ML090330464
| ML090330464 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/28/2009 |
| From: | Ellen Brown Plant Licensing Branch II |
| To: | |
| Brown E, NRR/DORL, 415-2315 | |
| Shared Package | |
| ML090780746 | List: |
| References | |
| TAC ME0438 | |
| Download: ML090330464 (15) | |
Text
Browns Ferry 1 Areva Fuel Transition NRC Meeting - White. Flint January 28, 2009
Agenda
- Transition Overview l Discuss Deliverables and Schedule
" Methods Discussion
- BLEU Overview
Transition Overview
=
Background===
" Browns Ferry 2 and 3 were transitioned to ATRIUM TM-10 fuel starting in 2004 with Unit 3 Cycle 12 Primary driver was the ability to utilize Blended Low Enriched Uranium (BLEU) feed material First BLEU reload was Unit 2 Cycle 14 in 2005
- TVA economic analysis in 2007 showed it was advantageous to terminate the GNF contract and transition Unit 1 to BLEU
" TVA transition of Unit 1 to BLEU fuel will be Fall of 2010 Plan is to use BLEU on Unit 1 for Cycles 9 and 10
° Unit 1 will use ATRIUM-10 fuel
- Same proven fuel design as currently used on BFN 2 and 3
Background (cont)
- Transition status GNF data to model legacy Cycles 7 and 8 provided to Areva Modeling of legacy cycles nearing completion Reload milestone schedule established
° Transition plan Initial Tech Spec submittal one year in advance
- Supporting information provided in stages, consistent with the reload schedule
- Submittals will include documentation similar to what was submitted for Brunswick Information and analyses applicable for all units not re-submitted
" LOCA break spectrum report
- MAPLHGR limits if Unit 1 fuel types bounded by existing limits
Planned Deliverables and Schedule
Tech Spec Change Request
" Tech Spec 4.2.1 - Fuel Assemblies Current wording consistent with use of ATRIUM-10 fuel and BLEU No change required
" Tech Spec 4.3.1 - Criticality Current wording is K-eff based with no fuel design specific restrictions No change required
" Tech Spec 3.2 - Power Distribution Limits LCO wording states the thermal limits shall be maintained in compliance with the values in the COLR Any vendor unique thermal limits administration captured in COLR No change required
Tech Spec Change Request
- Tech Spec 5.6.5 -COLR
- Requirement 5.6.5.b lists the approved analytical methods used to determine COLR limits
- Current Unit 1 wording only lists GNF methods
- Tech Spec will be changed to list the appropriate Areva analysis methods
- Change request will be provided one year in advance
- Target date for submittal 10/1/2009
- Tech Spec 2.1.1.2 (SLMCPR) has potential to change
- Separate Tech Spec change request if required
Supporting Information Submittals
" Thermal Hydraulic Design Report
- ANP-2637 - BWR Licensing Methodology Compendium
" SLMCPR Tech Spec (if required)
- Fuel Cycle Design Report
- Reload Safety Report 12/22/09 12/22/09 02/03/10 03/29/10 04/16/10
Methods Aspects
Methods to be Used
- All methods that will be used are NRC approved
- No open topical issues
- List of approved Areva methods will be added to Tech Spec 5.6.5. b
Approved Methodologies COLR TS References - Mechanical Analysis
° XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.
- XN-NF-85-67(P)(A), Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel.
° EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model
° ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs
Approved Methodologies COLR TS References - Neutronic Analysis XN-NF-80-19(P)(A) Volume 1, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis.
XN-NF-80-19(P)(A) Volume 4, Exxon Nuclear Methodology for Boilinq Water Reactors: Application of the ENC Methodology to BWR Reloads.
EMF-2158(P)(A), Siemens Power Corporation Methodologq for Boilin Wa er Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2.
XN-NF-80-19(P)(A) Volume 3 Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description
Approved Methodologies COLR TS References - Transient Analysis XN-NF-84-105(P)(A) Volume 1, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis.
ANF-524(P)(A), ANF Critical Power Methodology for Boiling Water Reactors.
ANF-913(P)(A) Volume 1, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses.
ANF-1358(P)(A), The Loss of Feedwater Heating Transient in Boiling Water Reactors.
Approved Methodologies COLR TS References - CPR and LOCA EMF-2209(P)(A), SPCB Critical Power Correlation EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel.
EMF-2361(P)(A), EXEM BWR-2000 ECCS Evaluation Model.
EMF-2292(P)(A), ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients.