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:
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 Nuclear Power Plants” (Ref. 7), describes a method that the NRC staff considers acceptable for use in identifying and classifying those features of LWR nuclear power plants that must be designed to withstand the effects of the SSE. DG-1372, Page 4 • RG 1.35.1, “Determining Prestressing Forces for Inspection of Prestressed Concrete Containments” (Ref. 8), provides guidance on determining prestressing forces in containment tendons to be used for ISI of prestressed concrete containment structures. • RG 1.61, “Damping Values for Seismic Design of Nuclear Power Plants” (Ref. 9), provides guidance on damping values that the NRC staff considers acceptable for use in the seismic response analysis of seismic Category I nuclear power plant structures. • RG 1.69, “Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants” (Ref. 10), describes a method acceptable to the NRC staff for determining the minimum thickness, based on radiation shielding requirements (only), of concrete radiation shields in nuclear power plants. Note that the approach for determining minimum thickness of concrete radiation shields, based on structural requirements, in RG 1.69 is not applicable to concrete containments. For concrete containments, the minimum concrete thickness based on structural requirements is determined using this RG (1.136). • RG 1.76, “Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants” (Ref. 11), provides guidance that the NRC staff considers acceptable for use in selecting the design-basis tornado and design-basis tornado-generated missiles that a nuclear power plant should be designed to withstand to prevent undue risk to the health and safety of the public. • RG 1.90, “Inservice Inspection of Prestressed Concrete