CN107705018A - A kind of Demonstration Method for nuclear power plant's routine test cycle stretch-out - Google Patents
A kind of Demonstration Method for nuclear power plant's routine test cycle stretch-out Download PDFInfo
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Abstract
The present invention provides a kind of Demonstration Method for nuclear power plant's routine test cycle stretch-out, comprises the following steps：It is instrument check kind equipment and non-instrument check kind equipment by the safety-related device class in nuclear power plant, and different Demonstration Methods is used for the routine test of the safety-related equipment of different classifications.For non-instrument check kind equipment, introduce risk-informed type analysis method, caused reactor core probability of damage increment after routine test cycle stretch-out is assessed and proved, and by it compared with the permission increment criterion of rules and regulations, determines the feasibility of routine test cycle stretch-out.For instrument check kind equipment, the shift analysis based on mathematical statistics is used, quantitatively calculates the drift value after cycle stretch-out, carries out the feasibility of comprehensive descision cycle stretch-out.Mathematical statistics and risk-informed type analysis are combined by the Demonstration Method, and precisely effectively nuclear power plant's routine test cycle stretch-out can be assessed.
Description
Technical field
The present invention relates to nuclear power plant's routine test period modulation technical field, is united more particularly, to one kind based on mathematics
The Demonstration Method for nuclear power plant's routine test cycle stretch-out that meter and risk-informed type analysis are combined.
Background technology
In order to ensure the nuclear safety of nuclear power plant in the state of accident, nuclear power plant has all formulated strict routine test system,
Provide to be particularly equipment and should perform the problem of existing with discovering device in strict accordance with certain frequency with nuclear safety relevant device,
Ensure the availability and reliability of equipment.Domestic PWR nuclear power plant at present mainly using 18 months modes reloaded, by
There is different degrees of long-term low power run and shut down standby feelings in the influence of power network power demand, domestic multiple nuclear power plants
Condition.In order to improve nuclear power generating sets capability facfor, the flexibility for improving major overhaul arrangement, improvement economy of power plant benefit, nuclear power industry
It is main to wish under the restriction of current long-term low power run, increase single cycle run time (extending to 24 months), this just needs
Extension demonstration is carried out to the routine test cycle, test period extension must assure that nuclear safety and the availability of relevant device first
And reliability.
Current domestic nuclear power generating sets are in routine test cycle stretch-out demonstration, mainly using Experience Feedback method.Experience
Feedback transmitter is the system and equipment for intending extending the test period, passes through operating experience, failure mode analysis (FMA) and engineering judgement, opinion
Confirmatory test cycle stretch-out is to the feasibility for drafting the cycle.The system and equipment for intending the test period are characterized in, passes through operation
Experience, failure mode analysis (FMA) and engineering judgement, demonstration testing cycle are arranged to work out the feasibility in cycle.In principle, using this
Method needs to treat that demonstration system and equipment are all more than or equal to routine test is worked out in identical or close running environment
The operating experience and result of the test of phase is good, so as to support to work out the cycle less than or equal to empirical value.Wait to discuss if retrieved
Card equipment bad O＆M Experience Feedback data be present, then need one by one to analyze this part bad data, if from therefore
Barrier consequence and fault mode etc. can exclude influence of the bad data to security function, and proving result can be by.
If technical Analysis can not exclude influence of the bad data to security function, the demonstration result of Experience Feedback method cannot lead to
Cross.
Existing Experience Feedback method carries out cycle demonstration and needs to refer to the good long-term operation experience that power station has, and mesh
Preceding domestic nuclear power generating sets were generally reloaded using 18 months, therefore the test period only has 18 months.If be more than 18 months
Routine test cycle stretch-out prove (such as 24 months cycle), then may be referred to, therefore make without the service data of correlation
Drift value situation of change of the instrument for performing security function after cycle stretch-out can not be analyzed by obtaining Experience Feedback method, so that can not
Quantitative analysis is made in influence to safety；Experience Feedback method is unable to the risk change that quantitative analysis goes out after test period extension simultaneously
Situation, it can not also judge the sensitiveness that test period change influences on unit safety, be worked out for shortage and extend test period fortune
The equipment tested of passing through is also inapplicable.Because of the technical limitation of Experience Feedback method, simple Experience Feedback method is difficult to competent fixed
Phase experiment extends to the cycle demonstration of 24 months.
