CN-115965232-B - Nuclear power plant maintenance risk analysis method and system

CN115965232BCN 115965232 BCN115965232 BCN 115965232BCN-115965232-B

Abstract

The invention belongs to the technical field of maintenance management of nuclear power plants, and particularly relates to a maintenance risk analysis method and system of a nuclear power plant. The method comprises the following steps of 1, carding basic information, control logic information and signal channel information of equipment, 2, classifying equipment overhaul risks according to control logic results of the equipment and control logic results of adjacent equipment in a signal channel of the equipment, and 3, analyzing the equipment overhaul risks. The invention has the advantages that the manual analysis workload in the maintenance preparation process can be greatly reduced, the maintenance risk analysis reliability is improved, the shutdown or power transient of the unit caused by incomplete and incomplete risk analysis is reduced, and the safe and stable operation of the unit is ensured.

Inventors

WU GANG
LI YUANLIN
XU XINYOU
DONG JUNCHENG
ZHANG BING
LOU XIANGEN
YANG FAN
LI XIANJUN
ZHONG LIBO
SONG KAI

Assignees

中核核电运行管理有限公司
核电秦山联营有限公司

Dates

Publication Date: 20260512
Application Date: 20211008

Claims (5)

1. The maintenance risk analysis method for the nuclear power plant is characterized by comprising the following steps of: Step 1, basic information, control logic information and signal channel information of carding equipment; Step 2, classifying the overhaul risk of the equipment according to the control logic result of the equipment and the control logic result of the adjacent equipment in the signal channel; Step 3, analyzing equipment overhaul risks; Said step 3 comprises the steps of, S0, inputting a device number to be analyzed; s1, obtaining direct overhaul risks of equipment according to basic information and control logic information of the equipment, wherein the direct overhaul risks comprise one or more of direct shutdown a, direct shutdown b, direct control interlocking e and influence alarm display g; S2, according to the signal channel of the equipment, searching for adjacent equipment of the current equipment, namely equipment sharing the same junction box, the same junction box terminal row, the same cabinet terminal row and the same clamping piece; S3, traversing the adjacent equipment, and searching for direct overhaul risks according to the method of the step S1, wherein the direct overhaul risks comprise one or more of a direct shutdown a, a direct shutdown b, a direct control interlock e and an influence alarm display g, the direct overhaul risks of the adjacent equipment are the false collision risks of the current equipment, the corresponding relationship is that the direct shutdown a is converted into a false collision shutdown c, the direct shutdown b is converted into a false collision shutdown d, and the direct control interlock e is converted into an indirect control interlock f; S4, sorting all overhaul risks existing in the current equipment according to the risk level, and taking the maximum risk as the highest overhaul risk of the current equipment; And S5, summarizing and outputting risk analysis results to form a risk assessment list.
2. The method for analyzing maintenance risk of a nuclear power plant according to claim 1, wherein the basic information comprises a device name, a number, an installation position, a machine group number and a system number.
3. The method for analyzing maintenance risk of a nuclear power plant according to claim 1, wherein said control logic information includes end equipment information which changes state according to a logic diagram indication after the equipment state changes.
4. A method for analyzing maintenance risk of a nuclear power plant according to claim 1, wherein the signal path information comprises information of all terminal boxes, adapter boxes, clamping pieces, terminal blocks and cables which are arranged along the way from the actual installation position of the equipment to the control system.
5. The method for analyzing maintenance risk of a nuclear power plant according to claim 1, wherein the classification level of the maintenance risk of the equipment is as follows from high to low: a, directly shutting down, namely directly correlating reactor shutdown signals by equipment control logic; b, directly stopping, namely directly correlating a turbine stopping signal by equipment control logic; c, false collision shutdown, namely, the equipment control logic does not correlate with the reactor shutdown signal, but the adjacent equipment has correlated reactor shutdown signals, and the risk of triggering the shutdown signal due to false collision exists in the overhaul process; d, stopping the equipment by error collision, namely, the equipment control logic does not correlate with a turbine stopping signal, but the adjacent equipment has correlated turbine stopping signals, and the risk of triggering the stopping signal due to error collision in the overhaul process is caused; e, directly controlling and interlocking, namely directly associating the device control logic with other device actions; Indirect control interlock-device control logic does not directly associate other device actions, but its neighboring devices associate other device actions; And g, affecting the alarm display, namely, the control logic of the equipment and the adjacent equipment has no shutdown, shutdown and control interlocking functions, and only affecting the alarm display.

