[en] An approach combining deterministic and Monte Carlo neutron transport methods is applied to analyze the neutron streaming problem inside the containment at the Krsko Nuclear Power Plant. This problem has been raised due to the planned removal of the concrete missile shield blocks, which could potentially cause elevated neutron dose rates on the operating deck. In this analysis, the neutron source term leaking from the reactor vessel belt-line is calculated using the DORT/DOMINO/MCNPBQ code system to account for the cycle-specific core power distribution. This source term is then coupled with a detailed MCNP model of the containment building in order to calculate the neutron dose rates and solid state track recorder (SSTR) results on the operating deck. The cell-based weight window and other variance reduction techniques have been used in the MCNP transport simulations to improve the calculation efficiency. The results show reasonable agreement between the calculation and the measurements with the concrete missile shield. The calculation performed without the concrete missile shield considered present shows an increase in neutron dose rates for most of the locations of interest. However, the analysis also shows that, with proper back-fit shielding in place, the neutron dose rates on the operating deck can be reduced by a factor of up to 30 after removing the concrete missile shield, which is favorable from both regulatory and operational point of views. (authors)