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| {{#Wiki_filter:1 Prairie Island Nuclear Generating Plant (PINGP) Pre-Application Meeting April 14, 2015 Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (IFBA) | | {{#Wiki_filter:Prairie Island Nuclear Generating Plant (PINGP) |
| | Pre-Application Meeting April 14, 2015 Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (IFBA) 1 |
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| 2 Agenda *Purpose / Objectives / Principles
| | Agenda |
| *Current Condition
| | * Purpose / Objectives / Principles |
| *Merits of IFBA
| | * Current Condition |
| -Gad *Scope of Licensing | | * Merits of IFBA-Gad |
| *Spent Fuel Pool (SFP) Criticality Analysis
| | * Scope of Licensing |
| *Schedule *Conclusion / Summary
| | * Spent Fuel Pool (SFP) Criticality Analysis |
| | * Schedule |
| | * Conclusion / Summary 2 |
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| 3 Meeting Purpose
| | Meeting Purpose |
| *Describe an Xcel Energy initiative to use IFBA and Gadolinium (Gad) neutron absorbers in the Westinghouse 422 Vantage Plus (422V+) fuel assembly design for PINGP operations and fuel storage
| | * Describe an Xcel Energy initiative to use IFBA and Gadolinium (Gad) neutron absorbers in the Westinghouse 422 Vantage Plus (422V+) fuel assembly design for PINGP operations and fuel storage |
| *Describe preliminary evaluation of the effects of this proposed change and the extent of NRC review that may be required
| | * Describe preliminary evaluation of the effects of this proposed change and the extent of NRC review that may be required 3 |
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| 4 Meeting Objectives
| | Meeting Objectives |
| *Common understanding of licensing scope
| | * Common understanding of licensing scope |
| *Common understanding of schedule
| | * Common understanding of schedule |
| *NRC feedback
| | * NRC feedback |
| *NRC expectations for submittal content
| | * NRC expectations for submittal content |
| *Actions 5 Principles
| | * Actions 4 |
| *Maintain nuclear safety margins
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| *Reliable power in the Midwest Region
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| *High confidence in refueling cycle timing
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| *Reduce spent fuel inventory
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| *Maintain regulatory margin
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| *No impact on plant operations
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| *No new impact on storage (human factors)
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| 6 Current Condition PINGP Description
| | Principles |
| *2-reactor site
| | * Maintain nuclear safety margins |
| *2-loop Westinghouse NSSS
| | * Reliable power in the Midwest Region |
| *Vantage 422+ with Optimized ZIRLO TM Fuel
| | * High confidence in refueling cycle timing |
| * Previously | | * Reduce spent fuel inventory |
| -used grid and nozzle designs
| | * Maintain regulatory margin |
| *Gadolinium burnable poison
| | * No impact on plant operations |
| *Currently operating 18
| | * No new impact on storage (human factors) 5 |
| -23 month cycles Optimized ZIRLO is a trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
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| 7 Current Condition PINGP Spent Fuel Pool (SFP) Description
| | Current Condition PINGP Description |
| | * 2-reactor site |
| | * 2-loop Westinghouse NSSS |
| | * Vantage 422+ with Optimized ZIRLOTM Fuel |
| | * Previously-used grid and nozzle designs |
| | * Gadolinium burnable poison |
| | * Currently operating 18-23 month cycles Optimized ZIRLO is a trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. |
| | Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners. |
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| | Current Condition PINGP Spent Fuel Pool (SFP) Description |
| * Criticality Safety Analysis approved in 2013 | | * Criticality Safety Analysis approved in 2013 |
| * Compliant to DSS | | * Compliant to DSS-ISG-2010-01 |
| -ISG-2010-01 | |
| * No credit for SFP neutron absorber (Boraflex) | | * No credit for SFP neutron absorber (Boraflex) |
| * Subcriticality criteria met by reactivity balancing ("checkerboarding | | * Subcriticality criteria met by reactivity balancing (checkerboarding) 7 |
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| 8 Current Condition Independent Spent Fuel Storage Installation
| | Current Condition Independent Spent Fuel Storage Installation |
| * Site-specific license for TN | | * Site-specific license for TN-40 cask storage |
| -40 cask storage | |
| * IFBA-Gad not specifically licensed | | * IFBA-Gad not specifically licensed |
| * 10-year decay time requirement for spent fuel | | * 10-year decay time requirement for spent fuel 8 |
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| 9 Xcel Energy and Westinghouse investigated optimizing the Prairie Island fuel management while maintaining the current reload plan
| | Design Optimization Xcel Energy and Westinghouse investigated optimizing the Prairie Island fuel management while maintaining the current reload plan |
| *Maintain or improve safety margins
| | * Maintain or improve safety margins |
| *Minimize assemblies requiring storage
| | * Minimize assemblies requiring storage |
| *Maximize fuel cycle economics Design Optimization
| | * Maximize fuel cycle economics 9 |
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| 10 Gad alone has negative impact on economics
| | Design Optimization Gad alone has negative impact on economics |
| *Displaces uranium, decreasing core loading
| | * Displaces uranium, decreasing core loading |
| *Residual reactivity hold down at end
| | * Residual reactivity hold down at end-of-cycle |
| -of-cycle *Requires additional assemblies to be loaded each cycle or increased fuel enrichment | | * Requires additional assemblies to be loaded each cycle or increased fuel enrichment |
| *Reduced gad loading results in unacceptably high soluble boron concentrations Design Optimization
| | * Reduced gad loading results in unacceptably high soluble boron concentrations 10 |
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| 11 IFBA
| | Design Optimization IFBA |
