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MONTHYEARML21179A0052021-06-25025 June 2021 NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69 Project stage: Acceptance Review 1CAN072102, Inservice Inspection Summary Report for the Twenty-Ninth Refueling Outage (1R29)2021-07-19019 July 2021 Inservice Inspection Summary Report for the Twenty-Ninth Refueling Outage (1R29) Project stage: Request ML21200A0472021-07-19019 July 2021 Audit Plan and Setup of Online Reference Portal for LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (EPID L-2021-LLA-0105,-0106) Project stage: Approval 2CAN102101, Cycle 29 Core Operating Limits Report (COLR)2021-10-15015 October 2021 Cycle 29 Core Operating Limits Report (COLR) Project stage: Request ML21281A2542021-10-15015 October 2021 Audit Meeting Agenda & Audit Questions for LAR to Adopt 10 CFR 50.69,Risk-Informed Categorization and Treatment of Structures, System, and Components for Nuclear Power Reactors (EPIDs L-2021-LLA-0105, L-2021-LLA-0106 Project stage: Meeting ML22011A1462022-01-24024 January 2022 Audit Summary for LARs to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Approval 0CAN032201, Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2022-03-0909 March 2022 Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Request ML22124A2452022-05-0404 May 2022 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI 2 License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) Project stage: RAI 0CAN052203, Response to the Second Round of Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2022-05-18018 May 2022 Response to the Second Round of Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Request ML22165A2442022-07-19019 July 2022 Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Approval ML22236A5452022-08-26026 August 2022 Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Approval 2022-03-09
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Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEAR2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN052203, Response to the Second Round of Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2022-05-18018 May 2022 Response to the Second Round of Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 0CAN032201, Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2022-03-0909 March 2022 Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 0CAN022201, Response to the Second Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping2022-02-17017 February 2022 Response to the Second Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping 2CAN112104, Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)2021-11-12012 November 2021 Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP) 2CAN112105, Response to Request for Additional Information Concerning Relief Request ANO2-RR-21-002 Support the Repair of the Reactor Vessel Closure Head Penetration 462021-11-0707 November 2021 Response to Request for Additional Information Concerning Relief Request ANO2-RR-21-002 Support the Repair of the Reactor Vessel Closure Head Penetration 46 2CAN102103, Response to Request for Additional Information Concerning Relief Request ANO2-R&R-012 Support the Repair of the Reactor Vessel Closure Head Penetration 462021-10-12012 October 2021 Response to Request for Additional Information Concerning Relief Request ANO2-R&R-012 Support the Repair of the Reactor Vessel Closure Head Penetration 46 0CAN102101, Final Request for Additional Information Concerning Generic Letter 2004-022021-10-0404 October 2021 Final Request for Additional Information Concerning Generic Letter 2004-02 0CAN092102, Response to Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping2021-09-23023 September 2021 Response to Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping 0CAN092101, Unit 2 - Revised Proprietary Demarcation in Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-09-14014 September 2021 Unit 2 - Revised Proprietary Demarcation in Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping 0CAN072102, Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-07-22022 July 2021 Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping 2CAN052103, Response to Request for Additional Information Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)2021-05-24024 May 2021 Response to Request for Additional Information Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP) 0CAN042101, Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description2021-04-0505 April 2021 Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description 0CAN022101, Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-02-22022 February 2021 Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping ML21063A2442021-02-22022 February 2021 Enclosure 4 - Response to Request for Additional Information Related to Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping in Accordance with 10 CFR 50.55a(z)(1) (Non-Proprietary) CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L 1CAN122001, Responses to Request for Additional Information for the Request for Relief Related to American Society of Mechanical Engineers(Asme) Code Case N-770-5 Supplemental Examination Requirements - ANO1-ISI-0342020-12-10010 December 2020 Responses to Request for Additional Information for