Abstract: A water monitoring system for a nuclear reactor is provided. In an exemplary embodiment, the water monitoring system includes a fiber optic cable having a first end and a second end, with the first end configured to optically couple to the reactor cooling water distribution system, and at least one laser light source optically coupled to the second end of the fiber optic cable. The water monitoring system also includes a spectrophotometer optically coupled to the second end of the fiber optic cable.

Abstract: A reactor power output measurement device measuring a neutron flux with a traversing incore probe (TIP) traversing in a vertical direction in a core of a reactor, and calibrating a detection sensitivity of a local power range monitor based on a measured neutron flux distribution in the axial direction inside the reactor, which is provided with an integrated control device 9 for transmitting control data to all of TIP drive control devices 13a through 13e and performing control/monitor of all of detector drive systems 17a through 17e.

Abstract: The method involves measuring hydrogen permeation in the tubes by mass spectrometry, wherein the tube is inserted into a high or ultrahigh vacuum device in which a mass spectrometer and a total pressure gauge are located. H2 or H2 and inert gas mixtures are circulated inside the tube at the required partial pressure. The tube is then heated and the appearance of H2 outside the tube is observed. The flow thereof inside the tube and emergence time, called permeation time, are determined based on permeation curves. The emergence time of the first microcrack is also determined.

Abstract: An inspection apparatus for inspecting jet pump beams of nuclear reactors is provided. The inspection apparatus includes a base straddlingly mountable on a jet pump beam. The base includes a beam bolt opening sized to receive a jet pump beam bolt. A first transducer holder is coupled to a first side portion of the base, and a second transducer holder coupled to a second side portion of the base. The first side portion is opposed to the second side portion. Each holder includes an adjustment cylinder configured to contact the jet pump beam when activated.

Abstract: A method and system for thermal-dynamic modeling and performance evaluation of a nuclear Boiling Water Reactor (BWR) core design is presented. A data processing system is used to execute specific program routines that simultaneously simulate the thermal operating characteristics of fuel rods within the reactor during a transient operational condition. The method employs a multi-dimensional approach for the simulation of postulated operational events or an anticipated operational occurrence (AOO) which produces a transient condition in the reactor—such as might be caused by single operator error or equipment malfunction. Based on a generic transient bias and uncertainty in the change in critical power ratio (&Dgr;CPR/ICPR), histograms of fuel rod critical power ratio (CPR) are generated.

Abstract: A sensor for measuring electrochemical corrosion potential, and a method for manufacturing a sensor, the sensor comprising a tubular ceramic probe having a closed tip at one end, the probe at least partially filled with a powder comprising metal and metal oxide; a metal support tube having one end receiving an opposite end of the probe, and joined thereto by a braze joint therewith; an electrical conductor extending through the support tube and into the probe, and having an end buried in the powder for electrical contact therewith; and a protective band bridging the probe and tube at the joint for sealing thereof, the protective band consisting essentially of a metallic coating.

Abstract: The measurement device comprises a real-time measurement-signal acquisition module (25) and means (23, 24) for connecting the cables for picking up the voltage from electrical windings for measuring the movement of the control rods to the acquisition module (25), in order to deliver, to the acquisition module (25), voltage signals corresponding to the voltage induced in the windings while the control rods are being dropped. The signal acquisition module (25) is thus permanently connected to the voltage-signal pickup cables (29) and the signals relating to the set of nuclear reactor control rods may be recorded simultaneously. Means (26, 27) for using the voltage signals delivered by the acquisition system (25) allow the drop times of the control rods to be determined.

Abstract: An inspection apparatus for inspecting jet pump beams of nuclear reactors is provided. The inspection apparatus includes a base straddlingly mountable on a jet pump beam. The base includes a beam bolt opening sized to receive a jet pump beam bolt. A first transducer holder is coupled to a first side portion of the base, and a second transducer holder coupled to a second side portion of the base. The first side portion is opposed to the second side portion. Each holder includes an adjustment cylinder configured to contact the jet pump beam when activated.

Abstract: The present invention provides an apparatus and method for measuring nonferrous electrical resistance measurement. The method includes providing a nonferrous material, inducing a magnetic field on the nonferrous material, measuring the remote magnetic field of the nonferrous material, and comparing the measured remote magnetic field to a standard.

