Document: NUREG-0800
Document ID: e40387bd-a6d6-49ae-a11b-6d22124df03a
Document Type: srp
Title: Each calculated spectrum of the artificial time history is considered to envelop the
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070317.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.0
CFR Part: 
CFR Title: 

Content:
sections) accurately and/or conservatively represent the behavior of SSCs during postulated seismic events. Applicable guidance for implementation of and achieving compliance with the requirements set forth in General Design Criterion 2 is provided in Regulatory Guides 1.60 and 1.61. Regulatory Guide 1.60 provides a procedure that is acceptable to the staff for defining response spectra for input into the seismic design analysis of nuclear power plants. Additionally, Regulatory Guide 1.61 delineates damping values acceptable to the staff, to be used in performing dynamic seismic analysis of Seismic Category I SSCs. Meeting the requirements of General Design Criterion 2, in conjunction with the guidelines provided in Regulatory Guides 1.60 and 1.61 assures that safety-related SSCs will continue to function following a seismic event, such that the plant can be brought to, and maintained in, a safe shutdown condition. 2. Appendix A to 10 CFR 100 requires that either a suitable dynamic analysis or an appropriate qualification test be used to demonstrate that all SSCs important to safety are capable of withstanding the seismic and other concurrent loads, except where it can be demonstrated that the use of an equivalent static load methodology provides adequate conservatism. The requirements of Appendix A to 10 CFR 100 assure that the applicable levels of vibratory ground motion corresponding to the OBE and the SSE are properly defined and that adequate accuracy and conservatism is being applied in defining the parameter values being used for input into the seismic design analysis. Compliance with the requirements detailed in Appendix A to 10 CFR 100 in conjunction with implementation of the requirements provided in General Design Criterion 2, as discussed above, assures that safety-related SSCs will continue to function following a seismic event, such that the plant can be brought to, and maintained in, a safe shutdown condition. III. REVIEW PROCEDURES For each area of