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MONTHYEARML1012503142010-05-10010 May 2010 04/06/2010 - Meeting Summary-CGS License Renewal Overview and Environmental Scoping Meetings Project stage: Meeting ML1012505192010-05-10010 May 2010 04/06/2010 - Summary of Public License Renewal Overview and Environmental Scoping Meetings Related to the Review of the Columbia Generating Station License Renewal Application (TAC Nos. ME3058 and ME3121) Project stage: Meeting ML1024403422010-08-19019 August 2010 Columbia Generating Station - Response to Request for Additional Information License Renewal Application Project stage: Response to RAI ML1022203732010-08-26026 August 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application for Fatigue Monitoring Program, TLAA Exemptions, Metal Fatigue TLAA, Cumulative Fatigue Damage, CASS, and Structural Project stage: RAI ML1024505712010-09-14014 September 2010 Summary of Telephone Conference Call Held on August 10, 2010, Between the U.S. NRC and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application Project stage: RAI ML1024506212010-09-14014 September 2010 Summary of Telephone Conference Call Held on August 26, 2010, Between the U.S. NRC and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application Project stage: RAI ML1024507272010-09-16016 September 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application Project stage: RAI ML1024507562010-09-16016 September 2010 8/12/10, Summary of Telephone Conference Call Held on Between NRC and Energy Northwest, Concerning the RAI Pertaining to the Columbia Generating Station, LRA Project stage: RAI ML1025306452010-09-21021 September 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application Project stage: RAI ML1027004332010-10-0404 October 2010 Summary of Telephone Conference Call Held on September 13, 2010, Between the U.S. Nuclear Regulatory Commission and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, License R Project stage: RAI ML1028004262010-10-14014 October 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application (TAC No. 3058) Project stage: RAI ML1028507352010-10-20020 October 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application (TAC ME3058) Concerning Structures Project stage: RAI ML1027303552010-10-20020 October 2010 Letter Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application, Concerning Structures (Tac No. ME3058) Project stage: RAI ML1027902232010-10-25025 October 2010 10/05/2010 Summary of Telephone Conference Call Held Between NRC and Energy Northwest, Concerning the Draft Rao Pertaining to the Columbia Generating Station, License Renewal Application Project stage: Draft Other ML1028702452010-10-25025 October 2010 October 13, 2010, Summary of Teleconference Held Between the U.S. NRC and Energy Northwest, Concerning the Draft Request for Additional Information Pertaining to the Columbia Generating Station License Renewal Application Project stage: Draft RAI ML1028701932010-10-25025 October 2010 9/22/10 Summary of Telephone Conference Call Held Between the USNRC and Energy Northwest Concerning the D-RAI Pertaining to the Columbia Generating Station, License Renewal Application Project stage: RAI ML1028501032010-10-27027 October 2010 Summary of Telephone Conference Calls Held on 9/20/10, Between Us NRC and Energy Northwest, Concerning the Response to RAI Pertaining to the Columbia Generating Station, LRA Project stage: RAI ML1029305932010-11-0101 November 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application Project stage: RAI ML1030100802010-11-0505 November 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application Project stage: RAI GO2-10-164, Response to Request for Additional Information License Renewal Application2010-11-11011 November 2010 Response to Request for Additional Information License Renewal Application Project stage: Response to RAI ML1030004792010-11-19019 November 2010 Summary of Telephone Conference Call Between the USNRC and Energy Northwest, Concerning the Draft Request for Additional Information Pertaining to the Columbia Generating Station, LRA Project stage: Draft RAI ML1030905662010-11-19019 November 2010 Summary of Teleconference Held on September 22, 2010, Between the U.S. NRC and Energy Northwest, Concerning the Responses to the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application Project stage: RAI ML1031305482010-11-19019 November 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application Project stage: RAI ML1032003382010-11-19019 November 2010 Summary of Teleconference Held on November 8, 2010, Between the U.S. Nuclear Regulatory Commission and Energy Northwest, Concerning the Responses to Request for Additional Information Pertaining to the Columbia Generating Station, LRA Project stage: RAI ML1035400222010-12-20020 December 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application Project stage: RAI ML1035506032010-12-27027 