CN110751571A - Method for identifying equipment of CPR1000 type nuclear power station in grading manner - Google Patents
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Abstract
A classification identification method for CPR1000 type nuclear power station equipment comprises the following steps: s1: determining a device list to be identified by the system in a grading way; s2: listing the failure states of the equipment to be classified; s3: analyzing the equipment failure consequence corresponding to the failure state of the step S2; s4: comparing the equipment failure result obtained in the step S3 with 22 different established criticality criteria to determine the criticality grade of the equipment; s5: comparing the running frequency of the equipment with the established 6 running frequency criteria to determine the running frequency level of the equipment; s6: comparing the working environment of the equipment with the established 8 working environment criteria to determine the grade of the working environment of the equipment; s7: comparing the equipment failure state obtained in the step S2 with the established visibility criterion to determine the visibility characteristic of the equipment failure; s8: the expert review conference performs the rationality determination on the data acquired in the above steps S2 to S7. The method solves the problem of how to judge the criticality grade, and lays a foundation for the subsequent hierarchical management of the nuclear power station equipment.
Description
Technical Field
The invention relates to a device classification technology, in particular to a device classification identification method for a CPR1000 type nuclear power station.
Background
According to the AP913 equipment reliability management process, equipment classification is an input point of the equipment management process, and equipment classification identification is necessary before performing classification fine management on the nuclear power plant equipment. At present, no mature equipment classification identification method exists in the domestic CPR1000 type nuclear power station.
Disclosure of Invention
The invention aims to provide a method for identifying equipment of a CPR1000 type nuclear power station in a grading manner, and aims to solve the technical problem that the prior art does not have a mature method for identifying equipment of the CPR1000 type nuclear power station in a grading manner.
The technical scheme adopted by the invention for solving the technical problems is as follows:
a classification identification method for CPR1000 type nuclear power station equipment is characterized by comprising the following steps:
s1: determining a device list to be identified by the system in a grading way;
s2: listing the failure states of the equipment to be classified;
s3: analyzing the equipment failure consequence corresponding to the failure state of the step S2;
s4: comparing the equipment failure result obtained in the step S3 with 22 different established criticality criteria to determine the criticality grade of the equipment;
s5: comparing the running frequency of the equipment with the established 6 running frequency criteria to determine the running frequency level of the equipment;
s6: comparing the working environment of the equipment with the established 8 working environment criteria to determine the grade of the working environment of the equipment;
s7: comparing the equipment failure state obtained in the step S2 with the established visibility criterion to determine the visibility characteristic of the equipment failure;
s8: the expert review conference judges the rationality of the data obtained in the steps S2-S7, if the data expert review conference has no objection, the step S9 is carried out, and if the data expert review conference has subversive opinions on the data, the step S1 is carried out after equipment classification is carried out again;
s9: the data acquired at S2-S7 are modified according to the review comments given by the expert review conference at step S8.
Further, the step S1 determines the device classification range and the device list according to the classification boundary hypothesis.
Further preferably, the step S3 lists the failure statuses of the devices to be classified according to a predetermined standard failure status.
The implementation of the method for identifying the equipment of the CPR1000 type nuclear power station in a grading way can achieve the following beneficial effects: the invention has detailed explanation from the equipment classification identification range and granularity of the CPR1000 type nuclear power station, the personnel hypothesis, the reactor operation mode related to the equipment classification and the classification identification criterion, and designs 22 different criticality levels, 6 operation frequency levels, 8 working environment levels and 2 fault apparent and recessive criteria by combining the actual operation of the domestic CPR1000 type nuclear power station, thereby providing a specific operable method for the equipment classification identification, solving the problem of how to judge the criticality level and laying a foundation for the subsequent nuclear power station equipment classification management.
Drawings
FIG. 1 is a flow chart of the operation of the classification identification method of CPR1000 type nuclear power station equipment of the present invention;
FIG. 2 is an example of a table of hierarchical identification criteria for the device of the present invention.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings. It is to be understood that the described embodiments are merely exemplary of the invention, and not restrictive of the full scope of the invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
A classification identification method for CPR1000 type nuclear power station equipment is characterized by comprising the following steps:
s1: the method comprises the steps of determining an equipment list to be classified and identified by a system, specifically determining an equipment classification range and the equipment list according to a classification boundary hypothesis, and specifically collecting data and arranging the equipment list and a table.
