Chinshan Unit 1 postulated small break LOCA analysis

Four postulated small break LOCA events have been analyzed using the RETRAN-02 code for Chinshan Nuclear Power Station to establish plant-specific information Results conclude that core coverage is assured with high pressure injection systems under loss of off-site power conditions in steam line, feedwater line, and recirculation suction line 0.1 ft/sup 2/ break events. The feedwater line break incident is the only case that requires operator's action to depressurize the core under containment isolation and loss of high pressure injection conditions