KR20230054026A - System and method for processing procedures in nuclear power plants - Google Patents

Abstract

A system for processing procedures in nuclear power plants according to the present invention includes: a document storage unit that stores documents and experience data generated during the life cycle of nuclear power plant equipment; an equipment storage unit in which information on equipment installed and operated at a nuclear power plant and maintenance/test equipment is stored for each life cycle of the nuclear power plant equipment; a document analysis unit that derives an experiment method for the nuclear power plant based on data provided from the document storage unit; and an equipment analysis unit that analyzes the suitability of the equipment in the experiment method of the nuclear power plant based on data provided from the equipment storage unit.

Description

Nuclear power plant procedure document processing system and method {SYSTEM AND METHOD FOR PROCESSING PROCEDURES IN NUCLEAR POWER PLANTS}

The present invention relates to a procedure document processing system and method of a nuclear power plant, and more particularly, to a procedure document processing system and method of a nuclear power plant that automatically creates and manages an experiment procedure document based on artificial intelligence technology.

In general, a nuclear power plant consists of hundreds of thousands of similar or heterogeneous facilities. Procedures are used for verification tests and maintenance of the facility. The procedure is prepared by the person in charge of the facility by referring to the codes and standards (Code & Std) provided on the basis of the baseline, the manufacturer's technical documents and the designer's design documents, etc.

The prior art for these procedures has already been disclosed by "Registration Patent Publication No. 10-1917038 (Integrated management of reference documents required for preparation of nuclear power plant commissioning test procedures and procedure expression device, 2018.11.02.). The registered invention is a technology for preventing redundant writing by providing timely and accurate information necessary for a trial run test.

In the preparation of these procedures, a difference in quality occurs depending on the experience and ability of the person in charge of the facility at the time of the procedure development. Accordingly, difficulties may arise in maintenance quality and work management of facilities due to lack of consistency in the inspection contents and procedures of the same facility.

In addition, during the inspection or procedure, the required M&TE (Measurement and Test Equipment) selection, confirmation of the corresponding inspection point in the signal wiring diagram, related reference documents and manufacturer documents, and past similar inspection history review are performed manually. Therefore, there are differences in the time required for actual implementation and completion, costs, and quality of performance results depending on the competence of the person in charge. In addition, in the case of large-scale facility replacement or design change, verification is performed in consideration of the understanding of documents generated in the life cycle of the facility and the connection between upper and lower documents, depending on the experience and ability of the person in charge of the facility, There were problems that persisted throughout the life cycle.

Republic of Korea Patent Registration No. 10-1917038 (Reference document integrated management and procedure expression device required for preparation of nuclear power plant commissioning test procedure, 2018.11.02.)

An object of the present invention is to provide a nuclear power plant procedure document processing system and method for automatically creating and verifying a procedure document for nuclear power plant facilities.

The nuclear power plant procedure processing system according to the present invention is a document storage unit in which documents and experience data generated during the life cycle of nuclear power plant facilities are stored, and information on facilities installed and operated in the nuclear power plant and maintenance/test facilities is stored in the nuclear power plant facilities. In the experimental method of the nuclear power plant based on the data provided from the document analysis unit and the data provided from the facility storage unit and the facility storage unit that derives the nuclear power plant test method based on the data provided from the facility storage unit and the document storage unit stored for each life cycle of It includes a facility analysis unit that analyzes the suitability of facilities.

The document analysis unit searches for a first keyword from data provided from the document storage unit, assigns a dictionary meaning to the first keyword, recognizes the meaning through artificial intelligence, and derives a test item from the data. Create a final identification factor, use the first final identification factor as a second keyword, and proceed with actual case and correlation learning through artificial intelligence to create a second final identification factor to derive the requirements in the test item, By using the second final identification factor as the third keyword, a third final identification factor is created to derive the restriction requirements for the test items through artificial intelligence, and the fourth final identification factor is used as the fourth keyword to create artificial intelligence. Through intelligence, it is possible to create a fourth final identification factor for deriving the test method.

The facility analysis unit may extract the system configuration of the nuclear power plant and analyze the suitability after deriving test equipment for each facility for conducting the experiment.