the Request for Relief Related to American Society of Mechanical Engineers(Asme) Code Case N-770-5 Supplemental Examination Requirements - ANO1-ISI-034 0CAN112001, Relief Request No. EN-20-RR-001, Revision 1 - Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in Class 2 and 3 Systems, Section XI, Div 12020-11-17017 November 2020 Relief Request No. EN-20-RR-001, Revision 1 - Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in Class 2 and 3 Systems, Section XI, Div 1 1CAN102002, Additional Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values2020-10-0505 October 2020 Additional Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values 2CAN092002, Response to Second Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations2020-09-22022 September 2020 Response to Second Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations ML20255A1182020-09-0101 September 2020 Enclosuresponse to Request for Additional Information Related to Exemption Request from Certain EP Requirements of 10 CFR 50 Appendix E ML20076C4152020-03-11011 March 2020 Response to Request for Additional Information Related to License Amendment Request to Revise the Control Element Assembly Drop Times 0CAN022001, Response to Request for Additional Information Related to License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis2020-02-19019 February 2020 Response to Request for Additional Information Related to License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis 2CAN022001, Response to Request for Additional Information Related to Alternative VRR-ANO2-2019-12020-02-11011 February 2020 Response to Request for Additional Information Related to Alternative VRR-ANO2-2019-1 CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary ML19322A7672019-11-14014 November 2019 Response to Request for Additional Information Related to License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis 1CAN111901, Response to Request for Additional Information Related to Request for Relief from American Society of Mechanical Engineers (ASME) Code Case N-729-4 Supplemental Examination Requirements ANO1-ISI-0332019-11-0707 November 2019 Response to Request for Additional Information Related to Request for Relief from American Society of Mechanical Engineers (ASME) Code Case N-729-4 Supplemental Examination Requirements ANO1-ISI-033 2CAN041904, Response to Request for Additional Information Related to the Application to Technical Specification Actions to Address Inoperability of the Containment Building Sump2019-04-30030 April 2019 Response to Request for Additional Information Related to the Application to Technical Specification Actions to Address Inoperability of the Containment Building Sump 1CAN021903, Response to Request for Additional Information Related to Relief Request ANO1-ISI-0322019-02-28028 February 2019 Response to Request for Additional Information Related to Relief Request ANO1-ISI-032 1CAN101801, Response to Request for Additional Information Related to the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ...2018-10-17017 October 2018 Response to Request for Additional Information Related to the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ... 2CAN101801, Responses to the Request for Additional Information Regarding License Amendment Request to Update the Reactor Coolant System Pressure-Temperature Limits2018-10-10010 October 2018 Responses to the Request for Additional Information Regarding License Amendment Request to Update the Reactor Coolant System Pressure-Temperature Limits 0CAN091801, Response to Request for Additional Information Related to the Application for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62018-09-17017 September 2018 Response to Request for Additional Information Related to the Application for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 1CAN081806, Response to Request for Additional Information (RAI) Regarding Relief Request ANO1-ISI-0312018-08-22022 August 2018 Response to Request for Additional Information (RAI) Regarding Relief Request ANO1-ISI-031 1CAN081801, Response to Request for Additional Information Related to License Amendment Request - Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves2018-08-10010 August 2018 Response to Request for Additional Information Related to License Amendment Request - Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves 2CAN081802, Responses to the Request for Additional Information Regarding License Amendment Request to Update the Reactor Coolant System Pressure-Temperature Limits2018-08-0101 August 2018 Responses to the Request for Additional Information Regarding License Amendment Request to Update the Reactor Coolant System Pressure-Temperature Limits ML18163A4182018-07-11011 July 2018 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident ML18215A1782018-06-30030 June 2018 WCAP-18169-NP, Rev 1, Arkansas Nuclear One Unit 2 Heatup and Cooldown Limit Curves for Normal Operation. 1CAN041803, License Amendment Request: Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves2018-04-26026 April 2018 License Amendment Request: Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves 1CAN041805, Supplemental Information Supporting the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee ...2018-04-26026 April 2018 Supplemental Information Supporting the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee ... 