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IAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

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IAEA-TECDOC-930

Generic componentreliability data

for research reactor PSA

INTERNATIONAL ATOMIC ENERGY AGENCY /A\

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The IAEA does not normally maintain stocks of reports in this series.However, microfiche copies of these reports can be obtained from

INIS ClearinghouseInternational Atomic Energy AgencyWagramerstrasse 5P.O. Box 100A-1400 Vienna, Austria

Orders should be accompanied by prepayment of Austrian Schillings 100,in the form of a cheque or in the form of IAEA microfiche service couponswhich may be ordered separately from the INIS Clearinghouse.

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The originating Section of this publication in the IAEA was:

Safety Assessment SectionInternational Atomic Energy Agency

Wagramerstrasse 5P.O. Box 100

A-1400 Vienna, Austria

GENERIC COMPONENT RELIABILITY DATAFOR RESEARCH REACTOR PSA

IAEA, VIENNA, 1997IAEA-TECDOC-930

ISSN 1011-4289

©IAEA, 1997

Printed by the IAEA in AustriaFebruary 1997

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FOREWORD

Probabilistic safety assessments (PSAs) are increasingly used for safety evaluation of researchreactors. PSA methodology and approaches for research reactors are in general similar to those usedfor power reactors. However, there are some significant differences. The main differences arerelated to the set of data to be used for quantifying the models.

As component reliability data for research reactors was not available in 1988, the IAEA initiateda co-ordinated research programme on data acquisition for research reactors. The aim of theprogramme was to develop rules and procedures for data collection (published as IAEA-TECDOC-636) and to conduct a data collection exercise on thirteen reactor facilities in ten participatingcountries.

The programme lasted for four years. The data collection exercise resulted in a databasecontaining reliability parameters for more than one thousand research reactor components. All thedata is based on the operating experience of participating reactors. The database was compiled duringthe final research co-ordination meeting held in Chalk River, Canada, in 1993.

The report was written by contributors from Austria, Canada and Switzerland and theproduction was co-ordinated by B. Tomic of the Safety Assessment Section of the Division of NuclearSafety. It includes data supplied by all the participants in the co-ordinated research programme.

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EDITORIAL NOTE

In preparing this publication for press, staff of the IAEA have made up the pages from theoriginal manuscript(s). The views expressed do not necessarily reflect those of the governments ofthe nominating Member States or of the nominating organizations.

Throughout the text names of Member States are retained as they were when the text wascompiled.

The use of particular designations of countries or territories does not imply any judgement bythe publisher, the IAEA, as to the legal status of such countries or territories, of their authorities andinstitutions or of the delimitation of their boundaries.

The mention of names of specific companies or products (whether or not indicated as registered)does not imply any intention to infringe proprietary rights, nor should it be construed as anendorsement or recommendation on the part of the IAEA.

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CONTENTS

1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

1.1. Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71.2. Purpose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

2. REACTOR FACILITIES AND DATA COLLECTION METHOD . . . . . . . . . . . . . . . 8

3. INSIGHTS FROM THE DATA COLLECTION PROCESS . . . . . . . . . . . . . . . . . . . 9

4. USE OF THE DATABASE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

4.1. Location of component reliability data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94.2. Accuracy of reliability data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10

4.2.1. Data collection and processing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104.2.2. Component reliability . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 114.2.3. Data selection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

4.3. Reliability data on common cause failure . . . . . . . . . . . . . . . . . . . . . . . . . . . . 134.4. Uncertainty bounds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13

TABLES

Table I. Alphabetical list of component groups and associated codes . . . . . . . . . . . . . . 15Table II. Component type descriptions and associated codes . . . . . . . . . . . . . . . . . . . . 19Table III. Failure mode code definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27Table IV. Features of the contributing research reactor facilities and data collection

process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29Table V. Overview of component types and populations documented for each facility . . . . 31Table VI. Specific information on component types for each facility . . . . . . . . . . . . . . . 41Table VII. Component reliability database . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53

REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69

CONTRIBUTORS TO DRAFTING AND REVIEW . . . . . . . . . . . . . . . . . . . . . . . . . . 71

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1. INTRODUCTION

Information on reliability data for research reactor components was not readily available in theliterature in 1988. Similar information for power reactors is widely available for most power reactortypes, either on a commercial basis or from open literature sources [1-3]. Component reliability datasources for power reactors should provide the best alternative source of relevant data, in the absenceof either site-specific or generic research reactor data. The use of component reliability data forpower reactors, as an alternative to site-specific or generic research reactor data, does however havetwo basic disadvantages. Firstly, design and operational differences in many power reactorcomponents make comparisons difficult. The result is increased uncertainty in the application of ageneric reliability data source for power reactors to a specific research reactor application due todifferences in component type, size and application. Secondly, there are numerous research reactorcomponents that have no counterpart in power reactors.

To overcome the problem of data availability, the IAEA initiated a Co-ordinated ResearchProgramme (CRP) on Data Acquisition for Probabilistic Safety Analysis (PSA) Studies for ResearchReactors, aimed at providing the necessary generic component reliability database. The database,used by most CRP participants, was generated using the DES Data Entry System [4]. The CRPparticipant from ANSTO developed this system for use in conjunction with the data collectionprocess. DES was made available to other participants for data collection and is available from theIAEA for use as a reliability database. The report provides the user with the generic componentreliability database in a summarized spreadsheet format.

While this report focuses primarily on the needs of research reactor PSA, the genericcomponent database also provides a useful reference source of reliability data for other researchreactor applications. For example, typical applications would be the comparison of generic datasources for other research reactor types for the purposes of producing annual reactor operating reviewreports, or for updating reactor safety analysis reports. This type of comparison may assist inproviding useful information about both systems and component operation, in light of internationalexperience with similar research reactor types and equipment. For example, fuel failure rate data orregulating system failure rate comparisons could provide valuable input into research reactorupgrades/deterministic safety analysis programmes in order to supplement the decision making processfor potential design and/or operational changes.

Ideally, failure data used for safety and reliability analyses should be based on site-specific data.However, the production of accurate site-specific data requires the expenditure of considerableresources to develop and maintain an extensive database. The collection of database sourceinformation from the field — i.e. from reactor maintenance and/or operations reports — requires asystematic approach and an ongoing commitment, if the information is to be processed efficiently andif it is to be kept up to date. In addition to the need for operational and maintenance staff to provideraw data input, a software system and analytical personnel to process the raw data are also required.The data processing primarily produces component-reliability-parameter statistics and trend analysisdata. The reliability parameter data is often formatted so that information can interface directly withPSA studies. For example, component failure rate data may be linked to a PSA-specific basic eventlabelling format. The use of generic data by itself will not provide an adequate data source to aid intrend analysis of site-specific system equipment. Generic data can still, however, indicate whetherthere may be site-specific features or site-specific equipment problems that may be considerablydifferent from that which might be predicted from international generic sources of other researchreactors. The component reliability data in this report is applicable across a broad range of researchreactor types and sizes.

1.1. BACKGROUND

During 1986-1988 the IAEA undertook a Co-ordinated Research Programme (CRP) on PSAfor research reactors which helped to promote and foster an international exchange of information

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between national institutes and universities on the subject [5, 6]. During this period, extensivesystematic PSA studies on research reactors were also being both contemplated for the first time andinitiated. The need for development of a research reactor component reliability database wasidentified from the research reactor PSA CRP work. This resulted in the setting up of the researchreactor data acquisition CRP. The application of PSA and the subsequent relevant databasedevelopment on research reactors followed similar developments for power reactors [1].

The current document was prepared using the framework of the data acquisition CRP. It isbased on the first meeting of the CRP held in Vienna in October 1989. A second meeting was heldin Beijing, China, in October 1990 and the final meeting was held in Chalk River, Canada in July1993. The report was completed in Vienna in December 1993. All members of the CRP contributedcomponent reliability data to the final database.

The CRP project officer was B. Tomic from the IAEA's Safety Assessment Section of theDivision of Nuclear Safety. Following the Beijing meeting, IAEA-TECDOC-636 was produced [7].This document provided the definition of terms to be used in the component data collection, derivedspecifically to cover research reactors. It also contains all the definitions necessary to classifyresearch reactor equipment, and to identify and group individual component boundary and componentfailure type definitions. Relevant reliability parameters are also defined and the method of calculationis shown in Ref. [7]. The various definitions are not repeated in the current report since Ref. [7] isintended to be a supporting document for the user of the database. An updated version of thecomponent group listing, the breakdown of component groups into component types, and theassociated coding is provided in Tables I and II. The failure mode code definitions of Ref. [7] arelisted in Table III.

1.2. PURPOSE

The purpose of this document is to supplement the information in Ref. [7] and to providereference generic component-reliability information for a variety of research reactor types. As notedin Section 2 and Table IV, component data accumulated over many years is in the database. It isexpected that the report should provide representative data which will remain valid for a number ofyears. The database provides component failure rates on a time and/or demand related basisaccording to the operational modes of the components.

No update of the database is presently planned. As a result of the implementation of datacollection systems in the research reactors represented in these studies, updating of data fromindividual facilities could be made available by the contributing research reactor facilities themselves.

As noted in Section 1.1, the report does not include a detailed discussion of informationregarding component classification and reliability parameter definitions, which is provided in Ref. [7].The report does provide some insights and discussions regarding the practicalities of the datacollection process and some guidelines for database usage.

2. REACTOR FACILITIES AND DATA COLLECTION METHOD

A total of 12 research reactors from 9 participating countries are represented within the CRP.Failure data on components have been submitted from each of these facilities. The data collectionperiod varied according to the facility, ranging from 2 to 28 years. Reactor-power ratings variedfrom 100 kW(th) to 135 MW(th). The number of components monitored varied from fewer than 20to about 10 000 per facility. Essentially all participants used component definitions from Ref. [7].The raw data sources were reactor log books, maintenance records and other documented operationalexperience. A compilation of the various general features of the reactor facility types and data issummarized in Table IV.

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At the start of this programme no formal system for recording component reliability data wasin place in most facilities. After 1986 the initiation of PSA studies at most of these facilities providedan impetus for the development of a component reliability database. The database systems in thecontributing facilities are subsequently being maintained on a continuing basis for the purpose of long-term trend and equipment monitoring.

As noted in Section 1, the DES data entry system [4], was used by a number of participants toinput and record raw data. The component database for this report has been compiled from the DESoutput information provided by the participants. It is represented in an easy-to-use spreadsheet formatin Table VII. A description of the procedure for extracting reliability data from Table VII is providedin Section 4.

A wide variety of component types are referenced in the database coding system. Data isavailable on most component types. Coding for component types without data is maintained, forreference purposes, to allow for future additions to the database. In general, the data emphasizesmajor component types and failure rates which are dominated by top-event failure frequencies fromPSA studies. Most of these components are of the active type (i.e. they rotate or move), althoughpassive components (i.e. such as the reactor vessel and transformers) are also included.

The systems represented by the majority of the components are listed for each facility inTable IV. In general these are the most important safety systems, safety-related systems and keyprocess systems that are most commonly analyzed in PS As. The typical function and descriptions ofthese systems are provided in Ref. [8].

3. INSIGHTS FROM THE DATA COLLECTION PROCESS

The collection of component reliability data is invariably a tedious task unless a system is inplace to perform this on a continuous long-term basis. This was rarely the case until relativelyrecently for research reactor facilities. By contrast, many power reactors have had formalizedcollection systems for component reliability data for many years. The lack of staff resources atresearch reactor facilities is one of the main reasons for the absence of a formal system. Anotherfrequent difficulty is the lack of a computerized system for documenting maintenance and operatingrecords. This means that the collection of field data from a variety of hard copy recording systemsis time consuming. The quality of failure information also varies; it is primarily determined by theskill of maintenance and operations staff and how useful this type of information is regarded byreactor staff.

The features noted above are also not uncommon for non-nuclear process plants. Many of thecontributing facilities utilized students for data collection and analysis.

After the data collection and analysis process, very useful feedback was received on operationsand performance of equipment maintenance which led to improvements on equipment test andmaintenance procedures and in the failure record keeping process. Identification of potential incipientfailures and the trend of decreasing component reliability were other benefits obtained from theprocess. Generally, only when maintenance and operations staff can see direct usefulness of areliability data system will improvements be made in the quality of inputting field data.

4. USE OF THE DATABASE

4.1. LOCATION OF COMPONENT RELIABILITY DATA

This section describes the process for use of the reliability database. To locate a specificcomponent in the database, Table I should first be consulted. This list provides an alphabetic orderingby description/name of the different component groups. These component groups are defined ascomponents of a given general component category (Table II column 1) e.g. sensors, which have

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different functions (e.g. flow sensors, level sensors). Having identified the two letter componentgroup coding from Table I column 1, Table II is then consulted to locate the description of the closestmatch for a desired component. Table II, column 6 provides a component type listing which givesthe highest level of description for a component. For example, different types of pressure sensorsmay be identified. The component type coding is a three letter code, given in Table II, column 5.Table II provides a complete listing of the component category, group and type descriptions, andcodes in alphabetical order of the component type code. Table II is utilized by first locating thedesired two letter component group code, provided in alphabetic ordering in column 3, and thenreviewing the associated list of component types in column 6 until the closest match of a desireddescription is found.

Having identified the most relevant component type by its three letter identification code,Table V can then be used to provide an overview of the number of facilities which have recorded dataon that component type. Table V also provides the relevant component type populations for eachcontributing facility. Table VI summarizes information on component types including manufacturer'sinformation for each contributing facility. The table is presented per facility. A three-character codesimilar to that used in Table V is associated with each component type. To locate the specificreliability data available for the identified component type, Table VII is used.

