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:
SRP Section 3.9.5. 3.9.2-23 Revision 3 - March 2007 6. For requirements of GDC 1, as to the correlation of tests and analyses of reactor internals, the applicant should address the following items to ensure the adequacy and sufficiency of the test and analysis results. A. Comparison of the measured response frequencies with the analytically obtained natural frequencies of the reactor internals for validation of the mathematical models used in the analysis. Comparison of the measured and predicted damping factors as a function of natural frequencies for validation of the damping assumed in the analysis. B. Comparison of the analytically obtained mode shapes with the shape of measured motion for identification of the modal combination or verification of a specific mode. C. Comparison of the response amplitude time variation and the frequency content from test and analysis for verification of the postulated forcing function. D. Comparison of the measured amplitudes, frequencies, and time variations of loads with those predicted by test-analysis combination method for validation of the predicted forcing function. E. Comparison of the maximum responses from test and analysis for verification of stress levels. F. Comparison of the mathematical model for dynamic system analysis under operational flow transients and under combined LOCA and SSE loadings for similarities. G. Comparison of measurements and predictions of any adverse flow phenomena (e.g., flow-excited acoustic and/or structural resonances) for validation of the model(s) predicting the loading induced by the phenomena. 7. For new applications, test specifications should be in accordance with ASME OM-S/G-1990, "Standards and Guides For Operation of Nuclear Power Plants," Part 3, "Requirements for Preoperational and Initial Start-Up Vibration Testing of Nuclear Power Plant Piping Systems," and Part 7, "Requirements for Thermal Expansion Testing of Nuclear Power Plant Piping Systems." Technical Rationale The