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Category:Status Report
MONTHYEARGO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023
Plant Decommissioning Fund Status Report
GO2-20-054, Decommissioning Funds Status Report2020-03-18018 March 2020
Decommissioning Funds Status Report
GO2-19-082, Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only2019-06-24024 June 2019
Energy Northwest'S Final Six-Month Status Update Report for the Implementation of Nuclear Regulatory Commission (NRC) Order EA-13-109, Phase 2 Only
GO2-19-052, Plant Decommissioning Fund Status Report2019-03-19019 March 2019
Plant Decommissioning Fund Status Report
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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Event Notification Report for June 25, 2004 Page 1 of 1 U.S. Nuclear Regulatory Commission Operation Center Power Reactor Event Number:39945 Facility:COLUMBIA GENERATING STATION Notification DateD6/1 6/2003 Region:4 State: WA Notification Time2O:36 [EST]
Unit: [2] Event Date:06/16/2003 RXType:[2] GE-5 Event Time:13:30 [PDT]
NRC Notified By:SCOTT BOYNTON Last Update DateD6/16/2003 HO OPS Officer: STEVE SANDIN Emergency Class: NON EMERGENCY Person (Organization):
10 CFR Section: DAVID GRAVES (R4) 50.72(b)(3)(v)(B) - POT RHR INOP Event Text UNEXPECTED ISOLATION SIGNAL DURING TESTING WHICH RESULTED INA MOMENTARY LOSS OF SHUTDOWN COOLING
'This event notification Is being made to report an event that could have prevented the fulfillment of the safety function to remove residual heat. On June 16, 2003, the plant was shutdown in Mode 4 with reactor vessel level being maintained between 60-120 inches. Operators were performing surveillance testing on the manual pushbutton Isolation logic to the Nuclear Steam Supply Shutoff System when an unexpected general outboard isolation signal was received. This resulted Inthe closure of RHR-V-8 (RHR shutdown cooling outboard containment isolation valve) and the interruption of shutdown cooling. Reactor Recirculation Pump B remained in service providing forced flow through the reactor core. Operators restored from the surveillance, reset the isolation signal, and reopened RHR-V-8. Shutdown cooling was restored 12 minutes after RHR-V-8 went closed. Reactor vessel level and temperature remained stable during the period shutdown cooling was not in service.'
The licensee's Incident and review board determined that the procedure was deficient in that it did not alert operators to the isolation signal which functioned as required. The licensee will Inform the NRC resident inspector.
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