Table VII, column 1 lists the three-letter component type codes alphabetically. Having locatedthe component type code, the available data on that component for each facility can then be found.The legend for Table VII provides the necessary explanations for each of the columns. The two basicparameters: failure rate and failure per demand, with associated 90% confidence bounds, areprovided. The raw data on component population, operating or calendar time, number of failures ordemands are provided for the user as a check on the extent of the raw data.

4.2. ACCURACY OF RELIABILITY DATA

In addition to statistical uncertainty, discussed in Section 4.4, there are a number of causeswhich contribute to the inaccuracy of reliability data. Those causes influence both generic andfacility-specific data. The following sections discuss the various causes.

The causes of differences in reliability data can be grouped in two areas, namely:

differences in data collection or data processing;the actual component reliability is different.

In each of these areas a number of individual factors influencing reliability parameters has beenidentified. A short discussion of the most important factors is given below. Also, a discussion on dataselection is included.

4.2.1. Data collection and processing

The inaccuracy in reliability data caused by data collection or data processing can be significant.Factors related to the following are discussed here:

data sources;the ways the data is collected;data processing;definitions.

Data sources

The raw data is collected from historical records — i.e. log books, maintenance work recordsand test records. While the log books are generally considered to be the most accurate, a number offailures, especially on non-safety equipment, may not have been recorded. However, collecting datafrom the log books is extremely time consuming. Maintenance work orders are considered to be the

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most complete records, but the reliability of the information depends on the person completing thereport. In many cases these are maintenance staff themselves, therefore the accuracy of the records(usually not computerized in research reactor facilities) varies. The direct consequence of incompleterecords is usually an overestimation of component reliability. Therefore the reliability data may bebiased.

Events without work request

Sometimes, relatively minor failures (such as mis-positioned valves) are reported during a testwithout a work request having been prepared. One example is a valve that opens only on second trialduring a test (or after a small, local repair). Only a comment on a test sheet is written. There is noformal work order or any other documented evidence. Since some of the failures are not accountedfor, reliability could be overestimated.

Failure of supporting equipment

Equipment failures may often be directly related to the failure of auxiliary equipment, supportor control systems. Such failures, although effectively disabling the component, are not failures ofthe component. Some databases do not separate such failures. Since supporting equipment failurescould actually dominate overall failure rate, this can cause substantial inaccuracy in the reportedfailure rate.

Coding errors

Coding errors are a classic problem encountered in every data collection exercise. Codingerrors are present in both computerized and manual data collection, and are generally related todiffering interpretations of criteria.

Failure rate denominators

The number of failures collected from the log books or maintenance/testing sheets are only oneinput used for the failure rate calculation. The number of demands, the failure exposure time or thecomponent's running time, are also essential. In the standard failure rate calculation, the denominatoris a quantitative measure of the stress that the component was subject to, related to a specific type offailure which may occur (failure mode).

The way the failure rate denominators are determined may produce a sizeable inaccuracy in acomponent's calculated failure rate. For equipment usually in standby mode, the data sourcesavailable today provide separate data on failures to start and failures to run (and sometimes on otherfailure modes such as leakage/rupture). The denominator for failures to run is a component's actualrunning time, which is usually estimated (e.g. 1 hour per test) and sometimes recorded.

4.2.2. Component reliability

Component reliability is a function of its design, use and maintenance. Components designedfor specific research reactor application (especially safety related) are usually highly reliable andshould be maintained as such during their lifetime. The reliability data, however, often showvariations which are related to operating conditions and practices, component application andmaintenance, and testing practices. A brief discussion of the influence of each of these is givenbelow.

Operating conditions and practices

A facility's operating conditions and practices may greatly influence component reliability.Some of the influence factors are:

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operating mode;operating time and demands;operating environment.

The operating mode has been recognized as influencing equipment reliability, especially onactive components (such as pumps). Some data sources provide separate data for running, alternatingand standby categories. In the IAEA survey [9], variations of more than two orders of magnitudehave been documented for the failure to run of motor-operated pumps when comparing betweenalternating pumps, running pumps and pumps where no mode has been specified. This findingsupports the view that failure data for similar equipment having differing operating modes should bekept separate.

A component's failure to start may be caused by a demand related stress (e.g. vibration), orstress in standby (e.g. corrosion) or a combination of both. Most data sources disregard thesedifferences and provide data on failure to start either as demand related or time related. When timerelated data are provided, the failure rate denomination is usually calendar time, or sometimes plantoperating time. Since similar components at a different location may have a substantially differenttest interval, the actual number of demands in a period may vary, which in turn may greatly influencethe failure rate. Some data collection systems also systematically collect information on the numberof demands; in others the number of demands is estimated on the basis of testing demands owing tothe costs of collecting the information.

Operating conditions may also influence component reliability. Examples of this would beambient temperature, humidity, chemical control, radiation fields and vibration.

Design and application

Design and application of a component will have an important influence on reliability. Theapplication of the component will determine the operating mode and environment. Variations due tothese causes has been discussed in previous sections.

Maintenance and testing practices

Significant plant-to-plant variations for otherwise identical components can be identified. Thesevariations are most probably caused by facility-specific maintenance and testing differences. Theinfluence of the testing interval and practice has been extensively investigated. The testing intervalhas an influence on the failure rate, but it is strongly related to component type. The testing intervalhas greater influence on components where standby stresses dominate failure probability (usuallymotor operated valves) and lower on components with higher demand stresses (such as dieselgenerators and similar).

4.2.3. Data selection

As discussed, a number of factors may influence reliability data. Although it is difficult toquantify these, an order-of-magnitude estimate could be made.

The overall effect of the factors noted below can therefore substantially influence the results.

Since there is the possibility of a considerable variation in reliability data between differentfacilities, facility-specific data is the best possible source. However, when this data is sparse, otherdata sources must be used. In this case, their compatibility and applicability should be carefullyassessed.

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ESTIMATE OF RELIABILITY DATA ACCURACY WITH VARIOUS CAUSES OF VARIABILITY

Variability factor Estimated accuracy

Collection related (comprehensiveness)Failure severity/failure modeDemand/operation attributesFailures in shut down taken into accountNon-representative samplesCollection of denominatorsSite effects (testing, maintenance)

2 to 5< 2< 222 to 102 to 52 to 10

When adopting reliability data from a data source, the definitions and their compatibility arefirst assessed. The background of a data source, including the ultimate data source,comprehensiveness of the data collection and data processing methods should be considered next.Finally, for reliability data originating at a research reactor, design (including age of design),operation, testing and maintenance practice should be examined for compatibility.

Although even the most careful data selection would not fully exclude the possibility of adoptingincompatible data, the fact that the factors contributing to data accuracy have been recognized shouldensure that the choice of data is reasonable.

4.3. RELIABILITY DATA ON COMMON CAUSE FAILURE

Quantification of common cause failure (CCF) data, in particular for system designs withredundant components, is an important aspect of PSA studies. CCF is also one of the most difficultareas in principle and in practice to obtain data. Collecting and reporting CCF data is a special aspectof reliability data collection. It is beyond the scope of this report to provide quantified data regardingcomponent CCFs, as defined in Ref. [7], Section 5.2.5. Therefore CCF specific data are not includedhere. To provide this type of data requires a detailed review of individual failure events. The failuredata provided by participants may include some common cause events. Experience with generic CCFdata has shown that it is very unlikely that the common cause contribution is a significant percentageof the recorded failure events. It can therefore reasonably be assumed that data uncertainties due tocommon cause failures are negligible compared with statistical uncertainties, Section 4.4, and theother contributing sources of inaccuracy, Section 4.2, in the data.

4.4. UNCERTAINTY BOUNDS

Following accepted practice in most databases, statistical uncertainty is calculated as discussedin Ref. [7], Appendix D. The 90% confidence range with 5% and 95% limits around the mean valueis defined. As noted in Ref. [7], failure rates and failures per demand utilize different expressionsfor the uncertainty calculations, although the differences between the calculations are not large. Thespreadsheet software EXCEL, version 4.0A, used for the production of the Table VII database,provided the necessary chi-square and F function variables needed for the uncertainty calculation.

The uncertainty bound values for the failure rates are provided in the last columns of Table VII.Note that the uncertainty bounds associated with a demand failure are in dimensionless units. Forcases with zero failure the numerator is set to 0.693 (taken from the 50% chi-squared value for onefailure) for the entry in the "failure rate" column of Table VII and a zero value is entered into the"5%" sub-column of the "90% confidence bounds" column. In all other cases the entry in "failurerate" column is the mean failure rate.

NEXT PAQE(S) I«•ft BLANK § 13

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TABLE I. ALPHABETICAL LIST OF COMPONENT GROUPS AND ASSOCIATED CODES

The following list provides component groups in alphabetical order with the associatedcomponent group coding. The group coding consists of two capital letters: the first describes themain component type category, the second describes the component group.

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Component Group Code

QAYAUNBTBCGBQBCBCCKAKDKl

KCKRJEQCNKNCOCORUCECHCJCQDDEDGEXQFKSYFXTXHXLXMXPXCXAKTDTFYHXEHQVUlNOIA1CIDNIElJlJLTEUMMAMGMSFXEB

Component Group Description

Air coolerAir filterAnnunciatorBatteryBattery chargerBeam ports, beam tubesBlower fanBusCableCircuit breakerCircuit breaker DCCircuit breaker indoorCircuit breaker molded typeCircuit breaker, high reliabilityClutchCompressorComputational moduleComputerControl rodControl rod driveControllerConverterCooling towerCore structureDamperDiesel engineDiesel generator emergency ACElectrical equipment for experimentsFan cooler, containmentFeeder (branch, junction)FilterFlux shaping elementFuel element HEUFuel element LEUFuel element MEUFuel element process tubesFuel element handling toolFuel, generalFuseGas turbine driven generator emergency ACGasketHeat exchangerHeater electricHVAC unit annulus ventilationIndicating instrumentInput/output deviceInstrumentationInstrumentation channel analogInstrumentation channel digitalInterfaceInverterIrradiation facilitiesLube oil coolerMain facility transformerManual control deviceMotorMotor generatorMotor servoOrificePanelboard

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Component Group Code

JPFEFNFSFTFWGPEPNDNPPDPMPTPWARURERXRXB

RWRARYRXRCRPRRRTFRACAFAAALAPASATAQWAWFWXNSNMUEGSYSSCSDSFSLSI

SMSPSTSQSAJTGTTATTTlTV

Component Group Description

Penetration containmentPiping expansion jointPiping nozzlePiping straight sectionPiping teesPiping weldsPool, open swimming poolPower supplyPrinterProgramable logic controllerPump diesel drivenPump motor drivenPump turbine drivenPump without driverRadiation monitorsReactor scram systemRectifierReflector element, graphiteReflector, BerylliumRelayRelay auxiliaryRelay coilRelay contactsRelay controlRelay powerRelay protectiveRelay time delayRupture diaphragmSensor core fluxSensor flowSensor generalSensor levelSensor pressureSensor speedSensor temperatureSensor water chemistryShielding generalShielding irradiated fuelShielding of experimentsSignal conditioning systemSignal modifierSolid state deviceStorage containersStrainerSwitch contactsSwitch digital channelSwitch flowSwitch levelSwitch limitSwitch manualSwitch pressureSwitch temperatureSwitch torqueSwitch, generalTankTank, closed vesselTransformerTransformer autoTransformer instrumentationTransformer regulating

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Component Group Code

TXTULCLFLALLLPLTVAVEVHVXVMVPVCVDVWCW

Component Group Description

Transformer for main facility supplyTransformer substationTransmitter core fluxTransmitter flowTransmitter generalTransmitter levelTransmitter pressureTransmitter temperatureValve air operatedValve explosive operatedValve hydraulic operatedValve manualValve motor operatedValve piston operatedValve self operatedValve solenoid operatedValve without operatorWire

18

Page 18: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

TABLE II. COMPONENT TYPE DESCRIPTIONS AND ASSOCIATED CODES

This table gives a description of each component category, group and type, in alphabeticalorder, of the three letter coding system. To find a specific component type, Table I may first haveto be consulted as it provides the component group listing in alphabetical order. The coding systemis based, to a large extent, on that formulated in Ref. [l].

