|
---|
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
[Table view] |
Text
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5138 Ron Gaston Director, Nuclear Licensing 10 CFR 50.90 1CAN102002 October 5, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Additional Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values Arkansas Nuclear One, Unit 1 NRC Docket No. 50-313 Renewed Facility Operating License No. DPR-51 By letter dated January 24, 2020 (Reference 1), as supplemented by letter dated March 19, 2020 (Reference 2), Entergy Operations, Inc. (Entergy), requested NRC approval of a proposed change to the Arkansas Nuclear One, Unit 1 (ANO-1) Technical Specifications (TSs) that would revise the 4160 volt switchgear Loss of Voltage relay setpoints. During the course of review, the NRC determined additional information was required to complete the acceptance review process.
The NRC issued a draft request for additional information (RAI) on August 5, 2020. A clarification call was held with the NRC staff at 1330 eastern time on August 10, 2020. A revised final version of the RAI was issued on September 9, 2020 (Reference 3). The requested additional information is included in the attached enclosure. This information does 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 supplemental information 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.
1CAN102002 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on October 5, 2020.
Respectfully, ORIGINAL SIGNED BY RON GASTON Ron Gaston RWG/dbb
Enclosure:
Additional Information Related to Revising the Loss of Voltage Relay Allowable Values
References:
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "License Amendment Request to Revise Loss of Voltage Relay Allowable Values," Arkansas Nuclear One, Unit 1 (1CAN012002) (ML20024E639), dated January 24, 2020.
- 2. Entergy letter to NRC, "Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values," Arkansas Nuclear One, Unit 1 (1CAN032001) (ML20079K973),
dated March 19, 2020.
- 3. NRC email to Entergy, "ANO-1 Final RAI RE: License Amendment Request to Revise LOV Relay Allowable Values (EPID L-2020-LLA-0013)," (1CNA092001) (ML20260H476), dated September 9, 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 1CAN102002 Additional Information Related to Revising the Loss of Voltage Relay Allowable Values
1CAN102002 Enclosure Page 1 of 5 ADDITIONAL INFORMATION RELATED TO REVISING THE LOSS OF VOLTAGE RELAY ALLOWABLE VALUES By letter dated January 24, 2020 (Reference 1), as supplemented by letter dated March 19, 2020 (Reference 2), Entergy Operations, Inc. (Entergy), requested NRC approval of a proposed change to the Arkansas Nuclear One, Unit 1 (ANO-1) Technical Specifications (TSs) that would revise the 4160 volt (V) switchgear Loss of Voltage (LOV) relay setpoints. The NRC issued a final request for additional information on September 9, 2020 (Reference 3), with a required response due October 26, 2020. The requested supplemental information is included below.
Background/Discussion As discussed in the LAR, SAR Section 8.3.1.2, related to conformance to GDC 17, and SAR section 8.3.1.5, "Grid Undervoltage Protection (Millstone 2 and ANO Events)," the current licensing basis of ANO-1 includes requirements for protection of safety-related equipment in the event of sustained degraded voltage conditions.
In the LAR, the licensee stated, "The most recent offsite power grid study (completed in 2017) supports the assumption that sustained voltage degradation below the DV setpoint is not credible for the ANO-1 unit." The licensee further stated, "Because the current ANO-1 design and licensing basis does not assume a sustained undervoltage condition as described above
[i.e., at a voltage below the current DV setpoint in the TSs], Entergy does not intend to include the new additional DV relays within the TSs. The relays will be controlled and tested, however, consistent with requirements for Class 1E devices."
ANO-1 SAR Section 8.3.1.5.1, "NRC Positions/ANO Responses," Position 1, "Second Level of Under- or Over-Voltage Protection With a Time Delay," describes requirements for a second level of voltage protection for the onsite power system. Position 1, item C.3 states, "The allowable time duration of a degraded voltage condition at all distribution system levels should not result in failure of safety systems or components."
In the LAR, the licensee stated, "The MSP [motor start protection] relays will be set at a slightly lower voltage than the DV relays and will ensure that 480 V motor voltage is maintained above the 80% start voltage. No change is proposed for the existing DV relays or associated TS allowable voltage and time delay values." The licensee further stated that reducing the time delay of the existing DVRs could increase the potential of inadvertent separation from operable offsite power sources. The licensee noted that this would be contrary to the intent of RIS 2011-12.
Request for Additional Information (RAI)
Request for Additional Information (RAI) EEOB-1 The existing DV and LOV relays perform certain safety functions and, in conformance with requirements of 10 CFR 50.36, are included in TS 3.3.8, "Diesel Generator (DG) Loss of Power Start (LOPS)." In the LAR, the licensee provided an overview of the functions of the MSP relays. In order to understand all the safety functions performed by MSP relays in combination with DV and LOV relays for conformance with requirements of GDC 17, the NRC staff is
1CAN102002 Enclosure Page 2 of 5 requesting additional information. Specifically, the information in the LAR does not make it sufficiently clear that the protection afforded by the proposed LOV relays and existing DV relays meet the current licensing basis without the proposed new MSP relays.
