0
TECHNICAL PAPERS

Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation

[+] Author and Article Information
Fredric A. Simonen, Stephen R. Gosselin

Pacific Northwest National Laboratory,1 Richland, WA 99352

J. Pressure Vessel Technol 123(1), 58-64 (Oct 23, 2000) (7 pages) doi:10.1115/1.1344237 History: Received January 01, 2000; Revised October 23, 2000
Your Session has timed out. Please sign back in to continue.

References

Bush,  S. H., 1988, “Statistics of Pressure Vessel and Piping Failures,” ASME J. Pressure Vessel Technol., 114, pp. 389–395.
Bush,  S. H., 1992, “Failure Mechanisms in Nuclear Power Plant Piping Systems,” ASME J. Pressure Vessel Technol., 110, pp. 225–233.
Jamali, K., 1992, Pipe Failures in U.S. Commercial Nuclear Power Plants, EPRI TR-100380, prepared by Halliburton NUS, Gaithersburg, Maryland, for Northeast Utilities Service Company and the Electric Power Research Institute.
Thomas, H. M., 1981, “Pipe and Vessel Failure Probability,” Reliability Engineering, 2 , pp. 83–124.
Wright, R. E., Stevenson, J. A., and Zuroff, W. F., 1984, Pipe Break Frequency Estimation for Nuclear Power Plants, NUREG/CR-4407, Idaho National Engineering Laboratory, Idaho Falls, ID.
Kulat, S., Riccardella, P., and Fougerousse, R., 1995, Evaluation of Inservice Inspection Requirements for Class 1, Category B-J Pressure Retaining Welds in Piping, ASME Section XI Task Group on ISI Optimization, White Paper Report No. 92-01-01.
EPRI, 1990, Metal Fatigue in Operating Nuclear Power Plants-A Review of Design and Monitoring Requirements, Field Failure Experience, and Recommendations for ASME Section XI Action, prepared by ASME Boiler and Pressure Vessel Code, Section XI Task Group on Fatigue in Operating Plants, for Section XI Working Group on Operating Plant Criteria.
Bush, S. H., Do, M. J., Slavich, A. L, and Chockie, A. D., 1996, Piping Failures in the United States Nuclear Power Plants: 1961–1995, SKI Report 96:20.
Miraglia, F. J., Jr., 1988, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping—Generic Letter 88-01, U.S. Nuclear Regulatory Commission.
Hazelton, W., and Koo, W. H., 1988, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, NUREG-0313, Rev. 2, U.S. Nuclear Regulatory Commission, Washington, DC.
Wu, P. C., 1989, Erosion/Corrosion-Induced Pipe Wall Thinning in U.S. Nuclear Power Plants, NUREG-1344, Division of Engineering and Systems Technology, USNRC, Washington, DC.
EPRI, 1993, Recommendations for an Effective Flow-Accelerated Corrosion Program, NSAC-201L, Electric Power Research Institute, Palo Alto, CA.
Puckorius, P. R., 1993, Service Water System Corrosion and Deposition Sourcebook, EPRI TR-103403, Electric Power Research Institute, Palo Alto, CA.
Licina, G. J., 1988, Sourcebook for Microbiologically Influenced Corrosion in Nuclear Power Plants, NP-5580, Electric Power Research Institute, Palo Alto, CA.
Licina, G. J., 1990, Detection and Control of Microbiologically Influenced Corrosion—An Extension of the Sourcebook for Microbiologically Influenced Corrosion, NP-6815, Electric Power Research Institute, Palo Alto, CA.
Olson, D. E., 1985, “Piping Vibration Experience in Power Plants,” Pressure Vessel and Piping Technology—A Decade of Progress, Pressure Vessel and Piping Division, ASME, NY, pp. 689–705.
EPRI, 1994, EPRI Fatigue Management Handbook, EPRI TR-104534, Electric Power Research Institute, Palo Alto, CA.
Riccardella, P. C., Rosario, D. A., and Gosselin, S. R., 1997, “Fracture Mechanics Analysis of Socket Welds under High Cycle Vibrational Loading,” ASME PVP-Vol. 353, pp. 23–34.
ASME, 1991, ASME Code for Operation and Maintenance of Nuclear Power Plants, Part 3, Requirements for Preoperational and Initial Start-Up Testing of Nuclear Power Plant Piping Systems, American Society of Mechanical Engineers, New York, NY.
ASME Research Task Force on Risk-Based Inspection Guidelines, 1992, Risk-Based Inspection-Development of Guidelines: Volume 2-Part 1 Light Water Reactor (LWR) Nuclear Power Plant Components, CRTD-Vol. 20-2, published by the American Society of Mechanical Engineers Center for Research and Technology Development.
EPRI, 1996, Risk-Informed Inservice Inspection Evaluation Procedures, EPRI TR-106706, Electric Power Research Institute, Palo Alto, CA.
Westinghouse Electric Corporation, 1997, Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection - Topical Report Revision 1, WECAP-14572, Revision 1, work performed by Westinghouse Electric Corporation in collaboration with Northeast Utilities and Virginia Power for the Westinghouse Owners Group.
EPRI, 1997, Application of EPRI Risk-Informed Inservice Inspection Guidelines to CE Plants, EPRI TR-107531, Volumes 1 and 2, Electric Power Research Institute, Palo Alto, CA.
USNRC, 1997, Draft Regulatory Guide DG-1063 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Inspection of Piping, U.S. Nuclear Regulatory Commission, Aug.
Harris, D. O., and Dedhia, D., 1991, Theoretical and Users Manual for pc-PRAISE, A Probabilistic Fracture Mechanics Computer Code for Piping Reliability Analysis, NUREG/CR-5864, U.S. Nuclear Regulatory Commission, Washington, DC.

Figures

Grahic Jump Location
Piping failure events in U.S. nuclear plants (1961–1996)
Grahic Jump Location
Service failures in small-bore piping (<2 in. NPS)
Grahic Jump Location
Service failures in large-bore piping (>2 in. NPS)
Grahic Jump Location
Service failures by system groups
Grahic Jump Location
BWR SCC failures per plant year
Grahic Jump Location
Erosion-corrosion failures per plant year
Grahic Jump Location
Vibration fatigue failures per plant year
Grahic Jump Location
Calculated probability of leak before and after implementation of inspection program

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In