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In modern tokamak devices with a divertor is a very urgent task of monitoring the plasma boundary and the “mustache” of the separatrix in order to control the direction of flow of particles from the plasma. This paper describes the results of the application code, which restores the plasma boundary on the base of magnetic measurements. In more detail, explores the question of the necessary precision of measurements of the flux, magnetic field, as well as the provisions of the probes and loops, for a given error in the determination of the plasma boundary and the separatrix. Calculations are performed for a tokamak KTM (Kazakhstan), which is now in the stage of starting. http://ocs.ciemat.es/EPSICPP2012PAP/pdf/P5.053.pdf