Nuclear Plant Journal Outage Management ... - Digital Versions

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Contracts... Continued from page 14 Contracts MOX Fuel AREVA recently signed a contract to supply MOX fuel assemblies for Japan’s Ohma nuclear power plant, scheduled to be in operation in 2014, located in the Aomori prefecture and which will be operated by the Japanese utility Electric Power Development Co., Ltd. Under the terms of the contract, the fuel will be fabricated at AREVA’s MELOX plant in southern France, using Japanese plutonium recovered from the treatment operations performed at AREVA’s La Hague plant, thereby recycling it to be used in Japan as MOX fuel. Contact: Donna Gaddy-Bowen, telephone(434) 832-3702, email: Donna. GaddyBowen@areva.com. Annual Editorial Schedule January-February International Trade & Waste & Fuel Management Issue March-April Plant Maintenance & Plant Life Extension Issue May-June Outage Mgmt. & Health Physics Issue July-August New Plants & Vendor Advertorial Issue September-October Plant Maintenance & Advanced Reactors Issue November-December Annual Product & Service Directory Issue Reactor Coolant Pumps AREVA, through its subsidiary AREVA DONGFANG, has won two contracts worth over 150 million euros to supply Chinese utility CNPEC with 18 reactor coolant pumps. These pumps, which are essential components of the primary system of a nuclear reactor, will equip the 1000 MW Generation II plants in Yangjiang in Guangdong province and Ningde in Fujian province in South Eastern China. Production will begin in 2009 and the pumps will be delivered in batches between 2011 and 2013. Contact: Donna Gaddy-Bowen, telephone(434) 832-3702, email: Donna. GaddyBowen@areva.com. Desktop Simulator L-3 MAPPS has been awarded a contract from Romania’s Nuclearelectrica SA (SNN) for replacing the Cernavoda Unit 1 digital control computer (DCC) central processing unit (CPU) equipment and to provide a desktop simulator to validate DCC software. Project work is proceeding immediately and the new DCCs are expected to be in service during summer 2010. Contact: Andre Rochon, telephone: (514) 787-4953. Simulator Upgrade L-3 MAPPS has been awarded a contract from Hydro-Québec to significantly upgrade its Gentilly-2 simulator. The simulator upgrade is part of a plant refurbishment project which will extend the life of the Gentilly-2 Nuclear Generating Station until the year 2040. The order also includes optional phases which could be selected later by Hydro-Québec for emulating the plant’s new turbine control system, a new plant display system and further modeling changes. Work has already started under a pre-authorization from Hydro-Québec and the new simulator is expected to enter service progressively in various phases until fall 2011. Cooperation Agreement The Shaw Group Inc. signed a strategic cooperation agreement with China’s State Nuclear Power Technology Corporation (SNPTC). The agreement is a task-order based contract, which allows both companies to issue tasks to support each other in growing nuclear infrastructure businesses. Shaw currently is under contract with SNPTC and other Chinese organizations to provide engineering, procurement, commissioning, information management and project management services for four AP1000 nuclear plants being built at the Haiyang nuclear power plant project in China’s Shandong province and the Sanmen nuclear power plant project in Zhejiang province. Contact: Gentry Grann, telephone: (225) 987-7372, email: gentry.brann@ shawgrp.com. Construction Cleared Local authorities in South Bohemia have signed a contract with Czech utility CEZ that clears obstacles to the construction of units 3 and 4 at the Temelin nuclear power plant in Czech Republic. CEZ confirmed to NucNet that the Council of South Bohemia had overturned a 2004 resolution blocking construction of the units. The contract, signed yesterday, will bring the equivalent of about 200 million US dollars to the region by 2018 for general infrastructure and development. Contact: David Dalton, email: david. dalton@worldnuclear.org. 16 www.nuclearplantjournal.com Nuclear Plant Journal, May-June 2009
