The preliminary analysis of an inherently safe nuclear power plant is presented. The system, based on the state-of-the-art technology of light water and gas-cooled nuclear power plants, features a multicavity prestressed concrete vessel, which houses a reduced boiling water reactor (BWR)-6 core and heat exchangers. Steam with a quality of 16.5 % at a pressure of 7.24 MPa (1050 psia) at the core exit flows through steam generators and preheaters arranged symmetrically around the core. The flow is maintained by natural circulation. Two turbine-generator-pump sets replace the high- and low-pressure injection systems as the emergency core cooling systems. The secondary system operates at a maximum pressure of 5.03 MPa (730 psia) and is rated at 1000 MW(thermal). The use of a prestressed concrete reactor vessel for ducting and containment and the replacement of forced recirculation with natural recirculation on the primary side significantly improve the inherent safety of the plant. The availability of a large thermal inventory on the primary side and the elimination of many engineered safety systems present in current BWR/pressurized water reactors should considerably simplify the operating procedures. It is expected that the modular design of the heat exchangers and the small size of the plant will reduce construction time and make it cost-effective.