The work aims to verify whether the design of the spent nuclear fuel transport cask body, the inner and outer lids, the fuel basket and the bolts as well as its transportation package meets the standard requirements of GB 11806 Regulations for Safe Transport of Radioactive Materials when they are freely dropped to the horizontal rigid ground at the most dangerous angle from the height of 9 m under the accident conditions. The finite element method was utilized to simulate the drop process with LS-DYNA instead of the drop test. The 9 m free drop impact analysis of spent nuclear fuel transport cask was carried out. The stress checking of the cask body, the inner and outer lids, the fuel basket and the bolts was conducted according to the stress limits as specified by ASME. The results of stress checking showed that, the spent nuclear fuel transport cask body, the inner and outer lids, the fuel basket and the bolts met the requirements of design strength. The design of the spent nuclear fuel transport cask body, the inner and outer lids, the fuel basket and the bolts as well as its transportation package satisfies the requirements of GB 11806.