Document: NRC Regulatory Guide
Document ID: 9c99a4b7-8619-41f0-b716-262bfdb03941
Document Type: regulatory_guide
Title: Developing Principal Design Criteria for Non-Light Water Reactors + HISTORY - HISTORY 02/2017 – DG-1330 , Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1630/ML16301A307.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.232
CFR Part: 
CFR Title: 

Content:
rating containment. Not applicable to mHTGR. This criterion is not applicable to the mHTGR. The mHTGR designs do not have a “pressure retaining reactor containment structure” but instead rely on a multibarrier functional containment configuration to control the release of radionuclides. See the mHTGR-DC 16 rationale. 56 Primary Containment isolation. Not applicable to mHTGR. This criterion is not applicable to the mHTGR. The mHTGR designs do not have a “pressure retaining reactor containment structure” but instead rely on a multibarrier functional containment configuration to control the release of radionuclides. See the mHTGR-DC 16 rationale. APPENDIX C. MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR DESIGN CRITERIA Appendix C to DG-1330, Page C-23 V. Reactor Containment Criterion mHTGR-DC Title and Content NRC Rationale for Adaptions to GDC 57 Closed system isolation valves. Not applicable to mHTGR. This criterion is not applicable to the mHTGR. The mHTGR designs do not have a “pressure retaining reactor containment structure” but instead rely on a multibarrier functional containment configuration to control the release of radionuclides. See the mHTGR-DC 16 rationale. VI. Fuel and Reactivity Control Criterion mHTGR-DC Title and Content NRC Rationale for Adaptions to GDC 60 Control of releases of radioactive materials to the environment. Same as GDC 61 Fuel storage and handling and radioactivity control. Same as ARDC The fuel storage and handling, radioactive waste, and other systems which may contain radioactivity shall be designed to assure adequate safety under normal and postulated accident conditions. These systems shall be designed (1) with a capability to permit appropriate periodic inspection and testing of components important to safety, (2) with suitable shielding for radiation protection, (3) with appropriate containment, confinement, and filtering systems, (4) with a residual heat removal capability having reliability and testability that