Pressurized Thermal Shock Evaluation of the H. B. Robinson Unit 2 Nuclear Power Plant. Volume 1. Chapters 1-8.

摘要

An evaluation of the risk of pressurized thermal shock (PTS) resulting in a through-the-wall crack in a reactor pressure vessel was performed for the H. B. Robinson Unit 2 nuclear power plant. The specific objectives of the H. B. Robinson study were (1) to further refine the methodology for evaluating the risk of PTS; (2) to provide a best estimate of the frequency of a through-the-wall crack for the H. B. Robinson Unit 2 vessel; (3) to determine the dominant PTS sequences for the unit; and (4) to evaluate the effectiveness of potential corrective measures. The examination of tens of thousands of transients indicated that PTS was not an important core melt initiator for H. B. Robinson Unit 2. The dominant risk sequences were determined to be failure of steam relief valves to close on multiple steam lines.