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IEEE 497-2010

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

Standard by IEEE, 2010

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  • Availability: Immediate Download
  • Language: English
  • License Type: Single User
  • Updates: Not Included
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  • Language: English
  • License Type: Enterprise / Multi User
  • Updates: Included

About This Item

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IEEE 497-2010 is a technical standard for accident monitoring instrumentation at nuclear power generating stations, setting criteria that help ensure key measurements remain dependable during abnormal or emergency conditions. It is relevant to power and energy applications, with a clear focus on nuclear engineering and the systems used to detect, display, and support accident-related plant conditions. For projects, operations, and procurement, the standard provides a focused reference for instrument performance and safety-related planning.

About IEEE 497-2010

This standard addresses the criteria for accident monitoring instrumentation used in nuclear power generating stations, where reliable indication of important plant conditions can support response actions and engineering review. IEEE 497-2010 is concerned with the technical expectations for instrumentation that may be needed when normal operating conditions are disrupted. In practice, it serves as a reference for specifying, evaluating, and maintaining monitoring functions tied to nuclear plant safety and operational control. The document is useful where consistent requirements are needed across design and compliance work.

Where is IEEE 497-2010 used?

IEEE 497-2010 is typically used in nuclear power plant environments where accident monitoring signals are needed from plant systems, control rooms, and related safety instrumentation channels. It can apply to equipment and workflows involved in measuring reactor or containment conditions, supporting operator awareness, and documenting abnormal event data. The standard is most relevant to engineers, integrators, and reviewers working on instrumentation selection, system qualification, and plant modifications within the nuclear power sector.

Importance in practice

In practice, IEEE 497-2010 helps reduce ambiguity in how accident monitoring instrumentation should be considered, specified, and assessed for nuclear facilities. That matters because dependable monitoring supports safer decision-making, clearer compliance review, and more consistent engineering across projects and plant changes. For procurement and design teams, the standard can also help align technical expectations for performance and suitability under accident conditions. Using IEEE 497-2010 may contribute to better control of risk and stronger documentation.

  • Accident monitoring instrumentation criteria
  • Nuclear power generating station application
  • Plant safety and operator indication
  • Design, review, and compliance reference
SKU: 8fe967711965

  • Publication Date: 2010
  • Standard Status: Superseded
  • Publisher: IEEE
  • Subject: Power, Energy and Industry Applications; Nuclear Engineering
  • Official IEEE: Doi link
  • New Version Available: 497 (2016)
  • This Version: 497 (2010)
  • Previous Version: 497 (2007)
  • Previous Version: 497 (2002)
  • Previous Version: 497 (1981)
  • Previous Version: 497 (1977)

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