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:
nts for the principal design criteria for DG-1363, Page 2 water-cooled nuclear power plants.. The General Design Criteria are also considered to be generally applicable to other types of nuclear power units and are intended to provide guidance in establishing the principal design criteria for such other units. The following GDC are of importance to setpoints for safety-related instrumentation of nuclear power plants: o GDC 13, “Instrumentation and Control,” requires operating reactor licensees to provide instrumentation to monitor variables and systems over their anticipated ranges for accident conditions as appropriate to ensure adequate safety. o GDC 20, “Protection System Functions,” requires, among other things, that the protection system be designed to initiate operation of appropriate systems to ensure that specified acceptable fuel design limits are not exceeded. • Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 requires, in part, that licensees have programs and administrative controls in place that are intended to ensure that safety-related structures, systems, and components perform as designed.. • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. o 10 CFR 52.47, “Contents of applications; technical information,” contains the application requirements cited above for standard design certifications issued under 10 CFR Part 52. In particular, 10 CFR 52.47(a)(11) references 10 CFR 50.36, “Technical specifications,” 10 CFR 52.47(a)(3)(i) references the GDC (Appendix A to 10 CFR Part 50), and 10 CFR 52.47(a)(19) references Appendix B to 10 CFR Part 50. • 10 CFR 50.55a(h) states that protection systems of nuclear power reactors of all types must meet the requirements specified in 10 CFR 50.55a(h), and each combined license for a