As part of the process of renewing the operating license for an additional 20 years after the original 40-year design life, nuclear plant owners in the United States (US) are required to show that they are managing the effects of aging of systems, structures, and components. US Nuclear Regulatory Commission (NRC) report NUREG-1801, the “Generic Aging Lessons Learned (GALL) Report,” identifies acceptable aging management programs, including programs for fatigue and cyclic operation. This includes fatigue usage analyses that account for reduced fatigue life for components in a reactor water environment. Earlier revisions of the GALL report required plants to perform environmentally-assisted fatigue (EAF) analyses using the rules in reports NUREG/CR-6583 (for carbon and low alloy steels) and NUREG/CR-5704 (for austenitic stainless steels), which were developed in 1998 and 1999, respectively. However, GALL Revision 2, issued in December 2010, requires that the rules in NUREG/CR-6909, issued in 2007, be used for nickel alloy materials, and allows it to be used for carbon, low-alloy and stainless steels as an alternative to those in the previous reports. This paper presents an application of the NUREG/CR-6909 rules, and makes several observations about the differences between using the newer and older rules. The analyses presented were performed for a sample set of boiling water reactor (BWR) locations.
Skip Nav Destination
ASME 2011 Pressure Vessels and Piping Conference
July 17–21, 2011
Baltimore, Maryland, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-4451-9
PROCEEDINGS PAPER
Use of NUREG/CR-6909 Environmentally-Assisted Fatigue Rules for a Nuclear Plant License Renewal Application
William F. Weitze,
William F. Weitze
Structural Integrity Associates, Inc., San Jose, CA
Search for other works by this author on:
Matthew C. Walter,
Matthew C. Walter
Structural Integrity Associates, Inc., Centennial, CO
Search for other works by this author on:
Keith R. Evon
Keith R. Evon
Structural Integrity Associates, Inc., Centennial, CO
Search for other works by this author on:
William F. Weitze
Structural Integrity Associates, Inc., San Jose, CA
Matthew C. Walter
Structural Integrity Associates, Inc., Centennial, CO
Keith R. Evon
Structural Integrity Associates, Inc., Centennial, CO
Paper No:
PVP2011-57274, pp. 243-246; 4 pages
Published Online:
May 21, 2012
Citation
Weitze, WF, Walter, MC, & Evon, KR. "Use of NUREG/CR-6909 Environmentally-Assisted Fatigue Rules for a Nuclear Plant License Renewal Application." Proceedings of the ASME 2011 Pressure Vessels and Piping Conference. Volume 1: Codes and Standards. Baltimore, Maryland, USA. July 17–21, 2011. pp. 243-246. ASME. https://doi.org/10.1115/PVP2011-57274
Download citation file:
15
Views
Related Proceedings Papers
Related Articles
Review and Consideration of Unsettled Problems on Evaluation of Fatigue Damage in LWR Water
J. Pressure Vessel Technol (February,2007)
Revised Proposal of Fatigue Life Correction Factor F en for Carbon and Low Alloy Steels in LWR Water Environments
J. Pressure Vessel Technol (November,2004)
Current Status of Reactors Deployment and Small Modular Reactors Development in the World
ASME J of Nuclear Rad Sci (October,2020)
Related Chapters
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Section III: Subsections NC and ND — Class 2 and 3 Components
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Fourth Edition
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards