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MONTHYEAR0CAN072004, Withdrawal of Request for Exemption from 10 CFR 50, Appendix B Requirements to Support Application of ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 22020-07-15015 July 2020 Withdrawal of Request for Exemption from 10 CFR 50, Appendix B Requirements to Support Application of ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 Project stage: Withdrawal ML20260H4852020-09-10010 September 2020 NRR E-mail Capture - ANO-1 and ANO-2 - Acceptance Review of Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping (L-2020-LLR-0104) Project stage: Acceptance Review ML20293A1842020-11-0404 November 2020 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21022A0842021-01-22022 January 2021 Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping - Arkansas Nuclear One,Units 1 and 2 -Entergy Operations, Inc. NON-PROPRIETARY Redacted Project stage: RAI 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 Project stage: Response to RAI ML21116A1092021-04-26026 April 2021 NRR E-mail Capture - ANO-1 and ANO-2: Final Supplemental RAI Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping Project stage: RAI ML21141A1822021-05-21021 May 2021 Closed Teleconference with Entergy Operations, Inc. Concerning Proposed Alternative to Allow Use of a Carbon Fiber Reinforced Polymer Composite System at Arkansas Nuclear One, Units 1 and 2 Project stage: Meeting 0CAN052103, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency .2021-05-25025 May 2021 Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency . Project stage: Response to RAI 0CAN062101, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling2021-06-15015 June 2021 Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Project stage: Response to RAI ML21145A0042021-06-28028 June 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 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 Project stage: Response to RAI ML21225A3012021-08-25025 August 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 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 Project stage: Response to RAI ML21225A5432021-09-23023 September 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21188A0222021-09-30030 September 2021 Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID L-2020-LLR-0104) (Redacted) Project stage: Other 2021-05-25
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Category:Letter type:
MONTHYEAR0CAN102401, Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzle2024-10-16016 October 2024 Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 2CAN102401, Cycle 31 Core Operating Limits Report (COLR)2024-10-14014 October 2024 Cycle 31 Core Operating Limits Report (COLR) 1CAN082401, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 1 Thirty-First Refueling Outage (1R312024-08-13013 August 2024 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 1 Thirty-First Refueling Outage (1R31 2CAN072401, Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02)2024-07-19019 July 2024 Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) 0CAN072401, Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes2024-07-0808 July 2024 Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply 0CAN062403, Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels2024-06-25025 June 2024 Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels 0CAN062402, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-06-0606 June 2024 Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 0CAN052401, – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 20232024-05-13013 May 2024 – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 2023 1CAN052401, Cycle 32 Core Operating Limits Report2024-05-0404 May 2024 Cycle 32 Core Operating Limits Report 2CAN042403, Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C2024-04-24024 April 2024 Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C 0CAN042402, Annual Occupational Radiation Exposure Report for 20232024-04-23023 April 2024 Annual Occupational Radiation Exposure Report for 2023 0CAN042401, Radioactive Effluent Release Report for the 2023 Calendar Year2024-04-15015 April 2024 Radioactive Effluent Release Report for the 2023 Calendar Year 2CAN042402, Special Report of Non-functional Main Steam Line Radiation Monitor2024-04-11011 April 2024 Special Report of Non-functional Main Steam Line Radiation Monitor 2CAN042401, Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications2024-04-0404 April 2024 Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications 2CAN012401, 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 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 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 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 2024-08-13
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEAR0CAN102401, Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzle2024-10-16016 October 2024 Response to Request for Additional Information - Arkansas Nuclear One – Units 1 and 2, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 2CAN042403, Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C2024-04-24024 April 2024 Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C 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 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 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) 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 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 2024-04-24
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Text
This letter contains proprietary information.
Withhold Enclosure 1 from public disclosure in accordance with 10 CFR 2.390.
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5138 Ron Gaston Director, Nuclear Licensing 10 CFR 50.55a(z)(1) 0CAN072102 July 22, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping Arkansas Nuclear One, Unit 1 and Unit 2 NRC Docket Nos. 50-313 and 50-368 Renewed Facility Operating License Nos. DPR-51 and NPF-6 By letter dated July 15, 2020 (Reference 1), Entergy Operations, Inc. (Entergy), requested NRC approval of a proposed alternative to American Society for Mechanical Engineers (ASME)
Boiler & Pressure Vessel Code Section XI requirements for repair/replacement of Emergency Cooling Pond (ECP) supply piping in accordance with 10 CFR 50.55a(z)(1). During the course of the review, the NRC determined that additional information is needed to support completing the review process (Reference 2). Entergy provided responses to the Request for Additional Information (RAI) (Reference 3). To complete its review, the NRC staff requested additional supplemental information to NRC Mechanical Engineering and Inservice Testing Branch (EMIB)
EMIB-RAI-10 (Reference 4).
