To provide a refueling support system in which fuel transfer procedure establishing operations and associated operations precisely reflecting the fuel burnup conditions can be efficiently performed at the time of scheduled outages at a nuclear power plant. a reactor core performance calculation means for evaluating neutronic characteristics per fuel assembly from core loading pattern input data of a reactor core before beginning of refueling at the end of predetermined cycle n and candidate reactor cores at the end of refueling at the beginning of the following cycle n+1 and from core performance calculation results from a process computer; a transfer condition setting means for determining an intermediate fuel loading pattern target which should be realized in the process of refueling from transfer condition input data including intermediate fuels-to-be-unloaded and transfer priority levels; and a transfer procedure planning means for determining fuel transfer procedures from the neutronic characteristics per fuel assembly which are output from said reactor core performance calculation means and from the intermediate fuel loading pattern target which is output from said transfer condition setting means are comprised.