Status of Radioactive Waste Management in Japan

Transcription

1 Status of Radioactive Waste Management in Japan Regional Meeting on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Gyeongju, 5-8 November, 2013 OTSUKA, Ichiro Nuclear Fuel Cycle and Radioactive Waste Management Safety Department Japan Nuclear Energy Safety Organization (JNES) 1

2 Contents 1. Major update of regulatory system on RW management 2. Current status of Fukushima Daiichi NPS 3. On-site activities related to the Fukushima Daiichi accident 3.1 Progress of mid-to-long term roadmap 3.2 Management of contaminated water 4. Off-site activities related to the Fukushima Daiichi accident 4.1 Decontamination work 4.2 Interim storage program Annex 1: Summary of basic information on the national program Annex 2: Main challenges in these 3 years Annex 3: Legal framework of decontamination work 2

3 1. Major update of regulatory system on radioactive waste management New Nuclear Regulation Authority Since 19 September, 2012 (source: NRA web site ) 3 3

4 1. Major update of regulatory system on radioactive waste management Competent minister Previous System Present System Waste Management Facility Decommissioning Rad-waste generated from commercial reactor and fuel cycle facilities Rad-waste generated from research reactor, research lab, and RI (since April 2013) Commercial reactor and fuel cycle facilities Research reactor and research lab. (since April 2013) METI MEXT METI MEXT Nuclear Regulation Authority (NRA) At the present, major change in regulation of radioactive waste management is only the change of competent minister. New regulatory requirements on RW management facility are under discussion in NRA (it will be implemented in this December). 4

5 1. Major update of regulatory system on radioactive waste management Outline of new regulatory requirements on rad-waste disposal facilities (source: NRA web site) 5

6 1. Major update of regulatory system on radioactive waste management (source: NRA web site) 6

7 2. Current status of Fukushima Daiichi NPS (source: NRA web site) 7

8 2. Current status of Fukushima Daiichi NPS Molten cores and spend fuels Molten cores in RPV and PCV, and spent fuels in SFP have been cooled. H 2 concentration in PCV have been much lower than flammability limit. (source: NRA web site) 8

9 3. On-site activities of related to the Fukushima Daiichi accident Mid-to-long term roadmap towards the Decommissioning of Fukushima Dai-ichi Nuclear Power Station Units 1-4 Step 2 Completion on Dec. 16, 2011 Within 2 Years Within 10 Years After Years STEP 1, 2 Phase 1 Phase 2 Phase 3 Removal of spent fuel from pools Removal of fuel debris Decommissioning Actions towards systematic staff training and allocation, improving motivation, and securing worker safety will be continuously implemented (source: TEPCO web site ) 9

10 3.1 Progress of mid-to-long term roadmap (1) Radiation Dose Reduction and Contamination Mitigation Effective dose reduction at site boundaries (aiming to achieve 1mSv/year by the end of FY 2012) and purification of the water in the port are proceeded for the purpose of mitigating radiation impact on the outside environment. Effective dose reduction at site boundaries The goal: 1mSv/y (additional exposure dose at site boundaries) The goal was achieved by transporting debris to the soil-covered-type temporary storage facilities etc. The breakdown of radiation exposure amount Gaseous waste:0.03msv/y Solid waste: 0.69mSv/y Total: 0.72mSv/y. Closure of the blow out panel (BOP) opening at Unit 2 Reactor Building Construction of impermeable walls (source: TEPCO web site ) 10

11 (2) Fuel removal from SFP 3.1 Progress of mid-to-long term roadmap Work towards spent fuel removal is being steadily progressed while ensuring seismic capacity and safety. In particular, efforts are being made to achieve the early start and completion of Unit 4 spent fuel removal (Planned to be started in November 2013 and completed at around the end of 2014). Unit 4: The cover installation for Fuel removal is ongoing. Unit 3: Platform installation and debris removal from upper part of reactor building is ongoing. Soundness inspection of Unit 4 reactor building and SFP was performed. Temporary dry cask storage facility is in operation (source: TEPCO web site ) 11

12 (3) Fuel debris removal 3.1 Progress of mid-to-long term roadmap In addition to decontamination and shield installation being carried out for improved accessibility to the PCV, technology development and data acquisition necessary to prepare for fuel debris removal (such as investigating and repairing the leakage location of the PCV) are being advanced. Development of remote control decontamination technology Removal of obstacles from the first floor of Units 1 and 3 Investigation of Units 1-2 Torus Room (source: TEPCO web site ) 12

