One of the methods currently under consideration for the disposal of radioactive wastes is emplacement in a repository within deep, continental formations. A licensing requirement for such a facility will presumably be some form of safety analysis report on the radiological impact of the facility. A methodology has been developed to make an assessment of the radiological consequences both for normal operation and for possible accident situations for a specific repository design in a salt dome at Gorleben in Germany, a repository which has been designed to accommodate all categories of radioactive waste (low, intermediate, and high level). Radionuclide release scenarios were derived from a systematic analysis of the facility design and proposed operational procedure. Where necessary, simple numerical models for such topics as direct radiation exposure from waste containers, release and transport of radionuclides, radiolysis, heat transfer, creep, and impact were developed to give a first estimate of the radiological consequences due to radionuclide releases. The results enabled sensitive areas of the design and the operational procedure to be identified, and thus possible modifications and/or precautionary measures could be recommended. The results also gave an indication of those parts of the analysis requiring more sophisticated and specialized modeling techniques to yield a more detailed radiological consequence analysis in preparation for a safety analysis report.