61
LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear Regulatory Commission Office of Nuclear Regulatory Research I $*, -~ e&->.- .%aZ Washington, DC 20555 8L Los Alamos National Laboratory, an affirmative actionlequal opportunity employer, is operated by the University of California for the U.S. Department of Energy under contract W-7405-ENG-36. By acceptance of this article, the publisher recognizes that the US. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or to allow others to do so, for U.S. Government purposes. The Los Alamos National Laboratory requests that the publisher identify this article as work performed under the auspices of the US. Department of Energy. Form No. 836 R5 ST 2629 10/91

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Page 1: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

LA-UR- 9 7 4 '$" 3 1 Title:

Author(s):

Submitted to:

ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE

19980422 098 Leslie M. Moore

US Nuclear Regulatory Commission Office of Nuclear Regulatory Research I $*, -~

e&->.- .%aZ

Washington, DC 20555 8L

Los Alamos National Laboratory, an affirmative actionlequal opportunity employer, is operated by the University of California for the U.S. Department of Energy under contract W-7405-ENG-36. By acceptance of this article, the publisher recognizes that the US. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or to allow others to do so, for U.S. Government purposes. The Los Alamos National Laboratory requests that the publisher identify this article as work performed under the auspices of the US. Department of Energy. Form No. 836 R5

ST 2629 10/91

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DISCLAIMER

This repon was prepared as an account of work sponsored by an agency of the United States Government Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assues any legal liability or responsibility for the accuracy, completeness, or use- fulness of any infomation, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any spe- cific commercial product, pro#ss, or sewice by trade name, trademark, manufac- turn. or otherwise does not necessarily constitute or imply its endorsement, morn- mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not ncccssady state or reflect those of the United States Government or.any agency thereof.

Page 3: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Analysis of .Valve Failures from the NUCLARR Data Base

Leslie M. Moore Los Alamos National Laboratory

Prepared for:

US Nuclear Regulatory Commission Office of Nuclear Regulatory Research

Washington, DC 20555

Under:

NRC Job Code W6505, Task 10 Los Alamos National Laboratory

Harry F, Martz, Principal Investigator

Dr. Lee R. Abramson NRC Technical Monitor

November 1997

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ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE

Leslie M. M m

Los Alamm National Labcxatory. MS-F600, Los Alamos, NM 87545

ABSTRACT

The "Nuclear C o m p u m Library for Assessing Reactor Reliabfity" (NUUARR) contains data on compo-

nent fail- with categorical and qualifying information such as component design, normal F a t i n g state. system

application and safety grade information which is impartant to the development of risk-based mpiment surveil-

lance testing requhments. This report presents descriptions and results of analyses of valve component failm

data and covariate information available in the document "Nuclear Computerid Library for Assessing Reactar

Reliability Data Manual, Part 3: Hardware Component Fail= Data" (NUUARR Data Manual). Although there

are substantial recacds on valve performance. the= are many categories of the cOrreSpOnding descriptors and quali-

fying infomation for which specific values are missing. Ccmsequently this limits the data available for analysis of

covariate effects. This report pments am tabulations by different covariate categaies and limited modeling of

covariate effects for data subsets with substantive non-missing covariate information.

KEY WORDS: NUCLARR Data Manual, Binomial m t s , Poissan m t s , Logistic model, Log-linear model

1. INTRODUCTION

This letter report describes the results of work performed on Task 10 GLMM Analysis of Selected Reliability

Data. The goal is to demonstrate the feasibility of identifyhg and quantifying the effect of categatical descriptive

and qualifying infurmatian, such as component design, system application or safety grade category, on selected

component fahe rates. This report strictly considers valve failm rates based on data available in the document

"Nuclear computerized Library for Assessing Reactor Reliability Data Manual, Part 3: Hardware Component

Failm Data'' (NUCLARR Data Manual). The table titled "Aggqated Data" in Appendix A of the NUCLARR

Data Manual indicates over 400 recatds available an valves, although there are also many categdes of descriptive

and sualifying infcnmatiioa available with these f a h e recatds. The= are more records on valves than any other

1

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component listed in the "Aggregated Data" Table of Appendix A. so valves were selected as the basis for the study

undertaken for Task 10.

Two types of failure reuxds are identified in the NUCLARR Data Manual according to whether valve failure

modes of interest are time related (time-related data) or demand related (demand-related data). In Section 2,

definitions of the variables and records extracted from the NUCLARR Data Manual for the valve data sets are

provided. W o n 3 and Section 4 respectively deal with analysis of available demand-related and time-related

valve recards. Although there are substantial recclrds available for valves, there are also many categories of the

cOrreSpOnding descriptors and qualifying infomation. refeed to generally as covariates. for which specific covariate

information is missing. consequently, this further limits the data available for d y s i s of covariate effects. Among

boiling water reactors (BWRs), there are a substantive number of records from Plant Y combining reactors Unit

1 and Unit 2. Among pressurized water reactors (PWRs). Plant X has a substantive number of records as well as

specific covariate information available. Data records from the two reactoT types will be studied separately, with

BWR types in subsections 3.1 (demand-reated data) and 4.1 (time-related data) and FWR types in subsections 3 2

and 42.

2. DEMAND-RELATED AND TIME-RELATED VALVE DATA SETS

The NU- Data Manual lists 548 valve failure recards, including 147 recatds that are missing pertinent

failure information such as number of fail- or total h m and total demands. The recatds with missing failure

infoxmation are excluded from failure rate analysis. Of the remaining mds, 222 are demand-related failure

records and 179 are time-related failure records. Table A.l and Table A 2 in Appendix A list respectively the

demand-related and time-related valve failure infomatian obtained from the NUCLARR Data Manual.

Nineteen variables, . to table columns. are included in each of the data sets listed in Table kl,

demand-related data, and Table A.2, time-related data. Column headings in these tables indicate a label for the

variable as well as a brief description. "Read. labeled recno, is the unique number from the NUCLARR Data

Manual ident3ji.q each individual data m d . "Failures" (numfail) and "demands" (totd) or 'rh<lLlfstt(tothrs) are

the observed failm information fran the NUCLARR Data Manual. "Failms" is the observed count of fail-

on valves included in a recard. All valve fail- in the NUCLARR Data Manual are classified as catastrophic in

severity. 'Demands'' and "hours", respecsively are the exposme informatim for the failure records in the demand-

2

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related and time-related data sets. '?)emands" is the count of total demands on the valves in a recurd in the

demand-related data set. "Hours". in the time-related data set. is the count of total hours on the valves in a recurd.

The value of "failure rate" (frate) is computed as the ratio of "failures"/"demands" and "failm"l'hou"'' respectively

in the demand-related and time-related data sets. "Failm rate" represents the observed failure rate for each record.

For modeling demand-related data, the failure count response, numfail, is assumed to be distributed as a binomial

random variable with totd ('I-) the number of trials. For time-related data, the failwe count response.

numfail, is assumed to be distributed as a Poisson random variable with tothfi ("hm") exposure time. Log-linear

and logistic models for analyzing Poisson and binomial counts are described in depth in Atwood (1995) and these

techniques form the basis for analysis of failm rates in this repd. As in Atwood (19951, the SAS computer

package, in particular the GENMOD procedure, is used for model fitting.

The remaining 15 variables constitute the available potential explanatopy variables, or covariates, effecting the

component failure rates from the NUCLARRData Manual. In some cases the value ofacavariate in the NUCLARR

Data Manual is indicated as unknown or non-specific. so the covariate value is amsidered missing for modeling

purposes and is indicated with a blank or '*." in the appropriate field in Table A.l and Table A2. The following

list defines the explanatopy variables including the level descriptions and cOrzeSpOnding coded values that appear

in Table A1 and Table A2.

0 rtype: The two types of wakr reactoa are pmswized, codedFVR, and b o i . coded BWR. Each facility is

one of these types so that facility (ofl) is nested in rtype.

0 ofl: The NUCLARR Data Manual includes a field i d e m the plant from which the data was couected

This plant is d e e d to as the originating facility and AppendkE4 afthe NUCLARRData Manual contains

alist of all codes and data sou~rce names. The following is alist. by rtype. of facility codes and the NUCLARR

Data Manual data some names for which there is valve data

BWR facilities:

-Yx: Plant Y. 1st U or 2nd U (SAIC data)

-BRPl: Big Rock Point

-MNSl: Millstone 1

-BWR: All BWR Plants

3

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-IP4 IPRDS Plant 4

PWR ftKilities:

-X Plant X (SAIC Data)

-DBS1: Davis-Besse

-NEE3: oconee3 -IP1: IPRDS Plant 1

-B&W Babcock & Wilcax

-FpRA: Proprietary PRA "F"

-21S1: Zion 1 and Zion 2

-BREL: Proprietary REL, 'B"

-m European comm (SAIO

-IPS2 Indian Point 2

-RGLS: R@h& 2 (Swedish)

-m All PWR Plants

Facilities with unknown rtype:

--. Proprietary REL "A"

0 systl: This variable identifies a specific system. if known. from which the valve data were collected. Appendix

E-6 of the NUCLARR Data Manual lists two-character d e s and descriptions for nuclear power plant systems.

Some systems OCCUT in only one ofthe two reactor types. The following lists the system codes and descriptions

from the NUCLARR Data Manual for which there is valve data and indicates in parentheses which, if only

one. of the reractor types include the identified system.

-AA: control rod drive system

-AB: Reactar coolant system (PWR)

-AB/& AB and AP systems c o m b i n e d

-m pressurrze * r system (PWR)

-BA: AmZary/-rgency feedwater system (PWR)

-BE -t spray system rn) 4

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-BG/BM High or low p s u r e core spray system (BWR)

-BI Essential service water system

-BL Isolation condenser system (BWW

-BN React<H core isolation cooling system (BWR)

-BP Low pressure safety injection system (FWR)

-BS: Ultimate heat sink system

-BY Automatic depressUriZation system

-CB: Chemical and VO~UUE controVMakeup and purification system (€WR)

-cc aosed/component cooling water system

-cH: Residual heat remo~al system (BWR)

-cI: Residual heat remo~al system (PWR)

-JI: Turbine steam bypasS control system

-JM. contaimnent isolation Umtrol system

-KA: C o n h a t e storage and transfer system

-KE: Heat rejection system

-m Instrwment air supply system

-MS Main steam isolation valves

-NT: Drywell

-SB: S ~ S ~ ~ I U

-SD candensate system

-SG. condenser system

-sJ. Feedwater system

-xc Eccs

0 capll: This variable identifies the application environmea for the valves included in the record. Appendix

E 3 of the NUCLARR Data Marmal Umtains the applicatim codes. The following lists the application codes

and descriptions from the NUCLARRData Manual far whichtbere is valve data.

_ _ ~ -INTEARAirAir-a

5

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-INTEcs: Chemical solution other than boric acid

-INTEST: steam internal environment

-INTJWB: Water, borated internal environment

-INTEwc: Water, high purity/demineralized intemal environment

-INTEND: Water, silt/particle entrained internal environment

-INTEWS: Water, brackish sea intemal environment

0 optypl: This variable identifies valve operator type. Its value is derived from the Scharacter component

type/component design code in the NUCLARR Data Manual, Appendix Kl. The following lists the opera-

tur type codes, a brief description and the cOfTeSpOnding component type/commt design codes from the

NUCLARR Data Manual, with * indicating all values.

- 1: -tic operata. NUCLARR codes VLP** and VLCPN

-2 Solenoid operator, NUCLARR codes VU**

-3: Motor operator. NUCLARR codes VLM** and VLCMO

- 4 Hydraulic operator, NUCLARR codes VI,€€**

-5: M a n d operata. NUCLARR codes VU)**, V L W , VLCNO a d VLCXT

-6: Mechanical pera at^. NUCLARR codes VLD**

-7: Relief valvedvacuum breaker, NUCLARR codes VLR** and VLV**

0 vlvtypl: This variable identilies valve type. Its value is derived from the 5character component

type/mponent design code in the NUCLARR Data Manual, Appendix 5 1 . The following lists the valve type

d e s , a brief description and the corresponding component typelcom-t design codes from the NUCLARR

Data Manual, with * indicating all values.

-1: Ball valve. NUCLARR codes ***BL

- 2 Butterfly valve, NUCLARR codes ***BF

-3: check valve, NUCLARR codes VLC**

- 4 Gate valve, NUCLARR codes **%T

-5: Globe valve, NUCLARR codes **a

- 6 Plug valve, NUCLARR codes ***PI,

6

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-7: Relief valvesivacuum breaker, NUCLARR codes VLR** and VLV**

-8: Angle valves, NUCLARR codes ***AN

0 icl: This variable is an indicator for reccmds where the control circuitry is included in the component’s

boundary and CoIlSeqzLenty control circuitry failures are included in the failure counts. A value icl=l indicates

that circuitry failures are included and a value i c l 4 indicates no or unknown. More than 500/0 of the recopds

indicate that control circuitry failures are included.

0 sgl: This variable is an indicator for whether the cmnponents associated with the recafd are safety graded

with sgl=l indicating the components are safety graded and s g l 4 indicating unknown or not safety graded.

Less than 15% of the valve recmds are i n d i d as safety graded.

pfl: This variable indicates cases where the failure counts include primary failures only. pfl=l indicates only

primary failures are included and pfl=O indicates that secondary failures may also be included. Less than 15%

of the valve recurds indicate that only primary failures are included.

0 fm& Failm mode descn’bes how the failed component’s state or condition differs from the desired or normal

plant operating state for the recurded valves. Appendix I52 of the NUCLARR Data Manual lists failure mode

codes. The majority of failure modes are identified as failures to operate @TO). In the case of demand-related

data, all failure modes are equivalent to FIO and no modeling considerations are required for this covariate.

For time-related failure data, separate analyses for data under diffmnt failure modes is consided appropriate.

The following lists failure mode d e s and descriptions that occur for the two data sets, demand-related data

and time-related data

Demand-related data:

-FTC Failure to Uo~e

-FTp: Failure to Open

-I30 Failure to operate

Time-related data:

-BP: Plugsed

-LE: Exkmal leakage/luptuIe

-LI:rntemalleakage

7

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-SC Spurious (transfer) close

-SO Spurious operation

-SP Spurious (transfer) open

-FIy): Failure to Operate

0 nstate: This variable identifies the normal operating state associated with the valves m d e d . The normal

operating state codes are listed in Appendix B ofthe NUCLARRData Manual. In more than75% ofthe valve

records, nstate is unspecified and otherwise there are two values of nstate that OCCUT: normally open, d e d

NO, and normally closed, d e d NC. Data is hsufficient to characterize an effect due to normal operating state

so this variable is not considered in any modeling analyses.

0 fdorig This variable indicates the origin or source of the failure count data and is described in Appendix B

of the NUCLARR Data Manual. For the valve reuxds, the majority of the failure counts are obtained fram

plant experience i n d i d by f d d F l " . Only a few case.s (8) indicate fdorig=OTEIR for "other". It is

not expected that the failwe data soulce would have an impact on the plant component failure rates but the

quality ofthe data maybe a f f d BccoTding to soulce. With so few cases other than plant experience, there

is limited ability to characterrze differences in failwe rates according to fdatig.

0 expsdat: This variable indicates the origin or source ofthe data on operatiug hours or number of demands and

is described in Appendix B of the NUCLARR Data Manual. Again, the majority of valve records indicate

plant experience, expsdat=pLNT. as source for exposure data. The following lists codes and descriptions that

OCCUT for the valve data sets.

-pLNT: Plant experience

- T W Total calendar hours

- T a r Total dtid hours

- O m Other

0 ir This variable indicates data records that achieve quality levels established through the Integrated Risk

Assessment Data Acquisition Program ORADAP). Almost WO of tbe data reu-xds achieve IRADAP quality

levels. It is not expected that IRADAP quality assessment of the data reuxds would have any effect on plant

component faihm rates but the quality assessment of the data may be correlated with some moredevant

8

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covariates. With relatively few m d s that are not IRADAp qualified, there is limited ability to characterize

differences in failm rates according to ir.

In addition to facility (ofl) b e i i nested in reactor type (rtype), cross tabulatiam in Tables A.3 and A4

indicate that system is also, virtually, nested in m t o r type. For demanddated valve records. Table A3 is a cross

tabulation including the number of recards, the number of failm counts and the total demands for valve m d s in

a given system and reactor type category. For time-related valve m d s . Table A4 contains similar iuformation.

With the exceptions of systems BI and SJ, each system, for which there is data, uniquely coincides with one reactor

type. This property is d e d collinearity or umfounding of the variables system and reactor type and indicates

dependency between the covariates. Thus, system and mta type cannot me modeled independently. One solution

in modeling is to include a system effect nested in mctm type; however, as will be seen in the following. there are

several problems with collinearity between covariates that further restrict modeling options. For NUCLARR Data

Manual valve recatds. separate analyses by m t o r type will be umdwted in turn in the following.

3. DEMAND-RELATED DATA ANALYSES

Of the 222 demand-related valve failm recatds. 64 are recards on BWR plants, 135 are from PWR plants.

and 23 are missing leactar type information. The BWR and PWR m d s are analyzed respectively in subsections

3.1 and 32.

3.1 Boiling Water Reactor Plants

For the 64 m d - r e h d data rec<Hds ~ ~ C I U J I BWR plants, the wariate pfl is the with pfl=O indicating

that failme unmts may include secondary as well as primary failures. Tables B.l-B.13 provide cross tabulatiiaas

listing thenumberofrecclrds. the totalnumberoffailmmts and total demands on all recclrds, and the observed

failm rate in the cmmpmdq * identified cell. With the exception of Table B.3. B.8 and B.lO. Tables B.l-B.13

all have originating facility, ofl. corresponding to the column dimension of the tables. These tables repeatedly

demonstrate the major problem with the valve data set with there many empty counts. The= is insufficient data

available on covariate values to gemrally assess effects on failm rates.

Table B.l is a cross tabulath h e e n system and originating facility, ofl. and clearly indicates m w t y

between these twocovariates. Only the 34recards far which there is a specified system value are includedinthe

9

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tabled summary information. The collinearity property between system and originating facility means that a system

effect estimate would be biased by an originating facility &=t. From the bottom row of Table B.l, the summary

of recotds by originating facility indicates some striking differences in the observed failure rates with plant BRPl

having a collsiderably higher observed failure rate. This suggests perhaps analyzing of1 c8ses separately; however.

with the possible exception of plant Yx, there is insufficient data for each plant.

Table B.2 cross tabulates recQcds by originating facility, ofl, and component application environment, capll.

This table shows that, outside of plant Yx. there are only 7 records with component application environment

specified and 4 of those are in the single environment capll=INTEWC. Even restricted to plant Yx, the majority

of recoTds with capll specified have capll=INTEWC. The= is hmfficient data to model capll.

Table B.3, B.4, and B.5, are cross tabulatiam between originating facility (ofl), operatop type (optypl) and

valve type (vlvtypl). Table B.3. cross tabulating by operator type and valve type, suggests some confounding

between these two covariates so that only one of operator type or valve type might be modeled. Additionally,

Table B.4 indicates very few c8ses in plants other than Yx when operatur type is specified and Table B.5 indicates

confoundiug between of1 and vlvtypl. In order to assess some effect attributable to operator, again the data from

plant Yx alone might be umsided and it should be understood that the operator covariate also carries valve type

informatim

Table B.6 that aoss tabulates the indicator covariate icl with ofl, originating facility, is interesting and provides

a possiile illustration of the problems that can occur when collinearity or confounding between covariates occuts.

