In the process of transporting spent fuel, a design is adopted to prevent the sealed canister from being damaged under hypothetical accidents or natural phenomena, but conservative consideration is still needed for the radioactive dose consequences caused by drop accidents when exceeding a certain height to the public outside the site. Containers containing components may experience component drop accidents and container drop accidents during transportation. The calculation of the source term for drop accidents is based on parameters such as the accumulation of components, the fraction of fission product of different nuclides, and the decontamination factor of the water tank. This article takes a drop accident at a spent fuel dry storage facility as an example to conduct sensitivity analysis on the effects of parameters such as nuclide release fraction, filter efficiency, and pool decontamination factor on the source term and accident dose consequences of the drop accident. The results show that changes in each parameter have a certain impact on the results.