5 October 2006 JAPAN

Transcription

1 5 October 2006 JAPAN 1. NATIONAL FRAMEWORK FOR MANAGEMENT AND REGULATION OF RADIOACTIVE WASTE AND DECOMMISSIONIING 1.1 National Framework Overview of National Policy In Japan, the disposal of lowlevel radioactive waste originating from nuclear reactor operation has been implemented since For highlevel radioactive waste, the Specified Radioactive Waste Final Disposal Act, which was enacted by the National Diet on 31 May, 2000, defines the procedures of site selection, executive body and fund accumulation in relation to the disposal of vitrified waste originating from the reprocessing of spent fuel. As regards the disposal of the other types of radioactive waste such as transuranic (TRU) waste (originating from reprocessing facilities and MOX fuel fabrication facilities), uranium waste (originating from uranium fabrication facilities), and so on, basic principles of safety regulation are not yet established. The responsibility for the treatment and the disposal of radioactive waste originating from the operations basically lies with the operators themselves Overview of Relevant Institutions Japan Nuclear Fuel Ltd. (JNFL) disposes of lowlevel radioactive waste and stores highlevel radioactive waste. The Nuclear Waste Management Organization of Japan (NUMO) was established and chartered under the Specified Radioactive Waste Final Disposal Act on 1 October, 2000, as an executive body for disposal of highlevel radioactive waste. 1.2 National, technical regulatory organisations Regulatory function The key organizations for nuclear safety regulation are as following (see Figure 1): Nuclear Safety Commission (NSC) in Cabinet Office (CAO) Deciding the basic principles related to nuclear safety regulation Establishment of safety standards Review of results of the safety examination by regulatory bodies (socalled double check ) Ministry of Economy, Trade and Industry (METI) Regulation of the use of nuclear materials for energy utilization Ministry of Education, Culture, Sports, Science and Technology (MEXT) Regulation of scientific use of nuclear materials, use of radioisotopes, radiation generating apparatuses Ministry of Land, Infrastructure and Transport (MLIT) Regulation of maritime transportation of nuclear materials 1

2 Cabinet Office Cabinet Nuclear Safety Commission (Advisory Committee to Prime Minister) Ministry of Economy, Trade and Industry Ministry of Education, Culture, Sports, Science and Technology Ministry of Land, Infrastructure and Transport Figure 1 Governmental Organizations Related to Nuclear Safety Regulation Organisation and resources The main organisations and resources for radioactive waste regulation are as following (see Fig.2): Subsequent Regulation Review Division, Secretariat of Nuclear Safety Commission (NSC) Investigation and examination concerning basic principles of regulation of radioactive waste management Establishment of safety standards of radioactive waste management Review of the safety examinations of radioactive waste management facilities by regulatory bodies Radioactive Waste Regulation Division, Nuclear and Industrial Safety Agency (NISA), METI Drafting of regulatory laws and provisions Regulation of radioactive waste disposal facilities and storage facilities Regulation of offsite radioactive waste management Regulation of decommissioning of nuclear facilities Radioactive Waste Safety Subcommittee, Nuclear and Industrial Safety Subcommittee, Advisory Committee for Natural Resources and Energy, METI Investigation into safety policy concerning radioactive waste disposal and storage NISA plays a role as a secretariat of this subcommittee Nuclear Safety Division, Science and Technology Policy Bureau, MEXT Regulation of management of radioactive waste originating from scientific use of nuclear materials and use of radioisotopes and radiationgenerating apparatuses Technology and Safety Division, Policy Bureau, MLIT Regulation of the maritime transportation of radioactive waste Japan Nuclear Energy Safety Organization (JNES), Japan Atomic Energy Agency (JAEA) and 2

3 National Institute of Advanced Industrial Science and Technology (AIST) Implementing the safety research activities or evaluations necessary for NISA Nuclear Safety Commission (5 commissioners) Special Committee on Radioactive Waste Disposal Safety and Decommissioning Safety Special Advisory Board on HighLevel Radioactive Waste Disposal Safety Secretariat (ca.100) Subsequent Regulation Review Division Ministry of Economy, Trade and Industry Advisory Committee for Natural Resources and Energy (Advisory Committee to Minister of Economy, Trade and Industry) Nuclear and Industrial Safety Subcommittee Radioactive Waste Safety Subcommittee Nuclear and Industrial Safety Agency (ca. 440) Radioactive Waste Regulation Division Ministry of Education, Culture, Sports, Science and Technology Science and Technology Policy Bureau Nuclear Safety Division (ca. 100) Ministry of Land, Infrastructure and Transport Policy Bureau Japan Nuclear Energy Safety Organization* (JNES) (ca. 440) Radioactive Waste Evaluation Office National Institute of Advanced Science and Technology* (AIST) (ca. 3200) Research Center for Deep Geological Environment Japan Atomic Energy Agency* (JAEA) (ca.4300) Nuclear Safety Research Center *Incorporated Administrative Agency Technology and Safety Division Figure 2 Governmental Organizations Related to Radioactive Waste Regulation (Number is persons of the organization in total) 3

4 2. REGULATORY ARRANGEMENT 2.1 Primary Legislation and General Regulation The Framework for the regulation on nuclear activities is as follows: The Atomic Energy Basic Law (The Basic Law): Basic Policy (peaceful uses, safety assurance, democratic management, autonomous activities, publication of results) The Law for the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors (Reactor Regulation Law): Ensures the peaceful and safe uses of nuclear source materials, nuclear fuels and nuclear reactors The Law Concerning Prevention from Radiation Hazards due to Radioisotopes, etc. (Radiation Hazards Prevention Law): Regulation of radioisotopes and radiationgenerating apparatuses 2.2 Regulations concerning specific activities or facilities Activities or site specific regulations do not exist in Japan. 2.3 Guidance on implementation Rules and standards are established for each nuclear facility under the Reactor Regulation Law. When conducting safety examination of a nuclear facility, safety regulatory guides established by the NSC are used. In addition, appropriate academic society and association Standards are used if necessary Radioactive waste management Fundamental guidelines of licensing review of land disposal facility of lowlevel radioactive waste Basic philosophy to assess safety of waste management facilities Guideline and Rule of the Atomic Energy Society of Japan: Measurement method of Sorption Distribution Coefficient Basic Procedure of Batch Method for Barrier Material of Near Surface Disposal Decommissioning Safety Regulatory Guide of NSC: Basic philosophy to assure safety for dismantling nuclear reactor facilities Guideline and Rule of the Atomic Energy Society of Japan: Planning and Practice of the Nuclear Facilities Decommissioning 3. STATUS, STRATEGIES AND CURRENT ISSUES AT THE NATIONAL LEVEL CURRENT STATUS 3.1 Status Waste Classification and quantities The amounts of stored radioactive wastes are as follows: 4

5 Category of Wastes Cumulative Amount of Wastes as of March 2006 HighLevel Radioactive Waste (vitrified waste) 1,398 canisters (vitrified waste) Waste generated by nuclear reactors LowLevel Radioactive Waste Containing Comparatively High Radioactivity (core internal structures, etc.) 411 m 3 control rods: 8,373 channel boxes, etc. : 59,433 etc.: 19,935 m 3 LowLevel Radioactive Waste 590,235 drums (200L) at nuclear power plant 184,059 drums (200L) were disposed at Rokkasho Disposal Facility VeryLowLevel Radioactive Waste 1,670 t was disposed at JAERI s Tokai site TRU Waste 90,958 drums (200L) 3,659 m 3 Waste originating from uranium fabrication facilities 41,794 drums (200L) Waste originating from medical, industrial and research 391,538drums (200L) * facilities * This number includes only solid waste at the end of March Installations in a decommissioning phase The list of nuclear facilities in the process of being decommissioned and planned to be decommissioned with respect to power reactors is as follows; Name of facility Japan Atomic Power Co., Tokai Power Plant Japan Atomic Energy Agency, the advanced thermal reactor Fugen Nuclear Power Plant Location Electrical Reactor Commercial output type operation ( MW) Ibaraki GCR 166 Jul 1966 pref. Mar 1998 Fukui pref. (As of the end of March 2005) ATR Mar 2003 Status of decommissioning Decommissioning started in 2001 Termination of operation in March Continue taking out of spent fuels and preparation for decommissioning. The list of nuclear facilities in the process of being decommissioned and planned to be decommissioned with respect to research reactors is as follows; 5

6 Name of facility Location Reactor type Japan Atomic Energy Agency Tokai Research and Development Center JRR2 Japan Atomic Energy Agency Tokai Research and Development Center VHTRC Japan Atomic Energy Agency Mutsu Establishment The Reactor Facilities of The First Nuclear Ship (Mutsu) Ibarakipref. Ibarakipref. Aomoripref. Heavywater moderated cooling tank reactor Graphitemoder ated reactor Pressurized lightwater moderated and cooled reactor, PWR Therma l output (kw) Service period 10,000 Oct 1960 Dec Jan 1961 Jun ,000 Aug 1974 Jan 1992 Status of decommissioning The following activities for decommissioning have been completed. Shipment of spent fuel and heavy water, isolation of reactor cooling system and reactor body, removal of secondary cooling system and experimental equipment. Dismantling and removal of the reactor body have been completed. Dismantling has been completed. Accessory land facilities are currently being maintained for the purpose of storing solid waste and processing liquid waste. Japan Atomic Energy Agency Oarai Research and Development Center Deuterium Critical Assembly (DCA) Hitachi, Ltd. Power Systems Nuclear System Division Ozenji Center Ibarakipref. Kanagawapref. Heavywater moderated reactor Lightwater moderated and cooled reactor 1 Dec 1969 Sep Dec 1961 Feb 1975 Deactivation has been completed. Carry out heavywater and remove cooling system Dismantling has been completed. Currently being proceeding is the storage and maintenance of radioactive waste. Toshiba Corporation Research Reactor Center Toshiba Training Reactor1 (TTR1) Kanagawapref. Lightwater moderated inhomogeneous reactor 100 Mar 1962 Mar 2001 Permanent suspension of operational functions and removal of reactor cooling system facilities. Carry out spent fuel. 6

7 Name of facility Location Reactor type Musashi Institute of Technology Kanagawapref. Lightwater cooled reactor Therma l output (kw) Service period 100 Jan 1963 Mar 1985 Status of decommissioning Under dismantling Rikkyo University Institute for Atomic Energy Kanagawapref. (As of the end of March 2005) Zirconium hydride moderated lightwater cooled reactor 100 Dec 1961 Dec 2001 Extendedshutdown, carry out spent fuel. 3.2 National strategies Waste Management The AEC, in its LongTerm Program and other documents, states that the present generations, which receive the benefits of nuclear energy, are obliged to do their utmost to ensure the safe disposal of radioactive waste generated in the research, development and utilization of nuclear energy, and should invest continued efforts in achieving this goal, that the waste producers has the primary responsibility for safe processing and disposal of the waste, and that the government has the responsibility for taking necessary measures to ensure that this processing and disposal are carried out appropriately and safely by the producers, through giving adequate guidance and establishing necessary regulations. Furthermore, the AEC states that the government should play an appropriate role in implementing disposal program for radioactive waste, particularly HLW, ensuring longterm safety, in addition to its activities related to promotion of research and development activities and safety regulation Decommissioning The AEC states that nuclear facilities should be decommissioned safely by the responsibility of license holder with understanding and support of the local community, and also states that generation of radioactive waste should be minimized. The AEC encourages research and development efforts aimed at recycling and/or reusing waste and the land, after decommissioning of commercial power reactors, is expected to serve as sites for new nuclear power plants again with the understanding of their communities. 3.3 Issues at national level Waste Management METI and MEXT have established and continued to improve the legal framework consisting of the Reactor Regulation Law and the Radiation Hazards Prevention Law, for safe and proper processing, storage and disposal of radioactive waste, on the bases of studies and decisions made by the AEC and the NSC. Among these regulations, the criteria for gaseous and liquid radioactive waste discharge have been established in accordance with relevant international recommendations. Solid radioactive waste is classified into two categories, namely HLW (liquid waste generated from spent fuel reprocessing and its vitrified package) and other LLW. The LLW is subclassified according to origin (differing radionuclide composition) and level of radioactivity. The Reactor 7

