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:
for materials, design, construction, fabrication, examination, and testing of concrete (reinforced or prestressed) containments in nuclear power plants. Applicability This RG applies to non-power and power reactor licensees and applicants subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 1), and 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 2). Applicable Regulations • 10 CFR 50.34(f), “Additional TMI-related requirements,” requires, for certain reactors specified therein, that plant designs must accommodate loadings associated with hydrogen generation that result from metal-water reaction of the fuel cladding accompanied by hydrogen burning or the added pressure of inerting system actuation. • 10 CFR 50.44, “Combustible gas control for nuclear power reactors,” provides the requirements for combustible gas control for currently licensed reactors (with an operating license on October 16, 2003), for future water-cooled reactor applicants and licensees (comparable to light-water reactor (LWR) designs licensed as of October 16, 2003), and for future nonwater-cooled DG-1372, Page 2 or other water-cooled (not comparable to those licensed as of October 16, 2003) reactor applicants and licensees. • 10 CFR 50.55a(g)(4) requires that inservice inspection (ISI) of Class CC concrete containments and metallic shell and penetration liners of concrete containments shall be performed in accordance with the applicable edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, Division 1, “Rules for Inspection and Testing of Components of Light-Water-Cooled Plants,” Subsections IWE and IWL (Ref. 3), as incorporated by reference and subject to conditions stated in this regulation. • Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50,