Document: NUREG-0800
Document ID: 97a2640e-1397-48f5-9deb-e66c4209c27f
Document Type: srp
Title: -16
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1233/ML12334A360.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.3
CFR Part: 
CFR Title: 

Content:
Draft Revision 3 – June 2013 The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision The positions stated in Section C.1.1, 4th and 5th paragraphs of Appendix A to this SRP section, and SRP Section 3.12, to address stress and fatigue evaluation/analyses for ASME Code Class 1 piping (including susceptible Class 2 and 3 piping) subject to cyclic thermal stratification and striping, etc. apply to new applications only. VI. REFERENCES 1. 10 CFR 50.55a, "Codes and Standards." 2. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants": (a) GDC 1, "Quality Standards and Records," (b) GDC 2, "Design Bases for Protection Against Natural Phenomena," (c) GDC 4, "Environmental and Dynamic Effects Design Bases," (d) GDC 14, "Reactor Coolant Pressure Boundary," and (e) GDC 15, "Reactor Coolant System Design." 3 ASME Boiler and Pressure Vessel Code, Section III, Division 1, "Nuclear Power Plant Components," American Society of Mechanical Engineers. 4. 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." 5. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Appendix O, "Rules for the Design of Safety Valve Installations." 6. ASME Code for Operation and Maintenance of Nuclear Power Plants. 7. ASME Standard QME-1-2007, “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants.” 8. NUREG-0484, "Methodology for Combining Dynamic Loads." 9. NUREG-0609, "Asymmetric Blowdown Loads on PWR Primary Systems." 10. NUREG-1367, "Functional Capability of Piping Systems." 11. NRC Bulletin 88-08, “Thermal Stresses in Piping Connected to Reactor Coolant Systems,” June 22, 1988 and its Supplements 1 through 3. 12. NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification,