Decommissioning Report. Vandellos I Nuclear Power Plant

Transcription

1 Decommissioning Report Vandellos I Nuclear Power Plant

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3 Co n t e n t s Chairman s address 3 Introduction 7 Chapter 1. Background 11 Chapter 2. A commitment to safety 15 Chapter 3. The decommiossioning process 25 Chapter 4. Support activities 51 Chapter 5. Projection of decommissioning 55 Chapter 6. Mestral Technology Centre 65 Summary 69 Acronyms 73 Decommissioning Report Vandellos I Nuclear Power Plant

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5 Chairman s address

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7 CHAIRMAN S ADDRESS. The decommissioning of the Vandellós I nuclear power plant is above all else a test of the maturity of the Spanish industry and of its capacity to solve the new issues and challenges that certain of its processes and technologies might pose. The demands placed by the need for sustainable development have led to the implementation of sophisticated environmental optimisation programmes. Our industry is committed, with increasing efficiency, to make its legitimate aim of being competitive compatible with the minimisation of its releases, the management of its wastes or the restoration of the land once its production activities have ceased. This is precisely the reason underlying the creation of the Empresa Nacional de Residuos Radiactivos, S.A. (ENRESA), which since it was set up in 1984 has been charged with the management of all the radioactive wastes generated in Spain, regardless of whether they come from the nuclear industry, research laboratories, healthcare centres or other industrial activities. Likewise, ENRESA is the public company responsible for the decommissioning of nuclear power plants in Spain. In this respect, when the Ministry of Industry and Energy commissioned ENRESA to prepare a decommissioning project for the Vandellós I nuclear power plant, the company accepted the challenge of successfully undertaking an activity for which there were very few references internationally. Now, several years later, following major efforts in engineering and a period of work in which radiological and conventional safety has been the unwavering governing principle, the Vandellós I nuclear power plant has been dismantled to Level 2. This has meant the release of most of the site and its return to the original owner company, along with the initiation of a period of latency for the reactor shroud pending the decay of the radioactivity in its internal structures, thus simplifying complete decommissioning. The know-how generated in the decommissioning of the Vandellós I nuclear power plant has placed ENRESA in a position of relevance at international level, and has attracted the attention of leading companies such as the French EDF, BNFL from Great Britain and JNC from Japan, which have JOSÉ ALEJANDRO PINA. PRESIDENT expressed their interest in collaborating with ENRESA in future projects. Likewise, the experience acquired by the Spanish companies that have collaborated in this decommissioning is already providing them with service contracts abroad. Furthermore, the International Atomic Energy Agency has requested the participation of our experts in advisory and technical assessment missions in support of those countries that have recently joined the European Union and that have nuclear power plants similar to Vandellós I scheduled for decommissioning in the near future. The present document covers the five years of decommissioning of Vandellós I, defining the main lines of the project and describing the activities that have arisen from them. It is, in short, an example of the commitment to transparency and collaboration with society that has always characterised ENRESA s activities. I should like to express my satisfaction at the high level of participation that has come from the local community, which provided three quarters of the 2,500 people whose work has made this project possible, as well as my thanks to all the groups that have intervened, with a special mention of the local institutions, media and society for the support that they have always given ENRESA in the decommissioning of the Vandellós I nuclear power plant. p.5

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9 Introduction

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11 INTRODUCTION. The Empresa Nacional de Residuos Radiactivos (ENRESA) has concluded the decommissioning of the Vandellós I nuclear power plant after five years of complex work. The reactor box now having been sealed and the greater part of the site released, ENRESA will keep the rest of the facility in a situation of latency for the next 25 years, until such time as the radioactivity of the internal structures of the reactor decreases naturally to levels allowing for level 3 decommissioning. The decommissioning of a nuclear power plant is a pioneer activity in Spain and there are few references at international level. For this reason, ENRESA designed and performed the project using radiological and conventional safety as an unalienable premise, the work having been planned, undertaken and controlled on the basis of a well studied action protocol aimed at minimising risks for people and the environment. In this respect, ENRESA s commitment to the sustainability of its actions led to the establishment of a philosophy of environmental optimization allowing the volume of wastes generated by the decommissioning process to be reduced to the greatest possible extent. The correct management of materials and the priority given to their recycling or reuse have been the pillars supporting this policy. The decommissioning of Vandellós I has also been a task that has been undertaken with the transparency that characterises all the activities of ENRESA. With this aim in mind, efficient channels were set up from the beginning for communication with the most important administrations and political institutions, the media and the general public. THE SITE IN THE LATENCY CONDITION UNDER ENRESA RESPONSIBILITY Likewise, and in view of the unique characteristics of the project undertaken and the possibility of applying the experience acquired to other decommissioning operations, ENRESA has adopted international cooperation as a vocation. ENRESA has hosted visits by national and international experts interested in gaining first-hand insight into the activities carried out at Vandellós I. It has also organized forums for debate on the decommissioning of nuclear power plants and has actively collaborated with different supranational organizations having responsibilities in this area. The company s keen interest in optimizing decommissioning projects and in training professionals in this field are now reflected in the start-up of the Mestral Technology Centre. This centre, located at the facilities currently maintained in the latency situation and under the responsibility of ENRESA, aims to become a base for the development of technologies allowing future nuclear power plant decommissioning projects to be performed with increasing levels of efficiency, safety and sustainability. p.9

12 CHAPTER 1

13 Background

14 The Vandellós I nuclear power plant, located at Vandellòs i l Hospitalet de l Infant in the province of Tarragona, was first coupled to the electricity grid on March 6th This facility, owned by the Spanish-French company Hispano-Francesa de la Energía Nuclear, S.A. (HIFRENSA), was the only Spanish plant to use natural uranium and graphite-gas technology, which was developed mainly in Great Britain and in France. VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) The first decommissioning The nuclear power plant was retired from service as a result of the fire that occurred in the second turbine-alternator set on October 19th Although this incident had no radiological consequences and damaged only conventional areas of the facility, the Ministry of Industry and Energy suspended the plant s operating licence, thus putting an end to its activities after 17 years of operation and the generation of 55,647 million kilowatts, a production equivalent to the entire electricity consumption of the city of Barcelona during that same period. The high cost involved in recovering the plant led the owner company to shut it down definitively. As a result, in July 1990 the Ministry of Industry and Energy issued a Ministerial Order establishing the conditions under which HIFRENSA was to keep the plant in the safe shutdown mode, undertake the first level of decommissioning and subsequently transfer ownership of the site to the CONSTRUCTION OF THE VANDELLÓS I REACTOR IN 1969 Empresa Nacional de Residuos Radiactivos, S.A. (ENRESA). The aforementioned Ministerial Order commissioned ENRESA to draw up a plan for the decommissioning of the nuclear power plant. In May 1994, after studying various alternatives, ENRESA submitted the Vandellós I Decommissioning Plan to the Provincial Directorate of the Ministry of Industry and Energy in Tarragona. The decommis- CONSTRUCTION OF THE MAIN MAINTENANCE DEVICE (DPM) IN 1970 VANDELLÓS I NUCLEAR POWER PLANT DURING THE OPERATING PHASE p.12

15 BACKGROUND. CHAPTER1 POOLS BUILDING sioning was to be to level 2, as established in the terminology of the International Atomic Energy Agency (IAEA), which consists of the decommissioning and removal of all the structures and components external to the reactor box, with the exception of those ensuring its confinement. CONTROL ROOM OF THE PLANT On January 28th 1998, the Ministry of Industry and Energy, following a favourable report by the Nuclear Safety Council (CSN) and an environmental impact statement by the Ministry of the Environment, approved the Decommissioning Plan for Vandellós I nuclear power plant, and on 4th February ENRESA became the operator responsible for the facility. Vandellós I is the first nuclear power plant to be dismantled in Spain and constitutes one of the first experiences at world level of the decommissioning of a high power commercial facility. Transfer of Ownership LEVEL LEVEL 2 HIFRENSA Unloading and removal of fuel from reactor Waste conditioning Pre-conditionig of grafite from the silos Decommissioning support services CSN DGMA MIE Favourable assessment of the Decommissioning Plan (DP) Environmental Impact Statement Approval of DP and transfer to ENRESA of operational responsibility Feb , TRANSFER ENRESA Preparation for transfer and decommissioning Performance of decommissioning at level 2 p.13

16 CHAPTER 2

17 A commitment to safety

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19 A COMMITMENT TO SAFETY. CHAPTER2 DISASSEMBLY OF THE REACTOR BUILDING One of the basic objectives of the decommissioning of Vandellós I nuclear power plant has been to guarantee the long-term safety of the site. Using this premise as input, ENRESA designed the Decommissioning Plan on the basis of a calculated intervention protocol that has guaranteed the safety of the process for all the people participating and for the environment. In this respect, ENRESA has managed the project by means of a well studied organizational model that places priority on the achievement of high standards of quality without renouncing the optimization of the work and resources. Consequently, priority has been given in decommissioning Vandellós I to responsible performance and to the guarantee of conventional and radiological safety both on the site and in the surrounding area. ENRESA has developed its action philosophy through a methodology presided over by safety, control and quality assurance. For this reason, each and every one of the interventions undertaken throughout the decommissioning process have been designed, managed and performed by multidisciplinary teams. REMOVAL OF EQUIPMENTS FROM THE POOLS BUILDING p.17