19

Page 19: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

<UT3OO

A

B

C

D

E

Component CategoryDescription

Sensors

Batteries and chargers

Conductors

Diesel generators, gasturbine driven generators

Other electricalequipment, electrical partof experimentalinstallations

<o73OO

AAAC

AF

AL

AQ

AP

AR

ASAT

BC

BT

CB

CC

cw

DE

DG

DT

ES

EC

EH

El

EP

ER

Component Group Description

Sensor generalSensor core flux

Sensor flow

Sensor level

Sensor water chemistry

Sensor pressure

Radiation monitors

Sensor speedSensor temperature

Battery charger

Battery

Bus

Cable

Wire

Diesel engine

Diesel generator emergencyACGas turbine driven generatoremergency AC

Panelboard

Converter

Heater electric

Inverter

Power supply

Rectifier

CD73OO

AAAACÁACIACFACSAFAAHAALAALRAQCAQPAPAAPDARAARGARNAROARUASAATA

BCABCSBTABTLBTN

CB2CB3CB6CBACBDCCPCCSCWACWC

DEA

DGA

EBA

ECM

EHAEHPEHOEHTEHWEIAEliEIXEIZEPA

EPHEPUERS

Component Type Description

Sensor generalSensor core fluxIonisation chamberFission counterSelf powered detectorSensor flowSensor humiditySensor levelSensor pool water levelSensor conductivitySensor pH-valueSensor pressureSensor pressure differenceAerosol monitorgamma monitorneutron monitoroff-gas monitorradiation monitoring alarm unitsensor speedsensor temperature

battery chargerbattery charger solid statebatterybattery lead acid accumulatorbattery nickel cadmium accumulator

bus 120Vac , 220Vac sing, phasebus 220Vac, 380Vac three phasebus 6kVbus general power distrbus DCcable power connectioncable signal (supervisory)wirewire control circuit typical circuit, severaljoints

diesel engine

diesel generator emergency AC

terminal board

static converter for reactor main coolantpumpsair heaterpressunzer heateroil heaterheat tracing pipe heaterwater heaterinverterinverter instrumentinverter static three phaseinverter static single phasepower supply (instrumentation and controlequipment)high voltage p.s. instrumentationuninterruptible p.s. < 1 kVArectifier static

20

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a¡•a0U

F

G

H

1

Component CategoryDescription

Piping

Pool, grid plate, beamports, D20-tank, storagecontainers

Heat exchanger

Instrumentation(channels, reactorprotection system)

aT30u

EX

FEFN

FRFS

FTFWFXFY

GB

GP

GS

GT

HCHX

IA

1C

ID

Component Group Description

Electric equipment forexperiments

Piping expansion jointPiping nozzle

Rupture diaphragmPiping straight section

Piping teesPiping weldsOrificeGasket

Beam ports, beam tubes

Pool, open swimming pool

Storage containers

Tank, closed vessel

Cooling towerHeat exchanger

Instrumentation

Instrumentation channelanalog

Instrumentation channeldigital

CO•oouEXA

FEAFNAFNSFRAFS3FSAFSMFSSFTAFWAFXAFYA

GBC

GBRGBTG PLG PSGSFGSHGTAGTDGTE

HCAHXAHXB

HXFHXH

HXM

HXPHXRHXTHXV

IAA

IARICA

ICCICFId-IC?ICSICTIDA

(DCIDFIDLIDPIDT

Component Type Description

Electric equipment for experiments, general

piping expansion jointpiping nozzlepiping nozzle sprayRupture diaphragm, generalpiping medium, 1" < diameter < = 3"piping straight sectionpiping large, > 3" diameterpiping small, < = 1 " diameterpiping teespiping welds, generalorificegasket

thermal column

beam port, radialbeam port, tangentialpool linerstorage rack for fuelstorage and transp cont irrad fuelstorage, fresh fueltank, reactor vesseltank, heavy water containerexpansion tank

cooling tower generalheat exchangerheat exch. straight tube horizontal shell andtubeheat exch. fuel storageheat exch. U tube horizontal shell and tube

heat exch. straight tube vertical shell andtubeheat exch. plate typeheat exch. pond heat removalheat exch. cleaning systemheat exch. U tube vertical shell and tube

instrumentation

control rod position indicationinstr. ch. analog general

instr. ch. analog core fluxinstr. ch. analog flowinstr. ch. analog levelinstr. ch. analog pressureinstr. ch. analog seismicinstr. ch. analog temperatureinstr. ch. digital, general

instr. ch. digital core fluxinstr. ch. digital flowinstr. ch. digital levelinstr. ch. digital pressureinstr. ch. digital temp

21

Page 21: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

0)EJ

K

L

M

N

Component CategoryDescription

Other mechanicalequipment, lifting gear,structures, experimentalsetup

Circuit breakers

Transmitters

Motors

Signal conditioningsystem, computers

0)13OO

JC

JE

Jl

JLJP

JT

KA

KCKDKl

KR

KSKT

LALCLFLLLPLT

MA

MGMS

NC

NDNINKNM

Component Group Description

Core structure

0)•o0U

JCA

JCGJCT

clutch IJEE

Irradiation facilities

Lube oil coolerPenetration

Tank

Circuit breaker

Circuit breaker molded typeCircuit breaker DCCircuit breaker indoor

Circuit breaker, high reliability

Feeder (branch, junction)Fuse

Transmitter generalTransmitter core fluxTransmitter flowTransmitter levelTransmitter pressureTransmitter temperature

Motor

Motor generatorMotor servo

Computer

PrinterInterfaceComputational moduleSignal modifier

JEMJIAJIHJIPJIRJISJLCJPE jJPPJTFJTR

KAAKACKCAKDCKIAKIDKIS

KRP

KSFKTA

LAALCALFFLLLLPPLTTLXR

MAAMACMADMAIMGXMSS

NCA

NCBNCDNCHNCWNDANINNKANMANMO

NMP

NMSNMTNMV

Component Type Description

core structure, general

grid platefuel guide tubesclutch electricalclutch mechanicalrradiation containerhydraulic transfer systemaneumatic transfer systemrradiation rig, staticrotary specimen rigübe oil coolerpenetration electricalaenetration pipingtank resin flushingtank storage RWST (refueling water storagetank)

circuit breaker, generalcircuit breaker ACCircuit breaker molded typecircuit breaker DCcircuit breaker indoor AC applicationcircuit breaker indoor DC applicationcircuit breaker isolation, ground fault circuitinterruptercircuit breaker reactor protection system

feeder (junction box)fuse all voltage levels

transmitter generaltransmitter core fluxtransmitter flowtransmitter leveltransmitter pressuretransmitter temperaturetransmitter pressure difference

motormotor ACmotor DCmotor AC inductionmotor generatormotor servo

signal comparator bistable

personal computer, PCdata acquisition systemhigh quality computerworkstation computerprinter, generalcomputer network, generalcomputational modulesignal modifiersignal modifier voltage-pneumatic transducer

signal modifier current-pneumatic transducer

signal modifier square root extractorsignal modifier current-current transducersignal modifier current voltage transducer

22

Page 22: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

IllT30O

O

P

Q

R

S

Component CategoryDescription

Control rods and drivemechanisms

Pumps

HVAC and air handlingequipment

Relays

Switches

0)13OU

NONPNS

OC

OR

PDPMPTPW

QA

QBQCQD

OF

QV

RA

RC

RP

RR

RT

RWRXRY

SA

SCSD

SFSI

Component Group Description

Input/output deviceProgramable logic controllerSignal conditioning system

Control rod

Control rod drive

Pump diesel drivenPump motor drivenPump turbine drivenPump without driver

Air cooler

Blower fanCompressorDamper

Fan cooler containment

HVAC unit annulus ventilation

Relay auxiliary

Relay control

Relay power

Relay protective

Relay time delay

RelayRelay contactsRelay coil

Switch, general

Switch contactsSwitch digital channel

Switch flowSwitch limit

3ooNOANPANSA

NSCNSFNST

OCC

OCRDCS

ORA

PDAPMAPTAPWBPWCPWEPWSQAA

QBFQCIQDAQDMQFHQFVQVA

QVBOVE

O.VRQVS

RAARASRCARCDRCLRPHRPLRRARRFRRORRVRTARTBRTPRTSRWARXARYA

SAASAMsecSDA

SFASIASIE

Component Type Description

Input/output deviceProgramable logic controllersignal conditioning system for core flux,level, pressure, temperature generalsign cond sys core fluxsign cond sys flowsign cond sys temperature

control rod cruciform, boron carbide controlrodscontrol rod single control rod assemblycontrol rod clustered silver, indium, cadmiumcontrol rodcontrol rod drive

pump diesel drivenpump motor drivenpump turbine drivenpump horiz. 22-820 l/spump centrifugalpumpl vert 70-1900 l/spumpair cooler

blower fancompressor instrument airdamperdamper manual(HVAC)fan cooler reactor building cooling unitfan containment ventilation fanhvac unit auxiliary building

hvac unit battery room ventilationhvac unit electric equipment area ventilation

hvac unit control room ventilationhvac unit reactor hall

relay auxiliarysolid state relayrelay control ACrelay control DCrelay controlrelay power 300-460 Arelay power 40-60 Arelay protectiverelay, frequency protectionrelay, overload protectionrelay, voltage protectionrelay time delayrelay time delay bimetallicrelay time delay pneumaticrelay time delay solid staterelay, generalrelay contactsrelay coil

switch, generalmicro switchswitch contactsswitch digital channel pressure / vacuum,pressure, levelswitch flowswitch limitswitch limit electronic

23

Page 23: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

cu•ooO

T

U

V

W

Component CategoryDescription

Transformers

Other I&C equipment,instrumentation forexperiments

Valves

Shielding and relatedmechanics

0>T3O

<J

SLSMSPSQST

TA

TI

TTTUTVTX

DC

UE

Ul

UMUN

UR

VA

VCVDVEVHVMVP

VW

VX

WA

WF

Component Group Description

Switch levelSwitch manualSwitch pressureSwitch torqueSwitch temperature

Transformer

Transformer instrumentation

Transformer autoTransformer substationTransformer regulatingTransformer for main facilitysupply

Controller

Solid state device

Indicating instrument

Manual control deviceAnnunciator

Reactor scram system

Valve air operated

Valve self operatedValve solenoid operatedValve explosive operatedValve hydraulic operatedValve motor operatedValve piston operated

Valve without operator

Valve manual

Shielding general

Shielding irradiated fuel

<DT3OO

S LASMASPASQASTA

TA2TA6TAATIC

TIPTTATUATVA

UCA

UCEUCFUCPUEHUELUEYUIAUIDUIEUILUIMUIRUIXUMCUNAUNS

URS

VA1VAR

VGAVDAVEAVHAVMAVPAVRAVSAVWAVWBVWGVWJVWLVWNVWPVWTVWUVXA

WAA

WFA

Component Type Description

switch levelswitch manualswitch pressureswitch torqueswitch temperature

transformer 220/120 Vtransformer 6KV/380Vtransformer, generaltransformer (instrument transformer, currenttransformer)transformer instrument potentialautotransformer, generaltransformer 500 to 1 000 kVAregulating transformer

controller

controller electronicflow controllercontroller pneumaticsolid state devices high power applicationsolid state devices low power applicationisolating diode assemblyanalog displaydigital instrumentindicating instrument electronicindication lampCRT screen, monitorrecorderother indicating instrumentmanual control device pushbuttonannunciator, generalannunciator module solid state, LED-, LCD-displayreactor scram system

valve air operatedvalve air operated all systems except rawwater return linevalve self operated checkvalve solenoid operatedvalve explosive operatedvalve hydraulic operatedvalve motor operatedvalve piston operatedvalve reliefvalve safetyvalve angle valvevalve ball valvevalve gatevalve plug valvevalve globe valvevalve needle valvevalve diaphragmvalve butterfly valvevalve nozzle valvevalve manual

shielding general

shielding irradiated fuel

24

Page 24: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Il)•ooU

X

Y

Component CategoryDescription

Fuel elements, reflector

Strainers, filters,demmerahzer

Oí•oo(J

WX

XA

XB

XC

XH

XM

XL

XPXR

XT

YA

YF

YSYT

Component Group Description

Shielding of experiments

Fuel, general

Reflector, Beryllium

Fuel elm handling tool

Fuel element HEU

Fuel element MEU

Fuel element LEU

Fuel element process tubesReflector element, graphite

Flux shaping element

Air filter

Filter

StrainerIntake screen

a>T3oO

WXA

XAAXAMXATXBMXBNXCAXCMXCRXHAXHMXHNXHOXHPXHTXMMXMNXMOXMPXMRXLAXLMXLNXLOXLPXLTXLUXPAXRMXRTXTM

YAA

YFDYFMYFXYSFYTS

Component Type Description

shielding of experiments

fuel elm., generalMTR fuel element, generalTRIGA fuel element, generalMTR stand refl. element Be metalMTR stand, refl element Be oxidfuel element handling tool, gen.fuel element handling tool, manualfuel element handling tool, remotefuel element HEU generalfuel element HEU MTR standardfuel element HEU MTR regulatingfuel element HEU generalfuel element HEU generalfuel element TRIGA, stand. FLIP

fuel element rod type MEUfuel element LEU, general

fuel element TRIGA, stand. LEUfuel element TRIGA, mstr. LEUfuel element process tube, gen.Refl. element graphite, MTRRefl element graphite, TRIGAFlux shaping element, MTR

air filter

demmerahzerfilter liquid, mechanical restrictionIon exchanger filterstrainer / filterintake screen service water system

NEXT PAQEÍ8J••ft BLANK

25

Page 25: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

TABLE III. FAILURE MODE CODE DEFINITIONS

Failure mode code

B

C

D

E

O

F

G

H

I

QK

R

S

X

Y

J

M

Failure mode

Degraded

Failure to change position

Failure to remain in position

Failure to close

Failure to open

Failure to function

Short to ground

Short circuit

Open circuit

Plugged

Spurious function

Failure to run

Failure to start

Other critical faults

Leakage

Rupture

Control rod failure

Note: Detailed definitions of each failure mode (with associated examples) are provided in IAEA-TECDOC-636 [7].

