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| Issue date | Title | Topic | |
|---|---|---|---|
| ML21349B352 | 15 December 2021 | Attachment 4: Licensee Controlled Specifications, Revision 122 | Safe Shutdown Unanalyzed Condition Time of Discovery High winds Reactor Vessel Water Level Ultimate heat sink Grab sample Fire Barrier Safe Shutdown Earthquake Post Accident Monitoring Coatings Met Tower Operator Manual Action Functionality Assessment FLEX B.5.b Missed surveillance Scram Discharge Volume Excess Flow Check Valve Operability Determination Battery sizing Earthquake Turbine Missile Operability Assessment Power Uprate Measurement Uncertainty Recapture |
| ML21349B353 | 15 December 2021 | Attachment 4: Technical Specification Bases, Revision 124 | |
| GO2-20-039, Energy Northwest to EFSEC, Fish Entraiment Characterization Final Report | 26 February 2020 | Energy Northwest to EFSEC, Fish Entraiment Characterization Final Report | Biofouling |
| GO2-19-136, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to 10 CFR 50.54(F)Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-Ichi | 26 September 2019 | Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to 10 CFR 50.54(F)Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-Ichi | Safe Shutdown Ultimate heat sink Mission time Internal Flooding Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Seismically rugged Scram Discharge Volume Large early release frequency Severe Accident Management Guideline Earthquake |
| GO2-19-100, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109) | 20 August 2019 | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109) | |
| GO2-19-035, Energy Northwest to Energy Facility Site Evaluation Council, Columbia Generating Station Fish Entrainment Study Interim Report | 7 February 2019 | Energy Northwest to Energy Facility Site Evaluation Council, Columbia Generating Station Fish Entrainment Study Interim Report | Biofouling |
| ML18285A450 | 18 April 2018 | 1175ENWCGS, Revision 00, Computational Fluid Dynamics Analysis of Perforated Intake Screens at Columbia Generating Station. | |
| ML17072A036 | 10 March 2017 | Endangered Species Act Section 7(a)(2) Biological Opinion, and Magnuson-Stevens Fishery Conservation Act Essential Fish Habitat Response for Renewing the Operating License for Columbia Generating Station, Richland, Washington | Grab sample Offsite Dose Calculation Manual Incorporated by reference Annual Radiological Environmental Operating Report License Renewal |
| ML15355A486 | 21 December 2015 | Revision 87 to Licensee Controlled Specifications (LCS) | Safe Shutdown Unanalyzed Condition Time of Discovery Reactor Vessel Water Level High Radiation Area Grab sample Fire Barrier Safe Shutdown Earthquake Post Accident Monitoring Coatings Met Tower Operating Basis Earthquake Operator Manual Action Functionality Assessment Missed surveillance Scram Discharge Volume Excess Flow Check Valve Operability Determination Battery sizing Earthquake Turbine Missile Grace period Operability Assessment |
| GO2-15-110, Enclosure 2, Revision 2 to 001N6043.5-NP, Energy Northwest Columbia Generating Station Jet Pump 17/18 Riser Evaluation at 106% Rated Core Flow (115 Mlbs/Hr), Non-Proprietary | 31 August 2015 | Enclosure 2, Revision 2 to 001N6043.5-NP, Energy Northwest Columbia Generating Station Jet Pump 17/18 Riser Evaluation at 106% Rated Core Flow (115 Mlbs/Hr), Non-Proprietary | Non-Destructive Examination Safe Shutdown Earthquake MELLLA Earthquake EVT-1 Flow Induced Vibration |
| GO2-15-045, Seismic Hazard and Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 12 March 2015 | Seismic Hazard and Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | Unanalyzed Condition Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi License Renewal Earthquake Seismic Walkdown Report |
| ML14176A961 | 24 June 2014 | Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 | Fire Barrier Coatings Foreign Material Exclusion |
| ML14064A311 | 11 March 2014 | Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident | Unanalyzed Condition Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML13337A266 | 29 January 2014 | Interim Staff Evaluation and Audit Report Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting Incorporated by reference FLEX B.5.b Tornado Generated Missile Fukushima Dai-Ichi Containment Hardened Vent Frazil ice Battery sizing Earthquake Hardened vent GOTHIC |
| ML13357A322 | 21 December 2013 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Columbia Generating Station, TAC No.: MF0796 | Safe Shutdown High winds Reactor Vessel Water Level Ultimate heat sink Tornado Missile Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Emergency Lighting Incorporated by reference FLEX B.5.b Tornado Generated Missile Fukushima Dai-Ichi Containment Hardened Vent Frazil ice Battery sizing Earthquake Hardened vent GOTHIC |
| GO2-13-151, NEDO-33813, Rev. 2, Technical Specification Change Support for Rhr/Lpci and LPCS Flow Rate. Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations. | 30 September 2013 | NEDO-33813, Rev. 2, Technical Specification Change Support for Rhr/Lpci and LPCS Flow Rate. Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations. | Safe Shutdown Anticipated operational occurrence MELLLA Power Uprate |
| ML13108A219 | 4 April 2013 | RWCU Regenerative Heat Exchanger Piping Repair Patch Analysis | Finite Element Analysis |
| ML13015A273 | 31 December 2012 | NEDO-33698, Rev 2, Columbia Generating Station Power Range Neutron Monitoring System Design Report on Computer Integrity, Test and Calibration, and Fault Detection | Temporary Modification |
| ML13015A272 | 31 December 2012 | NEDO-33685, Rev 2, Digital I&C-ISG-06 Compliance for Columbia Generating Station Numac Power Range Neutron Monitoring Retrofit Plus Option III Stability Trip Function. | Anticipated operational occurrence Commercial Grade Dedication MELLLA |
| ML12328A079 | 30 November 2012 | NEDO-33789, Revision 0, Numac Power Range Neutron Monitoring Components 268X1331TCG001, 268X1332TCG001, G002 268X1333TCG001, Qualification Summary for Energy Northwest (Enw) Columbia Generating Station (Cgs), Attachment 5 | |
| ML12328A078 | 31 October 2012 | NEDO-33751, Revision 3, Columbia Generating Station Power Range Neutron Monitoring System Reliability Analysis, Attachment 3 | |
| GO2-12-165, Initial Seismic Walkdown Summary Report, Enclosure 2 | 30 October 2012 | Initial Seismic Walkdown Summary Report, Enclosure 2 | Safe Shutdown Unanalyzed Condition Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi B.5.b Mitigating Strategies Earthquake Scaffolding |
| GO2-12-105, Submittal of Phase 2 Information in Support of License Amendment Request to Change Technical Specifications in Support of Prnm /Arts/Mellla Implementation; NEDO-33750, NEDO-33753; NEDO-33754: NEDO-33755; & NEDO-33758 | 31 July 2012 | Submittal of Phase 2 Information in Support of License Amendment Request to Change Technical Specifications in Support of Prnm /Arts/Mellla Implementation; NEDO-33750, NEDO-33753; NEDO-33754: NEDO-33755; & NEDO-33758 | MELLLA Earthquake |
| ML12102A238 | 13 June 2012 | Memo Conclusion of Informal Section 7 Consultation with U.S. Fish and Wildlife Service for Columbia Generating Station and Section 7 Consultation Report | License Renewal |
| ML12040A074 | 31 January 2012 | NEDO-33685, Revision 1, Digital I&C-ISG-06 Compliance for Columbia Generating Station Numac Power Range Neutron Monitoring Retrofit Plus Option III Stability Trip Function | Anticipated operational occurrence Commercial Grade Dedication MELLLA |
| ML12040A076 | 31 January 2012 | NEDO-33694, Revision 1, Columbia Generating Station Power Range Neutron Monitoring System Diversity and Defense-in-Depth (D3) Analysis | Shutdown Margin Anticipated operational occurrence MELLLA |
| ML12040A079 | 31 January 2012 | NEDO-33698, Revision 1, Columbia Generating Station Power Range Neutron Monitoring System Design Report on Computer Integrity, Test and Calibration, and Fault Detection. Enclosure 2, Attachment 14 to List of Commitments and Enclosure 3 Are | Anticipated operational occurrence Commercial Grade Dedication Temporary Modification MELLLA Fuel cladding |
| ML12040A077 | 31 January 2012 | NEDO-33697, Revision 1, Columbia Generating Station Power Range Neutron Monitoring System Design Analysis Report | MELLLA |
| ML12040A080 | 31 January 2012 | NEDO-33507, Revision 1, Columbia Generating Station Aprm/Rbm/Technical Specifications / Maximum Extended Load Line Limit Analysis (Arts/Mellla) | Safe Shutdown Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Safe Shutdown Earthquake Feedwater Controller Failure MELLLA Earthquake Fuel cladding Power change Coast down GOTHIC |