The content of the invention
The technical problem to be solved in the present invention is, can not analyze for the Experience Feedback method of prior art and performs safety
Drift value situation of change of the instrument of function after cycle stretch-out, so as to which quantitative analysis can not be made to the influence of Nuclear Safety,
Experience Feedback method is unable to the defects of risk situation of change after quantitative analysis goes out test period extension simultaneously, there is provided a kind of by mathematics
Statistics is combined with risk-informed type application, and effectively nuclear power plant's routine test cycle stretch-out can be assessed is used for nuclear power
The Demonstration Method of factory's routine test cycle stretch-out.
The technical solution adopted for the present invention to solve the technical problems is：One kind is provided and is used for nuclear power plant's routine test cycle
The Demonstration Method of extension, comprises the following steps：
S1, it is instrument check kind equipment and non-instrument check kind equipment by the safety-related device class in nuclear power plant, and
Routine test for the safety-related equipment of different classifications uses different Demonstration Methods, and non-instrument check kind equipment is performed
Step S2, and step S3 is then performed to instrument check kind equipment；
S2, for non-instrument check kind equipment, introduce risk-informed type (Risk Informed) analysis method, assess and
Prove caused reactor core probability of damage increment after routine test cycle stretch-out, and the permission increment criterion of itself and rules and regulations is entered
Row compares, and determines the feasibility of routine test cycle stretch-out；Then step S4 is performed；
S3, for instrument check kind equipment, use the shift analysis based on mathematical statistics, quantitatively calculate cycle stretch-out
Drift value afterwards, analysis drift value whether influence system perform security function ability, carry out comprehensive descision cycle stretch-out can
Row；Then step S4 is performed；
S4, for non-instrument check kind equipment, if analysis result shows that routine test cycle stretch-out is horizontal to overall risk
The influence of (CDF and LERF) then judges that routine test cycle stretch-out is feasible, otherwise adjusts within the scope of the receiving of defined risk
Routine test frequency re-starts risk assessment；
For instrument check kind equipment, if the drift value after cycle stretch-out judges week in protection setting limits
Phase extends feasible.
Preferably, in step s 4, for instrument check kind equipment, if the drift value after cycle stretch-out is set beyond protection
Limits, then modification protection setting limit value makes it not be broken, while changes corresponding running technology specification.
In addition to following sub-step preferably, in step s 2,：
If not S21, instrument check kind equipment are then carried out quantifying risk analysis, performed by nuclear power plant PSA model modellings
Step S22；If not instrument check kind equipment can not then be carried out risk and qualitatively analyzed, performed by nuclear power plant PSA model modellings
Step S23；
S22, modelling will be carried out according to PSA models by the non-instrument check kind equipment of routine test cycle stretch-out, and obtained
Overall risk horizontal (CDF and LERF) before and after routine test cycle stretch-out situation of change；
S23, this body structure of non-instrument check kind equipment and residing system are analyzed.
Preferably, step S22 also includes following sub-step：
S221, according to nuclear power plant's PSA models, mould is carried out to the non-instrument check kind equipment by routine test cycle stretch-out
Change；
S222, analyze increment of the routine test cycle stretch-out to risk level；
If the risk increment after S223, assessment routine test cycle stretch-out, which belongs to, receives scope, judge to receive periodically examination
Cycle stretch-out is tested, the effect for otherwise adjusting the frequency of routine test and re-starting risk level is assessed.
Preferably, in step S221, PSA pattern dies is carried out to non-instrument check kind equipment and are divided into direct modelling and not
Two kinds of situations of direct modelling, in the case of not direct modelling, it is fixed to be embodied by way of changing PSA models or indirect modelling
Test period phase extends the influence to the non-instrument check kind equipment.
Preferably, in step S222, divide in terms of origination event influence, mitigation capability influence and combined effect three
The effect of analysis and assessment routine test cycle stretch-out to risk level, and the dependability parameter of non-instrument check kind equipment is lost
The hypothesis for imitating data performs sensitivity analysis, it is ensured that the hypothesis coherent reasonability and conservative.
