Document: NRC Regulatory Guide
Document ID: bcbe26a0-004f-4616-b7f4-b32b2bfe4909
Document Type: regulatory_guide
Title: Setpoints for Safety-Related Instrumentation (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2005/ML20055G823.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.105
CFR Part: 
CFR Title: 

Content:
gulatory guide to support NRC staff actions in a manner that would constitute backfitting as that term is defined in 10 CFR 50.109, “Backfitting,” and as described in NRC Management Directive 8.4, “Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests,” (Ref. 14) nor does the NRC staff intend to use the guidance to affect the issue finality of an approval under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” The staff also does not intend to use the guidance to support NRC staff actions in a manner that constitutes forward fitting as that term is defined and described in Management Directive 8.4. If a licensee believes that the NRC is using this regulatory guide in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfitting or forward fitting appeal with the NRC in accordance with the process in Management Directive 8.4. DG-1363, Page 12 REFERENCES 1 1. American National Standards Institute (ANSI)/International Society of Automation (ISA), Standard 67.04.01-2018, “Setpoints for Nuclear Safety-Related Instrumentation,” ISA, Research Triangle Park, NC, 2018. 2. U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy.” 3. CFR, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter 1, Title 10, “Energy.” 4. Institute of Electrical and Electronics Engineers (IEEE), Standard 279-1968, “Proposed IEEE Criteria for Nuclear Power Plant Protection Systems,” Piscataway, NJ, 1968. 5. IEEE, Standard 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Piscataway, NJ, 1971.2 6. IEEE, Standard 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations” (including the correction sheet dated January 30, 1995), Piscataway, NJ, 1995. 7. U.S. Nuclear Regulatory