Letter Sequence Response to RAI |
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MONTHYEARML14303A0262014-10-29029 October 2014 Letter to K. Manzione Holtec International Request for Withholding Information from Public Disclosure (TAC No. L24954) Project stage: Withholding Request Acceptance ML14308A0152014-11-0303 November 2014 Ltr to S. L. Pyle Request for Exemption from Holtec International Certificate of Compliance No. 1014 Fuel Specification and Loading Conditions at Arkansas Nuclear One Independent Spent Fuel Storage Installation - Request for Additional Info Project stage: Approval 0CAN111405, Response to Request for Additional Information Request for Exemption from Holtec International Certificate of Compliance (CoC) (72-1014) Fuel Specification and Loading Conditions (TAC No. L24954)2014-11-0707 November 2014 Response to Request for Additional Information Request for Exemption from Holtec International Certificate of Compliance (CoC) (72-1014) Fuel Specification and Loading Conditions (TAC No. L24954) Project stage: Response to RAI ML14328A2872014-11-21021 November 2014 E-Mail from B. Bevill to W. C. Allen Arkansas Department of Health'S Review - Ano'S Exemption Request and the NRC Environmental Assessment, November 21, 2014 Project stage: Other ML14346A6512014-12-11011 December 2014 Ltr s L Pyle, Arkansas Nuclear One, EA and Fonsi for Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at ANO ISFSI (72-1014, 72-13) TAC L24954 Project stage: Approval ML14346A6502014-12-11011 December 2014 Encl (Ea/Fonsi) to Ltr s L Pyle, Arkansas Nuclear One, EA and Fonsi for Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at ANO ISFSI (72-1014, 72-13) TAC L24954 Project stage: Approval ML14351A2612014-12-19019 December 2014 Federal Register - Notice of Issuance of Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at Arkansas Nuclear One ISFSI Project stage: Approval ML14353A4662014-12-19019 December 2014 Ltr s L Pyle, Arkansas Nuclear One, Request for Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at ANO ISFSI (72-1014, 72-13) TAC L24954 Project stage: Approval ML14353A4652014-12-19019 December 2014 Encl (Copy of Exemption) to Ltr s L Pyle, Arkansas Nuclear One, Request for Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at ANO ISFSI (72-1014, 72-13) TAC L24954 Project stage: Approval ML14351A2602014-12-19019 December 2014 Memo C K Bladey Re Notice of Issuance of Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at Arkansas Nuclear One ISFSI Project stage: Approval 2014-11-03
[Table View] |
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Category:Exemption from NRC Requirements
MONTHYEARML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML22083A1912022-03-24024 March 2022 Request for Exemption from an Allowable Contents Requirement Contained in the Certificate of Compliance No. 1014 for the HI-STORM 100S Version E Cask ML20304A2862020-11-20020 November 2020 Federal Register Notice for COVID-19 October 2020 Group Exemptions ML20265A0572020-10-0606 October 2020 Temporary Exemption from Biennial Emergency Preparedness Exercise Frequency Requirements of 10 CFR Part 50, Appendix E, Sections IV.F.2.b and IV.F.2.c (EPID L-2020-LLE-0113 (COVID-19)) 0CAN101901, Request for Exemption from Requirements of 10 CFR 72.212(b)(3)2019-10-11011 October 2019 Request for Exemption from Requirements of 10 CFR 72.212(b)(3) ML15056A3672015-03-16016 March 2015 Letter, Exemption from Certain 10 CFR 50.61 and 10 CFR 50, Appendix G Requirements to Allow Use of Alternate Method to Determine Initial Nil Ductility Reference Temperature for Linde 80 Welds ML14346A2102015-01-13013 January 2015 Letter, Exemption from 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors NRC-2015-0008, Exemption from 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactor2015-01-12012 January 2015 Exemption from 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactor ML14346A2402015-01-12012 January 2015 Exemption from 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactor ML14353A4652014-12-19019 