Abstract: A neutron flux measuring apparatus, adapted to a boiling-water reactor (BWR) of a nuclear power plant and an advanced boiling-water reactor (ABWR) of a nuclear power plant, for measuring a neutron flux in a reactor pressure vessel, comprises a neutron flux detector assembly incorporating a local power range monitor detector assembly and a start-up range neutron monitor detector, a preamplifier amplifying a detector signal obtained from said start-up range neutron monitor detector, a start-up range neutron monitor operation unit operating, indicating and monitoring the amplified signal of the start-up range neutron monitor detector, and a local power range monitor operation unit operating, indicating and monitoring a signal obtained from the local power range monitor detector.

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: 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: 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: 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: 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: An improved heated junction thermocouple cable arrangement for use with a nuclear reactor heated junction thermocouple having sensors with an unheated thermocouple, a heated thermocouple, and a heater coil, shares power conductors between multiple heater coils. The thermocouple conductors are separated from the power conductors to eliminate the possibility of interference with the thermocouple conductor signals. The heater coils are ganged in parallel and if one heater coil fails, power is still supplied to the remaining heater coils connected to a pair of power conductors.

Abstract: A method of controlling the system pressure in a power generating system, having a turbine-generator and a BWR, that modulates the core thermal power of the reactor while maintaining the main turbine control valves in a constant steady position is described. The core thermal power may be adjusted by adjusting the control rod density within the reactor core or by adjusting the flow rate through the reactor which may be accomplished by modulating the speed of variable frequency recirculation pumps or by modulating recirculation flow control valves. The method includes transferring the power generation system from normal turbine control valve modulation pressure control to core thermal power modulation pressure control. Additionally the method includes modifying the bypass valve closure bias and the power control bias to accommodate the variances from core power modulation pressure control over normal pressure control.

Abstract: The reactor start-up monitoring apparatus is provided with an SRNM detector, an analog amplifier, an N/D converter, a pulse measurement system, a Campbell measurement system and reactor power monitoring means. The pulse measurement system is provided with pulse counting means for counting the pulse number of output pulses of the detector from the first digital data from the converter, and pulse measurement evaluating means for converting the measurement value to reactor power and evaluating the reactor power. The Campbell measurement system is provided with sum operating means for adding a plurality of sampling values forming the first digital data from the converter and acquiring the second digital data having accuracy of bits more than those of the first digital data, power operating means for obtaining mean square values based on the second digital data and Campbell measurement evaluating means for converting the mean square values to reactor power and evaluating the reactor power.

Abstract: A power oscillation monitoring system and method for indicating instability of a nuclear reactor. The monitoring system facilitates monitoring reactor instability and maintaining a nuclear reactor in the stable state. In one embodiment, the monitoring system is implemented in a computer workstation having memory and a processor. The workstation is electrically coupled to neutron detectors, and a period based algorithm and a confirmation density algorithm are stored in the workstation memory. The processor contains a Period Based Algorithm (PBA) and a Confirmation Density Algorithm (CDA). Under the control of the system the PBA algorithm evaluates the periodicity of the neutron detector output signals to identify the presence of density waves in the reactor. The CDA utilizes the PBA output signals to identify confirmation density, which is the fraction of active neutron detectors in the core that reach a target successive oscillation period confirmation count.

Abstract: A transiently unstable state of a boiling-water reactor is damped by measuring the oscillating neutron flux and, after a first threshold value is exceeded over a plurality of oscillation periods, the rate of increase of the oscillation is determined. Depending on the slope of the increase, and after a further threshold value (in particular one dependent on the rate of increase) for the oscillating flux is exceeded, a selection is made which one of various stabilization strategies for damping the oscillation should be triggered before a SCRAM becomes necessary. A hierarchy of stabilization strategies is available: blocking a power increase, for instance, in the control system, controlled slow reduction of the power, or rapid power reduction by a "partial SCRAM". The monitoring of the unstable state is effected with a system of sensors strategically distributed throughout the core and which redundantly measure the flux in one region of the core.

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: A temperature measurement system includes, for each of two nuclear steam supply system (NSSS) loops, four temperature sensors each of which provides a value of the temperature of reactor coolant flowing in the NSSS hot leg of the loop; a mechanism for determining, for the hot leg, a first bias value associated with a first pair of the temperature sensors and a second bias value associated with a second pair of the temperature sensors from the value of the temperature of the reactor coolant of each of the temperature sensors; a mechanism for averaging the first bias value and the values of the first pair of the temperature sensors to determine a first average temperature therefrom; and a mechanism for averaging the second bias value and the values of the second pair of the temperature sensors to determine a second average temperature therefrom, whereby two separate average temperatures of the temperature of the reactor coolant are determined for each of the two loops.

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 plant operation apparatus for satisfying a separation criteria includes an operation panel, an operation display screen control device for controlling a display on the operation panel and a touch operation and for selecting a train in a software selection function based on the operation signal from the operation panel, a selection device having momentary push buttons and for resetting other push buttons in a hardware train selection function when an operator pushes one of the push buttons to select a train, and for outputting a control signal to select the train corresponding to the button pushed by the operator. The plant operation apparatus realizes the train selection system having multiplicity, diversity, and independence for satisfying the separation criteria.

Abstract: A received light level is displayed by a plurality of LEDs of a received light level display device like a bar graph. A set threshold value is indicated by a plurality of LEDs of a threshold value display device in correlation with the bar graph display. Adjustment of the threshold value is performed stepwise.

Abstract: The present invention is an electronic awareness system for evaluating, monitoring, and controlling, in real-time, an outside environment having entities and occurrences with characteristics. The electronic monitoring system includes input sensors for receiving real-time data produced by the entities, a computer workstation for storing the input data in a database, a computer program having a graphical user interface for interfacing a user with the workstation and the computer program. The graphical user interface comprises a map frame chart function, a worksheet function, a utility function, and a priority navigator function for monitoring and evaluating the input data graphically, tabularly, statistically, and comparatively with a predetermined relative priority scale, respectively, for producing output data. The electronic awareness system also includes output reactors for receiving the output data for controlling certain entities and occurrences of the outside environment.

Abstract: A CEDM data acquisition system (40) receives analog coil-current signals from control element drive mechanism coils (18, 20); conditions the analog signals to remove noise induced therein by the electronic circuitry (44) associated with the control element drive mechanisms; digitizes the conditioned analog signals; displays the acquired test data; and records the data for future use. The inventive data acquisition system preferably has the ability to simultaneously measure, display and record coil-current data for all of the five coils associated with each CEDM rod-group with respect to time. Further, the inventive data acquisition system preferably allows the user to monitor, display and record data for up to eight CEDMs simultaneously. It also allows the measurement of rod-drop times during rod-drop testing of the CEDMs.

Abstract: A power range monitor apparatus includes a plurality of average power range monitors for calculating/monitoring local power values, average reactor power values, and core flow rate values, a plurality of rod block monitors for monitoring the average values of local power values, and a plurality of flow rate signal converters for converting the signal form of recirculation rate detection signals. The flow rate signal converters concurrently transmit recirculation rate detection signals as digital signals to the average power range monitors. The average power range monitors obtain core flow rate signals from the respective recirculation rate detection signals, use them to monitor the average reactor power, and transmit them to the rod block monitors. The rod block monitors select optimal values from average reactor power values and core flow rate signals to perform a monitoring operation.

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 (or plural groups of fuel rods) within the reactor during a transient operational condition. The data processing system is also used for compilation of a transient response histogram that incorporates the effect of inherent "uncertainties" in various parameters of interest. In an initial phase, 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.