8 Regulation Law was amended in May 2005 to provide for clearance level and the procedure for its verification, while the relevant regulations are going to be established in the future. The AEC makes decision on the basic policy for radioactive waste disposal. Based on the policy, the NSC decides on the basic concept for the safety regulations for land disposal, upper bounds of radioactivity concentration for disposal of radioactive materials and methods for safety assessment of disposal facilities. METI and MEXT establish relevant regulations. A summary of the basic concepts for radioactive waste disposal is as follows. There are two basic concepts for land disposal, i.e. geological disposal and near surface and intermediate depth disposal with institutional control. The near surface and intermediate depth disposal consists of near surface disposal with artificial barrier (concrete vault), near surface disposal without artificial barrier (trench) and intermediate depth disposal (disposal at a depth sufficient to safety margin for conventional underground building). HLW is disposed of solely by geological disposal, and LLW can be disposed of either by geological disposal or near surface and intermediate depth disposal with institutional control, depending on the property of the waste. Vitrified HLW is emplaced in a stable geological formation at a depth of more than 300 meters, following 30 to 50 years of interim storage to allow cooling. Among LLWs from power reactors, relatively higher radioactive wastes are disposed of in intermediate depth disposal facilities, relatively lower radioactive waste are disposed of in near surface disposal facilities with artificial barriers, and very low level waste are disposed of in near surface disposal facilities without artificial barriers. Radioactive wastes containing transuranic nuclides from reprocessing process, uranium waste from enrichment and/or fuel manufacturing, and radioactive waste from medical, industrial and research facilities are disposed of either by geological disposal or near surface and intermediate depth disposal with institutional control, depending on types of radionuclides and levels of radioactivity. In the future, discussions will continue on measures that can be taken to provide different disposal methods in a single disposal facility, or to dispose of wastes of different origin in a single disposal facility. Concerning the regulations for disposal of LLW from power reactors, the upper bounds of radioactivity concentration, to be applied for license for radioactive waste disposal, have already been established on the basis of the Reactor Regulation Law. The radioactive waste returned from overseas reprocessing is to be disposed of together with waste from domestic reprocessing. The Specified Radioactive Waste Final Disposal Act, enacted in the year 2000, provides for the establishment of an implementing organization for disposal of HLW, the financial resources reserved for disposal, and procedure for selecting a disposal site, etc. The nuclear industry established Nuclear Waste Management Organization of Japan (NUMO), the implementing organization for HLW disposal approved by the government on the basis of the law. In compliance with the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (1972) and its amendment to Annex I in 1993, the AEC decided on November 2, 1993 to eliminate the option of sea dumping of radioactive waste. Based on this decision the Reactor Regulation Law was amended in May, Decommissioning The regulatory policy for dismantling or decommissioning of reactor facilities has been investigated and discussed, resulting as following three reports; (1) "Basic Philosophy to Assure Safety for the Dismantling Nuclear Reactor Facilities" (December 1985, Decision by the NSC, revised in August 2001), (2) "Aiming at Decommissioning of Commercial Nuclear Power Facilities" (January 1997, Nuclear Energy Subcommittee, Advisory Committee for Natural Resources and Energy), (3) "Philosophy for Safety Assurance and Safety Regulation on the Decommissioning of Commercial Power Reactor Facilities" (August 2001, Decommissioning Safety 8