December 2014 Encl (Copy of Exemption) to Ltr s L Pyle, Arkansas Nuclear One, Request for Exemption from Holtec Intl CoC No. 1014 Fuel Specification and Loading Conditions at ANO ISFSI (72-1014, 72-13) TAC L24954 0CAN111405, Response to Request for Additional Information Request for Exemption from Holtec International Certificate of Compliance (CoC) (72-1014) Fuel Specification and Loading Conditions (TAC No. L24954)2014-11-0707 November 2014 Response to Request for Additional Information Request for Exemption from Holtec International Certificate of Compliance (CoC) (72-1014) Fuel Specification and Loading Conditions (TAC No. L24954) NRC-2010-0314, Exemption from Requirements of 10 CFR 50.36a(a)(2) Submittal Date for Radioactive Effluent Release Report (TAC ME3548 and ME3549)2010-09-28028 September 2010 Exemption from Requirements of 10 CFR 50.36a(a)(2) Submittal Date for Radioactive Effluent Release Report (TAC ME3548 and ME3549) ML1009205752010-09-28028 September 2010 Exemption from Requirements of 10 CFR 50.36a(a)(2) Submittal Date for Radioactive Effluent Release Report ML1006306762010-03-23023 March 2010 Exemption from 10 CFR Part 73 Physical Security Requirements ML1006306362010-03-23023 March 2010 Letter, Exemption from 10 CFR Part 73, Physical Security Requirements NRC-2010-0111, Exemption from 10 CFR Part 73 Physical Security Requirements (TAC Nos. ME3089 and ME3090)2010-03-23023 March 2010 Exemption from 10 CFR Part 73 Physical Security Requirements (TAC Nos. ME3089 and ME3090) 0CAN031002, Exemption from the Requirements of 10 CFR 50.36a(a)(2) with Regards to Submittal Date for the Radioactive Effluent Release Report2010-03-18018 March 2010 Exemption from the Requirements of 10 CFR 50.36a(a)(2) with Regards to Submittal Date for the Radioactive Effluent Release Report ML0803700122008-03-19019 March 2008 Exemption from Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50, to Allow Use of Optimized ZIRLO-TM as Fuel Rod Cladding Material GO2-06-119, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 72.214 for Dry Cask Storage2006-09-14014 September 2006 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 72.214 for Dry Cask Storage ML0627200702006-09-14014 September 2006 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 72.214 for Dry Cask Storage ML0517904172005-07-25025 July 2005 Exemption from 10 CFR 50.46 and 10 CFR Part 50, Appendix K ML0429601802005-04-15015 April 2005 Arkansas, Units 1 and 2 - Safety Evaluation and Exemption from the Requirements 10 CFR Part 50, Appendix a NL-04-2181, Joseph M. Farley Nuclear Plant, Request for Exemption from 10 CFR 72.124(c) - Criticality Monitors2005-01-19019 January 2005 Joseph M. Farley Nuclear Plant, Request for Exemption from 10 CFR 72.124(c) - Criticality Monitors ML0435102072004-12-0303 December 2004 OCFR50 Appendix a Exemption Request for Steam Trap Isolation Valves ML0330701432003-10-30030 October 2003 CFR 50 Appendix a Exemption Request for Steam Trap Isolation Valves ML0225505592002-09-12012 September 2002 Exemption from Requirements of 10 CFR Part 20, Section 20.1003 Definition of Total Effective Dose Equivalent (TEDE) 2023-11-29
[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:Request for Additional Information (RAI)
MONTHYEARML24031A5622024-01-24024 January 2024 Enclosure 1 -(Public) - Second Round Requests for Additional Information Clarifications ML23324A0942023-12-0606 December 2023 Request for Additional Information ML23283A1242023-11-0202 November 2023 Enclosure 1 (Public) - HI-STORM 100 Amd 18 - 2nd RAI Round ML23257A0402023-09-12012 September 2023 SUNSI and Proprietary Review Determination Email Regarding: Holtec HI-STORM 100 Amd. 18 - Supplemental RAI Responses ML23230B1582023-08-28028 August 2023 Amendment 16 to Certificate of Compliance 1014 for HI-STORM 100 Multipurpose Canister Storage System Request for Additional Information Second Round ML23215A0612023-08-0202 August 2023 Enclosure - Summary of Discussion ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23104A1052023-03-10010 March 2023 NRR