NEXT PAQE(S)toft BLANK 27

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TABLE IV. FEATURES OF THE CONTRIBUTING RESEARCH REACTOR FACILITIES AND DATA COLLECTION PROCESS

Facility

Max Power1st critical

Appro*OperatingHours/Year

MamUtilization

Periodof Data

Collection

Total Number ofComponents

Investigated

Data Sources

Mam Systems of theComponentsInvestigated

Australia

HIFARLucas Heights

10 MW1958

6500

Isotope Production,Neutron Activation

Analysis (NAA)Silicon Doping

Basic&Appl PhysicsPostdoc Studies

1/85 - 6/93

-200

Maintenance Records

ECCS,Confinement HeatRemoval System,

ConfinementIsolation System

Austria

TRIGA Mark-IIVienna250 kW1962

2000

University Training,Education

Basic & AppliedResearch

11/81 -3/93

-200

Log Books,Maintenance Records,Operating Exp

RCS&RSS, I&C,Reactor, Sec Cooling,

Ventilation System,Fuel, Electrical Power

Systems

Canada

NRUChalk River

135 MW1957

6500

Isotope ProductionMaterials TestingBasic & Applied

Physics

1970 - 1993

-100

Log Books,Maintenance Records,Operating Exp

RCS&RSS, I&C,Reactor, Sec Cooling,

Service Systems,Electrical Power Systems

China

(PRC-M) (PRC-H)

MTRChina Atomic

Inst Beijmg3 5 M W1965

3200

ResearchTraining

Isotope Production

1/65 - 6/93

-200

Log Books,Maintenance Records

RCS&RSS, I&C,Reaclor, Sec Cooling,

Fuel, ECCS,Ventilation

HWRRChina AtomicInst Beijmg

15 MW1980

2600

Basic & AppliedResearch

Isotope Production

7/58 - 6/93

-500

Log Books,Maintenance Records

RCS&RSS, I&C,Reactor, Sec Cooling,

Fuel, ECCS,Ventilation

Czech Rep

LVR 15Rez/Praha

15 MW1990

3000

Isotope ProductionReactor Eng ExpMaterials Testing

Silicon Doping

1/91 - 3/93

18

Log Books,Operating Exp

RCS&RSS, I&C,Reactor, Sec Cooling,

Power Supply,Electrical Power Systems

Systems classified as in Ref [8]to

Page 27: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

OJo

Facility

Max Power1st critical

ApproxOperatingHours/year

MamUtilization

Periodof Data Collection

Total Numberof ComponentsInvestigated

Data Sources

Mam Systems of theComponentsInvestigated

Indonesia

(IN-S) (IN-B) (IN-Y)

MPR-30Serpong30 MW1987

1300

Isotope ProductionReactor EngineerMaterials Testing

7/87 - 4/93

-10000

Log BooksMaintenance Records

RCS&RSS, I&C,Reactor and

Reac Cooling Systems,Fuel, Ventilation,

Electrical Power Supply

TRIGA Mark-IIBandung

1 MW1965

1500

Education & TrainingBasic & Applied

Physics

1/71 -4/93

620

Log BooksMaintenance Records

RCS&RSS. I&C,Reactor and

Reac Cooling Systems,Fuel, Ventilation,

Electrical Power Supply

TRIGA Mark-IIYogjakarta

100 kW1979

1000

Education & TrainingBasic & Applied Physics

1/85 - 4/93

940

Log BooksMaintenance Records

RCS&RSS, I&C,Reactor and

Reac Cooling Systems,Fuel, Ventilation,

Electrical Power Supply

Slovenia

(SLO)

TRIGA Mark-IILjubljana

250 kW1966

3000

Basic & AppliedResearch

Isotope ProductionTraining & Education

1/85 - 3/93

-200

Log BooksMaintenance Records

Operating Exp

RCS&RSS, I&C,Reactor and

Reac Cooling Systems,Ventilation, Radiation

Monitoring,Electrical Power Supply

Switzerland

(CH)

MTRWürenlmgen

10 MW1957

6000

Basic & AppliedResearch

Isotope Production

11/91 -6/93

-400

Log BooksMaintenance Records

RCS&RSS, I&C,Reactor and

Reac Cooling Systems,Ventilation, Radiation

Monitoring,Electrical Power Supply

Vietnam

(VN)

IVV-9Dalat500 kW

1983

1500

Basic & AppliedResearch

Isotope ProductionTraining & Education

NAA, SiliconDoping

2/84 - 10/92

-80

Log BooksMaintenance Records

RCS&RSS, I&C,Reactor and

Reac Cooling Systems,Ventilation,

Electrical Power Supply,Systems

Systems classified as in Ref [8]

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TABLE V. OVERVIEW OF COMPONENT TYPES AND POPULATIONSDOCUMENTED FOR EACH FACILITY

31

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Comp.TypeCodeAAAACAACIACFACSAFAAHAALAALRAQCAQPAPAAPDARAARGARNAROARUASAATA

BCABCSBTABTLBTN

CB2CB3CB6CBACBDCCPCCSCWA

CWC

DEADGA

Component Type Description

sensor generalsensor core fluxionisation chamberfission counterself powered detectorsensor flowsensor humiditysensor levelsensor pool water levelsensor conductivitysensor pH-valuesensor pressuresensor pressure differenceaerosol monitorgamma monitorneutron monitoroff-gas monitorrad. monitoring alarm unitsensor speedsensor temperature

battery chargerbattery charger solid statebatterybattery lead acid accumulatorbattery nickel cadmium accumulator

bus 120Vac, 220V ac sing, phasebus 220Vac, 380Vac three phasebus 6kVbus general power distr.bus DCcable power connectioncable signal (supervisory)wirewire control circuit typical circuit,several joints

diesel enginediesel generator emergency AC

AUS

HIPAR

17

A

TRIGA-Wien

31

2

444

2

112121

9

1

CND

NRU

8

4

2

11

11

11

PRC-M

MTR

8

1

PRC-H

HWRR

I

cz

LVR 15

12

3

1

IN-B

TRIGA-Band.

4

3

1

112

71

6

1

4

111

1

IN-Y

TRIGA-Yogya

4

4

1

111

61

7

1

4

11

1

IN-S

MPR30-Siwa

9

29

3452

142521017

_3J

35124

• 9

3

231

9

3

SLO

TRIGA-Ljubljana

41

13

1

4

CH

SAPHIR

7215

1330001

12021

15

22

0

VN

IVV9-Dalat

9

2

1

9

3

210

2

TOTAL

all facilities

02642

41

580

1012144

147521275t

7¿

35174

0110

142006

1131

121000

000

200

Page 30: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Comp.TypeCode

EBA

ECM

EHAEHPEHOEHTEHWEIAEllEIXEIZ

EPAEPHEPUERSEXA

FEAFNAFNS

FS3FSAFSMFSSFTAFWAFXAFYA

GBCGBRGBTGBLGBSGSFGSH

Component Type Description

terminal boardstatic converter for reactor maincoolant pumps

air heaterpressunzer heateroil heaterheat tracing pipe heaterwater heaterinverterinverter instrumentinverter static three phaseinverter static single phasepower supply (instrumentation andcontrol equipment)high voltage p.s. instr.uninterruptible p.s. < 1 kVArectifier staticel equip, for exp. general

piping expansion jointpiping nozzlepiping nozzle spray

3"piping straight sectionaiping large, > 3" diameterDiping small, < = 1 " diameterpiping teespiping welds, generalorificegasket

thermal columnbeam port, radialbeam port, tangentialpool linerstorage rack for fuelstorage and transp. cont. irrad. fuelstorage, fresh fuel

,

,.

.

,,

,

.

.

.

.

,.

AUS

HIFAR

A

TRIGA-Wien

1

4

JJ311316

CND

NRU

36

2

26

407

148

113

1

PRC-M

MTR

2

6

PRC-H

HWRR

2

2

1

cz

LVR 15

12

IN-B

TRIGA-Band

4

1

1

138

28

18

1

131121

IN-Y

TRIGA-Yogya

1

1

1235

22198

2136

131121

IN-S

MPR30-Siwa

4340

11

12

3

2

9

2378

12301144433

19393

42

• 1

SLO

TRIGA-Ljubljana

CH

SAPHIR

1

1

521

1022

VN

IVV9-Dalat

8j

9

9

TOTAL

all facilities

04353

00

110

1204403

10

12130

1900

27020

26395

12671144473605

22677

04

3185

1758

Page 31: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

U)

Comp.TypeCodeGTAGTE

HCAHXAHXF

HXH

HXMHXPHXRHXT

HXV J

IAAIARICAICCICFICLICPíesICTIDAIDCIDFIDLIDPIDT

JCAJCGJCTJEEJEMJHAJIAJIHJIP

Component Type Description

tank, reactor vesselexpansion tank

cooling tower generalheat exchangerheat exch. fuel storageheat exch. U tube horizontal shell andtubeheat exch. straight tube vertical shelland tubeheat exch. plate typeheat exch. pond heat removalheat exch. cleaning systemheat exch. U tube vertical shell andtube

instrumentationcontrol rod position indicationinstr. ch. analog generalinstr. ch. analog core fluxinstr. ch. analog flowinstr. ch. analog levelinstr. ch. analog pressureinstr. ch. analog seismicinstr. ch. analog temperatureinstr. ch. digital, geninstr. ch. digital core fluxinstr. ch. digital flowinstr. ch. digital levelinstr. ch. digital pressureinstr. ch. digital temp.

core structure, generalgrid platefuel guide tubesclutch electricalclutch mechanicalHeaterrradiation containerhydraulic transfer systempneumatic transfer system

AUS

HIPAR

6

3

7

4

3

5

A

TRIGA-Wien

1

3

32

3

4

8

12

3

CND

NRU

3

8

1

PRC-M

MTR

2

426

6

PRC-H

HWRR

2

60

73112

51

cz

LVR 15

12

12

IN-B

TRIGA-Band.

2

1

1

2312

6

12

1

IN-Y

TRIGA-Yogya

2

2

1

1

4411

6

6

1

IN-S

MPR30-Siwa

3

3

' 2

3

1

92913471140

40

5

SLO

TRIGA-Ljubljana

12

6

9

3

CH

SAPHIR

1

2

1

5741

15

1

1

1

VN

IVV9-Dalat

1

1

155

9

TOTAL

all facilities

4402

193

2

21130

30

858

16574930521 1

13012710080220005

580

12

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U)

CompTypeCodeJIRJISJLCJPEJPPJTF

JTR

KAAKAC

KDC

KIAKID

KISKRPKSFKTA

LAALCALFFLLLLPPLTTLXR

MAAMACMADMAIMGXMSS

NCANCBNCD

Component Type Description

irradiation rig, staticrotary specimen riglube oil coolerpenetration electricalpenetration pipingtank resin flushingtank storage RWST (refueling waterstorage tank)

circuit breaker, generalcircuit breaker ac

circuit breaker DC

circuit breaker indoor AC applicationcircuit breaker indoor DC applicationcircuit breaker isolation, ground faultcircuit interruptercircuit breaker reactor protectionfeeder (junction box)fuse all voltage levels

transmitter generaltransmitter core fluxtransmitter flowtransmitter leveltransmitter pressuretransmitter temperaturetransmitter pressure difference

motormotor acmotor dcmotor AC inductionmotor generatormotor servo

signal comparator bistableaersonal computer, PCdata acquisition system

AUS

HIFAR

18

A

TRIGA-Wien

6

10

115

20

42

49

3

2

CND

NRU

417

2

PRC-M

MTR

4

2

PRC-H

HWRR

1

cz

LVR 15

1

IN-B

TRIGA-Band

1

251

2

1

23

1

13

4

3

IN-Y

TRIGA-Yogya

1

221

1

23

1

13

3

2

IN-S

MPR30-Siwa

2

153

1

40892

1178

11

13121225

8

SLO

TRIGA-Ljubljana

CH

SAPHIR

9

6

1

2

5

15

VN

IVV9Dalat

13

3

1921

TOTAL

all facilities

19004

285

40002000

43192

117

5207

012132213164900064

612

180362

Page 33: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

u>CTv

CompTypeCodeNCHNCWNDANINNKANMA

NMO

NMPNMS

NMT

NMV

NSANSCNSFNST

OCCOCR

DCS

ORA

PDAPMAPTAPWBPWCPWEPWS

QAA

Component Type Description

high quality computerworkstation computerprinter, generalcomputer network, generalcomputational modulesignal modifiersignal modifier voltage-pneumatictransducersignal modifier current-pneumatictransducersignal modifier square root extractorsignal modifier current-currenttransducersignal modifier current-voltagetransducer

signal conditioning system for coreflux, level, pressure, temperaturegeneralsign. cond. sys. core fluxsign. cond. sys. flowsign. cond. sys.temperature

control rod cruciform, boron carbidecontrol rodsassemblycontrol rod clustered silver, indium,cadmium control rod

control rod drive

pump diesel drivenpump motor drivenpump turbine drivenpump honz. 22-820 l/spump centrifugalpumpl vert. 70- 1900 l/spump

air cooler

AUS

HIPAR

2

8

A

TRIGA-Wien

1

2

429

3

3

1

1

2

CND

NRU

18

18

16

108

2

PRC-M

MTR

8

11

1

10

8

111

2

PRC-H

HWRR

8

20

1

2

cz

LVR 15

12

4

IN-B

TRIGA-Band

2

4

4

4

2

IN-Y

TRIGA-Yogya

3

2

IN-S

MPR30-Siwa

2

13

29

8

21

6

3

SLO

TRIGA-Ljubljana

5

15

7

CH

SAPHIR

1

5

2

2

VN

IVV9-Dalat

1

7

7

5

TOTAL

all facilities

40213

16

0

00

0

000

216

290

060

10

9300

640

1437

8

07

Page 34: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Comp.TypeCodeQBFQCIQDAQDMQFHQFVQVAQVB

QVEQVRQVS

RAARASRCARCDRCLRPHRPLRRARRFPRORRVRTARTBRTPRTSRWARXARYA

SAASAMsec

SDASFASIASIESLA

Component Type Description

blower fancompressor instrument airdamperdamper manual (HVAC)unitfan containment ventilation fanhvac unit auxiliary buildinghvac unit battery room ventilationhvac unit electric equipment areaventilationhvac unit control room ventilationhvac unit reactor hall

relay auxiliarysolid state relayrelay control ACrelay control DCrelay controlrelay power 300-460 Arelay power 40-60 Arelay protectiverelay, frequency protectionrelay, overload protectionrelay, voltage protectionrelay time delayrelay time delay bimetallicrelay time delay pneumaticrelay time delay solid staterelay, generalrelay contactsrelay coil

switch, generalmicro switchswitch contactsswitch digital channel pressure /vacuum, pressure, levelswitch flowswitch limitswitch limit electronicswitch level

AUS

HIFAR

93

3

58

15

A

TRIGA-Wien

2

1

12

9

93

CND

NRU

75

5

PRC-M

MTR

PRC-H

HWRR

cz

LVR 15

17

IN-B

TRIGABand

2143

112

8104

1

216

26

8

1

IN-Y

TRIGA-Yogya

21

3

112

810

4

1

IN-S

MPR30-Siwa

332

86

15

39

67

15231

939

35

9

SLO

TRIGA-Ljubljana

11

CH

SAPHIR

112

2

VN

IVV9-Dalat

8

6

4

2

TOTAL

all facilities

541695

6151700

12700

392

240

16204

6702

16232

10

9581600

4426

04

669

30

Page 35: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

U>co

CompTypeCodeSMASPASQASTA

TAATA2TA6

TICTIP

TVA

UCAUCEUCFUCP

UEH

UELUEYUIAUIDUIEUILDIMUIRUIXUMCUNA

UNSURS

VA1

Component Type Description

switch manualswitch pressureswitch torqueswitch temperature

transformertransformer 220/120 Vtransformer 6kV/380V

transformer (instrument transformer,current transformer)transformer instrument potential

regulating transformer

controllercontroller electronicflow controllercontroller pneumaticsolid state devices high powerapplicationsolid state devices low powerapplicationsolating diode assemblyanalog displaydigital instrumentndicating instrument electronicndication lampCRT screen, monitorrecorderother ind. instr.manual control device pushbuttonannunciatorannunciator module solid state, LED-,LCD-displayreactor scram system

valve air operated

AUS

HIPAR

3

A

TRIGA-Wien

10

13

2010

3032

CND

NRU

3

2

PRC-M

MTR

2

6

6

4

PRC-H

HWRR

2

cz

LVR 15

10

IN-B

TRIGA-Band

25

111

8

1

1

11

26

1

11

4

IN-Y

TRIGA-Yogya

1423

111

8

1

1

16

3024

1

3

IN-S

MPR30-Siwa

1268

31

3

431

1

147

24722

1

3

SLO

TRIGA-Liubljana

CH

SAPHIR

56

200

12

2

1

VN

IVV9-Dalat

8

2

1

6

2

52

131

TOTAL

all facilities

18313

32

363

110

4470000100

16103

0

00

199180

5337

268

179

01702

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CompTypeCode

VARVGAVDAVEAVHAVMAVPAVRAVSAVWAVWBVWGVWJVWLVWNVWPVWTVWUVXA

WAAWFA

XAAXAMXATXBMXBN

XCAXCMXCRXHAXHMXHNXHOXHPXHTXMM

Component Type Description

valve air operated all systems exceptraw water return linevalve self operated checkvalve solenoid operatedvalve explosive operatedvalve hydraulic operatedvalve motor operatedvalve piston operatedvalve reliefvalve safetyvalve angle valvevalve ball valvevalve gatevalve plug valvevalve globe valvevalve needle valvevalve diaphragmvalve butterfly valvevalve nozzle valvevalve manual

shielding generalshielding irrad. fuel

fuel elm., generalMTR fuel elm., generalTRIGA fuel elm., generalMTR stand, refl.elm. Be metalMTR stand, refl.elm. Be oxid

fuel elm. handling tool, gen.fuel elm, handling tool, manualfuel elm. handling tqol, remotefuel elm. HEU general

Fuel elm. TRIGA, stand. FLIP

.

.

.

.

AUS

HIFAR

17

3

2

5

2

A

TRIGA-Wien

1

30

11

1

9

CND

NRU

8

22

PRC-M

MTR

11

7

20

10

PRC-H

HWRR

3

3

74

cz

LVR 15

2

18

IN-B

TRIGA-Band

31

2

IN-Y

TRIGA-Yogya

31

1

IN-S

MPR30-Siwa

136

13

30

SLO

TRIGA-Ljubljana

CH

SAPHIR

2

12

120

VN

IVV9-Oalat

5

6

21

TOTAL

all facilities

0271700

1820000

15200000

350

229021000

12000000300000090

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ëCompTypeCodeXMNXMOXMPXMRXLAXLMXLNXLOXLPXLTXLUXPAXPMXRMXRTXTM

YAAYFDYFMYFXYSFYTS

Component Type Description

fuel elm. rod type M EUfuel elm. LEU, general

Fuel elm. TRIGA, stand LEUFuel elm. TRIGA, instr. LEUfuel elm process tube, gen.fission products monitoring systemRefl. elm. graphite, MTRRefl. elm graphite, TRIGATail. elm. MTR standard

air filterdeminerahzerfilter liquid, mechanical restrictionIon exchanger filterstrainer / filterintake screen service water system

Total

AUS

HIPAR

193

^J

TRIGA-Wien

8Sj4

16

50|

411

512

CND

NRU

795

PRC-M

MTR

30

191

PRC-H

HWRR

1

245

cz

LVR 15

116

IN-B

TRIGA-Band

951

22221

630

IN-Y

TRIGA-Yogya

1434

11

907

IN-S

MPR30-Siwa

58

15

41210234

14203

SLO

TRIGA-Ljubljana

91

CH

SAPHIR

534

VN

IVV9-Dalat

89

1

12

329

TOTAL

all facilities

000

1190

580

150

32390

01700

506

191528

50

18743

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TABLE VI. SPECIFIC INFORMATION ON COMPONENT TYPESFOR EACH FACILITY

This table provides specific information on component type, in alphabetical order, andcomponent type code for each facility. The information is not intended to provide completedescriptions of components, but does provide some information on the component manufacturer,component design specifics and any test or operational features that the contributors consider relevant.It is recognized that this information does not provide complete descriptions but it neverthelessprovides information at a more specific level than the component type descriptions of Table II.

41

Page 39: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Name of Facility: NRU REACTOR FACILITY CHALK RIVER, CANADA

ACI Trip and control ion chambers TQU (6 x lO^A/n) 300 Vdc input

ARG Gamma monitor (1) actuates Emergency Filter System (AEP 5180 type)

ARG Gamma monitor (3) actuates EPS system (Eberline type)

BTL 120 x 2.15 V cells, Gould 2 banks of 60 cells each, discharge tested twice per year3 hr mission (degraded failure is failure to complete mission test), failure to run isfailure to operate on demand

CBA Bus 600 Vac

CBD Bus 115 DC

CB2 Bus 120 Vac

DGA Emergency diesel generator (10) (125 to 200 kVA) 6 cyl Cummins & GM, testedonce per 4 weeks

DGA Emergency diesel generator (1) (250 kVa) 6 cyl Cummins, tested once per week

EIZ Inverter (old) CTS sine wave, AC, static switch bypass, 7.5 kW, input 125 Vdcoutput 115 Vac

EIZ Inverter (new) SAB NIFE, 120PW7-5-107, input 120 Vdc, 84 amp, 7.5 kW 120Vac output 60 cps single phase

ERS Stativolt silicon diode, 150 kW, 600 V, 3 phase, output 120 Vdc, convection cooled

FEA Steel expansion bellows, 304 st steel (> 15 cm diam), main coolant system

FSL Piping st steel, 142 m length, > 15 cm diam, (<700 kPa service), main coolantsystem, 270 welds

FSM Carbon steel secondary system piping, 120 cm diam, 0.95 cm thick, 536 m totallength, < 700 kPa service

FSM Carbon steel 46 cm diam process system piping =60 m total length

FSS St steel instrumentation piping, < 1 cm diam, total length approx 200 m (<700kPaservice)

FS3 Carbon steel piping 5 cm process water lines, <700kPa service

FYA Main coolant system stainless steel piping flange joints (gasket and flangeassemblies) 25" diam

GCB graphite thermal column outside calandria (2.4 m x 3.2 m x 3.7 m long)

GBR Calandria beam hole tube (13), re-entrant tube, leaks requiring replacement

GBT Calandria elliptical through tube (1) (leaks requiring replacement)

GTD Calandria (3), Alean 57SASTM 5052 (leak level sufficient for replacement)

HXM Heat exchanger 304 stainless steel =25 MW, single pass countercurrent shell andtube Ándale company, vertical

JI9 Pneumatic transfer system piping installation (in core and out of core)

MAD Motor generator set, Westinghouse, shunt wound, 75 kW, 125DC supply 1200 rpm,output 600 Vac 60 cps, 1 operational, 1 stand-by

OCS Shut off rod, mechanical failure to drop, 18 rods

42

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OCS Shutoff rod magnet failure to release on de-energization, 18 rods

ORA Control rod (18) weight (211 kg) 12 cm diam, max speed 15 cm/sec motor Diehlinduction 200 watt, 115 Vac

PMA Hydraulic pumps fuelling machine 6 kW Sperry Controller GE motor 11 kW, 700rpm variable speed VSG pump

PMA Main pump AC motors (8), 187 kW, 2300 V, 2 speed AC, 1800 rpm, 60 cps, 3phase

PMA Main pump DC motors (4), 15 kW, Westinghouse, DC shunt, 690 rpm, 115 Vdc

PMA Purification system pump motors (2), AC induction, Westinghouse, vertical, 19 kW,3600 rpm, 550 V

PWC Main circulating pumps, centrifugal, 230 kg/s, Ingersoll Rand, (57 m head)

PWS Purification system pumps (2), Allis Chalmers, 21 kg/s, head 64 m, centrifugal

QCI Worthington (3), reciprocating, 17 nrVm, discharge pressure 700 kPa, 75 kWEnglish Electric motor, 600 V, 3 phase 60 cps

QCI Joy Manufacturing (1), 3 stage centrifugal 57 m3/m, 700 kPa discharge pressure,336 kW Reliance electric motor, 2300 V, 3 phase 60, cycles

QCI Nash Nytor (3), 11 mVm, rotary vane water seal, 520 kPag, GE, 110 kW motor600 V, 3 phase, 60 cps

QDA Fan dampers (6), butterfly double acting electric solenoid for dampers (monthly test)5.7 mVs flow

QDA Emergency filter system dampers (4), 90 cm diam, pneumatic, flow 6m3/s

QFV Ventilation fans, Canadian Sirocco Company, 12000 cfm, 5.7 mVs, 56 kW

QFV El & C controls fan motors 56 kW, 600 V, 395 rpm fan 1800 rpm motor, 3 phase,double vbelt

TUA Transformer substation English Electric 500 kVa, 2400/600 V 3p 60 cps deltaprimary star secondary

TUA Transformer substation English Electric 1000 kVa, 2400/600 V 3p 60 cps deltaprimary star secondary

VA1 emergency check valve, pneumatic operation, 30 cm diam

VGA Pump discharge check valve, horizontal swing 25 cm tilting dist, dominion

VMA Main isolating electric operated gate valve 30 cm diam

VMA Main isolating electric operated gate valve 15 cm diam

43

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Name of Facility: BANDUNG, INDONESIA

ACA Reuter StokesReuter Stokes

EPA ORTEC

IAA General Atomic

ICC General Atomic

ICF General Atomic

ICL General Atomic

ORA General Atomic

PMA General Atomic

PWC General Atomic

UIR General Atomic

VMA General Atomic

44

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Name of Facility: BEIJING MTR, CHINA

ICF Flow rate measuring system with indicator

ICT Temperature measuring system with thermo couple sensor and recorder

PMA Feed water make-up pump, horizontal motor drive, low flow rate

PWC Pump motor drive centrifugal, horizontal low head

VMA Motor operated valve, 200 cm diam

VXA Manually operated valve, 20 to 40 cm diam

XMR 16 rod fuel element assembly

45

Page 43: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Name of Facility: DALAT, VIET NAM

ACA Sensor core flux: Type: KNK-15, KNK-3. Number of sensors: 9Operational mode: in operation. Time period: 22/2/84 - 31/10/92.Operational time: 13348 hr.

ATA Sensor temperature. Type: TCP-5076, TCM-5071. Number of sensors: 9.Operational mode: in operation. Time period: 22/2/84 - 31/10/92.

EPA Power supplies: 5V, 24V and 48V power supplies

IAA Control and averaging block, type BM-14R. Automatic regulating block type: BUM-21-R- AR regulating logic block - Shim rod control logic block - shim rod drive control relayblock - safety control logic block - safety drive control relay block.

ICC Channel power measurement of source range, type BIK01.Channel power measurement, intermediate range, type BIK02Channel power measurement, power range, type BIK03.

KTA Fuse 6kV, type: PK4-10-160/160/-20IZ. Number of fuses: 3Operational mode: in operation. Time period: 22/2/84-31/10/92

ORA AR control rod drive. Type ADP-362. AC-motor, end position contactor, positionpotentiometer, speed generator, steel cable/drum drive with counter weight.

Shim and safety rod drive, type D-500 MF. DC-motor, magnet, position potentiometer, endposition contactor, fiction gear, steel cable and drum drive.

PMA - Primary pump, type 4KG-12K-14-2, flow: 90 nrVhr- Secondary pump type KM-90/25, flow: 90 m3/h- Purification system pump, of spent fuel storage, type: XM2/25-K-2V

QBF - Cooling tower fan, type 1 VG-25- V-l fan, type CP 7-40-5- V-2, type CT-70-8- P-3, type CT-70-8

VIR - Recorder, primary coolant flowmeter type KCU 2-004- Recorder, secondary coolant flowmeter, type KCU 2-004- Recorder, temperature type KCM2-028, KCM2-021

VMA - V-l motor operated valves, type IAO 1009- V-2 motor operated valves, type IAO 1009- P-3 motor operated valves, type IAO 1009

VXA - Manual valve in reactor cooling primary circuit- Manual valve in reactor cooling secondary circuit- Manual valve in the reactor purification system, manual valve in purification

system of spent fuel storage

46

Page 44: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Name of Facility: KARTINI, INDONESIA

ACA Reuter Stokes

EPA ORTEC

IAA General Atomic

ICC General Atomic

ICF General Atomic

ICL General Atomic

ICT Leader

ORA General Atomic

PMA General Atomic

PWC General Atomic

UIR Honeywell

47

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Name of Facility: REZ (LVR-15), CZECH REPUBLIC

ACA Fission chambers wide-band RJ-1300 for startup channels and fission chambers RWKJ-81cfor other (log, lin. and power protection) channelsManufacturer: IBJ Swierk, Poland

EPA Power supply ZRM-6B3Manufacturer: IBJ Swierk, Poland

ICC Startup (TIP-GB2), lin. TPP-6B12, log. TPL-6B12 and power protection channels (linearscale) Manufacturer: IBJ Swierk

ORA Control electronic unit UR-70 Manufacturer Skoda, Czech Republic

PMA Main and emergency pumps 150-NHD-250-55-7C-20-09 (META34 YC-AC motor; META34 - DC motor) Manufacturer SIGMA, Czech Rep.

