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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
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| page count = 42
| page count = 42
| project = TAC:MF5839, TAC:MF5840
| project = TAC:MF5839, TAC:MF5840
| stage = RAI
| stage = Meeting
}}
}}


=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)
{{#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
2 Agenda Purpose / Objectives / Principles Current Condition Merits of IFBA-Gad Scope of Licensing Spent Fuel Pool (SFP) Criticality Analysis Schedule Conclusion / Summary  
*Current Condition
*Merits of IFBA
-Gad *Scope of Licensing
*Spent Fuel Pool (SFP) Criticality Analysis
*Schedule *Conclusion / Summary


3 Meeting Purpose
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  
*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
4 Meeting Objectives Common understanding of licensing scope Common understanding of schedule NRC feedback NRC expectations for submittal content Actions  
*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
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)
*2-reactor site
*2-loop Westinghouse NSSS
*Vantage 422+ with Optimized ZIRLO TM 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.


7 Current Condition PINGP Spent Fuel Pool (SFP) Description
6 Current Condition PINGP Description 2-reactor site 2-loop Westinghouse NSSS Vantage 422+ with Optimized ZIRLOTM Fuel
* Criticality Safety Analysis approved in 2013
* 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.
* Compliant to DSS
Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
-ISG-2010-01
* No credit for SFP neutron absorber (Boraflex)
* Subcriticality criteria met by reactivity balancing ("checkerboarding
")
8 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


9 Xcel Energy and Westinghouse investigated optimizing the Prairie Island fuel management while maintaining the current reload plan
7 Current Condition PINGP Spent Fuel Pool (SFP) Description Criticality Safety Analysis approved in 2013 Compliant to DSS-ISG-2010-01 No credit for SFP neutron absorber (Boraflex)
*Maintain or improve safety margins
Subcriticality criteria met by reactivity balancing (checkerboarding)
*Minimize assemblies requiring storage
*Maximize fuel cycle economics Design Optimization


10 Gad alone has negative impact on economics
8 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
*Displaces uranium, decreasing core loading
 
*Residual reactivity hold down at end
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
-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
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
11 IFBA


== 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 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
*Complete depletion, no residual penalty *No residual poison, no displaced uranium
 
*Dilute absorber, low power peaking
12 IFBA alone has limited reactivity control Provides diminishing reactivity hold down over cycle IFBA depletion rate higher at Beginning of Cycle (BOC)
*ZrB 2 extensively used in Westinghouse PWRs today Design Optimization
Results in soluble boron increases at BOC Loading IFBA alone results in unacceptably high soluble boron concentrations Design Optimization  


12 IFBA alone has limited reactivity control
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
*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
14 Merits of IFBA-Gad  
*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
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)
-Gad *Reactor operations
Spent Fuel Storage Requirements 39 fewer spent fuel assemblies over plant life 1 fewer spent fuel cask
*SFP operations Preliminary
 
16 Scope of Licensing Preliminary TS / 50.59 Reviews of IFBA-Gad Reactor operations SFP operations Preliminary


== Conclusion:==
== Conclusion:==
License Amendment for
License Amendment for SFP Criticality Technical Specification (TS) changes  
*SFP Criticality Technical Specification (TS) changes 17 Scope of Licensing TS Review  
 
- Reactor No TS changes for fuel design change
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  
*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


18 Scope of Licensing 50.59 Review  
20 Scope of Licensing TS Review - SFP
- Reactor No new material interactions, no new type of failure
* TS do not constrain fuel design in SFP
*Fabrication processes are unchanged
* Coefficients in TS Table 4.3.1 will change slightly Bu = A1*En3 + A2*En2 + A3*En + A4
*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
21 Scope of Licensing 50.59 Review - SFP No increased probability of failure (e.g., drop, clad failure)
- Reactor *No TS changes required
* Clad, geometry, weight, strength, decay heat are same No increased consequence of failure
*No 50.59 criteria exceeded
* Radiological source term change is insignificant Methods of Evaluation
*Prior NRC approval not required for reactor operations
* Same calculational framework (WCAP-17400-P)