December 2010 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application (TAC No. Me3058) Project stage: RAI ML1100500182011-01-0606 January 2011 Summary of Telephone Conference Call Held on January 3, 2011, Between the NRC and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application (TAC Number ME3 Project stage: RAI ML1034305262011-01-10010 January 2011 Schedule Revision for the Review of the Columbia Generating Station License Renewal Application (TAC Nos. ME3058, ME3121) Project stage: Approval ML1036307392011-01-11011 January 2011 Safety Project Manager Change for the License Renewal of Columbia Generating Station (Tac No. ME3058) Project stage: Other ML1100604382011-01-13013 January 2011 Summary of Telephone Conference Call Held on 1/5/11, Between NRC and Energy Northwesy, Concerning the RAI Pertaining to the Columbia Generating Station License Renewal Application (Tac No. ME3058) Project stage: RAI ML1101405882011-01-31031 January 2011 01/12/11 Summary of Telephone Conference Call Held Between NRC and Energy Northwest, Concerning the Responses to RAI Pertaining to the Columbia Generating Station. License Renewal Application Project stage: RAI ML1102402022011-02-0303 February 2011 01/20/2011 Summary of Telephone Conference with NRC and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application Project stage: RAI ML1102404262011-02-0303 February 2011 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application for Metal Fatigue (Tac No. ME3058) Project stage: RAI ML1102007102011-02-0303 February 2011 01/11/11 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Energy Northwest Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Applicat Project stage: RAI ML1102603802011-02-16016 February 2011 January 24, 2011, Summary of Telephone Conference Call Held Between U.S. Nuclear Regulatory Commission and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station Project stage: RAI ML1104702152011-02-23023 February 2011 Summary of Telephone Conference Call Held on February 14, 2011, Btw the USNRC and Energy Northwest, Concerning the Responses to the Request for Additional Information Pertaining to the Columbia Generating Station, LRA Project stage: RAI ML1105401262011-02-28028 February 2011 2/17/11 Summary of Telephone Conference Call Held Between the USNRC and Energy Northwest, Concerning the Responses to the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application Project stage: RAI ML1106107122011-03-0909 March 2011 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application for Buried Piping and Tanks Inspection Project stage: RAI ML1106909972011-03-15015 March 2011 Summary of Telephone Conference Call Held on 3/8/11 Btw the USNRC and Energy Northwest Concerning the Responses to the RAI Pertaining to the Columbia Generating Station, License Renewal Application (TAC Number ME3058) Project stage: RAI ML1106806702011-03-18018 March 2011 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application for Drywell Floor Peripheral Seal Assembly (TAC Number ME3058) Project stage: RAI ML1106303602011-03-23023 March 2011 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application for Time-Limited Aging Analyses of Reactor Vessel Neutron Embrittlement (TAC Number ME3058) Project stage: RAI ML1108714952011-04-0505 April 2011 Summary of Telephone Conference Call Held on March 23, 2011, Between NRC and Energy Northwest, Concerning the RAI Pertaining to the Columbia Generating Station, LRA (Tac No. ME3058) Project stage: RAI ML11138A3232011-05-24024 May 2011 RAI for the Review of the Columbia Generating Station, License Renewal Application for Operating Experience Project stage: RAI ML11140A1612011-06-0202 June 2011 RAI for the Review of the Columbia Generating Station, License Renewal Application Regarding Core Plate Assembly Project stage: RAI ML11137A0442011-06-0808 June 2011 05/06/2011-Summary of Telephone Conference Call Between the NRC and Energy Northwest, Concerning the Draft Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application Project stage: Draft RAI ML11165A2432011-06-22022 June 2011 Summary of Telephone Conference Call Held on June 1, 2011, Between the U.S. Nuclear Regulatory Commission and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, LRA Project stage: RAI ML11188A2382011-07-12012 July 2011 07/06/2011-Summary of Telephone Conference Call Between NRC and Energy Northwest, Concerning the Request for Additional Information Response Pertaining to the Columbia Generating Station, License Renewal Application Project stage: RAI ML11195A2402011-07-19019 July 2011 Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application Regarding High Voltage Porcelain Insulators Project stage: RAI ML11208B0492011-08-0202 August 2011 07/19/11 Summary of Telephone Conference Call Held Between the NRC and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application (TAC No. Me3058) Project stage: RAI ML11216A2532011-08-11011 August 2011 August 3, 2011, Summary of Telephone Conference Call Held Between the NRC and Energy Northwest, Concerning the Response to the Request for Additional Information Pertaining to the Columbia Generating Station, LRA Project stage: RAI 2011-01-13