9 Subcommittee in METI (NISA)). Based on these reports, in order to ensure the safety during the decommissioning of commercial nuclear power reactors, the regulation was implemented by applying existing provisions in the Reactor Regulation Law, such as notification of dismantling or modification of Operational Safety Program, by the operators. So far, the decommissioning of reactor facilities was implemented at the Power Demonstration Reactor of the Japan Atomic Energy Research Institute (JPDR) and the Tokai Power Station of Japan Atomic Power Co. Inc., etc. and the development and application of dismantling technologies have been progressed, and the knowhows for decommissioning have been accumulated through these processes. Under such a circumstance, in October 14, 2004, the NSC pointed out, that it is required to investigate the development of a graded approach in safety regulation system to cope with the progress of dismantling processes, as the main activities during the period after the cease of operation are safety management of spent fuels, dismantling works and the radiation control, and handling of radioactive wastes, and the regulatory experiences concerning dismantling and decommissioning of test and research reactors have been accumulated, as the conclusion of the regulatory activities investigation concerning the safety regulation system during the period after the cease of operation of reactor facilities. 4. CURRENT ISSUES AND PRIORITIES FOR THE REGULATOR 4.1 Waste Management Issues and Priorities The most pressing current issue is the establishment of national safety standards, laws and provisions for disposal of radioactive waste as shown below: Highlevel radioactive waste Radioactive Waste Safety Subcommittee in METI (NISA) concluded the report on regulatory framework for geological disposal in September NSC is in the process of discussing the guideline of regulation for geological disposal. TRU waste, uranium waste NSC is in the process of discussing the upper limit of the radioactivity concentration for the intermediate depth disposal as well as the clearance level for uranium waste. Lowlevel waste containing comparatively high radioactiveconcentration waste (e.g., reactor core internal structures, etc.) NSC is in the process of discussing the standard for safety evaluation for LLW including the waste containing comparatively high radioactiveconcentration waste. 9

10 4.1.2 Developments in policy and regulation Waste Categories Highlevel radioactive waste (vitrified waste) Waste originating from nuclear reactors Lowlevel waste containing comparatively high radioactivity (core internal structures, etc.) Lowlevel waste (disposed in concrete pits) Very lowlevel waste (disposed in trenches) TRU waste Waste generated by uranium fabrication facilities Waste generated by medical and research facilities Clearance levels Atomic Energy Commission Disposal Scheme (May 98) (Oct 98) (Aug 84) (Mar 00 Apr 06) (Dec 00) (May 98) (Aug 84 Dec 00) Basic concept of safety regulation*1 (Nov 00) *2 (Sep 00) (Oct 85) Nuclear Safety Commission Restrictions at repositories, etc. (Sep 00) (Feb 87 Jun 92) (Jun 92 Sep 00) Method of safety examination To be studied To be studied (Mar 88 Jan 93) Almost (Jan 93)*4 Situation of establishment of regulatory laws and provisions To be studied To be established Almost established (Dec 00) Almost established (Mar 87Sep 92)*3 Almost established (Sep 92Dec 00)*5 Under study To be studied To be established Under study To be studied To be established (Jan 04 Apr 06) (Mar 99Dec 04) *6 To be studied To be established Almost established (Dec 05)*7 *1 A document on Important common matters for the safety regulation of radioactive waste disposal was issued on 10 June, *2 The basic concept of safety regulation of highlevel radioactive waste disposal (the first report) was issued. *3 A technical standard is necessary for the largesize metal waste. *4 Further study for metal waste is planned. *5 A technical standard is necessary for the metal waste. *6 Clearance Levels for Main Nuclear Reactors, Clearance Levels for HeavyWater Reactors and Fast Neutron Reactors, and Clearance Levels for Fuel Material Use Facilities (Facilities where Irradiated Fuel and 10

