Company Profile the Company

Company Profile The Company

Who we are Where we operate Ansaldo Nucleare is the premier Italian company in the Ansaldo Nucleare operates in the domestic and civil nuclear sector, with over fifty years international international nuclear markets, managing the entire experience in delivering technological and innovation business from its headquarters and operations office excellence. in Genova (Italy), directly and through the branches The company provides EPC services, as well as, located in Romania, Slovakia, Argentina, France and component design and supply for the following business the representative office in Russia. lines: In the UK, Ansaldo Nucleare operations rely on the • Nuclear New Build; fully owned company Ansaldo NES. In Romania and • Plant Operation Assistance; in France, Ansaldo Nucleare provides service support • Decommissioning and Waste Management. through participated companies, "Polaris-Anserv" for Cernavoda NPP and "NNS" devoted to Creys-Malville In May 2014, Ansaldo Nucleare completed the NPP. acquisition of NES (Nuclear Engineering Services) Ltd., In the other countries, Ansaldo Nucleare relies bringing the workforce to a total of more than 650 on numerous Representative Offices of its parent employees, almost half of which are in the Engineering company, Ansaldo Energia, located in over twenty and Design departments. The new Ansaldo NES countries in the world. provides an in-house, fully integrated capability which includes design, engineering, manufacturing, assembly, testing, commissioning, site installation and integrated logistics through-life support of bespoke solutions for the nuclear decommissioning, nuclear new build markets and defence. Ansaldo Nucleare, together with recently acquired Ansaldo NES in UK, represent the nuclear arm of Ansaldo Energia Group (more than 3700 employees, 1,2 billion Euros revenues in 2014), a leading player in the power generation sector with an installed capacity of more than 190 GW completed in 90 countries worldwide. Quality & Environment Innovation & Patents

Ansaldo Nucleare performs its activities in accordance Patents with a Quality and Environment Management System During its multi-decennial activity as prime nuclear in compliance with the International standards UNI EN player in Italy, Ansaldo Nucleare has been involved ISO 9001:2008, ASME NQA-1 2012, IAEA GS-R-3, in the design and supply of various types of Nuclear UNI EN ISO 14001:2004. Power Plants and Research Facilities. Through the From order entry through design, manufacturing and development of these activities Ansaldo Nucleare has servicing, activities are controlled in accordance with registered or applied for several patents for application the commitments of the Quality Management System. to different nuclear plant technologies including: Ansaldo Nucleare is both ASME and ISO 9001 certified. Our goal is to continually improve the quality, safety • Passive Containment Cooling Condenser for SBWR and efficiency of our services and products, fostering • Isolation Condenser for SBWR the Nuclear Safety Culture among our employees and • Method and Device for Neutrons’ Production in a supply chain. Sub-critical Nuclear Reactor (Accelerator Driven Ansaldo Nucleare is committed to a system of continual System ADS) improvement to create a competitive advantage for our customers and ourselves, striving to constantly exceed • Nuclear reactor, in particular liquid-metal-cooled the needs and expectations of our customers. nuclear reactor (Metal-cooled Fast Reactor technology)

Certification • Load compensating device for a nuclear fuel element handling machine (Fuel Handling Equipment - PWR, The Quality Management System of Ansaldo VVER, BWR) Nucleare is certified according to the following international standards: • Auxiliary system for assisting a movement system of a nuclear reactor fuel elements (Fuel handling • UNI EN ISO 9001:2008 for Quality Management Equipment - PWR, VVER, BWR) System • Nuclear fuel elements gripping tool provided with an • ASME Section III, Division 1 - Certificate of emergency opening device (Fuel Handling Equipment Authorization N-2961 - PWR, VVER, BWR) • The National Board of Boiler & Pressure Vessel • Device and method for detecting neutrons and Inspectors - NB certificate of authorization gamma rays (Radioactive Waste Management) The company's Environmental Management Sy- • Detector Mesh for Nuclear Repositories (Radioactive stem is certified according to the international stan- Waste Management) dard: EN ISO14001:2004. Safety is a top priority for Ansaldo Nucleare. The company's Occupational Health • Device and Method for passive adjustment of decay and Safety Management System is certified in BS heat removal systems performance (Application ohsas 18001:2007. to BWR, PWR, LFR, SFR, MSR).

