A toroidal equilibrium of a poloidal divertor RFP is analyzed as a free boundary problem including an external coil current of a vertical field and a poloidal divertor. Effects of poloidal divertor upon equilibrium parameter of RFP and the proximity of plasma to the conducting shell are investigated and the poloidal divertor configuration is shown to decrease the proximity of plasma to the shell to the value, <rp/aw>≤ 0.75, and be high Θ RFP without additional plasma surface controls.