Document: NUREG-0800
Document ID: c165ebfe-8431-4d56-8bc9-97c2227d45bb
Document Type: srp
Title: SEISMIC SYSTEM ANALYSIS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070640311.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.2
CFR Part: 
CFR Title: 

Content:
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 3.7.2 describes acceptable methods for the seismic analysis and modeling of seismic Category I structures and major plant systems to assure that they accurately and/or conservatively represent the behavior of SSCs during postulated seismic events. These criteria include acceptable methods/procedures for performing a suitable dynamic analysis, including the effects of soil-structure interaction. For additional guidance reference is made to RGs 1.92, and 1.122. RG 1.92, provides various procedures acceptable to the staff for combining the three dimensional modal responses for both the response spectrum analysis approach and the time history analysis approach of nuclear power plant structures. Additionally, RG 1.122 describes methods acceptable to the NRC staff, as augmented in this SRP section, to be used in developing two horizontal and one vertical in-structure design response spectra at various floors or other equipment support locations of interest, from the time history motions resulting from the dynamic analysis of the supporting structure. Criteria and/or requirements are also described for considering the interaction of non-Category I structures with Category I SSCs, the treatment of torsional effects, the procedures for considering the effects of damping, and the determination of seismic overturning moments and sliding forces. Meeting these requirements provides assurance that seismic Category I systems 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, Appendix A provides definitions for the OBE