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Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection ML22343A1802022-12-0808 December 2022 February 2023 Emergency Preparedness Program Inspection - Request for Information ML22301A1432022-10-28028 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Adopt TSTF-505 - EPID L-2022-LLA-0023 ML22242A1082022-08-30030 August 2022 Information Request, Information Request, Security IR 2022404 ML22235A1052022-08-22022 August 2022 August 2022 Emergency Preparedness Exercise Inspection Request for Information ML22145A4462022-06-0606 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000397/2022401 ML22144A0342022-05-18018 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22041A4572022-02-10010 February 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000397/2022010) and Request for Information ML21277A3572021-10-12012 October 2021 CGS Brq RFI Letter, Columbia Generating Station - Notification of Inspection (NRC Inspection Report 05000397/2021004) and Request for Information ML21216A0502021-08-0303 August 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia - License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO EPID L-2021-LLA-0259 ML21209A9792021-07-28028 July 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) - EPID L-2021-LLA-0074 ML21120A1182021-04-30030 April 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - On-Site Cooling System Sediment Disposal Approval Request - EPID L-2020-LLL-0031 ML21068A2842021-03-0404 March 2021 2021002 Inservice Inspection (ISI) Request for Information (RFI) ML20336A1852020-11-30030 November 2020 NRR E-mail Capture - Final - RAI - Columbia - One -Time Exemption from 10 CFR 73, App B, Sect VI, Subsection C.3.(l)(1) Regarding Annual Force-On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172 ML20325A0402020-11-19019 November 2020 NRR E-mail Capture - Draft - RAI - Columbia - One -Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force -On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172 ML20267A5162020-09-23023 September 2020 NRR E-mail Capture - Columbia Generating Station - Final - Request for Additional Information - Fourth Ten-Year Interval Inservice Inspection (ISI) Program Relief Request 4ISI-09 - EPID L-2020-LLR-0068 ML20245E2822020-08-31031 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time ML20239A9702020-08-26026 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time ML20149K4362020-05-26026 May 2020 NRR E-mail Capture - Formal RAIs for Columbia (COVID-19) QA Plan Change Surveillance, Request Response by Tuesday June 2, 2020 ML20112F4572020-04-21021 April 2020 NRR E-mail Capture - Official Release of NRC RAIs for Columbia Covid Exigent Due Friday April 24, 2020 ML20034E6082020-02-0303 February 2020 NRR E-mail Capture - RAI Formal Release Columbia TSTF 563 LAR, 30 Day Response Period Due March 3, 2020 ML20028E1512020-01-27027 January 2020 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000397/2020002) and Request for Information ML19267A1842019-09-24024 September 2019 Request for Information for Upcoming Open Phase Condition Inspection at Columbia Generating Station ML19232A2282019-08-20020 August 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia Exigent Amendment - One Electrical RAI, ML19183A4752019-07-0202 July 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia HVAC LAR L-2019-LLA-0034 ML18088A0152018-03-29029 March 2018 Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment Plans (05000397/2018010) and Request for ML17341B0272017-12-0707 December 2017 NRR E-mail Capture - RAI Associated with Columbia Amendment Request Revise Tech Spec 5.5.12 for Permanent Extension of Type a and Type C Containment Testing Frequencies for MF9469, EPID: L-2017-LLA-0197, ILRT, LLRT LAR - New RAI Response Da ML17292A0572017-10-18018 October 2017 NRR E-mail Capture - New RWCU RAI Due Date Now November 24, 2017 ML17249A6882017-09-0606 September 2017 NRR E-mail Capture - RAIs for Columbia Relief Request RAI (MF8925), 3ISI-19 ML17205A3152017-07-20020 July 2017 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000397/2017004) and Request for Information ML17193A2192017-07-12012 July 2017 NRR E-mail Capture - Columbia RWCU LAR MF8318, Formal Release of RAIs ML17144A1702017-05-24024 May 2017 NRR E-mail Capture - NRC RAIs for Columbia Relief Request MF8922, 3ISI-16 ML17047A7492017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais ML17006A0922017-01-0404 January 2017 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML17006A0902017-01-0404 January 2017 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML16356A1382016-12-21021 December 2016 NRR E-mail