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| == Description:== | | == Description:== |
| Advanced fuel development program in the early 1980s led to development of a thin ZrB 2 coating on the UO 2 pellet as the optimum design *Integral to fuel rod, no separate component handling | | Advanced fuel development program in the early 1980s led to development of a thin ZrB2 coating on the UO2 pellet as the optimum design |
| *Complete depletion, no residual penalty *No residual poison, no displaced uranium
| | * Integral to fuel rod, no separate component handling |
| *Dilute absorber, low power peaking
| | * Complete depletion, no residual penalty |
| *ZrB 2 extensively used in Westinghouse PWRs today Design Optimization
| | * No residual poison, no displaced uranium |
| | * Dilute absorber, low power peaking |
| | * ZrB2 extensively used in Westinghouse PWRs today 11 |
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| | Design Optimization IFBA alone has limited reactivity control |
| | * Provides diminishing reactivity hold down over cycle |
| | * IFBA depletion rate higher at Beginning of Cycle (BOC) |
| | * Results in soluble boron increases at BOC |
| | * Loading IFBA alone results in unacceptably high soluble boron concentrations 12 |
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| | Merits of IFBA-Gad IFBA-Gad combination optimizes all three parameters |
| | * IFBA and Gad not in the same fuel pin |
| | * Combination maximizes or maintains safety margins |
| | * IFBA provides the necessary cycle length benefit to reduce assembly loading and maximize fuel economics |
| | * Gad provides the necessary reactivity hold down to obtain acceptable soluble boron concentrations |
| | * Both IFBA and Gad have extensive operating experience 13 |
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| 12 IFBA alone has limited reactivity control
| | Merits of IFBA-Gad 14 |
| *Provides diminishing reactivity hold down over cycle
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| *IFBA depletion rate higher at Beginning of Cycle (BOC) *Results in soluble boron increases at BOC
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| *Loading IFBA alone results in unacceptably high soluble boron concentrations Design Optimization
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| 13 IFBA-Gad combination optimizes all three parameters
| | Fuel Storage Considerations ISFSI will not require amendment until 2032 |
| *IFBA and Gad not in the same fuel pin
| | * 2018 First IFBA-Gad fuel load |
| *Combination maximizes or maintains safety margins
| | * 2022 First discharge of IFBA-Gad (2 cycles) |
| *IFBA provides the necessary cycle length benefit to reduce assembly loading and maximize fuel economics
| | * 2032 First IFBA-Gad in storage (10 yr decay) |
| *Gad provides the necessary reactivity hold down to obtain acceptable soluble boron concentrations
| | Spent Fuel Storage Requirements |
| *Both IFBA and Gad have extensive operating experience Merits of IFBA
| | * 39 fewer spent fuel assemblies over plant life |
| -Gad 14 Merits of IFBA
| | * 1 fewer spent fuel cask 15 |
| -Gad 15 Fuel Storage Considerations ISFSI will not require amendment until 2032
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| *2018 First IFBA
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| -Gad fuel load | |
| *2022 First discharge of IFBA
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| -Gad (2 cycles) | |
| *2032 First IFBA
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| -Gad in storage (10 yr decay) Spent Fuel Storage Requirements | |
| *39 fewer spent fuel assemblies over plant life
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| *1 fewer spent fuel cask
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| 16 Scope of Licensing Preliminary TS / 50.59 Reviews of IFBA
| | Scope of Licensing Preliminary TS / 50.59 Reviews of IFBA-Gad |
| -Gad *Reactor operations | | * Reactor operations |
| *SFP operations Preliminary
| | * SFP operations Preliminary |
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| == Conclusion:== | | == Conclusion:== |
| License Amendment for | | License Amendment for |
| *SFP Criticality Technical Specification (TS) changes 17 Scope of Licensing TS Review
| | * SFP Criticality Technical Specification (TS) changes 16 |
| - Reactor No TS changes for fuel design change
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| *TS 2.1.1.2.b Gad thermal conductivity penalty is unchanged *TS 4.2.1 description does not constrain IFBA
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| 18 Scope of Licensing 50.59 Review
| | Scope of Licensing TS Review - Reactor No TS changes for fuel design change |
| - Reactor No new material interactions, no new type of failure | | * TS 2.1.1.2.b Gad thermal conductivity penalty is unchanged |
| *Fabrication processes are unchanged
| | * TS 4.2.1 description does not constrain IFBA 17 |
| *Use existing Gad and IFBA specifications, good OE No increased probability of failure (e.g., clad failure) *Clad, geometry, weight, strength is same No increased consequence of failure
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| *Radiological source term change is insignificant
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| 19 Scope of Licensing Conclusion
| | Scope of Licensing 50.59 Review - Reactor No new material interactions, no new type of failure |
| - Reactor *No TS changes required | | * Fabrication processes are unchanged |
| *No 50.59 criteria exceeded
| | * Use existing Gad and IFBA specifications, good OE No increased probability of failure (e.g., clad failure) |
| *Prior NRC approval not required for reactor operations
| | * Clad, geometry, weight, strength is same No increased consequence of failure |
| | * Radiological source term change is insignificant 18 |
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| 20 Scope of Licensing TS Review
| | Scope of Licensing Conclusion - Reactor |
| - SFP *TS do not constrain fuel design in SFP
| | * No TS changes required |
| *Coefficients in TS Table 4.3.1 will change slightly Bu = A1*En3 + A2*En2 + A3*En + A4
| | * No 50.59 criteria exceeded |
| | * Prior NRC approval not required for reactor operations 19 |
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| 21 Scope of Licensing 50.59 Review