CERTIFICATO N. CERTIFICATO N. OHS-2274 CERTIFICATE No. CERTIFICATE No. 15633/06/S SI CERTIFICA CHE IL SISTEMA DI GESTIONE PER LA QUALITÀ DI Si certifica che il Sistema di Gestione della Sicurezza e della Salute sul luogo di lavoro di IT IS HEREBY CERTIFIED THAT THE QUALITY MANAGEMENT SYSTEM OF It is hereby certified that the Occupational Health and Safety Management System of

ANSALDO NUCLEARE S.P.A. Per informazioni sulla validità CERTIFICATO N. ANSALDO NUCLEARE S.P.A. del certificato, visitare il sito www.rina.org VIA LORENZI, 8 16152 GENOVA (GE) ITA VIA LORENZI, 8 16152 GENOVA (GE) ITALIA For information concerning CERTIFICATE No. validity of the certificate, you NELLE SEGUENTI UNITÀ OPERATIVE can visit the site nelle seguenti unità operative / in the following operational units IT IS HEREBYSI CERTIFICACERTIFIED CHETHAT IL THE SISTEMA ENVIRONMENTAL DIEMS-1768/S GESTIONE MANAGEMENT AMBIENTALE DISYSTEM OF / IN THE FOLLOWING OPERATIONAL UNITS www.rina.org ANSALDO NUCLEARE S.P.A. CORSO PERRONE, 25 16152 GENOVA (GE) ITALIA CORSO PERRONE, 25 16161 GENOVA (GE) ITALIA E CANTIERI OPERATIVI E CANTIERI OPERATIVI VIA LORENZI, 8 16152 GENOVA (GE) ITALIA NELLE SEGUENTI UNITÀ OPERATIVE

