Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML20248H5072020-09-0404 September 2020 Acceptance of License Amendment Request to Technical Specification 3.8.6, Battery Cell Parameters Project stage: Acceptance Review ML21173A1042021-06-21021 June 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to TS 3.8.6 Project stage: RAI CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)2021-07-21021 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531) Project stage: Response to RAI ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters Project stage: Approval 2021-06-21
[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
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2022-04-0606 April 2022 Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-22-028, Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-03-18018 March 2022 Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)2021-07-21021 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531) CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components2021-04-28028 April 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)2020-12-29029 December 2020 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099) CNL-20-089, Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)2020-12-21021 December 2020 Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518) CNL-20-059, Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals2020-08-10010 August 2020 Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals CNL-19-122, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights2019-12-17017 December 2019 Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...2019-08-0808 August 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water... CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second2019-07-19019 July 2019 Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information CNL-19-007, Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus2019-01-16016 January 2019 Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results2019-01-16016 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information2018-12-14014 December 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 CNL-18-117, Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-462018-10-17017 October 2018 Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-46 CNL-18-120, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ..2018-10-11011 October 2018 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ... ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-032, Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program2018-03-27027 March 2018 Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program CNL-18-011, Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2018-02-0505 February 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-130, Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For..2017-10-23023 October 2017 Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For.. CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera2017-09-18018 September 2017 Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generati CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-17-035, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information2017-03-0303 March 2017 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information CNL-17-017, Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects2017-02-0303 February 2017 Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-161, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional..2016-10-13013 October 2016 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional.. CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 302016-09-23023 September 2016 Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30 CNL-16-150, Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 312016-09-21021 September 2016 Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 31 CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 72016-09-15015 September 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7 CNL-16-152, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information2016-09-12012 September 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)2016-08-24024 August 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) CNL-16-129, Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 292016-08-0303 August 2016 Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 29 CNL-16-127, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information2016-08-0303 August 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information CNL-16-114, Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate .2016-08-0303 August 2016 Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate . 2024-01-11
[Table view] |
Text
1101 Market Street, Chattanooga, Tennessee 37402 CNL-21-052 July 21, 2021 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:
Browns Ferry Nuclear Plant, Units 1, 2, and 3 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)
(EPID L-2020-LLA-0177)
References:
- 1. TVA Letter to NRC, CNL-20-013, Application to Revise Browns Ferry Nuclear Plant, Units 1, 2, and 3, Technical Specification 3.8.6, Battery Cell Parameters (TS-531), dated August 6, 2020 (ML20219A762)
- 2. NRC Electronic Mail to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Request for Additional Information Regarding Request to TS 3.8.6 (EPID L-2020-LLA-0177), dated June 21, 2021 (ML21173A104)
In Reference 1, Tennessee Valley Authority (TVA) submitted a request for an amendment to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, respectively. The proposed amendment would modify BFN Technical Specification (TS) 3.8.6, Battery Cell Parameters, to clarify the operability requirements for the unit, shutdown board, and diesel generator batteries.
In Reference 2, the NRC issued a Request for Additional Information (RAI) and requested TVA respond by July 21, 2021. Enclosure 1 provides the TVA response to the RAI. Enclosure 2 provides the revised BFN Units 1, 2, and 3 TS pages marked up to show the revised proposed changes. Enclosure 2 supersedes the corresponding information provided in Attachments 1, 2, and 3 of the Enclosure to Reference 1.
U.S. Nuclear Regulatory Commission CNL-21-052 Page 2 July 21, 2021 This letter does not change the no significant hazards considerations or the environmental considerations contained in Reference 1. Additionally, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.91(b)(1), TVA is sending a copy of this letter and the enclosure to the Alabama Department of Public Health.
There are no new regulatory commitments contained in this letter. If you have any questions regarding this submittal, please contact Kimberly D. Hulvey, Senior Manager, Fleet Licensing at 423-751-3275.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 21st day of July 2021.
Respectfully, James Barstow Vice President, Nuclear Regulatory Affairs & Support Services
Enclosures:
- 1. Response to Request for Additional Information Regarding Technical Specification 3.8.6, Battery Cell Parameters (TS-531)
- 2. Revised Technical Specification Page Markups cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant State Health Officer, Alabama Department of Public Health
Enclosure 1 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)
(EPID L-2020-LLA-0177)
CNL-21-052
Enclosure 1 Response to NRC Request for Additional Information NRC Introduction By application dated August 6, 2020 (Agencywide Documents Access and Management System Accession No. ML20219A762), the Tennessee Valley Authority (the licensee) requested amendments to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, respectively. The proposed amendments would revise Technical Specification (TS) 3.8.6, Battery Cell Parameters, to clarify the operability requirements for the Unit, Shutdown Board, and Diesel Generator batteries.
The U.S. Nuclear Regulatory Commissions Electrical Engineering Branch staff is reviewing the license amendment request and has identified where additional information is needed to complete its review. The NRC staffs request for additional information is below.
Regulatory Requirements Part 50.36, Technical Specifications, of Title 10 of the Code of Federal Regulations requires, in part, that the operating license of a nuclear production facility include TS. Paragraph 50.36(c)(2) of Title 10 of the Code of Federal Regulations requires, in part, that the TS include limiting conditions for operation (LCOs), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS, until the condition can be met.
EEEB RAI - 1 The licensee proposed to revise TS 3.8.6 by deleting the existing alternate condition One or more batteries with one or more battery cell parameters not within Category C values, in Condition B and adding the proposed new Condition C:
Condition C One or more batteries with one or more battery cell parameters not within Category B limits AND Any corresponding battery cell parameter for that battery not within its Category C limit.
Required Action C.1 Declare associated battery inoperable Completion Time Immediately The licensee also proposed to revise Table 3.8.6-1, Battery Cell Parameter Requirements, by adding Note (e):
(e) Category C battery cell parameters are not considered when the corresponding Category B cell parameters are met.
The Table 3.8.6-1 Category C allowable value for each connected cell specific gravity is: Not more than 0.020 below average of all connected cells AND average of all connected cells 1.195.
CNL-21-052 E1 1 of 3
The licensee provided the following basis for the proposed changes:
When the average specific gravity of all connected cells is near the nominal, fully charged value, this limit [i.e., not more than 0.020 below average of all connected cells]
provides a valid indication of a cell that may not be able to meet its design basis requirements. When the average specific gravity is high, having one cell more than 0.020 below the average of all connected is not necessarily an indication of a problem and is an invalid basis on which to declare the battery inoperable when all other parameter limits are met. Likewise, because the acceptable range of specific gravity is wider than 0.020, the natural variance of specific gravity can cause a given cell to be lower than 0.020 below the average and still be acceptable, notwithstanding the LCO.
The proposed change corrects this situation.
The licensee also stated:
This proposed change clarifies the usage of the Category C limits as allowable values that determine operability only if any of the corresponding Category B limits are not met.
In a case when a battery pilot cell specific gravity does not meet Categories A and C limits in Condition A, the TS requires the licensee to declare the battery inoperable in Condition B (Required Action and associated Completion of Condition A not met). In this case, Category C limits would determine the operability of the battery if Category A limits are not met. Thus, the situation that the licensee would correct with the proposed change remains in the TS when Categories A and C limits are not met.
- 1. Provide a discussion of the TS requirements when Categories A and C are not met.
- 2. Clarify how the Category C limits would determine the operability of the battery when they are not considered, as stated in the proposed Note (e).
TVA Response to EEEB RAI - 1
- 1. Revised TS page markups are provided in Enclosure 2. When Category A limits are not met, Condition A is entered. Action A.1 requires verification within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> that electrolyte level and float voltage meet Category C limits. Action A.2 requires verification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the battery cell parameters meet the Category C limits. When performing these actions, the new Note (e) is used to first verify that the Category B limits are met.
If the Category B limits are met, the corresponding Category C limits are met as well and Action A.3 controls at that point.
If the Category B limits are not met, the Category C limits are verified to be met. If the Category C limits are met, Action A.3 controls at this point. If the Category C limits are not met, then Condition B is entered with the Required Action A not met. Required Action B.1 requires the associated battery to be declared inoperable with an immediate Completion Time. Because not meeting the Category C limits is already managed by the first criterion of Condition B after not meeting the Required Actions of Condition A, the last criterion of Condition B regarding Category C limits is redundant and is being deleted as shown in Enclosure 2.
CNL-21-052 E1 2 of 3
- 2. The wording of Note (e) has been revised as shown in Enclosure 2 to read:
Category C battery cell parameters are considered met when the corresponding Category B cell parameters are met.
Category C limits determine operability of the battery when the corresponding Category B limits are not met.
CNL-21-052 E1 3 of 3
Enclosure 2 Revised Technical Specification Page Markups for Browns Ferry Nuclear Plant, Units 1, 2, and 3 CNL-21-052
7`k-8k}~-N``kk-
59VCLJS-9LJ;CVCLJ- Q=PZCQ=;-59VCLJ- 9LIOH=VCLJ-VCI=-
5- -cvkh- 5%- Qkk-a`k§-ck- %!- h`§-
``kk--9`kr§ `h---}vv-o-
W`blk-%.* !--
-- Qkvkh-5cv-`h- -!- ;kc}`k-`cv`kh- Ckhv`k}§-
`cv`kh-9lkv- a`k§-vk`a}k-
Vvk-o-9hvv-5--
k-
Mk--k-a`kvk-
¢vu-`k`rk-k}kc}¨k-kk`k-o-uk-kkk`vk-ck}}--
¢vuv-}vv-
Mk-- k-a`kvk-
¢vu-k--k-a`k§-
ck}}-``kk--¢vuv-
- `kr^-:-`} k-
->K ZKDX-!- 6kik-K-#%'-
7`k_-8k-N``kk-
%/+-
Y`ak-&.* !- `rk-!- o-! -
7`k-8k-N``kk-Qkwkk-85V=ALQ] - 85V=ALQ] HCICVT-?LQ-=58B- 85V=ALQ]- 5HHL\57H=-[5HZ=-
;=TCAJ5V=;-OEHLV- HEIFVT-?LQ-=58B- ?LQ-=58B-O5RI=V=Q- 8=HH- 8LJJ=8V=;-8=HH- 8LJJ=8V=;-8=HH- (e)
- =kd§l- 4 Ivv-?kl- 4-Ivv-ll- 5ak--o-`l-
Hlk- vhvd`v-`{-`h- vhvd`v-`{-`h- `h--m£vr-
¬-veu-`al- ¬-veu-`ak-
`v-kk- `v-kk-vhvd`v-`{`- vhvd`v-`{ ` -
@`-[`rk-
Tkdvovd- -! $- -""0(- J-k-u`- $-
A`v§-a- ak£-`k`rk-o-`-
d h- ckekh-cl-5k`rk-o-`-
ckekh-ek-4-! $(- 5k`rk-q-`-
ckekh-g-
-""0(-
`- G-v-`eek`ak-p-ulkke©k-kk--k`v§-vek`k-`ak-uk-kexpxkh- <<-
- `x-kk-jxr-n`xxr-eu`rk-vjlj-v-v--k£vr-
a - 8kekh-p-kke©k-kk`k-
e- 5-`-`k`xk--uk-kexpxe-s`v§-k`kk-`-a`k§-eu`sxr-ek-p-3-"-`-q-Zx-`h-Uuj¥-7`j-a`kvk-`j- )-`-p-<A-a`kvk-k--p`-eu`sk-v-`eek`ak-§-jvr-`-`x-q-,-j`§-p£xr-`-
a`k§-keu`rk- \uk-eu`rxr-ek-v-kh--`xq§-kevqye-r`v§-
kxkk-kezowe-s`v§-o-k`eu-ekekh-ek-u`-ak-k`kh-v--
kx`x-q-uk-,-j`§-`£`ek-
h- 5k`k-`k-`§-ak-kj-p-`-xxkj-ak-q-ek-xjkh-jk`kj-a`k§-f`ex§-`-uk-`-jxeu`sk-k-kk-uk-xx-`xq§xt-`k-
7>J ZJCV "- %/ %$- 5khk-J-$%'-
Category C battery cell parameters are considered met when the (e) corresponding Category B cell parameters are met.
.TT4M[_ 4@@_&.M.B4T4MR_
_
,$"+_
$",$"_ )(-*_,$"_ $!' ,$"_
,!_
_ 1HFU9FX42_ _ )4SUHM4_0/UU4P_14<<_ _ 2/[S_
K/N/C4U4NS_VH_/U47HN[__
/F2__;9C9US_I5_
,/0<4_ __
)4LX9N42_1U9HF_/F2_ _ 41=/N4_/RRH19/U42_ CC429/U4<[\_
/SSH19/U42_HCK<4U9HF_ 0/UU4N[_:FHK4N/0<4_
,9C4_H6_HF29U9HF__FHU_
D4U_
%F4_HN_DHN4_0/UU4N94S_
Z9U8_/Y4N/74_4>41UNH>[U4_
V^CK4N/UXN4_H5_V84_
]_O4KN4R4FU/U9Y4_14<<R_FHU_
Z:U89F_?9C9US_
%F4_HN_DHN4_0/WU4N94R_
Z9U8_HF4_HN_DHN4_0/WU4Q_
14<A_K/N/C4U4NR_FHU_Z9U89F_
/U47HP_Y/<X4S_
4G3E4GT_#J_ _
1S] 4]uu HSSv))
' $
LSUp^ (% ?Sf] z`
2S] 3]ss ISSv)) J]l]v]w 30L6:GJQ 0+ 30L6:GJR3, C?D>LK 7GJ 603< 30L6:GJR)- 0CCGP01C6 O0CN6 56K?:F0L65 I?CGL CAD@LK 8GJ 603= 8GJ 603=
I0J0D6L6J 36CC 3GFF63L65 36CC 3GFF63L65 36CC (e) 6p]W{p] / Eiwivv q))p / Eiwivv q))p 0Ul] l? z` ?rS]
C))p iw\iZilw vSo Sw\ iw\iZilw vSo Sw\ Sw\ xl z]sliwf
iwWh SUl] iwWh SUl]
vSivv p))s vSlvv p))p iw\lZizw vSoS iw\lZilw vSoS
8plS OlpSf] ! O O /&O K?]WmciW *" Fl vl] hSw
- Sn V V]sl S]Sf] la Sss
X\ 0F5 [ww]W]\ W]pp 0]Sf] la Spp
[ww]W]\ W]ss
/ " 0]Sf] l` Sss
[ww]W]\ X]ss
*"
S B i SWW]?SVs] bl h] ]s]Wlp] p))s l ]v?lSis iwW]S] SVl] h] ?]Wlal]\
vSlvv p))u \lwg ]Ssllwf WhSg] ?ll\]\ i i wl l]ullwg
V 4l]W]\ cl ]s]Wlp] _v?]S]
W 0 Sw St] Sj] }h] ?]WkcjYgSj v]S]v]w S VT] WhSglwf W]w la. Sv? cl Nwl Sw\ Kh\l 1lS\ VS]l] Sw\. # Sv? c~ 5; VS]l]
h]w lw cslS XhSg] i SWW]?SVs] lws \iwf S vSlvv la & \S clssllwg S VS] ]WhSg] Ph]w WhSglwf W]w l ]\ l Sle ?]WjalW fSl
]i]v]w ?]WjdjW gSi l` ]SWh Xlww]W]\ W]ss hSss V] v]S]\ ?ll l
]?lSllw la h] & \S SsslSwW]
\ 0u] S] Ss] vS V] ]\ cl S plvl]\ wvV] la W]us ?ll\]\ \]vlyS]\
VS] Z?SWl S h] pS \lWhSf] ] v)) h] vlwlvv Sulelwg Su]
19F NF?M ' 0v]w\v]w Fl "
(e) Category C battery cell parameters are considered met when the corresponding Category B cell parameters are met.
