Document: NRC Regulatory Guide
Document ID: 3c238fa7-baa2-41c1-ac85-868fcda6b038
Document Type: regulatory_guide
Title: Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments + HISTORY – HISTORY 07/2020 – DG-1372 , Proposed Revision 4 05/2019 – Periodic Review of Revision 3 – Revise 10/2015 – Periodic Review of Revision 3 – Reviewed with issues identified for future consideration 10/2006 – DG-1159, Proposed Revision 3 Prior to the issuance of DG-1159, RG 1.136 was entitled "Materials, Construction, and Testing of Concrete Containments (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2010/ML20105A215.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.136
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Content:
quirements for the operating-basis earthquake (OBE) and the safe-shutdown earthquake (SSE). • 10 CFR Part 52 governs the issuance of, among others, standard design certifications, combined licenses, and standard design approvals for nuclear power facilities. o 10 CFR 52.47, “Contents of applications; technical information,” provides requirements for the technical information for standard design certifications submitted under 10 CFR Part 52. o 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report,” and 10 CFR 52.80, “Contents of Applications; Additional Technical Information,” provide requirements for the technical information needed in combined license applications. o 10 CFR 52.137, “Contents of applications; technical information,” provides requirements for the technical information needed for standard design approval applications. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” Chapter 3, “Design of Structures, Components, Equipment, and Systems,” Section 3.8.1, “Concrete Containment” (Ref. 4), provides guidance that the NRC staff uses for performing structural safety reviews relating to concrete containments or to concrete portions of steel/concrete containments as part of a license application. • RG 1.7, “Control of Combustible Gas Concentrations in Containment” (Ref. 5), describes methods that are acceptable to the NRC staff for implementing the requirements of 10 CFR 50.44 for reactors subject to the provisions of 10 CFR 50.44(b) or (c). • RG 1.28, “Quality Assurance Program Criteria (Design and Construction)” (Ref. 6), describes acceptable methods for establishing and implementing a QA program for the design and construction of nuclear power plants and fuel reprocessing plants to comply with the requirements of Appendix B to 10 CFR Part 50. • RG 1.29, “Seismic Design Classification for