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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 September 16, 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. 3058)
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: See next page
COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI 3.1.2.3.1-1
Background:
In license renewal application (LRA) Table 3.1.2-1, the applicant stated that the steel nozzle (N06) safe-end extension (RHR/LPCI) exposed to air-indoor uncontrolled (external) does not require any aging effect to be managed. The related aging management review (AMR) line item cites generic note G, indicating that this environment is not in the GALL Report for the aging effects of this component and material combination. Also, the associated plant-specific note 0101 states that there is no identified aging effect for these components, based on their being exposed to indoor air, where temperature is >212°F.
Issue The staff noted that the applicant has listed in row item 313 of LRA Table 3.1.2 that reactor pressure vessel stabilizer brackets made of steel exposed to air-indoor uncontrolled (external) are being managed for "cracking - flaw growth" by the ASME Section XI lSI - IWB, IWC and IWD aging management program (AMP), and classified this with the Generic Note H. This classification does not appear consistent with the AMR item classified with the Generic Note G discussed above.
Request Justify why the treatment of these two AMR items is different for the same material exposed to same environment for managing the aging effect in one and not in the other item, and reconcile the differences.
RAI 3.1.2.3.1-2 Backqround In LRA Tables 3.1.2-1 and 3.1.2-3 the applicant stated that various reactor vessel components of steel, steel with stainless steel cladding, stainless steel, and nickel alloys exposed to reactor coolant (internal) are being managed for "cracking - flaw growth" by the ASME Section XI lSI IWB, IWC and IWD Program. The related AMR line items cite generic note H, indicating that the aging effect is not in the GALL Report for this component, material, and environment combination. These components include: RPV shells or shell rings, various nozzles and associated safe-ends/thermal sleeves, penetrations, and support attachments/welds.
Issue The LRA refers to "Cracking - Flaw Growth" as a time dependent aging effect/mechanism being managed by the ASME Section XI lSI program. The applicant's usage (or intended meaning) of "Cracking - Flaw Growth" is not clear to the staff. Also, depending on the interpretation of "Flaw Growth," it would seem that these items should be addressed as "TLAA" which is covered under the GALL Report, instead of generic note "H" items.
Request (a) Clarify the meaning and intended usage of "Cracking - Flaw Growth" aging effecUmechanism.
(b) Identify any of the items for "Flaw Growth" (as associated with the Generic Note H of this Enclosure
- 2 AMR) in the current licensing basis (CLB) for flaw growth or flaw tolerance evaluations to analyze fatigue that involved the current operating term (40 years) and were determined to be relevant in making the safety determination? If so, justify the adequacy of aging management of applicable items by the ASME Section XIISI-IWB, IWC and IWD Program (as Generic Note H items), or include these under time-limited aging analysis (TLAA) assessment.
RAI3.1.1.x-1
Background
Cracking due to intergranular stress corrosion cracking (IGSCC) has occurred in small- and large-diameter boiling water reactor (BWR) piping made of austenitic stainless steels and nickel alloys. The IGSCC has also occurred in a number of vessel internal components, such as core shrouds, access hole covers, top guides, and core spray spargers (NRC Bulletin 80-13, NRC Information Notice [IN] 95-17, NRC Generic Letter [GL] 94-03, and NUREG-1544). Cracking due to thermal and mechanical loading have occurred in high pressure coolant injection (HPCI) piping (NRC IN 89-80) and instrument lines (NRC Licensee Event Report [LER] 50-249/99-003 1). Jet pump BWRs are designed with access holes in the shroud support plate at the bottom of the annulus between the core shroud and the reactor vessel wall. These holes are used for access during construction and are subsequently closed by welding a plate over the hole. Both circumferential (NRC IN 88-03) and radial cracking (NRC IN 92-57) have been observed in access hole covers.
Issue Columbia Generating Station (CGS) has a jet-pump BWR designed with access holes in the shroud support plate which were closed by a welded cover plate. In this case one of the plates is welded only from the top and the plate material is austenitic stainless steel. This has the potential for IGSCC from the bottom where crevice conditions exist, requiring augmentation of the ASME Section XIISI-IWB, IWC and IWD Program. In contrast to these plant conditions, the applicant, in its LRA Table 3.1.1 Item 3.1.1-49, states that access hole covers were modified to eliminate the crevice and that the component material is nickel alloy.
