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up group discussions in order to evaluate these methods and develop them further. The results were reported in the workshop and as a written report.
• Altogether four conference papers were written and presented in two workshops:
• INAC 2005 – International Nuclear Atlantic Conference, NKM Workshop
• CSNI Workshop on Better Nuclear Plant Maintenance: Improving Human and Organisational Performance
• Two journal articles were approved for publishing:
• Kuronen, T. & Rintala, N. (2005). The Classification of Knowledge and Expertise in Finnish Nuclear Power Plants. International Journal of Nuclear Knowledge Management, 2 (2), in press.
• Rintala, N. & Kuronen, T. (2005). How to Share Tacit Nuclear Knowledge.
International Journal of Nuclear Knowledge Management, 2 (2), in press.
• A visit from Forsmark HR department was realized in order to outline possibilities for research co-operation.
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using the developed new TMMC (Two Model Monte Carlo) platform are carried out to quantify fire risks on most safety relevant spaces.
Our progress during the two previous years calls for the proposing of new calculation algorithms of flame spread on solids, and a new test rig to measure the needed experimental parameters. Scaling up the screening tests to real size will be started to build up numerical tools and experimental test rigs.
Specific goals 2005
Successful experiments of asymptotic flame spread models will be continued towards a real size test rig, where vertical samples up to 2 m length can be used heated to needed initial temperature up to 500 oC. As scaling tests of vertical flame spread on cables a series of flame spread experiments using long samples of various materials and diameters will be carried out to test the proposed models, utility of the rig, and performance of the instrumentation needed. Working out, evaluating and proposing the flame spread models to be included into CFD calculation algorithms. Proposing a new test rig for measuring the needed input data of these models.
For probabilistic fire development in safety relevant spaces calculation of probability distributions of a target function from given scenarios. Improve numerical performance of the Monte Carlo platform for use of even more advanced variations of FDS fire models.
One new safety relevant NPP fire scenario is calculated and needed data is collected to statistical data base.
International Collaborative Project to Evaluate Fire Models for Nuclear Power Plant Applications (ICP). Participation in the evaluation project selectively according to the tasks for year 2005, and on next scheduled meeting at Duke Power Co., Charlotte, NC, USA, May 18–20, 2005.
For reliability of fire detection in different NPP environments finishing of a scientific manuscript on smoke detector time lag.
Deliverables 2005
Modeling experiments on 0.8 m samples were carried out, a new test rig was designed, tested by CFD simulations and all the phases were reported. Very important contribution was testing of new thermocouple tree instrumentation tested under real conditions.
Outside the project, but as a direct continuation of the observations made a double cone calorimeter concept was tested and found practical. It allows accurate mass and energy balances to be tested, where adiabatic energy and impermeable mass boundary condition is strictly fulfilled at the backing (central plane) of the sample.
Modeling of flame spread using DNS-like simulations by FDS-code were carried out and reported. Preliminary comparison with 0.8 m experiments confirmed a simplified heat transfer subgrid flame spread model is possible.
The goal of Monte Carlo simulations was changed slightly towards more practical needs of plant personnel by the ad hoc group and accepted by the reference group. Modeling of MC was continued by looking convergence, influence of the shape of input distributions, and
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approximate modelling of the main fire scenarios to understand better the most strongly influencing factors. Finishing the report is slightly delayed.
Participation in and a travel report from ICP meeting, Huntersville, NC, USA, May 18–20, 2005.
Manuscript of a scientific publication is still pending.
Travel reports from participation (outside the project) in PRISME pre-meetings. Finnish participation in and project administration of the PRISME-program carried out under auspices of OECD/NEA by IRSN in Cadarache, France, was included as a subtask of POTFIS-project for 2006.
2.6.2 Principles and Practices of Risk-Informed Safety MAnagement (PPRISMA)
Risk-informed safety management means use of information from probabilistic safety assessment (PSA) to support decision making in various contexts. Generally, the project deals with the whole scope of risk-informed methods and application areas related to safety of nuclear power plants. The objectives are
• to develop risk-informed decision making methods that integrate results from risk and reliability analyses with other expertise in the problem domain
• to develop assessment methods for nuclear power plants operation and maintenance in order to enhance risk-informed ways of planning of activities and acting in situations
• to develop methodologies in the problem areas of PSA
• to advance skills in nuclear risk analysis, assure the competence transfer to the new generation and to participate in international co-operation.