VMA Gate valve type C23-204-040-200 (DN 200), C23-204-040-300 (DN 300). ManufacturerSkoda, Czech Rep.

48

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Name of Facility: TRIGA LJUBLJANA, SLOVENIA (SLO)

ICC Compensated ion chamber (LOG channel) sensitivity: 2 x 10"u amp/nvManufacturer H&B (Hartman & Brown)

ICC Uncompensated ion chamber (LIN channel) sensitivity 7.7 x 10"15 amp/nvManufacturer: H&B (Hartman & Brown)

ICC Compensated ion chamber (startup) 5 x 10"5 watt to 50 wattManufacturer: H&B (Hartman & Brown)

ORA Rod drive mechanismRod drive mechanism has a selection switch for setting operating mode stationary(continuous) or pulse. The power level in stationary mode is manually by a twelve positionswitch on the control panel

PWC Primary coolant pump, flow: 70 m3/h, head: 20 m.Centrifugal AC motor driven pump, motion line diameter of 5 cm, discharge line diameterof 4 cm

PMA Water tower pump, flow: 23 m3/min, discharge line diameter: 10 cm

49

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Name of Facility: SAFIR, SWITZERLAND

ACA lonization chamber 20th century RC6EB

ARA Aerosol monitor LBxxxx Berthold

EPA Outdoor 220V 50Hz 10U VA 30 min

IAA EIR op amp - channel

ICC Merlin, Gerin, transistorized equipment, lin DC-channels

ICF Fischer & Porter - magneto-dynamic flow meter channel, 51/s

PWC motor drivenpump, vertical 201/s, 4 kW

YFZ mixed bed ion exchanger 1201 Lewatit (M500 + S 100)

50

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Name of Facility: TRIGA VIENNA, AUSTRIA

AC A Compensated ionization chamber: RC6EB, 20th century

ARA Hartmann & Braun, GM counter with filter (1975)

EPA Hartmann & Braun HR Series, (1968)

IAA Hartmann & Braun HR Series, 5 nuclear channels (1968)

ICC Hartmann & Braun HR - linear channel (1968)

ICF (1) Flow channel for primary cooling circuit: up to 30 m3/h(2) Flow channel for purification flow: up to 3 m3/h

ICL Hartmann & Braun HR-Series (1968)

ICT Hartmann & Braun HR-Series (1968)

KTA Fuses in each circuit of RSS, 1C system

ORA BODINE Motor, General Atomic, rod drives for shim., reg. and transient rod

PMA (1) Primary pump: 11 kW, flow up to 30 m3/h(2) Purification pump: 2 kW, flow up to 3 m3/h

UIR AEG (1968), 2 recorders, type CL 20, CL 21

VMA Motor operated valve to close secondary water supply, pipe diameter 80 mm

VXA Manual valves in primary and secondary coolant, pipe diameter 80 mm

NEXT PAOE(S)toft BLANK I 51

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TABLE VII. COMPONENT RELIABILITY DATABASE

Table VII provides the raw component reliability data and associated calculated reliabilityparameters. Specific definitions of the information in each column is provided.

Code

Component typedescription

Reactor code

Components

Calendar time

Operating time

Demands

Failure mode

Failures

Failure rate

Demand failure rate1

Failure rate 90%confidence bounds

3 letter component type code from Table II reference listing

A description of the component type

The alphanumeric code of Table IV, row 1, which identifies thereactor facility for the component type

The total number of component types for which data are available fora given facility

The cumulative component (x) calendar time for the specificcomponent type (component calendar hours)

The cumulative component (x) operating time for the specificcomponent type (component operating hours)

The cumulative component (x) demands to operate for the specificcomponent type (component demands)

The failure mode code for the component type from Table III

The number of failures of a given failure mode, corresponding toeither the cumulative calendar time, cumulative operating time or thecumulative number of demands

The number of failures per million hours, the number of failures percumulative million operating hours or per cumulative million calendarhours. For certain components: piping and piping welds. Thefailure rate units are quoted in failures per h and failures per m.h andfailures per weld.h

The failure per cumulative number of demands

The 5 % and 95 % confidence bounds for either the failure rateor the demand failure rate, based on Ref. [7]. For zero failures onlythe 95% bound is quoted

1 For zero failures the corresponding chi-square 50% statistical predictionX2(0.50,2)/2T is used where T is the total time or total number of demands.

53

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codeAAAACAACAACA

ACAACIACIACFACSAFAAFA

AHAALAALAALA

ALAALRAQCAQPAPAAPDARAARAARAARAARAARGARGARGARGARGARGARGARGARGARGARNAROARU

component type descriptionsensor generalsensor core flux

ionisation chamber

fission counterself powered detectorsensor flow

sensor humiditysensor level

sensor pool water levelsensor conductivitysensor pH-valuesensor pressuresensor pressure differenceaerosol monitor

gamma monitor

1

neutron monitoroff-gas monitoradiation monitoring alarm unit

Reactor

code

AVNIN-YIN-SIN-BCZ

CND

CHVNIN-YIN-S

CHCHCH

IN-SIN-BVNIN-SIN-SIN-S

CHCHA

SLOSLOCHCHCHCHA

AUSAUSCNDCNDAUS

Components

#

39494

128

324

70

12121238

1152

142

11111

12121212121717

13

17

Cummulativecalendar time

Mill. h

0.297

0.2820.6030.483

2.220

0.042

0.2824.687

0.1670.1670.1672.5440.121

0.3350.1349.508

0.0140.0140.0990.0440.0440.1670.1670.1670.1671.1901.2581.2580.0350.0261.258

Cummulativeoperating

time

Mill, h

0.120

0.076

0.057

0.025

Demands

ff

Failure modes

crit

F

FFFCF

XFFF

XFFFFFF

F

FF

X

FFF

F

deg

B

BK

R

K

KB

B

K

Failures

tt

2116

1041

2358

171

101022

16

120

2215

61312

101340

13

Failure rate

1e-6/h

6.78.33.5

10.020.752.90.5

-48.053.017.7

1.7-

6.042.06.03.98.3

28.26.0

14.91.7

-72.0

1439.320.246.023.030.0

365.818.06.01.77.9

10.3114.2

26.710.3

---

Failureprobability

1 /demand

-----------------------------------------

90% Confidence bounds

5%

1.22.70.24.3

11.236.40.0

-8.5

36.47.00.8

-0.3

19.70.32.10.40.01.12.71.1

-3.7

953.83.68.21.2

11.8292.3

4.90.30.34.36.1

39.00.06.1

-

-

95%

15.924.910.617.432.5

102.61.3

-113.8111.2

32.52.8

-18.071.018.06.2

24.8121.7

14.235.42.4

-215.6

2006.347.8

109.168.954.9

446.137.818.04.0

12.515.5

221.3115.2

15.5---

Page 51: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

codeASAATAATAATAATA

BCABCSBTABTABTLBTLBTL

CB2CB2CB3CB6CBACBDCCPCCSCWA

CWC

DEADGADGADGADGADGADGADGADGA

EBAEBAEBAEBA

component type descriptionsensor speedsensor temperature

battery chargerbattery charger solid statebattery

battery lead acid accumulatorbattery lead acid accumulatorbattery lead acid accumulator

bus 120Vac , 220Vac sing,phase

*•bus 220Vac, 380Vac three phasebus 6kVbus general power distr.bus DCcable power connectioncable signal (supervisory)wirewire control circuit typical circuit,several joints

diesel enginediesel generator emergency AC

125to200kVA1 25 to 200 kVA250 kVA250 kVA

switchgear panel'

Reactor

code

. SLOVNIN-BIN-S

CZIN-S

PRC-MCNDCND

CHCNDVN

CNDVNVN

CZVNVNIN-SCNDCNDCNDCND

CZIN-YIN-BIN-S

Components

tt

196

124

4164

111

113

12

10

1223

101011

1244

4340

Cummulativecalendar time

Mill. h

0.7258.303

0.02510.9810.0730.0880.219

0.0140.300

0.300

0.201

0.483290.606

Cummulativeoperating

time

Mill, h

0.0200.120

0.225

0.0270.751

0.006

0.024

0.004

0.00068

0.076

Demands

tt

12

1606

4250

1123

Failure modes

crit

FFF

FF

B/RF

1

F

FF

SRFSRSR

1FFF

deg

K

Failures

tt

101

13

111401

100

000

10177

14927

85

2517

Failure rate

1e-6/h-

50.05.81.41.6

---

27.510.154.7

7.94.6

-

72.02.33.1

-2.3

25.80.9

--

.--

110.0-

702.234.8

-6818.2

-7309.9

-26.5

-2.10.0

Failureprobability

1 /demand-----------

0.056--

.--------

.---

0.003--

0.004-

0.007------

90% Confidence bounds

5%-

34.80.00.10.9

---

0.08.6

18.70.00.2

-

3.70.00.0

-0.00.00.0

--

.--

0.00.0

641.516.4

-4000.0

-5000.0

-15.4

-0.10.0

95%-

149.824.94.12.3

---

118.911.7

106.134.213.7

-

215.610.013.3

-10.0

111.44.0

--

,--

475.50.0

1003.859.00.0

9110.30.0

13382.3-

62.7-

6.20.0

Page 52: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

code

ECMEHAEHPEHOEHTEHWEIAEllEIXEIZEIZEPAEPAEPAEPAEPAEPAEPAEPHEPHEPUERSEXA

FEAFEAFNAFNSFRAFS3FS3FS3FSA

FSLFSMFSM

FSMFSM

component type descriptionstatic converter for reactor mamcoolant pumpsair heaterpressurizer heateroil heaterheat tracing pipe heaterwater heaterinverterinverter instrumentinverter static three phaseinverter static single phase (old)inverter static single phase (new)power supply (instrumentation and

/

ligh voltage p.s. instr.

uninterruptible p.s. <1kVArectifier staticel. equip, for exp. general

piping expansion joint

piping nozzlepiping nozzle spraybursting diskpiping medium, 1 " < diameter

carbon steelpiping straight sectionst. steel piping large, 137m, 270weldspiping large, > 3" diameter

'carbon steel, 120 cm diameter,536 mcarbon steel, 46 cm diameter

Rbdctor

code

IN-S

CNDCNDCHCHCZA

VNVNVNVNVN

CND

IN-YCND

AUSIN-YIN-SCND

CNDVNIN-B

CNDCND

Components

It

11

3311

12488899

2

226

210

237

93

Cummulativecalendar time

Mill. h

0.737

0.1220.0600.0060.014

0.397

7.500

0.1480.705

15.8700.270

0.270

0.363

0.2900.290

Cummulativeoperating

time

Mill, h

0.076

0.107

0.107

0.120

0.175

0.141

0.131

Demands

tf

7511

9657

Failure modes

crit

F

FFF

FFF

F

F

YY/J

YYY

Y/JYY

deg

BB

B

B

Failures

#

4

24111424

37122

2

20

218

21

Failure rate

1e-6/h

m

5.4-------

196.716.7

181.872.052.9

5.037.5

-9.4

-16.6

-11.4

--

14.20.09

--

13.51.40.52.6

-

2.615.32.8

2.42.4

Failureprobability

1 /demand

.---------------

0.001-0.00002--------------

.--

.

-

90% Confidence bounds

5%

_

1.9-•--

--

135.60.99.33.7

36.40.9

24.1-

3.3-

8.0-

4.6--

6.60.0

--

2.40.10.30.0

-

0.07.30.1

0.00.0

95%

.10.5

-------

267.149.9

544.7215.6102.6

12.072.60.0

28.10.0

39.5-

27.1--

33.70.4

--

32.04.20.8

11.1-

11.136.38.3

10.310.3

Page 53: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

code

FSSFTAFWAFXAFYAFYAFYA

GBCGBRGBRGBTGBLGBSGSFGSHGTAGTAGTAGTAGTE

HCAHXAHXAHXAHXAHXA

HXBHXBHXF

HXHHXMHXM

HXMHXPHXR

component type descriptionpiping small, < = 2.5 cmdiameter, 1 69 weldspiping teespiping welds, generalorificegasket

thermal columnbeam port, radial

beam port, tangentialpool linerstorage rack for fuelstorage and transp. cont. irrad.storage, fresh fueltank, reactor vessel

expansion tank

cooling tower generalteat exchanger

heat exch. straight tube horizontalshell and tube

heat exch. fuel storageheat exch. U tube horizontal shelland tube

neat exch. straight tube verticalshell and tubeheat exch. plate typeleat exch. pond heat removal

Reactor

code

CNDIN-Y

IN-YIN-SCND

CNDCH

CNDCND

IN-B

CHIN-BCNDCND

IN-YIN-BIN-BIN-SAUSHXM

PRC-MPRC-H

IN-SCND

IN-B

Components

«

22

136393148

11

131

2

2133

244768

22

28

2

Cummulativecalendar time

Mill. h

0.2901.551

9.58626.31522.169

0.1840.0142.3900.184

0.242

0.0280.1210.6840.684

0.1410.4830.4830.4690.444

0.1450.149

0.1342.200

0.242

Cummulativeoperating

time

Mill, h

0.272

Demands

#

Failure modes

crit

JY

YYJ

FYYY

F

F???YJ

OJJF

Y

FF

YY

Y

deg

B

Failures

#

1

1047

1

0601

1

1210

411510

2123

10

2

Failure rate

1e-6/h

2.40.6

--

1.01.8

0.05-

3.8431.8

0.295.4

-4.1

--

36.016.5

1.51.0

--

28.42.12.1

10.72.32.6

144.5154.2

-

.

