RG 1.168核电厂安全系统中使用的数字计算机软件的验证、确认、审查和监查 2004.pdfVIP

U.S. NUCLEAR REGULATORY COMMISSION Revision 1 February 2004 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.168 (Draft was issued as DG-1123) VERIFICATION, VALIDATION, REVIEWS, AND AUDITS FOR DIGITAL COMPUTER SOFTWARE USED IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS A. INTRODUCTION In 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” paragraph 50.55a(a)(1) requires, in part, that structures, systems, and components be designed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. In Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50, Criterion 1, “Quality Standards and Records,” requires, in part, that a quality assurance program be established and implemented in order to provide adequate assurance that structures, systems, and components important to safety will satisfactorily perform their safety functions. Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 describes criteria that must be met by a quality assurance program for structures, systems, and components that prevent or mitigate the consequences of postulated accidents. In particular, besides the structures, systems, and components that directly prevent or mitigate the consequences of postulated accidents, the criteria of Appendix B also apply to all activities affecting the safety-related functions of such struct