JPH05172983A - Inspection work administration system for nuclear power plant - Google Patents

Abstract

PURPOSE:To reduce the load of administration work in inspection works in a nuclear power plant and raise the safety and intactness during inspection and safety of an operator. CONSTITUTION:This system is provided with an inspection plan work file 3 to preserve the work plan for inspection, an inspection work recording part 6 to record the present status of the on-going inspection works, a simulator 7 to presume the plant change as the result of the planned inspection works, and a work evaluation part 1 to evaluate the practicability of the planned inspection works by evaluating the presumed result of the simulator 7 based on a evaluation basis, also a work execution/surveillance part 4 to output an operation command to order workers an operation for the work evaluated to be practicable by the work evaluation part 1 and to output an automatic operation command to the plant for direct operation and simultaneously, monitor the plant status continuously and execute the corresponding operation in case of unsatisfactory evaluation result, a data base for evaluation 2 to record the evaluation basis used in the work evaluation part 1 and the work execution/surveillance part 4, and a man-machine interface 5 to input the direction of the inspection work, plant status, output of the inspection work status and the inspection plan works.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a regular inspection work management system for a nuclear power plant in which various operations of periodic inspections (hereinafter referred to as regular inspections) performed in the nuclear power plant are managed by a computer.

[0002]

2. Description of the Related Art Normally, a nuclear power plant, for example, a boiling water type (BWR) nuclear power plant, is operated in a cycle of plant start after regular inspection → normal operation → plant stop → constant inspection.

This inspection will prevent the accidental failure and expansion of electric facilities used for power generation such as nuclear reactors and their ancillary facilities, steam turbine facilities, etc. so as not to significantly hinder the supply of electricity. In order to do so, it is an inspection that is regularly performed, and it is legally obliged to implement it.

During this regular inspection, the plant state changes greatly as shown in the regular inspection main process diagram of FIG. For example, the reactor water level first rises when the fuel in the reactor pressure vessel (RPV) is taken out of the reactor. In other words, first raise the reactor water level, and then
This is a case where the fuel pool is connected to a fuel pool adjacent to it by a water channel to transfer the fuel from the reactor pressure vessel to the fuel pool.
The reactor water level is maintained until the fuel transfer is completed.

On the contrary, when the reactor pressure vessel is capped, it is necessary to lower the reactor water level. Further, in the high pressure test of the reactor pressure vessel, the reactor water level is raised to fill the pressure vessel with the reactor water. Then, after the containment vessel (RCV) returns to the original state, it returns to the normal water level.

In order to measure the water level during such a regular inspection, a water level meter dedicated to the regular inspection is prepared, and the water level control is carried out by the fuel storage pool cooling and purification system.

The reason why such a complicated process is required is
This is because it is necessary to remove the upper lid of the containment vessel and the reactor pressure vessel and replace the fuel in the reactor pressure vessel. Equipment disassembly inspections, replacements, and repairs are carried out along this main process. At this point, it is important to ensure plant safety and soundness.

Here, ensuring the safety of the plant relates to fuel. That is, the fuel at the time of regular inspection is in a subcritical state, but since decay heat is generated, it must be surely cooled.

In addition, since the control rod is inserted at the time of regular inspection to maintain its subcriticality, it is necessary to be careful not to break it. Also, ensuring soundness is not as big a rule as ensuring safety, but it is to prevent deterioration of equipment by maintaining good plant conditions such as water management. Since the purpose of the regular inspection is to enhance the soundness of the plant through the repair and inspection of the equipment, it is natural to operate it so as to hold it as the entire plant. In addition to these, ensuring safety for workers is also an important factor.
It is necessary to take care so that workers do not suffer electric shock or water damage during work.

In FIG. 3, CR is a control rod, LPRM is a local output monitor system, RHR is a residual heat removal system, and LPCI.
Indicates the low-pressure water injection system, respectively.

In summary, at the time of regular inspection, it is necessary to maintain the safety and soundness of the plant and ensure the safety of the workers while carrying out various operations such as division inspection and repair of the equipment.

For this reason, conventionally, the feasibility of scheduled scheduled inspection work is evaluated by comprehensively judging the functions of the entire plant including other repair work scheduled by the engineer. ..

Then, when the engineer determines that the regular inspection work can be executed, the work sheet and procedure manual of the regular inspection work are issued.

The work sheet specifies the device to be operated and its period, which means that while the work to be carried out is being carried out, the device is changed to a different state for other work. This is to prevent it from happening.

On the other hand, if there is a plant parameter that requires special attention in the procedure manual, the plant parameter is clearly stated to call attention. The worker performs the work while monitoring the plant parameters according to this procedure manual. If a problem occurs during work, the operator can take appropriate action according to his judgment.

As described above, the management of the conventional regular inspection work is basically left to the human resources of the engineer who issues the work permit and the worker who works based on this.

[0017]

However, since the management of such conventional regular inspection work is left to an engineer, a worker, etc., when both the engineer and the worker are excellent human resources, Although the problem does not become apparent, there are many items to be considered in regular inspections, and unless systematic management is performed by making maximum use of plant information, the burden on humans becomes very large.

Therefore, the present invention has been made in consideration of such circumstances, and its purpose is to reduce the burden of labor by computerizing the management of regular inspection work, and to increase the safety of both work and plant. It is to provide a regular inspection work management system for a nuclear power plant.

[0019]

According to the present invention, a computer is used to manage the regular inspection work of a BWR nuclear power plant, and is configured as follows.

That is, according to the present invention, a scheduled inspection scheduled work storage section for storing a work plan at the time of scheduled inspection, a scheduled inspection work recording section for recording the state of the currently performed regular inspection work, and a nuclear power plant Estimate the change in the plant state when the scheduled work saved in the scheduled inspection scheduled work storage unit is performed based on the plant information and the information indicating the state of the regular inspection work currently being performed from the scheduled inspection work recording unit A simulator to
When performing the required regular inspection work stored in the scheduled inspection scheduled work storage unit, whether or not the work can be executed,
A work evaluation unit that evaluates the estimation result from the simulator according to an evaluation criterion, and a manual operation command that guides an operation that should be manually operated by the operator for the work evaluated as executable by the work evaluation unit. While outputting, while outputting and executing an automatic operation command for automatically operating the plant, continue to evaluate the plant state by monitoring the plant state at this time, when this evaluation does not reach the evaluation criteria A work execution / monitoring unit that executes a corresponding operation satisfying the evaluation criteria, an evaluation database that stores the evaluation criteria used by the work evaluation unit and the work execution / monitoring unit, and the work execution / monitoring unit While receiving and displaying the manual operation command and the plant state evaluation result from the above, and the information indicating the work state from the above-mentioned regular inspection work recording unit, Characterized in that it has a man-machine interface that allowed to enter the work.

[0021]

[Operation] The simulator executes the scheduled work saved in the scheduled inspection scheduled work storage unit based on the plant information and the information indicating the state of the currently performed regular inspection work recorded in the scheduled inspection work recording unit. Estimate the change in the plant state at.

The work evaluation unit evaluates the estimation result according to the evaluation standard to evaluate whether or not the work to be performed is executable.

If it is evaluated as executable, the work execution / monitoring section gives a manual operation procedure to the man-machine interface to display a guide, and also gives an automatic operation signal to the plant to directly and automatically perform the operation. Manipulate. Moreover, the latest plant state at this time is evaluated, and when this evaluation does not reach the evaluation standard, the corresponding operation is obtained and further executed.

Since a guide for the manual operation procedure is displayed on the man-machine interface, the worker performs the manual operation based on this display.

Therefore, according to the present invention, by taking into consideration the plant state and other regular inspection work states being performed, the safety and soundness of the plant and the safety of the workers are ensured, and the regular inspection work is performed. Can direct and perform work.

Moreover, the monitoring of the plant state during the regular inspection work is continued, and when an unplanned situation occurs, the corresponding operation for ensuring the safety and soundness of the plant is instructed and executed. Therefore, it is possible to secure the safety and soundness of the plant by reducing the labor of manpower, and at the same time, it is possible to secure the safety of the worker.

[0027]

Embodiments of the present invention will be described below with reference to the drawings.

FIG. 1 is an overall configuration diagram of an embodiment of the present invention. In FIG. 1, a regular inspection work management system for a nuclear power plant is a work evaluation unit 1, an evaluation database 2, a scheduled inspection work file 3, work execution / It is composed of a monitoring unit 4, a man-machine interface 5, a regular inspection work recording unit 6, and a simulator 7.

The work evaluation unit 1 selects the required regular inspection work recorded in the scheduled inspection scheduled work file 3 for storing the work plan at the time of regular inspection, and the work which has not been executed yet and has been executed.
The soundness and safety of the plant 8 and whether or not they are against the safety of workers are evaluated according to the evaluation criteria recorded in the evaluation database 2.

