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Category:Letter
MONTHYEARML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 2024-08-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2022-04-0606 April 2022 Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-22-028, Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-03-18018 March 2022 Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)2021-07-21021 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531) CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components2021-04-28028 April 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)2020-12-29029 December 2020 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099) CNL-20-089, Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)2020-12-21021 December 2020 Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518) CNL-20-059, Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals2020-08-10010 August 2020 Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals CNL-19-122, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights2019-12-17017 December 2019 Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...2019-08-0808 August 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water... CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second2019-07-19019 July 2019 Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information CNL-19-007, Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus2019-01-16016 January 2019 Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results2019-01-16016 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information2018-12-14014 December 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 CNL-18-117, Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-462018-10-17017 October 2018 Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-46 CNL-18-120, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ..2018-10-11011 October 2018 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ... ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-032, Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program2018-03-27027 March 2018 Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program CNL-18-011, Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2018-02-0505 February 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-130, Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For..2017-10-23023 October 2017 Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For.. CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera2017-09-18018 September 2017 Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generati CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-17-035, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information2017-03-0303 March 2017 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information CNL-17-017, Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects2017-02-0303 February 2017 Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-161, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional..2016-10-13013 October 2016 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional.. CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 302016-09-23023 September 2016 Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30 CNL-16-150, Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 312016-09-21021 September 2016 Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 31 CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 72016-09-15015 September 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7 CNL-16-152, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information2016-09-12012 September 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)2016-08-24024 August 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) CNL-16-129, Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 292016-08-0303 August 2016 Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 29 CNL-16-127, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information2016-08-0303 August 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information CNL-16-114, Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate .2016-08-0303 August 2016 Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate . 2024-01-11
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Text
1101 Market Street, Chattanooga, Tennessee 37402
CNL-16-066
April 15, 2016
10 CFR 50.90
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 1
References:
- 1. Letter from TVA to NRC, CNL-15-073, "Application to Modify the Browns Ferry Nuclear Plant, Units 1, and 2 Technical Specifications by Adding New Specification TS 3.3.8.3, 'Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic,' and Unit 3 TS by adding New Specification TS 3.3.8.3, 'Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic,' (BFN-TS-486)," dated September 16, 2015 (ML15260B125)
- 2. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (CAC Nos. MF6738, MF6739, and MF6740)," dated March 21, 2016 (ML16074A126)
By letter dated September 16, 2015 (Reference 1), Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, to revise the BFN, Units 1 and 2, Technical Specifications (TS) by adding a new specification governing the safety func tions for the Emergency Core Cooling System (ECCS) Preferred Pump Logic, Common Accident Signal Logic, and the Unit Priority Re-Trip Logic. In addition, the LAR relocated the BFN, Unit 3 requirements for Common Accident Signal Logic and Unit Priority Re-trip Logic to a new specification governing the safety functions for the Common Accident Signal Logic, and the Unit Priority Re-Trip Logic for consistency with the changes to the BFN, Units 1 and 2 TS.
CNL-16-066 Enclosure 1, Page 1 of 6 ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 TVA Responses to NRC Request for Additional Information: Set 1 Probabilistic Risk Assessment (PRA) Licensing Branch (APLA) RAI 1
The LAR does not appear to clearly indicate the proposed risk-informed TS changes.
Please summarize which TS Limiting Conditions of Operation (LCOs) and Conditions or Surveillance Requirements, are being proposed as risk-informed TS changes and have been evaluated using PRA for this LAR.
TVA Response The Completion Time of proposed Browns Ferry Nuclear Plant (BFN), Units 1 and 2 Technical Specification (TS) 3.3.8.3, Condition A for one or more inoperable divisions of Emergency Core Cooling System (ECCS) Preferred Pump Logic (PPL) is the only change being proposed as a risk-informed change. The following information is provided to clarify the proposed changes contained in Enclosure, Section 4.3 Technical Analysis of the TVA License Amendment Request (LAR) dated September 16, 2015.
Browns Ferry Nuclear Plant, Units 1 and 2 ECCS PPL The ECCS PPL receives input signals from TS Table 3.3.5.1-1, Core Spray (CS)
Functions 1a, 1b, and 1c and Low Pressure Coolant Injection (LPCI) Functions 2a, 2b, and 2c.
In the event one or more required channels specified in TS Table 3.3.5.1-1 is found to be inoperable, current TS 3.3.5.1, Condition A requires immediately entering the Condition referenced in Table 3.3.5.1-1 for the affected channel(s). The two Conditions specified by TS Table 3.3.5.1-1 associated with CS Functions 1a, 1b, and 1c and LPCI Functions 2a, 2b, and 2c are Conditions B and C.
