Document: NUREG-0800
Document ID: 585516eb-af20-45dc-a470-9638ec9381f3
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/ML0706/ML070640306.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.0
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Content:
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 Regulatory Guides 1.60, 1.165, 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 assurance that seismic Category I SSCs 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 seismic criteria. 10 CFR 100, Appendix 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 associated with the SSE, involve the use of either a suitable dynamic analysis or an appropriate qualification test methodology. 10 CFR 100, Appendix A requires that the applicable levels of vibratory ground motion corresponding to the OBE and the SSE are properly defined, and that adequate methods are used to demonstrate that SSCs important to safety can withstand the seismic and other concurrently applied loads. 10 CFR Part 100, Subpart B which is applicable to power reactor site applications on or after January 10, 1997, refers to 10 CFR 100.23 of this part for seismic criteria. 10 CFR 100.23 describes the criteria and nature of investigations required to obtain the