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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
[Table view] |
Text
Tennessee Valley Authority Browns Ferry Nuclear Plant I Unit 1 Restart 7
z TVA/NRC Meeting-.
Nuclear Reýa.qto ulolifi fi`- Rockville, MD June 12 2002 S."'**""i
-1*
Enclosure 2
Agenda
"* Introduction/Meeting Objectives - Jon Rupert
- Tim Abney
"* Regulatory History
- Jon Rupert/Joe Valente
"* Overview and Schedule
- Joe Valente
"* Methodology for Special Programs
- Tim Abney
- Licensing Actions - Tim Abney
° Generic Communications - Tim Abney
- Licensing Actions of Special Interest - Tim Abney
- Commitment Closure - Tim Abney
- Unit I Regulatory Framework - Jon Rupert Summary and Open Discussion I
Unit 1 Restart - Introduction/Meeting Objectives Objectives of this meeting are:
Provide overview of Unit 1 Restart Project Discuss regulatory history of Units 2 and 3 restarts Present licensing actions, and other reviews that will be needed from NRR Initiate dialogue on Regulator3 Framework for Unit I restart 2
Jon Rupert
Regulatory History
- Unit 2 Restart of safety, All 3 BFN units voluntarily shatdown by TVA in March, 1985 because regulatory and management issues TVA committed to obtain NRC approval prior to restart of any BFN unit 1985, NRC issued a "show cause" letter for all TVA nuclear plants in September, under 10 CFR 50.54 (f), and requested TVA to specify corrective actions 1986 TVA submitted the Nuclear Performance P1 n, Volume 3, in August, to Unit 2 outlining the steps needed to recover the BFtN units, specifically directed to TVA and NRC conducted several meetings and TVA made several submittals fully define the regulatory actions needed to restart BFN Unit 2
- NRC issued NUREG 1232, Volume 3, Supplement 2 in January, 1991, concluding that TVA's actions acceptably addressed deficiencies in BFN NRC approved Unit 2 restart on May 23, 1991 Unit 2 restarted on May 24, 1991 3
Tim Abney
Regulatory History U-,.
Unit 3 Restart and 3 in July, 1991, TVA proposed regulatory framework for restart of Units 1 outlining improvements from the Unit 2 precedent
- NRC approved framework proposed by TVA in April, 1992 Programs, as the Unit 3 restart effort dealt prin .ly with resolving Special management issues had been resolved for Unit 2 restart of Unit 3 on November 1, NRC staff issued SECY-95-264 recommending restart 1995 NRC approved Unit 3 restart on November 15, 1995 Unit 3 restarted on November 19, 1995 4
Tim Abney
Regulatory History EnW Unit 1 on Based on Energy Vision 2020 recommendations, TVA decided to delay decision Unit 1 restart
- Unit 1 was removed from the NRC's problem plant list on June 21,1996 based on commitments from an April 16, 1996 TVA letter to:
"° Implement same special programs on Unit 1 that were done for Unit 3
"* Not restart Unit 1 without prior approval of NRC Ao 1-5 Tim Abney
Overview and Schedule MA Detailed Scoping, Estimate and Planning (DSEP)
- Extensive effort to support Unit 1 restart decision on restart
- Utilized key TVA personnel with both discipline expertise and experience of units 2 and 3 effort Results in organizational structure and strong team in place for recovery Unit 1 Restart Principles BFN units will be operationally the same at completion of Unit 1 Restart available Unit 1 Restart activities will use plant processes and procedures when 6
Jon Rupert
Overview and Schedule LL[
Workscope Required for Unit 1 Restart
- Special Programs using criteria consistent with Unit 3 Restart
- Design changes since Units 2/3 restart
- Future design changes in 5 year BFN Project Plan
- Corrective/Preventive Maintenance
- Regulatory Issues
- Licensing Actions
- Inservice Inspection 7
Joe Valente
Methodology for Special Programs Special Program Differences in Unit 1 vs. Unit 3 Approach None Configuration Mana it None Design Calculations None Equipmnmt Qualification None Seismnic Design None Fire Protection Improvement None Instumunt Sensing Lines None Wall Thinning Not Reuired PRA None Compoent &PiecePart Qualification None Electrical Issues None Q-List None MEfLB None Platform Thermal Growth Complete replacenmmt of recirculation pipinn IGSCC None Coatings None Restart Test Not Required Plant Weldin Not Required Heat Code Traceability 8
Joe Valente
2M2.. . 2003 ..
SO RD APPROVAL N RD MAJOR CONTRACTS EN NEERING PROGRAMS REQD FOR MODS
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INEERING ISSUE DRYWELL DCWS NR BRIEF OBILIUEMODIFICATIONS SUPPORT TEAM NG LEAD MATERIAL- ORDER MODIFCATIONS - DEMOLITION & NON DCN ACTIVITIES PREPARE & ISSUE BULK MATERIAL ORDER LONG LEAD MATERIAL - DELIVER ENGINEERING ISSUE REACTOR BUILDING OCN'S DESIGN ENGINEERING SUPPORT ENGINEERING ISSUE CONTROL BUILDING DCN'S MODIFICATIONS IMPLEMENT DRYWELL DCN'S CRD:
=70 ALREADINESS REVIEW 4IRCTESTING N071FICATION LICENSING TO NOTIFY NRC OF FUEL LOAD FUEL LOAD TURBINE GENERATOR ON TURNING GEAR NCR APPROVAL FOR RESTART POWER ASCENSION TESTING BREAKER CLOSURE
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Licensing Actions Technical Specifications Changes/ cense Amendments High Range Primary Containment Radiation Monitors Monitor Power Range Neutron Monitor (PRNM) Upgrade With Implementation of Average Power Range (APRM) and Rod Block Monitor (RBM) TS ARTS/MELLL 14 Day Allowable Outage Time for Emergency Diesel Generators Extended Power Uprate Operation 24 Month Fuel Cycle for Emergency Core Crediting of Containment Overpressure for Net Positive Suction Head Calculations Cooling Pumps Change Setpoint of Scram Discharge Volume PT Curves Safety Limit Minimum Critical Power Ratio (SLMCPR)
Allowable Value for Reactor Vessel Water Level - Low, Level 3 Oscillation Power Range Monitor (OPRM) 50 Appendix J Main Steam Isolation Valve (MSIV) Leakage Rate Limits and Exemption from 10 CFR Excess Flow Check Valve Surveillance Intervals Containment Air Dilution (CAD) AOT Alternative Source Term Miscellaneous I & C Changes 10 Tim Atbney
Licensing Actions Relief Requests Inservice Inspection Program - 11 requests for relief including one which provides of the RPV for permanent deferral of examinations for circumferential shell welds Containment Inspection Program - 5 requests for relief System Pressure Test (SPT) Program - 6 re( iests for relief Programmatic Relief Request, 5 requests for relief Risk-Informed ISI Program - 1 request for relief 11 Tim Abney
Generic Communications -I Bulletins GE 88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by 88-04 Potential Safety Related Pump Loss 90-01 Loss of Fill Oil in Rosemount Transmitters 93-02 Debris Plugging of Emergency Core Cooling Suction Strainers Suppression Pool Cooling Mode 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in 12 Tim Abney
Generic Communications Generic Letters 88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping 88-20, S4 Individual Plant Examination of External Events for Severe Accident Vulnerabilities 89-13 Service Water System Problems Affecting Safety Related Equipment 92-01 Reactor Vessel Structural Integrity 94-02 Long Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs 94-03 Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs 95-07 Pressure Locking and Thermal Binding of Safety Related and Power-Operated Gate Valves 96-06 Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions 97-04 Assurance of Sufficent Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps 98-04 Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss of Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment 13 S1111 M-AVo1y
Generic Communications
- NUREG-0737 (TMI Action Plan) Action Items LD.1 Control Room Design Review I.D.2 Safety Parameter Display Console II.B.2 Plant Shielding II.B.3 Post-Accident Sampling System II.E.4.2. 1-4 Containment Isolation Dependability - Implement Diverse Isolation II.F. 1.2.C Accident - Monitoring - Containment High Range Radiation II. F.1.2.D Accident - Monitoring - Containment Pressure 1.F. 1.2.E Accident - Monitoring - Containment Water Level II.F.2.4 (Generic Letter 84-23) - Instrumentation for Detection of Inadequate Core Cooling II.K.3.13 HPCI/RCIC Initiation Levels II.K.3.18 ADS Actuation Modifications II.K.3.28 Qualification of ADS Accumulators Tim Abney 14
Licensing Actions of Special Interest
° Extended Power Uprate
° Unit 1 license condition to provide analysis for Technical Specifications changes since 1985 Tim Abney 15
Commitment Closure 0 268 total open Unit 1 commitments
- 68 associated with Generic Communications 0 70 from LERs, violations and inspections
- 130 from other miscellaneous sources
- These will be evaluated in accordance with NEI 99-04 for potential decommitments Tim Abney 16
Unit 1 Regulatory Framework Eu".
