NPP-Nuclear Island Design From conceptual design to Project execution … · 2016-08-25 ·...
Transcript of NPP-Nuclear Island Design From conceptual design to Project execution … · 2016-08-25 ·...
NPP-Nuclear Island Design From conceptual design to Project execution
Atoms for the Future
Paris – SFEN - October 14, 2014
D. Lanchet
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NPP-Nuclear Island Design From conceptual design to Project execution
Introduction
Conceptual phase
Basic Design
Project execution
Conclusion
Division 2
Division 3
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Introduction
Stakeholders:
Designer/Vendor, Utilities/Investor, Safety Authority, Government
Time measured in decade till project execution
Huge financial and intellectual investment
Sequences are well known but definition of each phases are
arbitrary and boundaries between them could be fuzzy.
Conceptual Design (relatively short)
Basic Design ( several years)
Detailed – Manufacturing design (several years)
Focus on industrial models (not reactor at R&D phase)
Conceptual Design Basic Design
2006 2007 2008 2009 2010 2011
Detailed Design Preparation
2012
Generic Detailed Design
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NPP-Nuclear Island Design From conceptual design to Project execution
Introduction
Conceptual phase
Basic Design
Project execution
Conclusion
Division 2
Division 3
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Conceptual phase
What to be considered keeping in mind our stakeholders:
Technical performance
Economic and market goals (competition)
Safety features, compliance with regulation, environmental aspects
Wide range of approaches between start from scratch or
evolutionary
level of investment and risks
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Conceptual phase Technical performance
Type of reactor (PWR, BWR…)
Power level, core size
Number of loops (main equipment sizing)
Flexibility in operation
Type of Fuel, MOX capability
Human factor
Availability, maintenance in service, dose reduction
Plant life time
Capable of, in terms of climatic, seismic, environmental conditions
(river, sea, water and air temperatures…)
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Conceptual phase Economic and market goals – competition
Price for investment (total and €/KWi), for production (€/KWh)
Lead time
Construction time (modularity)
Power level (Grid acceptability) and need for flexibility
Proven technology
Utilities requirements: EUR, EPRI-URD
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Conceptual phase Safety features, regulations, environmental aspects
Compliant with GEN 3+ requirements + REX (i.e. post-Fukushima)
Core damaged frequency, Large release frequency
AIEA, US regulations and codes and standards (US, Europe, Japan…)
Licensibility for which country in front of which safety requirements
Safety concepts:
Air Plane Crash
Passive and Active safety functions
Redundancy, Diversity, Number of trains
Severe accident strategy
Beyond design basis events
I&C concept (digital, analog, back-up)
Waste quantities, Dismantling
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Consistent approach for AREVA EPR and ATMEA1™
Environmental Protection
Lower volume of final waste
Reduced collective dose
Energy Supply Certainty
Gen III+ based on evolutionary designs
Integrated supply chain strategy for critical components
Proven Digital Safety I&C technology
Large commercial airplane crash resistance
Advanced features for core melt and releases management
Optimized level of redundancy, diversity of systems and incremental mitigation of abnormal events
Outstanding Safety
Key
Benefits
Business Performance
Maximized availability design target >92%
Short outages
High thermal efficiency
Minimized global power generation costs
Low O&M costs
Fuel cycle flexibility
MOX fuel
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EPR- The Best from French and German Technology
German
KONVOI (~1300 MWe)
• Neckar 2
• Emsland
• Isar 2
French N4
(~1450 MWe)
• Chooz 1- 2
• Civaux 1-2
The EPR™ design is built on experience of over 100 plants, 87 of which are PWRs.
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High adaptability to Market
1,000 MWe range adapted to various grid capabilities
Could cope with multiple country regulation
High seismic areas, 50Hz/60Hz, …
Customer’s satisfaction for economy, reliability, and operability
Superior efficiency and generation cost
Competitive construction duration
Flexible operation and maintenance capability
Relief of people around site area
No evacuation required, less impact for environment
Clear logic for Severe Accident, Air Plane Crash
ATMEA1™, a Gen III+ Plant Based on proven AREVA and MHI Technology
Improved economics, Enhanced safety, Minimized waste
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NPP-Nuclear Island Design From conceptual design to Project execution
Introduction
Conceptual phase
Basic Design
Project execution
Conclusion
Division 2
Division 3
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Basic Design Before starting
Freeze conceptual design (First step of configuration)
Make sure high level requirements are exhaustive, clearly expressed and consistent.
