NuScale Power – A Scalable Clean Energy Solution

NuScale Nonproprietary Copyright © 2021 NuScale Power, LLC.

NuScale Power –A Scalable Clean Energy SolutionJanuary 11, 2020

José ReyesCo-founder & Chief Technology Officer

National Academies Study - Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors

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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.

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Questionnaire Topics• NuScale Engineering Team is preparing a detailed response to the questionnaire.

• The topics that will be briefly discussed during this presentation are: ADVANCED REACTOR DESIGN− RESOURCE UTILIZATION− ADVANCED FUEL CYCLE NUCLEAR WASTE MANAGEMENT and DISPOSAL NUCLEAR SECURITY and PROLIFERATION RESISTANCE NUCLEAR SAFETY ADVANTAGES or ATTRIBUTES of your ADVANCED REACTOR DESIGN CHALLENGING TECHNICAL ISSUES for COMMERCIALIZATION CHALLENGING LICENSING ISSUES for COMMERCIALIZATION CONSTRUCTION and OPERATING COSTS

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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 up to 77 MWe− Small enough to be factory built for easy transport and installation− Dedicated power conversion system for flexible, independent

operation− Incrementally added to match load growth− 12 module plant – up to 924 MWe gross− 6 module plant – up to 462 MWe gross− 4 module plant – up to 308 MWe gross

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NuScale Major Technical Parameters

MAJOR TECHNICAL PARAMETERSPlant Parameters Description

4-pack/6-pack/12-pack MW(e) gross 308/462/92412-pack Plant Footprint (m2) 140,000

Reactor Parameters DescriptionReactor type Integral PWRDesign Life (years) 60RPV height/diameter (m) 17.7/2.7Thermal/electrical capacity MW(t)/MW(e) gross

250/77

Coolant/moderator Light water/Light waterPrimary circulation Natural circulationNSSS Primary Side Pressure, MPa 13.8Fuel type/assembly array UO2 pellet/17x17

square, Fuel Cladding Material M5 (Framatome)Number of fuel assemblies in the core

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Fuel Enrichment (%) < 4.95Refueling cycle 18 monthsReactivity control mechanisms Control rod drive, boron

acid solution

MAJOR TECHNICAL PARAMETERSReactor Parameters Description

Fuel Cycle Requirements 3-stage in-out refuelingBalance of Plant Description

Steam Power Conversion Rankine Cycle with Feedwater HeatersSecondary Side Pressure, MPa

4.3

Steam Generators Two Helical Coil Steam Generators with superheat

Key Safety Features DescriptionDecay Heat Removal System Emergency Core Cooling System

Unlimited coping time for core cooling without Operator action, AC or DC power or

water addition. NRC approved for no 1-E power for safety systems.

ATWS Large inherent negative reactivity feedback coefficient

Core Damage Frequency (CDF) 3E-10/module critical year (internal events)

Large Release Frequency (LRF) 2E-11/module critical year (internal events)Seismic Design (SSE) 0.5 g ZPA

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Advance Features of NuScale Technology

34.5 acres (~14 hectares) within the protected area fence

• Safety − Core Damage Frequency (CDF), 3x10-10/module critical year (internal

events)− Seismic Design (SSE), 0.5 g ZPA− No 1-E power for safety− Significant Risk Reduction from ATWS

− Large negative reactivity feedback (moderator and void)− Designed for Site Boundary Emergency Planning Zone

• Functionality− Multi-module control room (6-operators for 12 reactors)− No AC grid connection required for safety

− Off-grid operation− Island Mode, Black-start, First Responder Power− Sized for Coal-fired plant repurposing− Approved for end of the transmission line siting.

• Construction and Operation− Factory fabrication of Modules− In-series refueling with in-house refueling team− Reduced staffing size− Reduced Reactor Scrams

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Overcoming Technology Challenges• NuScale Integral System Test (NIST-1) facility located at Oregon

State University in Corvallis, Oregon• Critical Heat Flux testing at Stern Laboratories in Hamilton,

Ontario Canada• Helical Coil Steam Generator testing at SIET SpA in Piacenza,

Italy• Fuels Mechanical Testing at AREVA’s Richland Test Facility (RTF)

in Richland, WA, USA• Critical Heat Flux testing at AREVA’s KATHY loop in Karlstein,

Germany• Control Rod Assembly (CRA) drop / shaft alignment testing at

AREVA’s KOPRA facility in Erlangen, Germany• Steam Generator Flow Induced Vibration (FIV) testing at SIET

SpA in Piacenza, Italy• Steam Generator Inlet Flow Restrictor Test at Alden Laboratory,

Holden, MA, USA• ECCS Valve Proof of Concept and Demonstration Tests, Target

Rock, NY, USA

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Integrated System Validation; Technology Readiness

• Early completion of Integrated System Validation (ISV) − Systematic approach to verification that the integrated system

supports safe operation− Resulting in NRC approval of operational staffing for safe

operations− Performance based evaluation of hardware, software, and

personnel− Involved training multiple operational crews

− Operators trained similar to a license class; ISV conducted over 30 weeks

• NuScale focuses on maturing SSCs with lower TRLs (<7).

