ML010260475
| ML010260475 | |
| Person / Time | |
|---|---|
| Issue date: | 01/23/2001 |
| From: | Christopher Jackson, Withee C NRC/NMSS/SFPO |
| To: | Nuclear Energy Institute |
| Jackson C NMSS/SFPO (301) 415-2947 | |
| Shared Package | |
| ML010260441 | List: |
| References | |
| Download: ML010260475 (11) | |
Text
NEW STANDARD TECHNICAL SPECIFICATIONS Christopher P. Jackson Carl J. Withee Spent Fuel Project Office, NMSS
ÿ Assure overall storage goals are met (subcriticality, control radiation exposure, retreivability, confinement)
ÿ Remove unnecessary detail
ÿ Move less safety significant parameters to administrative programs PHILOSOPHICAL GOALS
ÿ Make specifications more performance-based
ÿ Establish new process to change cask contents
ÿ Maintain consistency with site-specific requirements (10 CFR 72.44)
PHILOSOPHICAL GOALS CONTINUED
ÿ To implement, a CoC holder will have to;
Identify appropriate LCO completion times, based on safety significance and safety analysis
For TSs removed or relocated into the administrative programs, verify that the SAR describes a method for determining acceptable values
Request NRC approval through 72.230 or 72.244, as applicable IMPLEMENTATION
ÿ The NRC will encourage CoC holders to transition completely to new STS.
ÿ Cask STS can be used as a model for site-specific TS.
IMPLEMENTATION CONTINUED
ÿ Approval occurs through the normal certificate amendments
ÿ Methods will need to be described in enough detail for the NRC to make a finding
ÿ Methods need to stand alone
ÿ NRC anticipates that some SAR described methodologies are already sufficient (e.g., structural), other methodologies may require additional work (e.g, criticality)
METHODS REVIEW
ÿ We welcome any feedback from the public
ÿ NRC intends to issue STS as a draft NUREG report
ÿ After gaining experience using the STS, the NRC plans to issue final NUREG report FINALIZATION
ÿ Sub-Criticality
Fuel Specifications
Poison Plate Loading
Assembly Pitch
ÿ Minimize Dose
Fuel Specifications (limit source term)
Surface Dose Rate Program
Surface Contamination Program MEETING STORAGE GOALS
ÿ Retrievability
Fuel Temperature
Decay Heat
G-Load (fuel)
ÿ Confinement
G-Load (cask)
Leak Rate Program MEETING STORAGE GOALS CONTINUED
ÿ Fissile Isotopes (UO2 vs. MOX)
ÿ Maximum Enrichment
ÿ Fuel Class (e.g., 14x14, 15x15)
ÿ Number of Fuel Rods
ÿ Number of Water Holes
ÿ Maximum Burnup FUEL PARAMETERS
ÿ Minimum Cooling Time
ÿ Minimum Enrichment
ÿ Cladding Material
ÿ BPRA/TPAs (cooling time and burnup)
ÿ Maximum Design Fuel Assembly Weight
ÿ Decay Heat
ÿ Fuel Condition (intact, damaged or debris)
FUEL PARAMETERS CONTINUED