JP2022089317A - Plant earthquake impact monitoring system - Google Patents

Abstract

To provide a plant earthquake impact monitoring system that is able to easily and chronologically check a degree of impact of an earthquake on the entire plant.SOLUTION: In a nuclear power plant earthquake impact monitoring system 1 according to the present invention, concerning an impact of an earthquake on a plant parameter change in a nuclear power plant, an earthquake impact monitoring device 10 acquires an earthquake occurrence trigger signal as a system start signal, collects difference data from an initial value of a plant parameter, performs normalization, displays the impact with a cumulative number per unit time, displays the impact simultaneously with a maximum acceleration waveform as a trend graph on an indicator 20, and enables the occurrence and convergence of a plant change and a residue of anomaly, which correspond to the magnitude of the earthquake, to be checked.SELECTED DRAWING: Figure 1

Description

The present invention relates to a plant earthquake impact monitoring system capable of monitoring the impact of an earthquake on a plant when an earthquake occurs in a nuclear power plant (nuclear power plant), a chemical plant, or the like.

For nuclear power plants, the NRA's review guide on standard ground motion and seismic design policy indicates the formulation of standard seismic motion for nuclear power plants and the accompanying seismic design policy. Its basic policy is "Earthquake-resistant important facilities (of the facilities subject to design standards, those with a particularly large degree of impact on the public by radiation due to the loss of safety functions that may occur due to the occurrence of an earthquake) are in service. The safety function must not be impaired by the seismic force exerted by the acceleration caused by the earthquake, which may have a significant impact on the important seismic facilities. ].

In the examination of installation permission, it was confirmed that the design policy meets the following requirements, and the seismic importance classification of reactor facilities is based on the safety functions of facilities subject to design standards that may occur due to an earthquake. From the viewpoint of preventing loss and subsequent effects of radiation on the public, it is classified into S class, B class and C class, and seismic design is to be carried out according to each class of importance.

With regard to these S, B, and C class buildings, structures, equipment, and piping systems under the strictly defined standard ground motion, each S class facility must be able to maintain its safety function against the seismic force caused by the standard ground motion. In addition, it must withstand the seismic force of the elastic design seismic motion, whichever is greater, within the range that remains in the elastic state. Each B-class facility should withstand static seismic forces as long as it remains generally elastic. For facilities that may resonate, consider the effects. Each C-class facility should withstand static seismic forces as long as it remains generally elastic. It is said that.

In the case of major earthquakes in the past at nuclear power plants, damage included damage to ducts due to uneven ground subsidence, leakage of insulating oil, and internal flooding due to sloshing of spent fuel pools. After that, there was a case where a severe accident occurred due to the loss of all AC power supply due to the occurrence of the tsunami and the loss of the final heat sink due to the loss of the function of the reactor auxiliary cooling seawater system. From past cases, seismic motion exceeding expectations at the time of design was observed due to the characteristics of the epicenter and underground structure, but the design is elastic against the static seismic force required for equipment important for safety, and there is a safety margin. Since it was a certain design, no serious problems were seen.

In this way, the buildings, structures, equipment, and piping systems are designed to have more margin than the standard seismic motion, but if the nuclear power plant is operated or stopped and is vibrated by these earthquakes, The effects of earthquakes naturally affect not only structures and equipment, but also the fluid inside the equipment.

For example, if the vibration force due to an earthquake is applied, the flow rate, flow velocity, pressure, temperature, liquid level, and other parameters of the fluid inside the tank and piping inside the power plant will change, for example, a liquid such as a used fuel pool. In the case of a water tank with an open surface, there is a possibility that the water surface will overflow into the building due to the large undulating fluctuation (sloshing). In addition, if the equipment / piping system is damaged, the radioactive substances inside will leak out of the system, resulting in the loss of safety functions and the subsequent effects of radiation on the public. Since the seismic force also affects the internal fluid (especially liquid) in this way, if the magnitude of the earthquake is large, it is easily assumed that the effect will have a strong effect on the entire nuclear power plant.

As a known technique, the acceleration of an earthquake is measured by a seismograph installed in the reactor building and the premises of a nuclear power plant, its scale and seismic intensity are measured, data is collected, and the maximum horizontal and vertical acceleration is displayed. There is a system. However, in the conventional system, the acceleration parameters and plant parameters at the time of an earthquake are evaluated by another system. Therefore, it is difficult to make a relative evaluation between the seismic acceleration and the impact evaluation on the plant. The prior art techniques for solving these problems are as follows.

