ML110120630
| ML110120630 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/12/2011 |
| From: | Southern California Edison Co |
| To: | Plant Licensing Branch IV |
| Hall, J R, NRR/DORL/LPL4,301-415-4032 | |
| References | |
| Download: ML110120630 (24) | |
Text
San Onofre Nuclear Generating Statio (SONGS) icense Amendment Request to Support Use of AREVA Nuclear Fuel January 12, 2011
'I Agenda
.:. Introduction and Overview (Non-Proprietary)
.:. AREVA Fuel Design (AREVA Proprietary)
.:. Core Thermal Hydraulics (SCE Proprietary)
.:. Fuel Rod Behavior Analysis (SCE Proprietary)
.:. Non-LOCA Transient Analysis (SCE Proprietary)
.:. LOCA Analysis (AREVA Proprietary)
.:. Summary and Schedule (Non-Proprietary)
January 12,2011 2
~
Introduction and Overview (Non-Proprietary)
Owen Thomsen Nuclear Fuel Management Southern California Edison
Overview
.:. General
- Need for Fuel Design Change at SONGS
- AREVA Fuel Design Solution
- SONGS Licensing Amendment Roadmap
.:. Implementation into SCE Reload Analysis
- Reload Analysis Process
- Changes Required to Implement AREVA Fuel
- LOCA / Mechanical Design Methods
- Recent Methodology Related Audit Items
.:. Summary and Conclusion January 12, 2011 4
eed for Fuel Design Change at SONGS
.:. SONGS has ongoing Grid-To-Rod Fretting (GTRF) fuel failures
- Did not meet INPO Zero-By-2010 goal with existing fuel design
- Restrictive GTRF mitigation strategy
- Unit 3 Cycle 15 had GTRF fuel pin failures in first cycle fuel
.:. Fuel inspection and core redesign required due to GTRF failures
.:. Transition to preferred longer fuel cycles significantly hampered
.:. High seismic requirements
.:. Implement fretting resistant fuel design January 12, 2011 5
AREVA GTRF Solution
.:. AREVA High Thermal Performance (HTpTM) design has proven track record for preventing grid-to-rod fretting failures at other reactors
.:. HTpTM design meets SONGS seismic requirements
.:. HTpTM Lead Assemblies implemented in Unit 2, Cycle 16 (currently in first cycle of operation)
- Post irradiation examination (PIE) to validate GTRF performance expectations January 12. 2011 6
seE Reload Design Methodology Licensing Overview
.:. CE LOCA Methodology (CENPD-132-P-A, CENPD-137-P-A)
.:. SCE Reload Topical (SCE-9801-P-A)
.SCE licensed to use Combustion Engineering (CE) methods for reload analysis for COLSS/CPC plants
.:. Topical Report CEN-635(S)-P "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology:
Tabulation of Other SER Limitations and/or Constraints" February 1999
.:. Subsequent Approvals
.Westinghouse ZIRLOTM Cladding (CENPO-404-P-A)
.SCE PWR Physics using Studsvik codes (SCE-0901-P-A)
.AREVA M5' Clad Temporary 10 CFR 50.46 Exemption (12/17/2009)
.CENTS NSSS Simulation Code for CEA Ejection Peak Pressure (CENPO 282-P-A)
.Oeparture from Nucleate Boiling (ONB) Statistical Convolution Methodology for Estimating Fuel Failure for Non-LOCA Events, SONGS Units 2/3 License Amendments 210/202, September 2008 January 12, 2011 7
SONGS License Amendment Roadmap
.:. The application of AREVA's Approved LOCA methodology to SONGS
.:. Implement AREVA fuel correlations and parameters into SCE Reload Analysis Methodology
.:. Permanent M5' cladding exemption to 10CFR50.46
- Assemblies placed in limiting locations in batch quantities
- Unit 3 Cycle 17 planned mini-batch
- Existing AREVA Lead Fuel Assemblies will continue per Commitments in SONGS License Amendments 222 (Unit 2) and 215 (Unit 3), December 15,2009
.:. Technical Specification Changes January 12, 2011 8
seE Reload Design Methodology
.:. SCE performs reload design and non-LOCA analysis for SONGS (SCE-9801-P-A)
.:. SCE has independently performed design and analyses for fourteen (14) reload cycles
.:. Fuel Mechanical Design and LOCA Analyses are scope of the fuel vendor, using NRC approved methods January 12, 2011 9
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Des AREVAFuel January 12. 2011 11
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Fuel Mechanical Design and LOCA Analyses
.:. Current SCE Fuel Mechanical Design and LOCA analyses are performed by Westinghouse
.:. For AREVA fuel, AREVA will perform equivalent scope
.:. AREVA will use current NRC approved methods
- EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Revision 0, February 1999
- EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 0, April 2003
.:. Tech Spec change to list AREVA LOCA methods in TS 5.7.1.5 January 12, 2011 12
Thermal I Hydraulic Analyses
.:. SCE analysis uses TORC/CETOP codes
+TORC is COBRA based code, similar to VIPRE, X-COBRA
+ Implementation of Approved BHTP Critical Heat Flux (CHF) correlation for AREVA fuel
+Allows for DNBR calculation for both Westinghouse (CE16) and AREVA (HTpTM) fuel
+SCE TORC code, using the AREVA BHTP CHF correlation, will be validated to test cases used in approved AREVA topical report
+ Implementation of AREVA BHTP CHF correlation into TORC does not change CE methods or SCE's analysis capability
+ Mixed core explicitly modeled in TORC
.:. Same process used by Westinghouse to implement other CHF correlations into TORC I~"I sam January 12, 2011 13
'I Fuel Rod Behavior Analyses
.:. seE methods use the FATES38 code
