Document: NUREG-0800
Document ID: e8ae4ac1-29ed-46b1-b4c2-19c7f632e815
Document Type: srp
Title: DYNAMIC TESTING AND ANALYSIS OF SYSTEMS, COMPONENTS, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070336.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
iteria, and the methods of verifying predictions by means of tests should be determined. If the reactor internal structures are a non-prototype design, reference should be made to the results of tests and analyses for the prototype reactor and a brief summary of the results should be given. 4. Flow-induced vibration testing of reactor internals should be conducted during the preoperational and startup test program. The purpose of this test is to demonstrate that flow-induced vibrations similar to those expected during operation will not cause unanticipated flow-induced vibrations of significant magnitude or structural damage. The test program description should include a list of flow modes, a list of sensor types and locations, a description of test procedures and methods to be used to process and interpret the measured data, a description of the visual inspections to be made, and a comparison of the test results with the analytical predictions. If the reactor internal structures are a non-prototype design, reference should be made to the results of tests and analyses for the prototype reactor and a brief summary of the results should be given. 5. Dynamic system analyses should be performed to confirm the structural design adequacy and ability, with no loss of function, of the reactor internals and unbroken loops of the reactor coolant piping to withstand the loads from a loss-of-coolant accident (LOCA) in combination with the SSE. The staff review covers the methods of analysis, the considerations in defining the mathematical models, the descriptions of the forcing 3.9.2-5 DRAFT Rev. 3 - April 1996 functions, the calculational scheme, the acceptance criteria, and the interpretation of analytical results. 6. A discussion should be provided which describes the methods to be used to correlate results from the reactor internals vibration test with the analytical results from dynamic analyses of the reactor internals under steady-state and operational flow transient