Overview of National Regulatory Practices for Using PSA in Slovakia

  • Jan Husarcek
Conference paper


This paper describes regulatory practices for using PSA in Slovakia. The approach of the Nuclear Regulatory Authority of the Slovak Republic to the PSA and its applications in practice are shortly outlined. Duties of the utility are provided on the scope, contents, review, quality assurance, and upgrading of PSA. Probabilistic safety criteria are given. Requirements to the PSA methodology, documentation, and results presentation are summarized. An overview of the PSA developments and comprehensive results of recent level-1 PSA studies for Slovak nuclear power plants Bohunice V-1, V-2, and Mochovce are given. Risk profile is shortly commented. PSA applications to plant design evaluation, support of plant upgrade and backfit activities, use of PSA in connection with plant technical specifications and evaluation of operational events are shortly described.


Slovak Republic Full Power Probabilistic Safety Nuclear Installation Probabilistic Safety Assessment 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.


Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.


  1. 1.
    Decree on safety documentation, No. 318/2002, UJD SR, Bratislava, April 2002Google Scholar
  2. 2.
    Application of PSA methodology in regulatory process, UJD SR guideline. BNS I.4.2/1999, UJD SR, Bratislava, 2000 (in Slovak)Google Scholar
  3. 3.
    Post-reconstruction full power and shutdown level-1 PSA study for unit 1 of Bohunice V-1 NPP. Relko, Bratislava, Bohunice V-1 NPP, 2002 (restricted)Google Scholar
  4. 4.
    Full power level-1 PSA study for unit 3 of Bohunice V-2 NPP, after implementation of changes in the emergency feed water system. Relko, Bratislava, Bohunice V-2 NPP, 2003 (restricted)Google Scholar
  5. 5.
    Shutdown PSA model for unit 3 of Bohunice V-2 NPP. Relko, Bratislava, Bohunice V-2 NPP, 2001 (restricted)Google Scholar
  6. 6.
    Probabilistic safety assessment of shutdown reactor and reactor on low power states (SPSA) for unit 1 SE-EMO. Report on harmonisation of full power and shutdown PSA models. VUJE, Mochovce NPP, 2002 (restricted)Google Scholar
  7. 7.
    Optimisation of allowed outage times and test intervals of safety systems for units of V-2 Bohunice NPP. Relko, 2R098, Bratislava, 1999 (restricted)Google Scholar
  8. 8.
    Evaluation of technical specifications and PSA-based analyses for Bohunice V-2 NPP. UJD SR, 99-08, Bratislava, 1999 (in Slovak)Google Scholar
  9. 9.
    Review of documentation submitted to fulfilment of UJD SR Decision No. 4/96, Task 6.1 and to proposed changes of LCOs. UJD SR, 110-01/2000, Bratislava, 2000 (in Slovak)Google Scholar
  10. 10.
    Review of the PSA study Bohunice V-l NPP after reconstruction. UJD SR 110-07/2000, Bratislava, 2000Google Scholar
  11. 11.
    Review of PSA study level-1 for NPP Mochovce. UJD SR, 110-06/2001, Bratislava, 2001 (in Slovak)Google Scholar
  12. 12.
    IPERS for the Bohunice V-2 NPP — low power and shutdown level-1 PSA. September 27-October 6, 1999, IAEA, RU-8978, Vienna, 2000Google Scholar
  13. 13.
    1PSART mission to the Mochovce NPP, level-1 PSA. 12-22 November, 2001, IAEA, TCR-01292, Vienna, 2002Google Scholar
  14. 14.
    IPSART for the Bohunice V-1 NPP, level-1 PSA. June 10-19, 2002, IAEA, TCR-01441, Vienna, 2002Google Scholar
  15. 15.
    Operational event analyses. UJD SR, 99-04, Bratislava, 1999Google Scholar
  16. 16.
    Probabilistic operational event analysis — break of the drainage line in Mochovce NPP. UJD SR, 240-04/2003, Bratislava, 2003 (in Slovak)Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Jan Husarcek
    • 1
  1. 1.Nuclear Regulatory Authority of the Slovak Republic (UJD SR)BratislavaSlovakia

Personalised recommendations