Annex VIII

RUSSIAN FEDERATION

Reactor unit AES-2006

VIII–1. HISTORY OF THE DEVELOPMENT AND INTEGRATION OF DESIGN SOLUTIONS IN THE REPUBLIC OF RUSSIA

At the end of 2005 the management of the Federal Atomic Energy Agency (FAEA) set the objective to develop the design of a two-Unit NPP with a lead unit of enhanced safety — AES-2006, to be highly competitive in the foreign and domestic markets. The goal was to be met at the expense of achieving the world level of engineering and economic indices and safety criteria accepted by the international energy community.

With this goal in mind, the design requirements of the AES-2006 of 1100–1200 MW per unit were set to allow construction of 2–3 Units per year with commissioning of the lead Unit at the beginning of 2013 at the latest.

Following the evolutionary approach to design, the fundamental design features, the calculations and experimental verification of the V-320, V-392 reactors were used in the development of the basic design of the AES-2006 reactor unit. In addition, the whole operations feedback experience from the VVER-1000 Reactor units was also incorporated. As a result, the following technical requirements were set for the AES-2006 reactor unit:

TABLE VIII–1. TECHNICAL REQUIREMENT OF AES-2006 REACTOR.

The primary sites for implementation of the AES-2006 design were designated in Russia:

—Novovoronezh NPP (NVNPP-2), General Design Organization is “Atomenergoproekt” (AEP), Moscow;

—Leningrad NPP (LNPP-2), General designer is “St. Petersburg Atomenergoproekt” (SPb AEP), Saint Petersburg.

For the above sites the General Design Organization used to the maximum extent the practical experience in design solutions of “Kudankulam” NPP in India (AEP) and “Tianwan” NPP in China (SPb AEP) as those units were at a further degree of implementation.

To reach the stated goal and the maximum integration of RU equipment the list of the unified solutions on the AES-2006 Reactor unit was prepared under the guidance and the responsibility of the “Rosenergoatom” Engineering Unit in August–September 2006. The list of technical design improvements was selected and these solutions, being implemented, achieved the goal of an evolutionary development of the main components of a Reactor unit design and of its verification.

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Development of the basic design of the Reactor unit for AES-2006 was started in 2006. The organizational structure of two AES-2006 designs was arranged in the following way:

Customer of NPP designs for NVNPP-2 and LNPP-2 is Operating Organization “Rosenergoatom” Concern:

—Subcontractor-1 of RU design for the NVNPP-2 site is the Organization of General designer, AEP;

—Subcontractor-2 of RU design for the LNPP-2 site is Organization of General designer, SPb AEP;

—and two organizations on the side of Subcontractors:

—Subcontractor-1 is Organization of Reactor unit General designer, OKB “GIDROPRESS”;

—Subcontractor-2 is Organization of research supervisor, RRC “Kurchatov Institute”.

The basic design of the Reactor unit was developed during 2006-2009. In the course of the development the following approach was implemented on the design documentation deriving from the principle of unification of the technical solutions for the conditions at NVNPP-2 and LNPP-2 sites:

(1)Documentation was divided into three types:

—Generic design documents (applicable to the conditions of both the NVNPP-2, and LNPP-2 site);

—Plant-specific documents for NVNPP-2 site;

—Plant-specific documents for LNPP-2 site.

—RU design documentation for NVNPP-2, index V-392M, contains the whole scope of RU basic design documents, and, respectively, they can be both generic and plant-specific for the NVNPP-2 site.

—RU design documentation for LNPP-2, index V-491, contains only plant-specific documents for LNPP-2 site, the rest of documentation can be taken from V-392M as applicable.

—Identification of the site specific documents was made with the appropriate labeling and the specific letter- and-digit symbols in the code of each document:

—2006 – generic documents;

—NW2O – plant-specific documents only for NVNPP-2 site;

—LN2O – plant-specific documents only for LNPP-2 site.

In 2007 the equipment with a long-lead manufacturing cycle was already put into production according to the primary documentation. The Construction licenses for the Reactor unit and the NPP design were granted in 2008 for Units 1&2 on NVNPP-2 site and Units 1&2 on the LNPP-2 site. The basic design was completed in 2008–2009. The process of ordering and manufacturing the equipment outside the long-lead item list has been underway since 2009. At present construction activities for the AES-2006 design are being carried out at the NVNPP-2 and LNPP-2 sites. In 2009 construction started on the Baltic NPP site (similar to LNPP-2 design). At the same time work is underway on an extension to the LNPP-2 site (Units 3 & 4).

