Document: NRC Regulatory Guide
Document ID: 12dd3f35-6baa-4f6a-8372-84c90ef96a91
Document Type: regulatory_guide
Title: Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1207 , Proposed Revision 1 08/1996 – DG-1056 , Proposed Revision 0 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0833/ML083370243.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.170
CFR Part: 
CFR Title: 

Content:
he safety-related functions of such systems and components. In 10 CFR 50.55a(a)(1) the regulations require, in part, that systems and components be designed, fabricated, erected, tested, and inspected to quality standards commensurate with the safety function to be performed. 10 CFR 50.55a(h) requires that reactor protection and safety systems satisfy the criteria in DG-1207, Page 2 Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations” (Ref. 2), including a correction sheet dated January 30, 1995, 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 and that it will perform the required safety function. The guidance on the safety systems equipment employing digital computers, and programs or firmware requires quality standards in the use of software test documentation. This regulatory guide endorses IEEE Std. 829-2008, “IEEE Standard for Software and System Test Documentation,” (Ref. 4), with the exceptions stated in the regulatory positions. IEEE Std. 829-2008 describes methods that the NRC considers acceptable for use in complying with NRC regulations for achieving high functional reliability and design quality in the software used in safety systems.1 In particular, the methods are consistent with the GDC in Appendix A to 10 CFR Part 50 and the criteria for quality assurance programs in Appendix B to 10 CFR Part 50 as they apply to the documentation of software testing activities. The criteria in Appendices A and B apply to systems and related quality assurance processes, and the requirements extend throughout the life cycle of the protection system especially when