Document: NRC Regulatory Guide
Document ID: 87c94eb7-1d88-4510-b85b-196ad319d0ae
Document Type: regulatory_guide
Title: Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1208 , Proposed Revision 1 08/1996 – DG-1057 , Proposed Revision 0 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1031/ML103120751.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.171
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Content:
GITAL 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 with respect to the software unit testing of 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 software unit testing of 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 systems and components important to safety will satisfactorily perform their safety functions. GDC 21, “Protection System Reliability and Testability,” requires, in part, that the protection system be designed for high functional reliability. 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 for systems and components that prevent or mitigate the consequences of postulated accidents must meet. In particular, in addition to the systems and components that directly prevent or mitigate the consequences of postulated accidents, 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. In 10 CFR 50.55a(a)(1) requires, in part, that systems and components be designed, fabricated, erected, tested, and inspected to quality standards