OSART mission highlights 1991-1992. Operational safety practices in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

This report continues the practice of providing summaries of the OSART missions but the format is the first of its kind. Summaries of missions in the period 1983-1990 have covered missions to operational plants, missions to plants under construction or approaching commissioning and a compilation of good practices identified in OSART missions as separate publications. The format of this report includes all such aspects in one document.

OSART mission highlights 1991-1992. Operational safety practices in nuclear power plants

International Nuclear Information System (INIS)

1995-05-01

This report continues the practice of providing summaries of the OSART missions but the format is the first of its kind. Summaries of missions in the period 1983-1990 have covered missions to operational plants, missions to plants under construction or approaching commissioning and a compilation of good practices identified in OSART missions as separate publications. The format of this report includes all such aspects in one document

OSART Independent Safety Culture Assessment (ISCA) Guidelines

International Nuclear Information System (INIS)

2016-01-01

Safety culture is understood as an important part of nuclear safety performance. This has been demonstrated by the analysis of significant events such as Chernobyl, Davis Besse, Vandellos II, Asco, Paks, Mihamma and Forsmark, among others. In order to enhance safety culture, one essential activity is to perform assessments. IAEA Safety Standard Series No. GS-R-3, The Management System for Facilitites and Activities, states requirements for continuous improvement of safety culture, of which self, peer and independent safety culture assessments constitute an essential part. In line with this requirement, the Independent Safety Culture Assessment (ISCA) module is offered as an add-on module to the IAEA Operational Safety Review Team (OSART) programme. The OSART programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. By including the ISCA module in an OSART mission, the receiving organization benefits from the synergy between the technical and the safety culture aspects of the safety review. The joint operational safety and safety culture assessment provides the organization with the opportunity to better understand the interactions between technical, human, organizational and cultural aspects, helping the organization to take a systemic approach to safety through identifying actions that fully address the root causes of any identified issue. Safety culture assessments provide insight into the fundamental drivers that shape organizational patterns of behaviour, safety consciousness and safety performance. The complex nature of safety culture means that the analysis of the results of such assessments is not as straightforward as for other types of assessment. The benefits of the results of nuclear safety culture assessments are maximized only if appropriate tools and guidance for these assessments is used; hence, this comprehensive guideline has been developed. The methodology explained

The work of the Operational Safety Review Team (OSART)

International Nuclear Information System (INIS)

Hide, K.W.

1996-01-01

The Operational Safety Review Team (OSART) programme was set up by the IAEA in 1982 to assist Member States to enhance the operational safety of nuclear power plants. Each team is staffed by senior experts in the relevant fields. The review team discusses with plant staff the existing operational programmes for plant which may be under construction, being commissioned or already operating. Following a detailed examination of a safety programme, the OSART team lists strengths and weaknesses and makes recommendations on how to overcome the latter. Since their conclusions are based on the best prevailing international practice, they may be more stringent than those based on national criteria. The results of the 77 missions conducted at 62 plants in 28 countries by the end of 1994 are summarised. (UK)

OSART mission highlights related to on-the-job training

International Nuclear Information System (INIS)

Mazour, T.; Hide, K.

1996-01-01

This paper summarizes the highlights, related to the topic of on-the-job training (OJT), for Agency OSART missions conducted since 1990 (a total of 27 missions). Recommendations and suggestions for improvements related to on-the-job training and qualification programmes are discussed, as well as Good Practices and Good Performances. For Good Practices and Good Performances, the plant is identified to aid in follow-up by meeting participants. For recommendations and suggestions, the number of plants that had recommendations/findings in this area are identified by a number in parentheses after the item. The paper takes a broad approach toward highlights that are related to OJT. For example, there have been a number of OSART recommendations and suggestions concerning responsibilities, authorities and interfaces for NPP activities. These recommendations and suggestions relate not only to responsibilities and interfaces for on-the-job training and qualification programmes, but also to other areas as well

IAEA Operational Safety Team (OSART) Reviews Progress at Fessenheim Nuclear Power Plant, France

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has evaluated the French Nuclear Power Plant (NPP) at Fessenheim to assess how the facility has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2009. The IAEA assembled a team of experts at the request of the Government of France to conduct the mission. Follow-up missions are standard components of the OSART programme and are conducted 18-24 months after the initial OSART mission. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the team performed its review from 7 to 11 February 2011. The team assessed how the Fessenheim NPP has addressed the recommendations and suggestions made during the 2009 OSART mission. The team was made up of experts from Slovakia, Switzerland and the IAEA. The review covered the areas of Management, Organization and Administration; Training and Qualifications; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. The conclusions of the follow-up review are based on the IAEA's Safety Standards and proven good international practices. There were 21 issues raised by the 2009 mission. During the follow-up mission, the team assessed that six issues had been resolved, thirteen had made satisfactory progress to date and two had made insufficient progress to date. 'Resolved' describes action plans for improvement that have been fully implemented; 'satisfactory progress to date' describes action plans that have been developed but are not yet fully implemented; and 'insufficient progress to date' describes situations where additional consideration or strengthening of improvement plans is necessary. Examples of issues falling into different resolution categories include: The plant has resolved the suggestion to establish a process to review initial training materials on a regular basis

Energies and media Nr 38 - Always improving safety: the intervention of 'peers'; IAEA, its OSART, etc.; WANO must be known

International Nuclear Information System (INIS)

Baschwitz, Robert

2012-06-01

The first part of this issue comments the 'peer review' as a promising approach to avoid nuclear accidents and incidents to occur again. Such a review or inspection could be performed by international experts at regular intervals. In order to outline the interest of this approach, the authors describe who used to be in charge of safety before 2010-2011, i.e. what was the mission of the operator, what was the role of the national nuclear safety authority, what were the missions of the IAEA. It notably addresses the role of its OSARTs (Operational Safety Review Teams) by briefly describing how these teams were built up and operated. It also describes the role of WANO (World Association of Nuclear Operators) and its 'peer reviews'. It evokes the activities of this association (number of studied events, of inspection missions, of published reports). Then, the authors describe the evolution since 2010 and Fukushima (March 2011): planned evolutions within WANO by 2015, evolutions within the IAEA and its OSARTs (notably design reviews), and within the safety authorities

Report of the OSART (Operational Safety Review Team) mission to the Ignalina, units 1 and 5 nuclear power plant Republic of Lithuania 4 to 22 September 1995

International Nuclear Information System (INIS)

1996-03-01

This report presents the results of the IAEA Operational Safety Review Team (OSART) review of Ignalina nuclear power plant in Lithuania. It describes recommendations and suggestions for improvements affecting operational safety provided to the responsible Lithuanian authorities for consideration and also describes a good practice for consideration by other nuclear power plants. Distribution of this OSART report is at the discretion of the Government of Lithuania and, until it is derestricted, the IAEA will make the report available to third parties only with the express permission of the Government of Lithuania. Any use of, or reference to, this report that may be made by the competent Lithuanian organizations is solely their responsibility

IAEA OSART/EXPERT follow-up review mission completes assessment of actions taken by Paks Nuclear Power Plant

International Nuclear Information System (INIS)

2004-01-01

On 28 February 2004 the IAEA completed its follow-up review mission to assess the actions taken by Paks nuclear power plant (NPP) in response to the Agency's recommendations and suggestions made during the 2001 Operational Safety Review Team (OSART) mission and the 2003 Expert mission that investigated the fuel cleaning incident at the Paks NPP in Hungary. The mission was requested by the Hungarian Government to provide an independent assessment of the actions taken by Paks NPP. The IAEA team determined that the actions taken by Paks have resulted in tangible progress and concluded that all issues were either fully resolved or progressing satisfactorily. In a press conference, the team's conclusions in five areas were highlighted: management, Regulatory Oversight/Interface, operations and maintenance, including operating experience, radiation protection, emergency planning and preparedness, and transparency

IAEA Completes First Ever Corporate Safety Review, at Czech Republic's CEZ

International Nuclear Information System (INIS)

2013-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of corporate safety performance at CEZ a.s., the largest national electricity company in the Czech Republic. For the first time since the Agency launched its Operational Safety Review Team (OSART) missions in 1982, the team addressed corporate aspects of a company in relation to nuclear safety. The team noted a series of good practices and proposed recommendations to strengthen some safety measures. Assembled at the request of the Government of the Czech Republic, the first ''Corporate OSART'' review, which ran from 30 September to 9 October 2013, addressed corporate aspects necessary to ensure the safe operation of the Dukovany and Temelin Nuclear Power Plants (NPPs). The mission included experts from Finland, France, Romania, USA and the IAEA. OSART services aim to improve operational safety at nuclear facilities by objectively assessing safety performance using the IAEA's Safety Standards and proposing recommendations for improvement where appropriate. The missions serve as a channel to exchange information and experience and provide Member States with good practices. A ''Corporate OSART'' is an OSART mission organized to review those centralized functions of the corporate organization of a utility with multiple nuclear plant sites and conventional plant sites that affect all the operational safety aspects of the nuclear power plants of this utility. ''OSART missions are one of the most important tools of the Agency to ensure better and wider implementation of the IAEA Safety Standards,'' said Denis Flory, Deputy Director General in the IAEA Department of Nuclear Safety and Security. ''Since 1982, we have conducted close to 200 safety review missions around the globe; however, this mission is the first of its kind because we focused on the corporate performance that is a necessity for a safe operation of NPPs,'' Flory added

Osnovnye printsipy lecheniya diabeticheskoyneyroosteoartropatii

Directory of Open Access Journals (Sweden)

Irina Nikolaevna Ul'yanova

2006-12-01

Full Text Available Диабетическая нейроостеоартропатия (артропатия Шарко, ДНОАП является одним из поздних осложнений сахарного диабета (СД, которое сопровождается асептической деструкцией костного скелета стопы на фоне выраженной диабетической нейропатии. Частота развития ДНОАП колеблется от 1,5% среди всех больных СД до 50% среди пациентов с диабетической нейропатией. Учитывая то, что продолжительность жизни больных СД растет, увеличивается и частота ДНОАП. Несмотря на то, что характерные изменения при ДНОАП были описаны более ста лет назад, до сих пор не существует однозначных данных о распространенности, патогенезе и наиболее эффективной тактике лечения больных с этой патологией.

