REPORT ON THE DECOMMISSIONING OF THE JOSÉ CABRERA NPP

Transcription

1 2010 REPORT ON THE DECOMMISSIONING OF THE JOSÉ CABRERA NPP performed Activities

2 ISSUED BY Empresa Nacional de Residuos Radiactivos S.A. C/ Emilio Vargas 7, Madrid. Text and graphic editing Training and Communication Service of the José Cabrera NPP. Design and publishing Manager of the Office of the Chairman, Institutional Relations and Information Media. Legal deposit M Printing Addicta.

3 CONTENTS 6 PRESENTATION 5 DECONTAMINATION AND CHARACTERIZATION 56 8 INTRODUCTION 6 UPCOMING ACTIVITIES AN INDUSTRIAL PROCESS 7 MATERIALS MANAGEMENT BACKGROUND 1 8 SAFETY CULTURE / QUALITY ASSURANCE PREPARATORY ACTIVITIES ( ) 2 9 COMPLEMENTARY POLICIES DECOMMISSIONING OF CONVENTIONAL ELEMENTS 3 MILESTONES OF THE DECOMMISSIONING PROJECT RADIOLOGICAL DISMANTLING 4 KEY FIGURES

4 PRESENTATION This report sets out the main activities completed over the first six years of the decommissioning of the José Cabrera NPP. This was the first NPP to enter into operation in Spain and will also be the first one to be completely dismantled. The plant is located in the municipality of Almonacid de Zorita (Guadalajara). It started operating in 1968 and ended 38 years later, on 30th April Enresa became the license of the facility NPP in 2010, and the site will be resturned to Gas Natural Fenosa at the end of the dismantling process. Enresa is in charge of the safe management of the radwaste and of the restoration of the sites where nuclear and uranium mining activities have taken place. We are therefore responsible for returning the site that is still occupied by the NPP commonly known as Zorita to its original state. To do this, we have implemented groundbreaking techniques that have aroused the interest of experts in this field, both within Spain and abroad. The large number of visits to the decommissioning site, mostly by international experts, bear witness to this interest. The work performed includes the segmentation of the reactor internals. This is a singular operation that was performed underwater and in a completely automated way, using the same mechanical saws that were used to cut the vessel. The dismantling operation shall yield a total of 104,000 tons of material that will need to be managed, although most of these materials will be conventional waste. Nevertheless, the site will be completely cleared only after the low and medium level waste will be transported to the disposal center in El Cabril, in Córdoba. Spent fuel, as well as reactor internals, will also need to be transferred to the Centralised Temporary Storage (CTS) facility in Villar de Cañas (Cuenca). This waste is already isolated in four containers in the Independent Spent Fuel Storage Installation (ISFSI) next to the plant. This decommissioning process will only be possible by applying the know-how gained during the partial dismantling of the Vandellós I NPP and during environmental restoration projects such as the decommissioning of the Andújar uranium milling plant. These interventions have allowed us to develop methods and improve processes that have placed us at the forefront in this field on an international scale. This report serves to show just that. View of the José Cabrera NPP 6 7

5 INTRODUCTION Initial status (1989) The dismantling of the José Cabrera NPP (also known as Zorita NPP) is an almost unprecedented international technological milestone. It is the first Spanish facility of its type to be completely dismantled, and it will allow the site on which it is built to return to its original form. This goal inevitably requires all the components of the primary circuit, including the plant reactor, to be segmented and a large part of the resulting materials to be placed in special containers. These significant activities are the real differentiating factor of this project. Andújar Uranium Milling Plant Final status (1994) Enresa, in its role as public agency in charge of this task, is tackling this challenge with the maturity and expertise gained during the decommissioning of the Andújar uranium milling plant and the dismantling of the Vandellós I NPP and of several other CIEMAT nuclear facilities, including an experimental reactor and a fuel reprocessing pilot plant. These projects have allowed Enresa to develop and consolidate dismantling methods and technology in Spain. Final status (2003) Initial status (1998) Over the coming chapters, this report provides a mostly graphical and visual description of the decommissioning works developed by Enresa in the José Cabrera NPP between 2010 and Vandellós I 8 9

6 Enresa views decommissioning projects as industrial processes that aim to restorate the site entirely and to manage the resulting materials adequately. These processes start with the initial characterisation and preparation of the inventory of systems and components within the facility. They also involve the modification of many plant systems and infrastructures, which are adapted to new functions during the project. They are followed by the disassembling, decontamination and demolition works, the true core of the dismantling process, and finally, by the site restoration. AN INDUSTRIAL PROCESS At the same time, the resulting materials are managed in an integrated approach, in accordance with their origin and nature. This is the first complete dismantling of a nuclear power plant in Spain 2010 Transfer authorisation Characterisation 1 3 Dismantling 2 Modifications Initial status of the José Cabrera NPP (2010) Final status projected of the José Cabrera NPP MATERIALS MANAGEMENT Demolition 4 5 Restoration 2018 Statement of closure 10 11

7 BACKGROUND 1 (1968) Construction of the José Cabrera nuclear power plant, located in the municipality of Almonacid de Zorita, in Guadalajara, started in Its inauguration was held on 12 th December Construction José Cabrera NPP (1965) The plant had a pressurised light water reactor that produces an electrical power output of 160 MWe. It was one of the biggest technological challenges of its time because it was the first nuclear power plant that entered operation in Spain. On 14th October 2002, the Ministry of the Economy, after receiving a preliminary report from the Spanish Nuclear Safety Council, allowed the last renewal of the operating licence, until its definitive shutdown on 30 th April LIFE CYCLE OF THE FACILITY TRANSFER OF RESPONSIBILITY 2018 CONSTRUCTION OPERATION TRANSITION POST-OPERATION ACTIVITIES EXECUTION OF THE DISMANTLING RETURN OF THE SITE KEY DISMANTLING PLAN RESPONSIBILITY OF ENRESA RESPONSIBILITY OF THE OWNER 12 13

8 Post-operational activities ( ) Once the plant was shut down, a series of preliminary activities were performed, as required to start the dismantling. Twelve steel and concrete casks are placed vertically in the ISFSI. These containers hold 377 fuel elements in total. One of the first actions, which was indispensable to tackle the dismantling, was the removal of the spent nuclear fuel from the plant pool to a dry storage area: the Independent Spent Fuel Storage Installation (ISFSI). Independent Spent Fuel Storage Installation (ISFSI) During this initial stage, Enresa completed the planning, engineering and licensing activities required to obtain the authorisation to start the dismantling of the José Cabrera NPP. Transfer operation of spent fuel to the ISFSI Fuel loading 14 15

9 2 PREPARATORY ACTIVITIES ( ) Adaptation of the Water Intake and Mechanical Systems Tag-Out* Cooling towers equipment Before the dismantling operations start, many plant systems, equipment and infrastructures need to be adapted so as to resize them, avoid hazards and interferences and adapt their functionality to the new activities to be performed at the plant. Electrical Modifications Adaptation of the cooling tower electrical building Installation of the general service pump * TAG-OUT Activities such as the draining of fluids, the elimination of hazardous substances, the reduction of fire loads or the disconnection from the power of the various equipment and systems to be dismantled, for the purpose of working in complete safety

10 Strengthening of the Fire Protection Modifications of the Ventilation Systems System Adaptation of the ventilation systems Main fire protection pump FP facilities Installation of the new VA-90N fan 18 19

11 Official test Adaptation of Auxiliary Facilities Official Tests All the systems and processes related to waste management and radiological protection are required to pass an official test process that is assessed by the regulatory body. Refurbishment of the Turbine Building as the Decommissioning Auxiliary Building (DAB) The turbine building housed the turbine generator unit and the auxiliary equipment needed to produce electrical power. The turbine and its auxiliary systems were dismantled, and the building was converted into a Decommissioning Auxiliary Building (DAB). The purpose of the DAB is to condition the radwaste that is arisen from the containment building and that goes along the transference tunnel linking both enclosures. To do this, it is fitted with a decontamination workshop, facilities for radwaste conditioning and areas to store containers temporarily, before they are shipped to the low and medium level disposal centre in El Cabril. Construction of the Decommissioning Auxiliary Building (DAB) Dismantling of the condenser Dismantling of the turbine generator unit Transference tunnel 20 21

12 Initial status of the operations plant, Turbine Building Waste storage area II Upgrades in the Radwaste Storage Areas In order to optimise the management of the waste to be treated during the dismantling operations, existing waste storage areas I, II and III, as well as the clearance area, have been adapted. They have been used to install the Box Counter, a key equipment for the material segregation process. Clearance area Final status of the Decommissioning Auxiliary Building (DAB) 22 23