Preferably, in step S23, this body structure and residing system of non-instrument check kind equipment are analyzed
Afterwards, if it is determined that this body structure or residing system are associated with reactor core security risk, then device level labor, the analysis bag are performed
Include routine test cycle stretch-out in PSA models it is risky contribution item influence.
In addition to following sub-step preferably, in step s3,：
S31, according to mathematical statistics carry out shift analysis, the shift analysis is based on instrument history verification data；
S32, the drift value after cycle stretch-out is quantitatively calculated using statistical method, remembered during analysis meter verification or supervision
The AFAL data of record；
S33, judge whether cycle stretch-out is feasible.
Preferably, in step S33, judge include following factor when whether cycle stretch-out is feasible：
A) by AFAL verification datas, judge whether the instrument drift value before cycle stretch-out exceedes protection setting limit value；
B) judge whether drift value caused by cycle stretch-out influences safe shutdown；
C) judge the condition of protection setting limit value and safety analysis is in the acceptance criteria of routine test program with hypothesis
It is no to be embodied；
D) routine test program is established, monitored for prolonged periods of time and assessment cycle extend to instrument drift and the influence of safety.
The beneficial effects of the present invention are mathematical statistics and risk-informed type analysis are combined by the Demonstration Method, can
Precisely effectively nuclear power plant's routine test cycle stretch-out is assessed, after the evaluation test cycle extended to 24 months by 18 months
Influence to npp safety, and then realize and extend nuclear power plant's test period, on the premise of nuclear safety level is ensured, improve core
Group of motors capability facfor, the flexibility of major overhaul arrangement is improved, so as to comprehensive improvement nuclear power plant economic benefit.
Brief description of the drawings
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing：
Fig. 1 is that the general flow for the Demonstration Method preferred embodiment that the present invention is used for nuclear power plant's routine test cycle stretch-out is shown
It is intended to；
Fig. 2 is the son that the present invention is used for step S2 in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
The schematic flow sheet of step；
Fig. 3 is that the present invention is used for step S22 in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
The schematic flow sheet of sub-step；
Fig. 4 is that the present invention is used to be directed to non-instrument in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
Verify the analysis process schematic diagram of kind equipment；
Fig. 5 is that the present invention is used for protection setting limit in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
The relation schematic diagram of value；
Fig. 6 is that the present invention is used to be directed to instrument school in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
Test the analysis process schematic diagram of kind equipment.
Embodiment
In order to which technical characteristic, purpose and the effect of the present invention is more clearly understood, now compares accompanying drawing and describe in detail
The embodiment of the present invention.
First, pair present invention demonstrates that the multiple nuclear power field important terms repeatedly occurred in method have following definition to conciliate
Release：
Routine test：In order to ensure the good operation of nuclear power plant system or equipment, by the way of experiment periodic verification with
Nuclear safety function related system and equipment availability, unit shape when content is including test objective, the function to be verified, experiment
State, test period (how long carrying out a test)；When above-mentioned requirements can not meet, it is believed that the work(to be verified of the experiment
Energy or equipment are unavailable；
Cycle proves：By the analysis of science, the cycle of routine test is proved, is ensureing that npp safety is horizontal
On the premise of, (as extended the test period) is optimized to the cycle of routine test, so as to improve nuclear power generating sets capability facfor, change
Kind nuclear power plant economy；
Instrument is drifted about：The slow change of measuring instrument meter characteristic, the index are reflected under the conditions of defined, measuring instrument
Meter characteristic caused change with the time.
AFAL：By to drift of the instrument passage after a period of time is run compared with initial drift, to characterize this
Drift value situation of change of the passage in this period.
Risk-informed type (Risk Informed) analysis method：It is in Traditional project analysis (it is determined that by, engineering judgement etc.)
On the basis of supplement probabilistic safety analysis evaluation (PSA) analysis result formed it is a kind of cover analysis information analysis, certainly
Plan and the method for management.It considers the influence of various factors, and carries out quantitative analysis to risk, is carried for security-related problem
For comprehensive decision recommendation, the economy of raising nuclear power on the premise of npp safety level is ensured.
