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Category:Letter type:CNL
MONTHYEARCNL-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 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-013, Cycle 22 Reload Analysis Report2024-03-14014 March 2024 Cycle 22 Reload Analysis Report CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 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 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-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report 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-23-024, 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-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding 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-23-019, 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) 2024-05-08
[Table view] Category:Technical Specification
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-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-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-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-22-008, 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) ML21335A0672021-11-26026 November 2021 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions ML24019A1192021-04-0808 April 2021 Technical Specification 3.1.6, Rod Pattern Control CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-062, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 12018-04-19019 April 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 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 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus ML18066A1202018-02-20020 February 2018 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions - Updated CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change2016-10-31031 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information CNL-16-073, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information2016-04-22022 April 2016 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information CNL-15-240, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information2015-11-13013 November 2015 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..2015-09-25025 September 2015 Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In.. NL-15-169, Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 32015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 3 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 42015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1692015-09-21021 September 2015 Proposed Technical Specification Markups, Part 2 of 2 ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 52015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1802015-09-21021 September 2015 Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1782015-09-21021 September 2015 Retyped Proposed Technical Specifications Changes, Attachment 3 ML15282A1672015-09-21021 September 2015 License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes ML15282A1792015-09-21021 September 2015 Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1662015-09-21021 September 2015 Proposed Technical Specification Markups, Part 1 of 2 CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)2015-03-0606 March 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499) CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)2015-02-17017 February 2015 Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479) CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML12242A4772012-08-28028 August 2012 License Amendment Request to Change Technical Specifications to Delete References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25 Percent Extension of Surveillance Intervals to Accel ML1106004082011-02-25025 February 2011 Technical Specification Change TS-429 - Deletion of Low Pressure Coolant Injection Motor-Generator Sets ML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D ML1024305282010-08-27027 August 2010 Technical Specifications Change TS-474 - Request to Add TS 3.7.3, Control Room Emergency Ventilation (Crev) System, Action to Address Two Crev Subsystems Inoperable Due to Inoperable Crev System High Efficiency Particulate ML1005507002010-02-18018 February 2010 Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D ML0933506552009-11-17017 November 2009 Technical Specification Change TS-467-S - Utilization of Areva Fuel & Associated Analysis Methodologies - Non EPU Supplement ML0930801582009-10-23023 October 2009 Technical Specification Change TS-467 - Utilization of Areva Fuel and Associated Analysis Methodologies ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0922904712009-08-11011 August 2009 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation ML0921101192009-07-27027 July 2009 Technical Specifications Change 465 - Revision of Technical Specifications to Eliminate Unnecessary Water Local Leak Rate Tests 2023-03-10
[Table view] Category:Bases Change
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-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-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) ML21335A0672021-11-26026 November 2021 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 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 ML18066A1202018-02-20020 February 2018 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions - Updated CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change2016-10-31031 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates CNL-16-073, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information2016-04-22022 April 2016 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information CNL-15-240, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information2015-11-13013 November 2015 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..2015-09-25025 September 2015 Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In.. CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML1106004082011-02-25025 February 2011 Technical Specification Change TS-429 - Deletion of Low Pressure Coolant Injection Motor-Generator Sets ML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D ML1024305282010-08-27027 August 2010 Technical Specifications Change