scope:

Forward

(This Foreword is not a part of ANSI/IEEE Std 362-1987, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety systems.)

This document is basically tutorial and has been prepared to provide the user with the basic principles that are needed to conduct a reliability analysis of safety systems. It is not expected or intended that ainnyd ividual or organization would need all of the principles that are presented.F or example,a n organization mayb e concerned with quantitative analysis and mathematical modeling as discussed in Section 5. The veryi mportant problem of failure data is discussed in Section6 ; the material on probability distributions, estimation,a nd confidence intervals mayb e used by those who are concernedw ith analysis and evaluation of failure and repair rate data thawt libe accumulated as nuclear power generating station operating experience is accrued. The material on establishedda ta programs mayb e of more immediate use to those who makreel iability or availability predictions on current safety system designs.

This document was originally prepared to provide a common and consistent means of reliability analysis for protection systems coverbeyd IEEE Std 279-1971, Criteria for Protection Systems for Nuclear Power Generating Stations. In the intervening years, Standard 279 has been superseded by Standard 603, and in March, 1984, Standard 279 was withdrawn. This standard has been expanded in revisions since1 971 to include many technicaal reas as they have become important. In accordw ith the current version of Standard 603, IEEE Std 603-1980, it has been generalized to apply to safetys systems.

The general principles presented in this document,and further information given by the references, are sufficient to conduct the reliability/availability analyses of safety systems, but not every analysis wil necessarily employ all of the general principles that are presented. Furthermore, the principles contained hereina re not necessarily limited to nuclear power plant safety systems. The users may be applied, as applicable, to the analyses of other systems. The users may select those parts of the document that apply to their particular problem.

The current revision of this document contains much updated information and clarification, but adheres to the general principles put forth in previous editions.

The IEEE will update this document as the state of the technology changes. Comments and suggestions for additional materital to be added should be addressed to the Secretary of the IEEE Standards Board.

This document was prepared by Subcommittee 5, Reliability, of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. The members of the working group and other major contributors were as follows:

R. L. Olson, Chairman

F. J. Baloh

R. G. Easterling

W. C. Gangloff

S. H. Hanauer

I. M. Jacobs

H. T. Martz

E. Nomm

J. R. Penland

F. Rosa

B. M. Tashjian

M. I. Temme

I. B. Wall

J. J. Wroblewski

At the time this guide was approved, the members of the subcommittee were as follows:

W. C. Gangloff, Chairman

P. F. Albrecht

A. Barchas

L. E. Booth

F. Chamow

K. Comer

W. I. Crowley

D. Finnicum

J. R. Fragola

J. F. Fussell

P. Haas

W. Hannaman

B. W. Logan

W. J. Luckas, Jr

R. Miles

S. P. Mitra

P. K. Niyogi

R. L. Olson

E. S. Patterson

J. W Pegram

J. R. Penland

J. Pittman

S. Reizenstein

F. Rosa

B. M. Tashjian

M. I. Temme

E. Wittry

J. J. Wroblewski

At the time this guide was approved, the members of the Nuclear Power Engineering Committee were as follows:

R. E. Allen, Chairman

B. M. Rice, Vice Chairman

G. R. Leidich, Secretary

J. T. Bauer, Vice Chairman and Standards Coordinator

J. F. Bates

T. M. Bates, Jr

F. D. Baxter

R. G. Benham

J. T Boettger

D. F. Brosnan

W. Buxton

D. G. Cain

F. W. Chandler

C. M. Chiappetta

R. P. Daigle

E. F. Dowling

J. J. Ferencsik

E. P. Fogarty

J. M. Gallagher

W. C. Gangloff

J. B. Gardner

L. Hanes

I. M. Jacobs

R. F. Karlicek

A. Laird

D. C. Lamken

P. G. Lyons

L. C. Madison

T J. McGrath

W. E. ONeal

R. W. Pack

M. 'Pai

A. Petrizzo

E. S. Patterson

J. R. Penland

N. S. Porter

W. S. Rautio

H. V, Redgate

A. R. Roby

W. F Sailer

W. G. Schwartz

A. J. Spurgin

L. Stanley

D. F. Sullivan

P. Szabados

L. D. Test

J. E. Thomas

T. R. Vadaro

F. J. Volpe

The following persons were on the balloting committee that approved this document for submission to the IEEE Standards Board:

R. E. Allen

J. T. Bauer

F. D. Baxter

R. G. Benham

D. F. Brosnan

W. E. Buxton

F. W. Chandler

R. P. Daigle

E. F. Dowling

J. J. Ferencsik

E. F. Fogarty

J. M. Gallagher

W. C. Gangloff

J. B. Gardner

L. C. Gonzalez

B. Grim

R. E. Hall

L. Hanes

G. K. Henry

R. F. Karlicek

J. T. Keiper

T. S. Killen

A. Laird

D. C. Lamken

G. R. Leidich

P. C. Lyons

W. E. O'Neal

R. W. Pack

M. Pai

J. R. Penland

C. A. Petrizzo

N. S. Porter

W. S. Rautio

H. V. Redgate

B. M. Rice

A. R. Roby

Z. Sabri

W. F. Sailer

A. J. Spurgin

L. Stanley

D. F. Sullivan

P. Szabados

W. G. Schwartz

L. D. Test

J. E. Thomas

T. R. Vardaro

F. J. Volpe

When the IEEE Standards Board approved this standard on June 13, 1985, it had the following membership:

John E. May, Chairman

John P. Riganati, Vice Chairman

Sava I. Sherr, Secretary

James H. Beall

Jay Forster Lawrence

V. McCall Fletcher

J. Buckley Daniel

L. Goldberg Donald

 T. Michael*

Rene Castenschiold

Kenneth D. Hendrix

Frank L. Rose

Edward Chelotti

Irvin N. Howell

Clifford O. Swanson

Edward J. Cohen

Jack Kinn

J. Richard Weger

Paul G. Cummings

Joseph L. Koepfmger *

W. B. Wilkens

Donald C. Fleckenstein

Irving Kolodny

Charles J. Wylie

R. F. Lawrence

Scope

Introduction.

This guide was prepared to provide the designers and operators of nuclear power plant safetys ystems and the concerned regulatory groupws ith the essential methods and procedureosf reliability engineering that area pplicable to suchs ystems. By applying the principles given, systems mayb e analyzed, results may be compared with reliability objectives, and the basis for decisions may be suitably documented.

The quantitative principles are applicable to thea nalysis of the effects of component failures on safety system reliability. The principles are applicable during any phase of the system's lifetime. They have their greatest value during the design phase. .During this phase, reliability engineering can make the greatest contribution toward enhancing safety.

These principles maya lso be applied during the preoperational phase oart any time during the normliafle time of a system. When the principles are applied during either of these two phases, theyw il aid in the evaluation of systems, in the preparation or revision of operating or maintenance procedures, and in improving test programs. Although not inherentllyim ited, these principles are intendedf or application to systems covered in the scope of ANSI/IEEE Std 603-1980 [5].^l