DECOMMISSIONING OF THE NUCLEAR RESEARCH REACTOR VVR-S MAGURELEBUCHAREST ROMANIA M. DRAGUSIN, R. DEJU, V. POPA AND I. IORGA, presented by email
Summary • Introduction • General Data from decommissioning plan for VVR-S Research Reactor • Work Breakdown Structure (WBS) of Decommissioning Project • Work Packages (WP) • Good Practices Examples in pre-decommissioning activities • Description of Actual Work • Results/Lessons Learned • Acknowledgements • References 9/1/2011
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Introduction • The VVR-S Nuclear Research Reactor from “Horia Hulubei” National Institute of Physics and Nuclear Engineering- Magurele Bucharest will be decommissioned. • The strategy selected is immediate dismantling. • 2010 is the first year of the project. • Duration of the decommissioning project will be 11 years. • Three phases of decommissioning will be for finalization entire project.
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Introduction • In the first 4 years planning to repatriated in Russian Federation all low enriched uranium type EK-10 nuclear fuel irradiated assemblies, while in the framework of US Department of Energy-National Nuclear Security Administration Program Russian Research Reactor Fuel Return –RRRFR, all highly enriched uranium spent fuel assemblies type C-36 were repatriated from Magurele site in Russian Federation in June 2009.
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Introduction • Also, in the first three years of the project the Radioactive Waste Treatment Plant from the same site with the VVR-S research reactor will be up-graded for material management resulted from decommissioning activities. For execution the Dismantling & Decontamination activities selected, as best option, fully participation the members team of the operators and engineers from research reactor.
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Introduction • End state of the decommissioning project will be reutilization of the buildings for sitting a new electron linear accelerator with maximum 10 MeV energy used in material sciences studies and applications. • Commercial equipment obtained during deployment the IAEA Technical Cooperation Project (2004-2008), technical cooperation project with US Argonne National Laboratory (2003-2007), EU PHARE project (2008-2009), US RRRFR program (2004-2009) and national projects will be used in decommissioning project. Good practices in planning, organization; funding and logistics will be presented. 9/1/2011
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General Data from decommissioning plan for VVR-S Research Reactor • Reactor Hall May 2009, before the loading operations of the highly enriched spent nuclear fuel assemblies (C-36) in order to be repatriated in Russian Federation.
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General Data from decommissioning plan for VVR-S Research Reactor • By Governmental Decision on April 2002, VVR-S reactor was permanently shutdown for decommissioning. • The Immediate Dismantling Strategy was selected for decommissioning the VVR-S Reactor. -The implementation of the strategy is based on the Decommissioning Plan and the Project Management. • The spent nuclear fuel assemblies resulted from operation period was removed from the reactor building before starting the decommissioning process. 9/1/2011
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General Data from decommissioning plan for VVR-S Research Reactor • The C-36 highly uranium enriched spent fuel assemblies were sent back to Russian Federation according to the agreement between DOE – USA & Russian Federation and Romanian Government and Russian Federation Government. • In respect of EK-10 low uranium enriched spent fuel assemblies will be sent to Russian Federation (like C-36) with Romanian funding. The concept (design) of isolating the DCNU building away from the Reactor Building was applied in view of implementing the decommissioning project upon safety & efficiency conditions. The fresh fuel was sent to Russian Federation.
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General Data from decommissioning plan for VVR-S Research Reactor • Decommissioning technologies for decontamination (in wet condition for primary circuit and dry conditions in the rest of materials) and dismantling process will be implemented with mechanical cutting commercial equipments for free release of the site.
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General Data from decommissioning plan for VVR-S Research Reactor • The VVR-S reactor is the first major nuclear facility in Romania which will be decommissioned. • The same site also includes some other nuclear facilities which are to be decommissioned in future, considering that the local community is in process of expanding.
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General Data from decommissioning plan for VVR-S Research Reactor • The radioactive waste streams will be safely managed taking into account the already existing Radioactive Waste Treatment Plant situated in the immediate vicinity of the VVR-S reactor and the National Repository for Radioactive Waste Baita–Bihor, which are to be refurbish as per a refurbishment program.
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General Data from decommissioning plan for VVR-S Research Reactor • The radioactive waste streams were estimated by direct and indirect measurements. Thus, at the end of the decommissioning project the radiation dose is estimated to be about 0.1 mSv/year (as individual dose limit), for the release of the VVR-S nuclear facility from regulatory body control. As regards the radiation protection program the radiation dose limit is 20 mSv/year for the personnel professionally exposed, 1 mSv/year for population and 10 micro Sv/year for the free release of the material resulted from decommissioning. The aluminium and graphite activated wastes will be stored in the existing storage facilities in Radioactive Waste Treatment Plant. 9/1/2011
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General Data from decommissioning plan for VVR-S Research Reactor • The duration of the decommissioning project is 11 years and the financing mechanisms are based on the public funds and represent an reinvestment process. IFIN-HH has all responsibilities related to finalization of decommissioning the research reactor, and almost work packages will be executed by IFINHH. Will be used also contractors for executed some activities where the institute don’t have technical capabilities. 9/1/2011
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General Data from decommissioning plan for VVR-S Research Reactor
• The key issues of decommissioning are the following:
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• implementation of Phare project for research reactor( 2008-2009) • comply requirements of Euratom Treaty art. 37; • obtain the funding for decommissioning project and starting the decommissioning project -2010; • approval of quality manual for decommissioning-2009 • repatriation of HEU spent nuclear fuelS-36 in 2009 within US DOE RRRFR Program; IFIN-HH DDR
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General Data from decommissioning plan for VVR-S Research Reactor • Phase 1: 3 years, start point 2010
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• application of isolation concept for DCNU, elaboration of decommissioning plan for DCNU, obtaining the license for DCNU and will continued funding from governmental allocations as national nuclear installations. • upgrading of Radioactive Waste Treatment Plant and National Repository for Radioactive Waste 2010-2012; • implementing the work packages from phase 1 for research reactor-2010-2012; • repatriation in Russian Federation of LEU spent nuclear fuel-EK-10- 2010-2013. IFIN-HH DDR
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General Data from decommissioning plan for VVR-S Research Reactor • Phase 2: 2 years, start point 2013
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• decontamination and dismantling of the primary circuit • decontamination of the hot cells • dismantling the secondary circuit • dismantling the internal components from core zone
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General Data from decommissioning plan for VVR-S Research Reactor • dismantling the internal components from reactor block • Phase 3: 6 years, • demolition reactor block, aerator, hot cells start • dismantling the active drainage up to 30 point m3 underground pond 2016 • final radiological survey • completion of the project
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Work Breakdown Structure (WBS) of Decommissioning Project • •
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Dismantling primary circuit up to reactor block (non activated parts) Dismantling core/absorber rods, drive assembly, core components, other internal components, thermal column, cooling pond Demolition of de aerator, hot cells, biological shield of reactor block Dismantling underground structure: secondary circuit, connected pipes between Reactor and effluents buffer (30 m3) tank IFIN-HH DDR
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Work Breakdown Structure (WBS) of Decommissioning Project •
• •
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Dismantling technological ventilation, active drainage, electrical for equipment used in decommissioning, air services Dismantling ancillary buildings (temporary structures for material storage) Final radiological survey for building and site
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Work Packages (WP) • WP.1. Predecom missio ning activiti es
1. 2. 3. 4. 5. 6. 7. 8.
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Spent Nuclear Fuel management – removal from site; Up-grading Radioactive Waste Treatment Plant and National Repository for Radioactive Waste; Commission the Radiological Characterization Laboratory & Free Release of materials for initial planning, packaging, storing, conditioning and un-conditioning release; Dose-meter system in site; Equipment for environmental protection and monitoring systems in/off site; Commission mechanical workshop for cutting and light decontamination in Reactor Hall Funding mechanism; Elaboration of documentation: organizational, QMS, H&S, Safety & Security & Safeguards, Technical, Packages and Transport Specifications, Radiation Protection;
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Work Packages (WP) • WP.1. Predecom missio ning activiti es
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9. Worker route in site; 10. Material route in/off site; 11. Removal from site of equipment and materials resulted from research activities and radio-isotopes production; 12. Drainage of water from primary & secondary circuit, cooling pond 13. Authorization from regulatory bodies: in nuclear, environmental, industrial; 14. Maintenances of SSC in transition period and during decommissioning; 15. Training of workers, public relation plan, definition of stakeholders.
