Chinese fusion engineering test reactor (CFETR) is designed to bridge gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO). Phase II of CFETR aims for DEMO validation with a fusion power over 1 GW, H-mode physics. In order to get this high operation parameters, the superconducting magnet system of CFETR has been designed based on the larger machine with R = 7.2 m, a = 2.2 m, BT = 6.5 T, and the maximum field at CS (Central Solenoid) Coils will be over 15 T. A hybrid superconducting CS magnet employing Bi-2212 round wires and Nb3Sn strands is considered for CFETR. In this paper, a design of 10 kA CICC twisted by Bi-2212 round wires at 15 T field and 4.5 K temperature was introduced, and a method was study to calculate AC losses of Bi-2212 cable in different indentation and strain conditions. In the CS coils, AC losses were calculated in detail, hysteresis loss was sensitive to indentation and strain, however, coupling losses were sensitive to indentation depth only.