Document: NUREG-0800
Document ID: b3748a15-3b80-4626-a0a5-eb9f270739ad
Document Type: srp
Title: DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS ASSOCIATED
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340555.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2
CFR Part: 
CFR Title: 

Content:
pt of physical separation to the extent practical and has been used for those plants for which construction permit applications were tendered after July 1, 1973 and before July 1, 1975 as specified in Section B.4 of BTP ASB 3-1. BTP MEB 3-1 has been used for all construction permit applica- tions, in lieu of References 2 and 3, since July 1, 1975 and should be used for future applications. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases." 2. Attachment to letter from A. Giambusso, December 1972, "General Information Required for Consideration of the Effects of a Piping System Break Outside Containment," Appendix B to BTP ASB 3-1 (attached to SRP Section 3.6.1). 3. Letter from J. F. O'Leary, July 12, 1973, and attachment entitled, "Criteria for Determination of Postulated Break and Leakage Locations in High and Moderate Energy Fluid Piping Systems Outside of Containment Structures,' Appendix C to BTP ASB 3-1 (attached to SRP Section 3.6.1). 4. Branch Technical Position MEB 3-1, "Postulated Rupture Locations in Fluid System Piping Inside And Outside Containment," attached to this SRP section. 5. Branch Technical Position ASB 3-1, "Protection Against Postulated Piping Failures in Fluid Systems Outside Containment" (attached to SRP Section 3.6.1). 6. F. J. Moody, "Prediction of Blowdown and Jet Thrust Forces," ASME Paper 69 HT-31, August 6, 1969. 7. NUREG-0609, "Asymmetric Blowdown Loads on PWR Primary Systems," resolution of Generic Task Action Plan A-2. | 3.6.2-9 Rev. 1 - July 1981 BRANCH TECHNICAL POSITION MEB 3-1 POSTULATED RUPTURE LOCATIONS IN FLUID SYSTEM PIPING INSIDE AND OUTSIDE CONTAINMENT A. BACKGROUND This position on pipe rupture postulation is intended to comply with the require- ments of General Design Criteria 4, of Appendix A to 10 CFR Part 50 for the design of nuclear power plant structures and components. It is recognized that pipe rupture is a rare event which may only occur under