Document: NUREG-0800
Document ID: 3d8f7691-e488-4083-af2f-eef689c0ec98
Document Type: srp
Title: ASME CODE CLASS 1, 2, AND 3 COMPONENTS AND COMPONENT SUPPORTS,
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0704/ML070430397.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.3
CFR Part: 
CFR Title: 

Content:
riterion 1, "Quality Standards and Records"; (b) General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena"; (c) General Design Criterion 4, "Environmental and Dynamic Effects Design Bases"; (d) General Design Criterion 14, "Reactor Coolant Pressure Boundary"; and (e) General Design Criterion 15, "Reactor Coolant System Design." 4. Standard Review Plan Section 3.10, "Seismic and Dynamic Qualification of Mechanical and Electrical Equipment." 5. Appendix A to SRP Section 3.9.3, "Stress Limits for ASME Class 1, 2, and 3 Components and Component Supports, and Core Support Structures Under Specified Service Loading Combinations." 6. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Appendix O, "Rules for the Design of Safety Valve Installations." 7. Regulatory Guide 1.124, "Service Limits and Loading Combinations for Class 1 Linear-Type Component Supports." 8. Regulatory Guide 1.130 "Service Limits and Loading Combinations for Class 1 Plate- and Shell-Type Component Supports." 9. NUREG-0484, "Methodology for Combining Dynamic Loads." 10. NUREG-0609, "Asymmetric Blowdown Loads on PWR Primary Systems." 11. NUREG-1367, "Functional Capability of Piping Systems." 12. NRC Bulletin 88-08, “Thermal Stresses in Piping Connected to Reactor Coolant Systems,” June 22, 1988 and its Supplements 1 through 3. 13. NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification, December 20, 1988. 14. 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). 3.9.3-17 Revision 2 - March 2007 APPENDIX A STRESS LIMITS FOR ASME CODE SECTION III CLASS 1, 2, AND 3 COMPONENTS AND COMPONENT SUPPORTS, AND CORE SUPPORT STRUCTURES UNDER SPECIFIED SERVICE LOADING COMBINATIONS 1. INTRODUCTION Nuclear power plant components and supports are subjected to combinations of loadings derived from plant and