Document: NRC Regulatory Guide
Document ID: b143ccef-ed08-482d-bc4b-b4e012328090
Document Type: regulatory_guide
Title: Applications for Nuclear Power Plants (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1523/ML15233A056.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.206
CFR Part: 
CFR Title: 

Content:
.................................. 3B.2.7 Other Mechanisms .................................................................................................... 3B.3 Leak-before-Break Bounding Analysis ...................................................................................... 3B.3.1 Procedure for Stainless Steel Piping ........................................................................... Appendix A to DG-1325, Page A-8 3B.3.2 Procedure for Non-stainless Steel Piping .................................................................... 3B.3.3 Evaluation of Piping System Using Bounding Analysis Curves ................................... 3B.3.4 Bounding Analysis Results ........................................................................................ 3B.4 Differences in Leak-before-Break Analysis for Stainless Steel and Ferritic Steel Pipe .................. 3B.5 Differences in Inspection Criteria for Class 1, 2, and 3 Systems .................................................. 3B.6 Differences in Fabrication Requirements of ASME Class 1, Class 2, and Class 3 Piping .............. 3B.7 Sensitivity Study for the Constraint Effect on LBB .................................................................... 3B.8 References .............................................................................................................................. APPENDIX 3C REACTOR COOLANT LOOP ANALYSIS METHODS 3C.1 Reactor Coolant Loop Model Description .................................................................................. 3C.1.1 ....Steam Generator Model ............................................................................................ 3C.1.2 Reactor Coolant Pump Model .................................................................................... 3C.1.3 Reactor Pressure Vessel Model .................................................................................. 3C.1.4 Containment Interior Building Structure Model