Patent Document 1 holds a seismic accelerometer installed in a nuclear power plant, a computer that processes the obtained acceleration data, a screen on the central control panel that displays the processed data, and a record displayed on this screen. In a system consisting of devices that operate, the seismic waveform, maximum acceleration, floor response spectrum, etc. are displayed on the screen to give the operator appropriate seismic information, and the equipment that requires continuous operation and meticulous inspection. An earthquake instruction system that displays the presence or absence is described.

In Patent Document 2, in the operation method of a plant having a plurality of plant component devices, signals from the device monitoring unit for monitoring the plant component devices and a seismograph are taken in to evaluate the state of each plant component device. The priority of repair according to the importance of each of the above plant components is determined from the condition evaluation and the importance evaluation result obtained from the plant-specific information stored in advance, and the loss prediction value related to the plant start calculated based on this priority. Describes the operation method of the plant in which the start timing is adjusted so that the value is equal to or less than the predetermined value.

In Patent Document 3, the process value database update unit inputs process values from a plurality of process input devices to update the process value database, and the difference value calculation unit accesses the process value database to obtain a reference plant unit. The reference difference value, which is the difference between the process value of the plant unit other than the above and the reference process value of the reference plant unit, is calculated, and the monitoring status determination unit compares the reference difference value with the difference threshold value. Describes a plant monitoring system and a plant monitoring method capable of determining whether the monitoring of the plant unit is in an abnormal state when the reference difference value is larger than the difference threshold value and whether or not the monitoring state is normal. Has been done.

Patent Document 1 displays the earthquake waveform and the like at the time of an earthquake, Patent Document 2 evaluates the state of plant component equipment from the occurrence of an earthquake, and Patent Document 3 displays process values and standards of plant units other than the reference plant unit. The reference difference value, which is the difference from the reference process value of the plant unit, is calculated, and whether or not the monitoring status is normal is determined.

Japanese Unexamined Patent Publication No. 62-169085 Japanese Unexamined Patent Publication No. 2004-227298 Japanese Unexamined Patent Publication No. 2016-012222

Generally, when an earthquake occurs, the plant parameters change according to the scale of the earthquake, and when the shaking of the earthquake ends, the parameter changes gradually converge. As it is likely to rise, the operators in the central control room are strengthening the monitoring of radiation monitors and the monitoring of leak-related parameters.

The technique described in the patent document focuses on the evaluation of the state of the plant after the occurrence of an earthquake, and is not intended to contribute to the easy understanding of the state of the plant during the occurrence of an earthquake. Generally, an alarm setting point, a design limit value, or a maximum value is used as a threshold value, but it is not easy to set all threshold values. In addition, if an alarm setting point, a design limit value, or a maximum value is used for the threshold value, there is a risk that threshold value abnormalities will occur frequently during plant shutdown.

As mentioned above, since the impact of an earthquake affects the entire plant at the same time, the number of parameters that change all at once, including large and small, is enormous, and it is difficult for operators to sequentially monitor all parameters shown in the central control room. Become. In addition, it is difficult to understand the total amount of changing parameters, and until now there has been no system that can easily monitor the degree of impact of an earthquake on a plant.

Significant effects occur during and after an earthquake, and the seismic force continues to some extent, the plant parameters change over time, and the parameters do not converge for some time after the earthquake ends. In some cases. The magnitude of the impact on the entire plant can be confirmed by monitoring by the operators of the warning system and monitoring control system, but until now there was no system that could confirm the degree of impact on the entire plant in chronological order.

An object of the present invention is to provide a plant earthquake impact monitoring system that can easily and in chronologically confirm the degree of impact of an earthquake on the entire plant.

The present invention includes an earthquake impact monitoring device that connects to a plant control system and an earthquake observation device, and calculates and creates data for seismic impact evaluation based on plant parameters that represent the state of the plant, and the seismic impact monitoring device. The seismic impact monitoring device includes an input / output means for inputting and outputting data to be connected and a display means for displaying data connected to the seismic impact monitoring device, and the seismic impact monitoring device is an earthquake generation signal transmitted by the seismic observation device. A data sampling unit that acquires data on the plant parameters before and after the earthquake from the control system, a data processing unit that calculates the integrated value of changes in the plant parameters before and after the earthquake in real time, and a data processing unit when an earthquake occurs. It is a plant earthquake impact monitoring system characterized by comprising a data aggregation unit for creating seismic impact evaluation data to be displayed on the display means, including a trend graph of the change amount integrated value from the end to the end.

In the plant earthquake impact monitoring system according to the present invention, the earthquake impact monitoring device divides the plant parameters into radiation monitor data and other data, and the radiation monitor data is the difference between the radiation monitor data before and after the occurrence of the earthquake. Is divided by the full-scale value of the radiation monitor, expressed as a percentage, and the difference normalization processing data is calculated. For the data other than the radiation monitor data, the absolute value of the difference between the data before and after the earthquake is measured. It is characterized by dividing by the full-scale value of the measuring instrument, expressing it as a percentage, calculating the difference normalization processing data, and integrating only the difference normalization processing data exceeding 0 to calculate the change amount integrated value. ..

In the plant earthquake impact monitoring system according to the present invention, the earthquake impact monitoring device divides the plant parameters into a plurality of categories according to the importance to the plant, and calculates the integrated value of changes in the plant parameters before and after the occurrence of an earthquake. It is characterized in that it is calculated for each category and the display means displays the trend graph of the integrated value of the amount of change for each category.

In the plant earthquake impact monitoring system according to the present invention, the earthquake impact monitoring device causes at least the display means to display a trend graph of the integrated value of the amount of change from the time of the occurrence of the earthquake to the end of the earthquake together with the seismic acceleration data. It is characterized by.

According to the present invention, it is possible to provide a plant earthquake impact monitoring system that can easily and in chronologically confirm the degree of impact of an earthquake on the entire plant.

It is a system block diagram of the plant earthquake influence monitoring system 1 of this invention. It is explanatory drawing of the data processing carried out by the seismic influence monitoring apparatus 10 of the plant seismic influence monitoring system 1 of this invention. This is a display example of the display 20 of the plant earthquake impact monitoring system 1 of the present invention. It is a database output result of the plant earthquake influence monitoring system 1 of this invention. It is a flow chart which shows the data processing procedure of the plant earthquake influence monitoring system 1 of this invention.

FIG. 1 is a system configuration diagram of the plant earthquake impact monitoring system 1 of the present invention. The system configuration will be described with reference to FIG. The plant earthquake impact monitoring system (hereinafter, may be referred to as this monitoring system) 1 shown in FIG. 1 is a system for monitoring the impact of an earthquake at a nuclear power plant.

This monitoring system 1 is connected to a control measurement system 100 and an earthquake observation system 200 of a nuclear power plant via a network device, and is an earthquake impact monitoring device 10 for evaluating the impact of an earthquake based on plant parameters, and an earthquake impact monitoring device 10. It includes a display 20 for displaying data and an input / output device 30 for inputting / outputting data.

Plant parameters are variables that represent the state of the plant, including process data consisting of physical quantities such as flow rate, temperature, pressure, differential pressure, and radiation amount, ON / OFF signals, alarms, pumps, fan start / stop, and valves. Variables that represent the state of equipment such as opening and closing, leakage of plant equipment, damage to the nuclear fuel placed in the used fuel pool and core, damage to the reactor pressure vessel including leakage from the reactor main steam piping, reactor storage Includes data and variables that represent leaks to the vessel and increased radiation levels within the reactor facility. Hereinafter, plant parameters may be referred to as parameters.

The earthquake impact monitoring device 10 includes a system start signal processing unit 11, a data sampling unit 12, a data processing unit 13, a data aggregation unit 14, and a measuring instrument full-scale database 15, and operates a control measurement system 100 of a nuclear power plant. Digital / analog data which is plant side data from the monitoring computer 125, maximum seismic acceleration waveform data input for safety confirmation from the seismic observation device 210 of the seismic observation system 200, and an earthquake occurrence trigger signal are input data / input signals.

The seismic impact monitoring device 10 is connected to the control and measurement system 100 of the nuclear power plant and the seismic observation system 200 via a network device, and the operation monitoring computer 125 of the seismic impact monitoring device 10 and the control and measurement system 100 of the nuclear power plant. A data gateway may be provided between the seismic impact monitoring device 10 and the seismic observation device 210 of the seismic observation system 200.

The control measurement system 100 of a nuclear power plant includes a plant measuring instrument transmitter 110, an input / output device 115, a digital controller 120, an operation monitoring computer 125, and an operation monitoring flat display display 130. The analog signal of the plant measuring instrument transmitter 110 at the site of the nuclear plant is AD-converted by the input / output device 115 and output to the operation monitoring flat display 130 in the nuclear plant control console as an output from the digital controller 120. , Used for monitoring by operators. The digital signal is also input to the operation monitoring computer 125, and the measured value, the calculated value, and the device status digital signal are output to the operation monitoring flat display display 130.

The seismic observation system 200 includes a seismic observation device 210, a building seismometer 220 arranged from the basement floor to the upper floor of the reactor building, a ground seismometer 230 installed on the reactor building ground, and a site surface. It also has a site-based seismometer 240 located underground. The seismic observation device 210 is separated from the control measurement system 100 of the nuclear power plant, and seismic measurement is performed by these dedicated systems.

The seismic observation device 210 transmits an earthquake occurrence trigger signal when a plurality of seismographs having an acceleration of about 1 gal or less detect it. The earthquake occurrence trigger signal is an activation signal of the monitoring system 1. After transmitting the earthquake occurrence trigger signal, the seismic observation device 210 issues an alarm to the central control room, collects seismic data, calculates the seismic intensity, and measures the maximum acceleration in the horizontal and vertical directions. The collected data is filed and saved as data.

The earthquake impact monitoring device 10 has a CPU (central processing unit) and a ROM (read only memory), reads an operating system OS from the ROM, expands the operating system OS on the main memory unit, starts the OS, and manages the OS. The application software program (processing module) is read from the ROM, and the GUI (Graphical User Interface) function and various processes are executed. Further, a command input is performed by connecting to an input / output device 30 such as a display 20, a key device, and a mouse.

Since the seismic impact monitoring device 10 handles all plant data in real time and therefore has a large load, it may adopt a multi-CPU compatible with multi-threads or may have an array structure of a plurality of PC units.

The processing and operation of the processing unit of the earthquake impact monitoring device 10 will be described.

The system start signal processing unit 11 is responsible for receiving the earthquake occurrence trigger signal emitted from the seismic observation device 210, inputting the maximum seismic acceleration waveform data for safety confirmation, and processing the start signal of the device.

At the same time as receiving the earthquake occurrence trigger signal, the data sampling unit 12 requests the operation monitoring computer 125 for all analog data and digital data as plant parameters one minute before the earthquake occurrence, and reads them into the data sampling unit database. Start and download as the initial value before the earthquake. The pre-earthquake initial value data downloaded here is used as A data.

Further, after downloading the A data, the data sampling unit 12 takes in the data of the operation monitoring computer 125 as a plant parameter after the occurrence of an earthquake, for example, in a sampling cycle of every second, and sequentially divides the data into X, Y, and Z. Download to the database. Here, the data downloaded in real time is referred to as B data. The X, Y, and Z categories will be described later. Further, the full-scale value of the parameter sampled from the measuring instrument full-scale database 15 is called and used as the data of the difference normalization process.

The data processing unit 13 performs the following data processing according to the classification. FIG. 2 is an explanatory diagram of data processing. The data processing unit 13 performs differential normalization processing of analog data and digital data received from the operation monitoring computer 125. These analog data and digital data are displayed on the operation monitoring flat display display 130 so that the operator can monitor the data.

The analog data is digital, in which an electric signal transmitted from the on-site plant measuring instrument transmitter 110 due to a current or voltage change is digitized by the input / output device 115 and input to the operation monitoring computer 125 via the digital controller 120. It is digitalized process data.

The digital data is a digital signal represented by ON / OFF, such as an alarm alarm ON / OFF signal, a device start / stop signal, and a valve fully open / fully closed signal. In addition, it refers to data that has been digitized by performing calculations based on analog signals.

The difference normalization processing of analog data (analog signal) and digital data (digital signal) will be described. In general, nuclear power plants are operated at rated output operation, and there is no change in output with time, and some parameters change slowly, but most of them are almost constant. Therefore, it is easy to understand the fluctuation by comparing the process data after the earthquake with the initial value data. The initial value data is process data before the occurrence of an earthquake, for example, process data one minute before the occurrence of an earthquake and A data.

