ENS 40974
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ENS Event | |
|---|---|
15:10 Aug 22, 2004 | |
| Title | Reactor Trip During Surveillance Test |
| Event Description | At 1010 CDT on 8-22-2004, during the performance of STS IC-211B, 'ACTUATION LOGIC TEST TRAIN B SOLID STATE PROTECTION SYSTEM,' Control Room operators received a reactor trip concurrent with power range flux lo [low] setpoint trip and intermediate range hi [high] flux reactor trip alarms.
All safety-related equipment operated as required. The Steam Dump valves, which function to remove excess heat as the secondary systems shutdown, did not initially operate as expected, resulting in the operation of the Steam Generator Atmospheric Relief Valves (ARVs) to control Reactor Coolant pressure for approximately three minutes following the reactor trip, at which time the Steam Dump valves responded as expected and the ARVs closed. The Steam Dumps are currently operating correctly in automatic. The Auxiliary Feedwater System actuated as designed. The plant is currently stable in Mode 3 at Normal Operating Temperature and Pressure while plant personnel investigate the causes of the reactor trip and formulate the repair/ restart plan. A press release is planned. During the reactor trip, all control rods fully inserted. The electric plant is in a stable shutdown plant lineup. Plant personnel also intend to investigate the unusual response of the steam dump valves. The licensee has notified the NRC Resident Inspector.
Upon data review related to the operation of the Steam Dump valves and the Atmospheric Relief Valves (ARVs), plant staff has determined that the ARVs and Steam Dump valves operated as expected. The Steam Dump valves opened immediately following the reactor trip, as designed, due to the difference between their setpoint and the Reactor Coolant System (RCS) temperature at the time of the reactor trip. The Steam Dump valves remained open for approximately 20 to 30 seconds, at which time the RCS temperature had decreased to a value within the control range for the Steam Dump valves, causing them to close. The opening of the ARVs was in response, as designed, to the increase in Steam Generator pressure that resulted from the turbine trip shortly after the reactor trip." NRC R4DO (Tom Farnholtz) notified. The NRC Resident Inspector was notified of this update by the licensee |
| Where | |
|---|---|
Wolf Creek  Kansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.78 h-0.0325 days <br />-0.00464 weeks <br />-0.00107 months <br />) | |
| Opened: | Charles Sibley 14:23 Aug 22, 2004 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Aug 23, 2004 |
| 40974 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Wolf Creek with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 580262025-11-05T16:03:0005 November 2025 16:03:00
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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 2025-11-05T16:03:00 | |
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