Description

Nuclear power plant maintenance risk analysis method and system Technical Field The invention belongs to the technical field of maintenance management of nuclear power plants, and particularly relates to a maintenance risk analysis method and system of a nuclear power plant. Background The nuclear power plant maintenance risk analysis is a maintenance preparation work with stronger professionality, higher difficulty and higher requirement, especially the maintenance of instrument control and electric remote transmission equipment, has stronger relevance, leads to a whole body, needs to refer to a large number of drawings and rich maintenance experience, and often needs to include maintenance related file preparation including drawing data such as a flow chart, a logic diagram, a simulation diagram, a termination diagram and the like, direct influence evaluation of equipment maintenance, namely, functional analysis such as protection, control, alarm, display and the like of the equipment is obtained through reading and understanding the drawings, the operation evaluation of channels (including cable termination, operation in the termination box, operation in a control cabinet and the like) which are required to be related by the equipment maintenance, the potential risk evaluation in maintenance implementation work, namely, risk analysis related to the maintenance equipment, such as risk recognition and evaluation of other important equipment in the same termination box or control cabinet and the like, is required to be ascertained. At present, the risk analysis link of the maintenance work file package mainly depends on manual analysis, and has the following defects: (1) Each analysis needs to look up a large number of drawings and read the drawings one by one, time and effort are wasted; (2) The business capability and responsibility of each person are different, and the analysis results may be different and reliable; (3) The risks of the overhaul path and the adjacent equipment are difficult to analyze completely, and the maximum overhaul risk has certain concealment; (4) The inaccessible (difficult) areas or the important areas of interest are not intuitive enough and are difficult to describe in place before being implemented on site; (5) The single risk analysis result is not reserved, and the single risk analysis result is lost after one package is made, so that maintenance accumulation is lacked. The risk assessment is not in place for many times in the operation power plant, the risk of the equipment overhaul channel is not identified, and the shutdown and transient events of the unit are caused by the miswire in construction. Disclosure of Invention The invention aims to provide a method and a system for analyzing maintenance risks of a nuclear power plant, which can automatically analyze the control logic analysis of equipment and the risks of adjacent equipment of an inspection channel, output the maximum risks possibly occurring when the equipment works, prompt a working responsible person and related personnel, reduce the workload of manual analysis and the probability of error generation, and improve the reliability of analysis results. The technical scheme of the invention is as follows, and the maintenance risk analysis method of the nuclear power plant comprises the following steps: Step 1, basic information, control logic information and signal channel information of carding equipment; Step 2, classifying the overhaul risk of the equipment according to the control logic result of the equipment and the control logic result of the adjacent equipment in the signal channel; and 3, analyzing equipment overhaul risks. The basic information includes equipment name, number, installation position, machine set number, system number, etc. The control logic information comprises end equipment information which changes the state according to the logic diagram indication after the equipment state changes. The signal channel information comprises information such as all terminal boxes, adapter boxes, clamping pieces, terminal rows, cables and the like which are arranged along the way from the actual installation position of the equipment to the control system. The overhaul risk classification level of the equipment is respectively from high to low: a, directly shutting down, namely directly correlating reactor shutdown signals by equipment control logic; b, directly stopping, namely directly correlating a turbine stopping signal by equipment control logic; c, false collision shutdown, namely, the equipment control logic does not correlate with the reactor shutdown signal, but the adjacent equipment has correlated reactor shutdown signals, and the risk of triggering the shutdown signal due to false collision exists in the overhaul process; d, stopping the equipment by error collision, namely, the equipment control logic does not correlate with a turbine stopping signal, but the adjacent equipment has corr