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Current Affairs in the Finnish Nuclear Sector

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Title: Current Affairs in the Finnish Nuclear Sector


1
Current Affairs in the Finnish Nuclear Sector
  • The 21st Meeting of the IAEA TWG-NPPCI
  • May 23-25, 2007
  • Vienna
  • Janne Valkonen

2
Contents of the presentation
  • Finnish nuclear industry in brief
  • Loviisa (Fortum) activities
  • Olkiluoto (TVO) activities
  • Research activities
  • Recommendations

3
Finnish nuclear industry in brief
Olkiluoto 1 BWR 75, 840MWe, 1979 Olkiluoto 2
BWR 75, 840MWe, 1982 (Olkiluoto 3 EPR, 1600MWe,
2010-11)
Loviisa 1 VVER-440, 488MWe, 1977 Loviisa 2
VVER-440, 488MWe, 1981
4
Finnish nuclear industry in brief
  • Power utilities
  • Regulatory authority
  • Research centre
  • Waste management

5
Activities related to IC systemsin the Loviisa
NPP
  • IAEA-TWG-NPPCI
  • (Technical Working Group on Nuclear Power Plant
    Control and Instrumentation)
  • May 2007
  • Slides by Martti Välisuo

6
Loviisa 1 and 2 automation renewal (LARA-project)
  • In the LARA-project the IC systems of the plant
    will be renewed gradually there will be four
    stages per plant unit.
  • The first system commissioning will take place
    this year (2007) and the last in the year 2014.

7
Automation renewal supports the operation of the
plant
  • The goals of the plant operation are
  • maintaining safety on its current good level
  • maintaining availability on its current good
    level
  • long operation time (50 years).

8
Scope of the renewal project
To be renewed
Control room
IC cabinets (Data acquistion, control logic)
Switchgear
Training simulator
Measurements
Actuators
9
Main principles of the renewal
  • The IC functions will remain as they are, as a
    rule.
  • Tolerance of CCFs will be built in the IC
    concept.
  • New IC cabinets will be placed in new buildings
    that fulfill all new requirements.
  • Fortum selected a competent supplier with
    applicable products.
  • Simulators will be used extensively for various
    purposes
  • process and control design
  • transient and accident analyses
  • development and validation of the HMI
  • testing of IC
  • operator training.

10
Stages of renewal (1)
  • There will be four renewal stages
  • Part of reactor IC and nuclear water treatment
    IC
  • Reactor protection system
  • Scram
  • ESFAS
  • IC of the emergency diesel generators
  • IC of the primary circuit and the relating
    auxiliary systems
  • IC of the secondary circuit and the relating
    auxiliary systems

11
Stages of renewal (2)
12
Supplier and platforms
  • Fortum has made a contract of the first three
    stages with the consortium of AREVA NP (former
    Framatome ANP) and Siemens AG.
  • AREVA's platforms are used for the safety IC
  • TELEPERM XS
  • QDS (Qualified Display System)
  • Hardwired equipment (for the Manual Backup of the
    Reactor Protection System).
  • Siemens' platforms are used for the operational
    IC (and for the Automatic Backup of the Reactor
    Protection System)
  • SPPA T2000 (former TELEPERM XP)
  • OM690 (operating stations).

13
Diversity
  • The Reactor Protection functions will be
    implemented with two independent and diverse
    protection layers.
  • Protection layer 1
  • Reactor Protection System (automatic)
  • TELEPERM XS
  • Protection layer 2
  • Manual Backup
  • Hardwired equipment
  • Automatic Backup (includes only urgent functions)
  • SPPA T2000
  • Additionally, functional diversity is designed
    inside each protection layer.

14
Illustration of the future control room
15
New control building (Loviisa 1, building 2.
Autumn 2005)
16
  • TVO 1 AND 2
  • MAIN IC ACTIVITIES
  • 9.5.2007

17
GENERAL
  • OL1 and OL2 plants have operated well without any
    remarkable technical disturbances
  • Average capacity factor 2006 was 95,4 and total
    production 14,3 TWh
  • Lot of effort have been concentrated to
    management of ageing

18
MAIN RENEWAL
  • 2006 were finalized turbine island modernization
    including
  • HP-turbine modifications
  • New 2-stage reheater
  • New steam dryer (moisture 0,3 -gt 0,01)
  • New turbine automation system including control
    room equipment
  • New 6,6 kV switchgears
  • Net power increase about 20 MW per unit
  • Also water handling and desalination system
    automation were modernized

19
IC MAIN ACTIVITIES DURING 2007
  • Gas turbine plant will be finalized, 100 MW unit
    for grid support and emergency power
  • Minor IC renewals will be started
  • Plant radiation monitoring system renewal
  • Environment radiation monitoring system
  • Weather station
  • Seawater cleaning screens automation