| | Scope of Licensing TS Review - SFP |
| - SFP No increased probability of failure (e.g., drop, clad failure) | | * TS do not constrain fuel design in SFP |
| *Clad, geometry, weight, strength, decay heat are same No increased consequence of failure
| | * Coefficients in TS Table 4.3.1 will change slightly Bu = A1*En3 + A2*En2 + A3*En + A4 20 |
| *Radiological source term change is insignificant Methods of Evaluation
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| *Same calculational framework (WCAP
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| -17400-P) 22 Scope of Licensing Conclusion
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| - SFP *No 50.59 criteria exceeded
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| *TS (Table 4.3.1) changes required *Prior NRC approval required for criticality function
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| 23 Background
| | Scope of Licensing 50.59 Review - SFP No increased probability of failure (e.g., drop, clad failure) |
| - LAR Scope No Complicating Factors | | * Clad, geometry, weight, strength, decay heat are same No increased consequence of failure |
| : *No significant change in fuel design
| | * Radiological source term change is insignificant Methods of Evaluation |
| *No credit for neutron poison inserts
| | * Same calculational framework (WCAP-17400-P) 21 |
| *No rerack, no rack design changes
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| *No new SFP loading restrictions
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| *No New Fuel Vault analysis
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| 24 Licensing Schedule 11/2015 Submit SFP Criticality LAR 11/2017 License Amendment 8/2018 Receipt of IFBA
| | Scope of Licensing Conclusion - SFP |
| -Gad Fuel 25 Spent Fuel Criticality Analysis Outline *Supplement Scope
| | * No 50.59 criteria exceeded |
| *Comparison with Current Analysis of Record
| | * TS (Table 4.3.1) changes required |
| *Compliance to DSS-ISG-2010-01 (ISG) *Summary *Conclusions
| | * Prior NRC approval required for criticality function 22 |
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| 26 Supplement Scope
| | Background - LAR Scope No Complicating Factors: |
| *Supplement WCAP
| | * No significant change in fuel design |
| -17400 (AoR) w/ IFBA-Gad *Incorporate multiple misload accident *Retain compliance with ISG
| | * No credit for neutron poison inserts |
| *Determine TS impacts Spent Fuel Criticality Analysis
| | * No rerack, no rack design changes |
| | * No new SFP loading restrictions |
| | * No New Fuel Vault analysis 23 |
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| 27 Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400 *Approved in 2013
| | Licensing Schedule 11/2015 Submit SFP Criticality LAR 11/2017 License Amendment 8/2018 Receipt of IFBA-Gad Fuel 24 |
| *Compliant to ISG *422V+ is limiting fuel design *IFBA-Gad fuel not specifically addressed
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| 28 Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400 *Important technical conclusions
| | Spent Fuel Criticality Analysis Outline |
| -Ignores gadolinia; shown to be conservative
| | * Supplement Scope |
| -Up to 100 MWd/MTU rodded operations in SER
| | * Comparison with Current Analysis of Record |
| -Fission product worth addressed in RAIs -Annular axial blankets conservatively modeled as solid -Confirmation of design basis fuel type (422V+)
| | * Compliance to DSS-ISG-2010-01 (ISG) |
| | * Summary |
| | * Conclusions 25 |
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| 29 *Objectives of the SFPC Analysis Supplement
| | Spent Fuel Criticality Analysis Supplement Scope |
| -Evaluate the impact of a new burnable absorber (BA) design on the discharge reactivity
| | * Supplement WCAP-17400 (AoR) w/ IFBA-Gad |
| -Minimize impact on AoR (supplement format)
| | * Incorporate multiple misload accident |
| *Methods to be used in the analysis
| | * Retain compliance with ISG |
| -Based on current AoR calculational framework
| | * Determine TS impacts 26 |
| *Selection of depletion calculation inputs
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| *Development of biases & uncertainties
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| *Accidents, interface conditions & soluble boron credit analysis Spent Fuel Criticality Analysis
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| 30 Analysis Supplement Scope
| | Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400 |
| *Configurations: no c hanges *IFBA-Gad 422V+ Fuel
| | * Approved in 2013 |
| -No credit for gadolinia -Planned max 120 IFBA pattern
| | * Compliant to ISG |
| -Cycle Avg Boron: 900 ppm to 1000 ppm
| | * 422V+ is limiting fuel design |
| -Fuel Density: 98% TD
| | * IFBA-Gad fuel not specifically addressed 27 |
| -Axial burnup and moderator temperature profiles
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| -Blankets fully enriched Spent Fuel Criticality Analysis
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| 31 *AoR depletion calculations based on burnup bins of 0-18, 18-30, 30-38, 38-48, and > 48 GWD/MTU -Limiting burnup profiles from the AoR to be checked against IFBA
| | Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400 |
| -Gad design profiles | | * Important technical conclusions |
| -Uniform profile considered
| | - Ignores gadolinia; shown to be conservative |
| *The following slides outline potential impacts related to ISG Spent Fuel Criticality Analysis
| | - Up to 100 MWd/MTU rodded operations in SER |
| | - Fission product worth addressed in RAIs |
| | - Annular axial blankets conservatively modeled as solid |
| | - Confirmation of design basis fuel type (422V+) |
| | 28 |
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| 32 ISG Criteria
| | Spent Fuel Criticality Analysis |
| *2a - 5% decrement method for depletion uncertainty
| | * Objectives of the SFPC Analysis Supplement |
| - same as AoR methodology | | - Evaluate the impact of a new burnable absorber (BA) design on the discharge reactivity |
| *2b - Nominal values m ay not b e appropriate, discuss selected values -PINGP IFBA
| | - Minimize impact on AoR (supplement format) |
| -Gad supplement analysis
| | * Methods to be used in the analysis |
| *Updated conservative average cycle soluble boron concentration
| | - Based on current AoR calculational framework |
| *Increase in fuel theoretical density Spent Fuel Criticality Analysis
| | * Selection of depletion calculation inputs |
| | * Development of biases & uncertainties |
| | * Accidents, interface conditions & soluble boron credit analysis 29 |
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| 33 ISG Criteria
| | Spent Fuel Criticality Analysis Analysis Supplement Scope |
| *2c - Consider Burnable Absorber Usage
| | * Configurations: no changes |
| -IFBA-Gad rods conservatively modeled during depletion, no pool credit for residual absorber
| | * IFBA-Gad 422V+ Fuel |
| *2d - Consider Rodded Depletion -No change expected due to IFBA
| | - No credit for gadolinia |
| -Gad fuel Spent Fuel Criticality Analysis | | - Planned max 120 IFBA pattern |
| | - Cycle Avg Boron: 900 ppm to 1000 ppm |
| | - Fuel Density: 98% TD |
| | - Axial burnup and moderator temperature profiles |
| | - Blankets fully enriched 30 |
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| 34 ISG Criteria
| | Spent Fuel Criticality Analysis |
| *3a - Select limiting axial b urnup profile using NUREG-6801 or plant
| | * AoR depletion calculations based on burnup bins of 0-18, 18-30, 30-38, 38-48, and > 48 GWD/MTU |
| -specific data -Use bounding profile from AoR site-specific burnup profiles and IFBA | | - Limiting burnup profiles from the AoR to be checked against IFBA-Gad design profiles |
| -Gad design profiles | | - Uniform profile considered |
| -An axially
| | * The following slides outline potential impacts related to ISG 31 |
| -uniform profile will be considered and used at those burnups if/when it is limiting
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| -Determine appropriate limiting moderator temperature profiles (distributed and uniform profile) Spent Fuel Criticality Analysis
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| 35 ISG Criteria
| | Spent Fuel Criticality Analysis ISG Criteria |
| *3b - Modeling SFP racks including geometry and neutron absorbers - same as AoR Methodology
| | * 2a - 5% decrement method for depletion uncertainty - same as AoR methodology |
| *3c - Interfaces
| | * 2b - Nominal values may not be appropriate, discuss selected values |
| - no methodology impact *3d - Normal Conditions | | - PINGP IFBA-Gad supplement analysis |
| - no impact expected *3e - Accident Conditions
| | * Updated conservative average cycle soluble boron concentration |
| -Incorporation of multiple misload event
| | * Increase in fuel theoretical density 32 |
| -No other changes from AoR methodology Spent Fuel Criticality Analysis
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| 36 ISG Criteria (Section 4)
| | Spent Fuel Criticality Analysis ISG Criteria |
| *Validation of Codes
| | * 2c - Consider Burnable Absorber Usage |
| -Code validation suite addresses ISG | | - IFBA-Gad rods conservatively modeled during depletion, no pool credit for residual absorber |
| -No impact to the AoR Spent Fuel Criticality Analysis | | * 2d - Consider Rodded Depletion |
| | - No change expected due to IFBA-Gad fuel 33 |
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| 37 WCAP Supplement Format
| | Spent Fuel Criticality Analysis ISG Criteria |
| *IFBA-Gad evaluation as WCAP-17400 Supplement
| | * 3a - Select limiting axial burnup profile using NUREG-6801 or plant-specific data |
| -Generate of burnup limits for IFBA
| | - Use bounding profile from AoR site-specific burnup profiles and IFBA-Gad design profiles |
| -Gad with current configurations | | - An axially-uniform profile will be considered and used at those burnups if/when it is limiting |
| -Evaluate normal conditions
| | - Determine appropriate limiting moderator temperature profiles (distributed and uniform profile) 34 |
| -Evaluate interface conditions
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| -Update accident analysis - Including multiple misload analysis -Soluble boron credit (normal and accident conditions)
| | Spent Fuel Criticality Analysis ISG Criteria |
| Spent Fuel Criticality Analysis
| | * 3b - Modeling SFP racks including geometry and neutron absorbers - same as AoR Methodology |
| | * 3c - Interfaces - no methodology impact |
| | * 3d - Normal Conditions - no impact expected |
| | * 3e - Accident Conditions |
| | - Incorporation of multiple misload event |
| | - No other changes from AoR methodology 35 |
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| | Spent Fuel Criticality Analysis ISG Criteria (Section 4) |
| | * Validation of Codes |
| | - Code validation suite addresses ISG |
| | - No impact to the AoR 36 |
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| | Spent Fuel Criticality Analysis WCAP Supplement Format |
| | * IFBA-Gad evaluation as WCAP-17400 Supplement |
| | - Generate of burnup limits for IFBA-Gad with current configurations |
| | - Evaluate normal conditions |
| | - Evaluate interface conditions |
| | - Update accident analysis - Including multiple misload analysis |
| | - Soluble boron credit (normal and accident conditions) 37 |
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| 38 Spent Fuel Criticality Analysis Summary
| | Spent Fuel Criticality Analysis Spent Fuel Criticality Analysis Summary |
| *Addition of IFBA (IFBA/IFBA
| | * Addition of IFBA (IFBA/IFBA-Gad design) to AoR |
| -Gad design) to AoR *Analysis remains in alignment with ISG *Supplement to WCAP | | * Analysis remains in alignment with ISG |
| -17400 will evaluate impact of IFBA | | * Supplement to WCAP-17400 will evaluate impact of IFBA-Gad fuel (introduction of IFBA) |
| -Gad fuel (introduction of IFBA) | | - Updated burnup limits |
| -Updated burnup limits
| | - Updated soluble boron requirements for normal and accident conditions 38 |
| -Updated soluble boron requirements for normal and accident conditions Spent Fuel Criticality Analysis
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| 39 In Conclusion
| | Spent Fuel Criticality Analysis In Conclusion |
| *SFP criticality analysis supplement w ill: -Conservatively bound proposed future operating conditions with regards to IFBA & IFBA
| | * SFP criticality analysis supplement will: |
| -Gad fuel -Address NRC Staff expectations (ISG) | | - Conservatively bound proposed future operating conditions with regards to IFBA & IFBA-Gad fuel |
