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:
ents. The staff added text to identify other SFR plant areas that should also be included to maintain consideration of all potential discharge paths and areas subject to monitoring. Therefore, primary system sodium and cover gas cleanup systems that may be outside containment and effluent processing systems are considered in place of the current text. VII. Additional SFR-DC Criterion SFR-DC Title and Content NRC Rationale for Adaption to GDC 70 Intermediate coolant system. If an intermediate coolant system is provided, then the system shall be designed to transport heat from the primary coolant system to the energy conversion system as required. The intermediate coolant system shall be designed with sufficient margin to assure that (1) the design conditions of the intermediate coolant boundary are not exceeded during normal operations, including anticipated occupational occurrences, and (2) the integrity of the primary coolant boundary is maintained during intermediate coolant system accidents. NUREG-1368 (Ref. 4) (page 3-57), Section 3.2.4.5, suggested the need for a separate criterion for the intermediate coolant system. Also, separate criteria were included in NUREG-0968 (Ref. 5) (Criterion 31, “Design of Intermediate Cooling System,” and Criterion 33, “Inspection of Intermediate Cooling System”). The staff revised SFR-DC 70 to focus on the function of the intermediate coolant system, and to use language that is consistent with other design criteria. The discussion related to sodium leakage and required barriers was moved to a new SFR-DC 78. Assurance that components of the intermediate coolant system are also designed, as necessary, to prevent the transport of radionuclides between the primary coolant system and the energy conversion system is provided by the design criteria proposed for the intermediate coolant boundary (SFR-DC 75, SFR-DC 76, and SFR-DC 77). Examples of intermediate coolant system accidents would include: rupture (including at a