• Detailed program plans with DOE monitored milestones for timely maturing every SSC with TRL less than 9.

Technology Readiness Level of Systems, Structures & Components (SSCs)

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Fuel Cycle, Waste Storage & DisposalLow & Medium Waste• Designed for better than current U.S. fleet top quartile performance in waste minimization on a per megawatt

basis− Less nuclear equipment in design reducing volume of low level waste; Operational best practices utilized

• Design incorporates on-site radioactive waste processing facility− Well established and safe waste handling systems, storage, and removal; Maximize re-use of liquid

waste• Operational practices

− “Zero discharge” operational program• Waste segregation program

− Maximize ability to identify material that can be disposed of through use of industrial waste landfills

High Level Waste• After cooling in the spent fuel pool, used fuel is placed into certified casks – steel containers with concrete shells

– on site of the plant.− NRC’s Waste Confidence Rule states that dry cask storage is a safe and acceptable way to store used fuel

for an interim period at the plant up to 60 years beyond the licensed life of any reactor (i.e., for up to 120 years).

− NuScale’s standard facility design includes an area for the dry storage of all of the spent fuel produced during the 60-year life of the plant.

• U.S. Department of Energy (DOE) has responsibility for the final disposal of used fuel under the Nuclear Waste Policy Act.− Under the Act, the generators of electricity from nuclear power plants must pay into a fund to be used for the

long term disposal of this used fuel; over $40 billion is currently in the Nuclear Waste Fund.Sources: U.S. NRC; U.S. DOE; Nuclear Energy Institute

Image Credit: Nuclear Energy Institute

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Reactors shutdown without Operator Action, AC or DC power, and remains cooled for an unlimited period without adding water.

Reactor Safety(NuScale FSER issued August 2020 on NRC ADAMS website)

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NuScale Safeguards by Design - Preventing Proliferation

• NuScale Safeguards by Design Program Underway since 2012.

− PNNL Study, Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design, PNNL-22000, November 2012.

− PNNL Study, Design Information Verification for Small Modular Reactors, PNNL-29455, issued in December 2019.− PNNL Reaffirmed that the NuScale design is safeguardable.− Many standard International Safeguards methods can be

applied to the NuScale design.− NuScale was commended for accepting and acting upon

feedback from prior PNNL interactions.− PNNL and NuScale already sharing information with IAEA

regarding Design Information Verification (DIV) inspection activities in the NuScale NPM manufacturing and site construction phase.

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First SMR to Undergo Licensing in the U.S.• Design Certification Application (DCA) completed in December 2016.

• Docketed and review commenced by U.S. Nuclear Regulatory Commission (NRC) in March 2017.

NuScale made HISTORY in August 2020 as the first SMR technology to receive U.S. NRC design approval

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A New Approach to Construction and Operation

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NuScale 924 MWe U.S. Plant Cost Summary

• NOAK based on the following First-of-a-Kind (FOAK) cost:

• Design maturity− 2014 original estimate updated in 2017.− Equipment lists, P&IDs, 3D plant models, etc.

• Rigorous and systematic “bottoms up” approach− Conforms to AACE International 18R-97 – Class 4 cost estimate.− Over 14,000 line items (equipment, material, etc.) priced using

Fluor’s current proprietary cost data or actual vendor quotes.

− Labor costs and productivity data from recent U.S. new build projects or applicable Fluor EPC experience and industry data.

Nth-of-a-Kind Cost (NOAK)

2017 USD Generic Southeast U.S. Site 12 module plant 884 MWe net

Excludes:• Warranty• Contingency• Fee

$2,458,735,000$2,850/KW

• NuScale Power Module™ cost estimate – conforms to AACE International Class 3 cost estimateo Performed by experienced large nuclear component manufacturer

Includes: Manufacturing bill of material. Welding, machining, and non-destructive examination processes developed.

o Transportation costs developed by expert heavy load transport engineering team.

o Fluor estimated EPC scope.

• NOAK based on assumed learning from FOAK cost estimate

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Blazing the Trail to Commercialization

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Questions

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José ReyesCo-founder and Chief Technology [email protected]

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Backup Slides

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Who is NuScale Power?• 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 $300M in DOE funding since then.