E-mail Capture - ANO-2 Final RAI Alternative Request for Life-of-Repair of RVCH Pen. 46 ML23058A1282023-03-0606 March 2023 CoC No.1014 Amendment 18 - RAI Letter (Public) ML23058A1272023-03-0606 March 2023 CoC No.1014 Amendment 18 - Enclosure RAI (Public) ML23019A0672023-01-19019 January 2023 Inservice Inspection Request for Information ML22349A0112022-12-14014 December 2022 NRR E-mail Capture - Final RAI Relief Request ANO1-ISI-035 ML22335A4572022-12-13013 December 2022 Enclosure 1- Amendment 16 to Certificate of Compliance No. 1014 for Hi-Storm 100 Multipurpose Canister Storage System Request for Additional Information Batch 5 ML22297A1252022-10-31031 October 2022 Enclosure 1 - Summary of RAI Discussion Between NRC and Holtec Staff ML22213A1662022-08-0101 August 2022 Information Request, Security IR 2022401 ML22208A0542022-07-26026 July 2022 Request for Information ML22167A1202022-07-0101 July 2022 Amendment No. 16 to Certificate of Compliance No. 1014 for the HI-STORM 100 Multipurpose Canister Storage System - Request for Additional Information First Batch ML22122A2002022-06-23023 June 2022 Enclosure - Request for Supplemental Information - Rsi ML22174A1362022-06-23023 June 2022 NRR E-mail Capture - ANO-2 Final RAI Relief Requests ANO2-ISI-023 Through -028 (EPIDs L-2022-LLR-0022 Through -0027) ML22159A3242022-06-0909 June 2022 Notification of NRC Triennial Heat Exchanger/Sink Performance Inspection (05000313/2022003 and 05000368/2022003) and Request for Information ML22151A3262022-05-31031 May 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22122A2952022-05-0404 May 2022 Notification of Inspection NRC Inspection Report 05000368/2022003 and Request for Information ML22124A2452022-05-0404 May 2022 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI 2 License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22108A1642022-04-18018 April 2022 NRR E-mail Capture - ANO-1: Final RAI License Amendment Request Concerning TS Changes Due to Revised Dose Calculations (L-2021-LLA-0181) ML22034A5482022-02-0303 February 2022 NRR E-mail Capture - Final RAI License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22021B5632022-01-19019 January 2022 Enclosure 2 - NRC Staff Comments on Draft RAI Response ML22020A0822022-01-19019 January 2022 NRR E-mail Capture - ANO-1 and 2 - Final RAI 2 License Amendment Requests to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML21312A0382021-11-0505 November 2021 NRR E-mail Capture - ANO-2 RAI Relief Request ANO2-RR-21-002 ML21299A2652021-11-0303 November 2021 RAI Letter to Holtec_Shielding Moe Topical Report ML21299A2662021-11-0303 November 2021 Enclosure - Moe Topical Report RAIs ML21286A7132021-10-15015 October 2021 ANO2022010 Tfp RFI Stg, Arkansas Nuclear One, Units 1 and 2 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000313/2022010 and 05000368/2022010) and Request for Information ML21273A0672021-09-29029 September 2021 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request to Adopt a Safety Function Determination Program ML21236A3222021-09-19019 September 2021 Request for Information ML21252A0052021-08-20020 August 2021 NRR E-mail Capture - ANO-1 and 2 Final RAI License Amendment Request to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML21217A3302021-08-0505 August 2021 (ANO) Problem Identification and Resolution (PIR) Request for Information Combined ML21204A0842021-07-28028 July 2021 ANO Phase 4 2021013 RFI Gap ML21197A0372021-07-16016 July 2021 NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02 ML21176A1102021-06-29029 June 2021 Moe Fqt Topical Report - Enclosure (Request for Supplemental Information) 0CAN042105, Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description2021-04-30030 April 2021 Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description 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 ML21105A0122021-04-0909 April 2021 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request to Adopt a Safety Function Determination Program ML21071A2172021-03-10010 March 2021 