Spent Fuel Transportation Package Response to the Newhall Pass Fire Scenario

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG/CR, NUREG/CR-7207, ``Spent Fuel Transportation Package Response to the Newhall Pass Fire Scenario.'' This report presents analyses that were performed to examine the hypothetical effects on a spent fuel transportation package from conditions during the Newhall Pass accident in 2007. The analyses undertaken include FDS fire modeling, physical examination of material samples, ANSYS and COBRA-SFS code thermal modeling of a GA-4 package, and fuel performance modeling using the FRAPTRAN-1.4, FRAPCON-3.4, and DATING codes. The estimated release from the hypothetical scenario is below the prescribed limit for safety.