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Category:Meeting Agenda
MONTHYEARPMNS20240078, Meeting with Tennessee Valley Authority to Discuss a Future License Amendment Request to Revise the Final Safety Analysis Report Regarding the Hydrologic Analysis for the Browns Ferry Nuclear Plant2024-01-24024 January 2024 Meeting with Tennessee Valley Authority to Discuss a Future License Amendment Request to Revise the Final Safety Analysis Report Regarding the Hydrologic Analysis for the Browns Ferry Nuclear Plant PMNS20240028, Meeting with Tennessee Valley Authority to Discuss Proposed Use of the Risk-Informed Process for Evaluations (RIPE) for an Upcoming License Amendment Request for the Browns Ferry Nuclear Plant2024-01-12012 January 2024 Meeting with Tennessee Valley Authority to Discuss Proposed Use of the Risk-Informed Process for Evaluations (RIPE) for an Upcoming License Amendment Request for the Browns Ferry Nuclear Plant PMNS20231329, Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants2023-11-28028 November 2023 Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants PMNS20230966, Pre-Application SLRA Meeting with TVA for Browns Ferry Cathodic Protection2023-09-11011 September 2023 Pre-Application SLRA Meeting with TVA for Browns Ferry Cathodic Protection PMNS20230712, Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants2023-06-12012 June 2023 Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 PMNS20230568, Pre-Submittal Meeting for Subsequent License Renewal Application for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Bfnp) - Safety2023-05-10010 May 2023 Pre-Submittal Meeting for Subsequent License Renewal Application for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Bfnp) - Safety PMNS20230570, Pre-Submittal Meeting for Subsequent License Renewal Application for Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Environmental2023-05-10010 May 2023 Pre-Submittal Meeting for Subsequent License Renewal Application for Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Environmental PMNS20230549, Annual Assessment Virtual Meeting for the 2022 Assessment Period2023-04-25025 April 2023 Annual Assessment Virtual Meeting for the 2022 Assessment Period PMNS20230446, Annual Assessment Public Poster Session and Openhouse Meeting2023-04-17017 April 2023 Annual Assessment Public Poster Session and Openhouse Meeting 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 PMNS20230053, Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 32023-01-18018 January 2023 Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides PMNS20221018, Meeting with the Tennessee Valley Authority to Discuss Proposed Alternative Requests for the Browns Ferry Nuclear Plant2022-10-12012 October 2022 Meeting with the Tennessee Valley Authority to Discuss Proposed Alternative Requests for the Browns Ferry Nuclear Plant ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) PMNS20220991, Meeting with Tennessee Valley Authority to Discuss Severe Accident Mitigation Alternatives Analysis for the Browns Ferry Nuclear Plant, Subsequent License Renewal Application2022-10-0606 October 2022 Meeting with Tennessee Valley Authority to Discuss Severe Accident Mitigation Alternatives Analysis for the Browns Ferry Nuclear Plant, Subsequent License Renewal Application 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 PMNS20220953, Meeting with Tennessee Valley Authority to Discuss Proposed Alternative Request for Browns Ferry Nuclear Plant2022-09-21021 September 2022 Meeting with Tennessee Valley Authority to Discuss Proposed Alternative Request for Browns Ferry Nuclear Plant PMNS20220312, Meeting with Tennessee Valley Authority to Discuss the Criticality Analysis License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 32022-03-31031 March 2022 Meeting with Tennessee Valley Authority to Discuss the Criticality Analysis License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 PMNS20220285, Annual Assessment Meeting2022-03-29029 March 2022 Annual Assessment Meeting PMNS20220206, Meeting with Tennessee Valley Authority Regarding Framatome Advanced Methodologies for the Browns Ferry Atrium 11 Fuel Transition License Amendment Request2022-03-0707 March 2022 Meeting with Tennessee Valley Authority Regarding Framatome Advanced Methodologies for the Browns Ferry Atrium 11 Fuel Transition License Amendment Request 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) ML21270A0492021-09-27027 September 2021 Teleconference with Tennessee Valley Authority to Discuss a Planned Alternative Request to ASME Code Case N-526 for Browns Ferry Nuclear Plant, Unit 2 ML21270A0322021-09-27027 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting September 27, 2021 ML21265A1322021-09-22022 September 2021 Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 PMNS20211154, Meeting with Tennessee Valley Authority Regarding a Proposed Fleet Amendment Request2021-09-21021 September 2021 Meeting with Tennessee Valley Authority Regarding a Proposed Fleet Amendment Request ML21265A0422021-09-21021 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting 09/22/2021 ML21256A1962021-09-13013 September 2021 Teleconference with Tennessee Valley Authority to Discuss a Planned Alternative Request to ASME Code Case N-526 for Browns Ferry Nuclear Plant, Unit 2 ML21252A5352021-09-0909 September 2021 Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML21242A0582021-08-30030 August 2021 Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML21152A1872021-06-0101 June 2021 TVA Slides for June 1, 2021, Presubmittal Meeting to Discuss Planned Control Bay Chiller Cross-Tie License Amendment Request PMNS20210702, Closed Meeting with Representatives from the Tennessee Valley Authority to Discuss a Planned Request for Exemption2021-05-25025 May 2021 Closed Meeting with Representatives from the Tennessee Valley Authority to Discuss a Planned Request for Exemption ML21141A1152021-05-21021 May 2021 Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 PMNS20210392, Annual Assessment Meeting2021-04-12012 April 2021 Annual Assessment Meeting ML20167A1202020-06-30030 June 2020 Public Meeting Notice - Notice of Predecisional Enforcement Conference (Pec) Between U.S. Nuclear Regulatory Commission (NRC) and Tennessee Valley Authority (TVA) (EA-20-006, EA-20-007) ML16356A0342017-01-0404 January 2017 Pre-app Meeting Mellla+ LAR Final ML16161A0642016-06-15015 June 2016 Notice of Forthcoming Closed Meeting with Tennessee Valley Authority and Its Consultant, GEH, Regarding Steam Dryers Structural Adequacy for Browns Ferry Units 1, 2 & 3 Extended Power Uprate (EPU) License Amendment Request (LAR) ML15062A5402015-03-0303 March 2015 March 8, 2015, Rescheduled Forthcoming Closed Meeting with Tennessee Valley Authority Browns Ferry Nuclear Plant Main Steam Isolation Valve Leakage Rate License Amendment Request ML14076A0692014-03-17017 March 2014 Notice of Public Meeting with the TVA to Discuss TVA 2013 Synergy Safety Culture ML14065A4952014-03-0606 March 2014 March 26, 2014 Notice of Category 3 Meeting with TVA to Present the 2013 Synergy Safety Culture Survey Results ML14014A2402014-01-14014 January 2014 Meeting Notice with Public to Discuss the Results of the Follow-up Inspection of the Items Identified in Confirmatory Action Letter of August 22, 2013 (ML13232A105) and the Status of the Nrc'S Performance Assessment of Browns Ferry Unit 1 ML14014A1572014-01-14014 January 2014 Meeting Announcement - Category One - Browns Ferry Nuclear Plant ML13191A1722013-07-10010 July 2013 Notice of Category 1 Meeting - Regulatory Conference Browns Ferry ML13178A3532013-06-27027 June 2013 Notice of Meeting with Tennessee Valley Authority to Discuss the Annual Assessment & Inspection Procedure 95003 Supplemental Inspection for Browns Ferry Nuclear Plant ML12321A2522012-11-16016 November 2012 12/5/2012 - Meeting Announcement - Category One - Browns Ferry Nuclear Plant ML12320A4812012-11-15015 November 2012 Meeting Slides Regarding Browns Ferry Xm Fuel Transition Update ML12306A4092012-11-0202 November 2012 Notice of Forthcoming Meeting with Tennessee Valley Authority Regarding Areva Xm Fuel Transition Request ML12272A0612012-09-28028 September 2012 11/8/12 Notice of Forthcoming Meeting with Tennessee Valley Authority Regarding Voluntary Fire Protection Risk Initiative for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML12240A0802012-09-10010 September 2012 10/3/2012 Notice of Forthcoming Meeting with Tennessee Valley Authority Regarding Voluntary Fire Protection Risk Initiative 2024-01-24
