UAMPS and NuScale Carbon Free Power Project

Transcription

1 UAMPS and NuScale Carbon Free Power Project Intermountain Energy Summit Idaho Falls, Idaho August 9, 2016 NuScale Nonproprietary 2016 NuScale Power, LLC

2 What is a NuScale Power Module? A NuScale Power Module (NPM) includes the reactor vessel, steam generators, pressurizer and containment in an integral package that eliminates reactor coolant pumps and large bore piping (no LB- LOCA) Each NPM is 50 MWe and factory built for easy transport and installation Each NPM has its own skid-mounted steam turbine-generator and condenser Each NPM is installed below-grade in a seismically robust, steel-lined, concrete pool NPMs can be incrementally added to match load growth - up to 12 NPMs for 600 MWe gross (~570 net) total output 2

3 Size Comparison *Source: NRC 3

4 Coolant Flow Driven By Physics Convection energy from the nuclear reaction heats the primary reactor coolant causing it to rise by convection and natural buoyancy through the riser, much like a chimney effect Conduction heat is transferred through the walls of the tubes in the steam generator, heating the water (secondary coolant) inside them to turn it to steam. Primary water cools. Gravity colder (denser) primary coolant falls to bottom of reactor pressure vessel, cycle continues 4

5 NuScale Fuel (NuFuel HTP2 ) Standard 17 X 17 PWR Fuel Assembly Half height 37 FA s/core Enriched ~3.7% ~ 4% MTU of 1000MW core RFO 24-month cycle ~1/3 core replaced MOX capable Areva design and Fab, Richland, Washington 5

6 Full Length SG Testing (TF-2) at SIET Labs Italy Objectives: Obtain tube bundle T/H and flow induced vibration data for validating NRELAP5 and design codes Status: Testing complete Reporting complete NRELAP5 assessment complete Test Article Design: Large tube bundle array w/252 tubes Prototypic fluid conditions inside and outside of tubes Instrumented to characterize global parameters Person 6

7 Testing Progress Test/Demonstration Program Test Facility Status Critical Heat Flux Test Initial Fuel Design Stern Lab, Canada Complete Steam Generator Tube Inspection Feasibility Study Corvallis, Oregon Complete SIET TF1; 3-Coil, Full-Length, Electrically Heated Steam Generator SIET, Piacenza, Italy Complete SIET TF2; 252-Coils, Full-Length, Prototypic Fluid Heated Steam Generator SIET, Piacenza, Italy Complete Upper Module Mock-up OIW, Vancouver, WA Complete Fuel Mechanical and Hydraulic NuFuel HTP2 TM AREVA, Richland, WA Complete Retesting w/hold-down Spring - Complete NIST-1 Facility; Integral System OSU, Corvallis, OR LOCA, Stability, non-loca, Long Term Cooling - Complete Critical Heat Flux NuFuel HTP2 TM AREVA, Karlstein, Germany Complete Steam Generator Orifice Hydraulic Testing Alden, Holden, MA Complete CRA and Drive Shaft Alignment and Drop AREVA, Erlangen, Germany In Test Steam Generator Flow Induced Vibration AREVA, Erlangen, Germany Under Construction CRA/CRAGT Flow Induced Vibration AREVA, Erlangen, Germany Under Construction Percentage of Required DCA Testing Completed: ~90% Total Testing Expenditures to Date: > $30 Million 7

8 LOCA testing for NRELAP5 validation complete HP-01 (volume and elevation) HP-02 (high pressure condensation) HP-03 (DHRX characterization) HP-04 (cooling pool characterization) HP-05 (powered natural circulation flow) HP-06 (CVCS discharge line break) HP-07 (pressurizer spray line break) HP-09 (ECCS RVV spurious opening) NIST-1 Test Facility Stability testing for PIM code validation complete NRC inspection of NIST-1 is complete Long Term Cooling Testing is underway New laser PIV system to measure local cooling pool liquid velocities at containment heat transfer plate. 8

9 Preliminary NRELAP 5 Predictions of NIST-1 CVCS piping rupture (LOCA): Excellent predictions of: reactor and containment vessel water levels reactor and containment vessel pressures through ECCS valve opening Significant margin to core uncovery NRELAP5 correctly captures LOCA physics ECCS trips 9

10 SG Flow Induced Vibration (FIV) Test Hardware Machining of Tube Sheet Tube Bending Rig Tube Supports Vessel Head Tube Bending 10 T

11 11 SG FIV Testing Specimen Vessel Head

12 CRA and Drive Shaft Drop Alignment Test Hardware Counterweight Guide Assembly Fuel Assembly Housing Support Beam Guide Tube/Card Housing 12

13 Pre-Application Activities DCA/NRC Update completed 75+ NRC presentations / pre-application engagements completed five successful test facility NRC QA inspections/audits conducted training sessions for NRC staff submitted seven topical reports that are under acceptance or technical review plans to submit six additional topical reports prior to DCA submittal (August/September) 13

