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MONTHYEARML16133A1132016-05-12012 May 2016 NRR E-mail Capture - Acceptance Review: Arkansas Nuclear One Unit 1, License Amendment Request to Adopt TSTF-545 Project stage: Acceptance Review ML16165A4232017-03-10010 March 2017 Issuance of Amendment No. 257 Adoption of Technical Specifications Task Force Traveler TSTF-545, Revision 3, Project stage: Approval 1CAN031801, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-03-12012 March 2018 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) Project stage: Request ML18108A2952018-04-19019 April 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Adoption of Technical Specification Task Force (TSTF)-424, Revision 3 Project stage: Acceptance Review 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 ... Project stage: Supplement ML18124A0682018-05-15015 May 2018 Acceptance of Requested Licensing Action License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425, Revision 3 Project stage: Acceptance Review ML18263A3022018-09-19019 September 2018 NRR E-mail Capture - ANO-1 - Final RAI License Amendment Request to Adopt TSTF-425, Revision 3 Project stage: RAI 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 ... Project stage: Response to RAI 1CAN121802, Supplement to the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-12-11011 December 2018 Supplement to the Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) Project stage: Supplement ML19098A9552019-05-22022 May 2019 Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 Project stage: Approval ML19232A3792019-09-19019 September 2019 Correction to Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 Project stage: Approval 2018-04-19
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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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Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Richard L. Anderson ANO Site Vice President 10 CFR 50.90 1CAN041805 April 26, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
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 Program (TSTF-425)
Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCES:
- 1. Entergy Letter dated March 12, 2018, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425), Arkansas Nuclear One, Unit 1 (1CAN031801) (ML18071A319)
- 2. NRC Letter dated April 19, 2018, Arkansas Nuclear One, Unit 1 -
Supplemental Information Needed for Acceptance of Requested Licensing Action re: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 (EPID L-2018-LLA-0063)
(1CNA041803) (ML18108A295)
Dear Sir or Madam:
In accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR Part 50.90), Application for Amendment of License, Construction Permit, or Early Site Permit, Entergy Operations, Inc. (Entergy) submitted a request for an amendment (Reference 1) to the technical specifications (TSs) for Arkansas Nuclear One, Unit 1 (ANO-1).
The proposed amendment would modify ANO-1 TSs by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute 04-10, Risk-Informed Technical Specification Initiative 5B, Risk-Informed Method for Control of Surveillance Frequencies.
1CAN041805 Page 2 of 5 By letter dated April 19, 2018 (Reference 2), the NRC informed Entergy that additional information was needed to support completion of the Staffs acceptance review of the Reference 1 license amendment request (LAR). The Reference 2 letter stipulated that the supplemental information would be required to be submitted no later than May 9, 2018. The following states the specific information requested by the NRC. The corresponding Entergy response immediately follows each bullet listed.
NRC Request:
In Attachment 2, page 37 of 102 of the LAR, the licensee states that the large early release frequency (LERF) model was not considered in the internal flooding PRA, and the LAR does not present the results of its peer review. Consistent with Regulatory Position 4.2 of Regulatory Guide (RG) 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities (ADAMS Accession No. ML090410014) and Regulatory Issue Summary 2007-06, "Regulatory Guide 1.200 Implementation" (ADAMS Accession No. ML070650428), please provide the necessary documentation to demonstrate the technical adequacy of the licensee's PRA with respect to RG 1.200, Revision 2, as addressed below.
- 1. Provide a description of the LERF analysis that was considered in the 2016 Internal Flooding PRA and describe the adjustments made to the internal events LERF model to develop the internal flooding LERF model.
Entergy Response:
The internal flooding probabilistic risk assessment (PRA) model is built on the internal events PRA model for both core damage frequency (CDF) and LERF. The internal flooding LERF analysis is simply an expansion of the internal events LERF analysis. Flood-induced failures, which are detailed in the internal flooding PRA Accident Sequence Analysis Report, are entered in a database. This database is constructed for use with the Electric Power Research Institute (EPRI) FRANX software. The FRANX database and software are used to add failure logic for flood-induced equipment failures and human failure events into the PRA CAFTA model. The FRANX database links the flood-induced equipment failures and changes to human failure events with basic events in the internal events PRA model in order to quantify internal flooding risk. The same FRANX database is used for both CDF and LERF, thereby ensuring consistent treatment and inclusion of flood-induced failures regardless of the consequence being evaluated.
