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:
stems, 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 safety function to be performed. The regulations in 10 CFR 50.55a(h) require that reactor protection and safety systems satisfy DG-1267, Page 2 the criteria in Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations” (including a correction sheet dated January 30, 1995) (Ref. 2), or in IEEE Std. 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations” (Ref. 3). These criteria shall be part of the evaluation of the recognized quality codes and standards selected for their applicability, adequacy and sufficiency and shall be supplemented or modified as needed to assure a quality product that will perform the required safety function. The guidance on the safety systems equipment employing digital computer software or firmware requires quality standards for verifying and validating computer software used in safety systems of nuclear power plants. This regulatory guide endorses IEEE Std. 1012-2004, “IEEE Standard for Software Verification and Validation” (Ref. 4), and IEEE Std. 1028-2008, “IEEE Standard for Software Reviews and Audits” (Ref. 5). IEEE Std. 1012-2004, with the exceptions stated in the regulatory positions, describes a method acceptable to the NRC staff for complying with the NRC’s regulations for promoting high functional reliability and design quality in software used in safety systems.1 In particular, the method is consistent with GDC 1 in Appendix A to 10 CFR Part 50 and the criteria for quality assurance programs in Appendix B, as they apply to software verification and validation (V&V). The criteria of Appendices A and B apply to systems and related quality assurance processes, and the requirements also