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:
of the program differ substantially from the guidelines specified in RG 1.20, the applicant has justified the differences. B. The applicant has addressed 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 applicant has addressed the applicability of the designated valid prototype, including the design and operating condition similarities of the reactor internal structures to those of the prototype. Additional detailed analysis, SMTs, 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 under faulted condition loadings, the applicant should make available this analysis or identify the applicable document with the required information. The scope and methods of analysis should be described. 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 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 of the forcing functions, the mathematical models to represent the dynamic system, and the stability investigations for the core barrel and essential compressive elements. Acceptance of the analysis is based on (1) the technical soundness of the analytical methods, (2) the degree of compliance with the acceptance criteria listed, and (3) verification that stresses under the combined loads are within allowable limits of the applicable code and 3.9.2-36 Revision 4 – March 2017 deformations are within the limits set to ensure the ability of reactor internal structures to perform needed safety