Abstract: An automated system for identifying nuclear power plant components includes a camera which provides an input signal from an image of the nuclear power plant components. A digitizer generates a digitized image of the nuclear power plant components from the input signal. A workstation locator routine locates the component identifier of the nuclear power plant components from pixel elements of the digitized image and a workstation determining routine determines the component identifier. The determining routine includes plural recognizer routines each having an output providing an intermediate recognition of the component identifier, and a combining routine combining the outputs of the recognizer routines to recognize the component identifier. Each of the outputs includes an intermediate identifier and a corresponding confidence value.

Abstract: A functional approach to an information display system that enables a fast and easy understanding of the status of a complex process. The display screen is organized by process goals. Each process goal is then tied to a number of process objectives which directly relate individually to the goals. The objectives are in turn tied to the process functions which must be substantially maintained in order to achieve the respective objectives. A display of control functions related to each process function is mapped onto the regional displays. The individual display elements use a combination of coded background color, border color and other indicia of information, e.g., mimics, meters, etc. to present a significant amount of information about the status of the process and its components in a manner that is readily absorbed and easily understood.

Abstract: An electrical circuit backfits into different instrumentation and control (I&C) system hardware configurations as a replacement or upgrade. The circuit has a multiple signal path processing circuit including a multi-functional ASIC. A fixedly configured, multiple signal path connector such as a hardwired multi-pin package removably connected with a pin socket in the processing circuit connects the ASIC with the I&C system for coupling inputs to and outputs from the ASIC and for selecting operative signal paths of the ASIC.

Abstract: The present invention relates to an operator work station for nuclear power plants which can provide plant information in an effective way during abnormal/emergency conditions so that the operator can take necessary actions to recover the nuclear power plants. The operator work station for nuclear power plants of the present invention comprises dynamic alarm console; system information console; computerized operating procedure console; system-alarm connecting system which connects the alarm console with the system information console; and, system-procedure connecting system which connects the system information console with the computerized operating procedure console. According to the operator work station, efforts and time required for the operator to judge for himself, and possibility of mistakes of judgement are properly excused, since the operator can easily recognize the system where abnormality occurs, based on the generated alarms.

Abstract: A method and system for identifying the maximum adverse impact of a mislocated nuclear fuel bundle placement in an nuclear core loading arrangement is presented. The method generally has an initialization phase and a "swap" case evaluation, or "search," phase. In the initialization phase, base conditions for a selected core loading arrangement are determined and parameters for exploring the mislocated fuel bundle loading error problem are set up. In the search phase, the core loading arrangement design space is explored for many combinations of mislocated fuel bundle pairs in order to find a mislocated fuel bundle pair that yields the most limiting core state. A computer system is used to execute specific program routines that simulate the operating conditions of a reactor having mislocation errors involving fuel bundle pairs in a core loading arrangement.

Abstract: A neutron particle measuring apparatus includes a neutron converter to generate alpha rays in response to incidence of neutron, a scintillator to receive as input the alpha rays generated from the neutron converter so as to emit and transmit scintillation, two photoreceptive portions to receive the scintillation through different transmitting paths, and a signal processing portion to measure a neutron distribution depending upon times at which the scintillation can reach the photoreceptive portions according to a time-of-flight method. The single particle measuring apparatus can be used to measure the neutron distribution in the vicinity of a nuclear reactor in a nuclear power plant.

Abstract: Prioritization logic determines the final command applied to a process control component from a plurality of commands generated by diverse independent control subsystems, each utilizing different hardware and software to implement a common algorithm to preclude common mode failures. In one embodiment, priority is given to commands generated by one control subsystem, such as a safety grade subsystem, over commands provided by a second, non-safety grade control subsystem. In another embodiment, equal priority is given to commands from two control subsystems. In this case, ambiguous commands from either or both subsystems are ignored, but conflicting commands produce a final command which provides a safe state.

