Letter Sequence Response to RAI |
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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: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:Slides and Viewgraphs
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23296A1002023-10-24024 October 2023 Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR ML23223A2032023-08-11011 August 2023 (ANO) Unit 1 Licensee'S Slide Presentation for 8/15/23 Public Meeting Pressurizer Heaters ML22193A0262022-07-12012 July 2022 (ANO) RICT License Amendment Request TSTF-505 NRC Pre-Submittal Meeting Presentation - July 13, 2022 ML22164A8012022-06-13013 June 2022 Entergy Fleet (GGNS, RBS, and WF-3) - Code Case N-752 RR 6-14-22 Pre-Submittal Public Meeting Presentation Slides ML22124A0692022-05-10010 May 2022 RVCH Penetration No. 1 Relief Request Public Meeting May 10, 2022 (EPID L-2022-LRM-0036) (Slides) ML21351A0282021-12-16016 December 2021 Preliminary Information of ANO-1 1R17 (2002) Findings on CRDM Nozzle 56, and Presentation Slides for PT Exam of Nozzle 56 ML21348A1262021-12-14014 December 2021 RCP TS LAR Pre-Submittal Meeting Slides, December 16, 2021 ML21319A2452021-11-15015 November 2021 Natrium Energy Island Decoupling Strategy - 11-17-2021 ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21306A3162021-11-0909 November 2021 Digital IC Presentation 11/09/2021 ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor 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 ML21095A2122021-04-0808 April 2021 Pre-Submittal Meeting - ANO-1 LAR Related to RCS Primary Activity and Primary-to-Secondary Leak Rate ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20315A1582020-11-17017 November 2020 Presentation Meeting Slides for the 11/17/20 Teleconference ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20255A0242020-09-11011 September 2020 (Ano), Pre-Submittal Meeting with NRC - Request to Extend Allowable Outage Time (AOT) for the Emergency Cooling Pond (ECP) ML20211L7052020-08-0404 August 2020 (ANO) Units 1 & 2, Pre-Submittal Slide Presentation for August 4, 2020 Public Meeting ML20114E2752020-04-29029 April 2020 (ANO) Carbon Fiber Reinforced Polymer (Cfrp) Relief Request Pre-Submittal Meeting with NRC - April 29, 2020 ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML18081A1922018-03-20020 March 2018 Presentation at the PRA Workshop ML17328A3652017-11-30030 November 2017 Workshop on Sharing Operating Experience from Rigging, Lifting and Load Handling Events - Temporary Overhead Crane Failure at Arkansas Nuclear One Presented to IAEA ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML15014A0842015-01-14014 January 2015 NRC ANO Unit 1 Stator Drop SDP Evaluation ML14329B2092014-11-25025 November 2014 Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Flood Protection Deficiencies ML14259A5972014-09-16016 September 2014 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance ML14169A0722014-06-19019 June 2014 Entergy Public Meeting Presentation Slides ML13142A2272013-05-22022 May 2013 Summary of Public Meeting to Discuss Results of Augmented Inspection at Arkansas Nuclear One ML12332A1792012-11-26026 November 2012 Power Point Presentation by Entergy at the November 26, 2012 Meeting (TAC No. ME9706.) ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML1218003062012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Power Point Slides ML1202501112012-01-25025 January 2012 Licensee Slides Arkansas Nuclear One, Unit 1 - Steam Generators Tube to Tube Wear ML1126502692011-09-22022 September 2011 Licensee Handouts for 10/05/2011 Presubmittal Meeting ML11221A3212011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 17 ANO-1 Seal Failure ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1107504262011-03-15015 March 2011 Licensee Slides from 3/15/11 Pre-Sumittal Meeting SWS Room Cooling Required Action ML1107504162011-03-15015 March 2011 Licensee Slides from 3/15/11 Meeting with Entergy Operations on Technical Specification Change - Testing of Idle RCS Cooling Loop ML1016705012010-06-17017 June 2010 Discussion of Screening Criteria - Arkansas Nuclear One (ANO) ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0913104172009-05-11011 May 2009 Summary of Meeting with Entergy to Discuss Arkansas Nuclear One 2008 Performance ML0831102062008-11-0606 November 2008 Summary of Meeting with Entergy to Discuss an Open Substantive Crosscutting Issue at Arkansas Nuclear One ML0828000612008-10-0101 October 2008 Enclosure 3-Technical Papers 2 - Plant Application of Weld Onlay for Butt Weld Mitigation ML0828300322008-08-31031 August 2008 NRC Presentation Arkansas Nuclear One - Unit One ML0814306742008-05-22022 May 2008 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One ML0718004262007-06-29029 June 2007 Summary of Arkansas Nuclear One End-Of-Cycle Public Meeting ML0627703242006-10-19019 October 2006 Draft Slide Presentation for Nrc/Entergy/Westinghouse Pre-Submittal Meeting (Non-Proprietary) ML0619203612006-06-30030 June 2006 Storage Project and Spent Fuel Pool - Meeting Slides Meeting - June 2006 2023-08-11
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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 601-368-5102 Phil Couture Sr. Manager, Fleet Regulatory Assurance 10 CFR 2.390 0CAN062101 June 15, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
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, 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), "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 (0CAN052103) (ML21144A087), May 25, 2021.
