ML102660187

Licensee Slides from July 21, 2010 Meeting on License Amendment Request to Support Use of Areva Nuclear Fuel

ML102660187
Person / Time
Site:	San Onofre
Issue date:	07/21/2010
From:	Southern California Edison Co
To:	Office of Nuclear Reactor Regulation
Hall, J R, NRR/DORL/LPL4, 301-415-4032
References
TAC ME4191, TAC ME4192
Download: ML102660187 (21)

Text

San Onofre Nuclear Generating Station (SONGS)

License Amendment Request to Support Use of AREVA Nuclear Fuel July 21, 2010

Agenda

.:. Overview (Vick Nazareth)

Need for Fuel Design change at SONGS

• AREVA Fuel Design Solution LAR Submittal

.:. Implementation into SCE Reload Analysis (Steve Sparks)

Reload Analysis Process Changes required to implement AREVA fuel LOCA/Mechanical Design methods

.:. License Submittal Schedule (Linda Conklin) 2

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SONGS Fuel Information

.:. Two CE NSSS Units 3438 MW thermal (1185 MWe)

.:. 16x16 Fuel Assembly 217 Assembly core Erbia/Gadolinia burnable absorber ZIRLOTM Clad

.:. Assembly Spacer Grids Westinghouse Guardian Lower Grid 6 HID-1 grids (3 top and 3 bottom) 4 HID-2 middle grids An WISON n*rrERNJlTltJNAL' compan) 4

Need for Fuel Design Change at SONGS

.:. SONGS has ongoing Grid-To-Rod Fretting (GTRF) fuel failures

.:. Will not meet INPO Zero-By-201 0 goal with existing fuel design High Seismic Requirements Restrictive GTRF mitigation strategy Half core reloads, Shorter cycles, vendor fuel management restrictions Fuel inspection and core redesign required due to GTRF failures

.:. Transition to preferred longer fuel cycles significantly hampered

.:. Solution:

Implement GTRF fretting resistant fuel design

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AREVA GTRF Solution

.:. AREVA HTpTM design has proven track record for preventing grid-to-rod fretting failures

.:. HTpTM design meets SONGS seismic requirements

.:. HTpTM Lead Assemblies implemented in Unit 2, Cycle 16 (currently in 1st cycle of operation)

.:. Post irradiation examination (PIE) expected to validate GTRF performance expectations

.:. Planned mini-batch of eight assemblies for unrestricted operation in SONGS Unit 3, Cycle 17.

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SONGS Reload Analysis Key Licensing Reports

.:. CE LOCA Methods (CE-NPD-132P, CENPD-137P)

.:. SCE Reload Topical (SCE-9801-P-A)

.:. SCE licensed to use Combustion Engineering (CE) methods for reload analysis

.:. Westinghouse ZIRLOTM Cladding (CENPD-404-P-A)

.:. AREVA M5TM Clad Temporary 10 CFR 50.46 Exemption (12/17/2009)

.:. SCE PWR Physics using Studsvik codes (SCE-0901) 7

SONGS License Amendment Request

.:. The application of AREVA's LOCA and fuel mechanical design methods to SONGS

.:. Permanent M5' cladding exemption to 10CFR50.46

.:. Remove all LFA restrictions (non-limiting location, burnup, PIE inspections, etc.)

.:. Technical Specification / COLR Updates for AREVA fuel design

.:. Methods referenced in Section 5.7

.:. Fuel cladding material in Section 4.2

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.:. Implement AREVA fuel parameters into SCE methods 8

Implementation of AREVAfuel into SeE Reload Analysis Methods Steve Sparks Southern California Edison Nuclear Fuel Management

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seE Reload Analysis Methodology

.:. NRC approved SCE to perform reload design and non-LOCA analysis for SONGS SCE-9801-P-A, "Reload Analysis Methodology for the San Onofre Nuclear Generating Station", June 1999

.:. SCE has performed reload design independently for SONGS Cycles 10-16

.:. Fuel Mechanical Design and LOCAAnalyses are scope of the fuel vendor, using NRC approved methods It"I.aurn IJIt'7'JilUIA TJONAL' COalpU*

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Fuel Mechanical Design and LOCA Analyses

.:. Current SCE Fuel Mechanical Design and LOCA analyses 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.

• . 15 change to list AREVA LOCA methods in 15 5.7.1.5 l..A!....L IRNlA N

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Thermal I Hydraulic Analyses SONGS analysis uses TORC/CETOP codes

.:. TORC is COBRA based code, similar to VIPRE, X-COBRA.

• . Implementation of NRC Approved Critical Heat Flux correlations for AREVA fuel EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Revision 1, January 2005.

• . Allows for DNBR calculation for both Westinghouse (CE16) and AREVA (HTpTM) fuel

.:. Code modifications will be benchmarked to test cases used in the NRC submittals for the appropriate CHF correlations

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hermall Hydraulic Analyses Mixed Core analysis methods

.:. Based on NRC approved topical report XN-NF-82-21 (P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to mixed Core Configurations," Revision 1, September 1983.

- recently implemented for Calvert Cliffs transition

.:. T/H Analysis of full AREVA and CE16 cores, compared to analysis of mixed core

.:. Result is a mixed core penalty may be needed

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Fuel Rod Performance Analyses

.:. SCE methods use the FATES code

.:. AREVA fuel rod performance uses RODEX code, and performed as part of the fuel mechanical design analyses. This scope/process unchanged.

• . M5' cladding properties added to FATES code, to allow SCE to provide needed input to Transient Analyses.

• . Following same process used to implement Westinghouse ZIRLOTM cladding properties into FATES code CENPD-404-P-A, "Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs", November 2001.

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SCENendor Inteerface

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SCE Scope

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Summary - SCE Method Changes Changes required to implement AREVA fuel at SONGS using already approved reload analysis methods

.:. Methods and CHF Correlations already NRC approved and implemented at other plants

.:. Vendor Scope unchanged

.:. T/H Code modified to add AREVA CHF Correlations

- mixed core methodology applied to transition core

.:. Fuel Rod Performance handled by

- Vendor during mechanical design

- Modification to FATES to implement M5 material properties to provide SCE required inputs to Transient Analyses CAUFOR N'

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Summary - SCE Method Changes Method changes required to implement AREVA fuel at SONGS using already approved methods

.:. Methodology changes will be tested by a simulated Reactor Core design with a mixed core and a full AREVA core

.:. Actual use begins with the U3C17 core design in 2012 (8 AREVA assemblies)

.:. Reduced scope and risk compared to full scope vendor switch 11

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LAR Submittal Schedule

.:. 07/10- Initial meeting with NRC

.:. 12/10 - Finalize reload design approach

.:. 12/10 - Update & detail meeting with NRC

.:. 2011 - Target for LAR submittal

.:. 12/11 - Begin U3C17 core design

.:. 09/12 - Mini-Batch fuel delivery for Unit 3 Cycle 17 (8 assemblies in limiting locations)

.:. 10/12 - NRC SER 13