Reviewing computer capabilities in nuclear power plants

International Nuclear Information System (INIS)

1990-06-01

The OSART programme of the IAEA has become an effective vehicle for promoting international co-operation for the enhancement of plant operational safety. In order to maintain consistency in the OSART reviews, OSART Guidelines have been developed which are intended to ensure that the reviewing process is comprehensive. Computer technology is an area in which rapid development is taking place and new applications may be computerized to further enhance safety and the effectiveness of the plant. Supplementary guidance and reference material is needed to help attain comprehensiveness and consistency in OSART reviews. This document is devoted to the utilization of on-site and off-site computers in such a way that the safe operation of the plant is supported. In addition to the main text, there are several annexes illustrating adequate practices as found at various operating nuclear power plants. Refs, figs and tabs

IAEA Concludes Safety Review at Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of nuclear safety experts noted a series of good practices and made recommendations to reinforce some safety measures during a review of operational safety at France's Gravelines Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 12 November 2012, focused on aspects essential to the safe operation of the NPP. The team was composed of experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain, Ukraine and the IAEA. The review covered the areas of management, organization and administration; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their possible use elsewhere. Examples include the following: - The Power Plant uses a staff-skills mapping process that significantly enhances knowledge of the facility's collective and individual skills and provides proactive management to address the loss of such skills; - As a measure to reduce the risk of workers' radiation exposure, the Power Plant uses a system to ensure that dose rate measurements are carried out at a precise distance from the source of radiation; and - Flood protection of the Power Plant is supported by special technical guidance documents and associated arrangements. The team identified a number of proposals for improvements to operational safety at Gravelines NPP. Examples include the following: - The Power Plant should reinforce its measures to prevent foreign objects from entering plant systems; - The Power Plant should ensure the 24-hour presence of an operator

Long term operation of nuclear power plants – IAEA SALTO missions observations and trends

Energy Technology Data Exchange (ETDEWEB)

Krivanek, Robert, E-mail: r.krivanek@iaea.org [Operational Safety Section, Department of Nuclear Safety and Security, International Atomic Energy Agency (IAEA), Vienna 1400 (Austria); Havel, Radim, E-mail: Radim.Havel@gmail.com [RESCO, Nitranska 894/8, 10100 Praha 10 (Czech Republic)

2016-08-15

Highlights: • During the period 2005–mid 2015, 22 SALTO peer review missions and 2 LTO modules of OSART missions were conducted. • Analysis of these mission results and main trends observed are gathered in this paper. • The main task of the assessment performed was to evaluate and give a weight to the evaluation. • Results of SALTO follow-up missions as well as OSART follow-up missions with LTO module are summarized. • The SALTO peer review service is strongly recommended for NPPs prior to entering LTO period. - Abstract: This paper builds on paper “Long term operation of nuclear power plants – IAEA SALTO peer review service and its results”, NED8070, presented in Nuclear Engineering and Design in September 2014. This paper presents the analysis of SALTO mission results and main trends observed so that all the most important results of SALTO missions are gathered in one paper. The paper also includes the results of LTO module reviews performed in the frame of OSART missions where applicable as well as follow-up missions. This paper is divided in three main Sections. Section 1 provides brief introduction to SALTO peer review service. Section 2 provides overview of performed SALTO missions and LTO modules of OSART missions performed between 2005 and mid-2015. Section 3 summarizes the most significant observations and trends resulting from the missions between 2005 and mid-2015. Section 4 summarizes the results of SALTO follow-up missions as well as OSART follow-up missions.

Operational safety of nuclear installations, Netherlands, Borssele, 6-10 April, 1987

International Nuclear Information System (INIS)

1987-01-01

The OSART team observed the increased supervision during shift operations and noticed a positive impact due to increased management presence in the plant. No discrepancies or instances of questionable safety system status was found. The completion of these post OSART long term projects will more clearly identify and formalize some of the processes in the plant in order to continue to assure that the Borssele plant will continue to be operated safely

IAEA Operational Safety Team Reviews Cattenom Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has reviewed operational safety at France's Cattenom Nuclear Power Plant (NPP) noting a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled an international team of experts at the request of the Government of France to conduct an Operational Safety Review (OSART) of Cattenom NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 14 November to 1 December 2011. The team was made up of experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Japan, Russia, Slovakia, South Africa, Sweden, Ukraine, the United Kingdom and the IAEA. The team at Cattenom conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. Cattenom is the first plant in Europe to voluntarily undertake a Severe Accident Management review during an OSART review. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: Sheets are displayed in storage areas where combustible material is present - these sheets are updated readily and accurately by the area owner to ensure that the fire limits are complied with; A simple container is attached to the neutron source handling device to ensure ease and safety of operations and reduce possible radiation exposure during use

IAEA Concludes Safety Review at Chooz Nuclear Power Plant in France

International Nuclear Information System (INIS)

2013-01-01

Full text: An IAEA-led international team of nuclear safety experts noted good practices and made recommendations to reinforce safety measures during a review of operational safety at France's Chooz Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 17 June, focused on aspects essential to the safe operation of the NPP. The team comprised experts from Switzerland, Belgium, Germany, China, India, United Kingdom, Czech Republic, Canada, Hungary and the IAEA. The review covered the areas of management, organization and administration; training and qualification of personnel; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team identified good plant practices that will be shared with the rest of the nuclear industry for consideration. Examples include: The plant has a professional development programme as part of a joint employment effort shared by the plant and its contractors. This enables trainees to develop professional capability, understand practices and gain experience from other nuclear power plants in terms of work planning and coordination; The plant has built a strong relationship between the on-shift response team of the plant and the local fire brigade to improve firefighting and rescue operations; Self-assessment groups discuss and resolve specific issues within operations, empowering operations personnel to take ownership of improvement programmes; and The plant has improved warnings at entrances to all o range zones , areas of elevated dose rates to which only authorized staff have access. The team identified a number of improvements to operational safety at Chooz NPP. Examples include: The plant should review its process for the

IAEA Team Reviews Safety Progress at French Nuclear Power Plant 19-23 May 2014

International Nuclear Information System (INIS)

2014-01-01

An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has evaluated the Gravelines Nuclear Power Plant (NPP) in France to assess how the station has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2012. The IAEA assembled a team of experts at the request of the Government of France to conduct the follow-up OSART mission at Gravelines NPP from 19 to 23 May 2014. Follow-up missions are standard components of the OSART programme; they are typically conducted 15-24 months after the initial OSART mission. The IAEA mission in 2012 made a number of recommendations and suggestions for consideration by the Gravelines NPP operators. The station thoroughly analyzed the OSART recommendations and suggestions and developed corrective action plans. In 18 months, the Gravelines plant has achieved the level ''resolved;; or ''satisfactory progress'' in almost all of the recommendations and suggestions made by the OSART in November 2012. During the follow-up mission, the team assessed that the operators have resolved the issues in several areas, including: Undertaking initiatives to improve fire prevention; Reinforcing contamination control practices; and Enhancing capabilities to protect emergency workers in the event of a release of radioactivity. The team identified some issues which have achieved satisfactory progress toward resolution, but need further work, including: Further improvement of measures to preventing the ingress of items or chemicals into circuits and equipment; Comprehensive application of the corrective actions programme; and Reinforcement of the containment protection system in the event of an extremely adverse situation. The team identified the following issue as one which has made insufficient progress toward resolution and needs further work: Emergency response arrangements do not follow current IAEA safety standards recommending that the plant should have a person on

IAEA Newsbriefs. V. 9, no. 1(63). Feb-Mar 1994

International Nuclear Information System (INIS)

1994-01-01

This issue gives brief information on the following topics: IAEA Safeguards Inspections Resume in the DPRK, Nuclear Safety Convention, Nuclear Inspections in Iraq, Strengthening the Safeguards System, Nuclear Non-proliferation and Verification, Ban on Sea Dumping of Radioactive Waste, The Decades Project, Food Irradiation's Practical Utilization, International Nuclear Event Scale, Asset and Osart Missions with the subtopics 'Assessment of Safety Significant Events Team (ASSET)', and 'Operational Safety Review Teams(OSARTs)', Transport of Radioactive Waste, and other short information

IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed Slovakia's Bohunice Nuclear Power Plant (BNPP) for its safety practices and has noted a series of good practices as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of Slovak Republic to conduct an Operational Safety Review (OSART) of Bohunice NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 1 to 18 November 2010. The team was made up of experts from Belgium, Canada, China, the Czech Republic, France, Sweden, the United Kingdom and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at BNPP conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely is under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. Long Term Operation assessment has been requested by the plant in addition to the standard OSART program. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: BNPP has implemented a comprehensive set of technical and organizational measures which have significantly reduced the production of liquid radioactive waste; BNPP has developed an automatic transfer of dosimetry data

IAEA Leads Operational Safety Mission to Smolensk Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) has reviewed the Smolensk Nuclear Power Plant (NPP) near Desnogorsk, in Russia's Smolensk region, for its safety practices and has noted a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled the team at the request of the Government of the Russian Federation to conduct an Operational Safety Review (OSART) of the NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 5 to 22 September 2011. The team was made up of experts from China, India, Lithuania, Slovakia, South Africa, Sweden, UK, USA, the World Association of Nuclear Operators and the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Smolensk NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; and Chemistry. Throughout the review, the exchange of information between the OSART experts and plant personnel was very open, professional and productive. The plant's staff were found to be motivated, well trained, knowledgeable and experienced. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include the following: Illuminated hot-spot wire to identify higher radiation levels is used in the radiation-controlled area to reduce exposures when working in the controlled area; Modern and state-of-the-art training infrastructure and facilities are available at the plant. These include: maintenance training centre; multimedia simulator for the refueling machine; and safety

IAEA Leads Operational Safety Mission to Rajasthan Atomic Power Station 3 and 4

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of safety practices at Units 3 and 4 of the Rajasthan Atomic Power Station in Rawatbhata. The team noted a series of good practices and made recommendations and suggestions to reinforce safety practices. The IAEA assembled the Operational Safety Review Team (OSART) at the request of the Government of India. Led by the IAEA's Division of Nuclear Installation Safety, the team performed an in-depth operational safety review from 29 October to 14 November 2012. The team was comprised of experts from Canada, Belgium, Finland, Germany, Romania, Slovakia, Slovenia, Sweden and the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Power Plant. The conclusions of the review are based on the IAEA's Safety Standards and good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. The OSART team identified a number of good practices of the plant. These will be shared in due course by the IAEA with the global nuclear industry for consideration. Examples include the following: - The Power Plant's safety culture cultivates a constructive work environment and a sense of accountability among the Power Plant personnel, and gives its staff the opportunity to expand skills and training; - The Power Plant's Public Awareness Programme provides educational opportunities to the local community about nuclear and radiation safety; - The Power Plant has a Management of Training and Authorization system for effective management of training activities; and - The Power Plant uses testing facilities and mockups to improve the quality of maintenance work and to reduce radiation doses. The OSART

Reviewing surveillance activities in nuclear power plants

International Nuclear Information System (INIS)

1989-03-01

This document provides guidance to Operational Safety Review Teams (OSARTs) for reviewing surveillance activities at a nuclear power plant. In addition, the document contains reference material to support the review of surveillance activities, to assist within the Technical Support area and to ensure consistency between individual reviews. Drafts of the document have already been used on several OSART missions and found to be useful. The document first considers the objectives of an excellent surveillance programme. Investigations to determine the quality of the surveillance programme are then discussed. The attributes of an excellent surveillance programme are listed. Advice follows on how to phrase questions so as to obtain an informative response on surveillance features. Finally, specific equipment is mentioned that should be considered when reviewing functional tests. Four annexes provide examples drawn from operating nuclear power plants. They were selected to supplement the main text of the document with the best international practices as found in OSART reviews. They should in no way limit the acceptance and development of alternative approaches that lead to equivalent or better results. Refs, figs and tabs

IAEA Leads Operational Safety Mission to Armenian Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed the Armenian Nuclear Power Plant (ANPP) near Metsamor for its safety practices and has noted a series of good practices, as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of the Republic of Armenia to conduct an Operational Safety Review (OSART) of the NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 16 May to 2 June 2011. The team was made up of experts from Finland, France, Lithuania, Hungary, Netherlands, Slovakia, UK, USA, EC and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. Experts participating in the IAEA's June 2010 International Conference on Operational Safety of Nuclear Power Plants (NPP) reviewed the experience of the OSART programme and concluded: In OSART missions NPPs are assessed against IAEA safety standards which reflect the current international consensus on what constitutes a high level of safety; and OSART recommendations and suggestions are of utmost importance for operational safety improvement of NPPs. Armenia is commended for openness to the international nuclear community and for actively inviting IAEA safety review missions to submit their activities to international scrutiny. Examples of IAEA safety reviews include: Design Safety Review in 2003; Review of Probabilistic Safety Assessment in 2007; and Assessment of Seismic Safety Re-Evaluation in 2009. The team at ANPP conducted an in-depth review of the aspects essential to the safe operation of the plant, which is largely under the control of the site management

IAEA Operational Safety Team Reviews Saint-Alban Nuclear Power Plant, France

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed safety practices at France's Saint-Alban Nuclear Power Plant (NPP) and has highlighted a set of strong practices as well as a series of recommendations to reinforce them. The IAEA assembled the team at the request of the Government of France to conduct an Operational Safety Review (OSART) of the Saint-Alban NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review from 20 September to 6 October 2010. The team was made up of experts from Belgium, Canada, the Czech Republic, Germany, Lithuania, the Netherlands, Slovakia, Sweden and the USA. An OSART mission is designed to review programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Saint-Alban conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely are under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: A safety guideline for outages; The use of remote video surveillance of fuel inspection and handling activities; A motivational tool for plant staff regarding the benefits of operating experience and associated corrective actions; and Use of a sophisticated key control system

Report of a consultants` meeting to review the IAEA programme on operational safety services as part of the programme performance assessment system (PPAS) within the IAEA

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

The consultants consider that the ASCOT (Assessment of Safety Culture in Organizations Team), ASSET (Assessment of Safety Significant Events Team), and OSART (Operational Safety Review Team) programmes contribute to enhancing safe performance of Member States nuclear power plants. Continued co-ordination with the World Association of Nuclear Operators and national programmes in addition to continued emphasis on developing self assessment capabilities at the power plants will contribute to continuing improvement. International performance indicators clearly portray improvements in almost all areas. For example, the incidence of unplanned scrams and the unavailability of systems important to safety reduced. All three programmes ASCOT, ASSET and OSART may be improved by: tailoring them to meet the requested need. This includes not only the use of the OSART modular concepts but also the mixing and matching of the programmes. All three programmes can be enhanced by the sharing and use of their individual current techniques. The balance between assistance for conducting self assessment and direct assessment activities must be carefully considered. Country profiles could assist the Agency staff in advising Member States on request in the technique; power plant assistance or direct assessment, that would yield the best result. It is therefore recommended that the Agency go forward with the effort to develop these profiles. Figs, tabs.

Report of a consultants' meeting to review the IAEA programme on operational safety services as part of the programme performance assessment system (PPAS) within the IAEA

International Nuclear Information System (INIS)

1996-09-01

The consultants consider that the ASCOT (Assessment of Safety Culture in Organizations Team), ASSET (Assessment of Safety Significant Events Team), and OSART (Operational Safety Review Team) programmes contribute to enhancing safe performance of Member States nuclear power plants. Continued co-ordination with the World Association of Nuclear Operators and national programmes in addition to continued emphasis on developing self assessment capabilities at the power plants will contribute to continuing improvement. International performance indicators clearly portray improvements in almost all areas. For example, the incidence of unplanned scrams and the unavailability of systems important to safety reduced. All three programmes ASCOT, ASSET and OSART may be improved by: tailoring them to meet the requested need. This includes not only the use of the OSART modular concepts but also the mixing and matching of the programmes. All three programmes can be enhanced by the sharing and use of their individual current techniques. The balance between assistance for conducting self assessment and direct assessment activities must be carefully considered. Country profiles could assist the Agency staff in advising Member States on request in the technique; power plant assistance or direct assessment, that would yield the best result. It is therefore recommended that the Agency go forward with the effort to develop these profiles. Figs, tabs

IAEA Leads Operational Safety Mission to Muehleberg Nuclear Power Plant

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency today concluded a review of the safety practices at the Muehleberg Nuclear Power Plant (NPP) near Bern in Switzerland. The team noted a series of good practices and made recommendations and suggestions to reinforce them. The IAEA assembled the Operational Safety Review Team at the request of the Swiss government. The team, led by the IAEA's Division of Nuclear Installation Safety, performed an in-depth operational safety review from 8 to 25 October 2012. The team comprised experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Slovakia, Sweden, the United Kingdom and the United States as well as experts from the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Muehleberg NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry, Emergency Planning and Preparedness, Severe Accident Management and Long-Term Operation. The OSART team made 10 recommendations and 11 suggestions related to areas where operations of Muehleberg NPP could be further improved, for example: - Plant management could improve the operating experience program and methods throughout the plant to ensure corrective actions are taken in a timely manner; - In the area of Long-Term Operation, the ageing management review for some systems and components is not complete and the environmental qualification of originally installed safety cables has not yet been revalidated for long-term operation; and - The plant provisions for the protection of persons on the site during an emergency with radioactive release can be improved to minimize health risks to plant personnel. The team also identified 10 good

IAEA Completes Safety Review at Czech Nuclear Power Plant

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts, led by the International Atomic Energy Agency (IAEA), today completed a review of safety practices at Temelin Nuclear Power Station in the Czech Republic. The team highlighted the Power Plant's good practices and also recommended improvements to some safety measures. At the request of the Government of the Czech Republic, the IAEA assembled a team of nuclear installation safety experts to send an Operational Safety Review Team (OSART) to the Power Plant, and the mission was conducted from 5 to 22 November 2012. The team was comprised of experts from Brazil, Hungary, Slovakia, South Africa, Sweden, Ukraine and the United Kingdom. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the Plant's overall safety status. The team at Temelin conducted an in-depth review of the functions essential to the safe operation of the Power Plant, which are under the responsibility of the site's management. The review covered the areas of management, organization and administration; operations; maintenance; technical support; operating experience; radiation protection; chemistry; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of potential application elsewhere. Examples include the following: - The Power Plant has adopted effective computer software to improve the efficiency of the plant to prepare and isolate equipment for maintenance; - The Power Plant undertakes measures to control precisely the chemical parameters that limit corrosion in the reactor's coolant system, which in turn reduce radiation exposure to the workforce; and - The Temelin

IAEA-led Operational Safety Team Reviews Dukovany Nuclear Power Plant, Czech Republic

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has commended the Dukovany Nuclear Power Plant (NPP) in the Czech Republic for its safety practices and has also made a series of recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of the Czech Republic to conduct an Operational Safety Review (OSART) of Dukovany NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 6 to 23 June 2011. The team was made up of experts from Armenia, Germany, Hungary, Romania, Slovenia, Sweden, the UK and the USA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Dukovany conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: The plant uses an integrated approach to recruit, select, psychologically assess and train new employees. This approach has resulted in consistently high success rates for licensed operator examinations and the identification of potential candidates for various plant departments; The performance

International co-operation

International Nuclear Information System (INIS)

1998-01-01

A brief account of activities in international co-operation carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. Professionality of the Bohunice NPPs staff was highly appreciated by inviting them to be the OSART team members

Sovremennye printsipy vedeniya bol'nykh s sindromom diabeticheskoy stopy

Directory of Open Access Journals (Sweden)

Gagik Radikovich Galstyan

2005-09-01

Full Text Available В последние 15-20 лет отмечается определенный прогресс в понимании патогенетических основ поражений нижних конечностей при сахарном диабете (СД. Значительные успехи в лечении данной категории пациентов на сегодняшний день не подвергаются сомнению. Вместе с этим проблема оказания помощи больным с поражениями стоп является одной из самых актуальных, а число ампутаций нижних конечностей в большинстве развитых стран неуклонно растет. Это ведет к увеличению числа инвалидов, высокой смертности лиц с диабетом, существенным образом увеличивает расходы здравоохранения и социального обеспечения.

Reviewing operational experience feedback

International Nuclear Information System (INIS)

1991-04-01

The purpose of this document is to provide detailed supplementary guidance to OSART experts to aid in the evaluation of operational experience feedback (OEF) programmes at nuclear power plants. The document begins by describing the objectives of an OEF programme. It goes on to indicate preparatory work and investigatory guidance for the expert. Section 5 describes attributes of an excellent OEF programme. Appended to these guidelines are examples of OEF documents from various plants. These are intended to help the expert by demonstrating the actual implementation of OEF in practice. These guidelines are in no way intended to conflict with existing national regulations and rules. A comprehensive OEF programme, as described in Section 2, would be impossible to evaluated in detail in the amount of time typically allocated for assessing OEF in an OSART review. The expert must use his or her time wisely by concentrating on those areas that appear to be the weakest

Glucocorticosteroid-induced osteoporosis: pathogenesis, prevention, treatment

Directory of Open Access Journals (Sweden)

I A Baranova

2008-01-01

Full Text Available Glyukokortikoidindutsirovannyy osteoporoz (GIO - odno iz naibolee tyazhelykh oslozhneniy dlitel'noy (bolee 3 mes sistemnoy terapii glyukokortikoidami (SGK. On razvivaetsya u bol'nykh lyubogo vozrasta i pola i yavlyaetsya naibolee chastoy sistemnoy formoy vtorichnogo osteoporoza (OP. Bystraya poterya kostnoy massy proiskhodit uzhe v pervye mesyatsy lecheniya SGK. Perelomy ot minimal'noy travmy voznikayut pri bolee vysokikh pokazatelyakh mineral'noy plotnosti kosti, chem u bol'nykh pervichnym OP. Dazhe ispol'zovanie malykh doz SGK privodit k povysheniyu riska perelomov, s uvelicheniem sutochnoy dozy risk perelomov vozrastaet. U patsientov, primenyayushchikh vysokie dozy ingalyatsionnykh GK (IGK, uvelichenie riska OP i perelomov v bol'shey stepeni obuslovleno tyazhest'yu respiratornogo zabolevaniya, chem terapiey IGK. Predstavleny sovremennye printsipy profilaktiki i lecheniya GIO.

Reviewing industrial safety in nuclear power plants

International Nuclear Information System (INIS)

1990-02-01

This document contains guidance and reference materials for Operational Safety Review Team (OSART) experts, in addition to the OSART Guidelines (TECDOC-449), for use in the review of industrial safety activities at nuclear power plants. It sets out objectives for an excellent industrial safety programme, and suggests investigations which should be made in evaluating industrial safety programmes. The attributes of an excellent industrial safety programme are listed as examples for comparison. Practical hints for reviewing industrial safety are discussed, so that the necessary information can be obtained effectively through a review of documents and records, discussions with counterparts, and field observations. There are several annexes. These deal with major features of industrial safety programmes such as safety committees, reporting and investigation systems and first aid and medical facilities. They include some examples which are considered commendable. The document should be taken into account not only when reviewing management, organization and administration but also in the review of related areas, such as maintenance and operations, so that all aspects of industrial safety in an operating nuclear power plant are covered

Printsipy mestnogo lecheniya troficheskikh yazv stop u bol'nykh sakharnym diabetom

Directory of Open Access Journals (Sweden)

Alla Yur'evna Tokmakova

2001-06-01

Full Text Available Выбор оптимальных средств местного лечения трофических нарушений кожи нижних конечностей является достаточно актуальной и недостаточно изученной проблемой не только для эндокринологов, но и для дерматологов и хирургов. Большое количество современных средств для местного лечения трофических поражений кожи и язв, представленных на рынке в настоящее время, с одной стороны, облегчает ведение этой группы больных в амбулаторных условиях, а с другой влечет возможность неправильного выбора того или иного средства, не соответствующего состоянию раневого дефекта. Это часто приводит к ошибкам в лечении осложнений сахарного диабета (СД ? синдрома диабетической стопы, а также сопутствующих заболеваний, протекающих с нарушением целостности кожных покровов. Основные правила консервативного лечения трофических язв нижних конечностей у больных СД следующие: достижение компенсации углеводного обмена; ликвидация механического давления на пораженный участок; адекватная очистка дефекта от некротических масс и последующее дренирование; антибиотикотерапия под строгим бактериологическим контролем; борьба с явлениями гипоксии в зоне раневого дефекта; создание оптимальной среды в ране для обеспечения ее скорейшей эпителизации. Достичь успеха в создании оптимальной раневой среды можно только при правильном использовании современных перевязочных средств. Необходимо помнить о строгом соответствии каждого перевязочного средства определенной фазе, или стадии, раневого процесса.

IAEA Sees Safety Commitment at Spain’s Almaraz Nuclear Power Plant, Areas for Enhancement

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts said the operator of Spain’s Almaraz Nuclear Power Plant demonstrated a commitment to the long-term safety of the plant and noted several good practices to share with the nuclear industry globally. The team also identified areas for further enhancement. The Operational Safety Review Team (OSART) today concluded an 18-day mission to Almaraz, whose two 1,050-MWe pressurized-water reactors started commercial operation in 1983 and 1984, respectively. Centrales Nucleares Almaraz-Trillo (CNAT) operates the plant, located about 200 km southwest of Madrid. OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing recommendations for improvement where appropriate. Nuclear power generates more than 21 per cent of electricity in Spain, whose seven operating power reactors all began operation in the 1980s.The mission made a number of recommendations to improve operational safety, including: • The plant should implement further actions related to management, staff and contractors to enforce standards and expectations related to industrial safety. • The plant should take measures to reinforce and implement standards to enhance the performance of reactivity manipulations in a deliberate and carefully-controlled manner. • The plant should improve the support, training and documented guidance for Severe Accident Management Guideline users in order to mitigate complex severe accident scenarios. The team provided a draft report of the mission to the plant’s management. The plant management and the Nuclear Safety Council (CSN), which is responsible for nuclear safety oversight in Spain, will have the opportunity to make factual comments on the draft. These will be reviewed by the IAEA and the final report will be submitted to the Government of Spain within three months. The plant management said it would address the areas

IAEA Leads Operational Safety Mission To Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of experts today began an in-depth operational safety review of the Gravelines Nuclear Power Plant in France. The review, conducted at the invitation of the French government, focuses on programmes and activities essential to the safe operation of the nuclear power plant. The three-week review will cover the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. The conclusions of the review will be based on the IAEA Safety Standards and on well-established international good practices. The mission is not a regulatory inspection, a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team, led by the IAEA's Division of Nuclear Installation Safety, comprises experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain and Ukraine. The Gravelines mission is the 173rd conducted as part of the IAEA's Operational Safety Review Team programme, which began in 1982. France participates actively in the programme and the Gravelines mission is the 24th hosted by the country. General information about OSART missions can be found on the IAEA Website: OSART Missions. (IAEA)

Enhancing operational nuclear safety

International Nuclear Information System (INIS)

Sengoku, Katsuhisa

2008-01-01

's safety standards and program which provides the safety objective following the 10 fundamental safety principles. The safety requirements defines the functional conditions required for safety and the safety guides provides user-friendly and up-to-date practical guidance representing good/best practices to fulfill the requirements. The IAEA provides safety review services and fields safety review teams upon request of member states for the regulatory, the International Regulatory Review Team (IRRT) and Operational Safety Review Team (OSART) and Peer Review of the Operational and Safety Performance Experience Review (PROSPER). The OSART programme's purpose is to assist member states in enhancing the operational safety of individual nuclear power plants and to promote the continuous development of operational safety within all member states by the dissemination of information on good practice. The OSART Mission Results (OSMIR) database contains the results from 73 OSART missions and 54 follow up visits from 1991 and its continually updated. The Asian Nuclear Safety Network (ANSN) was established to pool and share existing and new technical knowledge and practical experience to further improve the safety of nuclear installation in Asia. In summary, the enhancement of the GNSR is anchored in the recognition that all the states are in the same boat and the increasing importance of sharing and mutual learning, sharing knowledge and experience through regional and global networking. It requires joint and coordinated strategy by all states. The IAEA is willing and ready to support the GNSR through the establishment and application of safety standards, and safety review and advisory services and international instruments. (Author)

Experience of the United States in Hosting and Supporting IAEA Peer Review Missions

International Nuclear Information System (INIS)

Mamish, N.

2016-01-01

The International Atomic Energy Agency (IAEA) provides a number of peer review services to its Member States. The United States has strongly supported these peer reviews since their inception. In 2010, the United States hosted an Integrated Regulatory Review Service (IRRS) mission, with a follow-up mission completed in 2014. The missions provided valuable recommendations and suggestions, identified a number of best practices, and acknowledged the prompt and effective actions taken by the NRC following the Fukushima Daiichi accident. Through hosting an International Physical Protection Advisory Service (IPPAS) mission in 2013, the United States benefited both from the insights provided by the team, as well as the U.S. Government’s gap analyses and preparatory efforts in advance of the mission. The United States strongly supports the IAEA’s Operational Safety Review Team (OSART) program, inviting a peer review mission to a U.S. nuclear power plant every 3 years. Although OSART is an operational, not regulatory, peer review, the NRC provides funding for the mission and gives inspection credit to operators that host them. The United States also contributes significant technical expertise to IAEA peer review missions hosted by other Member States. With the IRRS and IPPAS reaching their 10th and 20th anniversaries respectively, these programs have improved as they have matured. However, it remains critical for Member States to continue to support these programs, and provide feedback to the IAEA Secretariat on their effectiveness and areas where IAEA might enhance them. Doing so will ensure peer reviews remain an effective tool for strengthening nuclear safety and security worldwide. (author)

IAEA Newsbriefs. V. 9, no. 3(65). Jul-Aug 1994

International Nuclear Information System (INIS)

1994-01-01

This issue gives brief information on the following topics: 38th IAEA General Conference to Convene in Vienna (with the subtopics 'At its meetings from 6-10 June 1994', 'Safeguards-related matters', 'Technical assistance and co-operation', 'Nuclear safety and radiological protection', and 'Programme and budget for 1995'), G-7 Summit Statement on Nuclear-Related Issues, Upcoming conferences, Conference on the Nuclear Power Option, Radiation and Society, Spent Fuel Storage, Isotope Techniques in Waste Disposal, Safety of Soviet-Designed Nuclear Plants, Arms Control and Disarmament, Safeguards Agreements, Nuclear Plant Safety Review (Future OSART missions), Feedback on Asset Safety Services, and New IAEA publications

Operational safety review programmes for nuclear power plants. Guidelines for assessment

International Nuclear Information System (INIS)

2002-01-01

The IAEA has been offering the Operational Safety Review Team (OSART) programme to provide advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Simultaneously, the IAEA has encouraged self-assessment and review by Member States of their own nuclear power plants to continuously improve nuclear safety. Currently, some utilities have been implementing safety review programmes to independently review their own plants. Corporate or national operational safety review programmes may be compliance or performance based. Successful utilities have found that both techniques are necessary to provide assurance that (i) as a minimum the NPP meets specific corporate and legal requirements and (ii) management at the NPP is encouraged to pursue continuous improvement principles. These programmes can bring nuclear safety benefits to the plants and utilities. The IAEA has conducted two pilot missions to assess the effectiveness of the operational review programme. Based on these missions and on the experience gained during OSART missions, this document has been developed to provide guidance on and broaden national/corporate safety review programmes in Member States, and to assist in maximizing their benefits. These guidelines are intended primarily for the IAEA team to conduct assessment of a national/corporate safety review programme. However, this report may also be used by a country or utility to establish its own national/corporate safety review programme. The guidelines may likewise be used for self-assessment or for establishing a baseline when benchmarking other safety review programmes. This report consists of four parts. Section 2 addresses the planning and preparation of an IAEA assessment mission and Sections 3 and 4 deal with specific guidelines for conducting the assessment mission itself

Slug-Burst Detection in the G3 Reactor; La detection de rupture de gaine au reacteur G3; Obnaruzhenie razryva obolochki v reaktore G3; Deteccion de fallas del revestimiento en el reactor G3

Energy Technology Data Exchange (ETDEWEB)

Plisson, J. [Centre d' Etudes Nucleaires de Marcoule (France)

1963-10-15

The author explains the principles underlying slug-burst detection and describes the construction of the apparatus concerned. The main features are a) fully automatic operation, b) centralization of data in the control room and c) measurement by electrostatic collection on a turntable. (author) [French] Dans ce memoire, l'auteur expose les principes sur lesquels est fondee la detection de rupture de gaines et il decrit la realisation des installations. Les caracteristiques principales sont a) l'automatisme integral, b) la centralisation des informations dans la salle de commande et c) mesure par collection electrostatique sur plaque tournante. (author) [Spanish] El autor expone los principios en que se basa la deteccion de las fallas en los revestimientos de los elementos combustibles y describe las caracteristicas principales de la instalacion, que son: a) automatizacion integral, b) centralizacion de las informaciones en la sala de mandos, y c) medicion por recoleccion electrostatica sobre una placa giratoria. (author) [Russian] Izlagayutsya printsipy, na kotorykh osnovano obnaruzhenie razryva obolochki, opisyvaetsya konstruirovanie ustanovok. Osnovnye kharakteristiki takovy: a) integral'nyj avtomatizm, b) tsentralizatsiya informatsii v komandnom zale i c) izmerenie putem ehlektrostaticheskogo sobiraniya na povorachivayushchejsya plastinke. (author)

Preparations for the 1994 OSART [operational safety review] at Hunterston Power Station

International Nuclear Information System (INIS)

Moir, I.A.

1993-01-01

The International Atomic Energy Agency have accepted an invitation from the Scottish Office to carry out an Operational Safety Review at Hunterston Power Station in April 1994. This paper outlines the preparations being undertaken by Scottish Nuclear Limited to ensure the standards set by the International Atomic Energy Agency are met. (author)

Improvement of NPP training to ensure a transfer of critical knowledge

International Nuclear Information System (INIS)

Vaisnys, P.; Bieth, M.; Kosilov, A.; Lipar, M.

2007-01-01

Full text: Maintaining nuclear competencies in the nuclear industry and nuclear regulatory authorities will be one of the most critical challenges in the near future. The adequate management of human resources, proper educational system and training approaches and methods to achieve and maintain the proper competencies of personnel are indispensable elements of knowledge management for nuclear industry. To transfer the knowledge from the experience to the newcomers, to establish the consistent links between the national educational system and qualification needs, to respond to the changes in the nuclear technology, to ensure the adequate level of corporate memory are the examples of the links between the knowledge management and the training. The paper presents the extensive information on the challenges, the nuclear industry encounters in the training and qualification (T and Q) of the personnel, and the good practises that are in use at nuclear power plants to respond to these challenges. The information presented is based on the experience from the IAEA OSART missions which review the training and qualification matters at the nuclear power plants among the other operational management programmes. IE/JRC-EC supports the OSART activities by providing the experts for the specific operational areas and participating in the development of the IAEA Safety Standards. New Project launched in the IE in 2007, SONIS (Safety of nuclear installations) is focused on the operational aspects of nuclear power plants, in particular maintenance, and the qualification and training of the maintenance personnel is of the particular interest of SONIS. The information presented in the paper is the result of the thorough analysis of the OSMIR Data Base. This database is a compilation of recommendations, suggestions and good practices from OSART mission reports, and covers all missions from January 1991 to the most recent missions for which an official reports have been published. It was

Summary of developments and future projects in nuclear power plant control and instrumentation in the Netherlands

International Nuclear Information System (INIS)

Plas, Y. van der

1990-01-01

A general view is given on the developments and trends due to instrumentation and control of the two nuclear power plants in the Netherlands around the year 1989. Several projects, under which for classification of systems and components and for emergency operating procedures, are executed in both plants. An OSART mission initiated a project to make possible the periodic test of safety commands during operation. An other large project concerned the replacement of the process presentation system in Nuclear Power Plant Borssele. In the article several other developments due to the application of I and C in existing plants are outlined generally. Since 1974, no new nuclear power plants have been constructed in the Netherlands. (author). 2 figs

SALTO Peer Review Guidelines. Guidelines for Peer Review of Safety Aspects of Long Term Operation of Nuclear Power Plants

International Nuclear Information System (INIS)

