Document: NUREG-0800
Document ID: c6f58bab-ddce-42eb-a3ef-02dd3da952fc
Document Type: srp
Title: Revision 3 – December 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16085A315.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3
CFR Part: 
CFR Title: 

Content:
iping and in those piping systems not excluded in 2.B(iii)(1) for moderate-energy fluid system piping. (1) Leakage cracks need not be postulated in 1-inch and smaller piping. (2) For high-energy fluid system piping, the leakage cracks should be postulated to be in those circumferential locations that result in the most severe environmental consequences. For moderate-energy fluid system piping, see 2.B(iii)(2). (3) Fluid flow from a leakage crack should be based on a circular opening of area equal to that of a rectangle one-half pipe diameter in length and one- half pipe wall thickness in width. (4) The flow from the leakage crack should be assumed to result in an environment that wets all unprotected components within the compartment, with consequent flooding in the compartment and communicating compartments. Flooding effects should be determined on the basis of a conservatively estimated time period necessary to effect corrective actions. C. REFERENCES 1. American Society of Mechanical Engineers, ASME Code, Section III, “Rules for Construction on Nuclear Power Plant Components,” and ASME Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components.” 2. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization,” Part 50, Chapter 1, Title 10, “Energy,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 4, “Environmental and Dynamic Effects Design Bases.” BTP 3-4-11 Revision 3 –December 2016 3. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization,” Part 50, Chapter 1, Title 10, “Energy,” Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 4. U.S. Nuclear Regulatory Commission, “Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11),” Regulatory Guide 1.11. BTP 3-4-12 Revision 3 –December 2016 PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the