Document: NUREG-0800
Document ID: a4232dd4-7548-4c1c-9a51-16dc766f1087
Document Type: srp
Title: Revision 2 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070800008.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3
CFR Part: 
CFR Title: 

Content:
, in the reduction of jet discharge. (5) Piping movement should be assumed to occur in the direction of the jet reaction unless limited by structural members, piping restraints, or piping stiffness as demonstrated by inelastic limit analysis. (iii) Leakage Cracks Leakage cracks should be postulated at those axial locations specified in 2.A(v) for high-energy fluid system piping and in those piping systems not exempted 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 BTP 3-4-10 Revision 2 - March 2007 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 A. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Dynamic Effects Design Bases." B. American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Section III, “ Rules for Construction on Nuclear Power Plant Components,” and XI, “Rules for Inservice Inspection of Nuclear Power Plant Components.”New York, NY American Society of Mechanical Engineers. C. Regulatory Guide 1.11, "Instrument Lines Penetrating Primary Reactor Containment." D. U.S. Nuclear Regulatory Commission. SECY-93-087, "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced