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:
ater, and condensate systems and components during the specified power levels; (5) methods to be used to trend plant parameters (see additional guidance below for details); (6) acceptance criteria for monitoring and trending plant parameters, and for conducting inspections (see item c below); (7) actions to be taken if acceptance criteria are not satisfied; (8) provisions for providing information to the NRC staff on plant data, evaluations, inspections, and procedures before and during power ascension. c. Guidance on acceptance criteria for measurements: The measurement program needs to include acceptance criteria for measurements during power ascension with permissible deviations, and the bases for the criteria. The criteria need to be established in terms of maximum allowable response levels in the structure, and presented in terms of maximum allowable response levels at sensor locations. For example, typical provisions, which may be made explicit in a license condition for BWR steam dryers depending on the application, are as follows. DG-1323, Page 32 (1) Power ascension limits for BWR steam dryers commonly are set for two sets of criteria – Level 1 and Level 2. Exceeding Level 2 criteria typically triggers additional engineering assessments, but does not specify a plant power reduction. Exceeding Level 1 criteria dictates (a) a reduction of plant power such that the limits are satisfied, and (b) completion of engineering assessments to demonstrate satisfactory structural integrity. (2) Power ascension limits might need to be reestablished immediately before reactor power ascension, particularly if they originally were developed earlier in the application process. If plant conditions or SSC designs change from those used to establish original limits, or sensors used to establish the limits fail before power ascension, the limits will need to be reestablished. Previous limits and accompanying benchmarking need to be updated at current plant conditions and with