Radiations are extensively used in nuclear industry and medical centers and can have either valuable or harmful effects depending upon their uses and control. Radiation shielding is major field of radiological protection and is one of the basic principle of protecting people and their environment from harmful effects of radiation exposure. This paper is concomitant to the radial and axial shield design of typical pressurized water reactor (PWR) using advanced Monte Carlo computer code MCBEND. In this regard, the Chashma Nuclear Power Plant Unit-2 (CNPP-II) was taken as a benchmark problem and transport theory based shielding computer codes DOT3.5 (2-D), MCNP5 (3-D) were qualified against the reference results along the radial and axial direction. The calculated results are in favorable agreement with the reference results. It has been observed that dose rate on operating floor is mainly due to streaming through insulation gap around the RPV. It is concluded that the above mentioned tools can be applied confidently for the shielding design of indigenous PWR type reactor.