IEEE 603-1998

The criteria contained in this standard establish minimum functional and design requirements for the power, instrumentation, and control portions of safety systems for nuclear power generating stations. (No change from existing revision). The safety system criteria established herein are to be applied to those systems required to protect the public health and safety by functioning to prevent or mitigate the consequences of design basis events. (No change from existing revision). The standard will be revised to clarify the application to computer based safety systems and to advanced nuclear power generating station designs. Clarification will also be considered in the use of the term "Class 1E" and in the treatment of EMI/RFI. Consideration will be given to IEEE documents issued or revised since issuance of Standard 603-1991. Revision Standard - Superseded. Minimum functional and design criteria for the power, instrumentation, and control portions of nuclear power generating station safety systems are established in this standard. The criteria are to be applied to those systems required to protect the public health and safety by functioning to mitigate the consequences of design basis events. The intent is to promote safe practices for design and evaluation of safety system performance and reliability. Although the standard is limited to safety systems, many of the principles may have applicability to equipment provided for safe shutdown, post accident monitoring display instrumentation, preventative interlock features, or any other systems, structures, or equipment related to safety.