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Activation and shielding analysis have been performed for CN helium cooled test blanket module (TBM) in ITER. In this paper, we examine the neutron induced radioactivity, decay heat and contact dose rate for the CN TBM recent design. In addition, we assess the shielding efficiency of TBM to satisfy the nuclear shield requirement of ITER. The 40 degree ITER 3D calculation model was used for the neutron transport calculation. Activation analysis were performed using FISPACT2007 code with activation cross section data file EAF2007. The dose rate distribution in the zone after shielding was calculated using two-step method. SA2 safety scenario was used as the irradiation scenario for activation analyses. The calculated results were discussed with a target of 100 microSv/hr after 12 days cooling for human access to the zones around port cell. It was shown that the shield efficiency of TBM system needs to be improved.