2014-01-01

International peer review is a useful tool for Member States to exchange experiences, learn from each other and apply good practices in the long term operation (LTO) of nuclear power plants (NPPs). The peer review is also an important mechanism through which the IAEA supports Member States in enhancing the safety of NPPs. The IAEA has conducted various types of safety review that indirectly address aspects of LTO, including safety reviews for design, engineering, operation and external hazards. Operational Safety Review Team (OSART) services include review of ageing management programmes. In addition, several Member States have requested Ageing Management Assessment Team (AMAT) missions. Through these experiences, it was recognized that a comprehensive peer review on LTO would be very useful to Member States. The Safety Aspects of Long Term Operation (SALTO) peer review addresses strategy and key elements for the safe LTO of NPPs, which includes AMAT objectives and complements OSART reviews. The SALTO peer review is designed to assist operating organizations in adopting a proper approach to LTP including implementing appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review can be tailored to focus on ageing management programmes (AMPs) or on other activities related to LTO to support the Member State in enhancing the safety of its NPPs. The SALTO peer review can also support regulators in establishing or improving regulatory and licensing strategies for the LTO of NPPs. The guidelines in this publication are primarily intended for members of a SALTO review team and provide a basic structure and common reference for peer reviews of LTO. Additionally, the guidelines also provide useful information to the operating organizations of NPPs (or technical support organizations) for carrying out their own self-assessments or comprehensive programme reviews. The guidelines are intended to be generic, as there are

IAEA Mission Sees Safety Commitment at Finland's New Olkiluoto Reactor Before Planned Start in December

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts observed a commitment to safety by the operator of Unit 3 at Finland’s Olkiluoto Nuclear Power Plant, ahead of the Evolutionary Pressurised Water Reactor’s (EPR) planned connection to the grid in December. The team also identified areas for further enhancements as the operator prepares to put the reactor online. The Pre-Operational Safety Review Team (Pre-OSART) concluded an 18-day mission today to assess operational safety at the 1600 MW reactor, located about 280 km northwest of the capital, Helsinki. Finland has engaged France’s Areva SA together with Germany’s Siemens to construct and commission the unit. The operator is Teollisuuden Voima (TVO). Pre-OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing recommendations for improvement where appropriate. The review covered the areas of leadership and management for safety; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency preparedness and response; accident management; and commissioning. The team identified a number of good practices that will be shared with the nuclear industry globally, including: • The plant has developed and implemented an efficient system for improving knowledge and skills of staff members. • The plant has developed and validated a unique method for performing suspended solids analysis using a microscope, imaging software and a digital camera. • The plant has introduced a system for systematically assessing nuclear safety culture in the plant supplier organization during construction and commissioning. The mission made several recommendations to improve operational safety, including: • Plant management should set appropriate expectations, communicate them to staff and reinforce them in the field. • The plant should improve the

IAEA Says Finland's Loviisa Nuclear Power Plant Committed to Safety, Sees Areas for Enhancement

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts said the operator of Finland’s Loviisa Nuclear Power Plant (NPP) demonstrated a commitment to safety. The team also identified areas for further enhancement. The Operational Safety Review Team (OSART) concluded an 18-day mission on 22 March to Loviisa NPP, whose two 531-MWe pressurized-water reactors started commercial operation in 1977 and 1980, respectively. Fortum Power and Heat OY operate the plant, located about 100 km east of Helsinki, the capital. Nuclear power generates one-third of electricity in Finland, which has four operating power reactors and is constructing a fifth reactor. OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing improvement where appropriate. The 16-member team comprised experts from Brazil, Canada, China, France, Germany, Hungary, Romania, Russia Federation, Slovak Republic, South Africa, Spain, Ukraine, United Kingdom, United States of America as well as IAEA officials. The review covered the areas of leadership and management for safety; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency preparedness and response; accident management; human, technology and organizational interactions; and long-term operation. The team identified a number of good practices that will be shared with the nuclear industry globally, including: • The plant has developed the capability to automatically calculate leak rate tests of containment. • The plant established a process to test and improve modifications and updates early. • The plant has adopted a key system to effectively control access to various rooms in the plant. The mission made several proposals to improve operational safety, including: • The plant management should improve communications of their expectations and consistently reinforce their

Procedures for self-assessment of operational safety

International Nuclear Information System (INIS)

1997-08-01

Self-assessment processes have been continuously developed by nuclear organizations, including nuclear power plants. Currently, the nuclear industry and governmental organizations are showing an increasing interest in the implementation of this process as an effective way for improving safety performance. Self-assessment involves the use of different types of tools and mechanisms to assist the organizations in assessing their own safety performance against given standards. This helps to enhance the understanding of the need for improvements, the feeling of ownership in achieving them and and the safety culture as a whole. The concepts developed in this report present the basic approach to self-assessment taking into consideration experience gained during Operational Safety Review Team (OSART) missions, from organizations and utilities which have successfully implemented parts of a self-assessment programme and from meetings organized to discuss the subject

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 2, January 2007

International Nuclear Information System (INIS)

2006-08-01

This newsletter reports on the training of cardiologists in radiation protection, IAEA's safety review services and the operational safety assessment review team (OSART), the international conference on management of spent fuel and the recent INSAG (International Nuclear Safety Group) publications. The IAEA has begun a major international initiative to train interventional cardiologists in radiation protection. Starting with the first course in May 2004, so far 6 regional and 3 national training courses have been conducted with the participation of over 400 health professionals putting the IAEA in a leading role in this area. A programme of two days' training has been developed, covering possible and observed radiation effects among patients and staff, international standards, dose management techniques, examples of good and bad practice and examples indicating prevention of possible injuries as a result of good practice in radiation protection. The training material is freely available on CD and will be placed on the Radiological Protection of Patients website at http://rpop.iaea.org/

National Peer Reviews. Self-assessment programs of German nuclear power plants

International Nuclear Information System (INIS)

Grauf, E.

2000-01-01

Preliminary experience seems to indicate that the concept of national peer reviews is a useful tool capable of improving and harmonizing the standards of operation in German plants. However, a final evaluation is possible only after completion of the program, i.e. probably by the end 2000. The internal national peer reviews do not replace existing reviews, such as the WANO peer reviews or the IAEA OSART missions, but rather supplement them. As a major element of self-assessment, they mainly serve to exchange effectively among German plants know-how and experience, to harmonize standards of plant operation, eliminate any weak spots identified, and generally counteract blindness to one's own faults. Whether the envisaged objective of standardized plant operations will be achieved in the end depends very much on the way in which the results of the reviews will be handled. In particular, it will be interesting to see to what extent there is willingness to take on board any recommendations and proposals made and/or introduce what is called good operating practice. (orig.) [de

Complex nuclear safety evaluation of the Bohunice V-1 nuclear power plant

International Nuclear Information System (INIS)

Kriz, Z.

1991-01-01

The safety concept of V-230 type reactor units dates back to the late 1960s. The units fail to be sufficiently dimensioned for emergency cooling of the reactor core and are fitted with no containment. So far, operating experience is good. The availability factor is 71.5% for unit 1 and 77.8% for unit 2. There occur 1 to 3 unscheduled shutdowns annually. The quality of steam generator tubes is very good. A complex safety assessment of the plant was accomplished in 1990. It concerned the concept and criteria of safety assessment, the earthquake situation, the condition of the primary coolant circuit equipment, the control system, the effect of the human factor, and preparedness of emergency plans. OSART and ASSET missions were accomplished at the plant. Based on the results of the missions as well as of inspections by the State Surveillance over Nuclear Safety, the decision has been adopted to operate the plant not longer than till 1995; the further fate of the plant will be decided on according to a future technical and economic analysis. (M.D.)

Basic principles of scintillation counting; Principes de Base du Comptage par Scintillations; Osnovnye printsipy stsintillyatsij; Principios fundamentales del recuento con aparatos de centelleo

Energy Technology Data Exchange (ETDEWEB)

Johns, H E; Cederlund, J F [Ontario Cancer Institute, Toronto (Canada)

1959-07-01

The effect of the energy of radiation, the crystal size, the collimation of the beam and scattering on the pulse-height distribution produced by monoenergetic radiation will be discussed. These aspects will be related to scintillation scanning. The effects of voltage on the operation of photomultiplier s and so-called plateaus will be dealt with. Glow-transfer tubes for counting will be dealt with and a useful substraction circuit for comparing the counting rate from two separate scintillation counters will be presented. (author) [French] Les auteurs examineront l'effet de l'energie du rayonnement, de la dimension du cristal, de la collimation du faisceau et de la diffusion sur la repartition de l'amplitude des impulsions dues au rayonnement monoenergetique, en rattachant l'etude de ces questions a l'exploration par scintillations. Ils etudieront egalement les effets de la tension sur le fonctionnement des photomultiplicateurs et des , ainsi que l'utilisation de pour le comptage; ils presenteront enfin un circuit de soustraction utile servant a comparer le taux de comptage de deux scintillometres distincts. (author) [Spanish] Los autores estudiaran el efecto que la energia de la radiacion, el tamano del cristal, la colimacion del haz y la dispersion ejercen sobre la distribucion de la amplitud de los impulsos debida a la radiacion monoenergetica, relacionando todas estas cuestiones con la exploracion mediante aparatos de centelleo. Examinaran tambien la influencia de las variaciones de tension sobre el funcionamiento de los fotomultiplicadores y sobre las denominadas , asi como los tubos luminiscentes de transmision para el recuento; por ultimo, presentaran un circuito de sustraccion que sirve para comparar el indice de recuento de dos contadores de centelleo distintos. (author) [Russian] Budet obsuzhdat'sya vliyanie ehnergii izlucheniya, velichiny kristalla, kollimirovaniya lucha i, nakonets, rasseyaniya na amplitudnoe raspredelenie impul'sov, proizvodimykh monoehnergeticheskoj radiatsiej. EHti voprosy budut zvzzany s primeneniem v issledovaniyakh metoda stsintillyatsij. Dalee budet rassmatrivat's ya vliyanie na rabotu fotoumnozhitelej i tak nazyvaemye . Kromo togo, budet obsuzhdat'sya primenenie lyuminestsentnykh peredatochnykh trubok dlya schetnykh operatsij i predstavleno poleznoe ustrojstvo vychitaniya dlya sravneniya skorosti raboty dvukh otdel'nykh stsintillyatsionnykh schetchikov. (author)

Best Practices in the Management of an Operating Experience Programme at Nuclear Power Plants

International Nuclear Information System (INIS)

2010-08-01

The IAEA Fundamental Safety Principles (IAEA Safety Standards Series No. SF-1) state the need for operating organizations to establish a programme for the feedback and analysis of operating experience in nuclear power plants. Such a programme ensures that operating experience is analysed, events important to safety are reviewed in depth, lessons learned are disseminated to the staff of the organization and to the relevant national and international organizations and corrective actions are effectively implemented. In IAEA Operational Safety Review Team (OSART) and Peer Review of the effectiveness of the Operational Safety Performance Experience Review (PROSPER) missions, weaknesses in the management of operating experience (OE) programmes have been identified as one of the root causes of the recurrence of events. This publication has been developed to provide advice and assistance to nuclear installation managers and related institutions, including contractors and support organizations, to strengthen and enhance the management of their OE processes. In this publication, a number of barriers to the successful management of an OE programme have been identified. Managers are encouraged to review and evaluate these barriers with a view to identifying and eliminating them within their own organizations

Santa Maria de Garona NPP

International Nuclear Information System (INIS)

Candas, C.

2004-01-01

Three especially significant milestones determine the positive assessment of Santa Maria de Garona nuclear power plant operation in 2003: the beginning of Project 2019, the quality and safety results in the Refueling Outage, and the good assessment obtained by the plant in the follow-up review of the OSART Mission. The operating factor of 91.52% obtained in 2003 is the Plant's best historical result in a year with a refueling outage. This factor is an indication of reasonable Plant operation throughout the year, and also of the results of the optimization and quality efforts made in preparing and executing the refueling outage. The collective dose indicator is also the best historical datum in year with a refueling outage and keeps our Plant in a relevant position among the world's BWR plants. The objective set by INPO is clearly achieved. The result is the outcome of the improvement studies and ALARA actions taken during job preparation and planning and also of equipment and installation improvements and modernization. The three differential follow-up objective of the NUCLENOR Corporate Project are: Strengthening of the Safety Culture, Operating License Renewal and Improved in-Plant Task Management

Experience with the export of nuclear plants

International Nuclear Information System (INIS)

Huettl, A.