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24032A2752024-02-0707 February 2024 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
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24032A2752024-02-0707 February 2024 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 ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23130A0332023-05-11011 May 2023 NRC Presentation Browns Ferry Subsequent License Renewal Pre-application Meeting, Environmental Overview ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23130A0302023-05-10010 May 2023 TVA Presentation Browns Ferry Nuclear Plant Subsequent License Renewal License Application Environmental Report 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 ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 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 ML21096A1002021-04-0606 April 2021 Annual Assessments 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 ML20112F5302020-04-21021 April 2020 TVA Nuclear Plants -2019 EOC Media Loop Slides for Automatic Play (Final) 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 ML19120A3692019-04-30030 April 2019 Public Meeting Summary - Browns Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 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 ML16341A7422017-01-0404 January 2017 Presentation Slides for Browns Ferry Pre-application Meeting Regarding Mellla+ ML16356A0342017-01-0404 January 2017 Pre-app Meeting Mellla+ LAR Final ML16279A2332016-10-0505 October 2016 Summary of Closed Pre-Decisional Enforcement Conference with Tennessee Valley Authority Regarding Browns Ferry Nuclear Plant ML16189A3482016-07-19019 July 2016 Presentation Slides for July 19, 2016, Public Meeting ML16200A2592016-07-19019 July 2016 July 19, 2016: NRC Public Meeting on Browns Ferry Nuclear Plant Extended Power Uprate License Amendment Request ML16153A1982016-06-0101 June 2016 2015 EOC Meeting Summary 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 ML16006A2882016-01-0606 January 2016 Significant Operational Experience: 7 Major Industry Events with Regulatory Implications ML15308A1002015-11-10010 November 2015 Public Meeting Presentation Slides Extended Power Uprate License Amendment Request NRC Public Meeting ML15293A4582015-07-14014 July 2015 Slides for July 14, 2015 Public Meeting on Browns Ferry Seismic Risk Evaluations (MF3764 Through MF3766) ML15195A1252015-07-14014 July 2015 July 14, 2015 - Public Meeting Slides on Browns Ferry Seismic Risk Insights 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 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 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 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 2024-02-07
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Browns Ferry Nuclear Plant (BFN) Subsequent License Renewal Application (SLRA) -
Severe Accident Mitigation Alternatives (SAMA) Analysis October 6, 2022
Introduction Pete Donahue - Director, Subsequent License Renewal (SLR)
Bill Baker - Senior Program Manager, SLR Plant Operations Ashley Michael - Senior Program Manager, SLR Mechanical Systems Dan Kearnaghan - Manager Nuclear Power Group Probabilistic Risk Assessment (PRA)
Projects Gerry Kindred - Senior Program Manager, PRA Bill Victor - Senior Program Manager, Corporate Nuclear Licensing Beau Eckermann - Program Manager, Fleet Licensing Joe Bashore - SLR Environmental Lead Dan Green - SLR Licensing Manager Nick Lovelace - Jensen Hughes - PRA 2
Agenda Introduction P. Donahue Background J. Bashore/D. Kearnaghan Model Development N. Lovelace Overview of SAMA Process N. Lovelace SAMA Results N. Lovelace Next Steps for Potentially Cost-Beneficial SAMAs J. Bashore SLRA Environmental Report Contents - SAMA J. Bashore Questions/Comments P. Donahue 3
Background Purpose of Analysis of Severe Accident Mitigation Alternatives (SAMAs)
Identify design alternatives, procedural modifications, or training activities that are costbeneficial and further reduce risks of severe accidents Analysis of SAMAs includes identification and evaluation of alternatives that reduce risk from severe accident by Preventing substantial core damage (preventing a severe accident) or Limiting releases from containment in event substantial core damage occurs (mitigating impacts of a severe accident)
In accordance with 10 Code of Federal Regulations (CFR) 51.53(c)(3)(ii)(L) and Table B1 of Appendix B to 10 CFR Part 51, Subpart A License Renewal Environmental Reports (ERs) must provide consideration of alternatives to mitigate severe accidents If NRC staff has not previously considered such alternatives for applicants plant in an Environment Impact Statement (EIS) or related supplement or in an Environmental Assessment (EA) 4
=
Background===
(continued) Nuclear Regulatory Commission (NRC) staff previously considered alternatives to mitigate severe accidents for BFN in Supplemental EIS for License Renewal Supplement 21 Regarding Browns Ferry Nuclear Plant Units 1, 2, and 3, to Generic EIS for License Renewal of Nuclear Plants (NUREG-1437) dated June 2005 Since that time, BFN Units 1, 2 and 3 and associated PRA models have undergone many modifications/changes Because of extent of changes to BFN Units 1, 2 and 3 and associated PRA models, TVA has determined that it would be more efficient to perform a full SAMA analysis rather than using Nuclear Energy Institute (NEI) 17-04, Model SLR New and Significant Assessment Approach for SAMA 5
=
Background===
(continued) BFN Modifications For example:
Numerous modifications to Unit 1 to support recovery to operating status Extended Power Uprate (EPU) and Maximum Extended Load Line Limit Analysis Plus (MELLLA+) for Units 1, 2, and 3 Numerous modifications for compliance with BFN National Fire Protection Association (NFPA) 805 analyses Diverse and Flexible Coping Strategies (FLEX) modifications 6
PRA Model Background Note: Previously submitted SAMA evaluation performed with RISKMAN model (continued) PRA model completely re-built using CAFTA software to meet Regulatory Guide 1.200 Substantial update to PRA internal events and internal flooding model Modeling changes PRA updated to model current as-built, as-operated plant Extended Power Uprate Several different analyses conducted to reflect EPU Fire PRA and seismic PRA models developed for BFN Modeling Updates from Internal and Industry Peer Reviews PRA model refined by incorporation of latest state of knowledge and recommendations from Internal and Industry Peer Reviews All Finding Level Facts & Observations (F&Os) have been closed using applicable NEI guidance Creation of One-Top Multi-Hazard Model (OTMHM)
Internal events, internal flood, fire and seismic PRA models integrated to create one-top model 7
Model Level 1, 2, and 3 Models Development Level 1 PRA model: One-Top Multi-Hazard Model (OTMHM)
Includes internal events, internal flood, fire, and seismic Level 2 analysis uses Containment Event Tree (CET) to analyze all core damage sequences identified in Level 1 analysis Results include each sequences release frequency, magnitude, and timing Level 2 bins:
High-Early Release (H-E), High-Intermediate Release (H-I), High-Late Release (H-L),
Medium-Early Release (M-E), Medium-Intermediate Release (M-I),
Low-Intermediate Release (L-I), Low Low-Intermediate Release (LL-I),
Containment Intact (Intact) 8
Model Level 1, 2, and 3 Models Development Level 3 PRA model created for BFN using Windows MELCOR Accident Consequences (continued) Code System (WinMACCS)
Site-specific meteorological, population, and economic data to estimate each accident consequences population dose and offsite economic costs Used to estimate accident consequences in terms of population dose and offsite economic costs for 50 miles around BFN Risks in terms of population dose risk and offsite economic cost risk also estimated in this analysis Calculated as product of WinMACCS consequence and frequency of different postulated accidental releases based on Level 2 analysis 9
Overview of NEI 05-01 Methodology SAMA NEI 05-01, Severe, Accident Mitigation Alternatives (SAMA) Analysis Guidance Document, guidance used for all three BFN units Process Guidance in NEI 17-04, Model SLR New and Significant Assessment Approach for SAMA, not used since full SAMA analysis performed except for SAMA candidate identification Analytical Steps Involved:
