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:
of fuel assemblies. Preoperational testing should be performed with the reactor internals important to safety and the fuel assemblies (or dummy assemblies that provide equivalent dynamic mass and flow characteristics) in position. The testing may be conducted without real or dummy fuel assemblies if it is justified (by analytical or experimental means) that such conditions will yield conservative results. DG-1323, Page 34 2.3 Inspection Program The applicant or licensee should describe the inspection program for inspections of the reactor internals both before and after operation in modes consistent with those tested and analyzed for the design. The reactor internals should be removed from the reactor vessel for these inspections if feasible. If removal is not feasible, the inspections need to be performed using examination equipment appropriate for in situ inspection. The inspection program documentation should include the following information: a. A tabulation of all reactor internals and local areas to be inspected, including the following details: (1) all major load-bearing elements of the reactor internals that are relied upon to retain the core support structure in position; (2) the lateral, vertical, and torsional restraints provided within the vessel; (3) those locking and bolting components whose failure could adversely affect the structural integrity of the reactor internals; (4) those surfaces that are known to be or might become contact surfaces during operation; (5) those critical locations on the reactor internals as identified by the vibration analysis, such as the steam dryers in BWRs; and (6) the interior of the reactor vessel for evidence of loose parts or foreign material. b. A tabulation of specific inspection areas to verify segments of the vibration analysis and measurement program. c. A description of the inspection procedure, including the method of examination (e.g., visual and nondestructive surface examinations), method of documentation,