TS-474 - Request to Add TS 3.7.3, Control Room Emergency Ventilation (Crev) System, Action to Address Two Crev Subsystems Inoperable Due to Inoperable Crev System High Efficiency Particulate ML1005507002010-02-18018 February 2010 Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D ML0922904712009-08-11011 August 2009 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation ML0921101192009-07-27027 July 2009 Technical Specifications Change 465 - Revision of Technical Specifications to Eliminate Unnecessary Water Local Leak Rate Tests ML0915400152009-05-29029 May 2009 Technical Specifications Changes TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 24 Request for Additional Information (RAI) EMCB.209 Regarding Steam Dryer Analyses ML0912000642009-04-24024 April 2009 Technical Specifications Change 464 - Application for Technical Specification Improvement to Adopt Technical Specification Task Force TSTF-476, Rev. 1, Improved BPWS Control Rod Insertion Process ML0904402062009-02-0909 February 2009 Response for Additional Information Regarding - Technical Specifications (TS) Change 444 - Adoption of Changes to Standard Technical Specifications Under Technical Specification Task Force (Tstf). ML0836501092008-12-22022 December 2008 Technical Specifications Change 463-T, One-time Extension of Surveillance Requirements (Srs) ML0835306192008-12-15015 December 2008 Technical Specifications Change TS-431 - Extended Power Uprate - Response to Round 22 Request for Additional Information - Unit 1 Large Transient Testing (Ltt) - ML0829602272008-10-17017 October 2008 Technical Specifications Change TS-418 - Extended Power Uprate - Response to Round 21 Request for Additional Information on Channel Bow ML0723602632007-08-31031 August 2007 07-31NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry, Unit 2 and 3, Revision 0 ML0723602622007-08-31031 August 2007 07-30NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry, Unit 1, Revision 0 ML0721303752007-07-31031 July 2007 CDI Report No. 07-05NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 1, Steam Dryer to 250 Hz ML0721303822007-07-31031 July 2007 CDI Report No. 07-06NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 2 & 2 Steam Dryer to 250 Hz ML0721303862007-07-31031 July 2007 CDI Report No. 07-09NP, Revision 0, Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with Inclusion of a Low Frequency Hydrodynamic Contribution ML0721304152007-07-31031 July 2007 CDI Report No. 07-11NP, Revision 0, Dynamics of BWR Steam Dryer Components ML0721304292007-07-31031 July 2007 C.D.I. Technical Memorandum No. 07-26NP, Revision 0, Comparison of Browns Ferry Unit 1 & Unit 2 Main Steam Line Strain Gage / Pressure Readings ML0721304012007-07-31031 July 2007 CDI Report No. 07-10NP, Revision 0, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry, Unit 2, Steam Dryer to 250 Hz ML0710100922007-04-0606 April 2007 (BFN) - Unit 3 - Technical Specifications (TS) Change TS-460-T - Request for One-Time Extension of Allowed Outage Time (AOT) - Emergency Diesel Generator (EDG) 3D ML0706003392007-02-26026 February 2007 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) - Response to Round 12 Request for Additional Information (RAI) ML0628602672006-10-0505 October 2006 Technical Specification Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 10 Request for Additional Information ML0627902302006-10-0303 October 2006 Technical Specifications Changes TS-431 and TS 418 - Extended Power Uprate - Steam Dryer Stress Report, Revision 4 ML0627901402006-10-0202 October 2006 Technical Specifications Change TS-443 - Request for Additional Information (RAI) Regarding Oscillation Power Range Monitor ML0629201562006-09-13013 September 2006 Rev 1 to Technical Specification, NPSH Transient Study RHR and Core Spray Pumps, E12.5.1296 ML0617803082006-06-15015 June 2006 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 5 Request for Additional Information ML0625103852006-05-31031 May 2006 Enclosure 3, Browns Ferry, Units 1, 2 & 3 - CDI Report No. 05-28P, Rev 1, Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements. ML0613004432006-05-31031 May 2006 GE-NE-0000-0053-7413-R0-NP, Browns Ferry, Units 1, 2 & 3 Steam Dryer Stress, Dynamic and Fatigue Analyses for EPU Conditions. ML0613004412006-05-31031 May 2006 C.D.I. Report 06-11, Rev 1, Hydrodynamic Loads on Browns Ferry, Unit 1 Steam Dryer to 200 Hz. ML0613601482006-05-11011 May 2006 Supplemental Response to NRC Round 3 Request for Additional Information Related to Technical Specifications Change No. TS-418 - Extended Power Uprate Operation 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 ML0606203282006-02-28028 February 2006 Technical Specifications (TS) Change TS-431 - Response to Request for Additional Information SPSB-A.11 Regarding Extended Power Uprate - Credit for Net Positive Suction Head 2023-03-10
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Text
Proprietary Information Withhold from Public Disclosure Under 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 1 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-240 November 13, 2015 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:
Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information (CAC Nos. MF4851, MF4852, MF4853)
Reference:
Letter from TVA to NRC, CNL-15-169, "Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)," dated September 21, 2015 By the reference letter dated September 21, 2015, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for the Extended Power Uprate (EPU) of Browns Ferry Nuclear Plant (BFN) Units 1, 2 and 3. The proposed LAR modifies the renewed operating licenses to increase the maximum authorized core thermal power level from the current licensed thermal power of 3458 megawatts to 3952 megawatts. of this letter provides supplemental information regarding recently identified issues with the AREVA analysis code MICROBURN-B2 and the effect of these issues on information provided in the BFN EPU LAR. It is expected that a supplement to the BFN EPU LAR will be submitted by December 15, 2015. The supplement to the BFN EPU LAR will provide revisions to the affected attachments that reflect the resolution of the identified issues.
