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IEEE 603-1977

Historical Revision

IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Systems

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New IEEE Standard - Superseded. This standard establishes functional and design criteria for nuclear power generating station "safety systems," that is, that collection of systems required to minimize the probability and magnitude of release of radioactive material to the environment by maintaining plant conditions within the allowable limits established for each design basis event. These criteria are established to provide a means of promoting safe practices for design and evaluation of safety system performance and reliability. The criteria herein represent an acceptable basis for ascertaining the adequacy of safety system performance and reliability. Adherence to these criteria does not necessarily fully establish the adequacy of safety system functional performance and reliability. However, omission of any of these criteria will, in most instances, be an indication of safety system inadequacy.
The criteria contained in this standard establish minimum functional and design requirements for safety systems for nuclear power generating stations. The safety system is the collection of systems required to minimize the probability and magnitude of release of radioactive material to the environment by maintaining plant conditions within the allowable limits established for each design basis event. Safety system functional and design criteria are also contained in other standards.

SDO IEEE: Institute of Electrical and Electronics Engineers
Document Number 603
Publication Date Aug. 15, 1977
Language en - English
Page Count 22
Revision Level
Supercedes
Committee
Publish Date Document Id Type View
Dec. 7, 2018 603-2018 Revision
Nov. 5, 2009 603-2009 Revision
Nov. 20, 1998 603-1998 Revision
Dec. 31, 1991 603-1991 Revision
Nov. 24, 1980 603-1980 Revision
Aug. 15, 1977 603-1977 Revision