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          This standard establishes application criteria for programmable digital computer systems in safety systems of nuclear power generating stations. These criteria are established to provide a means for promoting safe practices for design and evaluation of safety system performance and reliability. However, adhering to these will not necessarily fully establish the adequacy of any safety system's functional performance and reliability; nonetheless, omission of any of these criteria will, in most instances, be an indication of safety system inadequacy. This standard does not provide specific requirements for preparation or content of software quality assurance plans.<br />\n
          \t\t\t\t<br />\n
          This standard establishes application criteria for programmable digital computer systems used in safety systems for nuclear power generating stations by expanding the quality and equipment qualification requirements of IEEE Std 603-1980, &quot;Standard Criteria for Safety Systems for Nuclear Power Generating Stations,&quot;' to encompass software design, soft- ware implementation, and computer system validation. Figure 1 illustrates the inter- relationships among the various processes in the application of programmable digital computer systems in safety systems for nuclear power generating stations. This standard does not consider site installation, site testing, or maintenance of the computer system.
          """
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