Combustion Engineering, Inc.

Westinghouse Electric Company LLC

Ce Nuclear Power LLC

Donn Moore Matteson

Daniel A Peck

Joseph M Mazur

A nuclear steam supply containment system employing prefabricated component supports that are surrounded by steel concrete forms and anchored to the floor liner of a nuclear containment. The prefabricated component supports extend through the concrete forms and a reinforce concrete slab cap to a support elevation for the component. A second inner steel concrete form can be employed to form an annular concrete channel through which the supports extend. The center of the inner form can be filled with a sand-like substance, radiation absorber material or concrete grout.

Nuclear plant containment with prefabricated component support structure

A removable rail assembly for use with a spent fuel handling machine, including a support rail, a rail guide carried by the support rail, a rail joint connector supported by the rail guide for coupling the rail guide to adjacent rails, and at least one jacking screw supported by the support rail for lifting the support rail assembly. Another embodiment of the invention includes a second jacking screw received in the top surface of the rail guide. The joint connector is tongue and groove joint with a tapered parting line that permits a tight fit between the removable rail and adjacent fixed rails. During removal of the removable rail, the jacking screw distributes a uniform lifting force along the length of the rail, loosening the joint connector. Once the joint connector is loosened, the rail is coupled to a lifting crane and transported to a storage area.

Removable spent fuel handling machine rail

A seal assembly for sealing a space between an annular flange on a nuclear reactor vessel and a surrounding ledge of a refueling canal to provide a temporary water barrier during refueling operations. The seal assembly includes an annular closure plate having an outer portion secured to the surrounding ledge and an inner portion supporting a first sealing surface. A second sealing surface opposing the first sealing surface is formed on or secured to the annular flange of the reactor vessel. An annular space between the first and second sealing surfaces provides a ventilation path from the reactor cavity during normal plant operation. The annular space is sealed by an inflatable seal during refueling operations to provide a water barrier between the refueling canal and the reactor vessel. The inflatable seal is secured to and supported by an annular support structure that straddles the annular space. The annular support structure provides a structure for handling the inflatable seal during installation and removal. The annular support structure also provides a leak limiting function in the event the inflatable seal is pulled or pushed through the annular space or otherwise fails to seal the annular space. The inflatable seal is secured to the annular support structure in a manner that allows independent movement of the seal to conform to irregularities in the sealing surfaces. The closure plate has a plurality of normally closed access ports that permit access to the external core detectors and the reactor vessel cavity.

Floating pool seal assembly with leak limiting annular support structure

An augmented cooling system for a CEDM in a nuclear reactor includes self actuated louvers or flap valve louvers which allow hot air from the head lift rig to vent and cooler ambient air to enter the rig in the event that pressure is lost for the forced cooled air which normally cools the CEDM.

Self-actuated louvers for venting a CEDM cooling system of a nuclear reactor and method of using the same

A measurement chamber (18) having an upper and a lower region is at substantially the same elevation as a horizontal pipe (12) having a top region and a bottom region. An equalization line (14) fluidly connects the top region of the pipe (12) to the upper region of measurement chamber (18). A sample line (16) fluidly connects the bottom region of pipe (12) to the lower region of the measurement chamber (18). Heat junction thermocouples (22) generate a signal indicative of the level of fluid in the measurement chamber (12) which is equal to the level of fluid in the pipe (12). The signal is transmitted to a remote location by line (24).

Mid-loop fluid level measuring instrument for a nuclear power plant

In order to reduce the number of lifts which are required to remove the various equipment normally disposed above the reactor pressure vessel and to make way for refuelling or regular maintenance, the control rod element drive mechanisms are completely enclosed within a cylindrical enclosure which is attached to the head of the pressure vessel. The top of the cylindrical enclosure is closed with a cap-like member which acts as both a missile shield and a head area cable tray. The missile shield, the cylindrical enclosure, the control rod drive mechanisms and the pressure vessel head, are connected to form an integral unit which can be removed in a single lift. Cable trays are pivotally supported on a wall of a building to establish a bridge between the building and the head area cable array and to establish a connection with the control element drive mechanism cables. During lifting, the control element drive mechanism cables are disconnected and the pivotal bridge trays are swung out of the way. During normal operation, the cylindrical enclosure guides a flow of cooling air over the control rod drive mechanisms.

Integral head rig, head area cable tray and missile shield for

A tank (18) forms a chamber having an upper and lower region. The tank (18) is in even elevation with a horizontal pipe (12) having a top region and a bottom region. An upper connecting pipe (14) fluidly connects the top region of the pipe (12) to the upper region of tank (18). A lower connecting pipe (16) fluidly connects the bottom region of pipe (12) to the lower region of the tank (18). Heat junction thermocouples (22) generate a signal indicative of water in the pipe (12). The signal is transmitted to a remote location by line (24).

Midloop water level monitor

A head equipment support structure system (HESS) (10) particularly adapted to be cooperatively associated with a nuclear reactor vessel (12) for purposes of effecting a separation of the electrical cables (30) that are utilized in the head area of such a vessel (12), as well as for purposes of providing support for these cables (30). The subject HESS (10) which is in the form of an integral structure that is removably supported relative to the vessel (12) combines the features of cable support structure, missile shield, and cooling ductwork support structure. The HESS (10) embodies horizontally disposed multiple decks (14) to which the cables (30) are vertically routed from the reactor vessel head. The decks (14), which are located in vertically spaced relation directly above the reactor vessel head, support and separate the cables (30). The decks (14) further function to align the corresponding ends of the cables (30) with their respective mating connectors, the latter being associated with the reactor vessel head and the connection panels suitably mounted on the surrounding wall surfaces. The cable decks (14) and steel plates formed integral with the HESS (10) are operative in the manner of a missile shield in that they function to absorb the energy of any missiles generated at the reactor vessel head. Lastly, other equipment (66, 68, 70, 72, 74) normally located in the head area is cooperatively associated with the HESS (10) in mounted relation thereto so as to be capable of being handled as a unit therewith during refueling operations, etc.

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South Windsor, CT, United States of America

Donn Moore Matteson