2023 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 401-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

[2K07-09] Nuclear Plant Design 1

Thu. Sep 7, 2023 2:45 PM - 3:35 PM Room K (ES Bildg. 3F ES031)

Chair:Katsumasa Miyoshi(JAPC)

2:45 PM - 3:00 PM

[2K07] Technical Demonstration for NuScale “VOYGRTM

(5) NuScale Engagement with the U.S. NRC under Design Certification and Standard Design Approval

*Ryuki Tahara1,2, Hibiki Nakasone2, Masahiro Nagaki2, Takuya Seshimo2, Yasutomi Morimoto1, Daisuke Koike3, Paul Boyadjian4 (1. JGC, 2. JANUS, 3. IHI, 4. NuScale Power)

Keywords:Small Module Reactor, SMR, NuScale, VOYGR, Nuclear Regulation, DC, SDA

NuScale SMR VOYGRTM is the first SMR design which got approval of Design Certification (DC) and Standard Design Approval (SDA) from the US NRC as US600.
NuScale demonstrates that licensing success for its SMR design depends on three things; (1) Pre-application interactions with the regulator, (2) NRC’s regulatory exemptions mechanism and (3) Objection and Escalation to NRC.
This paper presents the interactions between NRC and NuScale during the period leading up to the application of the DC review. It also highlights NuScale's efforts leading up to the issuance of the SDA for US600. This paper reports on the improvement that was introduced in the US460 SDA application as a result of NuScale's experience with the US600 review.

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