Document: NRC Regulatory Guide
Document ID: 2980f2d9-2e7d-4afa-9e1f-a8abe5fb7507
Document Type: regulatory_guide
Title: Software Requirement Specifications for Digital Computer Software and Complex Electronics Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1209 , Proposed Revision 1 08/1996 – DG-1058 , Proposed Revision 0 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1030/ML103080963.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.172
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Content:
CATIONS FOR DIGITAL COMPUTER SOFTWARE AND COMPLEX ELECTRONICS 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 software requirement specifications (SRSs) 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 SRSs 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, requires, in part, that systems and components be designed, tested, and inspected to quality standards commensurate with the safety function to be performed, while the nuclear power unit licensee maintain, or control the maintenance of, appropriate records on the design and testing of 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 a quality assurance program must meet for systems and components that prevent or mitigate the consequences of postulated accidents. 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 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