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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 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) Project stage: Response to 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:Legal-Affidavit
MONTHYEAR1CAN122301, 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) 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) ML23020A9442023-01-20020 January 2023 Enclosure 3: Affidavit 2CAN122103, Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Submittal of Analyses - Affidavits and Calculation Summary Sheet2021-11-19019 November 2021 Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Submittal of Analyses - Affidavits and Calculation Summary Sheet 2CAN102102, Relief Request ANO2-R&R-012: Support the Repair of the Reactor Vessel Closure Head Penetration 462021-10-10010 October 2021 Relief Request ANO2-R&R-012: Support the Repair of the Reactor Vessel Closure Head Penetration 46 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 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 . 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 2CAN032001, Response to Request for Additional Information Related to License Amendment Request to Revise the Control Element Assembly Drop Times2020-03-11011 March 2020 Response to Request for Additional Information Related to License Amendment Request to Revise the Control Element Assembly Drop Times 1CAN121601, Arkansas Nuclear One Unit 1, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan2016-12-21021 December 2016 Arkansas Nuclear One Unit 1, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan 1CAN121601, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan2016-12-21021 December 2016 Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan 1CAN121502, Evaluations Described Response to Requests for Additional Information 3, 5, 6(a), and 7, Reactor Vessel Internals Aging Management Program Plan2015-12-30030 December 2015 Evaluations Described Response to Requests for Additional Information 3, 5, 6(a), and 7, Reactor Vessel Internals Aging Management Program Plan ML15278A0242015-09-28028 September 2015 Attachment 2, Areva Document ANP-3417NP, Revision 0, MRP-227-A Applicant / Licensee Action Item No. 7 Analysis for Arkansas Nuclear One, Unit 1 (Non-Proprietary), Attachment 3, Affidavit, and Attachment 4, List of Commitments 2CAN051504, Revised Affidavit for Request for Relief ANO2-ISI-0162015-05-19019 May 2015 Revised Affidavit for Request for Relief ANO2-ISI-016 1CAN031504, Arkansas Nuclear One, Unit 1 - Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2015-03-25025 March 2015 Arkansas Nuclear One, Unit 1 - Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN031504, Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2015-03-25025 March 2015 Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits ML15041A0742015-02-0606 February 2015 ANP-3300Q1NP, Rev. 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1, Attachment 2 to 1CAN0 2CAN111402, Unit 2, Revised Affidavit for Request for Relief ANO2-ISI-0162014-11-11011 November 2014 Unit 2, Revised Affidavit for Request for Relief ANO2-ISI-016 2CAN041402, Successive Examination Plans, Request for Relief ANO2-ISI-016. Weld Scan Plans & Preliminary Coverage Estimates, Pdqs Number 783 & Affidavit Enclosed2014-04-15015 April 2014 Successive Examination Plans, Request for Relief ANO2-ISI-016. Weld Scan Plans & Preliminary Coverage Estimates, Pdqs Number 783 & Affidavit Enclosed 0CAN041401, NRC Augmented Inspection Team Follow-up Inspection Report 05000313/2013012 and 05000368/2013012; Preliminary Red and Yellow Findings2014-04-0101 April 2014 NRC Augmented Inspection Team Follow-up Inspection Report 05000313/2013012 and 05000368/2013012; Preliminary Red and Yellow Findings 0CAN071303, Units 1 and 2, Augmented Inspection Team Information Request2013-07-31031 July 2013 Units 1 and 2, Augmented Inspection Team Information Request ML12038A1772012-02-0303 February 2012 Units 1 and 2, HI-STORM 100 Cask System, Thermal Validation Test Using Air Mass Flow Rate ML0935005322009-12-11011 December 2009 Affidavit from Gayle F. Elliot, Manager of Product Licensing for Areva, Np Inc ML0828300342008-08-20020 August 2008 Affidavit of Gayle F. Elliott, for Areva Np Inc., Regarding NRC Presentation of August 2008 ML0627703182006-09-28028 September 2006 Transmittal of Draft Slide Presentation for Nrc/Entergy/Westinghouse Pre-Submittal Meeting (Proprietary/Non-Proprietary) ML0514603882005-05-10010 May 2005 Units 1 and 2, Request for Additional Information Concerning Request for Exemption from Holtec International Certificate of Compliance 2CAN010402, Revisions to Wesdyne Proprietary Reports in Support of Relaxation from Performing a Bare Metal Visual Inspection2004-01-16016 January 2004 Revisions to Wesdyne Proprietary Reports in Support of Relaxation from Performing a Bare Metal Visual Inspection ML15350A2151985-09-0505 September 1985 Overview Description of Core Operating Limit Supervisory System (Colss)(Rev 00-NP to CEN-312-NP) 2023-06-08
[Table view] 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
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) 0CAN092101 September 14, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
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 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
Reference:
Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond (ECP) Supply Piping,"
Arkansas Nuclear One, Units 1 and 2 (ML21203A198) (0CAN072102), dated July 22, 2021.
