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A study on the quantitative evaluation for the software incIuded in digital of nuclear power plants DISCLAIMER

Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. 2002. 3.

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Summary

Recently, newly being developed nuclear power plants (NPPs) accept digital instrumentation and control (I&C) systems because the limitations such as mrrectness, maintainability, enhancement of the operational reliability and complexity of conventional analog systems arise. In addition, in the case of currently being operated nuclear power plants, the tendency of adopting digital I&C systems is increasing because it is difficult to prepattdestablish spear parts of installed analog I&C systems. In general, probabilistic safety analysis (PSA) has been used as one of the most important methods to evaluate the safety of NPPs. The PSA, because most of NPPs have been installed and used analog I&C systems, has been performed based on the hardware perspectives. In addition, since the tendency to use digital I&C systems including software instead of analog I&C systems is increasing, the needs of quantitative evaluation methods so as to perform PSA are also increasing. Nevertheless, several reasons such as software did not aged and it is very perplexed to estimate software failure rate due to its non-linearity, make the performance of PSA difficult. In this study, in order to perform PSA including software more eficiently, test-based software reliability estimation methods are reviewed to suggest a preliminary procedure that can provide reasonable guidances to quantifj, software failure rate. In addition, requisite research activities to enhance applicability of the suggested procedure are also discussed.

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4 4 3 c]XI%!%%! %!XIS =41%4 PSA +qEf-%+lQ *-"E44AlgBA) 9 ++S&4 S3 ...... 29 41 1 @%Is -439 71% ...... 29 41 2 4 qX1l@+%! @XIS YS4]g.n 2EqM &nE4]qq+lqE4+ *.---.31 1. kEEq1qq 34~34. A]%* 4+4 g +3€ ~S)JZS!.) 3%...... 31 2 . A] 4%...... 34 3 . A]% QS?aq8% ...... 34 4 . ?2JqJ-+%&* ...... 35 5 . 4-=qq x%bs3% ...... 35 6. Watchdog A]&@q 44E coverage ...... 35 7 . &mE$Jqq test coverage ...... 36 8 . PSA +q-&+1Sfl &qq& &-ILEq]q oJ1G @A) ...... -37

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! -C. -1 - -2 - -3 - .... -4 - - modeling the multi-tasking of digital systems - modeling the features of phased mission systems - digital induced initiating events including human errors

* -5 - -6 - (test-based software reliability estimation methods)

ANSI(American National Standards 1nstitute)oft qS$ 4= E aq dq2Z-k "the probability of failure-fiee software operation for a specific period of time or demand in a specified environment" e) 301 348C) [ANSIgl]. 4714A1, hZEqq 3% (failure= cM1) %-& %qS 2-k &*(enor), ag(fau1t) 9 aB(defect)q 481 %+jQc)~ 34 8~) [PfleegerE].

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J 4 1 3 ‘Select inputs’ @a

-9 - Laplace'. mk of number of tests point cstlmation succession

Assuming Binnomhl Independent trial distribution

The t-dSstributSon method

-10- e=- 1 N+2

F 1-c Ncj(i-e)N-jej2 C, ~=0,1,2,... j==

F i-z N+,c,(i-e)N+l-jej2 C, ~=0,1,2,... ]d

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ln(1- c) - ln(1- 0) N21+ > In( 1- 0 + p.0) (4 4)

2NAH = X: (1 - C) AH=H,-H k=n-m fi = frequency of the occurrence of the i”’ outcome = -*i N 6 H=-~(’In(fa) (4 5) i=l

-13- 6 Cf, = 1.0 i=l

x:(O.OS) - 11.07 N= -- 2.m 2.m

-14- -i.. -15- psiiirk Random sampling selectlon method Input sampling Bin (urn) sampling

execution coverage -1 7- a is integer, b = a/2; if (b 2 2.5) then @ else @I a is integer, b = a + 1; if (b 2 5) then @ else @

-L. -18- No yes A, B, C, D = deckbn points , '6', affected by input data t + Perform PerfOlIll segment i segment 2

-19- A: integer; 0 < A < 20

.. .. -20- B: Integer; -20 < B < 0

Binl: 2 Bin2: 3 I 1 Bin3: 5

I I I I I I I 1 1 I 0246 000 20 b A

-21-

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-PZ- -_ -25- 6enerating correct outputs for ghn input data

......

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-26- e Bug included in software

2%3-8. AZE4q4 test coverage 9 input coverage4

-27-

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-28- Analog/ Digital Comparator Rndog/Diglhl - trfp QDM Input moduk 0 (to check trip outputmodule % (contmlekmant (plant parameters) parameters) - (generating trip rlgnal) driving mechanism)

- Trip Manual trip signal slgnst (from manual trip buttons) 1% 4-1. 7]Sq +k3&

-29- input module -- (to check trip __c outputmodule S (wntmlahnt (plant parametars) parunatan) (generating Mp signal) drMng mchanlm) L

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-30-

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-33- -<. -34- -35- I. -36- -37- ...... ^...... -...... -...... -.-...... -...... -...... -...... -...... -.

Considering 'safety' perspective software reliablli

Considering ccrfK7ation test

Define re/ative target reliability

Assuming independent triak between successive tests Considering conffdence level

Sekcfing inpuk based on 'safety' perspecfive Input cases Sekcfing test inpub based on fhe combination of whife-box approach- L .-...... _...... -...... -...... ^...... __...... -...... -. -. ..-...... -.-...... -..-...... Perform I tests

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Dennc Assuming ai/ failures from processor i falluro modes of moduk were due to soRware faub processor module Assuming no masking effects

Quantify software reliaQllity

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BIBLIOGRAPHIC INFOMATION SHEET

Perfonning Org. Sponsoring Org. Standard Report No. INIS Subject Code ReDort No. ReDort No. I I I I I I KAE~-2091/2o(n I I A study on the quantitative evaluation for Title / Subtitle I the software included in digital systems of nuclear power plants

~~ ~ Manager J.K. Park (Integrated Safety Assessment team) and Department

Researcher and T.Y. Sung (ISA team), H.S. Eom (ISA team), H.S. Jeong (Hanaro), Department H.G. Kang (ISA team), K.Y. Lee (ARTD team), J.K. Park (NTC) I Publication Publication Taejon Publisher KAERI 2002.3. Place Date 21 x Page 55 p. Ill. & Tab. Yes( 0 1, No ( 1 Size 29.7cm

Open( 0 1, Restricted( 1, Classified Report Type Technical Report - Class Document sponsoring Contract No. Org. In general, probabilistic safety analysis (PSA) has been used as one of the most important methods to evaluate the safety of NPPs. The PSA, because most of NPPs have been installed and used analog I&C systems, has been performed based on the hardware perspectives. In addition, since the tendency to use digital I&C systems including software instead of analog I&C systems is increasing, the needs of quantitative evaluation methods so as to perform PSA are also increasing. Abstract Nevertheless, several reasons such as software did not aged and it is very (15-20 Lines) perplexed to estimate software failure rate due to its non-linearity, make the performance of PSA difficult. In this study, in order to perform PSA including software more efficiently, test-based software reliability estimation methods are reviewed to suggest a .preliminary procedure that can provide reasonable guidances to quantify software failure rate. In addition, requisite research activities to enhance - applicabdity of the suggested procedure are also.discussed. Subject Keywords digital I&C system, probabilistic safety assessment, software, reliability, (About 10 quantitative evaluation

words) 2.