A meeting between Entergy Operations, Inc. (Entergy), Structural Group, Inc. (SGI), Simpson Gumpertz & Heger, Inc. and the U. S. Nuclear Regulatory Commission (NRC) was held on May 26, 2021, in order to discuss an NRC Request for Additional Information (RAI). The RAI is concerning the proposed alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond piping at Arkansas Nuclear One (ANO).
From preparation of the presentation material to be used in the meeting, it was determined that the material is proprietary to SGI. On that basis, the meeting on May 26, 2021, was closed to the public. The proprietary presentation was provided to the NRC via the referenced submittal.
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.
0CAN062101 Page 2 of 2 In performing the proprietary review of the meeting slides, the NRC staff has determined that Entergy must submit a non-proprietary version of the slides in accordance with the requirements of 10 CFR 2.390 and the NRC staff guidance in LIC-204 Revision 1.
For completeness, the proprietary version of the presentation material used in the meeting is provided in Enclosure 1. These slides are considered proprietary to SGI and are to be withheld from public disclosure in accordance with 10 CFR 2.390 of the Commissions regulations. provides the non-proprietary version of the presentation material in accordance with the NRC's request.
This information is supported by affidavit, signed by Scott Greenhaus, Executive Vice President of SGI, the owners of the information. The affidavits 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 the SGI letter to the NRC entitled, "Application for Withholding Proprietary Information from Public EMIB-2-RAI-1 Pre-submittal Meeting". The SGI 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.
Respectfully, ORIGINAL SIGNED BY PHIL COUTURE PC/rwc
Enclosures:
- 1. Presentation Material for May 26, 2021, Meeting (Proprietary)
- 2. Presentation Material for May 26, 2021, Meeting (Non-Proprietary)
- 3. SGI Application for Withholding Proprietary Information from Public 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 0CAN062101 Presentation Material for May 26, 2021, Meeting (Non-Proprietary)
Entergy Nuclear Arkansas Nuclear One ASME B&PV Code Section XI Material Relief Request EMIB2RAI1 Response PUBLIC VERSION 1
Introductions
- Entergy/Arkansas Nuclear One - Licensee
- Bob Clark, Mark Reid (Regulatory Assurance)
- Terry Freeman, Mike Hedgecock (Projects)
- Vince Bond, Bob Thweatt, Dan Sojka, Ryan Brumwell (Engineering)
- Structural Technologies, LLC - CFRP Composite System
- Anna Pridmore, Emily Cernic, Leo Nadeau, Chris Burton
- Simpson Gumpertz & Heger (SGH) - CFRP Designer
- Rasko Ojdrovic PUBLIC VERSION 2
Agenda Topic Speaker Introductions NRC/ENTERGY Licensee Presentation Reason for Relief Request Definitions/Acceptance Criteria Mechanical Behavior ENTERGY
(( )) Test Results Cure Temperature Material Properties Summary Open Discussion NRC Meeting Adjournment PUBLIC VERSION 3
Reason for the Relief Request
- Piping systems constructed of similar materials and transporting similar water have experienced degradation.
- ASME B&PVC Section XI, Rules for InService Inspection of Nuclear Power Plant Components, Article IWA4000, subparagraph IWA4221(b)(1) states:
An item to be used for repair/replacement activitiesshall meet the Construction Code to which the original item was constructed.
- Entergy/ANO is submitting a relief request in accordance with 10 CFR 50.55a(z)(1) requesting approval to use a CFRP Composite System because CFRP was not a material available for use in the original construction codes (Entergy Letter No.
0CAN072001, dated July 15, 2020, ADAMS ML20218A672).
PUBLIC VERSION 4
Definitions NRC RAI: Explain why the minimum cure temperatures of 90 °F and 121 °F and the resultant Tg values are acceptable, even though the licensees Tg criteria (Tg Tmax + 40 °F) may not be met?
