Spotlight
Past Non-Light Water Reactor Activities and Pre-application Safety Evaluation Reports
In the past, the US Nuclear Regulatory Commission (NRC) and its predecessor, the Atomic Energy Commission (AEC), performed reviews of advanced non-Light Water Reactor (non-LWR) designs using the regulations applicable at the time. The table below includes several of the pre-application Safety Evaluation Reports (SERs), along with other NRC documents pertinent to advanced non-LWR technologies. In addition, prelicensing interactions regarding the Next Generation Nuclear Plant (NGNP) began in 2006 and were suspended in 2013.
| Date | Title |
|---|---|
| November 2020 | EPRI Topical Report on Uranium Oxycarbide (UCO) Tristructural Isotropic (TRISO) Coated Particle Fuel Performance |
| July 2014 | Next Generation Nuclear Plant - Assessment of Key Licensing Issues |
| April 2014 | NUREG/KM-0007, NRC Program on Knowledge Management for Liquid-Metal-Cooled Reactors |
| August 2012 | Report to Congress on Advanced Reactor Licensing |
| March 2008 | NUREG/CR-6944, Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) |
| December 2007 | NUREG-1860, Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing - Main Report |
| December 2007 | NUREG-1860 Appendices, Feasibility Study for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing - Appendices |
| October 2004 | Pre-application Safety Assessment Report Related to the Advanced CANDU Reactor 700 Mwe |
| July 2004 | NUREG/CR-6844, TRISO-Coated Particle Fuel Phenomenon Identification and Ranking Tables (PIRTs) for Fission Product Transport Due to Manufacturing, Operations, and Accidents |
| June 2002 | Request for Additional Information on Pebble Bed Modular Reactor (PBMR) Nuclear Fuel; Fuel Fabrication Quality Control Measures and Performance Monitoring Plans and; PBMR Fuel Qualification Test Program |
| February 1994 | NUREG-1368, Pre-application Safety Evaluation Report for the Power Reactor Innovative Small Module (PRISM) Liquid-Metal Reactor |
| April 1993 | SECY 93-092, Issues Pertaining to the Advanced Reactor (PRISM, MHTGR, & PIUS) and CANDU3 Designs and their Relationship to Current Regulatory Requirements |
| December 1991 | NUREG-1369, Pre-application Safety Evaluation Report for the Sodium Advanced Fast Reactor (SAFR) Liquid Metal Reactor |
| March 1989 | NUREG-1338, Draft Pre-application Safety Evaluation Report for the Modular High-Temperature Gas-Cooled Reactor |
| May 1988 | NUREG-1226, Development and Utilization of the NRC Policy Statement on the Regulation of Advanced Nuclear Power Plants |
| March 1983 | NUREG-0968, Safety Evaluation Report Related to the Construction of the Clinch River Breeder Reactor Plant |
| October 1961 | Report from AEC Division of Licensing and Regulation to Advisory Committee on Reactor Safeguards on Peach Bottom Atom Power Station |
Page Last Reviewed/Updated Friday, August 15, 2025
Page Last Reviewed/Updated Friday, August 15, 2025