Recall this covariate indicates whether circuitry failures 82e included in the failure count. It would be expected that

inclusion of circuitry failures with component fail- results in higher failure counts and thereby higher failure

rates. However. the summary of observed failure rates by icl categcry in the last column of Table B.6 indicates

that for cases where Circuitry failures are not included, icl=O, the observed failure rate is .00219407. which is larger

than the observed failure rate .O007601 for recurds where icl=l, where circuitry failures are included in failure

counts. If the column corresponding to reusrds fmn plant Yx alone is studied then the aggregate c8ses where

icl=O and ofl=Yx have observed failure rate .00006378 which is d e r , as expected, than the observed failure

rate .00056281 for plant Yx cases where icl=l. Excluding tbe plant Yx cases. Table B.6 shows that the covariates

icl and of1 a~ fully collinear with recotds fran plants BRPl and h4NSl having icl4 and recanls from plants

10

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BWR (a compilation of several BWR plants) and IP4 having icl=l. It just so hap^ that m d s fram plant

BRPl (whm icl=O) seem to have relatively high failure rates and those (few) from plant BWR (where icl=l) seem

to have low failure rates. This alignment of data perhaps masks the expected effect of icl in the overall results

aggregating across all originating facilities. This again provides an argument for looking at date from different

originating faci€ities separately since covariate levels a~ not fully repmented in each facility aUming aggregation

for assesmat of cavariate effects.

Table B.7 a o s s tabulates sgl. the indicator for safety graded components. with originating facility. The only

recokds on safety graded c~mp~nent~ come from plants BRPl and MNS1. A similar phenomena may be ocmming

here as occurred with the covariate icl. Safety graded c~mp~nent~ might be expected to perform better and this

appears to be the case for the few m d s f~om plant MNS1. However, the reverse trend occurs for plant BRPl

and this trend is sustained in the summary across of1 appearing in the last column of Table B.7. The data is clearly

insufficient to make a definitive statement regarding the a€fect of use of safety graded cOmpOnentS on failure rates.

Tables B.8 and B.9 provide some informatim regarding failure mode (hode), n d Operating state (nstate)

and originating facility (ofl). Table B.8 indicates that bode and nstate are collinear, or equivalent, in cases where

nstate is specified. Table B.9 indicates that the cases where a failure mode is specified altemative to fmtxkm0 all

OCCUT in plants BRP1. MNS1 and BWR. cansidering previous reservations regarding operating facilities and noting

that observed failure rates are not substantively d i f f m in columns cOrzeSpOnding to alternative failure modes,

failure mode is not considered as a pdential covariate for modeling the demand related BWR data Tec<gds.

Tables B.lO, B.ll and B.12 illustrate that, for the majority of records, failure data and expome i~~€ormaticm

saun;es areplant experience. Since there are so few cases ofother somes. thesecovariates are assessedmhpormt

to modeling considerations.

Table B.13 indicates that very few data recacds are not N A P qualified. It is interesting that tbe few that are

not qualified came fr<m originating facilities that have previously been put forth as problematic. However, since

the observed failure rates do not seem substantively affected and there are so few cases where kN, this c o v e

is not COIlsidered further.

Table B.14 lists the 35 demand-related data records frun Plant Yx in order Bccording to tbe observed number

offaihrres, with only nondegemmte covaciates include& Specifidy, each d the set ofplant YX demsnd-relnted

11

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data recurds has sgl=O. pfl=O. fmode=FlD, fdoripexpsdat=PLNT and k Y so these values are not listed in Table

B.14. Also, nstate=XX except in 6 cases where nstate=NC and nstate is considered equivalent to fmode so nstate

is not included. Table B.14 demonstrates still many missing values of the remaining 5 covariates: systl, capll,

optypl, vlvtypl and icl. In fact, thexe are only 15 rec<lrds with specific values for each of the 5 covariates and

only 3 of these cases has non-zero failure count. This is insufficient data toevaluate effects of all 5 covariates, or

even subsets of 2 or 3. on failure rate. Even considering only modeling one variable at a time there are few cases

(1 or 2) on most levels of each covariate and thexe is no variability in the observed failure counts which are often

0. Tables B.15-19 show aggregate numbex of records. observed failure m t s , total demands and observed failure

rates by level I;espectively for each of the 5 non-degenerate cavariatas. Fits of logistic regression models each with

a single mariate. systl. capll, optypl, vlvtypl or icl, indicate significant diffemxes in failure rates with diffmnt

levels of any one of these cavariates; however. given the problems stated above. the estimates obtained from these

limited models are suspect and they are not included here.

3 3 Pressurized Water Reactor Plants

Of the 135 demand-related data recards frm PWR type Te8cta[s, 64 are fram Plant X Table C.l is a cross

tabulation of numbex of recards. observed failure counts, total demands and observed failure rate by system (systl)

and plant (ofl). Only the 88 recocds for which there is a specific system value m included in the tabled summary

counts. Alth@ collinearity of these two covariates is somewhat less striking than the same table for BWR

demand-dated data, it is clear again that many cells are missing data In fact, there are few cases where specific

system information is available in plant data other than Plant X For reasons similar to those given previously. we

f m analyses of demanddated datafrcmn PWR type reactocs <HIPlant X records. eliminating collsideration of 80.

originating facility (plant) effect.

For Plant X records. pfl=O, by, fdorig=expsdat=PLNT, fmode=m and nstate=XX except for 3 cases where

nstatsNC. Additionally, there are relatively few cases, 33, where valve type is specified, and Table C 2 illustrates

that operata type and valve type are umfmded. with valve type 3 OcCzItTiDg when operatar is type 3 or5 and valve

type 7 OcCLIcring when operata is also7. This means that operatar type does not strictly represent operator and

actually npresents acornbination of valve and operata type. Fwr this reason valve type iselimhed frcnnmodeling

consideration. This leaves 5 co~ariates for modeling faihrre rates in Plant X: systl (system), capll (applicatim

12

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environment). optypl (operatop type), icl (Circuitry inclusion indicator)). and sgl (safety gr& indicator).

Table C.8 lists 26 recards which form a basis for i d e m and quantifying the effect on failure rates of

the categorical descriptive and qualifying information available for component system, application environment and

opexatop type. With the exception of valve type and sgl, values of the other covariates are fixed. The following

discussion describes how the data of Table C.8 was obtained. For 47 recards in Plant X values for all 5 of the

covariates systl. capll, optypl. icl and sgl are p i f i e d . Initial restriction to this set of recards allowed the

possibiity of simultaneously assessing the effects of these 5 covariates without missing in€ormation. at least among

the origiml set of covariates, and without potentially &own co-ty or umfounding problems that could lead

to errors in inference. Among these limited numbex of records, there are some cases of covariate values for which

there are very few recards or total failme coullt values of 0. This means that there is bmfficient information to

assess the effect for that particular value of the covariate and that it does not contribute to modeling differenus in

covariate levels. Specifically, Table C.3 lists several systems (SB. CI, KA. LD) with few recacds or total failme

counts of 0. Table C.4 lists the number of recards, total failure counts and total demands for the values of capll

that OCCUT. Except for capll values INTEWC and INTEWB, there are very few m d s with alternate values of

capll and as a result hufficient data for assessing the effect of these alternate values of capll. Restricting to the

records for which capll is INTEWC or IN’IEWB allows the possibity of modeling whether there is an effect of

capll at least for these two values of capll. Table C.5 bonstrates that operator type 2 has 0 failure counts based

on 4 recohds. There is no variabiity measured in such a performance and hence the best estimate of the failure

probability associated with operator type 2 is 0. A t w d (1995) observed that based on this type of data t h e is no

informatim contributed about dif€emxxis between operatas and hence this is not of use in modeling 811 operatar

effect. Table C.6 demonstrates that once data is restricted to cases for which capll is INTEWC or INTEWB. then

there isno failure count among records for which i c l 4 so these records are eliminated to focus oncovariate&&

in cases where icl=l. Table C.7 indicates very few cases for which sgl=l, and with the restrictions on capll, sgl

becames umfmded with system. Rather than delete the few cases for which sgl=l and dilute the data set further,

it is undentood that an estimate for system effect may be biased by a potential effect due to sgl. To smmmke,

the data of Table C.8 is a subset of the demand-related valve data from PWR Plant X obtained by deleting cases

as follows:

13

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1. If capll is missing or capll=INTECS or capll=INTEsT or capll=JNTEwS then delete;

2. If systl is missing or systl=KA or systl=Q[ then delete;

3. If optypl is missing or optypl=2 then delete;

4. If i c l4 then delete.

The data of Table C.8 constitutes a subset of the demand-related valve recards with constant (known) values

of the potential covariates rtype. ofl. icl, pfl, fmode. nstate. fdatig. and expsdat. The remaining covariates are

systl. capll, optypl, vlvtypl and sgl. The two covariates vlvtypl and sgl are not considered for modeling as they

are respectively confounded with optypl and systl; however, it should be noted that estimates of o p a h type

effects or system effects will be biased by any me effect due to valve type or safety grade categary. It should also

be cautioned that this data is limited to evaluating the ef€ects of tbe covariates with respect to the few levels that

OCCUT.

Table C.9 and Table C.10 list analysis results for fitting a logistic model to the data of Table C.8. The model

for Table C.9 is the simple intercept model while the model for Table C.10 fits main effects due to optypl, capll

and systl. The intercept model fits with a deviance of402.%78 with 25 mor degrees of W o m . The main effects

model based on optypl, capll and systl fits with a deviance of 51.1245 with 15 mor degrees of freedom. This

duction in deviance from the intercept model to the main effects model with acost of 10 degrees offmdomis

significant at any reasonable level. The test of forward and backward klusicm of each covariate presented under

the titles "LR Statistics for Type 1 Analysis" and 'ZR Statistics for Type 3 Analysis" in Table C.10 indicates that

each covariate is a significant ContfibutOT to the model. The table of parameter estimates in Table C.10 indicates

significantly non-zero estimates for most parmeten. with exceptions b e i i effects of systems BA, SD and SJ.

Graphs C.l and C 2 are diagnostic plots. The purpose of Graph C.l which plots the d e v i i residuals against

predicted values is to evaluate goodness of fit. The= is a seemingly random scatter of the deviance residuals

relative to the horizontal with no clear pattern although the= are a couple of large residual values. This together

with the relatively large deviance value for 15 mor degrees of freedom for the main effects model suggests that the

model falls some short ofexplaining all ofthevariabiity in the data. However, tbe limited data set willnot support

estimation of a much mare complicated model so this model is accepted as adequate. The purpose of Graph C 2

which plots the adjusted dependent variable value, predicted + residual/predicted, against predicted is to evaluate

14

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the goodness of the logistic link function Graph C.2 suggests that the logistic link is adequate.

Table C.ll provides a listing of failure rate predictions and bounds for each of the possible combinations

of the three cavariates optypl, capll and systl by levels which occur in the data of Table C.8. Graph C.3 is a

graphical display of the failure rate interval estimates listed in Table C. 11 with an overlay of the observed failure

rates. The labels on the x-axis cOrreSpOnd respectively to a numeric coding of optypl. capll and systl that is used

and described in Table C.ll. The order of the cases on the x-axis is by system within operata within application

environment. It is apparent frm this plot that the model estimates of all three mariates lead to significantly

different modeled failure rates.

4. TIME-RELATED DATA ANALYSES

Of the 179 time-related valve failure recurds. 41 are recurds on BWR plants, 129 are from PWR plants. and

9 are missing &or type information. The BWR and PWR nxmrds are analyzed respectively in subsections 4.1

and 42.

Also, for the time-related failure data, failure mode categories provide more detail for tbe type of failure that

occurs. Generally separate failure rate analyses are CondUcQd for each category. Recall the failure mode categories

include tbe following:

-BP PlUggea

-LE: E x w leakagehpture

-LI: Internal leakage

-SC Spurious (transfer) close

-so: spurious operation -SP Spurious (transfer) opea

-FTO Failm to Opere.

4.1 Boiling Water Reactor Plants

The available time-~lated data for BWR facilities is insufficient to model mariate &e& on failure rates for

the different failwe mode Categories. Table D.l is a CTOSS tabulatcm between facility, ofl. and failure

mode, fmode adindicates that t h e i s veay little data with the possible exception of plant Yx and failure modes

15

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LI and FM). For all 41 time-dated data mmds frm BWR plants, the potential covariate sgl is fixed with sgl=O.

The same is true for the potential covariate pfl which has value pfl=O except for records (2) that OCCUT in failure

mode fmodsLE where pfl=l. In fact, for failure modes LE. SC and SP all potential covariate information is

either fixed or missing within the failure mode category. For failure mode SO there are only four records with only

operatat/valve type (optypl and vlvtypl) having four distinct values. This is insufficient data to assess effects on

failure rates for these failure mode categories.

Table D.2 lists number of mmds. observed failures, exposures in total hours. and observed failure rate for cell

categories dekrmined by system (systl) and operating facility (ofl) listed by the two failure mode categories FID

and LL Table D.3 lists the same information for cell categories defined by operator type (optypl) and operating

facility (ofl) listed by the two failure made categoria FM) and LI. Other potential covariates, including capll,

vlvtypl. nstate. fdarig. expsdat. icl and ir. are either missing values, constaut for all but perhaps a single recad,

or collinear with one of the covariates of Tables D 2 and D.3. Tables D.2 and D.3 indicate many empty cells and

substantial missing covariate information in spite of what initially appears to be a large number of valve records.

As result of these limitations, there is insufficient data to model covariate effects.

4.2 Pressurized Water Reactor Plants

Of the 129 time-dated reads fram PWR type readats. 74 are from Plant X (51 under failure mode calegay

FID, 22 under categay LI, and 1 under categary SP). Table El provides a o s s tabulation of number of recatds.

observed failm counts, exposure in total hours, and observed failure rate by failure mode (bode) and plant (ofl).

This table indicates there is very little data with the possible exception of plant X and failure modes FID and U

so the maindex of tb is section focuses on plant X data for these two failure modes in turn.

The 22 time-dated recotds fram plant X with fail- mode LI are listed in Table E 2 in order of observed

nurnber of failures. These reccrds have common values for the potential covariates fdorig. expsdat. ir, and pfl so

these covariates are not included in the listing in Table E2. The wariates nstate. optypl and vlvtypl also have

common values with one exception (recard numbex 938) which is missing a specific value for system and capll

and eliminated fram modeling considerations. Only four potential covariates remain: systl, capll. icl and sgl.

Table E3, a cross tabulation of recoeds by system and application envin)srment. shows collinearity between k s e

twocovariates. Also, there are only tworeads for wbichsgl=l and the.re is no failure count for these recoeds

16

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and thereby imnflicient information to contribute about diffemus in failure rates for safety graded components.

In fact them are few m d s (5) with non-zero failure count. Table E.4. a cross tabulation of records by system and

icl, shows that there are 13 system categories (11 if the two recacds for which sgl=l are eliminated). This means

that there are few records, less than 3 in all but one case, on any single system and as a result insufficient data to

model even a single effect due to system. Generally, as a result of the sparseness of this data, there is hmfficient

information for modeling the two covariates which do vary.

The 51 time-mlated recokds from plant X with failure mode FTO are listed in Table E5 in order of observed

number of f a i lm . These records have common values for the potential covariates nstate. fdarig, expsdat. and pfl

so these covariates are not included in Table E.5. Also, the potential covariate vlvtypl is not included in Table E.5

since it is missing in all but 16 records and in those recards is identical to optypl. Six potential covariates remain:

systl, capll, optypl, icl. sgl, and ir. As with the failure records for failure mode LI, there are few records (6) with

non-zero failure counts. and almost a dozen categcuies of system and almost half that many of operata type (5)

occur. This makes for a sparse data set with insufficient informafim for modeling covariates independently. Fits of

Poisson regression models, each with a single covariate restricted to categories for which there is either failure count

or a substantive number of recards, indicates significant diffmmx in failure rates with diffexent levels of all of the

six above potential covariates except for icl; however. the mariates are pairwise collinear to some degree so there

is no clear identillcation of a single covariate effect and given the problems stated above, estimates obtained from

these limited models are suspect and these are not included hem. Tables E610 show aggregate number ofrecurds.

observed failure counts, exposures in total hours. and o k e d failure rates cross tabulated by system (systl) and

each of application environment (capll), operata type (optypl). idusim of circuit indicator (icl), safety grade

indicator (sgl). and IRADAP quality data indicator (ii).

5. SUMMARY AND CONCLUSIONS

Although the NUCLARR Data Manual valve failure data is limited by missing covariate informatian and

gnaU numbers in some covariate cells, there are clear significrmt covariate effects particularly for the data of Plant

X and for covariates aperator type. application environment and system. As a result of these si- it is

inappropriate to ignore many missing covariate values and a l l a l p data acm6s levels of certain covariates. Instead

weidentified subsets oftbe data fur which some covariatevalues are fixed and others that vary are known. This

17

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resulted in limited data and in some cases insufficient data for model fitting. The model fitting that is possible

demonstrates significant covariate effects but with the limited data available specific estimates of effects afcovariate

levels are limited to a few and likely suspect.

ACKNOWLEDGEMENTS

The author gratefully aclolowledges the assistance of &alp Hemphill, Claudia Peck, Vivian Ramero, Harry

Martz and T. S. A. Juan with the work performed for this task.

REFERENCES

1. Reece, W. J.. Gilbert, B. G., and Richards, R. E. (1994). "Nuclear Camputerized Library for Assessing Reactar

Reliability (NUCLARR) Data Manual, Part 3: Hardware Component Failure Data," NUREG/CR4639, EGG-

2458, Volume 5. Revision 4.

2. Atwood, C. L. (1985). "Modeling Patterns in Count Data Using Log-linear andRelated Models." INEL-95B121.

18

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APPENDIX A Demand-related and Timerelated Failure Data from NUCLARR Data Manual

19

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Table A.1

c2demand.ssd: Demand-related failure data

cap11 Applica -tion

systl Environ System -ment

fdoriq expsdat Fail Expo -ure -sure Data Data Source Source

PLNT PLNT PLNT TCRT PLNT PLNT PLNT TCRT PLNT PLNT PLNT PLNT PLNT TCRT PLNT TCRT PLNT TCRT PLNT TCRT PLNT TCRT PLNT TCRT PLNT TCRT PLNT PLNT PLNT TCRT PLNT TCRT PLNT TCRT PLNT TCRT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT OTHR TCRT OTHR TCRT OTHR OTHR OTHR TCRT OTHR TCRT OTHR OTHR PLNT OTHR PLNT MHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT

vlvtypl iCl sq1 Valve Includes Safety Type Circuit? Graded?

3 0 1 3 1 0

0 1 1 0 0 1 0 1 1 0 1 0 1 0

3 1 0 3 1 0 3 1 0 3 1 0

0 1 1 0

7 1 0 7 1 0 7 1 0 7 0 1 7 0 1 7 0 1

0 1 0 .l 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 0 1 1 0

3 1 0 3 1 0 3 1 0

i

i

;

i

Pfl Primary Failures Only?

1 0 1 0 1 1 0 0 0 0 0 0 0 1 0 0 0 0 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

.. 0 0 0 0 0 0 0 0 0 0 0 0 0 0

fmode Failure Mode

FTP FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTC FTC FTP FTP FTC FTP FTP FTP FTO FTC FTP FTP FTC FTP FTP FTC FTP FTC FTP FTC FTC FTP FTP FTO FTO FTO FTO FTO FTO FTO FTC FTP FTC FTP FTC FTP FTC FTP FTO FTO FTO FTO FTO FTO FTO FTO - FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FM FTO FTO FTO FTO FTO

nstate Normal State

NC xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx NC NC xx xx NO NC NC NO NC NC NO NC NO NC xx xx xx xx NC NC xx xx xx xx xx xx xx xx xx NO NC NO NC xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx NC NC NC NC NC NC xx xx xx xx xx

numfail Failures

totd Demands

frate Failure Rate

0.00006 0.00316 0.00090 0.00647 0.01063 0.00418 0.00485 0.00336 0.00167 0.00509 0.00717 0.00719 0.01093 0.00006 0.00118 0.00156 0.00078 0.00828 0.00307 0.00889 0.00393 0.00259 0.00382 0.02576 0.02133 0.00465 0.08370 0.14286 0.01600 0.01565 0.00708 0.03846 0.01304 0.00055 0.00343 0.00000 0.00031 0.00592 0.00014 0.00269 0.00069 0.00417 0.00104 0.00198 0.00000 0.00000 0.00444 0.00000 0.00346 0.00528 0.01897 0.01355 0.00000 0.00000 0.00000 0.00036 0.03922 0.00170 0.00141 0.02830 0.00000 0.00000 0.01370 0.01020 0.00000 0.00000 0.00070 0.00503 0.00000 0.00038 0.00103 0.00000 0.00000 0.00000 0 .00000 0 .00000 0 .00000 0.00000 0 . 0 0 0 0 0 0.00000 0 . 0 0 0 0 0 0 .00000 0 .00000 0 .00000 0.00000 0.00000 0.00000 0.00739 0.00000 0.00000 0.00018 0.00000

Of1 Facility

ir IRADAP?

