ML19105A148: Difference between revisions
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| docket = 07109356 | | docket = 07109356 | ||
| license number = | | license number = | ||
| contact person = White B | | contact person = White B | ||
| package number = ML19098A079 | | package number = ML19098A079 | ||
| document type = Safety Evaluation Report | | document type = Safety Evaluation Report | ||
Revision as of 12:23, 14 June 2019
| ML19105A148 | |
| Person / Time | |
|---|---|
| Site: | 07109356 |
| Issue date: | 04/05/2019 |
| From: | Bernie White Spent Fuel Licensing Branch |
| To: | |
| White B | |
| Shared Package | |
| ML19098A079 | List: |
| References | |
| Download: ML19105A148 (135) | |
Text
Code of Federal RegulationsStandard Review Plan for Transportation Packages for Spent Nuclear Fuel
Load Combinations for the Structural Analysis of Shipping Casks for Radioactive MaterialStandard Review Plan for Transportation Packages for Spent Nuclear FuelCladding Considerations for the Transportation and Storage of Spent FuelSpecial Lifting Devices for Shipping Containers Weighing 10,000 Pounds (45000 kg) or More for Nuclear MaterialsDesign Criteria for the Structural Analysis of Shipping Package Containment Vessels
a prioria priori***
- a priori
Standard Review Plan for Transportation Packages for Spent Nuclear FuelAmerican National Standard for Leakage Tests on Packages for Shipment of Radioactive Materials, New York, NY, 1997.
Closure Analysis
Containment Systems and Transport Packagings For Spent Nuclear Fuel and High Level Radioactive WasteAmerican National Standard for Leakage Tests on Packages for Shipment of Radioactive Materials, New York, NY, 1997.
Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear FuelSpent Fuel Assembly Hardware: Characterization and 10 CFR 61 Classification for Waste DisposalPhysical Descriptions of LWR Nonfuel Assembly HardwareAmerican National Standard for Neutron and Gamma-Ray Flux to Dose Factors
6.7.5.1 Misload Analyses **
- Standard Review Plan for Transportation Packages for Spent Nuclear FuelDivision ofSpent Fuel Storage and Transportation Interim Staff Guidance - 8, Revision 3 - Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Packages Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage PackagesReview and Prioritization of Technical Issues Related to Burnup Credit for LWR FuelStudy of the Effect of Integral Burnable Absorbers for PWR Burnup CreditParametric Study of the Effect of Burnable Poison Rods for PWR Burnup CreditParametric Study of the Effect of Control Rods for PWR Burnup Credit Recommendations for Addressing Axial Burnup in PWR Burnup Credit AnalysesAn Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Isotopic Composition PredictionsEvaluation of the French Haut Taux de Combustion (HTC) Critical Experiment DataAn Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff ) Predictions
American National Standard for Leakage Tests on Packages for Shipment of Radioactive Materials, New York, NY, 1997.