The commercial operation of nuclear power plant is started in Korea from 1978, and since then about 23 NPP are connected to gird and more NPPs are being constructed and planned to construct. The latest development of NPP is APR1400. The design re-engineering was carried out for training endeavor and as educational reasons to check APR1400 Steam Generator design whether it follows required ASME codes. The support of Steam Generator is one of the SG components that support all the weight of SG and loads caused by interacting components to ensure the integrity of the SG. The goal of this paper is to analyze the Linearized Stress Intensity change through the paths in the continuous and discontinuous regions of the support. This phenomenon is modeled using the ANSYS analysis tool and the results compared to the standard values given ASME code. The close proximity of the results obtained ascertains the accuracy of the FEM analysis even with the simplified 2D axisymmetric model. This paper demonstrated the strength of the support and the validity of commercial software.