- 1. Identification of Potential SAMA Candidates Potential SAMA candidates were identified from following sources, based on NEI 05-01 and NEI 17-04 in relation to potentially cost beneficial SAMAs from other BWR plants SAMA analyses for other BWR plants; (NEI 17-04 includes review of SAMAs identified as potentially cost beneficial for other industry plants that have been determined to be applicable, but not already implemented at the analyzed plant)
NRC and industry documentation discussing potential plant improvements; and BFN updated PRA model lists of risk significant contributors (Including internal flood, fire, and seismic hazards) 10
Overview of NEI 05-01 Methodology SAMA 2. Preliminary Screening (Phase I)
Potential SAMA candidate was screened out if:
Process It modified features not applicable to BFN; (continued) It had already been implemented at BFN; or It was similar and could be combined with another SAMA candidates
- 3. Final Screening and Cost-Benefit Evaluation (Phase II)
Cost-benefit analysis was performed for each SAMA candidate remaining after preliminary screening Benefit of implementing a SAMA candidate was estimated in terms of averted consequences
- 4. Sensitivity Analyses Two sensitivity cases Instead of using a 20-year license renewal period, the full period is used (31 years for Unit 1, 32 years for Unit 2, and 34 years for Unit 3)
Conservative discount rate (3% instead of 7%)
11
Overview of Phase II Analysis SAMA Result of implementation of each SAMA candidate would be change in severe accident risk (change in frequency of severe accidents or change in frequency of subsequent Process release to environment)
(continued) Calculate baseline risk and cost Calculate each SAMAs risk and cost Calculate each SAMAs benefit 12
Phase II Analysis: Severe Accident Risk Overview of After baseline risk is calculated, severe accident risk after implementation of each SAMA SAMA candidate is calculated Process Level 2 PRA model was modified to reflect maximum benefit of each improvement (continued) Generally, maximum benefit of a SAMA candidate was determined with bounding modeling assumption For example, if objective of SAMA candidate was to reduce the likelihood of a certain failure mode, then eliminating the failure mode from PRA would bound the benefit, even though SAMA candidate would not be expected to be 100% effective in eliminating the failure Severe accident impacts were calculated based on:
Offsite exposure costs (monetary value of dose consequences to offsite population);
Offsite economic costs (monetary value of damage to offsite property);
Onsite exposure costs (monetary value of dose to workers); and Onsite economic costs (monetary value of damage to onsite property)
Results of Level 2 model were combined with Level 3 model to calculate post-SAMA costs These values are subtracted to calculate SAMA benefit 13
Overview of Phase II Analysis: Cost/Benefit Analysis SAMA Cost/Benefit Analysis of each SAMA performed Process Estimate each SAMAs cost (continued) Expected cost of enhancement to implement each SAMA established from existing estimates of similar modifications combined with engineering judgment Compare each SAMAs cost estimate to benefit calculations To assess viability of each SAMA considered for final cost-benefit evaluation, cost of implementing that SAMA was estimated and compared with estimated benefit If cost of implementation was greater than attainable benefit of a particular SAMA, then modification was not considered economically viable and was eliminated from further consideration 14
Overall Results SAMA Results Identification of Potential SAMA Candidates: 298 SAMA candidates Evaluation addressed 298 SAMA candidates for mitigating severe accident impacts Preliminary Screening (Phase I): 229 screened, 69 remain Eliminated 229 SAMA candidates from further consideration Based on either inapplicability to BFNs design, or features that had already been incorporated into BFNs current design, procedures, or programs Final Screening and Cost-Benefit Evaluation (Phase II): 63 screened, 6 remain Additional 63 SAMA candidates were eliminated because their cost was expected to exceed their benefit Six SAMAs found to be potentially cost-beneficial for mitigating consequences of severe accident at BFN Sensitivity Analyses: No additional cost-beneficial SAMAs Sensitivity studies indicated results of analysis would not change for conditions analyzed 15
