CN117522108A - Nuclear power plant configuration risk management method, system and computer storage medium - Google Patents
Nuclear power plant configuration risk management method, system and computer storage medium Download PDFInfo
- Publication number
- CN117522108A CN117522108A CN202311316983.5A CN202311316983A CN117522108A CN 117522108 A CN117522108 A CN 117522108A CN 202311316983 A CN202311316983 A CN 202311316983A CN 117522108 A CN117522108 A CN 117522108A
- Authority
- CN
- China
- Prior art keywords
- risk
- power plant
- nuclear power
- current
- area
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000003860 storage Methods 0.000 title claims abstract description 8
- 238000007726 management method Methods 0.000 title claims description 73
- 238000011156 evaluation Methods 0.000 claims abstract description 21
- 238000000034 method Methods 0.000 claims abstract description 21
- 238000012423 maintenance Methods 0.000 claims description 59
- 230000000694 effects Effects 0.000 claims description 21
- 238000004590 computer program Methods 0.000 claims description 10
- 230000008859 change Effects 0.000 claims description 7
- 238000012360 testing method Methods 0.000 claims description 7
- 238000012545 processing Methods 0.000 claims description 5
- 239000003086 colorant Substances 0.000 claims description 4
- 238000011161 development Methods 0.000 claims description 4
- 230000003449 preventive effect Effects 0.000 claims description 4
- 230000008439 repair process Effects 0.000 claims description 4
- 238000004364 calculation method Methods 0.000 description 4
- 238000012502 risk assessment Methods 0.000 description 4
- 230000007547 defect Effects 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 238000012954 risk control Methods 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 230000008030 elimination Effects 0.000 description 2
- 238000003379 elimination reaction Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012544 monitoring process Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000007123 defense Effects 0.000 description 1
- 230000009474 immediate action Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 238000011002 quantification Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 238000012216 screening Methods 0.000 description 1
- 238000004904 shortening Methods 0.000 description 1
- 230000003442 weekly effect Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
- G06Q10/06—Resources, workflows, human or project management; Enterprise or organisation planning; Enterprise or organisation modelling
- G06Q10/063—Operations research, analysis or management
- G06Q10/0635—Risk analysis of enterprise or organisation activities
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
- G06Q10/20—Administration of product repair or maintenance
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q50/00—Information and communication technology [ICT] specially adapted for implementation of business processes of specific business sectors, e.g. utilities or tourism
- G06Q50/06—Energy or water supply
Landscapes
- Business, Economics & Management (AREA)
- Human Resources & Organizations (AREA)
- Engineering & Computer Science (AREA)
- Economics (AREA)
- Strategic Management (AREA)
- Tourism & Hospitality (AREA)
- Theoretical Computer Science (AREA)
- General Physics & Mathematics (AREA)
- Entrepreneurship & Innovation (AREA)
- General Business, Economics & Management (AREA)
- Marketing (AREA)
- Physics & Mathematics (AREA)
- Operations Research (AREA)
- Quality & Reliability (AREA)
- Health & Medical Sciences (AREA)
- Game Theory and Decision Science (AREA)
- Educational Administration (AREA)
- Development Economics (AREA)
- Public Health (AREA)
- Water Supply & Treatment (AREA)
- General Health & Medical Sciences (AREA)
- Primary Health Care (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to a method, a system and a computer storage medium for managing configuration risk of a nuclear power plant, wherein the method for managing the configuration risk of the nuclear power plant comprises the following steps: when a specific event occurs, acquiring the current running state of the nuclear power plant in real time, and judging whether the current running state meets the preset entering condition or not; when the entering condition is met, carrying out configuration risk evaluation according to a risk model of the nuclear power plant, and obtaining a current evaluation result; determining a current risk zone corresponding to the current risk level value according to a specific event, a plurality of preset risk zones and the risk level range value corresponding to each risk zone; acquiring current risk management measures corresponding to current risk areas according to the risk management measures corresponding to each risk area under different preset specific events; outputting the current risk area and the current risk management measure. By the technical scheme, the method and the device can be suitable for the condition of multiple failures of equipment/systems of the nuclear power plant, so that the configuration risk management flow of the nuclear power plant is perfected and improved.
