Document: NUREG-0800
Document ID: b6b57a00-5b85-4f0c-965c-ca89ef4265e7
Document Type: srp
Title: DETERMINATION OF RUPTURE LOCATIONS AND DYNAMIC EFFECTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16088A041.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2
CFR Part: 
CFR Title: 

Content:
des an acceptable method of complying with the regulations that underlie the SRP acceptance criteria. If the design assumptions in the DC application deviate significantly from the SRP, the staff will use the SRP as specified in 10 CFR 52.47(a)(9). Alternatively, the staff may supplement the SRP section by adding appropriate criteria to address new design assumptions. The same approach may be used to meet the requirements of 10 CFR 52.79(a)(41) for COL applications or 10 CFR 52.17(a)(1)(xii) for ESP applications. VI. REFERENCES 1. American Nuclear Society. “Design Basis for Protection of Light Water Nuclear Power Plants Against the Effects of Postulated Pipe Rupture,” ANSI/ANS 58.2-1988, LaGrange, IL., 1988 Edition. 2. American Society of Mechanical Engineers,ASME, “Power Piping,” B31.1-2004, New York, NY., 2004. 3. Moody, F. J., “Prediction of Blowdown and Jet Thrust Forces,” ASME Paper 69 HT-31, August 6, 1969. 4. Ransom, V., “Comments on GSI-191 Models for Debris Generation,” September 14, 2004, ADAMS Accession No. ML050830341, and No. ML051320338. 5. 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.” 6. U.S. Code Of Federal Regulations, “Reactor Site Criteria,” Part 100, Chapter 1, Title 10, “Energy,” Appendix A, “Seismic and Geologic Siting Criteria for Nuclear Power Plants.” 7. U.S. Nuclear Regulatory Commission, “Protection against Postulated Piping Failures in Fluid Systems Outside Containment,” BTP 3-3. 3.6.2-14 Revision 3 – December 2016 8. U.S. Nuclear Regulatory Commission, “Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment,” BTP 3-4. 9. U.S. Nuclear Regulatory Commission, “Asymmetric Blowdown Loads on PWR Primary Systems,” (resolution of Generic Task