13 3.1 Progress of mid-to-long term roadmap (4) Radioactive Waste Management Rubble segregation <0.1mSv/h Open air storage 0.1~ less than 1mSv/h Covered by sheet 1~ less than 30mSv/h Temporary storage facility (if necessary, covered by soil) 30mSv/h~ less than 1Sv/h Storage in building or container >1Sv/h Container storage in building (source: TEPCO web site ) 13

14 3.1 Progress of mid-to-long term roadmap (5) R&D program related to radioactive waste Management Board and Research and Development Management Headquarters have been established under the Council on Mid-to-Long-Term Response for Decommissioning (December 21, 2012)*. Meetings have been held monthly to manage progress on the Roadmap. 3 Working groups and one Task Force were established. Working Group for Fuel Removal from the Spent Fuel Pool Working Group for Fuel Debris Removal Working Group for Waste Management Task Force on the Remote handling * The Council on Mid-to-Long-Term Response for Decommissioning is reformed as The Council for the Decommissioning of TEPCO Fukushima Daiichi Nuclear Power Station as of Feb. 8, (source: TEPCO web site ) 14

15 3.1 Progress of mid-to-long term roadmap (5) R&D program related to radioactive waste (cont d) Working Group for Fuel Debris Removal Characterization and treatment - Characterization (2014~) - Develop treatment process suitable for waste reacted with sea water and core internals - Develop disposal concept Working Group for Waste Management Secondary Waste from treatment of waste water (sludge, zeolite absorbent etc.) - Characterization of waste - Long-term storage - Study on waste form Rubble and trimmed trees - Measurement of radioactivity - Develop analysis method of nuclides difficult to measure (e.g. Mo-93 and Zr-93 (source: TEPCO web site ) 15

16 3.2 Management of contaminated water Contaminated water in turbine buildings is treated and injected to RPVs. 400m 3 /d of ground water is inflowing buildings forces increase of capacity of tanks. (source: NRA web site) 16

17 3.2 Management of contaminated water Radioactivity level of contaminated water 340,000m 3 of various activity levels of contaminated water is stored in the storage tank. 280,000m 3 out of total volume is and low-level Cs water that was treated with reverse osmosis (RO) membrane. It is stored in steel-made cylindrical storage tank with flange. [Sep.3] (source: NRA web site) 17

18 3.2 Management of contaminated water Leakage of β and low-level Cs Water from Cylindrical Tank Puddle and trace of water flow with nuclide were found by TEPCO (August 19, 2013) (source: NRA web site) 18

19 3.2 Management of contaminated water (source: NRA web site) 19

20 Hot spots in the storage area 3.2 Management of contaminated water (source: NRA web site) 20

21 Radioactivity of ground water 3.2 Management of contaminated water (source: NRA web site) 21

22 Radioactivity of sea water in harbor 3.2 Management of contaminated water (source: NRA web site) 22

23 3.2 Management of contaminated water Radioactivity of sea water near Fukushima Daiichi NPS (source: NRA web site) 23

24 3.2 Management of contaminated water NRA s Action (source: NRA web site) 24

25 3.2 Management of contaminated water (source: NRA web site) 25

26 4.1 Decontamination work (source: MOE document) 26

27 (1)Countermeasure area Reclassified the Evacuation Areas by Nuclear Emergency Response Headquarters (August 7, 2013) 3. Progress of interim storage program Area1; <20mS/y Areas in which evacuation orders are ready to be lifted Area2; 20-50mSv/y Areas in which residents are not permitted to live Area3; >50mSv/y Areas where it is expected that residents will face difficulties in returning for a long time (source: METI web site) METI: Ministry of Economy, Trade and Industry 27

28 3. Progress of interim storage program (2)Basic approach of decontamination work (source: MOE document) 28

29 Amount of contaminated soil and wastes generated by decontamination will be over 30million m 3 in maximum. Require ISF to be approx. 28million m 3 capacity in maximum. Estimated Volume:approx. 500,000 t/y. approx. 60,000 t/y. approx million m 3 Specified waste 4.2 Interim storage program Countermeasure area waste 8,000Bq/kg+ Designated waste Contaminated soil etc. below 8,000Bq/kg over 8,000Bq/kg Combustibles Incinerate Ash etc. Incinerate combustibles Usual process as in non-mgmt. areas (source: MOE web site) below 100,000Bq/kg Controlled repository/disposal sites Monitor by national government Over 100,000Bq/kg Temporary storage Interim Storage Facility (ISF) Final disposal 29 29

30 4.2 Interim storage program (source: MOE document) 30

31 4.2 Interim storage program (source: MOE document) 31

32 4.2 Interim storage program (source: MOE document) 32

33 3. Progress of interim storage program 33

34 Thank you for your attention!! 34

35 Annex 1: Summary of basic information on the national program Overview of Policy and Practice on Spent Fuel Management and Radioactive Waste Management. Based on the accident at TEPCO s Fukushima NPPs, now deliberations are being conducted to formulate the new policy in the Japan Atomic Energy Commission. (source: 4 th review meeting of JC) 35

36 Annex 1: Summary of basic information on the national program Current Status -Nuclear Installations- Nuclear Reactor: 83 Nuclear Fuel Cycle Facilities: 11 Power reactors:64 Fuel facilities: 6 in operation: 50 uranium enrichment facility: 2 under construction: 3 fuel fabrication facility: 3 under decommissioning: 8 fuel conversion and Research reactors: 22 fabrication facility: 1 in operation :15 Reprocessing facilities: 2 under decommissioning: 7 in operation: 1 under construction: 1 Waste storage facilities: 2 Waste disposal facilities: 2 Nuclear fuel material utilization Facility: 15 (source: 4 th review meeting of JC) As of April

37 Annex 1: Summary of basic information on the national program Recycle fuel storage center Mox fabrication facility Fugen ATR (Under decommissioning) (source: 4 th review meeting of JC) 37

38 Annex 1: Summary of basic information on the national program Radioactive wastes are appropriately categorized and safely disposed of. Waste to be geologically disposed of High level radioactive waste Long lived low heat generating radioactive waste (TRU waste) [Waste beyond a certain level of activity only] Waste disposed of at subsurface or near surface Waste other than the waste which is disposed of in geological disposal Prohibition of sea dumping Amendment of the Reactor Regulation Law in May 2005 <Categorization of Radioactive Waste Disposal Methods in Japan> (source: 4 th review meeting of JC) 38

39 Annex 1: Summary of basic information on the national program Spend Fuel <Dry storage> Nuclear power plant : approx. 14,000t* Reprocessing plant : approx. 3,300t** Research reactor: 34t* * As of March 2011 ** As of August 2012 <Wet Storage> 39

40 Annex 1: Summary of basic information on the national program High level radioactive waste Vitrified Waste: 1,882 packages Rokkasho Reprocessing site Reprocessing facility: 221 packages Waste storage facility: 1,442 packages ( returned from overseas) Tokai Reprocessing Facility: 247 packages As of October

41 Annex 1: Summary of basic information on the national program Inventory of low-level waste disposed Rokkasho disposal site No.1: 147,187(200L drums) No.2: 109,432(200L drums) Tokai R&D Center Disposal site: 1,670 ton As of October

42 Annex 1: Summary of basic information on the national program Facilities in decommissioning state 4 Power Reactors 7 Research Reactors Power Reactors Research Reactors Name of facility Output Operation Status Tokai Power Plant 166MWe 1966~1998 Under decommissioning ATR Fugen 165MWe 1979~2003 Under decommissioning Hamaoka NPS unit 1 540MWe 1976~2009 Under decommissioning Hamaoka NPS unit 2 840MWe 1978~2009 Under decommissioning JRR 2 10MW 1960~1996 Under decommissioning Nuclear ship Mutsu 36MW 1974~1992 dismantled DCA 1kW 1969~2001 Under decommissioning HTR 100kW 1961~1975 Under decommissioning TTR 1 100kW 1962~2001 Under decommissioning RUR 100kW 1961~2001 Under decommissioning MITRR 100kW 1963~2004 Under decommissioning As of October

43 Start of Decommissioning of Hamaoka Nuclear Power Station Units 1 and 2 of the Chubu Electric Power Co. Inc Unit1 12/10/1970 Permit for reactor installation 6/20/1974 First criticality 3/17/1976 Start commercial operation 11/7/2001 Stop operation (19th periodic inspection) 11/11/2005 Completion of fuel removal from reactor 1/30/2009 Terminate commercial operation 11/18/2009 Approval for decommissioning plan 2/16/2011 Approval for modification of decommissioning plan Unit2 6/9/1973 Permit for modification of reactor installation 3/28/1978 First criticality 11/29/1978 Start commercial operation 2/21/2004 Stop operation (20 th periodic inspection) 3/1/2004 Completion of fuel removal from reactor 1/30/2009 Terminate commercial operation 11/18/2009 Approval for decommissioning plan 2/16/2011 Approval for modification of decommissioning plan (source: 4 th review meeting of JC) Annex 2: Main challenges in these 3 years General Information Electric Power : 1Unit1 540 MWe 2Unit2 840 MWe Reactor type : Boiling Water Reactor (BWR) Start operation : 1March 17,1976 2November 29,1978 Stop operation : 1November 7,2001 2February 21,2004 operation period : 126 years 227 years Location : Omaezaki City, Shizuoka Prefecture The decommissioning schedule of unit 1 and unit2(outline) Approval for decommissioning plan Early 2010 s Late 2010 s Application for approval for modification of decommissioning plan Preparation for dismantlement(fuel removal from SFP decontamination) Dismantlement of the facilities outside reactor As of April 2009 Dismantlement of reactor 2020 s 2030 s Application for confirmation about termination of decommissioning Confirmation Disposal of waste generated by dismantlement 43

44 Annex 2: Main challenges in these 3 years Start of Decommissioning of Hamaoka Nuclear Power Station Units 1 and 2 of the Chubu Electric Power Co. Inc Unit1 12/10/1970 Permit for reactor installation 6/20/1974 First criticality 3/17/1976 Start commercial operation 11/7/2001 Stop operation (19th periodic inspection) 11/11/2005 Completion of fuel removal from reactor 1/30/2009 Terminate commercial operation 11/18/2009 Approval for decommissioning plan 2/16/2011 Approval for modification of decommissioning plan General Information Unit1 Unit2 Electric Power 540 MWe 840 MWe Reactor type Boiling Water Reactor (BWR) Start operation March 17,1976 November 29,1978 Stop operation November 7,2001 February 21,2004 operation period 26 years 27 years Location Omaezaki City, Shizuoka Prefecture Unit2 6/9/1973 Permit for modification of reactor installation 3/28/1978 First criticality 11/29/1978 Start commercial operation 2/21/2004 Stop operation (20 th periodic inspection) 3/1/2004 Completion of fuel removal from reactor 1/30/2009 Terminate commercial operation 11/18/2009 Approval for decommissioning plan 2/16/2011 Approval for modification of 44 decommissioning plan

45 Annex 2: Main challenges in these 3 years Start of Decommissioning of Hamaoka Nuclear Power Station Units 1 and 2 of the Chubu Electric Power Co. Inc The decommissioning schedule of unit 1 and unit2 (outline) Early 2010 s Late 2010 s 2020 s 2030 s Approval for decommissioning plan Application for Application for confirmation approval for about termination of modification of decommissioning decommissioning plan Confirmation Preparation for dismantlement(fuel removal from SFP decontamination) Dismantlement of the facilities outside reactor Dismantlement of reactor Disposal of waste generated by dismantlement 45

46 Annex 2: Main challenges in these 3 years Study for basic safety of returned waste (CSD B and CSD C) Confirm specification and production method of returned waste Confirm its conformity with Nuclear Safety Commission(NSC) decision* The contents of the NSC decision The selection of considerable evaluate items and abstract of related specification Understanding of the necessary data for evaluation Stability of returned waste itself Confirm that returned waste is stable solid and the canister has sufficient corrosion resistance based on the NSC decision. Safety of storage Confirm whether it is possible to design radioactive waste management facility for returned waste based on the NSC decision. Study for basic safety Stability of returned waste itself Safety of storage Safety of disposal Confirm its conformity with the ministerial ordinance for disposal of nuclear fuel material and material contaminated by nuclear fuel material outside the factory or the place of activity Waste management facility in Japan (Abstract from web page of Japan Nuclear Fuel Limited) Safety of disposal Confirm sufficiency of necessary information for safety assessment of 46 disposal based on the NSC decision.