20 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Decommissioning Plan The project designed by ENRESA and approved by the Ministry of Industry and Energy implies decommissioning to level 2, in accordance with the terminology coined by the IAEA. This process, which was carried out after the owner company had unloaded and removed the fuel and conditioned the operating wastes during the so-called level 1 phase, has meant the dismantling and removal of all the structures and components external to the reactor box. This latter component has been confined and must now remain for some 25 years for the radioactivity of its internal structures to decay naturally before level 3 decommissioning may be undertaken with guarantees of safety for the workers and the environment. This option implies a series of advantages, particularly important among which are the absence of risks of accidents due to the failure to operate of components, since the system is passive, the non-generation of secondary wastes and the low cost of implementation, surveillance and conservation. Furthermore, from the operational point of view, the decommissioning project has been considered technically feasible at all times, since it has implied the general use of straightforward technologies widely available in Spain and of well proven working methodologies and tools. The optimum performance of the level 2 decommissioning carried out by ENRESA and the initiation of the so-called reactor box latency period constitute a decisive step forward in the overall decommissioning of the Vandellós I nuclear power plant. Described below are the three levels of intervention on which this pioneer project hinges, in accordance with IAEA directives: LEVEL 1 Conditioning activities These activities were carried out by HIFRENSA, the plant operator, during the period 1991 to 1997 in compliance with the Ministerial Order of July 1990 establishing the definitive shutdown of the plant. The work performed during this period included the unloading of the reactor core and the removal of the fuel from the site, the conditioning of the operating wastes and the removal and preliminary conditioning of the Organizational Flowchart for Decommissioning Site Management Administration and Services Deputy Management Communication and Training Quality Assurance and Documentation Technical Management Technical Office Radiological Protection and Safety Materials Control Works Engineering Operation and Maintenance Performance Radiological Protection Security Industrial Safety p.18

21 A COMMITMENT TO SAFETY. CHAPTER2 wastes stored in the graphite silos. In addition, certain disassembly tasks were performed on conventional elements such as the CO 2 tanks and the main turbine-alternator sets. LEVEL 2 Decommissioning of structures and preparation for the latency period This level was carried out under the responsibility of ENRESA between February 1998 and June It included the dismantling of all the structures, systems and components except the reactor box, releasing most of the site and leaving the rest as a regulated zone with the reactor box confined and covered by a newly built structure providing protection against weather.. This level has included two phases of performance: LEVEL 1 DECOMMISSIONING. REMOVAL OF CO 2 TANKS First phase This phase was carried out between February 1998 and February 1999 and had the following objectives: - Conditioning of the site for the performance of disassembly work in radiological zones. Decommissioning schedule Preparatory activities Dismantling of active parts Decontamination of significant elements and zones Reactor isolation Scarification of facings Dismantling of graphite silos Disassembly of conventional elements Protection against the weather and latency infrastructures Dismantling of other buildings and facilities p.19

22 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) The overall budget for Level 2 decommissioning amounts to 94.6 million. LATENCY PERIOD On completion of Level 2 decommissioning, the unreleased parts of the site remain under the responsibility and surveillance of ENRESA. This situation will continue for 25 years, during which time the radiological activity of the internal structures of the reactor will decay to approximately 5% of the initial level. This will allow them to be dismantled with a minimum radiological burden for the personnel performing the work. LEVEL 3 Decommissioning of reactor box On completion of the latency period, around the year 2028, work will begin on the last level of decommissioning, which will include the removal of the reactor box and its internals and the complete release of the site. DISMANTLING OF ONE OF THE REACTOR BOX TURBO-BLOWERS - Dismantling and removal from the site of conventional equipment and structures not logistically required to support project activities. These activities are described in the Conventional Components Decommissioning Plan (PDCC). Second phase This phase was carried out between March 1999 and June 2003 and had the following objectives: - Performance of the Active Parts Decommissioning Plan (PDPA). - Application of the Declassification Plan to ensure that clean materials are not contaminated and may, therefore, be managed by conventional means. - Continuation of the PDCC. - Dispatch of low and intermediate level radioactive wastes (LILW) to the El Cabril Disposal Facility. - Dispatch of conventional materials to authorised centres for recycling. - Dispatch of conventional wastes to specialist tips. CUTTING AND CONDITIONING OF MATERIALS FROM DISASSEMBLY OF THE REACTOR BUILDING p.20

23 A COMMITMENT TO SAFETY. CHAPTER2 Planning and Safety IN SITU RADIOLOGICAL MEASUREMENT In the Vandellós I Decommissioning Plan priority has been given to the safety of the scheduled work and of the workers. This unalienable maxim translated into a planned and mandatory operating system that left nothing to chance, since all the action protocols were carefully studied and subjected to a strict control system. Described below are certain of the pillars that have guaranteed the safe performance of the decommissioning process: Radiological Protection All the activities carried out in the active areas of the facility have been rigorously analysed to determine their radiological implications, such that workers were allowed to operate only if bearing a Radiation Work Permit (PTR) establishing the radiological protection standards to be adhered to by the personnel in each specific zone. All the tasks performed were first analysed to plan the safest way to perform them, this being carried out by the ALARA Committee and approved by the facility s Radiological Protection and Safety service. The activities have been performed at preventive, operational and data control level. In this respect, the main activities carried out have been work authorisations, radiological surveillance, training in radiological protection, dose controls, work planning and reporting to the Nuclear Safety Council s resident inspector. ALARA Programme ALARA stands for As Low As Reasonably Achievable. The objective of this programme is to reduce exposure to ionising radiations to the lowest levels that might reasonably be achieved, taking into account technical, economic and p.21

24 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) social factors. The programme has been applied to all activities and/or tasks having radiological implications and has involved the organizations of ENRESA and contractor companies and all the professionally exposed workers who have intervened in the processes of design, planning, performance, dismantling, decontamination and demolition that might imply a radiological risk for the workers, the general public and the environment. The ALARA criterion rests on a series of radiological parameters (collective dose, maximum individual dose, dose rates and levels of surface and airborne contamination) that determine the implementation of a protocol for performance and protection, compliance with this protocol being obligatory. This prioritises maximum dose reduction for the performance of each activity in the active zones of the facility. Work Permit Requests (SAT) All activities carried out during the decommissioning of Vandellós I had to be previously authorised by way of the corresponding Work Permit Request (SAT). This administrative document established the safety conditions to be adhered to by the personnel responsible for each task and the suitable means for its performance. emphasising on-going improvement in prevention and the participation of all those collaborating in the project. In order to make this possible, ENRESA has applied the Framework Occupational Risk Prevention Plan at Vandellós I, this having implied periodic safety inspections at all the site installations, the signposting of all accesses to work areas and the performance of sampling tasks, controls and assessments of the environmental conditions in which the work was performed. Multidisciplinary teams The achievement of success in managing the safety of the decommissioning work has rested on the coordinated activity of the different services participating. Within this framework, the coordination and planning of the activities performed has been a vital element for the correct functioning of the entire process. Consequently, teamwork has represented one of the main assets in the decommissioning of Vandellós I nuclear power plant. During the period March 1998 to June 2003, 854 SAT s were authorised. Prevention of Occupational Risk Despite the nuclear nature of the site, most of the risks faced by the workers involved in decommissioning related to the performance of work at heights and to the movement of large volumes of materials. These are, therefore, conventional risks that have been addressed from the perspective of the Prevention of Occupational Risk. Throughout the project this aspect has been integrated into a decision-making structure affecting all levels of project responsibility, from the technicians to the upper management of ENRESA and of the contractor companies. In order to implement the ENRESA commitment to the achievement of optimum conditions of health, occupational welfare and safety and hygiene at all its work centres and convert it into a reality, the decommissioning of Vandellós I has rested on an integrated safety policy PREPARATION OF DECLASSIFIABLE MATERIALS HANDLING UNITS IN THE CUTTING WORKSHOP p.22

25 A COMMITMENT TO SAFETY. CHAPTER2 Institutional control In view of the unique characteristics of the work performed at the plant and the nuclear nature of the site, the decommissioning of Vandellós I has been subjected to exhaustive controls by the most important competent institutions. The main control function has been undertaken by two state organizations: the Nuclear Safety Council (CSN) and the Directorate General for Energy Policy of the Ministry of Economy. As at other nuclear sites, the CSN has kept a resident inspector at Vandellós I, who has been in charge of continuous tracking of the different activities. In addition, this organization has carried out periodic audits on the different departments involved in the project in order to specifically analyse each of the significant interventions. In this respect, the CSN has performed 75 audits throughout the project relating, among other things, to different aspects of the Active Parts Decommissioning Plan, the management of materials, the declassification of the site and the preparation of the site for the latency period. Ministerial control has been carried out through the Vandellós I Decommissioning Information Committee, a panel presided over by a delegate of the Ministry of Economy and comprising also representatives of the Ministry of the Environment, the CSN, the Government Delegation in Catalonia, the Regional Government of Catalonia and the Town Council of Vandellòs i l Hospitalet de l Infant. At local level, the decommissioning of Vandellós I has been subject to the control of the Municipal Tracking Commission of Vandellòs i l Hospitalet de l Infant, an organization made up of members of the town hall, representatives of the surrounding municipal areas, and of the most important local groups, associations and entities. As regards the purposes of this Commission, included in its bye laws, mention may be made of the verification of the origins and destination of contaminated materials and checking that the works performed on site do not entail any risk for the population or the environment. Likewise, ENRESA has kept various other entities and institutions informed of specific aspects of the dismantling operations, such as the Regional Council of the Baix Camp area, the Rovira i Virgili University, the Professional Association of Engineers of Catalonia and the provincial media. VISIT FROM THE DECOMMISSIONING INFORMATION COMMITTEE. JULY 2003 p.23

26 CHAPTER 3

27 The decommissioning process

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29 THE DECOMISSIONING PROCESS. CHAPTER3 3.1 Preparatory activities Construct to dismantle ENRESA s activities at the Vandellós I nuclear power plant began in March 1998 and included the start-up of a programme of preparatory activities necessary for decommissioning of the radiologically active parts of the facility. As a result, ENRE- SA spent the first few months working on the adaptation, installation and implementation of all types of infrastructures and systems required for optimum performance of the project. In other words, during the initial phase ENRESA was building in order to dismantle. Consequently, ENRESA s first activities consisted of definitively removing from service those systems that would not be required during dismantling and of removing from the plant all inflammable or toxic products that might pose a problem during the works. CONSTRUCTION OF THE MEASURING GANTRY FOR MATERIALS TRANSPORT The electrical systems were modified, this including the installation of a new distribution arrangement adapted to the needs of the decommissioning process and running along different routes from those followed by the original system and the incorporation of new ventilation systems ensuring the confinement of areas in which work with radiological implications was to be performed. The Control Room was replaced with a new Surveillance Post from which systems still in operation in the plant were controlled and monitored. Also modified were the effluents treatment and dilution system and the fire-fighting system, this p.27

