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AbstractAbstract
[en] The role of the regulator to progressively assure safety in order to arrive at the licensing stage without significant safety related issues is presented. Mexico considers such a role as a responsibility, especially when dealing with a utility that is building its first reactor. This concept may appear novel, however, it is presented here as inherent in any regulatory scheme. Based on the above mentioned considerations, the regulatory body of Mexico is prepared to provide assurance that during the transition period from construction to operation of the Laguna Verde facility, all possibile errors and defects are detected and corrected. In this manner Mexico will build its nuclear plant as safe as possible
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American Nuclear Society, Chicago, IL; p. 59-65; Feb 1983; p. 59-65; International meeting on thermal nuclear reactor safety (ANS topical meeting); Chicago, IL (USA); 29 Aug - 2 Sep 1982; Available from NTIS, PC A99/MF A01; 1 - GPO $13.00 as DE83901497
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Report
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Conference
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INIS IssueINIS Issue
Troncoso Fleitas, Mayra; Lopez Morones, Ramon; Huerta Bahena, Alejandro; Perez Diaz, Martin
2 nd Workshop on Nuclear Safety and Radiation Protection1996
2 nd Workshop on Nuclear Safety and Radiation Protection1996
AbstractAbstract
[en] This work intends to analyze 5 incidents at the Green Lagoon NPP and to characterize their relative importance in the risk level obtained in the APS original and thus to help to evaluate the specific operational and design problems of the plant according to the methodology proposed by the IAEA
Original Title
Evaluacion de incidentes en la unidad 1 de la Central Nuclear Laguna Verde usando su APS especifico
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Centro Nacional de Seguridad Nuclear; Centro de Proteccion e Higiene de las Radiaciones; 255 p; 1996; p. 164-166
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Book
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AbstractAbstract
No abstract available
Original Title
Rohrleitungen fuer ein mexikanisches Kernkraftwerk
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Source
Published in summary form only.
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Journal Article
Journal
Industrie-Anzeiger; ISSN 0019-9036; ; v. 104(26); p. 48-49
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AbstractAbstract
[en] The main features of the unit 1 of the Laguna Verde Power Plant is presented as well as the phases of the start-up process. The process includes various steps and tests up to start the commercial operation. (author)
Original Title
Puesta en marcha y operacion comerical de la unidad uno de la central Laguna Verde
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Source
American Nuclear Society, Rio de Janeiro, RJ (Brazil). Latin American Section; 569 p; 1991; p. 363-380; Symposium on Safety of Nuclear Power Plants in Latin America; Rio de Janeiro, RJ (Brazil); 9-13 Jun 1991; Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil
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Miscellaneous
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Conference
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AbstractAbstract
[en] In response to generic letter GL 88-20, Comision Federal de Electricidad and Instituto de Investigaciones Electricas have jointly developed the individual plant examination (IPE) for the Laguna Verde nuclear power station unit I (LVNPS). This plant is a 675-MW(electric) boiling water reactor (BWR/5) with a reinforced concrete Mark-II containment. The approach used to fulfill the IPE requirements was to make a level-1 probabilistic risk assessment (IPE level 1) plus a containment performance analysis including the behavior and release of the fission products to the environment (IPE level 2). This paper describes the level-2 portion of the LVNPS IPE, paying special attention to both some improvements to the traditional analytical methods and to the main results
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Winter meeting of the American Nuclear Society (ANS) and the European Nuclear Society (ENS); Washington, DC (United States); 10-14 Nov 1996; CONF-961103--
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Journal Article
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AbstractAbstract
[en] The present work describes the event occurred at the Laguna Verde nuclear power plants Unit 1 during its fourth cycle ensembles; the first failure, by means of a test of power suppression, and the second one, during the sipping accomplished in the four refuelling of the unit. Also it describes the re-evaluation of the event accomplished by the licenser, the manufacturer and the Mexican agency
Original Title
Falla de combustible en la central de Laguna Verde unidad 1 durante el ciclo 4
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Source
Centro Nacional de Seguridad Nuclear; Centro de Proteccion e Higiene de las Radiaciones; 255 p; 1996; p. 141-144
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Book
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INIS IssueINIS Issue
AbstractAbstract
[en] The paper addresses the regulatory framework established for the design, construction and operation of the NPP. The regulatory bases of the inspection program are mentioned.A summary of the inspection and reviewing activities carried out by the former Nuclear Safety Management Construction area during the construction stage, taking the year 1977 as the beginning of regular inspection activities for this construction stage, and up to the year 1987, when this one is considered as practically completed, and a stage of pre-operational tests has been started. Finally, the main inspection areas are described, and a summary is given of the classification of deficiencies detected during the inspections
Original Title
Actividades de inspeccion del organo regulador mexicano durante la fase de construccion de la unidad 1 de la central nucleoenergetica de Laguna Verde
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Source
Centro Nacional de Seguridad Nuclear, La Habana (Cuba); Centro de Proteccion e Higiene de las Radiaciones, La Habana (Cuba); 255 p; 1996; p. 92-94
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Book
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Alvaradao, F.B.