Description
Technical Field
The present invention relates to the field of nuclear security, and in particular, to a method and system for managing configuration risk of a nuclear power plant, and a computer storage medium.
Background
The nuclear power plant implements a deep defense concept in the design operation process, a large number of special safety facilities and supporting systems thereof are arranged for preventing and relieving design reference accidents, and technical specifications are adopted for managing the configuration of the systems, but are usually directed to risk control when a single device/system fails. However, in view of the diversity, complexity and timeliness of the nuclear power plant configuration, technical specifications are not effective in controlling the risk of multiple failures.
Disclosure of Invention
The invention aims to solve the technical problem that the prior art has the defect that multiple failure risks cannot be effectively controlled, and provides a nuclear power plant configuration risk management method, a system and a computer storage medium.
The technical scheme adopted for solving the technical problems is as follows: a method for managing configuration risk of a nuclear power plant is constructed, comprising:
step S10, when a specific event occurs, acquiring the current running state of the nuclear power plant in real time, and judging whether the current running state meets a preset entering condition or not according to the running state, wherein the specific event comprises the occurrence of configuration change of the nuclear power plant and the development of planned maintenance of the nuclear power plant;
step S20, when the entering condition is met, carrying out configuration risk evaluation according to a risk model of the nuclear power plant so as to obtain a current evaluation result, wherein the evaluation result comprises a risk level value;
step S30, determining a current risk zone corresponding to the current risk level value according to the specific event, a plurality of preset risk zones and the risk level range value corresponding to each risk zone;
step S40, acquiring current risk management measures corresponding to the current risk areas according to the risk management measures corresponding to each risk area under different preset specific events;
step S50, outputting the current risk area and the current risk management measures.
Preferably, the determining whether the preset entry condition is satisfied according to the operation state includes:
step S11, determining current affected equipment according to the running state, wherein the affected equipment comprises equipment involved in out-of-service equipment or experimental maintenance activities;
step S12, determining whether a preset entry condition is satisfied according to a first list, a second list, a third list and the affected device, where the first list is a system/device/structure list related to a configuration risk management outline of a nuclear power plant, the second list is a system/device/structure list related to an implementation outline of a maintenance rule of the nuclear power plant, and the third list is a device list related to at least one technical specification.
Preferably, the step S12 includes:
judging whether the shutdown equipment is equipment which exists in the first list and the third list at the same time, if so, judging whether the management measures aiming at the shutdown equipment in the technical specification are not immediately shutdown and back-off, and if not, determining that a preset entry condition is met; and/or the number of the groups of groups,
judging whether equipment related to the test maintenance activity exists in the first list, and if so, determining that a preset entering condition is met; and/or the number of the groups of groups,
judging whether equipment related to the test maintenance activity exists in the second list, if so, determining that a preset entering condition is met;
judging whether the out-of-service equipment belongs to specific equipment related to specific technical specifications in the third list, and if so, determining that a preset entering condition is met.
Preferably, the risk level values include an instantaneous risk level value and an accumulated risk level value;
the step S30 includes:
when the specific event is a configuration change of the nuclear power plant, determining a risk zone corresponding to the current instantaneous risk level value according to a plurality of preset risk zones and the instantaneous risk level range value corresponding to each risk zone;
and when the specific event is the planned maintenance of the nuclear power plant, determining a risk zone corresponding to the current accumulated risk level value according to a plurality of preset risk zones and the accumulated risk level range value corresponding to each risk zone.
Preferably, the preset multiple risk areas comprise a risk unacceptable area, a risk management area and a normal control area;
in the step S50, the step of outputting the determined risk area includes:
and determining the color corresponding to the current risk area according to the colors corresponding to the multiple risk areas respectively, and displaying the current risk area by adopting the determined color.
Preferably, the evaluation result further includes an allowable configuration time;
the step S40 includes:
when the specific event is that the configuration of the nuclear power plant is changed, if the current risk area is a risk unacceptable area, the corresponding risk management measure is that the unit is immediately retracted to a safe state; if the current risk area is a risk management area, the corresponding risk management measures are entering an operation decision flow and tracking fault processing of the out-of-service equipment in the allowed configuration time; if the current risk area is a normal control area, the corresponding risk management measure is to normally execute daily work;
when the specific event is the planned maintenance of the nuclear power plant, if the current risk area is a risk unacceptable area, the corresponding risk management measure is to immediately adjust the maintenance plan; if the current risk area is a risk management area, the corresponding risk management measures are entering a major repair decision flow and tracking subsequent plan adjustment in the allowed configuration time; if the current risk area is a normal control area, the corresponding risk management measures are to carry out maintenance according to the plan.