30 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) including the acquisition of new equipment and the setting up and training of the 41-strong fire brigade. As regards the project organization infrastructures, the Administration offices were taken to the easternmost area of the site, in order to clearly separate works activities from purely administrative tasks. In this respect, advantage was taken of the former large materials store, which from then on housed the offices of all the project organization services. During 1998, various infrastructures of logistical interest for the decommissioning process were adapted. Specifically, a materials declassification and cutting workshop was set up in an enclosure adjacent to the reactor building. This was used for the reception, cutting, segregation and classification of all the materials arising from radiological areas. Mention may be made also of the improvement and adaptation of the medical service, which was provided with new equipment especially adapted to the decommiossining works, and a new reactor building entrance and exit radiological control post was installed for the dosimetry control of the personnel. decommissioning, the fuel-oil and gasoil tanks were also removed, as were the demineralised water tanks. Overall, during 1998 ENRESA managed 2,798 tons of conventional materials, basically consisting of scrap, effluents from the cleaning of tanks and electrical cables. Start-up of new systems The phase of preparatory activities finished with the performance of tests on all the systems implemented or modified during the works, these being evaluated by the CSN. Overall, 15 tests were carried out between October 26th 1998 and January 26th The tests consisted of verifying the correct operation of both individual components and overall systems and checking that they met the requirements applicable to their design. On March 17th 1999, the CSN approved the results of the tests and authorised the initiation of decommissioning works in active zones. Finally, a weighing device was installed, fitted with a radioactivity monitor serving as a final radiological control prior to the exit of the materials from the facility. Preliminary conventional disassembly and demolition works In parallel to these preparatory activities, certain of the activities contemplated in the Conventional Components Decommissioning Plan (PDCC) were initiated. Specifically, these were the disassembly and removal of the structures and buildings that would not be of any logistical use during decommissioning and that might leave free a space of value for other uses. Among these activities, mention may be made of the disassembly of the auxiliary plant, the installation that supplied electrical energy to all the auxiliary services during plant operation. The four boilers, four auxiliary turbine-generator sets and compressed air system were removed and taken to recycling facilities, after which the demolition process began. During these early months of DEMOLITION OF THE AUXILIARY PLANT p.28

31 THE DECOMISSIONING PROCESS. CHAPTER3 3.2 Decommissioning An industrial process ENRESA views the Vandellós I nuclear power plant decommissioning project as an industrial process in which, starting with a set of raw materials and certain initial resources, a final transformed product is achieved. Specifically, in the ENRESA philosophy, the raw materials are the plant site itself and a series of productive resources (human resources, installations, machinery, energy, etc.). For its part, the process of transformation consists of a sequence of activities including, among others, disassembly, decontamination, declassification, demolition and the restoration of the land. The industrial process concludes with two types of results, firstly the site now partially released and partially in a state of latency, and secondly another set of materials and wastes that are to be managed. Initiated in March 1998, this industrial process actually began to operate in full swing one year later, in April 1999 when, the preparatory activities having concluded, authorisation was received for work in plant areas with radiological implications. Accordingly, ENRESA began to work simultaneously on the two pillars supporting the Decommissioning Plan: the Conventional Components Decommissioning Plan (PDCC), which had been in force since 1998, and the Active Parts Decommissioning Plan (PDPA). An industrial process INPUTS Raw materials + Productive resources TRANSFORMATION Removal of linings OUTPUTS Site in latency + Materials to be managed In situ decontamination Cutting and packaging Declassification Demolition Dispatch p.29

32 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Decommissioning Plan of Conventional Components (PDCC) This set of activities includes disassembly, demolition and restoration of the land in relation to all the buildings, systems and components not having any radiological implications. Generally, these were tasks that, while not requiring the radiological protection demands typical of the PDPA, did need to be carried out with major safety measures applied, since the very dimensions of the facilities implied the movement of many tons of material and the performance of work at a significant height from the ground. The conventional installations of the site were for the most part reused in different ways during the project, and were dismantled and demolished only when they ceased to have any logistical use. As a result, it has been necessary throughout the decommissioning process to schedule the sequence of the tasks to be performed, with emphasis on avoiding tasks carried in parallel interfering with each other and on the availability of infrastructures and space for the temporary storage of materials arising from disassembly. DISMANTLING OF THE AUXILIARY ELECTRICAL EQUIPMENT BUILDING This action philosophy explains how, during the early months of the project and in parallel with the activities for the preparation of interventions in active zones, certain conventional installations were removed from the site, such as the auxiliary plant and the fuel-oil, gasoil and demineralised water tanks, the land they had occupied remaining free for reuse as storage areas for clean materials from active areas pending declassification. Consequently, these initial interventions in conventional facilities were also preparatory activities. Another of the major facilities to be dismantled, once it was no longer of any use for the project, was the auxiliary electrical equipment building, which housed the former control room and many of the plant feed systems. After more than two years of work for the removal of kilometres of cables from the entire site and their replacement with the new systems to be used during the latency period, the upper floors of the building were dismantled and demolished between September p.30

33 THE DECOMISSIONING PROCESS. CHAPTER and March The lower floors were used for construction of the facilities for the new Mestral Technology Centre and for support during the latency period. Among the other activities carried out by ENRESA within the framework of the PDCC, mention should be made of the disassembly of the former plant administration building, which was temporarily used as a store for containers with clean and declassifiable materials, the former maintenance building, which was temporarily used as offices for contractor companies, the high voltage pylons and the former radiological protection, engineering, archives and medical services pavilions. DISASSEMBLY OF THE ADMINISTRATION BUILDING Restoration of industrial land The ENRESA project established the requirement that the land previously occupied by the nuclear power plant buildings, equipment and systems be released and restored. This last step in the complex process of decommissioning a building consists of filling in the holes left in the ground as a result of the disassembly of the equipment, systems and structures. In keeping with recycling policy implemented by ENRESA during the project, such restoration was accomplished using crushed and compacted concrete backfill material from the rubble arising during the demolition of the buildings belonging to the facility itself. Consequently, the methodology has required the rate of demolition and of treatment of the concrete to be adapted to that of the generation of land to be restored, the objective being to prevent the excessive accumulation of rubble or, on the other hand, of large areas pending restoration. In total, some 77,000 tons of concrete rubble from the site itself were used in restoration of the land. p.31

34 The decommissioning of the active parts, which consists of disassembling the systems and components located in areas having radioactive implications, began in March 1999 following CSN approval of the testing of the modified or newly constructed systems. The Active Parts Decommissioning Plan (PDPA) was applied as from that time, this being a detailed industrial process in which the decommissioning of radiologically active facilities and the disassembly, segregation and transfer of the resulting materials were performed in such a way as to minimise the final volumes of radioactive wastes. In this respect, the materials declassification process, the decontamination techniques and the policy of reusing materials have been the main routes that have made it possible to significantly reduce the final amount of radioactive wastes. VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Decommissioning Plan of Active Parts (PDPA) The decommissioning of a contaminated building begins with a characterization campaign aimed at determining the location of contamination and radiation hot spots. This is used to draw up a radiological map of the building making it possible to design the most efficient decommissioning strategy. The minimisation of the doses received by the workers and of the volume of radioactive wastes generated is the priority objective of this strategy. DISMANTLING OF THE MAIN MAINTENANCE DEVICE This is followed by the disassembly of all the equipment and systems in the building. Of the resulting materials, those that exceed the levels of contamination established by the competent authority are managed as low and intermediate level wastes and are sent to the El Cabril Disposal Facility. Radiologically clean materials, on the other hand, are included in the declassification process, which will allow them to be managed as conventional materials and, therefore, be recycled or disposed of at authorised tips. The next step after dismantling of the interior is to focus on the structure of the building itself. All the facings are re-measured to locate contamination hot spots and depth. This is followed by decontamination of the affected areas and a new characterization campaign to demonstrate the absence of radioactivity. The building is then declassified and demolished. Finally, the land is released and restored. DISMANTLING OF EQUIPMENT AND SYSTEMS IN THE REACTOR VAULT. ELEVATION +3.5 p.32

35 THE DECOMISSIONING PROCESS. CHAPTER3 Detailed below are the main activities included in the PDPA and performed by ENRESA in the decommissioning of Vandellós I. Reactor building The disassembly of the equipment in this major building was initiated in April 1999 and concluded in late Parallel to this, the reactor box was sealed to guarantee its static confinement for the period of 25 years that would elapse prior to the initiation of decommissioning to level 3. The zone having been reclassified and a structure designed to provide protection against weather having been constructed, the building was declassified thanks to approval by the Nuclear Safety Council of a course of action combining materials and surfaces declassification methodologies. Finally, the building was disassembled via a major engineering effort that required a crane with a 150-metre boom and a load capacity of some 800 tons. This project milestone, which completely changed the external appearance of the plant, took place between the months of May and October Characterization and scarification of facings and floors These tasks for the decontamination of surfaces consisted of measuring and marking 136,000 m 2 of wall facings and floors for the subsequent segregation of the contaminated surfaces. This allows the volume of materials from the plant structures that eventually have to be managed as radioactive wastes to be minimised. Characterization and scarification are two complementary activities that have required the intervention of both the Radiological Protection and Safety personnel, for marking, and operators dedicated to cleaning and segregating the contaminated parts. Irradiated fuel building The equipment in this building, which was formerp.33

36 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) ly used to channel the spent fuel to the storage pools, was disassembled during the period 1999 to 2001 and the decontamination of structures extended to February 2002, at which time the building was declassified. In the months that followed, and as the structure of the reactor building was disassembled, this building was demolished. REMOVAL OF THE METALLIC LINER OF THE FUEL POOLS BUILDING Fuel pools building In view of its radiological implications, the decommissioning of this building was one of the most complex tasks undertaken during the entire project. The removal of the equipment and systems was undertaken between April 1999 and the end of 2001, after which work began on the decontamination of the structures, a particularly meticulous task in the case of the chipping off of the concrete surrounding the fuel transfer tubes. The declassification of this building and its subsequent demolition took place during the month of February 2002, except in the case of the fuel han- Comparative evolution of works progress % annual progress by quarters Accumulated work scheduled Accumulated work performed T-1 T-2 T-3 T-4 T-1 T-2 T-3 T-4 T-1 T-2 T-3 T-4 T-1 T-2 T-3 T-4 T-1 T-2 T-3 T-4 T-1 T-2 T-3 T-4 p.34