The data collection options include the system data that the equipment classification engineer needs to collect in advance:
1. a System Design Manual (SDM);
RCM repair guide documents (if any);
3. system equipment operating maintenance manual, EOMM (if necessary);
4. an Operating Technical Specification (OTS) and an operating technical specification interpretation specification;
5. chemical and radiochemical specifications;
6. periodic test supervision schemas (PTS);
7. a periodic test procedure;
8. an alarm card;
9. system operating procedures;
10. system retrofit files (if necessary);
a list of SAP function locations;
12. note that: the latest version of the executable file is confirmed before using the file.
Sorting device lists and tables
The equipment list of the export system from the SAP system should include data of function location, function location description, geographical location, main work center, etc., as shown in table 1 below;
TABLE 1 device inventory example
Note that:
1. the table title fields and the arrangement sequence thereof are completely consistent with the requirements of 'annex 5 equipment hierarchical identification standard table';
2. the condition that the merging cells are not allowed to exist when the form is sorted and filled in;
3. when the form is sorted and filled, the geographical position and the functional position description of the machines 1 and 3 are forbidden to be copied to the machines 2 and 4 because SAP (service provider applications) of all machine sets are different;
4. in order to ensure the accuracy of the adopted SAP data, functional positions in the gulf power station, the Ling-Auo first-stage power station and the Ling-Auo second-stage power station are replaced by functional position codes of other power stations in batch without being checked one by one;
5. if the classification engineer or OPE engineer finds that some equipment needing analysis is not in the SAP list, the equipment needs to be supplemented in the table, and the coding rule is formulated by the OPE engineer and marked as 'suggesting a new function position' in a remark column;
6. if the functional position is found to be wrong, missing or redundant, the modified content and the suggestion should be written into the remark column and confirmed by the OPE engineer. Finally, transferring the functional positions determined to be redundant or wrong to a sheet2 page of an EXCEL table, and annotating a comment column on a sheet2 page to indicate 'propose deletion' or 'propose modification'; the correct SAP function location after modification is retained on sheet1 of the EXCEL form and noted in the remarks column;
s2: listing the failure states of the equipment to be classified, specifically listing the failure states of the equipment to be classified according to a specified standard failure state;
s3: analyzing the equipment failure consequence corresponding to the failure state of the step S2;
s4: comparing the equipment failure result obtained in the step S3 with 22 different established criticality criteria to determine the criticality grade of the equipment;
s5: comparing the running frequency of the equipment with the established 6 running frequency criteria to determine the running frequency level of the equipment;
s6: comparing the working environment of the equipment with the established 8 working environment criteria to determine the grade of the working environment of the equipment;
s7: comparing the equipment failure state obtained in the step S2 with the established criterion of the invisibility, determining the invisibility characteristic of the equipment failure,
dominant failure: under normal operation, a single failure of a device will be discovered by the user sooner or later.
Hidden failure: under normal operation, a user cannot find a device after a single failure, and only when one or more other failures are superposed, a deterministic effect is generated and is found by the user.
S8: the expert review conference judges the rationality of the data obtained in the steps S2-S7, if the data expert review conference has no objection, the step S9 is carried out, and if the data expert review conference has subversive opinions on the data, the step S1 is carried out after equipment classification is carried out again;
s9: the data obtained from S2-S7 are modified according to the review comments given in the patent review conference of step S8, and the final device classification identification standard table shown in FIG. 2 is prepared.
The invention discloses detailed steps for identifying CPR1000 type nuclear power station equipment in a grading way: 1. determining the range of equipment classification and an equipment list by using the assumption of combining the actual classification boundary of the nuclear power plant; 2. listing the failure states of the equipment to be classified according to a specified standard failure state; 3. analyzing the equipment failure consequence by using a failure consequence analysis method, and comparing the equipment failure consequence with 22 different established criticality criteria shown in the table 2 to determine the equipment criticality grade; 4. comparing the actual operation frequency and the working environment of the equipment with 6 operation frequency criteria shown in a table 4 and 8 working environment criteria shown in a table 3, and determining the operation frequency and the working environment grade of the equipment; 5. comparing the failure state of the equipment with the established failure explicit-implicit criterion to determine the failure explicit-implicit characteristic of the equipment; 6. in the process of grading and grading failure consequences, the assumed conditions of personnel operation, running state, severity, periodic test and the like are also considered; 7. the invention also provides a regulation for the hierarchical compiling and examining process.