Riferirsi al Manuale della Qualità È CONFORME ALLA NORMA è conforme alla norma / is in compliance with the standard per i dettagli delle esclusioni ai / IN THE FOLLOWING OPERATIONAL UNITS / IS IN COMPLIANCE WITH THE STANDARD requisiti della norma E VALUTATO SECONDO LE PRESCRIZIONI DEL REGOLAMENTO TECNICO RT-05 BS OHSAS 18001:2007 ISO 9001:2008 Reference is to be made to the E AL DOCUMENTO SINCERT RT-12 Quality Manual for details CORSO PERRONE, 25 16152 GENOVA (GE) ITALIA per le seguenti attività / for the following activities PER I SEGUENTI CAMPI DI ATTIVITÀ regarding the exemptions from the requirements of the standard EA:28 / FOR THE FOLLOWING FIELD(S) OF ACTIVITIES E CANTIERI OPERATIVI EA:18 EA:34 PROGETTAZIONE, FABBRICAZIONE ED INSTALLAZIONE DI IMPIANTI E SISTEMI NUCLEARI; TECNOLOGIE PER LA EA:28B È CONFORME ALLA NORMA GESTIONE E SUPERVISIONE DELLE ATTIVITA' DI REALIZZAZIONE DI IMPIANTI NUCLEARI E SUCCESSIVI EA:18 INTERVENTI. SVILUPPO DI NUOVE TECNOLOGIE RELATIVE A PRODOTTI NUCLEARI E TECNOLOGIE PER LA MANUTENZIONE E LO SMANTELLAMENTO DI CENTRALI NUCLEARI. MANUTENZIONE E LO SMANTELLAMENTO DI CENTRALI NUCLEARI. / IS IN COMPLIANCE WITH THE STANDARD PER I SEGUENTI CAMPI DI ATTIVITÀ Per informazioni sulla validità E ALISO DOCUMENTO 14001:2004 ACCREDIA RT-09 del certificato, visitare il sito DESIGN, CONSTRUCTION AND INSTALLATION OF NUCLEAR POWER PLANTS AND SYSTEMS; TECHNOLOGIES www.rina.org FOR MAINTENANCE AND DECOMISSIONING OF NUCLEAR POWER PLANTS. GESTIONE E CONTROLLO DELLE ATTIVITA' DI REALIZZAZIONE/ FOR THE FOLLOWING DI IMPIANTI FIELD(S) NUCLEARI OF ACTIVITIES E SUCCESSIVI MANAGEMENT AND SUPERVISION OF CONSTRUCTION ACTIVITIES OF NUCLEAR POWER PLANTS AND For information concerning INTERVENTI. SVILUPPO DI NUOVE TECNOLOGIE RELATIVE A PRODOTTI NUCLEARI E TECNOLOGIE PER LA SUBSEQUENT INTERVENTION WORKS. DEVELOPMENT OF NEW TECHNOLOGY RELATED TO NUCLEAR validity of the certificate, you PRODUCTS AND TECHNOLOGY FOR THE MAINTENANCE AND DECOMMISSIONING OF NUCLEAR POWER can visit the site La presente certificazione si intende STATIONS. www.rina.org riferita agli aspetti gestionali MANUTENZIONE E LO SMANTELLAMENTO DI CENTRALI NUCLEARI. dell'impresa nel suo complesso ed è utilizzabile ai fini della qualificazione delle imprese di costruzione ai sensi dell'articolo 40 della legge 163 del 12 La validità del presente certificato è subordinata a sorveglianza periodica annuale / semestrale ed al riesame completo del sistema di gestione con periodicità triennale aprile 2006 e successive modificazioni e del DPR. 5 ottobre 2010 n. 207 EA:28 The validity of this certificate is dependent on an annual / six monthly audit and on a complete review, every three years, of the management system MANAGEMENT AND CONTROL OF CONSTRUCTION ACTIVITIES OF NUCLEAR POWER PLANTS AND EA:18 L'uso e la validità del presente certificato sono soggetti al rispetto del documento RINA: Regolamento per la Certificazione di Sistemi di Gestione per la Qualità SUBSEQUENT INTERVENTION WORKS. DEVELOPMENT OF NEW TECHNOLOGY RELATED TO NUCLEAR La validità del presente certificato è subordinata a sorveglianza periodica annuale / semestrale ed al riesame completo del sistema di gestione con periodicità triennale The use and validity of this certificate are subject to compliance with the RINA document : Rules for the certification of Quality Management Systems PRODUCTS AND TECHNOLOGY FOR THE MAINTENANCE AND DECOMMISSIONING OF NUCLEAR POWER The validity of this certificate is dependent on an annual / six monthly audit and on a complete review, every three years, of the management system Prima emissione L’uso e la validità del presente certificato è soggetto al rispetto del documento RINA: Regolamento per la Certificazione dei Sistemi di Gestione della Sicurezza e Salute sul luogo di lavoro First Issue The use and validity of this certificate are subject to compliance with the RINA document: Rules for the Certification of Occupational Health and Safety Management Systems Emissione corrente 21.12.2006 Dott. Roberto Cavanna Prima emissione L'uso e la validità del presente certificato sono soggetti al rispetto del documento RINA: Regolamento per la Certificazione di Sistemi di Gestione Ambientale Ing. Michele Francioni CISQ è la Federazione Italiana di Current Issue (Managing Director) 01.03.2015 The use and the validity of this certificate are subject to compliance with theSTATIONS. RINA document: Rules for the Certification of Environmental Management Systems First Issue (Chief Executive Officer) Organismi di Certificazione dei 08.01.2013 Data scadenza La validità del presente certificato è subordinata a sorveglianza periodica annuale / semestrale ed al riesame completo del sistema di gestione con periodicità triennale Emissione corrente sistemi di gestione aziendale Expiry Date Per informazioni sulla validità Current Issue 11.03.2015 CISQ è la Federazione Italiana di The validity of this certificate is dependent on an annual / six monthly audit and on a complete review, every three years, of the management system 19.12.2015 del certificato, visitare il sito Organismi di CertificazionePrima dei emissione Data scadenza CISQ is the Italian sistemi di gestione aziendaleFirst Issue www.rina.org Expiry Date 28.02.2018 Federation of management For information concerning system Certification Bodies RINA Services S.p.A. CISQ is the ItalianEmissione corrente validity of the certificate, you RINA Services S.p.A. Via Corsica 12 - 16128 Genova Italy Federation of managementCurrent Issue 26.04.2007 Via Corsica 12 - 16128 Genova Italy system Certification Bodies can visit the site SGQ N° 002 A SSI N° 001 G Data scadenza SGA N° 002 D DAP N° 001 H Dott. Roberto Cavanna www.rina.org PRD N° 002 B PRS N° 066 C Expiry Date 17.01.2013 SGQ N° 002 A SSI N° 001 G SCR N° 003 F LAB N° 0832 (Managing Director) SGA N° 002 D DAP N° 001 H Membro degli Accordi di Mutuo PRD N° 002 B PRS N° 066 C Riconoscimento EA, IAF e ILAC 19.12.2015 SCR N° 003 F LAB N° 0832 Signatory of EA, IAF and ILAC Mutual Membro degli Accordi di Mutuo Recognition Agreements Riconoscimento EA, IAF e ILAC CISQ è la Federazione Italiana di Signatory of EA, IAF and ILAC Mutual Recognition Agreements RINA Services S.p.A. Organismi di Certificazione dei Via Corsica 12 - 16128 Genova Italy sistemi di gestione aziendale