Specific goals in 2005 were
• A method for periodic review and analysis of maintenance history for systematic identification, analysis and prevention of human originated common cause failures (CCFs) and single errors, including support and review of regular human CCF and single error studies of the case utility.
• A paper on human errors and their prevention in relation to maintenance will be written for the OECD/NEA/SEGHOF workshop "Better Nuclear Plant Maintenance – Improving Human and Organisational Performance".
• A process model constructed and reported for the maintenance strategy planning process.
• A conference paper on the development of maintenance strategies for Loviisa NPP written together with Fortum.
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• Development of the method focusing on the management of fire situations from the co-operation point of view, based on interdisciplinary expert group work at both nuclear power plants in Finland.
• The possibilities to utilize the method as a practical tool for expert collaboration in the construction of relevant knowledge for Human Reliability Assessment in fire-PSA considered (PSA’05, San Francisco).
• M.Sc. Thesis on the use of risk-informed methods to support classification of functions, systems, structures and components at NPPs.
• Representation of Finland in the Working Group RISK (WGRISK) of OECD/CSNI and its Task "Framework for HRA Information Exchange."
• A case study applying the Bayesian reliability assessment method for a motor protection relay.
• Conclusions on how to apply expert judgements in the building of prior reliability estimate is summarised in a scientific article.
• Arrangement of IAEA specialist meeting on implementation and licensing of digital I&C systems and equipment in nuclear power plants is arranged and are preparation of the proceedings.
• To follow the OECD/NEA/CSNI/WGRISK task "Software Reliability – Task on the Safety Assessment of Programmable Computers", to manage the activity of the ad hoc -group in the research topic and to participate in relevant conferences (SAFECOMP 2005).
• Pre-study on the development of methods to model long term missions by means of PSA techniques (event tree-fault tree) or by using more enhanced reliability model methods, e.g. Markov models.
• To participate in and to follow-up the OECD/NEA/CSNI/WGRISK and WGOE incl.
WGOE task "Minor and non-identified modifications that may impact safety", EU research in reactor safety (6th Framework programme), ESReDA working groups, Nordic PSA-group, ESREL/PSAM/PSA conferences, co-operation with NKS work and the Halden Reactor Project.
• Payment of the fee of the OECD/NEA's ICDE project.
Deliverables in 2005
• A report on identification and analysis of single human errors in relation to maintenance covering the maintenance history 2003 of the Loviisa NPP was prepared together by Fortum and VTT based on 7 daily analysis sessions at the NPP and the methods described in the intermediate method description report.
• A paper on "Systematic analysis and prevention of human errors and common cause failures in relation to maintenance" was prepared and presented for the
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OECD/NEA/SEGHOF workshop "Better Nuclear Plant Maintenance – Improving Human and Organisational Performance".
• Models for maintenance strategies and information, and for selection of maintenance tasks, have been constructed and documented in an intermediate report of a risk- informed and cost-effective maintenance planning process. Information and brainstorming sessions, incl. evaluation of opportunities to test and implement R&D analysis methods as analysis, planning and information management methods for maintenance and operability planning, held at both Finnish utilities.
• The abstract on "Development maintenance strategies for a nuclear power plant" was accepted by the programme committee for the Euromaintenance World Congress 2006.
• A seminar on "Risk-informed management of nuclear power plant fire situations"
arranged. Expert groups from both Finnish NPPs, and representatives from STUK, regional fire brigades and insurance company participated. Interim report prepared.
• Conference paper "Interdisciplinary Expert Collaboration Method (IECM) for supporting Human Reliability Analysis in Fire PSA" presented in PSA’05.
• MSc Thesis on risk-informed classification of systems, structures and components in nuclear power plants, and a paper on the same subject for the SAFIR Interim report.
• Follow-up of WGRISK and CSNI activities. Participation in the annual meeting of WGRISK. Travel report.