- FATES3B is a fuel behavior code that provides fuel behavior input data to Westinghouse Fuel Mechanical Design, LOCA and Non LOCA transient analyses
- Approved M5TM cladding properties added to FATES3B code, to allow SCE to provide needed input to Non-LOCA Transient Analyses
- FATES3B will not be used for AREVA LOCA and Fuel Mechanical Design calculations
- Implementation of AREVA M5TM cladding properties into FATES3B does not change CE methods or SCE's analysis capability
.:. Follows same process used to implement Westinghouse ZIRLOTM cladding properties into FATES38 code January 12, 2011 14
Non-LOCA ansient Analyses
.:. AREVA M5' and BHTP critical heat flux correlation are inputs to Non-LOCA Transients
- BHTP correlation impact on DNB Statistical Convolution for fuel failures is bounded by CE-1 correlation (example: pre-trip steam line break will be discussed)
- M5' clad is addressed by inputting properties into strain limit calculation in DNBR propagation methodology used to verify coolable geometry
- M5' clad is addressed by inputting properties into STRIKIN-II code
- Follows same process used to implement Westinghouse ZIRLOTM clad (example: CEA ejection will be discussed)
- BHTP correlation is addressed in the Core Thermal Hydraulic analysis
- Follows same process used for CE-1 correlation
.:. Incorporation of AREVA fuel does not change the Non-LOCA CE methods or SCE's analysis capability January 12~ 2011 15
'I SONGS Implementation of Fuel Vendor Transition
.:. SCE is implementing limited cladding and fuel assembly design properties to its methodology
- SCE performs these analyses and is very familiar with the licensing basis
.:. AREVA Approved Realistic Large Break (RLB) LOCA methodology will be employed
- Westinghouse current approve method for SONGS Units 2 and 3 is an Appendix K model
.:. SCE recognizes the potential for errors when implementing methodology changes and has compensatory processes in place
- Section 4 of SCE's Reload Topical (SCE-9801-P-A)
January 12.. 2011 16
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SONGS Activities Added or Modified Due to Reload Technology Transfer NFM Procedures:
Software V&V Computer Hardwal-e Control Calculation Documentation Quality Program Implementation Reload Analyses SCE/ASS CE Interface Monitoring 17
Responses to Recent Fuel Transition Issues
.:. seE has a robust Reload Analysis process
- Use of human performance tools (barriers)
- Roles and responsibilities are specified in SONGS Quality Procedure S0123-XXXVI-1
- Significant supervisor and management involvement
.:. Implemented as part of the original approval
- Audited by the NRC
- Have completed fourteen (14) reload analysis campaigns
.:. Have used outside expertise to supplement in-house capability
- e.g., used a third party to assist in the review of AREVA's seismic analyses for the AREVA Lead Fuel Assemblies
.:. As part of this License Amendment Request, SeE will provide SONGS specific responses for docketed RAls January 12, 2011 18
Summary of Changes
.:. Changes required to implement approved AREVA fuel at SONGS:
- M5' material and SHTP CHF Correlation approved for implementation into SCE's approved reload analysis methodology
- Added AREVA SHTP CHF Correlation into TORC
- M5' material properties added to FATES3S to provide SCE required inputs to Non-LOCA Transient Analyses
January 12.. 2011 19
Conclusion
.:. Design change needed to eliminate GTRF fuel failures
.:. AREVA HTP/HMP fuel design has proven track record for preventing GTRF fuel failures at other reactors
.:. Implementation process designed to minimize changes to SeE's approved methodology and analysis capability
.:. Initial implementation of mini-batch in Unit 3 Cycle 17
.:. Recent docketed RAI's will be explicitly addressed January 12. 2011 20
License Amendment Request Submittal Summary Steve Sparks & Linda Conklin Southern California Edison
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Agenaa
.:. Overview (Non-Proprietary)
.:. Fuel Design (AREVA Proprietary)
.:. Core Thermal Hydraulics (SCE Proprietary)
.:. Fuel Rod Behavior Analysis (SCE Proprietary)
.:. Non-LOCA Transient Analysis (SCE Proprietary)
.:. LOCA Analysis (AREVA Proprietary)
.:. Summary and Schedule (Non-Proprietary) anuary 12, 2011
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echnical Summary
.:. SCE uses NRC Approved Reload Analysis Methods
.:. Previously approved correlations and properties are being added to the SCE Codes for analysis of AREVA fuel
.:. Results of code testing - SCE codes accurately modeling AREVA fuel
.:. Current Fuel Vendor scope will remain Fuel Vendor scope, using previously approved methods for Mechanical Design and LOCA
.:. License Amendment Request (LAR) is a request to implement AREVA fuel into SCE approved Westinghouse-CE methods January 12, 2011 3
AR Schedule
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- . June 2011 - LAR Submitta
.:. December 2011 - Begin SONGS 3 Cycle 17 core design
.:. September 2012 - Delivery of Mini-Batch of AREVA fuel for SONGS 3 Cycle 17
.:. October 2012 - NRC Safety Evaluation with LAR approval needed for Core Reload January 12, 2011
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