IEEE 382 IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations

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IEEE 382 Document Information:

Title
IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations

The Institute of Electrical and Electronics Engineers, Inc.

Publication Date:
Dec 6, 2006

Scope:

Foreword

(This introduction is not part of IEEE Std 382-1996, IEEE Standard for Qualification of Actuators for Power-Operated Valve Assemblies With Safety-Related Functions for Nuclear Power Plants.)

Applicants for a construction permit or operating license for a nuclear generating station are required to provide assurance that systems, components, and structures are adequate for their service conditions to comply with the Code of Federal Regulations 10 CFR 50, Appendix B Quality Assurance Criteria, and Criterion III Design Control. Each applicant has the responsibility to ensure that this or any other standard, if used, is pertinent to the application and that the integrated performance of the station is acceptable. Implementation of this standard requires the applicant to produce documentary evidence to ensure that the valve actuator can perform its intended function.

Typical design basis event conditions for principal reactor types are presented as one source of parameters for generic-type tests. If the actual conditions of a specific application differ, it will be the obligation of the user to specify these actual conditions.

The numerical values presented in this standard envelop current industry design with respect to radiation types and levels; seismic levels; temperature, pressure, and humidity levels; post-accident periods of operability; spray initiation, and duration. Composition of environment may change in the future, so the user is cautioned to verify the suitability of these values for each application.

This revision was prepared by Working Group SC2.3 of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. The membership of the working group at the time this revision was completed included the following:

Ivan Wilkinson, Chair

Robert Arnold

Nissen M. Burstein

Sal P. Carfagno

Walter J. Denkowski*

W. F. Murray

Clyde T. Nieh 

*Deceased 1995

The following persons were on the balloting committee:

Wes W. Bowers

Dan F. Brosnan

Nissen M. Burstein

Aris S. Candris

S. P. Carfagno

Robert C. Carruth

Robert L. Copyak

Gary L. Doman

Edward F. Dowling

Arthur R. DuCharme

Rich E. Dulski

Jay Forster

J. R. Fragola

John M. Gallagher

Wil C. Gangloff

Louis W. Gaussa

Luis C. Gonzalez

Lawrence P. Gradin

J. K. Greene

Britton P. Grim

Robert E. Hall

Joe Hazeltine

Gregory K. Henry

Sonny Kasturi

James T. Keiper

J. Donald Lamont

Alex Marion

John R. Matras

R. B. Miller

Burt Nemroff

Newell S. Porter

Neil P. Smith

Donald J. Spellman

Peter B. Stevens

James E. Stoner

Peter Szabados

James E. Thomas

John T. Ullo

Raymond Weronick

G. O. Wilkinson

Mark S. Zar

James B. Zgliczynski

When the IEEE Standards Board approved this standard on 21 March 1996, it had the following membership:

Donald C. Loughry, Chair

Richard J. Holleman, Vice Chair

Andrew G. Salem, Secretary

*Member Emeritus

Also included are the following nonvoting IEEE Standards Board liaisons:

Satish K. Aggarwal

Alan H. Cookson

Chester C. Taylor

Kristin M. Dittmann

IEEE Standards Project Editor

This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components.

Keywords:

qualification

nuclear power plants

Class 1E safety equipment

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