TS Table 3.3.5.1-1 references Condition B for CS Functions 1.a and 1.b, and LPCI Functions 2.a and 2.b during operation in Modes 1, 2, and 3, and CS Functions 1.a and 1.c and LPCI Functions 2.a and 2.c during operation in Modes 4 and 5 when the associated subsystem(s) are required to be operable. TS Table 3.3.5.1-1 references Condition C for CS Function 1.c and LPCI Function 2.c during operation in Modes 1, 2, and 3.
TS 3.3.5.1, Condition B requires placing the channel in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in Modes 4 and 5, when the associated subsystem(s) are required to be operable. In addition, TS 3.3.5.1, Condition B requires declaring the supported ECCS feature(s) inoperable when the redundant feature ECCS initiation capability is inoperable within one hour from discovery of loss of initiation capability for features in both divisions.
CNL-16-066 Enclosure 1, Page 2 of 6 TS 3.3.5.1, Condition C requires restoring the channel to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In addition, TS 3.3.5.1, Condition C requires declaring the supported ECCS feature(s) inoperable when the redundant feature ECCS initiation capability is inoperable within one hour from discovery of loss of initiation capability for features in both divisions.
In the event the Required Action and associated Completion Time of TS 3.3.5.1, Conditions B and C are not met, TS 3.3.5.1, Condition H requires immediately declaring the associated support ECCS feature(s) inoperable. Therefore, Required Action of TS 3.3.5.1, Condition H requires entry into the appropriate Conditions of TS 3.5.1, during operation in Modes 1, 2, and 3, or TS 3.5.2, during operation in
Modes 4 and 5.
With one low pressure ECCS injection/spray subsystem inoperable during operation in Modes 1, 2, and 3, TS 3.5.1, Condition A requires restoring the affected ECCS injection/spray subsystem to operable status within seven days. With two or more low pressure ECCS injection/spray subsystem inoperable during operation in
Modes 1, 2, and 3, TS 3.5.1, Condition H requires immediate entry into Limiting Condition for Operation (LCO) 3.0.3.
With one required low pressure ECCS injection/spray subsystem inoperable during operation in Modes 4 and 5, except with the spent fuel storage pool gates removed
and water level 22 feet over the top of the reactor pressure vessel flange, TS 3.5.2, Condition A requires restoring the required ECCS injection/spray subsystem to operable status within four hours.
With two required ECCS injection/spray subsystems inoperable during operation in Modes 4 and 5, except with the spent fuel storage pool gates removed and water
level 22 feet over the top of the reactor pressure vessel flange, TS 3.5.2, Condition C requires that action be initiated immediately to suspend operations that could result in draining the reactor vessel and restoring one ECCS injection/spray subsystem to operable status within four hours.
The proposed TS 3.3.8.3, Condition A allows one or more required ECCS PPL divisions to be inoperable for seven days before restoration to operable status. This is a less restrictive requirement than currently specified by TS 3.3.5.3, Conditions B and C. Therefore, the proposed TS 3.3.8.3, Condition A Completion Time is considered risk-informed.
During operation in Modes 1, 2, and 3, proposed TS 3.3.8.3, Condition D requires placing the unit in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, if the Required Action and associated Completion Time of TS 3.3.8.3, Condition A are not met. This is a more restrictive requirement than currently required by TS 3.3.5.3, Condition H. Therefore this change is not risk-informed.
During operation in Modes 4 and 5 with the opposite unit in Modes 1, 2, or 3, proposed TS 3.3.8.3, Condition E requires immediately declaring the associated ECCS components inoperable, if the Required Action and associated Completion Time of TS 3.3.8.3, Condition A are not met. TVA letter dated September 16, 2015, Enclosure, Section 4.3 provides the justification for why the requirement for the opposite unit to be in Modes 1, 2, or 3 is added to the Condition. This change is not
risk-informed.
CNL-16-066 Enclosure 1, Page 3 of 6 The proposed SR 3.3.8.3.1 is consistent with the existing Logic System Functional Test required currently specified by SR 3.3.5.1.6. The six-hour allowance in the proposed SR 3.3.8.3.1, Note 1 is also consistent with the current Note 2 allowance of the TS 3.3.5.1 Surveillance Requirements table. The allowance to not require actuation of breakers in the opposite unit provided in the proposed SR 3.3.8.3.1, Note 2 is necessary to preclude unnecessary challenges to an operating unit.