The procedure document processing system of the nuclear power plant may further include a facility verification unit that verifies the facility based on the suitability analyzed by the facility analysis unit and the data provided from the document storage unit.

The procedure document processing system of the nuclear power plant may further include a linkage analysis unit for linkage analysis of the data provided from the document analysis unit and the data provided from the facility storage unit.

The document storage unit includes a code and standard document module in which documents related to at least one of IEEE, ASME, ANSI, ISA and NUREG are stored, and a concept design document module in which documents related to at least one of concept design and system design are stored and, a basic design document module in which documents related to at least one of C&ID, CLD, P&ID and PSAR are stored, a detailed design document module in which documents related to at least one of Technical Spec, SDD, SRS and FSAR are stored, and UT , a facility manufacturing document module in which documents related to at least one of IST and FAT are stored, a commissioning document module in which documents related to commissioning test procedures are stored, and documents related to at least one of fixed cycle procedures and maintenance procedures are stored. It includes an operation document module and other experience data modules in which other experience data of workers necessary for managing and generating procedures are stored, and the modules can be managed based on artificial intelligence.

The equipment storage unit includes a plant system module in which documents related to at least one of a turbine and a control rod system are stored, a plant equipment module in which documents related to at least one of a pump, a motor, a valve, and a heat exchanger are stored, and an alarm, control, and stop A digital system module in which documents related to at least one of the systems are stored, a digital component module in which documents related to at least one of a controller, an I/O module, and a network are stored, and documents related to at least one of CPU, RAM, and ROM are stored. A device module, a software module in which documents related to at least one of OS, firmware, and applications are stored, and an equipment module in which documents related to at least one of a DMM and an oscilloscope are stored, and the facility storage unit stores the documents It can be stored and managed in a matrix form by linking from upper level equipment to lower level equipment and software unit devices.

On the other hand, the method for processing nuclear power plant procedures according to the present invention includes the steps of deriving an experiment method of the nuclear power plant by acquiring data from a document storage unit in which documents and experience data generated during the life cycle of the nuclear power plant facility are stored, and installing the nuclear power plant. and obtaining data from a facility storage unit in which information on facilities operated and maintenance/test facilities are stored for each life cycle of the nuclear power plant facilities, and analyzing the suitability of the facilities in the nuclear power plant experiment method.

The nuclear power plant procedure processing system and method according to the present invention has an effect of ensuring consistency in the procedure performance results of the person in charge of the facility using artificial intelligence, regardless of the facility's experience and individual capabilities.

In addition, the nuclear power plant procedure processing system and method according to the present invention solves problems such as human errors and requirement violations that may occur in the preparation of procedures, improves the safety of power plants, and improves the reliability of devices by storing and managing the history of procedure execution results. It has the effect of predicting evaluation and performance degradation.

The technical effects of the present invention as described above are not limited to the effects mentioned above, and other technical effects not mentioned will be clearly understood by those skilled in the art from the description below.

1 is a configuration diagram schematically showing a procedure document processing system of a nuclear power plant according to this embodiment,
2 is a configuration diagram showing a document storage unit of a procedure document processing system of a nuclear power plant according to this embodiment;
3 is a configuration diagram showing a facility storage unit of a procedure document processing system of a nuclear power plant according to this embodiment;
Figure 4 is a flow chart showing the process proceeding in the document analysis unit of the procedure document processing system of the nuclear power plant according to this embodiment,
5 is a flow chart showing a linkage analysis process performed in a linkage analysis unit according to this embodiment;
6 is a flowchart showing a test equipment derivation process performed in a facility analysis unit according to this embodiment;
7 is a flowchart illustrating a facility verification process performed in the facility verification unit according to the present embodiment.

Hereinafter, embodiments of the present invention will be described in detail with reference to the accompanying drawings. However, this embodiment is not limited to the embodiments disclosed below and may be implemented in various forms, but this embodiment only makes the disclosure of the present invention complete, and the scope of the invention to those skilled in the art. It is provided for complete information. The shapes of elements in the drawings may be exaggeratedly expressed for more clear description, and elements indicated by the same reference numerals in the drawings mean the same elements.

1 is a configuration diagram schematically showing a procedure document processing system of a nuclear power plant according to this embodiment.

As shown in FIG. 1, the procedure document processing system (1000, hereinafter referred to as a processing system) of a nuclear power plant according to this embodiment includes a document analysis device 100 and a facility analysis device 200, Create and manage procedure documents.

The document analysis device 100 may include a document storage unit 110 , a document analysis unit 120 and a linkage analysis unit 130 . Also, the facility analysis device 200 may include a facility storage unit 210 , a facility analysis unit 220 , and a facility verification unit 230 .

2 is a configuration diagram showing a document storage unit of a procedure document processing system of a nuclear power plant according to this embodiment, and FIG. 3 is a configuration diagram showing a facility storage unit of a procedure document processing system of a nuclear power plant according to this embodiment.

As shown in FIGS. 2 and 3 , the document storage unit 110 according to the present embodiment stores documents and experience data generated during the life cycle of nuclear power plants in a modularized manner for each life cycle. The document storage unit 110 may manage documents based on artificial intelligence.

The document storage unit 110 includes a code and standard (Code & Std) document module 111, a concept design document module 112, a basic design document module 113, a detailed design document module 114, and a facility manufacturing document module. (115), commissioning document module 116, operation document module 117, and other experience data module 118. In each document module, documents necessary for creating procedures are stored and managed according to types.

For example, documents related to IEEE, ASME, ANSI, ISA, and NUREG may be stored and managed in the code and standard document module 111 .

For example, the concept design document module 112 may store and manage documents related to concept design and system design.

For example, in the basic design document module 113, documents related to C&ID, CLD, P&ID, and PSAR may be stored and managed.

For example, the detailed design document module 114 may store and manage documents related to Technical Spec, SDD, SRS, and FSAR.

For example, documents related to UT, IST, and FAT may be stored and managed in the facility manufacturing document module 115 .

For example, a document including a trial run test procedure may be stored and managed in the trial run document module 116 .

For example, documents including fixed cycle procedures and maintenance procedures may be stored and managed in the operation document module 117 .

For example, in the other experience data module 118, a document including other experience data of a worker necessary for managing and generating a procedure document may be stored and managed.

Meanwhile, in the facility storage unit 210, information on facilities installed and operated in a nuclear power plant and maintenance/test facilities may be stored for each life cycle of the nuclear power plant facility. In particular, in the facility storage unit 210, information on upper systems and lower unit facilities constituting the nuclear power plant is modularized and stored. At this time, the configuration of the facility storage unit 210 may be information collected and stored based on the detailed design document module 114 and the facility manufacturing document module 115. Information can be managed based on artificial intelligence.

The facility storage unit 210 includes a plant system module 211, a plant equipment module 212, a digital system module 213, a digital component module 214, a device module 215, a software module 216, and an equipment module. (217) may be included.

For example, the plant system module 211 may store and manage documents related to turbines and control rod systems.

For example, the plant equipment module 212 may store and manage documents related to pumps, motors, valves, and heat exchangers.

For example, the digital system module 213 may store and manage documents related to an alarm, control, and stop system.

For example, the digital component module 214 may store and manage documents related to a controller, an I/O module, and a network.

For example, documents related to the CPU, RAM, and ROM may be stored and managed in the device module 215 .

For example, the software module 216 may store and manage documents related to OS, firmware, and applications.

For example, the equipment module 217 may store and manage documents related to a DMM and an oscilloscope.

This facility storage unit 210 connects the identification factor of the plant system, which is the upper facility, to the device, which is the lower facility, and the unit device of the software loaded in the lower facility. In addition, the facility storage unit 210 configures, stores, and manages data by serial numbers in a matrix form, each of which is connected from an upper structure to a lower structure.

For example, the data stored in the facility storage unit 210 is an artificial intelligence-based top-down (Top -Down and Bottom-up are possible. In addition, the facility storage unit 210 is an integrated storage device equipped with each internal unit storage device, and it is possible to recognize the connection between each module.

Referring to FIG. 1 again, the document analysis unit 120 may sequentially proceed with a test item derivation process, a requirement derivation process, a restriction requirement derivation process, and a test method derivation process based on the data provided from the document storage unit 110. there is.

4 is a flowchart illustrating a process performed in the document analysis unit of the procedure document processing system of the nuclear power plant according to the present embodiment.

