Overview of NuScale Design

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NP-PM-MMYY-XXXX-NP Rev. X

1 © 2013 NuScale Power, LLC

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Overview of NuScale Design

Chris Colbert Chief Operating Officer

Technical Meeting on Technology Assessment

of SMRs for Near-Term Deployment

Chengdu, China -- September 2-4, 2013

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© 2013 NuScale Power, LLC

Outline

• NuScale Background

• NuScale Power Module

• NuScale Power Plant

• Safety

• Economics

• Deployment Status

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NuScale Background

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NuScale Power History

One-third Scale Integral Test Facility

NuScale Control Room Simulator

NuScale Engineering Offices in Corvallis

• Basic design under development since

2000 MASLWR program

• Integral test facility first operational in

2003

• NuScale Power formed in 2007

• Began NRC design certification pre-

application project in April 2008

• Fluor became major investor and

strategic partner in October 2011

• Twelve-reactor simulated control room

commissioned in May 2012 for Human

Factors Engineering development

• Announced Western Initiative for

Nuclear in April 2013

• Currently ~245 FTE’s on project and

~$130MM investment to-date

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Fluor Overview • One of the world's largest publicly owned engineering, procurement,

construction, maintenance, and project management companies.

• Nuclear Engineering and Construction Continuously Since the 1940s

– More than 1,000 projects annually,

serving more than 600 clients in

66 different countries

– Over 42,000 workforce

– Fortune 500 company (#124 in

2012)

– Provided engineering,

construction or maintenance

support to 90 U.S. reactors

– Revenue: $20.8 billion

– New Awards: $27.3 billion

– Backlog: $34.9 billion Fluor Corporate

Headquarters

Dallas, Texas

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NuScale Power Module

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NuScale Power Module

• Factory built nuclear steam supply system:

– Primary system and containment is prefabricated

and shipped by rail, truck or barge

• Integral design with natural circulation cooling:

– Eliminates major accident scenarios

– Eliminates many pumps, pipes, valves

• Immersed in large ultimate heat sink

– Simplifies and enhances safety case

• Built on proven technology

– Innovation is in the design and engineering

• Constructed below grade

– Enhances security and safety

Video 1 Video 2

1 - NSSS and Containment.mp4

2 - How It Works.mpg

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Integrated Helical Coil SG

• Steam Generator is fully integrated

within the reactor pressure vessel

(RPV)

• Contained in annulus between the

upper riser and the RPV shell

• Feed flow enters the feed plenums,

flows upward through the inside of the

tubes and is discharged via the steam

headers

• Reactor coolant flows upward through

the upper riser, is turned by the

pressurizer baffle plate, and flows

down through the helical bundle

RPV

Feed

Inlet

Steam

Outlet

RCS Inlet

Upper

Riser

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New Containment Paradigm

Compact, High-Pressure Containment:

• Equilibrium pressure between reactor and containment following any LOCA is always below containment design pressure

• Insulating Vacuum

– Significantly reduces convection heat transfer during normal operation

– No insulation on reactor vessel -- eliminates sump screen blockage issue (GSI-191)

– Improves steam condensation by eliminating air

– Prevents combustible hydrogen mixture in the unlikely event of a severe accident (i.e., little or no oxygen)

– Eliminates corrosion and humidity problems inside containment

• Immersion in reactor pool provides assured access to ultimate heat sink for long-term cooling

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• Skid mounted

• Controlled fabrication

• Easily transported to site

• Fast onsite installation

• Off-the-shelf models

currently available

• Air-cooled generator

• Adaptable to water or

air-cooled condenser

Independent Turbine/Generators

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Power Module Parameters Reactor Core

Thermal Power Rating 160 MWt

Operating Pressure 8.72 MPa (1850 psia)

Fuel UO2 (< 4.95% enrichment)

Refueling Intervals 24-48 months

Dimensions 19.2 meters x 2.8 meters (Height x Diameter)

Weight 264 tonnes

Containment

Dimensions 25.0 meters x 4.6 meters (Height x Diameter)

Weight 303 tonnes

Power Generation Unit

Number of Reactors One

Electrical Output > 47.5 MWe (gross)

Steam Generator Number Two independent tube bundles

Steam Generator Type Vertical helical tube

Steam Cycle Superheated

Turbine Throttle Conditions 3.1 MPa (450 psia)

Steam Flow 71.3 kg/s (565,723 lb/hr)

