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MONTHYEARGO2-15-007, License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 32015-03-17017 March 2015 License Amendment Request for Adoption of Technical Specification Task Force Traveler-425, Revision 3 Project stage: Request ML15126A2142015-05-0606 May 2015 NRR E-mail Capture - Acceptance Review - License Amendment Request for Adoption of Technical Specification Task Force Traveller (TSTF)-425 - TAC No. MF6042 Project stage: Acceptance Review ML15307A8252015-11-0303 November 2015 NRR E-mail Capture - License Amendment Request for Adoption of Technical Specification Task Force (TSTF) - 425, Revision 3, Request for Additional Information Project stage: RAI GO2-16-057, Response to Second Request for Additional Information RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program2016-04-0707 April 2016 Response to Second Request for Additional Information RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program Project stage: Request ML16253A0252016-11-0303 November 2016 Issuance of Amendment No. 238, Adopt Technical Specification Task Force Traveler TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b Project stage: Approval 2015-05-06
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Category:Letter type:GO
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan 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 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 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 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) 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 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 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 GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report 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 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 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 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 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 GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023 Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01 GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022 Guarantee of Payment of Deferred Premium GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022 Status of License Renewal Commitments GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-085, Docket No. 50-397, Evacuation Time Estimate Analysis2022-08-30030 August 2022 Docket No. 50-397, Evacuation Time Estimate Analysis GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-22-072, Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing2022-07-11011 July 2022 Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-22-062, Registration of Spent Fuel Cask Use2022-05-19019 May 2022 Registration of Spent Fuel Cask Use GO2-22-049, Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors2022-05-10010 May 2022 Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors GO2-22-054, Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report2022-05-0909 May 2022 Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report GO2-22-056, Registration of Spent Fuel Cask Use2022-04-21021 April 2022 Registration of Spent Fuel Cask Use GO2-22-055, 2021 Annual Environmental Operating Report2022-04-20020 April 2022 2021 Annual Environmental Operating Report GO2-22-048, 2021 Annual Radioactive Effluent Release Report2022-04-15015 April 2022 2021 Annual Radioactive Effluent Release Report GO2-22-045, Registration of Spent Fuel Cask Use2022-04-0606 April 2022 Registration of Spent Fuel Cask Use GO2-22-044, Level of Financial Protection - Annual Reporting Requirement2022-03-21021 March 2022 Level of Financial Protection - Annual Reporting Requirement GO2-22-038, Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462022-03-0909 March 2022 Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-22-031, Response to Audit Plan and Online Reference Portal Request2022-02-15015 February 2022 Response to Audit Plan and Online Reference Portal Request GO2-22-011, Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report2022-02-0808 February 2022 Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022 License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-012, Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report2022-01-24024 January 2022 Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report 2024-01-08
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARGO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-21-101, Response to Request for Additional Information Related to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35)2021-08-24024 August 2021 Response to Request for Additional Information Related to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) GO2-21-108, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-08-20020 August 2021 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO GO2-21-084, Response to Request for Additional Information Related to On-Site Cooling System Sediment Disposal2021-06-23023 June 2021 Response to Request for Additional Information Related to On-Site Cooling System Sediment Disposal GO2-20-150, Response to Request for Additional Information Related to Request for a 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-192020-12-0303 December 2020 Response to Request for Additional Information Related to Request for a 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 GO2-20-127, Response to Request for Additional Information Related to Fourth Interval Inservice Inspection (ISI) Program Request 4ISI-092020-10-22022 October 2020 Response to Request for Additional Information Related to Fourth Interval Inservice Inspection (ISI) Program Request 4ISI-09 GO2-20-120, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2020-09-0101 September 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating ML20240A3452020-08-27027 August 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-20-118, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2020-08-24024 August 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-20-086, Response to Request for Additional Information Related to Reduction in Commitment to the Columbia Operational Quality Program Description2020-06-0101 June 2020 Response to Request for Additional Information Related to Reduction in Commitment to the Columbia Operational Quality Program Description GO2-20-071, Response to Request for Additional Information Related to Exigent License Amendment Request for One-Time Change to Completion Times for Inoperable Electrical Distribution Systems2020-04-23023 April 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for One-Time Change to Completion Times for Inoperable Electrical Distribution Systems GO2-20-029, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance...2020-02-19019 February 2020 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance... GO2-19-124, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2019-08-20020 August 2019 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-19-111, Response to Request for Additional Information Related to License Amendment Request for Licensing Basis Change to Control Room Air Conditioning System2019-07-30030 July 2019 Response to Request for Additional Information Related to License Amendment Request for Licensing Basis Change to Control Room Air Conditioning System GO2-18-102, Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Re-Renewed Facility Operating License and Technical Specification Clean-Up2018-08-0707 August 2018 Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Re-Renewed Facility Operating License and Technical Specification Clean-Up GO2-18-075, Response to Request for Additional Information for TSTF-542 License Amendment Request2018-06-27027 June 2018 Response to Request for Additional Information for TSTF-542 License Amendment Request ML18191A2052018-06-19019 June 2018 Forwards Response to NRC Comments of July 7, 1977 and February 23, 1978 on Caorso Test Plan GO2-17-186, Response to Request for Additional Information Related to License Amendment Request - Revise Technical Specification 5.5.12 for Permanent Extension of Type a Test and Type C Leak Rate Test Frequencies2018-01-0202 January 2018 Response to Request for Additional Information Related to License Amendment Request - Revise Technical Specification 5.5.12 for Permanent Extension of Type a Test and Type C Leak Rate Test Frequencies GO2-17-204, Energy Northwest Submittal of the Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 Crf 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review ...2017-12-28028 December 2017 Energy Northwest Submittal of the Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 Crf 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review ... GO2-17-175, Response to Request for Additional Information Related to License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System2017-11-20020 November 2017 Response to Request for Additional Information Related to License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System GO2-17-166, Response to Request for Additional Information for Relief Request 3ISI-192017-10-0303 October 2017 Response to Request for Additional Information for Relief Request 3ISI-19 GO2-17-107, Response to Request for Additional Information for Relief Request 3ISI-162017-06-26026 June 2017 Response to Request for Additional Information for Relief Request 3ISI-16 GO2-17-119, Supplement to Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01 Revision 62017-06-21021 June 2017 Supplement to Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01 Revision 6 GO2-17-093, Response to Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutro-Absorbing Materials in Spent Fuel Pools - Licensee-Reported Category 3 Plants2017-05-0202 May 2017 Response to Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutro-Absorbing Materials in Spent Fuel Pools - Licensee-Reported Category 3 Plants ML17066A4932017-03-0707 March 2017 Submittal of Additional Information in Response to Mur LAR: Primary Element Accuracy Calculation GO2-17-048, Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI-99-01 Revision 6 (MF8219)2017-02-23023 February 2017 Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI-99-01 Revision 6 (MF8219) GO2-17-049, Response to Request for Additional Information, Columbia Mur LAR Evib Rais, Enclosure 22017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais, Enclosure 2 GO2-17-014, Response to Request for Additional Information Human Performance2017-01-0909 January 2017 Response to Request for Additional Information Human Performance GO2-16-173, Supplement to Response to Request for Additional Information Related to Columbia LAR: Fire Protection RAI-12016-12-12012 December 2016 Supplement to Response to Request for Additional Information Related to Columbia LAR: Fire Protection RAI-1 GO2-16-161, Response to Request for Additional Information, Columbia Mur LAR: Esgb, Coating and FAC2016-12-0808 December 2016 Response to Request for Additional Information, Columbia Mur LAR: Esgb, Coating and FAC GO2-16-155, Response to Request for Additional Information for