Capture - Columbia Mur LAR Evib RAIs Non - Proprietary Version - Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate ML16342C4322016-12-0707 December 2016 NRR E-mail Capture - Columbia Measurement Uncertainty Recapture Power Uprate LAR Rais: Human Performance: MF8060, Formal Release for Response on Monday January 9, 2017 ML16327A1842016-11-22022 November 2016 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML16323A1192016-11-16016 November 2016 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML16218A3902016-08-0808 August 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Request for Measurement Uncertainty Recapture (Mur) Power Uprate (from 3486 Mwt to 3544 Mwt) ML16194A3702016-07-11011 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection 05000397/2016003 and Request for Information ML16069A3592016-03-0909 March 2016 NRR E-mail Capture - Second Round Rais: Columbia MF6042 LAR TSTF-425 ML16061A5542016-03-0101 March 2016 Notification of NRC Design Bases Inspection (05000397/2016007) and Initial Request for Information ML16061A5662016-03-0101 March 2016 Notification of Design Bases Inspection (Programs)(Inspection Report 05000397/2016008) and Initial Request for Information ML15254A2572015-09-16016 September 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1 Seismic Reevaluations ML15215A0432015-08-18018 August 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations ML14262A3412014-09-24024 September 2014 Request for Additional Information, Round 2, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High ML14192B0312014-08-13013 August 2014 Redacted, Request for Additional Information, Nrr/Dss/Scvb, Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows ML14206A0112014-07-31031 July 2014 Request for Additional Information, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High 2024-01-10
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 20,2010 Mr. S. K. Gambhir Vice President Technical Services Columbia Generating Station Energy Northwest MD PE04 P.O. Box 968 Richland, WA 99352-0968
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. ME3058)
Dear Mr. Gambhir:
By letter dated January 19, 2010, Energy Northwest submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew Operating License NPF-21 for Columbia Generating Station, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Abbas Mostala and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-4029 Or bye-mail at evelyn.gettys@nrc.gov.
Sincerely, Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
As stated cc w/encl: Distribution via Listserv
COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI4.2-1
Background:
The Columbia Generating Station (Columbia) reactor vessel (RV) N12 water level instrumentation nozzles (4 nozzles) are considered to be in the beltline region of the RV 17 2 because they are projected to experience neutron fluence greater than 1 x 10 n/cm (E> 1.0 MeV) at the end of the period of extended operation, corresponding to 54 effective full power years (EFPY) of facility operation. The staff had requested in a previous request for additional information (RAI) that the applicant supplement license renewal application (LRA)
Sections 4.2.1, 4.2.2, and 4.2.3 to include data for the neutron fluence, Charpy upper shelf energy (USE) evaluation, and adjusted nil-ductility reference temperature (ART) analysis for the four N 12 instrumentation nozzles. The applicant's RAI response provided some information concerning a fluence value and a projected USE decrease for one of the four N12 nozzles; however, the RAI response did not provide sufficient data for the staff to conclude that the projected USE and ART analyses for these N 12 nozzles would remain acceptable for the period of extended operation (54 EFPY), in accordance with to CFR 54.21 (c)(1)(ii) and 10 CFR Part 50, Appendix G requirements.
The staff has also determined that the applicant has not demonstrated that the use of the BWRVIP-74-A, "BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal," equivalent margins analysis (EMA) for plate material is a valid EMA acceptance criterion for nozzle forgings. Furthermore, the staff found that the applicant has not provided analyses of either the ART or the USE for the N12 instrumentation nozzle-to-RV welds for the period of extended operation.
Issue:
The requirements of 10 CFR Part 50, Appendix G apply to "ferritic materials of pressure retaining components of the reactor coolant pressure boundary ... " The 10 CFR Part 50, Appendix G requirements do not apply to austenitic-phase materials, such as nickel-based alloys and austenitic stainless steels. Therefore, if the N 12 nozzles and the associated N 12 nozzle-to-RV welds are composed of an austenitic material, then the N12 nozzles and their associated welds are not subject to 10 CFR Part 50, Appendix G requirements, and they do not need to be analyzed for neutron fluence, USE, or ART in LRA Section 4.2.