1991-01-01

Licensing and regulatory aspects represent an important issue during the definition and implementation phase of a nuclear power project. Strict adherence to the principles 'licensability in country of origin' and 'reference plant as built' may prove to be counterproductive on account of the differences in licensing infrastructure in vendor's and buyer's countries and of the difficulty in striking a balance between proven and up-to-date designs. In order to repeat good experience in safety, consistency of the applicable rules and regulations is important when performing the necessary adaptations to local requirements. The use of an internationally accepted body of rules such as NUSS as a yardstick for safety evaluation helps to identify special requirements in vendor's country, thus minimizing distortions in evaluation of competing bids. Benefitting from ongoing efforts to improve transparency and mutual understanding of the national safety approaches through bodies and missions like INSAG, WANO, OSART, a graded approach for implementing safety review during construction and operation is suggested, matching it to the scope of a national program of NPP construction. Together with efficient project control this will minimize the demands on resources - both human and financial - required for a successful launch of a nuclear power plant. (orig.)

New IAEA guidance on safety culture

International Nuclear Information System (INIS)

Haage, Monica; )

2012-01-01

Monica Haage described a project for Kozloduy Nuclear Power Plant in Bulgaria which was also funded by the Norwegian government. This project included the development of guidance documents and training on self-assessment and continuous improvement of safety culture. A draft IAEA safety culture survey was also developed as part of this project in collaboration with St Mary's University, Canada. This project was conducted in parallel with an IAEA project to develop new safety reports on safety culture self-assessment and continuous improvement. A safety report on safety culture during the pre-operational phases of NPPs has also been drafted. The IAEA approach to safety culture assessment was outlined and core principles of the approach were discussed. These include the use of several assessment methods (survey, interview, observation, focus groups, document review), and two distinct levels of analysis. The first is a descriptive analysis of the observed cultural characteristics from each assessment method and overarching themes. This is followed by a 'normative' analysis comparing what has been observed with the desirable characteristics of a strong, positive, safety culture, as defined by the IAEA safety culture framework. The application of this approach during recent Operational Safety Assessment Review Team (OSART) missions was described along with key learning points

Report on operation of nuclear facilities in Slovenia in 1991

International Nuclear Information System (INIS)

1992-11-01

Slovenian Nuclear Safety Administration (SNSA) is responsible for: nuclear safety, transport of nuclear and radioactive materials, safeguarding nuclear materials, and conducting regulatory process related to liability for nuclear damage, qualification and training of operators at nuclear facilities, quality assurance and inspection of nuclear facilities. The major nuclear facility supervised by SNSA is the Nuclear Power Plant in Krsko with a pressurized water reactor of 632 MW electric power. Beside the nuclear power plant, TRIGA Mark 11 Research Reactor of 250 kW thermal power operates within the Reactor Center of Jozef Stefan Institute. There is an interim storage of low and medium radioactive waste at the Reactor Center. Also the Uranium mine Zirovski Vrh was supervised by SNSA. All the nuclear power facilities in Republic of Slovenia were operating safely in 1991. There were no significant events that could be evaluated as a safety problem or a breach of technical specifications. A great part of activities of SNSA was focused on the next visit of the IAEA OSART team (Operational Safety Assessment Review Team) in Krsko Nuclear Power Plant and on the visit of the INSARR mission (Integrated Safety Assessment of Research Reactors) for the TRIGA Mark 11 Research Reactor. (author)

Problems and principles of NPP diagnostics on the basis of mode parameter monitoring. Problemy i printsipy diagnostirovaniya YaEhU na osnove kontrolya rezhimnykh parametrov

Energy Technology Data Exchange (ETDEWEB)

Znyshev, V V

1990-01-01

Ideology of an approach to solving the problem of functional NPP diagnostics according to data on the dynamics of the plant monitored mode parameter dynamics, is presented. Difficulties in solving caused by NPP specific features as a diagnostics object are considered. Practical reasons simplifying the problem are expressed.

Management of procurement activities in a nuclear installation

International Nuclear Information System (INIS)

1996-12-01

Discussions held within the framework of IAEA regional technical co-operation projects implemented in the Latin America, Asia-Pacific and eastern Europe regions revealed an area of frequent difficulties related to the proper control, by the management of nuclear utilities, of the effective fulfilment of contractual quality and safety requirements. Evaluation of the results of a number of OSART missions has also pointed to a need for improving the control that some utilities exercise on their suppliers. The IAEA was thus prompted to initiate the development of a technical document providing guidance on these subjects. In October 1995, a consultants meeting was convened to determine the target users of the technical document and to develop the scope, contents, structure and the reference material. A first draft was then prepared. An Advisory Group meeting consisting of experts from 17 Members States was held in Vienna in May 1996 to review and complete the draft. The technical document is intended to provide practical guidance on controlling procurement, with supporting information for senior management, line managers and line supervisors in a nuclear installation. Although the guidance is structured to address the needs during the operating stage of a nuclear power plant, much of the material is also applicable to the construction and decommissioning stages and to other nuclear installations. 1 fig

Long term operation of nuclear power plants – IAEA SALTO peer review service and its results

Energy Technology Data Exchange (ETDEWEB)

Krivanek, Robert, E-mail: r.krivanek@iaea.org

2014-12-15

Highlights: • SALTO peer review service is designed for reviewing of ageing management and NPPs’ preparedness LTO. • It has been established as an effective tool to review the compliance with IAEA safety standards. • The important issues for safe LTO are being identified by SALTO missions. • Analysis of those issues is provided in the paper. • This peer review service is strongly recommended for NPPs prior to entering LTO period. - Abstract: This paper presents main IAEA activities for safe long term operation (LTO) which includes establishment of IAEA Safety Standards and other LTO related documents, fostering information exchange and establishing databases and provision of SALTO (Safety Aspects of Long Term Operation) peer review service. This paper provides insights into IAEA SALTO peer review service objectives, scope and methodology. The SALTO peer review service was designed to assist nuclear power plant (NPP) operators in adopting a proper approach to LTO of their plants and in implementing complete and appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review service can also support regulators in establishing or improving regulatory and licensing strategies for LTO of NPPs. Issues derived from 19 SALTO missions and 2 LTO modules of OSART (Operational Safety Review Team) missions conducted during the period of 2005 to March 2014 are also analyzed in this paper.

Start-up and operation of Laguna Verde-2

International Nuclear Information System (INIS)

Torres Ramirez, J.F.

1996-01-01

The 665 MWe Laguna Verde-2 nuclear generating unit was accepted into commercial operation on April 10, 1995. The boiling water reactor plant by General Electric (GE) was first synchronized with the grid on November 11, 1994. Laguna Verde-2 is identical with Laguna Verde-1 on the same site. That unit had gone critical for the first time in November 1988 and had first been synchronized with the power grid on April 13, 1989. Commercial operation of Laguna Verde-1 had been started on July 29, 1990. Mexico's only nuclear power plant had been built 70 km north of Veracruz on the east coast and had been scheduled to start operation in 1976. As the Mexican nuclear power program was reduced, the scheduled commissioning dates suffered more and more delays. In the full of 1987, the investigation by the Operational Safety Review Team (Osart) of the International Atomic Energy Agency (IAEA) had indicated that the safety requirements of installations and equpiment were met, and that the whole plant was well prepared for fueling. In mid-1988, the Mexican Government had issued the permit to fuel the Laguna Verde-1 reactor. The contract to build the two units had been awarded in 1972/73. No other nuclear power plants are currently under construction or in the planning phase in Mexico. (orig.) [de

Self-assessment of operational safety for nuclear power plants

International Nuclear Information System (INIS)

1999-12-01

Self-assessment processes have been continuously developed by nuclear organizations, including nuclear power plants. Currently, the nuclear industry and governmental organizations are showing an increasing interest in the implementation of this process as an effective way for improving safety performance. Self-assessment involves the use of different types of tools and mechanisms to assist the organizations in assessing their own safety performance against given standards. This helps to enhance the understanding of the need for improvements, the feeling of ownership in achieving them and the safety culture as a whole. Although the primary beneficiaries of the self-assessment process are the plant and operating organization, the results of the self-assessments are also used, for example, to increase the confidence of the regulator in the safe operation of an installation, and could be used to assist in meeting obligations under the Convention on Nuclear Safety. Such considerations influence the form of assessment, as well as the type and detail of the results. The concepts developed in this report present the basic approach to self-assessment, taking into consideration experience gained during Operational Safety Review Team (OSART) missions, from organizations and utilities which have successfully implemented parts of a self-assessment programme and from meetings organized to discuss the subject. This report will be used in IAEA sponsored workshops and seminars on operational safety that include the topic of self-assessment

Temelin safety monitor

International Nuclear Information System (INIS)

Mlady, O.

2000-01-01

Temelin NPP is a WWER-1000/320 two unit plant under construction, originally designed according to the standards of the former Soviet Union. After a series of reviews in the 80s, a decision was taken to upgrade the design of Temelin, including the supply of fuel and instrumentation and instrumentation and control system (I and C). Details on the current design and other related safety matters were presented to the nuclear community in a meeting organized by the IAEA in November 1994. Based upon recommendations of IAEA OSART missions, post TMI requirements and Temelin Risk Audit recommendations it was decided to perform a Probabilistic Safety Assessment within the Temelin PSA Project. The general purpose of this project was to perform systematic examination of the Temelin Unit 1 NPP for severe accident vulnerabilities by performance of a Level 1 and 2 PSA study. In addition to the completion of Temelin documented living PSA model, the decision was to develop and implement a PSA based software tool able to analyze real and scheduled plant conditions for determining the risk impact of plant configurations and on-line maintenance activities. This paper provides an overview of the key features of the Temelin Safety Monitor, describes its development activities and its current status and intended use at Temelin NPP for PSA applications. (author)

Managing human resources in the nuclear power industry: Lessons learned

International Nuclear Information System (INIS)

2003-08-01

This report is intended for senior and middle level managers in nuclear operating organizations. Its objectives are to facilitate the recognition of priority issues with respect to managing human resources, and to provide pragmatic ideas regarding improvements. The human resource issues addressed in this report, if not managed effectively, can result in significant performance problems at nuclear power plants. About 10 years ago the IAEA initiated an effort to identify such management issues and to find effective practices to deal with them. This information was provided in IAEA Technical Reports Series No. 369, Management for Excellence in Nuclear Power Plant Performance - A Manual (1994). This report builds upon the information in the subject manual. In the past 10 years there have been significant changes in the nuclear power industry resulting primarily from more competitive energy markets and privatization of nuclear power plant operating organizations. In general, the industry has responded positively to these changes, as indicated by IAEA/WANO performance indicators that show both improved operational and safety performance. This report provides examples of approaches to managing human resources that have been effective in responding to these changes. This report was produced through a series of meetings, where meeting participants were asked to share information regarding effective practices in their organizations with respect to managing human resources. The information provided through these meetings was supplemented with good practices in this area identified through IAEA Operational Safety Review Teams (OSARTs) conducted during the past 10 years

Implementation of Industry Experience at Nuclear Power Plant Krsko

International Nuclear Information System (INIS)

Heruc, Z.; Kavsek, D.