U.S. Nuclear Regulatory Commission CNL-15-240 Page 2 November 13, 2015 AREVA considers portions of the information provided in Enclosure 1 of this letter to be proprietary and therefore, exempt from public disclosure pursuant to 10 CFR 2.390, Publ ic inspections , exemptions, requests for withholding. An affidavit for withholding information, executed by AREVA, is provided in Enclosure 3. A non-proprietary version of the document is provided in Enclosure 2. Therefore , on behalf of AREVA, TVA requests that Enclosure 1 be withheld from public disclosure in accordance with the AREVA affidavit and the provisions of 10 CFR 2.390.
TVA has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in the reference letter. The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration . In addition, the supplemental information in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed license amendment.
Additionally, in accordance with 10 CFR 50.91 (b)(1 ), TVA is sending a copy of this letter and the non-proprietary enclosures to the Alabama State Department of Public Health.
There are no new regulatory commitments associated with this submittal. If there are any questions or if additional information is needed, please contact Mr. Edward D. Schrull at (423) 751-3850.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 13th day of November 2015.
ice President, Nuclear Licensing
Enclosures:
- 1. Browns Ferry EPU Low Flow Issues Impact (Proprietary) ,
AREVA FS1-0024528 , Revision 1.0, November 2015
- 2. Browns Ferry EPU Low Flow Issues Impact (Non-Proprietary) ,
AREVA FS1-0024530, Revision 1.0, November 2015
- 3. AREVA Affidavit cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama Department of Public Health (w/o Enclosure 1)
Proprietary Information Withhold from Public Disclosure Under 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 1 ENCLOSURE 1 Browns Ferry EPU Low Flow Issues Impact (Proprietary)
AREVA FS1-0024528, Revision 1.0, November 2015
ENCLOSURE 2 FS1-0024530 Revision 1.0, Browns Ferry EPU Low Flow Issues Impact (Non-Proprietary)
IDENTIFICATION REVISION FS1-0024530 1.0 AREVA Front End BG Fuel BL TOTAL NUMBER OF PAGES: 14 Browns Ferry EPU Low Flow Issues Impact ADDITIONAL INFORMATION:
This document is the non-proprietary version of FS1-0024528.
PROJECT DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING Restricted AREVA CATEGORY DTR - Data Report STATUS This document is electronically approved. Records regarding the signatures are stored in the Fuel BU Document Database. Any attempt to modify this file may subject employees to civil and criminal penalties. EDM Object Id: I - Release date (YYYY/MM/DD) : [Western European Time]
RoleROLES This Nametext shall NAMES not be visible - Adjust frames overDate DATES to ensure signature block willOrganization ORGANIZATIONS (YYYY/MM/DD) completely cover this text SIGNATURES
- ULWHU 5,/(<(DUO $5(9$,QF
5HYLHZHU AUTHOR :$1*3HQJ RILEY, Earl $5(9$,QF
5HYLHZHU 7289$11$6*HRUJH $5(9$,QF
REVIEWER
$SSURYHU TOUVANNAS, 6&+1(335REHUW George/WANG, $5(9$,QF
$SSURYHU -25'+(,0'DQLHO Peng $5(9$,QF
APPROVER
$SSURYHU 0(*,11,6$ODQ $5(9$,QF
JORDHEIM, Daniel/SCHNEPP, Robert/MEGINNIS, Alan This text shall not be visible - Adjust frames over to ensure signature block will completely cover this text Exportkennzeichnung AL: N ECCN: 0E001 RELEASE DATA: Die mit "AL ungleich N" gekennzeichneten Güter unterliegen bei der Ausfuhr aus der EU bzw.
innergemeinschaftlichen Verbringung der europischen bzw. deutschen Ausfuhrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten Güter unterliegen der US-Reexportgenehmigungspflicht. Auch ohne Kennzeichen, bzw. bei Kennzeichen "AL: N" oder
"ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendungszweck der Güter, ergeben.
