SYSTEMATIC EVALUATION PROGRAM REVIEW OF NRC SAFETY TOPIC VI-10.A ASSOCIATED WITH THE ELECTRICAL, INSTRUMENTATION AND CONTROL PORTIONS OF THE TESTING OF REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES, INCLUDING RESPONSE TIME FOR THE DRESDEN STATION, UNIT II NUCLEAR POWER PLANT

摘要

Tins report documents the technical evaluation and review or NRU Safety Topic VI-10.A, associated with the electrical, instrumentation, and control portions or the testing or reactor trip systems and engineered safety features including response time for the Dresden binuclear power plant, using current licensing criteria.