Patent Number: 
Section: claims

1. A method of passively, safely maintaining a coolant level of a nuclear power generating facility, above a nuclear core at a preprogrammed level for an extended period of time during a facility outage in which a reactor vessel housing the nuclear core is substantially depressurized, the power generating facility comprising:a containment building that houses the reactor vessel which has an elongated axial dimension that surrounds the nuclear core in which fission reactions take place, and an open end of the reactor vessel is axially spaced from the nuclear core, with the open end sealed by a head at a reactor vessel flange;a spent fuel pool supported outside the containment building at an elevation that extends substantially above the reactor vessel, the spent fuel pool being in fluid communication with an interior of the reactor vessel through a first valve that is configured to automatically supply coolant from the spent fuel pool to the interior of the reactor vessel when a sensed level of coolant within the reactor vessel is below a given level; andan ultimate heat sink coolant reservoir whose upper level of a coolant under normal operation of the nuclear power generating facility is supported at an elevation substantially above the spent fuel pool, with a lower portion of the ultimate heat sink coolant reservoir in fluid communication with the spent fuel pool through a second valve whose operation is automatically controlled by a level of coolant in the spent fuel pool to maintain the coolant in the spent fuel pool at approximately a preselected level;the method including the steps of:sensing coolant level within the reactor vessel above the nuclear core from a gauge on a branch coolant line connected to the reactor vessel, having an output indicative of a coolant level above the nuclear core;automatically controlling the first valve to drain coolant from the spent fuel pool into the reactor vessel when the sensing step identifies the coolant level is at the given level to maintain the coolant level within the reactor vessel at the preprogrammed level above the nuclear core; andautomatically controlling the second valve to drain coolant from the ultimate heat sink coolant reservoir into the spent fuel pool to maintain the coolant in the spent fuel pool at approximately the preselected level. 2. The method of claim 1 in which the nuclear power generating facility has a station blackout including the steps of:opening the first and second valves; andflooding the reactor vessel. 3. The method of claim 1 wherein the preprogrammed level is approximately at the reactor vessel flange. 4. The method of claim 1 wherein the nuclear power generating facility includes a refueling cavity supported above the reactor vessel flange and the reactor vessel head has been removed, the gauge controls the level of coolant above the nuclear core within the refueling cavity. 5. The method of claim 4 wherein the nuclear power generating facility includes a refueling canal establishing a fluid communication path between an inside of the refueling cavity at an elevation above the reactor vessel flange, and the spent fuel pool, through which a fuel assembly can pass, and means for isolating the fluid communication path from the inside of the refueling cavity, including the steps of:opening the means for isolating the fluid communication path; andcontrolling a level of the coolant within the refueling cavity through the fluid communication path. 6. The method of claim 5 in which the nuclear power generating facility has a station blackout including the steps of:opening the first valve; andflooding the containment building.