IEEE 497-2016 - IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

Standard

Active

Standard Details

Established in this standard are criteria for variable selection, performance, design, and qualification of accident monitoring instrumentation for anticipated operational, design basis events and severe accidents.

Standards Committee	PE/NPE - Nuclear Power Engineering
Status	Active
Board Approval	2016-05-15
History	Published Date:2016-07-29

Additional Resources Details

PAR	Approved PAR

Working Group Details

Working Group	WG_6.1 - Monitoring Instrumentation Working Group
Working Group Chair	Cherie Paugh
Standards Committee	PE/NPE - Nuclear Power Engineering
Society	IEEE Power and Energy Society
IEEE Program Manager	Christian Orlando
Existing Standards	Superseded IEEE 497-2002/Cor 1-2007 - IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations - Corrigendum 1: Incorporation of User Feedback through 2005 This corrigendum incorporates user feedback by providing editorial and minor technical corrections to IEEE Std 497-2002. The corrigendum also incorporates published errata into the document. The stakeholders for the project are 1) organizations designing new nuclear power generating stations, 2) owners of operating nuclear power generating stations, and 3) regulatory agencies.
	Superseded IEEE 497-2010 - IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations Criteria are established in this standard for variable selection, performance, design, and qualification of accident monitoring instrumentation, and include requirements for display alternatives for accident monitoring instrumentation, documentation of design bases, and use of portable instrumentation.
	Active IEEE/IEC 63113-2021 - IEC/IEEE International Standard--Nuclear facilities--Instrumentation important to safety--Spent fuel pool instrumentation This document provides criteria for spent fuel pool instrumentation for nuclear power generating stations and other nuclear facilities. The document applies to water filled spent fuel pools where the water volume is necessary to prevent a release of fission products that exceeds allowed operational limits.