Current Affairs in the Finnish Nuclear Sector

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Current Affairs in the Finnish Nuclear Sector

• The 21st Meeting of the IAEA TWG-NPPCI
• May 23-25, 2007
• Vienna
• Janne Valkonen

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Contents of the presentation

• Finnish nuclear industry in brief
• Loviisa (Fortum) activities
• Olkiluoto (TVO) activities
• Research activities
• Recommendations

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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
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Finnish nuclear industry in brief

• Power utilities
• Regulatory authority
• Research centre
• Waste management

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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

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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.

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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).

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Scope of the renewal project
To be renewed
Control room
IC cabinets (Data acquistion, control logic)
Switchgear
Training simulator
Measurements
Actuators
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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.

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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

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Stages of renewal (2)
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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).

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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.

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

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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

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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

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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

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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

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Source TVO image archive
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Source TVO image archive
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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

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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.

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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

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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

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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

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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.

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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

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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.

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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.

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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.

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Acknowledgements

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