SAFETY RELATED DOCUMENT: 1
Export classification AL: N ECCN: 0E001 Goods labeled with AL not equal to N are subject to European or German export authorization CHANGE CONTROL RECORDS: France: N when being exported within or out of the EU. Goods labeled with ECCN not equal to N are subject USA: Y to US reexport authorization. Even without a label, or with label AL: N or ECCN: N, authorization This document, when revised, must be may be required due to the final whereabouts and purpose for which the goods are to be used.
reviewed or approved by the following regions: Germany: N
CW01L Rev. 4.3 - 3/4/15
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 2/14 REVISIONS REVISION DATE EXPLANATORY NOTES 1.0 See 1st page New document release date AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 3/14 Nomenclature 2PT 2 Recirculation Pump Trip APRM Average Power Range Monitor ARTS APRM Rod Block Monitor Technical Specification Improvement BFN Browns Ferry Nuclear Plant BSP Backup Stability Protection CPR Critical Power Ratio CRWE Control Rod Withdrawal Error DIVOM Delta over Initial MCPR Versus Oscillation Magnitude EPU Extended Power Uprate FUSAR Fuel Uprate Safety Analysis Report HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line LAR License Amendment Request LHGRFACf Linear Heat Generation Rate Flow Dependent Adjustment Factors MCPR Minimum CPR MCPRf Flow Dependent MCPR Operating Limits NCL Natural Circulation Line OLMCPR Operating Limit MCPR OPRM Oscillation Power Range Monitor RLA Reload Licensing Analysis SS Steady State AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 4/14 TABLE OF CONTENTS
- 1. PURPOSE AND
SUMMARY
............................................................................................................ 6
- 2. DESCRIPTION OF ISSUES AND EXTENT OF CONDITION .......................................................... 6 2.1. MICROBURN-B2 HYDRAULIC CONVERGENCE AT LOW FLOW CONDITIONS ................ 6 2.2. VOID QUALITY CORRELATION BEHAVIOR AT LOW FLOW CONDITIONS ....................... 7
- 3. EFFECTS TO BFN EPU LAR DOCUMENTATION .......................................................................... 8 3.1. FUEL UPRATE SAFETY ANALYSIS REPORT (FUSAR) ....................................................... 8 3.2. RELOAD LICENSING ANALYSIS (RLA) REPORT FOR THE UNIT 3 CYCLE 19 REFERENCE CYCLE ............................................................................................................. 9
- 4. CONCLUSION ................................................................................................................................ 10 LIST OF TABLES Table 1 FUSAR Equilibrium Cycle - BSP Region Intercepts, Nominal Feedwater Temperature (Table 2.8-2) ........................................................................................................................... 11 Table 2 FUSAR Equilibrium Cycle - BSP Region Intercepts, Reduced Feedwater Temperature (Table 2.8-3) ........................................................................................................................... 11 Table 3 FUSAR Equilibrium Cycle - Option III Setpoints (Table 2.8-1) ............................................... 12 Table 4 RLA Report Representative Cycle - Option III Setpoints (Table 4.3) ..................................... 13 LIST OF FIGURES Figure 1 FUSAR Equilibrium Cycle - Limiting Cycle Specific DIVOM Results (Figure 2.8-3) ............... 14
AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 5/14 REFERENCES
- 1. Letter from J. W. Shea (TVA) to NRC, PROPOSED TECHNICAL SPECIFICATIONS CHANGE TS-505 - REQUEST FOR LICENSE AMENDMENTS - EXTENDED POWER UPRATE, September 21, 2015. (Accession Number ML15282A152)
- 2. Fuel Uprate Safety Analysis Report a) ANP-3403P Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, proprietary version (Attachment 8 of the BFN EPU LAR), AREVA Inc., August 2015.
b) ANP-3403NP Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, non-proprietary version (Attachment 9 of the BFN EPU LAR), AREVA Inc., August 2015.
