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Category:Status Report
MONTHYEARGO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023
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Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
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GO2-18-145, Energy Northwest'S December 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2018-12-13013 December 2018
Energy Northwest'S December 2018 Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
GO2-18-050, Plant Decommissioning Fund Status Report2018-03-22022 March 2018
Plant Decommissioning Fund Status Report
GO2-17-201, Energy Northwest'S Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2017-12-28028 December 2017
Energy Northwest'S Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
GO2-17-210, Anchor Darling Double Disc Gate Valve Information and Status2017-12-21021 December 2017
Anchor Darling Double Disc Gate Valve Information and Status
GO2-17-118, Second Combined Six-Month Status Update Report for the Implementation of NRC Orders EA-12-049 and EA-13-1092017-06-27027 June 2017
Second Combined Six-Month Status Update Report for the Implementation of NRC Orders EA-12-049 and EA-13-109
GO2-17-058, Confirmatory Order EA-14-240, Element V.J.1 - Sixth Status Update2017-03-14014 March 2017
Confirmatory Order EA-14-240, Element V.J.1 - Sixth Status Update
GO2-16-171, Combined Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Orders EA-12-049 and EA-13-1092016-12-29029 December 2016
Combined Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Orders EA-12-049 and EA-13-109
GO2-16-170, Confirmatory Order EA-14-420, Element V.J.1-Fifth Status Update2016-12-21021 December 2016
Confirmatory Order EA-14-420, Element V.J.1-Fifth Status Update
GO2-16-125, Seventh Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond Design Basis External Events2016-08-30030 August 2016
Seventh Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond Design Basis External Events
GO2-16-098, Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2016-06-30030 June 2016
Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-13-109, Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
GO2-16-052, Confirmatory Order EA-14-240, Element V.J.1 - Second Status Update2016-03-24024 March 2016
Confirmatory Order EA-14-240, Element V.J.1 - Second Status Update
GO2-16-037, Sixth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events2016-02-24024 February 2016
Sixth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events
GO2-15-124, Fifth Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events2015-08-25025 August 2015
Fifth Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events
GO2-15-093, Second Six-Month Status Update Report for the Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Vents Under Severe Accident Conditions2015-06-30030 June 2015
Second Six-Month Status Update Report for the Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Vents Under Severe Accident Conditions
GO2-15-034, Northwest'S Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events2015-03-0202 March 2015
Northwest'S Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-049 Mitigation Strategies for Beyond Design Basis External Events
GO2-15-032, Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2015-02-27027 February 2015
Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation
GO2-14-175, First Six-Month Status Update Report for Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Events Under Severe Accident Conditions2014-12-17017 December 2014
First Six-Month Status Update Report for Implementation of NRC Order EA-13-109 - Overall Integrated Plan for Reliable Hardened Containment Events Under Severe Accident Conditions
GO2-14-105, Cyber Security Plan - Milestone 1-7 Completion Status2014-06-19019 June 2014
Cyber Security Plan - Milestone 1-7 Completion Status
GO2-14-030, Northwest'S Second Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2014-02-27027 February 2014
Northwest'S Second Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation
GO2-13-121, First Six Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2013-08-23023 August 2013
First Six Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation
GO2-13-051, Decommissioning Fund Status Report2013-03-28028 March 2013
Decommissioning Fund Status Report
GO2-12-151, Energy Northwest'S Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation2012-10-25025 October 2012
Energy Northwest'S Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation
GO2-07-057, Decommissioning Fund Status Report2007-03-27027 March 2007
Decommissioning Fund Status Report
GO2-05-062, Decommissioning Fund Status Report2005-03-30030 March 2005
Decommissioning Fund Status Report
ML0419402742003-06-16016 June 2003
Event Notification 39945 for Columbia Unit 2
ML0418904332003-06-0909 June 2003
Event # 39910, Columbia Generating Station Re Temporary Loss of Residual Heat Removal Pump Used for Shutdown Cooling
2023-03-15
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0610712004 U.S. Nuclear Regulator Commission Operations CenterEvent Report Pajre I Power Reactor Event# 39910 Site: COLUMBIA GENERATING STATION Notification Date/Time: 06/09/2003 21:18 (EDT)
Unit: 2 Region: 4 State: WA Event Date/Time: 05/21/2003 11:55 (PDT)
Reactor Type: [2] GE-5 Last Modification: 06109/2003 Containment Type: MARK II NRC Notified by: DAVE BROWN Notifications: DAVID GRAVES R4 HQ Ops Officer: ARLON COSTA Emergency Class: NON EMERGENCY 10 CFR Section:
50.72(b)(3)(v)(B) POT RHR INOP 2 J Unit I Scram Code [RX Crit Ilnit Power I Initial RX Mode N No 0 lRefueling lCurr Power I Current RX Mode 10 lRefueling TEMPORARY LOSS OF RESIDUAL HEAT REMOVAL PUMP USED FOR SHUTDOWN COOLING "This event notification is being made to report an event that could have prevented the fulfillment or the safety function to remove residual heat. On May 21, 2003, the plant was shutdown in Mode 5, with reactor pressure vessel (RPV) level being maintained greater than 22 feet above the RPV flange. Technicians were performing routine maintenance and removed an electrical lead from the wrong relay. As a result of removing the wrong lead, Residual Heat Removal (RHR) valve RHR-V-9 closed after receiving a close signal. RHR-V-9 is one of two primary containment isolation valves in the common suction piping to both RHR shutdown cooling loops. The valve closure caused pump RHR-P-2A to trip resulting in a loss of RHR shutdown cooling, and a loss of forced flow through the reactor core. Natural circulation was verified. RHR shutdown cooling could have been promptly restored if desired, but the plant remained in natural circulation to support other maintenance activities. The RHR-V-9 isolation logic was reset 31 minutes after the isolation occurred, at which time RHR-A was declared operable.
This event was originally deemed to be not reportable by Columbia. This 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report is being made 19 days after the event date."
The licensee notified the NRC Resident Inspector.
