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:
the net effect of the prompt inherent nuclear feedback characteristics tends to compensate for a rapid increase in reactivity. The wording has been changed to broaden the applicability from “coolant systems” to additional factors (including structures or other fluids) that may contribute to reactivity feedback. These systems are to be designed to compensate for rapid reactivity increase. 12 Suppression of reactor power oscillations. Same as ARDC The reactor core; associated structures; and associated coolant, control, and protection systems shall be designed to ensure that The word “structures” was added because items such as reflectors, which could be considered either outside or not part of the reactor core, may affect susceptibility of the core to power oscillations. APPENDIX B. SODIUM-COOLED FAST REACTOR DESIGN CRITERIA Appendix B to DG-1330, Page B-4 II. Multiple Barriers Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC power oscillations that can result in conditions exceeding specified acceptable fuel design limits are not possible or can be reliably and readily detected and suppressed. 13 Instrumentation and control. Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions, as appropriate to ensure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the primary coolant boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges. “Reactor coolant pressure boundary” has been relabeled as “primary coolant boundary” to conform to standard terms used in the liquid- metal reactor (LMR) industry. The use of the term “primary” indicates that the SFR-DC are applicable to the primary cooling system, not the