However, if the N 12 nozzles and the associated N 12 nozzle-to-RV welds are composed of a ferritic material (such as an ASME Code,Section II, SA-50a alloy steel or carbon steel), then the 10 CFR Part 50, Appendix G requirements are applicable to these nozzles and their associated nozzle-to-RV welds, and the N12 nozzles and their associated welds must be analyzed for the USE and the ART in Sections 4.2.2 and 4.2.3 of the Columbia LRA.
ENCLOSURE
- 2 Request:
(a) Please state the general type of material (e.g., austenitic nickel-based alloy, austenitic stainless steel, or a ferritic carbon or low alloy steel) from which the N12 water level instrumentation nozzles and their associated nozzle-to-RV welds are fabricated. If all N12 nozzles and associated N12 nozzle-to-RV welds are composed of an austenitic material, then no further information is required concerning the N 12 instrumentation nozzles.
The following questions apply only if the N 12 instrumentation nozzles are fabricated from a ferritic-phase material such as carbon or low alloy steel.
(b) Please provide the following information, if available, for the N12 RV beltline instrumentation nozzle forgings and their associated nozzle-to-RV weld materials:
- i. The ASME Code,Section II Material Specification (e.g., SA-###, Grade ## and/or Class
- ) for each N12 RV beltline nozzle forging; ii. the heat number for each N12 RV beltline nozzle forging; iii. the heat number of wire and flux lot number used to fabricate each N 12 RV beltline nozzle-to-RV weld; iv. the chemical composition (i.e., the weight percent (wt%) of copper and nickel) for each N12 RV beltline nozzle forging;
- v. the chemical composition (Le., the wt.% of copper and nickel) for each N12 RV beltline nozzle-to-RV weld; vi. the unirradiated nil-ductility reference temperature (RT NDT) for each N 12 RV beltline nozzle forging; vii. the unirradiated RT NDT for each N 12 RV beltline nozzle-to-RV weld; and viii. the method of determining the unirradiated reference temperature from the Charpy and drop weight tests for each N 12 RV beltline nozzle forging and associated nozzle-to-RV weld.
(c) Based on the information provided in part (b) above for the N12 RV beltline nozzle forgings and associated nozzle-to-RV welds, please provide a calculation of the 54 EFPY ART values for the N12 RV beltline nozzle forging and associated nozzle-to-RV weld materials. If actual values for the wt. % copper and nickel are not available for any of these N12 nozzle forgings or associated nozzle-to-RV welds, then 54 EFPY ART values must be calculated for these materials based on a determination of acceptable wt. % copper and nickel values from the evaluation of a statistically significant set of representative materials or based on limiting values for the wt. % copper and nickel listed in the applicable ASME Code, Section 1/
material specifications for these N 12 nozzle forging and associated nozzle-to-RV weld materials.
- 3 (d) Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements," states that RV beltline
[ferritic] materials have Charpy USE in the transverse direction for base metal and along the weld for weld metal of no less than 75 ft-Ib initially and must maintain USE throughout the life of the RV of no less than 50 ft-Ibs unless it is demonstrated in a manner approved by the Director, Office of Nuclear Reactor Regulation, that lower values of Charpy USE will provide margins of safety against fracture equivalent to those required by Appendix G of Section XI of the ASME Code.
The applicant's RAI response concerning the USE evaluation for the N 12 water level instrumentation nozzles states that that the BWRVIP-74-A EMA acceptance criterion for plate material was used to determine that N12 instrumentation nozzle forgings meet the USE requirements of 10 CFR Part 50, Appendix G. In BWRVIP-74-A, Appendix B, Section B.2, EMA for BWR/3-6 plates, the materials addressed in the analysis included: ASME Code,Section II, SA-302 Grade B and Grade B Modified low allow steel plate and SA-533 Grade B, Class 1 low alloy steel plate. Nozzle forging materials, including nozzle-to-RV welds, were not included in the BWRVIP-74-A, Appendix B analysis. Therefore, the staff does not find the application of BWRVIP-74-A acceptable for demonstrating compliance with Appendix G to 10 CFR Part 50 for the Columbia nozzle materials. The methodology contained in BWRVIP-74-A is applicable only to the materials analyzed in the report.
- i. For all ferritic N12 instrumentation nozzle forgings, the staff requests that the applicant submit EMAs to demonstrate that the 54 EFPY Charpy USE will provide margins of safety against fracture equivalent to those required by Appendix G of Section XI of the ASME Code. .
ii. For all ferritic N12 instrumentation nozzle-to-RV welds, the staff requests that the applicant provide an evaluation of the 54 EFPY USE values, based on either a direct calculation of the 54 EFPY USE values, or, if initial USE value are unknown, EMAs to demonstrate that the 54 EFPY Charpy USE will provide margins of safety against fracture equivalent to those required by Appendix G of Section XI of the ASME Code.
RAI4.2-2
Background:
The Columbia RV N6 residual heat removaillow-pressure coolant injection (RHR/LPCI) nozzles (3 nozzles) are considered to be in the beltline region of the RV because they are projected to experience neutron fluence greater than 1 x 10 17 n/cm 2 (E > 1.0 MeV) at the end of the period of extended operation (54 EFPY). The staff had requested in a previous RAJ that the applicant supplement LRA Section 4.2.2 to include data for the USE evaluation for the three N6 RHR/LPCI nozzles. The applicant's RAI response provided information concerning a projected percent decrease in the USE value for these nozzles valid for 54 EFPY. The applicant stated in its RAI response that this value is below the 23.5% USE EMA acceptance criterion established for rolled plate material in BWRVIP-74-A.
-4 Issue:
The staff reviewed the applicant's RAI response and determined that the applicant had provided an acceptable calculation of the projected percent decrease in the USE value for these nozzle forgings (9.6% at 54 EFPY). However, the staff found that the applicant had not demonstrated that the use of the BWRVIP-74-A EMA for plate material is a valid EMA acceptance criterion for nozzle forgings. Furthermore, the staff found that the applicant had not provided analyses of either the adjusted RTNDT (ART) or the USE for the N6 RHR/LPCI nozzle-to-RV welds for the period of extended operation.
Request:
(a) Please provide the following information for the N6 RV beltline RHR/LPCI nozzle forging and the associated nozzle-to-RV weld materials, as follows:
- i. The ASME Code,Section II Material Specification (e.g., SA-###, Grade ## and/or Class
- ) for each N6 RV beltline nozzle forging; ii. the heat number of wire and flux lot number used to fabricate each N6 RV beltline nozzle-to-RV weld; iii. the chemical composition (i.e., the wt.% of copper and nickel) for each N6 RV beltline nozzle-to-RVweld; iv. the unirradiated RTNDT for each N6 RV beltline nozzle-to-RV weld; and
- v. the method of determining the unirradiated reference temperature from the Charpy and drop weight tests for each N6 RV beltline nozzle-to-RV weld.
(b) Based on the information provided in part (a) above for the N6 RV beltline nozzle-to-RV welds, please provide calculations of the 54 EFPY ART values for the nozzle-to-RV weld materials. If actual values for the wt.% copper and nickel are not available for any of these N6 nozzle-to-RV welds, then 54 EFPY ART values must be calculated for these materials based on a determination of acceptable wt.% copper and nickel values from the evaluation of a statistically significant set of representative materials or based on limiting values for the wt.% copper and nickel listed in the applicable ASME Code,Section II material specifications for these N 12 nozzle forging and associated nozzle-to-RV weld materials.
(c) Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements," states that reactor vessel (RV) beltline [ferritic] materials have Charpy USE in the transverse direction for base metal and along the weld for weld metal of no less than 75 ft-Ib initially and must maintain USE throughout the life of the RV of no less than 50 ft-Ibs unless it is demonstrated in a manner approved by the Director, Office of Nuclear Reactor Regulation, that lower values of Charpy USE will provide margins of safety against fracture equivalent to those required by Appendix G of Section XI of the ASME Code." The applicant's RAI response concerning the USE evaluation for the N6 RHR/LPCI nozzles states that that the BWRVIP-74-A EMA acceptance criterion for plate material was used to determine that N6 RHR/LPCI nozzles forgings meet the USE requirements of 10 CFR Part 50, Appendix G. In BWRVIP-74-A, Appendix B, Section B.2, EMA for BWR/3-6 plates, the materials addressed in the analysis
-5 included: ASME Code,Section II, SA-302 Grade B and Grade B Modified low allow steel plate and SA-533 Grade B, Class 1 low alloy steel plate. Nozzle forging materials, including nozzle-to-RV welds, were not included in the BWRVIP-74-A, Appendix B analysis.