37 THE DECOMISSIONING PROCESS. CHAPTER3 dling cell, in which decontamination work continued until the month of May. Finally, the building was demolished and the land restored. Graphite silos/conditioning workshop This work consisted of dismantling the three silos that were formerly used for the graphite sleeves from the plant fuel and the workshop for the conditioning of this material. This last facility was dismantled and demolished during the latter months of 2002, while work on the three graphite silos focused on a complete process of decontamination of structures that concluded in March 2003 with its declassification. Effluents building The building that was used during plant operation for the treatment and discharge of liquid effluents became one of the radioactive waste storage facilities during decommissioning. Part of the installations was also used during much of the project as a materials decontamination area. Finally, as the radioactive wastes were sent to El Cabril Disposal Facility, the process of removing the equipment and decontaminating the structures got under way. Given that this was the last building with radiological implications to be removed from service, its declassification in April 2003 marked the end of the activities corresponding to the Active Parts Decommissioning Plan. Its demolition and following restoration of the land took place in May Other installations Among the activities performed by ENRESA within the framework of the PDPA, attention may be drawn also to the dismantling, declassification and recovery of certain smaller buildings that had been left disused during the project, for example the drums silos, the irradiated parts wells, the former laundry and the radiological area of the Medical Services facility. WORK BEING PERFORMED SIMULTANEOUSLY ON THE REACTOR SLAB: SEALING OF REACTOR BOX AND DISASSEMBLY OF THE MAIN MAINTENANCE DEVICE p.35

38 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Decommissioning of the reactor building The disassembly of the reactor building was the largest scale intervention carried out during the decommissioning of Vandellós I nuclear power plant. The works began in May 2002, following the dismantling of all the equipment and components formerly housed in this 80-metre high building, which contained all the reactor box auxiliary facilities. In July of that year, the CSN authorised the implementation of the declassification methodology for the structures of the building, a methodology that combined the declassification of surfaces and materials, allowing them to be managed as conventional wastes and sent to recycling plants. Advantage was taken of the summer months for the performance of this work, with a view to avoiding to the extent possible the impact of the strong winds that usually blow in this area, since the manoeuvres were to be performed at a considerable height and involved very heavy parts. The disassembly of the building generated some 3,200 tons of steel, 14,000 m 2 of shaped plating, almost 2,000 m 2 of waterproofing asphalt cloth, and some 3,500 m 3 of concrete. The works also included the removal of heavy girders and other parts, which required the contracting of a large crane. This was a lattice-type structure, unique in Spain, capable of operating at a height of 150 metres and of loading parts weighing up to 800 tons. The heaviest parts handled by this crane during the disassembly of the reactor building weighed up to 240 tons. The works concluded in October 2002, leaving the external appearance of the plant what it would be throughout the latency period. With its 39,000 m 3, the structure protecting the reactor against wind and weather implies a reduction in volume and consequently in visual impact of 75% with respect to the 162,000 m 3 of the former reactor building. p.36

39 THE DECOMISSIONING PROCESS. CHAPTER3 3.3 Materials management A controlled process, suitable destinations The magnitude of the decommissioning of the Vandellós I nuclear power plant has implied the generation of a large amount of materials from both active and conventional areas, the management of which has consisted of determining in each case whether they should be recycled or stored as wastes. In this respect, the priority objective of the project has been to minimise the volume of both conventional and radioactive wastes, a use being found for the rest of the materials either on or off the site. One of the essential points of the project has been the exhaustive control of all the materials from the site with a view to segregating those that had radiological implications from those others that were clean and might be reused. It is estimated that between March 1998 and June 2003 some 15,900 tons of non-contaminated materials were generated, mainly metallic materials, which were recycled, and minor amounts of conventional wastes that were sent to authorised centres. To these should be added 1,961 tons of rubble from the active zones, which were reused for land restoration following declassification, along with almost 77,000 tons of concrete from the demolition of the plant buildings. As regards the volume of radioactive wastes, the 2,000 tons initially foreseen finally ended up at 1,763 tons. This reduction in waste volume has been possible thanks to the segregation and decontamination techniques used and to the policy of recycling implemented by ENRESA during the decommissioning. TRANSPORT OF RADIOACTIVE GRAPHITE TO THE TEMPORARY STORAGE FACILITY FOR THE LATENCY PERIOD p.37

40 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) STORE FOR RADIOACTIVE WASTES PENDING DISPATCH TO EL CABRIL CENTRALIZATION OF DECLASSIFIABLE MATERIALS In order to minimise the volume of wastes and identify ways for reusing the rest of the materials, there was a need to implement a management system guaranteeing their correct destination, especially for those arising from the active parts of the facility. In this respect, ENRESA set up a management system that established up to five obligatory controls for all those materials from active areas that, given their background and characteristics, were candidates for declassification and, therefore, for management as conventional materials. Only a methodology as meticulous as this made it possible to ensure that no material leaving the plant exceeded the levels of activity required by the CSN for consideration as non-radioactive. Declassification is a technical and administrative activity in which the acceptable levels for materials and surfaces from active areas are certified. Consequently, materials meeting these levels have been able to leave the site for conventional destinations. The decommissioning of Vandellós I is the first project in which this activity has been undertaken with quantities of materials and surfaces at industrial levels. Since their initiation in April 1999, the activities included in the Active Parts Decommissioning Plan (PDPA) have generated 11,736 tons of materials, of which 1,763 tons are low and intermediate radioactive wastes and the remaining 9,973 tons are materials (8,012 t) and facings (1,961 t) included in the materials and structures Declassification Plan, which has allowed them to be managed as conventional materials and dispatched to recycling plants for other industrial uses or reuse in restoration of the site. During decommissioning, the tasks included in the Conventional Components Decommissioning Plan (PDCC) have generated 7,894 tons of materials, mainly scrap and ferrous materials, which have been removed from the site under the control of the Waste Council of the Regional Government of Catalonia. The main destination of these materials has been recycling plants. To this figure for materials from conventional areas are to be added almost 77,000 tons of concrete rubble from the demolition of buildings, which have been used throughout decommissioning for the restoration of land on the site. p.38

41 THE DECOMISSIONING PROCESS. CHAPTER 3 Material s destination 15,906 t Minor quantities Initial situation 78,960 t 1,763 t Conventional scrap Toxic and hazardous Products Conventional concrete rubble Low and intermediate radioactive wastes Recycling Controlled tip Final situation El Cabril Disposal Facility p.39

42 Control system basis VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) The policy designed by ENRESA for the management of all the materials generated in areas having radiological implications includes a declassification plan aimed at reducing to the maximum possible extent the volume of radioactive wastes produced. In this respect, ENRESA has applied this plan both to materials arising from the dismantling of equipment and components and to the structures and wall facings of the buildings that previously housed them. In order to ensure the absence of contamination, ENRESA designed a system based on five controls. The process began with the application of two of these controls, the objective being planning of the work. These initial controls related to knowledge of the operating history of the equipment or system to be dismantled, and analysis of up to three overall radiometry studies carried out on site. These two preliminary controls were complemented at the place of intervention with the so-called in situ characterization, performed by technicians from the Radiological Protection Service using portable equipment. Once a favourable result was obtained from these three controls, the presumably clean material was subjected to a process of declassification by means of spectrometric measurements, which constituted the fourth control. For their part, contaminated materials were managed as radioactive wastes and conditioned directly for dispatch to the El Cabril Disposal Facility. The Declassification Plan established three lines of activity with different methodologies and operational formulas: the materials declassification line, the structures declassification line and the combined declassification line, which integrated methodologies from the other two. The materials management control system could also be complemented, if necessary, with a fifth and last control applied only to materials removed from the site for recycling. This control consisted of a large surface exit gantry through which all vehicles had to pass before leaving the site. The function of this device was to definitively verify the absence of any radioactive component in both materials prepared for dispatch to conventional destinations and the corresponding means of transport. Decommissioning process controls 1 2 OPERATING HISTORY DATE RADIOMETRY STUDIES CONVENTIONAL ZONES PDCC ACTIVE ZONES PDPA Disassembly and preparation of CIM Handling Units RADIOACTIVE WASTE 3 IN SITU RADIOLOGICAL CONTROL CLEAN Disassembly and preparation of CMD Handling Units, Big-Bag, etc. CONDITIONING AND PREPARATION FOR TRANSPORT NO 4 DECLASSIFICATION TRANSPORT YES 5 EXIT GANTRIES EL CABRIL DISPOSAL FACILITY POINTS OF DESTINATION (Administrative control) p.40

43 THE DECOMISSIONING PROCESS. CHAPTER3 Courses of action 1st course of action: materials declassification This line of activity, authorised by the CSN in July 2001, has made it possible to manage all the clean materials generated during the decommissioning of areas with radiological implications as conventional materials. The materials entering the declassification process were grouped into Authorised Handling Units (UMA) and introduced, depending on their characteristics, into special containers for measurement (CMD s), drums or big-bags. These units were then subjected to a process of integral measurement using the low background measuring device, an apparatus that analysed the radiological load of the material by means of gamma spectrometry and that allowed work to be performed at industrial scale with laboratory precision. Only when this equipment had once more ratified that the materials did not exceed the levels established by the CSN they were declassified by the Radiological Protection Service. REMOVAL OF SHIELDING FROM THE MAIN MAINTENANCE DEVICE AND STORAGE AS DECLASSIFIABLE MATERIAL 2nd course of action: surfaces declassification The surfaces of concrete walls located in radiological zones had to be declassified prior to their demolition, in order to ensure the absence of contamination. This conditioning factor made it necessary to develop a specific course of action for the declassification of surfaces, the methodology of which was approved by the CSN in February On the basis of the operating history and the values provided by the previously performed radiological studies, an initial measurement was carried out to characterize the entire surface of the wall facing, in order to identify possible points of contamination. This characterization process allowed the surface to be classified as contaminated or declassifiable. The latter type then underwent a process of gamma spectrometry, p.41