14 Licensing Plan and Status Design Certification Application ~12,000 pages currently - reduce for submittal 94% complete Submittal before 12/31/16 40-month review schedule Request for Additional Info (RAI) responses ~$60-70 MM in NRC fees for DC from start of project NRC pre-application readiness reviews between Aug-Sep 14

15 15 NuScale Advisory Board (NuAB)

16 NuEx Tours NIST, Control Room Simulator and UMM 16

17 NuScale RPV Head Ingot Being Forged 150 inches diameter 30 inches high 142,000 pounds Images Provided courtesy of Sheffield Forgemasters International Ltd 17

18 Project-Based Energy Services Not-for-Profit

19 19 Load growth Regulation Distributed Generation Changing Markets Replacement Capacity Future of Coal fueled generation Clean Air Act Clean Power Plan Future of power market Derivative of coal fueled generation Future of natural gas fueled generation What is the end-goal for C02 reduction Fuel price volatility

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21 UAMPS CFPP Update April 12, 2016 NRC Public Meeting First public NRC Meeting for CFPP UAMPS working to maximize Member Participation in CFPP 33 members involved Utah outreach and stakeholder communications underway Site Use Permit Permit executed February 17 between DOE and UAMPS 99 year term Site Selection Process 4 Acceptable Sites finalizing selection of Preferred Site Engaged in outreach with tribes and state government agencies 21

22 NuScale Plant at INL Preferred Site Location on INL NuScale Impact Plant on View at Preferred Shed of Big Site Southern Location Butte on INL Impact on View Shed of Big Southern Butte 22

23 N NuScale Plant Site Overview cooling towers A warehouse annex building turbine building A reactor building control building switchyard parking turbine building B protected area fence administration building radwaste building ISFSI (dry cask storage) cooling towers B Outer Fence (Protected Area) 1176 X 1278 ft (34.5 Acres) 23

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25 Satellite View of Site Big Lost River Rest Stop ATR CFA INTEC N Closest points of public approach to plant Hwy 20 Big Southern Butte Hwy 26 Proposed location of NuScale Site (approximate) Note: the actual location has not yet been determined within the boundary 25

26 View of Site From Lost River Rest Stop Viewing elevation ~ 6, wide angle rendering NuScale Site (partially occluded, ~ 6 miles from viewer) Big Southern Butte (~ 10 miles from viewer) Southeast Viewing direction South 26

27 NuScale includes unique capabilities for following electric load requirements as they vary with customer demand and rapid output variations from renewables: NuFollow There are three means to change power output from a NuScale facility: Dispatchable modules taking one or more reactors offline for extended periods of low grid demand or sustained wind output Power Maneuverability adjusting reactor power for one or more modules (intermediate time frames) Turbine Bypass bypassing turbine steam to the condenser (short time frames Explored integration with Horse Butte wind farm in Idaho Partnered with Utah Associated Municipal Power Systems and Energy Northwest 27

28 Power (MWe) Typical electrical demand Horse Butte Output NuScale Output (target) 0 4:00 5:00 6:00 7:00 8:00 9:00 10:00 11:00 12:00 13:00 14:00 15:00 16:00 17:00 18:00 19:00 20:00 21:00 22:00 23:00 28

29 Overall UAMPS CFPP Project Schedule Project Development (see detail) Define Team Members and structure Develop Business Model Onboard Partners Site Use Agreements Site Selection Design & Engineering Reference Plant Design Start Finalized Plant Design Complete Final Plant Design Draft DSRS Submit DCA NRC Issue DC Licensing Final DSRS Start COLA Submit COLA NRC Issue COL Site Characterization Construction and Fabrication NPM Fabricator Site Prep & Mobilization Order Modules Start Module Fabrication 1st Safety Concrete Pour 1 st Fuel load Install Module 1 Install Module 12 Operations Start Operational Readiness Program Operator Training Program Accreditation Complete Operational Readiness Program Module 1 COD Module 12 COD 29

30 30 UAMPS and DOE has entered into a use agreement February 2016 Use agreement would serve as the vehicle to allow UAMPS to explore certain sites at INL Final site for CFPP would not be designated in the use permit until after NRC NEPA is complete NEPA strategy DOE conditionally agrees to the future actions pending NRC completing its permitting process Other Provisions Site Access Security Plan Emergency Planning Licensee Control of CFPP Facility Fuel Transport Spent Fuel Storage on site storage covered under NRC COL issued to CFPP Decommissioning DOE Orders

31 EIA LCOE (2013 $/MWh) Conventional Coal $95.10 NGCC $75.20 Advanced Nuclear $95.20 UAMPS Estimated LCOE Reactor ($/MWh) $80.00 UAMPS Estimated LCOE NGCC ($/MWh) $

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33 Mike McGough Chief Commercial Officer The Element of Nu 33