Control of Beyond Design Basis Accident in Rbmk with Total Blackout with Prolonged Core Dewatering

A scenario is examined for the development of a beyond design basis accident with loss-of-power for internal needs and functional failures/delays in the actuation of mobile means for emergency cooling RBMK in application to the No. 3 unit of the Kursk NPP. It is shown that actions taken by operating personnel to control pressure in the circulation loop, primarily with the aid of the valves of fast reduction setup for dumping steam in the turbine condensers are effective. The sequence of these actions makes it possible to prevent collapse of the channel tubing at high pressure, preserve the integrity of the reactor space, and effectively limit the accidental emission of radionuclides into the environment.