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IEEE 497-2010

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
Available format(s)

PDF

Superseded date

07-29-2016

Language(s)

English

Published date

11-10-2010

1. Overview
2. Normative references
3. Definitions
4. Selection criteria
5. Performance criteria
6. Design criteria
7. Qualification criteria
8. Display criteria
9. Quality assurance
Annex A (informative) - Accident monitoring instrument
                        channel accuracy
Annex B (informative) - Examples of monitoring channel
                        displays
Annex C (informative) - Operational state diagram
Annex D (informative) - Bibliography

This standard contains the functional and design criteria for accident monitoring instrumentation for nuclear power generating stations.

Committee
Nuclear Power Engineering Committee
DevelopmentNote
Supersedes IEEE DRAFT 497. (02/2005) Also numbered as IEC 63147. (12/2017)
DocumentType
Standard
ISBN
978-0-7381-6937-8
Pages
34
PublisherName
Institute of Electrical & Electronics Engineers
Status
Superseded
SupersededBy
Supersedes

IEEE 1023-2004 REDLINE IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities
ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
IEC TR 63123:2017 Nuclear power plants - Instrumentation, control and electrical power systems - Guidance for the application of IEC 63147:2017/IEEE Std 497™ -2016 in the IAEA / IEC framework
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IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
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IEC 60880:2006 Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions
IEEE 344-2004 IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations
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IEEE 379-2000 IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
IEC 60780:1998 Nuclear power plants - Electrical equipment of the safety system - Qualification
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ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
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IEEE 1023-2004 REDLINE IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities
IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
IEEE 577-2004 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities

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