N Y N Y N N Y Y Y Y Y Y Y N Y Y Y Y N N N Y Y N N Y Y Y Y Y Y Y Y N N N N N N Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y

recno Record

571 592 803 549 967

727 728 453 454 455 456 457 747 849 850 855 856 890 927 928 986 700 977 983 985 978 982 984 667 702 666 703 566 567 517 580 800 799 786 791 612 630 609 564 575 565 576 668 704 669 705 980 981 569 810 553 551 554 555 550 552 951 952 953 950 684 602 603 749 472 478 470 474 471 473 476 469 477 475 488 894 973 974 891 892 893 682 680 599 765 767

678

3 2

46544 632

1 1 2 3 3 3 3 3 3 3 3 5 7 7 7 7 7 7 7

8 8 94

235

8843 1236 8843

56282 6181 1486 600 983

2512 3059 2012 63073 845

30 5 1 5 18 22 22 4 1 2 1

1281 1281

7 20 58 7 4

845 6524 6524 1783 1542 AREL

AREL BRP 1 BRP 1 BRP 1 BRPl BRP 1 BRP 1 BRPl BRP 1 BRPl BRPl BWR BWR BWR BWR BWR BWR I P 4 I P 4 I P 4 I P 4 I P 4 MNS 1 MNS1. MNS 1 MNS 1 MNS 1 MNSl MNSl MNS 1 YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX BSW BSW BLW BSW BLW

3 21 16

5500 621 BWR

BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR PWR PWR PWR PWR PWR

16 1 19

750 215 227 28 125 639 989 52

230 3628

BY J M JI INTEST BL INTEWC

4 2 10 7

MS INTEST BG/BM INTEWB

2 3 2 11 0 1 14

3211 3628 3211 2366 27816

1 1 1

1 0 1 0

2 1 0 AA INTEWC 4

19 1 9 7 1 0 0

7060 1440 2160 6700 504

1 3

5 1 0 2 1 0

3 3

4 1 0 8 1 0 3 0 1 3 0 1 3 0 0 3 0 0

0 0 0 0 0 0 0 0 1 0 1 0 0 0 1 0

i

xc xc S J INTEWC S J INTEWC

1272 1272

3 0

676 676

5497 5497 369 369 429 463 724

49889 102 588 708 106 926 856 73 98 704 582

46983 199 1522 5292

19 29 7 5 0 0 0 18 4 1

NT NT CH INTEWB CH INTEWB

i 1 1 1

3 1 0 3 1 0 BG/BM INTEWC

BG/BM INTEWC BN INTEWC CH INTEWC CH INTEWC

3 1 0 3 1 0 3 1 0 3 1 0

1 0 1 0 1 0 1 0 1 0 1 0 1 0 0 0 0 0

3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 0 0 3 1 0 7 0 0 7 1 0 7 1 0 7 0 0 7 0 0 7 0 0

1 0 1 0 1 0 1 0 1 0

i

1 3 1

1 0 0 1 1 0 0

33 1 0 2

1 2 2

BG/BM BG/BM INTEWC

2 2 3 4 4 5 5 5 5 5 5 5 5 5 5 5

1 0

971 816

3493 704

10273 4230

BG/BM BN CH BG/BM INTEWC BN INTEWC CH INTEWC

INTEWD B I INTEWD €31 INTEWD

INTEAR BN INTEAR BG/BM INTEWC BN INTEWC BN INTEWC C I SB SB INTEST C I C I

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13 0 0

504 11112 891 7855 7665 131

5 7 7 7 7 7 7 3 3 4 5 5

25 20 10 18 15

1760 973 605

1 0

5532 14612

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Table A . 1 (continued)

c2demand.ssd: Demand-related fai lure dat a

rtype recno Reactor Record Type I

763 PWR 899 PWR 901 PWR 896 PWR 581 PWR 827 PWR 671 PWR 706 PWR 568 PWR 804 PWR 679 PWR 627 PWR 597 PWR 604 PWR 467 PWR 516 PWR 858 PWR 861 PWR 838 PWR 839 PWR 889 PWR 929 PWR 809 PWR 670 PWR 748 PWR 925 PWR 570 PWR 826 PWR 701 PWR 860 PWR 926 PWR 785 PWR 795 PWR 792 PWR 946 PWR 613 PWR 629 PWR 616 PWR 739 PWR 738 PWR 888 PWR 895 PWR 574 PWR 802 PWR 677 PWR 563 PWR 572 PWR 798 PWR 674 PWR 675 PWR 598 PWR 468 PWR 515 PWR 531 PWR 539 PWR 847 PWR 851 PWR 848 PWR 852 PWR 578 PWR 579 PWR 593 PWR 808 PWR 816 PWR 806 PWR 811 PWR 812 PWR 813 PWR 814 PWR 815 PWR 801 PWR 958 PWR 960 PWR 965 PWR 959 PWR 689 PWR 686 PWR 692 PWR 688 PWR 687 PWR 690 PWR 691 PWR 461 PWR 460 PWR 756 PWR 758 PWR 754 PWR 755 PWR 753 PWR 759 PWR 752 PWR 761 PWR

cap11 Applica -tion

of1 systl Environ "acility system -ment

B6W SB B6W CI B6W CI B6W SB BREL BREL BREL BREL DBSl DBSl DBSl DBSl SB DBSl SB DBSl SB DBSl DBS 1 DBSl ABlAP DBSl AB/AP DBSl SB DBSl SB DBSl SB DBSl SB EUR EUR EUR EUR FPRA FPRA FPRA FPRA AP FPRA AP IP1 IP1 IP1 IP1 IP1 IP1 IP1 IP1 IP1 IP1 IP1 IPS2 IPS2 IPS2 NEE3 NEE3 NEE3 NEE3 NEE3 SG INTEWC NEE3 NEE3 NEE3 NEE3 NEE3 NEE3 NEE3 NEE3 AP NEE3 AP RGLS RGLS X SB X CI X KE X SB X BP INTEWB X CB INTEWB X BA INTEWC X CC INTEWC X SD INTEWC X SJ INTEWC X BE INTECS X AB INTEWC X BA INTEWC X CB INTEWC X BE X BP INTEWB X CB INTEWB X AB INTEWC X BA INTEWC X SD INTEWC X SJ INTEWC X BA INTEWC X SJ INTEWC X BE X BS X KE X I 9 X SB X AB INTEWB X BP INTEWB X CB INTEWB

OPtYPl

Type Operator

5 7 7 7

1 3 3

1 3 3 4 4 5 5 7 7 7 7 7 7 1 3 5 7

1 1 1 2 3

7 7

i 3

1 3 3 4 5 5 5 5 7 7 7 7

1 1 1 1 1 1 1 1 1 2 2 2 2 3 3 3 3 3 3 3 3 3 5 5 5 5 5 5 5 5

P f l vlvtypl icl sgl Primary Valve Includes Safety Failures Type Circuit? Graded? Only?

; 1 0 0 1 0 0

7 1 0 0 7 1 0 0 3 0 1 1

0 1 1 0 1 1 0 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

3 0 0 0 3 0 0 0 7 0 0 0 7 0 0 0 7 0 0 0 7 0 0 0 7 0 0 0 7 0 0 0

1 0 0

i

i

i 3

7 7 3

3 3

i 3 3 3 7 7 7 7 3 3 3

3 3

1 0 1 0 1 0 0 1 0 1 0 1 0 1 0 1 1 0 1 0 1 0 1 0 1 0 1 0 1 0

0 1 0 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 0 0 0 1 0 1 0 1 0 1 1 1 0 1 0 1 0 1 0 1 0 1 0 1 0 0 0 1 0 1 0 1 1 1 0 1 1 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 1 1 1 1 0

.1

0 0 0 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

fmode Failure Mode

FTO FTO FTO FTO FTP FTP FTC FTP FTC FTO FTO FTC FTC FTP FTC FTP FTC FTP FTC FTP FTC FTP FTO FTC FTO FTP FTO FTO FTO FTP FTP FTO FTO FTO FTO FTO FTO FTO FTO FTO FTC FTO FTP FTO FTO FTC FTP FTO FTO FTO FTO FTC FTP FTC FTP FTC FTP FTC FTP FTP FTP FTO FTO FTO FTO FTO F M FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO

nstate Normal State

xx xx xx xx xx xx xx xx xx xx xx NO NC NC xx xx NC NC NC NC NC NC xx NO xx NC xx xx xx NC NC xx xx xx xx xx xx xx xx xx NC NC xx xx xx xx xx NC NO NO NO xx xx xx xx NO NC NO NC xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx

fdorig expedat Fail Expo -ure -sure Data Data Source Source

PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT OTHR PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT OTHR PLNT OTHR PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT

ir numfail IRADAP? Failures

Y 0 Y 1 Y 0 Y 0 Y 0 Y 0 Y 1 Y 0 U 3 U 21 u 80 U 1 u 2 U 3 u 3 U 2 U 2 U 1 U 2 U 2 U 5 U 2 Y 2 Y 7 Y 1 Y 0 Y 12 Y 7 Y 50 Y 0 Y 0 Y 4 Y 25 Y 28 Y 2 Y 13 Y 6 Y 16 Y 3 Y 2 Y 4 Y 6 Y 0 Y 1 Y 3 Y 1 Y 0 Y 3 Y 42 Y 5 Y 10 Y 0 Y 0 Y 1 Y 0 Y 1 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 2 Y 14 Y 0 Y 3 Y 15 Y 0 Y 13 Y 5 Y 6 Y 0 Y 0 Y 0 Y 0 Y 3 Y 3 Y 18 Y 15 Y 5 Y 1 Y 22 Y 0 Y 0 Y 2 Y 2 Y 9 Y 2 Y 0 Y 2 Y 0 Y 5

totd Demands

25876 568 90 735 2084 167 1693

50 4126 4276 9798 159 727 727 1438 1438 175 175 1873 1873 253 253 869

2388 1949

84 8716 2720 14200

18 131 1560 2520 7080 120 1800 5700 1740 1200 600 7860 7860 1444 1050 1261 321 251 1349 6725 30

2564 426 427 2719 2707

31 31 10 10

1844 658 564 554 68

1538 24 862 89 222 813 1715 1488 105 356 67

215 60

855 97 879 367 3679 191 346 225 199 598 515 7866 1329 297 1184

frate Failure Rate

0 . 0 0 0 0 0 0.00176 0 . 0 0 0 0 0 0.00000 0.00000 0.00000 0.00059 0.00000 0.00073 0.00491 0.00816 0.00629 0.00275 0.00413 0.00209 0.00139 0.01143 0.00571 0.00107 0.00107 0.01976 0.00791 0.00230 0.00293 0.00051 0.00000 0.00138 0.00257 0.00352 0.00000 0.00000 0.00256 0.00992 0.00395 0.01667 0.00722 0.00105 0.00920 0.00250 0.00333 0.00051 0.00076 0.00000 0.00095 0.00238 0.00312 0.00000 0.00222 0.00625 0.16667 0.00390 0.00000 0.00000 0.00037 0.00000 0.03226 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00361 0.20588 0.00000 0.12500 0.01740 0.00000 0.05856 0.00615 0.00350 0.00000 0.00000 0.00000 0.00000 0 .On95 0.05000 0.02105 0.15464 0.00569 0.00272 0.00598 0.00000 0.00000 0.00889 0.01005 0.01505 0.00388 0.00000 0.00150 0.00000 0.00422 .

Page 25: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

rtYPe recno Reactor

Record Type

760 PWR 757 PWR 751 PWR 487 PWR 482 PWR 534 PWR 479 PWR 449 PWR 538 PWR 537 PWR 483 PWR 535 PWR 485 PWR 486 PWR 481 PWR 533 PWR 448 PWR 480 PWR 532 PWR 484 PWR 536 PWR 908 PWR 902 PWR 906 PWR 907 PWR 904 PWR 859 PWR 905 PWR 903 PWR 912 PWR 909 PWR 910 PWR 911 PWR 573 PWR 817 PWR 676 PWR 672 PWR 673 PWR

cap11 Applica -tion

of1 systl Environ Facility system -ment

X BA INTEWC X CC INTEWC X SJ INTEWC X KE X BE INTECS X BE INTECS

OPtYPl operator

Type

5 5 5 5 5 5

X X X X X X X X X X X X X X X X X X X X X X X X X X X ZlSl ZlSl ZlSl ZlSl ZlSl

SB INTEST 5 INTEWC 5

BA INTEWC 5 CB INTEWC 5 CC INTEWC 5 CC INTEWC 5 CI INTEWC 5 CI INTEWC 5 KA INTEWC 5 SD INTEWC 5 SJ INTEWC 5 SJ INTEWC 5 SJ INTEWC 5 BS INTEWS 5 BS INTEWS 5 BE 7 BS 7 KE 7 LD 7 SB 7 SB INTEST 7 AB INTEWB 7 BP INTEWB 7 CB INTEWB 7 CC INTEWC 7 SD INTEWC 7 SJ INTEWC 7

i 3

BE INTEWB 3 CB INTEWB 3

Table A.l (continued)

c2demand.ssd: Demand-related failure data

fdorig expsdat Pfl Fail Expo

vlvtypl icl sgl Primary fmode nstate -ure -sure Valve Includes Safety Failures Failure Normal Data Data Type Circuit? Graded? Only? Mode State Source Source

1 0 0 FTO XX PLNT PLNT 1 0 0 FTO XX PLNT PLNT 1 0 0 FTO XX PLNT PLNT

3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO M PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0. 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 3 0 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO NC PLNT PLNT 7 1 1 0 FTO XX PLNT PLNT 7 1 1 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 7 1 0 0 FTO XX PLNT PLNT 3 0 0 0 FTP XX PLNT PLNT

0 0 0 FTO XX PLNT PLNT 0 0 0 FTO XX PLNT PLNT 0 1 0 FTO NC PLNT PLNT 0 0 0 FTO NC PLNT PLNT

i 1 0 0 FTO XX PLNT PLNT

frate ir numfail totd Failure

IRADAP? Failures Demands Rate

Y 0 Y 12 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0

201 0.000000 1064 0.011278

21051 0.000000 19 0.000000

2245 0.000000 700 0.000000 431 0.000000 134 0.000000 716 0.000000 327 0.000000 38 0.000000 381 0.000000

Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y

0 0

182 0.000000 320 0.000000

0 631 0.000000 0 140 0.000000 0 147 0.000000 0 572 0.000000 0 1425 0.000000 0 22 0.000000 1 371 0.002695 0 21 0.000000 0 30 0.000000 0 14 0.000000 0 30 0.000000 0 200 0.000000 0 172 0.000000 1 42 0.023810 0 12 0.000000 0 93 0.000000 1 307 0.003257 0 24 0.000000 4 621 0.006441 0 6968 0.000000 3 1540 0.001948

Y 14 11310 0.001238 Y 1647 0.006072 Y 7 1720 0.004070

10

Page 26: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

cap11

Table A.2

c2time.ssd: Time-related failure data

fdorig expsdat Applica Pfl Fail Expo

recno Reactor of1 syetl Environ operator Valve Includes safety Failure8 Failure Normal Data Data rtype -tion optypl vlvtypl icl sgl Primary fmode nstate -ure -sure

746 582 828 583 710 836 942 943 944 994 995 715 949 989 990 787 930 789 614 641 939 979 955 956 954 957 685 601 975 976 991 992 587 588 829 559 557 560 561 556 558 518 520 931 934 935 932 933 936 937 683 681 600 764 766 762 898 900 897 596 94 5 584 711 589 833 782 834 941 590 835 969 790 796 793 788 797 794 94 7 615 642 617 743 586 832 709 781 837 713 714 887 591 830

Record Type

BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR BWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR

Facility system -ment

BRP 1 BRP 1 BRP 1 BWR BWR BWR IP4 IP4 IP4 IP4 IP4 IP4 M S 1 YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX YX BKW BCW BKW BCW BCW BCW BLW BCW B6W BREL DBSl DBSl DBSl EUR EUR EUR EUR EUR FPRA FPRA FPRA IP1 IP1 IP1 IP1 IP1 IP1 IP1 IP1 IP 1 IP1 IP 1 IPS2 IPS2 IPS2 IPS2 IPS2 IPS2 IPS2 IPS2 NEE3 NEE3

SJ

BG/BM BG/BM

BN CH CH

BG/BM BG/BM BN CH CH

BI

BG/BM BG/BM BN BN CI SB SB CI CI SB CI CI SB BA

INTEWC

INTEWC INTEWC

INTEAR INTEAR INTEWB INTEWB

INTEWC INTEWC INTEWC INTEWC INTEWC

INTEWD

INTEWC INTEWC INTEWC INTEWC

INTEST

Type

5

i i 1 7 7 7

i

i

2

7 1 3 3 7

; 2 2 2 3 4 7 7

i 1 1 1 1 1 1 5 5 7 7 7 7 7 7 7 3 3 4 5 5 5 7 7 7 6 2

i 1 5 1 7

1 2 1 1 1 1 1 1 2 3 3 3 5

i 3 5 1 3 3 7

i

Type

i i

; 7 7

; 7 2 2 4 7

;

i

i

7

3

3 3 3 3 3 3 3 7 7 7 7 7 7 7

7 7 7

i

i 3

7 3

i 4 5 2 4 5 5 2 4 5 4 3

i 3

Circuit? Gradedi

0 0 0 0 1 1 0 0 1 0 0 0 1 0 0 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 1 1 1 1 1 0 0 0 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0

1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

Only?