44 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Types of containers CMT (Metallic Transport Container) Container used for radioactive wastes from the decommissioning of systems and structures in active zones. These containers were conditioned by filling them up with concrete so as to immobilize their content before being dispatched to the El Cabril Disposal Facility. DV Drum (Decommissioning of Vandellós) Container designed for secondary radioactive wastes such as gloves, masks, filters, etc. These were called DV packages until the wastes contained were measured and conditioned, as from when they were called DV drums and were sent to the El Cabril Disposal Facility. CMD (Measuring and Declassification Container) Container used for the management of conventional and declassifiable materials. During the different phases of this process, the materials had to be moved in CMD containers around the site following previously established management routes. Big-Bag Bags containing non-radioactive but toxic insulation materials (glass fibre, asbestos, etc.). As it happened with the materials which were housed in CMD containers, these were also required to be measured and controlled by the Materials Control service. p.42

45 THE DECOMISSIONING PROCESS. CHAPTER3 ISOCS, the results obtained being compared to limits established by the CSN. Once the facing had been considered as declassifiable, work could proceed on its demolition. 3rd course of action: combined line There have been certain structures, such as the reactor building, that constituted a last level of protection and that could not be disassembled prior to being declassified. Furthermore, the measuring equipment available could not be used on these structures due to accessibility restrictions. These two conditioning factors led ENRESA to develop a specific course of action, the methodology of which was approved by the CSN in July In addition to the operating history of the plant and the results of the radiometry studies performed, this course of action included a surveillance analysis of incidents occurring throughout the entire operating lifetime of the plant. Complementary to the above, there was a general verification measurements campaign and specific campaigns in areas implying a potential risk. To these were added the direct measurement of a percentage of the materials from the structure disassembled, housed in CMD s, which were analysed using the low background measuring device, as in the case of the course of action for materials. This percentage of the structure was grouped in so-called contrast handling units (contrast UMA s). Following the analysis of the operating and radiological histories and the measurements acquired from the contrast handling units, the structure could be declassified and subsequently dismantled. Declassification equipment The declassification of materials and surfaces has been performed using two gamma spectrometry measuring devices. After each of the different controls established by the corresponding line of declassification, the materials and surfaces were subjected to a final measurement, the results of which certified their declassification. In the case of the materials, the equipment used was the low background monitor, a device containing four germanium detectors that, coupled to three different measuring positions, allowed the spectrum of twelve segments of the container to be obtained, in addition to a sum spectrum. In this way it was possible to detect and segregate possible hot spots and thus prevent radioactive parts from being diluted in the mass of materials introduced into the container. The equipment used for surfaces was the ISOCS, a portable measuring device that, using a technology similar to that of the low background monitor, allowed the declassification equipment to be taken to the structures prior to their demolition. p.43

46 Recycling, a priority VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) The policy for the recycling of materials implemented by ENRESA in the decommissioning of the Vandellós I nuclear power plant has allowed new uses to be found for approximately 95% of the materials generated during the works. This systematic process of optimization has made it possible to minimise the volume of wastes while fully exploiting the possibilities offered by these resources. The different materials recycling routes used during the decommissioning of Vandellós I are described below. 1. Conventional materials Conventional materials are those that have never entered into contact with radiologically active areas or those that, despite their coming from active zones, have been declassified by the Radiological Protection Service. In order to fulfil the objective of minimising waste volumes, the materials generated have been reused at two levels: Internal recycling. This is the priority destination. The Decommissioning Plan foresaw the reuse on CENTRALIZATION OF DECLASSIFIABLE MATERIALS IN CMD S site of most of the materials generated as a result of the disassembly and demolition of the equipment, structures and buildings. External recycling. The optimization of the conventional materials was completed with the recycling, in various industrial activities, of the majority of the off-site dispatched materials. Like the conventional wastes (non-radioactive but toxic and/or hazardous), after leaving the site the aforementioned materials were managed by Autonomous Community organizations such as the Waste Council of the Regional Government of Catalonia and the Regional Council of the Baix Camp. 2. Contaminated materials As in the case of conventional materials, waste volume reduction was also an objective of the management policy for contaminated materials. p.44

47 THE DECOMISSIONING PROCESS. CHAPTER3 Internal optimization. This consisted of decontaminating on site those materials that, as a result of their low activity or components and geometry, were open to a simple decontamination process. These materials were then incorporated into the declassification process for conventional management. External optimization. This was the industrial reuse of contaminated materials that, in view of their nature, isotopic composition and low degree of contamination, might be recycled within the nuclear field. In this context, ENRESA dispatched 72 tons of ferrous materials to the United States, 98% of which were reused by the company Duratek for the construction of new shielding for the Fermi Laboratory in Chicago. The rest of the contaminated materials, i.e. those that could not be decontaminated or reused, were managed as low and intermediate level radioactive wastes and sent to the El Cabril Disposal Facility. TRANSPORT OF DECLASSIFIED MATERIALS TO RECYCLING PLANTS Diagram of recycling at Vandellós I SITE CONVENTIONAL RECYCLING CONVENTIONAL MATERIALS DISMANTLED MATERIALS CONVENTIONAL MATERIALS IN SITU RECYCLING CONTROLLED TIP CONVENTIONAL WASTES LILW CONTAMINATED MATERIALS EL CABRIL DISPOSAL FACILITY NUCLEAR CYCLE RECYCLING p.45

48 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Transport of radioactive materials The transport of radioactive materials was accomplished in accordance with the recommendations of the International Atomic Energy Agency (IAEA), incorporated in the national legal system. The objective of the set of measures established by the regulations was to minimise the probability of an accident occurring and, were it to occur, to mitigate its consequences. Safety in transport is based on the concept of the waste package, this being understood as the assembly formed by the radioactive material to be transported and the packaging in which it is confined. The legal framework regulating the transport of this type of merchandise is included in the European regulations on the International Road Transport of Hazardous Goods (ADR). This means that the degree of resistance of a waste package is proportional to the radioactivity contained and to the harmfulness of the substances transported. This guarantees that even in the case of a package being completely destroyed in an accident, the radioactivity contained must be limited in such a way that the damage caused by the dispersion of the radioactive substances be acceptable for the environment. In order to guarantee the suitability of the packages to be transported, the regulations establish a series of tests to which they are to be subjected: free fall, resistance to knocks and high temperatures, leaktightness, etc. In addition, ENRESA reinforces safety in transport through the in-depth training of the drivers and the design of especially conditioned vehicles fitted, among other things, with automatic sealing systems, satellite tracking and additional shielding systems. Dispatch of radioactive wastes to El Cabril The transport of the first containers with low and intermediate level radioactive wastes from the decommissioning of Vandellós I to the El Cabril Low and Intermediate Level Waste Disposal Facility took place in July Since then 188 CMT container and DV drum transport operations have been carried out. Dispatch of radioactive wastes NUMBER OF TRANSPORT OPERATIONS p.46

49 THE DECOMISSIONING PROCESS. CHAPTER3 Movement of materials MATERIALS FROM ACTIVE PARTS Weight (Kg.) MATERIALS DECLASSIFIED AND DISPATCHED Thermal insulation 98,404 Cables 152,975 Ferrous scrap 7,553,490 Non-ferrous scrap 85,955 Others 121,216 TOTAL 8,012,040 MATERIALS DECLASSIFIED AND REUSED ON SITE Concrete 1,961,835 RADIOACTIVE WASTES DISPATCHED TO EL CABRIL Radioactive Wastes 1,763,722 TOTAL GENERATED IN ACTIVE PARTS 11,737,597 CONVENTIONAL MATERIALS No Transport Operations Weight (Kg.) Absorbents and filtering materials 3 11,660 Lubricating oils ,180 Hydrochloric acid 1 80 Wastewaters and sewage 7 37,500 High voltage pylon insulation 2 5,240 Alumina 1 2,360 Asbestos Miscellaneous materials ,300 Batteries 5 17,900 Electrical cables ,580 Sodium carbonate 1 3,960 Ash 1 4,640 Scrap 470 5,884,820 Detergents 1 1,220 Halogenated solvents 1 3,000 Non-halogenated solvents 1 3,000 Effluents and sediments ,280 Electronic equipment 8 39,450 Foamer 1 3,140 Glass fibre and wool 17 46,180 Fibrocement 12 60,870 Fluorescent tubes Graphite 1 5,260 Sodium hydroxide Cooling gas mixtures Used tyres 2 2,080 Paper and cardboard 35 56,095 Small batteries Plastics Radiographies Small amounts of special wastes 7 6,367 Ion exchange resins 2 46,160 Saline solutions 2 15,740 Vegetable fabrics 28 84,500 Asphalt cloth ,980 Transformers containing PCB s 5 83,480 TOTAL GENERATED IN CONVENTIONAL AREAS 923 7,894,825 p.47

