Upload
lyduong
View
223
Download
0
Embed Size (px)
Citation preview
Experience on APR1400 Construction
IAEA TWG-LWRVienna, July 26-28, 2011
Jong Tae Seo
1/14
1. APR1400 Design Development
2. APR1400 Design Characteristics
3. FOAK Project – Shin Kori 3&4
4. Summary
2 APR1400
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
Development Strategy
APR1400 Design Development
3 APR1400
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
Uprate power to 4,000 MWth (1,450 MWe) based on OPR1000’s 2,825 MWth (1,050 MWe) technology
Incorporate Advanced Design Features to enhance safetyand operational flexibility
Meet the Utility Requirements (domestic & world-wide) Proven Technology Constructability Maintainability Regulatory Stabilization
Development Strategy
APR1400 Design Development
4 APR1400
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
* OPR1000 : Optimized PowerReactor 1000
*APR1400 :Advanced Power Reactor 1400
1,400 MWeUnder Construction
- SKN # 3,4, SUN # 1,2
NSSS DesignPalo Verde #2 (CE,1300MWe)
Core DesignANO #2 (CE,1000MWe)
OPR10001,000 MWe
- In Operation - YGN #3,4 (’95/’96) - UCN #3,4 (’98/’99)
Improved OPR10001,000 MWe
- In Operation - YGN #5,6 (’02/’02) - UCN #5,6 (’04/’05)- Under Construction - SKN #1,2 - SWN #1,2
ADF/PDFLatest Codes & Standards
EPRI URDSystem 80+
APR1400 Design Development
5 APR1400
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
Phase I (’92.12 – ’94.12): Conceptual Design- Reactor Type Selection- Development of Top-Tier Design Requirements- Comparative Study on Major Systems and Components
Phase I (’92.12 – ’94.12): Conceptual Design- Reactor Type Selection- Development of Top-Tier Design Requirements- Comparative Study on Major Systems and Components
Phase II (’95.3 – ’99.2): Basic Design- Development of Detailed Design Requirements- Development of Design Specifications for NSSS Major Components- Preparation of Standard Safety Analysis Report
Phase II (’95.3 – ’99.2): Basic Design- Development of Detailed Design Requirements- Development of Design Specifications for NSSS Major Components- Preparation of Standard Safety Analysis Report
Phase III (’99.3 – ’01.12): Optimization and Licensing- Design Optimization- Detailed Design of Long-Lead Items- Licensing of the Standard Design
Development Phases
APR1400 Design Development
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
6 APR1400
Standard Design Approval by KINS in 2002
Design Review
Standard Design Approvalof APR1400
Standard Safety Analysis Report
APR1400 Design Development
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
7 APR1400
Parameters APR1400Thermal/ Elec. Power 4,000 MWt / 1,450 MWeDesign Life 60 YearsSeismic Acceleration 0.3 g
Operating Parameters- Thot / Tcold 615 / 555 OF- Operating Pressure 2250 psia- RCS Flow Rate 1.66 x 106 lb/hr- Main Steam Pressure (@Full Power) 1000 psia- Main Steam Flow Rate 8.975 x 106 lb/hr
Safety Parameters - CDF 2.25 x 10-6 < 10-5/RY- Containment Failure Frequency 7.19 x 10-7 < 10-6/RY- Thermal Margin >10%- Emergency Core Cooling System 4-train, DVI,
Fluidic Device in SITPerformance Requirements- Plant availability More than 90 %- Unplanned trip Less than 0.8/year- Refueling cycle 18 ~ 24 months
Design Parameters
APR1400 Design Development
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
8 APR1400
RCS Configuration
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
9 APR1400
Reactor Core
Number of assemblies : 241
Thermal margin : above 10 %
Refueling cycle : over 18 months
Batch average burn-up : 55,000 MWD/MTU
Enhanced operational flexibility
- Daily load follow operation capability
- MOX loading capability up to 1/3 core
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
10 APR1400
Reactor Vessel & Internal
Reduced radiation exposureReduced radiation exposure• Reduced Cobalt contents in base material
Integrated Lower Internal AssemblyIntegrated Lower Internal Assembly
• Welded IBA to UGS upper flange - Eliminate tie rods, round nuts,
snubber flange & Block
Integrated Inner Barrel AssemblyIntegrated Inner Barrel Assembly
• Integrated core support barrel, core shroud,and lower support structure in one assembly
Enhanced RV integrityEnhanced RV integrity• No weld seam in fuel region shell• Using low Copper contents material
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
11 APR1400
Integrated Head Assembly (IHA)
Integrated ComponentsIntegrated Components• Head area cable tray
system, CEDM air handling unit, cooling duct, cooling manifold and head lift rig, etc.
IHA ReducesIHA Reduces• Refueling Time• Occupational Radiation
Exposure• Component Storage Area• Seismic Load
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
12 APR1400
Reactor Coolant Pump
Vertical pump
Motor-driven centrifugal pump
Bottom suction & horizontal discharge
Single stage impeller
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
13 APR1400
Pressurizer with POSRV
Increased VolumeIncreased Volume• Total volume : 2,400 ft3
• Enhancing coping capability against plant transients
• Performing over-pressure protection and safety depressurization
• Main valve open by pilot valve actuation • Steam/Water/Two-Phase discharge• No drift of the opening set-point• Reliable valve operation without
chattering and leakage• Low susceptibility for valve stuck-open
Pilot Operated Safety Relief ValvePilot Operated Safety Relief Valve
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
14 APR1400
Steam Generator
• Increasing space to install SG nozzle dam- Improving stability in mid-loop operation
Modified SG Inlet Nozzle AngleModified SG Inlet Nozzle Angle
• Increased anti-vibration bars- Reducing flow-induced tube vibration
Improved Tube Support Bars and PlateImproved Tube Support Bars and Plate
Design ParametersDesign Parameters• Integral Economizer• Number of tubes : 13,102 / SG• Plugging margin : 10 %• Tube material : Inconel 690
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
15 APR1400
Safety Injection System
CONTAINMENT
SITSIT
SIT SIT
S/G RV S/G
SIP
SIP
SIP
SIP
IRWSTRCP
RCP
RCP RCP
• No safety injection water spillage in cold-leg break LOCA
• Increase the reliability of the injection during LOCA
Simplified DesignSimplified Design
Direct Vessel InjectionDirect Vessel Injection
• Mechanically independent 4 train• 1 SIP/train• 1 SIT/train• No low pressure pumps• One injection mode
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
16 APR1400
Safety Injection Tank with Fluidic Device
Fluidic Device Fluidic Device
• Extend injection duration of SIT
• Playing a role of low pressure SIP
• Flow rate depends on the Stand Pipe
height and resistance of Supply Port &
Control Port
Safety Injection TankSafety Injection Tank
• Design pressure : 700 psig
• Volume : 18000 gal (1 ea)
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
17 APR1400
Cylindrical Containment with IRWST
Pre-stressed concrete structurePre-stressed concrete structure
Steel-lined inner surface for leak-tightnessSteel-lined inner surface for leak-tightness
• Height: 229.5 ft, Diameter: 150 ft, Thickness: 4 ft• Design Pressure: 60 psig
• Eliminates switch-over operation during LOCA• Heat sink for feed and bleed operation• Minimizes contamination of Reactor Containment Building
In-containment Refueling Water Storage Tank (IRWST)
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
18 APR1400
Containment Protection System
Containment Hydrogen Control SystemContainment Hydrogen Control System
Containment Spray SystemContainment Spray System• Design characteristics
- 2 pumps (Backed up by 2 SCPs)- Water source : IRWST
• Functions- Maintaining hydrogen concentration belowdesign criterion
• Design characteristics- 30 Passive Autocatalytic Recombiners(PAR) - 10 Glow plug type igniters
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
19 APR1400
Severe Accident Mitigation System
Reactor Cavity Flooding SystemReactor Cavity Flooding System
In-Vessel Retention – ERVC strategyIn-Vessel Retention – ERVC strategy
• Flooding reactor cavity to cool molten core• Water Source : IRWST• Water driving force : Gravity• Designed in accordance with SECY-93-087
- Cavity floor area > 0.02 ㎡/MWt
• Submerging reactor vessel lower head to cool and to retain molten core in reactor vessel
• Water source : IRWST• Water driving force : SCP, BAMP
M M
M
ExistingNew
Cavity
Reactor Coolant System
Containment Building
HVT
IRWST IRWSTM M
External Reactor Vessel Cooling System for In-Vessel Retension (Active Feature)
Gravity Driven Cavity Flooding System for Ex-Vessel Coooling (Passive Feature)
Aux. Building
SCP (5000 gpm)
BAMP (200 gpm)
CVCS
RCS
M
M MMM
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
20 APR1400
MMIS Overview
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
21 APR1400
APR1400 Design CharacteristicsAdvanced Control Room
• Major components
- Redundant compact workstation
with soft control
- Large display panel
- Advanced alarm system
- Safety console
· Backup for common mode failure
- Computerized procedure system
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
22 APR1400
Layout : Slide-along Arrangement (2 units)
• Auxiliary Building (AB)- Quadrant arrangement to enhance safety- Accommodating MCR, Emergency D/G,Fuel handling facilities
• Reactor Containment Building (RCB)- Pre-stressed cylindrical wall and hemi-spherical dome concrete structure
- Wrapped around by auxiliary building
• Compound Building (CB)- Accessible from both units- Housing common facilities of Access control, Radwaste treatment, Hot machine shop, etc
• Turbine Building (TB)- Steel structure with reinforced concrete
turbine pedestal- Common tunnel for all underground facilities
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
23 APR1400
Quadrant Arrangement of Safety Components
Quadrant C Quadrant A
Quadrant D Quadrant B
CCWP 3
CCWP 4 CCWP 2
CCWP1
SCP 1
SCP 2
SIP 3
SIP 2
SIP 1
SIP 4CSP 2
CSP 1
SIP ( Safety Injection Pump) SCP (Shutdown Cooling Pump) CSP (Containment Spray Pump) CCWP (Component Cooling Water Pump)
APR1400 Design Characteristics
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
24 APR1400
FOAK Project – Shin Kori 3&4
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
25 APR1400
Brief History
FOAK Project – Shin Kori 3&4
Feb. 2001 : Set up basic construction plan for SKN 3&4
May 2002 : Received Standard Design Certification for APR1400
Aug. 2006 : Contract signing for A/E, NSSS, TG
Nov. 2006 : Contract signing for ICD/Fuel
Mar. 2007 : Contract signing for Construction
Sep. 2007 : Started site grading
Apr. 2008 : Received Construction Permit / Started excavation
May 2011 : Operating License Application
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
26 APR1400
Milestone Schedule (Unit 3)
FOAK Project – Shin Kori 3&4
Site Grading : Sep. 13, 2007
Excavation(CP) : Apr. 15, 2008
First Concrete Pouring : Oct. 16, 2008
Set Reactor Vessel : Jul. 15, 2010
First Energization : Jun. 1, 2011
Cold Hydro Test : May 2012
Fuel Loading(OL) : Jan. 2013
Commercial Operation : Sep. 2013
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
27 APR1400
Project Progress
FOAK Project – Shin Kori 3&4
2007 2008 2009 2010 2011 2012 2013 2014
Unit3
Unit4
10/169/13 4/15
9/13 4/15
SiteGrading(9/13)
Excava-tion(4/15)
RVSet(8/1)
1st
Energ-ization(7/1)
FirstConcrete(11/1)
7/1 5/1 9/1 1/1 9/308/19 7/18
HFT(9/1)
FuelLoading(1/1)
CHT(5/1)
Commercial Operation(9/30)
7/15 6/1
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
28 APR1400
Project Progress
FOAK Project – Shin Kori 3&4
0.00
10.00
20.00
30.00
40.00
50.00
60.00
70.00
80.00
90.00
100.00
0.00
5.00
10.00
15.00
20.00
25.00
2001년 2002년 2003년 2004년 2005년 2006년 2007년 2008년 2009년 2010년 2011년 2012년 2013년 2014년
As of June 30, 2011
○ Plan : 74.26%
○ Actual : 74.85%
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
29 APR1400
Project Structure
FOAK Project – Shin Kori 3&4
Equipment Start-upConstruction
T/G
DOOSAN
BOP
KHNP
A/E
KEPCO E&C KHNP
KEPCO E&C WEC
LocalConstructors
Project Management
KHNP
FUEL
KEPCO NF
NSSS
DOOSAN
GE Vendors
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
30 APR1400
Construction Activities
FOAK Project – Shin Kori 3&4
Reinforcing Bar of Basemat
RCB Exterior Wall 3-tiered CLP ModuleMSIV Room Piping & Valve
MCR Ceiling Structural Steel, etc
Installation of Single or 2 Pieces-Dome Liner Plate
Structural Steel
Pre-fabrication & ModularizationPre-fabrication & Modularization
Improvement of TBN Sole Plate ChippingShortened Post-Tensioning Period
Automatic Welding of Reactor Coolant LoopConcurrent Installation of RC Loop Pipe & RV Internals
Shortened Installation Period of TBN LP Hood & IHA
Other Advanced & Optimized
Process
Other Advanced & Optimized
Process
Steel Deck Plate Method
3D CAD Models for Construction4D Simulation, etc
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
31 APR1400
4D Simulation
FOAK Project – Shin Kori 3&4
Integration of 3D CAD and schedule for providing optimized construction schedule, visualization, and information management Improves constructability Shortens the construction period
4D System
3D CAD
Schedule
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
32 APR1400
Site Views
FOAK Project – Shin Kori 3&4
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
33 APR1400
Manufacturing
FOAK Project – Shin Kori 3&4
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
34 APR1400
Construction Pictures
FOAK Project – Shin Kori 3&4
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
35 APR1400
Construction Pictures
FOAK Project – Shin Kori 3&4
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
36 APR1400
Construction Pictures
FOAK Project – Shin Kori 3&4
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
37 APR1400
Major Contributing Factors
FOAK Project – Shin Kori 3&4
Infrastructure Design, Manufacturing, Procurement, Construction, and
Operation Supply Chain
Well established through continued construction projects Human Resource
Engineers and Workers with ample experience Project Management
Owner (KHNP) leadership and experience National Policy
Strong support from government with long-term plan
IAE
A T
ech
nic
al W
orki
ng
Gro
up
-L
WR
38 APR1400
Summary
• Increased thermal margin• Physically separated quadrant arrangement of safety systems• Adoption of new design features confirmed through design
validation program• Reinforced seismic design basis
Enhanced Safety
• Increased capacity factor and reduced unplanned trips• Reduced construction time by advanced technologies• Extended plant design life
Improved Cost Effectiveness
• Full digitalized I&C system and operator-friendly man-machine interface• Increased operator action time• Reduced occupational radiation exposure
Convenient Operation & Maintenance
39Init
ial P
re-a
pp
lica
tion
Mee
tin
g