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:
esting should be conducted during startup testing. The systems to be monitored should include: A. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code) Class 1, 2, and 3 systems, B. other high-energy piping systems inside seismic Category I structures (“seismic Category I” is defined in Regulatory Guide (RG) 1.29, “Seismic Design Classification”) C. high-energy portions of systems whose failure could reduce the functioning of any seismic Category I SSCs to an unacceptable safety level, and D. seismic Category I portions of moderate-energy piping systems located outside containment. The supports and restraints necessary for operation during the life of the nuclear power plant are considered to be part of the piping system. The purpose of these tests is to confirm that these piping systems, restraints, components, and supports have been adequately designed to withstand flow-induced dynamic loadings under the steady-state and operational transient conditions anticipated during service and to confirm that normal thermal motion is not restrained. Particular attention should be given to any potential adverse flow conditions that could lead to abnormally strong pressure pulsations and vibrations, such as those caused by flow over valve openings. The test program description should specify the different flow modes, selected locations for visual inspections and other measurements, the acceptance criteria, and corrective actions if excessive vibration or indications of thermal motion restraint occur. 2. The following areas related to the seismic analysis of seismic Category I mechanical equipment described in the applicant's safety analysis report (SAR) are reviewed. For the methods and criteria for seismic qualification testing of seismic Category I mechanical equipment, refer to SRP Section 3.10. For the design of nuclear air and gas treatment systems and components, acceptable methods and criteria are described in ASME Code