Preferably, after the step S50, the method further includes:
and step S60, judging whether the current state meets the preset exit condition according to the current running state of the nuclear power plant, and if so, ending.
Preferably, in the step S60, it is determined whether a preset exit condition is currently satisfied, including at least one of the following:
the maintenance activities for the out-of-service equipment have been completed and no new specific event has occurred within a specific time;
preventive, corrective maintenance activities for the equipment involved in the trial maintenance activities have completed and no new specific event has occurred within a specific time;
the systems/devices/structures in the first list are all in a usable state.
The nuclear power plant enters an emergency incident management code.
The invention also constructs a nuclear power plant configuration risk management system, which comprises a processor and a memory storing a computer program, wherein the processor realizes the steps of the nuclear power plant configuration risk management method when executing the computer program.
The present invention also constructs a computer storage medium storing a computer program which, when executed by a processor, implements the steps of the nuclear power plant configuration risk management method described above.
In the technical scheme provided by the invention, when a specific event occurs, whether the nuclear power plant configuration risk management process needs to be entered is firstly judged according to the running state of the nuclear power plant, if so, the configuration risk level can be quantitatively evaluated based on a risk model, and then the corresponding risk area and risk management measures are determined based on the risk level value so as to guide a user to perform risk control on the nuclear power plant configuration. Compared with the existing mode of adopting technical specifications, the technical scheme is more suitable for the condition of multiple failures of equipment/systems of the nuclear power plant, so that the configuration risk management flow of the nuclear power plant is perfected and improved.
Drawings
In order to more clearly illustrate the embodiments of the present invention, the drawings that are required for the description of the embodiments will be briefly described below, it being apparent that the drawings in the following description are only some embodiments of the present invention and that other drawings may be obtained from these drawings without inventive effort for a person of ordinary skill in the art. In the accompanying drawings:
FIG. 1 is a flowchart of a first embodiment of a method for managing risk of a nuclear power plant configuration according to the present invention.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
FIG. 1 is a flowchart of a first embodiment of a method for managing a risk of configuring a nuclear power plant according to the present invention, the method for managing a risk of configuring a nuclear power plant according to the present invention includes the steps of:
step S10, when a specific event occurs, acquiring the current running state of the nuclear power plant in real time, and judging whether the current running state meets a preset entering condition or not according to the running state, wherein the specific event comprises the occurrence of configuration change of the nuclear power plant and the development of planned maintenance of the nuclear power plant;
in this step, it should be noted that, when the configuration of the nuclear power plant is changed or a planned maintenance is performed, the configuration risk management of the nuclear power plant is required, but in view of the huge number of systems and devices of the nuclear power plant, in order to effectively perform risk evaluation and management, a range of the configuration risk management needs to be determined, specifically, whether a flow of the configuration risk management needs to be entered may be determined according to an actual operating state of the nuclear power plant, and it should be noted that the actual operating state may include a case where a single device/system is unavailable or a case where a plurality of devices/systems are unavailable.
Step S20, when the entering condition is met, carrying out configuration risk evaluation according to a risk model of the nuclear power plant so as to obtain a current evaluation result, wherein the evaluation result comprises a risk level value;
in this step, a real-time risk model (PSA) of the nuclear power plant may be used for configuration risk assessment, for example, in one embodiment, the PSA model is modeled first, after a specific event occurs, the fault tree and the event tree are re-parsed by boolean operations and a new minimum cut set is obtained, and a new CDF/LERF result (risk level value) and related risk information are obtained according to the new minimum cut set. In another embodiment, a minimum cut set library can be established first, and after a specific event occurs, the minimum cut set is calculated in a re-quantification mode to acquire the risk level of the nuclear power plant and provide corresponding risk information.
In addition, it should be noted that an operation state of the nuclear power plant corresponds to a risk level value, for example, only one device is not available at the beginning, and corresponds to a risk level value, after a period of time, another risk level value is corresponding to the occurrence of a device that is not available at the same time, and after a period of time, the initially unavailable device is restored to be available, and then a different risk level value is corresponding to the moment.
Step S30, determining a current risk zone corresponding to the current risk level value according to the specific event, a plurality of preset risk zones and the risk level range value corresponding to each risk zone;
in this step, the preset plurality of risk areas may be three, for example, respectively: the risk unacceptable area, the risk management area and the normal control area, of course, the preset plurality of risk areas can also be four, for example, the risk management area can be subdivided into two areas according to the level of risk. Moreover, each risk area corresponds to a risk level range value. In this way, the current risk area can be judged according to the risk evaluation result and the risk level range value corresponding to each risk area.
Step S40, acquiring current risk management measures corresponding to the current risk areas according to the risk management measures corresponding to each risk area under different preset specific events;
step S50, outputting the current risk area and the current risk management measures.
In the technical scheme of the embodiment, when a specific event occurs, whether the nuclear power plant configuration risk management process needs to be entered is firstly judged according to the running state of the nuclear power plant, if so, the configuration risk level can be quantitatively evaluated based on a risk model, and then the corresponding risk area and risk management measures are determined based on the risk level value so as to guide a user to perform risk control on the nuclear power plant configuration. Compared with the existing mode of adopting technical specifications, the technical scheme is more suitable for the condition of multiple failures of equipment/systems of the nuclear power plant, so that the configuration risk management flow of the nuclear power plant is perfected and improved.
Further, in an optional embodiment, in step S10, determining whether a preset entry condition is satisfied according to the running state includes:
step S11, determining current affected equipment according to the running state, wherein the affected equipment comprises equipment involved in out-of-service equipment or experimental maintenance activities;
step S12, determining whether a preset entry condition is satisfied according to a first list, a second list, a third list and the affected device, where the first list is a system/device/structure list related to a configuration risk management outline of a nuclear power plant, the second list is a system/device/structure list related to an implementation outline of a maintenance rule of the nuclear power plant, and the third list is a device list related to at least one technical specification.
In this embodiment, a SSC (System, component, structure, system/device/structure) list of CRMP (configuration risk management outline) and a SSC list of MR (nuclear power plant maintenance rule enforcement outline), that is, a first list and a second list, may be introduced into the system in advance, and of course, a list of related devices involved in various types of specifications, that is, a third list, may also be introduced into the system in advance. When judging whether the preset entering condition is met currently, setting corresponding triggers, such as trigger-CRMP and trigger-MR, and screening the equipment related to the current out-of-service equipment and test maintenance according to the lists to judge whether to trigger the configuration risk management flow.
In one embodiment, the entry conditions are four of:
1. the equipment in the technical specification is randomly unavailable, the affected equipment belongs to the range of the PSA model, and other conditions enter a configuration risk management flow except for the requirement of immediate shutdown and back-off in the technical specification;
2. performing risk assessment on planned maintenance activities which are brought into the configuration risk management scope SSC;
3. the situation that the maintenance rule implementation outline of the nuclear power plant requires to develop risk evaluation and risk management;
4. in the case of entering a risk management technical specification using risk guideline completion time (RICT), it is noted that this type of technical specification is a specific type of technical specification in which the length of time available for recovery after a device failure is required to be non-fixed is calculated.
Based on the above entry conditions, step S12 specifically includes:
judging whether the shutdown equipment is equipment which exists in the first list and the third list at the same time, if so, judging whether the management measures aiming at the shutdown equipment in the technical specification are not immediately shutdown and back-off, and if not, determining that a preset entry condition is met; and/or the number of the groups of groups,
judging whether equipment related to the test maintenance activity exists in the first list, and if so, determining that a preset entering condition is met; and/or the number of the groups of groups,
judging whether equipment related to the test maintenance activity exists in the second list, if so, determining that a preset entering condition is met;
judging whether the out-of-service equipment belongs to specific equipment related to specific technical specifications in the third list, and if so, determining that a preset entering condition is met.
Further, in an alternative embodiment, the risk level values include an instantaneous risk level value and an accumulated risk level value. Also, step S30 includes:
when the specific event is a configuration change of the nuclear power plant, determining a risk zone corresponding to the current instantaneous risk level value according to a plurality of preset risk zones and the instantaneous risk level range value corresponding to each risk zone;
and when the specific event is the planned maintenance of the nuclear power plant, determining a risk zone corresponding to the current accumulated risk level value according to a plurality of preset risk zones and the accumulated risk level range value corresponding to each risk zone.