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Work Packages (WP) 1. Remove control/absorber rods, drive • WP.2. assembly, I&C system; Disman 2. Remove primary heat exchangers and piping, tling pumps, water purification system; activitie 3. Remove core components and internal s
4. 5. 6. 7. 8. 9/1/2011
vessels from reactor block; Remove control room equipment; Remove secondary circuit, buffer tank, pipes from active drainage, including underground part, Remove cooling pond Remove active drainage Remove ventilation system, IFIN-HH DDR
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Work Packages (WP) 1. Decontamination of primary circuit (by • WP.3. washing with water and filtered in close Decontam circuit) ination activities 2. Decontamination of liner from hot cells
with dry methods 3. Decontamination of walls, floors 4. Decontamination of tools and equipment used in decommissioning 5. Other large pieces will be transported in Radioactive Waste Treatment Plant for decontamination in special room
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Work Packages (WP) • WP. 4. Demolition activities
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Demolition of biological shield from reactor block, hot cells, de aerator, stack
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Work Packages (WP) 1. The building purpose will be redirected • WP.5. to radiation processing facility for Radiological research, development and production characterizati of the water soluble polymers and on, recycling of other types of polymeric packaging, materials. Research and development in transportation the material science also will be deployed in the building released from , disposal, the regulatory control. storage, free release, final survey, archiving
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Good Practices Examples in predecommissioning activities • a) Paper and electronic archives arrangement • b) Setting up the decommissioning team • c) Organization and endowment of the radiological characterization laboratory • d) Making the decision in the selection process for equipments supplying/operating method • e) Dry, wet or semi wet decontamination? • f) Demolishing and dismantling equipments in phase 1 or in the next phases? 9/1/2011
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Good Practices Examples in predecommissioning activities • a) • • Paper and electronic archives arrangement
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Complying with the legal requirements, three different locations were set up for documents permanent disposal and keeping, in the reactor building which in the initial project was designed to house research laboratories. Two of these locations are provided with controlled humidity and temperature atmosphere, prevention and fire fighting means and with metallic cabinet outfitted with fire protection shelves which house the original project documents and their copies as well as current documents elaborated within the Quality Management System. In the third location is located the electronic archives with storage media and data security for the next 50 years. Another location is especially dedicated to original documents reconditioning, electronic scanning and printing of documents which are sent directly to the electronic archives.
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Good Practices Examples in predecommissioning activities • b) • • Setting up the decom mission ing team
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The first project for decommissioning a complex nuclear facility in Romania started in 2010. In 9 years was set up VVR-S nuclear reactor decommissioning team with specialists in different fields necessary for the implementation of the project. If in 2002 within the reactor there were 15 members, in 2010 there are 36 who benefited, within the different cooperation projects, from the appropriate training as a result being able to use in safety the equipment purchased with funds from international and national projects. In this manner is ensured the safe decommissioning of the reactor with own personnel and only a small part of the activities will be contracted with external contractors. IFIN-HH DDR
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Good Practices Examples in predecommissioning activities • c) Organization and endowment of the radiological characterization laboratory
NaI portable and GeHP portable spectrometers 9/1/2011
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Good Practices Examples in predecommissioning activities • c) Organization and endowment of the radiological characterization laboratory spectrometer GeHP for large radioactive waste packages
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Good Practices Examples in predecommissioning activities • c) Organization and endowment of the radiological characterization laboratory spectromete r with 12 plastic scintillators for free release 300 kg, materials and approx. 1 m3
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Good Practices Examples in predecommissioning activities • d) Making the decision in the selection process for equipments supplying/operating method Cutting with electrical equipment or hydraulic supplying
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Good Practices Examples in predecommissioning activities • d) Making the decision in the selection process for equipments supplying/operating method Radio remote control on demolition equipment
