Study on identification of design extension conditions without significant fuel degradation and safety features of nuclear power plant

According to the requirements of the new version of nuclear safety regulation HAF102, which is generally common with references about Design Extension Conditions (DECs) analysis from IAEA and EUR, a DEC analysis for nuclear power plant is performed to summary the methodology and procedure for analysis of DECs without significant fuel degradation and the design for their safety features. A list of DECs without significant fuel degradation for a typical generation-three advanced pressurized water reactor nuclear power plant is obtained based on engineering judgement, deterministic assessments and probabilistic assessments, and the safety features of these conditions are also determined, whose reliability meets the probabilistic safety goal of the nuclear power plant through PSA analysis. (author)