13 The first elements dismantled were the systems and equipment with no radiological implications that were of no use for the dismantling process. 3 DISMANTLING OF CONVENTIONAL ELEMENTS Initial status (May 2010) Diesel Generator Building Dismantling of components of the diesel generator building Demolition of the Cooling Towers Demolition of the cooling towers Final status (June 2010) storage area for conventional scrap Diesel generator building converted into a support storage area 24 25

14 Disassembling of the Control Room Dismantling of Transformers Dismantling of the main transformer Final status Storage of scrap from the control room Control room 26 27

15 RADIOLOGICAL DISMANTLING 4 Removal of fuel rack from the pool Preparatory activities The dismantling of the primary circuit components (reactor internals, vessel, steam generator, main pump, pressuriser, etc) is one of the activities that sets this project apart from previous ones and makes the complete dismantling of the facility possible. The preparatory activities prior to the removal of the reactor internals were performed throughout These activities involved the removal of various pieces that remained within the spent fuel pool and the partial cutting of the wall separating it from the refuelling cavity. The flood areas were then cleaned and made leak tight to allow the underwater segmentation of the internals and the reactor vessel. Head of the reactor vessel New floor slab of the reactor cavity and open wall between cavities Removal of wall blocks between the pool and cavity 28 29

16 Segmentation and conditioning of the reactor internals A total of 432 pieces were generated during these segmentation operations, with a complete weight of 59.5 tons and a total of 418 linear metres The segmentation of the Zorita reactor internals was performed underwater, within the cavity obtained by joining the spent fuel pool and the reactor cavity, with mechanical cutting tools under remote operation with the support of an underwater TV camera system. Cutting of the lower internal element The cutting of the upper internal elements started in May Its purpose was basically to facilitate the entry of the control rods into the reactor core. The segmentation of the lower internal elements was then tackled. This area had the highest level of radioactivity because it housed the fuel needed to complete the nuclear reaction. The purpose of this component was to attach the fuel elements to the inside of the reactor, act as shielding and allow the circulation of the water in the primary circuit. The segmentation was performed underwater with mechanical cutting tools under remote operation Underwater segmentation of the reactor internals 30 31

17 The segmentation of the reactor internals has been completed underwater with the support of TV cameras Basket loaded with pieces obtained from the segmentation General view of the spent fuel pool cavity during the segmentation of the lower internal element 32 33

18 Conditioning of Waste Lowering of the shielding bell to transfer the waste from the reactor to the DAB for their subsequent conditioning Once the segmentation is completed, the resulting pieces of Zorita reactor internals need to be conditioned. That is where the Decommissioning Auxiliary Building (DAB) comes in. Part of the waste, inside a metallic basket after the underwater segmentation, is removed from the containment building by means of a shielding bell and transferred to the ADB. It is then immobilised with mortar within a concrete container known as Disposal Unit (DU). DAB control room, to supervise the conditioning operations Positioning of the basket with waste in the centering structure 34 35

19 Operation of the Decommissioning Auxiliary Building (DAB) The waste produced in the reactor building is conditioned in the DAB Trasfer of the basket inside the container 3 Temporary waste storage area in the DAB 5 The shielding bell handles the basket with the waste for transference to the DAB The basket with the waste reaches the DAB through the transfer tunnel Injection of mortar to immobilise the waste Dispatch of the Disposal Unit to El Cabril

20 Conditioning of Special Waste Part of the lower internal elements (which were closest to the reactor) have been conditioned in four special HI-SAFE casks and stored in the ISFSI (Independent Spent Fuel Storage Installation) of the site. These pieces, weighing a total of 40 tons, are of a higher level than those contemplated in the acceptance criteria of the low and intermediate level waste disposal facility operated by Enresa in El Cabril (Córdoba), so they need to be temporarily stored in the ISFSI, next to the casks holding the spent fuel. Loading of the special reactor waste Transfer of the HI- SAFE cask with special waste to the site ISFSI 38 39

21 Dismantling of large components Pipes of the Primary Circuit The activities for the dismantling of large elements of the primary circuit started in Pipes of the primary circuit Main pump Pressurizer Steam generator The first step involved removing the thermal insulation from all these elements before segmenting them. In order to complete the segmentation of the internal elements in parallel with the dismantling of the rest of the elements of the primary circuit, the vessel needed to be isolated beforehand, by cutting and blocking the pipes. Images of the cutting of the intermediate branch by means of an orbital lathe Model of the primary circuit of the José Cabrera NPP 40 41

