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Containment Inservice Inspection, Repair, Replacement, and Testing | Journal of Pressure Vessel Technology | ASME DC
Proto-Power Corporation, 15 Thames Street, Groton, CT 06340-3652e-mail: RSammata@protopower.com
J. Pressure Vessel Technol 122(3), 255-266 (Apr 07, 2000) (12 pages) doi:10.1115/1.556182 History: Received February 01, 2000; Revised April 07, 2000
Topics: Concretes , Maintenance , Containment , In-service inspection , Inspection , Industrial plants , Leakage
American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWE, Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants.
American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWL, Requirements for Class CC Components of Light-Water Cooled Plants.
American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsection IWA, General Requirements.
United States Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities, Paragraph 50.55a, Codes and Standards.
10 CFR Part 50, 1996, Final Rule, Codes and Standards for Nuclear Power Plants; Subsection IWE and Subsection IWL, Federal Register, Vol. 61, No. 154, August 8, pp. 41303–41312.
10 CFR Part 50, 1999, Industry Codes and Standards; Amended Requirements; Final Rule, Federal Register, Vol. 64, No. 183, September 22, pp. 51370–51400.
American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Rules Construction of Nuclear Power Plant Components.
American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.
United States Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix A, General Design Criteria for Nuclear Power Plants.
United States Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
10 CFR Part 50, 1995, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Federal Register, Vol. 60, No. 186, September 26, pp. 49495–49505.
U.S. Nuclear Regulatory Commission, 1990, Regulatory Guide 1.35, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments, Revision 3, July.
U.S. Nuclear Regulatory Commission, 1990, Regulatory Guide 1.35.1, Determining Prestressing Forces for Inspection of Prestressed Concrete Containments, July.
ASNT, 1991, Standard for Qualification and Certification of Nondestructive Testing Personnel, ANSI/ASNT CP-189-1991, approved March 15.
American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Division 2, Code for Concrete Reactor Vessels and Containments.
ACI 201.1 R68, 1984, Guide for Making a Condition Survey of Concrete in Service, American Concrete Institute, (Note: ACI 201.1R-92, issued in March 1997, is a more recent revision than the R68 Revision referenced in Subsection IWL.)
U.S. Nuclear Regulatory Commission, 1999, Regulatory Guide 1.147, Inservice Code Case Acceptability, ASME Section XI, Division 1, Revision 2, May.
Return to: Containment Inservice Inspection, Repair, Replacement, and Testing
Sammataro RF. Containment Inservice Inspection, Repair, Replacement, and Testing. ASME. J. Pressure Vessel Technol. 2000;122(3):255-266. doi:10.1115/1.556182.