As shown in FIG. 4 , the document analysis unit 120 according to the present embodiment may proceed with a test item derivation process, a requirement derivation process, a restriction requirement derivation process, and a test method derivation process.

First, the document analysis unit 120 performs a test item derivation process.

At this time, the document analysis unit 120 acquires data from the code and standard document module 111 and the concept design document module 112 . Further, the document analysis unit 120 identifies the sentence structure of the obtained data as nouns, verbs, adjectives, and postpositions to retrieve and store a first keyword.

Then, the document analysis unit 120 generates a virtual first identification code by assigning a dictionary meaning to the retrieved first keyword. And, in order to determine what the imaginary first identification code means in the sentence, reinforcement learning is performed through documents uncorrelated with codes, standard documents, and conceptual design documents.

Further, the document analysis unit 120 determines what meaning the virtual first identification code has in the sentence by evaluating the relationship recognition rate between the sentences used in the trial operation document and the operation document and the extraction ability of the corresponding document through reinforcement learning. Due to this, the document analysis unit 120 may generate a first final identification factor for deriving a test item.

Then, the document analysis unit 120 evaluates the first final identification factor and proceeds with a requirement derivation process, which is the next process, when it has an accuracy of 95% or more. And, if the document analysis unit 120 is less than 95%, it assigns a dictionary meaning again to proceed with reinforcement learning and satisfies an accuracy of 95% or more. Here, the document analysis unit 120 proceeds with a requirement derivation process based on the first final identification factor when accuracy is satisfied.

In the requirement derivation process, the document analysis unit uses the first final identification factor as a second keyword. And the document analysis unit 120 proceeds to learn the correlation between the second keyword and actual examples used in the detailed design document, equipment manufacturing document, commissioning document, and operation document. Then, a virtual second identification code having a matrix between test items and requirements is generated.

For example, the document analysis unit 120 includes a code and standard document module 111, a concept design document module 112, a basic design document module 113, and Information is acquired from the detailed design document module 114. Further, the document analysis unit 120 recognizes a sentence including a second virtual identification code from codes and standard documents, concept design documents, basic design documents, and detailed design documents.

And, the document analysis unit 120 checks the correlation with the sentence including the virtual second identification code in the test requirements in the detailed design document, facility manufacturing document, commissioning document, and operation document. Further, the document analysis unit 120 checks the extraction rate of the sentences including the second imaginary identification code from the total sentences including the second imaginary identification code. And the document analysis unit 120 repeatedly performs learning to correct and remove error information in the first final identification factor, the second keyword, and the virtual second identification code. At this time, when a virtual second identification code satisfying accuracy is derived, the document analysis unit 120 identifies a sentence including the virtual second identification code as a second final identification factor.

After that, the document analysis unit 120 performs a restriction requirement derivation process.

At this time, the document analysis unit 120 uses the second final identification factor as a third keyword. Here, the constraints may mean setting values and logic.

The document analysis unit 120 calls information from the detailed design document module 114 and facility manufacturing document module 115 together with the third keyword. For example, the document analysis unit 120 may call various numerical information and input and output information required for a test from detailed design documents, equipment manufacturing documents, and drawings. Then, the document analysis unit 120 generates a virtual third identification code by incorporating detailed information related to the third keyword into the matrix substructure.

Thereafter, the document analysis unit 120 performs reinforcement learning to see if the matrix structure defined in the virtual third identification code is used as the same matrix structure within the information of the trial operation document module 116 and the operation document module 117 that are actually used. carry out At this time, the document analysis unit 120 repeatedly performs learning to correct and remove errors while changing the first comparison document to another document in the trial operation document module 116 and the operation document module 117 in the reinforcement learning process.

Thereafter, the document analysis unit 120 generates a third final identification factor when the virtual third identification code has a meaning in the matrix with an accuracy of 95% or more through reinforcement learning.

Then, the document analysis unit 120 performs a test method derivation process. At this time, the document analysis unit 120 utilizes the third final identification factor as a fourth keyword.

The document analysis unit 120 acquires information provided from the trial operation document module 116, the operation document module 117, and other experience data modules 118 together with the fourth keyword. For example, the document analysis unit 120 learns the correlation between identification factors such as nouns, verbs, adjectives, and postpositional sentence structures of trial operation documents, operation documents, and other experience data through machine learning.

And the learned fourth keyword links the test methods of the commissioning document module 116, the operation document module 117, and other experience data modules 118 in a matrix structure and gives a virtual fourth identification code.

The virtual fourth identification code is a virtual identification code of the document analysis unit 120 having a matrix structure of modules included in the document storage unit 110 . Thereafter, the virtual fourth identification code reinforces the sentence using the information of the operational document module 117 and other experiential data module 118, which are use cases including the fourth keyword, for sentence structure learning. Then, the document analysis unit 120 corrects and removes the error information of the sentence matrix and feeds back as a virtual identification factor, thereby deriving a valid fourth final identification factor of the document analysis unit 120.

Here, the fourth final identification factor of the document analysis unit 120 may have two forms: a sentence structure form and a unit sentence form. For example, the sentence structure form may have a structure of “subject + object + predicate”, and the unit sentence structure may have a structure of “subject, object, predicate”.

The fourth final identification factor is a test item of the code and standard document module 111, concept design document module 112, basic design document module 113, detailed design document module 114, and facility manufacturing document module 115. Requirements and limitations for each, and the test methods of the equipment manufacturing document module 115, commissioning document module 116, operation document module 117, and other experience data modules 118 are identified factors that are linked in a matrix.

Accordingly, the document analysis unit 120 may automatically create a report in a matrix structure of a sentence structure format and a matrix structure of a unit sentence format for test methods for each fourth final identification factor.

Meanwhile, the connection analysis unit 130 may perform connection analysis between data provided from the document analysis unit 120 and data provided from the facility storage unit 210 .

In addition, the connection analysis unit 130 is a sub-process of the document analysis unit 120 and the facility verification unit 230, and is a document and a document to transfer the fourth final identification factor of the document analysis unit 120 to the facility analysis unit 220. Conduct linkage analysis between facilities.

5 is a flowchart illustrating a linkage analysis process performed in the linkage analysis unit according to the present embodiment.

As shown in FIG. 5 , the link analysis unit 130 according to the present embodiment may link and analyze the data provided from the document analysis unit 120 and the data provided from the facility storage unit 210 .

The connection analysis unit 130 calls the fourth final identification factor derived from the document analysis unit 120 and transfers it to the facility storage unit 210 .

At this time, the facility storage unit 210 assigns the fourth final identification factor of the test item analyzed by the document analysis unit 120 a serial number based on the detailed design document module 114 and the facility manufacturing document module 115. The connected plant system module 211, plant equipment module 212, digital system module 213, digital component module 214, device module 215, and software module 216 are reinforced and learned. Information that is omitted or processed as an error in this process is updated through a relearning process through the equipment manufacturing document module 115, operation document module 117, and other experience data module 118 to update the linked learning.

Information derived in this way may be provided as an input to a test equipment derivation process described later.

6 is a flowchart illustrating a suitability analysis process performed in a facility analysis unit according to the present embodiment.

As shown in FIG. 6 , the facility analysis unit 220 according to the present embodiment may analyze the suitability of facilities in the experimental method of a nuclear power plant based on data provided from the facility storage unit 210 .

At this time, the facility analysis unit may extract the system configuration of the nuclear power plant and analyze suitability after deriving test equipment for each facility for conducting the experiment.

Facility analysis unit 220 is a test item of the fourth final identification factor, generating simulated signals, measuring input and output, and Acquire information on equipment constituting the test, such as condition creation.

In addition, the facility analysis unit 220 learns the M&TE equipment list in the equipment module 217 for consistency with equipment provided in the actual nuclear power plant in the facility storage unit 210. At this time, the information is updated and stored in the equipment module 217 of the equipment storage unit 210 by updating the fourth final identification factor and use history for each equipment into information in a matrix structure.

More specifically, the facility analysis unit 220 includes a plant system module 211, a plant equipment module 212, a digital system module 213, a digital component module 214, and a device module 215 to extract the plant system configuration. ) and call data from the software module 216.

The called data is data of matrix structure and has a serial number and is used as information necessary for deriving test equipment.