50 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) 3.4 Latency infrastructures A 25-year wait A s the decommissioning of the Vandellós I nuclear power plant progressed, ENRESA began to install all the infrastructures required to address the latency period, a wait of 25 years for the radioactivity in the reactor box internals to decay naturally to levels allowing for its decommissioning. The new structure for protection against the elements consists of a reactor box clad of galvanised steel sheet. This cladding, which is separated from the box by a distance of 1.5 metres, starts at elevation +16 and extends to six metres above the reactor slab, where a roof has been constructed (elevation +63). The total weight of the structure is 350 tons and its surface area measures 5,700 m 2. As many as 70 workers were involved in its construction. It is designed to withstand gusts of wind in excess of 200 km/h and rainfall of 140 l/m 2. It should be pointed out in this respect that the preparatory activities for the period of latency began practically in parallel with the decommissioning in areas with radiological implications. As a result, by 1999 ENRESA had begun the process of confining the reactor box, following the removal of all the equipment and systems connected to it. This complex task consisted of plugging and thermally insulating more than 1,700 penetrations, with the objective of ensuring static confinement in order to guarantee the impossibility of any contact between the inside and the outside of the box during the latency period. On completion of this process in early 2000, ENRESA successfully carried out a leaktightness test under the control of the Nuclear Safety Council. This test, to be repeated every five years during the latency period, is included in the reactor surveillance programme, which will also include checking for internal corrosion by periodic sampling and visual inspection by means of special cameras. The new electrical panels and the reactor box surveillance system were also installed during This was followed by the construction of the new structure protecting the reactor box against the elements which, following dismantling of the reactor building (May-October 2003) now constitutes the external image of the plant. This structure, which will safeguard the reactor box against atmospheric agents throughout the latency period, implies a 75% reduction in volume compared to the former reactor building, and therefore a reduction also in visual impact. p.48

51 THE DECOMISSIONING PROCESS. CHAPTER3 The year 2003 saw the completion of the perimeter fence for the new site, as it will stand during the latency period, and the installation of the new mechanical and security systems, as well as a new modular liquid effluent treatment plant. Leak testing TEMPORARY STORAGE FACILITY FOR GRAPHITE FROM THE PLANT FUEL SLEEVES Furthermore, during 2002 the new surveillance and services offices were built, which will be the headquarters of the team in charge of monitoring the status and maintenance of the reactor box during the period of latency. These offices are located on the lower floors of what was the auxiliary electrical systems building, the structures of which have been reused. The temporary graphite storage facility, located on the lower floor of the reactor building, was also finished thus reusing the area previously occupied by the cutting workshop. The shielding is 65 centimetres thick at the walls and 70 centimetres at the roof. In order to optimize control and maintenance tasks, the lead windows of the graphite conditioning workshop and the storage pool building fuel handling cell were reused. During the latency period, this 1,900 m 2 facility will be used for the temporary storage of some 1,100 tons of graphite from the sleeves of the fuel used during plant operation. The leak test will be carried out every five years in order to ensure the static confinement of the reactor box during the latency period. Controlled by the Nuclear Safety Council, the test is made up of five phases that are performed in a total 40 hours. The five phases are as follows: - Pressurisation phase - Stabilisation phase - Controlled leakage phase - Verification phase - Depressurisation phase The indicators of reactor box confinement depend, therefore, on the possible pressure differences that might appear during the process. The first test was performed in April 2000 and the next check on the leaktightness of the reactor box is expected to occur during the early months of p.49

52 CHAPTER 4

53 Support activities

54 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) The decommissioning of Vandellós I has been supported by a series of services guaranteeing the quality and safety of the process. In this respect, the Decommissioning Plan drawn up by ENRESA rests on a series of activities relating mainly to occupational safety, radiological protection, works engineering, quality assurance and on-going training. The different activities undertaken by these services throughout the decommissioning process are outlined below. Radiological Protection and Safety This service was in charge of overseeing the radiological and industrial safety of the workers, and comprised approximately 10% of the personnel working in decommissioning of the plant. The integration of Radiological Protection and Safety in a single service was the result of the need to ensure a coordinated control of the activities performed at the plant. Among the activities carried out by Radiological Protection during the decommissioning of Vandellós I, special mention should be made of the tracking and operational radiological control of the dismantling and decontamination tasks performed in the different radiation areas of the plant, the measurements taken for the declassification of the different materials and surfaces and the control and planning of effluent releases. Likewise, throughout the works the Environmental Radiological Surveillance Program (PVRA) has been satisfactorily applied and monitored. Also to be underlined is the practical application of the ALARA Programme for dose minimisation by the different working groups set up for the specific tracking of dismantling and decontamination of all the areas included in the PDPA, the doses received by the workers having been optimized to a significant extent. As the decommissioning was progressing, this service gradually reduced the radiological zones of the plant by way of area reclassification campaigns, applying the criteria established in the Radiological Protection Manual drawn up for the project. This campaign for the elimination of radiological islands was accompanied by a gradual reduction in the number of professionally exposed workers, this number being adapted at all times to the radiological status and the requirements for personnel working in radiological areas. HIGH VOLTAGE PYLON DISASSEMBLY WORK From the point of view of Occupational Safety, mention should be made of the constant efforts to identify potential risks and preventive measures. Specifically, throughout decommissioning almost 5,000 potential situations have been studied in 200 different areas of the site, and some 12,000 controls for the prevention of occupational risk have been applied. Also, more than 2,500 revisions of the equipment included in the Fire-Fighting Plan have been performed. The decommissioning of the Vandellós I nuclear power plant has required almost 2,750,000 man/hours overall, with losses as a result of absenteeism amounting to only 0.4 percent. On average, 25 tasks and activities were carried out on the site every day. On completion of the works, the number of incidents recorded amounted to 83, with periods of lost work of between 2 and 46 days. Finally, in the area of Security, during the five years of decommissioning 391,646 personnel entrance/exit movements have been recorded and 43,762 such movements in relation to vehicles. Engineering Another of the pillars supporting ENRESA s activities at Vandellós I has been the company s ability to adapt to the circumstances of the works. In this respect, the site engineering service has undertaken more than a hundred design modifications throughout the project, this having made it possible to comply with the require- p.52

55 SUPPORT ACTIVITIES. CHAPTER4 Prevention of Occupational Risk during the Decommissioning of Vandellós I, a document drawn up by ENRESA on the basis of the Occupational Risk Prevention Act. During the level 2 decommissioning, the plant Communication and Training Service has organized 1,537 courses, attended by some 7,800 people. These courses have included almost 4,000 classroom hours, implying some 21,400 man/hours. As a result, the 2,700 workers involved in the decommissioning have each attended three courses on average. TRAINING COURSE ON SAFETY FOR WORKERS ments imposed by the regulatory body prior to authorising the implementation of the different types of activities carried out during the decommissioning. Quality Assurance All the work performed during the decommissioning has been subjected to a Quality Assurance programme in order to verify application of the procedures and standards in force. The Quality Assurance service has been responsible for controlling and supervising the implementation of this programme during performance of the Decommissioning Plan. It has also undertaken responsibility for the quality records and documentation in the archives, for which it has been divided into the Quality Assurance (inspection and auditing) and Documentation (records and archives) sections. Training The decommissioning of a nuclear power plant implies the performance of complex tasks in both conventional areas and zones having radiological implications. For this reason ENRESA implemented a complete training plan, with a view to providing all the workers with the knowledge necessary to guarantee their safety and ensure strict compliance with the requirements imposed by the standards in force. The Training Plan for the Decommissioning of Vandellós I, which was reviewed annually, applied the directives of the Regulations on Nuclear and Radioactive Facilities, the Regulations on Protection against Ionising Radiations and the Framework Plan for the On-site training has been obligatory both for contractor company workers and for those already having years of experience at the plant. Consequently, one of the pillars of training for decommissioning has been the programming of recycling courses, which have periodically involved workers of all levels of responsibility. By subject areas, Radiological Protection, with 50% of the total hours dedicated to training, has been the discipline that has received most attention, due to the need for highly qualified workers for the performance of complex tasks. If to this is added the 19% of hours dedicated to Occupational Safety, it may be appreciated that more than two thirds of the training delivered during the decommissioning of Vandellós I has been aimed at guaranteeing the safety of the workers. Training by subject areas Radiological Protection Safety Emergency Plan Others p.53

56 CHAPTER 5

57 Projection of decommissioning

58 Communication policy One of ENRESA s main areas of interest in the decommissioning of Vandellós I has related to the establishment of a communication policy that has provided transparent information on the activities carried out throughout the project for different social groups. Thus, the establishment of channels of communication with the institutions, the media and the general public became one of the priority objectives of the project, embodying ENRESA s philosophy regarding relations with the surroundings in those areas in which the company performs its work. VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) At institutional level, ENRESA has promoted freeflowing relationships with local representatives of political parties, public institutions, associations and organizations of different types. In this respect, periodic meetings have been organized with the main public institutions in the area surrounding Vandellós I and visits to the site have been made by autonomous community, governmental and international organizations, lobbies and other groups interested in obtaining information on different aspects of decommissioning. ENRESA has also maintained frequent contacts with the local press from the area immediately surrounding Vandellós I, organizing in collaboration with the Professional Association of Journalists of Tarragona periodic meetings and seminars on the different activities carried out as the decommissioning progressed. Information on the activities carried out at Vandellós I was complemented with the publications issued by ENRESA, containing various news items on the performance of the decommissioning process. In this respect, the magazine WINDOWED POINT FOR VISITORS INSIDE THE REACTOR BUILDING Estratos dedicated a particularly large amount of space to tracking of the works. Estratos is a scientific journal to which highly relevant personalities contribute and which is aimed basically at professionals and members of the public interested in energy-related matters, waste management and the environment. As regards relations between ENRESA and the general public, special mention should be made of the visits organized for the latter. The objective of these visits was to provide the local population with all the necessary information on the activities carried out during the decommissioning of Vandellós I and allow them to gain a first-hand insight into these activities via a complete visit to the different points of interest of the plant. The Visitors ( ) ,862 4,710 5,005 4,500 4,285 24, , TOTAL p.56

59 PROJECTION OF DECOMMISSIONING. CHAPTER5 itinerary followed by these visits had to be varied continuously during the decommissioning process due to the space requirements of the works. On conclusion of the decommissioning, the Information Centre had received 24,398 visitors in 1,159 visits to the site. Almost 80% of these were from educational centres: secondary schools, vocational training centres and universities, the rest having been by official national and international organizations, the media, companies belonging to the sector and other institutions. OPEN DAY FOR THE MEDIA. JUNE 2002 The ENRESA communication policy for Vandellós I foresees the continuation of the Information Centre activities throughout the latency period. Promotion of local employment For ENRESA, promoting local employment has represented a valuable tool for social integration in the area surrounding the Vandellós I nuclear power plant. For this reason, 226 of the 323 workers that participated in the decommissioning, exactly 70%, came from municipal areas close to the plant. Likewise, ENRESA values very positively the high level of experience and specialisation existing in the area, as well as the high degree of adaptability of the local business sector, which has shown itself to be capable of responding to the varying operational requirements of a project as unique as it is the decommissioning of a nuclear power plant. Promotion of local employment Local employment Rest ENRESA PROMOTED LOCAL EMPLOYMENT DURING THE PROJECT p.57

