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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
Browns Ferry Nuclear Plant Maximum Extended Load Line Limit Analysis Plus License Amendment Request Gerry Doyle Director EPU January 4, 2017
BFN MELLLA+
Agenda Introductions G. Doyle Overview B. Baker Benefits for Browns Ferry Nuclear Plant B. Baker Project Goals B. Baker Approach to Fuel and Plant Licensing Analyses G. Storey
- GEH Methods Applicability to AREVA Fuel
- AREVA Methods Applicability to MELLLA+
Approach to Thermal Hydraulic Stability Solution G. Storey Approach to ATWS Analyses B. Bird Schedule P. Donahue Questions/Comments G. Doyle Browns Ferry MELLLA+ License Amendment Request l 2
BFN MELLLA+
Overview
- Extended Power Uprate (EPU) power levels restrict flow window Maximum Extended Load Line Limit Analysis (MELLLA) rod line extrapolated to EPU power
- Licensed flow window reduced: 99% - 105% core flow at rated EPU power
- Administrative margin would limit operating flow window: 100% - 104% range
- MELLLA Plus (MELLLA+) raises the maximum allowed rod line Licensed flow window: 85% - 105% core flow at rated EPU power Browns Ferry MELLLA+ License Amendment Request l 3
BFN MELLLA+
Benefits for Browns Ferry Nuclear Plant
- MELLLA+ expands nominal core flow window at EPU conditions Reduction in number of end of cycle down-powers Fewer control rod manipulations required to manage reactivity
- Detect and Suppress Solution - Confirmation Density (DSS-CD) provides improved core instability detection algorithm
- Increases station capacity factor during the operating cycle Browns Ferry MELLLA+ License Amendment Request l 4
BFN MELLLA+
Project Goals
- High quality License Amendment Request (LAR)
- Effective integration into plant systems
- Effective training for plant operators and plant maintenance staff
- Smooth transition to plant operations
- Implement MELLLA+ for all three units prior to Browns Ferry Nuclear Plant (BFN) Unit 3 End of Cycle conditions Browns Ferry MELLLA+ License Amendment Request l 5
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses All topical areas of the MELLLA+ Licensing Topical Report (NEDC-33006P-A) will be addressed in the BFN MELLLA+ LAR
- GE Hitachi (GEH) MELLLA+ Licensing Topical Report process with GEH methodologies and analyses will address:
Non-fuel impacts Long term Anticipated Transient Without Scram (ATWS) and ATWS Instability (ATWS-I) explicitly modeling ATRIUM 10XM fuel
- AREVA methodologies and analyses will address:
Fuel, core design, Core Operating Limits Report fuel limits, Loss of Coolant Accident (LOCA) and transient analyses ATWS and American Society of Mechanical Engineers overpressure Methods applicability to MELLLA+
Modifications to implement MELLLA+
- License Conditions and Technical Specifications Changes
- Average Power Range Monitor and Oscillating Power Range Monitor setpoints and implementation Probabilistic Risk Assessment, procedure updates, operator training Application of existing plant-specific EPU analysis Browns Ferry MELLLA+ License Amendment Request l 6
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses
- BFN MELLLA+ LAR to be based on current AREVA ATRIUM 10XM fuel type
- BFN MELLLA+ LAR to include GEH MELLLA+ Safety Analysis Report (M+SAR)
AREVA MELLLA+ SAR (AMSAR)
- Similar to Power Uprate Safety Analysis Report/Fuel Uprate Safety Analysis Report approach of BFN EPU LAR AREVA fuel related reports similar to recent BFN fuel transition LARs and BFN EPU LAR
- Transition cycle design report Basis of representative Reload Report analyses BFN 3 cycle 19 EPU core re-depleted at MELLLA+ conditions
- Equilibrium cycle ATRIUM 10XM design report Basis of AMSAR fuel related analyses EPU equilibrium core re-depleted at MELLLA+ conditions
- Reload Analysis Report (transition cycle based)
Full representative reload evaluation Browns Ferry MELLLA+ License Amendment Request l 7
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses AREVA fuel related reports similar to recent BFN fuel transition LARs and BFN EPU LAR (continued)
- Fuel rod thermal mechanical report Demonstrates application of RODEX4 to BFN at MELLLA+ conditions
- Fuel thermal hydraulic report Demonstrate continued acceptability of thermal hydraulic performance of ATRIUM 10XM and legacy ATRIUM 10 fuel at MELLLA+ conditions
- Safety Limit Minimum Critical Power Ratio Report Performed for representative transition core using SAFLIM3D
- Methods applicability report Plant specific demonstration of AREVA methods applicability at MELLLA+ conditions Update to prior supplements of ANP-2860, Browns Ferry Unit 1 -
Summary of Responses to Request for Additional Information, Extension to use ATRIUM 10XM Fuel for Extended Power Uprate Address prior Browns Ferry fuel related Requests for Additional Information (RAIs), including MELLLA+, as well as applicable RAIs from other utilities recent LARs Browns Ferry MELLLA+ License Amendment Request l 8
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses AREVA fuel related reports similar to recent BFN fuel transition LARs and BFN EPU LAR (continued)
- LOCA New break spectrum analysis at MELLLA+ conditions
- Consistent with ATRIUM 10XM EPU analysis in ANP-3377, Browns Ferry Units 1, 2, and 3 LOCA Break Spectrum Analysis for ATRIUM 10XM Fuel (EPU)
Break spectrum and ATRIUM 10XM fuel Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) reports included in LAR Legacy ATRIUM 10 LOCA approach
- LOCA system response from the MELLLA+ based ATRIUM 10XM analysis will be used to drive ATRIUM 10 hot channel heatup
- ATRIUM 10XM break spectrum is applicable because the two types are closely matched thermal hydraulically
- MAPLHGR report for ATRIUM 10 provided
- Limiting Peak Clad temperature is at Beginning of Life
- Legacy ATRIUM-10 fuel will be at twice burned exposure Browns Ferry MELLLA+ License Amendment Request l 9
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses Treatment of 10 CFR 50.46c Issues
- Same approach as included in BFN EPU LAR Update ANP-3409, Fuel-Related Emergent Regulatory Issues, for MELLLA+ conditions Treatment of Reactivity Initiated Accidents (RIAs)
- RIA will be evaluated with NRC-approved methodology 230 Calorie limit will be imposed for fuel fragmentation
- For BFN EPU LAR, an additional conservative RIA evaluation was presented in ANP-3409, Fuel-Related Emergent Regulatory Issues MELLLA+ has no effect on fuel failure thresholds ANP-3409 remains valid for MELLLA+
- Revised regulation could be issued prior to LAR submittal AREVAs AURORA-B Control Rod Drop Accident (CRDA) method is anticipated to be approved by NRC prior to issuance of new regulation AURORA-B CRDA evaluation could be submitted Browns Ferry MELLLA+ License Amendment Request l 10
BFN MELLLA+
GEH Methods Applicability to AREVA Fuel
- GEH previously presented information on methods applicability (during Brunswick Pre-application Meeting on August 20, 2013 (ML13277A038))
ATRIUM 10 Fuel Experience ATRIUM 10XM Fuel for ATWS Methods Uncertainty Identification/Management Process ATRIUM 10XM Modeling Approach Methods Application
- Core Modeling
- ATWS Analysis
- Applicable Interim Methods Licensing Topical Report and MELLLA+ Licensing Topical Report Limitations and Conditions
- Concluded GEH Methods are applicable to ATRIUM 10XM fuel in the MELLLA+ condition ATRIUM 10XM explicitly modeled Uncertainties in modeling ATRIUM 10XM fuel with GEH methods addressed in a conservative fashion Browns Ferry MELLLA+ License Amendment Request l 11
BFN MELLLA+
AREVA Methods Applicability to MELLLA+
- AREVA previously presented information on methods applicability (during Brunswick Pre-application Meeting on April 17, 2014 (ML14135A511))
Applicability of AREVA methods to MELLLA+ conditions is described in Methods Applicability Report
- Methods Applicability Report to be submitted in BFN MELLLA+ LAR Restrictions for fuel dependent analyses presented in NEDO-33006-A were reviewed for applicability to AREVA methods
