Document: NUREG-0800
Document ID: 45f5d841-54ef-4876-be3e-86eafc6ca90a
Document Type: srp
Title: Each calculated spectrum of the artificial time history is considered to envelop
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12352A305.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.0
CFR Part: 
CFR Title: 

Content:
n 4 - December 2012 Technical Rationale: The technical rationale for application of these requirements to reviewing this SRP section is discussed in the following paragraphs: 1. GDC 2 requires, in the relevant parts, that SSCs important to safety be designed to withstand the effects of natural phenomena such as earthquakes without loss of capability to perform 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 CP, OL, COL, ESP reviews, or for site parameters 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 3.7.1 describes acceptance criteria for developing seismic design parameters to assure that they are appropriate and contain sufficient margin such that seismic analyses (reviewed under other SRP sections) accurately and/or conservatively represent the behavior of SSCs during postulated seismic events. Criteria is provided for developing the seismic design ground motion, percentage of critical damping, supporting media, and the technical interface requirements for ESP, DC, and/or COL applications, as well as site acceptability determination. Reference is made to RG 1.60, and 1.208, which provide procedures that are acceptable to the staff for defining seismic ground motion response spectra for input into the seismic design analysis of nuclear power plants SSCs. In addition, RG 1.61 is referenced for guidance of acceptable damping values to be used in performing dynamic analyses of SSCs. Meeting these requirements provides