This information is information composed of a fourth final identification factor and equipment usage history for each facility in a matrix structure, and is a virtual fifth identification code. Thus, the virtual fifth identification code is provided as an input to the test method conformance process. At this time, the facility analysis unit 220 uses a facility manufacturing document module 115, a commissioning document module 116, an operation document module 117, and other experience data modules in a document storage unit, which is an actual case, to evaluate the suitability of the test method. Re-learning is carried out through (118). In addition, the fifth final identification factor is created by linking learning of related test items and test equipment based on the facility, and information of the linkage analysis unit 130 and the facility storage unit 210 is updated.

At this time, the report of the matrix structure of the sentence structure format and the matrix structure of the unit sentence format, which are the test methods for the fifth final identification factor, are automatically updated by the updated information. In the test method conformity analysis process, information can be updated through reinforcement learning until the conformance evaluation is satisfied.

Then, reinforcement learning is performed with the updated information, and if the suitability evaluation is at a satisfactory level, the selected equipment is equipped for the test procedure of the matrix structure in the form of a sentence structure including the test items and equipment and the test procedure of the matrix structure in the form of a unit sentence. Each test procedure report is automatically generated and confirmed. At this time, the input used is determined as a unique identification factor and does not change unless the input used is changed. In addition, the output report is a structure that clearly shows the input and output, set values, and execution method based on the testable level, that is, the design document.

Meanwhile, the facility verification module performs verification of facilities generated by the facility analysis unit 220 .

7 is a flowchart illustrating a facility verification process performed in the facility verification unit according to the present embodiment.

As shown in FIG. 7 , the facility verification unit 230 according to the present embodiment can verify the facility based on the suitability analyzed by the facility analysis unit 220 and the data provided from the document storage unit 110. .

The facility verification unit 230 calls a test procedure report for each facility from the facility analysis unit 220 .

In addition, the facility verification unit 230 generates a test template through a test procedure report for each facility. The shape of the created template may vary depending on the test items and input/output characteristics.

That is, the configuration of the test template is different depending on the difference between the analog input of voltage, current, and resistance and the digital input of the contact point, the analog output of voltage, current, and resistance, and the digital output of the contact point.

The test template determined according to the test procedure report for each facility is automatically created considering the combination of input and output, and input/output is automatically checked using the secured analog or digital M&TE equipment.

At this time, the output of the execution result is the code and the difference value compared with the latest execution history in the commissioning document module 116, operation document module 117, and other experience data module 118, and from the standard document module 111 to the detailed design document module (114) It checks whether it is out of the tolerance standard, and if it is dissatisfied, a dissatisfaction report is automatically output.

At this time, if both of the test of the matrix structure in the form of sentence structure and the test of the matrix structure of unit sentence form fail, the standard of conformity evaluation from the document analysis unit 120 to the facility analysis unit 220 is +1% each It is re-executed after correcting while increasing. also. If only one of the two fails, the conformity assessment standard is maintained and strengthened through the trial operation document module 116, operation document module 117, and other experience data module 118 in learning the fifth final identification factor of the document analysis unit 120. Learn and practice again. As a result, the unique identification factor of the facility analysis unit 220 is updated and provided as an input to the facility verification unit 230 .

Thereafter, the test procedure satisfied in the equivalence evaluation is transmitted and stored to the operation document module 117 and other experience data module 118 via the linkage analysis unit 130, and thereby the document analysis unit 120, facility storage The information stored in the unit 210 and the facility analysis unit 220 is updated, and the test procedure of the matrix structure of the sentence structure form in the facility analysis unit 220 and the test procedure of the matrix structure of the unit sentence form are maintained as the final test procedure. . When the user requests the next facility verification, the facility verification unit calls the facility analysis unit a test procedure report for each facility, and the process proceeds.

The nuclear power plant procedure processing system and method according to the present invention has an effect of ensuring consistency in the procedure performance results of the person in charge of the facility using artificial intelligence, regardless of the facility's experience and individual capabilities.

In addition, the nuclear power plant procedure processing system and method according to the present invention solves problems such as human errors and requirement violations that may occur in the preparation of procedures, improves the safety of power plants, and improves the reliability of devices by storing and managing the history of procedure execution results. It has the effect of predicting evaluation and performance degradation.