20 Scope of Licensing TS Review
22 Scope of Licensing Conclusion - SFP
- SFP *TS do not constrain fuel design in SFP
* No 50.59 criteria exceeded
*Coefficients in TS Table 4.3.1 will change slightly Bu = A1*En3 + A2*En2 + A3*En + A4
* TS (Table 4.3.1) changes required
* Prior NRC approval required for criticality function


21 Scope of Licensing 50.59 Review
23 Background - LAR Scope No Complicating Factors:
- SFP No increased probability of failure (e.g., drop, clad failure)
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
*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
24 Licensing Schedule 11/2015 Submit SFP Criticality LAR 11/2017 License Amendment 8/2018 Receipt of IFBA-Gad Fuel  
- 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
25 Spent Fuel Criticality Analysis Outline Supplement Scope Comparison with Current Analysis of Record Compliance to DSS-ISG-2010-01 (ISG)
-Gad Fuel 25 Spent Fuel Criticality Analysis Outline *Supplement Scope
Summary Conclusions  
*Comparison with Current Analysis of Record
*Compliance to DSS-ISG-2010-01 (ISG) *Summary *Conclusions


26 Supplement Scope
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  
*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
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  
*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
28 Spent Fuel Criticality Analysis Analysis-of-Record (AoR) WCAP-17400 Important technical conclusions  
-Ignores gadolinia; shown to be conservative
- Ignores gadolinia; shown to be conservative  
-Up to 100 MWd/MTU rodded operations in SER
- 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+)
- Fission product worth addressed in RAIs  
- Annular axial blankets conservatively modeled as solid  
- Confirmation of design basis fuel type (422V+)  


29 *Objectives of the SFPC Analysis Supplement
29 Objectives of the SFPC Analysis Supplement  
-Evaluate the impact of a new burnable absorber (BA) design on the discharge reactivity
- Evaluate the impact of a new burnable absorber (BA) design on the discharge reactivity  
-Minimize impact on AoR (supplement format)
- Minimize impact on AoR (supplement format)
*Methods to be used in the analysis
Methods to be used in the analysis  
-Based on current AoR calculational framework
- Based on current AoR calculational framework
*Selection of depletion calculation inputs
* Selection of depletion calculation inputs
*Development of biases & uncertainties
* Development of biases & uncertainties
*Accidents, interface conditions & soluble boron credit analysis Spent Fuel Criticality Analysis
* Accidents, interface conditions & soluble boron credit analysis Spent Fuel Criticality Analysis  


30 Analysis Supplement Scope
30 Analysis Supplement Scope Configurations: no changes IFBA-Gad 422V+ Fuel  
*Configurations: no c hanges *IFBA-Gad 422V+ Fuel
- No credit for gadolinia  
-No credit for gadolinia -Planned max 120 IFBA pattern
- Planned max 120 IFBA pattern  
-Cycle Avg Boron: 900 ppm to 1000 ppm
- Cycle Avg Boron: 900 ppm to 1000 ppm  
-Fuel Density: 98% TD
- Fuel Density: 98% TD  
-Axial burnup and moderator temperature profiles
- Axial burnup and moderator temperature profiles  
-Blankets fully enriched Spent Fuel Criticality Analysis
- 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
31 AoR depletion calculations based on burnup bins of 0-18, 18-30, 30-38, 38-48, and > 48 GWD/MTU  
-Gad design profiles
- Limiting burnup profiles from the AoR to be checked against IFBA-Gad design profiles  
-Uniform profile considered
- Uniform profile considered The following slides outline potential impacts related to ISG Spent Fuel Criticality Analysis  
*The following slides outline potential impacts related to ISG Spent Fuel Criticality Analysis


32 ISG Criteria
32 ISG Criteria 2a - 5% decrement method for depletion uncertainty - same as AoR methodology 2b - Nominal values may not be appropriate, discuss selected values  
*2a - 5% decrement method for depletion uncertainty  
- PINGP IFBA-Gad supplement analysis
- same as AoR methodology
* Updated conservative average cycle soluble boron concentration
*2b - Nominal values m ay not b e appropriate, discuss selected values -PINGP IFBA
* Increase in fuel theoretical density Spent Fuel Criticality Analysis  
-Gad supplement analysis
*Updated conservative average cycle soluble boron concentration
*Increase in fuel theoretical density Spent Fuel Criticality Analysis


33 ISG Criteria
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  
*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
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)
*3a - Select limiting axial b urnup profile using NUREG-6801 or plant
Spent Fuel Criticality Analysis  
-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
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  
*3b - Modeling SFP racks including geometry and neutron absorbers - same as AoR Methodology
- Incorporation of multiple misload event  
*3c - Interfaces  
- No other changes from AoR methodology Spent Fuel Criticality Analysis  
- 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)
36 ISG Criteria (Section 4)
*Validation of Codes
Validation of Codes Code validation suite addresses ISG No impact to the AoR Spent Fuel Criticality Analysis  
-Code validation suite addresses ISG
-No impact to the AoR Spent Fuel Criticality Analysis


37 WCAP Supplement Format
37 WCAP Supplement Format IFBA-Gad evaluation as WCAP-17400 Supplement  
*IFBA-Gad evaluation as WCAP-17400 Supplement
- Generate of burnup limits for IFBA-Gad with current configurations  
-Generate of burnup limits for IFBA
- Evaluate normal conditions  
-Gad with current configurations
- Evaluate interface conditions  
-Evaluate normal conditions
- Update accident analysis - Including multiple misload analysis  
-Evaluate interface conditions
- Soluble boron credit (normal and accident conditions)
-Update accident analysis - Including multiple misload analysis -Soluble boron credit (normal and accident conditions)
Spent Fuel Criticality Analysis  
Spent Fuel Criticality Analysis


38 Spent Fuel Criticality Analysis Summary
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)  
*Addition of IFBA (IFBA/IFBA
- Updated burnup limits  
-Gad design) to AoR *Analysis remains in alignment with ISG *Supplement to WCAP
- Updated soluble boron requirements for normal and accident conditions Spent Fuel Criticality Analysis  
-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
39 In Conclusion SFP criticality analysis supplement will:
*SFP criticality analysis supplement w ill: -Conservatively bound proposed future operating conditions with regards to IFBA & IFBA
Conservatively bound proposed future operating conditions with regards to IFBA & IFBA-Gad fuel Address NRC Staff expectations (ISG)
-Gad fuel -Address NRC Staff expectations (ISG)
Spent Fuel Criticality Analysis  
Spent Fuel Criticality Analysis


40 Summary of Actions
40 Summary of Actions Xcel Energy Actions  
*Xcel Energy Actions
- Points of Emphasis for LAR content NRC Actions  
-Points of Emphasis for LAR content
*NRC Actions


41 Summary Summary 1. Submit LAR 11/2015
41 Summary Summary
: 1. Submit LAR 11/2015
: 2. Include NRC expectations
: 2. Include NRC expectations
: 3. Other actions
: 3. Other actions  


42}}
42}}

Latest revision as of 13:19, 10 January 2025

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
ML15105A037
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 04/14/2015
From:
Xcel Energy
To:
Beltz T
Shared Package
ML15107A060 List:
References
TAC MF5839, TAC MF5840
Download: ML15105A037 (42)


Text

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

  • 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.

7 Current Condition PINGP Spent Fuel Pool (SFP) Description Criticality Safety Analysis approved in 2013 Compliant to DSS-ISG-2010-01 No credit for SFP neutron absorber (Boraflex)

Subcriticality criteria met by reactivity balancing (checkerboarding)

8 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

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

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+)

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