Criticality Safety Evaluation for Shipment of Radioactive Waste within the Boundaries of the INEL

DOE-STD-3007-93

Criticality Safety Evaluation for

Shipment of Radioactive

Waste within the Boundaries of the INEL

1.0 INTRODUCTION

Shipments of radioactive waste within the boundaries of the INEL are made in a variety of

shipping casks. The purpose of this report is to establish appropriate limits and demonstrate that

these limits are in compliance with the criticality safety requirements stated in DOE-ID 5480.5A1

and 10 CFR Part 712, Sections 71.55 and 71.61, for a Fissile Class III shipment.

Shipments of radioactive waste may be made within the boundaries of the INEL in several

different types of shipping casks. One such cask, TRUPACT-II, is licensed for Fissile Class I

shipments with up to 325 Fissile Gram Equivalent (FGE) of Pu-2393. Any number of

TRUPACT-II packages may be simultaneously transported.

Other shipping casks that do not have formally established fissile material limits may also

be used to make waste shipments, one-cask-at-a-time, with no more than 160 FGE of Pu-239 per

shipment. Loading of a second cask will not take place until the first cask is removed from the

area. The casks involved are typically constructed of concentric regions of lead and steel or

depleted uranium and steel. Limits for shipments involving these casks will be conservatively

based on generic minimum critical mass data. Therefore, details of the various cask designs are

not pertinent. However, if the limits identified in this evaluation are to be exceeded, an evaluation

specific to the cask shall be required.

[Note: The description section of this example evaluation does not include the level of detail (i.e.,

cask dimensions and sketches) that would normally be found in an evaluation due to the generic

nature of the evaluation.]

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