SAMA Results Resulting Potentially Cost-Beneficial SAMAs (based on conservative calculations)
SAMA 64: Enhance procedures for actions on loss of heating, ventilation and air conditioning (HVAC) (Units 1, 2, and 3)
SAMA 65: Add emergency diesel generator building high temperature alarm or redundant louver and thermostat (Unit 3)
SAMA 148: Install inter-unit control rod drive (CRD) system cross-tie as potential means of recovering from loss of CRD at a given unit (Unit 1)
SAMA 149: Diverse emergency diesel generator HVAC logic. (Units 1, 2, and 3)
SAMA 150: Provide diverse swing emergency diesel generator air start compressor (Units 1, 2, and 3)
SAMA 157: Add automatic fire suppression system (Fire Compartment 13 -
Electrical Board Room 3A) (Unit 3)
Note: None of these SAMAs are related to adequately managing effects of aging during subsequent period of extended operation 16
Next Steps for Potentially Cost-Beneficial SAMAs Potentially SAMA analysis is conservative and is not a complete engineering project cost-benefit analysis - does not estimate all benefits or costs of a SAMA Cost- For example:
Beneficial May not consider increases or decreases in maintenance or operation costs following SAMA implementation SAMAs May not consider possible adverse consequences of the changes.
Although none of these potentially cost-beneficial SAMAs are related to adequately managing effects of aging during the subsequent period of extended operation, the following actions are being taken:
Condition Report initiated within Corrective Action Program to investigate more detailed cost analysis and potentially implement these cost-beneficial SAMAs Knowledgeable AE for BFN currently working on more accurate minimum cost estimates for these SAMAs Resulting SAMAs determined to be cost effective to be processed through BFN Plant Health Committee for further consideration 17
SLRA ER Contents - SAMA SLRA SLRA ER Section 4.15, Severe Accident Mitigation Alternatives Environmental Description of Methodology including:
Report Establishing Baseline Consequences of Severe Accidents Identifying SAMA Candidates Contents - Phase I Preliminary Screening SAMA Phase II Final Screening and Cost Benefit Evaluation Sensitivity Analyses Tables with Potentially Cost-Beneficial SAMAs and Bases for Conclusion SLRA ER Appendix E.1, Evaluation of BFN PRA Model Description of BFN PRA Level 1, 2, and 3 analyses, uncertainty, and PRA model peer review SLRA ER Appendix E.2, Evaluation of BFN SAMA Candidates Description of generation of initial list of potential SAMA candidates, screening methods, and analysis of remaining SAMA candidates BFN SLRA currently scheduled for submittal by end of 2023 Note: Supporting Engineering Documents/Calculations available on BFN SLR online reference portal for NRC review/audit 18
Abbreviations BFN Browns Ferry Nuclear Plant L-I Low-Intermediate Release CET Containment Event Tree LL-I Low Low-Intermediate Release List CFR CRD Code of Federal Regulations Control Rod Drive M-E M-I Medium-Early Release Medium-Intermediate Release EA Environmental Assessment MELLLA+ Maximum Extended Load Line Limit Analysis Plus EIS Environmental Impact NEI Nuclear Energy Institute Statement EPU Extended Power Uprate NFPA National Fire Protection Association ER Environmental Report NRC Nuclear Regulatory Commission F&Os Facts & Observations OTMHM One-Top Multi-Hazard Model FLEX Diverse and Flexible Coping PRA Probabilistic Risk Assessment Strategies H-E High-Early Release SAMA Severe Accident Mitigation Alternatives H-I High-Intermediate Release SLR SLR - Subsequent License Renewal H-L High-Late Release (H-L) SLRA Subsequent License Renewal Application HVAC Heating, Ventilation and Air WinMACCSS Windows MELCOR Accident Conditioning Consequences Code System 19
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