ML16356A034
| ML16356A034 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/04/2017 |
| From: | Doyle G Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Saba F, NRR/DORL/LPL2-2, 415-1447 | |
| References | |
| Download: ML16356A034 (18) | |
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 Browns Ferry MELLLA+ License Amendment Request
Introductions
Overview Benefits for Browns Ferry Nuclear Plant Project Goals Approach to Fuel and Plant Licensing Analyses GEH Methods Applicability to AREVA Fuel AREVA Methods Applicability to MELLLA+
Approach to Thermal Hydraulic Stability Solution Approach to ATWS Analyses Schedule Questions/Comments G. Doyle B. Baker B. Baker B. Baker G. Storey G. Storey B. Bird P. Donahue G. Doyle l 2
BFN MELLLA+
Overview Browns Ferry MELLLA+ License Amendment Request l 3 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
BFN MELLLA+
Benefits for Browns Ferry Nuclear Plant Browns Ferry MELLLA+ License Amendment Request l 4 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
BFN MELLLA+
Project Goals Browns Ferry MELLLA+ License Amendment Request l 5 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
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses Browns Ferry MELLLA+ License Amendment Request 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+
TVA will address:
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 l 6
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses Browns Ferry MELLLA+ License Amendment Request 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 l 7
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses Browns Ferry MELLLA+ License Amendment Request 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 l 8
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses Browns Ferry MELLLA+ License Amendment Request AREVA fuel related reports similar to recent BFN fuel transition LARs and BFN EPU LAR (continued)
New break spectrum analysis at MELLLA+ conditions ATRIUM 10XM fuel based 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 l 9
BFN MELLLA+
Approach to Fuel and Plant Licensing Analyses Browns Ferry MELLLA+ License Amendment Request 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 regulatory guidance 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 regulatory guidance
AURORA-B CRDA evaluation could be submitted l 10
Browns Ferry MELLLA+ License Amendment Request 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 l 11 BFN MELLLA+
GEH Methods Applicability to AREVA Fuel
Browns Ferry MELLLA+ License Amendment Request 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 l 12 BFN MELLLA+
AREVA Methods Applicability to MELLLA+
Browns Ferry MELLLA+ License Amendment Request 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 l 13 BFN MELLLA+
Approach to Thermal Hydraulic Solution
Browns Ferry MELLLA+ License Amendment Request BFN EPU increases Standby Liquid Control (SLC) System Boron-10 (B-10) enrichment to 94 atom percent 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 l 14 BFN MELLLA+
Approach to ATWS Analyses
Browns Ferry MELLLA+ License Amendment Request 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 l 15 BFN MELLLA+
Approach to ATWS Analyses
BFN MELLLA+
Schedule Browns Ferry MELLLA+ License Amendment Request l 16
BFN MELLLA+
Acronym List Browns Ferry MELLLA+ License Amendment Request l 17 AMSAR - AREVA MELLLA+ Safety Analysis Report ATWS - Anticipated Transient Without Scram ATWS-I - ATWS Instability B Boron-10 BFN - Browns Ferry Nuclear Plant CRDA - Control Rod Drop Accident DSS-CD - Detect and Suppress Solution - Confirmation Density ELLLA - Extended Load Line Limit Analysis EPU - Extended Power Uprate 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 MELLLA+ - MELLLA Plus 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 SE - Safety Evaluation SLC - Standby Liquid Control SPU - Stretch Power Uprate
BFN MELLLA+
Questions/Comments Browns Ferry EPU License Amendment Request FIV Monitoring Program l 18