BRUCE A NUCLEAR DIVISION - STEAM GENERATOR LIFE MANAGEMENT PROGRAM

摘要

Following a number of steam generator tube leaks in the early 1990's, management of the Bruce A nuclear station established the Steam Generator Program and instituted an extensive program of boiler inspection, cleaning and refurbishment. The dominant tube degradation mechanism was identified as circumferentially oriented ODSCC. However, a number of other tube degradation mechanisms were also identified as currently or potentially active. The Bruce A steam generator has a number of unique design features that both affect the degradation process and complicate the refurbishment activities. This paper will provide an overview of the steam generator design features, the degradation mechanisms, the approach adopted in three key areas of the Steam Generator Program - 1) Organization, 2) Strategic Planning and 3) the Boiler Cleaning and Refurbishment activities and a summary of key findings.