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MONTHYEAR0CAN041903, Submittal of Annual Radioactive Effluent Release Report for 20182019-04-25025 April 2019 Submittal of Annual Radioactive Effluent Release Report for 2018 Project stage: Request 2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations2019-12-16016 December 2019 License Amendment Request Technical Specification Deletions, Additions, and Relocations Project stage: Request ML20024E0232020-01-23023 January 2020 NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action LAR Concerning TS Deletions, Additions, and Relocations Project stage: Acceptance Review ML20154K7622020-06-0101 June 2020 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations Project stage: RAI ML20262H0752020-09-17017 September 2020 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations Project stage: RAI 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 Project stage: Request ML20351A1532021-02-0808 February 2021 Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations Project stage: Approval 2020-06-01
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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.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5138 Ron Gaston Director, Nuclear Licensing 10 CFR 50.90 2CAN092002 September 22, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Response to Second Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations Arkansas Nuclear One, Unit 2 NRC Docket No. 50-368 Renewed Facility Operating License No. NPF-6 By letter dated December 16, 2019 (Reference 1), as supplemented by letter dated June 17, 2020 (Reference 3), Entergy Operations, Inc. (Entergy), requested NRC approval of a proposed change to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) to enhance consistency with NUREG-1432, "Standard Technical Specifications - Combustion Engineering Plants," Revision 4. During the course of review, the NRC determined additional information was required to complete the review process.
The NRC notified Entergy of the request for additional information (RAI) on September 17, 2020 (Reference 4). The RAI provides a 30-day response period.
Entergy's RAI response is included in the attached enclosure. The responses do not impact the no significant hazards consideration provided in the original amendment request (Reference 1).
No new regulatory commitments are included in this submittal.
In accordance with 10 CFR 50.91, Entergy is notifying the State of Arkansas of Entergy's RAI response by transmitting a copy of this letter and enclosure to the designated State Official.
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.
2CAN092002 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on September 22, 2020.
Respectfully, ORIGINAL SIGNED BY RON GASTON Ron Gaston RWG/dbb
Enclosure:
Response to Second Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations Attachments to
Enclosure:
- 1. Technical Specification Page Markup
- 2. Retyped Technical Specification Page
References:
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "License Amendment Request related to Technical Specification Deletions, Additions, and Relocations," Arkansas Nuclear One, Unit 2 (2CAN121901) (ML19350B324), dated December 16, 2019.
- 2. NRC email to Entergy, "ANO-2 Final RAI RE: License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations (EPID L-2019-LLA-0284)," (2CNA062001)
(ML20154K762), dated June 1, 2020.
- 3. Entergy letter to NRC, "Response to Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations," (2CAN062001)
(ML20169A558), dated June 17, 2020.
- 4. NRC email to Entergy, "ANO-2 Final RAI #2 RE: License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations (EPID L-2019-LLA-0284)," (2CNA092001)
(ML20262H075), dated September 17, 2020.
cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Arkansas Nuclear One NRC Project Manager - Arkansas Nuclear One Designated Arkansas State Official
Enclosure 2CAN092002 Response to Second Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations
2CAN092002 Enclosure Page 1 of 3 RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST ASSOCIATED WITH TECHNICAL SPECIFICATION DELETIONS, ADDITIONS, AND RELOCATIONS By letter dated December 16, 2019 (Reference 1), as supplemented by letter dated June 17, 2020 (Reference 3), Entergy Operations, Inc. (Entergy), requested NRC approval of a proposed change to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) to enhance consistency with NUREG-1432, "Standard Technical Specifications - Combustion Engineering Plants," Revision 4. During the course of review, the NRC determined additional information was required to complete the review process.
The NRC notified Entergy of the request for additional information (RAI) on September 17, 2020 (Reference 4). The RAI provides a 30-day response period.
Each question associated with the subject RAI is repeated below followed immediately by Entergy's response to the specific question.
Background from NRC RAI
- 1. Reference 19 of the application identifies "NRC Branch Technical Position ETSB 11-5, Revision 3, 'Postulated Radioactive Release due to Waste Gas System Leak or Failure,'
([ADAMS Accession No.] ML052350110), July 1981." However, the identified ADAMS number does not correspond BTP 11-5, Rev. 3, July 1981. BTP ETSB 11-5, Rev. 0 (July 1981) is located at ADAMS Accession No. ML052350105), pages 11.3-11 to 11.3-16.
- 2. As noted in the licensees application, the licensee is proposing to adopt a new program in TS 6.5.8, that would replace TSs 3.11.1, 3.11.2, and 3.11.3. The licensee noted that the TS Bases for the three replaced TSs would also be deleted. The TS Bases for existing TS 3.11.2, currently states:
Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that, in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest EXCLUSION AREA boundary will not exceed 0.5 rem. This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.
