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:
s 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 conditions. In addition, test results from previous plants of similar characteristics may be used to verify the mathematical models used for the loading condition of LOCA in combination with the SSE by comparing such dynamic characteristics as the natural frequencies. The staff review covers the methods to be used for comparison of test and analytical results and for verification of the analytical models. Computer programs used in the analyses discussed in this SRP section are reviewed in accordance with SRP Section 3.9.1.14 Review Interfaces15 EMEB also performs the following reviews under the SRP sections indicated:16 1. Computer programs used in the analyses discussed in this SRP section are reviewed in accordance with SRP Section 3.9.1.17 2. The design of ASME Code Class 1, 2, and 3 component, component supports, and core support structures are reviewed in accordance with SRP Section 3.9.3. 3. The design of reactor vessel internal components is reviewed in accordance with SRP Section 3.9.5.18 In addition, the EMEB will coordinate other branches' evaluations that interface with the overall review of the system as follows:19 1. The Reactor Systems Branch (RSBSRXB ) verifies on request that (1) the various flow 20 modes to be used to conduct the vibration test of the reactor internals are representative of the steady-state and operational transient conditions anticipated for the reactor during its service, and (2) that an acceptable hydraulic analysis has been used to determine the loads acting on the reactor coolant system piping and the reactor internals. 2. The Materials and Chemical Engineering Branch (EMCB) performs a review of those applications that propose to eliminate consideration of design loads associated with the dynamic effects of pipe rupture, as part