New Documents EPRI 1. Nuclear Maintenance Applications Center: Preservation of Failed Parts to Facilitate Failure Analysis of Nuclear Power Plant Components. Product ID: 1016907, Published March, 2009. Equipment failure analysis and damage mode determination are cornerstones for improving equipment reliability. Methods and techniques for performing failure analysis are becoming more sophisticated and are used to prevent recurring equipment failures. Maintenance and engineering personnel usually perform at least initial troubleshooting and disassembly of failed components. 2. Nuclear Maintenance Applications Center: Tiered Valve Maintenance Program, Product ID: 1018015, Published March, 2009. Thousands of valves of various types with various actuators perform a variety of functions in a nuclear power plant. These valves require varying degrees of corrective, predictive, and preventive maintenance, depending on their safety significance, economic impact, or other factors such as operating environment or historical performance. 3. Steam Generator Management Program: Automated Analysis of Array Probe Eddy Current Data, Product ID: 1018559, Published March, 2009. Utilities perform eddy current tests on nuclear power plant steam generator (SG) tubes to detect degradation. This report summarizes the status of ongoing research to develop signal-processing algorithms that automate the analysis of eddy current test data. 4. US Steam Turbine Valve Metallurgy Guide, Product ID: 202+89+, Published March, 2009. This report provides nuclear and fossil plant personnel with current information on the metallurgical aspects of the steam turbine valve components used in U.S. power plants. 5. Materials Reliability Program: Inspection and Evaluation Guidelines for Reactor Vessel Bottom-Mounted Nozzles in U.S. PWR Plants (MRP-206), Product ID: 1016594, Published March, 2009. This report presents inspection and evaluation guidelines for reactor vessel bottom-mounted nozzles in U.S. pressurized water reactor (PWR) plants. 6. Quantifying Corrosion Products Removed from Fuel Assemblies by Ultrasonic Fuel Cleaning, Product ID: 1018718, Published April, 2009. Ultrasonic Fuel Cleaning (UFC) is a mechanical cleaning process developed by EPRI to remove corrosion product deposits (crud) that have formed on nuclear fuel assemblies during the operating cycle. This report documents the effort and procedure that will allow utilities to determine the mass of crud removed during UFC. 7. BWRVIP-210: BWR Vessel and Internals Project, XGEN Engineering Jet Pump Restrainer Bracket Repair Design, Product ID: 1018868, Published April, 2009. The purpose of this work is to develop conceptual designs for modification of jet pump restrainer brackets to provide rigid lateral restraint of the jet pump inlet mixers. 8. International Review Team Report: A Peer Review of the Yucca Mountain IM- ARC Total System Performance Assessment EPRI Model, Product ID: 1018711, Published April, 2009. The intent of this peer review is to provide an independent evaluation of EPRI’s TSPA code, IMARC, in light of EPRI’s role as an independent third party to the Yucca Mountain process. 9. Program on Technology Innovation: Information Integration for Equipment Reliability at Nuclear Plants, Product ID: 1018910, Published April, 2009. The nuclear power industry has made notable advances in the effectiveness of the equipment reliability process over the last decade. As the plants’ equipment and workforce age, it will be even more challenging to sustain and improve current high levels of equipment performance. 10. Surface Analysis of Pressurized Water Reactor Steam Generator Tubing Specimens: Results of Surface and Microstructural Analysis of Tubes from Diablo Canyon 1, Oconee 2, Seabrook, and Vogtle 1 and 2 PWRs, Product ID: 1018720, Published April, 2009. The amount and composition of surface oxides present on the surface of pressurized water reactor (PWR) reactor coolant system (RCS) components can have a major impact on fuel assembly corrosion product deposits during the operating cycle. This study analyzes primary side surface oxides of steam generator tubes from five U.S. PWRs. The above documents may be obtained from EPRI Order and Conference Center, 1300 West WT Harris Blvd., Charlotte, NC 28262; telephone: (800) 313-3774, email: orders@epri.com. Publication The ASTM International technical publication, STP 1492, Effects of Radiation on Materials: 23 rd International Symposium, features 18 peer-reviewed papers focused on the irradiation embrittlement of reactor pressure vessel steels. The new research provides a broad perspective on the development and application of trend curves used to predict fracture toughness transition temperatures in irradiated reactor pressure vessel steels. ISBN: 978-0- 8031-3421-8, 237 pages. Price: $74. Contact: ASTM Customer Service, telephone: (610) 832-9585, fax: (610) 832-9555, email: service@astm.org. Nuclear Plant Journal, May-June 2009 www.nuclearplantjournal.com 17
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