SGQ N° 002 A SSI N° 001 G SGA N° 002 D DAP N° 001 H PRD N° 002 B PRS N° 066 C SCR N° 003 F LAB N° 0832 CISQ is the Italian Membro degli Accordi di Mutuo Federation of management Riconoscimento EA, IAF e ILAC system Certification Bodies Signatory of EA, IAF and ILAC Mutual Recognition Agreements EPC Services and Nuclear new build

Ansaldo Nucleare supplies systems, components and Moreover, in the frame of Front End Engineering Design services for the NSSS (Nuclear Steam Supply System) (FEED) projects, Ansaldo Nucleare is participating in as well as BOP (Balance of Plant), for various Nuclear the design of systems and components for the Multi- Power Plants including PWR, BWR, CANDU and VVER Purpose hybrid Research Reactor for high-tech in accordance with vendor requirements. Applications (MYRRHA).

Ansaldo Nucleare is at the forefront of the technological The company is also present in the nuclear fusion development of new NNPs, taking advantage of its sector through the realization of the fusion reactor ITER experience of different types of reactors over the last (International Thermonuclear Experimental Reactor) fifty years. for which it contributes to the supply of fundamental components of the plant. Ansaldo Nucleare has provided a significant contribution to Generation III+, cooperating with Westinghouse since the early 1980s in the development of Passive Plant Technology and contributing to the Design Certification of AP600 and AP1000 NPPs. In addition, Ansaldo Nucleare is actively involved in Generation IV international programmes (the Sustainable Nuclear Energy Technology Platform (SNETP) and the European Sustainable Industrial Initiative on Nuclear Energy, ESNII). In this context, Ansaldo Nucleare is acting as leader for the Lead- Cooled Fast Reactors development programmes, for the successful completion of the “Advanced Lead-cooled Fast Reactor European Demonstrator” (ALFRED).

• Cernavoda Unit 2 Completion Contracts (Societatea Nationala Nucleareletrica, SNN, Romania) - in 2003 Ansaldo Nucleare and AECL, as Main Contractors, were awarded the completion of the Second Unit. Power operation initiated, according the initial schedule, at the end of 2007.

• AP1000 Sanmen Unit 1 (Westinghouse, China) - Detailed Design Activities and procurement activities.

• Eurex Saluggia (Sogin, Italy) - Intermediate Level Liquid Waste Storage Facility (NPS plant)- Design, procurement, erection and commissioning of the storage facility.

• ITER (Fusion for Energy (F4E), France) - Supply of 7 out of 9 sectors of the ITER Vacuum Vessel. Engineering & Design

Nuclear and Radiation Analysis Fluid and Thermal-Hydraulic Analysis Definition of radiological protection requirements, Advanced two-phase flow and inhouse developed development of nuclear calculations for the design computer codes to perform fluid and thermal hydraulic of storage facilities; calculation of radiations fields, analysis on a wide range of different fluids (including shielding sizing and verification. Design and supply molten metals) of engineering interest. Advanced CFD of radiation monitoring systems, implementation (Computational Fluid Dynamics) analysis tools routinely of ALARA requirements and dose evaluation of used to complement the transient thermal hydraulic professionally exposed personnel and the population. analysis.

• AP1000 Radiation Analyses (Westinghouse - USA): • Cernavoda NPP (SNN - Romania) – Design and In-containment radiation zoning during normal and analysis of the Recirculating Water System Loop accidental operations and post accident Skyshine including the Valve Slam Absorber Optimization Analyses. • AP1000 ThermalHydraulic Transients • Ignalina NPP Solid Radwaste Retrieval Facility B2 (Westinghouse - USA) - Design transients analyses (Nukem Technologies GmbH, Lituania) Radiation to support AP1000 Reactor Vessel internals. Monitoring & Control System.

Fluid System Design and Integration Fire Fighting Systems Definition of operational and safety performances of Definition of fire hazards and plant zoning; evaluation plant systems, conceptual and detailed designs of of potentially explosive zones (ATEX); identification of fluid systems aimed at optimizing solutions within the suitable means for firefighting, taking into account performance requirements, safety design guides, potential radiological releases; design of fire detection Clients’ needs, industry standards and good engineering systems. practice. • European Passive Plant Program (EU Utilities): • VVER/RBMK – R2.08/96 (EU - Tacis Program) - Detailed design of the AP1000 Defense-in-Depth Fire Risk Assessment for all Type of Reactors; Systems (e.g., Residual Heat Removal System, • Kozloduy NPP Units 1 to 4 (EBRD - Nuclear Safety Component cooling System). Account) - Fire Protection Equipment (Project B.9). • Trino NPP (Sogin - Italy): Integrated System for the Extraction, pre-treatment and Treatment by Wet Oxidation of Radioactive Sludge. Engineering & Design

Instrumentation & Control (I&C) Design and supply of I&C systems for power plants, fuel handling equipment and test facilities including: design, supply and commissioning of new, digitally- based automation systems for the whole Balance of Plant (Distributed Control System); control systems for Fuel Handling Machines (FHM-CS) for different types of reactors; control systems for waste management facilities and for on-site power supply systems.

• Cernavoda Unit 2 (SNN - Romania): Balance of Plant Distributed Control System (DCS) Integrated Plant Layout and Engineering • Tianwan NPP Units 3 & 4 (JSC Atomstroyexport - Space management of standard and bespoke design, China) - Supply of the Control systems for the Fuel operational decommissioning requirements. Handling Machines (FHM). Building 3D models to control engineering detailed design and the integration of various engineering disciplines into a single plant-engineering tool.

Electrical Systems • AP1000 Sanmen Unit 1 (Westinghouse, China): Design and supply of electrical distribution systems In-Containment Plant Layout and Space Management to feed operational and safety equipment: Medium including piping routing, supports location, mechanical and Low Voltage power systems and Emergency & steel frame modules design and electrical divisional Diesel Generator Stations (EDGS); Un-interruptible trains). Power Supply systems; protection systems based on selection studies and short circuit currents; grounding networks. Conceptual and detail design of cabling and cables routing and installation.

• Embalse NPP (NA-SA, Argentina) - Diesel Generator (DG) sets and associated auxiliaries (e.g., cooling system, lubrication oil, DG station control boards) • Cernavoda Units 1 & 2 (SNN - Romania) - Medium Voltage and Low Voltage plant distribution systems. Design of Civil Structures Piping Design Design of standard reinforced concrete structures and Mechanical stress analysis and the design of piping special construction techniques for accommodating systems, including piping supports. Fatigue analysis nuclear systems and components; complex steel for piping systems. Leak Before Break (LBB) and frame architectures for sustaining large components. High Energy Line Break analyses for piping systems. Design against external and internal events such as Guillotine-break analysis, pipe-whip restraints and jet aircraft collision, sloshing phenomena, seismic spectra impingement shielding. from time history, pressure spikes, thermal loads and structure-to-structure interaction. • Mochovce 3 & 4 (ENEL/Slovenske Elektrarne, Slovak Republic): Piping stress analysis validation. • Nuovo Parco Serbatoi Saluggia (Sogin, Italy) - • AP1000 (Westinghouse, USA): Design, stress analysis Intermediate Liquid Waste Storage facility. Bunkered and LBB evaluation for the AP1000 Class I & II piping. building designed to withstand Air Craft Crash (ACC). • AP1000 Standard Plant and AP1000 Sanmen Unit 1 (Westinghouse, USA / China) - Design of a Modularized Shield Building Roof capable to withstand ACC events.

Mechanical Modules Design and Prefabrication Design of complex integrated structures for the integrated assembly of equipment, piping, conduits and instrumentation, all organized and mounted on a sustaining steel frame. Structures are transportable by land or sea and provided with inspection and maintenance platforms with suitable connections for a simplified hook- up to related systems and anchoring to civil works.

• AP1000 Standard Plant / AP1000 Sanmen Unit 1 (Westinghouse, USA / China) – Mechanical Modules Design (KQ10, KQ11, DVI A/B, RNS). Component and equipment procurement and supply

Ansaldo Nucleare has consolidated experience in the design & supply of pressure-retaining nuclear components and special mechanical equipment for nuclear applications (Fission & Fusion Technologies. Components are usually manufactured by selected sub-suppliers based on Ansaldo Nucleare drawings and under our responsibility. Through Ansaldo Nes, we also have the opportunity to manufacture machines & tools directly in house.

Pressure Components • Concept design (performance and mechanical), for metal containment, pressure vessel, heat exchanger, etc. • Detail design in accordance with design specification and applicable codes. Stress calculations (thermal, thermo-mechanical, dynamic - seismic/flow-induced vibration/impact, fracture mechanics) and code verification, final design report comprehensive of manufacturing non-conformances evaluation/ disposition. • Manufacturing design, including the supply of material specifications, fabrication specifications, the review of supplier-generated documentation, follow-up of shop activities, inspections and testing. • Follow-up of erection/installation activities.

• Sanmen Unit 1 - AP1000 Passive Residual Heat Removal System (Westinghouse, China) - Design according to ASME-III and supply of a first of a kind passive heat exchanger for the AP1000 plant. • Sanmen Unit 1 - AP1000 Steel Containment Vessel (Westinghouse, China) - The containment vessel, 40 m diameter, 65 m height, has been designed according to ASME-III Class MC, Division 1. Machines & Tools • Design of in-reactor fuel handling machines • Design and supply of cranes and related tools for remote operation in inaccessible buildings/areas. • Design and Manufacturing of bespoken special tools for fuel and waste retrieval.

• Covra-Habog - Bunker And Transfer Cranes And Canister Crane (SGN, Holland) - Design and supply of two nuclear cranes, including all the related gripping devices, for the COVRA HABOG facility. • Ignalina NPP - Fuel Inspection Hot Cell Handler (NUVIA UK, Lituania) - Design and supply the crane and the associated tools to provide the required handling functions within the Fuel Inspection Hot Cell area. • Silo Emptying Plant (SEP) - Special tools for waste retrieval (sellafield, UK). Plant Operation Assistance

Ansaldo Nucleare provides a large range of service Execution of the fracture mechanics calculations - activities aimed at safe operation, system optimization elastic or elastic-plastic regime - for assumed through and performance enhancement of Nuclear Power wall cracks, both for crack stability and for leakage flow Plants. rates, using certified computer programs, according to the required methodology. Plant Life Extension (PLEX) and Power Uprating Engineering activities addressing walk down • AP1000 LBB Piping Analyses (Westinghouse, USA): inspections and engineering assessment to assure and Performance of the LBB analyses. validate PLEX to Customer requirements. • VVER 1000 Model 320 NPP / METSAMOR NPP Realization of the plant refurbishing and modifications UNIT 2 (EU Commission / Armenia) to restore the plant operation conditions and to obtain LBB Applicability Review and Basic Implementation a higher efficiency and better performance. Engineering, definition of new Leak Detection System (LDS) configuration. • Embalse Nuclear Power Plant (NA-SA, Argentina): BOP Condition Assessment & Residual Life Evaluation, of the thermal cycle, supply of systems and components, Supervision of Installation and commissioning activities.

BOP Optimisation Optimisation through Thermal Cycle analysis and performance testing. Safety and reliability enhancement by means of elimination of common failure causes and identification of system upgrading.

• Cernavoda Units 1 & 2 (SNN - Romania) - Plant uprate, optimization of the thermal cycle, increase of plant availability, replacement of pre-heaters, pumps and valves, supervision of installation and commissioning activities. • Embalse Nuclear Power Plant (NA-SA, Argentina): Power uprate through optimization of the thermal cycle and turbine replacement in parallel to the PLEX program.

