Document: NUREG-0800
Document ID: 10bc45c3-8e70-44ed-a57b-2dd08d4ef847
Document Type: srp
Title: SEISMIC SUBSYSTEM ANALYSIS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070640313.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.3
CFR Part: 
CFR Title: 

Content:
their intended safety functions. GDC 2 further requires that the design bases reflect appropriate consideration for the most severe natural phenomena that have been historically reported for the site and surrounding area, with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data have been accumulated in the past. These data shall be used to specify the design requirements of nuclear power plant components to be evaluated as part of construction permit (CP), operating license (OL), combined license (COL), early site permit reviews, or for site parameter envelopes in the case of design certifications, thereby ensuring that components important to safety will function in a manner that will maintain the plant in a safe condition. SRP Section 3.7.3 describes acceptable methods for the seismic analysis of seismic Category I subsystems such as platforms; support frame structures; yard structures; buried piping, tunnels, and conduits; concrete dams; and atmospheric tanks. Criteria is provided for the static and dynamic analysis of these subsystems subjected to earthquake loadings. These criteria include acceptable methods/procedures for analytical modeling, selection of damping, determination of the number of earthquake cycles, interaction of other systems with seismic Category I systems, and evaluation of multiply-supported equipment. Meeting these requirements provides assurance that seismic Category I subsystems will be adequately designed to withstand the effects of earthquakes, and thus, will be able to perform their intended safety function. 2. 10 CFR Part 100, Subpart A, which is applicable to power reactor site applications before January 10, 1997, refers to appendix A of this part for sesimic criteria. 10 CFR 100, A provides definitions for the OBE and the SSE, and requires that the engineering methods, used to ensure that the required safety functions are maintained during and after the vibratory ground motion