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Session 2 - Advanced Reactor Developers Perspectives on Codes and Standards
	ML22266A263
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Site:	Nuclear Energy Institute
Issue date:	09/28/2022
From:	Richter M, Robert Roche-Rivera; NRC/RES/DE/RGDB, Nuclear Energy Institute
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Ad va nce d Re a cto r De ve lo p e rs Pe rsp e ctive s o n Co d e s a nd Sta nd a rd s Moderator: Mark Richter, Technical Advisor, Nuclear Energy Institute Panelists/Speakers:

Mark Richter (NEI)

J.J. Arthur (NuScale)

Steven Unikewicz (TerraPower)

Timothy Lucas (X-Energy) 1

Advanced Reactor Developers Perspectives on Codes and Standards 2022 NRC Standards Forum Mark Richter - NEI September 28, 2022 2

Situational Context Increasing urgency for carbon reduction (electric and non-electric)

Path to zero-carbon must be reliable and affordable Nuclear energy must be meaningful part of future energy portfolio Advanced reactor deployment plans increasing rapidly and more urgently License applications could be more than regulators can currently process 3

Codes and Standards: Important Role The EPRI North American Advanced Reactor Roadmap points to timely development of codes and standard as necessary enablers to the large-scale deployment of advanced reactors Collaboration and engagement among SDOs, reactor designers, regulators, and other interested stakeholders enables development of code and standards Advanced reactor developers are moving forward rapidly with initial licensing and design activities. Consensus standards are design enablers and must move forward to support aggressive timelines 4

Codes and Standards: Focus and Priority Perspectives from three advanced reactor developers will be shared today:

NuScale

Terra Power

X-Energy Well have an opportunity for questions and open discussions following the presentation 5

NuScale Perspectives on Codes & Standards 2022 NRC Standards Forum September 22, 2022 J.J. Arthur, P.E.

Sr. Director, NSSS Engineering 6

Acknowledgement and Disclaimer This material is based upon work supported by the Department of Energy under Award Number DE-NE0008928.

This presentation was prepared as an account of work sponsored by an agency of the United States (U.S.)

Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

Who is NuScale Power?

NuScale Power Corporation is a public company trading on the New York INSERT NEW PHOTO WITH Stock Exchange (NYSE) under the ticker symbols SMR and SMR WS.

NYSE

NuScale Power was formed in 2007 for the sole purpose of completing the design and commercializing a small modular reactor (SMR) - the NuScale Power Module.'

Initial concept was in development and testing since the 2000 U.S.

Department of Energy (DOE) MASLWR program.

Fluor, global engineering and construction company, became lead investor in 2011

2013 - NuScale won a competitive U.S. DOE Funding Opportunity for matching funds, and has been awarded over $400M in DOE funding since then.

>500 employees in 5 offices in the U.S. and 1 office in the U.K.

NuScale valued at $1.9 B and merged with Spring Valley on May 2, 2022.

Investors include JGC, IHI and JBIC

645 patents granted or pending in 20 countries; ASME N-Stamp.

First project in Idaho (2029 COD); MOUs with several potential customers worldwide.

Potential projects being pursued in U.S., UK, Canada, eastern Europe, Middle East, southeast Asia, and Africa.

Core Technology:

NuScale Power Module

A NuScale Power Module' (NPM) includes the reactor vessel, steam generators, pressurizer, and containment in an integral package

Simple design that eliminates reactor coolant pumps, large bore piping and other systems and components found in large conventional reactors

Each module produces 250 MWt up to 77 MWe o Small enough to be factory built for easy transport and installation o Dedicated power conversion system for flexible, independent operation o Incrementally added to match load growth o 12 module plant - up to 924 MWe gross o 6 module plant - up to 462 MWe gross o 4 module plant - up to 308 MWe gross 9

NuScale Power Module Arrangement CIV = containment isolation valve CIVs CNV = containment vessel PZR = pressurizer RVV NPM RPV = reactor pressure vessel piping PZR RRV = reactor recirculation valve SG annular RVI = reactor vessel internals space RVV = reactor vent valve RPV RXM = reactor module SG = steam generator CNV RVI lower riser assembly RVI core support assembly Front of the NPM Section view of the NPM NPM in the bay 10 NuScale Nonproprietary Copyright © 2022 NuScale Power, LLC.

