IEEE 497-2002 pdf download IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
1. Overview
1.1 Scope
The criteria contain the functional and design requirements for accident monitoring instrumentation fornuclear power generating stations. This standard is intended for new plant designs. The guidance provided inthis standard may also prove useful for operating nuclear power stations desiring to perform desigrmodifications or design basis evaluations.
This standard contains guidance for the selection of variables and establishes design and performancerequirements. Guidance on the use of portable instrumentation and defining various display alternatives fotaccident monitoring instrumentation is also included.
1.2 Purpose
The purpose of IEEE Std 497″2002 is to direct the user in selecting and categorizing post accidentmonitoring variables; establishing design requirements; and establishing performance requirements. Iprovides guidance on the use of portable instrumentation and various display alternatives for accidentmonitoring instrumentation.
1.3 Application
This standard applies to accident monitoring instrumentation intended for use during the following controlroom operations:
aAs required for preplanned operator action related to accident mitigation6For assessing plant conditions, safety system performance and making decisions related to plantresponse to abnormmal events
For achieving and maintaining safe shutdown following an accidentd
This standard does not apply to accident monitoring instrumentation that is intended solely for historicarecording or solely for maintenance purposes. This standard also does not apply to instrumentation used tosupport contingency actions in emergency operating procedures or to instrumentation required to supportplant shutdown from outside the control room.
2. References
This standard shall be used in conjunction with the following publications, When the following standards aresuperceded by an approved revision, the revision shall apply.
ASME NQA-1-2001, Quality Assurance Requirements for Nuclear Facility Applications.
IEEE Std 7-4.3.2″-1993,IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear PowerGenerating Stations.2, 3
EEE Std 308″-2001, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power GeneratingStations.
IEEE Std 323″-1983 (R1996), IEEE Standard for Qualifying Class 1E Equipment for Nuclear PowerGenerating Stations.
IEEE Std 344″-1987 (R1993), IEEE Recommended Practice for Seismic Qualification of Class 1EEquipment for Nuclear Power Generating Stations.
IEEE Std 352″-1987 (R1999), IEEE Guide for General Principles of Reliability Analysis of Nuclear PowerStations.
IEEE Std 379″-2000 IEEE Standard Application of the Single-Failure Criterion to Nuclear PowerGenerating Station Safety Systems.
IEEE Std 384″-1992 (R1998), IEEE Standard Criteria for Independence of Class 1E Equipment andCircuits.
IEEE Std 577-1976 (R2001), IEEE Standard Requirements for Reliability Analysis in the Design andOperation of Safety Systems for Nuclear Power Generating Stations.
IEEE Std 603″-1998 IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
EEE Std 1023″-1988,1EEE Guide for Application of Human Factors Engineering to Systems, Equipmentand Facilities of Nuclear Power Generating Stations.
3. Definitions
The following definitions apply specifically to this standard. For other definitions, see The AuthoritativeDictionary ofIEEE Standards Terms, Seventh Edition (B4].
3.1 accident analysis licensing basis: The portions of the licensing basis documentation that describe thedesign basis events (including anticipated operational occurrences), the thermal-hydraulic response of theplant, and the subsequent response of the safety systems.
IEEE 497-2002 pdf download
PS:Thank you for your support!