After the earthquake, the parameter values fluctuate. The parameter value changes in the increasing or decreasing direction when it increases or decreases periodically due to the vibration force caused by the earthquake or when the interlock operates. The process data fluctuation values of all the parameters are real-time process data and B data after the occurrence of an earthquake. The fluctuating parameter (process data) is represented by the difference between BA, but by making the fluctuating value an absolute value, it is considered that the transient change continues even if it swings in the positive or negative direction. .. The fluctuation value is represented by | (BA) |, which is the absolute value of the difference.

Next, in order to normalize this fluctuation value, the fluctuation value is normalized to a percentage using the measurement range (full scale) of the parameter stored in the measuring instrument full-scale database 15. Specifically, if the lower limit of the measurement range is 0 and the upper limit is 1000, the full scale is upper limit-lower limit = 1000-0 = 1000. This full-scale value is used as C data, and the fluctuation value | (BA) | is divided by C data, which is expressed as a percentage and used as the difference normalization processing data. Round down to the nearest whole number.

The difference normalization processing of analog data and digital data is performed after classifying the signal group into X, Y, and Z categories. In the seismic design of reactor facilities, seismic importance classifications consisting of S class, B class and C class are used, but this monitoring system adopts a different classification. The data / signals of the X / Y / Z divisions are as follows.

The X-classified data (X-classified signal) refers to analog data other than radiation and leakage-related parameters in order to detect damage to equipment and leakage from piping. The X-classified signal is a set of analog data signals other than the Z-classified signal, which is important in the later earthquake, and is the conductivity, density, dew point, differential pressure, flow rate, and liquid of the analog signal system (other than radiation and leakage-related parameters). It refers to a group of signals represented by position, humidity, neutron flux, concentration, pressure, valve position, temperature, time, vibration, temperature difference, mass, current, potential difference, frequency, power, ineffective power, etc.

The Y-classified data (Y-classified signal) is a set of signals related to plant alarms and equipment operations, and is a signal group for signals that have reached or malfunctioned when the alarm was reached due to the occurrence of an earthquake or when the installed value was reached. It represents, and corresponds to alarm issuance of digital signal system (ON, OFF signal), pump, fan start / stop, valve opening / closing, etc.

The Z classification data (Z classification signal) is a reactor pressure vessel that includes leakage of plant equipment, damage to the used fuel pool and nuclear fuel located in the core, and leakage from the reactor main steam piping to the nuclear plant. It refers to important parameters related to damage to the reactor, leakage to the reactor containment vessel, and increased radiation levels in the reactor facility. Specifically, area process radiation dose, reactor containment vessel (drywell temperature, pressure, dew point, sump water level), main steam system (main steam pressure, main steam pipe temperature, main steam radioactivity, main steam flow rate, main Steam relief valve operation signal, main steam relief valve exhaust pipe temperature), reactor (reactor water level, reactor pressure), building leak system (each building floor leak detector operation, high conductivity drain sump start signal, used fuel Pool, fuel pool water level, water recovery device water level, water recovery device vacuum, etc.).

The Z-division data is a signal group in which an analog signal and a digital signal are mixed, and refers to the data related to the above-mentioned release of radioactive substances from the system and the data indicating damage to important equipment.

In the X division, the calculation of the difference normalization process is performed on the B data in real time by the above procedure. If the calculated value exceeds 0, the calculated value is output to the next process, and if it is 0, it is not output.

Similarly, in the Y division, the difference normalization process is calculated for the B data in real time according to the above procedure. The B data in the Y category is an ON / OFF signal, where the ON value is 1 and the OFF value is 0. The C data, which is a full-scale value, is 1. When the signal changes from ON to OFF or from OFF to ON before and after the occurrence of an earthquake, the calculated value becomes 100. If the calculated value is 100, the calculated value 100 is output to the next process, and if it is 0, the calculated value is not output.

In the Z division, the calculation method is changed between the radiation monitor and others. There is no problem if the radiation monitor value is smaller than the initial value. However, if it falls below the lower limit of the full scale, an alarm will be issued and it will be considered as a failure.

For analog data other than the radiation monitor, the difference normalization processing operation is performed in the same manner as the X division analog data processing. If this value exceeds 0, the calculated value is output to the next process, and if it is 0, it is not output. For digital data other than the radiation monitor, the difference normalization processing operation is performed in the same manner as in the Y division digital data processing. If this value is 100, the calculated value 100 is output to the next process, and if it is 0, it is not output.

