ML19219A036
| ML19219A036 | |
| Person / Time | |
|---|---|
| Site: | 07103092 |
| Issue date: | 08/12/2019 |
| From: | John Mckirgan Spent Fuel Licensing Branch |
| To: | Boyle R US Dept of Transportation (DOT) |
| Garcia Santos, Norma | |
| Shared Package | |
| ML19219A034 | List: |
| References | |
| EPID L-2018-LLA-0170 | |
| Download: ML19219A036 (28) | |
Text
1.1Package Description ....................................................................................................... 12.1Description of Structural Design ..................................................................................... 32.2Mechanical Analysis ....................................................................................................... 42.3Structural Evaluation under Normal and Accidental Conditions of Transport ................. 52.4Evaluation Findings ........................................................................................................ 63.1Safety Review of Contents ............................................................................................. 83.2Safety Review of Packaging ........................................................................................... 93.3Acceptance and Maintenance Testing ......................................................................... 134.1Description of the Thermal Design ............................................................................... 144.2Thermal Evaluation under Normal Conditions of Transport and Hypothetical Accident Conditions ....................................................................................................................
............... 154.3Evaluation Findings ...................................................................................................... 155.1Description of the Containment Boundary .................................................................... 155.2Evaluation Findings ...................................................................................................... 156.1Shielding Evaluation under Normal Conditions of Transport and Hypothetical Accident Conditions ....................................................................................................................
............... 156.2Evaluation Findings ...................................................................................................... 167.1Description of Criticality Design .................................................................................... 177.2Nuclear Fuel Contents .................................................................................................. 177.3General Consideration for Criticality Safety .................................................................. 177.4Demonstration of Maximum Reactivity ......................................................................... 187.5Evaluation Findings ...................................................................................................... 19 8.1Staff's Evaluation of the Quality Assurance Program ................................................... 198.2Evaluation Findings ...................................................................................................... 20
1.1 Package Description
uranium-based material inorganics solid-form organic solid-form residues.2.1 Description of Structural Design
2.2 Mechanical Analysis
2.3 Structural Evaluation under Normal and Accidental Conditions of Transport
2.4 Evaluation Findings
501 502 507 614 620 639 640 644 679
3.1 Safety Review of Contents
3.2 Safety Review of Packaging material specification closure/encasing requirements
3.2.2.1 Stainless steel 3.2.2.2 Phenolic foam (impact limiter/thermal insulation material)
3.2.2.3 Polyester-based BORA resin (neutron absorber material) 3.2.2.4 Ethylene propylene diene monomer (EPDM) seal material
3.2.2.5 Polymer bags:
3.3 Acceptance and Maintenance Testing
4.1 Description of the Thermal Design
4.2 Thermal Evaluation under Normal Conditions of Transport and Hypothetical Accident Conditions
4.3 Evaluation Findings
5.1 Description of the Containment Boundary 5.2 Evaluation Findings
6.1 Shielding Evaluation under Normal Conditions of Transport and Hypothetical Accident Conditions
6.2 Evaluation Findings
7.1 Description of Criticality Design
7.2 Nuclear Fuel Contents 7.3 General Consideration for Criticality Safety
7.4 Demonstration of Maximum Reactivity
7.5 Benchmark Evaluations 7.5 Evaluation Findings 8.1 Staff's Evaluation of the Quality Assurance Program
8.2 Evaluation Findings