1 1 1 1 1 1 1 1 0 0 0 0 0 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 1 1 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 0 0

node

BP LE LE LI SC so SP SP SP SC SP SP FTO LE LE LI LI SO SO SO SO FTO FTO FTO FTO FTO FTO FTO FTO FTO LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI FTO FTO FTO FTO FTO FTO FTO FTO FTO SO FTO LI SO LI SC SC SO SP LI SO SO LI LI LI SO SO SO SO SO SO SO SO LI SC SC SC SP SP SP SP SC SC

State

xx xx xx NC NO xx NC NC xx xx xx xx xx xx xx xx NC xx xx xx NC NC xx xx xx xx xx xx NC NC xx xx xx xx xx xx xx xx xx xx xx xx xx NC NC NC NC NC NC NC xx xx xx xx xx xx xx xx xx xx NO NC xx xx NO NO xx NC xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx NO NO NO NC NC NC NC NO NO

Source Source

PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT OTHR PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT OTHR PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT P LNT PLNT PLNT PLNT PLNT P LNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT

PLNT PLNT PLNT PLNT P LNT P LNT P LNT PLNT TCRT PLNT PLNT PLNT TCRT PLNT PLNT TCAL TCAL TCAL TCAL TCAL TCAL PLNT PLNT PLNT PLNT PLNT PLNT P LNT P LNT PLNT P LNT P LNT P LNT PLNT P LNT PLNT PLNT P LNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT P LNT P LNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT TCAL TCAL TCAL TCAL TCAL TCAL TCAL TCAL TCAL TCAL TCAL PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT

frate ir numfail tothrs Failure

IRADAP? Failures Hours Rate

N N N N N N N N Y Y Y Y N Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y U U U Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y

0 5 2 55 2 4 23 14 7 4 3 1 16 38 1 2 1 1 1 7 1 18 0 0 0 0 10 0 0 0 0 0 4 2 8 0 0 1 1 0 0 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 12 0 3 5 0 0 5 0 9 7 0 3 1 2 3 5 6 1 2 10 2 1 1 0 0 0 0 0 0 1 0 1

137818032 . O O O O O O O 101566848 . O O O O O O O 19322736 .0000001

101566848 .0000005 123802872 . O O O O O O O 19322736 .0000002 6646920 .0000035 4175880 .0000034 4040000 .0000017 3944160 .0000010 3944160 .0000008 1254960 .0000008

22600000 .0000007 3780000000 . O O O O O O O 3780000000 . O O O O O O O

5150000 .0000004 2150000 .0000005 5150000 .0000002 1580000 .0000006 4890000 .0000014 2150000 .0000005 148479 .0001212

89 .ooooooo 131 . O O O O O O O 295 . O O O O O O O 357 .ooooooo

239117 .0000418 262 . O O O O O O O 655 . O O O O O O O 488 .ooooooo

2501 . O O O O O O O 3737 .ooooooo 890 .0044944

966700 .0000021 5348898 .0000015

131 . O O O O O O O 295 . O O O O O O O 357 .0028011 122 .0081967 5002 . O O O O O O O 7474 .ooooooo

187067 .0000267 7690 . O O O O O O O 262 . O O O O O O O 178 . O O O O O O O

75151 . O O O O O O O 295 . O O O O O O O 357 .ooooooo 366 . O O O O O O O 264 . O O O O O O O

163280 . O O O O O O O 403572 . O O O O O O O 269048 . O O O O O O O 530660 . O O O O O O O

2630396 . O O O O O O O 11602695 . O O O O O O O

57148 .OOOOOOO 288702 . O O O O O O O 538096 .OOOOOOO 184104 .0000435 364728 .0000329 4324632 .OOOOOOO 4012008 .0000007 1497730 .0000033 699596 .OOOOOOO

2939265 .OOOOOOO 1120765 .0000045 53130 . O O O O O O O

376000 .0000239 1580000 .0000044 812000 .ooooooo 1840000 .0000016 1840000 .0000005 5170000 .0000004 1140000 .0000026 1840000 .0000027 5170000 .0000012

88000 .0000114 1310000 .0000015 4160000 .0000024 1270000 .0000016 876000 .0000011 444000 .0000023 444000 .OOOOOOO 6000000 .OOOOOOO 6000000 .OOOOOOO 37000 . O O O O O O O

703 . O O O O O O O 818 .ooooooo

301000 .0000033 342000 .OOOOOOO 194000 .0000052

~

Page 27: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table A.2 (continued)

c2time.ssd: Time-related failure data fdorig expsdat

Pf 1 Fail EXPO cap11 Applica ..

rtype -tion optypl vlvtypl i c l sgl Primary fmode nstate -ure -&re recno Reactor of1 systl Environ Operator Valve Includes Safety Failures Failure Normal Data Data Record Type

707 605 780 530 548 987 988 595 594 807 820 821 805 818 819 825 822 823 824 963 962 964 966 961 696 695 693 694 699 697 698 458 459 750 774 768 772 773 778 771 769 770 779 775 776 777 919 913 917 918 923 916 914 915 924 920 921 922 527 523 519 526 543 544 521 525 522 524 541 452 547 528 545 529 542 450 540 451 546 938 862 585 993 831 708 712 857

PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR PWR

Facility System -ment

NEE3 NEE3 NEE3 NEE3 NEE3 PWR PWR X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X ZlSl 21.51 ZlSl ZlSl ZlSl ZlSl

SB BP CI KE LD SB BP CB BA cc SD SJ LD BE AB BA CB BE AB BP CB BA SD SJ BA SJ

BE BI KE LD SB AB BP CB BA cc SD SJ BE BI KE ID SB AB BP CB BA cc SD SJ BE 81 CI KE LD BE SB BP CI CI BA CB CB cc cc SD SD SJ SJ BS BS

SB

INTEST INTEWB

INTEWB INTEWB INTEWC INTEWC INTEWC INTEWC INTEAR INTECS INTEWC INTEWC INTEWC

INTEWB INTEWB INTEWB INTEWC INTEWC INTEWC INTEWC INTEWC

INTEWB INTEWB INTEWB INTEWC INTEWC INTEWC INTEWC

INTEWB INTEWB INTEWB INTEWC INTEWC INTEWC INTEWC

INTEAR INTECS INTEST INTEWB INTEWB INTEWB INTEWC INTEWC INTEWC INTEWC INTEWC INTEWC INTEWC INTEWC INTEWC INTEWS INTEWS

INTEST

Type

3 4 5 5 5

; 1 1 1 1 1 1 1 1 1 2 2 2 2 2 3 3 3 3 3 3 3 3 3 5 5 5 5 5 5 5 5 5 5 5 5 5 7 7 7 7 7 7 7 7 7 7 7 7 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 7 7

; 3 3 7

Type

i

i

3

3

i 3

i 7 7 7 7 7 7 7 7 7 7 7 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 7 7 3

i

Circuit? Graded?

0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 1 0 0 1 1 1 1 0 0 0 1 0 1 0 0 0 0 0 1 1 0 0 0 0 0 0

0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 0 0 0 1 0 0 0 1 1 0 0 0 0 0 0 1 0 0 0 1 1 0 0 0 0 0 0 1 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

Only?

0 0 0 0 0 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

Mode

SC SC SC SC SC LE LE FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI LI SP LI SC SC SC SP SP

State

NO NO NO NO NO xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx NC NC xx NO NO NO NC NC

Source Source

PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT

PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT PLNT P LNT PLNT P LNT P LNT P LNT PLNT P LNT PLNT PLNT P LNT PLNT PLNT PLNT PLNT

ir numfail IRADAP? Failures

Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y N Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y N Y Y N Y Y Y Y Y Y Y N Y Y Y N Y Y Y Y Y Y Y N Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y Y

0 0 1 0 0 86 6 0 0 0 0 0 0 1 0 0 0 0 1 0 0 0 0 0 0 0 5 0 0 0 0 0 0 4 2 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 2 0 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 0 0 0 0 0 0 0 2

frate tothrs Failure Hours Rate

1890000 . O O O O O O O 274000 . O O O O O O O 3090000 .0000003 148000 . O O O O O O O 239000 . O O O O O O O

9500000000 .0000000 9500000000 .ooooooo

269048 . O O O O O O O 168155 .OOOOOOO 96234 . O O O O O O O

311841 . O O O O O O O 50688 . O O O O O O O

672620 . O O O O O O O 201786 .0000050 1200000 .ooooooo

54 .ooooooo 1571328 .OOOOOOO 369941 . O O O O O O O 336310 .0000030 101376 .OOOOOOO

1120 .ooooooo 315504 . O O O ~ O O O O

216 .OOOOOOO 101376 .OOOOOOO

560 .OOOOOOO 157752 .OOOOOOO 201786 .0000248 1100000 .ooooooo

486 .OOOOOOO 168155 .OOOOOOO 706251 . O O O O O O O

108 .ooooooo 67262 .OOOOOOO

101561962 . O O O O O O O 5320 .0003759

2027520 . O O O O O O O 2771920 . O O O O O O O 18000000 .ooooooo 3654886 .OOOOOOO 5915700 .OOOOOOO 15806571 .0000001 17000000 . O O O O O O O

1512 .OOOOOOO 18084928 . O O O O O O O 6154473 . O O O O O O O 4809233 . O O O O O O O

280 .ooooooo 202752 .OOOOOOO 69298 . O O O O O O O

304128 . O O O O O O O 134524 . O O O O O O O 197190 . O O O O O O O 67262 . O O O O O O O

861696 . O O O O O O O 54 .ooooooo

2889216 . O O O O O O O 134524 . O O O O O O O 134524 .OOOOOOO 2240 . O O O O O O O

1115136 .OOOOOOO 2665402 .0000011 103947 .0000192 101376 .OOOOOOO

700 .0014286 201786 . O O O O O O O 134524 . O O O O O O O 32656 . O O O O O O O 32078 . O O O O O O O 432 . O O O O O O O

709632 . O O O O O O O 912384 . O O O O O O O 304128 .0000033 253440 . O O O O O O O 302679 . O O O O O O O 67262 .OOOOOOO 33631 . O O O O O O O

336310 .OOOOOOO 50688 . O O O O O O O 152064 .0000066

6138382 .OOOOOOO 134524 . O O O O O O O 608000 .OOOOOOO

11100000 .ooooooo 2130000 .OOOOOOO 11100000 .ooooooo 695000 . O O O O O O O 619000 .0000032

Page 28: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table A.3

Demand-related failure data: Cross tabulation of total number of records, total failures, total demands and observed cell failure rate by System and Reactor Type

I Reactor Type I I I I

I I I I Ph'R I BWR I missing I RLL I I System I I I I I

I lmissing I I I I SB I I I 1 CI I I I I CB I I I I BE I I I I BA I 1 I I cc I I I IAP I I I

I I I I BP I I I I SD I I I IAB I I I I BS I I I IAB/AP I I I ILD I I I I SG I I I lIvL I I I

I I IBG/BM I I

I S J

N I 47 I 30 I 23 I loo i failures I 377 I 2231 5781 1178 I demands I 1377961 1556171 2284111 5218241 rate I 0.002735931 0.001433011 0.002530531 0.002257471

. I

.I

.I

.I . I .I . I .I .I .I . I . I .I .I .I .I .I - 1 * I .I .I .I .I .I .I . I .I .I .I .I . I . I .I .I .I .I .I .I . I . I .I .I .I .I .I .I . I .I . I . I .I .I .I .I .I .I .I . I .I .I . I .I .I .I 21 31

1352 I 0.002218931

81 5i

10545 I I rate I .I 0.000474161

N I 17 I failures I 17 I demands I 448251 rate I 0.000379251 N 1 81 failures I 17 I demands I 23618 I rate I 0.000719791 N I 71 failures I 45 I demands I 5108 I rate I 0.008809711 N I 71 failures I 15 I demands I 6541 I rate I 0.002293231 N I 61 failures I 51 demands I 2432 I rate I 0.002055921 N I 51 failures I 261 demands I 20121 rate I 0.012922471 N I 41 failures I 01 demands I 1691 rate I 0.000000001 N I 41 failures I 23 I demands I 6991 rate I 0.032904151 N I 41 failures I 61 demands I 393 I rate I 0.015267181 N I 41 failures I 61 demands I 1344 I rate I 0.004464291 N I 41 failures I 18 I demands I 1573 I rate I 0.011443101 N I 41 failures I 31 demands I 622 I rate I 0.004823151 N I 21 failures I 31 demands I 350 I rate I 0.008571431 N I 21 failures I 21 demands I 545 I rate I 0.003669721 N I 11

demands I 30 I rate I 0.166666671 N I 11 failures I 01 demands I 631 I rate I 0.000000001 N I 81 failures I 32 I demands I 295561 rate I 0.001082691 N I .I failures I .I demands I .I

failures I 51

.I 81

. I 17 I

.I 23618 I

.I 0.000719791 .I 71 . I 45 I .I 5108 I . I 0.008809711 . I 71 .I 15 I . I 6541 I . I 0.002293231 . I 61 . I 51 .I 24321 . I 0.002055921 . I 51 .I 26 I . I 2012 I . I 0.012922471 .I 41 . I 01 .I 1691 .I 0.000000001 .I 41 - I 23 I .I 6991 .I 0.032904151 . I 41 .I 61 .I 393 I . I 0.015267181 . I 41 . I 61 .I 1344 I . I 0.004464291 . I 41 .I 18 I .I 1573 I . I 0.011443101 .I 41 .I 31 . I 622 I .I 0.004823151 .I 21 .I 31 .I 350 I . I 0.008571431 . I 21 .I 21 . I 545 I .I 0.003669721 . I 11 .I 51 . I 30 I .I 0.166666671 .I 11 .I 01 .I 631 I .I 0.000000001 .I 10 I .I 35 I .I 309081 .I 0.001132391 .I 81 . I 51 .I 10545 I .I 0.000474161

.

Page 29: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table A.3 (continued)

Demand-related fa i lure data: Cross tabulation of t o t a l number of records, t o t a l fa i lures , t o t a l demands and observed cell fa i lure ra te by System and Reactor Type

I Reactor Type I I I I I

I I PWR I System I

I CH N I I f a i lu res I I demands I I r a t e I I BN N I I f a i lu res I I demands I I I xc I I I I NT I I I I BI I I I I BY I I I IJM I I demands I I r a t e I I JI N I 1 f a i l u r e s I I demands I I r a t e I

N I f a i lu res I demands I I

I r a t e I I= N I I f a i lu res I I demands I I rate I IAA N I I f a i lu res I I &emands I I r a t e I I ALL N I 135 I f a i lu res I 60C I demands I 258244 I r a t e I 0.0023233f

/ BL

r a t e I N I f a i lu res I demands I r a t e I N I f a i lu res I demands I r a t e 1 N I f a i lu res I demands I r a t e I N I f a i lu res I demands I r a t e I N I f a i lu res I

BWR I missing I ALL I I I I

61 01

240591 0.000000001

61 31

2544 I 0.000000001

21 12 I

738 I 0.01626016l

21 01

155201 0.000000001

11 11

215 I 0.00465116 I

11 191 227 I

0.083700441 11 41 28 I

0.142857141 11 21

125 I 0.016000001

41 278161

0.000143801 64 I

278 I 2:

516 24oZo5i 228411

0.001157341 0.0025305:

61 01

240591 0.000000001

61 31

1367 I 0.00219459 I

21 01

2544 I 0.000000001

ii 215 I

0.00465116 I 11

191 227 I

0.083700441 11 41

125 I 0.016000001

11

41

7268601 0.002003141

Page 30: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table A.4

Time-related failure data: total failures, total demands and observed cell failure rate by System and Reactor Type

