Document: NRC Regulatory Guide
Document ID: c6321e39-3d1b-40a6-ace3-8c6a0c54e2cd
Document Type: regulatory_guide
Title: Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1210 , Proposed Revision 1 08/1996 – DG-1059 , Proposed Revision 0 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1031/ML103120727.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.173
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Content:
YCLE PROCESSES 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 NRC regulations on the development of software life-cycle processes for digital computer software used in the 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 the development of software life-cycle processes for digital computer software. In Title 10, of the Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities," (Ref. 1), 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. Also in 10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants,” the General Design Criterion (GDC) 1, “Quality Standards and Records,” requires, in part, that quality standards be established and implemented to provide adequate assurance that 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,” of 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, in addition to the systems and components that directly prevent or mitigate the consequences of postulated accidents, the Appendix B criteria also apply to all activities, including design, purchasing, installation, testing, operation, maintenance, or modification, that affect the safety-related functions of such systems and components. DG-1210, Page 2 In 10 CFR 50.55a(a)(1), the NRC