| Spent Fuel Criticality Analysis
| | - Address NRC Staff expectations (ISG) 39 |
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| 40 Summary of Actions
| | Summary of Actions |
| *Xcel Energy Actions
| | * Xcel Energy Actions |
| -Points of Emphasis for LAR content
| | - Points of Emphasis for LAR content |
| *NRC Actions
| | * NRC Actions 40 |
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| 41 Summary Summary 1. Submit LAR 11/2015
| | Summary Summary |
| | : 1. Submit LAR 11/2015 |
| : 2. Include NRC expectations | | : 2. Include NRC expectations |
| : 3. Other actions | | : 3. Other actions 41 |
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| 42}} | | 42}} |
Letter Sequence Meeting |
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MONTHYEARML15105A0372015-04-14014 April 2015 Xcel Energy Slide Presentation to Support Pre-Application Meeting on April 14, 2015, to Discuss Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (Ifba) at the Prairie Island Nuclear Generating Plant Project stage: Meeting ML15107A0592015-05-15015 May 2015 Summary of the April 14, 2015, Public Meeting with Xcel Energy and Westinghouse to Discuss a Future License Amendment Request Regarding the Use of Ifba Rods in Nuclear Fuel at the Prairie Island Nuclear Generating Plant Project stage: Meeting 2015-04-14
[Table View] |
Xcel Energy Slide Presentation to Support Pre-Application Meeting on April 14, 2015, to Discuss Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (Ifba) at the Prairie Island Nuclear Generating PlantML15105A037 |
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Prairie Island |
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04/14/2015 |
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Xcel Energy |
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Beltz T |
Shared Package |
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ML15107A060 |
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TAC MF5839, TAC MF5840 |
Download: ML15105A037 (42) |
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24127A2402024-05-0707 May 2024 Presentation Slides for Prairie Island 2023 End-of-Cycle Meeting ML24029A0382024-01-31031 January 2024 January 31, 2024, Pre-application Meeting Presentation - Prairie Island ISFSI License Amendment Request to Add Grace to License Conditions ML23168A0032023-06-20020 June 2023 Handout for 6/23/2023 Pre-Application Public Meeting with Prairie Island Nuclear Generating Plant to Revise ISFSI TS 4.4 for TN-40HT Casks ML23156A2602023-06-0505 June 2023 2022 Prairie Island End-of-Cycle Meeting Presentation ML23102A1752023-04-14014 April 2023 April 14, 2023 TS 3.7.8 LAR Pre-Submittal Meeting Slides ML22130A5852022-05-10010 May 2022 2021 Monticello and Prairie Island Nuclear Generating Plant End-of-Cycle Meeting Presentation ML22048B1812022-02-18018 February 2022 Pre-Application Meeting for Prairie Island TS 5.6.6, PTLR, LAR ML21221A0202021-08-11011 August 2021 Nis Pr Bypass Test Panel License Amendment Request ML21166A3792021-06-15015 June 2021 Units 1 and 2 2020 End-of-Cycle Meeting Presentation ML21032A2632021-02-0303 February 2021 Slides for Public Meeting with Xcel Energy to Discuss a Planned Amendment to Combine the Emergency Plans and Create a Common Emergency Offsite Facility for Monticello and Prairie Island ML19347B0722019-12-12012 December 2019 TVA and Xcel Energy Slides for Joint Presubmittal Meeting to License Amendment Requests to Adopt WCAP-17661, Revision 1 ML19268A0422019-09-26026 September 2019 Pre-Application Meeting License Amendment Request Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19210D4512019-07-22022 July 2019 Abeyance Seal Preapplication Meeting Slides ML18051A1752018-02-20020 February 2018 Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy 2/20/2018 ML17240A3382017-08-30030 August 2017 Non-Safety Related Digital Feedwater and Amsac/Dss Control Systems Replacement Project Presentation ML17198A2632017-07-17017 July 2017 Pre-Application Meeting ML17066A3732017-03-0909 March 2017 Spent Fuel Pool Criticality Technical Specification Changes Round 2 Request for Additional Information Public Meeting: March 9, 2017 ML17037D1172017-02-0707 February 2017 License Amendment Requests for Change in Emergency Plan Staff Augmentation Response Times Pre-Submittal Meeting for Prairie Island Nuclear Generating Plant Monticello Nuclear Generating Plant: February 7, 2017 ML17023A0652017-01-24024 January 2017 Pre-Submittal Call Regarding License Amendment Requests for Prairie Island Nuclear Generating Plant, Units 1 and 2 and Monticello Nuclear Generating Plant Emergency Action Level Scheme Changes ML15140A3342015-05-13013 May 2015 Public Meeting 05132015 Licensee Slides Only ML15105A0372015-04-14014 April 2015 Xcel Energy Slide Presentation to Support Pre-Application Meeting on April 14, 2015, to Discuss Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (Ifba) at the Prairie Island Nuclear Generating Plant ML14323B0222014-11-19019 November 2014 Regcon, November 19-20, 2014: 03-Info-Session-2 Ronald Johnson - Tribal Perspective on Continued Storage ML14153A0242014-05-16016 May 2014 Xcel Energy'S Presentation Slides Supporting a May 16, 2014, Public Meeting to Discuss the Flood Hazard Reevaluation Schedule for the Monticello and Prairie Island Nuclear Generating Plants ML14058A1732014-02-19019 February 2014 Diesel Generator Steady State Voltage and Frequency Limits - Prairie Island Nuclear Generating Plant Meeting February 19, 2014 ML13210A2012013-07-29029 July 2013 2012 End-of-Cycle Slides - Licensee ML13210A2002013-07-11011 July 2013 2012 End-of-Cycle Slides ML13056A0262013-02-25025 February 2013 Regulatory Conference Slide Presentation ML12340A5402012-12-0606 December 2012 Reactor Core Cooling & Heat Removal FLEX Strategy - Phase 1 ML12326A9712012-11-21021 November 2012 Encl 3 (Handouts - Public) to Summary of October 24, 2012, Meeting with the Northern States Power Company, D/B/A Excel Energy Regarding Security Requirements and Changes Pertaining to Prairie Island TAC L24689 ML12277A1762012-10-0404 October 2012 Steam Generator Replacement Presentation ML12275A4652012-09-27027 September 2012 Meeting September 27, 2012 - Handouts ML12275A3782012-09-27027 September 2012 Xcel Energy Prairie Island Nuclear Generating Plant Meeting