Document: NRC Regulatory Guide
Document ID: c195adf7-a2ca-46e1-9071-9f87fd3d00ce
Document Type: regulatory_guide
Title: 10/2013 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1321/ML13210A463.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.73
CFR Part: 
CFR Title: 

Content:
ns The regulations established by the NRC in Title 10, Part 50, “Domestic Licensing of Production and Utilization Facilities,” of the Code of Federal Regulations (10 CFR Part 50) (Ref. 2), require that structures, systems, and components (SSCs) important to safety in a nuclear power plant be designed to accommodate the effects of environmental conditions (i.e., they must remain functional under postulated design-basis events (DBE)). General Design Criterion (GDC) 1, “Quality Standards and Records,” GDC 2, “Design Bases for Protection against Natural Phenomena,” GDC 4, “Environmental and Dynamic Effects Design Bases,” and GDC 23, “Protection System Failure Modes,” of Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50, contain general requirements to provide reasonable assurance that SSCs are designed to accommodate the effects of environmental conditions. Augmenting the above mentioned general requirements are specific requirements pertaining to qualification of certain electrical equipment important to safety described in 10 CFR 50.49, “Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.” In addition, Criterion III, “Design Control,” of Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50, requires that, when a test program is used to verify the adequacy of a specific design feature, the test program must include suitable qualification testing of a prototype unit under the most adverse design conditions. Additionally, in accordance with 10 CFR 52.48, “Standards for Review of Applications,” and 10 CFR 52.81, “Standards for Review of Applications,” these GDC and quality RG 1.73, Rev. 1, Page 2 assurance criteria also apply to nuclear power reactor licenses issued under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 3). Related Guidance In