2CAN031803, Supplemental Information Supporting the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled ...2018-03-26026 March 2018 Supplemental Information Supporting the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled ... 2CAN031802, Response to Request for Additional Information - Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2018-03-13013 March 2018 Response to Request for Additional Information - Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 2CAN091701, Response to Request for Additional Information Reactor Vessel Internals Aging Management Program Plan2017-09-0606 September 2017 Response to Request for Additional Information Reactor Vessel Internals Aging Management Program Plan 0CAN121601, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2016-12-20020 December 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... 2CAN121601, Response to Request for Additional Information License Amendment Request for Adoption of TSTF-545, TS Inservice Testing Program & Clarify SR Usage Rule Application to Section 5.5.2016-12-0707 December 2016 Response to Request for Additional Information License Amendment Request for Adoption of TSTF-545, TS Inservice Testing Program & Clarify SR Usage Rule Application to Section 5.5. 2024-01-11
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Phil Couture Senior Manager Fleet Regulatory Assurance Tel 601-368-5102 0CAN052203 10 CFR 50.90 10 CFR 50.69 May 18, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Response to the Second Round of Request for Additional Information Application to Adopt 10 CFR 50.69, "Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors" Arkansas Nuclear One, Units 1 and 2 NRC Docket Nos. 50-313 and 50-368 Renewed Facility Operating License Nos. DPR-51 and NPF-6 By References 1 and 2, Entergy Operations, Inc., (Entergy) requested that the U.S. Nuclear Regulatory Commission (NRC) modify the Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2) licensing basis to allow for the implementation of the provisions of 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors."
The NRC staff reviewed the application and determined that additional information was required (Reference 3). Entergy responded to the request via Reference 4.
The NRC staff has reviewed the Entergy submittals application and determined that additional information was required (Reference 5) to complete its review of the application.
The Requests for Additional Information (RAIs) and the associated responses are provided in the Enclosure.
The responses to the RAIs do not affect the no significant hazards consideration provided in References 1 and 2.
There are new regulatory commitments established in this submittal. The new commitments are summarized in the attachment to the enclosure.
Entergy Operations, Inc., 1340 Echelon Parkway, Jackson, MS 39213
0CAN052203 Page 2 of 3 If there are any questions or if additional information is needed, please contact Riley Keele, Manager, Regulatory Assurance, Arkansas Nuclear One, at 479-858-7826.
I declare under penalty of perjury; that the foregoing is true and correct.
Executed on May 18, 2022.
Respectfully, Digitally signed by Philip Philip Couture Couture Date: 2022.05.18 08:14:56
-05'00' Phil Couture PC/rwc
Enclosure:
Response to Request for Additional Information Attachment to Enclosure Commitments
References:
- 1. Entergy Operations, Inc. (Entergy) letter to the U. S. Nuclear Regulatory Commission (NRC), "Application to Adopt 10 CFR 50.69, 'Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors'", (1CAN052102) (ADAMS Accession No. ML21147A234), dated May 26, 2021
- 2. Entergy letter to the NRC, "Application to Adopt 10 CFR 50.69,
'Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors'", (2CAN052102) (ADAMS Accession No. ML21147A264), dated May 26, 2021
- 3. NRC email to Riley Keele (Entergy), "Final RAI RE: License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-
0106)", (0CNA022201), (ADAMS Accession No. ML22034A548), dated February 3, 2022
- 4. Entergy letter to the NRC, "Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, 'Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors'", (0CAN032201) (ADAMS Accession No. ML22068A170), dated March 9, 2022
0CAN052203 Page 3 of 3
- 5. NRC email to Riley Keele (Entergy), "ANO-1 and ANO Final RAI #2 RE:
License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106)," (0CNA052201), dated May 4, 2022 cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Arkansas Nuclear One NRC Project Manager - Arkansas Nuclear One Designated Arkansas State Official
ENCLOSURE 0CAN052203 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
0CAN052203 Enclosure Page 1 of 6 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION By References 1 and 2, Entergy Operations, Inc., (Entergy) requested that the U.S. Nuclear Regulatory Commission (NRC) modify the Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2) licensing basis to allow for the implementation of the provisions of 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors."
The NRC staff reviewed the application and determined that additional information was required (Reference 3). Entergy responded to the request via Reference 4.
