Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

In 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," paragraph 55a(a)(1) requires, in part,1 that systems and components be designed, tested, and inspected to quality standards commensurate with the safety function to be performed. Criterion 1, "Quality Standards and Records," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part,1 that appropriate records of the design and testing of systems and components important to safety be maintained by or under control of the nuclear power unit licensee throughout the life of the unit. Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 describes criteria that a quality assurance program for systems and components that prevent or mitigate the consequences of postulated accidents must meet.