The internal flooding PRA LERF quantification uses the internal events PRA LERF model.
Other than inserting the flood-induced failures using the FRANX software, no other adjustments are made to the internal events LERF model.
After inserting the flood-induced failures into the CAFTA logic models, the EPRI PRAQUANT software is used to quantify overall risk. The only differences between the internal flooding CDF quantification and the internal flooding LERF quantification are the selection of the top gate and the truncation value. That is, the overall process for quantification for each consequence (CDF or LERF) within the internal flooding PRA is the same.
The internal flooding model upgrade that was developed in 2016 underwent a focused-scope peer review in early 2017. Facts and observations (F&Os) which resulted from that review are currently being addressed, and associated model updates and documentation to address
1CAN041805 Page 3 of 5 the F&Os are nearly complete. The updated internal flooding model that addressed the F&Os used Revision 5p0 of the internal events model. The new internal flooding PRA model updated the logic to include the common feedwater system which is being installed in the current refueling outage, 1R27, for ANO-1 as well as to include LERF. These tasks were performed at the end of 2017.
The updated ANO-1 internal flooding model currently is undergoing technical review and owners acceptance. As mentioned above, changes to the internal flooding model to address F&Os from the 2017, PRA focused-scope peer review are nearly complete. These changes included adding LERF to the internal flooding PRA model. Current plans are to complete the technical review of the internal flooding update after the ANO-2 internal flooding model is completed during the summer of 2018, if not before. As a result, internal flooding LERF could be quantified, if necessary, using the recently-updated internal flooding PRA model.
As described above, the internal flooding update involves use of the FRANX software to insert the flood-induced failures into the internal events PRA models and then performing the quantification. As a result, the same PRA models that would be used for internal events PRA quantification of both CDF and LERF would also be used for the internal flooding quantification. The focused-scope peer review identified no significant errors for the internal flooding accident sequences, modeling, or quantification process. Therefore, no changes in the accident sequences considered by the internal flooding PRA are expected.
NRC Request:
- 2. Provide details of all changes that have been made to the LERF model since it was developed, justifying that no changes constitute a PRA upgrade as defined in the ASME/ANS PRA standard.
Entergy Response:
The internal events LERF model and quantification were subjected to a peer review as part of the overall internal events PRA peer review performed in August 2009. That review used Revision 4p0 of the ANO-1 internal events PRA model. Significant findings from that peer review were resolved in Revision 5p0 of the internal events PRA model as described in the Reference 1 submittal. No other changes to the LERF model were made. As described in the Reference 1 submittal, the changes made in the Revision 5p0 update did not constitute a PRA upgrade.
As discussed above, the internal flooding PRA model uses the internal events model as the basis. There have been no changes in the processes used to quantify the internal events LERF model or to insert flood-induced failures into the PRA logic models since completion of the PRA peer reviews. As stated in Section 1-A.2 of the ASME PRA standard:
However, it is not, for example, a PRA upgrade if an error or omission is addressed by using the existing methodology, and the change does not result in a significant change in risk-estimation capability. It is expected that such changes would generally be classified as PRA maintenance because, in most cases, the method of correction would be similar to that used for typical PRA maintenance where some new plant feature or change in operation is incorporated using the existing model structure and methods.
1CAN041805 Page 4 of 5 Because the internal flooding LERF uses the same methods and models as the peer-reviewed internal events PRA model, the internal flooding LERF model is not considered a PRA upgrade.
NRC Request:
- 3. If any changes do constitute an upgrade, provide the results of a focused-scope peer review complete with F&Os and dispositions, and address any effects on the application.
Entergy Response:
As discussed above, no changes that would constitute a PRA upgrade were made.