- Required analysis reports will be submitted in BFN MELLLA+ LAR
- Concluded AREVA methods are applicable to MELLLA+ conditions Steady state and transient neutronic and thermal-hydraulic analytical methods and codes systems supporting MELLLA+ will be applied within NRC approved applicability ranges Calculation and measurement uncertainties applied in MELLLA+ applications are valid Assessment database and uncertainty of model used to simulate the plant response to MELLLA+ conditions are equivalent to core and assembly conditions for which AREVA methodology was benchmarked AREVA analyses will comply with the fuel-specific limitations and conditions from the generic MELLLA+ Safety Evaluation for NEDO-33006-A
- Methods-specific limitations will be addressed consistent with NRC approved AREVA methodologies Browns Ferry MELLLA+ License Amendment Request l 12
BFN MELLLA+
Approach to Thermal Hydraulic Solution
- BFN will use GEH Detect and Suppress Solution - Confirmation Density (DSS-CD)
Referenced in MELLLA+ Licensing Topical Report BFN Unit 1 already has hardware - configured as Option III
- Some modification required to update to present day hardware configuration
- Make common with new BFN Unit 2 and 3 DSS-CD configuration
- BFN Operations and Maintenance personnel are familiar with the installed hardware on Unit 1 and will require limited training to implement DSS-CD BFN Units 2 and 3 require complete upgrade
- EPROM software and firmware plus voter hardware Adds a new stability analysis algorithm
- Confirmation Density Algorithm Retains current Option III algorithms as defense-in-depth backups GEH will determine DSS-CD set points and provide process for cycle specific validation for AREVA reloads Browns Ferry MELLLA+ License Amendment Request l 13
BFN MELLLA+
Approach to ATWS Analyses
- Long term ATWS MELLLA+ margin will be demonstrated with ATRIUM 10XM specific analyses SLC System B-10 enrichment increase should offset MELLLA+ heat load increase
- NEDC-33006P-A Generic MELLLA+ Licensing Topical Report and Safety Evaluation Report Best estimate TRACG or equivalent analysis of post depressurization ATWS required if Hot Shutdown Boron Weight (HSBW) not injected before shutdown/Heat Capacity Temperature Limit (HCTL) is reached Due to SLC system B-10 enrichment increase, HSBW expected to be injected before shutdown/HCTL reached Browns Ferry MELLLA+ License Amendment Request l 14
BFN MELLLA+
Approach to ATWS Analyses
- ATWS Instability GEH will explicitly analyze ATRIUM 10XM fuel for ATWS-I Treatment of uncertainties associated with modeling AREVA fuel will follow the conservative approach used for Brunswick Demonstrate that coolable geometry is maintained
- ATWS Overpressure mitigation Existing AREVA methodology will provide analysis of record Safety Relief Valve Out of Service analysis is expected to be supported for MELLLA+
Analysis will apply 95/95 Safety Relief Valve upper setpoint tolerance
- Different than Technical Specification requirement
- Based on plant performance Browns Ferry MELLLA+ License Amendment Request l 15
BFN MELLLA+
Schedule Browns Ferry MELLLA+ License Amendment Request l 16
BFN MELLLA+
Acronym List
- AMSAR - AREVA MELLLA+ Safety Analysis Report
- ATWS-I - ATWS Instability
- BFN - Browns Ferry Nuclear Plant
- DSS-CD - Detect and Suppress Solution - Confirmation Density
- ELLLA - Extended Load Line Limit Analysis
- GEH - General Electric Hitachi
- HCTL - Heat Capacity Temperature Limit
- HSBW - Hot Shutdown Boron Weight
- ICF - Increased Core Flow
- LAR - License Amendment Request
- LOCA - Loss of Coolant Accident
- MAPLHGR - Maximum Average Planar Linear Heat Generation Rate
- MELLLA - Maximum Extended Load Line Limit Analysis
- M+SAR - MELLLA+ Safety Analysis Report (GEH)
- NRC - Nuclear Regulatory Commission
- OLTP - Original Licensed Thermal Power
- RAIs - Requests for Additional Information
- RIAs - Reactivity Initiated Accidents
BFN MELLLA+
Questions/Comments Browns Ferry EPU License Amendment Request FIV Monitoring Program l 18