2002-01-01

Being a standalone comparatively small unit NPP Krsko has adopted a business philosophy to incorporate industry experience into its daily operations. The continuos and safe operation of the unit is supported through feedback from other utilities (lessons learned) and equipment vendors and manufacturers. A permanent proactive approach in monitoring the international nuclear technology practices, standards changes and improvements, and upon feasibility review, introducing them into processes and equipment upgrades, is applied. As a member of the most important international integrations, NPP Krsko has benefited from the opportunity of sharing its experience with others (World Association of Nuclear Operators -WANO, Institute of Nuclear Power Operations - INPO, International Atomic Energy Agency - IAEA, Nuclear Operations Maintenance Information Service - NOMIS, Nuclear Maintenance Experience Exchange - NUMEX, Electric Power Research Institute - EPRI, Westinghouse Owners Group - WOG, etc.). Voluntary activities and good practices related to safety are achieved by international missions (IAEA Assessment of Safety Significant Events Team - ASSET, IAEA Operational Safety Review Team - OSART, WANO Peer Review, International Commission for Independent Safety Analysis - ICISA) and operating experience exchange programs through international organizations. These missions are promoting the highest levels of excellence in nuclear power plant operation, maintenance and support. With time, the practices described in this paper presented themselves as most contributing to safe and reliable operation of our power plant and at the same time supporting cost optimization making it a viable and reliable source of electrical energy in the more and more deregulated market. (author)

VVER 1000-NPP Temelin safety upgrading

International Nuclear Information System (INIS)

Fleischhans, J.; Ubra, O.

1995-01-01

A modernisation program upgrading Temelin plant to meet internationally adopted standard has been implemented during plant design and construction phases. The initial Czech-Russian design (primary system was of Russian design, secondary system was of Czech design) has been extensively modified and adapted to present western safety criteria and operational requirements. The goals are to achieve a high level of safety, reliability, availability and load-following ability. The load-following ability and response to grid frequency changes are very important for the Czech Republic, since the nuclear capacity represents a high proportion of the overall electrical system there. On the basis of IAEA OSART missions and Halliburton NUS audit results and in compliance with recommendations of The State Office for Nuclear Safety, Czech Power Company and Czech scientists and researchers a modernisation program project for Temelin has been carried out. It includes three main groups of VVER1000 MW unit innovations: - Modernization and upgrading of the safety and control systems. - Fuel replacement and modification of the reactor core. - Innovation of some components of the primary and secondary systems. The tenders for instrumentation and control system, nuclear fuel, diagnostic system and radiation monitoring system were issued to the world-well known suppliers. The US company Westinghouse Electric >Corporation (WEC) was selected to submit contract for the delivery of instrumentation and control system primary side diagnostic system and for the delivery of nuclear fuel. The contract was signed in 1993

Creation of nuclear heating plants in Russia: present status and prospects for the future

International Nuclear Information System (INIS)

Gureeva, L.V.; Kurachenkov, A.V.

1998-01-01

History of heating reactor developments in two sites, Gorky and Voronezh, using AST-500 was reviewed. After interruption of construction for several years, decisions were made to resume the constructions. At Voronezh, based on the environmental assessment and the review of the IAEA OSART mission, the construction was resumed in 1996. In the course of construction resumption, design upgrading has been implemented in the following aspects: reclassification of station-level equipment concerning its importance for safety; control and instrumentation systems retrofitting with reliance on new generation element bases; application of self-actuated safety devices; and implementation of additional instrumentation for extended operating conditions. In Tomsk, Siberia, feasibility study is underway, which aims to replace the currently operating reactors with a twin-unit heating stations with AST-500 in order to provide heat to the district heating grids. In the study the NHP design is being assessed by a joint Russian-American Study Team from evaluation criteria such as design applicability and constructability, maturity of the design, safety aspects, technical uncertainty, available infrastructure, engineering and construction capabilities, site suitability, cost and schedule. Positive possibilities are foreseen to reuse the components previously delivered to the Gorky site, according to the assessments of structures and technological tools necessary for the re-erection work were, man-power needed for the equipment dismantling, inspection and re-erection and storage conditions. The construction cost is estimated as US$446 per KW(th). (author)

The Westinghouse approach - an I and C modernization program for WWERs

International Nuclear Information System (INIS)

Werner, C.L.; Wassel, W.W.; Novak, V.

1993-01-01

When entering into a design program that is a marriage between two designs it is very difficult to separate self imposed design criteria from the requirements of the program. Therefore, the criteria of and the requirements for the Westinghouse modernization program will be discussed as one. These are outlined below: 1) The OSART Mission that was conducted by the IAEA at the Temelin Plant in 1990 identified the need to provide a new comprehensive Safety Analysis to verify the various aspects of the WWER safety system design. This recommendation is one that Westinghouse will provide as part of the WWER I and C Modernization Program. The design, no matter how well proven or verified from a hardware design point of view, is only as good as the basis for the system design; 2) Minimize the impact on the civil design aspects of the plant where possible and where this requirements do not affect the safety features of the design; 3) Ensure compatibility of the design to meet the latest US NRC requirements and those of the implementing country, applicable to the systems functional and hardware designs. This is a Westinghouse standard corporate requirement for all nuclear plant and systems design whether they be foreign or domestic; 4) Provide the most modern, proven design for the I and C systems. Application of the Westinghouse Instrumentation and Control microprocessor based design to the WWER Modernization Program will provide the basis for upgrading plants to meet western standards. (author) 6 figs., 1 ref

Safety upgrading of the PAKS Nuclear Plant

International Nuclear Information System (INIS)

Vamos, G.; Vigassy, J.

1993-01-01

In the last several years the net electricity from the Paks NPP represents almost half of the Hungarian total. The 4 units of Paks belong to the latest generation of the VVER-440 units, the small-sized Russian designed PWRs. Reviewing the main design features of them, the safety merits and safety concerns are summarized. Due to the conservative design and the extensive operating experience the safety merits appear to be more significant than generally believed. The VVER-440 type has two models, the 230 and 213, which have a large number of distinctive safety features. These are highlighted in the section comparisons. A quality assurance program was initiated in Paks very early. A long-term safety upgrading program was also initiated, originating from vendor recommendations, regulatory decisions, in-house operating experience and safety concerns, and independent reviews. The main areas and some examples of the measures are described. This program, like all other activities related to nuclear safety, has been under regulatory control. The specific features of the Hungarian regulatory system are described. For advanced, general and new evaluation of the safety of the units in Paks in accordance with the internationally recommended criteria of the 90's, the project AGNES has been launched with international participation. The scope of this project is summarized. International efforts as the IAEA Regional Project on safety assessment of VVER-440/213 and VVER-440/230 units are underway. Since safety is not only a question of design, but it can be significantly influenced by operations and maintenance practices, the Paks NPP has invited LAEA's OSART and ASSET missions, WANO's Pilot Peer Review

Reviewing reactor engineering and fuel handling

International Nuclear Information System (INIS)

1991-12-01

Experience has shown that the better operating nuclear power plants have well defined and effectively administered policies and procedures for governing reactor engineering and fuel handling (RE and FH) activities. This document provides supplementary guidance to OSART experts for evaluating the RE and FH programmes and activities at a nuclear power plant and assessing their effectiveness and adequacy. It is in no way intended to conflict with existing regulations and rules, but rather to exemplify those characteristics and features that are desirable for an effective, well structured RE and FH programme. This supplementary guidance addresses those aspects of RE and FH activities that are required in order to ensure optimum core operation for a nuclear reactor without compromising the limits imposed by the design, safety considerations of the nuclear fuel. In the context of this document, reactor engineering refers to those activities associated with in-core fuel and reactivity management, whereas fuel handling refers to the movement, storage, control and accountability of unirradiated and irradiated fuel. The document comprises five main sections and several appendices. In Section 2 of this guide, the essential aspects of an effective RE and FH programme are discussed. In Section 3, the various types of documents and reference materials needed for the preparatory work and investigation are listed. In Section 4, specific guidelines for investigation of RE and FH programmes are presented. In Section 5, the essential attributes of an excellent RE and FH programme are listed. The supplementary guidance is concluded with a series of appendices exemplifying the various qualities and attributes of a sound, well defined RE and FH programme

Statement to World Association of Nuclear Operators Biennial General Meeting, 24 October 2011, Shenzhen, China

International Nuclear Information System (INIS)

Amano, Y.

2011-01-01

, interest in introducing nuclear power remains strong. WANO and the IAEA share a common central goal, which - to quote from WANO's mission statement - is to maximise the safety and reliability of nuclear power plants throughout the world. Our cooperation until now has focussed on sharing information, attending some of each other's meetings and participating in some peer review missions together. WANO has informally reviewed some of the IAEA draft Safety Standards. We hold joint workshops and seminars. The IAEA's 151 Member States want us to go further. In the Action Plan on Nuclear Safety, the IAEA Secretariat was asked to ''strengthen cooperation with WANO by amending their Memorandum of Understanding to enhance information exchange on operating experience and on other relevant safety and engineering areas.'' We were also requested to ''explore mechanisms to enhance communication and interaction among operating organizations.'' I would like to offer a few practical suggestions for your consideration. Peer reviews are a key area where I believe we could do more. The IAEA and WANO should continue to exchange information about results of their respective review missions to nuclear power plants, subject to any confidentiality considerations, while maintaining the distinctive features of their programmes. In the aftermath of the Fukushima Daiichi accident, both of our organizations plan to increase the frequency of such missions - OSART missions in the case of the Agency and Peer Reviews on WANO's part. We should improve coordination concerning our respective missions in order to avoid scheduling WANO Peer Reviews and IAEA OSART missions too close together. WANO's peer review missions take place much more frequently than IAEA missions and you amass considerable detailed information about the day-to-day safety issues dealt with by operators. Our OSART missions have the advantage of being carried out at the invitation of the governments of Member States.

SALTO guidelines. Guidelines for peer review of long term operation and ageing management of nuclear power plants

International Nuclear Information System (INIS)

2008-01-01

other and apply good practices in dealing with LTO of NPPs. The peer review service is also an important mechanism through which the IAEA supports Member States in enhancing the safety of NPPs. The IAEA has conducted various types of safety review services that indirectly address some aspects of LTO, including safety review services for design, engineering, operation and external hazards. OSART (Operational Safety Review Team) services include some review of ageing management programmes. In addition, several Member States have requested AMAT (Ageing Management Assessment Team) missions. Through these activities and considering the increasing average age of NPPs connected to the grid worldwide, it was recognized that a comprehensive engineering safety review service on LTO would be very useful to Member States. The Safe Long Term Operation (SALTO) peer review is a new comprehensive engineering safety review service directly addressing strategy and the key elements for safe LTO of NPPs, which includes AMAT objectives and complements OSART reviews. The SALTO peer review service is designed to assist NPP operators in adopting a proper approach to long term operation of their plants and in implementing complete and appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review service can be tailored to focus on AMPs and/or on other programmes related to LTO to support the Member State in enhancing the safety of its NPPs. The SALTO peer review service can also support regulators in establishing or improving regulatory and licensing strategies for LTO of NPPs. These guidelines are primarily intended for members of the SALTO review team and they provide a basic structure and common reference for peer reviews of LTO. However, the guidelines could provide useful information to operating organizations of NPPs (or technical support organizations) for carrying out their own self-assessments or comprehensive programme reviews. The

Rest lifetime evaluation and ageing management in NPP 'Kozloduy' unit 1-4

International Nuclear Information System (INIS)

Erve, M.; Heck, R.; Schmidt, J.; Daum, G.; Bataklieva, L.; Stoev, M.

