Document: NRC Regulatory Guide
Document ID: d6326081-f430-476d-8098-4edf00868dd9
Document Type: regulatory_guide
Title: Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1267 , Proposed Revision 2 01/2003 – DG-1123 , Proposed Revision 1 08/1996 – DG-1054 , Proposed Revision 0 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1031/ML103160431.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.168
CFR Part: 
CFR Title: 

Content:
REVIEWS, AND AUDITS 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 verification, validation, reviews, and audits for digital computer software used in safety systems of nuclear power plants. The regulatory framework that the NRC has established for nuclear power plants consists of a number of regulations and supporting guidelines applicable to verification, validation, reviews, and audits for digital 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. 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, such as designing, purchasing, installing, testing, operating, maintaining, or modifying, that affect the safety-related functions of such structures, systems, and components. In 10 CFR 50.55a(a)(1), the NRC requires, in part, that systems and components be designed, fabricated, erected, tested, and inspected to quality standards commensurate with the