For radiation monitor data (analog data), instead of the fluctuation value | (BA) |, the difference (BA) is divided by the C data, the difference normalization processing is performed, and this is expressed as a percentage and the difference normalization is performed. It is used as processing data. If the difference normalization processing data exceeds 0, the calculated value is output to the next processing, and if it is 0 or less, it is not output. This is because there is no problem with the radiation monitor value in the direction of being smaller than the initial value.

The absolute value of the difference between the B data and the A data is calculated in each category | (BA) |, but if the plant parameters fluctuate to the plus side and the minus side with respect to the initial value, this fluctuation is the earthquake. This is because it is considered to be fluctuation due to the excitation force, and it is considered to output as fluctuation except for the radiation monitor data.

The output difference normalization processing data (calculated value) of each division is aggregated for each division, and is output to the data aggregation unit 14 as an integrated value (change amount integrated value) for each unit time.

The data aggregation unit 14 includes a trend graph of the change amount integrated value from the time of the occurrence of the earthquake to the end based on the accumulated value (change amount integrated value) per unit time for each category calculated by the data processing unit 13. The seismic impact evaluation data is created and output to the display 20.

FIG. 3 is a display example of seismic impact evaluation data created by the data aggregation unit 14 and output to the display 20. In the cumulative trend graph of data, the horizontal axis is the elapsed time (SEC) with the earthquake occurrence trigger transmission time as 0, and the vertical axis is the total number of fluctuation data influences on the logarithmic scale. The cumulative value (change amount integrated value) of the conversion processing data is shown in a graph. The upper limit of the logarithmic scale on the vertical axis may be, for example, a value obtained by multiplying the total number of data of the operation monitoring computer 125 by 100. As for the elapsed time on the horizontal axis, when the data is displayed to the right edge of the screen to record the trend, the screen is scrolled and data collection is continued. A scroll button is provided at the bottom of the horizontal axis of the screen to reduce the scroll screen.

In FIG. 3, the order of the X, Y, and Z divisions is in order from the top because it is less susceptible to the influence of the earthquake in the order of X → Y → Z division. The X category is susceptible even if the magnitude of the earthquake is small. The Y category is an alarm or interlock that operates when the set value is reached after receiving a certain amount of fluctuation, and is affected by an earthquake larger than the X category. Equipment that ranks higher in the safety importance system or seismic importance classification belongs to the Z category, which has a significant impact on the plant, but is less susceptible to earthquakes than the X category and Y category.

The operator can see that the data of the X division fluctuates first due to the influence of the earthquake, and the size of the whole mountain becomes smaller by converging, and the influence on the plant is visually mitigated. On the contrary, it can be easily seen that the numerical values of the Y category and the X category increase with the progress of time, and the influence on the plant increases after the earthquake.

In the display example of the display 20 of FIG. 3, ON / OFF signals for starting and stopping the earthquake occurrence trigger are displayed at the lower part of the cumulative trend graph, and represents the time during which the acceleration of 1 gal or more of the trigger generation continues. .. By displaying the integrated value of the parameter change amount and the occurrence of the earthquake at the same time, it is easy to visually grasp when the change occurred.

In addition, the horizontal waveform and vertical waveform of the maximum acceleration for safety confirmation are displayed at the bottom, and the magnitude of the amplitude is made easy to understand visually by drawing. In the upper right part, the date and time of the earthquake, the maximum value of the horizontal component, the maximum value of the vertical component, the seismic intensity, and the number of earthquakes that have triggered from the first occurrence are displayed, and the earthquake data summary is displayed to the operator.

In addition, as a menu bar, earthquake occurrence trigger display, data record display, recording stop button, data storage 1 button, data storage 2 button, data storage 3 button, X division total number MAX value button, Y division total number MAX value button, Z division total number MAX A value button and a MAX value button for the total number of batch divisions are provided.

The display during the occurrence of the earthquake trigger shall be displayed while the ON signal of the earthquake occurrence trigger is being received. The display during data recording also displays the ON signal of the earthquake occurrence trigger during reception, and notifies the operator that data is being collected.

The recording stop button is provided to stop the data collection operation, but the recording is interlocked so that the recording is not stopped unless the earthquake occurrence trigger OFF signal is generated by the interlock.

