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Homepage>IEEE Standards>27 ENERGY AND HEAT TRANSFER ENGINEERING>27.120 Nuclear energy engineering>27.120.20 Nuclear power plants. Safety>IEEE 497-2002 - IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
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Released: 30.09.2002

IEEE 497-2002 - IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

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

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Standard number:IEEE 497-2002
Released:30.09.2002
ISBN:978-0-7381-3280-8
Pages:32
Status:Active
Language:English
DESCRIPTION

IEEE 497-2002

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.

Revision Standard - Superseded. Criteria for variable selection, performance, design, and qualification of accidentmonitoring instrumentation are established in this standard. Included requirements for displayalternatives for accident monitoring instrumentation, documentation of design bases, and use ofportable instrumentation.