Document: NRC Regulatory Guide
Document ID: 5810150e-ee20-4cd1-b72f-6e918a603f73
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:
........................................ 19.36.3 References ................................................................................................................ 19.37 Containment Isolation .............................................................................................................. 19.38 Reactor Vessel Reflooding ....................................................................................................... 19.39 In-Vessel Retention of Molten Core Debris ................................................................................ 19.39.1 Introduction ............................................................................................................ 19.39.2 Background on the Application of In-Vessel Retention to the Passive Plant ................. 19.39.3 Application of In-Vessel Retention to the AP1000 Passive Plant ................................ 19.39.4 Reactor Vessel Failure Criteria.................................................................................. 19.39.5 In-Vessel Melt Progression and Relocation ................................................................ 19.39.6 Application of Heat Transfer Correlations to the AP1000 ........................................... Appendix A to DG-1325, Page A-27 19.39.7 Quantification of Heat Load on the Reactor Vessel Wall............................................. 19.39.8 Reactor Coolant System Depressurization.................................................................. 19.39.9 Reactor Cavity Flooding .......................................................................................... 19.39.10 Reactor Vessel Insulation Design Concept ................................................................ 19.39.11 Reactor Vessel Failure.............................................................................................. 19.39.12 Summary ............................................................................................................