Abstract: The neutron monitoring system measures neutrons by counting both the negative pulse signals and the positive noise pulse signals output from a neutron detector 1, and subtracts the positive pulse count from the negative pulse count per unit time, thereby measuring the neutrons.

Abstract: A method for inspecting an irradiated fuel element in a nuclear power plant includes the step of measuring, with a measuring device, a spacer of a fuel element for providing measurements of the spacer. The measuring device also measures a calibration rod for providing measurements of the calibration rod, the calibration rod having known dimensions. The measurements of the spacer are calibrated by using the measurements of the calibration rod. It is possible thereby to measure at least the maximum width of the spacer with a measuring error of less than 20 &mgr;m. A device for inspecting an irradiated fuel element in a nuclear power plant is also provided.

Abstract: A method and system for demonstrating compliance of nuclear fuel rods with fundamental licensing criteria for fuel rod internal pressure during nuclear reactor operation is presented. A nuclear fuel rod evaluation process is performed during the fuel cycle design and licensing process for each operating cycle of a particular nuclear reactor. The evaluation process includes a rod-by-rod internal pressure analysis based on empirical data of actual operational power output levels of each fuel rod in the reactor core. A computer program constructs individual fuel rod power histories for each nuclear fuel rod in the reactor core based on empirical information acquired during previous fuel cycles and the projected operation of the reactor in an upcoming fuel cycle. Using the constructed power histories for each fuel rod, the program then computes thermal and mechanical overpower limits and a maximum internal pressure for each rod in the upcoming fuel cycle.

Abstract: A neutron rem meter utilizing proton recoil and thermal neutron scintillators to provide neutron detection and dose measurement. In using both fast scintillators and a thermal neutron scintillator the meter provides a wide range of sensitivity, uniform directional response, and uniform dose response. The scintillators output light to a photomultiplier tube that produces an electrical signal to an external neutron counter.

Abstract: An inspection apparatus for inspecting welds in a nuclear reactor jet pump includes a probe subassembly rotatably and linearly movably coupled to a frame structure configured to attach to a top flange of the reactor pressure vessel. The probe subassembly includes a plurality of probe arms pivotably coupled to a housing, with each probe arm including a sensor. The probe arms are pivotably movable between a first position where the probe arms are parallel to a longitudinal axis of the probe subassembly, and a second position where the probe arms are at an angle to the longitudinal axis of the probe subassembly. An insertion subassembly couples to the jet pump suction inlet. The insertion subassembly is sized to receive the probe subassembly and guide the probe subassembly into the jet pump through the jet pump suction inlet.

Abstract: The invention is directed to an apparatus and method for inspecting spring hold down bolts of an upper tie plate of a fuel rod assembly in a nuclear reactor and includes an inspection fixture adapted to be aligned with the upper tie plate of the nuclear reactor fuel rod assembly for placement into a position for rapid and easy insitu inspection of the hold down bolts of the upper tie plate. The fixture is provided with a plurality of ultrasonic transducers which are positioned on the fixture so that when the fixture is placed into the inspection position each transducer will be located proximate to one of the hold down bolts for conducting effective ultrasonic scanning of the bolt while the bolt is in place. A multi-channel ultrasonic flaw detector is connected to each of the transducers for indicating whether there are any flaws in each of the hold down bolts when the fixture is placed into the inspection position and the ultrasonic transducers are activated.

Abstract: A protective hose, and a method of making the same, for an in-core instrument assembly used in a nuclear reactor, including a first end that is hermetically sealed to a first member of in-core instrument assembly such as a bullet nose, a second end that is hermetically sealed to a second member of said in-core instrument assembly such as a seal plug, and a body portion that surrounds at least one detector in the in-core instrument assembly, and has flexible, corrugated outer and inner surfaces. The body portion includes a series of ribs having peaks. The hose is compacted in length to a degree that the peaks of the ribs are substantially adjacent to one another. The ribs also have side surfaces that decline from the peaks to valley portions that are disposed between the side surfaces. The hose is compacted in length to a degree that the side surfaces are completely in physical contact with one another.

