Two successive stages of the control of a beyond-design basis accident with de-energization of an RBMK reactor together with multiple equipment failures are analyzed: depressurization of the circulation loop and restoration of reactor cooldown with cold water as the reactor subsequently warms up. The factors affecting the pressure surge in the circulation loop on restoration of reactor cooling as the reactor heats up are examined. It is shown that the sequence of control actions and the employed equipment are effective from the standpoint of the possibility of overpressurization of the channel tubes and the reactor space. The state of the channel tubes and the reactor space in the presence of arising deformation loads was analyzed using an experimentally determined criterion for the acceptability (integrity) of a channel tube.