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IEEE 323

2003 Edition, September 11, 2003

Complete Document

Qualifying Class 1E Equipment for Nuclear Power Generating Stations

Includes all amendments and changes through Reaffirmation Notice , September 25, 2008

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Referenced Items:

IEEE 344
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(This introduction is not part of IEEE Std 323-2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations.)

IEEE Std 323-2003, a revision of IEEE Std 323-1983, is the result of a review of IEEE Std 323-1983 and present practices in equipment qualification. This revision incorporates current practices and lessons learned from the implementation of previous versions of this standard by the nuclear industry.

Several issues are clarified or changed in this revision:

— This standard defines the methods for equipment qualification when it is desired to qualify equipment for the applications and the environments to which it may be exposed. This standard is generally utilized for qualification of Class 1E (safety-related electric) equipment located in harsh environments, and for certain post-accident monitoring equipment, but it may also be utilized for the qualification of equipment in mild environments. The documentation requirements are, however, more rigorous for equipment located in a harsh environment.

— The term design basis event has been generally used instead of the acronyms DBE, DBA, LOCA, and HELB, and the term design basis accident in order to reduce the complexity of the text.

— Seismic events are identified as design basis events.

— The test margins have been updated to better identify the parameters that achieve test margin on design basis event profiles. Since quantitative margin can be adequately identified by increases in temperature, pressure, radiation, and operating time, the performance of two transients is no longer recommended.

— New digital systems and new advanced analog systems may require susceptibility testing for EMI/ RFI and power surges, if the environments are significant to the equipment being qualified. Since existing instrument and control (I&C) systems were less vulnerable and have the benefit of successful operation under nuclear power plant EMI/RFI and power surge environments, qualification to EMI/RFI and power surges was not previously significant enough to be considered in environmental equipment qualification. As existing I&C equipment in nuclear power plants may be replaced with computer-based digital I&C systems or advanced analog systems, these new technologies may exhibit greater vulnerability to the nuclear power plant EMI/RFI and power surges environments. Documents such as NUREG/CR-5700-1992 [B32], a NUREG/CR-5904-1994 [B33], NUREG/CR- 6384-1996, Volumes 1 and 2 ([B34], [B35]), NUREG/CR-6406-1996 [B36], NUREG/CR-6579- 1998 [37], and NRC IN 94-20 [B31] have documented the environmental influence of EMI/RFI and power surges on safety-related electric equipment. Guidelines for ensuring electromagnetic compatibility of safety systems can be found in IEEE Std 603 ™ -1998 and IEEE Std 7-4.3.2 ™ -2003. b

— An important concept in equipment qualification is the recognition that significant degradation could be caused by aging mechanisms occurring from the environments during the service life, and therefore safety-related electric equipment should be in a state of degradation prior to imposing design basis event simulations. Previous versions recognized that the period of time for which acceptable performance was demonstrated is the qualified life. The concept of qualified life continues in this revision. This revision also recognizes that the condition of the equipment for which acceptable performance was demonstrated is the qualified condition. Thus, new license renewal and life extension options are available by assuring that qualified equipment continues to remain in a qualified condition.

Industry research in the area of equipment qualification and decades of its application have greatly benefited this standard. Future activities of the working group to update this standard will consider the following:

— Risk-informed approaches and impact of condition monitoring, performance, safety function assessment, and qualified life precision.

— Significance of refinements in aging mechanisms, equipment sealing, interfaces, extrapolation, similarity, test sequence and parameters (such as ramp rates, time duration, timing of spray initiation and its duration), and qualification documentation.


This standard was prepared by Working Group (SC 2.1) of the Subcommittee on Qualification (SC 2) of the Nuclear Power Engineering Committee of the IEEE Power Engineering Society. At the time of completion, SC 2.1 had the following membership:

James F. Gleason, Chair

At the time this revised standard was completed, the Nuclear Power Engineering Committee/Subcommittee on Qualification (SC 2) had the following membership:

Satish K. Aggarwal, Chair

Satish K. Aggarwal

Anup K. Behera

Thomas Brewington

Nissen M. Burstein

Mike Dougherty

Quang H. Duong

Wells D. Fargo

Artur J. Faya

Christopher M. Gleason

Patrick Gove

Tom Hencey

Jerrell C. Henley

David A. Horvath

Serena A. Jagtiani-Krause

Sushant Kapur

Byung-Ryung Koh

Henry Leung

Robert J. Lofaro

Bruce M. Lory

Edward Mohtashemi

Nathalie Nadeau

Paul Shemanski

John Wheless

John White

Michael J. Wylie

Javier Alonso

Bohumil Bartonicek

P. D. Baughman

Anup K. Behera

Brij Bharteey

Thomas Brewington

Candace Brooks

Rufus A. Brown

Nissen M. Burstein

Craig R. Butcher

Steve Casadevall

Garry V. Chapman

Marty Chipkin

Jeff Chivers

Sun Y. Choi

James M. Dean

Liviu N. Delcea

Dennis E. Dellinger

Phillip DiBenedetto

Quang H. Doung

Frank Drumm

Jeffrey S. Esterman

Keith Evans

Wells D. Fargo

Artur J. Faya

Robert Francis

James F. Gleason

Patrick Gove

William L. Hadovski

Peter Helander

Jerrell C. Henley

Thomas R. Henry, III

David A. Horvath

Craig S. Irish

Serena A. Jagtiani-Krause

Sushant Kapur

Mohsin Khan

Gene R. Kopecky

Jacob M. Kulangara

Thoma Kurt

Henry Leung

Victor Loczi

Robert J. Lofaro

Bruce M. Lory

Darin R. Martin

Wolfgang Michel

Todd Milton

Edward Mohtashemi

Carole Monchy-Leroy

Bill Newell

James Parello

Janez Pavsek

Daniel J. Pomerening

John M. Richards

Zoltan R. Rosztoczy

Fred Roy

Steve Sandberg

Glen E. Schinzel

Roderick Simms

Kjell Spang

Richard G. Starck

Marek Tengler

Gary Toman

Marco Van Uffelen

Laszlo Varga

Carl Weber

John Wheless

John White

Richard T. Woods

Toshio Yamamoto

The following members of the balloting committee voted on this standard. Balloters may have voted for approval, disapproval, or abstention.

When the IEEE-SA Standards Board approved this standard on 11 September 2003, it had the following membership:

Don Wright, Chair

Howard M. Frazier, Vice Chair

Judith Gorman, Secretary

*Member Emeritus

Also included are the following nonvoting IEEE-SA Standards Board liaisons:

Alan Cookson, NIST Representative

Satish K. Aggarwal, NRC Representative

Savoula Amanatidis

IEEE Standards Managing Editor


This standard describes the basic requirements for qualifying Class 1E equipment and interfaces that are to be used in nuclear power generating stations. The principles, methods, and procedures described are intended to be used for qualifying equipment, maintaining and extending qualification, and updating qualification, as required, if the equipment is modified. The qualification requirements in this standard, when met, demonstrate and document the ability of equipment to perform safety function(s) under applicable service conditions including design basis events, reducing the risk of common-cause equipment failure. This standard does not provide environmental stress levels and performance requirements.

NOTE—Other IEEE standards that present qualification methods for specific equipment, specific environments, or specific parts of the qualification program may be used to supplement this standard, as applicable. Annex A lists other standards related to equipment qualification.