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:
taff. This position includes Division 2 Code Cases that were inadvertently included in RG 1.193, Revision 6, and any later Division 2 Code Cases issued up to the publication of the 2019 Edition of the ASME B&PV Code, “Code Cases—Nuclear Components.” Harmonization with International Standards The NRC has a goal of harmonizing its regulatory guidance with documents issued by the International Atomic Energy Agency (IAEA) to the extent practical. Although the NRC does not endorse the following IAEA safety standard(s) and/or guide(s), in general this RG incorporates similar guidelines and is generally consistent with the basic safety principles provided in them. • IAEA Safety Standards Series No. SSG-53, “Design of Reactor Containment and Associated Systems of Nuclear Power Plants,” issued 2019 (Ref. 47), provides guidance relevant to reactor containment and associated systems at a high level. It addresses the containment structure and the systems with the functions of isolation, control and management of mass and energy releases, control and limitation of radioactive releases, and control and management of combustible gases. • IAEA Safety Standards Series No. NS-G-1.6, “Seismic Design and Qualification for Nuclear Power Plants,” issued 2003 (Ref. 48), provides recommendations at a high level on a generally accepted way to design a nuclear power plant so that an earthquake motion at the site will not jeopardize the safety of the plant. It also gives guidance on a consistent application of methods and procedures for analysis, testing and qualification of structures and equipment so that they meet the safety requirements covering the design of nuclear power plants, safety assessments for the design and the regulatory issues concerned with the licensing of plants. • IAEA Safety Standards Series No. NS-G-2.6, “Maintenance, Surveillance and In-Service Inspections in Nuclear Power Plants,” issued 2002 (Ref. 49), covers the organizational and procedural