7.50.3

8.3--

Failureprobability

1 /demand

.---------------------------

.--

.--

.--

90% Confidence bounds

5%

0.00.0

-

0.61.40.0

-0.0

188.00.00.3

-0.2

--

1.82.90.10.0

--

9.70.10.14.20.10.0

96.9105.4

-

,0.40.0

1.5--

95%

10.31.9

--

1.62.20.1

-16.3

756.61.3

16.3-

12.4--

107.839.24.44.4

--

55.06.26.2

19.56.7

11.0

200.0210.6

-

.22.4

1.4

19.6--

Page 54: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

CO

code

HXV

IAAIÄAIAAIAAIAAIAAIAAIAAIA2IA2IA2IARIARICAICCICCICCICCICCICCICCICCICCICCICCICCICC

ICFICFICFICFICLICLICLICPICPICSICT

component type descriptionheat exch. U tube vertical shelland tube

instrumentation

instrumentation/2

control rod position indication

nstr. ch. analog generalnstr. ch. analog core flux

nstr. ch. analog flow

nstr. ch. analog level

1

nstr. ch. analog pressure

nstr. ch. analog seismicnstr. ch. analog temperature

Reactor

code

AVNVNIN-S

PRC-HAUSAUSAUSAUSAUSAUSSLOVN

CHCHCHCHCHCZCZ

SLOVNVNIN-B

PRC-MPRC-H

CHA

PRC-MPRC-H

IN-SPRC-HAUSIN-S

PRC-H

A

Components

#

41515

16044433315

77777

1212399226

2261

1314

472

3

Cummulativecalendar time

Mill.h

0.397

0.0673,7250.2960.2960.2960.2220.2220.222

0.0970.0970.0970.0970.097

0.2420.1460.372

0.0280.1980.3890.0720.8700.0620.2963.1470.124

0.297

Cummulativeoperating

time

Mill, h

0.2000.200

0.0200.067

0.0760.0760.0600.1200.120

Demands

tt

Failure modes

crit

FF

FFF

F

M

F

IXF

FFFF

FFFFF

FF

F

deg

B

BKB

K

B

B

K

BBB

B

B

Failures

n

31528

748

152

13732n

4

25121221183855

134

11

362134

137

3

Failure rate

1 e-6/h

.-

7.674.9

139.8104.5

12.93.4

16.96.8

58.631.513.5

100.059.9

-257.0123.4123.4

20.610.313.2

105.850.066.641.620.788.910.7

-36.0

5.092.427.7

1.148.313.54.1

56.4-

10.1

Failureprobability

1 /demand

.----------------------------------------

90% Confidence bounds

5%

.-

2.155.2

112.849.110.00.26.71.2

34.614.83.7

77.942.3

-178.7

71.271.2

3.70.55.9

82.434.848.327.38.2

52.63.7

-1.80.3

68.64.90.1

13.24.62.4

26.5-

2.7

95%

.-

15.9109.3186.0176.9

16.110.130.916.087.653.328.4

237.2116.2

-347.0187.2187.2

48.830.839.6

173.9104.9109.4

76.237.9

133.020.8

-107.8

15.1119.1

65.83.4

101.426.26.2

95.4-

21.2

Page 55: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

l/l

codeIGTICTIGTIDAIDCIDFIDLIDPIDTIRC

JCAJCGJCTJEEJEMJHAJH2JH2JIAJIHJIPJIPJIPJIPJIRJISJLCJPEJPPJTF

JTR

KAAKAAKAC

KDC

KIA

component type description

instr. ch. digital, generalinstr. ch. digital core fluxinstr. ch. digital flowinstr. ch. digital levelinstr. ch. digital pressureinstr. ch. digital temp.reactor reg sys.

core structure, generalgrid platefuel guide tubesclutch electricalclutch mechanicalheater fleater 2

rradiation containerlydraulic transfer systempneumatic transfer system

rradiation rig, staticrotary specimen rigübe oil coolerpenetration electricalpenetration pipingtank resin flushingtank storage RWST (refuelingwater storage tank)

circuit breaker, general

circuit breaker ac1

circuit breaker DC

circuit breaker indoor ACapplication

Reactor

codePRC-MPRC-HAUS

PRC-M

AUSAUSAUSCH

CHA

IN-YCND

A

AVN

Components

n153

2

233

15

13116

1013

Cummulativecalendar time

Mill. h0.0400.3102.220

0.127

0.1480.2220.2220.208

0.0140.2970.0700.3000.595

0.992

Cummulativeoperating

time

Mill, h

Demands

tt

Failure modes

critFFF

F

F

X

XYFFY

F

deg

B

B

Failures

tt13127

23

215

12

11101

2

Failure rate

1e-6/h321.1

38.73.2

------

181.0------

13.567.64.59.6

-72.03.4

14.22.31.7

-----

.-

2.0-----

.

Failureprobability

1 /demand-------------------------------

.-------

.

90% Confidence bounds

5%189.922.3

1.5------

123.7------

2.441.60.21.7

-3.70.20.70.00.1

-----

.-

0.4-----

.

95%480.3

58.75.3

------

247.3------

32.098.613.522.8

-215.6

10.142.510.05.0

-----

.-

4.8-----

.

Page 56: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

code

KID

KISKRPKSFKTAKTAKTA

LAALCALCALFFLFFLLLLLLLLLLPPLITLXR

MAAMAAMACMAOMAIMAIMAIMGXMSS

NCANCANCBNCDNCHNCHNCWNDANINNKA

component type descriptioncircuit breaker indoor DCapplicationcircuit breaker isolation, groundfault circuit interruptercircuit breaker reactor protectionfeeder (junction box)fuse all voltage levels

transmitter generaltransmitter core flux

transmitter flow

transmitter levelt

transminer pressuretransmitter temperaturetransmitter pressure difference

motor

motor acmotor dcmotor AC induction

motor generatormotor servo

signal comparator bistable

personal computer, PCdata acquisition systemligh quality computer

workstation computerprinter, generalcomputer network, generalcomputational module

Reactor

code

AIN-S

AIN-B^IN-S

VNVNSLOVNSLOVNVN

IN-BIN-S

CNDAUSAUSAUSCNDIN-S

CZPRC-H

A

CHCZ

IN-Y

Components

tt

151

203

178

9912111

1489

218181828

1712

21

2

Cummulativecalendar time

Mill.h

1.4870.0671.9830.363

11.919

0.044

1.6925.959

1.3321.3321.332

0.536

0.0620.198

0.028

0.141

Cummulativeoperating

time

Mill, h

0.120

0.0200.029

0.0250.025

0.130

0.130

0.107

0.006

Demands

tt

9657

Failure modes

crit

FFFFF

F

FF

F

SF

R

RSRF

FF

FF

F

deg

B

B

B

B

Failures

tt

405

102

26

12

8113

211

363114

442

21

1

Failure rate

1 e-6/h

.

.

26.974.7

5.05.52.2

--

8.3-

34.7275.3

23.040.6

121.9----

1.21.8

-23.14.52.30.87.77.5

-37.364.410.1

-72.0

158.7---

7.1

Failureprobability

1 /demand

_

.--------0.00002-----------------------------

90% Confidence bounds

5%

.

.

20.329.4

2.71.01.5

--

2.70.00.0

237.61.2

26.596.6

-

-

0.21.0

-13.12.00.60.02.22.6

-24.122.0

1.8-

12.8129.9

---

0.4

95%

_

_

34.2136.7

7.913.12.9

--

24.90.0

149.8452.5

68.9121.7255.8

---•

2.82.8

-48.4

7.94.72.2

23.014.5

-72.4

124.923.9

-170.7475.5

---

21.2

Page 57: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

codeNMA

NMO

NMP

NMS

NMT

NMV

NSANSCNSCNSCNSFNST

OCC

OCROCR

OCSDCSOCROCRORAORAORAORAORAORAORAORAORAORAORA

component type descriptionsignal modifiersignal modifier voltage-pneumatictransducersignal modifier current-pneumatictransducersignal modifier square rootextractorsignal modifier current-currenttransducersignal modifier current-voltagetransducer

signal conditioning system forcore flux, level, pressure,temperature generalsign. cond. sys. core flux

f

sign. cond. sys.flowsign. cond. sys.temperature

control rod cruciform, boroncarbide control rodscontrol rod single control rodassembly

control rod clustered silver,ndtum, cadmium control rod

electromagnet failuremech. failureCRDM

control rod drive

1

.

.

.

.

.

.

.

Reactor

codeSLO

IN-B

VNIN- YIN-BIN-Y

IN-S

APRC-M

CZPRC-MCNDCNDCZA

CZSLOVN

IN-YIN-B

PRC-MPRC-MPRC-HCND

Components

t>1

2

1422

8

311

121

1818123

121734

11111218

Cummulativecalendar time

Mill. h

0.242

0.2820.2420.141

0.536

0.2970.737

4.250

0.297

0.2110.483

0.310

Cummulativeoperating

time

Mill, h0.020

0.013

0.0760.067

0.076

0.0760.0200.093

0.3380.3380.754

Demands

tt

15940

Failure modes

crit

F

FFF

M

MM

CFFFCCDD JCFFSFFF

deg

B

Failures

tt

1

17131

1

214

10101

37221

132428

117

Failure rate

1e-6/h34.7

.

.

m

.

4.1-

1273.63.5

12.47.1

--

1.9

6.719.0

132.314.90.16

-489.4

6.726.550.0

139.19.58.35.9

23.714.622.6

IFailureprobability

1 /demand-

.

.

_

,

.-

------

_

_-

.--

0.000003---------.-

90% Confidence bounds

5%0.0

.

m

_

0.2-

650.00.23.40.4

--

0.1

1.211.5

106.56.60.00.0

438.71.2

15.434.8

112.81.72.81.1

13.16.6

10.6

95%149.8

_

_

.

_

12.4-

1820.610.626.021.2

--

5.6

15.928.1

207.744.70.70.0

628.815.962.7

149.8208.1

22.416.014.038.922.538.2

Page 58: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Os

codePDAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPMAPTAPWBPWBPWBPWCPWCPWCPWCPWCPWCPWCPWCPWCPWCPWCPWCPWCPWCPW2PW2PWEPWEPWEPWE

component type descriptionpump diesel drivenpump motor driven

main pump AC motors

main pump DC motorspurification pump motors f

pump turbine drivenpump horiz. 22-820 l/s

pump centrifugal

main pumpscentrifugal pump/2

1

pumpl vert. 70-1900 l/s

Reactor

code

CZCZCZA

SLOVNVNIN-YIN-B

PRC-MPRC-MAUSCNDCNDCNDCNDCND

CHA

PRC-MCHCH

SLOIN-YIN-YIN-BIN-BIN-B

PRC-MPRC-MAUSAUSAUSCNDAUSAUSCHCH

PRC-MPRC-H

Components

tt

99911554

2122288422

21111122444442228662223

Cummulativecalendar time

Mill. h

0.099

0.2821.4060.0280.0280.148

0.0280.0990.0010.0140.014

0.1410.1410.4830.4830.483

0.1480.1480.148

0.4440.4440.0280.028

Cummulativeoperating

time

Mill, h

0.0570.0570.057

0.0200.073

0.850

0.140

0.008

0.2910.291

0.850

0.0080.224

Demands

tt

1712

3700807

60

-

Failure modes

crit

RH1FRRSRFRS

RSSRS

RRRF"RFSRRSYRS

FYR

YRSSR

deg

B

B

B

Failures

tt

51111

1492

20205

278151

11111114111

398111832211

30

Failure rate

1 e-6/h-

88.217.617.610.150.0

192.7-

7.114.270.524.433.831.8

--

35.7--

36.010.1

2000.072.072.0

125.07.1

28.42.12.12.1

134.227.56.86.86.89.46.84.5

72.036.0

130.2134.1

Failureprobability

1 /demand-------

0.001------

0.00030.0003

-0.008

------------------------

90% Confidence bounds

5%-

67.48.78.70.5

34.8160.9

0.01.39.4

12.50.0

13.319.30.00.0

22.50.0

-1.80.5

102.63.73.7

100.20.49.70.10.10.1

108.316.20.30.30.33.31.80.8

12.81.8

104.7108.3

95%-

161.452.852.830.2

149.8284.5

0.016.819.8

167.2105.661.842.40.00.0

65.40.1

-107.830.2

5991.5215.6215.6374.5

21.255.0

6.26.26.2

171.445.220.220.220.215.514.210.7

170.7107.8390.1176.7

Page 59: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

codePWEPWSPWS

QAAQBFQBFQBFQBFQBFQBFQCIQCIQCIQCIQCIQCIQDAQDAQDAQDAQDM

QFHQFHQFHQFHQFVQFVQFVQVAQVB

QVEQVRQVS

RAARASRCARCDRCL

component type description

purification pumpspurification pumps

air coolerblower fan

compressor instrument air

(Worthington)(Joy)

/damper

damper manual(HVAC)fan cooler reactor building coolingunit

fan containment ventilation fanfan containment I&C controls

twac unit auxiliary buildinghvac unit battery room ventilationhvac unit electric equipment areaventilationhvac unit control room ventilationivac unit reactor hall

relay auxiliarysolid state relayrelay control ACrelay control DCrelay control

Reactor

codePRC-HCNDCND

VNVNIN-YIN-BIN-SAUSIN-SAUSAUSCNDCNDCNDIN-YIN-BCNDCND

CHCHCH

SLOCNDCND

A

Components

tt322

8822

3392333133764

222155

1

Cummulativecalendar time

Mill. h

0.1410.2422.2100.6660.1340.2220.222

0.2110.846

0.0280.0280.028

0.099

Cummulativeoperating

time

Mill, h0.2240.140

0.173

0.0150.0350.005

0.0200.6880.081

Demands

tt

60

6309

210359

Failure modes

critSRS

RSRSFFFFYRRRFF

E/O

X

RRR

F

deg

BK

Failures

tt661

16841

5929232

1611131

11

1051

18

1

Failure rate

1e-6/h26.842.9

---

92.3-

28.44.1

26.73.0

67.29.0

13.5133.3457.1201.4

4.71.2

---

36.036.0

359.8250.0

1.5222.2

---

.

