Document: NUREG-0800
Document ID: 22c713a3-851c-4195-8d52-e7a90bcbeed0
Document Type: srp
Title: LEAK-BEFORE-BREAK EVALUATION PROCEDURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600396.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.3
CFR Part: 
CFR Title: 

Content:
n Against Dynamic Effects of Postulated Pipe Ruptures.” October 27, 1987. 6. NUREG/CR-4575, Papaspyropoulos, V., and Others, “ Predictions of J-R Curves with Large Crack Growth from Small Specimen Data,” September 1986. 7. Boiler and Pressure Vessel Code. Section III, “Rules for Construction of Nuclear Power Plant Components.” American Society of Mechanical Engineers; New York, NY. 8. Boiler and Pressure Vessel Code. Section XI, “Rules of Inservice Inspection of Nuclear Power Plant Components.” American Society of Mechanical Engineers; New York, NY. PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.