Codes & Standards Needs ASME BPV Code, Section XI

New code rules need to be developed for IWB-3500 standards for application to austenitic vessel materials, dissimilar metal vessel material welds, and austenitic bolting material.

New code rules need to be developed for Section XI, Mandatory Appendix VIII for application to austenitic vessel materials and dissimilar metal vessel material welds.

ASME O&M Code

Need to resolve how to implement a single IST plan for multiple modules ANS 30.3 - Light Water Reactor Risk-Informed, Performance-Based Design

NRC Endorsement 11 NuScale Nonproprietary Copyright © 2022 NuScale Power, LLC.

J.J. Arthur, P.E.

Terra Power Advanced Reactor Types

Natrium Sodium Fast Reactor (SFR)

Molten Chloride Reactor Experiment (MCRE)

Molten Chloride Fast Reactor (MCFR)

Demin Water Firewater Turbine Building Steam Generation Standby Diesels Warehouse

& Admin TI Power Distribution Center Salt Piping Rx Aux. Building Energy Island Inert Gas Shutdown Cooling Rx Building Energy Storage Tanks Control Building Fuel Building NI Power Distribution Center &

Integrated Energy Storage Sodium-Salt Heat Exchanger Reactor Building Loop Tests Fuel Handling Building Reactor Aux. Building Salt loop w/ storage and heat removal Sodium to Salt heat exchanger /

Natrium Profile Conditioned Worker Space Reactor and Power Parameters

Reactor Power Class: 840 MWt

Reactor Type: Pool-Type Sodium Fast Reactor

Reactor Coolant: Liquid Metal (Sodium)

Reactor Fuel Type: Metal Uranium Fuel, Ferritic-Martensitic Outlet Cladding Temperature

Turbine Power Class (Nom): 345 MWe >950F

Turbine Output: Variable (150%+ rated w/ Storage)

Energy Storage Fluid: Molten Nitrate Salt

Energy Storage Capacity: 5+ hours, depending on load Cold Inlet Temperature

Molten Chloride Fast Reactor (MCFR)

The Molten Chloride Reactor Experiment (MCRE) will be the first critical MCFR and will focus on reactor physics Parameter MCRE 100% Thermal Power 200 kW Nominal Temperature 1200°F Nominal Pressure 37 PSI Design Temperature 1300°F Design Pressure 70 PSI Time at Temperature 6000 hr Time at Power 1000 hr (out of 6000 hr)

The MCFR is an advanced molten salt fueled reactor that operates in a breed & burn fuel cycle MCFR: Molten Chloride Fast Reactor

Pool design

Fast spectrum

Fuel salt: NaCl-UCl3 eutectic

Initial U enrichment of 11-13 wt%

Feed depleted UCl3

PuCl3 is bred up

Fuel salt flows out of active core around 8 discrete flow paths

8 axial flow pumps

8 shell & tube PHXs Copyright© 2022 TerraPower, LLC. All Rights Reserved. 20

Codes and Standards Needs

Sodium Fast Reactor applicability is not fully addressed by Codes and Standards currently endorsed and referenced by the NRC. Coordination with Standards Organizations and NRC is ongoing.

Examples - ASME BPV - Section III Division 5 Section XI Division 2, Appendix 7, RIM

- ASME OM-2

- ASME QME-2

Codes and Standards Activities

Activities are ongoing to identify:

- Consensus Codes and Standards or Code Cases intended for use with Advanced Reactors

- Standards or Code Cases that have not been endorsed or previously accepted by the NRC

The needs will be identified as the design progresses Copyright© 2022 TerraPower, LLC. All Rights Reserved. 22

Questions?