By the referenced submittal, Entergy Operations, Inc. (Entergy), provided the follow-up responses to the Request for Additional Information associated with the proposed alternative to American Society for Mechanical Engineers 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). Subsequent to the submittal, Entergy was asked to review the proprietary demarcations in the submittal to determine if they were too conservative.
As a result of this review, the proprietary markings were revised. The complete responses are provided in Enclosure 1. It should be noted that the only change between Enclosure 1 and the reference responses is where the brackets denoting proprietary material are located.
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.
0CAN092101 Page 2 of 3 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 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 September 14, 2021.
Respectfully, Digitally signed by Ronald W.
Ronald W. Gaston Gaston Date: 2021.09.14 14:03:42 -05'00' 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.
0CAN092101 Page 3 of 3 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 0CAN092101 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)
0CAN092101 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
((
))
0CAN092101 Page 2 of 16 Entergy Response:
For the purposes of this response the following definitions are provided:
((
))
Tmax is defined as the faulted maximum achievable ECP Supply system piping water temperature of 121 °F. Typical operating temperature range is 32 °F to 101 °F. The maximum faulted temperature of 121 °F peaks above 120 °F for a short duration of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The acceptance criteria for ((
))
As shown on Figures 2, 3, and 4, and as discussed below, a (( )) margin above Tmax (121
°F) will keep V-Wrap' 770 epoxy in the glassy phase.
General Design Criteria - Material Properties
(( )) is a general design criterion for the initial selection of an epoxy material for use at ANO. (( )) for an epoxy and depends on the American Society for Testing and Materials (ASTM) test method, specified ((
)). Using ASTM E1640 test methods (( )) for V-Wrap' 770 epoxy is (( )) °F. Based on ASTM E1640 test results for the initial selection of the epoxy material V-Wrap' 770 epoxy meets the general design criterion for ANO:
(( )) °F) > Tmax (121 °F) + (( )) °F = (( )) °F
0CAN092101 Page 3 of 16 Material Behavior Figure 1 below shows the theoretical behavior of an amorphous thermoplastic epoxy based on an ASTM E1640, Dynamic Mechanical Analysis (DMA) testing protocol. At lower temperatures, the epoxy remains in a glassy state. At the glass transition temperature, the epoxy becomes leathery and at a higher temperature it behaves like a soft elastic rubber.
Figure 1 (Reference 5)
0CAN092101 Page 4 of 16 V-Wrap' 770 (( ))
Figures 2, 3 and 4 provide (( )) test results for V-Wrap' 770 epoxy (( )). Results from these (( ))
laboratory tests demonstrate that V-Wrap' 770 epoxy ((
)) for the maximum achievable system temperature of 121 °F (Tmax) at ANO. These test temperatures ((( )) °F, (( )) °F and
(( )) °F) bound the design basis, normal operating, and maximum achievable temperatures for this system at ANO which has a typical operating temperature range of 32 °F to 101 °F. The installed CFRP composite system will be cured as determined by ANO specific ((
)). The maximum faulted temperature used for the ANO CFRP composite system design is 121 °F. ANO design basis calculations indicate the system temperature peaks at 120 °F for a short duration of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The ((
)) °F (Minimum). This approach ensures V-Wrap' 770 epoxy ((
)) at ANO using the criterion (( )) °F.
