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
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CFR Title: 

Content:
the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 3.9.2-39 Revision 4 – March 2017 1. American National Standards Institute, ANSI S2.31-1979 (R2004), “Methods for the Experimental Determination of Mechanical Mobility, Part 1: Basic Definitions and Transducers,” New York, NY. 2. American National Standards Institute, ANSI S2.32-1982 (R2004), “Methods for the Experimental Determination of Mechanical Mobility, Part 2: Measurements Using Single-Point Translational Excitation,” New York, NY. 3. American Society of Mechanical Engineers, ASME AG-1-2012, “Code on Nuclear Air and Gas Treatment,” New York, NY. 4. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, “Nuclear Power Plant Components,” New York, NY. 5. American Society of Mechanical Engineers, ASME OM-S/G-2012, “Standards and Guides For Operation of Nuclear Power Plants,” Part 3, “Requirements for Preoperational and Initial Start-Up Vibration Testing of Nuclear Power Plant Piping Systems,” including the addenda, and Part 7, “Requirements for Thermal Expansion Testing of Nuclear Power Plant Piping Systems,” New York, NY. 6. Chu, S. L., M. Amin, and S. Singh, “Spectral Treatment of Actions of Three Earthquake Components on Structures,” Nuclear Engineering and Design, Volume