Nuclear reactor pressure vessel support system

Claim 1

A nuclear reactor pressure vessel support system comprising: a generally cylindrical nuclear reactor pressure vessel having a fluid contained therein; a pressure vessel flange around the upper periphery of said pressure vessel, said flange having an annular vertical extension formed integral therewith, said vertical extension having width less than the radial width of said flange; a containment well radially surrounding said pressure vessel, said well having a containment support ledge thereon adjacent said flange extension; a support ring located on the upper surface of, and secured to, said flange vertical extension and said containment support ledge; a rotatable plug positioned within said pressure vessel, said rotatable plug having a radial extension formed integral therewith around the outer periphery thereof, said plug radial extension being located adjacent said flange vertical extension, said plug radial extension and said flange vertical extension forming a first annular space therebetween; an annular plug riser secured to the upper surface of said plug radial extension and the upper surface of said flange vertical extension, said flange vertical extension rotatably supporting said plug through said plug riser, said plug riser comprising two riser elements having a second annular space therebetween, said second annular space being in fluid communication with said first annular space; and sealing means for preventing the escape of contained fluids through said second annular space disposed within said first annular space adjacent said flange vertical extension, said sealing means preventing the escape of contained fluids through the joint formed by said flange vertical extension and said support ring.