Training for the qualification and competence of nuclear power plant personnel. Working material1993
Training for the qualification and competence of nuclear power plant personnel. Working material1993
AbstractAbstract
[en] This document describes the training of Laguna Verde Nuclear Power Plant Personnel, from recruitment and screening, through training to retraining to maintain the necessary skills and qualifications
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Source
International Atomic Energy Agency, Vienna (Austria); 401 p; 1993; p. 231-252; IAEA review meeting on training for the qualification and competence of nuclear power plant personnel; Vienna (Austria); 22-26 Feb 1993
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Report
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Ledesma Carrion, Rafael; Ramirez Guerrero, Ruben; Perez Perez, Ricardo; Mamani Alegria, Yuri
2nd Workshop on Nuclear Safety and Radiation Protection1996
2nd Workshop on Nuclear Safety and Radiation Protection1996
AbstractAbstract
[en] The work developed shows how the performance indicators are used with the objective of providing information of the trends and operational behavioural standards of the Laguna Verde NPP in a rapid and accessible way, so the this information could be useful to the personnel of the National Center of Nuclear Safety, in their tasks of identification and follow-up of the safe operational performance of the NPP, upon showing a reduction or an increase in the safe operation of the Laguna Verde NPP
Original Title
Incorporacion de los indicadores de desempeno como indices de la operacion segura de le central nucleoelectrica de Laguna Verde
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Secondary Subject
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Centro Nacional de Seguridad Nuclear; Centro de Proteccion e Higiene de las Radiaciones; 255 p; 1996; p. 174-176
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Book
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INIS VolumeINIS Volume
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Ocampo, H.; Esquivias, J.; Serrano, S.A.; Torres, C.; Perusquia, R.; Sanchez, L.; Naffah, G.
In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 19891990
In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 19891990
AbstractAbstract
[en] The Laguna Verde Nuclear Power Plant (LVNPP) is the first of its kind in Mexico. It is owned and operated by the Comision Federal de Electricidad (CFE), the National electric utility. Right now the plant is undergoing the start-up procedures and it reached 50% of power last September. In 1985 CFE received IAEA support to obtain a Fuel Management System (FMS) Computer Code Package from Scandpower Inc., and this paper presents the results of the calculation of the Nuclear Data Bank (NDB) and the simulation of the first cycle for the unit one of the LVNPP. The data have been tested and validated against the General Electric Cycle Management Report (GE-CMR). Results obtained using the FMS codes are compared to those obtained using GE codes. (author). 5 refs, 26 figs, 2 tabs
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Source
International Atomic Energy Agency, Vienna (Austria); 438 p; Nov 1990; p. 383-393; Technical committee meeting and workshop on in-core fuel management; Vienna (Austria); 4-7 Dec 1989
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Report
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