Abstract: A seal arrangement for providing a seal between a nuclear reactor in-core instrument housing and an instrument contained within the housing includes a lower seal assembly surrounding an outer portion of the in-core instrument housing, an upper seal assembly surrounding an outer portion of the in-core instrument, a seal housing enclosing the lower and upper seal assemblies, and lower and upper compression assemblies positioned on respective ends of the seal housing. The compression assemblies each include a drive nut and a compression collar. The compression collars engage and apply an axial load on the seal assemblies to maintain a reliable seal between the seal housing and the outer portion of the in-core instrument housing, and between the seal housing and the outer portion of the in-core instrument.

Abstract: The neutron monitoring system measures neutrons by counting both the negative pulse signals and the positive noise pulse signals output from a neutron detector 1, and subtracts the positive pulse count from the negative pulse count per unit time, thereby measuring the neutrons.

Abstract: A method and apparatus for controlling components in a component control system in a nuclear power plant includes an image processing system and display processor (IPS-DP) for issuing an encrypted command for a selected component in a component command system (CCS) in the nuclear power plant; a soft controller for receiving the encrypted command and matching the command with the selected component in the CCS for issuing a control command to the selected component; and control channel gateway for receiving the encrypted command from the IPS-DP and soft controller, deciphering the encrypted command, and, if authenticated, issuing a control command for said selected component in the CCS. Security and isolation, while complying with applicable codes and regulations, are assured.

Abstract: A reactor pressure vessel (RPV) for a nuclear reactor that permits measurement of the flow through each reactor internal pump (RIP) is described. The reactor pressure vessel also includes at least one reactor internal pump that includes an impeller and a pump diffuser. At least two seal rings extend circumferentially around an outer surface of the diffuser housing outer wall and are located in circumferential grooves in the housing outer wall. At least one lateral bore extends through the housing outer wall into a diffuser housing longitudinal flow passage. Each lateral bore is located in an area between two adjacent seal rings, with each inter-seal ring area containing one lateral bore. At least one pressure tap bore extends from the outer surface of the RPV bottom head petal, through the pump deck to an inner surface of a pump deck opening. Each pressure tap bore is aligned with an area in the RIP containing a corresponding lateral bore.

Abstract: The exit thermocouples of a pressurized water reactor (PWR) are calibrated by recording the thermocouple temperature measurements periodically during power ascension of the reactor together with a predicted power at the corresponding locations at the same time determined by a three-dimensional analytical nodal model of the core at the same core average power. The temperature measurements are converted to local core power values which are then divided into the corresponding predicted powers for the corresponding locations to arrive at mixing factors which are fitted to a selected function of core power. These mixing factors are recorded and subsequently applied to local power values calculated from measured exit thermocouple temperatures to adjust the three-dimensional nodal model power.

Abstract: A method and apparatus are provided for assaying a waste container. The method includes the steps of forming a plurality of slices through a volume of the waste container, performing a relatively fast passive prescan to measure a level of radioactivity of each of the plurality of slices and identifying at least some slices of the plurality of slices having a relatively high level of radioactivity. In addition, the method includes the steps for performing a relatively fast active prescan of the drum to determine the average attenuation of the plurality of slices. The method further includes the steps of determining an passive assay time for the identified slices based upon the measured radioactivity and average attenuation and performing relatively slow passive and active CT scans of the identified slices based upon the determined passive and active CT assay time to quantify a source of the measured radioactivity by weight.

Abstract: A nuclear reactor instrumentation system including a plurality of incore nuclear instrumentation assemblies arranged in a gap between a number of fuel assemblies charged in a reactor core. The incore nuclear instrumentation assemblies each include a fixed type neutron detector having a plurality of fixed type neutron detectors dispersively arranged in a core axial direction and a fixed type gamma thermometer assembly having a plurality of fixed type gamma ray heat detectors arranged at least in a same core axial direction as the fixed type neutron detectors. A power range detector signal processing device operatively connected to the fixed type neutron detector assemblies through signal cables. A gamma thermometer signal processing device is operatively connected to the fixed type gamma thermometer assembly of the incore nuclear instrumentation assembly through a signal cable.

Abstract: A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power pulse discrimination unit calculating n-th power values of the sampled data to discriminate the pulse component, where n is two or more, and a pulse counter counting a number of the discriminated pulse components.