Fig. 1 is that the general flow for the Demonstration Method preferred embodiment that the present invention is used for nuclear power plant's routine test cycle stretch-out is shown
It is intended to.Present invention demonstrates that method comprises the following steps：
S1, it is instrument check kind equipment and non-instrument check kind equipment by the safety-related device class in nuclear power plant, and
Routine test for the safety-related equipment of different classifications uses different Demonstration Methods, and non-instrument check kind equipment is performed
Step S2, and step S3 is then performed to instrument check kind equipment.Since it is considered that the instrument drift after routine test cycle stretch-out
It may result in instrument execution security function (including safe shutdown ability) to be affected, therefore be by safety-related device class
Instrument check kind equipment and non-instrument check kind equipment.
S2, for non-instrument check kind equipment, introduce risk-informed type (Risk Informed) analysis method, assess and
Prove caused reactor core probability of damage increment after routine test cycle stretch-out, and the permission increment criterion of itself and rules and regulations is entered
Row compares, and determines the feasibility of routine test cycle stretch-out；Then step S4 is performed.Gone through in addition, the analysis method can also combine
History operation data is analyzed, and judges influence of the cycle stretch-out to safety, and whether influence the hypothesis of license file.
S3, for instrument check kind equipment, it is necessary to which analysis meter drifts about to safety in the cycle stretch-outs demonstration of 24 months
The influence of function.The shift analysis based on mathematical statistics is used, quantitatively calculates the drift value after cycle stretch-out, analysis drift
Whether amount influences the ability that system performs security function, carries out the feasibility of comprehensive descision cycle stretch-out；Then step S4 is performed.
S4, for non-instrument check kind equipment, if analysis result shows that routine test cycle stretch-out is horizontal to overall risk
The influence of (CDF and LERF) then judges that routine test cycle stretch-out is feasible, otherwise adjusts within the scope of the receiving of defined risk
Routine test frequency re-starts risk assessment.For instrument check kind equipment, if the drift value after cycle stretch-out is set in protection
In the range of threshold value, then judge that cycle stretch-out is feasible.
CDF (Core Damage Frequency) is reactor core probability of damage, and LERF (Large Early Release
Frequency) it is radioactive substance early stage a large amount of release probability.The two probability are all the concepts in probabilistic safety analysis, are led to
Cross probabilistic safety analysis and calculate and above-mentioned risk is quantified.Probabilistic safety analysis method is a kind of to be based on probability theory
System analysis method.It is one of method of two kinds of safety analyses of nuclear power station, nuclear power can be found out with the security of qualitative assessment nuclear power station
Stand design, build and operating weak link, propose ensure nuclear plant safety operation recommendation on improvement.
In step s 4, for instrument check kind equipment, if the drift value after cycle stretch-out is beyond protection setting limit value model
Enclose, then modification protection setting limit value makes it not be broken, while changes corresponding running technology specification.
In cycle stretch-out analysis above, if final draw can prolong macrocyclic conclusion, analysis judgement must be
Influence after cycle stretch-out to Nuclear Safety is very little.Cycle stretch-out demonstration include following important consideration in terms of three because
Element：
1) whether equipment has high reliability, alternative means and redundancy, includes the inherent reliability of equipment；Verification experimental verification
Function whether by other it is more short-period experiment covered；Redundancy, the diversity of function performed by equipment.Simultaneously to going through
History data are analyzed, and are identified the Failure count of equipment, consequence, reason in historical events, are analyzed the seriousness of failure effect, are
It is no to have mitigation strategy, the relation with the time, influence of the comprehensive descision to safety.
2) when the conditions set forth above are not met, using risk-informed type (Risk Informed) analysis method, nuclear power plant is utilized
PSA models, by changing the failure probability of routine test correlation nuclear safety function, evaluate caused by after routine test cycle stretch-out
Reactor core probability of damage increment, by by the risk increment compared with the permission increment criterion in relevant laws and regulations and specification, really
Determine the feasibility of test period extension.
3) the safety hypothesis in safety analysis is not interfered with.
Fig. 2 is the son that the present invention is used for step S2 in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
The schematic flow sheet of step.In step s 2, in addition to following sub-step：
If not S21, instrument check kind equipment are then carried out quantifying risk analysis, performed by nuclear power plant PSA model modellings
Step S22；If not instrument check kind equipment can not then be carried out risk and qualitatively analyzed, performed by nuclear power plant PSA model modellings
Step S23.