Request Clarify and reconcile the actual plant conditions for the access hole welded cover plates and the LRA Table 3.1.1 Item 3.1.1-49. Justify the absence of any augmented inspection plan for the creviced location(s) and provide the method and basis for monitoring and inspection for the potential IGSCC of these locations such that their intended function(s) will be maintained consistent with the CLB during the period of extended operation, as required by 10 CFR 54.21 (a)(3).
RAI 3.3.1.68-1
Background
LRA Table 3.3.1, item 3.3.1-68 addresses steel piping, piping components, and piping elements and item 3.3.1-70 addresses copper alloy piping, piping components, and piping elements exposed to raw water (internal) which are being managed for loss of material due to pitting,
-3 crevice, and microbiologically influenced corrosion (MIC), and fouling. To manage these aging effects, in LRA Table 3.3.2-22, the applicant credits the Diesel-Driven Fire Pumps Inspection Program (B.2.18) for the components in the fire protection system, and in LRA Tables the applicant credits the Monitoring and Collection Systems Inspection Program (B.2.41) for the components in the fuel pool cooling, plant sanitary drains, and reactor closed cooling water systems.
For line items 3.3.1-68 and 3.3.1-70, the GALL Report recommends using GALL AMP XI.M27 "Fire Water System" which recommends performing wall thickness evaluations of system components using nonintrusive volumetric testing or plant maintenance visual inspections of the internal surfaces to ensure that aging effects are being adequately managed. GALL AMP XI.M27 recommends that these inspections be performed before the end of the current operating term and at plant-specific intervals thereafter during the period of extended operation to ensure that degradation will be detected before the loss of intended function.
Issue The staff noted that the Diesel-Driven Fire Pumps Inspection Program and the Monitoring and Collection Systems Inspection Programs propose to manage the aging of steel and copper alloy piping, piping components, and piping elements through the use of one-time inspections involving a combination of established volumetric and visual examination techniques that will detect and characterize the conditions on the internal surfaces of subject mechanical components that are exposed to raw water (or antifreeze). It is not clear to the staff how these programs are adequate to manage loss of material for these components given that the GALL Report recommends periodic inspections to ensure that aging effects are being adequately managed and the system maintains its intended function during the period of extended operation.
Request Justify how the Diesel-Driven Fire Pumps Inspection and Monitoring and Collection Systems Inspection Programs, which are both one-time inspection programs, are adequate to manage loss of material and reduction in heat transfer for piping and components in the fire protection, fuel pool cooling, plant sanitary drains, and reactor closed cooling water systems in place of a periodic inspection program as recommended by the GALL Report.
RAI 3.4.2.3-1
Background
In LRA Table 3.4.2-3, row number 33, the applicant proposes to manage loss of material for the external surfaces of steel piping exposed to uncontrolled indoor air using its Buried Piping and Tanks Inspection Program. The applicant cites plant-specific note 0408 which states that the carbon steel piping from the condensed storage tank (CST) is buried and is enclosed in guard pipe. The applicant also cites generic note E and line item 3.4.1-28. The GALL Report recommends GALL AMP GALL AMP XI.36 "External Surfaces Monitoring" to ensure that these aging effects are adequately managed.
Issue The staff notes that GALL AMP XI.36 "External Surfaces Monitoring" recommends periodic direct visual inspections of the surfaces managed by the program. The staff also notes that the
-4 applicant's Buried Piping and Tanks Inspection Program provides for visual inspections of the external surfaces of buried piping and tanks to determine coating integrity, but does not include access to or direct inspection of the external surfaces of buried pipe enclosed in an outer guard pipe. The staff further notes that the applicant's Buried Piping and Tanks Inspection Program does not include flow testing, pressure testing, or any other means to manage aging for piping within a guard pipe. It is unclear to the staff how the buried piping within a guard pipe will be adequately managed by the Buried Piping and Tanks Inspection Program.
Request Explain how the external surface of the underground piping enclosed in an outer guard pipe will be adequately managed for loss of material.
