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:
n. Finally, based on operating experience, Revision 3 provided new guidance for steam dryers in BWR plants and information that could be applied to monitoring programs for plant components outside the reactor vessel. Harmonization with International Standards The NRC staff reviewed guidance from the International Atomic Energy Agency (IAEA) and did not identify any standards related to the subject of RG 1.20 that provided useful guidance to NRC staff, applicants, or licensees. DG-1323, Page 8 C. STAFF REGULATORY GUIDANCE The NRC staff considers the guidance in this regulatory guide to provide an acceptable method for developing and implementing a CVAP for reactor internals at nuclear power plants. In particular, the applicant or licensee should apply the classifications identified in Section C.1 to categorize reactor internals according to design, operating parameters, and operating experience. The applicant or licensee should establish an appropriate CVAP using the guidance in Sections C.2, C.3, and C.4, as they relate to the specific classifications of the applicable reactor internals. This regulatory guide describes acceptable methods for evaluating the potential adverse effects from FIV, AR, AIV, and MIV. Section C.2.0 of this regulatory guide provides detailed information for these vibration mechanisms. In general, these vibration excitation mechanisms need to be assessed for reactor internals in BWR, PWR, and SMR nuclear power plants. Consistent with RG 1.68, “Initial Test Program for Water-Cooled Nuclear Power Plant,” (Ref. 5) the term “preoperational testing,” as used in this guide, consists of testing before fuel loading, and “startup testing” refers to testing after fuel loading. Reactor internals important to safety are designed to accommodate steady-state and transient vibratory loads throughout the service life of the reactor. The overall program includes predictive analysis, a measurement program, and an inspection program. The term