CNL-14-118, Confirmatory Action Letter Tier 2 Commitments Related to Integrated Improvement Plan: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 3: | Line 3: | ||
| issue date = 07/02/2014 | | issue date = 07/02/2014 | ||
| title = Confirmatory Action Letter Tier 2 Commitments Related to Integrated Improvement Plan | | title = Confirmatory Action Letter Tier 2 Commitments Related to Integrated Improvement Plan | ||
| author name = Shea J | | author name = Shea J | ||
| author affiliation = Tennessee Valley Authority | | author affiliation = Tennessee Valley Authority | ||
| addressee name = | | addressee name = Mccree V | ||
| addressee affiliation = NRC/Document Control Desk, NRC/RGN-II | | addressee affiliation = NRC/Document Control Desk, NRC/RGN-II | ||
| docket = 05000259 | | docket = 05000259 |
Revision as of 11:37, 21 June 2019
ML14190B160 | |
Person / Time | |
---|---|
Site: | Browns Ferry |
Issue date: | 07/02/2014 |
From: | James Shea Tennessee Valley Authority |
To: | Mccree V Document Control Desk, NRC/RGN-II |
References | |
CNL-14-118, IR-13-014 | |
Download: ML14190B160 (12) | |
Similar Documents at Browns Ferry | |
---|---|
Category:Graphics incl Charts and Tables
MONTHYEARML21286A5422021-10-0404 October 2021
[Table view]Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.5, Analyses of Abnormal Operational Transients ML21286A3972021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.12, Process Radiation Monitoring Systems Characteristics ML21286A3422021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.9, Reactor Water Cleanup System Equipment Design Data ML21286A3592021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 6, Table 6.4, (Deleted by Amendment 13) ML21286A3762021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.1, Systems (or Portions of Systems) Required to Mitigate LOCA And/Or HELB ML21286A3732021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.2, Reactor Protection System Instrumentation Specifications ML21286A3682021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.3, Primary Containment Isolation ML21286A3892021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.7, Reactor Manual Control System Instrumentation ML21286A3952021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.6, Refueling Interlocks Effectiveness ML21286A5662021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.13-1, Results of BFN Atwsi Evaluation ML21286A5522021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.5, Analyses of Abnormal Operational Transients ML21286A5502021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.4, Approach to Safety Analysis ML21286A5482021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.6, Iodine-131 Activity (Ci) by Location as Function of Time for CRDA ML21286A5432021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 13, Table 13.5, Startup and Power Test Program ML21286A4042021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.13, Area Radiation Monitoring ML21286A5322021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.6, Analysis of Design Basis Accidents ML21286A5282021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.4, Approach to Safety Analysis ML21286A5162021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 10, Table 10.17, Process Sampling Systems ML21286A4942021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 10, Table 10.11, Power Block Structures ML21286A4602021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 10, Table 10.4, Tools and Servicing Equipment ML21286A4572021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 12, Table 12.2, Reactor Building Concrete Structure Base Slab Design Data ML21286A4522021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 12, Table 12.3, Plant Radiation Zone Classification ML21286A4272021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 8, Table 8.4, Normal Auxiliary Power ML21286A4242021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 8, Table 8.6, 250-V DC Power Supply ML21286A4232021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.20, Design Output Documents ML21286A4142021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 8, Table 8.5, Standby AC Power Supply ML21286A4092021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.16, Process Computer System ML21286A2772021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table 2.3, Meteorology ML21286A2232021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G, State B ML21286A2222021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G - BWR Operating States ML21286A2262021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G, State D ML21286A2272021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix G, State a ML21286A2622021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Table 1.11, Id Resolution of Construction Permit Concern - Summary ML21286A2522021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Table 1.4-1, Class of BWR Systems Criteria Requirements for Safety Evaluation ML21286A2662021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table 2.5, Sheets 1-3, Historical Earthquake Listing 200 Mile Radius Around 87.11 W Lon 34/71 N Lat ML21286A3172021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.3, Reactor Recirculation System ML21286A2002021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Appendix a, AEC General Design Criteria - Group 1 (Overall Plant Requirements) ML21286A2722021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 1, Table 1.7, Comparison of Nuclear System Design Characteristics ML21286A3482021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 6, Table 6.5, Plant Parameters Used Locaa Analysis ML21286A3542021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 6, Table 6.3, Emergency Core Cooling Systems Equipment Design Data Summary ML21286A3672021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.5, Neutron Monitoring System, SRM Trips ML21286A3962021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Table 7.8, Reactor Vessel Instrumentation ML21286A3122021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 3, Table 3.2-1, Deleted by Amendment No. 16 ML21286A3132021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 3, Table 3.3, Reactor Vessel Internals, Mechanical Design Data ML21286A2962021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.2, Reactor Pressure Vessel Materials ML21286A2822021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table 2.4A, Maximum Possible Flood ML21286A2842021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Table, 2.4, Deleted ML21286A3112021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.4, Nuclear Steam Pressure Relief System ML21286A3242021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 3, Table 3.6, Definition of Fuel Design Limits ML21286A3432021-10-0404 October 2021 Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Table 4.8, Residual Heat Removal System Equipment Design Data 2021-10-04 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
[Table view]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 |