Document: NUREG-0800
Document ID: c73b236e-7145-44ae-bb8d-0fdef4b86d70
Document Type: srp
Title: -
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12353A365.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.1
CFR Part: 
CFR Title: 

Content:
Draft Revision 4 - December 2012 SRP Section 3.8.1 provides guidance related to static and dynamic loadings and evaluation programs for concrete containments. It also describes acceptable materials, design methodology, quality control procedures, construction methods, and inservice inspections, as well as documentation criteria for design and construction controls. SRP Section 3.8.1 cites RG 1.136 for guidance regarding load combination equations and ASME Code, Section III, Division 2, Section CC, for design guidance and acceptance criteria. Meeting these requirements and criteria provide assurance that engineering analysis and design of concrete containments for nuclear power plants will comply with 10 CFR Part 50 and that concrete containments will perform their intended safety function to prevent or mitigate the spread of radioactive material. 2. Compliance with GDC 2 requires that SSCs important to safety be designed to withstand the effects of expected natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions. The design bases for these SSCs should reflect appropriate combinations of the effects of normal and accident conditions with the effects of the natural phenomena. To ensure that the containment of a nuclear power plant is designed to withstand natural phenomena, it is necessary to consider the most severe natural phenomena that have been historically reported with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data have been accumulated. These data should be used to specify the design requirements of nuclear power plant components to be evaluated as part of CP, OL, COL, or ESP reviews, or for site parameter envelopes in the case of DCs, thereby ensuring that components important to safety will function in a manner that will maintain the plant in a safe condition. SRP Section 3.8.1 and RG 1.136 provide guidance