At this time, the plant state is grasped from the plant information from the nuclear power plant and the information indicating the current regular inspection work state recorded in the regular inspection work recording unit 6, and the plant is about to be implemented. The change in the plant state when the work is performed is estimated by the simulator 7, and the estimation result is evaluated based on the function evaluation method recorded in the evaluation database 2 to satisfy the safety and soundness of the plant. Confirm that the work can ensure the safety of personnel.

At this time, in order to satisfy these functions, operations are added or changed as necessary. A series of operation procedures obtained as a result is given to the work execution / monitoring unit 4.

The operation execution / monitoring section 4 sequentially executes the operation procedure. If it can be operated automatically, the operation command is directly given to the plant 8 to operate it. If manual operation is required, the man-machine interface 5 is used. The operation command is output together with the guide such as the operation procedure.

At this time, the latest plant state is grasped from the latest plant data obtained from the plant 8 and the latest regular inspection work recorded in the regular inspection work recording unit 6, and the function to be taken into consideration in the evaluation database 2 It is confirmed whether or not is realized, and if these are not realized, the corresponding operation required for realizing is executed.

The work performed by the work executing / monitoring unit 4 is recorded in the regular inspection work recording unit 6, and when the work is completed, the corresponding work in the scheduled inspection scheduled work file 3 is marked as completed.

From the man-machine interface 5, write the operating procedure of the scheduled inspection work in the scheduled inspection scheduled work file 3,
It can be referenced and modified. Further, the plant status, regular inspection work status, and satisfaction status of the evaluation function can be displayed.

By the way, the evaluation database 2 is a database for recording the evaluation contents carried out or possessed by an engineer, a worker or the like for a computer, and is the most important one.

The contents of this evaluation will be described below.

It is necessary to incorporate into the computer the items to be considered in carrying out the work at the time of regular inspection, and to realize the same or more judgments that the engineer (human) has been carrying out. For this purpose, the matters considered during the regular inspection are investigated, and as shown in FIG. 2, the functions to be maintained as a plant during the regular inspection are expressed hierarchically.

The plant safety maintenance function is composed of a fuel cooling function and a criticality prevention function, and the fuel cooling function is expanded to the core cooling and feed water functions. The purpose of the core cooling function is to remove the decay heat of the fuel, and it consists of the current core cooling function, preliminary core cooling function, and measurement function.

The current core cooling function evaluates whether or not it has a sufficient cooling capacity for decay heat. The cooling capacity is evaluated from the reactor water temperature / system flow rate and the secondary side temperature and flow rate. The flow rate is evaluated from the flow path resistance determined by the pump capacity and valve opening. This function is a residual heat removal system (RH
R).

The reactor water level is high and the reactor pressure vessel (RP
V) and the fuel pool are connected by a waterway, the reactor water volume is 10 times, so the temperature rise is extremely slow even if the cooling capacity is insufficient. Therefore, depending on the temperature and reactor water level, the cooling capacity may be insufficient. Allow for a certain period.

The preliminary core cooling function is a function for backing up the current core cooling function in the event of a trip. The system for preliminary core cooling is usually a residual heat removal system (RHR), but if this is not available, then there should be a mechanism for water injection and drainage into the reactor pressure vessel.

As an example of using a regular system as the injection system, condensate storage tank → condensate transfer pump → emergency core cooling system piping → reactor pressure vessel path or control rod drive system, and further boric acid water injection system test The route of tank → injection pump → reactor pressure vessel is considered.

An example of using an emergency core cooling system is R
Water injection from the HR and core spray systems into the core is considered. At this time, the flow rate can be adjusted by opening and closing the test valve.

On the other hand, as an example of using the regular system, the drainage system is drained to the main condenser through the reactor cleaning system and to the condensate storage tank through the fuel pool makeup water system. As an example of using an emergency core cooling system (ECC), discharge from the recirculation pump line to the suppression pool via the RHR pump through the RHR reactor shutdown cooling mode suction line, the RHR pump, and the RHR test line. To do.

These will be combined according to the state of the plant.

As a measurement function based on these functions, a measurement function of reactor water temperature and reactor water level is required. In the reactor water temperature measurement function, there are reactor water purification system pump outlet temperature recirculation pump inlet temperature, fuel storage pool cooling purification system inlet temperature RHR heat exchanger outlet temperature, and it is necessary to evaluate which measurement points can be used. The recirculation pump inlet temperature does not show a significant value when the recirculation pump is stopped, for example, when the measuring instrument is being inspected. Since each measurement point has a close correspondence with the operating state of the equipment, it is necessary to evaluate it including this.

During the regular inspection, the reactor water level changes greatly, and the instruments used for the reactor water level measuring function differ as follows.

High band water level meter Scrum transmission water level meter ECCS starting water level meter It is necessary to use these properly according to the reactor water level.

The water supply function is the current water supply function, the preliminary water supply function,
Expanded to the reactor water level measurement function.

As the current water supply function, the water level control at the time of regular inspection is performed by the fuel storage pool cooling purification meter. The soundness of this system is evaluated from the condition of water source, sink, lineup, and pump. During operation, water level trends are also evaluated.

As a preliminary water supply function, the outflow amount of reactor water which may be generated depending on the contents of the work at the time of regular inspection is evaluated,
Evaluate whether the piping connected to the equipment to be inspected is above the upper lattice plate of the reactor pressure vessel, the diameter of the piping, and the presence of a check valve.

During the regular inspection work, the water supply capacity that covers reactor water outflow that may occur is confirmed.

The equipment that can be injected into the core has been described in the system for injecting the preliminary core cooling capacity of the core cooling function.

ECCS equipment (CS * 2 LPCI * 2)
CRD (control rod drive) system MUW (make-up water) system
Water supply system SLC (Boric acid water poison injection) system Digestion equipment Evaluate the operating conditions of these various equipment and confirm that they can cover the expected outflow.

The criticality prevention function is developed into a reactivity control function, a neutron flux rapid rise prevention function, and a neutron measurement function.

During the regular inspection period, since the control rod drive water pressure supply system and the water pressure control unit are inspected and repaired, a change in water pressure occurs and the inserted control rod is naturally pulled out or pulled out. The removed control rod may be inserted naturally.

In order to avoid such a situation, the isolation valve of the water pressure control unit of each control rod may be closed. However,
Since the operation of the isolation valve itself will give a pressure disturbance,
To prevent this, the water in the control rod drive water pressure supply system
A return operation to return to PV will be performed.

However, since control rod operation is required for fuel transfer and inspection of the instrumentation system in the reactor, the control rod drive water pressure supply system is in return operation, and the isolation valve of the water pressure control unit of the control rod that needs operation is installed. Need to open. At this time as well, the same problem may occur, so it is necessary to monitor the pressure of the control rod drive water pressure supply system. The consideration in this respect is the establishment of the reactivity control function.

As a neutron flux rapid rising prevention function, the core during the regular inspection is subcritical, but when it becomes supercritical for some reason and the neutron flux rises, in order to prevent this, control rod withdrawal prevention, Scrum and boric acid water injection system are activated.

The neutron flux measurement function is a prerequisite for realizing the ability to prevent the neutron flux rapid rise. If the SRM (neutron source area monitor) count value is 3 cps or more, monitoring is impossible.

The plant soundness maintenance function is a water purification function,
It consists of a pressure boundary securing function and a drain processing function.

The water purification function is related to the operation of the reactor water purification system, and especially when inspection / replacement of the in-core instrumentation system is carried out in the core, the reactor water is highly likely to be contaminated.
It is necessary to operate the reactor water purification system. In principle, the reactor water purification system needs to be in operation.

The pressure boundary securing function processes the high pressure test performed when the pressure vessel is restored and the low pressure test performed when the containment vessel is restored so that excessive pressure is not applied to the valves and pipes without pressure resistance.

The drain tank treatment function evaluates whether or not the drain water generated in the scheduled work can be accommodated within the capacity or treatment capacity of the treatment tank.

In addition to this, functions such as air conditioning and fire extinguishing can be considered.

The safety measure function includes a radioactive material diffusion prevention function at the time of fuel damage, an electric shock prevention evaluation function, and a water leakage prevention evaluation function.

The function of preventing radioactive material diffusion at the time of fuel damage is to prevent radioactive material from scattering when fuel damage occurs due to dropping of fuel or the like when the upper lid of the pressure vessel is open. When it is used for gas processing and radioactivity measurement. This function only needs to function when the upper lid of the pressure vessel is open.

The emergency gas treatment function confirms that the function of the emergency gas treatment system is sound from the lineup, the standby state of the fan, and the like.

Regarding the radioactivity measurement function, the reactor building ventilation system radiation monitor must function normally and can detect an increase in radioactivity due to fuel damage.

The electric shock prevention evaluation function and the water leakage prevention evaluation function evaluate that the electric shock prevention and the water leakage prevention are considered in the operation procedure.

Next, the operation of this embodiment will be described.

Now, it is assumed that the scheduled inspection scheduled work recorded in the scheduled inspection scheduled work file 3 is the overhaul and inspection of the RHR A system pump, and the work procedure for this purpose is recorded. Further, it is assumed that the regular inspection work recording unit 6 records that the RHR system pump is being inspected.