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI Proposed Change to Quality Assurance Program Manual ML21029A1072021-02-18018 February 2021 HI-STORM 100 CoC Renewal Clarification RAIs ML21026A2682021-01-26026 January 2021 Request for Information 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 ML21019A5142021-01-14014 January 2021 March 2021 Emergency Preparedness Exercise Inspection - Request for Information ML20324A6412020-11-19019 November 2020 NRR E-mail Capture - ANO-1 - Final RAI Relief Request ANO1-ISI-034 ML20316A0102020-11-0202 November 2020 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI Concerning Relief Request EN-20-RR-01 ML20262H0752020-09-17017 September 2020 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations ML20260H4762020-09-0909 September 2020 NRR E-mail Capture - ANO-1 Final RAI License Amendment Request to Revise Lov Relay Allowable Values 2024-01-24
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Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 0CAN111405 November 7, 2014 ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information Request for Exemption from Holtec International Certificate of Compliance (CoC) (72-1014) Fuel Specification and Loading Conditions (TAC No. L24954)
Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313, 50-368, 72.13, and 72-1014 License Nos. DPR-51 and NPF-6
Dear Sir or Madam:
Pursuant to 10 CFR 72.7, Specific Exemptions, Entergy Operations (Entergy) requested an exemption from the requirements of 10 CFR 72.212(a)(2) and 10 CFR 72.212(b)(11) for Arkansas Nuclear One (ANO). The regulations require, in part, compliance to the terms and conditions of the Holtec International (Holtec) Certificate of Compliance (CoC) (72-1014).
Specifically, an exemption is requested from Appendix B, Section 2.1 of the Holtec CoC (72-1014), Fuel Specifications and Loading Conditions (Reference 1). Reference 1 was supplemented with an environmental report (Reference 2).
During review of the request, the NRC determined that additional information is needed to complete the technical review of the application. Reference 3 provides the NRCs request for that additional information. The purpose of this submittal is to provide the requested information. See the attached responses.
This letter contains no new commitments.
0CAN111405 Page 2 of 3 Should you have any questions concerning this submittal, please contact me.
Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/rwc
REFERENCES:
- 1. Entergy letter dated October 2, 2014, Request for Exemption from Holtec International Certificate of Compliance (CoC) (72-1014) Fuel Specification and Loading Conditions (0CAN101403)
(ML14279A246, ML14279A247)
- 2. Entergy letter dated October 14, 2014, Applicants Environmental Report Associated with the Request for Exemption from Holtec International Certificate of Compliance (CoC) (72-1014) Fuel Specification and Loading Conditions (TAC No. L24954)
(0CAN101406) (ML14289A239)
- 3. NRC Letter dated November 4, 2014, Request for Exemption from Holtec International Certificate of Compliance No. 1014 Fuel Specification and Loading Conditions at Arkansas Nuclear One Independent Spent Fuel Storage Installation - Request for Additional Information (TAC No. L24954) (ML14308A015)
Attachment:
Response to Request for Additional Information
0CAN111405 Page 3 of 3 cc: Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Ms. Andrea E. George MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Attn: Mr. William Allen MS 14A44 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 0CAN111405 Response to Request for Additional Information
Attachment to 0CAN111405 Page 1 of 2 Response to Request for Additional Information By letter dated October 2, 2014, as supplemented October 14, 2014, Entergy Operations, Inc. (Entergy) submitted a request for exemption from fuel specification and loading conditions in the Holtec International Certificate of Compliance No. 1014, Amendment No. 5, which is employed at their Arkansas Nuclear One Independent Spent Fuel Storage Installation.
Request for Additional Information
- 1. Identify the technical specifications or applicable Final Safety Analysis Report location where there is any specified limit on the MPC surface while it is located in the transfer cask (HI-TRAC).
Page 2 of Attachment 1 to ANO letter 0CAN101403 states that HI-TRAC/MPC annulus temperatures have remained steady at approximately 130°F to 135°F. This temperature monitoring may indicate the user needs to show compliance with an established limit. Therefore, the staff needs to make sure a thermal limit is not been exceeded for the MPC in this configuration.
This information is needed to assure compliance with 10 CFR 72.236(f).
Response
The fuel loading conditions of MPC-24-060 are as follows:
- Total Cask Heat Load = 15.384 kW
- Highest Fuel Bundle Heat Load = 0.823 kW
- Highest Assembly Average Burnup = 44,921.32 MWD/MTU The total MPC heat load and decay heat per storage location in the licensing basis thermal analysis presented in the HI-STORM 100 FSAR bounds the loading conditions specified above. Therefore, the fuel and component temperatures for MPC-24-060 will remain below the temperature limits specified in the FSAR. Although there is no temperature monitoring compliance limit for the as loaded MPC-24-060 conditions required by Amendment 5 of the Holtec Certificate of Compliance (CoC) (i.e., Technical Specifications) , the HI-TRAC/MPC annulus temperature was reported in the exemption request as additional information to show that the MPC was in a steady-state condition.
The HI-TRAC/MPC annulus temperature measurement of 130-135oF for MPC-24-060 does provide some additional insight. The thermal calculation reported in Table 4.5.4 of the FSAR shows that the annulus air temperature is between 455°F (MPC outer shell temperature) and 322°F (HI-TRAC inner shell inner surface). Therefore, the reported temperatures provide additional assurance that the peak clad temperature will remain below the allowable FSAR limit.
Attachment to 0CAN111405 Page 2 of 2
- 2. Clarify the statements None of the rectangular openings in the entire fuel basket are credited in the thermal analysis, so that the deposition of any fuel-related debris such as crud would be bounded. and A fuel pellet in contact with the baseplate would efficiently reject heat to the baseplate through conduction and would continue to be cooled by the thermosiphon natural convection flow through the mouseholes.
The first statement (see Section 2.2.3 of Holtec Report HI-2146265) seems to contradict Page 4.4.-4 of FSAR Section 4.4.1.1.ii.d which states the mouseholes are explicitly modeled, while the second statement (on same report) contradicts the first statement. In addition, the impact of one or more blocked mouseholes, either partially or completely, on the natural convection heat transfer capabilities of the MPC does not appear to have been analyzed in the FSAR. Therefore, since natural convection heat transfer was employed in the HI-STORM thermal model, it is difficult for staff to determine how the statements in the FSAR bound the current as-loaded configuration.
This information is needed to assure compliance with 10 CFR 72.236(f).
Response
The Staff is correct that the thermal model for normal storage conditions explicitly models the mouseholes. As described in Section 4.4.1.1 of the HI-STORM 100 FSAR, Revision 7, the flow area through the mouseholes is understated. For conservatism, only the area of the minimum semi-circular hole is credited in all the thermal models to evaluate normal, off-normal and accident conditions (i.e., the elongated rectangular portion of the hole is completely neglected). The results of the FSAR calculation conclude that the peak fuel cladding temperature is maintained, with the rectangular areas fully blocked. These modeling details are also described in Section 11.2.5 of the FSAR. Therefore, the statement in Holtec Report HI-2146265 None of the rectangular openings in the entire fuel basket are credited in the thermal analysis is appropriately supported by the FSAR. As stated in HI-2146265, the size of the rectangular openings is larger than the possible fuel pellets or cladding pieces; therefore, the current FSAR analyses assumption of partial blockage of MPC basket vent holes described in FSAR Section 11.2.5 bounds the current as-loaded configuration.