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Code of Conduct at the Slovenian TRIGA reactor with emphasis on Periodic safety Review Borut Smodiš Institut “Jožef Stefan”, Ljubljana, Slovenija 1 RM on the Application of CoC on the Safety of RR 2 - 6 November 2015

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Page 1: Code of Conduct at the Slovenian TRIGA reactor with emphasis on Periodic safety Review Borut Smodiš Institut “Jožef Stefan”, Ljubljana, Slovenija 1RM on

Code of Conduct at the Slovenian TRIGA reactor with emphasis on Periodic safety

ReviewBorut Smodiš

Institut “Jožef Stefan”, Ljubljana, Slovenija

1RM on the Application of CoC on the Safety of RR

2 - 6 November 2015

Page 2: Code of Conduct at the Slovenian TRIGA reactor with emphasis on Periodic safety Review Borut Smodiš Institut “Jožef Stefan”, Ljubljana, Slovenija 1RM on

CONTENTS

1.Application of Code of Conduct for RR in Slovenia

2.Legislation regulating research reactor – in implementation

3.New concept – graded approach4.Safety Assessment of TRIGA5.Periodic safety review6.Content of PSR; 7.Details about the scope and content of PSR8.Some results of PSR

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Page 3: Code of Conduct at the Slovenian TRIGA reactor with emphasis on Periodic safety Review Borut Smodiš Institut “Jožef Stefan”, Ljubljana, Slovenija 1RM on

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) 32 - 6 November 2015RM on the Application of CoC on the Safety of RR

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TRIGA Mark II Reactor

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Nuclear Training Centre

Reactor

LILW storageHot Cells

Facility

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

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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

52 - 6 November 2015RM on the Application of CoC on the Safety of RR

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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

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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

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Application of CC for RR in SI

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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

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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

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3. New concept – graded approach

• In JV5/JV9 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 10

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

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Regulatory supervision and fundingRegulatory 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

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

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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”

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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

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

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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

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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

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• 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. 1

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5. Periodic Safety Review (2)

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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

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• 14 thematic reports & coordination activities with SNSA• Duration of activities 36 months + extension• Final report was submitted on 8. 9. 2014

6. Timetable

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Safety factors defining the scope and contents of PSR included the following:

1. Facility1. Facility design2. Actual condition of SSCs 3. Equipment qualification4. Facility ageing

2. Safety analyses5. Deterministic safety analyses of the facility6. Probabilistic safety analyses of the facility7. 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 facility9. 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)

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4. Management10. Management systems and organizational arrangements of the facility operator11. Safety culture12. Facility operator’s written procedures13. Impacts of the personnel actions - human factor14. Emergency preparedness plan

5. Environment15. Radiation impacts on the environment

6. Conclusion16.Summary assessment including an action plan of implementation of modifications and improvements

7. Details about scope and content of PSR (2)

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• 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)

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• 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)

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Cleaning of the reactor vessel

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Visual inspection of the reactor vessel

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Ultrasound inspection of the reactor vessel

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Visual inspection of fuel elements

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NR inspection of fuel elements

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Thank You For Your Attention !