License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1, Reactor Core Sls from the Reactor Systems Branch2016-11-17017 November 2016 Response to Request for Additional Information for License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1, Reactor Core Sls from the Reactor Systems Branch GO2-16-153, Response to Request for Additional Information Regarding Mur License Amendment Request Fire Protection2016-11-10010 November 2016 Response to Request for Additional Information Regarding Mur License Amendment Request Fire Protection GO2-16-128, Response to Request for Additional Information Related to Relief Request 4ISI-06 Regarding Code Case N-666-12016-09-20020 September 2016 Response to Request for Additional Information Related to Relief Request 4ISI-06 Regarding Code Case N-666-1 GO2-16-107, Response to Request for Additional Information Related to Relief Request 4ISI-05 Regarding Reactor Pressure Vessel Flange Leak-Off Lines and Code Case N-8052016-08-0303 August 2016 Response to Request for Additional Information Related to Relief Request 4ISI-05 Regarding Reactor Pressure Vessel Flange Leak-Off Lines and Code Case N-805 GO2-16-090, Response to Request for Additional Information for Relief Request 4ISI-022016-07-14014 July 2016 Response to Request for Additional Information for Relief Request 4ISI-02 GO2-16-070, Response to Request for Additional Information Associated with Expedited Seismic Evaluation Process Submittal2016-05-17017 May 2016 Response to Request for Additional Information Associated with Expedited Seismic Evaluation Process Submittal GO2-16-057, Response to Second Request for Additional Information RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program2016-04-0707 April 2016 Response to Second Request for Additional Information RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program GO2-15-173, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 32015-12-28028 December 2015 Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3 GO2-15-152, Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 32015-11-17017 November 2015 Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3 GO2-15-145, Response to Request to Additional Information (RAI) 3 on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 32015-10-29029 October 2015 Response to Request to Additional Information (RAI) 3 on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3 GO2-16-021, R02 15-5462, Revision a, Expedited Seismic Evaluation Process (ESEP) Report2015-10-27027 October 2015 R02 15-5462, Revision a, Expedited Seismic Evaluation Process (ESEP) Report GO2-15-137, Response to the Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations2015-09-24024 September 2015 Response to the Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations GO2-15-128, Response to Request for Additional Information Regarding License Amendment Request for Adopt Technical Specification Task Force (TSTF)-425, Revision 32015-09-17017 September 2015 Response to Request for Additional Information Regarding License Amendment Request for Adopt Technical Specification Task Force (TSTF)-425, Revision 3 ML18191A2031978-06-30030 June 1978 Response to NRC Request for Additional Information (Round 3 Questions) ML18191A2381977-12-16016 December 1977 Advising of Intention to Complete Evaluation Regarding BWR Relief Valve Control System & Associated Containment Loads for Wppss Nuclear Project No. 2 Is Scheduled During 2nd Quarter of 1978 ML18191A8101976-04-28028 April 1976 Wppss Nuclear Project No. 2 Post-Construction Permit Item Drywell/Wetwell Leakage Study ML18191A2741976-01-12012 January 1976 Wppss Nuclear Project No. 2. Clarification of Criteria, Pipe Rupture Protection Inside Containment ML18191A8131975-08-18018 August 1975 Wppss Nuclear Project No. 2 Response to Request for Information Main Steam Isolation Valve Leakage Control System 2022-07-11
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William G. Hettel Vice President, Operations P.O. Box 968, Mail Drop PE23 Richland, WA 99352-0968 Ph. 509-377-8311 F. 509-377-4674 wghettel@energy-northwest.com April 7, 2016 GO2-16-057 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO AN AMENDMENT TO ADOPT TECHNICAL SPECIFICATION TASK FORCE (TSTF)-425, REVISION 3 TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCIES TO A LICENSEE CONTROLLED PROGRAM
References:
- 1. Letter, GO2-15-007, dated March 17, 2015, WG Hettel (Energy Northwest) to NRC, License Amendment Request for Adoption of Technical Specification Task Force Traveler (TSTF)-425, Revision 3
- 2. Email, dated August 12, 2015, Balwant Singal (NRC) to Lisa Williams (Energy Northwest), Request for Additional Information - License Amendment Request for Adoption of TSTF-425, Revision [3],
Columbia Generating Station - TAC No. MF6042
- 3. Letter, GO2-15-128, dated September 17, 2015, RE Schuetz (Energy Northwest) to NRC, Response to Request for Additional Information on License Amendment Request for Adopt Technical Specification Task Force (TSTF)-425, Revision 3
- 4. Letter, GO2-15-145, dated October 29, 2015, RE Schuetz (Energy Northwest to NRC, Response to Request for Additional Information (RAI) 3 on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
G02-16-057 Page 2 of 2
- 5. Email, dated March 9, 2016, John Klos (NRC) to Lisa Williams (Energy Northwest), "Second Request for Additional Information (RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-
425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
Dear Sir or Madam:
By Reference 1, Energy Northwest submitted for approval the License Amendment Request (LAR) to adopt TSTF-425, Revision 3.