Abstract: A neutron rem meter utilizing proton recoil and thermal neutron scintillators to provide neutron detection and dose measurement. In using both fast scintillators and a thermal neutron scintillator the meter provides a wide range of sensitivity, uniform directional response, and uniform dose response. The scintillators output light to a photomultiplier tube that produces an electrical signal to an external neutron counter.

Abstract: An end effector for supporting an ultrasonic testing probe on a robot arm having a robot mounting bracket for use in a nuclear reactor pressure vessel. The end effector has a wrist assembly with a rotatable wrist axle. The wrist assembly is coupled to the robot mounting bracket and a probe assembly is coupled to the wrist shaft. The ultrasonic testing probe is floatably disposed within the probe assembly.

Abstract: A combination of a master machine and a plurality of slave machines communicate wireless with each other. In case of a radiation leak accident, multitudes of inhabitants or workers dealing with the accident are made to carry the slave machines. The slave machine measure the degree of radiation exposure in real time, and notifies this measured result automatically to the master machine by wireless communication. The master machine recognizes the accurate radiation dose of the exposure and determines the degree of danger. The master machine notifies in real time the determined result individually to people carrying the slave machine, who are exposed victims or people that have a possibility of being exposed, according to the danger degree. The master machine is made to extract true radiation measurement data from the measurement signal data sent by the slave machine, by discriminating noise.

Abstract: An apparatus for ultrasonically examining a weld in a nuclear steam supply system includes an elongated guide rod for positioning within a pipe of the nuclear steam supply system. An ultrasonic transducer is positioned at an end of the elongated guide rod. A collapsible shoe encloses the ultrasonic transducer. The collapsible shoe includes a biasing mechanism to allow the collapsible shoe to pass through the pipe while the pipe is at a first circumference and while the pipe is at a second circumference. The collapsible shoe continuously contacts the pipe to establish ultrasonic coupling for the ultrasonic transducer.

Abstract: Nuclear fuels are taken from a nuclear reactor pressure vessel, a rail for running is mounted under the reactor pressure vessel drain piping in parallel with a horizontal portion of the reactor pressure vessel drain piping inside a pedestal positioned on the lower side of the reactor pressure vessel, an inspection apparatus is mounted on the rail, and the inspection apparatus is moved along the rail to inspect the reactor pressure vessel drain piping, whereby the reactor pressure vessel drain piping can be surely inspected while reducing radiation exposure to an inspector.

Abstract: Compliance with administrative limits on cumulative exposure of control rod groups in the reactor core, is monitored by computing the incremental effective exposure for each group commensurate with core power, for each time increment at which each group is within the position range where an administrative limit is imposed. The increments of effective exposures for each group are accumulated, and the accumulated effective exposure for each group is compared with the administrative limit to each group. This comparison is then displayed to the reactor operator, preferably using either a “rolling wheel” or “sliding bar” format.

Abstract: Nuclear fuels are taken from a nuclear reactor pressure vessel, a rail for running is mounted under the reactor pressure vessel drain piping in parallel with a horizontal portion of the reactor pressure vessel drain piping inside a pedestal positioned on the lower side of the reactor pressure vessel, an inspection apparatus is mounted on the-rail, and the inspection apparatus is moved along the rail to inspect the reactor pressure vessel drain piping, whereby the reactor pressure vessel drain piping can be surely inspected while reducing radiation exposure to an inspector.

Abstract: An inspection apparatus for inspecting welds in a nuclear reactor jet pump includes a probe subassembly rotatably and linearly movably coupled to a frame structure configured to attach to a top flange of the reactor pressure vessel. The probe subassembly includes a plurality of probe arms pivotably coupled to a housing, with each probe arm including a sensor. The probe arms are pivotably movable between a first position where the probe arms are parallel to a longitudinal axis of the probe subassembly, and a second position where the probe arms are at an angle to the longitudinal axis of the probe subassembly. An insertion subassembly couples to the jet pump suction inlet. The insertion subassembly is sized to receive the probe subassembly and guide the probe subassembly into the jet pump through the jet pump suction inlet.

Abstract: An ECP sensor includes a tubular ceramic probe having a closed tip at one end packed with a metal and metal oxide powder. A metal support tube receives an opposite end of the probe, and is joined thereto by a braze joint therewith. An electrical conductor extends through the support tube and probe, and has an end buried in the powder for electrical contact therewith. A ceramic band bridges the probe and tube at the joint for sealing thereof.