Regulatory Framework will includ(.
- Summary of Special Programs
- Submittals required Concurrent licensing actions for all 3 units, where applicable Commitment closure process Actions needed for NRC restart approval 0 TVA intends to submit proposed Regulatory Framework document by December 31, 2002
-F; A17 I IM 11A111y
Summary and Conclusions Jon Rupert 18
BFN UNIT I PROJECT PLAN 2
PRIORITY ISSUES ...............................................................................................................................................................
INSPECTIONS......................................................................................................................................................................2 2
MEETINGSN ISITS ...............................................................................................................................................................
2 PENDING NRC ACTIONS ....................................................................................................................................................
3 TECHNICAL SPECIFICATIONS ..........................................................................................................................................
SUBMITTALS .......................................................................................................................................................................
8 NRC COMMITMENTS ...................................................................................................................................
2 BFN UNIT 1 PROJECT PLAN Page 2 I CONTACT (NRC, TVA CONTACT MILESTONE DATE INPO, NEIL, ANI)
MEETINGSNISITS K. Jabbour T. Abney 6/12/02 M. Morrison K. Jabbour
-NRR - Unit 1 Restart Overview @ Rockville 7/24/02 NRR - License Renewal @ Rockville
Page 3 BFN UNIT I PROJECT PLAN SUBMITTAL --- r- FED REG TVA NEED TVA CONTACT SUBMITTAL DATE DATE TECHNICAL SPECIFICATIONS DATE
_________ L ________ 3UIUi I ________
t 4 3Q/03 Containment Air Dilution (CAD) AOT ______________
3Q103 3Q/03 Excess Flow CQeck Valve Surveillance Intervals _________ L 4Q/03 4 4Q/03 High Range Primary Containment Radiation Monitors I v 4Q/03 PT Curves 11Q/04
__________ I I ___
Q/04 Crediting of Containment Overpressure for Ne Positive Suction Head Calculations for Emergency Core Cooling Pumps I -i I-t -
1 Q/04 Allowable Value For Reactor Vessel Water Level - Low Level 3 ___________________ 4 20/04 2Q/04 Oscillation Power Range Monitor (OPRM)
___________ 4- 2Q04 1 1 2Q '04 Main Steam Isolation Valve (MSIV) Leakage Rate Limits and Exemption From 10 CFR 50 Appendix J 20/04 f 4
2Q/04 SDIV Setpoint Change 20104 2Q/04 14-Day Allowed Outage Time for Emergency Diesel Generators 3Q104 I I 3Q/04 Power Range Neutron Monitor (PRNM)
Upgrade with Implementation of Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) TS ARTS/MELLL 3Q1r -
3Q/04 Miscellaneous I & C Changes 30/04 3Q/04 24 Month Fuel Cycle t-Alternative Source Term 3Q/05 Extended Power Uprate Operation 4Q/05 FSafety Limit Minimum Critical Power Rýa-tio 4Q/05
_________________________________I
Page 4 BFN UNIT I PROJECT PLAN SUBMITTALS - LOOK AHEAD DUE DATE AND INPUT DUE _ _ _ _
Input Resp Org Input Rec'd Sch'd Actual Sch'd Actual Due Comment IJic Description Due
- ConcuriCocurnSignaure DDate to [Date to Signature Signaure Date to Signature Date De Eng Due Concur Concur ____
-t %.41v d-Regulatory 1 Framework 1Q/03 GL 88-01 NRC Position on IGSCC in BWR Austenitic Stainless Steel Part 1 Piping I I I I 1Q/03 GL 94-03 Intergranular Stress Part 2 Corrosion Cracking 3Q/03 of Core Shrouds in BWRs 2Q/03 inservice Inspection (ISI) Program Relief Requests 3Q/03 Containment Inspection Program Relief Requests ________________ -t r 3Q/03 16 System Pressure Test (SPT) Program Relief Requests _____
____ ____ 4- - II 4Q/03 L
Programmatic Relief Requests _______ 4- T 1 Q104 BL 93-02 Debris Plugging of Emergency Core Cooling Suction I Strainers i 1 I _____ _____ I _________
Page 5 BFN UNIT 1 PROJECT PLAN SUBMITTALS - LOOK AHEAD nI r-nATl Amnl NIDI IT flD IF In ut Re - A U m I- r-1-1AN I 9 1L14 -4.
