1. Code of Conduct at the Slovenian TRIGA reactor with emphasis on Periodic safety Review Borut Smodiš Institut “Jožef Stefan”, Ljubljana, Slovenija 1RM on the Application of CoC on the Safety of RR2 - 6 November 2015

2. CONTENTS 1.Application of Code of Conduct for RR in Slovenia 2.Legislation regulating research reactor – in implementation 3.New concept – graded approach 4.Safety Assessment of TRIGA 5.Periodic safety review 6.Content of PSR; 7.Details about the scope and content of PSR 8.Some results of PSR 22 - 6 November 2015RM on the Application of CoC on the Safety of RR

3. What is nuclear in SLO? Krško Nuclear Power Plant Research Reactor TRIGA Mark II Uranium Mine and Mill (closed) Interim Storage for LILW (not for waste from NPP) 3 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

4. TRIGA Mark II Reactor 4 Nuclear Training Centre Reactor LILW storage Hot Cells Facility 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

5. TRIGA Mark II Reactor 1st Criticality: 1966-05-31 Maximum steady state thermal power 250 kW 20% Low enriched uranium Fuel elements in the core: 61 Fresh fuel elements storage: 23 No spent fuel 1983: New fuel from Germany 1991: Reconstruction and upgrade to pulse mode operation: instrumentation, control panel, grid plates, fuel, control rods, irradiation channels, control rod mechanisms 1999: 219 fuel elements shipped back to US 2001: Replacement of primary coolant pumps 2003: Replacement of main parts of crane 5 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

6. TRIGA Mark II Reactor 2007: Fuel elements shipped to France 2008: Hot Cells Facility incorporated 2009: Upgraded electronic dosimetry system 2009: HD video camera for on-line video monitoring of tank installed 2009: Reactor building air conditioning system upgraded 2011: Electric supply renovation 2013: Fire protection system upgrade 2013: Entrance control modernisation In progress: Water leak control In progress: Pneumatic irradiation system modernisation 6 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

7. RESOLUTIONS Resolution on Nuclear and Radiation Safety in the Republic of Slovenia - for the period 2013-2023 Resolution on the 2006-2015 National Programme for Managing Radioactive Waste and Spent Nuclear Fuel 7 Application of CC for RR in SI 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

8. 1.Application of Code of Conduct for RR in Slovenia Convention on Nuclear Safety No. 2 (2001) Slovenian National Report on CNS – Annex K on TRIGA RR Code of Conduct on the Safety of Research Reactors (2004) SNSA accepted to apply the Code through new regulations In general, Slovenian regulations cover most of the Code 82 - 6 November 2015RM on the Application of CoC on the Safety of RR

9. 2.Legislation regulating research reactor Regulations on nuclear safety (2009) – based on the Ionising Radiation Protection and Nuclear Safety Act (2002, 2003, 2004, 2011, 2015) – JV5: Rules on radiation and nuclear safety factors (2009, 2010) – JV9: Rules on operational safety of radiation and nuclear facilities (2009, 2010, 2011) – Some specific exemptions in JV9 for TRIGA research reactor – JV5 Annex 2: Research Reactor Design Bases, prepared according to NS-R-4 “Safety of Research Reactors” (2005) – Both JV5 and JV9 are translated and available on the SNSA web site 92 - 6 November 2015RM on the Application of CoC on the Safety of RR

10. 3. New concept – graded approach In JV5/JV9 is introduced the co n cept of graded approach – Graded approach can be applied for NPPs, RR, other facilities: design bases for SSC preparation of SAR preparation of decommissioning plan safety management system design bases for a RR scope of a PSR – for the RR design bases - Par. 1.11 to 1.14 of the NS-R-4 for the RR Criteria for graded approach not defined yet - a proper justification is needed (case by case approach) Looking forward on the new IAEA safety standard 102 - 6 November 2015RM on the Application of CoC on the Safety of RR

11. Regulatory supervision and funding Regulatory and inspection authorities: Slovenian Nuclear Safety Administration (nuclear and radiation safety issues, radwaste) Slovenian Radiation Protection Administration (radiation protection of personnel) Administration for Civil Protection and Disaster Relief (emergency preparedness) Ministry of the Interior (physical protection) Financial resources for TRIGA operation: Ministry of Higher Education, Science and Sport 11 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

12. OO - requirements set by SNSA Head of RR, head of HCF (from 2009) 4 (3) operators, strong emphasis on personnel qualification and responsibilities (a new one in 2010) Reactor Safety Committee of IJS - review and control of all important safety issues Requirements for the organization in JV5, for the personnel qualifications in JV4 (2011) “Regulation on conditions to be fulfilled by workers performing safety-significant tasks at nuclear or radiation facilities” 12 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