Figure 2 - V-Wrap' 770 epoxy cured at (( )) °F
((
))
0CAN092101 Page 5 of 16 Figure 3 - V-Wrap' 770 epoxy (( )) °F
((
))
0CAN092101 Page 6 of 16 Figure 4 - V-Wrap' 770 epoxy (( )) °F
((
))
Glass Transition Temperature Summary
(( )) are acceptable for ANO.
(( )) for V-Wrap' 770 epoxy (( )) in the initial design process (( )):
(( )) °F.
As demonstrated by (( )) previously performed V-Wrap' 770 epoxy cured at a (( )) and will not behave (( )) at the maximum achievable system temperature of 121°F (Tmax) and satisfies the acceptance criterion:
(( ))
((
0CAN092101 Page 7 of 16
))
Entergy Response Material properties are initially determined to support the (( )) and are included in Enclosure 4, Attachment B of Reference 1, "Material Qualification and Testing",
Tables 1, 2, and 3. These test results represent the ((
)). These tests are performed at ((
)), or at other conditions as specified in the relevant standards.
As presented in Figure 5, below the (( )) requires these ((
)) of (( )) and (( )) to be controlled as ((
)).
Figure 5 (( ))
((
))
(( )) for (( )) are ((
)) as the V-Wrap' CFRP composite system installed in the pipeline. (( )) have demonstrated that ((
0CAN092101 Page 8 of 16
)) the maximum achievable temperature (Tmax = 121 °F) for ANO.
((
))
Entergy Response
(( )) will be performed on the witness panels cured at the ((
)) at those temperatures.
((
))
Entergy Response The information presented at the ASME Code Committee meeting was ((
)) to the V-Wrap' CFRP Composite System proposed at ANO. As discussed in the response to EMIB-2-RAI-1(A) the initial design criterion that uses a margin of (( )) °F is (( )) °F. (( ))
is used to evaluate if V-Wrap' 770 epoxy is suitable for the ANO application by comparing
0CAN092101 Page 9 of 16
(( )) with the ((
)).
(( )) will be used to determine the ((
`
)). V-Wrap' 770 epoxy ((test samples prepared in the field will be cured at a minimum of 90 °F throughout the pipe, and a minimum of 121 °F at the terminal ends)).
V-Wrap 770 epoxy will be verified ((
)) by ((
)). Preliminary data and the (( )) testing methods presented in the ASME Code Committee meeting are representative of the (( )) that will be used for the ANO CFRP composite system.
((
))
Entergy Response When the system is placed in-service, the epoxy will ((
)). See response to EMIB-2-RAI-1(A) which demonstrates based on Tg_Field previous test results V-Wrap' 770 epoxy ((will not transition out of the glassy phase and will not behave in a viscous manner)). The installed CFRP composite system will be cured as determined by ANO ((
` `` )) °F. At the (( )), the installed CFRP composite system will be (( )) °F.
Tests results can be made available.
Tmax of 121 °F at ANO conservatively bounds all of the design basis and severe accident conditions. Typical operating temperature range is 32 °F to 101 °F. Tmax (121 °F) is defined as the faulted maximum achievable ECP Supply system piping water temperature. The maximum faulted achievable temperature of 121 °F is based on calculations that show a temperature peak above 120 °F for a short duration of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
((
0CAN092101 Page 10 of 16
))
Entergy Response
((
)) defined by the ANO design basis conditions to ensure V-Wrap' 770 epoxy remains (( )) the performance criterion
(( )) °F.
((
))
Entergy Response The ((
)). The installed CFRP composite system ((
)) °F. At the
(( )), the installed CFRP composite system ((
)) °F. The cure temperature and durations used in the field will achieve the required minimum 85% degree of cure which will be verified using (( )) testing. Tests results will be available.
((
))
Entergy Response
((
)).
Witness panels will be ((
)). The witness panels ((
))
0CAN092101 Page 11 of 16
((
))
Entergy Response
(( ))
will be tested per the ((
))
((
))
Entergy Response As previously stated in response to EMIB RAI-9 (Reference 4), the ((
)). The (( )) will not be required since the terminal end zones will be (( )).
The design calculations previously submitted in Enclosure 5 of Reference 1 ((
)). See response to EMIB-2-RAI-1(A).
The CFRP repair is acceptable for (( )). This is demonstrated through ((
))
The NRC provided additional requests for information via Reference 7. These additional requests and Entergy's responses are provided below.
