Containment Tent for Opening of Containers at Materials and Fuels Complex 793C CX(s) Applied: B6.6Date: 42437 Location(s): IdahoOffices(s): Nuclear Energy
Office of NEPA Policy and Compliance
March 8, 2016
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Containment Tent for Opening of Containers at Materials and Fuels Complex 793C
CX(s) Applied: B6.6
Date: 42437
Location(s): Idaho
Offices(s): Nuclear Energy
The proposed action would procure a soft-walled containment tent inside MFC-793C that would be set-up within the facility as needed, and used to provide contamination control and containment for opening various radiologically contaminated or mixed waste containers for examination, maintenance, repackaging, or container treatment.