Fatigue and Leak Before Break (LBB) Analysis Justification of the LBB analysis applicability to Primary Coolant Loop (and Surge lines) of Eastern (and Western) Light Water Reactor, verifying that all the mandatory requirements are met; identification of material characteristics, possible degradation mechanisms, calculation of applied loads and stresses to exclude the possibility of a piping failure. Fuel Handling Equipment and Tools Instrumentation & Control (I&C), Automation and Customized development of Fuel Handling Machines Monitoring Systems (FHM) and Control Systems, including the design of Design and supply of automation systems for BOP. controlling architecture (safety monitoring and operating Design, supply and installation of monitoring systems functions) of the driving and actuation system. for Diesel Generating Stations. Integrated Monitoring systems dealing with radiation, • EUREX Saluggia (Sogin, Italy): Emergency Defueling nuclear safety, structural and seismic real time of the Saluggia Fuel Pool (Design and supply of monitoring. special components and tools for the safe removal of radioactive material). • Integrated Automatic Monitoring System (IAMS) (Chernobyl, Ukraine) – Integrated structural, seismic, • Tianwan NPP - Units 1 & 2 (Atommashexport radiation and criticality monitoring control system for “OJSC”, China) - Refurbishment and optimization the sarcophagus. of the Control System Sets of the FHMs. • Treatment Of Backlog Of Radioactive Waste Water (Khmelnitsky NPP, Ukraine) - Design, supply, installation, testing and commissioning of electrical, instrumentation & control equipment and radiation monitoring.

Post Fukushima Beyond Design Basis Events equipment Assessments to evaluate NPPs capabilities to withstand scenarios which are out of design requirements, covering - as initiating events - seismic excitation, tsunami, severe meteorological conditions. Mobile Emergency cooling system.

• Embalse NPP (NA-SA, Argentina) - Diesel Generator (DG) sets and associated auxiliaries (e.g., cooling system, lubrication oil, DG station control boards) PatentsDecommissioning of Nuclear Plants and Facilities

Our activities include feasibility studies, safety analysis, Management Tools basic and detailed design, procurement of equipment and Development of specific software packages and tools for the dismantling, packaging and transfer of waste computer tools to manage materials derived from materials produced in the frame of the decommissioning decommissioning and dismantling operations. and management of the on-site dismantling activities. • IDMT (Integrated Decommissioning Management Feasibility Studies and Decommissioning Plans Tool): This tool is conceived and designed to manage Decommissioning studies for NPPs and experimental the entire lifecycle of the Decommissioning of a reactors in Italy and abroad to analyse alternative solutions Nuclear Plant or Facility: and define the best decommissioning strategies based on • organization of dismantling activities technical, economical and ALARA requirements. • treatments / decontamination • management of primary and secondary wastes. • ISPRA European JRC (EU, Italy) - Engineering support services for the ISPRA JRC decommissioning Dismantling Equipment and Tools and waste management program. Concept and detailed design, procurement of equipment (innovative and/or prototype) for dismantling Integrated Detailed Design of primary plant structures and components, and Ansaldo Nucleare follows a systematic approach star- packing of waste resulting from decommissioning in ting from ‘reverse engineering’ to obtain a reliable pi- storage containers. cture of the plant up to the detailed design of the dismantling process. Multidisciplinary engineering work • Gioconda, Cart, Colibri Rigs (ISPRA JRC, Italy) - for the overall dismantling of buildings and plants on Retrieving, dismantling and packing of irradiated rigs nuclear sites, including 3D CAD models, choice of ap- and Irradiated Nuclear Material (INM) items stored in plicable cutting techniques, definition of dismantling ADECO and relevant supplies. and handling sequences, safety analysis, assessment of personnel radiation exposure, evaluation of costs and timeline scheduling. • CISAM Research Reactor Decommissioning. On-site Decommissioning Work Waste Management Facilities (WMFs) Management of in-field activities, coordination and Detailed design and provision of WMFs, including hot supervision of decommissioning activities (dismantling, workshop for segmentation and associated dedicated filtering physical and radiological characterization, waste disposal). systems, mechanical and/or chemical decontamination systems, temporary storage areas, radiological monitoring • Caorso NPP (Sogin, Italy): Caorso Turbine Building & stations and materials grouting station. Off-Gas dismantling. • PHADEC (Phosphoric Acid Decontamination) Facility (Sogin, Italy) - Industrial scale plant for carbon and stainless steel decontamination. • SALUGGIA NPS (Nuovo Parco Serbatoi) (Sogin, Italy) Bunkerized Storage Facility for Intermediate Level Liquid of Waste (ILLW).