((
0CAN092101 Page 12 of 16
))
Entergy Response
(( )):
(( )) in the design process since the design calculations provided in Enclosure 5, Attachment C of Reference 1, "Sample Calculations" (( )) of the CFRP composite.
Overlap Shear Strength:
There are currently ((
)) testing performed for V-Wrap' 770 epoxy indicates that (( )). As described in , Attachment D of Reference 1, "Design Illustrations", ((
)).
Shear Bond Strength (CFRP to Metal)
(( )) at the terminal ends. At the terminal ends the installed CFRP composite system ((
))
((
))
Entergy Response As stated in the response to EMIB-2-RAI-1, at ANO the ((
)) °F. Results of the design basis analysis at ANO calculated Tmax to be 121 °F. ((
)) °F. As shown on Figures 2, 3, and 4, and discussed in the response to EMIB-2-RAI-1, (( )) V-Wrap' 770 epoxy in the
(( )).
0CAN092101 Page 13 of 16 The (( )) specimens will be considered in the ((
)).
The determination of ((
)). There is ((
)).
As shown in the figure below, V-Wrap' 770 epoxy has ((
)). At ANO ((
)). Use of the (( )) Tg from V-Wrap' 770 epoxy ((
))
0CAN092101 Page 14 of 16
((
))
Entergy Response
((
[ `
))
((
))
Entergy Response
((
))
((
))
Entergy Response As necessary to meet ((
)). Structural Technologies has reviewed the ((
)) are provided below. ((
0CAN092101 Page 15 of 16
)).
((
))
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.
0CAN092101 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.
- 5. ((
6.
))
- 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.
- 8. ((
9.
))
Enclosure 3 0CAN092101 Structural Group Application for Withholding Proprietary Information from Public Disclosure (6 pages)
STRUCTURAL GROUP APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE August 26, 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 Alternative to ASME Boiler & Pressure Vessel Code Section Xl 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. NRC email (Thomas Wengert) to Entergy (Robert Clark), dated August 17, 2021 @
6:44 AM, Subject "Proprietary Review of 7/22/21 RAI Response RE: CFRP Alternative Request."
Ladies and Gentlemen:
Structural Group, Inc.,(SGl) has provided certain proprietary information to Entergy Operations, Inc. (Entergy), in connection with a supplemental response by Entergy to EMIB-2-RAI-1 from the U.S. Nuclear Regulatory Commission (NRC). This application requests that the information provided to Entergy related to the NRC's request in Reference 4 for Entergy to review the proprietary portions of the response to EMIB-2-RAI-1 and resubmit with appropriate bracketed redactions in accordance with 10 CFR 2.390 be withheld as SGI proprietary information.
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 Page 1 of 6
disclosure by the NRC and addressing with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390 of the NRC's regulations.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Entergy.
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, MD 21046.
Scott Greenhaus Executive Vice President O (410) 859-6458, M (410) 340-3205 SGreenhaus@structuralqroup.com Page 2 of 6
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 (NRC) regulations and in conjunction with SGI'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 commercial 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 NRC 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 by Entergy (Docket Nos. 50-313 and 50-368) to the NRC's request in Reference 4 to review the proprietary portions of the response to EMIB-2-RAl-1 and resubmit with appropriate bracketed redactions in accordance with 10 CFR 2.390 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 of that system provides a rational basis for maintaining confidentiality and justifies the NRC withholding the information from public disclosure.
Under SGI'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, as follows:
- 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.
- 6) It contains patentable ideas, for which patent protection may be desirable.
Page 3 of 6
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 SGI's competitive position.
- 2) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes SGI's ability to sell products and services involving the use ofthe 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) SGI'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 RAI (EMIB-2-RAI-1) being transmitted by Entergy letter (Docket Nos. 50-313/368) and reflected in SGI'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 Xl 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 ANO 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 SGI'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.
- 2) That SGI can sell support and defense of the technology to their customers in the licensing process.
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- 3) The information requested to be withheld reveals the distinguishing 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 development 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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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 this Affidavit are true and correct to the best of his knowledge, information, and belief.
Scott Greenhaus Executive Vice President Sworn to and subscribed before me this 26th day of August 2021 Page 6 of 6