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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CFR Title: 

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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 the safety function to be performed. 10 CFR 50.55a(h) require licensees to satisfy the criteria for reactor protection systems in Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 603-1991, “IEEE Standard DG-1209, Page 2 Criteria for Safety Systems for Nuclear Power Generating Stations,” issued 1991 (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,” issued 1971 (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 for safety system equipment employing digital computers and programs or firmware requires the use of a quality standard for the development of software and firmware requirement specifications. This regulatory guide endorses IEEE Std. 830-1998, “IEEE Recommended Practice for Software Requirements Specifications,” issued in 1998 and reaffirmed in 2009 (Ref. 4), with the exceptions stated in the regulatory positions. IEEE Std. 830-1998 describes methods that the NRC staff considers acceptable for use in complying with the NRC regulations for achieving high functional reliability and design quality in software used in safety systems.1 In particular, the methods are consistent with the previously cited GDC and the criteria for quality assurance programs in Appendix B to 10 CFR Part 50 as they apply to the development of SRSs. The criteria of Appendix A and Appendix B to 10 CFR Part 50 apply to systems and related quality standards and quality assurance processes as well