ANSI/IEEEStd603-1980 (AMERKAN NATIONAL (Revi ISTANDARD IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations IEEE Std 603-1980 Published by The Institute of Electrical and Electronics Engineers, Inc 345 East 47th Street, New York, NY 10017, USA November 24,1980 SHO7849 IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations 1. Scope Figure 4 illustrates typical equipment exam- ples for each portion of the matrix diagram. As The criteria contained in this standard estab. shown, some components can be fitted into lish minimum functional and design require- more than one category depending on the com- ments for safety systems for nuclear power ponent's use. Figure 5 illustrates where criteria for each stations. The criteria herein are generating applicable to the power, instrumentation, and portion of the matrix can be found in this stan- control portions of the safety systems. To dard. satisfy the criteria in this standard, interface 1.2 Application. The e safety system criteria requirements may be imposed on the other established herein are to be applied to those portions of the safety system as shown in Fig 1. systems required to protect the public health Safety system functional and design criteria and safety by functioning to mitigate the con- are also contained in other standards. I sequences of design basis events. However, this 1.1 Illustration. Figure 3 illustrates the scope standard does not apply to all of the safety- of this standard in the form of a 3 X 3 matrix. related systems, structures, and equipment re- The labeling across the top of the matrix illus- quired for complete plant safety, for example, trates that the safety systems can be subdivided fire protection systems. The electrical portion into the three general elements of sense and of the safety systems are classified as Class 1E. command features, execute features, and power These general elements represent a sources. grouping of devices which provides similar per- formance characteristics for many discrete 2. Definitions safety functions. The labeling on the left side of the matrix illustrates that the safety systems can also be subdivided into the three opera- The definitions in this section establish the tional elements of reactor trip system and engi- meaning of words in the context of their use in neering safety features, auxiliary supporting this standard. features, and other auxiliary features. When acceptable. Demonstrated to be adequate by viewing an entire row of the matrix, it can be the safety analysis of the station. seen that an operational element may form a system. actuated equipment. The assembly of prime Illustrating the scope of this standard in movers and driven equipment used to accom- matrix form shows that each operational ele- plish a protective action. ment contains one or more general elements. NOTE: Examples of prime movers are: turbines, motors, This matrix should not be interpreted to mean and solenoids. Examples of driven equipment are: con- that every operational element must contain all trol rods, pumps, and valves. of the general elements or that a particular gen- actuation device. A component or assembly of eral element is limited to application in only components that directly controls the motive one operational element. (electricity, compressed air, hydraulic power ( fluid, etc) for actuated equipment. 1See Fig 2 for IEEE Stds, ANSI/ANS 4.1-1978, ANSI N18.2-1973,ANSI N18.2a-1975,ANSI/ANS 52.1-1978, NOTE: Examples of actuation devices are : circuit break- ANSI N213-1975, and ANSI N214-1976. ers, relays, and pilot valves. 9