In this case, the work evaluation unit 1 uses the A of RHR.
In order to evaluate whether to disassemble and inspect the system pump, first, the plant safety maintenance function of FIG. 2 is evaluated based on the evaluation database 2. This is further developed to evaluate the core cooling function. As a measurement function for this, the reactor water temperature measurement function is evaluated.

Then, as the measurement point of the reactor water temperature, the reactor water purification system pump outlet temperature and the fuel storage pool cooling system inlet from the plant information and the information showing the regular inspection work state from the regular inspection work recording section 6 are obtained. The temperature is confirmed to be valid. Also for the reactor water measurement function, check the available measuring instruments from the inspection status of the measuring instruments. At this time, since the reactor water level is high, the reactor water temperature is low, and the decay heat of the reactor is low, it is evaluated that the function is established on the premise of establishing the preliminary core cooling function.

The preliminary core cooling function does not require a special function in such a plant state if the core cooling function is normally working under the present circumstances, but in this case, the establishment of the function in a strict sense is required. To be done.

As a result, the condensate storage tank which is the water injection route for the normal system → condensate transfer pump → emergency core cooling system piping → R
Valve actuation is required to establish the PV path. In addition, the route of drainage is confirmed. That is, a series of valve operations is required as the evaluation result of the preliminary core cooling function.

After this, similarly, the water supply function, the criticality prevention function,
The plant soundness maintenance function is evaluated, but it is confirmed that the function change does not occur due to the loss of function of the pump of interest. Finally, evaluate the specific operation procedure of the overhaul of the pump, and evaluate the electric shock prevention and water leakage prevention measures.

With the above, the evaluation by the work evaluation section 1 is completed,
A work procedure including the added procedure is given to the work execution / monitoring unit 4. Here, although the manual operation and the automatic operation are respectively performed according to the operation procedure, during this period, the plant state is monitored based on the evaluation database 2 from the plant information and the work state information of the regular inspection work recording unit 6.

Since the core cooling function is not perfect at present,
When the information that the inspection of the RHR B system pump has been completed is received, cooling by this system is immediately started. Further, when the reactor water temperature rises above the specified value, the preliminary core cooling function is activated.

The present embodiment can realize the regular inspection work which secures the safety and soundness of the plant and the safety of the worker by such evaluation and monitoring functions.

[0082]

As described above, the present invention reliably manages the regular inspection work of a nuclear power plant without relying on human labor, and can promptly deal with any trouble, so that the periodic inspection can be performed. Can improve the safety and soundness of the plant and the safety of workers.

[Brief description of drawings]

FIG. 1 is an overall configuration diagram of an embodiment of a regular inspection work management system for a nuclear power plant according to the present invention.

FIG. 2 is a diagram showing evaluation criteria recorded in an evaluation database shown in FIG.

FIG. 3 is a main process diagram of a regular inspection of a BWR nuclear power plant.

[Explanation of symbols]

 1 Work evaluation unit 2 Evaluation database 3 Scheduled inspection scheduled work file 4 Work execution / monitoring unit 5 Man-machine interface 6 Regular inspection work recording unit 7 Simulator 8 Plant

Claims (1)

[Claims] 1. A scheduled inspection scheduled work storage unit that stores a work plan at the time of regular inspection, a regular inspection work recording unit that records the state of the currently performed regular inspection work, plant information from the nuclear power plant, and A simulator for estimating a change in the plant state when the scheduled work saved in the scheduled inspection scheduled work storage unit is carried out based on the information indicating the state of the currently performed regular inspection work from the scheduled inspection work recording unit. When performing the required regular inspection work stored in the scheduled inspection scheduled work storage unit, whether or not the work can be executed is evaluated by evaluating the estimation result from the simulator according to an evaluation standard. For the work evaluation unit and the work evaluated by the work evaluation unit, a manual operation command for guiding the operation to be manually operated by the operator is output, and the plant is automatically operated. While outputting and executing an automatic operation command for monitoring the plant state at this time and continuing to evaluate the plant state, if this evaluation does not reach the evaluation standard, a corresponding operation that satisfies the evaluation standard is sought. And a work execution / monitoring unit to be executed, an evaluation database that stores the work evaluation unit and evaluation criteria used in the work execution / monitoring unit, a manual operation command from the work execution / monitoring unit, and a plant state evaluation As a result, a regular inspection work management system for a nuclear power plant, which has a man-machine interface for receiving and displaying information indicating a work state from the regular inspection work recording unit and inputting a scheduled scheduled inspection work, respectively. ..