Entergy presented preliminary responses to the NRC's request in a closed meeting on May 26, 2021. See Reference 5 for the presentation material. Subsequent to the meeting, the NRC provided a set of additional requests (Reference 6).
The request for additional supplemental information (References 4 and 6) and associated Entergy responses are included in Enclosure 1.
The response to the additional supplemental information provided in Enclosure 1 is considered proprietary to Structural Group, Inc., and is to be withheld from public disclosure in accordance with 10 CFR 2.390 of the Commissions regulations. The non-proprietary version is provided in .
This letter contains proprietary information.
Withhold Enclosure 1 from public disclosure in accordance with 10 CFR 2.390.
This letter contains proprietary information.
Withhold Enclosure 1 from public disclosure in accordance with 10 CFR 2.390.
0CAN072102 Page 2 of 3 This information is supported by affidavit, signed by Structural Group, Inc. the owner of the information. The affidavit set forth the bases by which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390 of the Commission's regulations. The affidavit is included in Structural Group, Inc. letter to the NRC entitled, "Application for Withholding Proprietary Information from Public Disclosure." The Structural Group, Inc. authorization letter is provided in Enclosure 3.
No new regulatory commitments are included in this submittal.
If there are any questions or if additional information is needed, please contact Riley Keele, Jr.,
Manager, Regulatory Assurance, Arkansas Nuclear One, at 479-858-7826.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on July 22, 2021.
Respectfully,
~1 Ron Gaston RWG/rwc
Enclosures:
- 1. Response to Final Supplemental 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) (Proprietary)
- 2. Response to Final Supplemental 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)
- 3. Structural Group Application for Withholding Proprietary Information from Public Disclosure This letter contains proprietary information.
Withhold Enclosure 1 from public disclosure in accordance with 10 CFR 2.390.
This letter contains proprietary information.
Withhold Enclosure 1 from public disclosure in accordance with 10 CFR 2.390.
0CAN072102 Page 3 of 3
References:
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Emergency Cooling Pond (ECP) Supply Piping in accordance with 10 CFR 50.55a(z)(1),"Arkansas Nuclear One, Units 1 and 2 (ML20218A672) (0CAN072001), dated July 15, 2020.
- 2. NRC email to Entergy, "Arkansas Nuclear One, Units 1 and 2 - Request for Additional Information RE: Proposed Alternative to ASME Code Requirements for the Repair of Emergency Cooling Pond Piping (EPID L-2020-LLR-0104)," (ML21022A084) (0CNA012105), dated January 22, 2021.
- 3. Entergy letter to NRC, "Response to Request for Additional Information -
Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping,"
Arkansas Nuclear One, Units 1 and 2 (ML21063A243) (0CAN022101),
dated February 22, 2021.
- 4. NRC email to Entergy, "Arkansas Nuclear One, Units 1 and 2 - Final Supplemental Request for Additional Information RE: Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Emergency Cooling Pond Supply Piping (EPID L-2020-LLR-0104)," (ML21116A109) (0CNA042102), dated April 26, 2021.
- 5. Entergy letter to NRC, "Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information -
Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping,"
Arkansas Nuclear One, Units 1 and 2 (ML21167A279) (0CAN062101),
dated June 15, 2021.
- 6. NRC email to Entergy, "As discussed during the pre-submittal meeting related to the response to EMIB-2-RAI-1, Entergy is providing our understanding of the scope of the response for NRCs review and agreement," (0CNA062104), dated June 1, 2021.
cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Arkansas Nuclear One NRC Project Manager - Arkansas Nuclear One This letter contains proprietary information.
Withhold Enclosure 1 from public disclosure in accordance with 10 CFR 2.390.
Enclosure 2 0CAN072102 Response to Final Supplemental 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)
0CAN072102 Page 1 of 16 RESPONSE TO FINAL SUPPLEMENTAL 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)
By letter dated July 15, 2020 (Reference 1), Entergy Operations, Inc. (Entergy), requested NRC approval of a proposed alternative to American Society for Mechanical Engineers (ASME)
Boiler & Pressure Vessel Code Section XI requirements for repair/replacement of Emergency Cooling Pond (ECP) supply piping in accordance with 10 CFR 50.55a(z)(1). During the course of review, the NRC determined that additional information is needed to support completing the review process (Reference 2). Entergy provided responses to the Request for Additional Information (RAI) (Reference 3). To complete its review, the NRC staff requested additional supplement information to NRC Mechanical Engineering and Inservice Testing Branch (EMIB)
EMIB-RAI-10 (Reference 4). The request for additional supplemental information and associated Entergy response is included in the attached enclosure.
Proprietary information is identified by text enclosed within double brackets ((Example)).