Actuation of the associated breakers on the opposite unit will be performed by the opposite unit's Logic System Functional Test. Therefore, the changes incorporating SR 3.3.8.3.1, the six-hour allowance, and the allowance to not require actuation of breakers in the opposite unit are not risk-informed changes.
BFN Units 1, 2, and 3 Common Accident Signal (CAS) and Unit Priority Re-Trip Logics The proposed changes relocating the requirements for CAS from the current Units 1, 2, and 3, TS 3.8.1 to the proposed Units 1, 2, and 3, TS 3.3.8.3 are administrative in that no technical changes are made to the LCO, Mode of Applicability, Conditions, Required Actions and Completion Times. Therefore, the relocation of the CAS requirements is not a risk-informed change.
The proposed changes providing explicit requirements for the Unit Priority Re-Trip Logic are not risk informed. The proposed changes are administrative in that the Unit Priority Re-Trip Logic is currently described in the TS 3.8.1 Bases Background discussion in the discussion of the CAS Signal Logic. The proposed change proposes the same Conditions, Required Actions, and Completion Times for the Unit Priority Re-Trip Logic as those currently specified in TS 3.8.1 for the CAS Logic.
The proposed SR 3.3.8.3.1 is consistent with the existing Logic System Functional Test required currently specified by SR 3.3.5.1.6. The six-hour allowance in the proposed SR 3.3.8.3.1 is also consistent with the current Note 2 allowance of the TS 3.3.5.1 Surveillance Requirements table. Therefore, the change incorporating SR 3.3.8.3.1 and the six-hour allowance is not a risk-informed change.
In summary, the only change that is considered to be risk-informed is the Completion Time of proposed BFN, Units 1 and 2 Technical Specification (TS) 3.3.8.3, Condition A for one or more inoperable divisions of ECCS PPL. This proposed Completion Time has been
evaluated using PRA for this LAR.
APLA RAI 2 Explain the equipment impact of the PPL unavailabilities allowed by the proposed TS change and how it is modeled in the internal events PRA. Include an explanation of same unit and opposite unit equipment impacts. Indicate whether the PRA evaluates single and multiple unit risk for the PPL unavailabilities and is included in the PRA results.
TVA Response A single event is used to model unavailability of PPL and this basic event is used for both BFN Units 1 and 2. The ECCS PPL unavailability basic event is included under the PPL logic for Low Pressure Injection (LPI), i.e., Unit 1 Residual Heat Removal (RHR) pumps 1A and 1C, and Unit 1 CS pumps 1A and 1C, or Unit 2 RHR pumps 1B and 1D, and Unit 2 CS
pumps 2B and 2D. Similarly, a single event is used for ECCS PPL failure on demand (i.e., the conservative approach taken did not include divisional ECCS PPL relays, or unavailability events). In addition, a spurious ECCS PPL event is included in the model. The logic is set up such that the pumps assigned divisionally for ECCS PPL (i.e., Unit 1 CNL-16-066 Enclosure 1, Page 4 of 6 RHR pumps 1A and 1C and Unit 1 CS pumps 1A and 1C, or Unit 2 RHR pumps 2B and 2D and Unit 2 CS pumps 2B and 2D) are assumed to be failed if ECCS PPL is unavailable and simultaneous loss of coolant accident (LOCA) signals occur in both units. The remaining RHR or CS pumps in a unit (not ECCS PPL) are assumed to fail if simultaneous signals occur. The logic is applicable in fast acting scenarios (e.g., Large LOCA, Medium LOCA, Small LOCA without high pressure injection (HPI), Break Outside Containment). The PRA Model does not include "bus separation" given ECCS PPL failure. However, in the remaining scenarios, the board and loads can be realigned because core damage would take over 36 minutes (i.e., without any injection), or many hours if steam driven HPI systems are available. The impact of single and multiple unit initiators is evaluated for Unit 1 and Unit 2. The following table lists the pumps of interest in the PRA ECCS PPL logic, and impact of ECCS PPL logic on Unit 1 and Unit 2.
Pump Shutdown Board (SDBD) Unit 1 Unit 2 Notes RHR 1A 4kV SDBD A PPL RHR 1C 4kV SDBD B PPL RHR 1B 4kV SDBD C Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur RHR 1D 4kV SDBD D Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur CS 1A 4kV SDBD A PPL CS 1C 4kV SDBD B PPL CS 1B 4kV SDBD C Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur CS 1D 4kV SDBD D Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur RHR 2A 4kV SDBD A Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur RHR 2C 4kV SDBD B Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur RHR 2B 4kV SDBD C PPL RHR 2D 4kV SDBD D PPL CS 2A 4kV SDBD A Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur CS 2C 4kV SDBD B Not PPL PRA assumes failure of this pump if simultaneous LOCA signals occur CS 2B 4kV SDBD C PPL CS 2D 4kV SDBD D PPL APLA RAI 3 Explain whether PPL unavailabilities could result in no low pressure injection (as well as no high pressure injection) following a LOCA (to include feedwater and steamline break). If so, explain the plant's defense-in-depth for the LOCA scenario.
TVA Response HPI systems are not affected by ECCS PPL, but may not be available if the reactor pressure vessel depressurizes quickly because the HPI systems use steam driven pumps. Initiator impact is modeled under the HPI system logic t hat would automatically fail HPI. The PRA ECCS PPL logic model is included under RHR or CS logic as described in the TVA response to APLA-RAI-2. ECCS PPL unavailability could result in failure of Low Pressure Injection (CS and RHR) during a fast acting LOCA scenario if a coincident spurious or actual accident signal occurs in the other unit. For instance, if ECCS PPL is unavailable and a CNL-16-066 Enclosure 1, Page 5 of 6 LOCA occurs in a unit combined with a simultaneous LOCA signal (real or spurious) in the opposite unit, then the PRA models assume all RHR and CS pumps are not available to mitigate core damage in these fast acting scenarios. These scenarios are assumed to result in core damage because no additional systems are credited (e.g., sequence LLOCA-005).
APLA RAI 8 Prior to the proposed TS change, there was no explicit LCO for UPRTL [Unit Priority Re-Trip Logic]. The LAR states that the LCO for UPRTL is implicitly required by the TS 3.8.1 Condition D, which applied to the CAS. In the proposed TS change for Unit 1 and Unit 2, LCO 3.3.8.3, Condition B applies to CAS and LCO 3.3.8.3, Condition C applies to UPRTL.
For Unit 3, LCO 3.3.8.3, Condition A applies to CAS and LCO 3.3.8.3, Condition B applies to UPRTL. These TS LCO Conditions for the UPRTL have a 7 day completion time and are new proposed changes. If these UPRTL TS LC Os are proposed as risk-informed changes, then include the associated risk for Units 1, 2, and 3 in the results reported in the LAR as part of APLA-RAI-14.
TVA Response The proposed changes providing explicit requirements for the Unit Priority Re-Trip Logic are not risk informed. The proposed changes are considered administrative in that the Unit Priority Re-Trip Logic is currently described in the TS 3.8.1 Bases Background discussion in the discussion of the CAS Signal Logic. The proposed change proposes the same Conditions, Required Actions, and Completion Times for the Unit Priority Re-Trip Logic as those currently specified in TS 3.8.1 for the CAS Logic.
APLA RAI 9 Note 1 to the proposed SR 3.3.8.3.1 states that, "when a division is placed in an inoperable status solely for performance of a surveillance, entry into associated Conditions and Required Actions may be delayed for up to six hours provided the associated redundant division is OPERABLE." The proposed TS Bases state that the "PRA demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly reduce the probability that the ECCS Preferred Pump, CAS and Unit Priority Re-trip Logics will initiate when necessary." If the LAR is justifying the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance time as a risk-informed TS change, then provide the PRA justification for the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance for the ECCS PPL, CAS, and UPRTL. Provide the LAR risk results impact as part of APLA-RAI-14.
TVA Response The six-hour allowance in the proposed SR 3.3.8.3.1 is not a risk-informed change. As stated in the current TS 3.3.5.1 Bases, the allowance is based on the reliability analysis (i.e., NEDC-30936-P-A, "BWR Owners' Group Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Part 2," December 1988) assumption of the average time required to perform channel surveillance. That analysis demonstrated that the six-hour testing allowance does not significantly reduce the probability that the ECCS will initiate
when necessary. The six-hour allowance was incorporated into the PRA when the ECCS PPL was first modeled. However, the six-hour allowance is not changed by the License Amendment Request. The Logic System Functional Test for ECCS PPL, CAS Logic and Unit Priority Re-Trip Logic is currently required by TS 3.3.5.1, SR 3.3.5.1.6. The current Surveillance Requirements Table of TS 3.3.5.1 is modified by Note 2, which states, "When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to six hours for Functions 3.c and 3.f; and (b) for up to six hours for CNL-16-066 Enclosure 1, Page 6 of 6 Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability." ECCS PPL receives input signals from TS Table 3.3.5.1-1, CS Functions 1a, 1b, and 1c and LPCI Functions 2a, 2b, and 2c. CAS Logic receives input from TS Table 3.3.5.1-1, CS Functions 1a, 1b, and 1c. Unit Priority Re-Trip Logic receives input from TS Table 3.3.5.1-1, LPCI Functions 2a, 2b, and 2c. Therefore, the six-hour allowance currently applies to the ECCS PPL, CAS Logic and Unit Priority Re-Trip Logic and is not a change from the current requirements.
CNL-16-066 Enclosure 2, Page 1 of 3 ENCLOSURE 2 Tennessee Valley Authority Browns Ferry Nuclear Plant, Units 1, 2, and 3 Summary of BFN Request for Additional Information Response Dates
CNL-16-066 Enclosure 2, Page 2 of 3 Request for Additional Information (RAI)
Question Number Due Date (NRC Letter dated March 21, 2016)
Revised Due Dates Actual Date of Response Electrical Engineering Branch (EEEB) EEEB RAI 1 April 15, 2016 May 11, 2016 Future Letter EEEB RAI 2 April 15, 2016 May 11, 2016 Future Letter EEEB RAI 3 April 15, 2016 May 11, 2016 Future Letter EEEB RAI 4 April 15, 2016 May 11, 2016 Future Letter Instrumentation and Controls Branch (EICB) EICB RAI 1 April 15, 2016 May 11, 2016 Future Letter EICB RAI 2 April 15, 2016 May 11, 2016 Future Letter EICB RAI 3 April 15, 2016 June 16, 2016 Future Letter Probabilistic Risk Assessment Branch (PRA) Licensing Branch (APLA)
APLA-RAI-1 April 15, 2016 No change CNL-16-066, April 15, 2016 APLA-RAI-2 April 15, 2016 No change CNL-16-066, April 15, 2016 APLA-RAI-3 April 15, 2016 No change CNL-16-066, April 15, 2016 APLA-RAI-4 May 25, 2016 May 11, 2016 Future Letter APLA-RAI-5 May 25, 2016 June 16, 2016 Future Letter APLA-RAI-6i April 15, 2016 May 11, 2016 Future Letter APLA-RAI-6ii April 15, 2016 May 11, 2016 Future Letter APLA-RAI-6iii April 15, 2016 May 11, 2016 Future Letter APLA-RAI-6iv May 25, 2016 June 16, 2016 Future Letter APLA-RAI-7 April 15, 2016 May 11, 2016 Future Letter APLA-RAI-8 April 15, 2016 No change CNL-16-066, April 15, 2016 CNL-16-066 Enclosure 2, Page 3 of 3 Request for Additional Information (RAI)
Question Number Due Date (NRC Letter dated March 21, 2016)
Revised Due Dates Actual Date of Response APLA-RAI-9 April 15, 2016 No change CNL-16-066, April 15, 2016 APLA-RAI-10 April 29, 2016 No change Future Letter APLA-RAI-11 April 29, 2016 No change Future Letter APLA-RAI-12 May 25, 2016 No change Future Letter APLA-RAI-13a May 25, 2016 June 16, 2016 Future Letter APLA-RAI-13b May 25, 2016 No change Future Letter APLA-RAI-13b May 25, 2016 No change Future Letter APLA-RAI-14 May 25, 2016 June 16, 2016 Future Letter APLA-RAI-15 May 25, 2016 No change Future Letter APLA-RAI-16 April 29, 2016 No change Future Letter Summary April 15, 2016: APLA RAI 1, 2, 3, 8, 9 April 29, 2016: APLA RAI 10, 11, 16 May 11, 2016: APLA RAI 4, 6i, 6ii, 6iii, 7; EEEB RAI 1, 2, 3, 4; EICB RAI 1, 2 May 25, 2016: APLA RAI 12, 13b, 13c, 15 June 16, 2016: APLA RAI 5, 6iv,13a, 14; EICB RAI 3