Therefore, the NRC staff requests the licensee to confirm whether the MSPs provide part of the protection needed to meet the current licensing basis for the ANO grid undervoltage protection scheme described in Section 8.3.1.5 of the ANO UFSAR.
Entergy Response With respect to the NRC Position quoted in the NRC Background/Discussion section above and in the ANO-1 Safety Analysis Report (SAR) Section 8.3.1.5.1, The allowable time duration of a degraded voltage condition at all distribution system levels should not result in failure of safety systems or components.
The ANO-1 post-Millstone event design met the intent of this position for credible degraded voltage scenarios. As stated in this SAR section in response to the above NRC position and in the Reference 1 license amendment request (LAR), the ANO-1 degraded voltage protection was designed as follows:
Under the conditions identified by the system analysis, the safety related equipment will function satisfactorily.
The SAR does not state in this section or any other section that the design accommodated a "sustained" undervoltage condition. This is because the "system analysis" on which the design is based indicates that a sustained undervoltage relevant to the 2016 NRC violation described in the Reference 1 LAR (voltage drop below the Degraded Voltage (DV) relay setpoints but holding above the LOV relay setpoints up to the 9-second time delay of the DV relays) is not credible. Voltage may drop during a large motor start, following a fault on the grid, or a generator trip but recovers before the DV relay time delay is reached. This voltage drop is also analyzed to not prevent other safety-related equipment from responding or operating as needed during transient or accident scenarios.
As is generically the case with NRC regulation and guidance, each commercial nuclear facility is responsible for assessing the conditions at the specific plant site and presenting a design to the NRC (when required) that addresses the requirements based on credible events. The design of structures, systems, and components (SSCs) normally do not accommodate those events that are deemed reasonably unlikely. As stated in the Reference 1 LAR, ANO-1 submitted information to the NRC in letter dated August 23, 1978 (Reference 2 of the LAR enclosure) detailing plant modifications and controls addressing the 1976 Millstone event. The NRC accepted the ANO-1 response in letter dated December 17, 1979 (Reference 3 of the LAR enclosure), including the studies performed to determine the settings for undervoltage protection devices. Appendix I of the 1978 LAR began by stating:
Based on the results of a grid system stability analysis, the following discussion provides the nominal, maximum, and minimum values of voltage and frequency of the offsite power source that assures satisfactory operability of all electrical equipment of the station during all modes of plant operation.
1CAN102002 Enclosure Page 3 of 5 The 1978 correspondence and the Reference 1 LAR do not discuss a design assuming a sustained undervoltage below the DV relay setpoints but above the LOV relay setpoints. The Reference 1 LAR provides a summary of the offsite grid configuration assumed in the analysis, which alone are reasonably considered incredible and unlikely to exist simultaneously.
Appendix I of the aforementioned 1978 correspondence contains additional information. While Entergy concludes that the analysis is reasonably bounding (as accepted by the NRC in 1979),
further discussion in this respect is provided in response to RAIs EEOB-2 and EEOB-3 below.
Based on the above, the ANO-1 licensing basis does not assume the DV relays were needed to protect against a sustained undervoltage condition as described herein. Nevertheless, the DV relays were installed as a 2nd level of protection consistent with the generic industry response to the NRC position related to the 1976 Millstone event.
In light of the above, the MSP relays are not required to meet the ANO-1 design or licensing basis but are intended to accommodate the subject sustained degraded voltage scenario when an Engineered Safeguards (ES) signal is present (accident condition). Entergy plans to install the MSPs as an enhancement at considerable cost even though the assumed scenario is not reasonably considered credible. Entergy considers this approach similar to plant modifications made in response to the Anticipated Transient Without Scram and Station Blackout rules, which added SSCs that were not required to be controlled by the plant TSs. In conclusion, because the MSP relays are not required to meet the existing ANO-1 design or licensing basis, Entergy proposes that the relays are not required to be controlled by the TSs.
RAI EEOB-2 The NRC staff needs additional information to verify the licensees conclusion in the LAR that, "instantaneous voltage drop below the DV relay setpoint which remains above the LOV relay setpoint is not considered credible." Therefore, the NRC staff requests the licensee to provide details of (or excerpts from) the technical justification contained in the system analysis (as defined by Section 8.3.1.5.1, Position 1: Response 1, Item C.3, of the ANO-1 SAR) for ANO-1 that forms the basis of the above conclusion.
