Steam Generator (SG) is an important system of a Nuclear Power Plant. It exchanges heat carried by primary coolant to secondary and produces steam. The inlet to SG is a nozzle that requires detailed structural evaluation. As part of this evaluation, stress analysis was carried out according to ASME Boiler and Pressure Vessel Code (BPVC) section III subsection NB to check the integrity of the nozzle region. This study analyses the structural and thermal stresses due to primary inlet nozzle in the APR1400 steam generator. The nozzle model was created and analyzed to get linearized stress intensities using ANSYS V.18.1. The results were evaluated by the ASME material allowable stress intensity value. The nozzle design was found to meet the ASME code requirements for both design and normal operating conditions