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 12/22/09
- ANP-2637 - BWR Licensing 12/22/09 Methodology Compendium
" SLMCPR Tech Spec (if required) 02/03/10
- Fuel Cycle Design Report 03/29/10
- Reload Safety Report 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.