NUREG-0193, Research Info Ltr 18:transmits Results of Completed Research on Development of Frantic Computer Code to Calculate Sys Unavailabilities.Forwards Users Manual (NUREG-0193) & Descriptive Rept.W/O Encl
| ML19212A546 | |
| Person / Time | |
|---|---|
| Issue date: | 11/09/1977 |
| From: | Levine S NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| RIL-018, RIL-18, NUDOCS 7912140518 | |
| Download: ML19212A546 (2) | |
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MX)%NDUM FOR: Edson G. Cas~e'. Acting Director
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Office of Nuclear Reactor Regulation FROM:
Saul Levine, Directier Office of Nuclear Regulatory Research
SUBJECT:
RESEARCH INFORMATION LETTER fl8 03 THE FRANTIC COMPUTER CODE This memorandu r. transmits the results of cor.pleted research on the develo m nt of the FRAtiTIC computer code to calculate system unavailabilities. The work was perfomed internally by the Probabilistic Analysis Branch. Attached please find a copy of the FRAiTIC user's manual (NUREG-0193) and a paper (printer's copy) describing the FRANTIC code which is to be published in the October issue of the IEEE Transactions on Reliability.
The FRAhTIC code calculates the instantaneous, time dependent unavailability of any systen model (such as a fault tree or block diagram). The testing models in FRANTIC are more detailed and more realistic than in other evaluation codes:
test downtimes, test inefficiencies, and test-caused failurcs are incorporated to allow comprehensive surveillance testing evaluations to be perfomed.
The calculations can be of either an absolute or relative nature.
Standard quantitative evaluations can also be performed with FRANTIC where only designs and component hardware are evaluated.
Extensive plo,ts can be produced for reporting purposes.
EVALUATION AND APPLICATION The enclosed FRANTIC user's manual, which describes the rnethodology
' and code utili:ations, has been reviewed by the Offices of Nuclear Reactor Regulation, Standards Developnent, and Inspection and Enforcement.
The FRANTIC methodolo2y has also had peer review before acceptance for publication in the IEEE Trar.sactions on Reliability.
As an example application of FRA*; TIC, the IEEE article and user's manual describe an evaluation in which test intervals are optimized for the aux-feed system analyzed in WASH-1400.
By testing the turbine pur.p,every 60 days and by staggering this test between the g
diesel tests, the average system unavailability is decreased by a
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factor of 23 as cmpared to the nor.-staggered case in which the pump is tested every 30 days.
Furthermore, the maximum instantaneous unavailability of the system is also reduced by a factor of 43. This M21902pg 1568 208 N] g~ T g--
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axwsple shoss the important effect of staggering tests not only within a subsystem (between diesels) but across subsystms in the sarne accident sequence (purip test between diesel tests). These results also indicate chat less testing can be perfomed (60 day intervals versus 30 day intervals for the pu:np) if the testing schines are optimized.
The FRNiTIC code has potential significant application in evaluating technical specifications on testing and allowed downtirnes. The evaluations can be of a generic nature or car. be applied to specific plant systens if applicable data are available. Sensitivity analyses can also be performed to evaluate detailed test properties.
FRANTIC also has potential use in assessing the systs: impact of ccznponent data collectec through hPRDS. The developraent of systs models and further analysis of data will allow wider applications to be evaluated and to be reviewed for practical utilization.
Orional Sagoed by S.iul Lence Saul Levine. Director Office'of Nuclear Regulatory Research
Enclosures:
1.
FRANTIC NUREG-0193 2.
Paper describing FRANTIC Code Distribution:
Sub. ject.
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- Enclosure I will be corinc to you at a later Jupiter (w/ encl 2) date from Publications. is Norry attached.
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