ENS 43457
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ENS Event | |
|---|---|
00:17 Jun 29, 2007 | |
| Title | Reactor Trip Due to Condensate Pump Trip |
| Event Description | Reactor trip at 1717 hrs PDT due to [condensate pump] COND-P-2B trip. Reactor power was at 70% with [condensate pump] COND-P-2A secured. Reactor vessel level reached -50 inches and was restored with High Pressure Core Spray and Reactor Core Isolation Cooling. Main Steam Isolation Valves closed as expected due to the reaching -50 inches. All systems operated as expected. Further investigation into COND-P-2B trip is underway. Plant is stable in mode three, heat removal is being maintained by RHR-P-2B and Safety Relief Valves.
All rods fully inserted on the automatic reactor scram. All safety systems were available at the time of the trip. The trip was considered uncomplicated. The reactor pressure is currently being maintained between 500 to 600 psi and water level between 60 to 80 inches. The licensee was at 70% power at the time of the trip due to maintenance of condensate pump P-2A. The licensee will notify the NRC Resident Inspector. |
| Where | |
|---|---|
Columbia Generating Station  Washington (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000397/LER-2007-004 |
| Time - Person (Reporting Time:+-2.4 h-0.1 days <br />-0.0143 weeks <br />-0.00329 months <br />) | |
| Opened: | Mike Ferry 21:53 Jun 28, 2007 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Jun 28, 2007 |
| 43457 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (70 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 534102018-05-18T13:51:00018 May 2018 13:51:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Caused by Main Transformer Trip ENS 529182017-08-20T23:05:00020 August 2017 23:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to a Rise in Main Condenser Back Pressure ENS 524422016-12-18T19:24:00018 December 2016 19:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Scram Due to Load Reject from Substation ENS 518262016-03-28T20:22:00028 March 2016 20:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Following Loss of Reactor Closed Cooling ENS 454842009-11-07T15:25:0007 November 2009 15:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to a Main Turbine Digital Electro-Hydraulic Control System Leak ENS 452452009-08-05T14:50:0005 August 2009 14:50:00 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 Toxic Gas from a Switchgear Fire in the Turbine Building ENS 451692009-06-27T03:05:00027 June 2009 03:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Based on Fire Lasting Greater than 15 Minutes ENS 450512009-05-08T17:45:0008 May 2009 17:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram After Loss of Generator Seal Oil ENS 448392009-02-08T19:25:0008 February 2009 19:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to a Governor Valve Fast Closure Signal ENS 444322008-08-21T23:06:00021 August 2008 23:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to a Main Turbine Trip ENS 434572007-06-29T00:17:00029 June 2007 00:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Condensate Pump Trip ENS 429502006-10-31T12:45:00031 October 2006 12:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip from Turbine Trip on Low Auto Stop Oil Pressure ENS 417902005-06-23T20:46:00023 June 2005 20:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit Experienced an Automatic Reactor Scram Due to a Loss of Feedwater Flow ENS 417792005-06-15T21:00:00015 June 2005 21:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Turbine Throttle Valve Closure ENS 409642004-08-17T12:28:00017 August 2004 12:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Trip of Reactor Feedwater Pump "a" on Low Suction Pressure. ENS 409592004-08-15T20:03:00015 August 2004 20:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Feedwater Pump Trip ENS 409102004-07-30T17:00:00030 July 2004 17:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Alert Declared at Columbia Generating Station 2018-05-18T13:51:00 | |
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