20
IC FUTURE PLANS (not fixed)
  • Half-long service outage 2010-2011
  • Low-pressure turbine modernisation
  • Low pressure turbine renewal
  • Turbine vibration monitoring renewal
  • Automation for condensation water handling
  • Generator renewal
  • Reactor main steam line isolation valves
  • Long service outage 2015-2016
  • Renewal of reactor automation
  • Renewal of reactor automation
  • Core shroud and other internals
  • High pressure turbine optimization
  • Cables

21
Source TVO image archive
22
Source TVO image archive
23
Research activities at VTT
  • SAFIR 20032006 research programme ended
  • New programme SAFIR2010 just started
  • Total volume in 2007 approximately 46 person
    years and 6,3 M

24
SAFIR2010 research areas
  • SAFIR2010 research programme is divided in eight
    research areas, which are
  • 1. Organisation and human factors
  • 2. Automation and control room
  • 3. Fuel and reactor physics
  • 4. Thermal hydraulics
  • 5. Severe accidents
  • 6. Structural safety of reactor circuit
  • 7. Construction safety
  • 8. Probabilistic safety analysis (PSA)
  • These research areas include both research
    projects of the named topic and interdisciplinary
    co-operation projects.

25
SAFIR2010 Projects 2007Area 2 Automation and
control room
  • MODSAFE Model-based safety evaluation of
    automation systems
  • CERFAS Certification facilities for software
  • OPRACTICE Operator practices and human-system
    interfaces in computer-based control stations

26
MODSAFE - Model-based safety evaluation of
automation systems (1)
  • Background
  • Formal models can be/are used in various phases
    of automation design (e.g. functional block
    diagrams, state machines, UML-models etc.)
  • Tools for model checking are available
  • Possibilities to get into a hazardous situation
    can be identified by analysing models
  • Need of tools for analysis of safety functions
    based on programmable technology

27
MODSAFE - Model-based safety evaluation of
automation systems (2)
  • Objectives
  • Development of methods for model based safety
    evaluation of NPP automation
  • Application of the methods in selected case
    studies
  • Evaluation of the suitability of formal model
    checking methods for NPP automation analysis
  • Operationalization of model based safety
    evaluation as a part of safety case of safety
    automation systems
  • Development of recommendations for the practical
    application of the methods

28
O'PRACTICE - Operator practices and human-system
interfaces in computer-based control stations (1)
  • Starting point
  • Challenges caused by control room (CR) and
    human-system interface (HSI) upgrades
  • Objectives
  • Develop practices of Human Factors Engineering
    (HFE) for the design, operation and evaluation of
    human-system interfaces at NPP control rooms
  • Promote safe use of digital technologies
  • Develop new methods and practices for the
    management of design process and evaluation of
    the safety of HSIs
  • Develop expertise on user-centred design of
    complex industrial systems in Finland
  • Promote international collaboration with research
    and expert organizations, and institutions
  • Strengthen delivery of expertise in the field of
    user-centred design.


29
O'PRACTICE - Operator practices and human-system
interfaces in computer-based control stations (2)
  • Key research activities in 2007
  • New tools of collaboration for operating
    personnel
  • Survey user needs for collaborative tools such as
    large screen displays
  • Study usage practices of large-screen displays
    and computer-based procedures
  • Development of new concept of operation for
    fully-digitalized control rooms
  • Study the use of Information Rich large screen
    displays for process control purposes
  • Develop a novel operating support system
    prototype based on methods of semantic modelling,
    dialogic interviews and user studies
  • Evaluation of control rooms and human-system
    interfaces
  • Study the adequacy, effectiveness and safety of
    hybrid human-system interfaces


30
CERFAS - Certification facilities for software
  • Purpose is to develop facilities for a software
    certification service
  • Networking in the area of software certification
    services. Certifiers must have competing products
    and unique features that are desired by the
    clients.
  • The objective is to develop facilities for
    flexible, supported, commercially exploitable,
    high quality software certification service able
    to certify safety critical and safety related
    software.
  • Also advanced methods for evaluation of software
    process and artefacts, that is, documents, code,
    test plans, etc. competence development to
    provide facilities for software certification
    service.

31
Recommendations to the TWG-NPPCI (1)
  • Possibilities of Open Souce in the area of
    safety-critical software.
  • Design and licencing patterns as a means to
    enhance readiness to develop and evaluate
    safety-critical software.
  • Automated tools for the analysis of software
    modules (model based approaches).
  • Managing the large difference in lifetime between
    nuclear power plants and their IC systems.

32
Recommendations to the TWG-NPPCI (2)
  • Concept of operations and operator practices in
    digitalised control rooms.
  • Functional task analysis for operator
    functions.
  • Information tools for improving collaboration
    between operations and maintenance.
  • Role of large screen displays in supporting
    situation awareness.
  • New methods to analyse and control mental effort
    in stress situations.
  • Human Factors Engineering practices in design of
    automation and control stations.

33
Acknowledgements
  • Martti Välisuo, Fortum Nuclear Services
  • Olli Hoikkala, TVO
  • Juhani Hyvärinen, STUK
  • Hannu Harju, VTT
  • Jari Laarni, VTT
  • THANK YOU FOR YOUR ATTENTION!
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