The capability to depressurize a three-loop pressurized water reactor during a station blackout sequence has been assessed using the SCDAP/RELAP5 computer code. During the initial calculations, failure of the pressurizer surge line from creep rupture was predicted prior to relocation of molten core material to the lower plenum. The system response from that pressure boundary failure was then simulated until the accumulators emptied. Additional calculations assessed the accident progression in the event that the surge line did not fail. These calculations were intended to bound in core damage progression prior to relocation of molten material to the lower plenum. Heat transfer from core material to the coolant was maximized and minimized by varying in-core relocation and fragmentation parameters within their uncertainty ranges. The calculated results indicate that the system pressure can be lowered significantly using pressurizer power-operated relief valves and the reactor vessel head vent, but core damage will be extensive. The magnitude of the system pressure during the later stages of depressurization was not strongly influenced by differences in the core melt progression. However, the amount of core material that relocated to form in a molten pool was strongly affected by variation of in-core damage progression parameters.