11 Materials are handled) were modified on 16 December, *7 The Bill to amend the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors was enacted in December 2005 to introduce clearance system for reactors and utilization facilities. 4.2 Decommissioning Issues and priorities The Decommissioning Safety Subcommittee in METI (NISA) has investigated appropriate regulatory system of decommissioning, based on the regulatory experiences on decommissioning of reactor facilities under the current system, aiming for amendment of legislations, with the principle of ensuring safety. The investigation is conducted from view points of ensuring transparency of regulations, and graded regulatory approach to cope with the progress of the decommissioning process, the diversity of each facilities, reflecting the experiences of decommissioning, and development of technology in the near future, and reported in "The Way of the Decommissioning Regulation of the Nuclear Facilities" (December 9, 2004)). In this investigation, the Subcommittee recognized that the decommissioning of nuclear reactors is becoming to a routine, and the amendment of legislation must cope with graded approach by regulatory body and clarification of the responsibilities of operators with the principle of ensuring safety, and it is considered to be important (i) to clarify the requirement in decommissioning regulations, (ii) to keep the transparency on procedures for the operators, and (iii) to obtain in the understanding and confidence of the national people and local residents on decommissioning regulations. The Subcommittee proposed the way of decommissioning regulations, as; (1) replacing dismantling notification by operator, to the approval of the operator s decommissioning plan of dismantling processes, methods etc. by regulatory body, (2) implementation of the decommissioning as approved in the plan, (3) completion of decommissioning is confirmed by regulatory body (4) After the confirmation of the completion of decommissioning, operator can dismiss the operation license (5) the regulatory activities during the decommissioning process ( example: Periodical Inspections, Nuclear Safety Inspections etc.) should be changed in accordance with the changes of the functions of the facilities and safety operation activities as the decommissioning is proceeded ( graded regulatory approach) Developments in policy and regulation In the proposal, it is stated that (1) The operator apply the decommissioning plan including process of decommissioning, methods of dismantling, method of managing the radioactive waste generated during the dismantling, the safety analysis, financial plan. (2) Regulatory body review the plan on the conformity with technical criteria and approve it. (3) The operator conduct the decommissioning in accordance with the decommissioning plan, usually the decommissioning takes a long time and consists of several steps, it is allowed to modify the program at the beginning of each step with the prospect that the completion of decommissioning is ensured, following the approval for the modification of decommissioning plan. The amendment of the Reactor Regulation Law was enacted in May 2005, along with the proposal, and the associated detailed provisions were also established and enacted in December 11

12 RESEARCH AND DEVELOPMENT PROGRAMME BY THE REGULATOR FOR BOTH WASTE MANAGEMENT AND DECOMMISSIONING 5.1 Functions JNES implements safety analysis and evaluation of designs of nuclear facilities and reactor facilities including radioactive waste management and disposal and decommissioning for NISA. JAEA is also in charge of research activities for the generic atomic energy field including radioactive waste management and disposal. 5.2 Contents of R&D plans The regulatory body establishes regulations on HLW disposal, while NUMO is responsible for implementing HLW disposal business economically and efficiently. Japan Atomic Energy Agency and other national institutes conduct various programs to develop safety assessment methodology, to promote fundamental research on deep geological formation, etc. and to enhance reliability of geological disposal technology. The NSC issued a report "Environmental Requirements to be Considered at the Selection of the Preliminary Investigation Areas for HighLevel Radioactive Wastes Disposal" in September The environmental requirements shown in the report are reflected in the report of NUMO "Considerations for Selection of the Preliminary Investigation Areas". Furthermore, the Committee made a report "Nuclear Research Programs Important to Safety" in July 2004, The report indicates, as safety researches on radioactive wastes and decommissioning field to be conducted intensively in five years starting 2005, two researches to promote the study about environmental requirements or basic guidelines for selection of the detailed investigation area, etc. of the construction site for the disposal facility of highlevel radioactive wastes and the study for developing the fundamental concept for safe operation of processing and disposal of high beta and gamma wastes, TRU wastes, uranium waste etc. The Radioactive Waste Safety Subcommittee in METI (NISA) issued, in July 2003, a report titled Toward Establishing Framework of Safety Regulation of HLW, which shows future objects of research and discusses research support organization to the regulatory body. Partitioning and transmutation is a technology to separate radioactive materials with long halflives in HLW from the rest of the waste and convert them into short halflives or stable materials. This technology, even though it is still in early stage of development, should be further pursued because it may contribute to reduction of waste processing and disposal cost and to effective use of available resources. 6. FINANCING OF RADIOACTIVE WASTE MANAGEMENT AND DECOMMISSIONING In issuing establishment licence of a nuclear facility, except for nuclear fuel material use facility, the regulatory body, in accordance with the Reactor Regulation Law, confirms that the applicant for the license possesses necessary financial basis, then consults with the Atomic Energy Commission. The Reactor Regulation Law stipulates that applicant should submit financial documents attached to the application format. For example, an applicant for waste repository should attach such documents as the "Scheduled Date of the Commencement of Operation of Facility and Activities", the "Annual Plan for Acceptance and Disposal of Radioactive Wastes", the "Financial Plan and Estimated Annual Financial Balance" and the "Other Financial Matters" to the application format. 12