47 Annex 2: Main challenges in these 3 years Outline of Establishment of the Clearance System for Uranium Processing Facilities Clearance object Metal generated from fuel (except MOX fuel) processing facility. Nuclide as object Select five nuclides based on the specification and performance of fuel processing facility. U 232,U 234,U 235,U 236,U 238 Clearance level Nuclide as object Clearance level (Bq/g) U U U U U

48 Annex 3: Legal framework of decontamination work Disaster Waste Safety Assessment Study Panel (1) Handling of the disaster waste in Fukushima Prefecture (2) Handling of general waste and the like in the concerned prefectures (3) Handling of the disaster waste in Iwate Prefecture and Miyagi Prefecture etc. Remediation Study Panel (1) Basic concepts of decontamination, matters that need to be borne in mind when implementing decontamination measures (2) Appropriate decontamination measures tailored to the amount of radiation (3) Requirements for designating areas and/or the principles of decontamination to be conducted by municipalities (4) Standards for the collection/transfer of waste to be stipulated pursuant to the relevant law. Act on Special Measures concerning the Handling of Radioactive Pollution Promulgated: at the end of August 2011, Fully came into force: January 1, 2012 Basic Principles of the Act (Decontamination works) -Decided by the Cabinet: November 11, 2011 (source: MOE document) 48

49 Purpose Annex 3: Legal framework of decontamination work Outlines of the Act on Special Measures concerning the Handling of Radioactive Pollution To promptly reduce the impacts of environment pollution by instituting measures taken by stakeholders, especially,the national and local governments, the relevant nuclear power producer (i.e. Tokyo Electric Power Company) Roles of Stakeholders (1) The national government: To implement any necessary measures in consideration of its social responsibilities associated with the promotional efforts thus far channeled into its nuclear energy policy. (2) Local governments: To carry out their proper role through cooperation with the measures by the national government. (3) The relevant nuclear power producer: To implement any necessary measures in good faith, while assisting the national and local governments. Basic principles formulation and others The Minister of the Environment develop a draft of the basic principles and seek a Cabinet decision. The Minister of the Environment set standards for the treatment of contaminated waste and soil The national government establish a system of unified monitoring and measurement (source: MOE document) 49

50 Annex 3: Legal framework of decontamination work Specified waste (1) Waste within the management area (2) Designated waste Contaminated waste management area designated by the Minister of the Survey on sewerage Environment sludge, incinerated ash, etc (obligatory) A treatment plan for waste within the management area is formulated by the Minister of the Environment Report to the Minister of the Environment Survey on waste other than that specified in the left box (voluntary basis) Application Designation as designated waste by the Minister of the Environment * Contaminated Waste above certain level Treatment by the national government pursuant to the treatment plan for waste Treatment by the national government Prohibition on unauthorized dumping and other actions Low-level contaminated waste other than specified waste To be treated in accordance with the Waste Management Act (source: MOE document) 50

51 Annex 3: Legal framework of decontamination work (1) Specific area for decontamination (2) Intensive contamination survey area Specific area for decontamination designated by the Minister of the Environment(MOE) A decontamination plan for a specific area is formulated by MOE Intensive contamination survey area designated by MOE Investigation and measurement of the status of pollution conducted by a prefectural governor, etc. * (*) Including municipality chiefs as designated by a ordinance. A decontamination plan is formulated by a prefectural governor, etc. * Implementation of decontamination by the national government Implementation of decontamination by the national government, prefectural governors, municipality chiefs, etc., in accordance with the decontamination plan 51 51

52 Annex 3: Legal framework of decontamination work Facilitation of the disposal of specified waste or removed soil (contaminated waste, etc.) The national government shall take any necessary steps aided by the relevant local government to properly promote measures to dispose of and decontaminate waste contaminated with radioactive materials, including the establishment of any facilities required for the treatment of contaminated waste, etc. Financial Resources The national government shall take fiscal action to finance the costs required for the promotion of measures to deal with any contamination by radioactive materials. Measures taken pursuant to this Act shall be considered to be related to damage under the Act on Compensation for Nuclear Damage, and are thus to be implemented at the expense of the relevant nuclear power producer. Taking its social responsibility into account, the national government shall implement any necessary measures to ensure that the relevant nuclear power producer makes payments smoothly to cover the cost of measures taken by any local government and others under this Act. Date of enforcement Fully come into force from January 1,