Document: NRC Regulatory Guide
Document ID: 776b9130-d4de-4c44-81a6-ecd8c36df0ca
Document Type: regulatory_guide
Title: Safety-Related Steel Structures and Steel-Plate Composite
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2033/ML20339A558.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.243
CFR Part: 
CFR Title: 

Content:
. . . without loss of capability to perform their safety functions.” o GDC 4, “Environmental and dynamic effects design bases,” requires, in part, that SSCs “important to safety be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents . . . .” Additional requirements applicable to this RG include the following: • Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 establishes overall quality assurance (QA) for SSCs important to safety. • Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants,” to 10 CFR Part 50 states, in part, requirements for the implementation of GDC 2 with respect to earthquakes. • 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 licensed under Section 103 of the Atomic Energy Act of 1954, as amended (68 Stat. 919), and Title II of the Energy Reorganization Act of 1974 (88 Stat. 1242). o 10 CFR 52.47, “Contents of applications; technical information,” provides requirements on the content of technical information for standard design certifications submitted under 10 CFR Part 52. o 10 CFR 52.77, “Contents of applications; general information,” and 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report,” provide requirements on the technical content of combined operating license applications. Related Guidance • RG 1.28, “Quality Assurance Program Criteria (Design and Construction)” (Ref. 4), describes methods that the NRC staff considers acceptable for complying with the provisions of 10 CFR Part 50 and 10 CFR Part 52, which refer to 10 CFR Part 50, Appendix B, for establishing and implementing a QA program for the design and