Document: NUREG-0800
Document ID: 92d817ac-3ce3-4cf7-8d1a-627e8242fbf2
Document Type: srp
Title: PLANT DESIGN FOR PROTECTION AGAINST POSTULATED PIPING FAILURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070312.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.1
CFR Part: 
CFR Title: 

Content:
The equipment assumed to function in the analyses should be identified and the capability of systems required to function to meet a single active component failure should be described. DRAFT Rev. 3 - April 1996 3.6.1-24 21. A description should be provided of the methods or analyses performed to demonstrate that there will be no adverse effects on the primary and/or secondary containment structures due to a pipe rupture outside these structures. The internal fluid energy level associated with the pipe break reaction may take into 1a. account any line restrictions (e.g., flow limiter) between the pressure source and break location, and the effects of either single-ended or double-ended flow conditions, as applicable. The energy level in a whipping pipe may be considered as insufficient to rupture an impacted pipe of equal or greater nominal pipe size and equal or heavier wall thickness. Piping is a pressure retaining component consisting of straight or curved pipe and pipe 2b. fittings (e.g., elbows, tees, and reducers). A piping run interconnects components such as pressure vessels, pumps, and rigidly fixed 3c. valves that may act to restrain pipe movement beyond that required for design thermal displacement. A branch run differs from a piping run only in that it originates at a piping intersection, as a branch of the main pipe run. Operational plant conditions include normal reactor operation, upset conditions 4d. (e.g., anticipated operational occurrences) and testing conditions. S is the design stress intensity as specified in Section III of the ASME Boiler and 5e. 46 m Pressure Vessel Code, "Nuclear Plant Components." S U is the cumulative usage factor as specified in Section III of the ASME Boiler and 6f. 47 48 A Pressure Vessel Code, Nuclear Power Plant Components." S is the stress calculated by the rules of NC-3600 and ND-3600 for Class 2 and 3 7g. h components, respectively, of the ASME Code Section III Winter 1972 Addenda. S is 49 A the allowable stress