[en] The scope and contents performed in this project are as follows : firstly, reviews of the structure and contents of local and foreign regulatory requirements as well as analysis of design features related to safety improvement and containment bypass during multiple steam generator tube failure of advanced reactors of domestic and foreign countries. Secondly, analyses of the state-of-the-art of the development of local and foreign regulatory requirements, research trends, design features and safety goals of advanced reactors, especially for technical issues related to the containment bypass during MSGTR event. Thirdly, analyses of the event of MSGTR for the KNGR using MAS 1.4 which is the best-estimate system code developed by Korea Atomic Energy Research Institute. Errors in input-decks established last year have been corrected during this analysis. Fourthly, assessment of the effects of several parameters on the consequences following a MSGTR event. Tube rupture location, selection of affected steam generator, tube modeling method, discharge coefficient (C_D) are examined. Fifthly, establishment of regulatory direction of technical issues related to the containment bypass during MSGTR event