Code Overview - NRC 9/28/2022 Dr. Timothy Lucas, Main Power Systems Engineering Manager 24

Agenda

Introduction of the Xe-100 Pebble Bed Reactor

ASME BP&V Section III-5 for RPV and Metallic Internals

ASME BP&V Section III-5 for Graphite Structures

Q&A 25

Xe-100 Introduction

200 MWt, HTGR, Pebble Bed, Helium Heat Transfer Fluid coupled to a Helical Steam Generator Pebble fuel

Proven High Temperature Pebble Bed Reactor elements

Derived from over 50 years of design and development to significantly reducing costs to enable competitive deployment

Proven fuel technology (US DOE Advance Gas Reactor irradiation program)

Versatile Nuclear Steam Supply System (NSSS) that can be deployed for electricity generation and/or process heat applications 26

ASME Code Section III, Division 5 Section III, Division 5 Scope

Construction of High Temperature Reactors

Pressure Boundary, Core Supports, and Supports Structures in an HTR

Covers both high and low temperature service

Construction, is an all-inclusive term comprising materials, design, fabrication, examination, inspection, testing, certification, and overpressure protection.

ASME Code does not address the classification of components, only the construction of components

Historically covered by ANS Standards

Addressed in Regulatory Guides The Xe-100 Safety Classification

NEI 18-04, Risk-Informed Performance-Based Technology Inclusive Guidance for Non-Light Water Reactor Licensing Basis Development

Endorsed by NRC Reg Guide 1.233 Section III, Division 5 Code Classes

Class A

Class B High Temperature Service

Temperatures in the creep regime

Ferritic materials > 375C, Austenitic and Inconel materials > 425C Low Temperate Service

Class A references Class 1 Rules

Class B references Class 2 Rules 27

RPV, PB and Metallic Internal Components Reactor Steam Generators

Pressure Vessel

Pressure Vessel

Reactor Internals

Internal Structures

Cross Vessel

Tubes, Tubesheets and Plenums

Safety Relief Valves

Steam and Feedwater Piping within Isolation Valves

Defuel Chute Vessel

MS and FW Isolation Valves NEI 18-04 Risk Classification Process

Determines AOO, DBE and BDBE based on risk consequence categorizations process

Generally, structures that are needed to stay within the acceptable risk and consequence line for AOO and DBEs are designed to the ASME Code, Section III, Division 5 Xe-100 Risk-Consequence Model

Does not require active cooling or retention of the coolant

Does require that the core geometry be maintained Pressure Retention is not a safety function

Section VIII, Div 2 provides adequate assurance of a high-quality vessel for pressure retention

Section III Design Rules address the unique needs related to nuclear service 28

RPV, PB and Metallic Internal Components X-energy submitted a White Paper to the NRC for comment

Docket No. 99902071

Submitted on July 13, 2020

Requesting informal review and feedback

Part of pre-submittal activities White Paper summarized the proposed approach to design and construct the reactor pressure vessel:

Construct and Stamp to Section VIII, for Design Condition

Design Pressure at Design Temperature and Deadweight

Material Specifications and Purchasing

Pressure Sizing

Quality Assurance

NDE and Testing

Design and Analysis Section III, Division 5, Class A

Design Conditions

Material Requirements

Service Levels A, B, C and D

RPV Embrittlement The CNSC and the USNRC reviewed the white paper and concluded that X-Energys proposed approach for the design and fabrication of the Xe-100 RPV is viable, provided:

X-Energy provides the full technical justification requested

Address both regulators observations documented in this report.

The proposed approach could be used to establish criteria for the Xe-100 design and fabrication of the 29

Graphite Reflector The main governing code of Concern is the ASME B&PV Code, Section III, Division 5, HHA and HAB.

The code provides standards and guidance on the:

Qualification of the Material

Irradiated Material Properties Material being tested for qualification use must be representative

Historical Data must be shown to be applicable if used

Reporting Requirements for Material Data Sheets

Material Specification and use of ASTM standards

Design of Graphite Components and Assemblies

Designer and Supplier Certification

Machining, Examination, Shipping and installation The main question concerning this portion of the code is when the NRC will issue their formal endorsement?

30

Questions 31

X Energy, LLC Phone: 301.358.5600 801 Thompson Avenue

Rockville, MD 20852 x-energy.com @xenergynuclear 32

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