For the data storage buttons 1 to 3, the filed past data collection record is reloaded and displayed on the screen. The latest data is set to 1, and as it becomes past, it is set to 2 or 3. Although the data storage buttons are set to 1 to 3 in FIG. 3, a command button for reloading past data may be provided.

The total number of X to Z division MAX value buttons are the division, parameter name, initial value data A, plus fluctuation MAX data B, plus fluctuation MAX data recording time, minus fluctuation MAX data B, and minus fluctuation MAX data recording as shown in FIG. A data sheet recording the time and the time of the earthquake occurrence trigger is output on a separate screen, and the impact of the earthquake on the plant is evaluated. The batch division total number MAX value button organizes the changes in these X, Y, and Z divisions in chronological order and outputs all the data.

In this way, it can be used for evaluation of plant parameter changes from the occurrence of an earthquake to the end of the earthquake, and also after the end of the earthquake, enabling rapid monitoring and evaluation.

FIG. 5 is a data processing flow diagram of the monitoring system 1. The operation of the monitoring system 1 will be described with reference to FIG.

When an earthquake occurs, the earthquake observation device 210 transmits an earthquake occurrence trigger signal. When the system start signal processing unit 11 receives the earthquake occurrence trigger signal (step S1), the system start signal processing unit 11 issues a system start signal (step S2). As a result, the data sampling unit 12 samples all the data one minute before from the operation monitoring computer 125, and starts downloading the real-time data database (step S3). Subsequently, the data processing unit 13 performs differential normalization / accumulation processing of real-time data for each of the X, Y, and Z categories (step S4), and the data aggregation unit 14 performs the aggregated data in a predetermined format for each unit time. Is displayed on the display 20 (step S5).

Further, the data aggregation unit 14 receives the maximum seismic acceleration horizontal / vertical waveform data for security confirmation and the seismic occurrence trigger start / stop signal (step S6) and displays them on the display 20 (step S5). Further, the data is stored in the storage device (step S7).

Data is recorded and collected even after receiving the earthquake occurrence trigger transmission stop signal (step S8), but data collection is terminated when the recording stop signal is input from the recording stop button (step S9). However, while the earthquake occurrence trigger signal is being received, the manual recording of data collection will not be stopped manually. The recorded data is converted into a file and stored in a disk array device or the like (step S10). When the earthquake occurrence trigger signal is retransmitted (step S11), the process returns to step S3 and the process of step S3 to step S10 is repeated.

As described above, the plant earthquake impact monitoring system according to the present invention aggregates plant parameters by using an earthquake detection means installed in a plant such as a nuclear power plant as a trigger (earthquake occurrence trigger) when an earthquake is detected. For example, process data one minute before the occurrence of an earthquake is acquired from the operation monitoring computer 125, and using this as reference data, real-time process data acquired from the operation monitoring computer 125 is differentially normalized and terminated from the time of the earthquake. Since the total number (magnitude) of the changed parameters up to is accumulated and displayed in time series per unit time, the influence of the plant on the earthquake can be easily grasped.

The plant seismic impact monitoring system according to the present invention classifies plant parameters into X, Y, and Z according to the importance of damage to plant equipment and radiation release, and thereby, the importance to the above-mentioned reference ground motion. Regardless of the S, B, and C classifications, it is possible to identify the device in which the abnormality has occurred. The accumulated data can be clearly understood by displaying the earthquake occurrence trigger ON / OFF signal, the earthquake waveform of the maximum acceleration data, and the cumulative diagram of the X / Y / Z division data at the same time.

It is thought that the changes in the parameters gradually converge to the data before the occurrence of the earthquake due to the end of the earthquake, but if the parameters that are changing remain even after the end of the earthquake, it is suggested that some abnormality continues. The operator can pay attention to the changed parameters and immediately grasp the abnormality of the plant.

The plant earthquake impact monitoring system according to the present invention is configured to be able to function not only during plant operation but also during plant shutdown. While the plant is shut down, there is a system with no internal fluid due to the isolation of the system by work, so the parameter value is different from the parameter value during operation, but the data 1 minute before the earthquake is used as the reference data, and then It works even when the plant is down to see the relative changes in the parameters of. By draining the isolated water from the equipment, the system in the state where no fluid exists inside has no internal hydrostatic pressure load, and the influence on the vibration force due to the earthquake is reduced.