Presentation, Diesel Generator Voltage and Frequency Limits. ML12205A2172012-07-23023 July 2012 NRC 2011 End-of-Cycle Slides ML12205A2202012-07-17017 July 2012 Licensee 2012 End-of-Cycle Slides ML12115A3112012-04-24024 April 2012 Meeting Slides: 04/24/2012 Meeting with Xcel Energy NFPA 805 Presubmittal - Prairie Island Nuclear Generating Plant ML1207904792012-03-14014 March 2012 March 14, 2012 Telecon Slides ML1122803892011-08-18018 August 2011 Pre-Application Meeting for Prairie Island Nuclear Generating Plant (Ping) Extended Power Uprate (EPU) ML1119903462011-07-28028 July 2011 Meeting Presentation, Prairie Island Nuclear Generating Plant - Failure to Maintain the Train a and B Direct Current Electrical Power Subsystems Operable ML1117804242011-06-22022 June 2011 June 22, 2011, Meeting Handout #1 - NRC Meeting Diesel Fuel Oil LAR for Prairie Island Ngp ML1120701572011-06-22022 June 2011 June 22, 2011, Meeting Handout #2 - Proposed Technical Specification Changes for Prairie Island Ngp Diesel Fuel Oil LAR ML1106600792011-03-0303 March 2011 March 3, 2011 Meeting Handouts - Revise Footnote in TS 3.8.1, Prairie Island Nuclear Generating Plant ML1034701142010-12-14014 December 2010 Excel Energy Slides for Public Meeting 12/14/2010 to Discuss Human Performance Issues ML1027802642010-10-0404 October 2010 Session 4 - Heather Westra Presentation at October 4, 2010, Public Meeting on Groundwater Protection ML1023805712010-08-25025 August 2010 Meeting Presentation Alternative Source Term Steam Generator Tube Rupture Margin to Overfill Evaluation - Prairie Island Nuclear Generating Plant ML1014502432010-05-26026 May 2010 Responses to Questions from the Prairie Island Indian Community Concerning Issues Related to Prairie Island Nuclear Generating Plant ML1012604192010-05-20020 May 2010 Meeting Presentation Prairie Island Annual Assessment Meeting - Reactor Oversight Program - 2009 ML1012503422010-05-0505 May 2010 Regulatory Conference Slides ML1015801072010-04-28028 April 2010 2R26 Outage, SG Tube Inspection Telecon Slides ML1010604782010-04-15015 April 2010 April 15, 2010, Meeting Slides - Pre-Application Meeting for Prairie Island Ngp Extended Power Uprate ML0932901282009-12-0101 December 2009 Licensee Slides for Public Meeting 2024-05-07
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24127A2402024-05-0707 May 2024 Presentation Slides for Prairie Island 2023 End-of-Cycle Meeting ML24059A4042024-03-0606 March 2024 March 6, 2023, Presubmittal Meeting for License Amendment Request to Modify Technical Specifications Definitions & Approve Plant-Specific Methods for Response Time Testing (EPID L-2024-LRM-0034) - Slides ML24029A0382024-01-31031 January 2024 January 31, 2024, Pre-application Meeting Presentation - Prairie Island ISFSI License Amendment Request to Add Grace to License Conditions ML23168A0032023-06-20020 June 2023 Handout for 6/23/2023 Pre-Application Public Meeting with Prairie Island Nuclear Generating Plant to Revise ISFSI TS 4.4 for TN-40HT Casks ML23156A2602023-06-0505 June 2023 2022 Prairie Island End-of-Cycle Meeting Presentation ML23102A1752023-04-14014 April 2023 April 14, 2023 TS 3.7.8 LAR Pre-Submittal Meeting Slides ML22130A5852022-05-10010 May 2022 2021 Monticello and Prairie Island Nuclear Generating Plant End-of-Cycle Meeting Presentation ML22048B1812022-02-18018 February 2022 Pre-Application Meeting for Prairie Island TS 5.6.6, PTLR, LAR ML21166A3792021-06-15015 June 2021 Units 1 and 2 2020 End-of-Cycle Meeting Presentation ML21124A0652021-05-0606 May 2021 Xcel Energy Presentation for May 6, 2021 Public Meeting to Discuss 24-Month Cycles at Prairie Island Nuclear Generating Plant, Units 1 and 2 ML21032A2632021-02-0303 February 2021 Slides for Public Meeting with Xcel Energy to Discuss a Planned Amendment to Combine the Emergency Plans and Create a Common Emergency Offsite Facility for Monticello and Prairie Island ML20266F1052020-09-23023 September 2020 (PINGP) COVID-19 Exemption Request for the 2020 Biennial Emergency Preparedness Exercise ML20212L8622020-07-29029 July 2020 2019 Monticello and Prairie Island EOC Presentation from Webinar ML20098F0682020-04-0909 April 2020 Preapplication Teleconference Presentation: License Amendment Request to Adopt TSTF-569 ML20057D3082020-02-18018 February 2020 Slides Potential License Amendment to Remove Note from LCO 3.4.12 and LCO 3.4.13 ML19268A0422019-09-26026 September 2019 Pre-Application Meeting License Amendment Request Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19210D4512019-07-22022 July 2019 Abeyance Seal Preapplication Meeting Slides ML19071A2782019-03-0707 March 2019 Enclosure 3: Meeting Slides (Summary of February 28, 2019, Public Meeting with Xcel Energy to Discuss Increasing the Amount of Special Nuclear Material Authorized for Storage at the Prairie Island ISFSI (W/Enclosures 1 and 2)) ML18162A0262018-06-12012 June 2018 License Amendment Request to Reclassify Certain Fuel Handling Equipment ML18051A1752018-02-20020 February 2018 Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy 2/20/2018 ML17240A3382017-08-30030 August 2017 Non-Safety Related Digital Feedwater and Amsac/Dss Control Systems Replacement Project Presentation ML17209A1192017-07-17017 July 2017 Summary of July 17, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request Related to Heavy Lifting Devices ML17198A2632017-07-17017 July 2017 Pre-Application Meeting ML17066A3732017-03-0909 March 2017 Spent Fuel Pool Criticality Technical Specification Changes Round 2 Request for Additional Information Public Meeting: March 9, 2017 ML17037D1172017-02-0707 February 2017 License Amendment Requests for Change in Emergency Plan Staff Augmentation Response Times Pre-Submittal Meeting for Prairie Island Nuclear Generating Plant Monticello Nuclear Generating Plant: February 7, 2017 ML17023A0652017-01-24024 January 2017 Pre-Submittal Call Regarding License Amendment Requests for Prairie Island Nuclear Generating Plant, Units 1 and 2 and Monticello Nuclear Generating Plant Emergency Action Level Scheme Changes ML16280A0372016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 2 of 3 ML16280A0422016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 3 of 3 ML16280A0352016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 1 of 3 ML15140A3342015-05-13013 May 2015 Public Meeting 05132015 