Entergy believes the preceding information effectively addresses the supplemental information requested, and should fully support final acceptance of the referenced application.
There are no new regulatory commitments included in this submittal.
In accordance with 10 CFR 50.91, Notice for Public Comment; State Consultation, a copy of this application, with attachments, is being provided to the designated Arkansas State Official.
If there are any questions or if additional information is needed, please contact Stephenie Pyle at 479-858-4704.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April 26, 2018.
Sincerely, ORIGINAL SIGNED BY RICHARD L. ANDERSON RLA/dbb
1CAN041805 Page 5 of 5 cc: Mr. Kriss M. Kennedy Regional Administrator U. S. Nuclear Regulatory Commission RGN-IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-08B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Richard L. Anderson ANO Site Vice President 10 CFR 50.90 1CAN041805 April 26, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
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 Program (TSTF-425)
Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCES:
- 1. Entergy Letter dated March 12, 2018, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425), Arkansas Nuclear One, Unit 1 (1CAN031801) (ML18071A319)
- 2. NRC Letter dated April 19, 2018, Arkansas Nuclear One, Unit 1 -
Supplemental Information Needed for Acceptance of Requested Licensing Action re: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3 (EPID L-2018-LLA-0063)
(1CNA041803) (ML18108A295)
Dear Sir or Madam:
In accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR Part 50.90), Application for Amendment of License, Construction Permit, or Early Site Permit, Entergy Operations, Inc. (Entergy) submitted a request for an amendment (Reference 1) to the technical specifications (TSs) for Arkansas Nuclear One, Unit 1 (ANO-1).
The proposed amendment would modify ANO-1 TSs by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute 04-10, Risk-Informed Technical Specification Initiative 5B, Risk-Informed Method for Control of Surveillance Frequencies.
1CAN041805 Page 2 of 5 By letter dated April 19, 2018 (Reference 2), the NRC informed Entergy that additional information was needed to support completion of the Staffs acceptance review of the Reference 1 license amendment request (LAR). The Reference 2 letter stipulated that the supplemental information would be required to be submitted no later than May 9, 2018. The following states the specific information requested by the NRC. The corresponding Entergy response immediately follows each bullet listed.
NRC Request:
In Attachment 2, page 37 of 102 of the LAR, the licensee states that the large early release frequency (LERF) model was not considered in the internal flooding PRA, and the LAR does not present the results of its peer review. Consistent with Regulatory Position 4.2 of Regulatory Guide (RG) 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities (ADAMS Accession No. ML090410014) and Regulatory Issue Summary 2007-06, "Regulatory Guide 1.200 Implementation" (ADAMS Accession No. ML070650428), please provide the necessary documentation to demonstrate the technical adequacy of the licensee's PRA with respect to RG 1.200, Revision 2, as addressed below.
- 1. Provide a description of the LERF analysis that was considered in the 2016 Internal Flooding PRA and describe the adjustments made to the internal events LERF model to develop the internal flooding LERF model.
Entergy Response:
The internal flooding probabilistic risk assessment (PRA) model is built on the internal events PRA model for both core damage frequency (CDF) and LERF. The internal flooding LERF analysis is simply an expansion of the internal events LERF analysis. Flood-induced failures, which are detailed in the internal flooding PRA Accident Sequence Analysis Report, are entered in a database. This database is constructed for use with the Electric Power Research Institute (EPRI) FRANX software. The FRANX database and software are used to add failure logic for flood-induced equipment failures and human failure events into the PRA CAFTA model. The FRANX database links the flood-induced equipment failures and changes to human failure events with basic events in the internal events PRA model in order to quantify internal flooding risk. The same FRANX database is used for both CDF and LERF, thereby ensuring consistent treatment and inclusion of flood-induced failures regardless of the consequence being evaluated.
The internal flooding PRA LERF quantification uses the internal events PRA LERF model.
Other than inserting the flood-induced failures using the FRANX software, no other adjustments are made to the internal events LERF model.