The NRC staff has reviewed the Entergy submittals application and determined that additional information was required (Reference 5) to complete its review of the application.
Below are the Requests for Additional Information (RAIs) and the associated responses for ANO-1 and ANO-2.
RAI 02.a(4).01 - FLEX as Key Source of Uncertainty The licensees responses to RAIs 02.a(4) and 02.b(4) (fire probabilistic risk assessment (FPRA) and full power internal events (FPIE) respectively) dated March 9, 2022, state that the uncertainties related to Diverse and Flexible Mitigation Capability (FLEX) modeling have no adverse impact to the risk insights in the ANO-2 categorization process. However, the sensitivity results based on the plant-specific risk analysis demonstrate that there are SSC categorizations that are impacted by this uncertainty. Specifically, as shown in the table on page 25 of Attachment 2 of the RAI response, the categorizations of two internal events SSCs were changed from low safety significance (LSS) to high safety significance (HSS), and the categorizations of eight internal events SSCs were changed from HSS to LSS. Similarly, as shown in the table on page 11 of Attachment 2 of the RAI response, the categorizations of six fire SSCs were changed from HSS to LSS and the categorizations of two fire SSCs were changed from LSS to HSS. Section 2.1.3 of NUREG-1855, Revision 1, states that a key source of uncertainty can be identified by quantitative analysis associated with alternative modeling methods and could impact the acceptance criteria for the application.
It is unclear to the NRC staff the licensees basis for determining that the FLEX uncertainty is not a key source of uncertainty to be presented to the Integrated Decisionmaking Panel (IDP).
a) Separately for internal events and fire PRA, provide a list of the SSCs that were recategorized in the sensitivity studies.
0CAN052203 Enclosure Page 2 of 6 Entergys Response On page 25 of Enclosure 2 of Reference 4, the eight SSCs that went from HSS to LSS using the internal events and internal flooding model are:
Component Description MAIN STEAM (MS) HEADER NO 1 DUMP TO ATMOSPHERE 2CV-0301 VALVE 2CV-0302 MS HEADER NO 1 DUMP TO CONDENSER 2E11A VALVE 2CV-0303 MS HEADER NO 1 BYPASS TO CONDENSER 2E-11B 2CV-0305 MS HEADER NO 2 DUMP TO ATMOSPHERE VALVE 2CV-0306 MS HEADER NO 2 DUMP TO 2E-11B VALVE 2SI-12 HIGH PRESSURE SAFETY INJECTION HEADER CHECK VALVE 2VUC-1D SHUTDOWN COOLING HEAT EXCHANGER (HX) ROOM COOLER 2VUC-1E SHUTDOWN COOLING HX ROOM COOLER On page 25 of Enclosure 2 of Reference 4, the two internal events SSCs that went from LSS to HSS are:
Component Description 2D-2304 4160V SWITCHGEAR 2A3 - DC POWER CIRCUIT BREAKER 2D-2404 4160V SWITCHGEAR 2A4 - DC POWER CIRCUIT BREAKER On page 11 of Enclosure 2 of Reference 4, the six fire PRA SSCs that went from HSS to LSS are:
Component Description UNIT 2 STEAM GENERATOR (SG) A INJECTION VALVE MOTOR 2CV-1070A OPERATED VALVE (MOV) 2CV-1070B UNIT 2 SG B INJECTION VALVE MOV VUC-51 START-UP BOILER CONTROL ROOM AIR HANDLER VUC-52 START-UP BOILER CONTROL ROOM AIR HANDLER VUC-53 START-UP BOILER ELECTRONICS ROOM AIR HANDLER VUC-54 START-UP BOILER ELECTRONICS ROOM AIR HANDLER
0CAN052203 Enclosure Page 3 of 6 On page 11 of Enclosure 2 of Reference 4, the two fire PRA SSCs that went from LSS to HSS are:
Component Description 2A-1001 4160 CIRCUIT BREAKER 2A10 SWITCHGEAR ALTERNATE AC GENERATOR FUEL OIL TRANSFER PUMP 2P-235 MOTOR b) Provide justification, based on the results of the sensitivity studies, that the uncertainty related to FLEX is not a key source of uncertainty for the categorization program.