- 3. Representative Cycle Reload Analysis Report a) ANP-3404P Revision 2, Browns Ferry Unit 3 Cycle 19 Representative Reload Analysis at Extended Power Uprate, proprietary version (Attachment 20 of the BFN EPU LAR), AREVA Inc.,
August 2015.
b) ANP-3404NP Revision 2, Browns Ferry Unit 3 Cycle 19 Representative Reload Analysis at Extended Power Uprate, non-proprietary version (Attachment 21 of the BFN EPU LAR), AREVA Inc., August 2015.
AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 6/14
- 1. Purpose and Summary The purpose of this document is to provide updated results for documentation supplied in support of an Extended Power Uprate (EPU) License Amendment Request (LAR) for the Browns Ferry Nuclear Plant (BFN) (Reference 1). The updated results address the effect of two recently identified issues within the AREVA MICROBURN-B2 core simulator code. Both issues are limited to low flow cases and the only identified effects on the BFN EPU LAR are associated with reactor stability calculations. These effects have been determined to be minor and do not affect any conclusions in the submitted reports.
This document is being provided to facilitate the NRC acceptance review of the BFN EPU LAR by quantifying the magnitude and potential effect of these issues on the previously provided results. AREVA will provide revisions to the affected reports in December 2015. This document provides an interim report on the effect of the identified issues.
- 2. Description of Issues and Extent of Condition The two issues described in this document are being addressed within AREVAs corrective action program. The investigation has not yet been completed for either issue. AREVA has identified solutions to technically address each issue; however, the final corrective actions have not been identified. The results presented in this document have been performed and reviewed by technically qualified individuals, but the supporting analyses have not yet been documented and reviewed according to AREVAs Quality Assurance Program.
The identified issues within MICROBURN-B2 are described in more detail below, but it is noted that both are only a concern in regard to low flow calculations.
x CR2015-7013: Potential hydraulic non-convergence in MICROBURN-B2 at low flow conditions.
x CR2015-7948: Behavior of the MICROBURN-B2 void quality correlation for low flow conditions.
Both issues are part of an active investigation within the AREVA corrective action program. AREVA will revise the affected reports with the new results upon completion of the investigation.
2.1. MICROBURN-B2 Hydraulic Convergence at Low Flow Conditions Condition report CR2015-7013 identifies that at some low flow conditions (i.e., below 50% rated core flow), the MICROBURN-B2 code hydraulic convergence might not be sufficient to ensure the accuracy of the resulting solutions. An evaluation was performed on existing analyses with statepoints in this flow range to determine whether the solutions were hydraulically converged. No unconverged solutions were identified above 40% rated core flow for Browns Ferry.
AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 7/14 For the BFN EPU LAR, the potentially affected analyses include:
x Stability Option III Delta over Initial MCPR Versus Oscillation Magnitude (DIVOM) calculations x MICROBURN-B2/STAIF calculations for Backup Stability Protection (BSP) x Oscillation Power Range Monitor (OPRM) Setpoint Analyses x Flow Runup Analyses including both flow dependent Linear Heat Generation Rate adjustment factors (LHGRFACf) and flow dependent operating limits (MCPRf) x Transients, infrequent events, or design basis accidents in which MICROBURN-B2 is used to set the initial conditions.
x Low power/flow ARTS* Control Rod Withdrawal Error (CRWE) cases Evaluation of the BFN EPU analyses determined that only the stability related calculations included any non-converged hydraulic calculations. The affected analyses include the BSP, DIVOM, and two recirculation pump trip (2PT) MCPR calculations for the OPRM setpoint. All other analyses supporting the Reference 1 submittal were found to be unaffected by the identified issue.
A new version of the MICROBURN-B2 code has been issued with a revised low flow convergence scheme that addresses this non-convergence issue. This new version of the code has been used in the revised calculations discussed later in this document.
2.2. Void Quality Correlation Behavior at Low Flow Conditions Condition report CR2015-7948 identifies that the current implementation of the void quality correlation used within MICROBURN-B2 includes by default [ ] . Investigations that have been carried out revealed that the correlation produces some potentially non-physical results at very low flow mass fluxes and high flow qualities, which is part of the reason for the implementation of the [
] into the correlation in MICROBURN-B2. This [ ] was implemented in the UNOV10 version of MICROBURN-B2.
The non-physical behavior is inherent in the formulation of the correlation and is not an implementation issue within the MICROBURN-B2 code. Investigation has determined that the correlation behaves in an expected manner for the following range of conditions:
[
]
All versions of the MICROBURN-B2 code since the release of UNOV10 have included a default [
] . While this appears to have mitigated the correlations non-physical
ARTS refers to Average Power Range Monitor (APRM), Rod Block Monitor (RBM), and Technical Specification (TS) improvements.
The range of applicability has been defined in a conservative manner. Falling outside this range does not mean that the void-quality correlation will provide a non-physical result; instead it indicates that the potential exists.
Analyses inside of this range of conditions produce the expected result.
AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 8/14 behavior it has been determined [
].
The evaluation of the effect of this issue is similar in scope in regard to the potentially affected calculations. Similar to the low flow convergence issue, the only BFN EPU LAR analyses that were determined to be affected were the stability related calculations.
Revised calculations were performed by eliminating the [ ] with an existing MICROBURN-B2 input. The analyses were then reviewed to ensure that the cases fall within [
] is as expected.
- 3. Effects to BFN EPU LAR Documentation The identified effects are limited to stability calculation results provided in two of the BFN EPU LAR reports* (References 2 and 3). The effects are provided in a series of tables and figures that contain both the revised and original results. Red bold font and red triangular symbols are used to identify the revised results. The new results include the corrective actions for both of the identified low flow issues (described in Section 2 above). All revised cases have been verified to be hydraulically converged and outside of the area of concern for non-physical behavior of the void-quality correlation.
3.1. Fuel Uprate Safety Analysis Report (FUSAR)
The FUSAR was provided in both proprietary (Reference 2.a) and non-proprietary (Reference 2.b) versions as Attachments 8 and 9 of the BFN EPU LAR, respectively. The effects of both issues have been incorporated and the effect to this report is limited to the BSP decay ratio results, the DIVOM plot, and the OPRM Setpoint results. These effects to the FUSAR are discussed below:
BSP Analyses (FUSAR Tables 2.8-2 and 2.8-3)
The revised BSP analyses result in minor changes to the decay ratios reported in the FUSAR. The BSP results are provided in FUSAR Tables 2.8-2 and 2.8-3 for nominal and reduced feedwater temperature conditions, respectively.
Table 1 and Table 2 of this document provide both the revised (in red bold font) and original results for the same conditions. As can be seen in these tables, the effect on the reported decay ratios is minor with some increasing and some decreasing in magnitude when compared to the original reported decay ratios.
In all cases, the limiting decay ratios continue to meet acceptance criteria and no change in the BSP regions is required as a result of the low flow convergence or void-quality issues.
DIVOM Analyses (FUSAR Figure 2.8-3)
The FUSAR provided the limiting DIVOM result as Figure 2.8-3. Figure 1 of this document provides a comparison of both the original and revised (in red triangular symbols) limiting DIVOM results. As can
- Proprietary and non-proprietary versions of these reports will be revised for a total of four affected documents.
AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 9/14 be seen in Figure 1, the effect on DIVOM results are minor and the generic slope of 0.45 continues to be supported. Consequently, there is no downstream effect on the OPRM setpoint calculation due to DIVOM.
OPRM Setpoint Analyses (FUSAR Table 2.8-1)
The results for the OPRM setpoint analysis for the EPU Equilibrium Cycle are provided in Table 2.8-1 of the FUSAR. The OPRM setpoint calculation includes two cycle-specific components that had the potential to be affected by the low flow issues in MICROBURN-B2, the DIVOM slope and the transient two recirculation pump trip (2PT) results. The other component of interest in the OPRM setpoint analysis is a plant-specific Hot Channel Oscillation Magnitude (HCOM) value. The HCOM analysis for BFN was performed with non-AREVA methods and is not affected by the MICROBURN-B2 issues addressed by this document.