Entergy Response As stated in the LAR, the ANO-1 degraded voltage protection is based on the assumption that the offsite power grid voltage is at the "minimum expected value" as opposed to a transient voltage that is not supported by grid analysis. At ANO, the minimum predicted grid voltage from grid stability analysis (load flow studies) is the most restricting when considering the guidance in Generic Letter (GL) 79-36, "Adequacy of Station Electric Distribution Systems Voltages." The minimum acceptable grid voltage is determined on the Entergy System by modeling the system in the configuration that would result from the loss through a single event of critical equipment on the transmission system, including the most critical transmission line, loss of multiple transmission lines on a common transmission tower, loss of the largest generating station on the grid, or removal of the largest load from the system. Applying that methodology, ANO uses the data provided in the grid analysis to evaluate the offsite power systems ability to power the safety equipment at ANO during nuclear accident conditions (ensures compliance with 10 CFR 50, Appendix A, General Design Criteria (GDC-5) and GDC-17). These evaluations demonstrate that there is adequate voltage to the Class 1E loads during load sequencing and subsequent steady-state conditions for the worst-case accident loading when the offsite power supply is at minimum expected conditions. These evaluations also demonstrate that when bus
1CAN102002 Enclosure Page 4 of 5 voltages drop below the DV, MSP, or LOV relay maximum dropout voltages due to starting of loads, the bus voltages recover above the maximum reset voltage of the relay prior to the actuation of the relay, assuming the minimum time delay of each relays. These evaluations show that when the offsite power supply is at minimum expected conditions there is no sustained voltage degradation below the DV relay setpoint.
In addition to the grid analysis discussed above, ANO also evaluates the results of the grid transient stability analysis. The grid transient stability analysis determines the degree of generator stability of the ANO and other nearby generators following major system disturbances in and around the ANO area. Stability of the ANO offsite power system must be maintained following these major disturbances to ensure that the offsite power requirements of the ANO nuclear power plants are maintained. Additionally, these studies provide the recommended restricted power levels for the ANO generators following the loss of major transmission facilities.
These generator power level restrictions ensure that damage to the ANO generators is avoided and unacceptable low voltage levels to the ANO plant auxiliaries are minimized. The results of the transient stability plots in the latest ANO Grid Stability Analysis determined that there is adequate offsite power capability to avoid actuation of the LOV and DV relaying at ANO.
RAI EEOB-3 In its LAR, the licensee stated, "The most recent offsite power grid study (completed in 2017) supports the assumption that sustained voltage degradation below the DV setpoint is not credible for the ANO-1 unit." The NRC staff requests the licensee to clarify if the offsite power grid study accounts for equipment malfunctions or failures, electrical faults, or human performance issues similar to those discussed in Licensee Event Reports and/or identified by the ANO corrective action program.
Entergy Response The grid analysis discussed above in response to RAI EEOB-2 accounts for specific conditions that could occur from equipment malfunctions or failures, electrical faults, or human performance issues similar to those discussed in Licensee Event Reports (LERs) and/or identified by the ANO corrective action program (CAP). Any event that results in an ANO or ANO system grid related LER is entered into the CAP. The CAP drives actions to assess the events or adverse conditions affecting ANO (whether internal or external) impact on other SSCs or design/licensing basis assumptions. The CAP is expected to identify if the event/condition requires review of the grid and site electrical analyses and document the results of such a review accordingly, including assigning corrective action if analyses require update to address the event/condition.
The CAP is effective in ensuring events and adverse conditions are appropriately evaluated against the assumptions in the ANO onsite and offsite electrical power calculations/studies where applicable. To validate this conclusion, a search of the ANO CAP and LERs over the previous 20 years was performed using 14 keywords/phrases (i.e., 14 separate searches using terms such as "lightning", "grid disturbance", "degraded voltage", "offsite grid", etc.). The results included not only events on the Entergy power grid (or local to ANO) but also the portion of the grid controlled by Oklahoma Gas & Electric (where ANO was impacted). While there were several grid related events including events due to personnel error, system/component failures, weather, etc., none of the events involved a sustained undervoltage condition as subject to this correspondence. Based on the above, the offsite power grid study accounts for equipment malfunctions or failures, electrical faults, or human performance issues identified in the CAP.
1CAN102002 Enclosure Page 5 of 5 REFERENCES
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "License Amendment Request to Revise Loss of Voltage Relay Allowable Values," Arkansas Nuclear One, Unit 1 (1CAN012002) (ML20024E639), dated January 24, 2020.
- 2. Entergy letter to NRC, "Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values," Arkansas Nuclear One, Unit 1 (1CAN032001) (ML20079K973), dated March 19, 2020.
- 3. NRC email to Entergy, "ANO-1 Final RAI RE: - License Amendment Request to Revise LOV Relay Allowable Values (EPID L-2020-LLA-0013)," (1CNA092001)
(ML20260H476), dated September 9, 2020.