The DOE Packaging Certification Program (PCP) can certify packagings or casks used for onsite
radioactive material storage. PCP Certification has several benefits for sites.
PCP will perform an independent review of the storage package or cask, using the existing staff of experienced, full-time, package safety reviewers.
Package approval liability shifts from the Site Manager to the Headquarters Certifying Official.
Storage packages and casks are independently reviewed by PCP to the criteria and standards.
First, if a packaging was previously certified for transportation in accordance with 10 CFR 71 by DOE or NRC, then PCP will perform an expedited simple review, based on the transportation certification, and issue a storage only certificate. This type of review is more suited for packagings that are only used for radioactive material storage
incident to transportation or
Second, for a new storage cask, PCP will conduct a thorough review in accordance with 10 CFR Part 72. Protocol for compliance with this review can be found on
Storage Cask Certification Program Protocols and Processes. This type of review is more suited for casks that are only used for radioactive material storage for
10 CFR Part 72:
Licensing Requirements for The Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste
SFST-ISG-1, Revision 2:
SFST-ISG-2, Revision 1:
Post Accident Recovery and Compliance with 10 CFR 72.122(l)
SFST-ISG-5, Revision 1:
SFST-ISG-8, Revision 3:
Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks
SFST-ISG-9, Revision 1:
Storage of Components Associated with Fuel Assemblies
SFST-ISG-10, Revision 1:
Alternatives to the ASME Code
SFST-ISG-11, Revision 3:
Cladding Considerations for the Transportation and Storage of Spent Fuel
Interim Storage of Greater Than Class C Waste
SFST-ISG-18, Revision 1:
The Design and Testing of Lid Welds on Austenitic Stainless Steel Canisters as the Confinement Boundary for Spent Fuel Storage
Use of Computational Modeling Software
Potential Rod Splitting Due to Exposure to an Oxidizing Atmosphere During Short-Term Cask Loading Operations in LWR or Other Uranium Oxide Based Fuel
Application of ASTM Standard Practice C1671-07 when performing technical reviews of spent fuel storage and transportation packaging licensing actions
Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility
Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance
Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety
Office of Environmental Management