Generally had to the Cycle Assessment mode of routine test using risk-informed type analysis method described above qualitative and fixed
Two methods of amount analysis, the analyst coverage of the two methods all include all risk contribution considerations, including inner primary
Power and the risk of shutdown, fire risk, water logging risk, earthquake and external disaster risk.
S22, modelling will be carried out according to PSA models by the non-instrument check kind equipment of routine test cycle stretch-out, and obtained
Overall risk horizontal (CDF and LERF) before and after routine test cycle stretch-out situation of change.In addition, also need to determine periodically to try
Test whether influence of the cycle stretch-out to a certain particular device can pass through FMEA methods by PSA model modellings, the process
To complete.
Importantly, after according to PSA model modellings, next it is required to determine that how to find a kind of rational expression side
Formula quantifies influence of the cycle stretch-out to nuclear power risk so as to realize.
S23, this body structure of non-instrument check kind equipment and residing system are analyzed.In step S23, to non-
After this body structure of instrument check kind equipment and residing system are analyzed, if it is determined that this body structure or residing system and reactor core
Security risk is associated, then performs device level labor, and the analysis includes routine test cycle stretch-out to owning in PSA models
Risk contributes the influence of item.
Fig. 3 is that the present invention is used for step S22 in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
The schematic flow sheet of sub-step.Step S22 also includes following sub-step：
S221, according to nuclear power plant's PSA models, mould is carried out to the non-instrument check kind equipment by routine test cycle stretch-out
Change；
S222, analyze increment of the routine test cycle stretch-out to risk level；
If the risk increment after S223, assessment routine test cycle stretch-out, which belongs to, receives scope, judge to receive periodically examination
Cycle stretch-out is tested, the effect for otherwise adjusting the frequency of routine test and re-starting risk level is assessed.
In step S221, PSA pattern dies are carried out to non-instrument check kind equipment and are divided into direct modelling and not direct mould
Change two kinds of situations, in the case of not direct modelling, embody routine test by way of changing PSA models or indirect modelling
Influence of the cycle stretch-out to the non-instrument check kind equipment.
In step S222, analyze and comment in terms of origination event influence, mitigation capability influence and combined effect three
Test period assessment phase extends the effect to risk level, and to the dependability parameter fail data of non-instrument check kind equipment
Hypothesis perform sensitivity analysis, it is ensured that the hypothesis coherent reasonability and conservative.
In step S22 and step 23, quantitative analysis either is carried out to risk and still qualitatively analyzed, all should
Analytical cycle extends front and rear risk change in terms of following three：
1) to the influence of origination event：I.e. whether routine test cycle stretch-out influences existing origination event frequency or introduces new
Origination event；
2) to the influence of mitigation capability：I.e. whether routine test cycle stretch-out causes the mitigation capability of safety-related systems to carry
High or degradation；
3) combined effect：Origination event and mitigation capability are all impacted after routine test cycle stretch-out.
In addition, the dependability parameter fail data of safety-related equipment is done necessarily in quantifying riskization analysis process
It is assumed that there is a certain internal relation in the reliability of i.e. experiment relevant device with the test period.During quantitative analysis, it should
Sensitivity analysis is performed to these hypothesis to ensure to assume being reasonable and conservative.If sensitivity analysis result shows periodically to try
Influence of the cycle stretch-out to CDF and LERF is tested still within the scope of risk receiving as defined in nuclear power generating sets is specified, then it is assumed that periodically
Test period optimization aim is acceptable, otherwise needs adjustment routine test frequency to reappraise its risk.
It should be noted that the risk increment after cycle stretch-out should be sufficiently small or reduce.Two sets of generally use
Whether reducing risk is subjected to determine that its risk changes：Risk change respectively caused by single test periodic change
Caused accumulative risk, this two classes risk must all are fulfilled for risk limit value with the change of multiple test periods.
