Code of Conduct at the Slovenian TRIGA reactor

Code of Conduct at the Slovenian TRIGA reactor with emphasis on Periodic safety Review Borut Smodiš Institut “Jožef Stefan”, Ljubljana, Slovenija 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR

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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 2

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) 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 3

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

TRIGA Mark II Reactor • 1 st Criticality: 1966 -05 -31 • Maximum steady state thermal power 250 k. W • 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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 5

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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 6

Application of CC for RR in SI 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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 7

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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 8

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) – JV 5: Rules on radiation and nuclear safety factors (2009, 2010) – JV 9: Rules on operational safety of radiation and nuclear facilities (2009, 2010, 2011) – Some specific exemptions in JV 9 for TRIGA research reactor – JV 5 Annex 2: Research Reactor Design Bases, prepared according to NS-R-4 “Safety of Research Reactors” (2005) – Both JV 5 and JV 9 are translated and available on the SNSA web site 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 9

3. New concept – graded approach • In JV 5/JV 9 is introduced the concept 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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 10

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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 11

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 JV 5, for the personnel qualifications in JV 4 (2011) “Regulation on conditions to be fulfilled by workers performing safety-significant tasks at nuclear or radiation facilities” 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 12

OO – Reporting Requirements • Reporting requirements are set in JV 9 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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 13

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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 14

5. Periodic Safety Review (1) • In Krško NPP, first PSR in 2003, second PSR in 2013 • PSR requirement set in 2002 Act, extended in JV 9 • 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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 15

5. Periodic Safety Review (2) • 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. 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 16

6. Content of the PSR 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. 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 17

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

7. Details about scope and content of PSR (1) Safety factors defining the scope and contents of PSR included the following: 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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 19

7. Details about scope and content of PSR (2) 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 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 20

7. Details about scope and content of PSR (3) • By reviewing of 14 security-related items, 100 findings has been detected • From 100 findings, 80 measures were determined 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. . . 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 21

7. Details about scope and content of PSR (4) • 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 JV 9 and practical guidelines PS 1: 01. • The authorized organization confirmed that the PSR report is acceptable. 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 22

Cleaning of the reactor vessel 23

Visual inspection of the reactor vessel 24

Ultrasound inspection of the reactor vessel 25

Visual inspection of fuel elements 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 26

NR inspection of fuel elements 2 - 6 November 2015 RM on the Application of Co. C on the Safety of RR 27

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Thank You For Your Attention ! 29