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.
- Standard Committee
- PE/NPEC - Nuclear Power Engineering Committee
- Status
- Superseded Standard
- PAR Approval
- 2009-06-17
- Superseded by
- 497-2016
- Superseding
- 497-2002
- Board Approval
- 2010-09-30
- History
-
- ANSI Approved:
- 2011-06-07
- Published:
- 2010-11-10
Working Group Details
- Society
- IEEE Power and Energy Society
- Standard Committee
- PE/NPEC - Nuclear Power Engineering Committee
- Working Group
-
WG_6.1 - Monitoring Instrumentation Working Group
- IEEE Program Manager
- Christian Orlando
Contact Christian Orlando - Working Group Chair
- Cherie Paugh
Other Activities From This Working Group
Current projects that have been authorized by the IEEE SA Standards Board to develop a standard.
P497
Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
This standard contains the functional and design criteria for accident monitoring instrumentation for new nuclear power plant designs and design modifications for nuclear power generating stations.
Standards approved by the IEEE SA Standards Board that are within the 10-year lifecycle.
497-2016
IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
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.
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.
These standards have been replaced with a revised version of the standard, or by a compilation of the original active standard and all its existing amendments, corrigenda, and errata.
497-2002
IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
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.
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.
These standards have been removed from active status through a ballot where the standard is made inactive as a consensus decision of a balloting group.
No Inactive-Withdrawn Standards
These standards are removed from active status through an administrative process for standards that have not undergone a revision process within 10 years.
No Inactive-Reserved Standards