• >400 employees in 6 offices in the U.S. and 1 office in the U.K.

• Total investment in NuScale to date is greater than (US) $1B. Over 530 patents granted or pending in 20 countries; ASME N-Stamp.

• First project in Idaho (2029 COD); MOU’s with several potential customers worldwide.

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

One-third Scale NIST-2 Test Facility

NuScale Control Room Simulator

NuScale Engineering Offices Corvallis

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NRC Approved NuScale Licensing Topical Reports (14 SERs issued) in addition to FSER

• TR-0116-20825-P-A - Applicability of AREVA Fuel Methodology for the NuScale Design, Revision 1

• TR-0116-21012-P-A NuScale Power Critical Heat Flux Correlation , Revision 1

• TR-0515-13952-NP-A - Risk Significance Determination, Revision 0

• TR-0516-49416-P-A - Non-Loss-of-Coolant Accident Analysis Methodology, Revision 3

• TR-0516-49417-P-A - Evaluation Methodology for Stability Analysis of the NuScale Power Module, Revision1

• TR-0516-49422-P-A - Loss-of-Coolant Accident Evaluation Model, Revision 2

• TR-0616-48793-P-A - Nuclear Analysis Codes and Methods Qualification, Revision 1

• TR-0716-50350-P-A - Rod Ejection Accident Methodology, Revision 1

• TR-0716-50351-P-A - NuScale Applicability of AREVA Method for the Evaluation of Fuel Assembly Structural Response to Externally Applied Forces, Revision 1

• TR-0815-16497-P-A - Safety Classification of Passive Nuclear Power Plant Electrical Systems, Revision 1

• TR-0915-17564-P-A - Subchannel Analysis Methodology, Revision 2

• TR-0915-17565-P-A - Accident Source Term Methodology, Revision 4

• NP-TR-1010-859-NP-A - NuScale Topical Report: Quality Assurance Program Description for the NuScale Power Plant, Revision 5

• TR-1015-18653-P-A - Design of the Highly Integrated Protection System Platform, Revision 2

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NRC Reviewed NuScale Supporting Technical Reports (21)• TR-0116-20781 - Fluence Calculation Methodology and Results, Revision

1

• TR-0316-22048 - Nuclear Steam Supply System Advanced Sensor Technical Report, Revision 3

• TR-0516-49084 - Containment Response Analysis Methodology Technical Report, Revision 3

• TR-0616-49121 - NuScale Instrument Setpoint Methodology Technical Report, Revision 3

• TR-0716-50424 - Combustible Gas Control, Revision 1

• TR-0716-50439 - NuScale Comprehensive Vibration Assessment Program Technical Report, Revision 2

• TR-0816-49833 - Fuel Storage Rack Analysis, Revision 1

• TR-0816-50796 - Loss of Large Areas due to Explosions and Fires Assessment, Revision 1

• TR-0816-50797 - Mitigation Strategies for Loss of All AC Power Event, Revision 3

• TR-0816-51127 - NuFuel-HTP2TM and Control Rod Assembly Designs, Revision 3

• TR-0916-51299 - Long-Term Cooling Methodology, Revision 3

• TR-0916-51502 - NuScale Power Module Seismic Analysis, Revision 2

• TR-0917-56119 - CNV Ultimate Pressure Integrity, Revision 1• TR-1015-18177 - Pressure and Temperature Limits Methodology,

Revision 2 • TR-1016-51669 - NuScale Power Module Short-Term Transient

Analysis, Revision 1• TR-1116-51962 - NuScale Containment Leakage Integrity

Assurance, Revision 1 • TR-1116-52011 - Technical Specifications Regulatory

Conformance and Development, Revision 4• TR-1116-52065 - Effluent Release (GALE Replacement)

Methodology and Results, Revision 1 • TR-1117-57216 - NuScale Generic Technical Guidelines, Revision

1• TR-0818-61384 - Pipe Rupture Hazard Analysis Technical Report,

Revision 2• TR-0918-60894 - NuScale Comprehensive Vibration Assessment

Program Measurement and Inspection Plan Technical Report, Revision 1

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Comparison to a Large Pressurized Water Reactor (PWR)

Typical Large PWR

NuScale Power ModuleTM

Image: U.S. Nuclear Regulatory Commission

Ground Level

Close in size to a largePWR power plant steam

generator

120 ft

200 ft

77 ft

12-Module Reference Plant

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Reactor Building Houses NuScale Power Modules™, Spent Fuel Pool, and Reactor Pool

Reactor Building CraneRefueling Machine Biological Shield

Reactor PoolReactor Vessel Flange Tool

Containment Vessel Flange Tool

NuScale Power Module

Spent Fuel Pool

Ground Surface

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Reliability - U.S. Plant Scrams in 2015

0

2

4

6

8

10

12

14

# Sc

ram

s

Initiating System

Reactor Scrams

Reactor Scrams avoided by innovativefeatures of the NuScale design

64

47

0

10

20

30

40

50

60

70

NuScale Plant avoids 73% of Reactor Scrams

by design

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Evacuated Containment—Enhanced Safety• Containment volume sized so that core does not uncover

following a LOCA• Large reactor pool keeps containment shell cool and

promotes efficient post-LOCA steam condensation • Insulating vacuum

– significantly reduces convection heat transfer during normal operation

– eliminates requirement for insulation on the reactor vessel, thereby minimizing sump screen blockage concerns (GSI-191)

– improves LOCA steam condensation rates by eliminating air– prevents combustible hydrogen mixture in the unlikely event of

a severe accident (i.e., little or no oxygen)– reduces corrosion and humidity issues inside containment

containment

reactor vessel

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Decay Heat Removal System

• Two, 100% redundant trains of DHRS per NuScale Power Module.

− Each train has an independent heat exchanger.

− Each train has two DHRS Actuation Valves.

− Operation of only one valve, in only one of the trains is sufficient to remove all core decay heat.

• DHRS Actuation Valves− No electrical power required to open the

valves.− Automatically opened by:

− An actuation signal, or− Loss of power to the valve

DHR actuation valves

DHR passive condenser

FWIVsMSIVs

UHS - Reactor Pool

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Emergency Core Cooling System (ECCS)

• During ECCS operation, reactor coolant is vented as steam into containment through the Reactor Vent Valves (RVVs).

• Because the containment is in direct contact with the UHS, the steam condenses on the inside surface of the containment vessel.

• The condensate collects in containment and flows back into the RPV through the Reactor Recirculation Valves (RRVs).

• The condensate is then heated again by the core to produce steam that is once again vented through the RVVs. This is a closed boiling-condensing cycle. NOT TO SCALE

3 RVVs

2 RRVs

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General Response to ATWS Events(Controls rods fail to insert on demand)

• Analyses of Loss of FW and LOCA events with failure of all control rods to insert indicate:

− Inherent core physics following ATWS significantly reduces core power without control rods.

− No fuel limits exceeded - Fuel temperature remains below normal operating fuel temperature.

− Self-stabilizing reactivity mechanisms cause core power to match the combined heat removal capability of the passive safety systems.

Core Power Decreases to <10%

Passive Safety Systems Establish Core Heat Removal

Rate

0

10%

Reactivity mechanisms cause core power to match passive

safety system heat removal rate

Core Power

Passive Heat Removal Rate

Perc

ent o

f Cor

e Po

wer

Time

INHERENT NEGATIVE REACTIVTY INSERTION

CORE POWER SELF-DAMPENING

LONG-TERM SYSTEM STABILIZATION

General Response to Anticipated Transients without Scram (ATWS)

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PRA Models Maintained with Design

• PRA in development for ~7 years• ~ 20 staff, includes severe accident analyses• Modeling done using SAPHIRE and MELCOR (and NRELAP5)• PRA models periodically updated to reflect design changes

− Approximately two or three times per year• All operating modes and all hazards

− full-power internal-events− low-power/shutdown− internal fire− internal flood− high winds and hurricanes− seismic− other external events

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Reactor Qualification Test Plan

Summarizes tests planned in support of design certification, first-of-a-kind-engineering and product commercialization

Supports reactor safety code development, validation, reactor design, and technology maturation to minimize technology risk

Structured risk-based process used to identify and prioritize required tests

Focuses on features unique to an integral pressurized water reactor

Includes information for project planning (test descriptions and requirements, etc.)

Living document that is periodically updated to reflect changes in risk or priority

NuScale Reactor Qualification Test Plan PL-1103-3463

(49 Test Programs)

INCLUDING:

Nuclear Fuel Mechanical Nuclear Fuel Thermal Tests Reactor Vessel Internals FIV Control Rod Drive Mechanism

Tests Steam Generator Mechanical Steam Generator Thermal Tests RXM Manufacturing Demo Valve Testing Instrument Sensors Module Protection System

Prototype Upper Module Mock-up Module Assembly Tools Integral System Tests Advanced Manufacturing Component Seismic Tests

The NuScale testing program is guided by the Reactor Qualification Test Plan

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Reports for associated technical studies are available at: www.nuscalepower.com/technology/technical-publications

Beyond Baseload Electricity

https://www.nuscalepower.com/technology/technical-publications

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NuScale Power – A Scalable Clean Energy Solution