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Category:Legal-Affidavit
MONTHYEARML24019A1122023-12-14014 December 2023 Affidavit by Alan B. Meginnis for Presentation Slide Deck Entitled, Modification of Browns Ferry TS to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth Minimizer Inoperable During Reactor Startup, Dated December 2023 ML24019A1722023-12-14014 December 2023 Affidavit by Alan B. Meginnis for ANP-3874P, Revision 2, Browns Ferry Atrium 11 Control Rod Drop Accident Analysis with the AURORA-B CRDA Methodology, Dated March 2021 CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-096, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-09-29029 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-056, Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-04-28028 April 2022 Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-061, Information Transmittal for NRC Confirmatory Calculations Regarding Transition to Atrium 11 Fuel2021-08-0606 August 2021 Information Transmittal for NRC Confirmatory Calculations Regarding Transition to Atrium 11 Fuel CNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535)2021-07-23023 July 2021 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535) CNL-19-125, Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition2019-12-19019 December 2019 Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition CNL-19-117, Extended Power Uprate - Units 1 and 2 Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information2019-12-12012 December 2019 Extended Power Uprate - Units 1 and 2 Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information CNL-19-076, Extended Power Uprate: Unit 1 Replacement Steam Dryer Final Load Definition and Stress Report, Revision 12019-10-10010 October 2019 Extended Power Uprate: Unit 1 Replacement Steam Dryer Final Load Definition and Stress Report, Revision 1 CNL-19-075, Extended Power Uprate - Unit 2 Replacement Steam Dryer Final Load Definition and Stress Report2019-09-19019 September 2019 Extended Power Uprate - Unit 2 Replacement Steam Dryer Final Load Definition and Stress Report CNL-19-042, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Report2019-04-29029 April 2019 Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Report CNL-19-045, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 9, Additional Information Regarding Anticipate Transient Without Scram with ...2019-04-24024 April 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 9, Additional Information Regarding Anticipate Transient Without Scram with ... CNL-19-028, Replacement Steam Dryer Revised Analysis and Limit Curves Report, Supplement 12019-02-14014 February 2019 Replacement Steam Dryer Revised Analysis and Limit Curves Report, Supplement 1 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-19-006, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information2019-01-0202 January 2019 Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information CNL-18-141, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report - Supplemental Information2018-12-14014 December 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report - Supplemental 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-18-131, Extended Power - Uprate Replacement Steam Dryer Core Flow Sweep Report - Supplemental Information2018-11-15015 November 2018 Extended Power - Uprate Replacement Steam Dryer Core Flow Sweep Report - Supplemental Information CNL-18-124, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports2018-10-24024 October 2018 Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports CNL-18-125, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-10-24024 October 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report CNL-18-103, Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041,.2018-09-0606 September 2018 Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041,. CNL-18-106, Extended Power Uprate Replacement Steam Dryer Core Flow Sweep Test Report2018-08-13013 August 2018 Extended Power Uprate Replacement Steam Dryer Core Flow Sweep Test Report CNL-18-081, Request for Review and Approval of Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041, Revision 12018-06-22022 June 2018 Request for Review and Approval of Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041, Revision 1 CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 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-16-056, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information2016-04-0404 April 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information CNL-15-247, Brown Ferry Unit 1, Submittal of Response to NRC Request for Additional Information Re Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506). Enclosure 2 ANP-3458NP Enclose2015-12-28028 December 2015 Brown Ferry Unit 1, Submittal of Response to NRC Request for Additional Information Re Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506). Enclosure 2 ANP-3458NP Enclosed CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 72015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7 CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information2015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information ML15282A2582015-09-17017 September 2015 General Electric Hitachi Affidavits NL-15-169, Browns Ferry, Units 1, 2, and 3, General Electric Hitachi Affidavits2015-09-17017 September 2015 Browns Ferry, Units 1, 2, and 3, General Electric Hitachi Affidavits CNL-15-169, Electric Power Research Institute Affidavit2015-09-14014 September 2015 Electric Power Research Institute Affidavit ML15282A2592015-08-12012 August 2015 Areva Affidavits NL-15-169, Browns Ferry, Units 1, 2, and 3, Areva Affidavits2015-08-12012 August 2015 Browns Ferry, Units 1, 2, and 3, Areva Affidavits CNL-15-103, Enclosure 2, ANP-3414NP Revision 0, Areva RAI Responses for Browns Ferry, Unit 3, Cycle 18 MCPR Safety Limits (Non-proprietary), and Enclosure 3, Affidavit2015-07-0707 July 2015 Enclosure 2, ANP-3414NP Revision 0, Areva RAI Responses for Browns Ferry, Unit 3, Cycle 18 MCPR Safety Limits (Non-proprietary), and Enclosure 3, Affidavit CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical2015-06-0303 June 2015 Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow ML13276A0632013-09-30030 September 2013 Response to Request for Additional Information on Technical Specification Change TS-478 ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML1121500962011-06-0808 June 2011 Appeal of Final Significance Determination of a Red Finding and Reply to a Notice of Violation; EA-11-018 ML1011602992010-04-16016 April 2010 Affidavit of Alan B. Meginnis Regarding Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request ML0902203942009-01-0808 January 2009 Response to Round 23 RAI Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate, Enclosure 2 - Structural Integrity Associates, Inc. Calculation Package 0006982.304, Revision 1 and Encls 4 and 5 ML0807104982008-03-0606 March 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Change TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 16 Request for Additional Information (RAI) - SRXB-74/86 and SRXB-87 Through SRXB-90 ML0721303712007-07-27027 July 2007 Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate - Steam Dryer Evaluations ML0621700042006-08-21021 August 2006 Proprietary Letter, Request for Withholding Information on EPU Round 3 (TS-431) ML0619506702006-07-0606 July 2006 Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Response to NRC Round 6 Request for Additional Information on GE Methods ML0613004362006-05-0505 May 2006 Transmittal of Browns Ferry, Units 1, 2 & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Steam Dryer Stress Report ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference ML0517201312005-07-0101 July 2005 Enclosure, Framatone Non-Propreitary Presentation 2023-12-14
[Table view] Category:Letter type:CNL
MONTHYEARCNL-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 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 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 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 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal 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-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 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-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) 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-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-105, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 222022-11-0808 November 2022 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22 CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-096, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-09-29029 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-083, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). 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-22-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322022-08-22022 August 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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-22-076, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel2022-07-28028 July 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel 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-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) 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-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-01-17
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Proprietary Information - Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from Enclosures 2, 4, and 6 1101 Market Street, Chattanooga, Tennessee 37402 CNL-21-061 August 6, 2021 10 CFR 50.4 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:
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Information Transmittal for NRC Confirmatory Calculations Regarding Transition to ATRIUM 11 Fuel
Reference:
TVA Letter to NRC, CNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant, Units 1, 2, and 3, in Support of ATRIUM 11 Fuel Use at Browns Ferry (TS-535), dated July 23, 2021 (ML21204A128 and ML21204A129)
By the referenced letter dated July 23, 2021, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed license amendment revises Technical Specification 5.6.5.b to allow application of Advanced Framatome Methodologies for determining core operating limits in support of loading Framatome fuel type ATRIUM 111.
The Nuclear Regulatory Commission (NRC) has requested certain information for the purposes of performing Anticipated Transient Without Scram with Instability (ATWS-I) confirmatory calculations using the TRACE computer code. The majority of the information requested was provided in the LAR; this transmittal provides requested information that was not included in the LAR. contains a roadmap for the information provided. Enclosure 2 contains FS1-0056904, Browns Ferry ATRIUM 11 LAR Flux Map, which provides regional flux maps and eigenvalues for exposure points of interest. Enclosure 4 contains FS1-0035159, Framatome U.S. BWR Fuel Assembly Weight Calculation for ATRIUM 11 Family of Fuel 1
ATRIUM 11 is a trademark or registered trademarks of Framatome, Inc., its affiliates and/or its subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
Proprietary Information - Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from Enclosures 2, 4, and 6
Proprietary Information - Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from Enclosures 2, 4, and 6 U.S. Nuclear Regulatory Commission CNL-21-061 Page 2 August 6, 2021 Designs, which provides ATRIUM 11 spacer grid information. Enclosure 6 contains drawings with fuel rod and channel box mechanical designs. Enclosures 2, 4, and 6 are proprietary in their entirety. Framatome, as owner of the proprietary information, has executed the affidavits provided in Enclosures 3, 5, and 7, which identify the information as proprietary, is customarily held in confidence, and should be withheld from public disclosure in accordance with 10 CFR 2.390. Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Framatome affidavits should reference the corresponding report and should be addressed to Alan Meginnis, Framatome, Manager, Product Licensing, 2101 Horn Rapids Road, Richland, Washington 99354.