Even if the parameter power is not supplied due to maintenance work or the value is incorrect due to drainage while the plant is stopped, there is no effect because the relative evaluation is performed using the reference data and the fluctuation value. Of course, the parameters that are shared even when the plant is stopped are determined in the same way as the parameters during operation. Since earthquakes may occur not only at the first earthquake but also continuously, it is possible to grasp the final changes in plant parameters by retaining and evaluating the data before the first earthquake.

The plant earthquake impact monitoring system according to the present invention has been described above with the system for monitoring the earthquake impact in a nuclear power plant as an embodiment, but the plant earthquake impact monitoring system according to the present invention is limited to the above embodiment. It is not a thing and can be changed without departing from the gist of the present invention.

For example, in the above embodiment, the process data 1 minute before the occurrence of the earthquake is used as the A data, but the average value of the process data for 10 minutes or 30 minutes before the occurrence of the earthquake may be used as the A data.

Although this system is a stand-alone type system, an appropriate data gateway may be provided to capture the seismic data of the seismic observation device into the operation monitoring computer and use it as application software for the operation monitoring computer.

The plant seismic impact monitoring system according to the present invention is not limited to nuclear power plants, but can also be applied to thermal power plants, chemical plants, and other plants equipped with seismometers, which are also equipment industries. When the plant earthquake impact monitoring system according to the present invention is applied to a thermal power plant, a chemical plant, or the like, the contents of the X, Y, and Z categories shown in the above embodiment may be changed according to the actual conditions of the plant. Further, the number of divisions may be divided into 2 divisions and 4 divisions according to the actual condition of the plant.

Although preferred embodiments have been described with reference to the drawings, one of ordinary skill in the art will readily assume various changes and modifications within the obvious scope of this specification. Therefore, such changes and amendments are construed as being within the scope of the invention as defined by the claims.

1 Plant earthquake impact monitoring system 10 Earthquake impact monitoring device 11 System startup signal processing unit 12 Data sampling unit 13 Data processing unit 14 Data aggregation unit 15 Measuring instrument Full-scale database 20 Display 30 Input / output device 100 Nuclear power plant control measurement system 210 Seismic observation device

Claims (4)

An earthquake impact monitoring device that connects to the plant control system and seismic observation device and calculates and creates data for seismic impact assessment based on the plant parameters that represent the state of the plant.
An input / output means for inputting / outputting data, which is connected to the earthquake impact monitoring device,
A display means for displaying data, which is connected to the earthquake impact monitoring device,
Including
The earthquake impact monitoring device is
A data sampling unit that acquires data on the plant parameters before and after the occurrence of an earthquake from the control system using an earthquake occurrence signal transmitted by the seismic observation device as a trigger.
A data processing unit that calculates the integrated value of changes in the plant parameters before and after the earthquake in real time.
A data aggregation unit that creates earthquake impact evaluation data to be displayed on the display means, including a trend graph of the integrated value of the amount of change from the time of the occurrence of the earthquake to the end of the earthquake.
A plant seismic impact monitoring system characterized by being equipped with. The seismic impact monitoring device divides the plant parameters into radiation monitoring data and other data.
For radiation monitor data, the difference between the radiation monitor data before and after the earthquake is divided by the full-scale value of the radiation monitor, expressed as a percentage, and the difference normalization processing data is calculated.
For data other than the radiation monitor data, divide the absolute value of the difference between the data before and after the earthquake by the full-scale value of the measuring instrument that measures each data, express it as a percentage, and calculate the difference normalization processing data.
The plant earthquake impact monitoring system according to claim 1, wherein only the difference normalization processing data exceeding 0 is integrated and the change amount integrated value is calculated. The earthquake impact monitoring device divides the plant parameters into a plurality of categories according to the importance to the plant, and calculates the integrated value of changes in the plant parameters before and after the occurrence of an earthquake for each category.
The plant earthquake impact monitoring system according to claim 1 or 2, wherein the display means displays the trend graph of the integrated value of the amount of change for each category. Any of claims 1 to 3, wherein the seismic impact monitoring device causes at least the display means to display a trend graph of the integrated value of the amount of change from the time of occurrence of the earthquake to the end of the earthquake together with seismic acceleration data. The plant earthquake impact monitoring system described in Section 1.

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