Via Reference 2, the Nuclear Regulatory Commission (NRC) submitted Requests for Additional Information (RAls) related to the Energy Northwest's probabilistic risk assessment (PRA) model. Via References 3 and 4, Energy Northwest submitted responses to Reference 2.
In response to Reference 5, Energy Northwest is submitting as Attachment 1, its response to the second RAI on the PRA model.
The No Significant Hazards Consideration determination (NSHCD) provided in the original submittal is not altered by this submittal. This letter and its attachment contain no regulatory commitments.
If there are any questions or if additional information is needed, please contact Ms. L. L.
Williams, Licensing Supervisor, at 509-377-8148.
I declare und~~ of perjury that the foregoing is true and correct. Executed this
~day of , 2016.
Respectfully, W.G. Hettel A~~~ ~
Vice President, Operations Attachments: As stated cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPN1399 (email)
WA Horin - Winston & Strawn RR Cowley-WDOH (email)
EFSECutc.wa.gov-- EFSEC (email)
GO2-16-057 Page 1 of 2 RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION NRC Request PRA RAI 1.1 (Follow up to PRA RAI 1)
In response to PRA RAI 1, the licensee provided the internal events PRA 2009 peer review facts and observations (F&Os), self-assessment findings, and their dispositions.
Please address the following regarding F&O 1-3.
- a. The peer review F&O 1-3 states In almost all of the post-initiator Human Error Probabilities (HEPs) where optimal stress is assumed, time is a factor with core damage occurring between 30 minutes and an hours.
Clarify if these post-initiator HEPs were assumed to be optimal stress in all cases involving this time frame or if such HEPs were determined on a case-by-case basis to represent optimal stress or high stress as appropriate. Please describe your process to make this determination.
- b. The peer review also observed, A second set of justification was provided, with discussion that basically justified moderate or low stress would be appropriate, given enough training for the operators. The peer review recommendation stated: Apply high stress factors per Table 17-1 of NUREG/CR-1278 to HEPs where time pressure is present during an accident situation.
Please clarify if high stress factors were used on a case-by-case basis from this table, and, if not provide justification. Please discuss whether time pressure was used to determine whether an execution operator action justified the application of a high stress factor.
Energy Northwest Response:
As part of the Rev. 7.2 PRA update performed in 2014, the assignments of stress levels were reviewed for all Columbia Generating Station (CGS) post-initiator human failure events, and all post-initiator human failure events now utilize the stress levels recommended by the Human Reliability Analysis (HRA) Calculator. The stress level recommended by the HRA calculator was reviewed by the HRA analyst and in some cases increased to a higher stress level. In this manner, the full intent of F&O 1-3 has been resolved.
By utilizing the HRA Calculator, the stress levels assigned to the CGS HFEs follow the NUREG/CR-1278 guidelines, including addressing the impact to stress levels from time pressure.
NRC Request PRA RAI 4.1 (Follow up to PRA RAI 4)
The NRC staff reviewed the response to PRA RAI 4 and found the response did not address the issue. The peer review observation in the LAR states:
GO2-16-057 Page 2 of 2 Estimates based on the surveillance tests and maintenance acts as described in DA-C6 and DA-C7 should be performed for significant components whose data are not tracked in the MSPI [Mitigating Systems Performance Index] data.
The peer review recommendations states:
Update the estimates for significant events based on surveillance test and maintenance records.
The response to PRA RAI 4 states:
A sensitivity study was performed by replacing the base data for these failure modes with generic data from NUREG/CR-6928. It was determined that the finding is unlikely to change the conclusions of risk-informed decisions.
Supporting requirements (SRs) DA-C6 and DA-C7 are not limited to the MSPI systems.
SR DA-C6 and SR DA-C7 include consideration of plant-specific data, and it is not clear how generic data has been demonstrated to be bounding for the non-MSPI components. That is, if the peer review recommendation were to be performed it is not clear that the generic data would necessarily be bounding.
Please provide justification why the use of generic data for performing sensitivity analyses is bounding without updating applicable component estimates with plant-specific data consistent with SR DA-C6 and SR DA-C7, or compete the work to meet SR DA-C6 and SR DA-C7 for applicable components and provide the disposition of the F&O.
Energy Northwest Response:
Finding F&O 2-2 against SR DA-C6 and SR DA-C7 from the 2009 peer review has been resolved. The disposition of the F&O is as follows:
Estimates for significant events not tracked in the Mitigating Performance System Index (MSPI) data are now based on plant-specific surveillance test and maintenance records.
Resolution of F&O 2-2 impacts the following component failure modes: C---W2 (compressor fails to start), C---W4 (compressor fails to run), FN--R3 (fan fails to start),
FR--W4 (fan fails to run), AHUS---S3 (air handling unit fails to start), AHUR---W4 (air handling unit fails to run).
The resolution to this F&O has been incorporated into a working model. This working model will be used for all Risk informed Technical Specification (RITS) 5B assessments until a model of record revision is released which contains the resolution to this F&O.
William G. Hettel Vice President, Operations P.O. Box 968, Mail Drop PE23 Richland, WA 99352-0968 Ph. 509-377-8311 F. 509-377-4674 wghettel@energy-northwest.com April 7, 2016 GO2-16-057 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO AN AMENDMENT TO ADOPT TECHNICAL SPECIFICATION TASK FORCE (TSTF)-425, REVISION 3 TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCIES TO A LICENSEE CONTROLLED PROGRAM
References:
- 1. Letter, GO2-15-007, dated March 17, 2015, WG Hettel (Energy Northwest) to NRC, License Amendment Request for Adoption of Technical Specification Task Force Traveler (TSTF)-425, Revision 3
- 2. Email, dated August 12, 2015, Balwant Singal (NRC) to Lisa Williams (Energy Northwest), Request for Additional Information - License Amendment Request for Adoption of TSTF-425, Revision [3],
Columbia Generating Station - TAC No. MF6042
- 3. Letter, GO2-15-128, dated September 17, 2015, RE Schuetz (Energy Northwest) to NRC, Response to Request for Additional Information on License Amendment Request for Adopt Technical Specification Task Force (TSTF)-425, Revision 3
- 4. Letter, GO2-15-145, dated October 29, 2015, RE Schuetz (Energy Northwest to NRC, Response to Request for Additional Information (RAI) 3 on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
G02-16-057 Page 2 of 2
- 5. Email, dated March 9, 2016, John Klos (NRC) to Lisa Williams (Energy Northwest), "Second Request for Additional Information (RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-
425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
Dear Sir or Madam:
By Reference 1, Energy Northwest submitted for approval the License Amendment Request (LAR) to adopt TSTF-425, Revision 3.
Via Reference 2, the Nuclear Regulatory Commission (NRC) submitted Requests for Additional Information (RAls) related to the Energy Northwest's probabilistic risk assessment (PRA) model. Via References 3 and 4, Energy Northwest submitted responses to Reference 2.
In response to Reference 5, Energy Northwest is submitting as Attachment 1, its response to the second RAI on the PRA model.
The No Significant Hazards Consideration determination (NSHCD) provided in the original submittal is not altered by this submittal. This letter and its attachment contain no regulatory commitments.
If there are any questions or if additional information is needed, please contact Ms. L. L.
Williams, Licensing Supervisor, at 509-377-8148.
I declare und~~ of perjury that the foregoing is true and correct. Executed this
~day of , 2016.
Respectfully, W.G. Hettel A~~~ ~
Vice President, Operations Attachments: As stated cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPN1399 (email)
WA Horin - Winston & Strawn RR Cowley-WDOH (email)
EFSECutc.wa.gov-- EFSEC (email)
GO2-16-057 Page 1 of 2 RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION NRC Request PRA RAI 1.1 (Follow up to PRA RAI 1)
In response to PRA RAI 1, the licensee provided the internal events PRA 2009 peer review facts and observations (F&Os), self-assessment findings, and their dispositions.
Please address the following regarding F&O 1-3.
- a. The peer review F&O 1-3 states In almost all of the post-initiator Human Error Probabilities (HEPs) where optimal stress is assumed, time is a factor with core damage occurring between 30 minutes and an hours.
Clarify if these post-initiator HEPs were assumed to be optimal stress in all cases involving this time frame or if such HEPs were determined on a case-by-case basis to represent optimal stress or high stress as appropriate. Please describe your process to make this determination.
- b. The peer review also observed, A second set of justification was provided, with discussion that basically justified moderate or low stress would be appropriate, given enough training for the operators. The peer review recommendation stated: Apply high stress factors per Table 17-1 of NUREG/CR-1278 to HEPs where time pressure is present during an accident situation.
Please clarify if high stress factors were used on a case-by-case basis from this table, and, if not provide justification. Please discuss whether time pressure was used to determine whether an execution operator action justified the application of a high stress factor.
Energy Northwest Response:
As part of the Rev. 7.2 PRA update performed in 2014, the assignments of stress levels were reviewed for all Columbia Generating Station (CGS) post-initiator human failure events, and all post-initiator human failure events now utilize the stress levels recommended by the Human Reliability Analysis (HRA) Calculator. The stress level recommended by the HRA calculator was reviewed by the HRA analyst and in some cases increased to a higher stress level. In this manner, the full intent of F&O 1-3 has been resolved.
By utilizing the HRA Calculator, the stress levels assigned to the CGS HFEs follow the NUREG/CR-1278 guidelines, including addressing the impact to stress levels from time pressure.
NRC Request PRA RAI 4.1 (Follow up to PRA RAI 4)
The NRC staff reviewed the response to PRA RAI 4 and found the response did not address the issue. The peer review observation in the LAR states:
GO2-16-057 Page 2 of 2 Estimates based on the surveillance tests and maintenance acts as described in DA-C6 and DA-C7 should be performed for significant components whose data are not tracked in the MSPI [Mitigating Systems Performance Index] data.
The peer review recommendations states:
Update the estimates for significant events based on surveillance test and maintenance records.
The response to PRA RAI 4 states:
A sensitivity study was performed by replacing the base data for these failure modes with generic data from NUREG/CR-6928. It was determined that the finding is unlikely to change the conclusions of risk-informed decisions.
Supporting requirements (SRs) DA-C6 and DA-C7 are not limited to the MSPI systems.
SR DA-C6 and SR DA-C7 include consideration of plant-specific data, and it is not clear how generic data has been demonstrated to be bounding for the non-MSPI components. That is, if the peer review recommendation were to be performed it is not clear that the generic data would necessarily be bounding.
Please provide justification why the use of generic data for performing sensitivity analyses is bounding without updating applicable component estimates with plant-specific data consistent with SR DA-C6 and SR DA-C7, or compete the work to meet SR DA-C6 and SR DA-C7 for applicable components and provide the disposition of the F&O.
Energy Northwest Response:
Finding F&O 2-2 against SR DA-C6 and SR DA-C7 from the 2009 peer review has been resolved. The disposition of the F&O is as follows:
Estimates for significant events not tracked in the Mitigating Performance System Index (MSPI) data are now based on plant-specific surveillance test and maintenance records.
Resolution of F&O 2-2 impacts the following component failure modes: C---W2 (compressor fails to start), C---W4 (compressor fails to run), FN--R3 (fan fails to start),
FR--W4 (fan fails to run), AHUS---S3 (air handling unit fails to start), AHUR---W4 (air handling unit fails to run).
The resolution to this F&O has been incorporated into a working model. This working model will be used for all Risk informed Technical Specification (RITS) 5B assessments until a model of record revision is released which contains the resolution to this F&O.