Document: NUREG-0800
Document ID: 93a26deb-9fac-4f56-a0c6-8addc960a55b
Document Type: srp
Title: ASME CODE CLASS 1, 2, AND 3 PIPING SYSTEMS, PIPING COMPONENTS AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0700/ML070040002.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.12
CFR Part: 
CFR Title: 

Content:
Review Plan Section 3.7.1, "Seismic Design Parameters.” 6. Standard Review Plan Section 3.7.2, "Seismic System Analysis.” 7. Standard Review Plan Section 3.7.3, "Seismic Subsystem Analysis.” 8. Standard Review Plan Section 3.9.1, "Special Topics for Mechanical Components.” 9. Standard Review Plan Section 3.9.2, "Dynamic Testing and Analysis of Systems, Components, and Equipment.” 3.12-22 March 2007 10. Standard Review Plan Section 3.9.3, "ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures.” 11. Standard Review Plan Section 3.10, "Seismic and Dynamic Qualification of Mechanical and Electrical Equipment Important to Safety.” 12. Appendix A to SRP Section 3.9.3, "Stress Limits for ASME Class 1, 2, and 3 Components and Component Supports, of Safety-Related Systems and Core Support Structures Under Specified Service Loading Combinations." 13. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Appendix O, "Rules for the Design of Safety Valve Installations. 14. Regulatory Guide 1.124, "Design Limits and Loading Combinations for Class 1 Linear-Type Component Supports." 15. Regulatory Guide 1.130, "Design Limits and Loading Combinations for Class 1 Plate- and Shell-Type Component Supports." 16. NUREG-0484, "Methodology for Combining Dynamic Loads." 17. NUREG-0609, "Asymmetric Blowdown Loads on PWR Primary Systems." 18. NUREG-1367, "Functional Capability of Piping Systems.” 19. NRC Bulletin 88-08, “Thermal Stresses in Piping Connected to Reactor Coolant Systems.” 20. NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification, December 20, 1988. 21. NUREG/CR-5416, "Technical Evaluation of Generic Issue 113: Dynamic Qualification and Testing of Large Bore Hydraulic Snubbers"; Nitzel, M. E.; Ware, A. G. EG&G Idaho, Inc.; Page, J. D. NRC; September 1992 (EGG-2571).109. 22. Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants." 23. Regulatory Guide 1.84, "Design and