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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CFR Title: 

Content:
finality of an approval under 10 CFR Part 52. The staff also does not intend to use the guidance to support NRC staff actions in a manner that constitutes “forward fitting” as that term is defined and described in Management Directive 8.4. If a licensee believes that the NRC is using this RG in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfitting or forward fitting appeal with the NRC in accordance with the process in Management Directive 8.4. DG-1372, Page 26 REFERENCES 1. U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy.”2 2. CFR, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter 1, Title 10, “Energy.” 3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Division 1, “Rules for Inspection and Testing of Components of Light-Water-Cooled Plants,” Subsection IWE and Subsection IWL, New York, NY. 3 4. U.S. Nuclear Regulatory Commission (NRC), NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” Chapter 3, “Design of Structures, Components, Equipment, and Systems,” Section 3.8.1, “Concrete Containment,” Revision 4, Washington, DC, September 2013.4 (ADAMS Accession No. ML13198A245) 5. NRC, Regulatory Guide (RG) 1.7, “Control of Combustible Gas Concentrations in Containment,” Washington, DC. 6. NRC, RG 1.28, “Quality Assurance Program Criteria (Design and Construction),” Washington, DC. 7. NRC, RG 1.29, “Seismic Design Classification,” Washington, DC. 8. NRC, RG 1.35.1, “Determining Prestressing Forces for Inspection of Prestressed Concrete Containments,” Washington, DC. 9. NRC, RG 1.61, “Damping Values for Seismic Design of Nuclear Power Plants,” Washington, DC.