Table 2: criticality rating and its identifying terms
TABLE 3 operating Environment ratings and clause description
Note that: when the 'working environment' is graded, only one item which is consistent with the fault consequence of the equipment is selected.
The "key level C" is mainly set to manage the devices directly related to the nuclear safety function, the safety shutdown function, the industrial safety function, the power generation capacity, and the functions are degraded, seriously degraded and damaged by a single fault of the devices. The power plant can maintain zero tolerance for the failure of key equipment.
The "importance level S" is set mainly from the viewpoint of reducing unsafe factors and protecting important equipment, and although a single failure of an importance level equipment does not directly lower the safety level and damage the equipment, it is necessary to manage these equipments in order to reduce these risks as much as possible.
Economic grade E: a single failure of such equipment does not normally directly or indirectly affect nuclear safety levels and power generation capacity, but is extremely economical for a power plant if the useful life of such equipment can be effectively extended with simple and economical maintenance means. It should be noted that economics often require more accurate data to verify. Maintenance cost x maintenance frequency < replacement cost x replacement frequency. Alternatively, the preventive maintenance cost × the maintenance frequency < the corrective maintenance cost × the maintenance frequency.
And (4) operating to maintenance R: devices that did not meet any of the provisions of C, S, E after analysis. The risk and consequences of these equipment failures are acceptable without having to perform preventive maintenance and without a simple, cost-effective way to extend the useful life of the equipment. Such equipment should be allowed to run to failure and corrective maintenance performed.
TABLE 4 run frequency ranking and clause description
While the present invention has been described with reference to the embodiments shown in the drawings, the present invention is not limited to the embodiments, which are illustrative and not restrictive, and it will be apparent to those skilled in the art that various changes and modifications can be made therein without departing from the spirit and scope of the invention as defined in the appended claims.
Claims (3)
1. A classification identification method for CPR1000 type nuclear power station equipment is characterized by comprising the following steps:
s1: determining a device list to be identified by the system in a grading way;
s2: listing the failure states of the equipment to be classified;
s3: analyzing the equipment failure consequence corresponding to the failure state of the step S2;
s4: comparing the equipment failure result obtained in the step S3 with 22 different established criticality criteria to determine the criticality grade of the equipment;
s5: comparing the running frequency of the equipment with the established 6 running frequency criteria to determine the running frequency level of the equipment;
s6: comparing the working environment of the equipment with the established 8 working environment criteria to determine the grade of the working environment of the equipment;
s7: comparing the equipment failure state obtained in the step S2 with the established visibility criterion to determine the visibility characteristic of the equipment failure;
s8: performing rationality judgment on the data obtained in the steps S2 to S7, if the data is judged to be not objected, proceeding to step S9, and if the data is subversive, performing equipment classification again, and proceeding to step S1;
s9: the data acquired at S2-S7 are modified according to the opinion obtained at step S8.
2. The method for identifying equipment hierarchy of CPR 1000-type nuclear power plant as claimed in claim 1, wherein step S1 determines equipment hierarchy range and equipment list based on a hierarchy boundary hypothesis.
3. The CPR 1000-type nuclear power plant equipment classification recognition method as claimed in claim 1, wherein the step S3 lists the failure states of the equipment to be classified according to a prescribed standard failure state.
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| CN2019104025602 | 2019-05-15 | ||
| CN201910402560.2A CN110223194A (en) | 2019-05-15 | 2019-05-15 | A kind of CPR1000 type nuclear power plant equipment hierarchical identification method |
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| CN114971417A (en) * | 2022-07-14 | 2022-08-30 | 三门核电有限公司 | Short-cycle work scheduling method and system based on hierarchical management |
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