1. Expert Review of the Licensing Documentation of the Centralized Facility for Long-Term Storage of Disused Sealed Radiation Sources Oleksii Tokarevskyi Regional Workshop on the Regulatory Review of the Safety Case and Safety Assessment for Safe Management of RW Vienna September 28 – October 2, 2015 State Nuclear Regulatory Inspectorate of Ukraine National Academy of Sciences of Ukraine SSTC NRS State Scientific and Technical Center for Nuclear and Radiation Safety

2. Contents 1. Ukrainian approach to Safety Case – the regulatory basis 2. Example of the Safety Case in the framework of licensing of the Centralized Storage Facilty for Disused SRS 2 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

3. 1. Ukrainian approach to the Safety Case State Nuclear Regulatory Inspectorate of Ukraine National Academy of Sciences of Ukraine SSTC NRS State Scientific and Technical Center for Nuclear and Radiation Safety

4. Safety Case - Definition SF-1 - IAEA Safety Glossary: Safety Case - a collection of arguments and evidence in support of the safety of a facility or activity This will normally include the findings of a safety assessment and a statement of confidence in these findings. For a repository, the safety case may relate to a given stage of development. In such cases, the safety case should acknowledge the existence of any unresolved issues and should provide guidance for work to resolve these issues in future development stages. 4 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

5. Approach to the Safety Case – Regulatory Basis (1) Laws of Ukraine: On Use of Nuclear Power On Radioactive Waste Management On Permit Activity in the Field of Nuclear Energy Utilization 5 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

6. Approach to the Safety Case – Regulatory Basis Safety Conditions and Requirements (Licensing Conditions) for Activities on Treatment, Storage and Disposal of Radioactive Waste (NP 306.5.04/2.060-02) Requirements on Structure and Contents of the Safety Analysis Report for Radioactive Waste Treatment Facilities (NP-306.3.02/3.043-01) Requirements on Structure and Contents of the Safety Analysis Report for Radioactive Waste Storage Facilities (NP-306.4.142-2008) Requirements on Structure and Contents of the Safety Analysis Report for Near-Surface Radioactive Waste Disposal Facilities (NP- 306.3.02/3.038-00) 6 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

7. Approach to the Safety Case – Regulatory Basis (2) Management of RW in places of its generation under licensing: of nuclear facility of production or use of radiation sources Following RW management activities are subject to licensing: treatment, storage of RW transportation of RW training, advanced training of specialists in field of RW management Law of Ukraine "On Permit Activity in the Field of Nuclear Energy Utilization" (Article 7) The Operator of RW disposal facility has to obtain license for: construction, operation, closure Law of Ukraine "On Permit Activity in the Field of Nuclear Energy Utilization" (Article 8) 7 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

8. Safety Case and Licensing Documents submitted in the framework of licensing process: Safety analysis report for design stage Technical specifications for safety-related systems and equipment Programs for acceptance tests for safety-related systems and equipment Program for integrated test of the facility Safety analysis report for operation stage Technological procedures for operation (decommissioning, closure) Technical specifications for packages Program (procedures, scope) of radiation control and environmental monitoring Emergency plan and instructions for the staff in case of accidents and emergencies Safety Conditions and Requirements (Licensing Conditions) for Activities on Treatment, Storage and Disposal of Radioactive Waste (NP 306.5.04/2.060-02) 8 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

9. Safety Case and Licensing Safety reassessment is carried out: – at least once in 10 years taking into account operation feedback, modifications and upgrades, conclusions of state expert reviews, etc. – more frequently if changes in technique may have an impact on safety level or if operational feedback indicates drawbacks of the technique Safety Conditions and Requirements (Licensing Conditions) for Activities on Treatment, Storage and Disposal of Radioactive Waste (NP 306.5.04/2.060-02) 9 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

10. 2. Example of the Safety Case in the framework of licensing of the Centralized Storage Facility for Disusrd SRS State Nuclear Regulatory Inspectorate of Ukraine National Academy of Sciences of Ukraine SSTC NRS State Scientific and Technical Center for Nuclear and Radiation Safety

11. Vector Complex – General Information The Vector site is located in the Chernobyl exclusion zone It is planned to supply to this site almost all Ukrainian waste (both conditioned and that require treatment): Chernobyl Exclusion Zone ≈ 1,500,000 m 3 ChNPP (including the Shelter Object) ≈ 650,000 m 3 NPPs in operation ≈ 200,000 m 3 «Radon» facilities ≈ 5000 m 3 Vector Complex: near-surface disposal facilities long-term storage facilities treatment facilities 11

12. Centralized Storage Facility for Disused SRS Main functions: Characterization and treatment of disused SRS Long-term storage of disused SRS 12 c The Centralized Storage for Disused SRS is intended for reception, identification, sorting, kitting, packaging, certification and further separate storage of disused sealed sources of alpha-, beta-, gamma- and neutron (α, β, γ, η) radiation sources up to their further transfer for disposal. Operation life – at least 50 years.

13. Centralized Storage Facility for Disused SRS (2) Where from disused SRS will arrive to the Centralized Storage? 13 ETSON WM&D Group Meeting Vienna, May 14-15, 2015

14. Centralized Storage Facility for Disused SRS (3) Technological streams: RTG (  -sources) – placement for storage without treatment BGI (  -source units) – treatment in hot cells neutron sources – treatment in hot cells other SRS with higher activity to be processed in the hot cell 14, May 14-15, 2015 other SRS with lower activity to be processed in the radiation protection box Specific criteria for segregation between streams 4 and 5 will be developed after “hot” tests and agreement of safety analysis report by the regulatory body.

