[en] Within the framework of this project a first long-term safety assessment study for a generic German repository with spent nuclear fuel in granite host formations has been performed. Conceptual models have been developed and implemented into the numerical codes. These models describe the relevant processes in the near and far field of the repository. For the nuclide mobilisation and the diffusion-controlled transport through the bentonite barrier the computer code GRAPOS for far-field transport the code CHETMAD has been developed. Transport in the far field has been assumed to take place in a fracture network. As retardation mechanism matrix diffusion accompanied by linear equilibrium sorption on the rock matrix is considered. Both codes have been tested by intercomparison with codes of other countries. The dose rates have been calculated by the code EXCON considering the transport pathways into the biosphere. A reference scenario has been defined. It considers instantaneous saturation of the bentonite immediately after the operational phase of the repository, failure of all containers after 1000 years, diffusion through the bentonite, transport through fractured dykes, which represent a fast transport pathway in the low permeability region of the granite. The nuclide mobilization has been calculated according to a common source term which has been developed by all participants of the SPA project. It is assumed that 25% of the containers are connected to the considered transport pathway in the far field. The nuclides are transported to layers close to the surface. The contaminated water is pumped from a surface well and used for drinking, irrigation, cattle feed and fish ponds. (orig.)