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IEEE 497-2002

Historical Revision

IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

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Revision Standard - Superseded. Criteria for variable selection, performance, design, and qualification of accident monitoring instrumentation are established in this standard. Included requirements for display alternatives for accident monitoring instrumentation, documentation of design bases, and use of portable instrumentation.
The criteria contain the functional and design requirements for accident monitoring instrumentation for nuclear power generating stations. This standard is intended for new plant designs. The guidance provided in this standard may also prove useful for operating nuclear power stations desiring to perform design modifications or design basis evaluations. This standard contains guidance for the selection of variables and establishes design and performance requirements. Guidance on the use of portable instrumentation and defining various display alternatives for accident monitoring instrumentation is also included.
The purpose of IEEE Std 497 -2002 is to direct the user in selecting and categorizing post accident monitoring variables; establishing design requirements; and establishing performance requirements. It provides guidance on the use of portable instrumentation and various display alternatives for accident monitoring instrumentation.

SDO IEEE: Institute of Electrical and Electronics Engineers
Document Number 497
Publication Date Sept. 30, 2002
Language en - English
Page Count 32
Revision Level
Supercedes
Committee Nuclear Power Engineering Committee
Publish Date Document Id Type View
July 29, 2016 497-2016 Revision
Nov. 10, 2010 497-2010 Revision
Sept. 30, 2002 497-2002 Revision
March 31, 1981 497-1981 Revision
June 17, 1977 497-1977 Revision