ML17283A310
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| ML17283A310 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/12/2017 |
| From: | Entergy Operations |
| To: | Lisa Regner Plant Licensing Branch IV |
| Regner, L M, 301-415-1906 | |
| References | |
| Download: ML17283A310 (6) | |
Text
NRC Pre-application Meeting River Bend Station Spent Fuel Pool Inserts and Criticality Safety Analysis October 12, 2017
1 Purpose
- Discuss the proposed change to install NETCOs SNAP-IN neutron absorber inserts into the RBS spent fuel pool storage cells
- Describe the methodology for a proposed spent fuel pool new criticality safety analysis supporting a license amendment request
- Seek feedback on the approach from the NRC staff 1
1 Background / Objective
- Current RBS spent fuel pool criticality analysis credits Boraflex neutron absorber material
- Contracted with Curtiss-Wright Nuclear Division to design, manufacture, and install inserts
- Contracted with Global Nuclear Fuel-Americas to prepare new criticality analysis which removes credit for Boraflex and credits inserts 2
1 SNAP-IN Inserts
- Simple design; L-shaped (chevron), full length inserts
- Robust material, Rio Tinto Alcans Boralcan TM; a metal matrix of aluminum alloy with nuclear grade B4C
- Similar inserts installed in BWR racks for Exelons LaSalle, Peach Bottom and Quad Cities
- Ample neutron absorption
- Nominal B4C content 21 wt%
- Minimum certified B10 areal density 0.0129 gm/cm2
- Monitoring coupons will accompany inserts; will follow most current industry guidance
- NEI 16-03, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools 3
1 Criticality Analysis Methodology
- Will follow most current NRC and industry guidance
- DSS-ISG-2010-01, Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools
- NEI 12-16, Guidance for performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants (sections applicable to BWRs)
- No credit for Boraflex neutron absorber; only credit for inserts
- Main codes will be TGBLA-06 and MCNP-05P with ENDF/B-VII.0
- Standard BWR cold, in-core kpeak reactivity methodology
- Will model most reactive lattice over entire axial length; no axial blankets credited
- Will establish maximum in-core kso that kmax < 0.95 for normal and accident conditions 4
1 Criticality Analysis Methodology
- Will address current fuel type (GNF2), next potential fuel product (GNF3) and all legacy fuel
- Uniform pool loading - all fuel storage locations with an insert and maximum reactivity fuel; no misload of fuel to consider in the rack
- Misload of fuel outside the rack is evaluated
- Missing insert evaluated to address removal during fuel movement and during periodic removal for inspection 5
1 Implementation Strategy
- Inserts installed through 10 CFR 50.59 process but not credited until license amendment request approval from NRC
- Installation scheduled April - November 2019
- Criticality analysis submission end of 1st quarter 2018
- Request 18 month review from NRC
- License amendment request submission end of 3rd quarter 2018
- Request 12 month review from NRC
- Incorporate updated Technical Specifications and incorporate other changes once NRC license amendment approval is received by end of 2019 6