22 Dismantling of the Main Pump Dismantling and removal of a piece of the main pump body The purpose of the main pump was to channel the water that flowed through the primary circuit, allowing the cooling of the reactor and the heat transfer in the steam generator. The different parts of the pump were dismantled once the auxiliary pump elements were removed. The pieces were cut either with thermal systems or with diamond wire, depending on the physical-radiological characteristics of each of them. Cutting of components of the Main Pump with diamond wire Initial status and removal of the main pump components 42 43

23 Pressurizer The purpose of the pressurizer was to maintain adequate pressure within the primary circuit, so as to ensure that the cooling water remained in a liquid state. The cutting workshop was installed in a confined room fitted with independent ventilation systems, so it was possible to use thermal cutting techniques, which are faster. The pressurizer was cut horizontally into three large pieces in its original in situ position. These segments were transferred to the cutting workshop, where they were cut into smaller pieces and placed in containers. Dismantling of auxiliary Pressuriser elements In situ cutting of pieces with diamond wire 44 45

24 Sequence of the Dismantling of the Pressurizer Transfer of a segment of the pressurizer (1, 2, 3) Cutting of a segment in the cutting area (6, 7) Transfer to the cutting area (4, 5) Loading of the piece into a container (8)

25 Steam Generator Dismantling of the bottom part of the Steam Generator The purpose of this component was to create the steam required to move the turbine generator, which produced the electrical power. The steam generator was so large that it needed to be segmented into several pieces. The secondary circuit was cut with thermal cutting techniques, whereas diamond wire was used for the primary circuit. Cutting of the top part of the Steam Generator Tube bundle 48 49

26 Disassembling of other systems and components Radiological dismantling Segmentation of the Reactor Vessel Equipment and systems of various areas within the Containment and Auxiliary Buildings were dismantled in parallel with the dismantling of the large components of the primary circuit. This was another significant dismantling action because these components accounted for 90% of the radwaste of the whole process. Extraction and transfer of Reactor Vessel Once segmentation and conditioning of the internal components of the reactor were performed, the segmentation of the vessel was the next goal of the dismantling project. For this purpose, the vessel had to first be extracted from its original cavity and transferred to the annex pool in which spent fuel was stored during the operational period. The reactor vessel has been segmented into 112 pieces The vessel was made of carbon steel and had an approximate weight of 100 tons. To conduct these extraction and transfer tasks, a series of activities must first be carried out to ensure that the operation was properly executed. In this way, the vessel was released from all connections that keep it joined to the rest of the primary circuit, either through piping or through instrument connections. Furthermore, due to its weight, a complementary hydraulic lift structure was installed to enable the lifting of this component and its transfer to the fuel pool. The underwater vessel segmentation was conducted in accordance to a similar technique that was employed with internal reactor components. After ten months of operations, a total of 172 lineal metres of cuttings were made. 112 pieces were obtained and conditioned in 15 concrete containers to be shipped to El Cabril low and intermediate level radioactive waste disposal facility (Cordoba). Picture of the underwater reactor vessel segmentation 50 51

27 Removal of the vessel from the reactor cavity Transfer of the vessel through the open wall between cavities Placement of the vessel on a support structure located in the spent fuel pool Reactor vessel segmentation beginning. Cutting of a hexagonal piece from the lower part with a short cut 52 53

28 Images of the segmentation tasks underwater reactor vessel. A few pieces obtained from within the basket can be discerned for their later transfer to the Decommissioning Auxiliary Building 54 55

29 DECONTAMINATION OF BUILDINGS AND CHARACTERIZATION OF THE SITE 5 Image of the reactor cavity and spent fuel pool after their drainage and removal of some structures Once the different equipment and systems have been removed from the buildings, the dismantling project enters into a new phase. This is the time to carry out the decontamination tasks of different radiological buildings. To that end, blocks of concrete are cut and S removed from the walls of the refueling cavity and the old spent fuel pool, as well as the reactor s biological shielding. These blocks are taken to the outside radwaste stores where they are subsequently conditioned. Furthermore, alongside these tasks are the decontamination tasks that apply to the surfaces (walls and floors) of the Auxiliary Building and the Containment Building; these are carried out through mechanical means. 6 wall blocks W 9 wall blocks 9 wall blocks E N 9 wall blocks 6 wall blocks 9 wall blocks 9 wall blocks 9 wall blocks 9 wall blocks 9 wall blocks 9 wall blocks 3D model of the reactor cavity and spent fuel pool concrete segmentation and removal 56 57