• Case study on reliability estimation of computer-based device for probabilistic safety assessment reported.
• Arrangement of the IAEA technical meeting on "Implementing and Licensing Digital I&C Systems and Equipment in NPPs" has been arranged in Nov. 22-24, in Espoo, Finland. 81 participants from 24 different countries attended the meeting. The three day meeting contained 25 presentations from different vendors, licensees, licensers and research organisations of nuclear industry.
• A conference paper on "Giving reliability estimates for digital devices and using the estimates in licensing" presented in IAEA technical meeting in Espoo.
• Two joint RECOM, ASDES and QETES ad hoc –group meetings on digital system reliability with representatives from STUK, TVO, Fortum NS, Adelard and VTT held.
• White paper of the OECD/NEA/CSNI/WGRISK task on Software Reliability commented and delivered to the authors of the paper.
• Papers of SAFECOMP 2005 reviewed and the accepted papers selected at the programme committee meeting in April. The conference has been participated in September.
• Research report on long mission time reliability analysis (pre-study).
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• VTT involved in submit of two project porposals within EU research in reactor safety (6th Framework programme): SERAMIC and ARIADO. The SERAMIC (Safety, Efficiency and ReliAbility of Modernisation of nuclear power plant Instrumentation &
Control) project consortium includes more than 20 participants from more than 10 EU countries. The ARIADON project (Network of excellence in Application of Risk- Informed Approaches to Design & Operation of Nuclear Plants) consortium includes about 10 participants from five countries.
• Paper presented at the OECD/CSNI Workshop on Better Nuclear Plant Maintenance- Improving Human and Organisational Performance.
• Contributions to conclusions from OECD/NEA/CSNI/WGOE Workshop on
"Modifications at Nuclear Power Plants – Operating Experience, Safety Significance and Role of Human Factors".
2.6.3 Assessment Smart Device Software (ASDES)
The assurance of smart devices for use in critical applications requires the safety assessment of their software. The overall objective of this project is to develop an approach to the assessment of such smart device software that takes into consideration
• the particular issues of assessing COTS and the design and accessibility of smart devices
• regulatory context of the nuclear industry in Finland (e.g. YVL guides 2.0, 2.1, 2.7, 2.8, 5.5)
• current practices of software assurance developed in Finland and more widely in the UK and European projects.
Specific goals in 2005 were
• specification of the project including selection of the case study device and example application cases
• development of the requirements set for the device in example application cases.
Deliverables in 2005
• An interim report describing case study device, example application cases and the requirements set for the device.
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3 FINANCIAL AND STATISTICAL INFORMATION
The total costs of the programme in 2005 were € 5.20 million. The major funding partners were VYR with € 2.68 million, VTT with € 1.47 million, Fortum with € 0.19 million, TEKES with € 0.16 million, EU with € 0.18 million and other partners with € 0.48 million.
The total extent of the programme in 2005 was 40 person years. The programme had 22 research projects and the administration project with partial or total VYR-funding and two research projects under the SAFIR-umbrella entirely with other funding sources. The total volume of the VYR-funded projects was € 4.85 million and the total volume of the other two projects € 0.35 million. The planned and realised financing and expenses of the VYR- funded projects have been indicated in Figures 3.1.and 3.2, respectively. The share of personnel costs was around 86% of the yearly expenses, as illustrated in Figure 3.2.
Figure 3.3 and 3.4 illustrates the distribution of funding and person years of all SAFIR research projects between the six research areas of SAFIR. The most "nuclear-specific"
research areas 3: Containment and process safety functions, 2: Reactor circuit and structural safety, and 1: Reactor fuel and core have the largest shares, whereas the three remaining areas with more connections and applications beyond the nuclear field, namely 4: Automation, control room and information technology, 5: Organisations and safety management and 6: Risk-informed safety management cover 17% of the entire programme volume.
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Financing in 2005
0 500 1000 1500 2000 2500 3000
VYR VTT Fortum Tekes NKS EU Other
k€
Plan Realised
Figure 3.1. Planned and realised financing in 2005.
Expenses in 2005
0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000
Personnel Mat&suppl Travel ExtServ Other
k€
Plan Realised
Figure 3.2. Planned and realised expenses in 2005.
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TOTAL FUNDING IN 2005
17 %
27 %
18 % 18 %
6 % 5 %
9 % 1. Reactor fuel & core
2. Reactor circuit &
structural safety
3a. Thermal hydraulics 3b. Containment
4. Automation, control room & IT 5. Organisations & safety
management
6. Risk-informed safety management
TOTAL FUNDING IN 2005
17 %
27 %
18 % 18 %
6 % 5 %
9 % 1. Reactor fuel & core
2. Reactor circuit &
structural safety
3a. Thermal hydraulics 3b. Containment
4. Automation, control room & IT 5. Organisations & safety
management
6. Risk-informed safety management
Figure3.3. Distribution of funding in SAFIR research areas in 2005.
TOTAL VOLUMES IN 2005
18 %
24 %
21 % 18 %
5 % 7 %
7 %
1. Reactor fuel & core
2. Reactor circuit &
structural safety
3a. Thermal hydraulics 3b. Containment
4. Automation, control room & IT 5. Organisations & safety
management
6. Risk-informed safety management
TOTAL VOLUMES IN 2005
18 %
24 %
21 % 18 %
5 % 7 %
7 %
1. Reactor fuel & core
2. Reactor circuit &
structural safety
3a. Thermal hydraulics 3b. Containment
4. Automation, control room & IT 5. Organisations & safety
management
6. Risk-informed safety management
Figure 3.4. Distribution of person years in SAFIR research areas in 2005.
The distribution of funding and volume in each research area in 2003-2006 have been indicated in Figures 3.5 and 3.6, respectively.
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Distribution of funding in SAFIR research areas 2003- 2006
0 1000 2000 3000 4000 5000 6000
1 2 3 4 5 6 7
Re se a rch a re a s (1-6) a nd tota l (7)
k euro
2003 2004 2005
"2006"
Figure 3.5. Realised cost in SAFIR in 2003-2005 and plan 2006. Research areas(1-6) and total (7).
Distribution of volume in SAFIR research areas in 2003- 2006
0 50 100 150 200 250 300 350 400 450
1 2 3 4 5 6 7
Re se a rch a re a s (1-6) a nd tota l (7)
person month 2003
2004 2005
"2006"
Figure 3.6. Realised volumes in SAFIR in 2003-2005 and plan 2006. Research areas (1-6) and total (7).
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The total planned and realised costs and volumes of each project have been given in Table 1.1. A more detailed survey of the planned and realised costs and funding for the VYR- funded projects is given in Table 3.1.
The programme produced 171 publications in 2005. Major part of the publications consisted of conference papers and extensive research institute reports. The number of scientific publications as well as the total number of publications varied greatly between the projects, as indicated in Table 3.2. The average number of publications was 4.38 per person year, and the average number of scientific publications was 0.41 per person year.
Corresponding numbers for the year 2004 were 3.4 publications per person year and 0.45 scientific publications per person year [4]. Many of the projects have deliberately aimed at publication of the results as extensive research institute reports. Thus, the number of scientific publications is fairly low.
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Table 3.2. Publications in the SAFIR projects in 2005.
Project Volume pers. year
Scientific Conference papers
Res. inst.
reports
Others Total
EMERALD 4,4 1 9 10 0 20
KORU 2,9 0 0 2 1 3
INTELI 7,4 3 12 7 0 22
LWROXI 0,3 1 2 1 0 4
CONSAFE 0,1 0 0 0 0 0
CONTECH 1,3 0 1 2 4 7
WARSI 0,7 0 2 1 0 3
IMPACT 1,1 0 0 0 0 0
MULTIP 1,2 0 1 1 0 2
TIFANY 1,4 0 1 2 0 3
THEA 1,4 1 3 3 2 9
SANCY 2,8 0 4 7 0 11
FIKA 2,4 2 4 3 0 9
KOETAR 0,5 0 1 0 0 1
POOLEX 3,4 0 2 3 0 5
ECE 0,7 0 0 0 3 3
IDEC 1,4 1 2 3 1 7
QETES 0,5 0 0 0 2 2
WHISKE 0,1 0 2 1 2 5
CULMA 1,6 3 6 3 3 15
TIMANTTI 1,1 2 3 0 0 5
POTFIS 1,0 2 8 5 5 20
PPRISMA 1,6 0 5 3 2 10
ASDES 0,2 0 0 0 0 0
SAHA 0,5 0 0 3 0 3
TOTAL 40 16 66 62 26 170
* IMPACT reporting included in WARSI
In the projects of SAFIR programme during the year 2005 one Doctoral degree was obtained in the EMERALD project and one in the INTELI project. Altogether seven Masters degrees were obtained, two in THEA project and one in KORU, INTELI, ECE, SANCY and PPRISMA projects.
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4 ORGANISATION AND INFORMATION
The programme management consisted of the steering group and the six reference groups.
During the year 2005 the steering group had four meetings and the reference groups four meetings each. Additionally, the reference groups performed a two-stage evaluation process with one extra meeting for the project proposals for the year 2006. The ad hoc groups that have a vital role in some research areas with many projects continued their operation and some new groups were formed by the project managers. The ad hoc groups met upon the needs of the specific project. Some groups had several meetings during the year and some groups worked only by email. All these groups were regularly informed using standard progress reports. The list of persons involved in the steering and reference groups, as well as programme staff and their main duties are presented in Appendix 6.
Figure 4.1 illustrates the structure of the SAFIR programme with the research projects forming the hot red core of the programme, the six reference groups and the various ad hoc groups having the principal responsibility of scientific guidance and surveillance of the various research projects, as depicted with the yellow layer encircling the red core. The steering group, depicted as the blue layer, administrates the entire research programme thus keeping the SAFIR ‘jewel’ together.
Figure 4.1 The three-layer structure of SAFIR programme with projects (red), reference and ad hoc groups (yellow) and steering group (blue).
The information on the research performed in SAFIR has been communicated formally via the quarterly progress reports, the annual report of the programme and the www-pages of the programme. The detailed scientific results have been published as articles in scientific journals, conference papers, and separate research reports.
The SAFIR interim seminar and interim report were prepared during the year 2004. The two-day seminar with nearly 120 registered participants was arranged in January 2005 and an extensive Interim Report was published.
The publications of the projects during the years 2003–2004 were collected on CD and distributed to all SAFIR organisations presented in the Steering Group.
Information on the SAFIR 2004 results was included in the EU JSRI-II database.
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An internal QA-audit with short audit report was performed covering project management and three selected projects.
In addition to conducting the actual research according to the yearly plans, SAFIR has functioned as an efficient network of all ‘players’ in the nuclear energy field in Finland and as an open discussion forum for participation in international projects, allocation of resources and in planning of new projects.
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5 REFERENCES
1 Kansallinen ydinvoimalaitosten turvallisuustutkimus 2003–2006, ehdotus uuden tutki- musohjelman sisällöksi ja organisoinniksi. Kauppa- ja teollisuusministeriö. Työryhmä- ja toimikuntaraportteja 13/2002, SAFIR suunnitteluryhmä. (Nuclear Power Plant Safety Research 1999–2002, A proposal for the content and organisation of the new research programme. Ministry of Trade and Industry, Finland, Ad hoc committee reports 13/2002, SAFIR Working Group, in Finnish.)
2 Puska, E.K.; SAFIR, The Finnish Research Programme on Nuclear Power Plant Safety, Annual Plan 2005. Espoo: VTT Processes Project Report PRO1/P1015/05, 22 p. + App.
130 p.
3 Puska, E.K.; SAFIR, The Finnish Research Programme on Nuclear Power Plant Safety, Annual Report 2003. Espoo: VTT Processes Project Report PRO1/P7001/04, 57 p. + App. 107 p.
4 Puska, E.K.; SAFIR, The Finnish Research Programme on Nuclear Power Plant Safety, Annual Report 2004. Espoo: VTT Processes Project Report PRO1/P1014/05, 60 p. + App. 126 p.