60 Projection overseas VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) The decommissioning of the Vandellós I nuclear power plant was an unprecedented undertaking in Spain, with very few references at international level, this implying major engineering efforts prior to the initiation of the work. The decommissioning of the Andújar Uranium Mill in Jaén and of other experimental and radioactive facilities, and now of the Vandellós I nuclear power plant, clearly demonstrate that ENRESA has the resources required to undertake whatever other decommissioning projects might be commissioned to it by the Government. In this respect, ENRESA has signed with the electricity utilities an agreement regulating the process of transfer of ownership of the facilities that will be decommissioned in the future. INTERNATIONAL SEMINAR ON DECOMMISSIONING STRATE- GIES, ORGANIZED BY THE NUCLEAR ENERGY AGENCY (ORGANI- ZATION FROM OECD) IN TARRAGONA. SEPTEMBER 2003 The experience acquired at Vandellós I also opens up the possibility of establishing a new line of business for the companies and professionals that have participated in the different areas of the decommissioning, since several countries have plant similar to Vandellós I currently pending dismantling. As a result, throughout the works experts from some of these countries have visited the plant to gain first-hand insight into the project. Consequently, the decommissioning of the Vandellós I nuclear power plant has allowed ENRE- SA to develop exportable technology. Its organizational and operational aspects might be applied in the future to decommissioning projects in Spain and abroad. p.58

61 PROJECTION OF DECOMMISSIONING. CHAPTER5 Main organizations that have visited Vandellós I during decommissioning: International Atomic Energy Agency (IAEA) EURATOM European Reconstruction Bank 33rd Meeting of the Technical Advisor Group cooperative programme on decommissioning (TAG33) European Union European Commission European Parliament Nuclear Energy Agency (NEA) Argentina CNEA (National Atomic Energy Commission) Canada Delegation of the ITER candidature South Korea Fusion Department of the Ministry of Science China CAEA Delegation France Commission of Graphite-Gas NPP managers (UNGG) Electricité de France (EDF) National Assessment Commission Slovakia Ministry of Industry USA Industry undersecretary Italy SOGIN (Nuclear Energy Management Society) Japan RANDEC delegation Delegation from Japan Atomic Power Company Director of the Fusion Department Ministry of Science and Technology Lithuania Ministry of Industry Great Britain BNFL UKEA Restoring our environment Ukraine Delegation from NRA Sweden Swedish Nuclear Fuel and Waste Management Co. (SKB) VISIT OF THE INDUSTRY UNDERSECRETARY OF THE USA. AUGUST, 2003 p.59

62 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) International collaboration EThe Vandellós I project has been a pioneer experience in Spain as regards the decommissioning of nuclear facilities, and, to a large extent, is a first also at international level, where most of the references existing to date have been projects on a smaller scale, either because the reactors dismantled have been of lower power or because the project objectives have been more limited. There are 39 graphite-gas reactor nuclear power plants (similar to Vandellós I) in the world, distributed between France (8), Great Britain (28), Spain (1), Italy (1) and Japan (1). Sixteen of these groups are currently in the decommissioning process. VISIT BY THE JAPANESE MINISTER OF INDUSTRY Likewise, in the field of research, the European Union s Fifth Framework Research and Development Programme on nuclear fission identified as one of its priorities the development of best practices and the maintenance and updating of databases on the decommissioning of nuclear facilities. ENRESA is participating in two specific projects in this area: TND (Thematic network on decommissioning) and CDD (Compendium on dismantling and decommissioning). PRESENTATION OF THE DECOMMISSION- ING PROJECT TO A GROUP OF INTERNA- TIONAL EXPERTS. MEETING HALL PRE- PARED IN THE REACTOR VAULT There are very few international references for this type of projects and it is quite clear that in the short to medium term it will be necessary to address programmes of this nature. Consequently, the European Commission is promoting active debate with a view to harmonising practices and regulations in the member countries from a common standards approach. Furthermore, the European Union promotes and finances technical assistance projects both within the Union and for advice to its future members. It is worth highlighting the launching of projects related to the decommissioning of the nuclear power plants of Ignalina (Lithuania), Bohunice (Slovak Republic) and Kozloduy (Bulgaria), which are financed through three specific funds managed by the European Bank for Reconstruction and Development (EBRD). ENRESA has been involved in some technical assistance projects launched by the European Union as well as following the projects approved to be financed through the mentioned funds, and advising the Ministry of Economy. Finally, in the area of bilateral agreements, ENRE- SA communicates and cooperates closely with the organizations responsible for this activity in Italy and Argentina (SOGIN and CNEA, respectively). p.60

63 PROJECTION OF DECOMMISSIONING. CHAPTER5 Perceptions in society A model of integration From the very beginning the decommissioning of the Vandellós I nuclear power plant was a challenge in many ways. In addition to the fact that this was a unique project in our country was the uncertainty generated by the closing of a plant that for many years had been one of the economic pillars of our municipal area. In view of the above, the Town Council of Vandellòs i l Hospitalet de l Infant began to explore ways of collaborating with ENRESA, this leading to the Municipal Tracking Commission, an organization for control and information on the works performed at Vandellós I that with time was to become a clear sample of the transparent policy adopted by ENRESA and a model of integration into the surroundings. JOSEP CASTELLNOU MAYOR OF VANDELLÒS I L HOSPITALET DE L INFANT Mention should be made also of the establishment of agreements aimed at promoting local employment throughout the decommissioning works, this undoubtedly being a key factor in our strategy of minimising the economic and labourrelated impact of closure of the plant. In this respect, the five years that it has taken to decommission Vandellós I have provided the time that we required to open up new routes for diversification in the local economy without the need to confront high unemployment rates. On behalf of the Town Council of Vandellòs i l Hospitalet de l Infant, it remains only for me to express my satisfaction at the success that has been achieved in a framework of collaboration that should serve as a model for future projects. I should also like to dedicate my closing words to the Mestral Technology Centre, an initiative that looks to the future and that will undoubtedly be an important asset for the municipal area. p.61

64 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Collaboration for the benefit of all For the Rovira i Virgili University, the decommissioning of the Vandellós I nuclear power plant has been an important focus of attention, both for its transcendence and for the value that it has implied in terms of education. Aware of this, ENRESA and the URV established an open relationship from the very beginning of the decommissioning process, this having benefited both organizations and, by extension, the society that they both serve. In this respect, the level of collaboration achieved in entities such as the Tracking Commission of this unique project has constituted a valuable experience for our teaching staff and research workers. Likewise, ENRESA s participation in the summer course on Waste Management, one of the best attended of all the courses we offer, represented a valuable educational bonus for our students. The decommissioning of Vandellós I having now been completed, ENRESA is initiating the development of the Mestral Technology Centre, an R&D programme in which the URV is keenly involved. LLUÍS AROLA I FERRER DEAN OF THE ROVIRA I VIRGILI UNIVERSITY Our research groups are already working with ENRESA in the performance of projects that will undoubtedly serve to perfect future decommissioning projects and train the professionals of the future in this emerging sector. The Rovira i Virgili University would like to reiterate its thanks to ENRESA and assure the company of its willingness to move forward within a framework of collaboration that benefits all. Great educational interest Being, as I am, profoundly grateful to ENRESA for the opportunity provided, I should like to evaluate our experience of the various visits we have made to the Vandellós I nuclear power plant decommissioning works. It might be interesting to look back to when we first received the invitation to visit the Vandellós I nuclear power plant installations, then in the decommissioning phase, with our students. At that time I though that it might be interesting for the students, and that is how our relation with ENRESA began. I JOAQUIM MUÑOZ PUIG PROFESOR DEL I.B. MERCÈ RODOREDA Since that time we have been coming to the plant with our secondary school pupils, since we consider that the visit has been a valuable way of complementing their education. During the early years there was also the excitement of encountering a plant that changed considerably from one year to the next, as the project unfolded. should like to express my thanks, personally and on behalf of the school that I represent, for the quality of the explanations provided, which were didactically of great value, and for the warm welcome that we have always been given. To this should be added the interest of the workshops that are now being offered, which make the visit even more complete, attractive and valuable. p.62

65 PROJECTION OF DECOMMISSIONING. CHAPTER5 Teamwork Al though the relationship between the Baix Camp region and the nuclear sector is now a longstanding one, having started with the construction of the plants at Vandellós i l Hospitalet de l Infant, the collaboration that was established with ENRESA as a result of the decommissioning of Vandellós I has been particularly fruitful and enriching for both the Regional Council that I represent and for all the town councils of the Baix Camp. The teamwork that has taken place and the different collaboration projects performed have allowed us to achieve the objectives mapped out and to get to know each other a lot better. They have also helped us to open up routes for cooperation in the future, which I am convinced will reinforce the good level of mutual understanding already reached. In short, from the Regional Council of the Baix Camp it remains only to express our sincerest satisfaction at the milestones achieved. These have improved services and the standard of living of ROBERT ORTIGA I SALVADÓ PRESIDENT OF THE REGIONAL COUNCIL OF THE BAIX CAMP the people of the Baix Camp, which is after all the common objective and the factor driving the excellent collaboration that exists with ENRESA. For all these reasons, I should like to express our profoundest thanks to ENRESA for the extraordinary human and professional quality that characterizes the company and that has taught us so much. Enresa paved the way The initiation of ENRESA s activities at Vandellós began following the shutdown of the nuclear power plant in the wake of the accident that occurred on 19th October ENRESA arrived to undertake the management of an issue that had a place reserved for it on the front page of all the newspapers and in the news, as a result of which it was quite clear that all movements made by this public company practically unknown by the general public would be examined under the looking glass. The scenario of this new activity by ENRESA required a policy of communications taking into account the avid demand for information that would come from the media. Decommissioning a nuclear power plant was something new in the country, and there would be a need for a great deal of didactic information to explain what the project was all about. ENRESA opted for a policy of transparency based on collaboration with the media, and especially with the professionals working for the media, through the Professional Association of Journalists of Catalonia and its Tarragona division, tired of feeling itself to be the victim of mistrust in all matters relating to contact with nuclear sector FRANCESC DOMÈNECH PRESIDENT OF THE TARRAGONA DIVISION OF THE PROFESSIONAL ASSOCIATION OF JOURNALISTS OF CATALONIA sources. The ease with which the journalists were able to access those responsible for the project and the organization of periodic meetings to report on the progress made at Vandellós generated an open relationship between the two groups, this facilitating the relations between the technical staff and the journalists, i.e. between ENRESA and the society that it serves. This is an example that has subsequently been followed by others in the nuclear industry. ENRESA paved the way at Vandellós I. p.63

66 CHAPTER 6

67 Mestral Technology Centre

68 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) New site, new activities The reduction in the dimensions of the plant managed by ENRESA as a result of entry into the latency phase also implies a minimum management infrastructure. However, the presence of ENRESA is not limited to maintenance tasks. During the latency phase the site of the former Vandellós I nuclear power plant constitutes a privileged location for the performance of research programmes and for the training of those who will be responsible for nuclear power plant decommissioning projects in the future. In this respect, ENRESA has signed a collaboration agreement with the Rovira i Virgili University in relation to the new research and development centre that is to work on technologies relating to the decommissioning of nuclear power plants. Consequently, the Mestral Technology Centre is a specific programme within the framework of the ENRESA R&D Plan that should lead to the development and fine tuning of technologies for the level 3 decommissioning of Vandellós I and of other nuclear power plants. The activities to be carried out by the Mestral Technology Centre rest on three basic pillars: management of the period of latency of Vandellós I, research into technologies, materials and procedures for future decommissioning projects and the training of qualified professionals for the performance of such projects. basis for know-how applicable to future decommissioning projects at national and international level. Some of the lines of research that are expected to be implemented at this technology centre are detailed below: Long-term performance/durability of the reactor box and internals. With a view to supervising the confinement of the reactor box, its structural stability will be monitored, the ageing of the concrete and reinforcing elements will be analysed and the evolution and degree of corrosion of the internal materials will be controlled. Radiological characterization of internal materials and components of the reactor. The objective of this line of research is to develop remote manipulators allowing samples to be taken from inside the reactor box for subsequent radiological characterization. Reactor box and internals dismantling technologies (level 3). This involves the comparative analysis of different strategies and methodologies for the level 3 decommissioning of the reactor box, in order to optimize costs and radiologi- 1. Management of the latency period In parallel with the R&D activities, ENRESA carried out tasks relating to the management of the latency period for the reactor of the former Vandellós I nuclear power plant. This is a period of passive latency, which implies minimum maintenance and surveillance of parameters that will evolve very slowly. Specifically, there will be continuous control of the temperature, humidity and pressure inside the reactor, while every five years a leak test will be performed to check the confinement of the box and a visual inspection to determine the possible corrosion of the reactor box internals. 2. Research into technologies, materials and procedures for future decommissioning projects The objective of the R&D activities foreseen for the Mestral Technology Centre is to serve as a SURVEILLANCE POINT FOR THE REACTOR VESSEL p.66

69 MESTRAL TECHNOLOGY CENTRE. CHAPTER6 cal impact, and the study of cutting and decontamination techniques. Waste management. This line includes tracking of the activities performed at international level and, in addition, the performance of a study on possible solutions for the treatment, conditioning and definitive disposal of high radioactive wastes. 3. Training of future professionals The third pillar of the Mestral Technology Centre is based on ENRESA s interest in training the professionals who will lead future decommissioning projects. Likewise, the centre aims to become a means of transmitting know-how to national and international scientific groups, with a view to gradually perfecting nuclear power plant decommissioning projects, according to the available advances of the technology. Technologies for the recovery of contaminated soils and their free use in the future. This line focuses on analysis of the processes of radionuclide transport in contaminated soils for the performance of the most adequate recovery actions. Data management. Establishment of databases including Enresa s experience of dismanling technologies, wastes, radiological impact and associated costs. Environment. Study of the environmental burden of decommissioning, integrated in general environmental burden projects relating to different energy sources. Mestral TC Objectives 1. To serve as a forum for the sharing of experiences with organizations involved in similar projects. 2. To serve as a platform for joint developments with other organizations. 3. To undertake research activities in relation to the structures remaining during the latency period. 4. To prepare the developments required for the level 3 decommissioning of Vandellós I. 5. To fine tune techniques relating to the decommissioning of nuclear facilities and associated activities. 6. To develop techniques for the decontamination of soils and structures. VISUAL INSPECTION OF THE REACTOR VESSEL S INTERNALS 7. Training on decommissioning and waste management issues. p.67

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71 Summary

72 VANDELLOS I NUCLEAR POWER PLANT DECOMMISSIONING REPORT ( ) Project milestones June 1991 Definition of the alternatives for the decommissioning of Vandellós I. Action proposals November 1992 May 1994 September 1996 September 1997 January 1998 February 1998 March 1998 March 1999 April 1999 April 2000 August 2000 October 2000 December 2000 June 2001 June 2001 December 2001 February 2002 July 2002 October 2002 June 2003 Acceptance of the alternative by the Ministry of Industry and Energy, following a favourable report from the Nuclear Safety Council. Resolution of the Directorate General for Energy on 11/27/92 Submittal of the Decommissioning Plan for Vandellós I nuclear power plant Submittal of the Environmental Impact Study Environmental Impact Statement. Resolution of the Directorate General for Environmental Quality and Assessment on 9/22/97 Approval of the Decommissioning Plan. Ministerial Order of 1/28/98 Transfer of ownership of the plant Initiation of the preparatory phase CSN authorisation for the dismantling of active parts Initiation of dismantling works in active areas Plugging and sealing of the reactor box First dispatch of radioactive wastes from decommissioning to the El Cabril Disposal Facility Completion of the Test Plan for the materials declassification process Initiation of implementation of infrastructures for the latency period Completion of construction of the new structure to protect the reactor box against the elements CSN approval of the materials declassification methodology and initiation of declassified materials dispatches to recycling plants Submittal to the CSN of the restoration plan for the released site and of the necessary documentation for the latency period CSN approval of the surfaces declassification methodology CSN approval of the combined declassification methodology and initiation of dispatches of declassified materials from the structure of the former reactor building Completion of disassembly of the external structure of the former reactor building End of Level 2 decommissioning of the former Vandellós I nuclear power plant p.70

73 SUMMARY Figures of the decommissioning General Information Radiological Protection and Safety 2,700 people having collaborated on the project 323 average workers 226 average local workers (70%) Maximum of 420 workers 63 companies involved 30 average companies 2,750,000 working hours 25 average daily works 854 work permit requests (SAT s) Execution period: 63 months Final decommissioning cost: 94.6 M Project s estimated collective dose: msv.p Final collective dose: msv.p 4,970 studies of potencially dangerous situations in 200 site areas 12,000 controls of working risks prevention 2,500 revisions of equipment belonging to the Fire Prevention Plan 0 accidents 83 incidents with periods of lost work between 2 and 46 days 0,4% of working days losts because of sick leaves 0 accidents Materials Management 7,894,825 kg. of conventional materials sent to recycling plants 8,012,040 kg. of declassified materials sent to recycling plants Total recycled materials: 15,906,865 kg. 77,000,000 kg. conventional concrete rubble reused for the site restoration 1,961,835 kg. declassified concrete rubble reused for the site restoration Total concrete rubble reused for the site restoration: 78,961,835 kg. 1,763,722 kg. low and intermediate radioactive wastes sent in 188 transports to El Cabril Disposal Facility Training 1,537 training courses 7,834 people (three average courses per worker) 3,955 classroom hours 21,394 person-hours Communication 1,159 visits 24,398 visitors (1,171 institutional viisitors in 115 visits) 12 meetings with local media 726 press appearences p.71

74

75 Acronyms

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77 ACRONYMS. ALARA As Low As Reasonable Achievable BERD The European Bank for Reconstruction and Development BNFL British Nuclear Fuels CMD Measuring and Declassification Container CMT Metallic Transport Container CNEA National Comission of Nuclear Energy (Argentina) CSN Nuclear Safety Council (Spain) DGMA Environmental General Direction (Spain) DP Decommissioning Plan DPM Main Maintenance Device EDF Electricity of France (Electricité de France) EURATOM European Atomic Energy Community HIFRENSA Spanish-French Nuclear Energy Company (Spain) IAEA International Atomic Energy Agency ITER International Thermonuclear Experimental Reactor JNC Japan Nuclear Cycle Development Institute (Japan) LIWL Low and Intermediate Level Waste MIE Ministry of Industry and Energy (Spain) NEA Nuclear Energy Agency NRA Nuclear Regulatory Authority (Ukraine) PDCC Conventional Components Decommissioning Plan PDPA Active Parts Decommissioning Plan RANDEC Radioactive Waste Management and Nuclear Facility Decommissioning Technology Center (Japan) SAT Work Permit Request SKB Swedish Nuclear Fuel and Waste Management Company (Sweden) SOGIN NPP Management Company (Italy) UKAEA The United Kingdom Atomic Energy Authority (UK) UMA Unit of Authorised Management UNGG Natural Uranium Grafite-Gas p.75

78 December º edition Published by: Empresa Nacional de Residuos Radiactivos, S. A. (Enresa) Development and coordination: Enresa / Iniciatives Mediterrànies de Comunicació (IMC) Photography and illustration: Enresa s files, HIFRENSA s files. Design, typesetting and production: IMC Printed by: Unigràfic Legal Deposit: B For further information, contact: Information Supports Department C/ Emilio Vargas, MADRID Ctra. Nacional 340, km 1123, Vandellòs i l Hospitalet de l Infant TARRAGONA

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