EMIB-2-RAI-1
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The NRC provided additional requests for information via Reference 7. These additional requests and Entergy's responses are provided below.
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REFERENCES
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC),
"Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Emergency Cooling Pond (ECP) Supply Piping in accordance with 10 CFR 50.55a(z)(1),"Arkansas Nuclear One, Units 1 and 2 (ML20218A672)
(0CAN072001), dated July 15, 2020.
- 2. NRC email to Entergy, "Arkansas Nuclear One, Units 1 and 2 - Request for Additional Information RE: Proposed Alternative to ASME Code Requirements for the Repair of Emergency Cooling Pond Piping (EPID L-2020-LLR-0104)," (ML21022A084)
(0CNA012105), dated January 22, 2021.
0CAN072102 Page 16 of 16
- 3. Entergy letter to NRC, "Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping," Arkansas Nuclear One, Units 1 and 2 (ML21063A243)
(0CAN022101), dated February 22, 2021.
- 4. NRC email to Entergy, "Arkansas Nuclear One, Units 1 and 2 - Final Supplemental Request for Additional Information RE: Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Emergency Cooling Pond Supply Piping (EPID L-2020-LLR-0104)," (ML21116A109) (0CNA042102), dated April 26, 2021.
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- 7. NRC email to Entergy, "As discussed during the pre-submittal meeting related to the response to EMIB-2-RAI-1, Entergy is providing our understanding of the scope of the response for NRCs review and agreement," (0CNA062104), dated June 1, 2021.
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Enclosure 3 0CAN072102 Structural Group Application for Withholding Proprietary Information from Public Disclosure (6 pages)
0CAN072102 Page 1 of 6 STRUCTURAL GROUP APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE struc*tura1 group June 29, 2021 U.S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD20852
Subject:
Application for Withholding Proprietary Information from Public
References:
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "Response to Request for Additional Information - Proposed A lternative to ASME Boiler & Pressure Vessel Code Section X I Requirements for Repair/Replacement of Emergency Cooling Pond (ECP) Supply Piping in accordance with 10 CFR 50.55a(z)(1)," Arkansas Nuclear One, Units 1 and 2, NRC Docket Nos. 50-313 and 50-368, Entergy letter no. 0CAN02201.
- 2. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Emergency Cooling Pond (ECP) Supply Piping in accordance with 10 CFR 50.55a(z)(1)," Arkansas Nuclear One, Units 1 and 2 (0CAN072001) (ML20218A672).
- 3. NRC email to Entergy, "Arkansas Nuclear One, Units 1 and 2 - Final Supplemental Request for Additional Information RE: Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Emergency Cooling Pond Supply Piping (EPID L-2020-LLR-0104)," (ML21116A109) (0CNA042102), dated April 26, 2021.
- 4. NRG email to Entergy, "As discussed during the pre-submittal meeting related to the response to EMIB-2-RAl-1, Entergy is providing our understanding of the scope of the response for NRC's review and agreement," dated June 1, 2021.
Ladies and Gentlemen:
Structural Group, lnc.,(SGI) has provided certain proprietary information to Entergy Operations, Inc. (Entergy), in connection with a supplemental response by Entergy to EMIB-2-RAl-1 from the U.S. Nuclear Regulatory Commission (NRC) which was provided in reference 4. This application requests that proprietary information of SGI provided in the response to EM IB-2-RA l-1 be protected from public disclosure.
The proprietary information for which withholding is being requested identified in the attached affidavit signed by the owner of the proprietary information, SGI, on behalf of itself and any wholly-owned subsidiaries or affiliated companies. An affidavit accompanies this letter, setting forth the basis on which the information may be withheld from public disclosure by the NRC and addressing with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390 of the NRC's reg ulations.
Page 1 of 6
0CAN072102 Page 2 of 6 struc'turat group Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Entergy.
zly; Correspondence with respect to the proprietary aspects of the Application or the Affidavit should reference this letter and be addressed to Scott Greenhaus, Executive Vice President, Structural Group, Inc., 10150 Old Columbia Road, Columbia, MD21046.
Scott Greenhaus Executive Vice President 0 (410) 859-6458, M (410) 340-3205 SGreenhaus@structuralgroup.com Page 2 of 6
0CAN072102 Page 3 of 6 struc'tura1 group AFFIDAVIT I, Scott Greenhaus, am Executive Vice President of Structural Group, Inc. (SGI).
In my capacity as Executive Vice President I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in conjunction with nuclear plant licensing and rulemaking proceedings and am authorized to apply for its withholding on behalf of SGI and its affiliates.
