Document: NRC Regulatory Guide
Document ID: ad61f8a3-1cce-4446-9542-dcdda55c1ec6
Document Type: regulatory_guide
Title: Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing + HISTORY - HISTORY 07/2015 – DG-1323 , Proposed Revision 4 03/2013 – Periodic Review of Revision 3 – No Issues Identified 11/2006 – DG-1163 , Proposed Revision 3 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1508/ML15083A390.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.20
CFR Part: 
CFR Title: 

Content:
ratio MIV mechanical-induced vibration MSL main steam line OMB Office of Management and Budget PSD power spectral density PWR pressurized water reactor RMS root mean square RPV reactor pressure vessel RRP reactor recirculation pump SG steam generator SMR small modular reactor SMT scale model testing SCF stress concentration factor SSC systems, structures and components VPF vane passing frequency DG-1323, Page 43 REFERENCES4 1. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy” (10 CFR 50). 2. U.S. Code of Federal Regulations, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter 1, Title 10, “Energy” (10 CFR 52). 3. U.S. Nuclear Regulatory Commission (NRC), “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” NUREG-0800, Section 3.9.2, “Dynamic Testing and Analysis of Systems, Structures, and Components. 4. American Society of Mechanical Engineers (ASME), “Rules for Construction of Nuclear Power Plant Components,” Boiler and Presssure Vessel Code, Section III, Division I, New York, NY.5 5. NRC, “Initial Test Program for Water-Cooled Nuclear Power Plant,” Regulatory Guide 1.68. 6. Weaver, D.S., et. al., “Flow-induced vibrations in power and process plants: Progress and prospects,” Journal of Pressure Vessel Technology, 122, pp. 339-347. 7. DeBoo, et. al., “Identification of Quad Cities Main Steam Line Acoustic Sources and Vibration Reduction,” ASME PVP2007-26658, Proceedings of ASME PVP 2007 conference, San Antonio, Texas, July 2007. 8. NRC, “Management of Facility-Specific Backfitting and Information Collection,” Management Directive 8.4. 9. NRC, “Backfitting Guidelines,” NUREG-1409. 4 Publicly available NRC published documents are available electronically through the NRC Library on the NRC’s public Web site at