Proposed TS 6.5.8 states the following, in part:
The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure."
There are no new TS Bases associated with proposed TS 6.5.8. Proposed TS 6.5.8 does not identify the specific version (i.e., Revision No. and date) of BTP ETSB 11-5.
2CAN092002 Enclosure Page 2 of 3 RAI-ARCB-1 Confirm the specific version and revision of BTP ETSB 11-5 that ANO-2 will be adopting upon implementation of this license amendment request.
Entergy Response The adoption of the Explosive Gas and Storage Tank Radioactivity Monitoring Program (EGSTRMP) is intended to be based on the current ANO-2 license basis as stated in the excerpt from the TS 3.11.2 Bases shown above. Therefore, Reference 19 of the December 12, 2019 LAR (Reference 1) should be stated as follows:
- 19. NRC Branch Technical Position ETSB 11-5, Revision 0, "Postulated Radioactive Release due to Waste Gas System Leak or Failure," (ML052350105), July 1981.
This reference can result in some confusion since Revision 0 of ETSB 11-5 is contained with Revision 2 of NUREG-0800, "Standard Review Plan" (same ADAMS Accession number ML052350105). Entergy's response to RAI-ARECB-2 below is intended to alleviate this potential.
RAI-ARCB-2 Modify proposed TS 6.5.8, as appropriate, to include the specific version (revision and date) of BTP ETSB 11-5 that will be applicable to the respective requirements in this TS section.
Entergy Response The above excerpted statement from proposed TS 6.5.8 is modified as follows to state the specific version of ETSB 11-5:
The gaseous radioactivity quantities shall be determined following the methodology contained in Revision 2 of NUREG-0800, "Standard Review Plan," Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure," Revision 0, July 1981.
A revised markup and retyped version of the affected TS page is included in Attachments 1 and 2 of this enclosure, respectively.
2CAN092002 Enclosure Page 3 of 3 REFERENCES
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "License Amendment Request related to Technical Specification Deletions, Additions, and Relocations," Arkansas Nuclear One, Unit 2 (2CAN121901)
(ML19350B324), dated December 16, 2019.
- 2. NRC email to Entergy, "ANO-2 Final RAI RE: License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations (EPID L-2019-LLA-0284)," (2CNA062001) (ML20154K762), dated June 1, 2020.
- 3. Entergy letter to NRC, "Response to Request for Additional Information Related to License Amendment Request Associated with Technical Specification Deletions, Additions, and Relocations," (2CAN062001) (ML20169A558), dated June 17, 2020.
- 4. NRC email to Entergy, "ANO-2 Final RAI #2 RE: License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations (EPID L-2019-LLA-0284)," (2CNA092001) (ML20262H075), dated September 17, 2020.
Enclosure, Attachment 1 2CAN092002 Technical Specification Page Markup (1 page)
ADMINISTRATIVE CONTROLS 6.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendation of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. The volumetric examination per Regulatory Position C.4.b.1 will be performed on approximately 10-year intervals.
6.5.8 DELETEDExplosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Decay Tanks, the quantity of radioactivity contained in the Waste Gas Decay Tanks, and the quantity of radioactivity contained in unprotected temporary outdoor liquid storage tanks. The gaseous radioactivity quantities shall be determined following the methodology contained in Revision 2 of NUREG-0800, "Standard Review Plan," Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure," Revision 0, July 1981. The liquid radwaste quantities shall be determined in accordance with the ODCM.
The program shall include:
- a. The limits for concentrations of hydrogen and oxygen in the Waste Gas Decay Tanks and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion),
- b. A surveillance program to ensure that the quantity of radioactivity contained in each Waste Gas Decay Tank is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents, and
- c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.
The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.
ARKANSAS - UNIT 2 6-7 Amendment No. 255,262,291,305,
Enclosure, Attachment 2 2CAN092002 Retyped Technical Specification Page (1 page)
ADMINISTRATIVE CONTROLS 6.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendation of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. The volumetric examination per Regulatory Position C.4.b.1 will be performed on approximately 10-year intervals.
6.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Decay Tanks, the quantity of radioactivity contained in the Waste Gas Decay Tanks, and the quantity of radioactivity contained in unprotected temporary outdoor liquid storage tanks. The gaseous radioactivity quantities shall be determined following the methodology contained in Revision 2 of NUREG-0800, "Standard Review Plan," Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure," Revision 0, July 1981. The liquid radwaste quantities shall be determined in accordance with the ODCM.
The program shall include:
- a. The limits for concentrations of hydrogen and oxygen in the Waste Gas Decay Tanks and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion),
- b. A surveillance program to ensure that the quantity of radioactivity contained in each Waste Gas Decay Tank is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents, and
- c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.
The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.
ARKANSAS - UNIT 2 6-7 Amendment No. 255,262,291,305,