Abstract: A locking device for a reactor instrumentation protective sleeve and reactor instrumentation column assembly. The locking device includes a protective sleeve coupled to the instrumentation column by a selectively operable and closeable clip assembly. The locking device also includes a locking sleeve supported by the protective sleeve. The locking sleeve is supported by the protective sleeve such that a portion of the locking sleeve covers a portion of the protective sleeve and the clip assembly.

Abstract: A nuclear reactor core performance data visualization system provides a method and apparatus for extracting and visually displaying large amounts of numerical performance data acquired from an operational nuclear reactor or from a nuclear reactor core simulator. The visualization system apparatus includes a color display device, a digital computer having a data storage memory, and one or more data communications links for communicating with reactor core sensors and/or other computers. After acquiring performance parameter data, the visualization system computer extracts selected performance data and constructs two distinct data arrays in memory that are used in creating formatted files for generating specific types of visual displays.

Abstract: A method for measuring the drop time of a rod in nuclear reactor with the rod position indication system coils remaining energized. The signal generated at the coils includes both the rod drop trace and the coil power. A filter is applied to separate the rod drop trace from the coil power. The drop time of all rods in a reactor can be measured simultaneously in a single test. Furthermore, the test data results are plotted automatically with plot overlay capability to compare rod drop traces to the results of previous tests or to compare an individual rod to another within the same test.

Abstract: An electrochemical corrosion potential sensor includes a ceramic tip insulating member, and a sensor tip joined to the ceramic tip insulating member, the sensor tip comprising an alloy. Further, a coating is provided on an outer surface of the sensor tip, the coating including a noble metal, and a conductor electrically connected to said sensor tip.

Abstract: An adjustment tool is provided, having a probe, a head, an arm and a micrometer attached to the head. With the probe inserted into a spacer cell opening, the micrometer handle is rotated to a predetermined setting to pivot the arm. The opposite end of the arm from its engagement with the micrometer drive head engages and displaces the spring of the spacer cell to adjust its spring force. In one form, the arm is housed within the probe and the micrometer drive head displaces the distal end of the arm outwardly to correspondingly displace the spring outwardly, thereby decreasing the spring force. In another form of the spacer tool, the arm is spaced from the probe and has pivotal contact surfaces to straddle the spring. Movement of the drive head by rotating the micrometer handle to a predetermined setting causes the spring to be displaced inwardly of the spacer cell opening to increase the spacer spring force.

Abstract: An in-situ testing apparatus for testing the integrity of rib plugs used to seal faulty reactor boiler tubes consists of a cup-shaped member with a groove on the open end, a tapped hole for attaching a hydraulic hose of known pressure, and a hole through the top of the member. A seal is installed in the groove on the open end of the cup to seal to the primary face of a tubesheet around the tested rib plug. A threaded mandrel goes through the hole in the top of the cup-shaped member and engages the expander member of the rib plug. The threading action of the mandrel into the expander draws the seal against the tubesheet to seal the testing apparatus and allows the rib plug to be in-situ pressure tested.

Abstract: An ECP sensor includes a tubular ceramic probe having a closed tip at one end packed with a metal and metal oxide powder. A metal support tube receives an opposite end of the probe, and is joined thereto by a braze joint therewith. An electrical conductor extends through the support tube and probe, and has an end buried in the powder for electrical contact therewith. A ceramic band bridges the probe and tube at the joint for sealing thereof.

Abstract: A method for measuring the thickness of a layer of crud containing ferromagnetic material deposited on nuclear fuel rods using eddy current lift-off (coil-to-conductor spacing) measurement by exciting a probe coil at predetermined frequency which penetrates only into the layer of crud containing the ferromagnetic material.

Abstract: A method for determining a reduced ICI patterns is provided to achieve core monitoring and surveillance and other required functions using fewer ICIs. Candidate ICI patterns having a reduced number of ICIs relative to the existing pattern are first selected according to predetermined selection considerations. After selection, the candidate patterns are evaluated according to predetermined evaluation criteria.

Abstract: The boron concentration can be measured without intervention into the cooling circuit of a nuclear power station. A mobile emitter and a mobile receiver are provided, with the interposition of at least one coolable region, for placement on a coolant-carrying component of the cooling circuit.

