IEEE 497-2010 pdf free.IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations.
IEEE 497 contains the functional and design criteria for accident monitoring instrumentation for nuclear power generating stations. This standard is intended for new plant designs and for operating nuclear power generating stations desiring to perform design modifications.
1.2 Purpose
The purpose of this standard is to establish selection, design. performance, qualification and display criteria for accident monitoring instrumentation. It provides guidance on the use of portable instrumentation and examples of accident monitoring display con figurations.
1.3 Application
This standard applies to accident monitoring instrumentation intended for use during the following control room operations:
— As required for planned operator action related to accident mitigation
— For assessing plant conditions, safety system performance, and making decisions related to plant response to abnormal events
— For achieving and maintaining sale shutdown following an accident
This standard does not apply to the following:
— Accident monitoring instrumentation that is intended solely for historical recording or solely for maintenance purposes
— Instrumentation used to support contingency actions that are not in the plant accident analysis licensing basis
— Instrumentation required to support plant shutdown from outside the control room
2. Normative references
The following referenced documents are indispensable for the application of this document (i.e., they must be understood and used, so each referenced document is cited in text and its relationship to this document is explained). For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments or corrigenda) applies.
For thc purposes of this documcnt. the following terms and definitions apply. The IEEE Standards 1)kiionarv: Glossary of Terms & Definitions should be referenced for terms not detined in this clause.4
accident analysis licensing basis: The portions of the licensing basis documentation that describe the design basis events (including anticipated operational occurrences), the thermal-hydraulic response of the nuclear power generating station, and the subsequent response of the safety systems.
accurac: A measure of the degree by which the actual output of a device approximates the output of an ideal device nominally performing the same function.
analog sensor: The portion of a channel that responds to changes in a plant vanahic or condition and converts the measured process variable into an electric. optic. or pneumatic signal.
anticipated operational occurrence (AOO): Those conditions of normal operations thai arc expected to occur one or more times during the life of the nuclear power generating station and include, but are not limited to, loss of power to all recirculation pumps. tripping of the turbine generator set, isolation of the main condenser, and loss of all oftsite power.
ausiliarv supporting features: Systems or components that provide services (such as cooling, lubrication. and energy supply) required for the safety systems to accomplish their safety functions.
common cause failure: Multiple failures of stnictures, systems, or components as a result of a single phenomenon.
contingency actions: Alternative actions taken to address unexpected responses of the plant or conditions beyond its licensing basis (for example. actions taken for multiple equipment failures).
current ‘.alue: That magnitude of a variable that is associated with the present time and is available for display within the response lime limits of an information display channel.
design basis event (DBE): Postulated events specified by the safety analysis for the station to establish the acceptable performance requirements of the structures and systems.
digital sensor: A device used for measuring process variables that operates on the basis of discrete numerical techniques in which the measured variables arc represented by coded pulses or states.
display channel: An arrangement of electrical and mechanical components or modules, or both, from the measured process variable to the display device as required to sense, process. and display conditions within the nuclear power generating station.IEEE 497 pdf free download.