ML21271A612
| ML21271A612 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/28/2021 |
| From: | Ameren Missouri |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21271A610 | List: |
| References | |
| ULNRC-06694 | |
| Download: ML21271A612 (15) | |
Text
Enclosure 1 to ULNRC-06694 Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Public Meeting)
Callaway VQP Pre-Submittal Meeting Stephanie Banker - Ameren - Vice President Nuclear Engineering & Support
- Welcome
- Meeting Purpose - to provide the NRC with information on the Vendor Qualification Program (VQP) of Framatome as a supplier of nuclear fuel to Callaway Energy Center
- Desired Outcomes - to solicit questions / comments and gain insight from the NRC regarding the VQP information presented.
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3 Team Members Presenters in Bold Ameren Team Members Titles Stephanie Banker Vice President Nuclear Engineering &
Support Steve Meyer Manager, Regulatory Affairs Tom Elwood Supervising Engineer, Regulatory Affairs Jim Kovar Regulatory Affairs Engineer Don Rickard Regulatory Affairs Engineer Brian Richardson Supervising Engineer, Reactor Engineering / Safety Analysis / Fuels Jim Knaup Reactor Engineer / Core Design Justin Vinyard Reactor Engineer / Fuels Jim McInvale Consultant Reactor Engineer Framatome Team Members Titles Rick Williamson Contract Manager Tom Gardner Project Manager Christy White Technical PM Greg Borza Thermal-Hydraulics Morris Byram Licensing Kevin Segard Neutronics Michael Harris Thermal-Mechanics Tim Lindquist Safety Analysis Gordo Wissinger LOCA Analysis Pam Reed Mechanical Design Brian Painter Mechanical Analysis
4 Agenda
- Purpose of Meeting / Desired Outcomes Callaway
- Background Callaway
- GAIA Fuel Assembly Design Description Framatome
- GAIA Experience Framatome
- Analyses Framatome
- Summary of NRC Approved Methods Framatome
- Technical Specification Changes Callaway
- Schedule Callaway
5 Background
- Callaway LFA / VQP Program for Framatome Fuel
- Lead Fuel Assemblies (LFA) - 4 Fuel Assemblies 3 cycles (Cycles 25, 27, 28)
Non-Limiting Operation (Cycle 25 only)
- Vendor Qualification Program (VQP)
Fuel Transition Licensing Submittal
- VQP Lead Fuel Assemblies - 4 Additional Fuel Assemblies 3 cycles (Cycles 27, 28, 29)
Fully Licensed Operation
- GAIA Fuel Design
- Based on currently approved methods (with some changes)
- Technical Specification changes to add Framatome methods
6 Fuel Assembly Design Description (ANP-10342P-A Revision 0, GAIA Fuel Assembly Mechanical Design)
- Standard Reconstitutable Top Nozzle
- M5 Fuel Rods
- M5 GAIA Mixing Grid (6x)
- M5 Intermediate GAIA Mixer (IGM) Grids (3x)
- Alloy 718 HMP Top (Relaxed) and Bottom Spacer Grids
- Q12 MONOBLOC Guide Tubes (24x)
- Q12 Instrument Tube
- GRIP Bottom Nozzle
7 Operating Experience (GAIA 12 ft. Design)
- LTAs have successfully completed failure-free performance in US and European reactors.
Plant (Year)
Cycle Length US Plant (2015-2019) 3x 18-month cycles Europe Plant (2012-2017) 5x 12-month cycles
- In the US, GAIA fuel assemblies in batch quantity will be in operation in 2021, as will GAIA LFAs at Callaway. GAIA LFAs with EATF features are in operation at another US Plant since 2019.
- Callaway LFAs (4) - Begin operation in Cycle 25, 3 cycles
- Callaway VQP LFAs (4) - Begin operation in Cycle 27, 3 cycles
- In Europe, GAIA fuel assemblies in batch quantity are in their first cycle of operation at two plants.
8 VQP Analyses
- Fuel rod thermal-mechanical
- Fuel assembly mechanical
- Neutronics
- Thermal-hydraulics
- Non-LOCA
- Rod Ejection Analysis - Method meets new RG 1.236
9 Summary of Methods (1 of 2)
Functional Area Topical Report Neutronics ARCADIA (ANP-10297 Supplement 1P-A Revision 1)
Thermal-Hydraulic XCOBRA-IIIC (XN-NF-82-21P-A and XN-NF-75-21P-A Revision 2),
COBRA-FLX (ANP-10311P-A Revision 1)
Non-LOCA S-RELAP5 (EMF-2310P-A Revision 1)
DNBR Correlation GAIA (ANP-10341P-A)
Control Rod Ejection AREA (ANP-10338P-A)
GALILEO (ANP-10323P-A)
SB LOCA S-RELAP5 (EMF-2328P-A and S1P-A)
LB LOCA S-RELAP5 (EMF-2103P-A Revision 3)
10 Summary of Methods (2 of 2)
Functional Area Topical Report Fuel Performance Code COPERNIC (BAW-10231P-A ),
CROV (BAW-10084PA Revision 3)
External Loads ANP-10337P-A and Supplement 1P-A GAIA Mechanical Design ANP-10342P-A Cladding BAW-10240PA, BAW-10227P-A Rev 1 Statistical Setpoints EMF-92-081P-A Fuel Rod Bow XN-75-32P-A DNB Propagation XN-NF-82-06P-A
11 Technical Specification Changes Tech Spec 2.1.1 - Reactor Core Safety Limits Revise to add Framatome DNBR and FCM limits Tech Spec 3.2.1 - Heat Flux Hot Channel Factor (FQ(Z))
Revise to reflect ARCADIA based power distribution control Tech Spec 3.2.3 - Axial Flux Difference (AFD) (Relaxed Axial Offset Control Methodology, RAOC)
Revise to reflect ARCADIA based power distribution control Tech Spec 4.2.1-Reactor Core Revise to refer to Zirconium clad Tech Spec 5.6.5 - Core Operating Limits Report (COLR)
Revise to add Framatome methods to list of methods used to support COLR Tech Spec 3.7.16 - Fuel Storage Pool Boron Concentration; Tech Spec 3.7.17 - Spent Fuel Assembly Storage; Tech Spec 4.3 - Fuel Storage Potentially impacted, an evaluation of the fuel storage rack subcriticality analysis is ongoing. Dependent upon the results of the evaluation of the analysis, these Tech Specs may require revision.
- M5 Cladding 10 CFR 50.46 and 10 CFR 50 Appendix K Exemption Request
- Similar to M5 cladding exemption requests for other plants
13 Schedule
- LAR submittal August 31, 2022
- Pre-submittal Meeting - May 2022
- Ameren/Framatome can support NRC Audit, if requested
- Including Rod Ejection Analysis
- Requested NRC approval of LAR September 30, 2023
- Supports Fuel Cycle 27, RFO begins October 2, 2023
- Note - Spent Fuel Pool - Criticality Safety Analysis LAR will be submitted in January 2022 Questions
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