Operating nuclear power plant fatigue assessments. Final report

Technical Report · Sat Apr 01 04:00:00 EST 1995

OSTI ID:71380

The purpose of the ASME Section XI Task Group on Operating Plant Fatigue Assessment was to examine the ASME Code requirements for fatigue and to develop a Section XI approach for managing fatigue concerns in operating nuclear plants. As part of this effort, the historical basis of the current ASME Section III design approach for fatigue was revisited. With the benefit of advancing technology, the appropriateness of the existing Code requirements for fatigue in operating nuclear plants was reexamined. The goals of the Task Group were to: review the current ASME Section III Class 1 design rules and evaluation methods for characterizing fatigue damage based on design basis transients and cumulative usage factors; consider prior experience of service-induced failures and adequacy of cumulative usage factor approach for determining actual fatigue life of nuclear Class 1 components; develop alternative analysis methods, guidelines, and criteria for evaluating fatigue concerns and demonstrating fitness for continued service of components subjected to cyclic loading conditions; and provide a Non-Mandatory Appendix for consideration by ASME Section XI which contains alternative evaluation methods and criteria for acceptance that could be used by utilities to evaluate fatigue concerns in operating nuclear plants. This report documents the efforts of the ASME Section XI Task Group. The report is intended to be a technical basis document for the proposed Code appendix, and it will serve as a reference for future ASME Code improvements regarding fatigue in operating nuclear plants.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); American Society of Mechanical Engineers Section XI Task Group on Operating Plant Fatigue Assessment (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 71380
• Report Number(s): EPRI-TR--104691
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
CRACK PROPAGATION
DEFECTS
ENGINEERED SAFETY SYSTEMS
FATIGUE
FRACTURE MECHANICS
INSPECTION
NUCLEAR POWER PLANTS
PIPES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
SEISMIC EVENTS
STANDARDS
STRESS INTENSITY FACTORS
SYSTEMS ANALYSIS
TRANSIENTS