Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor. Final report

Technical Report · Tue Feb 01 00:00:00 EST 1994

DOI:https://doi.org/10.2172/10133164· OSTI ID:10133164

Donoghue, J E; Donohew, J N; Golub, G R; Kenneally, R M; Moore, P B; Sands, S P; Throm, E D; Wetzel, B A ^[1]

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1. Nuclear Regulatory Commission, Washington, DC (United States). Associate Directorate for Advanced Reactors and License Renewal

This preapplication safety evaluation report (PSER) presents the results of the preapplication desip review for die Power Reactor Innovative Small Module (PRISM) liquid-mew (sodium)-cooled reactor, Nuclear Regulatory Commission (NRC) Project No. 674. The PRISM conceptual desip was submitted by the US Department of Energy in accordance with the NRC`s ``Statement of Policy for the Regulation of Advanced Nuclear Power Plants`` (51 Federal Register 24643). This policy provides for the early Commission review and interaction with designers and licensees. The PRISM reactor desip is a small, modular, pool-type, liquid-mew (sodium)-cooled reactor. The standard plant design consists of dim identical power blocks with a total electrical output rating of 1395 MWe- Each power block comprises three reactor modules, each with a thermal rating of 471 MWt. Each module is located in its own below-grade silo and is co to its own intermediate heat transport system and steam generator system. The reactors utilize a metallic-type fuel, a ternary alloy of U-Pu-Zr. The design includes passive reactor shutdown and passive decay heat removal features. The PSER is the NRC`s preliminary evaluation of the safety features in the PRISM design, including the projected research and development programs required to support the design and the proposed testing needs. Because the NRC review was based on a conceptual design, the PSER did not result in an approval of the design. Instead it identified certain key safety issues, provided some guidance on applicable licensing criteria, assessed the adequacy of the preapplicant`s research and development programs, and concluded that no obvious impediments to licensing the PRISM design had been identified.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Reactor Regulation; Nuclear Regulatory Commission, Washington, DC (United States). Associate Directorate for Advanced Reactors and License Renewal
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10133164
• Report Number(s): NUREG-1368; ON: TI94008221; TRN: 94:008467
• Resource Relation: Other Information: PBD: Feb 1994
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
LMFBR TYPE REACTORS
DESIGN
REACTOR SAFETY
CONTAINMENT
FUEL ELEMENTS
REACTIVITY
REACTOR CONTROL SYSTEMS
AFTER-HEAT REMOVAL
SAFETY ANALYSIS
TESTING
REACTOR LICENSING
PROGRESS REPORT
210500
220900
POWER REACTORS
BREEDING