Document: NUREG-0800
Document ID: 6b7eddf4-f7ce-4821-9f11-e37070221e57
Document Type: srp
Title: DYNAMIC TESTING AND ANALYSIS OF SYSTEMS, STRUCTURES, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16133A418.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
k 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 RG 1.20 for the conduct of preoperational and initial startup vibration tests by a preoperational and initial startup 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 provides adequate assurance that the reactor internals will, during their service lifetime, withstand the FIV 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. 3.9.2-38 Revision 4 – March 2017 4. The applicant has met the relevant requirements of GDCs 2 and 4 for design of systems and components important to safety to withstand the effects of earthquakes and appropriate combinations of the effects of normal and postulated accident conditions with the effects of the SSE by a dynamic system analysis which provides an acceptable basis for the structural design adequacy of the reactor internals to withstand the combined dynamic loads of postulated LOCA and SSE and (for a BWR) the combined loads of a postulated MSL rupture and SSE. The analysis provides adequate assurance that the combined stresses and strains in the reactor internals