Abstract: A system for ensuring the distribution of noble metal in the reactor circuit during plant application without measuring the reactor water for noble metal content by chemical analysis. The system performs the measurement of electrochemical corrosion potential in an autoclave or a high-flow test section that is connected to the reactor water circuit through sample lines downstream of the injection port, preferably the point in the reactor circuit which is furthest from the injection port. If the noble metal flows into the autoclave or test section at these distant points in the reactor circuit, then the noble metal will deposit on the test specimens inside the autoclave or test section.

Abstract: In a method of and an apparatus for checking the degradation of the pressure vessel of a nuclear reactor with the pressure vessel of the nuclear reactor being directly measured in a non-destructive manner, a magnetic yoke having an exciting coil and a magnetic flux measuring coil is closely placed in contact with the inner wall of the pressure vessel of the nuclear reactor. The hysteresis magnetization characteristics of the closed magnetic path formed by the magnetic yoke and the pressure vessel of the nuclear reactor are measured. The coercive forces are obtained by the hysteresis characteristics. The hardness of the material comprising the pressure vessel of the nuclear reactor at the part of the magnetic path formed in the pressure vessel of the nuclear reactor is obtained from the coercive forces and the degradation of the material comprising the pressure vessel is checked from the hardness.

Abstract: A reactor protection system having four divisions, with quad redundant sensors for each scram parameter providing input to four independent microprocessor-based electronic chassis. Each electronic chassis acquires the scram parameter data from its own sensor, digitizes the information, and then transmits the sensor reading to the other three electronic chassis via optical fibers. To increase system availability and reduce false scrams, the reactor protection system employs two levels of voting on a need for reactor scram. The electronic chassis perform software divisional data processing, vote 2/3 with spare based upon information from all four sensors, and send the divisional scram signals to the hardware logic panel, which performs a 2/4 division vote on whether or not to initiate a reactor scram. Each chassis makes a divisional scram decision based on data from all sensors. Each division performs independently of the others (asynchronous operation).

Abstract: An information system for a complex plant which clearly presents to the operator, in parallel as alarms, abnormal process changes which the operator can, at his discretion, manually respond to either to prevent conditions from deteriorating further to the point where automatic protective actuations will be initiated or where automatic protective actuations have not been completed because of a malfunction or were completed but have not been successful. Such alarms are displayed on a dedicated alarm display panel which spatially groups components and subsystems to show appropriate relationships, with the alarm messages shown in the associated area of the display so that possible disturbance propagation can be foreseen. Messages related to uncompleted automatic protective actuations may include a list of faults which prevented completion of those actuations.

Abstract: An automated system for determining positions of a plurality of nuclear fuel assemblies organized in an array within a housing of a nuclear power plant includes a radiation hardened, underwater camera for inputting images of the nuclear fuel assemblies with respect to each other or with respect to a baffle wall of a nuclear reactor core, a digital signal processor for generating a second digitized image including a plurality of pixel elements of the nuclear fuel assemblies from the first image, and a workstation for determining the positions of the nuclear fuel assemblies with respect to the baffle wall from counts of the pixel elements.

Abstract: In a drive device of control rod drive mechanisms, a large number of control rod drive mechanisms are divided into a plurality of groups, and there are provided, for each group, a control rod changeover device, and an inverter power source and inverter controller constituting the drive power source. The drive device comprises a control unit that receives control rod position signals from each of the control rod drive mechanisms and that outputs control signals to the control rod changeover device and inverter controller, and a man-machine device constituting an interface with the operator, that outputs control rod drive information to this control unit.

Abstract: A method and an apparatus for electrically suppressing electrochemical potential near highly susceptible components of a boiling water reactor. A small self-powered, electrical device is affixed to the metal area to be protected, which device has the capacity to locally suppress electrochemical potential automatically and continuously without provision for external power supplies, cables, penetrations, or other paraphernalia usually associated with electrical and electronic systems. The result is that components susceptible to intergranular stress corrosion cracking are not as sensitive to the details of the water chemistry flowing over them and do not crack as much, or as rapidly, as presently. The new technique is based on the concept of supplying electrons directly and locally to the sensitized zone(s) of the metal, thereby inhibiting intergranular stress corrosion cracking. The source of the electrons is .beta.-emitting material which is contained in a housing attached to the metal.

Abstract: A method for compensating a rod position indication system for non-linearity comprises the steps of applying an excitation current to a primary of a sensor for inducing a generally linear voltage that is representative of the position of a control rod on a secondary of the sensor. The excitation current includes a first frequency which is sufficient to provide the generally linear output for the sensor. The excitation current is then modified to include a second frequency which is sufficient for providing the generally linear output when the first frequency is insufficient to provide the generally linear output.

Abstract: The length of an object, particularly a spent fuel rod, is measured by taking an optical image of a support surface and then taking an optical image of a fuel rod when placed on the support surface. The two optical images are digitised, stored and then processed to obtain a difference in grey level values between the two stored images. The two images are stored as a plurality of columns each containing pixels having a grey level value. Using an algorithm, the difference between these values in corresponding columns of the two images are determined as root mean square values. The columns are processed in turn to determine which have a root mean square value above a threshold value, these being representative of the presence of a fuel rod. The number of such columns is a measure of the fuel rod length.

Abstract: An uncoupling tool has a two-module design: one module being a driver assembly for developing the uncoupling movement and the other module being a probe assembly for verifying the uncoupled condition. The probe assembly attaches to the threaded end of the piston tube with its probe extending inside the piston tube. The driver assembly attaches to the CRD ring flange. The probe assembly detects the ring magnet in the drive piston using analog position sensors which operate on the principle of the Hall effect and solid state circuitry. A top sensor provides a signal indicating that the control rod is in its "full out" position; a bottom sensor provides a signal indicating that the control rod is uncoupled; and an intermediate sensor provides a signal indicating that the control rod is in a transition position between the "full out" and uncoupled positions. The probe incorporates spacers which focus the magnetic flux onto the sensors.

Abstract: An online system for diagnosing operability of a rotating electrical apparatus includes sensors producing electrical variables corresponding to operating conditions of the apparatus, data converters for converting the electrical variables to digital values, a comparator for comparing the values to corresponding predetermined baseline values of the apparatus and producing a corresponding comparison value, and a signalling mechanism for outputting signals related to a period of predicted operability of the apparatus whenever the comparison value exceeds a corresponding predetermined deadband value. The operating conditions may be non-electrical operating conditions, such as a condition of a lubrication system or a bearing of the apparatus. Alternatively, the sensors may sense electrical insulation non-thermal parameters during operation of the apparatus, in order to produce signals related to the operability of an insulator of the apparatus.

Abstract: A method and a device for detecting oscillations in the core of a boiling-water nuclear reactor (BWR) comprising a plurality of neutron detectors, wherein instability is detected based on oscillations in the output signals of the neutron detectors. For each one of a number of selected neutron detectors, oscillations in the output signals of the neutron detectors are detected. The oscillations are detected on the basis of an oscillation signal (SS) which indicates that an oscillation criterion is fulfilled. An alarm signal for remaining oscillations Ka is generated if the oscillation signal (SS) remains during one delay interval (T3). A first alarm signal (LR) is generated if the oscillation signal (SS) indicates that the oscillation criterion is fulfilled at least once, during each of a predetermined number of consecutive alarm intervals (T1).

Abstract: A method and a device for minimizing electrostatically enhanced deposition of charged particulates in the jet pump nozzles of operating BWR plants. The jet pump nozzle has an inner conducting surface which is electrically isolated from the main body of the nozzle. An electrical circuit is electrically coupled to the inner conducting surface of the nozzle. The electrical circuit is designed to electrically minimize charged-particle deposition at the nozzle surface exposed to a free-stream electrical potential, using a DC circuit with active element feedback to adjust the surface potential to minimize the net current to the inner conducting surface, thereby minimizing deposition.

