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Released: 31.12.1987
IEEE C37.105-1987 - IEEE Standard for Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations
IEEE Standard for Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations
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Standard number: | IEEE C37.105-1987 |
Released: | 31.12.1987 |
ISBN: | 978-0-7381-0902-2 |
Pages: | 24 |
Status: | Active |
Language: | English |
DESCRIPTION
IEEE C37.105-1987
This standard describes the basic principles, requirements, and methods for qualifying Class 1E protective relays and auxiliaries such as test and control switches, terminal blocks, and indicating lamps for applications in nuclear power generating stations. When properly employed it can be used to demonstrate the design adequacy of such equipment under normal, abnormal, design basis event and post design basis event conditions in accordance with ANSI/IEEE Std 323-1983 [5].1 When protective relays and auxiliaries are located in areas not subject to harsh environments, environmental qualification is not required. Protective relays and auxiliaries located inside primary containment in a nuclear power generating station present special conditions beyond the scope of this document. The qualification procedure presented is generic in nature. Other methods may be used at the discretion of the qualifier, provided the basic precepts of ANSI/IEEE Std 323-1983 [5] are satisfied.The purpose of this standard is to 1) Define specific qualification methods for Class 1E protective relays and auxiliaries in accordance with the more general qualification requirements of ANSI/IEEE Std 323-1983. 2) Provide guidance in establishing a program for demonstrating the design adequacy of Class 1E protective relays and auxiliaries in nuclear power generating stations applications.
New IEEE Standard - Superseded. This IEEE Standards product is part of the C37 family on Switchgear, Substations and Protective Relays. The basic principles, requirements, and methods for qualifying Class 1E protective relays and auxiliaries, such as test and control switches, terminal blocks, and indicating lamps, for applications in nuclear power generating stations are described. The qualification procedure is generic in nature and can be used to demonstrate the design adequacy of such equipment under normal, abnormal, design-basis-event, and post-design-basis-event conditions. Protective relays and auxiliaries located inside primary containment areas in a nuclear power generating station are not covered.