Licensing Processes Support to the Client during the overall licensing process to meet Safety Authority requirements. • ISPRA INTERIM STORAGE FACILITY (EC JRC ISPRA, ITALY): Development of Safety Analysis and Preliminary Safety Analysis Report • CAORSO/GARIGLIANO NPPs: Application for overall Decommissioning. Radioactive Waste Management

Ansaldo Nucleare provides solutions for liquid, solid and Handling Systems organic radioactive waste management and disposal Concept definition and design of systems and for Low and Intermediate Level Waste (LILW). equipment for the handling and/or lifting of storage containers for radioactive waste and spent fuel. Conditioning of Liquid Waste Definition of treatment processes based on the chemical • Silo Emptying Plant (SEP) Mobile Caves (Sellafield, and radiological characteristics of waste produced UK): Supply of three SEP Mobile Caves for the during prior or current operation of nuclear plants and Remote retrieval of ILW sludge’s from multiple the waste generated during decommissioning. vertical silos.

• KHMELNITSKY - Turn key delivery of a LILW • Latina (Sogin, Italy) - Supply of No.2 Cranes For treatment facility with the purpose to separate The Movement Of Radioactive Waste At sludges by centrifugation and evaporation Decommissioning Area Of Latina NPP In Italy. • STEL (Stazione Trattamento Effluenti Liquidi) (JRC ISPRA, Italy) - Turn key delivery of a LILW treatment facility by co-precipitation and ultra-filtration.

Treatment of Solid Waste Definition of treatment technologies and handling systems for solid waste produced during prior the operation of nuclear installations and the waste generated during decommissioning.

• IGNALINA B2 (Nukem Technologies GmbH, Lituania) Retrieval and pretreatment of Low Level Solid Waste from existing storage buildings.

Treatment of Organic Waste Development of an innovative wet oxidation process Radioactive Waste Transport Storage Containers for waste consisting of organic material, specifically Design, construction and qualification of containers in for use in the treatment of nuclear waste including compliance with the requirements of IAEA Regulations ion exchange resins and waste conditioned in urea- and UNI standards for the transport and storage of formaldehyde. radioactive waste. • Trino WOX (Wet OXidation) Facility (Sogin, Italy) • LILW Containers for the National Repository Prototypical system for treatment and conditioning (Sogin, Italy): Design, qualification and procurement of radioactive organic waste in order to reducing of stainless steel containers (IAEA-IP2 packaging) for waste volume. Low & Intermediate Level Waste. • ISPRA European JRC (EU, Italy) - Design, qualification and procurement of carbon steel containers (IAEA-IP2 packaging) for Low & Intermediate Level Waste. Radioactive Waste Storage Facilities Design of Interim Storage Facilities for LILW including: civil works, handling systems, radiation monitoring, I&C, HVAC (Heating Ventilation and Air Conditioning), safety analysis. • Andreeva Bay (Russia) - Main contractor for Design of Solid & Liquid Radioactive Waste Management & Temporary Storage Facilities for radwaste produced by submarines dismantling.

Technological Developments in the field of RAW Management • Development of new methods for liquid radwaste • Scintillating fibres for radiation monitoring: conditioning: testing of innovative methods for the development of an innovative detector syste for vitrification of radioactive acid solutions coming from gamma portals and real time monitoring of LILW decontamination deposits. Nuclear Power Plants Main Research Reactors References Nuclear Facilities in the world

LITHUANIA NETHERLANDS Ignalina NPP Habog (HLW Storage) CZECH REPUBLIK UNITED KINGDOM Temelin NPP Sellafield RUSSIA Various Nuclear Sites ROMANIA FRANCE Cernavoda NPP Creys Malville NPP ITER UKRAINE Chernobyl NPP ITALY Khmelnitsky NPP CHINA Trino NPP Sanmen Npp Caorso NPP Tianwan NPP Latina NPP Garigliano NPP Stampa: Microart Recco - Genova 5/2015 Petergraf Stampa: Microart 5/2015 Petergraf Recco - Genova Eurex Center Casaccia Center SLOVAKIA ARMENIA Trisaia Center Mochovce NPP Medzamor NPP EU-JRC-Ispra BULGARIA Kozloduy NPP

ARGENTINA Embalse NPP

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