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| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
| | license number = DPR-042, DPR-060 | | | license number = DPR-042, DPR-060 |
| | contact person = Beltz T A | | | contact person = Beltz T |
| | case reference number = TAC MF5839, TAC MF5840 | | | case reference number = TAC MF5839, TAC MF5840 |
| | package number = ML15107A060 | | | package number = ML15107A060 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
| | page count = 42 | | | page count = 42 |
| | project = TAC:MF5840, TAC:MF5839 | | | project = TAC:MF5839, TAC:MF5840 |
| | stage = RAI | | | stage = Meeting |
| }} | | }} |
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| =Text= | | =Text= |
| {{#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) 2 Agenda *Purpose / Objectives / Principles *Current Condition *Merits of IFBA-Gad *Scope of Licensing *Spent Fuel Pool (SFP) Criticality Analysis *Schedule *Conclusion / Summary 3 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 4 Meeting Objectives *Common understanding of licensing scope *Common understanding of schedule *NRC feedback *NRC expectations for submittal content *Actions 5 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) 6 Current Condition PINGP Description *2-reactor site *2-loop Westinghouse NSSS *Vantage 422+ with Optimized ZIRLOTM Fuel | | {{#Wiki_filter:Prairie Island Nuclear Generating Plant (PINGP) |
| * 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. | | Pre-Application Meeting April 14, 2015 Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (IFBA) 1 |
| 7 Current Condition PINGP Spent Fuel Pool (SFP) Description
| | |
| | Agenda |
| | * Purpose / Objectives / Principles |
| | * Current Condition |
| | * Merits of IFBA-Gad |
| | * Scope of Licensing |
| | * Spent Fuel Pool (SFP) Criticality Analysis |
| | * Schedule |
| | * Conclusion / Summary 2 |
| | |
| | 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 feedback |
| | * NRC expectations for submittal content |
| | * Actions 4 |
| | |
| | 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 |
| | * 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. |
| | 6 |
| | |
| | Current Condition PINGP Spent Fuel Pool (SFP) Description |
| * Criticality Safety Analysis approved in 2013 | | * Criticality Safety Analysis approved in 2013 |
| * Compliant to DSS-ISG-2010-01 | | * Compliant to DSS-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 |
| 8 Current Condition Independent Spent Fuel Storage Installation
| | |
| | Current Condition Independent Spent Fuel Storage Installation |
| * Site-specific license for TN-40 cask storage | | * Site-specific license for TN-40 cask storage |
| * IFBA-Gad not specifically licensed | | * IFBA-Gad not specifically licensed |
| * 10-year decay time requirement for spent fuel 9 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 Design Optimization 10 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 Design Optimization 11 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 Design Optimization 12 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 Design Optimization 13 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 Merits of IFBA-Gad 14 Merits of IFBA-Gad 15 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 16 Scope of Licensing Preliminary TS / 50.59 Reviews of IFBA-Gad *Reactor operations *SFP operations Preliminary Conclusion: License Amendment for *SFP Criticality Technical Specification (TS) changes 17 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 18 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 19 Scope of Licensing Conclusion - Reactor *No TS changes required *No 50.59 criteria exceeded *Prior NRC approval not required for reactor operations 20 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 21 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 *Same calculational framework (WCAP-17400-P) 22 Scope of Licensing Conclusion - SFP *No 50.59 criteria exceeded *TS (Table 4.3.1) changes required *Prior NRC approval required for criticality function 23 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 24 Licensing Schedule 11/2015 Submit SFP Criticality LAR 11/2017 License Amendment 8/2018 Receipt of IFBA-Gad Fuel 25 Spent Fuel Criticality Analysis Outline *Supplement Scope *Comparison with Current Analysis of Record *Compliance to DSS-ISG-2010-01 (ISG) *Summary *Conclusions 26 Supplement Scope *Supplement WCAP-17400 (AoR) w/ IFBA-Gad *Incorporate multiple misload accident *Retain compliance with ISG *Determine TS impacts Spent Fuel Criticality Analysis 27 Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400 *Approved in 2013 *Compliant to ISG *422V+ is limiting fuel design *IFBA-Gad fuel not specifically addressed 28 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+) | | * 10-year decay time requirement for spent fuel 8 |
| 29 *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 Spent Fuel Criticality Analysis 30 Analysis Supplement Scope *Configurations: no changes *IFBA-Gad 422V+ Fuel -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 Spent Fuel Criticality Analysis 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-Gad design profiles -Uniform profile considered *The following slides outline potential impacts related to ISG Spent Fuel Criticality Analysis 32 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 Spent Fuel Criticality Analysis 33 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 Spent Fuel Criticality Analysis 34 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) Spent Fuel Criticality Analysis 35 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 *3e - Accident Conditions -Incorporation of multiple misload event -No other changes from AoR methodology Spent Fuel Criticality Analysis 36 ISG Criteria (Section 4) *Validation of Codes -Code validation suite addresses ISG -No impact to the AoR Spent Fuel Criticality Analysis 37 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) Spent Fuel Criticality Analysis 38 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 Spent Fuel Criticality Analysis 39 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) Spent Fuel Criticality Analysis 40 Summary of Actions *Xcel Energy Actions -Points of Emphasis for LAR content *NRC Actions 41 Summary Summary 1. Submit LAR 11/2015 2. Include NRC expectations 3. Other actions 42
| | |
| }} | | 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 |
| | * Reactor operations |
| | * 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 TS changes required |
| | * 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 |
| | * Same calculational framework (WCAP-17400-P) 21 |
| | |
| | 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 |
| | * Supplement Scope |
| | * Comparison with Current Analysis of Record |
| | * Compliance to DSS-ISG-2010-01 (ISG) |
| | * Summary |
| | * Conclusions 25 |
| | |
| | Spent Fuel Criticality Analysis Supplement Scope |
| | * Supplement WCAP-17400 (AoR) w/ IFBA-Gad |
| | * Incorporate multiple misload accident |
| | * Retain compliance with ISG |
| | * Determine TS impacts 26 |
| | |
| | Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400 |
| | * Approved in 2013 |
| | * Compliant to ISG |
| | * 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+) |
| | 28 |
| | |
| | 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 |
| | * IFBA-Gad 422V+ Fuel |
| | - 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 |
| | * 3e - Accident Conditions |
| | - Incorporation of multiple misload event |
| | - No other changes from AoR methodology 35 |
| | |
| | Spent Fuel Criticality Analysis ISG Criteria (Section 4) |
| | * Validation of Codes |
| | - Code validation suite addresses ISG |
| | - No impact to the AoR 36 |
| | |
| | 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 |
| | |
| | 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 |
| | * Xcel Energy Actions |
| | - Points of Emphasis for LAR content |
| | * NRC Actions 40 |
| | |
| | Summary Summary |
| | : 1. Submit LAR 11/2015 |
| | : 2. Include NRC expectations |
| | : 3. Other actions 41 |
| | |
| | 42}} |
Letter Sequence Meeting |
|---|
|
|
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] |
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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
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[Table view]
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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.
6
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+)
28
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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