This report discusses the shielding properties of the ITER/EDA NBI ducts based on the current JCT design of the 24 superconductive toroidal field coils (the 24 TFC). The two-dimensional transport calculations have been performed by DOT 3.5. First, the neutron fluxes, dose to insulator and peak nuclear heating rate were calculated in the TFC and the NBI duct. The X-Y calculational model with detail description of the neutron source shape and the TFC geometry is used for that calculation. Second, the R-Z calculational model with detail description of the NBI components was set up. The nuclear heating in the NBI cryo panels and displacement damage in NBI copper grids were obtained in that calculation. In summary, it it concluded that the shielding performance of the current NBI duct design is enough to decrease all considered neutronics responses below the limits. (author).