Document: NRC Regulatory Guide
Document ID: 7c9a00a8-375c-4641-bc1b-762a663a96d6
Document Type: regulatory_guide
Title: Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1417/ML14171A584.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.207
CFR Part: 
CFR Title: 

Content:
it or license by the Commission. Paperwork Reduction Act This regulatory guide contains information collections that are covered by the requirements of 10 CFR Parts 50, 52, and 54, which the Office of Management and Budget (OMB) approved under OMB control numbers 3150-0011, 3150-0151, and 3150-0155, respectively. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number. B. DISCUSSION Reason for Revision This revision of the RG (Revision 1) consolidates, updates, and replaces previous NRC staff guidance on the effects of LWR coolant environments on the fatigue lives of nuclear power-plant components. This revision provides an alternative to previous guidance for new reactors provided in Revision 0 of this guide, as well as previous guidance for license renewal of operating reactors in the GALL Report and the Standard Review Plan for License Renewal (SRP-LR). The guidance in Revision 0 of this RG, the GALL Report, and the SRP-LR was developed in response to the closeout of Generic Safety Issue (GSI) 190, “Fatigue Evaluation of Metal Components for 60-Year Plant Life” (Ref. 7), which documented the NRC staff’s selection of the Fen method as an acceptable method to properly incorporate LWR environmental effects into fatigue CUF calculations for ASME Code components. DG-1309, Page 3 Background This RG provides guidance for use in determining the acceptable fatigue lives of components evaluated by a CUF calculation in accordance with the fatigue design rules in Section III of the ASME Code, with consideration of LWR coolant environments. For operating reactors, the NRC staff’s closeout of GSI 190 identified that, because of significant conservatism in quantifying other plant-related variables involved in CUF calculations (such as cyclic behavior, including stress and loading rates), the 40-year design of the