13. OO – Reporting Requirements Reporting requirements are set in JV9 and in some decrees by the SNSA Annual reporting – basis for the SNSA annual report on nuclear and radiation safety (available on SNSA web site) Reporting in case of pulsing operation Reporting in case of emergency events International Safeguards reporting to IAEA and EURATOM Safety Performance Indicators – to IAEA Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management 13 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

14. 4. Safety Assessment of TRIGA TRIGA Mark II, “Safety Analysis Report” from 1991 following IAEA standard format, main document for safety evaluation Applications for all safety relevant modifications – including an Expert opinion by independent authorized organization on nuclear and radiation safety – implementation of modifications only upon approval from SNSA Periodic Safety Review International IAEA INSARR mission in 1992 at the request of the SNSA IAEA INSARR mission in 2012 142 - 6 November 2015RM on the Application of CoC on the Safety of RR

15. 5. Periodic Safety Review (1) In Krško NPP, first PSR in 2003, second PSR in 2013 PSR requirement set in 2002 Act, extended in JV9 PSR is required for extension of operational license! A practical guide issued by the SNSA on the PSR scope SNSA inspection in 2009 required TRIGA to prepare a PSR program – PSR scope agreed in 2010 152 - 6 November 2015RM on the Application of CoC on the Safety of RR

16. In 2011, the institute prepared an application for the approval of the periodic safety review programme, which the SNSA approved on 4 November 2011. The periodic safety review comprised 14 safety factors and was completed in 2014. Institute personnel and authorized external organizations performed periodic inspections and control of safety relevant structures, systems and components (SSC). The inspection did not recognize any improper SSC. In the course of the periodic safety review, inspection of the reactor vessel was performed. 16 5. Periodic Safety Review (2) 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

17. In PSR programme it was agreed: Scope and content Timetable Deadline to which the JSI had to submit a request for approval of the final report of the PSR. 6. Content of the PSR 2 - 6 November 2015RM on the Application of CoC on the Safety of RR17

18. 14 thematic reports & coordination activities with SNSA Duration of activities 36 months + extension Final report was submitted on 8. 9. 2014 6. Timetable 2 - 6 November 2015RM on the Application of CoC on the Safety of RR18

19. Safety factors defining the scope and contents of PSR included the following: 1. Facility 1. Facility design 2. Actual condition of SSCs 3. Equipment qualification 4. Facility ageing 2. Safety analyses 5. Deterministic safety analyses of the facility 6. Probabilistic safety analyses of the facility 7. Hazard and risk analyses regarding radiation or nuclear safety 3. Operation and application of operational experience feedback 8. Operational experience and operational indicators of the facility 9. Operational experience from other facilities and new results of scientific and technological development during the review period 7. Details about scope and content of PSR (1) 2 - 6 November 2015RM on the Application of CoC on the Safety of RR19

20. 4. Management 10. Management systems and organizational arrangements of the facility operator 11. Safety culture 12. Facility operator’s written procedures 13. Impacts of the personnel actions - human factor 14. Emergency preparedness plan 5. Environment 15. Radiation impacts on the environment 6. Conclusion 16.Summary assessment including an action plan of implementation of modifications and improvements 7. Details about scope and content of PSR (2) 2 - 6 November 2015RM on the Application of CoC on the Safety of RR20

21. By reviewing of 14 security-related items, 100 findings has been detected From 100 findings, 80 measures were determined and an Action Plan prepared to be implemented in 5 years It is most important that three security functions such as controlling the reactivity, fuel cooling and containment of radioactive substances are not compromised at any time so that the facility is safe. Majority of actions are related to regulatory compliance and the completion of a safety report and other documentation like for example: updating safety report, updating documentation for management system, updating decommissioning plan, etc... 7. Details about scope and content of PSR (3) 2 - 6 November 2015RM on the Application of CoC on the Safety of RR21

22. Implemented Action Plan will eliminate detected inconsistencies and the facility is licensed to operate for the next 10 years PSR also checked the implementation of the recommendations of the INSARR mission 2012 An expert opinion from authorised organization confirmed PSR compliance with the requirements of JV9 and practical guidelines PS 1:01. The authorized organization confirmed that the PSR report is acceptable. 7. Details about scope and content of PSR (4) 2 - 6 November 2015RM on the Application of CoC on the Safety of RR22

23. Cleaning of the reactor vessel 23

24. Visual inspection of the reactor vessel 24

25. Ultrasound inspection of the reactor vessel 25

26. Visual inspection of fuel elements 262 - 6 November 2015RM on the Application of CoC on the Safety of RR

27. NR inspection of fuel elements 272 - 6 November 2015RM on the Application of CoC on the Safety of RR

28. 28 2 - 6 November 2015RM on the Application of CoC on the Safety of RR

29. 29 Thank You For Your Attention !