| ML12040A075 | 30 November 2011 | NEDO-33690, Revision 0, Columbia Generating Station Power Range Neutron Monitoring System Response Time Analysis Report | MELLLA |
| GO2-10-071, 0000-0101-7647-R2, Columbia Generating Station. Plant-Specific Responses Required by Numac Prnm Retrofit Plus Option III Stability Trip Function Topical Report (NEDC-32410P-A) | 30 April 2010 | 0000-0101-7647-R2, Columbia Generating Station. Plant-Specific Responses Required by Numac Prnm Retrofit Plus Option III Stability Trip Function Topical Report (NEDC-32410P-A) | |
| ML100250654 | 19 January 2010 | Columbia Generating Station - License Renewal Application, Technical Information, Pages 3.4-1 to D-2 | |
| GO2-09-001, Gnf S-0000-0092-8136, Revision 0, GE14 Thermal Hydraulic Compatibility with Columbia Legacy Fuel, October 2008 (Non-Proprietary Version) | 31 October 2008 | Gnf S-0000-0092-8136, Revision 0, GE14 Thermal Hydraulic Compatibility with Columbia Legacy Fuel, October 2008 (Non-Proprietary Version) | |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
| GO2-08-108, NEDO-33419, GEXL97 Correlation Applicable to ATRIUM-10 Fuel, Non-Proprietary Version | 30 June 2008 | NEDO-33419, GEXL97 Correlation Applicable to ATRIUM-10 Fuel, Non-Proprietary Version | |
| GO2-06-105, Response to Request for Additional Information Related to Alternative Source Term License Amendment Request | 7 August 2006 | Response to Request for Additional Information Related to Alternative Source Term License Amendment Request | Met Tower |
| ML053270081 | 3 October 2005 | Rev. 0 to Inservice Testing Program Plan, Third Ten-Year Inspection Interval (December 13, 2005 Through December 2014). | High Radiation Area Ultimate heat sink Stroke time Probabilistic Risk Assessment Incorporated by reference Cold shutdown justification Power-Operated Valves Power Operated Valves |
| ML052280262 | 31 May 2005 | GE-NE-0000-0040-1432-00-01, Rev 0, Historical Licensing Evaluation of Post-CRDA RCIC Operation for Columbia Generating Station. | Safe Shutdown Anticipated operational occurrence Safe Shutdown Earthquake |
| ML051290107 | 6 April 2005 | Emergency Response Data System Change to Data Point Library | Reactor Vessel Water Level Met Tower |
| ML042230388 | 3 June 2004 | C106-04-0001-5801, Columbia Generating Station Risk Assessment to Support ILRT (Type a) Interval Extension Request. | Safe Shutdown High winds Internal Flooding Probabilistic Risk Assessment Large early release frequency |
| ML17037B885 | 27 January 1978 | Letter Regarding a GE Report, Analytical Model for Estimating Drag Forces on Rigid Submerged Structures Caused by LOCA and Safety Relief Valve Ramshead Air Discharges, NEDO-21471, Dated September, 1977 | |
| ML17037B888 | 21 November 1977 | Letter Regarding Nedo 24070, Mark II Containment Supporting Program Report - Ramshead Safety/Relief Valve Load - Methodology Summary, September, 1977 | |
| ML17037B891 | 3 November 1977 | Letter Regarding Amendment 2, Supplement 2 (September 1977) to Mark II Containment Dynamic Forcing Functions Information Report (Dffr), NEDO-21061, Rev. 2 | |
| ML17037B892 | 25 October 1977 | Letter Regarding GE Topical Report Nedo 23617 Mark II Lead Plant Topical Report: Pool Boundary and Main Vent Chugging Load Justification, Dated July, 1977 | |
| ML17037B894 | 26 September 1977 | Letter Regarding GE Report Technical Basis for the Use of the Square Root of the Sum of Squares (Srss) Method for Combining Dynamic Loads on Mark II Plants - July, 1977 | |
| ML17037B890 | 23 September 1977 | Letter Regarding Mark II Containment Program Report, Comparison of the 1/3 Scale Mark II Containment Multivent Pool Swell Data with Analytical Methods, NEDO-21667, August 1977 | |
| ML17037B895 | 15 September 1977 | Letter Regarding Amendment 2, Supplement 1 (August 1977) to Mark II Containment Dynamic Forcing Functions Information Report (Dffr), NEDO-21061, Rev. 2 | |
| ML18191A274 | 12 January 1976 | Wppss Nuclear Project No. 2. Clarification of Criteria, Pipe Rupture Protection Inside Containment | Finite Element Analysis |
| ML18191A360 | 5 September 1975 | Letter from Wppss to NRC of Final Report on the Successful Disposition of the Fabrication Difficulties on the WNP-2 Containment Vessel | Weld Overlay Hydrostatic Scaffolding |
| ML18191A236 | 26 March 1975 | Wppss Nuclear Project No. 2, Response to Request for Additional Information, Pipe Rupture Protection Inside Containment | Finite Element Analysis |