For each RU design (NVNPP-2, LNPP-2, Baltic NPP), with V-392-based common design solutions available, the Particular quality assurance programs were developed that meet the requirements of the Russian regulatory documents and of the plant specific general quality assurance programme. Quality assurance programmes take into account the specific requirements of different sites, but each program always includes the following main principles:

—A clear cut division of duties and responsibilities for the designers;

—Consistent supervision of compliance with the regulatory requirements and documentation of the findings;

—Responsibility for quality assurance on the contractor and not on the quality inspector;

—Involvement of all participants in the design process also in the management of quality and in quality assurance.

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Annex IX

SLOVAKIA

IX–1. BRIEF DESCRIPTION

According to the original design, Mochovce NPP consists of 4 pressurized water VVER 440 reactors (Vodo Vodni Energeticeskij Reaktor) of the V213 Russian class. The Mochove 3, 4 units are integrated to the Mochovce 1 & 2 units and use the same auxiliary systems common to all 4 units.

MO 1and2 have been in commercial operation since 1999 and 2000 respectively.

Construction for MO3,4 started in 1986 with the civil works for the foundations of the main buildings (reactor building, longitudinal electrical building, basement of transformers, cooling towers, vent stack) and continued until 1992. In 1992 construction was suspended. From 1992 to 2000 maintenance and conservation of the suspended equipment and components and of the civil structures were carried out by the original main suppliers and constructors. From 2000 to the re-opening of the construction site, preservation and protection have been carried out by the Owner/Operator Slovenske Elektrarne (SE) on the basis of programs approved by the NRA and in compliance with the relevant IAEA guidelines.

In 2006 Enel of Italy acquired 66% of the share capital of SE by the Slovak Ministry of Economy and committed to the Government of Slovakia to complete a feasibility study concerning the completion of units 3 and 4 of the Mochovce nuclear power plant. In 2007 Enel-SE completed the Feasibility Study and prepared the Investment Memo, necessary for the project evaluation. In July 2007 Enel-SE provided Communication about the Mochovce Project to the European Union as per Article 41 of the EURATOM Treaty. Construction (Early works) at the site was re-started in November 2008. The main contracts were signed in June 2009. See Table V–1 and V–2.

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IX–1.1. Project data

TABLE IX–1. MAIN PROJECT DATA

TABLE IX–2. ACTUAL STATUS OF WORKS (AUGUST 2010)

IX–1.2. Project organization

The combination of the experience of Slovenske Elektrarne in construction and operation of 6 WWER 440 units in the last 25 years with that of ENEL in the management of very large construction projects in an international context is the key to the success of the MO3,4 construction.

SE-Enel has set-up a large team with the purpose of managing the project. The team includes two parallel structures dealing with the nuclear and conventional island of the plant. The nuclear island is directly managed by SE-Enel, whereas the conventional island is managed by Enel Ingegneria e Innovazione through the EPCM contract. At the moment, the team counts 260 people for the nuclear island. The following figure shows the details of the organization of the nuclear island team. See Fig IX–1.

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FIG. IX–1. Project organization.

IX–1.3. Contract type

The strategy chosen for the completion work of MO 3,4 was a multi-contract (more than 100 contracts), that the Owner, acting as general contractor, assigned to suppliers of engineering, procurement, construction and commissioning services.

Main advantages of this approach compared to the turnkey lump sum are:

—Better control over safety at site, over the quality of design, equipment, construction, of the schedule and of the budget;

—Optimization of the project in terms of full cycle cost analysis;

—Maximization of local content (i.e. fragmentation of the scope assured access to local companies);

—Maximization of the interaction with centralized engineering functions and operational experience (leverage on experience of a first class nuclear operator);

—Financial solidity (compared to that of any other EPC contractor available);

—Long term well established relationship with NRA and other authorities in Slovakia. The main contractors were:

—For the Nuclear Island: Skoda JS, ASE, VUJE, Enseco, ISKE, PPA, Rolls Royce;

—For the Conventional Island: Enel (EPCM Contractor), Skoda Power, Brush, ZIPP;

—For Main Instrumentation and Control: Areva-Siemens.

See Fig IX–2 for contractor type.

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