30 Removal of one of the concrete blocks from the wall separating the cavities Extraction of one of the concrete blocks from the reactor cavity wall Panorama of the reactor cavity while the structures are being cut out of the concrete Management of one of the concrete blocks taken out of the cavities (above) Decontamination of surfaces 58 59

31 Site characterization In this phase of the project, site characterization campaigns are also developed, with the completion of surface measurements in certain structures as well as in-depth surveys in different parts of the terrain, in order to know their radiological situation. Bore hole execution (above); Containment Building Surveys (right); Discharge Channel Surveys (bellow) Stack characterization 60 61

32 UPCOMING ACTIVITIES 6 ( ) The decontamination and later surface declassification tasks (certifying absolutely no contamination) will continue throughout the next years. Buildings that are empty and entirely free of any radiological traces will be demolished and sent to on-site treatment of the resulting debris. Finally, a Restoration Plan will bring the site back to its original status. It will be at that time, once the Declaration of Closure has been duly obtained by the Nuclear Safety Council, when Enresa will return the site to its owner, Gas Natural Fenosa

33 MANAGEMENT OF MATERIALS The management of materials is one of the key activities of dismantling projects. Its purpose is to optimise the volume of waste to be managed and to encourage reuse and recycling policies. 1 2 Operational history data Radiometric studies 7 The logical sequence for the treatment of the material resulting from the dismantling activities is set out in the following table, which highlights the five most important points of the process control. Conventional areas Conventional component DP* The low and intermediate level radwaste is being transported to the El Cabril disposal facility, located in Sierra Albarrana (Córdoba). In turn, the releasable material underwent a clearance process to certify the absence of contamination. Conventional waste is being transported to the corresponding recycling plants and landfills. In situ radiological control of materials A total of 104,000 tons of materials are projected to be managed throughout the José Cabrera NPP dismantling project. Only 4% of these will be radwaste Active areas Active area DP* Preparation of containers Conditioning and preparation for transport Radwaste 3 In situ radiological control NO 4 Clean Clearance YES Preparation of handling units Exit gantries 5 Transport El Cabril disposal KEY DP* = Decommissionig Plan Destination points (administrative control) 64 65

34 Destination of the various materials Final state 104,000 tons 95,300 t Rubble and conventional debris Spent fuel and reactor internals 145 t Conventional scrap 4,700 t Radwaste 4,000 t Toxic and hazardous produ Small amounts 45 t 100 t El Cabril disposal centre Independent Spent Fuel Storage Installation (ISFSI) Recycling Treatment plant 66 67

35 Metallic transport container Material clearance Box Counter The clearance process involves proving that material from the radiological area may be treated as conventional material. To do this, the potentially clean material is comprehensively measured with the Box Counter equipment, which can analyse the radiological content of the material by means of gamma-ray spectrometry, thus allowing industrial-scale operation with laboratory accuracy. The material will be cleared only after this equipment certifies that the material complies with the clearance levels established by the CSN (Spanish Nuclear Safety Council). Box Counter Vehicle exit gantry 68 69

36 8 SAFETY CULTURE QUALITY ASSURANCE Completing the dismantling operations in complete safety and ensuring their quality are two of the priorities of the project. They can only be achieved by ensuring the adequate qualification of the intervening personnel, implementing a strict safety culture in the organisation and coordinating the work of all the specialities required for the execution of all the different activities. The José Cabrera NPP thus complies with IS-19, the instruction from the Spanish Nuclear Safety Council that establishes the requirements for the integration of the different nuclear facility management systems. This is a key element to guarantee the safety of personnel and the environment. Use of personal protection equipment Quality audit 30% of the personnel is assigned to supervise the quality and safety of the work 70 71

