1.
ASME Boiler and Pressure Vessel Code, 1989, Section III, Nuclear Power Plant Components, Division I and Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Division I, New York, NY.
2.
U.S. Code of Federal Regulations, “Reactor Site Criteria,” Part 100, Appendix A, Title 10, “Energy.”
3.
U.S. Nuclear Regulatory Commissions, 1981, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants—LWR Edition,” USNRC Report NUREG-0800, Revision 1, July.
4.
ASME, 1967, “Power Piping,” USAS B31.1.0, New York, NY.
5.
U.S. Nuclear Regulatory Commission, 1978 “Evaluation of the Plastic Characteristics of Piping Products in Relation to ASME Code Criteria,” NUREG/CR-0261, July.
6.
General Electric Company, 1978, “Functional Capability Criteria for Essential Mark II Piping,” NEDO-21985, Sept.
7.
U.S. Nuclear Regulatory Commission, 1984/85, “Report of the U.S. Nuclear Regulatory Commission Piping Review Committee,” NUREG-1061, 5 Vols.
8.
U.S. Nuclear Regulatory Commission, 1992, “Functional Capability of Piping Systems,” NUREG-1367, Nov.
9.
U.S. Nuclear Regulatory Commission, 1991, “Verification of Piping Response Calculations of SMACS Code with Data from Seismic Testing of an In-plant Piping System,” NUREG/CR-5757 (ANL-91/25), Sept.
10.
ASME Boiler and Pressure Vessel Code, “Code Cases,” 1984a, N-411, Alternative Damping Values for Response Spectra Analysis of Class 1, 2, and 3 Piping, Sept.
11.
ASME Boiler and Pressure Vessel Code, 1984b, “Code Cases,” N-397, Alternative Rules for Spectrum Broadening Procedures of N-1226.3 for Class 1, 2, and 3 Piping Section III, Division 1, Feb.
12.
U.S. Nuclear Regulatory Commission, 1988, “High-Level Seismic Response and Failure Prediction Methods for Piping,” NUREG/CR-5023 (WHC-EP-0081), Jan.
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