Identify possible customers support (possible external reviews, financing)
Decide what will be the licensing strategy to get some approval in principle by a safety authority of the safety concepts used for the model
And finally, set the goal for Basic Design output (and obviously budget and schedule)
Deepness of 3D model, I&C architecture, specifications, Bill of Quantities, construction principles, ready for quotation and offer.
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Basic Design
Select the regulations and codes on which the design works will be
based
Decide the methods and tools to be used (IMS, PLM…)
Goal for basic design
Define the technical options which will enable to reach the performance, safety
concepts and economics decided in the conceptual phase
Design, Integrate, verify and validate these technical solutions, (feasible,
consistent, and meeting the conceptual phase requirements)
As far as possible, validation in principle of the safety concepts by the safety
authorities
Plot plan, 3D model with Catalogues
Perform the necessary FOAK tests on new features
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EPR Basic Design
Technical choices for severe accidents mitigation
Division 2
Division 3
Containment designed to withstand hydrogen deflagration
Spreading Area Protection of the Basemat
Prevention of high
pressure core melt by
depressurisation
means
Containment Heat
Removal System
In Containment Refueling
Water Storage Tank
(IRWST)
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EPR Basic Design Protection Against Internal Hazards
Nuclear Auxiliary Building Fuel Building
Safeguard Building
Division 1 Safeguard Building
Division 4
Safeguard Building
Division 3
Safeguard Building
Division 2
2 t 2 t
2 t
2 t
-11.70
-8.60
-11.70
HOT PIPING
SE
RV
ICE
CO
RR
IDO
R
RETENTION
FPP PUMP
CVCS PUMP
EB
S P
UM
P
KTA/RPE
VALVE
PIPE DUCT
KGB/TEP
DEMINERALIZED WATER PUMP
EVAPORATOR
WASTE GAS COMPR.
FL
OO
R D
RA
IN 2
FL
OO
R D
RA
IN 1
PR
OC
ES
S D
RA
IN
PR
IMA
RY
SA
MP
LIN
G 2
SAMPLING
ACTIVE LABORATORYCONTENSATE
CA
BL
E S
HA
FT
SERVICE CORRIDOR SECONDARY SAMPLING
SE
RV
ICE
CH
EM
ICA
L
PR
IMA
RY
SA
MP
LIN
G 1
SECONDARY SAMPLING
KB
F/T
EP
QNB/DER
CHRS SUMP
SE
RV
ICE
CO
RR
IDO
R
CCWS PUMP
EFWS PUMP
AN
TE
RO
OM
AIR
CHRS PUMP
LHSI PUMP
SUMP VALVE
MHSI PUMP
SE
RV
ICE
CO
RR
IDO
R
SERVICE CORRIDOR
MHSI PUMP
VALVE
LHSI PUMP
CCWS PUMP EFWS PUMP
KT/RPE
ANTEROOM
SERVICE CORRIDOR
KBB/TEP FEED PUMPS
DR
AIN
TA
NK
VALVE
TR
AIN
4
CA
BL
E S
HA
FT
TR
AIN
3
PASSAGEWAY
EFWS PUMP
KT/RPE
CCWS PUMP
SERVICE CORRIDOR
LHSI PUMP
ANTEROOM
FPC PUMP
DISTRIBUTION
FPP
CVCS PUMP
FPC
FPS PUMP
DISTRIBUTION
HOT PIPING
PASSAGEWAY
MHSI PUMP
AN
TE
RO
OM
EFWS PUMP
SE
RV
ICE
CO
RR
IDO
R
SUMP
LHSI PUMP
CHRS PUMP
SUMP VALVE
AIR
CCWS PUMP
SUMPSUMP SUMP SUMP
IRWST IRWST
SPREADING AREA
EB
S P
UM
P
PUMP
PUMP
VALVE
LOCK CHRS
SUMP
PIT
VALVE
LOCK
ROOM
PUMP
COUNTING
WASTE GAS COMPR.
ROOM
KBB/TEP
ROOM
VALVE VALVE
ROOM
KBB/TEP
CO
RR
IDO
R
SUMP VALVE
SE
RV
ICE
CO
RR
IDO
R
MHSI
PUMP
A
B
A
B
KPL / TEG
KTA/
RPE
KPL / TEG
-11.1
0m
-5.90
-4.35
-4.35
-6.15 -6.15
0 2 4 6 8 10 20m
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EPR Basic Design Primary Side Safety Systems
• Four Train Safety Injection Systems
• In-Containment Borated Water Storage Pool
• No Necessity for Containment Spray for Design Basis Accidents
• Combined Residual Heat Removal System and Low-head Safety Injection System
• Extra Borating System (two trains not shown on this figure) M
M
M
M
M
M
M
M
M
M
M
M
M M
M
M
M
LHSI/RHR
ACCU ACCU
ACCU ACCU
LHSI
LHSI/RHR
LHSI
MHSI
MHSI
MHSI
MHSI
IRWST
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• Interconnecting headers at EFWS pump suction and discharge normally closed
• Additional diverse electric power supply for two of four trains, using two small Diesel Generator Sets
• Two 25% Safety valves and one 50% atmospheric relief valve per Steam Generator
• Four separate Emergency Feedwater trains
MSIV
MSIV
MSIV
MSIV
EFWS tank
EFWS tank
EFWS tank
EFWS tank
EFWS
EFWS
Safety & relief valves
Safety & relief valves
Safety & relief
valves
Safety & relief valves
Main Steam
Main Feed
EPR Basic Design Secondary Side Safety Systems
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ATMEA1™ Basic Design Core Design Features
Active core height 4200 mm Same as EPR and USAPWR
Fuel assembly geometry 17x17 Same as those used in operating PWRs
Number of fuel assemblies 157 Same as 3 loop PWRs designed by AREVA
or MHI
Fuel enrichment < 5.0 wt% Same as operating PWRs
Max. fuel assembly burn-up 62GWd/t Maximum value available without
development
Control rod absorber material AIC/B4C Used in operating PWRs
Core monitoring/protection Rh and Co SPND(*) Used in operating PWRs (Rh) and EPR (Co)
Operation method T-mode Adopted in EPR
Chemical shim Enriched Boron Adopted in EPR
Basic concept: Adopt proven / state-of-the-art technologies
(*) SPND: Self-Powered Neutron Detector
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ATMEA1™ Basic Design Reactor Building 3D views
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ATMEA1™ Basic Design I&C Architecture
PICSSICS
Non safety systems
instrumentation actuators
Safety systems
instrumentation actuators
RPS SAS
PACS
RCML
Rods
Breakers
Rods
control
Non safety systemsSafety systems
DASPAS
Level 2
Level 1
Level 0
Mainly to Safety related
Level 1 I&C Systems
To all Level 1 non safety
I&C Systems
To PACS To PACS To PACS To PACS
From other I&C systems
SA
To PACS
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Reactor Building is designed to be accessible 10 days before and 3 days after the outage
ATMEA1™ Basic Design Objective : high availability
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ATMEA1™ Basic Design External reviews
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Designed with U.S.NRC regulations, U.S. industry consensus
Codes and Standards and ICRP for radioprotection
Compliant with IAEA Safety Standards
Reviewed against the experience of Generation III+ AREVA’s
EPRTM
and MHI ’s APWR (i.e. French, Finnish, Chinese, US and
Japanese regulations)
Reviewed against the French Regulatory regime
Laws (Orders of 13/10/2003, 31/12/1999…)
Guidelines
Technical guidelines for new reactors (2004)
Applicable fundamental safety rules
ATMEA1TM Basic design Regulatory and Safety Frameworks
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NPP-Nuclear Island Design From conceptual design to Project execution
Introduction
Conceptual phase
Basic Design
Project execution
Conclusion
Division 2
Division 3
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Project execution Main parameters
FOAK or NOAK project
Site Technical Data
Contract specificities (contractual mode, scope, schedule)
Lead time, construction time
Specific country regulations
Localization (Industrial capability)
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Project execution
Adjust standard basic design requirements to the Project
and re-do accordingly parts of Basic Design (Configuration Zero)
Construction license
Launch detailed design (sample of activities)
Define technical configuration strategy up to commercial operation
Adjust equipment specifications, launch manufacturing design
Safety studies: PSAR, PSA, FSAR
Systems design
I&C Hardware and Software design
Produce execution drawings
Integrate feedback from manufacturing design and equipment suppliers
Support to Construction and Commissioning
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NPP-Nuclear Island Design From conceptual design to Project execution
Introduction
Conceptual phase
Basic Design
Project execution
Conclusion
Division 2
Division 3
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Conclusion
Long and ambitious venture
Require large financial and resource investment
Rely on an extensive pool of knowledge
(mix of R&D, proven technology)
Methods and tools are part of the success key
Flamanville 3 Taishan 1&2 Olkiluoto 3 Hinkley Point C
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NPP-Nuclear Island Design From conceptual design to Project execution
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