RAI 3.3.2.2.3.3 - 1
Background
The GALL Report, Table 3 item 6 ~tates that cracking due to stress corrosion cracking could occur in stainless steel diesel engine exhaust piping, piping components, and piping elements exposed to diesel exhaust. The GALL Report further states that these components require a further evaluation of a plant-specific aging management program to ensure that these aging effects are adequately managed. The LRA Section 3.3.2.2.3.3 states that during normal plant operations, diesel exhaust piping, piping components, and piping elements are exposed to outdoor air and are only exposed to diesel exhaust infrequently and for short durations. The LRA further states that due to these infrequent and short duration exposures, stress corrosion cracking is not identified as an aging effect requiring management for stainless steel diesel engine exhaust components.
Issue Stress corrosion cracking is a potential aging affect for stainless steel diesel engine exhaust piping, piping components, and piping elements exposed to diesel exhaust as indicated in the GALL Report. While there is an initiation period required for stress corrosion cracking to occur, it will depend on the material and environment. The LRA does provide enough information to rule out stress corrosion cracking of the stainless steel diesel engine exhaust piping, piping components, and piping elements exposed to diesel exhaust.
Request
- 1. Clarify how stress corrosion cracking was quantitatively ruled out by providing additional information on the actual cumulative exposure time that the stainless steel diesel exhaust components are expected to be subjected to diesel exhaust greater than 60°C
[140 OF] during the total period of extended operation.
- 2. Clarify what type of stainless steel is used in the diesel exhaust and provide the technical basis that substantiates the claim that the diesel exhaust piping, piping components, and piping elements are not susceptible to stress corrosion cracking under the cumulative exposure time during the period of extended operation.
- 5 RAI 3.3.2.2.7.3 - 1
Background
The GALL Report, Table 3 item 18 states that loss of material due to general (steel only), pitting, and crevice corrosion could occur for steel and stainless steel diesel engine exhaust piping, piping components, and piping elements exposed to diesel exhaust. The GALL Report further states that these components require a further evaluation of a plant-specific aging management program to ensure that these aging effects are adequately managed.
Issue The LRA Section 3.3.2.2.7.3 states that during normal plant operations, diesel exhaust piping, piping components, and piping elements are exposed to outdoor air and are only exposed to diesel exhaust infrequently and for short durations. The LRA further states that the loss of material will be managed by the Diesel Systems Inspection or the Diesel-Driven Fire Pumps Inspection Programs. It is not clear to the staff how the Diesel System Inspection or the Diesel-Driven Fire Pumps Inspection Programs, which is a one-time inspection program, will appropriately manage this aging effect.
Request Provide additional information on the technical basis for how the Diesel System Inspection and the Diesel-Driven Fire Pumps Inspection Programs will adequately managing loss of material for steel and stainless steel diesel engine exhaust piping, piping components, and piping elements exposed to diesel exhaust. Secondly, provide additional information why a program with a periodic inspection is not being used to manage this aging effect.
RAI 3.3.2.2.7.3 - 2
Background
The GALL Report, Table 3 item 18 states that loss of material due to general (steel only), pitting, and crevice corrosion could occur for steel and stainless steel diesel engine exhaust piping, piping components, and piping elements exposed to diesel exhaust. The GALL Report further states that these components require a further evaluation of a plant-specific aging management program to ensure that these aging effects are adequately managed. The LRA Section 3.3.2.2.7.3 states that during normal plant operations, diesel exhaust piping, piping components, and piping elements are exposed to outdoor air and are only exposed to diesel exhaust infrequently and for short durations. The LRA further states that the loss of material will be managed by the Diesel Systems Inspection or the Diesel-Driven Fire Pumps Inspection Programs, which are one-time inspection programs. The GALL Report states that the One Time Inspection Program is used to verify the effectiveness of an AMP or may also be used to provide additional assurance that aging that has not yet manifested itself is not occurring. The GALL Report states that the One-Time Inspection Program may also be used to provide additional assurance that the evidence of aging shows that the aging is so insignificant that an AMP is not warranted.
Issue That staff noted that the Diesel Systems Inspection or the Diesel-Driven Fire Pumps Inspection Programs (i.e., One-Time Inspection Programs) are not used to verify the effectiveness of an AMP as recommended by GALL Report. The staff further noted these programs to provide
- 6 assurance that aging that has not yet manifested or that the evidence of aging is so insignificant that an AMP is not warranted. However, the applicant has not indicated that corrosion of the diesel exhaust piping, piping components, and piping elements has not previously occurred.