Abstract: The invention concerns a method and a device for evaluating the integrity of the nuclear fuel in a nuclear plant having a reactor (1) enclosing a reactor core formed by a number of fuel cladding members (2) arranged to enclose said nuclear fuel. The value of each of a number of parameters including activity data (4) of the off-gases from the reactor is determined. The value of each of a number of second parameters including chemical data and activity data of the liquid (5) flowing through the reactor is determined. The value of each of a number of operational parameters (6) including at least one of the reactor effects, control rod position, actual fuel type, flow of off-gases, and flow of the liquid flowing through the reactor is determined. The value of the first and second parameters are standardized (7, 8) in relation to the values of said operational parameters.

Abstract: In a system for monitoring power of a nuclear reactor, a plurality of neutron flux measuring devices are arranged in a reactor core of the nuclear reactor for measuring neutron flux so as to generate neutron flux signals on the basis of the measured neutron flux. The neutron flux signals are filtered through a first weighting coefficient and a second weighting coefficient previously held in a monitoring signal calculating unit so as to generate stability monitoring signals. The first weighting coefficient corresponds to a fundamental mode of a neutron flux distribution in the reactor core and tire second weighting coefficient corresponds to a higher mode of the neutron flux distribution therein. The stability monitoring signal filtered through the first and second weighting coefficients are transmitted to a stability monitoring unit the stability monitoring unit monitors the stability of the core according to the transmitted stability monitoring signals.

Abstract: An apparatus and method for diagnosing rotating equipment commonly used in the factory and process control industry are provided. The apparatus and method are intended for use in assisting a maintenance engineer in the diagnosis of turbines, compressors, fans, blowers and pumps. The preferred embodiments are an apparatus and method for diagnosing pumps, with a focus on centrifugal pumps. The apparatus and method are based on the comparison of the current pump signature curves resulting from the acquisition of process variables from sensors monitoring the current condition of the pump and the original or previous pump performance curve from prior monitoring or knowledge of the pump geometry, installation effects and properties of the pumped process liquid. The diagnostic apparatus and method can be applied to any rotating machine, but the apparatus and method for pumps are described herein.

Abstract: In an in-core fixed nuclear instrumentation system for a reactor, each of a plurality of in-core nuclear instrumentation assemblies has a nuclear instrumentation tube. LPRM detectors are housed in the nuclear instrumentation tube for detecting LPRM signal in a core of the reactor. A GT assembly is housed in the tube. The GT assembly has fixed GT detectors for detecting &ggr;-ray heating values and a built-in heater therein for calibrating the fixed GT detectors. The fixed GT detectors are arranged at least close to the fixed LPRM detectors, respectively. GT signals by the detected &ggr;-ray heating values of the fixed GT detectors of each GT assemblies are processed by a GT signal processing unit. The heater in each GT assemblies is electrically energized by a GT heater control unit. Predetermined time intervals are stored in a memory unit.

Abstract: In an in-core fixed nuclear instrumentation system for a reactor, each of a plurality of in-core nuclear instrumentation assemblies has a nuclear instrumentation tube. LPRM detectors are housed in the nuclear instrumentation tube for detecting LPRM signal in a core of the reactor. A GT assembly is housed in the tube. The GT assembly has fixed GT detectors for detecting &ggr;-ray heating values and a built-in heater therein for calibrating the fixed GT detectors. The fixed GT detectors are arranged at least close to the fixed LPRM detectors, respectively. GT signals by the detected &ggr;-ray heating values of the fixed GT detectors of each GT assemblies are processed by a GT signal processing unit. The heater in each GT assemblies is electrically energized by a GT heater control unit. Predetermined time intervals are stored in a memory unit.

Abstract: The measurement device comprises a real-time measurement-signal acquisition module (25) and means (23, 24) for connecting the cables for picking up the voltage from electrical windings for measuring the movement of the control rods to the acquisition module (25), in order to deliver, to the acquisition module (25), voltage signals corresponding to the voltage induced in the windings while the control rods are being dropped. The signal acquisition module (25) is thus permanently connected to the voltage-signal pickup cables (29) and the signals relating to the set of nuclear reactor control rods may be recorded simultaneously. Means (26, 27) for using the voltage signals delivered by the acquisition system (25) allow the drop times of the control rods to be determined.

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.