Licensee Slides Only ML15127A6562015-05-0707 May 2015 PI EOC Mtg NRC Slides ML15105A0372015-04-14014 April 2015 Xcel Energy Slide Presentation to Support Pre-Application Meeting on April 14, 2015, to Discuss Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (Ifba) at the Prairie Island Nuclear Generating Plant ML14323B0222014-11-19019 November 2014 Regcon, November 19-20, 2014: 03-Info-Session-2 Ronald Johnson - Tribal Perspective on Continued Storage ML14162A5202014-06-11011 June 2014 Slides: Prairie Island Independent Spent Fuel Storage Installation - License Renewal Application - Discussion of Requests for Additional Information, for June 16, 2014, Public Meeting ML14153A0242014-05-16016 May 2014 Xcel Energy'S Presentation Slides Supporting a May 16, 2014, Public Meeting to Discuss the Flood Hazard Reevaluation Schedule for the Monticello and Prairie Island Nuclear Generating Plants ML14084A3242014-03-21021 March 2014 M140321: Slides - Presented by Multiple Participants at Commission Briefing on Waste Confidence Rulemaking ML13210A2012013-07-29029 July 2013 2012 End-of-Cycle Slides - Licensee ML13210A2002013-07-11011 July 2013 2012 End-of-Cycle Slides ML13056A0262013-02-25025 February 2013 Regulatory Conference Slide Presentation ML12340A5402012-12-0606 December 2012 Reactor Core Cooling & Heat Removal FLEX Strategy - Phase 1 ML12326A9712012-11-21021 November 2012 Encl 3 (Handouts - Public) to Summary of October 24, 2012, Meeting with the Northern States Power Company, D/B/A Excel Energy Regarding Security Requirements and Changes Pertaining to Prairie Island TAC L24689 ML12277A1762012-10-0404 October 2012 Steam Generator Replacement Presentation ML12275A3782012-09-27027 September 2012 Xcel Energy Prairie Island Nuclear Generating Plant Meeting Presentation, Diesel Generator Voltage and Frequency Limits. ML12205A2172012-07-23023 July 2012 NRC 2011 End-of-Cycle Slides ML12205A2202012-07-17017 July 2012 Licensee 2012 End-of-Cycle Slides ML12115A3112012-04-24024 April 2012 Meeting Slides: 04/24/2012 Meeting with Xcel Energy NFPA 805 Presubmittal - Prairie Island Nuclear Generating Plant ML1207904792012-03-14014 March 2012 March 14, 2012 Telecon Slides ML1122803892011-08-18018 August 2011 Pre-Application Meeting for Prairie Island Nuclear Generating Plant (Ping) Extended Power Uprate (EPU) ML1119903462011-07-28028 July 2011 Meeting Presentation, Prairie Island Nuclear Generating Plant - Failure to Maintain the Train a and B Direct Current Electrical Power Subsystems Operable ML1117804242011-06-22022 June 2011 June 22, 2011, Meeting Handout #1 - NRC Meeting Diesel Fuel Oil LAR for Prairie Island Ngp 2024-05-07
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Text
Prairie Island Nuclear Generating Plant (PINGP)
Pre-Application Meeting April 14, 2015 Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (IFBA) 1
Agenda
- Purpose / Objectives / Principles
- Spent Fuel Pool (SFP) Criticality Analysis
Meeting Purpose
- Describe an Xcel Energy initiative to use IFBA and Gadolinium (Gad) neutron absorbers in the Westinghouse 422 Vantage Plus (422V+) fuel assembly design for PINGP operations and fuel storage
- Describe preliminary evaluation of the effects of this proposed change and the extent of NRC review that may be required 3
Meeting Objectives
- Common understanding of licensing scope
- Common understanding of schedule
- NRC expectations for submittal content
Principles
- Maintain nuclear safety margins
- Reliable power in the Midwest Region
- High confidence in refueling cycle timing
- Reduce spent fuel inventory
- Maintain regulatory margin
- No impact on plant operations
- No new impact on storage (human factors) 5
Current Condition PINGP Description
- Vantage 422+ with Optimized ZIRLOTM Fuel
- Previously-used grid and nozzle designs
- Currently operating 18-23 month cycles Optimized ZIRLO is a trademark of Westinghouse Electric Company LLC, its Affiliates and/or its Subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved.
Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
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Current Condition PINGP Spent Fuel Pool (SFP) Description
- Criticality Safety Analysis approved in 2013
- No credit for SFP neutron absorber (Boraflex)
- Subcriticality criteria met by reactivity balancing (checkerboarding) 7
Current Condition Independent Spent Fuel Storage Installation
- Site-specific license for TN-40 cask storage
- IFBA-Gad not specifically licensed
- 10-year decay time requirement for spent fuel 8
Design Optimization Xcel Energy and Westinghouse investigated optimizing the Prairie Island fuel management while maintaining the current reload plan
- Maintain or improve safety margins
- Minimize assemblies requiring storage
- Maximize fuel cycle economics 9
Design Optimization Gad alone has negative impact on economics
- Displaces uranium, decreasing core loading
- Residual reactivity hold down at end-of-cycle
- Requires additional assemblies to be loaded each cycle or increased fuel enrichment
- Reduced gad loading results in unacceptably high soluble boron concentrations 10
Design Optimization IFBA
Description:
Advanced fuel development program in the early 1980s led to development of a thin ZrB2 coating on the UO2 pellet as the optimum design
- Integral to fuel rod, no separate component handling
- Complete depletion, no residual penalty
- No residual poison, no displaced uranium
- Dilute absorber, low power peaking
- ZrB2 extensively used in Westinghouse PWRs today 11
Design Optimization IFBA alone has limited reactivity control
- Provides diminishing reactivity hold down over cycle
- IFBA depletion rate higher at Beginning of Cycle (BOC)
- Results in soluble boron increases at BOC
- Loading IFBA alone results in unacceptably high soluble boron concentrations 12
Merits of IFBA-Gad IFBA-Gad combination optimizes all three parameters
- IFBA and Gad not in the same fuel pin
- Combination maximizes or maintains safety margins
- IFBA provides the necessary cycle length benefit to reduce assembly loading and maximize fuel economics
- Gad provides the necessary reactivity hold down to obtain acceptable soluble boron concentrations
- Both IFBA and Gad have extensive operating experience 13
Merits of IFBA-Gad 14
Fuel Storage Considerations ISFSI will not require amendment until 2032
- 2018 First IFBA-Gad fuel load
- 2022 First discharge of IFBA-Gad (2 cycles)
- 2032 First IFBA-Gad in storage (10 yr decay)
Spent Fuel Storage Requirements
- 39 fewer spent fuel assemblies over plant life
- 1 fewer spent fuel cask 15
Scope of Licensing Preliminary TS / 50.59 Reviews of IFBA-Gad
- SFP operations Preliminary
Conclusion:
License Amendment for
- SFP Criticality Technical Specification (TS) changes 16
Scope of Licensing TS Review - Reactor No TS changes for fuel design change
- TS 2.1.1.2.b Gad thermal conductivity penalty is unchanged
- TS 4.2.1 description does not constrain IFBA 17
Scope of Licensing 50.59 Review - Reactor No new material interactions, no new type of failure
- Fabrication processes are unchanged
- Use existing Gad and IFBA specifications, good OE No increased probability of failure (e.g., clad failure)
- Clad, geometry, weight, strength is same No increased consequence of failure
- Radiological source term change is insignificant 18
Scope of Licensing Conclusion - Reactor
- No 50.59 criteria exceeded
- Prior NRC approval not required for reactor operations 19
Scope of Licensing TS Review - SFP
- TS do not constrain fuel design in SFP
- Coefficients in TS Table 4.3.1 will change slightly Bu = A1*En3 + A2*En2 + A3*En + A4 20
Scope of Licensing 50.59 Review - SFP No increased probability of failure (e.g., drop, clad failure)
- Clad, geometry, weight, strength, decay heat are same No increased consequence of failure
- Radiological source term change is insignificant Methods of Evaluation
Scope of Licensing Conclusion - SFP
- No 50.59 criteria exceeded
- TS (Table 4.3.1) changes required
- Prior NRC approval required for criticality function 22
Background - LAR Scope No Complicating Factors:
- No significant change in fuel design
- No credit for neutron poison inserts
- No rerack, no rack design changes
- No new SFP loading restrictions
- No New Fuel Vault analysis 23
Licensing Schedule 11/2015 Submit SFP Criticality LAR 11/2017 License Amendment 8/2018 Receipt of IFBA-Gad Fuel 24
Spent Fuel Criticality Analysis Outline
- Comparison with Current Analysis of Record
Spent Fuel Criticality Analysis Supplement Scope
- Incorporate multiple misload accident
- Retain compliance with ISG
Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400
- 422V+ is limiting fuel design
- IFBA-Gad fuel not specifically addressed 27
Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400
- Important technical conclusions
- Ignores gadolinia; shown to be conservative
- Up to 100 MWd/MTU rodded operations in SER
- Fission product worth addressed in RAIs
- Annular axial blankets conservatively modeled as solid
- Confirmation of design basis fuel type (422V+)
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Spent Fuel Criticality Analysis
- Objectives of the SFPC Analysis Supplement
- Evaluate the impact of a new burnable absorber (BA) design on the discharge reactivity
- Minimize impact on AoR (supplement format)
- Methods to be used in the analysis
- Based on current AoR calculational framework
- Selection of depletion calculation inputs
- Development of biases & uncertainties
- Accidents, interface conditions & soluble boron credit analysis 29
Spent Fuel Criticality Analysis Analysis Supplement Scope
- Configurations: no changes
- No credit for gadolinia
- Planned max 120 IFBA pattern
- Cycle Avg Boron: 900 ppm to 1000 ppm
- Fuel Density: 98% TD
- Axial burnup and moderator temperature profiles
- Blankets fully enriched 30
Spent Fuel Criticality Analysis
- AoR depletion calculations based on burnup bins of 0-18, 18-30, 30-38, 38-48, and > 48 GWD/MTU
- Limiting burnup profiles from the AoR to be checked against IFBA-Gad design profiles
- Uniform profile considered
- The following slides outline potential impacts related to ISG 31
Spent Fuel Criticality Analysis ISG Criteria
- 2a - 5% decrement method for depletion uncertainty - same as AoR methodology
- 2b - Nominal values may not be appropriate, discuss selected values
- PINGP IFBA-Gad supplement analysis
- Updated conservative average cycle soluble boron concentration
- Increase in fuel theoretical density 32
Spent Fuel Criticality Analysis ISG Criteria
- 2c - Consider Burnable Absorber Usage
- IFBA-Gad rods conservatively modeled during depletion, no pool credit for residual absorber
- 2d - Consider Rodded Depletion
- No change expected due to IFBA-Gad fuel 33
Spent Fuel Criticality Analysis ISG Criteria
- 3a - Select limiting axial burnup profile using NUREG-6801 or plant-specific data
- Use bounding profile from AoR site-specific burnup profiles and IFBA-Gad design profiles
- An axially-uniform profile will be considered and used at those burnups if/when it is limiting
- Determine appropriate limiting moderator temperature profiles (distributed and uniform profile) 34
Spent Fuel Criticality Analysis ISG Criteria
- 3b - Modeling SFP racks including geometry and neutron absorbers - same as AoR Methodology
- 3c - Interfaces - no methodology impact
- 3d - Normal Conditions - no impact expected
- Incorporation of multiple misload event
- No other changes from AoR methodology 35
Spent Fuel Criticality Analysis ISG Criteria (Section 4)
- Code validation suite addresses ISG
- No impact to the AoR 36
Spent Fuel Criticality Analysis WCAP Supplement Format
- Generate of burnup limits for IFBA-Gad with current configurations
- Evaluate normal conditions
- Evaluate interface conditions
- Update accident analysis - Including multiple misload analysis
- Soluble boron credit (normal and accident conditions) 37
Spent Fuel Criticality Analysis Spent Fuel Criticality Analysis Summary
- Addition of IFBA (IFBA/IFBA-Gad design) to AoR
- Analysis remains in alignment with ISG
- Supplement to WCAP-17400 will evaluate impact of IFBA-Gad fuel (introduction of IFBA)
- Updated burnup limits
- Updated soluble boron requirements for normal and accident conditions 38
Spent Fuel Criticality Analysis In Conclusion
- SFP criticality analysis supplement will:
- Conservatively bound proposed future operating conditions with regards to IFBA & IFBA-Gad fuel
- Address NRC Staff expectations (ISG) 39
Summary of Actions
- Points of Emphasis for LAR content
Summary Summary
- 1. Submit LAR 11/2015
- 2. Include NRC expectations
- 3. Other actions 41
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