One embodiment of the present invention described above and shown in the drawings should not be construed as limiting the technical idea of the present invention. The protection scope of the present invention is limited only by the matters described in the claims, and those skilled in the art can improve and change the technical spirit of the present invention in various forms. Therefore, such improvements and changes will fall within the protection scope of the present invention as long as they are obvious to those skilled in the art.

Claims (8)

A document storage unit for storing documents and experience data generated during the life cycle of nuclear power plant facilities;
a facility storage unit that stores information on facilities installed and operated in the nuclear power plant and maintenance/test facilities for each life cycle of the nuclear power plant facilities;
a document analysis unit for deriving an experimental method of the nuclear power plant based on the data provided from the document storage unit; and
A nuclear power plant procedure processing system comprising a facility analysis unit that analyzes the suitability of facilities in the test method of the nuclear power plant based on the data provided from the facility storage unit.
According to claim 1,
The document analysis unit
A first keyword is retrieved from data provided from the document storage unit, a dictionary meaning is given to the first keyword, and a meaning is recognized through artificial intelligence to generate a first final identification factor for deriving a test item from the data. do,
Using the first final identification factor as a second keyword and conducting correlation learning with actual cases through artificial intelligence to generate a second final identification factor to derive requirements within the test item,
Using the second final identification factor as a third keyword to create a third final identification factor to derive the restriction requirements for the test item through artificial intelligence,
A procedure document processing system of a nuclear power plant that uses the fourth final identification factor as a fourth keyword to generate a fourth final identification factor for deriving the test method through artificial intelligence.
According to claim 1,
The facility analysis unit
The procedure document processing system of the nuclear power plant for extracting the system configuration of the nuclear power plant and analyzing the suitability after deriving test equipment for each facility for conducting the experiment.
According to claim 1,
The procedure document processing system of the nuclear power plant further comprising a facility verification unit for verifying the facility based on the suitability analyzed by the facility analysis unit and the data provided from the document storage unit.
According to claim 1,
The procedure document processing system of the nuclear power plant further comprising a linkage analysis unit for linkage analysis of the data provided from the document analysis unit and the data provided from the facility storage unit.
According to claim 1,
The document storage unit
A code and standard document module in which documents related to at least one of IEEE, ASME, ANSI, ISA, and NUREG are stored;
A concept design document module in which documents related to at least one of concept design and system design are stored;
A basic design document module in which documents related to at least one of C & ID, CLD, P & ID and PSAR are stored;
A detailed design document module in which documents related to at least one of Technical Specification, SDD, SRS, and FSAR are stored;
A facility manufacturing document module in which documents related to at least one of UT, IST and FAT are stored;
A commissioning document module in which documents related to commissioning test procedures are stored;
An operation document module in which documents related to at least one of fixed cycle procedures and maintenance procedures are stored;
Including other experience data modules in which other experience data of workers necessary for managing and generating procedures are stored,
The module is a nuclear power plant procedure processing system that is managed based on artificial intelligence.
According to claim 1,
The facility storage unit
A plant system module in which documents related to at least one of a turbine and a control rod system are stored;
A plant equipment module in which documents related to at least one of pumps, motors, valves, and heat exchangers are stored;
A digital system module in which documents related to at least one of an alarm, control and stop system are stored;
A digital component module in which documents related to at least one of a controller, an I/O module, and a network are stored;
A device module in which documents related to at least one of CPU, RAM and ROM are stored;
A software module in which documents related to at least one of OS, Firm ware, and Application are stored;
Including an equipment module in which documents related to at least one of the DMM and the oscilloscope are stored,
The facility storage unit
A nuclear power plant procedure processing system that stores and manages the documents in a matrix form by linking the documents from the upper level facility to the lower level facility and the unit device of the software.
Deriving an experiment method of the nuclear power plant by acquiring data from a document storage unit in which documents and experience data generated during the life cycle of the nuclear power plant facility are stored; and
Acquiring data from a facility storage unit in which information on facilities installed and operated in the nuclear power plant and maintenance/test facilities is stored for each life cycle of the nuclear power plant facility, and analyzing the suitability of the facility in the nuclear power plant experiment method. How to deal with nuclear power plant procedures.

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