37 Institutional control Dismantling operations are subject to extremely strict regulations from different organizations that supervise the development of the various activities. COMPLEMENTARY POLICIES 9 of the operation of the facilities and the development of the project (radiological protection, emergencies, waste management, etc). Training The complexity of the work involved in the dismantling operations, both in conventional areas and in areas with radiological implications, calls for a training plan to ensure that all workers have adequate training to guarantee the safety of all the activities and that the requirements of the regulations in force are met. The Nuclear Safety Council (CSN), which is the spanish body in charge of nuclear safety and radiological protection, is constantly supervising the different stages EURATOM and the OIEA are international agencies that also monitor the project and perform periodic inspections of the status of the facility and of the materials within it. Container conditioning tests (DAB control room) Fire fighting training 72 73

38 Communication From the start of the dismantling operations, the Enresa communication policy regarding all the activities in the José Cabrera NPP has been completely transparent. Several communication channels have been established to allow public opinion to discover and be a part of the distinctive nature of this project. Many national and international organisations (from the academic, institutional and professional spheres) are visiting the plant to gain first-hand knowledge of the progress of the work. José Cabrera NPP information area Students (1.388) Institutions (220) Professional groups (1.482) Press (172) Others (206) International projection The dismantling of the José Cabrera NPP is a groundbreaking project in Spain, as well as one of a few operations of its kind in the whole world, since only around ten commercial power plants have been dismantled. The innovative approach that has been applied to the segmentation of the large plant components and to the conditioning of the resulting materials has been a subject of attention and interest in the international community. Many companies and institutions, both national and international, are visiting the site to learn the dismantling operations. Furthermore, as part of its international collaboration, Enresa is participating in several working groups designed to share know-how and optimise the dismantling projects

39 MILESTONES OF THE DECOMMISSIONING PROJECT 2009 September End of the loading of the spent fuel casks and storage within the ISFSI of the facility st February Authorisation from the MITYC for the transfer of responsibility from Gas Natural Fenosa to Enresa to start the dismantling stage May Dismantling of the cooling towers June Start of the equipment dismantling and civil conditioning works of the turbine building November The CSN authorises the new ventilation systems for the Containment and Auxiliary Buildings May Start of the underwater segmentation of the upper reactor internals October Start of the dismantling operations of the main pump of the primary circuit April Completion of the adaptation of the Monitoring and Supervision Station (MSS) and of the Emergency Control Centre (ECC), replacing the original Control Room June Completion of the segmentation of the plant reactor internals August Loading of the first GWC with the special waste resulting from the segmentation of the reactor internals and with the operational waste June Extraction and removal of the reactor vessel th April Plant shutdown. Start of the spent fuel management operations and preliminary dismantling work th January The BOE (Spanish Official State Gazette) publishes the Environmental Impact Statement provided by the Ministry of the Environment th February Signature of the transfer of responsibility from Gas Natural Fenosa to Enresa June Dismantling of the diesel generator building June Dismantling of the transformers and civil conditioning of the site April Completion of the ADB adaptation work September Start of the underwater segmentation of the lower reactor internals October Conditioning within the ADB of the first container with waste from the reactor April Dismantling of the primary circuit pressuriser July Start of the Steam Generator dismantling operations October Completion of the loading of the fourth and last Special Waste Cask May End of reactor vessel segmentation and removal of all components from the primary circuit. KEY MITYC CSN Spanish Ministry of Industry, Energy and Tourism Spanish Nuclear Safety Council 76 77

40 Key Figures Radiological Protection and Safety Management of Materials Execution schedule 2,300,000 hours of work General Information INSTITUTIONAL CONTROL 89 CSN inspections 14 EURATOM inspections RELEASABLE MATERIAL 1,081 tons produced RADWASTE 2,637 tons produced RADIOLOGICAL PROTECTION 6,416 msv.p of collective CONVENTIONAL MATERIAL 5,958 tons produced An average of 35 companies are working at the site 851 SAT (Work Permit Requests) 278 visits 3,392 visitors estimated dose in the project 2,050 msv.p dreal collective dose (up to 31/12/2015) NUMBER OF SHIPMENTS 174 shipments to the El Cabril Disposal Centre 250 people are working every day on the dismantling 66% of the workers are from the province of Guadalajara training: 2,036 training actions 5,658 hours of tuition 36,998 man-hours QUALITY ASSURANCE 435 average of inspections per year 748 records archived in the Comprehensive Improvement System (CIS) OCCUPATIONAL RISK PREVENTION 851 risk analyses Key Figures

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42 ENRESA Emilio Vargas 7, Madrid Phone number: JOSÉ CABRERA NPP Almonacid de Zorita, 19119, Guadalajara Phone number: