Document: NUREG-0800
Document ID: 7c104096-d040-463a-a94b-a0af08ab3478
Document Type: srp
Title: DYNAMIC TESTING AND ANALYSIS OF SYSTEMS, STRUCTURES, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230008.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
ts. Modal response parameters are combined in accordance with the appropriate acceptable methods described in SRP Section 3.7.2 and/or RG 1.92. The square root of the sum of the squares of the maximum codirectional responses is used in accounting for three 3.9.2-31 Revision 3 - March 2007 components of the earthquake motion for both the time history and response spectrum methods. Floor spectra inputs to be used for design and test verifications of systems, components, equipment, and their supports are generated from the time history method, taking into account variation of parameters by peak widening. There will be a vertical seismic system dynamic analysis for all systems, components, equipment, and their supports where analyses show significant structural amplification in the vertical direction. 3. The applicant has met the requirements of GDCs 1 and 4 for design and testing of reactor internals with the potential to generate loose parts to quality standards commensurate with the importance of the safety functions performed with appropriate protection against dynamic effects. The applicant has met the regulatory positions of DG-1163 for the conduct of preoperational vibration tests by a preoperational vibration program planned for the reactor internals providing an acceptable basis for design adequacy of these internals under test loading conditions comparable to those experienced during operation. The combination of tests, predictive analysis, and post-test inspection provide adequate assurance that the reactor internals will, during their service lifetime, withstand the flow-induced vibrations of reactor operation without loss of structural integrity. The integrity of the reactor internals in service is essential to proper positioning of reactor fuel assemblies and unimpaired operation of the control rod assemblies for safe reactor operation and shutdown. 4. The applicant has met the relevant requirements of GDCs 2 and 4 for design of systems and components