Decommissioning and Radioactive Waste Management in Lithuania

Transcription

1 Conference Nuclear Power Safety Regulation Challenges to commemorate the 20 th anniversary of Lithuanian State Nuclear Power Safety Inspectorate (VATESI) Decommissioning and Radioactive Waste Management in Lithuania Vidas Paulikas Head of Radiation Protection Department State Nuclear Power Safety Inspectorate (VATESI) Vilnius, 10 November 2011

2 Regulation Requirements on release of radionuclides to environment from nuclear facilities and release plan, BSR ; Requirements on establishment and use of clearance levels of material and waste, produces during activities in the field of nuclear energy, BSR ; Requirements on Radiation protection in nuclear facilities, BSR ; Requirements on decommissioning of nuclear facilities, P ; Requirements on disposal of low and intermediate level radioactive waste, P ; Requirements on disposal of very low level radioactive waste, P ; Requirements on waste acceptance criteria to dispose radioactive waste to near surface facility, P

3 Nuclear facilities Ignalina nuclear power plant Units 1,2 Spent nuclear fuel storage Radioactive waste treatment facilities Maišiagala radioactive waste storage facility 3

4 Decommissioning Fund of decommissioning Planning of decommissioning Implementation of decommissioning 4

5 Funding National decommissioning fund International decommissioning fund Ignalina program 5

6 Decommissioning planning (1) Planning of state level : National strategy on energy; Law on Decommissioning; Governmental programme on decommissioning; Annual plan of measures of responsible ministry. Planning of operating organization level: Initial plan on decommissioning; Periodic review of decommissioning plan; Final decommissioning plan; Projects and its safety justification. 6

7 Decommissioning planning (2) Preliminary planning before construction license periodic review Final plan 2 years before shut down 7

8 Decommissioning planning (3) Initial decommissioning plan shall include following topics: Decommissioning strategy, Description of possibility of decommissioning, Demonstration that decommissioning implementation will be safe, Demonstration that proven or new technologies will influence safety, Quantities of radioactive waste, Funds needed for decommissioning and radioactive waste management. Review of Plan shall be performed together with Periodic Safety review of nuclear facility 8

9 Decommissioning planning (4)( Final decommissioning plan shall include: description of INPP and operating history; chosen decommissioning strategy; description of proposed decommissioning activities; description of decommissioning organization; description of proposed methods of waste management, including hazardous and mixed waste; description of safety and radiation protection procedures; description of quality management; estimate of decommissioning cost and etc. Review of Final Plan shall be performed each 5 years. 9

10 Dismantling & Decontamination project Objective: To dismantle equipment of 117/1 building; To decontaminate elements up to clearance levels. D&D of 117/1 Start of dismantling activities beginning of 2011; Completion of dismantling and decontamination at the end of

11 Dismantling & Decontamination project D&D of 117/1 11

12 Directions of radioactive waste management 12

13 New facilities Storage for spent nuclear fuel Objectives to store the rest spent nuclear fuel and manage damaged fuel will be stored. 13

14 New Facilities Treatment facilities for solid radioactive waste Objective to treat and store solid radioactive waste produced during operation and decommissioning m3 operational waste and m3 decommissioning waste will be treated Capacity of the facility will be 15 m3 per day. 14

15 New facilities Retrieval of radioactive waste from buildings155,155/1,157,157/1 Objective to retrieve, sort and prepare to treat solid radioactive waste m3 of group 1 waste are stored in buildings 155 and155/ m3 of groups 1,2 ir 3 waste are stored in buildings 157 and157/1. 15

16 New facilities Very low level radioactive waste disposal facility Objective to dispose short-lived very low level radioactive waste. Capacity of the facility is 3 modules for m 3 each. 16

17 New Facilities Low and intermediate level radioactive waste disposal falility Objective to dispose short-lived low and intermediate level radioactive waste. Capacity of the facility is about m3. 17

18 Thank you for your attention 18