0La1att>LLwaa
<<$!
-1D7<:C 1<:27D7<: A3@H7A32-1D7<: 1<9?83D7<:
D793
- [{lza_ - Aa~aPLbYtt _L
?LLxaa~1Lah~-
L{_0tlxk~d DLQsa%!
Aala_-`l~{Lz_ 2aRtLaL~RlLa_ 7xxa_lLat L~RlLa_1~w?tal~z PLalz~?aLQta
Dlxa~d1~z_ml~{-z~
wa
=A
<lb~x~bPLbla liLaLhaata]~t©a aw?aMa~dja a?aazLlaYttz~
¢ilzulxm
=A
=za~x~aPLala
¢i~{a~x~aPLa Ytt?LLxaaz~¢ilz 1Lah~1Lta
04:H:7D $ -xa{_wal;~
0La1att>LLwaa
¬ $"
ELQta$ " ?Lha~d
0La1att>LLwaaAakawaz 1-F35<AK-' 1-F35<AK1(
8797FC4<A3-16 1-F35<AK0) -88<J-083I-8H3 23C75:-F32>78<F 8797FC4<A3-16 4<A3-16
>-B93G3A 1388 1<::31F321388 1<::31G321388 (e) 3ua]~t©a ,9kzkwwuaau ,9kzkwwuaat .~a~?~e?uLa
8aat kz_kUk~zwLLz_ kz_kUk~zwL r Lz_ Lz_z~~a~ kzh
*kzRiNQ~a *kzRiLP~a wOkwyuaat wOkwwuaat kz_kUk~}wL rL nz_kVk~zwLrL
4u~LI~tLha SI SI , #I C?aRkdkR T T& :~w~aiLz
5Lk§Q Pat~ Laha~eNtt
R_ -:2 [zza]a_Ytt
-aha~dNtt -:2
[zza]a_Ytt
, -aha~eLtt
[zza]a_Ytt S&
L 7kLW?LPtaf~iaata]~t©auaat~aw?~ ot§oz\aLaLQ~aia?aRpdoa_
wLkwwuaat_kzhaLtkkzhZLha?~k_a_kkz~~at~ kzh
P 1~c]a_f~ata]~t©aaw?aa
R /LzLtaLka~ia?cRqRhLn§waLawaz LPLaZLhkzh^az
~e+Lw?f~HzkNz_Ci_~£0~L_PLakaLz_+ Lw?f~25PLaka iaz~zfv~LZLhak LX?LQta~zt§_kzhLwNkww~e#_L§f~tt~ kzhL PLaaRiLha JiazRiLhkzhRazka_~Lkg?aRkdkRhLk§ akawaz?aRkdkRhLk§~eaLRi[zza]a_YttiLttPawaLa_?k~~
a¥kk~z~dia#_L§ Ltt~zRa
_ -taLaLtawL§Paa_f~Ltkwka_zwPa~fYtt?~k_a__aw~zLa_
PLaU?LRk¨LiatL_kRiLaawaaiawkzkwwLtkd§kzhLta
04:H:7F $ -waz_waz:~
(e) Category C battery cell parameters are considered met when the corresponding Category B cell parameters are met.}}