Abstract: A method for removing a CRD with the position indicator probe in place. The method allows probe removal to be performed in a low-dose area, thereby effectively reducing the exposure received by the crew removing the probe to nearly zero. An electronic monitoring tool is provided for continuous CRD uncoupled monitoring during drive removal, using the position indicator probe to verify that the drive is uncoupled. The tool is mounted on the CRD removal equipment. The monitoring circuit is connected to selected position switches inside the position indicator probe. These switches are closed when a ring magnet on the drive piston is in proximity to the respective switch. The detected state of the switches can be used to determine whether the index tube/drive piston assembly is being extended as the CRD is lowered out of the housing. Indicator lights are activated to annunciate a coupled condition wherein the index tube is displacing relative to the piston tube as the CRD is lowered.

Abstract: A system for simultaneously testing at least two any control rod clusters contained within a reactor vessel, the system comprising a control rod drive mechanism attached to the control rod clusters for retracting the control rod clusters within said reactor vessel to a position suitable for testing. Electrical power means connected to the control rod drive mechanism for supplying electrical power to the control rod drive mechanism and for terminating the power to the control rod drive mechanism and, when terminated, causing said all said control rod clusters to fall into the reactor vessel. A rod position indicator attached to the control rod drive mechanism for monitoring the position of the control rod clusters; and computing means operatively connected to the rod position indicator and receiving a signal representing the fall time of each control rod cluster for generating an elapsed time profile of all the control rod clusters.

Abstract: The content of and hierarchical access to three levels of display pages containing information on critical function monitoring and success path monitoring.

Abstract: The use of alarm indication on the overview (IPSO) display to initiate diagnosis of challenges to critical functions or unavailability of success paths, and further alarm-based guidance toward ultimate diagnosis.

Abstract: A system for measuring water level includes a reactor pressure vessel containing a core and steam separator assembly, with the vessel being filled with water to a nominal level above the core. A reference leg contains a column of water having a reference level disposed above the nominal level, and a first variable leg has a first tap disposed in the vessel below the reference and nominal levels. A first monitor is disposed between the reference leg and the first leg for determining differential pressure therebetween to indicate level of the water in the vessel above the first tap. A second variable leg includes a second tap in the vessel below the first tap, and a second monitor is disposed between the first and second legs for determining differential pressure therebetween to indicate level of water in the vessel between the first and second taps when the water level falls below the first tap.

Abstract: The alarm activation set point and priority for a given, spatially fixed alarm tile can vary depending in part on the mode of plant operation.

Abstract: Indicating the priority of a spatially fixed, activated alarm tile on an alarm tile array by a shape coding at the tile, and preferably using the same shape coding wherever the same alarm condition is indicated elsewhere in the control room. The status of an alarm tile can change automatically or by operator acknowledgement, but tones and/or flashing cues continue to provide status information to the operator.

Abstract: Alarm acknowledgment can be made not only at the alarm tile array of a given console but via other touch sensitive alarm indications in the screen displays of the monitoring system at the same or other consoles; also, touching one tile can acknowledge multiple alarm sources.

Abstract: An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually.

Abstract: Process for carrying out an inspection or monitoring round of a nuclear site (5) consisting of recording in a central computer (22) connected to a radiofrequency transmitter/receiver or transceiver (24) a combination or sequence of different collection or reading points (12) grouping sensors (10) constituting the round to be performed. This sequence is copied again into a memory of a portable microcomputer (26) carried by the watchman during the round and connected to a radiofrequency transceiver (28). Each connection point (12) is validated and this validation is transmitted to the central computer (22). The sensors are checked and any abnormal condition is indicated to the central computer (22). All the checks carried out are recorded in the portable microcomputer (26) and copied again at the end of the round into a central computer (22) in such a way that they can be processed.