15. Safety Analysis Report – Structure Chapter 1. General information Chapter 2. Site characteristics Chapter 3. Basic design solutions Chapter 4. Waste acceptance criteria Chapter 5. Construction of the facility Chapter 6. Operation of the facility Chapter 7. Management of secondary waste Chapter 8. Physical protection Chapter 9. Radiation safety Chapter 10. Environmental impact assessment Chapter 11. Decommissioning Chapter 12. Quality assurance 15 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

16. Safety Analysis Report – Key Safety Issues 1. Reception of disused SRS at the Centralized Storage, ensuring safe identification of disused SRS during their segregation by streams. 2. Sorting criteria and characterization of disused SRS. 3. Determination of damaged disused SRS. 4. Sorting and certification procedures (in particular, prevention of mistakes during placement of disused SRS into packages after characterization of disused SRS). 5. Criteria of acceptability of disused SRS for their placement into package (capsule) (in particular, construction materials of disused SRS that impede their long-term storage in tight package, contamination of disused SRS with organic materials, moisture), and control of these criteria. 6. Characteristics of packages for long-term storage of disused SRS, as well as storage cells and pits 7. Control and monitoring during long-term storage of disused SRS. 16 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

17. Safety Analysis Report – Key Safety Issues (1) 1. Reception of disused SRS at the Centralized Storage, ensuring safe identification of disused SRS during their segregation by streams streams of disused SRS sorting by streams (at SISE or at Centralized Storage?) current condition of disused SRS on-receipt identification 17 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

18. Safety Analysis Report – Key Safety Issues (2) 2.Sorting criteria and characterization of disused SRS clearance levels as sorting criteria possibility and need for disposal in the near-surface facility determination of specific activity recommended to sort by time for reaching of compliance with waste acceptance criteria for disposal long-living RW – disposal in geological repository only high-level RW – is it necessary to sort them out? 18 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

19. Safety Analysis Report – Key Safety Issues (3) 3.Determination of damaged disused SRS possible only in radiation protection box or hot cells dependence on design of disused SRS criteria for permissible release of aerosols from the package during long-term storage should be established minimum activities of disused SRS for which the above-mentioned criteria may be exceeded surface-type disused SRS – damage is not so critical for long-term storage 19 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

20. Safety Analysis Report – Key Safety Issues (4) 4.Sorting and certification procedures (in particular, prevention of mistakes during placement of disused SRS into packages after characterization of disused SRS) Entering initial data about disused SRS, obtained from the Supplier, to the database of the Centralized Storage Removal of disused SRS from the container in RPB or HC and identification of disused SRS Measurement of radiation characteristics of disused SRS and their entering to the database Calculation of time to reach the clearance levels (or acceptance criteria for disposal) and determination of capsule/container for placement of disused SRS Placement of disused SRS into appropriate capsule/container and capsule into the loading sleeve Drawing up certificate for package of disused SRS (sleeve, container or collection container) Placement of sleeve into storage cell or container into storage pit 20 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

21. Safety Analysis Report – Key Safety Issues (5) 5.Criteria of acceptability of disused SRS for their placement into package (capsule) (in particular, construction materials of disused SRS that impede their long-term storage in tight package, contamination of disused SRS with organic materials, moisture), and control of these criteria chemical interaction between stainless steel, lead and construction materials of disused SRS gas generation prevention of penetration of contamination and moisture and package inside the package 21 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

22. Safety Analysis Report – Key Safety Issues (6) 6.Characteristics of packages for long-term storage of disused SRS, as well as storage cells and pits packages for long-term storage of disused SRS: – capsules – collection containers – containers for neutron sources cells and pits for long-term storage of disused SRS: – storage cells – storage pits for neutron sources – section for storage of containers of stream 5 22 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

23. Safety Analysis Report – Key Safety Issues (7) 7.Control and monitoring during long-term storage of disused SRS monitoring of radiation parameters control of condition of barriers of the package control of conditions of storage locations 23 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

24. Centralized Storage for Disused SRS – Licensing Steps Design was approved (including SAR for the design stage) License for the type of activity – storage of RW – was granted (License No.OV000975) License permitted construction of the Centralized Storage Facility for Disused SRS provided that: Technical specifications for safety-related systems are to be developed and agreed by SNRIU List of constructions activities related to the technological process is submitted to SNRIU (such activities had to be performed only after agreement of technical specifications) SAR to be updated as regards the next stage of life cycle of the facility 24 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

25. Licensing Process – Documents under Review Technical specifications for safety-related systems: hot cells radiation protection box ventilation radiation monitoring Programs for acceptance tests for safety-related equipment Programs for integrated "cold" test of the facility 25 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

26. Licensing Process – Other Documents to be Reviewed Safety Analysis Report for Operation Program for "hot" test of the facility Technological procedures for operation Emergency plan Technical specifications for packages Program of radiation control and radiation monitoring 26 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

27. Centralized Storage for Disused SRS – Actual Situation construction is completed cold tests are completed final TS are agreed by the regulatory body safety case for operation is under preparation 27 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015

28. Thank you for your attention! 28 Technical Meeting of the International Project on Demonstration of the Operational and Long- Term Safety of Predisposal Management Facilities for Radioactive Waste (CRAFT Part II) Vienna, September 28 – October 2, 2015