ENS 40522
ENS Event | |
---|---|
21:19 Feb 15, 2004 | |
Title | Automatic Reactor Trip with Auxiliary Feedwater Actuation |
Event Description | The following information was received from the licensee via facsimile:
At 1519 [CDT] on 2-15-04, the plant was at 20 power, increasing load. During the transfer from the bypass feedwater regulating valves to the main feedwater regulating valves, the main turbine tripped due to a P-14 S/G Hi-Hi level signal. The P-14 signal also caused a Feedwater Isolation Signal (FWIS), which resulted in a Motor Driven Aux Feedwater Actuation (MDAFAS), and Steam Generator Blowdown Isolation Signal. Steam Generator levels subsequently shrunk to low levels causing a Steam Generator low level reactor trip at 1524 [hrs]. Sometime after the turbine trip, the turbine driven aux feed pump [(TDAFP)] was manually started to help restore S/G levels. The pump was later manually secured, but then received a subsequent auto-start signal and tripped on overspeed. The TDAFP was declared inoperable at 1535 [hrs]. With the exception of the TDAFP, all safety systems operated properly. The plant is currently stable in Mode 3, with the primary plant at 557 deg F and 2235 psig, and pressurizer level at 25%. The licensee has notified the NRC Resident Inspector.
The following information was received from the licensee via facsimile as a "rewrite of above paragraph 2. Sometime after the turbine trip, the Turbine Driven Aux Feedwater Pump (TDAFP) was manually started to help restore S/G levels. Due to decreasing reactor coolant system (RCS) temperature, it was decided to stop the TDAFP since it is a steam load. The steam supply valves were remote manually closed from the control room. At the same time the steam supply valves were closing, the steam generator levels shrunk to low levels causing a Steam Generator low level reactor trip and Turbine Driven Aux Feedwater Actuation (TDAFAS) at 1524. The steam supply valves immediately reopened due to the TDAFAS. It is postulated that this transient in the steam supply caused the pump to overspeed trip. The TDAFP was declared inoperable at 1535. With the exception of the TDAFP, all safety systems operated properly. The licensee notified the NRC Resident Inspector. Notified R4DO (Cain). |
Where | |
---|---|
Callaway ![]() Missouri (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:+-1.02 h-0.0425 days <br />-0.00607 weeks <br />-0.0014 months <br />) | |
Opened: | Hope Bradley 20:18 Feb 15, 2004 |
NRC Officer: | Howie Crouch |
Last Updated: | Feb 16, 2004 |
40522 - NRC Website
Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 40522\u003C/a\u003E - \u003Ca href=\"/Callaway\" title=\"Callaway\"\u003ECallaway\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EAutomatic Reactor Trip with Auxiliary Feedwater Actuation\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 40522 - Callaway\n","link":"","lat":38.76076111111111,"lon":-91.78175833333333,"icon":"/w/images/0/06/Ameren_icon.png"}],"imageoverlays":null} ![]() ![]() ![]() ![]() ![]() | |
Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (20 %) |
After | Hot Standby (0 %) |
Callaway ![]() | ||
WEEKMONTHYEARENS 570432024-03-22T01:56:00022 March 2024 01:56:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Driven Auxiliary Feedwater Pump Actuation ENS 569682024-02-15T08:47:00015 February 2024 08:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Trip/Reactor Trip ENS 556982022-01-07T18:23:0007 January 2022 18:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Trip / Reactor Trip ENS 550492020-12-24T18:35:00024 December 2020 18:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Turbine and Reactor Trip ENS 549162020-09-27T07:03:00027 September 2020 07:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation | Automatic Reactor Trip ENS 546392020-04-04T06:15:0004 April 2020 06:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 540692019-05-17T04:03:00017 May 2019 04:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation En Revision Imported Date 6/6/2019 ENS 540052019-04-17T06:37:00017 April 2019 06:37:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Undervoltage to a Safety Related Bus Resulting in Valid System Actuation ENS 518462016-04-03T04:02:0003 April 2016 04:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Protection System Actuation While Reactor Shutdown ENS 513082015-08-11T06:39:00011 August 2015 06:39:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip After an Offsite Electrical Fault ENS 512572015-07-23T18:57:00023 July 2015 18:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Manual Start Due to Loss of Main Feedwater Pump During Plant Cooldown ENS 506502014-12-03T06:22:0003 December 2014 06:22:00 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 Turbine Trip ENS 492192013-07-27T04:49:00027 July 2013 04:49:00 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(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to a Fire in the Turbine Building Lasting Greater than 15 Minutes ENS 457152010-02-20T03:45:00020 February 2010 03:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuations Due to Loss of the 'A' Safeguards Transformer ENS 447192008-12-14T23:14:00014 December 2008 23:14:00 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 Electrical Fault on an Operating Condensate Pump ENS 447172008-12-12T16:42:00012 December 2008 16:42:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Valid Reactor Trip and Feedwater Isolation Signals Due to Maintenance ENS 447142008-12-12T05:01:00012 December 2008 05:01:00 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 a Feedwater Transient ENS 446522008-11-12T00:46:00012 November 2008 00:46:00 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 a Feedpump Trip ENS 445612008-10-11T10:08:00011 October 2008 10:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Steam Generator Water Level Trip Actuation Initiated Reactor Trip System ENS 432272007-03-09T16:43:0009 March 2007 16:43:00 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 Manual Reactor Trip at Reduced Power Due to Inadequate Feedwater Control ENS 426212006-06-06T18:39:0006 June 2006 18:39:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of "a" Train of Offsite Vital Power Due to Relay Testing ENS 425712006-05-12T05:53:00012 May 2006 05:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip on High Steam Generator Level ENS 415462005-03-29T16:57:00029 March 2005 16:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of the Reactor Protection System and Auxiliary Feedwater System While Establishing Initial Conditions for Leak Test in Mode 3. ENS 413472005-01-19T18:51:00019 January 2005 18:51:00 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 Callaway Automatic Reactor Trip on Low Steam Generator Level ENS 405222004-02-15T21:19:00015 February 2004 21:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip with Auxiliary Feedwater Actuation ENS 405152004-02-12T04:58:00012 February 2004 04:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Eccs Actuation During Rcs Heatup ENS 405002004-02-03T10:39:0003 February 2004 10:39:00 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 Main Genrator Output Breakers Opening. ENS 404842004-01-27T23:30:00027 January 2004 23:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 403172003-11-12T20:21:00012 November 2003 20:21:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Actuation of Essential Service Water System 2024-03-22T01:56:00 [Table view] | |