Aa-% .-I 1 Uf~ A,4..d I ue mm nt LiLi Resp Org /Actual Date to Date to V Vlgl .......
Input Input Rec'd Scn'dto Date to Eng Description Date Date Due Signature Signature I Concur Concur
=I1'0I0A I I r- I I I I I ikýuu-+
1 1.41 --
I 9 BL 95-02 Unexpected Clogging of a RHR Pump Strainer While Operating in Suppression Pool _ _ __ _ _ _ -I-2Q/04 0 BL 88-03 Inadequate Latch Engagement in HFA Type Relays Manufactured by GE ___________ I 4- t -T 2Q/04 I1 BL 88-04 Potential Safety Related Pump Loss 2Q/04 12 GL 89-13 Service Water System Problems Affecting Safety Related Equipment I 1 T 2Q/04 13 GL 94-02 Long Term Solutions Thermal-Hydraulic Instabilities in BWRs I 3Q/04 14 BL 90-01 Loss of Fill Oil in Rosemount Transmitters I _____ _______ ______________ I _____ _______ - _______ -
Page 6 BFN UNIT I PROJECT PLAN SUBMITTALSAmn - LOOK AHEAD nl Ir- nATP I IPOI TntFlI U1t1,./ li lt .AUI i rI .. IU 1= Sch'd Actualto Due Comment Lic Eng Input Resp Org Input Rec'd Sch'd Actual Date to Date Date Description Oate to Date to Due Signature Concur Concur Signature T 1 12/0ý4 Owl U-T 157GL 95-07 Pressure Locking and Thermal Binding of Safety-Related and power-Operated Gate Valves _ I I__ 1 3Q/04 19 GL 96-06 Assurance of Equipment Operability and Containmeni Integrity During Design Basis Accident Conditions _________ __ 4.1 tI 3Q/04 17 GL 97-04 Assurance of Sufficient Net Positive Suction for Emergency Core Cooling and Containment Heat Removal Pumps ________ ___ - II 4Q/04 18 GL 98-04 Potential for Degradation of the Emergency Core Cooling Systems Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment I ______________________ I ______________ I _____________ __________________ j _________________ __________________ ___________________ --
BFN UNIT I PROJECT PLAN Page SUBMITTALS - LOOK AHEAD DUE DATE AND INPUT DUE Description Input Resp Org Input Rec'd Sch'd Actual Sch'd Actual Due Comment Lic Due Due Date Dte to t Date Dat to to Date ate to o Date Dae tojDateEm toDate E Concur Concur Signature Signature 19 Risk-Informed 3Q/05 Inservice Inspection Program 20 GL 88-20, S4 4Q/05 Individual Plant Examination of External Events for Severe Accident Vulnerabilities
-I I T T r t I 4 I L 21
,-21 1 GL 92-01 Reactor 4Q/05 Vessel Structural Integrity
- - I - - - - - I
Page 8 NRC COMMITMENTS - TOTAL OPEN (14) - FOUR-WEEK LOOK AHEAD None
[CCTS Number Originating Lead Coord. Closure TVA Due Commitment Description Lic Document Pkg Due to Date Eng.
Lic Eng.
None s:lic/everyone/Project Plan Unit 1/020614 Unit 1.doc