After inserting the flood-induced failures into the CAFTA logic models, the EPRI PRAQUANT software is used to quantify overall risk. The only differences between the internal flooding CDF quantification and the internal flooding LERF quantification are the selection of the top gate and the truncation value. That is, the overall process for quantification for each consequence (CDF or LERF) within the internal flooding PRA is the same.
The internal flooding model upgrade that was developed in 2016 underwent a focused-scope peer review in early 2017. Facts and observations (F&Os) which resulted from that review are currently being addressed, and associated model updates and documentation to address
1CAN041805 Page 3 of 5 the F&Os are nearly complete. The updated internal flooding model that addressed the F&Os used Revision 5p0 of the internal events model. The new internal flooding PRA model updated the logic to include the common feedwater system which is being installed in the current refueling outage, 1R27, for ANO-1 as well as to include LERF. These tasks were performed at the end of 2017.
The updated ANO-1 internal flooding model currently is undergoing technical review and owners acceptance. As mentioned above, changes to the internal flooding model to address F&Os from the 2017, PRA focused-scope peer review are nearly complete. These changes included adding LERF to the internal flooding PRA model. Current plans are to complete the technical review of the internal flooding update after the ANO-2 internal flooding model is completed during the summer of 2018, if not before. As a result, internal flooding LERF could be quantified, if necessary, using the recently-updated internal flooding PRA model.
As described above, the internal flooding update involves use of the FRANX software to insert the flood-induced failures into the internal events PRA models and then performing the quantification. As a result, the same PRA models that would be used for internal events PRA quantification of both CDF and LERF would also be used for the internal flooding quantification. The focused-scope peer review identified no significant errors for the internal flooding accident sequences, modeling, or quantification process. Therefore, no changes in the accident sequences considered by the internal flooding PRA are expected.
NRC Request:
- 2. Provide details of all changes that have been made to the LERF model since it was developed, justifying that no changes constitute a PRA upgrade as defined in the ASME/ANS PRA standard.
Entergy Response:
The internal events LERF model and quantification were subjected to a peer review as part of the overall internal events PRA peer review performed in August 2009. That review used Revision 4p0 of the ANO-1 internal events PRA model. Significant findings from that peer review were resolved in Revision 5p0 of the internal events PRA model as described in the Reference 1 submittal. No other changes to the LERF model were made. As described in the Reference 1 submittal, the changes made in the Revision 5p0 update did not constitute a PRA upgrade.
As discussed above, the internal flooding PRA model uses the internal events model as the basis. There have been no changes in the processes used to quantify the internal events LERF model or to insert flood-induced failures into the PRA logic models since completion of the PRA peer reviews. As stated in Section 1-A.2 of the ASME PRA standard:
However, it is not, for example, a PRA upgrade if an error or omission is addressed by using the existing methodology, and the change does not result in a significant change in risk-estimation capability. It is expected that such changes would generally be classified as PRA maintenance because, in most cases, the method of correction would be similar to that used for typical PRA maintenance where some new plant feature or change in operation is incorporated using the existing model structure and methods.
1CAN041805 Page 4 of 5 Because the internal flooding LERF uses the same methods and models as the peer-reviewed internal events PRA model, the internal flooding LERF model is not considered a PRA upgrade.
NRC Request:
- 3. If any changes do constitute an upgrade, provide the results of a focused-scope peer review complete with F&Os and dispositions, and address any effects on the application.
Entergy Response:
As discussed above, no changes that would constitute a PRA upgrade were made.
Entergy believes the preceding information effectively addresses the supplemental information requested, and should fully support final acceptance of the referenced application.
There are no new regulatory commitments included in this submittal.
In accordance with 10 CFR 50.91, Notice for Public Comment; State Consultation, a copy of this application, with attachments, is being provided to the designated Arkansas State Official.
If there are any questions or if additional information is needed, please contact Stephenie Pyle at 479-858-4704.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April 26, 2018.
Sincerely, ORIGINAL SIGNED BY RICHARD L. ANDERSON RLA/dbb
1CAN041805 Page 5 of 5 cc: Mr. Kriss M. Kennedy Regional Administrator U. S. Nuclear Regulatory Commission RGN-IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-08B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205