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:
include the PDC for a proposed facility. o 10 CFR 52.79(a)(4)(i) requires that an application for a combined license include the PDC for a proposed facility. o 10 CFR 52.137(a)(3)(i) requires that an application for a standard design approval include the PDC for a proposed facility. o 10 CFR 52.157(a) requires that an application for a manufacturing license include the PDC for a proposed facility. Related Guidance, Communications, and Policy Statements • NUREG-1338, “Draft Preapplication Safety Evaluation Report for the Modular High-Temperature Gas-Cooled Reactor (MHTGR),” issued December 1995, provides the NRC staff’s review and insights on the mHTGR design (Ref. 3). • NUREG-1368, “Preapplication Safety Evaluation Report for the Power Reactor Innovative Small Module (PRISM) Liquid Metal Reactor,” issued February 1994, provides the NRC staff’s review and insights on the design for the GE-Hitachi PRISM liquid-metal reactor (LMR) (Ref. 4). • NUREG-0968, “Safety Evaluation Report Related to the Construction of the Clinch River Breeder Reactor Plant,” issued March 1983, provides the staff’s evaluation of the Clinch River construction permit application (Ref. 5). • NUREG-1369, “Preapplication Safety Evaluation Report for the Sodium Advanced Fast Reactor (SAFR) Liquid-Metal Reactor,” issued December 1991, provides the NRC staff’s review and insights on the SAFR design (Ref. 6). • SECY-93-092, “Issues Pertaining to the Advanced Reactor (PRISM, mHTGR, and PIUS) and CANDU 3 Designs and their Relationship to Current Regulatory Requirements,” dated April 8, 1993, provides staff insights on issues pertaining to advanced designs and proposes resolutions (Ref. 7). • Staff Requirements Memorandum (SRM)-SECY-93-092, “Issues Pertaining to the Advanced Reactor (PRISM, mHTGR, and PIUS) and CANDU 3 Designs and their Relationship to Current Regulatory Requirements,” issued July 1993, provides the Commission position on topics discussed in