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
CFR Part: 
CFR Title: 

Content:
describes methods and procedures that the NRC considers acceptable for compliance with NRC regulations in the analysis, design, construction, testing, and DG-1372, Page 5 evaluation of safety-related nuclear concrete structures, excluding concrete reactor vessels and concrete containments. • RG 1.199, “Anchoring Components and Structural Supports in Concrete” (Ref. 18), describes a method acceptable to the NRC staff for the design, installation, testing, evaluation, and QA of anchors (steel embedments) used for component and structural supports in concrete. • RG 1.208, “A Performance-Based Approach To Define the Site-Specific Earthquake Ground Motion” (Ref. 19), provides guidance on the development of the site-specific ground motion response spectrum, which is part of the development of the SSE for a site as a characterization of the regional and local seismic hazard. • RG 1.216, “Containment Structural Integrity Evaluation for Internal Pressure Loadings above Design-Basis Pressure” (Ref. 20), describes methods that the NRC staff considers acceptable for satisfying applicable regulations for the structural integrity of containments under internal pressurization that pertain to the containment structural capacity above design-basis pressures, to combustible gas control, and to the prevention and mitigation of severe accidents. • RG 1.217, “Guidance for Assessment of Beyond-Design-Basis Aircraft Impacts” (Ref. 21), describes considerations for aircraft impacts on new nuclear power reactors. • RG 1.221, “Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants” (Ref. 22), provides guidance that the NRC staff considers acceptable for use in selecting the design-basis hurricane windspeed and hurricane-generated missiles that a new nuclear power plant should be designed to withstand to prevent undue risk to public health and safety. • RG 1.231, “Acceptance of Commercial-Grade Design and Analysis Computer Programs Used in