Request Provide additional information on the operating experience of the diesel exhaust piping, piping components, and piping elements indicating if corrosion has been observed in the past. If operating experience does reveal corrosion of the diesel exhaust piping, piping components, and piping elements, provide additional information on why the Diesel Systems Inspection or the Diesel-Driven Fire Pumps Inspection Programs are appropriate to manage the aging of these components.
RAI 3.5.2.1-1
Background
In LRA Table 3.5.2-1, row number 9, the applicant states that stainless steel drywell sump liners exposed to raw water are being managed for loss of material by the Structures Monitoring and BWR Water Chemistry Programs. The AMR line item cites generic note J and plant specific note 0508, which states that, in addition to the Structures Monitoring Program as the applicable AMP, the BWR Water Chemistry Program is also credited with the elimination of excessive chlorides and sulfates from the water. In LRA Section 2.4.1, the applicant also states that it has two drywell sumps; one for unidentified leakage, and one for identified leakage. The applicant further states that the floor drain sump collects unidentified leakage from sources within the drywell, such as valve stem, and control rod drive (CRD) leakage; and the drywell equipment drain sump receives identified reactor coolant leakage from the reactor vessel head flange vent and pump seal leak-off lines.
The staff notes that the applicant's BWR Water Chemistry Program includes monitoring and control of contaminants, such as chlorides and sulfates, in primary and secondary water in accordance with Electrical Power Research Institute water chemistry guidelines. However, the staff also notes that water collected by the drywell sumps include normal leakage which could have been exposed to contaminants in the drywell as it drains from the leak point to the drywell sump. The staff further notes that closed cooling water leakage from the drywell cooling units, which is not monitored by the BWR Water Chemistry Program, could also enter the drywell sumps.
Issue The configuration of the floor drain and drywell equipment drain sumps do not prevent the intrusion of water that was part of the primary water system but has been exposed to contaminants or water from the closed cooling water system that is not monitored by the BWR Water Chemistry Program. It is unclear to the staff how the BWR Water Chemistry Program is being used to reduce chlorides and sulfates in the water being collected by the drywell sumps in order to manage loss of material for the drywell sump liners.
Request Explain how the BWR Water Chemistry Program is being used to manage loss of material for the drywell sump liners.
-7 RAI B.2.43-3
Background
SRP-LR, Appendix A.1.1.2.3.5, states that monitoring and trending activities should be described and should provide predictability of the extent of degradation in order to effect timely corrective or mitigative actions. It also states that the methodology for analyzing inspection results against acceptance criteria should be described.
Issue The Potable Water Monitoring Program's "monitoring and trending" program element provides information on monitoring activities for water quality; however, there is no description of monitoring or trending activities associated with the planned enhancement to the program for periodic inspection activities.
Request Provide information regarding monitoring and trending activities associated with the planned program enhancement for periodic inspection activities, or provide a basis for not monitoring and trending these periodic inspection results.
RAI B.2.43-4
Background
SRP-LR, Appendix A.1.1.2.3.1 0 states that operating experience information, including past corrective actions which result in program enhancements, should be considered. It continues by stating this information can show where an existing program failed to intercept aging degradation in a timely manner, resulting in appropriate program enhancements, and the information should provide objective evidence to support the conclusion that the effects of aging will be managed so that intended function(s) will be maintained.
The Potable Water Monitoring Program's "detection of aging effects" element states that based on operating experience, it is necessary that inspections be conducted at least one every 5 years, and to include components in the potable cold water, potable hot water and reactor building outside air systems. The program's "operating experience" element states that there have been recurrent problems mainly related to PVC piping, which are not in-scope for license renewal and that none of the leakage problems have occurred where they could have affected safety-related equipment due to leakage or spray. However, based on the staff's onsite review of operating experience involving corrosion or indications of corrosion, even though these components may not have been in-scope for license renewal, they are indicative of corrosion occurring in both copper and iron alloys in the potable water system. It was not clear to the staff if the operating experience provides objective evidence to support the conclusion that the effects of aging will be managed adequately by a periodic inspection of the potable water system every 5 years so that intended function(s) will be maintained.
Request Provide additional information on the technical basis for conducting periodic inspections at 5 year intervals; including relevant operating experience for components that have the same
-8 material, environment, and aging affects, consistent with the in-scope components in the potable water system.
September 16,2010 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. 3058)
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, IRA!
Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
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Letter to S.K. Gambhir from E. Gettys dated September 16, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. 3058)
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