IEEE 279-1971

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IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations

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New IEEE Standard - Inactive-Withdrawn. These criteria established minimum requirements for the safety-related functional performance and reliability of protection systems for stationary land-based nuclear reactors producing steam for electric power generation. Fulfillment of these requirements does not necessarily fully establish the adequacy of protective system functional performance and reliability. On the other hand, omission of any of these requirements will, in most instances, be an indication of system inadequacy. For purposes of these criteria, the nuclear power generating station protection system encompasses all electric and mechanical devices and circuitry (from sensors to actuation device input terminals) involved in generating those signals associated with the protective function. These signals include those that actuate reactor trip and that, in the event of a serious reactor accident, actuate engineered safeguards such as containment isolation, core spray, safety injection, pressure reduction, and air cleaning.


SDO	IEEE: Institute of Electrical and Electronics Engineers
Document Number	279
Publication Date	Nov. 30, 1970
Language	en - English
Page Count	12
Revision Level
Supercedes
Committee	Nuclear Power Engineering Committee

Publish Date	Document Id	Type	View
Nov. 30, 1970	279-1971	Revision
Aug. 30, 1968	279-1968	Revision

SDO	Document	Title
IEEE	IEEE 279	IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
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IEEE 279-1971

IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations

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IEEE 279-1971

IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations

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