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:
ements to be fulfilled. 57 Closed system isolation valves. Each line that penetrates the reactor containment structure and is neither part of the primary coolant boundary nor connected directly to the containment atmosphere shall have at least one containment isolation valve unless it can be demonstrated that the containment safety function can be met without an isolation valve and assuming failure of a single active component. The isolation valve, if required, shall be either automatic, or locked The word “structure” was added to this SFR-DC to clearly convey the understanding that this criterion applies to designs employing containment structures. In some cases, the word “the” was also added to make the phrase grammatically correct. “Reactor coolant pressure boundary” has been relabeled as “primary coolant boundary” to reflect that the SFR primary system operates at low-pressure and to conform to standard terms used in APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-28 V. Reactor Containment Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC closed, or capable of remote manual operation. This valve shall be outside containment and located as close to the containment as practical. A simple check valve may not be used as the automatic isolation valve. the LMR industry. The use of the term “primary” implies the SFR- DC are applicable to the primary cooling system, not the intermediate cooling system. VI. Fuel and Reactivity Control Criterion SFR-DC Title and Content NRC Rationale for Adaption 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 that may contain radioactivity shall be designed to ensure adequate safety under normal and postulated accident conditions. These systems shall be designed (1) with a capability to