Entergys Response See response to item c) below.
c) As an alternative to Part (b), propose a mechanism to present the results of the FLEX uncertainty for both internal events and fire PRA SSCs to the IDP for their consideration.
Entergys Response The identification of key sources of model uncertainties and related assumptions for the application will be followed based on Section 2.1.3 of NUREG 1855 Revision 1 (Reference 6). Given that currently the FLEX failure rate data is a key source of uncertainty for this application, a FLEX sensitivity will be performed for both the internal events and fire PRA SSCs, using the 5th and 95th percentile for the ANO FLEX equipment failure rates listed in Reference 7, will be provided to the ANO 10 CFR 50.69 IDP for their consideration during the categorization process.
RAI 02.a(5).01 - Use of Safety-Related Failure Rates for the Portable FLEX Diesel Generator in the Fire PRA In its response to RAI 02.a(2), the licensee states that the failure rates for the portable FLEX diesel generator (DG), which is a non-safety related SSC, were estimated using the failure rates for station emergency diesel generators (EDGs), which are safety related SSCs. The licensee further states that only one FLEX DG train is credited to account for some of the uncertainty of the data. Similarly, for ANO-1, the licensee states that only one FLEX feed pump is modeled for each portable equipment function in the model to bound the risk estimate that would otherwise require additional model complexity and introduce additional uncertainties.
It is unclear to the NRC staff if this approach is bounding for these non-safety related SSCs. In its response to RAI 02.a(5I), the licensee further states that the FLEX DG failure rate of 3.0E-02 is comparable to the 2015 supplement to the industry data failure rate of 3.1E-02 cited in NUREG/CR-6928, "Industry Average Performance for Components and Initiating Events at U.S.
Commercial Nuclear Power Plants" for non-safety related station blackout (SBO) DGs. The NRC staff notes that there are three failure modes available for the EDG (i.e., fail-to-start, fail-to-
0CAN052203 Enclosure Page 4 of 6 load and run early, and fail-to-run late), whereas there are two failure modes for SBO DGs (i.e.,
fail-to-start and fail-to-run). It is unclear to the NRC staff which failure modes the licensees response is addressing. Finally, the licensees response to RAI 02.a(5II) states that the model update process will implement the latest industry guidance associated with the FLEX failure rates during the next model update. Based on discussions held during the regulatory audit, it is not clear to the NRC staff that the fire portion of the newly updated PRA will be updated prior to implementation of categorization.
a) Provide the specific failure modes and respective failure rates used in the ANO-2 model for the FLEX portable DG.
Entergys Response The specific failure modes and respective failure rates used in the ANO-2 fire PRA model for the FLEX portable DG are provided in the following table.
Failure Mode Failure Rate DG Fails to Load and Run During First Hour of Operation 3.9E-03 DG Fails to Run After First Hour of Operation 2.3E-02 DG Fails to Start 3.0E-03 b) Provide justification that the DG failure rates provided in the Part (a) response are conservative for a non-safety related DG. Include in this discussion:
- 1) How crediting only one train of the FLEX portable DGs, and the resulting 3.0E-02 failure probability, is bounding for a non-safety related DG.
Entergys Response See response to item c) below.
- 2) How crediting only one component (pump) for ANO-1 for each portable equipment function bounds the risk estimate.
Entergys Response See the response to item c) below.
c) As an alternative to Part (b), propose a non-safety related DG failure rate.
Entergys Response ANO-2 proposes the FLEX equipment failure modes and their associated failure rates specified in Table 6-1 of Reference 7 for PRA credited FLEX equipment to be used in
0CAN052203 Enclosure Page 5 of 6 the Fire PRA, specifically the failure modes and failure rates in response to item a) for the FLEX DG.