The DIVOM slope is used in the calculation of the required OLMCPR for both the steady-state (SS) results and the transient 2PT results. As discussed above, the generic DIVOM slope remains supported so this component did not affect the reported results. Because this is the only cycle-specific component used for the SS results, the OLMCPR(SS) column of FUSAR Table 2.8-1 is not affected.
The 2PT results include the effect of the flow runback on the initial MCPR by use of a MCPR_P1 to MCPR_P2 (i.e., P1/P2) ratio where P1 represents the full power statepoint and P2 represents the post trip statepoint on the natural circulation line. The low flow issues have the potential to effect the P2 MCPR result. Because the P1/P2 ratio is a multiplier in the calculation of OLMCPR(2PT), increases or decreases in the P1/P2 ratio will have a corresponding effect on the 2PT results. For the equilibrium cycle analysis, the P1/P2 ratio decreases with the corrections to address the low flow issues with a corresponding decrease in the OLMCPR(2PT) results.
The effect on the FUSAR Table 2.8-1 results is provided in Table 3 of this document. This table provides both the original and revised (in red bold font) results. The discussion on allowable OPRM setpoint in Section 2.8.3.1.2 of the FUSAR is not affected by the changes in the OLMCPR(2PT) results.
3.2. Reload Licensing Analysis (RLA) Report for the Unit 3 Cycle 19 Reference Cycle The RLA report was included in both proprietary (Reference 3.a) and non-proprietary (Reference 3.b) versions as Attachments 20 and 21 of the BFN EPU LAR, respectively. The effect of both low flow issues discussed in Section 2 has been incorporated in the results discussed below. The effect to the RLA report is limited to the OPRM Setpoint results as discussed below:
BSP Analyses (RLA Table 4.4)
The BSP results are provided in RLA Table 4.4 for both nominal and reduced feedwater temperature conditions. The revised decay ratios continue to meet the acceptance criteria. Therefore, the BSP endpoints remain valid and no changes are required to this table.
OPRM Setpoint Analyses (RLA Table 4.3)
As discussed in Section 3.1, the OPRM setpoint analysis can be affected by changes in the cycle-specific DIVOM and 2PT MCPR P1/P2 ratio.
AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 10/14 The reanalysis of the DIVOM calculation for the reference cycle continues to support the generic slope of 0.45. No specific DIVOM results are reported so no changes to the RLA are required for the DIVOM results. Because this is the only cycle-specific component used for the OPRM setpoint SS results, the OLMCPR(SS) column of RLA Table 4.3 is not affected.
Similar to the equilibrium cycle analysis, the P1/P2 ratio for the reference cycle decreases with the corrections to address the low flow issues with a corresponding decrease in the OLMCPR(2PT) results.
The effect on the RLA Table 4.3 results is provided in Table 4 of this document. This table provides both the original and revised (in red bold font) results.
- 4. Conclusion The evaluation of the effects on the BFN EPU LAR of the identified low flow issues within MICROBURN-B2 identified only minor effects on the stability calculations. All other analyses supporting the LAR submittal are not affected.
Effects on the BSP calculations were minor changes to the decay ratios, with some limiting results experiencing small increases and some small decreases. In all cases, the stability acceptance criteria remain supported and no change in the BSP regions is required.
The DIVOM analyses showed small effects to the individual results but the generic 0.45 DIVOM slope remains supported.
The OPRM setpoint calculation for the OLMCPR(SS) results is unaffected because the assumed DIVOM slope does not change. The OLMCPR(2PT) results change; however, the change is a reduction in the required OLMCPR because the limiting P1/P2 ratio decreases for both the equilibrium and reference cycle cores.