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PUBLIC VERSION 5
Acceptance Criteria for ANO
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PUBLIC VERSION 6
Material Behavior
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PUBLIC VERSION 7
(( )) Test Results
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PUBLIC VERSION 8
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PUBLIC VERSION 9
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PUBLIC VERSION 10
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PUBLIC VERSION 11
Cure Temperatures NRC RAI: Explain why the minimum cure temperatures of 90 °F and 121 °F and the resultant Tg values are acceptable, even though the licensees Tg criteria (Tg Tmax + 40 °F) may not be met?
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PUBLIC VERSION 12
Material Properties NRC RAI: Clarify whether the mechanical properties of the composite materials cured at 90 °F and 121 °F can meet the design criteria specified in Enclosure 4, Attachment B, Table 1, of the license amendment request (such as tensile, flexure and overlap shear strengths) at the maximum temperature (121 °F). If not, discuss why the material properties are acceptable.
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PUBLIC VERSION 13
Design Verification
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PUBLIC VERSION 14
Summary - Cure Temperature Effect
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PUBLIC VERSION 15
Cure Temperature Test Program Objective
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PUBLIC VERSION 16
Test Program
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PUBLIC VERSION 17
Test Sample in the (( ))
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PUBLIC VERSION 18
Conclusions from Test Program
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PUBLIC VERSION 19
Conclusions from Test Program
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PUBLIC VERSION 20
Test Program
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PUBLIC VERSION 21
Test Program
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PUBLIC VERSION 22
Conclusions from Test Program -((
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PUBLIC VERSION 23
Conclusions from Test Program -((
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PUBLIC VERSION 24
Summary
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PUBLIC VERSION 25
Summary
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PUBLIC VERSION 26
Open Discussion PUBLIC VERSION 27
Enclosure 3 0CAN062101 SGI Application for Withholding Proprietary Information from Public (6 pages)
struc*tura1 group May 21 , 2021 U .S. Nuclear Regulatory Commiss ion Document Control Desk 11555 Rockville Pike Rockville, MD20852
Subject:
Application for Withholding Proprietary Information from Public EMIB-2-RAl-1 Pre-submittal Meeting References :
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regu latory Commission (NRC) , "Response to Request for Additional Information - 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, NRC Docket Nos. 50-313 and 50-368 , Entergy letter no. 0CAN02201.
- 2. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Comm ission (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 - Request for Additional Information RE : Proposed Alternative to ASME Code Requirements for the Repair of Emergency Cooling Pond Piping (EPID L-2020-LLR-0104) ," (0CNA012105) .
- 4. NRC (Thomas Wengert) email to Entergy (Riley Keele) , April 26, 2021 at 6:54 AM ,
"ANO-1 and ANO-2 : Final Supplemental RAI RE : Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping (EPID L-2020-LLR-0104)."
Ladies and Gentlemen:
Structural Group, lnc.,(SGI) has provided certain proprietary information to Entergy Operations, Inc. (Entergy) in connection with a pre-submittal meeting to review the response to EMIB-2-RAl-1 provided by the U.S . Nuclear Regulatory Comm ission (USN RC) in Reference 4. This application requests that SGI proprietary information provided in the pre-submittal meeting documents related to EMI B-2-RAl-1 be protected from public disclosure.
The proprietary information for which withholding is being requested is 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 regulations .
struc*tura1 group Accordingly , this letter authorizes the utilization of the accompanying Affidavit by Entergy.
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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, St ctural Group, Inc., 10150 Old Columbia Road , Columbia, MD 21046.
~cerely; Scott Green aus Executive Vice President 0 (410) 859-6458, M (410) 340-3205 SGreenhaus@structuralqroup.com
struc'turc11 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 (NRC) 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 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 documents provided in the Entergy pre-submittal meeting with the USN RC in response to Reference 4 (EM IB-2-RAl-1) include SGI proprietary information and are requested to be protected from public disclosure.
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 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.
- 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
struc'tura1 group 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 publ ic 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 responses to the NRC RAI (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 prov ide 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 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.
- 2) That SGI can sell support and defense of the technology to their customers in the licensing process.
- 3) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by SGI.
- 4) Pub lic disclosure of th is proprietary information is likely to cause substantial harm to the
struclural group 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.
struclural group struc'tural group AFF IDAVIT 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 re true and correct to the best of his knowledge , information , and belief.
Scott Greenhaus Executive Vice President Sworn to and subscribed before me this 17th day of May 2021 N~~
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