I am making this Affidavit in conformance with the provisions of 10 CFR 2.390 of the U.S. Nuclear Regulatory Commission (NRG) regulations and in conjunction with SGl's Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
I have personal knowledge of the criteria and procedures utilized by SGI in designating information as a trade secret, privileged or as confidential commercia l or financial information.
Pursuant to the provisions of paragraph (b) (4) of 10 CFR 2.390 of the NRC's regulations, the following is furnished for consideration by the NRG in determining whether the information sought to be withheld from public disclosure should be withheld.
The information sought to be withheld from public disclosure is owned by and has been held in confidence by SGI. The response provided in Entergy's letter (Docket Nos. 50-313 and 50-368) to the NRC's "Request for Additional Information" in Reference 4 (EMIB RAl-1) includes SGI proprietary information.
The information is of a type customarily held in confidence by SGI and not disclosed to the public. SGI has a rational basis for determining the types of information customarily held in confidence by it and utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance ofthat system provides a rational basis for maintaining confidentiality and justifies the NRG withholding the information from public disclosure.
Under SGl's system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, asfollows:
- 1) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by a competitor of SGI without license constitutes a competitive advantage over other companies.
- 2) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
- 3) Its use by a competitor would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
- 4) It reveals cost or price information, production capacities, budget levels, or commercial strategies of SGI, their customers or suppliers.
- 5) It reveals aspects of past, present, or future development plans funded by SGI or its customer, and programs of potential commercial value to SGI.
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0CAN072102 Page 4 of 6 struc*tura1 group
- 6) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the SGI system which include the following;
- 1) The use of such information by SGI gives it a competitive advantage over competitors. It is, therefore, withheld from disclosure to protect SGl's competitive position.
- 2) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes SGl's ability to sell products and services involving the use of the information.
- 3) Use by a competitor would put SGI at a competitive disadvantage by reducing the competitor's expenditure of resources and capital.
- 4) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.
If competitors acquire components of proprietary information, any one component may be the key to the entire process, thereby depriving SGI of its competitive advantage.
- 5) Unrestricted disclosure would jeopardize the position of prominence of SGI in the world marketplace, and thereby give a market advantage to competitor in those countries in which SGI operates.
- 6) SGl's capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
The information is being transmitted to the NRC in confidence and, under the provisions of 10 CFR 2.390, it is to be received in confidence by the NRC. The information sought to be protected is not available in public sources and, to the best of our knowledge and belief, available information has not been previously employed in the same original manner or method.
The proprietary information sought to be withheld in this submittal is that which is appropriately marked in Entergy's response to the NRC RAJ (EMIB-2-RAl-1) being transmitted by Entergy letter (Docket Nos. 50-313/368) and reflected in SGl's Application for Withholding Proprietary Information from Public Disclosure addressed to the NRC Document Control Desk. The proprietary information as submitted by SGI is that associated with the "Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond (ECP) Supply Piping for Entergy Arkansas Nuclear One (ANO) Units 1 and 2" (Reference 2) and may be used only for that purpose.
This information is part of that which will enable SGI to:
- 1) Provide input to Entergy to provide to the NRC for the A NO Units 1 and 2, RAI response; and
- 2) Provide licensing support for the Entergy response.
SGI owns or is permitted to use the proprietary information referenced in this Affidavit under agreements that include SGl's maintaining the confidentiality of such information, as contemplated in this Affidavit.
Further this information has substantial commercial value as follows;
- 1) The SGI plan to sell the use of this information to their customers for the purpose of installing Carbon Fiber Reinforced Polymer (CFRP) in safety related piping.
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- 2) That SGI can sell support and defense of the technology to their customers in t he licensing process.
- 3) The information requested to be withheld reveals the distinguishi ng aspects of a methodology which was developed by SGI.
- 4) Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of SGI because it would enhance the ability of competitors to provide similar licensing services for commercial power reactors without commensurate expenses.
- 5) Public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
- 6) The developme nt of the technology described in part by the proprietary information is the result of applying the results of many years of experience in an intensive effort by SGI and the expenditure of a considerable sum of money and resources. In order for competitors to duplicate this information , similar technical programs would have to be performed including a significant expenditure money and resources.
Further the deponent sayeth not.
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0CAN072102 Page 6 of 6 struc'tural group strucl ural group AFFIDAVIT State of Maryland )
County of Howard )
Before me, the undersigned authority, personally appeared Scott Greenhaus, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Structural Group, Inc. and that the averments of fact set forth in th;sr ; ; ; ~ [ o r r e c t to the best of h;s knowledge, ;nformaHon, and beHef WoJ Greenhaus Executive Vice President Sworn to and subscribed before me thisA1ay of June 2021 Public 1 1-f "",....h-,.-J &P,7 lf/dJ
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aom,,,,,/5 'j / d>'f. 1 t,/tr/z.oz.tj Page 6 of 6