ML24019A132
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| ML24019A132 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/09/2020 |
| From: | Storey G Framatome |
| To: | Office of Nuclear Reactor Regulation |
| Green K, NRR/DORL/LPL2-2 | |
| Shared Package | |
| ML24019A097 | List: |
| References | |
| L32 201105 801 ANP-3874NP, Rev 1 | |
| Download: ML24019A132 (1) | |
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:Meeting Briefing Package/Handouts MONTHYEARML24032A2752024-02-0707 February 2024
[Table view]Pre-Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates (Slides) ML24019A1512024-01-22022 January 2024 Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23025A0472023-01-25025 January 2023 Pre-Submittal Meeting for Proposed License Amendment Request Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves - January 25, 2023 ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 2022-TVA Slides ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22264A2332022-09-22022 September 2022 Slides for Pre-Submittal Meeting for Request to Use a Later Edition of the ASME OM Code for the Fifth Inservice Testing (IST) 10-Year Interval ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21270A0322021-09-27027 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting September 27, 2021 ML21265A0422021-09-21021 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting 09/22/2021 ML21250A3012021-09-0707 September 2021 TVA Slides for September 7, 2021, Presubmittal Meeting to Discuss Planned Browns Ferry TSTF-505 License Amendment Request ML21152A1872021-06-0101 June 2021 TVA Slides for June 1, 2021, Presubmittal Meeting to Discuss Planned Control Bay Chiller Cross-Tie License Amendment Request ML24019A1322020-11-0909 November 2020 ANP-3874NP, Revision 1, Browns Ferry Atrium 11 Control Rod Drop Accident Analysis with the AURORA-B CRDA ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20156A2812020-06-0808 June 2020 TVA Slides for June 8, 2020, ATRIUM-11 Presubmittal Meeting ML20092F5742020-04-0202 April 2020 TVA Slides for Browns Ferry 50.69 License Amendment Request Presubmittal Meeting ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML24019A1482019-01-28028 January 2019 Surveillance Procedure 2-SR-3.1.6.1, BPWS Compliance Verification, Revision 006 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML18255A0102018-09-12012 September 2018 NRC Slides for Target Rock Public Meeting ML18239A2522018-08-27027 August 2018 Proposed Changes to NFPA 805 License Conditions ML18158A2862018-06-0707 June 2018 May 30, 2018 Summary of Public Meeting with Browns Ferry Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML17271A0162017-09-28028 September 2017 Meeting Slide for Tennessee Valley Authority (TVA) Hydrology Precipitation Model Topical Report Review Status ML17212A8432017-08-0101 August 2017 Meeting Slides for Pre-submittal Meeting with Tennessee Valley Authority on Unbalanced Voltage License Amendment Request for TVA Nuclear Plants ML17034A3322017-02-0303 February 2017 Presentation Slides for Public Meeting Regarding Browns Ferry Extended Power Uprate License Amendment Request Transmission System Update Supplements ML16356A0342017-01-0404 January 2017 Pre-app Meeting Mellla+ LAR Final ML16341A7422017-01-0404 January 2017 Presentation Slides for Browns Ferry Pre-application Meeting Regarding Mellla+ ML16350A2962016-12-14014 December 2016 Enclosure 3- Reactor Oversight Process Task Force FAQ Log- November 16, 2016 ML16279A2332016-10-0505 October 2016 Summary of Closed Pre-Decisional Enforcement Conference with Tennessee Valley Authority Regarding Browns Ferry Nuclear Plant ML16200A2592016-07-19019 July 2016 July 19, 2016: NRC Public Meeting on Browns Ferry Nuclear Plant Extended Power Uprate License Amendment Request ML16189A3482016-07-19019 July 2016 Presentation Slides for July 19, 2016, Public Meeting ML16028A0962016-02-0101 February 2016 Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal Logic, and Unit Priority Re-Trip Logic License Amendment Request ML15308A1002015-11-10010 November 2015 Public Meeting Presentation Slides Extended Power Uprate License Amendment Request NRC Public Meeting ML15195A1252015-07-14014 July 2015 July 14, 2015 - Public Meeting Slides on Browns Ferry Seismic Risk Insights ML15293A4582015-07-14014 July 2015 Slides for July 14, 2015 Public Meeting on Browns Ferry Seismic Risk Evaluations (MF3764 Through MF3766) CNL-15-122, Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request2015-07-0808 July 2015 Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request ML15146A2792015-05-21021 May 2015 Bf EOC Meeting Summary 2015 ML15099A2912015-04-22022 April 2015 4/22/2015, Enclosure 2, Slides for TVA Presentation to the NRC in Support of Steam Dryer Replacement ML14147A3222014-05-27027 May 2014 Public Meeting Summary 05/21/2014 to Present Annual Assessment ML14101A1522014-04-11011 April 2014 Summary of Public and Closed Meeting for Tennessee Valley Authority 2013 Synergy Safety Culture Survey Results ML14090A4582014-03-31031 March 2014 Public Meeting Summary TVA Synergy Safety Culture Survey Results ML14036A3872014-02-0505 February 2014 Summary of Meeting with Public to Discuss the Results of the Follow-up Inspection of the Items Identified in Confirmatory Action Letter (ML13232A105) of August 22, 2013, and the Status of Nrc'S Performance Assessment of Browns Ferry Unit 1 IR 05000260/20132012013-07-30030 July 2013 07/24/2013 Summary of Public Conference Meeting With Tennessee Valley Authority to Discuss Safety Significance of One Preliminary Greater Than Green Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000260 ML13212A0842013-07-30030 July 2013 Summary of Public Conference Meeting with Tennessee Valley Authority to Discuss Safety Significance of One Preliminary Greater than Green Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000260/20132012 ML13199A4522013-07-17017 July 2013 Summary of Meeting with Browns Ferry 2024-02-07 |
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