Feedwater Temperature 149º C (300º F)

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NuScale Power Plant

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Site Layout

Reactor Building

Radwaste Building

Turbine Building

Switchyard

Water Treatment Facility

Cooling Towers

Warehouse and

Administration

Buildings

Protected Area

ISFSI

Cooling Towers Turbine Building

Video 3

3 - Reactor Loading.mov

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Reactor Building

Main Control Room

Spent Fuel Storage

NuScale Power Modules

Reactor Pool

Video 3

3 - Reactor Loading.mov

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Robust Reactor Building Design

• Robust Seismic Spectrum Bounds most of USA sites (0.5 g ZPA)

– Structure composed almost entirely out of concrete, with well arranged

shear walls and diaphragms which provides for high rigidity.

– Significant portion of the structure located below grade.

• Meets aircraft Impact criteria

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Basic Plant Parameters

Site Plot Plan

Protected Area 42 acres

Construction Area (includes protected area) 520 acres

Water Consumption During Operations

Cooling Water Consumption 36 m3/minute

Potable Water Consumption 34 m3/day

Construction Workforce

Craft Labor (peak) 600

Staff (peak)

(supervisory, field engineers, QA, management, etc) 400

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NuScale Safety

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Passively Safe Reactor Modules

• Natural Convection for Cooling

– Inherently safe, gravity-driven natural

circulation of water over the fuel

– No pumps, no need for emergency

generators

• Seismically Robust

– Containment is submerged in a pool of

water below ground in an robust building

– Reactor pool attenuates ground motion and

dissipates energy

• Simple and Small

– Reactor is 1/20th the size of large reactors

– Integrated reactor design, no large-break

loss-of-coolant accidents

• Defense-in-Depth

– Multiple additional barriers to protect

against the release of radiation to the

environment

High-strength stainless

steel containment 10

times pressure capability

than typical PWR

Water volume to thermal

power ratio is 4 times

larger resulting in better

cooling

Reactor core has only

5% of the fuel of a large

reactor

45 MWe Reactor Module

Pressurizer volume to

thermal power ratio is 5

times larger resulting in

better pressure control

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Decay Heat Removal System

• Two passive, independent single-failure-proof trains

• Closed loop system

• Two-phase natural circulation operation

• DHRS heat exchangers mounted directly on exterior of containment vessel--nominally full of water

• Supplies the coolant inventory

• Natural circulation of primary coolant is maintained

• Pool provides a 3 day cooling supply for decay heat removal

DHR

Actuation

Valve

DHR Heat

Exchanger

FWIV

MSIVs

FWIV

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Emergency Core Cooling System

• Provides a means of removing core decay heat and limits containment pressure by:

– Steam condensation

– Convective heat transfer

– Heat conduction

– Sump recirculation

• Reactor vessel steam is vented through the Reactor Vent Valves (flow limiter)

• Steam condenses on containment

• Condensate collects in lower containment region

• Reactor Recirculation Valves open to provide recirculation path through the core

• Provides >30 day cooling followed by unlimited period of air cooling.

Reactor Building

Pool

Containment

Reactor Vent

Valve

Reactor

Recirculation

Valve

Reactor Vent

Valve

Reactor

Recirculation

Valve

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WATER COOLING BOILING AIR COOLING

Ensuring Long-term Cool-down Unlimited cooling of nuclear fuel without AC or DC power*

*Alternate 1E power system design eliminates the need for 1E qualified batteries to perform

ESFAS protective functions – Patent Pending

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Spent Fuel Pool Safety Increased Cooling Capacity

• More water volume for cooling per fuel assembly than current designs

• Redundant, cross-connected reactor and refueling pool heat exchangers provide full back-up cooling to spent fuel pool.

External Coolant Supply Connections

• Auxiliary external water supply connections are easily accessible to plant personnel and away from potential high radiation zones.

Below Ground, Robust Deep-Earth Structure

• Below ground spent fuel pool is housed in a seismically robust reactor building.

• Stainless steel refueling pool liners are independent from concrete structure to retain integrity.

• Pool wall located underground is shielded from tsunami wave impact and damage.

• Construction of structure below ground in engineered soil limits the potential for any leakage.

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Response to Classic Accident Initiators

Design Basis Accident NuScale Response

Steam system pipe break Reduced consequences from lower energy

release due to low steam generator

inventory

Feedwater system pipe break No change

Reactor coolant pump shaft failure Eliminated with use of natural circulation of

primary coolant

Control rod ejection accident No change

Steam generator tube rupture Reduced likelihood because tubes are in

compression (shell-side primary flow)

Large break loss-of-coolant accident Eliminated by use of integral design

Small break loss-of-coolant accident Reduced consequences due to no heatup

of fuel (already in natural circulation)

Design basis fuel handling accident Reduced consequences due to smaller

source term in half-height assemblies

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Probabilistic Risk Assessment Summary

• State-of-the-art process to evaluate all potential failures

– Risk = frequency of event x consequences

• Used early in design process

• Very low risk profile from internal events

– Full Power Internal Events CDF = 2.9x10-9 module/yr

• Translation:

– Probability of core damage due to NuScale reactor equipment

failures is 1 in 345,000,000 years.

– Operating nuclear reactors in the U.S. have a CDF of ~1x10-5

reactor/yr

– Likelihood of an accident in NuScale reactor is >3,000 times

lower compared to currently operating reactors in the US

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Result: Low Core Damage Frequency

Source: NRC White Paper, D. Dube; basis for discussion at 2/18/09 public

meeting on implementation of risk matrices for new nuclear reactors

10-8

10-7

10-6

10-5

10-4

10-3

NRC Goal (new reactors)

Operating PWRs

Operating BWRs

New LWRs (active)

New PWRs (passive)

NuScale 10-9

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Added barriers between fuel and environment

Conventional Designs

1. Fuel Pellet and Cladding

2. Reactor Vessel

3. Containment

NuScale’s Additional Barriers

4. Water in Reactor Pool

5. Stainless Steel Lined Concrete Reactor Pool

6. Biological Shield Covers Each Reactor

7. Reactor Building

1

2

3 4

5

6

7

Ground level

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Risk = (frequency of failure) X (consequences)

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27 © 2011 NuScale Power, Inc.

Basis for Reducing Emergency Planning Zone

• Passive safety

• Smaller fission product inventory

• Additional fission product barriers

• Longer delay in release of radiation

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Emergency Planning Zone Sizing

• Objective: Change the perception of SMR safety in the simplest

terms by establishing appropriate EPZ limits consistent with the

safety profile of SMR designs at an equivalent level of protection for

people in or beyond the EPZ

• Method: Use the same analytic framework as existing regulations and

modern, risk-informed analytical methods to establish appropriate

EPZ sizes.

• Expectation: results may support EPZ that could be as near as the

site boundary vs. current 10 miles which opens up siting and

application options • NRC early indications supportive (SECY 11-0152)

• Technical results for a design type are prerequisite to NRC approval

• A great deal of policy work and socialization needed with other

government agencies (EPA, HSA, FEMA, state, etc) and stakeholders

(Congress, utilities) that industry must lead and NRC is indicating support.

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Emergency Planning Zone Sizing - Next Steps

• Submit technical methodology paper in August that

provides basis for next round of policy discussions for

technical answer

• Develop overarching Emergency Planning strategy that

includes technical, operational, public outreach and

political components consistent with SMR vendor DCA

submittal timelines.

• Establish specific work that must be done by client

COLA applicants to drive the ultimate solution

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Deployment Status

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Testing: Proving Our Safety Case

Our testing supports reactor safety code development, validation, reactor

design and technology maturation to reduce FOAK risk.

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NuScale Integral System Test Facility

• Q/A program in place

• Initial shakedown tests

completed

• IAEA international standard

problem test completed

• Test facility scaling methodology

sent to NRC - 12/10

• NuScale modifications began

January 2010

• NRC certification testing

underway

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NIST Results and Predictions

RVV Fails

Open

RVV + 2

RRVs Open

SBLOCA Transient (RVV break)

• Core remains covered

• Significant margin to critical heat flux, no fuel heat-up

• Excellent NRELAP5 test predictions

Vessel Pressure Water Level

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Examples: Separate Effects Testing Hardware

Critical Heat Flux Test at Stern Lab (Candada)

Steam Generator Tests at SIET (Italy)

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Full-Scale 12-module Control Room Simulator

ALL MATERIAL COPYRIGHT © 2013 NUSCALE POWER, LLC

Supports HFE studies, control room

staffing exemption, and plant performance

studies

Visited by NRC team in October 2012

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NRC Engagement

Beginning in 2008, we have:

• Held more than 45 NRC technical meetings

• Submitted more than 30 technical/topical papers,

• Supported four NRC staff site visits to NuScale or contractor

facilities as well as visits by two NRC Commissioners to review

progress.

• Initiated the development of a design-specific review standard

• Invested substantial time on generic SMR work that directly

benefits our DC project.

• As of June 2013, NRC has expended over 7000 hours of staff time

(over $2 million in fees) on NuScale work

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NRC Engagement (cont’d)

To complete DCA pre-application, we plan to:

• Hold more than 15 additional NRC technical meetings

• Submit 28 additional technical/topical papers to NRC

• Support at least 2 NRC staff site visits/inspections to NuScale

or contractor facilities as well as solicit visits by at least 1 more

NRC Commissioner

• Obtain over 10,000 hours of additional NRC staff review time

(~$3 million in fees)

• Continue substantial effort on generic SMR work that directly

benefits our program

• Receive NuScale Draft DSRS Q2 2014

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NRC Timeline

Year 1 Year 2 Year 3 Year 4

ACRS

Review &

Approval

DCD

approved

& Issued

Q4 2018

Submit DC

Application

Q3 2015

NRC

Acceptance

Final Safety

Evaluation

Report (SER)

to ACRS for

review

Rulemaking and

public hearings

Review and response to

Requests for Additional

Information

18 Months 9 Months 10 Months

Total projected duration for NRC

Review and Approval -

39 months

Advisory Committee (to the

NRC) on Rector Safeguards

Consistent

with Mike

Mayfield –

NRC Dir ARO

views

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NuScale Deployment

• Western Initiative for Nuclear (WIN) is an exclusive multi-western state collaboration to pursue the deployment of the innovative NuScale SMRs in western states.

• Current participants: NuScale, UAMPS, Energy Northwest, and the states of ID, UT, OR, WA, WY, AZ

• First project expected to be on the Idaho National Laboratory Site

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Deployment Schedule

Fig 5.2_timeline.v7.pdf

Fig 5.2_timeline.v7.pdf

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SMR Economics

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NuScale Value Proposition

Simple

Safe

Economic

Significant improvement in safety

Electricity generation below that of current baseload options

Reduced capital at risk

Flexibility/Scalability in plant size and application

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SMR Vendor Price Estimates

Based on public statements from various US SMR

vendors:

• Levelized cost of electricity (LCOE) estimates of $80-

$100/MWH

• Three years from first safety related

concrete to commercial operation

• Overnight capital costs of $4000-$5000

per kilowatt

• Plant staffing equivalent to existing fleet

FTE / MW

Capital

Taxes (Incl. Property Taxes)

O&M

Fuel and Spent Fuel Costs

Decommissioning Other

2013 Levelized CostsExcludes Owner's Costs

Capital Taxes (Incl. Property Taxes) O&M Fuel and Spent Fuel Costs Decommissioning Other

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SMRs Can Provide Competitive Power

SMR

Vendors

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The dynamics of shale gas

exploration have decoupled

global NG prices

According to WEO 2012, in

June 2012 pricing was as low

as 2.10 $/mmBtu for Henry

Hub, compared to 9.9 in the

UK, 12 in the Mediterranean,

and 17.40 $/mmBtu in NE

Asia

These differentials are driving

a push for increasing LNG

export capacity – increased

US exports would reduce

global spreads and increase

US pricing

Source: BP Statistical Review of World Energy, June 2013

Notes Gas Prices in Selected Global Markets

0.00

2.00

4.00

6.00

8.00

10.00

12.00

14.00

16.00

18.00

20.00

$/M

MB

tu Crude Oil

Japan

Germany

UK

US

Higher Natural Gas Prices ex-US

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Summary

• The NuScale Design:

– Offers proven LWR components in a simple and

innovative operational framework.

– Is supported by comprehensive test programs and

modeling.

– Provides a truly scalable approach to nuclear plant

deployment.

– Captures the “Economy of Small”

– Provides long term protection against “Fukushima type

events (i.e., prolonged SBO) without additional water,

power, or operator action

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47

1100 NE Circle Boulevard, Suite 200

Corvallis , OR 97330

541.207.3931

http://www.nuscalepower.com

Nonproprietary


Chris Colbert

([email protected])

http://www.nuscalepower.com/china

http://www.nuscalepower.com/

http://www.nuscalepower.com/

http://www.nuscalepower.com/china

Documents

Overview of NuScale Design