Recommendations on Fuel Parameters for Standard Technical Specifications for Spent Fuel Storage Casks (NUREG/CR-6716)

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Publication Information

Manuscript Completed: February 2001
Date Published: March 2001

Prepared by:
S.M. Bowman, I.C. Gauld, J.C. Wagner

Oak Ridge National Laboratory
Managed by UT-Battelle, LLC
Oak Ridge, TN 37831-6370

C.J. Withee, NRC Project Manager

Prepared for:
Spent Fuel Project Office
Office of Nuclear Material Safety and Safeguards
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC Job Code B0009

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Abstract

The U.S. Nuclear Regulatory Commission (NRC) is currently reviewing the technical specifications for spent fuel storage casks in an effort to develop standard technical specifications (STS) that define the allowable spent nuclear fuel (SNF) contents. One of the objectives of the review is to minimize the level of detail in the STS that define the acceptable fuel types. To support this initiative, this study has been performed to identify potential fuel specification parameters needed for criticality safety and radiation shielding analysis and rank their importance relative to a potential compromise of the margin of safety.