10.1-------

Failureprobability

1 /demand--

0.008----------------

0.0020.0007

-

.--------

_-------

90% Confidence bounds

5%15.428.10.0

--

70.9-

9.70.2

21.30.5

35.11.63.7

107.4408.4169.2

0.20.10.00.0

-

1.81.8

195.2214.4

0.0188.5

---

_

0.5-------

95%47.075.10.1

--

133.20.0

55.012.432.77.1

107.821.428.4

316.3659.9603.2

14.23.50.00.0

-

107.8107.8565.1457.7

4.4314.8

---

m

30.2-------

Page 60: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

codeRPHRPLRRARRFRRORRVRTARTBRTPRTSRWAjRWAJRXARYA

SAASAMsecsecsec

SDASFASIASIASI2SI2SIESLASLASLASMASMASMASPASPASPASQASTA

TAATA2

component type descriptionrelay power 300-460 Arelay power 40-60 Arelay protectiverelay, frequency protectionrelay, overload protectionrelay, voltage protectionrelay time delayrelay time delay bimetallicrelay time delay pneumaticrelay time delay solid staterelay, general

relay contactsrelay coil

switch, generalmicro switch <switch contacts

switch digital channel pressure /vacuum, pressure, levelswitch flowswitch limit

imit switch

switch limit electronicswitch level

evel switchswitch manual

switch pressure

switch torque 'switch temperature

ransformerransformer 220/120 V

Reactor

code

VN

IN-BIN-SIN-B

IN-YIN-BIN-S

CHVN

AUSAUSAUSAUS

CHAUSAUSVNIN-BIN-SAUSAUSAUS

CND

Components

tt

6

2939

1

92635

24

5252

66

1968

1317333

2

Cummulativecalendar time

Mill. h

0.24262.875

0.121

0.6343.1422.344

0.028

3.8483.8480.4440.444

0.6660.444

1.5711.1380.2220.2220.222

0.600

Cummulativeoperating

time

Mill, h

0.013

0.107

Demands

tt

6438

1624

Failure modes

crit

C

FFF

FFF

F

F

CE

FFF

deg

KF

K

B

B

K

BK

Failures

tt

1

291

47

25

11

23124

3922

127242

0

Failure rate

1 e-6/h----------

8.30.18.3

----

6.32.2

10.7

36.0-

6.00.34.59.0

-224.8

13.54.5

18.77.66.19.0

18.09.0

--

1.2-

Failureprobability

1 /demand------

0.000--------

----

.0.000

----------------

--

90% Confidence bounds

5%------

0.0---

1.50.10.4

----

2.21.07.4

1.80.04.10.00.83.1

-190.4

7.00.89.44.42.91.66.21.6

--

0.0-

95%------

0.0---

19.60.2

24.8----

12.23.8

14.4

107.80.08.20.8

10.717.5

-471.7

21.710.744.411.610.421.434.921.4

---

5.0-

Page 61: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Os

codeTA6TEATEA

TICTIP

TVA

UCAUCEUCFUCP

UEH

UELUEYUIAUIDUIEUILUIMUIRU!RUIRUIRUIXUIXUIX

UMCUMCUNAUNA

UNSURSURS

VA1

component type descriptiontransformer 6kV/380Vtransformer 1 000 kVatransformer 500 kVatransformer (instrumenttransformer, current transformer)transformer instrument potential

regulating transformer

controllercontroller electronicflow controllercontroller pneumaticsolid state devices high powerapplicationsolid state devices low power/applicationsolating diode assemblyanalog displaydigital instrumentndicating instrument electronicndication lampCRT screen, monitorrecorder

other ind. instr.

manual control device pushbutton .

annunciator

annunciator module solid state,LEO-, LCD-displayreactor scram system

valve air operated

Reactor

codePRC-MCNDCND

IN-S

IN-YVNIN-B

VNIN-SIN-BIN-YVNIN-S

PRC-M

CHVNCHVN

CHCH

CND

Components

tt212

431

462

37

5214226

11311

11

2

Cummulativecalendar time

Mill. h

0.3000.600

28.860

3.242

4.472

0.1340.1210.282

0.134

0.014

0.014

0.0140.014

Cummulativeoperating

time

Mill, h0.436

0.027

0.067

0.027

0.439

0.174

0.013

Demands

«

560

Failure modes

critFFF

F

FFF

FFFF

FF

X

XF

KX

E/O

deg

B

K

Failures

ff600

2

41

20

20311

30141

1141

11

4

Failure rate

1e-6/h13.82.31.2

0.1---------

.

-1.2

37.54.5

--

299.722.4

8.33.5

1123.8104.5

2.3-

72.05.8

287.974.9

m

72.072.0

--

IFailureprobability

1 /demand---

.--------•

.

.------------------

.---

0.004

90% Confidence bounds

5%5.90.00.0

0.0---------

.

.-

0.424.13.0

--

259.96.10.40.2

900.063.20.1

-3.71.1

98.355.2

.

3.73.7

-0.0

95%24.110.05.0

0.2---------

.

.-

2.4112.2

6.2--

417.747.024.810.6

1481.2154.3

6.8-

215.617.3

558.0224.4

.

215.6215.6

-0.0

Page 62: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

0\

codeVA1

VARVGAVGAVGAVGAVDAVDAVDAVD2VEAVHAVMAVMAVMAVMAVMAVMAVMAVMAVMAVMAVMAVPAVRAVSAVWAVWBVWBVWGVWGVWGVWJVWLVWNVWPVWTVWTVWTVWUVXA

component type description

valve air operated all systemsexcept raw water return linevalve self operated check

valve solenoid operated

valve explosive operatedvalve hydraulic operatedvalve motor operated

f

30 cm diameter)1 5 cm diameter) mech. fail.1 5 cm diameter) electrical fail

valve piston operatedvalve reliefvalve safetyvalve angle valveball valve

valve gate

valve plug valvevalve globe valvevalve needle valvevalve diaphragmvalve butterfly valve

valve nozzle valvevalve manual

Reactor

codeCND

PRC-MPRC-HCNDCNDAUSAUSAUSAUS

AVNVN

PRC-MPRC-MPRC-MPRC-HAUSCNDCNDCND

AUSAUSCZGZ

PRC-M

AUSAUSAUS

A

Components

tt2

73B8

1515152

16677733

1666

66

202010

555

30

Cummulativecalendar time

Mill. h

1.1101.1101.1100.148

0.099

0.2222.100

0.4440.444

0.3700.3700.370

2.975

Cummulativeoperating

time

Mill, h0.560

0.5090.2242.000

0.5090.5090.5090.224

0.8400.840

0.1260.1260.142

Demands

ff

512

18635589

190190

Failure modes

critE/0

FF

E/OE/O

F

YY

EEO0IDA

FCF

KYFYD

FY

F

deg

K

B

B

Failures

tt4

25225181

21342003153

21711

r 58178

1

Failure rate

1 e-6/h7.1

.3.9

22.41.0

-4.50.97.26.8

--

20.2--

7.93.91.43.1

13.50.56.03.6

----

4.52.3

55.67.97.1

-.--

156.745.921.6

-0.3

Failureprobability

1 /demand-

.---

0.0005-------

0.00010.0001

------

0.0040.003

------------------

90% Confidence bounds

5%2.2

.0.4

12.30.00.01.80.03.60.3

--

3.60.00.02.20.40.00.03.70.01.10.4

----

0.80.1

39.02.22.2

----

124.529.310.8

-0.0

95%13.8

.9.3

40.92.40.08.22.7

11.820.2

--

47.80.00.0

15.29.35.9

13.428.4

1.410.9

7.5----

10.76.7

94.023.821.1

----

192.165.735.5

-1.0

Page 63: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

ON

codeVXAVXAVXAVXA

WAAWFA

XAAXAMXATXBMXBN

XCAXCMXCMXCRXHAXHMXHNXHOXHPXHTXMMXMNXMOXMPXMRXLAXLMXLNXLOXLPXLTXLTXLUXPAXRMXRTXTM

component type description

shielding generalshielding irrad. fuel

fuel element, generalMTR fuel element, generalTRIGA fuel element, generalMTR stand, refl. element Be metalMTR stand, refl. element Be oxid

fuel element handling tool, genfuel element handling tool, manual

*fuel element handling tool, remotefuel element HEU general

Fuel element TRIGA, stand. FLIP

fuel element rod type MEUfuel elm. LEU, general

Fuel element TRIGA, stand LEU

Fuel element TRIGA, instr. LEUfuel element process tube, genRefl. element graphite, MTRRefl. element graphite, TRIGATail, element MTR standard

.

.

.

.

.

.

.

.

.

.

.

,

Reactor

codePRC-MPRC-HAUSAUS

CH

AIN-B

A

PRC-M

AIN-Y

PRC-H

Components

»5

7622

60

12

9

195

85143

81 71

Cummulativecalendar time

Mill h

0 1480 148

0834

00990242

0 892

842910080

Cummulativeoperating

time

Mill h0 3635 668

3566

6.094

Demands

#

Failure modes

cnt

FY

B

XF

Y

YY

J

degBB

Failures

tt2

2622

11

21

1

0

41

9

Failure rate

1e-6/h5 546

13.5135

-----

132-----

20.24 1

------

1 1----

0.2-----

0.50.1

-1.5

----

Failureprobability

1 /demand------------------------------------------

90% Confidence bounds

5%1 1072 42 4

-

---

7 4-----

3602

------

0 1----

00-----

0200

-0.0

----

95%13 16 2

32.032.0

-----

20 3-----

47.8124

------

34----

08-----

0.90.3

-2.4

----

Page 64: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Os00

codeYAAYFDYFMYFMYFMYFXYFXYFXYSFYSF

component type descriptionair filterdemineralizerfilter liquid, mechanical restriction

Ion exchanger filter

strainer / filter

.

Reactor

code

IN-YIN-YIN-SIN-BCHIN-BIN-SIN-BIN-S

Components

ff

11

12242

102

23

Cummulativecalendar time

Mill.h

0.0700.0700.8040.2420.0560.2420.6700.2421.540

Cummulativeoperating

time

Mill, h

Demands

ff

Failure modes

crit

FQQQYFQQQ

deg

Failures

#

33

2741511

11

Failure rate

1 e-6/h-

42.642.633.616.518.020.7

1.54.17.1

Failureprobability

1 /demand----------

90% Confidence bounds

5%-

11.611.623.7

5.70.98.20.10.24.0

95%-

89.389.344.932.153.937.94.5

12.411.0

Page 65: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

REFERENCES

[1] INTERNATIONAL ATOMIC ENERGY AGENCY, Component Reliability Data for Use inProbabilistic Safety Assessment, IAEA-TECDOC-478, Vienna (1988).

[2] UNITED STATES NUCLEAR REGULATORY COMMISSION, Nuclear Plant Reliability DataSystems (NPRDS), Annual Report of Cumulative Systems and Component Reliability,NUREG/CR-2232, Washington, DC (1980).

[3] UNITED STATES NUCLEAR REGULATORY COMMISSION, Data Summaries of LicenseeEvent Reports of Selected Instrumentation and Control Components at US Commercial NuclearPower Plants, NUREG/CR-1740, EG&G Idaho Inc. (1984).

[4] WITT, H.H., BASTINS, S., NGUYEN, V., Data Entry System (DES), Australian NuclearScience and Technology Organization, ANSTO-ARTS, ARTS/UG-22 (1991).

[5] INTERNATIONAL ATOMIC ENERGY AGENCY, Probabilistic Safety Assessment forResearch Reactors, IAEA-TECDOC-400, Vienna (1986).

[6] INTERNATIONAL ATOMIC ENERGY AGENCY, Application of Probabilistic SafetyAssessment to Research Reactors, IAEA-TECDOC-517, Vienna (1989).

[7] INTERNATIONAL ATOMIC ENERGY AGENCY, Manual on Reliability Data Collection forResearch Reactor PSAs, IAEA-TECDOC-636, Vienna (1992).

[8] INTERNATIONAL ATOMIC ENERGY AGENCY, Code on the Safety of Nuclear ResearchReactors: Design, Safety Series No. 35-S1, IAEA, Vienna (1992).

[9] INTERNATIONAL ATOMIC ENERGY AGENCY, Survey of Ranges of ComponentReliability Data for Use in Probabilistic Safety Assessment, IAEA-TECDOC-508, Vienna(1989).

NEXT PAQE(S)¡•ft BLANK 69

Page 66: Generic component reliability data for research reactor · PDF fileIAEA-TECDOC-930 Generic component reliability data for research reactor PSA INTERNATIONAL ATOMIC ENERGY AGENCY /A\

Bock, H.

DuSek, J.

Hammer, J.

Li, Z.

Mavko, B.

Suprawardhana,

Tomic, B.

Van Lam, P.

Winfield, D.

Witt, H.

M.S.

CONTRIBUTORS TO DRAFTING AND REVIEW

Atominstitut der Österreichischen Universitäten, Austria

Nuclear Research Institute, Czech Republic

Paul Scherrer Institute, Switzerland

China Institute of Atomic Energy, China

"Jozef Stefan" Institute, Slovenia

Yogyakarta Nuclear Research Centre, Indonesia

International Atomic Energy Agency

Dalat Nuclear Research Institute, Viet Nam

AECL Research, Canada

Australian Nuclear Science and Technology Organization, Australia

71