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:
t to the prototype test if timely adequate test results are not obtained for the designated prototype. At the OL stage, the staff review includes the following procedures: A. A detailed preoperational vibration test program and the tentative schedule for the test are reviewed. If elements of the program differ substantially from the guidelines specified in Regulatory Guide 1.20, there should be discussion of the need and justification for the differences. On request, the reviewer verifies whether the flow modes are acceptable. 3.9.2-29 Revision 3 - March 2007 B. For a prototype plant and plants reviewed for extended power uprate, the review includes the acceptability of vibration prediction, the visual surface inspection procedures, the details of instrumentation for vibration monitoring, the methods and procedures for processing the test results, and such supplementary tests as component vibration tests, flow tests, and scaled model tests. C For a non-prototype plant, the staff verifies the applicability of the designated prototype, including the design and operating condition similarities of the reactor internal structures to those of the prototype. Additional detailed analysis, scaled model tests, or vibration monitoring in the confirmatory tests may be needed to complete the review. 5. In the CP stage review of the dynamic analysis of the reactor internals and unbroken loops of the reactor coolant piping under faulted condition loadings, the applicant should commit to this analysis or identify the applicable document, usually a topical report, with the required information. The scope and methods of analysis should be described briefly. In the OL review, the staff reviews the detailed information for whether an adequate analysis has been made of the capability of reactor internal structures and unbroken loops to withstand dynamic loads from the most severe LOCA in combination with the SSE. The staff review includes the analytical methods and procedures, the basis