There are no new regulatory commitments in this letter. Please address any questions regarding this submittal to Kimberly D. Hulvey, Senior Manager, Fleet Licensing, at (423) 751-3275.
Respectfully, for James T. Polickoski Director, Nuclear Regulatory Affairs Enclosures
- 1. Roadmap for Framatome Input Data for NRC TRACE Analysis
- 2. FS1-0056904 Revision 1, Browns Ferry ATRIUM 11 LAR Flux Map, Framatome Inc., June 2021 (proprietary)
- 3. Affidavit for Enclosure 2
- 4. FS1-0035159 Revision 7.0, Framatome U.S. BWR Fuel Assembly Weight Calculation for ATRIUM 11 Family of Fuel Designs, Framatome Inc., March 2021.
(proprietary)
- 5. Affidavit for Enclosure 4
- 6. Fuel Rod and Channel Box Drawings (proprietary)
FS1-0036099, Revision 1, "FLFR Non-Liner Cladding," February 2018 FS1-0036100, Revision 1, "LPLFR Non-Liner Cladding," February 2018 FS1-0036101, Revision 1, "SPLFR Non-Liner Cladding," February 2018 FS1-0014017 Revision 4, "Fuel Channel," June 2019 FS1-0014478 Revision 4, "Fuel Channel Weldment," September 2020
- 7. Affidavit for Enclosure 6 cc (Enclosure):
NRC Regional Administrator - Region II NRC Project Manager - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Browns Ferry Nuclear Plant Proprietary Information - Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from Enclosures 2, 4, and 6
ENCLOSURE 1 Roadmap for Framatome Input Data for NRC TRACE Analysis CNL-21-061
Enclosure 1 The roadmap below provides information requested by the Nuclear Regulatory Commission for the purposes of performing Anticipated Transient Without Scram with Instability confirmatory calculations using the TRACE computer code.
- 1. Equilibrium cycle design is provided in Reference 1.
- 2. Statepoint data is provided in Reference 1.
- 3. Beginning of Cycle/End of Cycle burnup and power maps are provided in Reference 1.
- 4. Lattice configurations are provided in Reference 2.
- 5. Fuel assembly thermal-hydraulic design The Browns Ferry ATRIUM 11 assembly thermal hydraulic design is the same as the Brunswick design. Note that plant parameters, such as the fuel support orifice sizing, are not necessarily equivalent between the Browns Ferry and Brunswick units.
- 6. Fuel rod and channel box material and mechanical design Fuel Rod Mechanical Designs are provided in References 3, 4, and 5.
Fuel Channel Designs are provided in References 6 and 7.
Fuel rod material, end cap material, plenum spring material, part length fuel rod Plenum Spacer material, and pellet material are specified in Reference 9.
Fuel Channel Material is specified in Reference 9.
- 7. The first flux harmonic shape and eigenvalue separation for the time in cycle of peak hot excess reactivity is provided in Reference 8.
- 8. Spacer grid material and masses are provided in Reference 9.
References:
- 1. ANP-3854P Revision 1, Browns Ferry ATRIUM 11 Equilibrium Cycle Fuel Cycle Design Report, Framatome Inc. June 2020 (Attachment 6a of LAR (ML21204A128))
- 2. ANP-3850P Revision 0, Browns Ferry ATRIUM 11 Equilibrium Cycle Nuclear Fuel Design Report, Framatome Inc. May 2020 (Attachment 7a of LAR (ML21204A128))
- 3. FS1-0036099 Revision 1, FLFR Non-Liner Cladding, Framatome Inc.
February 2018 (provided in Enclosure 6)
- 4. FS1-0036100 Revision 1, LPLFR Non-Liner Cladding, Framatome Inc.
February 2018 (provided in Enclosure 6)
- 5. FS1-0036101 Revision 1, SPLFR Non-Liner Cladding, Framatome Inc.
February 2018 (provided in Enclosure 6)
CNL-21-061 E1 1 of 2
Enclosure 1
- 6. FS1-0014017 Revision 4, Fuel Channel, Framatome Inc. June 2019 (provided in Enclosure 6)
- 7. FS1-0014478 Revision 4, Fuel Channel Weldment, Framatome Inc.
September 2020 (provided in Enclosure 6).
- 8. FS1-0056904 Revision 1, Browns Ferry ATRIUM 11 LAR Flux Map, Framatome Inc. June 2021 (provided in Enclosure 2)
- 9. FS1-0035159 Revision 7.0, Framatome U.S. BWR Fuel Assembly Weight Calculation for ATRIUM 11 Family of Fuel Designs, Framatome Inc. March 2021 (provided in Enclosure 4)
CNL-21-061 E1 2 of 2
Proprietary Information - Withhold Under 10 CFR 2.390 ENCLOSURE 2 FS1-0056904 Revision 1, Browns Ferry ATRIUM 11 LAR Flux Map, Framatome Inc.,
June 2021 Proprietary Information - Withhold Under 10 CFR 2.390 CNL-21-061
ENCLOSURE 3 Affidavit for Enclosure 2 CNL-21-061
AFFIDAVIT
- 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
- 3. I am familiar with the Framatome information contained in the report FS1-0056904, Revision 1, "Browns Ferry ATRIUM 11 LAR Flux Map," dated June 2021 and referred to herein as "Document." Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information. "
- 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
(a) The information reveals details of Framatome's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to Significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
(e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
- 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: June 14, 2021
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Alan B. Megin~ tl
Proprietary Information - Withhold Under 10 CFR 2.390 ENCLOSURE 4 FS1-0035159 Revision 7.0, Framatome U.S. BWR Fuel Assembly Weight Calculation for ATRIUM 11 Family of Fuel Designs, Framatome Inc., March 2021 Proprietary Information - Withhold Under 10 CFR 2.390 CNL-21-061
ENCLOSURE 5 Affidavit for Enclosure 4 CNL-21-061
AFFIDAVIT
- 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
- 3. I am familiar with the Framatome information contained in the report FS1-0035159 Revision 7, "Framatome U.S. BWR Fuel Assembly Weight Calculation for ATRIUM 11 Family of Fuel Designs," dated March 2021 and referred to herein as "Document."
Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) 'Trade secrets and commercial or financial information. "
- 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
(a) The information reveals details of Framatome's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
(e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
- 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: June 14, 2021 11- ~-. '--
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Alan B. Meginnis ~
Proprietary Information - Withhold Under 10 CFR 2.390 ENCLOSURE 6 Fuel Rod and Channel Box Drawings FS1-0036099, Revision 1, "FLFR Non-Liner Cladding," February 2018 FS1-0036100, Revision 1, "LPLFR Non-Liner Cladding," February 2018 FS1-0036101, Revision 1, "SPLFR Non-Liner Cladding," February 2018 FS1-0014017 Revision 4, "Fuel Channel," June 2019 FS1-0014478 Revision 4, "Fuel Channel Weldment," September 2020 Proprietary Information - Withhold Under 10 CFR 2.390 CNL-21-061
ENCLOSURE 7 Affidavit for Enclosure 6 CNL-21-061
AFFIDAVIT
- 1. My name is Alan B. Meginnis. I am Manager, Product licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
- 3. I am familiar with the Framatome information contained in the Drawings, FS1-0036099, Revision 1, "FLFR Non-Liner Cladding," dated February 2018, FS1 0036100, Revision 1, "LPLFR Non-Liner Cladding," dated February 2018, FS1-0036101, Revision 1, "SPLFR Non-Liner Cladding," dated February 2018, FS1-0014017 Revision 4, "fuel Channel,"
Dated June 2019, and FS1-0014478 Revision 4, "Fuel Channel Weldment," Dated September 2020 referred to herein as "Documents." Information contained in these Documents has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
- 4. These Documents contain information of a proprietary and confidential nature and are of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in these Documents as proprietary and confidential.
- 5. These Documents have been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in these Documents be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure
is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
- 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
(a) The information reveals details of Framatome's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
(e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
The information in these Documents is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.
- 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in these Documents have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: June 14, 2021