Cross tabulation of total number of records,

~~~ ~~~~~~~~~~

I Reactor Type I I I

I I I I PWR I BWR I missing I ALL I ISystem I I I I I lmissing I I I I SB I I I I CI I I I I BA I I I I CB I I I I BP I I I I SD I I I I BE I I I ILD I I I I cc I I I II(E I I I IAB I I I I BS I I I ISJ I I I I BI I I I IBG/BM I I I IBN I I I I CH I I I IALL I I I

N I 47 I failures I 1791 hours I 191958407191 rate I 0.000000011 N I 10 I failures I 01 hours I 178807991 rate I 0.000000001 N I 91 failures I 31 hours I 64965561 rate I 0.000000461 N I 81 failures I 81 hours I 1869661 rate I 0.000042791 N I 71 failures I 01 hours I 218850881 rate I 0.000000001 N I 61 failures I 71 hours I 165800841 rate I 0.000000421 N I 61 failures I 01 hours I 71970341 rate I 0.000000001 N I 61 failures I 31 hours I 10220 I rate I 0.000293541 N I 51 failures I 01 hours I 185575681 rate I 0.000000001 N I 51 failures I 11 hours I 231030401 rate I 0.000000041 N I 41 failures I 21 hours I 32570061 rate I 0.000000611 N I 41 failures I 01 hours I 65861461 rate I 0.000000001 N I 21 failures I 11 hours I 2027521 rate I 0.000004931 N I 71 failures I 11 hours I 64235211 rate I 0.000000161 N I 31 failures I 01 hours I 33454081 rate I 0.000000001 N I .I failures I .I hours I .I rate I .I N I .I failures I - 1 hours I .I rate I N I failures I hours I rate I N I 1291 failures I 205 I hours I 193275529071 rate I 0.000000011

.I

.I * I .I .I

25 I 105 I

76196328111 0.000000011

.I

.I

.I

. I

. I

. I

.I

.I

.I

.I

. I

. I

. I

. I

. I

.I

.I

.I - 1 .I .I . I . I .I . I . I . I .I .I .I .I .I .I .I .I .I .I .I . I . I .I .I .I .I .I .I .I .I 11

18 I 1484791

0.000121231 11 01

7690 I 0.00000000~

61 11

19561 0.000511251

41 11

12401 0.000806451

41 o i

18714 I 0.00000000~

4 1 I 1251

91 112 I

5182628721 0.000000221

.I

. I

. I

. I

. I

. I

.I

.I

.I

. I

. I

. I

. I

. I

. I . I .I . I .I . I . I . I . I .I .I .I .I .I .I - 1 .I * I - 1 .I . I . I .I . I .I .I . I .I .I * I - 1 .I * I .I . I .I .I . I . I .I .I .I * I .I .I .I . I .I .I .I

8 1 I 3961

27333736402 I 0.000000011

10 I 01

178807991 0.000000001

91 31

6496556 I 0.00000046 I

81 81

1869661 0.000042791

71 01

21885088 I 0 . 0 0 0 0 0 0 0 0 ~

61 71

16580084 I 0.000000421

61 01

7197034 I 0.000000001

61 31

10220 I 0.000293541

51 01

18557568 I 0.000000001

51 11

23103040 I 0.000000041

41 21

32570061 0.000000611

41 01

65861461 0.000000001

21 11

202752 I 0.000004931

81 191

6572000 I 0.000002891

41 01

3353098 I 0.00000000~

61 11

19561 0.000511251

41 11

1240 I 0.000806451

* I 41 .I 01 .I 18714 I .I 0.00000000~ 91 1791

112 I 442 i 0.000000021 0.000000221 0 .00000002~ 76198108901 5182628721 274656266691

Page 31: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

APPENDIX B: Analyses for BWR Plants, Demand-related Failure Data

20

Page 32: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table B.l: Cross tabulation by system and originating facility for the BWR demand- related data of Table A.l

I OF1 I I I

I I YX I System I

IBG/BM I I I I CH I I I I BN I I I IBI I I I I BY I I I IJM I I I I JI I I I I BL I I I I E I I I I xc I I I ISJ I I I I NT I I I IAA I I I lALL I I I

N I 7 failures I 2 demands I 10315 rate I 0.00019389 N I 6 failures I 0 demands I 24059 rate I 0.00000000 N I 6 failures I 3 demands I 1367 rate I 0.00219459 N I 2 failures I 0 demands I 15520 rate I 0.00000000 N I failures I demands I rate I N I failures I demands I rate I N I failures I demands I rate I N I failures I demands I rate I N I failures I demands I rate I N I failures I demands I rate I N I failures I demands I rate I N I failures I demands I rate I N I failures I demands I rate I N failures I I ’: demands I 51261 rate I 0.00009754

B Wl I MNSl I

11 3;

230 I 0.013043481

- 1 .I . I . I .I . I . I . I . I .I .I

iI 11

215 I 0.00465116 I

11 191 227 I

0.083700441 11 41 28 I

0.142857141 11 zi

125 I 0.01600000 I

11 21 52 I

0.038461541 . I . I ( . I 2541

. I

.I

.I 135;

.I 0.0022189~

.I

.I 1;

.I 731

.I 0.01626011 - 1 .I .I

.I 0.0000000~

61 ( 31 I 1: 877 I 4631

0.035347781 0.0032369’

BWR I ALL I I I

. I 81

. I 51

. I 105451

. I 0.000474161

. I 61

. I 01

.I 240591

.I 0.000000001 - 1 61 . I 31 . I 1367 I . I 0.002194591 . I 21 . I 01 .I 155201 .I 0.000000001 .I 11 .I 11 .I 215 I .I 0.004651161 .I 11 .I 191 . I 227 I . I 0.083700441 . I 11 . I 41 .I 28 I .I 0.142857141 .I 11 .I 21 . I 125 I . I 0.016000001 . I 11 .I 21 . I 52 I . I 0.038461541 . I 21 . I 01 . I 2544 I .I 0.000000001 . I 21 .I 31 .i 1352 I .I 0.002218931 .I 21 .I 12 I .I 738 I . I 0.016260161 11 11 41 41

278161 278161 0.000143801 0.000143801

ii 34 i 41 55 I

278161 845881 0.000143801 0.000650211

Table B.2: Cross tabulation by application environment and originating facility for the BWR demand-related data of Table A.l

I OF 1 I I I I

I I I I Yx I BRPl I MNSl I BWR I ALL I IApplication I I I I I I IEnvironment I I I I I I

I INTEWC N I 121 11 21 11 161 I failures I 51 21 31 41 14 I I demands I 196551 125 I 13521 278161 489481 I rate I 0.000254391 0.016000001 0.002218931 0.000143801 0.000286021 I INTEWB N I 21 11 .I .I 31 I failures I 01 31 . I .I 31 I demands I 892 I 230 I .I . I 1122 I I rate I 0.000000001 0.013043481 .I .I 0.002673801 I INTEWD N I 31 . I .I . I 31 1 failures I 01 .I - 1 . I 01 I demands I 164111 .I . I .I 164111 I rate I 0.000000001 .I . I .I 0.000000001 I INTEAR N I 21 .I . I .I 21 I failures 1 01 - 1 . I .I 01 I demands I 45 I - 1 . I .I 45 I I rate I 0.000000001 .I .I .I 0.000000001 I INTEST N I . I 21 . I .I 21 I failures I . I 61 . I .I 61 I demands I . I 80 I . I .I 80 I I rate I . I 0.075000001 . I .I 0.075000001 I ALL N I 191 41 21 11 261 I failures I 51 11 I 31 41 23 I I demands I 370031 435 I 13521 278161 666061 I rate I 0.000135121 0.025287361 0.002218931 0.000143801 0.000345311

Page 33: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table 8.3: Cross tabulation by operator type and valve type for the BWR demand-related data of Table A.l

I Valve Type I I

I I I I I I I I

15 I 11 I . I . I - 1 . I .I 11 I 11 . I . I .I . I .I 11 I f a i lu res I

I demands I 485141 . I . I .I . I . I 485141 .I . I 0.000020611

il il . I . I 81 I r a t e I 0.000020611 .I I1 I 61 . I

91 .I 191 11 . I . I 291 I f a i lu res I I demands I 32861 . I 70601 1440 I . I . I 117861

. I . I 0.002460551 I r a te I 0.002738891 . I 0.002691221 0.000694441 I .I 61 . I . I . I . I 61 17

.I 01 . I . I . I . I 01 I f a i lu res I I demands I .I 2191 . I . I . I . I 2191

. I .I . I 0 . 00000000~ I r a t e I . I 0 .000000001 13 I .I . I i f . I 11 11 31

. I . I 91 .I 71 11 17 I I f a i lu res I

.I . I 2160 I . I 6700 I 504 I 9364 I I demands I I r a t e I .I . I 0.004166671 . I 8 001044781 0.001984131 0.001815461

I 17 I 61 21 I 1 11 11 28 I I ALL 10 I 01 28 I 71 11 471 I f a i lu res I

I demands I 518001 2191 9220 I 1440 l ' I 67001 5041 698831 I r a te I 0.000193051 0.000000001 0.003036881 0.000694441 0.001044781 0.001984131 0.000672551

I I I

I I 3 I 7 I 2 I 5 I 4 I 8 I ALL I loperator Type

N

N

N

N

N

I I 17 I I I 12 I

I I I ALL I I I

il 20 I

85001 0.002352941

- I

N I 11 31 fa i lures I 33 I 17 I demands I 469831 9364 I r a t e I 0.000702381 0.001815461 N I 12 I - I fa i lures I 31 .I demands I 538061 - I r a t e I 0.000055761 N I 71 fa i lures I 27 I demands I 531751 r a t e I 0.000507761 N I 61 fa i lures I 01 demands I 2191 r a t e I 0.000000001 N I 41 fa i lures I 21 demands I 1457 I r a t e I 0.001372681 N I 21 fa i lures I 11 demands I 1721 I r a t e I 0.000581061 N I 32 I fa i lures I 66 I demands I 1573611 ra te I 0.000419421

.I

.I

.I

.I - I - I - I .I .I .I . I si

37 I 178641

0.002071201

41 22 I

1910 I 0.011518321

. I

. I

. I

.I

.I

.I

. I

. I

. I

.I

.I

.I

.I

. I

. I

. I

.I

.I

.I

il 22 I

1910 I 0.011518321

41 .I 12 I 60 I .I 132 I

11732 I .I 699891 0.005114221 . I 0.001886011

. I . I 12 I

. I . I 31

. I . I 538061

.I . I 0.000055761

. I 21 11 I

.I 18 I 65 I

. I 301821 918571

. I 0.000596381 0.000707621

. I . I 61

. I . I 01

.I . I 2191

. I . I 0.000000001

.I .I 41

. I .I 21

. I .I 1457 I

. I . I 0.001372681

.I . I 21

.I . I 11

.I . I 1721 I .I 0.000581061 ;I 21 47 I

60 I 18 I 203 I 117321 301821 2190491

0.005114221 0.000596381 0.000926731 __

Table B.5: Cross tabulat ion by valve type and or iginat ing f a c i l t i y for the BWR demand-related data of Table A.l

- __-_ OF1 I I

I I I I I I i--Yx I IP4 I BWR I MNSl I ALL I

I I I I I I IValve Type I I ----+-------+-----------+ t t __

I 18 I . I 41 41 261 13 10 I .I 31 27 I I f a i lu res I

I demands I 525241 .I 136781 14' 38961 700981 I r a t e I 0.000190391 . I 0.001023541 0.000770021 0.000385181

I 61 .I .I .I 61 17 I f a i lu res I I demands I 2191 .I . I . I 2191

I f a i lu res I I demands I . I 9220 I . I . I 9220 I I r a t e 1 . I 0.003036881 .I . I 0.00303688 I 15 I f a i lu res I I demands I * I 1440 I . I . I 1440 I I r a t e I . I 0.000694441 .I . I 0.000694441 14 I f a i lu res I

.I 6700 I . I . I 6700 I I demands I I r a t e I . I 0.001044781 . I . I 0.001044781 N 18 I f a i lu res 1

dsmads I .I 504 I . I . I 504 I I I r a t e I . I 0.001984131 . I . I 0.001984131

N 1 24 I 51 41 41 37 I IW 10 I 37 I 14 I 31 64 I I f a i lu res I

38961 881811 I demands I 527431 178641 136781 I 0.000189601 0.002071201 0.001023541 0.000770021 0.000725781 I

-

N

N 01 .I .I . I 01

I r a t e I 0.00000000~ . I . I 0.000000001

.I 28 I . I .I 28 I

I . I 11 - I . I 11 .I 11 .I . I 11

I .I 11 .I . I 11 .I 71 - 1 . I 71

I .I 11 . I . I 11 .I 11 . I . I 11

N 12 I .I il . I . I 21

N

N

r a t e -- -___

Page 34: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table B.6: Cross tabulation by ic l and or iginat ing fac i l i ty for the BWR demand-related data of Table A . l

I O N I I f a i lu res I I demands I I r a t e I I1 N I I f a i lu res I I demands I I r a t e I I ALL N I I f a i lu res I I demands I I r a t e I

161 31

470391 0.000063781

191 63 I

1119381 0.00056281 I

35 I 66 I

158977 I 0.000415151

10 I 80 I

38761 0.020639831

. I

.I

.I

.I 10 I 80 I

38761 0.02063983 I

I I OF1 I I I I I I Yx I BRPl I MNSl I BWR I IP4 I ALL I

I I

I Includes Circui t? I

34 I 1461

665431 0.002194071

.I 6 i 5 i 30 I

.I 32 I 37 I 132 I

.I 438601 178641 1736621 . I 0.000729591 0.002071201 0.000760101 81 61 51 64 I

63 I 37 I ?l I 278 I 2402051

0.001157341

.---_______ I I I I I

1 5 0.00403

15628 i 43860 i 17864 i 0.004031231 0.000729591 0.002071201

Table B.7: Cross tabulaton by sgl and or iginat ing fac i l i ty for the BWR demand-related data of Table A . l

I OF1 I I I I I

I I I I I I I

I

I I Yx I B W l I MNSl I BWR I IP4 I ALL I [Safety Graded?

I O N I 35 I 71 61 61 51 591 I f a i lu res I 66 I 561 6 3 I 32 I 37 I 254 I I demands I 1589771 3367 I 13084 I 43860 I 17864 I 237152 I I r a t e I 0.000415151 0.01663202 I 0.00481504 I 0.000729591 0.00207120 I 0 .00107104 I

N I1 I . I 31 21 . I . I 51 I f a i lu res I . I 24 I 01 .I . I 24 I I demands I . I 5091 2544 I .I . I 3053 I I r a t e I . I 0.047151281 0.000000001 . I 0.007861121 I ALL I 3 5 I 1 0 I 81 61 51 64 I I f a i lu res I 66 I 80 I 6 3 I 32 I 37 I 2781 I d e m a n d s I 1589771 38761 156281 438601 178641 2402051 I r a t e I 0.00041515 I 0.020639831 0.004031231 0.000729591 0.00207120 I 0 .00115734 I

N

Table 8.8: Cross tabulation by fa i lure mode and normal operating s t a t e for the BWR demand-related data of Table A . l

I I I I

I I I I X X I N C I N 0 I A L L I

I I I I I I Fa i lure Mode I

I 34 I 81 .I 42 I I FTO I f a i lu res I 1031 1 8 I .I 1 2 1 I I demands I 1766221 304011 . I 2070231 I r a t e I 0.000583171 0.000592091 . I 0.000584481

I 41 81 - 1 121 I FTP 11 67 I .I 68 I I f a i lu res I

I demands I 87871 82031 . I 169901 I r a t e I 0.000113801 0.008167741 . I 0.004002351

I 41 .I 61 1 0 I I FTC I f a i lu res 1 1 6 I .I 7 3 I 891 I demands I 8787 I .I 74051 161921 I r a t e I 0.001820871 . I 0.009858201 0.005496541 I ALL I 42 I 161 61 64 I I f a i lu res I 1201 85 I 7 3 I 278 I I demands I 1941961 386041 74051 2402051 I r a t e I 0.000617931 0.002201841 0.009858201 0.001157341

I Normal State

N

N

N

N

__--

Table B.9: Cross tabulation by fa i lure mode and originating f a c i l i t y for the BWR demand-related data of Table A . l

I OF1 I I

I I I I

I I I I I I Y x I BRPl I MNSl I BWR ! IP4 ALL I IFailure Mode I____ I FTO I I

I ~ _ _ _ _ _

I

I I I I FTC I I I I ALL I I I

I FTP

t- --____ N I f a i lu res I demands I r a t e I N I f a i lu res I demands I r a t e I N I f a i lu res I demands I r a t e I N I f a i lu res I demands I r a t e I

t- 3 5 I 66 I

1589771 0.000415151

.I

. I

. I

. I

. I

.I

. I 15391 . I 0 .03053931 I 35 I 661

1589771 0.000415151 --__-I

t .I .I

I

61 33 I 34 i

2331 I 7814 I 0.014120671 0.004351161

41 41 471

1 0 I 80 I

38761 0.020639831

291 7814 I

0.003711291 81

6 3 I 15628 i

0.004031231

--___ 21

1 8 I 30182 I

0.00059638 I 21 11

6839 I 0.000146221

21 13 I

6839 I 0.001900861

61 32 I

43860 I 0.00072959 1

51 421 37 I 1 2 1 I

178641 2070231 0.002071201 0.000584481

51 421 37 I 1 2 1 I

178641 2070231 0.002071201 0.000584481

. I 1 2 I

. I 68 I

.I 169901

. I 0 .004002351

. I 1 0 I - 1 891 .I 161921 . I 0 .005496541 51 64 I

37 I 2781 17864 I 240205 I

0.002071201 0.001157341

I I .I i 6 1 9 2 i . I 0 .005496541 51 64 I

37 I 2781 17864 I 240205 I

i734 I

Page 35: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table 8.10: Cross tabulation by fdorig and expsdat for the BWR demand- related data of Table A.l

I Exposure Data Source I I I

I I I I PLNT I OTHR I TCRT I ALL I !Failure Data Source I I I I I IPLNT N I 53 I 51 . I 58 I

Ti

- - . I failures I 2091 37 i . I 2461 I demands I 1784811 178641 .I 1963451 I rate I 0.001170991 0.002071201 . I 0.001252901 I OTHR N I - I 21 41 61 I I I I ALL I I I

failures I demands I rate I N I failures I demands I rate I 0

- I - I .I

53 I 2091

178481 I .001170991

4;

71

31444 I 0.000127211

41 I 49308 I

0.000831511

28 i 124161

0.002255151 41 28 I

124161 0.002255151

32 I 43860 I

0.00072959 I 64 I

278 I 240205 I

0.001157341

1: Cross tabulation by fdorig and originating facility for the BWR demand-related data of Table A.l

~~~~~~

I OF1 I I I I_________________________________I______------------I

I I I I Yx I BRPl I MN.51 I BWR I IP4 I ALL I

I I I I I I IFailure Data Source I

I 35 I 10 I 81 .I 51 58 I I PLNT I failures I 66 I 80 I 63 I . I 37 I 2461 I demands I 1589771 38761 156281 . I 17864 I 196345 I I rate I 0.000415151 0.020639831 0.004031231 . I 0.002071201 0.001252901

N I OTHR I . I - I .I 61 . I 61 I failures I . I - I .I 32 I .I 32 I I demands I . I .I .I 438601 .I 43860 I

N

. I .I .I 0.000729591 . I 0.000729591 I rate I I ALL I 35 I 10 I 81 61 51 64 I I failures I 661 80 I 63 I 32 I 37 I 278 I I demands I 1589771 38761 156281 438601 178641 2402051 I rate I 0.000415151 0.020639831 0.004031231 0.000729591 0.002071201 0.001157341

N

Table B.12: Cross-tabulation of expsdat and originating facility for the BWR demand-related data of Table A.l

~__---_~----_----_____--___I____________--______

I OF1 I I I I

I I I I Yx I BRPl I MNSl I BWR I IP4 I ALL I

I I I I I I IExposure Data Source I I

I 35 I 10 I 81 .I .I 53 1 I PLNT I failures I 66 I 80 I 63 I .I .I 2091 I demands I 1589771 38761 156281 . I .I 1784811

.I 0.001170991 I rate I 0.000415151 0.020639831 0.004031231 I OTHR I . I .I .I il 51 71

.I . I .I 41 37 I 41 I I failures I I demands I .I .I .I 314441 178641 493081 I rate I .I . I .I 0.000127211 0.002071201 0.000831511

I .I .I .I 41 .I 41 I TCRT .I .I . I 28 I .I 28 I I failures I

I demands I . I .I . I 124161 .I 124161 . I .I . I 0.002255151 .I 0.002255151 I rate I

I ALL I 35 I 10 I 81 61 51 64 I I failures I 66 I 80 I 63 I 32 I 37 I 278 I I demands I 1589771 38761 156281 438601 178641 2402051 I rate I 0.000415151 0.020639831 0.004031231 0.000729591 0.002071201 0.00115734 I

I - ___ --_--______

N

N

N

N

~ ~ - _ _ _ _ _ _ _ _ _ ____-- ____

Table B.13: Cross tabulation by ir and originating facility for the BWR demand-related data of Table A.l

--__I-_-______ ~ - - _ _ ________ ___--- ! I I OF1 I I I

I I Yx I BRPl I IIRADAP quality data? I I I I---------------+----+ 4 IY N I 35 I 81

failures I 48 I demands I 1589771 661 25051

I I I rate I 0.000415151 0.019161681 IN N I . I 21 I failures I . I 32 I I demands I . I 1371 I I rate I . I 0.02334063 I I ALL N I 35 I 10 I I failures I 66 I 80 I I demands I 1589771 38761

rate I 0.000415151 0.020639831 I I_-___

--_-______

MNSl I BWR I IP4 I ALL I I I I I +----I

81 .I 51 561 63 I . I 37 I 214 I

15628 I . I 178641 1949741 0.004031231 . I 0.002071201 0.001097581

.I 61 .I 81

.I 32 I .I 64 I

.I 438601 .I 452311

.I 0.000729591 .I 0.001414961 81 61 51 64 I 63 I 32 I 37 I 278 I

156281 438601 178641 2402051 0.004031231 0.000729591 0.002071201 0.001157341

----+ +

-___I

Page 36: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table B.14

BWR Plant Y, both Unit 1 and Unit 2: Demand-related failure data

OBS

1 2 3 4 5 6 7 8 9

1 0 11 1 2 13 1 4 15 1 6 1 7 1 8 1 9 20 2 1 22 2 3 24 25 26 27 28 29 30 31 3 2 33 34 35

RECNO

980 981 5 6 9 550 552 953 950 603 478 470 474 4 7 1 473 476 469 477 475 488 894 973 974 8 9 1 892 8 9 3 551 554 951 952 602 472 749 555 553 810 684

OF1

Yx Yx YX YX Yx YX YX YX YX Yx YX YX Yx YX YX Yx YX Yx YX YX YX YX YX YX YX YX Yx YX YX Yx YX YX YX YX YX

SYSTl

CH CH

CH CH BG/BM BG/BM

BG/BM BN CH BG/BM BN CH

BI BI

BN BG/BM BN BN BG/BM BG/BM

BN

CAPLl OPTYF'l

INTEWB INTEWB

INTEWC INTEWC

INTEWC

INTEWC INTEWC INTEWC INTEWD INTEWD INTEND

INTEAR INTEAR INTEWC INTEWC INTEWC INTEWC INTEWC

INTEWC

1 1 2 2 4 5 5 5 5 5 5 5 5 5 5 7 7 7 7 7 7 1 1 2 2 4 5 5 1 1 1 3

VLVTYPl

i 3 3

i 3 3 3 3 3 3 3 3 3 7 7 7 7 7 7 3 3

3 i 3

IC1 NUMFAIL

1 0 1 0 0 0 1 0 1 0 1 0 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 1 0 0 0 0 0 0 0 1 1 1 1 1 1 0 0 1 1 1 1

1 1 1 1 1 2 3 4

18 33

Table B.15: Cross tabulation by system for BWR Plant Y demand-related data of Table B.14

I I N lfailuresl demands I rate I I

I System I I I I I I BG/BM I 71 21 1031510.000193891 I CH I 61 01 240591 0.000000001 I BN I 61 31 136710.002194591 I BI I 21 01 1552010.000000001 I ALL I 211 5 I 51261 10.00009754 I

Table B.16: Cross tabulation by application environment for BWR Plant Y demand-related data of Table B.14

I I N lfailuresl demands I rate I I

IApplication I I I I I I I I I I IEnvironment

I INTEWC I 121 51 1965510.000254391 I INTEWD I 31 01 1641110.000000001 I INTEWB I 21 01 89210.00000000~ I INTEAR I 21 01 4510.000000001 I ALL I 191 51 3700310.000135121

Table B.17:

_--___ ___ ___

Cross tabulation by operator type for BWR Plant Y demand-related data of Table 8 . 1 4

I N lfailuresl demands I rate I I +--+-+---.---+----

I I

15 I 121 31 538061 0.00005576 I I1 I 71 271 5317510.000507761 17 I 61 01 21910.000000001

21 145710.001372681 12 I 41 14 I 21 11 172110 .00058106~ 13 I 11 331 4698310.000702381 I ALL I 321 661 15736110.000419421

Table B.18:

---- __ -

loperator Type I I I I I

--I--___----_________ __ __

Cross tabulation by valve type for BWR Plant Y demand-related data of Table B.14

I I N lfailuresl demands I rate I IValve Type I3 I 181 101 5252410.000190391

I ALL I 241 101 5274310.000189601

I I I I I

17 I 61 01 21910.00000000~

__

TOTD

429 4 63 724 92 6 85 6 704 582

1522 816

3493 704

10273 4230

504 11112

8 91 7855 7665 131

25 20 10 1 8 1 5

588 708

7 3 98

1 9 9 971

5292 106 102

49889 46983

FRATE

0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.000000 0.001701 0.001412 0.013699 0.010204 0.005025 0.001030 0.000378 0.028302 0.039216 0.000361 0.000702

Table B.19: Cross tabulation by icl for BWR Plant Y demand-related data of Table B.14

I I N lfailuresl demands I rate I I l- +---+------- -+---

IIncludes Circuit? I I I I I I1 I 191 631 11193810.000562811 IO I 161 31 470391 0.00006378 I IW I 351 661 15897710.000415151

- ______

Page 37: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

APPENDIX C: Analyses for PWR Plants, Demand-related Failure Data

21

Page 38: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table C.1: Cross tabulation by system and originating facility for the PWR demand-related data of Table A.l

I OF1 I I I I

I I I I X I B6W I DBSl I NEE3 I FPRA I ZlSl I ALL I

I System I SB I I I I CI I I I ISJ I I I I CB I I I I BE I I I IBA I I I I cc I I I IKE I I I I BP I I I I SD I I I IAB I I I I BS I I I ILD I I I IEZi I I I IAB/AP I I I IAP I I I I SG I I I I ALL I I I

I N 4 61

I I

failures I 01 0 demands I 107711 28185 rate I 0.000000001 0.00000000 N I 31 5 failures I 21 15 demands I 10561 22562 rate I 0.001893941 0.00066483 N I 8 i failures I 32 I demands I 295561 rate I 0.001082691 N I 61 failures I 38 I demands I 3388 I rate I 0.011216061 N I 61 failures I 51 demands I 4894 I rate I 0.001021661 N I 61 failures I 51 demands I 2432 I rate I 0.002055921 N I 51 failures I 261 demands I 20121 rate I 0.012922471 N I 41 failures I 23 I demands I 6991 rate I 0.032904151 N I 41 failures I 61 demands I 393 I rate I 0.015267181 N I 41 failures I 61 demands I 1344 I rate I 0.004464291 N I 41 failures I 18 I demands I 15731 rate I 0.011443101 N I 41 failures I 31 demands I 622 I rate I 0.004823151 N I 21 failures I 21 demands I 545 I rate I 0.003669721 N I 11 failures I 01 demands I 631 I rate I 0.000000001 N I .I failures I .I demands I .I rate I .I N I .I failures I .I demands I .I rate I .I N I .I failures I .I demands I .I rate I .I N I 63 I 9 failures I 1661 15 demands I 599161 50751 rate I 0.002770551 0.00029556

I 71 17 I

58651 0.002898551

.I

.I

.I

.I

.I

.I

.I

. I

.I

.I

.I

.I

.I

. I

.I

.I - 1 . I .I .I . I .I . I . I . I . I . I . I .I . I . I . I .I . I . I . I .I . I .I .I . I . I . I . I . I .I .I .I .I .I .I

31 350 I

0.008571431 - 1 .I _ I

il

I . I . I . I . I . I . I . I . I . I . I . I . I . I . I . I . I . I . I . I .I .I .I . I .I .I .I .I .I .I . I . I .I . I . I . I . I . I . I . I . I .I . I . I . I . I . I . I . I . I . I . I .I . I .I .I .I .I .I .I . I 21 01

i 0 - . 20 i 149

.I 0.000000001 0.00000000

.I 11

.I 51

.I 30 I

. I 0.166666671 91 31 i 20 I 51 0

6215 I 50 I 149 0.003218021 0.100000001 0.00000000

I i . I 17 I . I 17 I . I 448251 . I 0.000379251 . I 81 . I 17 I . I 236181 . I 0.000719791 . I 81 . I 32 I .I 295561 . I 0.001082691 11 71 71 45 I

1720 I 51081 0.004069771 0.008809711

11 71 10 I 15 I

16471 6541 I 0.006071651 0.002293231

.I 61

.I 51

.I 2432 I

.I 0.002055921 - 1 51 .I 261 .I 2012 I .I 0.012922471 .I 41 . I 23 I .I 6991 . I 0.032904151 .I 41 .I 61 . I 393 I .I 0.015267181 - 1 41 .I 61 .I 1344 I .I 0.004464291 .I 41 .I 18 I .I 1573 I .I 0.011443101 .I 41 * I 31 .I 622 I .I 0.004823151 * I 21 - 1 21 .I 545 I . I 0.003669721 .I 11 .I 01 . I 631 I . I 0.000000001 .I 21 .I 31 .I 350 I . I 0.008571431 . I 4 1 .I 01 - 1 1691 .I 0.000000001 .I 11 * I 51 .I 30 I .I 0.166666671 2i 88 I 17 I 223 I

3367 I 120448 I 0.005049011 0.001851421

,

Page 39: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

0

Graph C.1: Subset of PWR Plant X Demand-related Valve Failure Data' Model with optypl , capll and systl

e

e

e

e

e

e

e e

e.