In this embodiment, a risk assessment effort may be performed based on a real-time risk model and risk monitoring tool of the nuclear power plant, according to the current or expected configuration of the nuclear power plant, inputting the affected systems, equipment, and reasons for decommissioning, obtaining risk levels of the current or expected configuration of the nuclear power plant, including instantaneous risk (including CDF and LERF) and accumulated risk (ICDP and ILERP), etc., and providing a risk assessment report. Then comparing the risk evaluation result with a predefined risk threshold, wherein the risk level threshold used in comparison is different for different specific events, specifically, firstly determining that the event entering the configuration risk management flow is operation configuration risk management or maintenance configuration risk management, and the risk threshold of operation configuration risk management is mainly instantaneous risk (CDF/LERF); the risk threshold for maintenance configuration risk management is mainly based on the accumulated risk (ICDP/ilep).
Further, in a specific embodiment, the instantaneous risk CDF/LERF increment and the accumulated risks ICDP and ILERP may be further calculated, where the core damage frequency increment Δcdf in a specific state is equal to the difference between the CDF (core damage frequency) in a specific state and the reference CDF, and the calculation method of the early large-scale radioactivity release frequency increment Δlerf is similar to the same, and the specific calculation formula is as follows:
ΔCDF configuration =CDF point-in-time –CDF baseline
ΔLERF configuration =LERF point-in-time -LERF baseline
wherein CDF point-in-time Refers to the instantaneous risk level value at the current time, typically calculated by a risk monitoring tool or PSA software, CDF baseline Refers to a baseline risk level value, i.e., a zero maintenance risk level value, when all devices are available. Similarly, LERF point-in-time And LERF baseline The early-stage high-dose radioactive release frequency and the zero-maintenance early-stage high-dose radioactive release frequency of the current moment are respectively.
And the increment of the core damage probability under a specific state, the accumulated risk ICDP is equal to the increment of the core damage frequency multiplied by the related duration of the state, the accumulated risk LERP is equal to the increment of the early-stage large-amount radioactivity release frequency multiplied by the related duration of the state, and the specific calculation formula is as follows:
ICDP config =ΔCDF config ×T config
ILERP config =ΔLERF config ×T config 。
further, in an alternative embodiment, the preset plurality of risk areas includes a risk unacceptable area, a risk management area, a normal control area;
in the step S50, the step of outputting the determined risk area includes:
and determining the color corresponding to the current risk area according to the colors corresponding to the multiple risk areas respectively, and displaying the current risk area by adopting the determined color.
In one particular embodiment, different risk zones may be displayed in different colors, e.g., red zones represent risk unacceptable zones; orange or yellow areas represent risk management areas; the green area represents the normal control area.
Further, in an alternative embodiment, the evaluation result further includes an Allowable Configuration Time (ACT), wherein the ACT is calculated from a combination of the accumulated risk and the instantaneous risk. Further, step S40 includes:
when the specific event is that the configuration of the nuclear power plant is changed, if the current risk area is a risk unacceptable area, the corresponding risk management measure is that the unit is immediately retracted to a safe state; if the current risk area is a risk management area, the corresponding risk management measures are entering an operation decision flow and tracking fault processing of the out-of-service equipment in the allowed configuration time; if the current risk area is a normal control area, the corresponding risk management measure is to normally execute daily work;
when the specific event is the planned maintenance of the nuclear power plant, if the current risk area is a risk unacceptable area, the corresponding risk management measure is to immediately adjust the maintenance plan; if the current risk area is a risk management area, the corresponding risk management measures are entering a major repair decision flow and tracking subsequent plan adjustment in the allowed configuration time; if the current risk area is a normal control area, the corresponding risk management measures are to carry out maintenance according to the plan.
In this embodiment, for a configuration change event occurring in a nuclear power plant, that is, when running configuration risk management is performed, if a risk unacceptable area is entered, measures are required immediately, and if the reactor is in a power running mode, shutdown and back-off are required immediately; if entering the risk management area, corresponding risk management measures and risk compensation measures are needed to be adopted, and the Allowable Configuration Time (ACT) is controlled according to an accumulated risk threshold (ICDP/ILERP); if the normal control area is entered, the daily work can be normally performed in the area. For the development of planned maintenance events occurring in a nuclear power plant, namely, when maintenance configuration risk management is performed, if a risk unacceptable area is entered, active entry is not allowed, namely, preventive maintenance work for entering a red area is not arranged any more, and a maintenance plan needs to be adjusted; if the risk management area is entered, the ACT is controlled, corresponding risk management and risk compensation measures are adopted, and the risk management measures are evaluated; if the normal control area is entered, maintenance can be carried out according to the plan.
In a specific embodiment, regarding the operation configuration risk management flow, it should be further noted that, when the power plant is in normal operation, an abnormal operation occurs, that is, an unintended situation that causes one or more safety critical devices (SSC within the configuration risk management range) to be unavailable, and in addition to the supervision measures specified by the implementation technical specification, the flow of performing the operation configuration risk management by the nuclear power plant operator will be described, including quantitatively evaluating the configuration risk by using a risk monitor tool, and taking corresponding risk management measures according to the region where the risk is located, where the risk zone may be specifically classified into a red zone, an orange zone, a yellow zone, and a green zone according to the risk level. If the running configuration risk is in the green area, normal daily work is performed, and usually, a red area is not needed to be entered, and risk management measures are needed to be taken immediately after the red area is entered. When the emergency power plant enters an orange zone, an emergency defect elimination processing flow is entered, and an operation decision flow is started, wherein the emergency defect elimination processing flow and the operation decision flow are all existing flows of the nuclear power plant. And when entering the yellow area, calculating and controlling the ACT, namely finishing the operation time as soon as possible, shortening the unavailable time of the system/equipment, formulating corresponding risk management measures according to the requirement of a risk management matrix, and carrying out evaluation.
In a specific embodiment, regarding the maintenance configuration risk management flow, it should be further noted that, for a power plant maintenance plan, including a daily work plan, a weekly rolling plan and a major repair production plan, configuration risk evaluation is performed, especially, risk evaluation and management content required in a maintenance rule outline, then a risk monitor tool is adopted to quantitatively evaluate configuration risk, and corresponding risk management measures are adopted according to an area where the risk is located, specifically, a risk area is divided into a red area, an orange area, a yellow area and a green area according to a risk level from high to low. If the maintenance is in the risk green zone, normally executing maintenance activities; if the maintenance action is in the risk management area, the maintenance action is required to be completed as soon as possible, the configuration time is allowed to be determined by the accumulated risk limit value calculation result, the ACT is calculated and controlled, namely, the ACT cannot be consumed through various resources, compensation measures are taken when necessary, and the risk management measures are evaluated; if the risk is in the red region, immediate action is needed to reduce the risk. Typically, nuclear power plants do not actively enter into a risk red zone when making and conducting maintenance activities.
Further, in an alternative embodiment, after step S50, the method further includes:
and step S60, judging whether the current state meets the preset exit condition according to the current running state of the nuclear power plant, and if so, ending.
Further, in step S60, it is determined whether a preset exit condition is currently satisfied, including at least one of the following:
the maintenance activities for the out-of-service equipment have been completed and no new specific event has occurred within a specific time;
preventive, corrective maintenance activities for the equipment involved in the trial maintenance activities have completed and no new specific event has occurred within a specific time;
the systems/devices/structures in the first list are all in a usable state.
The nuclear power plant enters an emergency incident management code.
In this embodiment, after the running configuration risk management or the maintenance configuration risk management is completed, if it is determined that the above condition is satisfied, the configuration risk management flow may be exited.
The invention also constructs a nuclear power plant configuration risk management system comprising a processor and a memory storing a computer program, the processor implementing the steps of the method for nuclear power plant configuration risk management described above when executing the computer program.
The present invention also constructs a computer storage medium storing a computer program which, when executed by a processor, implements the steps of the nuclear power plant configuration risk management method described above.
The above description is only of the preferred embodiments of the present invention and is not intended to limit the present invention, but various modifications and variations can be made to the present invention by those skilled in the art. Any such modifications, equivalents, and improvements that fall within the spirit and principles of the present invention are intended to be covered by the following claims.
