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IEEE 497-2016

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

Standard by IEEE, 2016

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  • Language: English
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  • Language: English
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About This Item

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IEEE 497-2016 is the standard for accident monitoring instrumentation used in nuclear power generating stations. It addresses the technical criteria for instrumentation that supports detection, measurement, and indication of abnormal or accident conditions in plant environments where reliable data is critical. By defining expectations for these systems, the document helps support consistent engineering practice, safer operation, and more dependable response during events that may affect nuclear plant safety.

IEEE 497-2016 overview

This standard focuses on the instrumentation needed to monitor accident conditions in nuclear power generating stations, with attention to the performance and design expectations relevant to power, energy, and nuclear engineering applications. IEEE 497-2016 is used as a technical reference for selecting, evaluating, and applying monitoring equipment intended to remain useful when plant conditions become challenging. It is especially relevant where accurate indication and dependable operation support operator awareness and plant safety decision-making.

Typical use cases

IEEE 497-2016 is typically referenced when engineering accident monitoring channels for nuclear plant systems that must track key process variables during abnormal events. It may be used in the specification of sensors, signal paths, displays, and supporting equipment associated with radiation, temperature, pressure, level, or related plant conditions. The standard is also useful during design reviews, procurement, and verification of instrumentation intended for emergency response and post-accident assessment in nuclear power generating stations.

Why this standard matters

Accident monitoring instrumentation must provide trustworthy information when normal operating assumptions no longer apply, and IEEE 497-2016 helps define that technical basis. Using a recognized standard supports consistency across design, documentation, and testing, which can reduce ambiguity in specification and review. For organizations responsible for nuclear facilities, it can also help strengthen compliance efforts, improve confidence in instrument performance, and lower the risk of incomplete or unsuitable monitoring capability during accident conditions.

  • Accident monitoring criteria
  • Nuclear plant instrumentation
  • Design and verification guidance
  • Safety-related indication needs
  • Engineering and procurement reference
SKU: 98b6a49343fd

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

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