WCNOC [Wolf Creek Nuclear Operating Corporation] is retracting the 10 CFR 50.72(b)(3)(iv)(A) notification based on further review of the event. A valid AFAS [Auxiliary Feedwater Actuation signal] actuation occurred during the planned shutdown as a result of SG [Steam Generator] water level reaching the lo lo level setpoint. The AFAS actuation was an expected actuation that occurred due to preplanned activities covered by GEN 00-005. On-shift control room personnel were aware that an AFAS actuation would occur as a result of tripping the plant between 30% and 25% power. The AFAS actuated consistent with the planned shutdown with no anomalies. This is consistent with NUREG-1022, Rev. 3, Section 3.2.6 that states, in part: 'With regard to preplanned actuations, operation of a system as part of a planned test or operational evolution need not be reported. Preplanned actuations are those that are expected to actually occur due to preplanned activities covered by procedures. Such actuations are those for which a procedural step or other appropriate documentation indicates that the specific actuation is actually expected to occur. Control room personnel are aware of the specific signal generation before its occurrence or indication in the control room.' The NRC Resident Inspector was notified. Notified R4DO(Okeefe). |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.6 h-0.025 days <br />-0.00357 weeks <br />-8.2188e-4 months <br />) | |
| Opened: | Daniel Bowers 05:24 Feb 28, 2015 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Mar 11, 2015 |
| 50855 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (25 %) |
| After | Hot Standby (0 %) |
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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