Document: NRC Regulatory Guide
Document ID: c6321e39-3d1b-40a6-ace3-8c6a0c54e2cd
Document Type: regulatory_guide
Title: Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1210 , Proposed Revision 1 08/1996 – DG-1059 , Proposed Revision 0 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1031/ML103120727.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.173
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a method acceptable to the NRC staff for meeting a regulatory requirement as described in the specific regulatory guide. If a referenced standard has been neither incorporated into NRC regulations nor endorsed in a regulatory guide, licensees and applicants may consider and use the information in the referenced standard, if appropriately justified and consistent with current regulatory practice. Harmonization with International Standards This regulatory guide endorses, in whole or in part, international consensus standards and reports produced by international organizations such as the Institute of Electrical and Electronic Engineers (IEEE). The IEEE is a non-profit professional association dedicated to advancing technological innovation and excellence. It has more than 400,000 members in more than 160 countries and produces 30 percent of the world's literature in the electrical and electronics engineering and computer science fields including multiple tutorials and standards produced by its standardization committees. Endorsement, in whole or in part, of international standards reduces the need for the development of unique NRC standards and is consistent with the agency goal of improved harmonization with international organizations. C. STAFF REGULATORY GUIDANCE IEEE Std. 1074-2006 provides an approach that the NRC staff considers acceptable for meeting the requirements in 10 CFR Part 50 and the guidance in Regulatory Guide 1.152 as they apply to development processes for safety system software with the exceptions and additions listed in these regulatory positions. In this section of the guide, the cited criterion refers to Appendix A or B to 10 CFR Part 50 unless otherwise noted. The NRC staff will consider these exceptions and additions in its review of submittals from applicants and licensees. 1. Clarifications Because IEEE Std. 1074-2006 was not written specifically for nuclear safety, the following clarifications apply to the standard: DG-1210, Page 7 a.