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:
............................................................................. 5.1.4 System Performance Characteristics ........................................................................... 5.1.5 Combined License Information .................................................................................. 5.2 Integrity of Reactor Coolant Pressure Boundary ......................................................................... 5.2.1 Compliance with Codes and Code Cases .................................................................... 5.2.2 Overpressure Protection ............................................................................................ 5.2.3 Reactor Coolant Pressure Boundary Materials ............................................................ 5.2.4 Inservice Inspection and Testing of Class 1 Components ............................................. 5.2.5 Detection of Leakage Through Reactor Coolant Pressure Boundary ............................. 5.2.6 Combined License Information Items.......................................................................... 5.2.7 References ............................................................................................................... 5.3 Reactor Vessel ......................................................................................................................... 5.3.1 Reactor Vessel Design .............................................................................................. 5.3.2 Reactor Vessel Materials ........................................................................................... 5.3.3 Pressure-Temperature Limits ..................................................................................... 5.3.4 Reactor Vessel Integrity ............................................................................................ 5.3.5 Reactor Vessel Insulation .......................................................................................... 5.3.6