- e

e 0 e e

e e

e

e

e

e

e

e

e

e

I I I I I I I

-8 -7 -6 -5 -4 -3 -2

Predicted

Page 40: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table C.2: Cross tabulation by operator type and valve type for the PWR Plant X demand-related failure data

~~~ ~~~~~~ ~~~

I Valve Type I I I

I I I I 3 I 7 I A L L I

I I Opera- I I I I ltor I I I I

N I 18 I .I 18 I I failures I 11 . I 11 I I 13 I

I ;YP I I I I

I I 17 I I I I ALL I I I

demands I 8801 i . I 8801 i rate I 0.000113621 .I 0.000113621 N I 21 .I 21 failures 1 01 * I 01 demands I 537 I .I 537 I rate I 0.000000001 . I 0.000000001 N I .I 1 2 I 12 I failures I .I 61 61 demands I .I 15661 15661 rate I .I 0.003831421 0.003831421 N I 20 I 12 I 32 I

demands I 9338 'I I 15661 109041 rate I 0.000107091 0.003831421 0.000641971

failures I 61 7 1

Table C.3: Cross tabulation by system for the PWR Plant X demand-related failure data

_-___---__________________I_____________--

I I N lfailuresl demands I rate I

I System I I I I 1 ISJ I 81 321 2955610.001082691 I SB I 61 01 1077110.000000001

i 6 i 5 i 243210.00205592i I 61 51 489410.001021661 I 61 381 33881 0.01121606l I 51 261 201210.012922471 I 41 181 157310.011443101 I 41 61 39310.015267181 I 41 31 62210.004823151 I 41 231 69910.032904151 I 41 61 134410.004464291 I 31 21 105610.001893941 I 21 21 54510.003669721 I 11 01 63110.000000001 I 631 1661 5991610.002770551

Table C.4: Cross tabulation by application environment for the PWR Plant X demand-related failure data

I I N lfailuresl demands I rate I I 1 --------+-+-+--~+

IApplication I I I I I I Environment I I I I I I INTWC I 311 841 3720710.002257641

I INTEST I ALL

I 101 471 475810.009878ioi I 31 01 443310.000000001 I 21 11 39310.002544531 I 21 01 60310.000000001 I 481 1321 4739410.002785161

Table C.5: Cross tabulation by operator type for the PWR Plant X demand-related failure data

___ I N lfailuresl demands I rate I +--+--I- +-- +------I

I I __--_ loprator Type I I I I I 15 1 2 9 1 351 4333010.000807751 17 I1 13 12 I ALL

61 156610.003831421 I 121 I 91 581 588510.009855561 I 91 671 668910.010016441 I 41 Ql 2O161O.OOOQOOOOl I 631 1661 5948610.002790571

Page 41: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Graph C.2: Subset of PWR Plant X Demand-related Valve Failure Data Model with optypl , capll and systl

-8 -7 -6 -5 -4 -3 -2

Predicted

Page 42: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Q a L

0 . .. I8

M

I I

Y

I I

CI,

I I

I I

No I - I

I

I

n 9

w I

Y

I

I

U

w - I - I

n - m

* I I

w

(3

I

9'0

n U .

+a - .

n

I

S O I

9'0 I

E'O I

Z.0 I

L.0 I

0'0

1 Z S 9 Z S S Z S P Z S E Z S Z Z S 1 Z S L Z L 9 Z L S Z L P Z L E Z L Z Z L C Z L L Z 1 9 z 1 S Z 1 P Z 1 E Z 1 Z Z 1

L C L 9 C L S l L P C L E L L Z C L C l L L l l 9 1 1 Sll PCC E l l Zll 1 1 1 L C E 9 l E S C E P C E E C E Z C E 1 CE

Page 43: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

' OBS PXCNO

1 752 2 903 3 912 4 813 5 461 6 460 7 760 8 751 9 910 10 759 11 690 12 909 13 801 14 761 15 687 16 691 17 815 18 911 19 757 20 812 21 692 22 905 23 686 24 814 25 811 26 688

OF1

X X X X X X X X X X X X X X X X X X X X X X X X X X

Table C.6: Cross tabulation by application environment and icl for the PWR Plant X demand-related failure data

I I I

IAppli- I cation IEnvir- I onment I INTEWB I I I I INTEWC I I I

I I I I INTEST I I I

I I demands I . I 393 i 393 i I rate I . I 0.002544531 0.002544531 I ALL N I 30 I 18 I 48 I I failures I 131 I 11 132 I I demands I 382561 91381 473941 I rate I 0.003424301 0.000109431 0.002785161

I INTECS

I INTEWS

I Includes Circuit? I I I

I 1 I O I A L L I I

I I I I I I I I I I I I I I I I

N I 10 I . I 10 I

I I I I I I I I I 10 I

failures I 47 I . I 47 i demands I 47581 . I 4758 I rate I 0.009878101 . I 0.009878101 N I 18 I 13 I 31 I failures I 84 I 01 84 I demands I 318381 53691 372071 rate I 0.002638361 0.000000001 0.002257641 N I 11 21 31 failures I 01 01 01 demands I 1488 i 2945 i 4433 i rate I 0.000000001 0.000000001 0.000000001 N I 11 11 21 failures I 01 01 01 demands I 172 I 431 i 603 i rate I 0.000000001 0.000000001 0.00000000~ N I .I 21 21 failures I . I 11 11

Table C.7: Cross tabulation by sgl for the PWR Plant x demand-related failure data

~~

I I N lfailuresl demands I rate I I------------------+--+------+-------+--+---------I I Safety Graded? I I I I I I O I 571 1421 5818910.002440321

I 71 241 186110.012896291 I1 I ALL I 641 1661 6005010.002764361

Subset of PWR Table C.8

Plant X Demand-related Failure Data

SYSTl CAPLl OPTYPl VLVTYPl SG1 NUMFAIL TOTD

BP BP CB BA BA SJ BA SJ SD AB SD cc SJ CB BA SJ SD SJ cc CB CB AB BP cc BP AB

INTEWB INTEWB INTEWB INTMC INTMC INTEhT INTEWC INTEWC INTEWC INTEWB INTEWC INTMC INTMC INTEWB

INTEhT INTEXC INTEWB INTEWB INTEWB INTEWB INTEUC INTEWB INTMC

5 7 7 1 3 3 5 5 7 5 3 7 1 5 3 3 1 7 5 1 3 7 3 1 1 3

i 7

3 3

7

7

i

7

1 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 1 0 1 1

2 1 1 6 5 5 22 5 4 12 15 18 1 3 13 3 15

297 12 93 89

191 34 6 201

21051 24

1329 367 307 1715 1184 879

3679 813 621

1064 862 855 42 60

222 24 97

FRATE

0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00150 0.00272 0.00326 0.00350 0.00422 0.00569 0.00598 0.00615 0.00644 0.01128 0.01740 0.02105 0.02381 0.05000 0.05856 0.12500 0.15464

Page 44: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

T a b l e C.9: A n a l y s i s R e s u l t s

S u b s e t o f Ph'R P l a n t X Demand-re la ted F a i l u r e Data: The GENMOD P r o c e d u r e

Modal I n f o r m a t i o n

I n t e r c e p t Only Model

D e s c r i p t i o n V a l u e Label

Data S e t D i s t r i b u t i o n L i n k F u n c t i o n Dependent V a r i a b l e Dependent V a r i a b l e O b s e r v a t i o n s Used Number Of E v e n t s Number O f T r i a l s

WORK. TEMP BINOMIAL LOGIT NUME'AIL F a i l u r e s TOTD D e m a n d s 26 131 36424

C l a s s L e v e l I n f o r m a t i o n

Class L e v e l s V a l u e s

OPTYPl 4 1 3 5 7 SYSTl 7 AB BA BP CB CC SD SJ CAPLl 2 INTEWB INTEWC

P a r a m e t e r I n f o r m a t i o n

P a r a m e t e r E f f e c t

P W l INTERCEPT

Criteria F o r b s e s s i n g Goodness Of F i t

C r i t e r i o n DF V a l u e Value/DF

Deviance 25 402.9678 16.1187 S c a l e d Deviance 25 402.9678 16.1187 P e a r s o n C h i - s q u a r e 25 1172.4070 46 .8963 S c a l e d P e a r s o n X2 25 1172.4070 46 .8963 Log L i k e l i h o o d . -868.0041

A n a l y s i s Of P a r a m e t e r E s t i m a t e s

P a r a m e t e r DF E s t i m a t e S t d E r r C h i s q u a r e

INTERCEPT 1 -5.6242 0 .0875 4128.8147 SWLLE 0 1 .0000 0.0000

NOTE: The scale p a r a m e t e r was h e l d f i x e d .

Normal C o n f i d e n c e Intervals For P a r a m e t e r s

Two-sided C o n f i d e n c e C o e f f i c i e n t : 0 .9500 P a r a m e t e r C o n f i d e n c e L i m i t s

PRMl Lower -5.7957 PRMl upper -5.4526

LR S t a t i s t i c s For Type 1 A n a l y s i s

S o u r c e Deviance DF Chisquare P r > C h i

INTERCEPT 402.9678 0

Pr>Chi

0 .0001

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T a b l e C.10: A n a l y s i s R e s u l t s

S u b s e t o f PWR P l a n t X Demand-related F a i l u r e Data: Model w i t h o p t y p l , c a p 1 1 and s y s t l The GENMOD P r o c e d u r e

Model I n f o r m a t i o n

D e s c r i p t i o n Va lue Label

Data S e t WORK. TEMP D i s t r i b u t i o n BINOMIAL Link F u n c t i o n MGIT Dependent V a r i a b l e NUMFAIL F a i l u r e s Dependent V a r i a b l e TOTD D e m a n d s O b s e r v a t i o n s Used 26 Number Of E v e n t s 131 Number Of T r i a l s 36424

Class Level I n f o m a t i o n

C l a s s Levels V a l u e s

OPTYPl 4 1 3 5 7 SYSTl 7 AB BA BP CB CC SD SJ CAPLl 2 INTEWB INTEWC

P a r a m e t e r I n f o r m a t i o n

P a r a m e t e r E f f e c t OPTYPl SYSTl CAPLl

PRMl INTERCEPT PRMZ OPTYPl 1 PRM3 OPTYPl 3 PRM4 OPTYPl 5 PRM5 OPTYPl 7 PRM6 W L l INTEWB PRM7 W L l INTEWC PRM8 SYSTl AB PRM9 SYSTl BA PRMlO SYSTl BP PRMll SYSTl CB PRM12 SYSTl cc PRM13 SYSTl S D PRMl4 SYSTl SJ

C r i t e r i a F o r Assessing Goodness Of F i t

C r i t e r i o n DF V a l u e Value/DF

Deviance 15 51.1245 3 .4083 S c a l e d Dev iance 15 51.1245 3.4083 P e a r s o n Ch i - squa re 15 58.3583 3 .8906 S c a l e d P e a r s o n X2 15 58.3583 3.8906 Log L i k e l i h o o d . -692.0824

A n a l y s i s Of P a r a m e t e r E s t i m a t e s

DF E s t i m a t e S t d E r r C h i s q u a r e P r > C h i

1 -7.1285 0.4856 215.4884 0.0001 1 1 .5139 0.4593 10 .8641 0.0010 1 1 .7615 0.4887 12 .9911 0.0003 1 -0.9428 0.4896 0 0.0000 0.0000 1 -1.7663 0.7096 0 0.0000 0.0000 1 3.6684 0.3458 112.5150 0.0001

3 .7091 0.0541

6.1948 0.0128

P a r a m e t e r

INTERCEPT OPTYPl 1 OPTYPl 3 OPTYPl 5 OPTYPl 7 CAPLl INTEWB CAPLl INTEWC SYSTl AB SYSTl BA SYSTl BP SYSTl CB SYSTl CC SYSTl SD SYSTl SJ SCALE

NOTE: The scale p a r a m e t e r was h e l d f i x e d .

P a r a m e t e r Number PRMl

PRMl PRM2 PRM3 PRM4 PRM6 PRM8 PRM9 PRMlO PRMll PRMl2 PPJ413

PRMZ PREU

1 -0.0694 0.4889 0 .0201 0.8872 1 4.3589 0.8412 26 .8511 0 .0001 1 3.3989 0.7618 19 .9089 0 .0001 1 2.9745 0.3059 1 0.2503 0.4563 0 0.0000 0.0000 0 1.0000 0.0000

E s t i m a t e d C o r r e l a t i o n m a t r i x

94.5703 0.0001 0.3010 0.5833

PRH4 PPJ46 PRH8 PRM9 PRMlO P W l l PRMl2 PRM13

1.0000 -0.8633 -0.9142 -0.8234 -0.1039 -0.1123 -0.0867 0 .0076 0 .0095 - -0.8633 1 .0000 0.8741 0.7974 0.0929 -0.0231 -0.0194 -0.0744 -0.1065 -0.9142 0.8741 1.0000 0.7982 0.1791 -0.1295 -0.0784 -0.1474 -0.1649 -0.8234 0.7974 0.7982 1.0000 -0.0887 0.0283 0.0206 0 .0765 0 .1071 -0.1039 0.0929 0.1791 -0.0887 1.0000 -0.4285 -0.0671 -0.8422 -0.9459 -0.1123 -0.0231 -0.1295 0.0283 -0.4285 1.0000 0.2326 0.4687 0 .5191 -0.0867 -0.0194 -0.0784 0.0206 -0.0671 0.2326 1.0000 0 .1325 0.1484

-0.5290 -0.1587 0.2088 -0.0581 0.3941 0.0270 0.2305 0.0580 0.1242 -0.0184 0.1859 0.1847 0.1453 0.1352

0.0076 -0.0744 -0.1474 0.0765 -0.8422 0.4687 0.1325 1 .0000 0 .8453 0.0183 0.0967 0.0095 -0.1065 -0.1649 0.1071 -0.9459 0.5191 0.1484 0 .8453 1.0000 0.0293 0.1220

-0.5290 0.2088 0.3941 0.2305 0.1242 0.1859 0.1453 0 .0183 0.0293 1.0000 0.2764 -0.1587 -0.0581 0.0270 0.0580 -0.0184 0.1847 0.1352 0.0967 0.1220 0.2764 1 .0000

Page 46: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

. ~ .. . .. . ... . . .. .. .. _ _ _ _ “I- . . . . . . . , . . . . . . . . , .

NtMFAIL

0 0 0 0 0 0 0 0 0 2 1 1 6 5 5 22 5 4 12 15 18 1 3 13 3 15

Table C.10 (continued) : Analysis Results

Subset of PWR Plant X Demand-related Failure Data: Model with optypl, cap11 and systl

Normal Confidence Intervals For Parameters

Two-sided Confidence Coefficient: 0.9500 Parameter Confidence Limits

PRMl PRMl PRM2 PRM2 PRM3 PRM3 PRM4 PRM4 PRM6 PRM6 PRM8 PRMB PRM9 PRM9 PRMlO PRMlO PRMll PRMll PRM12 PRMl2 PRMl3 PRM13

Lower -8.0803 upper -6.1767 Lower 0.6137 upper 2.4142 L o W K 0.8036 Upper 2.7193 Lover -1.9024 upper 0.0167 Lower -3.1572

Lower 2.9905 upper 4.3462 Lower -1.0276 upper 0.8889 Lower 2.7102 upper 6.0076 Lower 1.9059 upper 4.8920 LoWK 2.3750 upper 3.5740 Lower -0.6440 upper 1.1446

upper -0.3754

LR Statistics For Type 1 Analysis

source Deviance DF Chisquare PoChj

INTERCEPT OPTYPl W L l SYSTl

402.9678 231.1275 202.5210 51.1245

0 3 1 6

171.8403 28.6065 151.3965

0.0001 0.0001 0.0001

LR Statistics For Type 3 Analysis

source DF Chisquare Pr>Chi

OPTYPl 3 114.9624 0.0001 CAPLl 1 7.4516 0.0063 SYSTl 6 151.3965 0.0001

TOTD Pred

297 0.004157 12 0.0106 93 0.004087 89 0.003389

191 0.004336 346 0.004646

307 0.0155 1715 0.003631

1064 0.006079 862 0.0183 855 0.0233 42 0.005344 60 0.0587

222 0.0666 24 0.0464

Observation Statistics

Xtata Std HessWgt Lower Upper

-5.4787 0.4751 1.2296 0.001642 0.0105 -4.5359 -5.4958 -5.6839 -5.4364 -5.3670 -8.1407 -8.0713

0.6133 0.4821 0.5008 0.4485 0.2018 0.5401 0.2898

0.1259 0.3785 0.3006 0.8246 1.6002 0.0585 6.5715

0.003211 0.001593 0.001272 0.001805 0.003133 0.000101 0.000177

0.0344 0.0104

0.008993 0.0104

0.006885 0.000839 0.000551

201 0.000291 21051 0.000312

24 0.001029 -6.8782 0.6113 0.0247 0.000311 0.003402 1329 0.002088 -6.1692 0.5792 2.7697 0.000672 0.006470 367 0.005960 -5.1167 0.4366 2.1743 0.002542 0.0139

-4.1540 0.4150 4.6725 0.006913 0.0342 -5.6146 0.2484 6.2049 0.002235 0.005895

1184 0.001596 879 0.004336

3679 0.004646 -5.3670 0.2018 17.0143 0.003133 0.006885 813 0.004659 -5.3642 0.4185 3.7703 0.002057 0.0105 621 0.000801 -7.1285 0.4856 0.4972 0.000309 0.002073

-5.0968 0.2990 6.4286 0.003392 0.0109 -3.9819 0.2107 15.4932 0.0122 0.0274

97 0.1546

-6.4387 0.3144 1.8866 0.000863 0.002951 -5.4364 0.4485 3.7951 0.001805 0.0104

-3.7344 0.1969 19.4827 o.oiS0 0.0539 -5.2264 0.7344 0.2233 0.001272 0.0222 -2.7744 0.4291 3.3165 0.0262 0.1264 -2.6401 0.2383 13.8013 0.0428 0.1022 -3.0219 0.4529 1.0629 0.0197 0.1058 -1.6987 0.2808 12.6804 0.0954 0.2408 -

Resraw Reschi Resdev

-1.2347 -1.1135 -1.5731 -0.1272 -0.3586 -0.5058 -0.3801 -0.6178 -0.8728 -0.3016 -0.5501 -0.8282 -0.9121 -1.6076 -1.2709 -0.0586 -0.2420 -6.5736 -2.5643 -0.0247 -0.1572 -0.7755 -0.4660 -1.1873 -0.8052 -3.7459 -1.7329 -0.2275 -0.0913 3.1104 2.2645 1.1884 0.6100 4.9063 1.1894 1.2120 0.6242

-0.7773 -1.2884 -1.7952 -0.3423 -3.6262 -0.2223 -0.4907 -0.9018 -2.1032 -0.0919 1.8756 0.5820 1.1387 0.5948

3.5024 4.9670 3.1127 5.5320 2.1819 1.9488

-0.7822 -0.1987 -0.2004 -1.9481 -0.4413 -0.4487 0.7755 1.6414 1.2048

-0.5234 -0.2874 -0.2945 -1.7861 -0.4808 -0.4903 1.8853 1.8287 1.5263

-3.55E-15 -9.98E-16 0

Page 47: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table C . l l P r e d i c t i o n s Based on Model inc luding optypl , c a p l l , and s y s t l F i t t o

Subset of PWR P l a n t X Demand-related F a i l u r e Data i n Table C.8

Code corresponding t o f a c t o r l e v e l s def ined i n Sec t ion 2: optypl=1,3,5, o r 7 a s def ined previous ly i n s e c t i o n 2 c a p l l = l o r 2 r e s p e c t i v e l y f o r INTEWB o r INTEWC s y s t l = l - 7 r e s p e c t i v e l y f o r systems AB, BA, BP, CB, CC,

OPtYPl

Type O p e ra t o r

3 3 3 3 3 3 3 1 1 1 1 1 1 1 7 7 7 7 7 7 7 5 5 5 5 5 5 5 3 3 3 3 3 3 3 1 1 1 1 1 1 1 7 7 7 7 7 7 7 5 5 5 5 5 5 5

c a p l l Appl ica t ion Environment

1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2

s y s t l System

1 2 3 4 5 6 7 1 2 3 4 5 6 7 1 2 3 4 5 6 7 1 2 3 4 5 6 7 1 2 3 4 5 6 7 1 2 3 4 5 6 7 1 2 3 4 5 6 7 1 2 3 4 5 6 7

Predic t ion

0.03033 0.00074 0.05872 0.02333 0.01539 0.00102 0.00080 0.02383 0.00058 0.04644 0.01831 0.01205 0.00080 0.00062 0.00534 0.00013 0.01060 0.00409 0.00268 0.00018 0.00014 0 -00209 0.00005 0.00416 0.00160 0.00104 0.00007 0.00005 0.15465 0.00434 0.26735 0.12259 0.08375 0.00596 0.00465 0.12497 0.00339 0.22172 0.09835 0.06660 0.00466 0.00363 0.03047 0.00075 0.05899 0.02344 0.01546 0.00103 0.00080 0.01209 0.00029 0.02384 0.00926 0.00608 0.00040 0.00031

Lower 95%

Bound

0.008644 0.000143 0.026200 0.015982 0.003004 0.000191 0.000176 0.006824 0.000113 0.019653 0.012189 0.002655 0.000164 0.000145 0.001272 0.000022 0.003211 0.001593 0.000547 0.000031 0.000028

0.000011 0.001643 0.000863 0.000257 0.000015 0.000014 0.095441 0.001805 0.071229 0.033530 0.047585 0.002542 0.003133 0.064790 0.001272 0.051344 0.024097 0.042814 0.002056 0.002235 0.010304 0.000206 0.009197 0.004039 0.006913 0.000311 0.000309 0.005358 0.000101 0.003947 0.001707 0.003392 0.000151 0.000177

a.000672

SD, S J

Upper 95%

Bound

0.10087 0.00387 0.12638 0.03394 0.07495 0.00547 0.00362 0.07984 0.00298 0.10580 0.02741 0.05295 0.00390 0.00267 0.02216 0.00075 0.03443 0.01045 0.01299 0.00101 0.00068

0.00023 0.01048 0.00295 0.00424 0.00032 0.00020 0.24081 0.01038 0.63454 0.36009 0.14325 0.01391 0.00689 0.22745 0.00899 0.59991 0.32517 0.10220 0.01052 0.00589 0.08664 0.00271 0.29742 0.12440 0.03420 0.00340 0.00207 0.02707 0.00084 0.13080 0.04863 0.01087 0.00106 0.00055

0.00647

Page 48: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

APPENDIX D: Analyses for BWR Plants, Timerelated Failure Data

22

Page 49: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table D.l: Cross tabulation by failure mode and originating facility for the BWR time-related data of Table A.2

I OF1 I I I I I I

IFailure Mode I Yx I IP4 I B W l I BWR I MNSl I ALL I

I L I N I 201 71 I I I 7 7 I

I I I

failures i times I rate I 0 N I failures I times I rate I 0 N I failures I times I rate I N I failures I

51 i 6607737 I

1.00000318 I 0 . 81 10 I

241394 I .000041431

. I

.I

.I

.I 0.

.I

.I

5 i 73000001

.000000411 . I

io i 13770000 I 000000731

.I

.I

. I

. I 0

11 161

226000001 .000000711

. I

. I

.I

24 I 13907737 I

0.000001731 10 I I FTO

I I I

I I I SP I I times I . I . I . I 51991201

. I . I 0.000000771 I rate I . I . I 0.000000771 I - 1 .I 11 .I .I 11 I sc

.I . I 41 .I . I 41 I failures I I times I . I . I 39441601 .I . I 39441601

.I 0.000001011 . I . I 0.000001011 I rate I . I I . I .I . I 21 . I 21 ILE

* I .I . I 39 I .I 39 I I failures I I times I .I . I .I 75600000001 .I 75600000001 I rate I .I .I 0.00000001~ .I 0.000000011

N I 28 I 61 31 31 11 41 I I ALL I failures I 31 I 13 I 81 55 I 18 I 125 I I times I 68491311 210700001 91432801 75826000001 1484791 76198108901 I rate I 0.000004531 0.000000621 0.000000871 0.000000011 0.000121231 0.00000002~

I so

. I

N

N

0

18 I 1484791

.000121231 .I .I . I . I

44 i 22989873 I

0.000001911 41 10 I

13770000 I 0.000000731

Table D.2: Cross tabulation by originating facility and system, listed by failure mode for BWR time-related data of Table A.2.

I I I Failure Mode I I

I FTO I I I L I I

I OF1 I I I System I OF1 I I I 1

I I YX I ALL I YX I MNSl I ALL I

I 41 41 21 .I 21 I BG/BM N 11 11 01 .I 01 I failures I

I hours 1 1304 I 1304 I 652 I . I 652 1 I rate I 0.000766871 0.000766871 0.00000000~ . I 0.000000001

I 31 31 11 . I 11 I BN 11 11 01 . I 01 I failures I

I hours I 752 I 752 I 488 I * I 488 I I rate I 0.001329791 0.001329791 0.000000001 .I 0.000000001

I 41 41 .I . I .I I CH 01 01 .I . I .I I failures I

.I .I .I I hours I 187141 187141

.I . I I rate I 0.000000001 0.000000001

- 1 .I .I 18 I 18 I I failures I I hours I .I . I .I 1484791 1484791 I rate I .I .I 0.000121231 0.000121231

01 01 .I .I . I I failures I 76901 7690 I .I . I .I I hours 1

.I .I .I I rate I 0.000000001 0 .00000000~ I 12 I 12 I 31 11 41 I ALL

21 21 01 18 I 18 I I failures I I hours I 284601 284601 11401 1484791 1496191 I rate I 0.000070271 0.000070271 0.000000001 0.000121231 0.000120311

N

N

N ISJ I .I .I .I il 11

I BI I il 11 .I .I .I N

N

_____

Page 50: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table D.3 : Cross tabulation by originating facility and operator type, listed by failure mode for BWR time-related data of Table A.2.

I I I Failure Mode I

I L I I FTO I I I

I I OF1 I I I

loperator Type I I_______________________I I I Yx I IP4 I ALL I Y x I BWR I ALL I

I 71 11 81 21 .I 21 17 N 01 11 11 01 . I 01 I failures I

I hours I 768731 21500001 22268731 I rate I 0.000000001 0.000000471 0.000000451 0 . 0 0 0 0 0 0 0 0 ~ . I 0.000000001

I 71 11 81 . I . I . I I1 10 I 21 1 2 I . I . I . I I failures I

. I .I .I I hours I 53622791 51500001 105122791

. I . I . I I rate I 0.000001861 0.000000391 0 . 0 0 0 0 0 1 1 4 ~ I . I .I .I 41 11 51 I 2

. I - 1 .I 01 161 161 I failures I I hours I .I . I .I 8721 226000001 226008721 I rate I . I . I 0.000000001 0.000000711 0 . 0 0 0 0 0 0 7 1 ~

51 .I 51 . I . I . I I failures I . I 1947571 . I . I . I I hours I 1947571

. I . I I rate I 0.000025671 . I 0.000025671

.I . I .I 10 I .I 1 0 I I failures I I hours I .I .I . I 2391171 . I 2391171 I rate I .I . I . I 0.000041821 . I 0.000041821

I .I .I .I 11 .I 11 14 .I . I .I 01 .I 01 I failures I

I hours I . I . I .I 2621 .I 262 I . I 0.000000001 . I 0.000000001

N I rate I .I I ALL I 161

15 I 31 1 8 I 10 I 161 261 I failures I I hours I 56339091 13000001 129339091 2413941 226000001 228413941 I rate I 0.000002661 0.000000411 0.000001391 0.000041431 0.000000711 0 . 0 0 0 0 0 1 1 4 ~

I OF1

11431 . I 11431

N

N

N 15 I il .I 21 .I . I .I

13 I . I . I .I il .I 11 N

N

il 1 8 I 81 11 91

Page 51: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

APPENDIX E: Analyses for PWR Plants, Timerelated Failure Data

23

Page 52: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table E.l: Cross tabulation by failure mode and originating facility for the PWR time-related data of Table A.2

I I Failure Mode I I OF1 I FTO I L I I SC I SO I SP I LE

I X I I I lBhW I I I IDBSl I I I I IP1 I I I I IPS2 I I I 121s1 I I I IEUR I I I I FPRA I I I INEE3 I I I I BREL I I I I PWR I I I I ALL I I I

N I failures I hours 1 rate I N I failures I hours I rate I N I failures I hours I rate 1 N I failures I hours I rate I N I failures I hours I rate I N I failures I hours I rate I N I failures I hours I rate I N I failures I hours I rate I N I failures I hours I rate I N I failures I hours 1 rate I N I failures I hours I rate I N I failures I hours I rate I

51 I 14 I

2089594301 0.000000071

91 01

164835971 0.000000001

11 12 I

364728 I 0.000032901

.I

.I

. I

.I

. I

. I

. I

. I

. I - I .I .I .I .I .I . I . I . I . I . I . I . I .I . I .I * I .I .I .I .I .I .I

61 I 26 I

2258077551 0.000000121

22 I 81

13650877 I 0.000000591

. I

.I

. I

01 4324632 I

0.00000000~

61 8850000 I

0.000000681 11 11

444000 I 0.000002251

11 01

608000 I 0.000000001

11 51

14977301 0.000003341

11 91

376000 I 0.000023941

. I

. I

. I

. I

. I

.I

. I

.I

. I

.I

.I

.I 30 I 29 I

297512391 0.000000971

iI

31

.I

.I

.I * I .I . I - 1 . I . I . I . I . I .I .I .I

01 124440001

0.000000001 31 01

24330000 I 0.000000001

21 01

36388611 0.000000001

. I

.I

.I

21 61770001

0.000000321 .I .I .I .I .I .I . I .I

15 I 21

4 658 98 61 I 0.000000041

II

i l

.I

. I

. I

.I

.I

.I

.I

.I 11 31

4012008 I 0.000000751

81

15854000 I 0.000001891

.I

.I

.I

.I

.I

.I

.I

51 1120765 I

0.00000446 I 21 71

2392000 I 0.00000293 I

.I

.I

.I

.I 11 81

1841041 0.000043451

.I

.I

.I

.I 13 I 53 I

235628771 0.000002251

30 I

il

11 01

134524 I 0.00000000~

. I

.I

. I

.I

.I

. I

. I

. I

. I

. I

. I

. I

. I

. I

. I

. I

. I

.I

.I

.I

.I

.I

.I

.I 92

.119000000000

.I 0.00000000 81 2 31 92

1841175119000000000 0.000001631 0.00000000

.I i

OBS

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20 21 22

RECNO OF1

527 X 523 X 543 x 521 X 525 X 522 X 524 X 541 X 452 X 547 x 545 x 529 X 542 X 450 X 540 X 451 X 938 x 544 x 528 X 546 X 526 X 519 X

SYSTl

BE B I LD SB BP CI C I BA CB CB cc SD SD SJ SJ BS

BE cc BS KE CI

PWR Plant X, Failure Mode

CAPLl OPTYPl VLVTYPl

5 3 5 3

INTEAR 5 3 INTEST 5 3 INTEWB 5 3 INTEWB 5 3 INTEWB 5 3 INTEWC 5 3 INTEWC 5 3 INTEWC 5 3 INTEWC 5 3 INTEWC 5 3 INTEWC 5 3 INTEWC 5 3 INTEWC 5 3 INTEWS 5 3

7 7 INTECS 5 3 INTEWC 5 3 INTEWS 5 3

5 3 5 3

Table E.2

L I records: Th-related

IC1 SG1 M O D E

1 0 L I 1 1 L I 0 0 L I 1 0 L I 1 1 L I 1 0 L I 1 0 L I 0 0 L I 0 0 L I 0 0 L I 0 0 L I 1 0 L I 0 0 L I 0 0 L I 0 0 L I 0 0 L I 1 0 L I 0 0 L I 1 0 L I 0 0 L I 1 0 L I 0 0 L I

Failure

NSTATE

xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx xx NC xx xx xx xx xx

Data

IR NUWAIL

Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 0 Y 1 Y 1 Y 1 Y 2 Y 3

i i

ALL I i

74 I 22 I

2227448311 0.000000101

91 01

164835971 0.000000001

31 15 I

8701368 I 0.000001721

11 I 36 I

24704000 I 0.00000146 I

81 21

132275211 0.000000151

61 21

26252000 I 0.000000081

51 10 I

63104861 0.000001581

31 161

27680001 0.000005781

71 21

61770001 0.000000321

11 81

184104 I 0.000043451

21 92 I

90000000001 0.00000000~

1291 205 I

93275529071 0.000000011 -

TOTHRS

2240 1115136 101376 201786 134524 32656 32078

432 709632 912384 253440 302679 67262 33631

336310 50688

6138382 700

304128 152064 103947

2665402

FP.ATE

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.ooooooo

.0014286

.0000033

.0000066

.0000192

.0000011

Page 53: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table E.3: Cross tabulation by system and application environment for the PWR Plant X time-related failure data, for failure mode fmode=LI

isyetem I INTEWC I INTEWB I INTEWS I --- I CB I I I I cc I I I I SD I I I ISJ I I I I BA I I I I CI I I I I BP I I I I BS I I I ILD I I I I SB I I I I BE I I I I ALL I I I

N I 21 failures I 01

rate I 0.000000001 N I 21 failures I 11 hours I 5575681 rate I 0.000001791 N I 21 failures I 01 hours I 3699411 rate I 0.000000001 N I 21

hours I 16220161

failures I 01 hours I 3699411 rate I 0.000000001 N I 11 failures I 01 hours I 432 i N I .I i rate I 0.000000001

failures I .I 0

rate I . I 0.00000000 N I . I 1 failures I . I 0 hours I . I 134524 rate I . I 0.00000000 N I . I failures I .I hours I rate I N I failures I

rate I N I failures I hours I rate I N I failures I hours I rate I N I failures I

rate I

hours I .I 64734

hours I

hours I

.I

.I

.I

.I

.I

.I

.I

.I

. I

. I

. I

.I

.I

11 29198981

0.000000341

91 1 0

199258 0.00000000

i 1

202752 0.00000493

i 1

202752 0.00000493

INTEAR

i 0

101376 0.00000000

i 0

101376 0.00000000

INTEST I INTECS I ALL I

. I .I 21

. I .I 01

. I .I 16220161

. I . I 0.000000001

. I . I 21

.I . I 11 . I . I 5575681 .I . I 0.000001791 .I . I 21 .I . I 01 .I . I 3699411 .I .I 0.00000000~ . I . I 21 .I . I 01

.I 21

.I 01

.I 647341

.I 0.000000001

. I 11

. I . I 36994ii

. I . I 0.000000001

. I . I 11

. I . I 01

.I . I 432 I

.I .I 0.000000001

.I

.I

.I

. I

. I

. I .I 1345241

.I . I 0.000000001

. I . I 21

. I . I 11

. I . I 2027521

.I . I 0.000004931

. I . I 11

.I .I 01

.I .I 1013761 .I 0.000000001

0 1 .I 01 2017861 .I 2017861

0.000000001 . I 0.000000001 .I 11 11 . I 11 11 .I 700 I 700 I . I 0.001428571 0.001428571 11 11 17 I 01 11 31

7001 3625770 I 0.000000001 0.001428571 0.000000831

. I . I oi

il - I 11

2017861

Page 54: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table E.4: Cross tabulation by system and icl, indicator for inclusion of circuit failures in observed failure count, for the PWR Plant X time-related failure data, for failure mode fmode=LI

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

System

CB

SJ

BS

LD

BA

CI

BE

cc

SD

BI*

SB

BP

KE

ALL

I Includes Circuit? I I I

I O I 1 I A L L I

N I 21 .I 21 failures I 01 .I 01 hours I 16220161 .I 16220161 rate I 0.000000001 .I 0.000000001 N I 21 .I 21 failures I 01 * I 01 hour6 I 3699411 .I 3699411 rate I 0.000000001 .I 0.000000001 N I 21 . I 21 failures I 11 . I 11 hours I 2027521 . I 2027521 rate I 0.000004931 . I 0.000004931 N I 11 . I 11 failures I 01 . I 01 hour6 I 1013761 . I 1013761 rate I 0.000000001 . I 0.000000001 N I 11 . I 11 failures I 01 . I 01 hours I 432 I . I 432 I rate I 0.000000001 .I 0.000000001 N I 11 21 31 failures I 01 31 hour6 I 26654021 31 647341 27301361 rate I 0.000001131 0.000000001 0.000001101 N I 11 11 21 failures I 01 11 hours I 700 'I I 22401 29401 rate I 0.001428571 0.000000001 0.000340141 N I 11 11 21 failures I 01 11 11 hours I 2534401 3041281 5575681 rate I 0.00000000l 0.000003291 0.000001791 N I 11 11 21 failures I 01 01 01 hours I 672621 3026791 3699411 rate I 0.000000001 0.000000001 0.000000001 N I .I 11 11 failures I .I 01 01 hours I .I 11151361 11151361 rate I . I 0.000000001 0.000000001 N I . I ii ii failures I . I 01 01 hours I .I 2017861 2017861 rate I .I 0.000000001 0.000000001 N I .I 11 11 failures I . I 01 01 hours I .I 1345241 1345241 rate I .I 0.000000001 0.000000001 N I .I 11 11 failures I * I 21 21 hours I .I 1039471 1039471 rate I .I 0.000019241 0.000019241 N I 12 i 9i 21 i failures I 51 31 81 hours I 52833211 2229174 I 7512495 I rate I 0.000000951 0.000001351 0.000001061

For the single records of system BI and BP, sgl=l. All other records included in this table have sgl=O.

Page 55: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

OBS

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51

RECNO

5 95 5 94 807 820 821 805 819 825 822 823 963 962 964 966 961 696 695 694 699 697 698 458 459 768 772 773 778 771 770 779 775 776 777 919 913 917 918 923 91 6 914 915 924 920 921 922 818 824 769 774 750 693

OF1

X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X

T a b l e E.5

PWR P l a n t X, Fai lure Mode FTO records:

SYSTl

SB BP C I FE LD SB CB BA cc SD LD BE AB BA CB BE AB CB BA SD S J BA SJ B I m LD SB AB CB BA cc SD S J BE B I FE LD SB AB BP CB BA cc SD SJ BP SJ BP BE

BP

W L l

INTEST INTEWB

INTEWB INTEWC INTEWC INTEWC INTEAR INTECS INTEWC INTEWC INTEWC

INTEWB INTEWB INTEWC INTEWC INTEWC INTEWC INTEWC

INTEWB INTFME INTEWC INTEWC INTEWC INTEWC

INTEWB INTEWB INTEWB INTEWC INTEWC INTEWC INTEWC INTEWB INTEWC INTEWB

INTEWB

OPTYPl

i 1 1 1 1 1 1 1 2 2 2 2 2 3 3 3 3 3 3 3 3 5 5 5 5 5 5 5 5 5 5 7 7 7 7 7 7 7 7 7 7 7 7 1 1 5 5 5 3

IC1

0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 1

SG1

0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 0 0 0 1 0 0 0 0 0 0 1 0 0 0 1 1 0 0 0 0 0 1 0 1 0 0 1

Time- re l a t ed Failure D a t a

FMODE

FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO FTO

IR

Y Y Y Y Y Y Y N Y Y Y Y Y Y Y Y Y Y Y Y Y N Y Y Y Y Y Y Y N Y Y Y N Y Y Y Y Y Y Y N Y Y Y Y Y Y N Y Y

NOMFAIL

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 2 4 5

TOTHRS

269048 168155 96234

311841 50688 672620

12 0 0 0 0 0 54

1571328 369941 101376

1120 315504

216 101376

560 157752

1100000 486

168155 706251

108 67262

2027520 2771920

18 0 0 0 0 0 0 3654886 5915700 17 0 0 0 0 0 0

1512 18084928 6154473 4809233

280 202752 69298

304128 134524 197190 67262

861696 54

2889216 134524 134524 201786 336310

15806571 5320

101561962 201786

FRATE

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.oooooooo

.00000496

.00000297

.00000006

.00037594

.00000004

.00002478

Page 56: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table E . 6 : Cross tabulation by system and application environment for the PWR Plant X time-related failure data, for failure mode fmode=FTO

I Application Environment I I I

I I

rate i o.ooooooooi N I 11

I System I INTEWC I

I BA N I 61 I failures I 01 I hours I 2430 I I rate I 0.000000001 ISJ N I 51 I failures I 11 I hours I 60535801 I rate I 0.000000171 I SD N I 41 1 failures I 01 I hours I 68270931 I rate I 0.00000000~ I cc N I 31 I failures I 01 1 hours I 225454721 I I CB I I I IRB I I I I BP I I I I S B I I I ILD I I I I BE I I I rate I IALL N I I failures I I hours I I rate I

failures i o i o i hours I 1013761 201616961 rate I 0.000000001 0.000000001 N I 11 31 failures I 01 01 hours I 3155041 62706421 rate I 0.000000001 0.000000001 N I failures I hours I rate I N I failures I hours I rate I N I failures I hours I rate I N I failures I hours I

. I 5 i

. I 71

. I 164455601

. I 0.000000431

. I * I 1

. I .I 0

. I .I 269048

. I .I 0.00000000

. I

. I

.I

.I

.I

.I

. I

. I .I 20 I 12 I 1 11 71 0

35845455i 42877898i 269048 0.000000031 0.000000161 0.00000000

INTEAR I INTECS I ALL I I

. I .I 61

. I . I 01

. I . I 2430 I

. I . I 0.000000001

. I

. I

.I

. I

. I

.I

. I

. I

.I

. I

. I

. I

. I

. I

. I

. I

. I

. I

.I

. I

. I

.I

.I

.I

.I

. I

.I

01 1013761

0.000000001 .I

. I 1120 I 1120 I

.I 0.000000001 0.000000001 11 11 35 I

iI

.I o i o i

. I 51

. I 11

. I 60535801

. I 0.000000171

. I 41

. I 01

. I 68270931

.I 0.000000001

. I 31

.I 01

. I 225454721 . i o.ooooooooi

.I 51

.I 01

. I 202630721

.I 0.000000001

. I 41

.I 01

. I 65861461

.I 0.000000001

. I 11 ~. ~.

.I 01

. I 2690481

.I 0.000000001

.I . I 11

. I .I 01

.I . I 2690481 .I 0.000000001

01 . I 01 1013761 .I 1013761

0.000000001 . I 0.000000001 .I .I 01 01 . I 1120 I 1120 I .I 0.000000001 0.000000001 11 11 35 I

iI

01 01 81 1013761 11201 790948971

0.000000001 0.000000001 0.000000101

Page 57: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table ' E.7: C r o s s t a b u l a t i o n by s y s t e m and o p e r a t o r t y p e f o r t h e PWR P l a n t X t i m e - r e l a t e d f a i l u r e d a t a , f o r f a i l u r e mode fmode=FTO

I I I I

I I 11 11 11 21 11 61 I BA

I f a i l u r e s I 15121 54 I 54 I 594 I 2161 2430 I I h o u r s I

I r a t e I 0.00000000l 0.000000001 0.000000001 0.000000001 0.00000000~ 0.00000000~ I 11 11 11 11 11 51 I CB

I f a i l u r e s I I h o u r s I 170000001 8616961 12000001 11000001 1013761 202630721 I rate I 0.000000001 0.000000001 0.000000001 0.000000001 0.000000001 0.00000000~

I 11 11 11 21 . I 51 ISJ I f a i l u r e s I I h o u r s I 48092331 1345241 3363101 7735131 . I 60535801 I rate I 0.000000001 0.000000001 0.000002971 0.00000000~ .I 0.000000171

I 11 11 11 11 . I 41 I BP 11 01 11 51 .I 71 I f a i l u r e s I

I h o u r s I 158065711 672621 2017861 2017861 . I 162774051 I r a t e I 0.000000061 0.000000001 0.000004961 0.000024781 .I 0.000000431

I 11 11 11 11 .I 41 I SD I f a i l u r e s I I h o u r s I 61544731 1345241 3699411 1681551 .I 68270931

I 11 11 11 . I 11 41 ILD I f a i l u r e s I I h o u r s I 180000001 3041281 506881 .I 1013761 184561921

I 11 11 11 .I - 1 31 IKE I f a i l u r e s I I h o u r s I 27719201 692981 3118411 .I .I 31530591

I 11 11 11 .I .I 31 I SB I f a i l u r e s I

. I 44620301 I h o u r s I 36548861 1345241 6726201

1 11 11 11 .I . I 31 I cc I f a i l u r e s I I h o u r s I 180849281 28892161 15713281 .I .I 225454721

I 11 11 - 1 11 11 41 I BE I f a i l u r e s I

5320 I 280 I .I 560 I 1120 I 72801 I h o u r s I I r a t e I 0.000375941 0.00000000~ - 1 0.000000001 0.000000001 0.000274731

I 11 11 . I 11 11 41 (AB I f a i l u r e s I I h o u r s I 59157001 1971901 . I 1577521 3155041 65861461

I B I I f a i l u r e s I I h o u r s I 20275201 2027521 .I * I . I 22302721

I CI I f a i l u r e s I I h o u r s I .I .I 962341

I ALL I failures I I h o u r s I 942320631 49954481 48108021 24023601 5195921 1069602651 I rate I 0.000000031 0.000000001 0.000000421 0.000002081 0.000000001 0.000000091

I I O p e r a t o r Type I I Sys tem I 5 I 7 I 1 I 3 I 2 I ALL I

01 01 01 01 01 01

01 01 01 01 01 01

01 01 11 01 .I 11

N

N

N

N

N 01 01 01 01 .I 01

I r a t e I 0.000000001 0.000000001 0.00000000~ 0.00000000~ .I 0.000000001

01 01 01 .I 01 01

I rate I 0.000000001 0.000000001 0.00000000~ .I 0.000000001 0.000000001

01 01 01 .I .I 01

I rate I 0.000000001 0.000000001 0.00000000~ .I .I 0.000000001

01 01 01 .I *I 01

I rate I 0.000000001 0.000000001 0.00000000~ . I .I 0.000000001

01 01 01 . I .I 01

I rate I 0.000000001 0.000000001 0.000000001 .I .I 0.000000001

21 01 *I 01 01 21

01 01 .I 01 01 01

I rate I 0.000000001 0 .00000000~ .I 0.000000001 0.000000001 0.000000001 I 11 11 .I .I .I 21

01 01 . I .I - 1 01

I rate I 0.000000001 0.00000000~ .I .I .I 0.000000001 I .I . I 11 .I . I 11

.I .I 01 . I .I 01

I r a t e I . I .I 0.000000001 .I 0.00000000~ I 12 I 12 I 10 I 91 51 481

31 01 21 51 01 10 I

N

N

N

.I N

N

N

N

N

.I 962341 - 1

N

__--____ __

Page 58: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table E.8: Cross tabulation by system and icl, indicator for inclusion of circuit failures in observed failure count, for the PWR Plant X time-related failure data, for failure mode fmode=FTO

I Includes Circuit? I I I

I I I I 1 I O I A L L I

I System I I I I I BA N I 61 . I 61 I failures I 01 . I 01 I hours I 2430 I . I 2430 I

. I 0.000000001 I rate I 0.000000001 I CB N I 51 .I 51 I failures I 01 .I 01 I hours I 202630721 .I 202630721 I ISJ

im I I I I SD I I I I BE I I I

I lIcE I failures I 01 .I o i I hours I 31530591 .I 31530591 I rate I 0.000000001 .I 0.000000001 I cc N I 31 .I 31 I failures I 01 .I 01

I rate I 0.000000001 .I 0.000000001 IBI N I 21 .I 21 I failures I 01 .I 01

I rate I 0.000000001 .I 0.000000001 I CI N I 11 .I 11 I failures I 01 . I 01

I rate I 0.000000001 . I 0.000000001 I BP N I 41 11 51 I failures I 71 01 71 I hours I 162774051 1681551 164455601 I rate I 0.000000431 0.000000001 0.000000431 I SB N I 31 11 41 I failures I 01 01 01 I hours I 44620301 2690481 47310781 I rate I 0.000000001 0.000000001 0.000000001 IALL N I 48 I 21 50 I I failures I 10 I 01 10 I I hours I 1069602651 4372031 1073974681 I rate I 0.000000091 0.000000001 0.000000091

I hours I 225454721 . I 225454721

I hours I 22302721 .I 22302721

I hours I 962341 . I 962341

rate I 0.000000001 N I 51 failures I 11 hours I 60535801 rate I 0.000000171 N I 41 failures I 01 hours I 184561921 rate I 0.000000001 N I 41 failures I 01 hours I 68270931 rate I 0.000000001 N I 41 failures I 21 hours I 72801 rate I 0.000274731 N I 41 failures I 01 hours I 65861461 rate I 0.000000001 N I 31

.I 0.000000001 - I 51 .I 11 . I 60535801 . I 0.000000171 . I 41 . I 01 . I 184561921 . I 0.000000001 . I 41 . I 01 . I 68270931 . I 0.000000001 . I 41 . I 21 . I 7280 I . I 0.000274731 .I 41 . I 01 .I 65861461 .I 0.000000001 . I 31

Page 59: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table E.9: Cross tabulation by system and sgl, indicator for safety graded components, for the PWR Plant X time-related failure data, for failure mode fmode=FTO

I Safety Graded? I I I I I __

I O I 1 I A L L I I

N I 51 .I 51 failures I 01 .I 01

rate I 0.000000001 .I 0.000000001 N I 51 .I 51 failures I 11 .I 11 hours I 60535801 .I 60535801 rate I 0.000000171 . I 0.000000171

hours I 202630721 .I 202630721

N I 41 failures I 01 hours I 47310781 rate I 0.000000001

- 1 4 i .I 01 .I 47310781 _ I 0 . 0 0 0 0 0 0 0 0 ~ .I 41 - 1 01 .I 184561921 .I 0.000000001

I I I System I I CB I I I ISJ I I I I SB I I I ILD I I I I SD I I I I BE I I I I= I I I I cc I I I I CI I I I IBA I I I I BP

I hours I 168155 I 16277405 I 16445560 I I rate I 0.000000001 0.000000431 0.000000431 IRB N I 11 31 41 I failures I 01 01 01 I hours I 3155041 62706421 65861461 I rate I 0.000000001 0.000000001 0.000000001 I BI N I . I 21 21 I failures I . I 01 01 I hours I . I 2230272 I 2230272 I I rate I . I 0.000000001 0.000000001 I ALL N I 40 I 10 I 50 I I failures I 31 71 10 I I hours I 826190951 247783731 1073974681 I rate I 0.000000041 0.000000281 0.00000009~

I failures I 01 71 7 i

. I 41

.I 21

.I 72801

.I 0.000274731

.I 31

N I 41 failures I 01 hours I 184561921 rate I 0.000000001 N I 41 failures I 01 hours I 68270931 rate I 0.000000001 N I 41 failures I 21 hours I 7280 I rate I 0.000274731 N I 31 failures I 01 . I 01 hours I 31530591 . I 31530591 rate I 0.00000000~ . I 0.000000001 N I 31 . I 31 failures 1 01 . I 01 hours I 225454721 . I 225454721 rate I 0.000000001 . I 0.000000001 N I 11 . I 11 failures I 01 . I 01 hours I 96234 I .I 962341 rate I 0.000000001 .I 0.000000001 N I 51 11 61 failures I 01 01 01 hours I 2376 I 54 I 2430 I rate I 0.000000001 0.000000001 0.00000000~ N I 11 41 51

Page 60: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

Table E.lO: Cross tabulation by system and ir, indicator for IRADAP quality data, for the Ph‘R Plant X time-related failure data, for failure mode fmode=FTO

I I I System I I BP I I I I CB I I I ISJ I I I I SB I I I ILD I I I I SD I I I IAB I I I IKE I I I I cc I I I I BI I I I I CI I I I I BA I I I I BE I I I I ALL I I I

I IRADAP? I I I I

I Y I N I R L L I I

N I 51 . I 51 f ailures I 71 . I 71 hours I 164455601 .I 164455601 rate I 0.000000431 . I 0.000000431 N I 51 . I 51 failures I 01 hours I 202630721 . I 202630721 rate I 0.000000001 . I 0.000000001 N I 51 51 failures I 11 . I 11 hours I 60535801 . I 60535801 rate I 0.00000017~ . I 0.000000171 N I 41 . I 41 failures I 01 . I 01 hours I 47310781 . I 47310781 rate I 0.000000001 . I 0.000000001 N I 41 . I 41 failures I 01 . I 01 hours I 184561921 . I 184561921 rate I 0.000000001 . I 0.000000001 N I 41 . I 41 failures I 01 . I 01 hours I 68270931 . I 68270931 rate I 0.000000001 . I 0.000000001 N I 41 . I 41 failures I 01 . I 01 hours I 65861461 . I 65861461 rate 1 0.000000001 . I 0.000000001 N I 31 _ I 31 - . failures I o i . I 01 hours I 31530591 . I 31530591 rate I 0.000000001 . I 0.000000001 N I 31 . I 31 failures I 01 . I 01 hours I 225454721 . I 225454721 rate I 0.000000001 . I 0.000000001 N I 21 . I 21 failures I 01 . I 01 hours I 22302721 . I 22302721 rate I 0.000000001 . I 0.000000001 N I 11 . I 11 failures I 01 . I 01 hours I 96234 I . I 962341 rate I 0.000000001 . I 0.000000001 N I 21 41 61 failures I 01 01 01 hours I 702 I 1728 I 2430 I rate I 0.000000001 0.000000001 0.000000001 N I 21 21 41 failures I 01 21 hours I 16801 5600 I 72801 rate i o.ooooooooi 0.00035714i 0.00027473i N I 44 I 61 50 I failures I 81 21 10 I hours I 1073901401 73281 1073974681 rate I 0.000000071 0.000272931 0.000000091

Page 61: 19980422 098 · 2019. 5. 3. · LA-UR- 9 7 4 '$" 3 1 Title: Author(s): Submitted to: ANALYSIS OF VALVE FAILURES FROM THE NUCLARR DATA BASE 19980422 098 Leslie M. Moore US Nuclear

M98004179 \llllllllllllllllllllllllllllllllllllllllllllllllllllll

Report Number (14) @ - (J R .-- 97973 3

Publ. Date (11)

Sponsor Code (18) bh? c/ f I I D E I $ UC Category (1 9) c

DOE