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N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 11/14
Table 1 FUSAR Equilibrium Cycle - BSP Region Intercepts, Nominal Feedwater Temperature (Table 2.8-2)
Region EPU Core Original / Core/Global Regional Channel Boundary Power Flow Revised Decay Decay Ratio Decay Ratio Intercept (% rated) (% rated) Calculation Ratio REGION 1: SCRAM Region Original 0.733 0.472 0.137 1A (HFCL) 56.55 40 Revised 0.714 0.474 0.129 Original 0.654 0.506 0.205 1B (NCL) 39.34 29 Revised 0.698 0.505 0.177 REGION 2: CONTROLLED ENTRY Region Original 0.698 0.423 0.089 2A (HFCL) 64.50 50 Revised 0.701 0.423 0.089 Original 0.526 0.420 0.068 2B (NCL) 27.54 29 Revised 0.513 0.376 0.055 Table 2 FUSAR Equilibrium Cycle - BSP Region Intercepts, Reduced Feedwater Temperature (Table 2.8-3)
Region EPU Core Original / Core/Global Regional Channel Boundary Power Flow Revised Decay Decay Ratio Decay Ratio Intercept (% rated) (% rated) Calculation Ratio REGION 1: SCRAM Region Original 0.830 0.606 0.154 1A (HFCL) 56.55 40 Revised 0.833 0.608 0.154 Original 0.837 0.596 0.180 1B (NCL) 37.00 29 Revised 0.817 0.576 0.165 REGION 2: CONTROLLED ENTRY Region Original 0.749 0.478 0.089 2A (HFCL) 64.50 50 Revised 0.753 0.479 0.090 Original 0.500 0.389 0.064 2B (NCL) 27.54 29 Revised 0.505 0.378 0.058 AREVA - Fuel BL This document is subject to the restrictions set forth on the first or title page
N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 12/14 Table 3 FUSAR Equilibrium Cycle - Option III Setpoints (Table 2.8-1)
OPRM Amplitude OLMCPR(SS) OLMCPR(2PT)
Setpoint Original Revised* Original Revised 1.05 1.15 1.15 1.11 1.06 1.06 1.17 1.17 1.12 1.06 1.07 1.19 1.19 1.14 1.06 1.08 1.20 1.20 1.16 1.07 1.09 1.22 1.22 1.18 1.09 1.10 1.24 1.24 1.20 1.11 1.11 1.26 1.26 1.22 1.12 1.12 1.28 1.28 1.24 1.14 1.13 1.30 1.30 1.26 1.16 1.14 1.33 1.33 1.28 1.18 1.15 1.35 1.35 1.30 1.20 Acceptance Off-rated OLMCPR Rated Power OLMCPR Criteria at 45% Flow
- There are no changes in the OLMCPR(SS) results.
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N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 13/14 Table 4 RLA Report Representative Cycle - Option III Setpoints (Table 4.3)
OPRM Amplitude OLMCPR(SS) OLMCPR(2PT)
Setpoint Original Revised* Original Revised 1.05 1.15 1.15 1.16 1.08 1.06 1.17 1.17 1.18 1.10 1.07 1.19 1.19 1.20 1.11 1.08 1.20 1.20 1.22 1.13 1.09 1.22 1.22 1.24 1.15 1.10 1.24 1.24 1.26 1.17 1.11 1.26 1.26 1.28 1.19 1.12 1.28 1.28 1.30 1.21 1.13 1.30 1.30 1.32 1.23 1.14 1.33 1.33 1.34 1.25 1.15 1.35 1.35 1.36 1.27 Acceptance Off-rated OLMCPR Rated Power OLMCPR Criteria at 45% Flow
- There are no changes in the OLMCPR(SS) results.
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N° FS1-0024530 Rev. 1.0 Browns Ferry EPU Low Flow Issues Impact Handling: Restricted AREVA Page 14/14
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Figure 1 FUSAR Equilibrium Cycle - Limiting Cycle Specific DIVOM Results (Figure 2.8-3)
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ENCLOSURE 3 AREVA Affidavit
AFFIDAVIT STATE OF WASHINGTON )
) SS.
COUNTY OF BENTON )
- 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for AREVA Inc. and as such I am authorized to execute this Affidavit.
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SUBSCRIBED before me this day of 0-" J ~ 9' , 2015.
Susan K. McCoy NOTARY PUBLIC, STATE OF WAS TON MY COMMISSION EXPIRES: 1/14/2016