Situation applicable step S23 is if the system or part that are influenceed by routine test periodic change can not pass through nuclear power
Factory PSA model modellings, then qualitative analysis or estimate analysis are performed, so as to which the prompting of the influence after routine test periodic change can be provided
Information.Qualitative analysis can be analyzed first since system or structure rank, if it find that system or structure are for reactor core safety wind
Danger has certain association, then needs further to perform the analysis of device level.As Such analysis, it should analyze the test period
The influence to all PSA risk contribution factors is changed, but generally should be since inner primary full power event analysis, specifically
During analysis, it can also be accounted for from following several respects：
1) the non-instrument check kind equipment influenceed by periodic change, whether it has an impact after failing to a certain origination event；
2) whether to preventing, reactor core damages the non-instrument check kind equipment influenceed by periodic change or a large amount of early stages discharge
Contribute；
3) whether it is prevention or alleviates the other systems of event or the support system of structure.
If after above-mentioned analysis, it is believed that the non-instrument check kind equipment of the periodic change that is put to the test influence and above-mentioned three kinds
Considerations are without obvious correlation, then it is assumed that and the test period extends on reactor core safety and radioactivity release frequency without influence,
The test period of this determination can be extended for the target period of selection.
, it is necessary to in-service according to nuclear power plant's inservice inspection outline, all previous overhaul after analyst coverage and analysis border is determined
Inspection result report, FSAR, system design handbook, system flow chart, isometric figure, stress analysis report, phase
Close the material such as log sheet collect weld information, piping material, pipeline specification, existing inservice inspection outline relevant information,
The information such as pipeline space arrangement, operation characteristic and history run are in order to follow-up correlation analysis.
It is further of importance that, it is necessary to follow when being analyzed using risk-informed type (Risk Informed) analysis method
Following principle：
1) cycle stretch-out can not reduce the requirement of nuclear power plant's depth defense；
2) cycle stretch-out can not influence the safety allowance that nuclear power plant keeps enough；
3) caused reactor core probability of damage increment must be sufficiently small after cycle stretch-out；
4) measure is must be set up to supervise the equipment performance variation tendency after test period extension.
Fig. 4 is that the present invention is used to be directed to non-instrument in the Demonstration Method preferred embodiment of nuclear power plant's routine test cycle stretch-out
Verify the analysis process synthesis schematic diagram of kind equipment.
In step s3, in addition to following sub-step：
S31, according to mathematical statistics carry out shift analysis, the shift analysis is based on instrument history verification data；
S32, the drift value after cycle stretch-out is quantitatively calculated using statistical method, remembered during analysis meter verification or supervision
The AFAL data of record；
S33, judge whether cycle stretch-out is feasible.
Wherein, evaluation history instrument check data provide a kind of mode for characterizing instrument or instrument group performance, and target is
The anticipatory behavior of instrument is understood by the performance before assessing.The attribute of performance paid close attention in this case is instrument drift.
Analytical technology mentioned here is recorded based on the drift value obtained using statistical during verifying or supervise by analysis meter
AFAL data, this analysis method be referred to as AFAL analysis.AFAL analyses are very suitable for characterizing instrument drift, can be used as instrument
The mode of table drift research.And Fig. 6 is the Demonstration Method preferred embodiment that the present invention is used for nuclear power plant's routine test cycle stretch-out
In be directed to instrument check kind equipment analysis process schematic diagram.
Drift forecasting gauge after cycle stretch-out calculates rear, it is necessary to come whether evaluation cycle can prolong with reference to following criterion
It is long：
A) by AFAL verification datas, judge whether the instrument drift value before cycle stretch-out exceedes protection setting limit value；
B) judge whether drift value caused by cycle stretch-out influences safe shutdown；
C) judge the condition of protection setting limit value and safety analysis is in the acceptance criteria of routine test program with hypothesis
It is no to be embodied；
D) routine test program is established, monitored for prolonged periods of time and assessment cycle extend to instrument drift and the influence of safety.
And it is unsanctioned for the cycle stretch-out demonstration of non-instrument check class, modification test method, change unit execution shape
The mode such as state, engineered is improved.
By above-mentioned instrument shift analysis and evaluation rubric, the drift of the instrument after cycle stretch-out to 24 months is quantitatively calculated
Amount, compared with setting limit value with protection, the drift value after cycle stretch-out is thought in the range of protection sets limit value
Demonstration passes through, and the cycle can extend；, can be by repairing when drift value after cycle stretch-out is in the range of protection setting limit value
Change nominal protection definite value, to ensure that protection setting limit value is not broken, while change corresponding running technology specification.Protection setting
Referring to Fig. 5, Fig. 5 is that the present invention is preferably real for the Demonstration Method of nuclear power plant's routine test cycle stretch-out for the setting and application of limit value
Apply the relation schematic diagram of protection setting limit value in example.
In summary, in the equipment of nuclear power plant, the instrument of security function is performed with the extension of run time, the drift of the instrument
Shifting amount can also change therewith, extend the cycle of check meter (perform security function, including provide safe shutdown ability)
When, it is necessary to solve the problems, such as that instrument drift changes with cycle stretch-out, because it is determined that security system setting value and performing safety
Can consider the instrument error as caused by drift during analysis, it is necessary to analysis meter drift to caused by safety influence, present invention demonstrates that
Method will carry out quantitative analysis using the method for mathematical statistics to the instrument drift after cycle stretch-out, so as to evaluate to Nuclear Safety
Influence.And for other non-instrument cycle stretch-out when, influence of the supervision cycle stretch-out to Nuclear Safety should be assessed, to adapt to
The fuel recycle of 24 months.The assessment should support a conclusion, i.e. influence of the cycle stretch-out to safety is very little.In addition, should
Ensure that history is safeguarded and monitoring data will not make this conclusion invalid.It is ensured that supervised to adapt to the fuel recycle of 24 months limiting
The supervision performance provided under the boundary of interval is provided, any hypothesis in nuclear power plant's licensing basis will not be made to fail.
Simultaneously with the development of the development of nuclear industry circle safety assessment technique, particularly probabilistic safety assessment (PSA) technology
With application, risk-informed type technology can optimize to the routine test cycle, using present invention demonstrates that method manages nuclear power
After factory's routine test, it can effectively extend the routine test cycle, the resource distribution of optimization power plant.
For these reasons, present invention demonstrates that mathematical statistics is combined by method with risk-informed type application, one is developed
The method that set is applied to 24 months cycle stretch-out demonstrations of domestic nuclear power plant, after the evaluation test cycle extended to 24 months by 18 months
Influence to npp safety, and then extend nuclear power plant's test period, on the premise of nuclear safety level is ensured, improve nuclear power machine
Group capability facfor, the flexibility for improving major overhaul arrangement, improve nuclear power plant's economic benefit.
Embodiments of the invention are described above in conjunction with accompanying drawing, but the invention is not limited in above-mentioned specific
Embodiment, above-mentioned embodiment is only schematical, rather than restricted, one of ordinary skill in the art
Under the enlightenment of the present invention, in the case of present inventive concept and scope of the claimed protection is not departed from, it can also make a lot
Form, these are belonged within the protection of the present invention.
Claims (9)
1. a kind of Demonstration Method for nuclear power plant's routine test cycle stretch-out, it is characterised in that comprise the following steps：
S1, by the safety-related device class in nuclear power plant it is instrument check kind equipment and non-instrument check kind equipment, and is directed to
The routine test of the safety-related equipment of different classifications uses different Demonstration Methods, and step is performed to non-instrument check kind equipment
S2, and step S3 is then performed to instrument check kind equipment；
S2, for non-instrument check kind equipment, introduce risk-informed type (Risk Informed) analysis method, assess and demonstration
Caused reactor core probability of damage increment after routine test cycle stretch-out, and the permission increment criterion of itself and rules and regulations is compared
Compared with determining the feasibility of routine test cycle stretch-out；Then step S4 is performed；
S3, for instrument check kind equipment, the shift analysis based on mathematical statistics is used, after quantitatively calculating cycle stretch-out
Whether drift value, analysis drift value influence the ability that system performs security function, carry out the feasibility of comprehensive descision cycle stretch-out；
Then step S4 is performed；
S4, for non-instrument check kind equipment, if analysis result shows routine test cycle stretch-out to overall risk level (CDF
And LERF) influence within the scope of the receiving of defined risk, then judge that routine test cycle stretch-out is feasible, otherwise adjustment is regular
Test frequency re-starts risk assessment；
For instrument check kind equipment, if the drift value after cycle stretch-out judges that the cycle prolongs in protection setting limits
Length is feasible.
2. the Demonstration Method according to claim 1 for nuclear power plant's routine test cycle stretch-out, it is characterised in that in step
In rapid S4, for instrument check kind equipment, if the drift value after cycle stretch-out is beyond protection setting limits, modification protection
Setting limit value makes it not be broken, while changes corresponding running technology specification.
3. the Demonstration Method according to claim 1 for nuclear power plant's routine test cycle stretch-out, it is characterised in that in step
In rapid S2, in addition to following sub-step：
If not S21, instrument check kind equipment then carry out quantifying risk analysis, perform step by nuclear power plant PSA model modellings
S22；If not instrument check kind equipment can not then be carried out risk and qualitatively analyzed, perform step by nuclear power plant PSA model modellings
S23；
S22, modelling will be carried out according to PSA models by the non-instrument check kind equipment of routine test cycle stretch-out, and determined
Test period phase extends front and rear overall risk horizontal (CDF and LERF) situation of change；
S23, this body structure of non-instrument check kind equipment and residing system are analyzed.
4. the Demonstration Method according to claim 3 for nuclear power plant's routine test cycle stretch-out, it is characterised in that step
S22 also includes following sub-step：
S221, according to nuclear power plant's PSA models, modelling is carried out to the non-instrument check kind equipment by routine test cycle stretch-out；
S222, analyze increment of the routine test cycle stretch-out to risk level；
If the risk increment after S223, assessment routine test cycle stretch-out, which belongs to, receives scope, judgement receives routine test week
Phase extends, and the effect for otherwise adjusting the frequency of routine test and re-starting risk level is assessed.
5. the Demonstration Method according to claim 4 for nuclear power plant's routine test cycle stretch-out, it is characterised in that in step
In rapid S221, PSA pattern dies are carried out to non-instrument check kind equipment and are divided into direct modelling and not direct two kinds of situations of modelling,
In the case of not direct modelling, routine test cycle stretch-out is embodied by way of changing PSA models or indirect modelling to this
The influence of non-instrument check kind equipment.
6. the Demonstration Method according to claim 5 for nuclear power plant's routine test cycle stretch-out, it is characterised in that in step
In rapid S222, analysis and assessment routine test week in terms of origination event influence, mitigation capability influence and combined effect three
Phase extends the effect to risk level, and the hypothesis execution to the dependability parameter fail data of non-instrument check kind equipment is quick
Perceptual analysis, it is ensured that the hypothesis coherent reasonability and conservative.
7. the Demonstration Method according to claim 3 for nuclear power plant's routine test cycle stretch-out, it is characterised in that in step
In rapid S23, after this body structure and residing system to non-instrument check kind equipment are analyzed, if it is determined that this body structure or institute
Place's system is associated with reactor core security risk, then performs device level labor, and the analysis includes routine test cycle stretch-out pair
In PSA models it is risky contribution item influence.
8. the Demonstration Method according to claim 1 for nuclear power plant's routine test cycle stretch-out, it is characterised in that in step
In rapid S3, in addition to following sub-step：
S31, according to mathematical statistics carry out shift analysis, the shift analysis is based on instrument history verification data；
S32, the drift value after cycle stretch-out is quantitatively calculated using statistical method, recorded during analysis meter verification or supervision
AFAL data；
S33, judge whether cycle stretch-out is feasible.
9. the Demonstration Method according to claim 7 for nuclear power plant's routine test cycle stretch-out, it is characterised in that in step
In rapid S33, judge include following factor when whether cycle stretch-out is feasible：
A) by AFAL verification datas, judge whether the instrument drift value before cycle stretch-out exceedes protection setting limit value；
B) judge whether drift value caused by cycle stretch-out influences safe shutdown；
C) whether the condition and hypothesis of judgement protection setting limit value and safety analysis obtain in the acceptance criteria of routine test program
To embodiment；
D) routine test program is established, monitored for prolonged periods of time and assessment cycle extend to instrument drift and the influence of safety.
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| CN111814337A (en) * | 2020-07-13 | 2020-10-23 | 上海核工程研究设计院有限公司 | Method for fire risk analysis of nuclear power plant compartment |
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