Document: NRC Regulatory Guide
Document ID: da269da5-7390-4252-b08f-bdb7aeb8beaf
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:
eference has been removed to provide for any postulated accident that might affect subject SSCs. The GDC reference to electric power was removed. Refer to ARDC 17 concerning those systems that require electric power. V. Reactor Containment Criterion ARDC Title and Content NRC Rationale for Adaptions to GDC 50 Containment design basis. The reactor containment structure, including access openings, penetrations, and the containment heat removal system shall be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from postulated accidents. This margin shall reflect consideration of (1) the effects of potential energy sources that have not been included in the determination of the peak conditions, (2) the limited experience and experimental data available for defining accident phenomena and containment responses, and (3) the conservatism of the calculational model and input parameters. ARDC 50 specifically addresses a containment structure in the opening sentence and ARDC 51–57 support the containment structure’s design basis. Therefore, ARDC 51–57 are modified by adding the word “structure” to highlight the containment structure- specific criteria. The phrase “loss-of-coolant accident” is LWR specific because this is understood to be the limiting containment structure accident for an LWR design. It is replaced by the phrase “postulated accident” to allow for consideration of the design-specific containment structure limiting accident for non-LWR designs. The example at the end of subpart 1 of the ARDC is LWR specific and therefore deleted. APPENDIX A. ADVANCED REACTOR DESIGN CRITERIA Appendix A to DG-1330, Page A-21 V. Reactor Containment Criterion ARDC Title and Content NRC Rationale for Adaptions to GDC 51 Fracture prevention of containment pressure boundary. The boundary of the