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Good Practices Examples in predecommissioning activities • d) Making the decision in the selection process for equipments supplying/operating method Sampling concrete from Reactor Block
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Good Practices Examples in predecommissioning activities • d) Making the decision in the selection process for equipments supplying/operating method Compressed air supply scarifying equipment for decontamination floor, wall Equipment for dismantling and demolition
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Good Practices Examples in predecommissioning activities • e) Dry, wet or semi wet decontamination? Dry and semi wet or dry decontami nation machine
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Good Practices Examples in predecommissioning activities • f) Demolishing and dismantling equipments in phase 1 or in the next phases? Area gamma monitori ng
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Beta airbone monitoring
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Good Practices Examples in predecommissioning activities • f) Demolishing and dismantling equipments in phase 1 or in the next phases? , , Airborne monitor
Whole body monitor
Instrumentation for monitoring and surveillance 9/1/2011
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Description of Actual Work • Benefiting from the acquired experience and lessons learned from the highly enriched irradiated nuclear fuel repatriation project to the Russian Federation [1], the decommissioning team started the preliminary activities for the repatriation of the low enriched irradiated nuclear fuel to the Russian Federation. The reactor’s team has a good experience which was proved in practice by the charging of the TUK-19 Russian transport container using for safety measures the transfer container. From TUK-19 transport containers reception to the airplane loading, the reactor’s team is prepared to work also in other repatriation projects within RRRFR Program. In phase 1 spent nuclear fuel will be released from the site [2], in phases 2 and 3 D&D (Dismantling & Decontamination) will be performed for the reactor’s SSEC (Structures, Systems, Equipments and Components). 9/1/2011
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Description of Actual Work • Because this is the first decommissioning project for a complex nuclear facility in Romania, the decommissioning team will specialize in building a decommissioning Excellency Centre in the area. For a good and efficient project management were elaborated WBS and Work Packages for the development of technical specifications sets, procedures, instructions, training programs on equipments adequate to the decommissioning activities. As a good practice during the approval period of the decommissioning documentations by the Romanian Regulatory Body, within IAEA technical cooperation project, with the participation of 6 international experts Peer Review of Decommissioning Plan of VVR-S Research Reactor was organized for a week. 9/1/2011
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Description of Actual Work • After the implementation of the observations made by the international expert’s team, the decommissioning plan was approved by the Romanian Regulatory Body. An intensive training and professional specialization program is developed at the beginning of the project (2010), and within the material management the waste routes are organized in a manner that makes their intersection impossible. Within the approved Quality Management System the information and documents circulation is controlled, maintaining temporary and permanent recordings. At the same time with the preparation and the repatriation of low enriched irradiated nuclear fuel assemblies, in order to ensure the management of radioactive wastes resulted from decommissioning the radioactive Waste Treatment Plant located on the same site with VVR-S reactor is being updated. [3] 9/1/2011
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Results/Lessons Learned • In this paper were presented examples of good practice identified in different stages of the decommissioning project, examples which became lessons learned for other decommissioning projects. Two essential aspects of decommissioning project preparation were pointed out: the release of the entire quantity of irradiated and fresh nuclear fuel from the site and the up-grading of the Radioactive Waste Treatment Plant. 9/1/2011
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Acknowledgements • To National Centre of Program Management for financial support in elaboration of this paper under Contract No 71-113/2007-2010 and Nucleus Program No PN 09 37 03 02/2009.
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References •
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I. BOLSHINSKY, K. J. ALLEN, N.V. ZAMFIR, M.DRAGUSIN, ET ALL, Research Reactor Preparations for the Air Shipment of Highly Enriched Uranium from Romania, PIME 2010, RRFM-2010, Morocco, Marrakech, M.DRAGUSIN, Lessons Learned from 50 Years Period the Storage of the Spent Fuel from Nuclear Research Reactor VVR-S, PIME 2010, RRFM-2010, Morocco, Marrakech, M.DRAGUSIN, V.COPACIU, V.POPA, ET ALL, Decommissioning Plan of VVR-S Research Reactor. (2010), Bucharest IFIN-HH DDR
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Thank you info email
[email protected] [email protected]
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