Therefore, the staff does not find the application of BWRVIP-74-A acceptable for demonstrating compliance with Appendix G to 10 CFR Part 50 for the Columbia nozzle materials. The methodology contained in BWRVIP-74-A is applicable only to the materials analyzed in the report.
- i. For all N6 RHR/LPCI nozzle forgings, the staff requests that the applicant submit EMAs to demonstrate that the 54 EFPY Charpy USE will provide margins of safety against fracture equivalent to those required by Appendix G of Section XI of the ASME Code.
ii. For all N6 RHRlLPCI nozzle-to-RV welds, the staff requests that the applicant provide an evaluation of the 54 EFPY USE values, based on either a direct calculation of the 54 EFPY USE values, or, if initial USE values are unknown, EMAs to demonstrate that the 54 EFPY Charpy USE will provide margins of safety against fracture equivalent to those required by Appendix G of Section XI of the ASME Code.
RAI4.7.1-1
Background:
For the time-limited aging analysis (TLAA) of the Columbia RV shell indications (i.e., flaws),
discussed in LRA Section 4.7.1, the staff issued an RAI (RAI 4.7.1-10(b>> requesting that the applicant add a license renewal commitment to re-inspect the subject flaws in 2015 and, based on the results of the 2015 inspection of the subject flaws, re-evaluate the subject flaws for the period of extended operation (54 EFPY) in accordance with ASME Code,Section XI, IWB-3600 flaw evaluation reqUirements, or continue augmented inspections as required by the ASME Code,Section XI. The staff had determined that this license renewal commitment is necessary, given that the current flaw evaluation referenced in LRA Section 4.7.1 will only remain valid through the end of the current 40-year licensed operating period (33.1 EFPY). In its response to RAI4.7.1-10(b), the applicant stated that all RV axial welds, including portions of RV axial welds BG and BM with the flaws, will be re-examined in 2015 as part of the NRC-approved Inservice Inspection (lSI) program for the current 10-year lSI interval. The applicant added that these examinations are required to be completed by 2015, well before the beginning of the period of extended operation. The applicant stated further that these examinations are required for the current 40-year license term, regardless of whether or not the Columbia operating license receives 20-year extension. Thus, the applicant concluded in response to RAI4.7.1-10(b) that "it is not a license renewal commitment to repeat these inspections."
Issue:
In reviewing the applicant's response to RAI4.7.1-10(b), the staff acknowledges that the RV axial welds, including the subject flaws, are required to be re-examined prior to the end of the third 10-year lSI interval at Columbia, in accordance with ASME Code,Section XI requirements for the current 40-year license term. However, the analysis of these RV shell indications is a license renewal TLAA that has not yet been projected to remain in compliance with ASME Code,Section XI 'flaw acceptance criteria through the end of the period of extended operation.
- 6 Furthermore, the Columbia lSI aging management program description in LRA Section 8.2.33 does not specifically address re-evaluation of existing flaws in ASME Code Class 1 components.
Request:
In order to ensure that the effects of aging for the subject RV shell weld flaws will be adequately managed in accordance with the requirements of 10 CFR 54.21 (c)(1 )(iii), the staff requests that the applicant include a license renewal commitment to re-evaluate the subject flaws for the period of extended operation (54 EFPY), in accordance with the requirements of the ASME Code,Section XI, IW8-3600 based on the results of 2015 lSI.
... ML103540022 *concurrence via e-mail OFFICE PM:RPB'I:DLR LADLR* BC: RPB1:DLR PM:RPB1:DLR NAME EGettys IKing BPham EGettys DATE 12/20/10 12/20/10 12/20/10 12/20/10
Letter to S.K. Gambhir from E. Gettys dated December 20,2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. 3058)
DISTRI BUTION:
HARDCOPY:
DLRRF E-MAIL:
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