13 Electric utilities have deposited two internal reserves for reprocessing of spent fuel and for decommissioning, on the basis of the Ministerial Order established under the Electricity Utilities Industry Law. The reserve of spent fuel reprocessing will pay for reprocessing expense subtracting the value of recovered uranium and plutonium. The amount of reserve by the end of March 2005 is about 3,100 billion yen by 10 electric utilities. As the Law on the Management of the Fund Reserved for Spent Fuel Reprocessing was enacted in May 2005, the internal reserve of electric utilities is to be transferred to an organization designated by the Minister of METI. The reserves for decommissioning of nuclear power generation facilities will pay for the expense of dismantling and removal of commercial power reactor facilities, and the processing and disposal of the waste. The amount of reserve by the end of March 2005 is about 1,100 billion yen by 10 electric utilities. In accordance with the Specified Radioactive Waste Final Disposal Act enacted in May 2000, operators of power reactor facilities deposit funds for disposal of high level radioactive waste to the Nuclear Waste Management Organization of Japan, the implementing body for disposal, who entrusts management of the fund to the Radioactive Waste Management Funding and Research Center. The Minister of METI, every year, notifies utilities of the amount of money to be deposited to the fund. The amount of deposit per vitrified package was 33,964,000 yen in the year of The amount of money for construction of depository in mid2030s and disposal of about 40,000 vitrified packages of high level waste is estimated about 3 trillion yen. Financial basis of a license holder of fuel material use is to be confirmed through procedures to approve the Operational Safety Program and the steps to be taken at the time of decommissioning. Financial basis of the operator of radioisotope waste management facility licensed under the Radiation Hazards Prevention Law is to be confirmed through the Periodical Inspection, obligation to maintain the facility in compliance with technical standards, implementation of education and training programs, notification of the Internal Rules for Prevention of Radiation Hazards and the steps to be taken at the time of decommissioning. 13

14 ACRONYMS AND ABBREVIATIONS AEC Atomic Energy Commission AIST National Institute of Advanced Industrial Science and Technology ATR Advanced Thermal Reactor DCA Deuterium Critical Assembly GCR Gas Cooled Reactor HLW HighLevel Waste JAEA Japan Atomic Energy Agency JNES Japan Nuclear Energy Safety Organization JNFL Japan Nuclear Fuel Ltd. JPDR Japan Power Demonstration Reactor JRR1,2 Japan Research Reactor 1, 2 LLW LowLevel Waste METI Ministry of Economy, Trade and Industry MEXT Ministry of Education Culture, Sports, Science and Technology MLIT Ministry of Land, Infrastructure and Transport NUMO Nuclear Waste Management Organization of Japan NSC Nuclear Safety Commission TRU Transuranic TTR1 Toshiba Test Reactor 1 VHTRC Very High Temperature Reactor Critical Assembly 14