Claims (10)
1. A method for managing configuration risk of a nuclear power plant, comprising:
step S10, when a specific event occurs, acquiring the current running state of the nuclear power plant in real time, and judging whether the current running state meets a preset entering condition or not according to the running state, wherein the specific event comprises the occurrence of configuration change of the nuclear power plant and the development of planned maintenance of the nuclear power plant;
step S20, when the entering condition is met, carrying out configuration risk evaluation according to a risk model of the nuclear power plant so as to obtain a current evaluation result, wherein the evaluation result comprises a risk level value;
step S30, determining a current risk zone corresponding to the current risk level value according to the specific event, a plurality of preset risk zones and the risk level range value corresponding to each risk zone;
step S40, acquiring current risk management measures corresponding to the current risk areas according to the risk management measures corresponding to each risk area under different preset specific events;
step S50, outputting the current risk area and the current risk management measures.
2. The method of claim 1, wherein determining whether a preset entry condition is satisfied according to the operating state comprises:
step S11, determining current affected equipment according to the running state, wherein the affected equipment comprises equipment involved in out-of-service equipment or experimental maintenance activities;
step S12, determining whether a preset entry condition is satisfied according to a first list, a second list, a third list and the affected device, where the first list is a system/device/structure list related to a configuration risk management outline of a nuclear power plant, the second list is a system/device/structure list related to an implementation outline of a maintenance rule of the nuclear power plant, and the third list is a device list related to at least one technical specification.
3. The method for managing risk of configuration of a nuclear power plant according to claim 2, wherein said step S12 comprises:
judging whether the shutdown equipment is equipment which exists in the first list and the third list at the same time, if so, judging whether the management measures aiming at the shutdown equipment in the technical specification are not immediately shutdown and back-off, and if not, determining that a preset entry condition is met; and/or the number of the groups of groups,
judging whether equipment related to the test maintenance activity exists in the first list, and if so, determining that a preset entering condition is met; and/or the number of the groups of groups,
judging whether equipment related to the test maintenance activity exists in the second list, if so, determining that a preset entering condition is met;
judging whether the out-of-service equipment belongs to specific equipment related to specific technical specifications in the third list, and if so, determining that a preset entering condition is met.
4. The method of claim 1, wherein the risk level values include an instantaneous risk level value and an accumulated risk level value;
the step S30 includes:
when the specific event is a configuration change of the nuclear power plant, determining a risk zone corresponding to the current instantaneous risk level value according to a plurality of preset risk zones and the instantaneous risk level range value corresponding to each risk zone;
and when the specific event is the planned maintenance of the nuclear power plant, determining a risk zone corresponding to the current accumulated risk level value according to a plurality of preset risk zones and the accumulated risk level range value corresponding to each risk zone.
5. The method for managing risk of configuring a nuclear power plant according to claim 1, wherein the preset plurality of risk areas includes a risk unacceptable area, a risk management area, a normal control area;
in the step S50, the step of outputting the determined risk area includes:
and determining the color corresponding to the current risk area according to the colors corresponding to the multiple risk areas respectively, and displaying the current risk area by adopting the determined color.
6. The nuclear power plant configuration risk management method of claim 5, wherein the evaluation result further includes a permissible configuration time;
the step S40 includes:
when the specific event is that the configuration of the nuclear power plant is changed, if the current risk area is a risk unacceptable area, the corresponding risk management measure is that the unit is immediately retracted to a safe state; if the current risk area is a risk management area, the corresponding risk management measures are entering an operation decision flow and tracking fault processing of the out-of-service equipment in the allowed configuration time; if the current risk area is a normal control area, the corresponding risk management measure is to normally execute daily work;
when the specific event is the planned maintenance of the nuclear power plant, if the current risk area is a risk unacceptable area, the corresponding risk management measure is to immediately adjust the maintenance plan; if the current risk area is a risk management area, the corresponding risk management measures are entering a major repair decision flow and tracking subsequent plan adjustment in the allowed configuration time; if the current risk area is a normal control area, the corresponding risk management measures are to carry out maintenance according to the plan.
7. The method of claim 2, further comprising, after step S50:
and step S60, judging whether the current state meets the preset exit condition according to the current running state of the nuclear power plant, and if so, ending.