To ensure item b.2 above is adequately answered, the phrase "bounds the risk estimate" in Reference 4 was specifically in reference to the omission of modeling of common cause failures using data failure rates available at the time of the last model update. The response on page 6 of Reference 4 is replaced by the following:
To simplify the modeling and address the data uncertainties, only one component (pump) is modeled for each portable equipment function in the model. This is recognized as potentially slightly conservative but bounds the risk estimates associated with common cause failures based on the available failure rates of the last model update that would otherwise require additional model complexity and introduce additional uncertainties. Additionally, the modeling of a single pump (one out of four functionally equivalent pumps) also provides a level of conservative mitigation in addressing the uncertainty of the failure rates for the FLEX portable equipment in the current PRA models.
Similar verbiage was used in Reference 4 for ANO-2 Internal Events and ANO-2 Fire PRA. Similarly, in both cases, the language was intended to communicate that the modeling of a single train of functionally equivalent components provides an approach to conservatively account for uncertainties associated with common cause using the failure rates at the time the model was updated, while providing a level of mitigation in addressing the uncertainty of the failure rates for the FLEX portable equipment in the current PRA models.
d) If the licensee determines that it is necessary to incorporate updated failure rates into the fire PRA models to be used in the categorization program, propose the mechanism by which the failure rates will be incorporated, and confirm that they will be incorporated before the implementation of categorization.
Entergys Response Following the ANO PRA update and maintenance procedures, the ANO-2 Fire PRA will be updated to revise the model failure rates listed in response to item a) above to incorporate the failure rates specified in Table 6-1 of Reference 7 for the portable DG failure rates (Fails to Start and Fails to Run) for the ANO FLEX DG prior to performing any categorization under the ANO 10 CFR 50.69 program.
0CAN052203 Enclosure Page 6 of 6 REFERENCES
- 1. Entergy Operations, Inc. (Entergy) letter to the U. S. Nuclear Regulatory Commission (NRC), "Application to Adopt 10 CFR 50.69, 'Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors'", (1CAN052102)
(ADAMS Accession No. ML21147A234), dated May 26, 2021
- 2. Entergy letter to the NRC, "Application to Adopt 10 CFR 50.69, 'Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors'", (2CAN052102) (ADAMS Accession No. ML21147A264), dated May 26, 2021
- 3. NRC email to Riley Keele (Entergy), "Final RAI RE: License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106)," (0CNA022201), (ADAMS Accession No. ML22034A548), dated February 3, 2022
- 4. Entergy letter to the NRC, "Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, 'Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors'", (0CAN032202) (ADAMS Accession No. ML22068A170), dated March 9, 2022
- 5. NRC email to Riley Keele (Entergy), "ANO-1 and ANO Final RAI #2 RE: License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106),"
(0CNA052201), dated May 4, 2022
- 6. NUREG-1855, "Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decisionmaking", Revision 1, (ADAMS Accession No. ML17062A466),
Published March 2017
- 7. PWROG-18042-P, "FLEX Equipment Data Collection and Analysis", Revision 1
ENCLOSURE, ATTACHMENT 0CAN052203 COMMITMENTS
Enclosure, Attachment to 0CAN052203 Page 1 of 1 This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRCs information and are not commitments.
TYPE (Check one) SCHEDULED COMMITMENT COMPLETION DATE ONE-TIME CONTINUING (If Required)
ACTION COMPLIANCE The identification of key sources of model uncertainties and related assumptions for the application will be followed based on Section 2.1.3 of NUREG 1855 Revision 1 (Reference 6).
Given that currently the FLEX failure rate data is a key source of uncertainty Prior to for this application, a FLEX sensitivity X categorization will be performed for both the internal events and fire PRA SSCs, using the 5th and 95th percentile for the failure rates listed in Reference 7 will be provided to the ANO 10 CFR 50.69 IDP for their consideration during the categorization process.
Following the ANO PRA update and maintenance procedures, the ANO-2 Fire PRA will be updated to revise the model failure rates listed in response to RAI 02.a(5).01, item a), to incorporate Prior to the failure rates specified in Table 6-1 of X categorization Reference 7 for the portable DG failure rates (Fails to Start and Fails to Run) for the ANO FLEX DG prior to performing any categorization under the ANO 10 CFR 50.69 program.