Document: NRC Regulatory Guide
Document ID: 3eb179d3-5491-407d-8b0e-eed083d58a17
Document Type: regulatory_guide
Title: Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1206 , Proposed Revision 1 08/1996 – DG-1055 , Proposed Revision 0 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1032/ML103200044.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.169
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Content:
LANS FOR DIGITAL COMPUTER SOFTWARE USED IN SAFETY SYSTEMS OF NUCLEAR POWER PLANTS A. INTRODUCTION This guide describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for use in complying with the NRC’s regulations with respect to configuration management plans for digital computer software used in the safety systems of nuclear power plants. The regulatory framework the NRC has established for nuclear power plants consists of a number of regulations and supporting guidelines applicable to configuration management plans for computer software. Title 10, of the Code of Federal Regulations, Part 50, “Domestic Licensing of Production and Utilization Facilities” (10 CFR Part 50) (Ref. 1), Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 1, “Quality Standards and Records,” requires, in part, that quality standards be established and implemented to provide adequate assurance that structures, systems, and components important to safety will satisfactorily perform their safety functions, and that the nuclear power unit licensee maintain or control appropriate records of the design and testing of structures, systems, and components important to safety 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 must be met by a quality assurance program for 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, such as designing, purchasing, installing, testing, operating, maintaining, or modifying, that affect the safety-related functions of such structures, systems, and components. Further, Criterion III, “Design Control,” of