[en] Safety design of radiation shielding is discussed for JT-60SA. The JT-60SA is the satellite tokamak of ITER Broader Approach. The JT-60SA is planned to be utilized in the existing JT-60 experimental building and operate for ten years with deuterium plasmas. Since the high performance discharges can be sustained for 100 seconds, the annual neutron fluence from the NCT plasma would be increased up to about two hundreds times of the present JT-60U plasma. For safety operation of the coils, the vacuum vessel is required to suppress the nuclear heating of superconductor. To satisfy the site boundary condition of JT-60 for radiation safety, the radiation shielding structure of vacuum vessel and cryostat is designed. Neutron and photon transport calculations have been performed using ANISN and DOT3.5 with nuclear cross-sections from the FUSION-40, which based on JENDL 3.3. In the activation calculations, ACT-4 has been employed. Nuclear heating of the coil and neutron flux through the vacuum vessel was considered to determine the basic structure of the vacuum vessel. For the material of vacuum vessel, radiation shielding performance of stainless steel and boron-doped stainless steel were evaluated. The thickness of the structural and shielding materials has been changed for the vacuum vessel to be optimized for the nuclear heating of the toroidal field (TF) NbTi superconducting coil. So, the vacuum vessel is designed to be a double-walled structure made of stainless steel (SS316L) less than 0.05 wt% Cobalt contamination. The inner space in the double wall is filled with a 140 mm thickness of borated water (95 % B-10 enriched) for neutron shielding. The maximum nuclear heating of the coil was suppressed to 0.23 mW/cc at inboard of the coil. The nuclear heating of the coil was sufficiently reduced the design criterion for the 100 sec heat load of the TF coil The cryostat made of stainless steel (SS304) is designed to be a double-walled spherical filled with boron doped low activation concrete for the biological shield. The cryostat consists of the 34 mm thickness of SS304, and the concrete of the 160 mm thickness is set up outside the steel. In addition, it is covered with SS304 of 6 mm thickness. The dose rate in the JT-60 torus hall is suppressed up to an acceptable level by the vacuum vessel and cryostat. The dose rate of JT-60SA site boundary is also satisfied without any additional shielding performance for the JT-60 building. (author)