ML23165A108

Enclosure 2 - SMR, LLC Meeting Presentation Materials for June 28, 2023

ML23165A108
Person / Time
Site:	99902049
Issue date:	06/28/2023
From:	Lietwiler C Holtec, SMR
To:	Office of Nuclear Reactor Regulation
Shared Package
ML23165A105	List: ML23165A106 ML23165A108 ML23165A109
References
160-USNRC-049
Download: ML23165A108 (1)

Text

10 CFR 50 Appendix K Application to SMR-160 HOLTEC INTERNATIONAL Date: 6/28/2023 Presented By: Clay Lietwiler SMR, LLC, A Holtec International Company Krishna P. Singh Technology Ca~ pus One Holtec Boulevard Camden,NJ08104,USA

[Not Export Controlled]

Agenda

Introductions

Purpose & Outcome LOCA Acceptance Criteria 10 CFR 50 Appendix K Applicability 10 CFR 50.46 Cladding Material Exemption Open Forum OLTEC

[KNA TIO NA L

0 L TEC Purpose & Outcome l ijlTEKNAT ICl N r\\L PURPOSE To provide an overview of the SMR-160 LOCA acceptance criteria, applicability of 10 CFR 50 Appendix K to SMR-160 LOCAs, and identify an exemption to 10 CFR 50.46 as a result of SMR-160 cladding material.

OUTCOME To obtain feedback from the NRC staff on SMR-160's LOCA acceptance criteria, applicability assessment of Appendix K, anld plan for the 50.46 cladding material exemption request.

Background

• . 1.* 0 L T E C l f)J r E R N A T IO N,\\ L The SMR-160 LOCA evaluation model (EM) will follow th guidance in Reg. Guide 1.203 and satisfy the applicable requirements of 10 CFR 50 Appendix K The SMR-160 is designed to reduce the consequences of design basis LOCAs compared to the existing light water reactor fleet for which 10 CFR 50 Appendix K was develooed Some of the phenomena pertaining to 10 CFR 50 Appen do not occur during SMR-160 design basis LOCAs

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SMR-160 LOCA Acceptance Criteria OLTEC l i\\,I I [R N A TIO Ntl l SMR-160 design basis LOCAs will use conservative surrogate acceptance criteria to replace the peak clad temperature (PCT),

oxidation, and hydrogen generation acceptance criteria defined irh 10 CFR 50.46 The SMR-160 LOCA acceptance criteria are:

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LOCA Acceptance Criteria - Questions for NRC Staff

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0 L TEC l!NT[RN A T I ON t\\L

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Appendix K IA - Sources of Heat

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Appendix KIA - Questions for NRC Staff

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Appendix K IB - Swelling and Rupture of the Cladding and Fuel Rod Thermal Parameters OLTEC 11\\1 l[RN A TIO NA L

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Appendix K IC - Blowdown Phenomena

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• . 1.* 0 L T E C l i'\\ITE R NAT I ONA L

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Appendix K IC1 - Questions for NRC Staff

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Appendix K IC2 and IC3 - Frictional Pressure Drops and Momentum Equation e,~N~T

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Appendix K IC4 and ICS-Critical Heat Flux and Post CHF Heat Transfer OLTEC ERN A T I ON,\\ L

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Appendix K ID - Post Blowdown Phenomena; Heat Removal by the ECCS OLTEC l i\\JT [RN A TION,\\L

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Additional 50.46 Cladding Material Exemption

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