Abstract: An interface between a Plant Protection System and Engineered Safety Features in a nuclear power plant is disclosed for continuously monitoring the plant protection system initiation circuit for each remotely actuated Engineered Safety Feature system to effect remedial action in the event that the Plant Protection System generates a ‘trip’ signal. By using actuation inputs from the Plant Protection System and manual, operator implemented inputs, controls are provided for remote equipment components, such as solenoid valves, motor operated valves, pumps, fans and dampers.

Abstract: A digital plant protection system for use in nuclear power plants of the pressurized water type includes cross-connected sensed-parameter processing channels that provide a suitably conditioned digital value to a digital comparator that tests the conditional digital value against a predetermined value to determine whether or not the sensed parameter has been exceeded. A comparator is associated with each of the plural channels and receives a separate measurement of the sensed parameter for each channel. If a sensed-parameter is determined to be out-of-specification by 2 of 4 or more channels, a `trip` signal is generated to effect remedial action.

Abstract: A universal base for a bracket system comprises an open ended tubular member having a rectangular cross section. A T-shaped tongue projects at an angle from one end of the base back wall and the opposite or front wall is formed with at least two laterally spaced pairs of vertically spaced slots. With the tongue of one base engaged in the opening of a lipped channel member, the slots are simultaneously engageable by two shelf brackets or alternatively the upper open end of the base may accept a cabinet bracket that is laterally positionable over part of the width of the base.