8. The method according to claim 7, wherein in step S60, it is determined whether a preset exit condition is currently satisfied, including at least one of:
the maintenance activities for the out-of-service equipment have been completed and no new specific event has occurred within a specific time;
preventive, corrective maintenance activities for the equipment involved in the trial maintenance activities have completed and no new specific event has occurred within a specific time;
the systems/devices/structures in the first list are all in a usable state.
9. A nuclear power plant configuration risk management system comprising a processor and a memory storing a computer program, wherein the processor, when executing the computer program, implements the steps of the nuclear power plant configuration risk management method of any of claims 1-8.
10. A computer storage medium storing a computer program, characterized in that the computer program, when executed by a processor, implements the steps of the nuclear power plant configuration risk management method of any of claims 1-9.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202311316983.5A CN117522108A (en) | 2023-10-11 | 2023-10-11 | Nuclear power plant configuration risk management method, system and computer storage medium |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202311316983.5A CN117522108A (en) | 2023-10-11 | 2023-10-11 | Nuclear power plant configuration risk management method, system and computer storage medium |
Publications (1)
Publication Number | Publication Date |
---|---|
CN117522108A true CN117522108A (en) | 2024-02-06 |
Family
ID=89746476
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202311316983.5A Pending CN117522108A (en) | 2023-10-11 | 2023-10-11 | Nuclear power plant configuration risk management method, system and computer storage medium |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN117522108A (en) |
-
2023
- 2023-10-11 CN CN202311316983.5A patent/CN117522108A/en active Pending
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN109102089A (en) | A kind of system monitor method based on effectiveness of maintenance assessment | |
CN107705018A (en) | A kind of Demonstration Method for nuclear power plant's routine test cycle stretch-out | |
CN109978500A (en) | A kind of nuclear power station power loss trial system | |
CN110782173A (en) | Deduction method for emergency power event of ubiquitous power Internet of things | |
Gil et al. | A code for simulation of human failure events in nuclear power plants: SIMPROC | |
CN113972019B (en) | Nuclear power plant accident handling strategy generation method and device and electronic equipment | |
CN117522108A (en) | Nuclear power plant configuration risk management method, system and computer storage medium | |
CN115660422A (en) | Safety barrier performance evaluation method and system for ship human-caused risk management and control | |
Wang et al. | Configuration Risk Management Support for the Maintenance Rules at Qinshan NPP1 | |
Hari Prasad et al. | Risk management of NPPs using risk monitors | |
Santoso et al. | Reactor Operational Experience Review and Analysis Based on Un-intended Reactor Trip Data | |
Yang | Application of risk-informed decision for online maintenance of Tianwan Nuclear Power Plant safety systems | |
Viktorova et al. | Reliability models and analysis of systems with protection | |
Zhang et al. | Review of the Configuration Risk Management Methodologies | |
CN114997437B (en) | Core damage frequency calculation method and system based on production tasks of nuclear power plant | |
Wang et al. | THE APPLICATIONS OF PSA TECHNIQUE IN IMPLEMENTING THE MAINTENANCE RULE FOR NPP | |
Liu et al. | Application of Risk-Informed Approach in Emergency Compressor Emergency Backup Function Test | |
Kancev et al. | Human reliability analysis in NPP: A plant-specific sensitivity analysis considering dynamic operator actions versus accident management actions | |
Puglia et al. | Examination of issues related to the development and implementation of real-time operational safety monitoring tools in the nuclear power industry | |
Min et al. | EQUIPMENT PERFORMANCE-BASED RISK MONITORING AND PREDICTION TECHNOLOGY FOR NUCLEAR POWER PLANT | |
CN118886710A (en) | Nuclear power unit safety state supervision and evaluation method, system and readable storage medium | |
CN117933965A (en) | Nuclear power plant maintenance activity optimization method and equipment based on maintenance rules | |
Liu et al. | Application of Probabilistic Safety Analysis for Nuclear Power Plant Overhaul Risk Assessment | |
CN114529201A (en) | System health state evaluation method, device, equipment and storage medium of nuclear power unit | |
Wu et al. | The Application of Risk-Informed Decision-Making Approach in Optimization of Allowed Outage Time for Safety System in Nuclear Power Plant |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PB01 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination |