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Formal Safety Assessment Methods in Olkiluoto 1&2 NPP I&C Renewal Project DIMA

  • Antti Pakonen*
  • , Lauri Tuominen
  • , Mauri Viitasalo
  • , Pekka Nuutinen
  • *Corresponding author for this work
  • Teollisuuden Voima Oyj

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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Abstract

Formal languages and methods provide a rigorous and systematic framework for requirement specification and design. A key benefit is the ability to logically prove the correctness of design solutions. TVO operates three nuclear power plants in Olkiluoto, Finland. Units 1 and 2 are BWR type reactors in use since 1979 and 1982. In 2020, TVO started the digital I&C lifetime management project DIMA, where selected I&C systems are renewed using mostly softwarebased
technology. In DIMA, VTT has used two different formal, computer-assisted methods to verify the design solutions. First, model checking was used to verify the functional architecture diagrams serving as design input, and then the detailed I&C logic diagrams developed by Westinghouse Electric Sweden. The analyses have revealed several issues related to spurious actuation, contradictory commands, frozen logic, and in general, incorrect response to inputs. Second, on the overall I&C architecture level, an ontology-based Defense-in-Depth (DiD) assessment method was used to perform interface analyses. The work succeeded in identifying violations of communication independence rules between DiD levels and safety classes. For each violation, TVO was then able to prove by their analyses that failure propagation could not cause unacceptable consequences at the plant level. In this paper, we introduce the formal methods used in the DIMA project, describe the scope of their application, and discuss the results.
Original languageEnglish
Title of host publicationProceedings of Nuclear Plant Instrumentation and Control and Human-Machine Interface Technology, NPIC and HMIT 2025
Subtitle of host publicationProceedings
PublisherAmerican Nuclear Society (ANS)
Pages1774-1783
Number of pages10
ISBN (Electronic)978-0-89448-224-3
DOIs
Publication statusPublished - 2025
MoE publication typeA4 Article in a conference publication
Event14th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC&HMIT 2025 - Chicago, United States
Duration: 15 Jun 202518 Jun 2025
https://www.ans.org/meetings/npichmit25/

Conference

Conference14th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC&HMIT 2025
Abbreviated titleNPIC & HMIT 2025
Country/TerritoryUnited States
CityChicago
Period15/06/2518/06/25
Internet address

Keywords

  • formal verification
  • model checking
  • defense-in-depth
  • digital I&C
  • ontology

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