1999-01-01

In 1992 as a result of an IAEA SRM review the 'WANO 6-month program' has been issued to improve operation, maintenance nad safety culture for the four WWER 440/230 units at the NPP 'Kozloduy' Siemens has awarded 3 contracts related to RTL evaluation of the main equipment, integrity of reactor pressure vessel and to the leak-before-break behaviour of the main piping od unit 2. It is pursuit an overall strategy that allows to: implement on the basis of RTL evaluation a long term ageing management program (AMAP) for Kozloduy's units 1-4 to assure their operation until the end of their design life; identify those components and equipment for which from the safety point of view urgent and immediate actions have to be performed; increase step by step the safety and reliability according to the Western standards and to internationally accepted safety culture; keep open the possibility of life extension as far as this would be technically feasible and acceptable and economically reasonable. Under the technical leadership of Siemens studies have been performed related to the subject of integrity and RTL, such as: reirradiation of RPV samples from Unit 1 and 2; evaluation of PV embrittlement of Unit 1; transfer of the results of LBB assessment of Unit 2 to Units 1, 3 and 4; transfer of results of RTL evaluation of Unit 2 to Units 1, 3 and 4; PTS analysis of RPV of Unit 1, 2,3 and 4. The main remarkable results are: no life-limiting mechanisms detected, requiring immediate actions, except for RPVs; residual lifetime determined for RPVs on reliable basis of advanced modern PTS analysis and sample testing; necessary activities in monitoring of ageing and in-service inspection clearly identified successful proof of lBB for main primary piping after slight modification of supports; international experts agreement reached (e.g. Risk Audit, successful IAEA experts meetings and OSART missions)

Integrated approach to fire safety at the Krsko nuclear power plant - fire protection action plan

International Nuclear Information System (INIS)

Lambright, J.A.; Cerjak, J.; Spiler, J.; Ioannidi, J.

1998-01-01

Nuclear Power Plant Krsko (NPP Krsko) is a Westinghouse design, single-unit, 1882 Megawatt thermal (MWt), two-loop, pressurized water nuclear power plant. The fire protection program at NPP Krsko has been reviewed and reports issued recommending changes and modifications to the program, plant systems and structures. Three reports were issued, the NPP Krsko Fire Hazard Analysis (Safe Shout down Separation Analysis Report), the ICISA Analysis of Core Damage Frequency Due to Fire at the NPP Krsko and IPEEE (Individual Plant External Event Examination) related to fire risk. The Fire Hazard Analysis Report utilizes a compliance - based deterministic approach to identification of fire area hazards. This report focuses on strict compliance from the perspective of US Nuclear Regulatory Commission (USNRC), standards, guidelines and acceptance criteria and does not consider variations to comply with the intent of the regulations. The probabilistic analysis methide used in the ICISA and IPEEE report utilizes a risk based nad intent based approach in determining critical at-risk fire areas. NPP Krsko has already completed the following suggestions/recommendations from the above and OSART reports in order to comply with Appendix R: Installation of smoke detectors in the Control Room; Installation of Emergency Lighting in some plant areas and of Remote Shout down panels; Extension of Sound Power Communication System; Installation of Fire Annunciator Panel at the On-site Fire Brigade Station; Installation of Smoke Detection System in the (a) Main Control Room Panels, (b) Essential Service Water Building. (c) Component Cooling Building pump area, chiller area and HVAC area, (d) Auxiliary Building Safety pump rooms, (e) Fuel Handling room, (f) Intermediate Building AFFW area and compressor room, and (g) Tadwaste building; inclusion of Auxiliary operators in the Fire Brigade; training of Fire Brigade Members in Plant Operation (9 week course); Development of Fire Door Inspection and

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

Nuclear Oversight Function at Krsko NPP

International Nuclear Information System (INIS)

Bozin, B.; Kavsek, D.

2010-01-01

The nuclear oversight function is used at the Krsko NPP constructively to strengthen safety and improve performance. Nuclear safety is kept under constant examination through a variety of monitoring techniques and activities, some of which provide an independent review. The nuclear oversight function at the Krsko NPP is accomplished by Quality and Nuclear Oversight Division (SKV). SKV has completed its mission through a combination of compliance, performance and effectiveness-based assessments. The performance-based assessment is an assessment using various techniques (observations, interviews, walk-downs, document reviews) to assure compliance with standards and regulations, obtain insight into performance, performance trends and also to identify opportunities to improve effectiveness of implementation. Generally, the performance-based approach to oversight function is based on some essential elements. The most important one which is developed and implemented is an oversight program (procedure). The program focuses on techniques, activities and objectives commensurate with their significance to plant operational safety. These techniques and activities are: self-assessments, assessments, audits, performance indicators, monitoring of corrective action program (CAP), industry independent reviews (such as IAEA's OSART and WANO Peer Review), industry benchmarking etc. Graded approach is an inherent product of a performance based program and ranking process. It is important not only to focus on the highest ranked performance based attributes but to lead to effective utilization of an oversight program. The attributes selected for oversight need to be based on plant specific experience, current industry operating experience, supplier's performance and quality issues. Collaboration within the industry and effective utility oversight of processes and design activities are essential for achieving good plant performance. So the oversight program must integrate relevant

Guidelines for Self-assessment of Research Reactor Safety

International Nuclear Information System (INIS)

2018-01-01

INSARR service. Other safety review services such as the Operational Safety Review Team (OSART) and the Integrated Regulatory Review Service (IRRS) have issued similar guidelines that have been proven to assist in the effective and consistent execution of missions. This publication was developed based on input from a consultants meeting and an IAEA workshop held in 2014 and 2016, respectively.

International relations

International Nuclear Information System (INIS)

Anon.

2009-01-01

The French nuclear safety authority (A.S.N.) has participated at different meeting in European Union as nuclear decommissioning assistance programme(N.D.A.P.), Regulatory assistance management group (R.A.M.G.) and Instrument for nuclear safety cooperation (I.N.S.C.). The members of Western European nuclear regulator association (W.E.N.R.A.) met and discussed about the future of W.E.N.R.A. and its representativeness and its cooperation with European nuclear safety regulator group (E.N.S.R.E.G.) and head of European radiation control authorities (H.E.R.C.A.). About International relations it is to noticed a meeting at the invitation of IAEA to discuss about the possibility to resort to the Ines scale for medical events. An audit mission under the IAEA aegis stood at Fessenheim, O.S.A.R.T. for operational safety review team. Two years and a half passed by between the audit mission Integrated regulatory review service (I.R.S.S.) welcome by A.S.N. in november 2006 and the audit mission follow up in 2009, 12 experts from 11 different countries and coordinated by three representatives of IAEA worked, the conclusions were that 90% of recommendations made to A.S.N. in 2006 were treated in a satisfying way; the evaluation gives three new recommendations, 7 new suggestions and 11 new correct practices. A meeting of the commission on safety standards (C.S.S.) stood in april 2009. Some others meeting are to be noticed: nuclear safety and security group (N.S.S.G.), expert group on nuclear and radiation safety (E.G.N.R.S.) instituted by the council of the Baltic sea states (C.B.S.S.) treats data exchange on the national networks of dose rates and surveillance of radioactivity in air. International nuclear regulator association (I.N.R.A.) held its first meeting in april 2009 at Seoul (Korea). Bilateral relations with Poland, Italy, Ukraine and Germany planed cooperation or information exchange in the field of nuclear safety. Participation to conference in Usa, meetings with United

Low Level Event and Near Miss Process for Nuclear Power Plants: Best Practices

International Nuclear Information System (INIS)

2012-01-01

The IAEA programme on the operational safety of nuclear power plants gives priority to the development and promotion of the proper use of IAEA safety standards through the provision of assistance to Member States in the application of safety standards, the performance of safety review missions and the conduct of training activities based on safety standards. A number of IAEA safety standards and nuclear safety publications discuss the processes that need to be put into place for the feedback and analysis of operating experience (OE) at nuclear power plants. These include: Fundamental Safety Principles (IAEA Safety Standards Series No. SF-1), Safety of Nuclear Power Plants: Commissioning and Operation (IAEA Safety Standards Series No. SSR-2/2), Application of the Management System for Facilities and Activities (IAEA Safety Standards Series No. GS-G-3.1) and A System for the Feedback of Experience from Events in Nuclear Installations (IAEA Safety Standards Series No. NS-G-2.11). Additionally, several IAEA TECDOCs cover many aspects of the establishment, conduct and continuous improvement of an OE programme at nuclear power plants, including the consideration of low level events (LLEs) and near misses (NMs). Although these IAEA safety standards and nuclear safety publications have been in existence for several years, 70 per cent of the IAEA Operational Safety Review Team (OSART) missions carried out at nuclear power plants between 2006 and 2010 identified weaknesses in the reporting and analysis process for LLEs and NMs. In fact, this has been one of the recurring issues most often identified in the area of OE during these missions. These weaknesses have been further confirmed by most of the IAEA Peer Review of the Operational Safety Performance Experience (PROSPER) missions that have been conducted to date. Finally, the IAEA International Nuclear Safety Group, in their report entitled Improving the International System for Operating Experience Feedback (INSAG-23

Radiation protection in Bohunice NPP. Description of present status

International Nuclear Information System (INIS)

Dobis, L.

2001-01-01

Radiation protection (RP) at Bohunice NPP has reached the high international standard. The fact was approved by several independent international missions (OSART , WANO, WENRA, ...). A lot of modifications have been done in order to improve the standard of radiation protection. All the BSS requirements have been implemented into the plant regulations before the State Law No 290/1996 and 470/2000 came into the force. Internal audits are regularly performed at NPP in order to reveal potential deficiencies. In 2001 there were 4 such audits focused on quality assurance, software operation, LBB concept and limits and condition of safe operation. State Health Institute, the regulatory body in the radiation protection, performs the inspection at least ones a month. Good relationship with the inspectors of State Health Institute also contributes to the safe operation of the NPP. There were not any radiation accident. All anomalies or radiation events are investigated at a plant level. The results of root cause analysis and proposal of corrective actions are provided to IAEA and WANO databases for the distribution. The Radiation protection department of Bohunice NPP cooperates with the other Czech and Slovak NPPs. Regular meetings on radiation protection and lately also on emergency preparedness are organized. The cooperation is excellent. Occupational exposure is reviewed also with respect of ISOE data. Bohunice NPP (even with high dose burden caused by reconstruction of V1 NPP) can be found in the first half of world PWR speaking about the collective exposure per reactor. V2 NPP itself reaches the lowest collective exposure in the world. All doses are below the limits and kept ALARA. ALARA system has been established already in 1997 at Bohunice NPP and its results are obvious for example looking at dose results during the reconstruction works at V1 NPP. The operation of Bohunice NPP has negligible influence to its surroundings. The values of gas and liquid effluents move

IAEA and WANO Mark Anniversary of Fukushima Accident, Increase Cooperation, 5 March 2012, Vienna/London

International Nuclear Information System (INIS)

2012-01-01

Full text: Next Sunday, 11 March 2012, marks the first anniversary of the devastating earthquake and tsunami that struck the east coast of Japan. One year on, the International Atomic Energy Agency (IAEA) and the World Association of Nuclear Operators (WANO) are increasing their mutual cooperation to maximise nuclear safety efforts around the globe. The two organisations are revising their Memorandum of Understanding in light of the lessons learned from the Fukushima accident, and will be stepping up their efforts to share expertise and knowledge between operators and governments. There will be greater coordination between WANO peer reviews and IAEA OSART missions, in which international experts assess the safety of individual nuclear power plants, and discussions are under way to examine further areas to improve information sharing. This is in addition to the other work each organisation is doing to reinforce nuclear safety worldwide. IAEA Director General, Yukiya Amano said: 'The IAEA is delighted to strengthen its coordination and cooperation with WANO. One of the lessons of Fukushima is the need for strong and effective communication between governments, regulators and nuclear operators. The IAEA's Action Plan on Nuclear Safety underlines the need for all stakeholders to work together to put these lessons into practice as tangibly and swiftly as possible, to deliver concrete results. By working more closely together, we can help to ensure that practical experience is properly shared to reinforce nuclear safety everywhere'. Laurent Stricker, Chairman of WANO, commented: 'While the terrible events of last year had a major lasting impact on the industry, they have also served as the catalyst for huge change. WANO has shifted from primarily focusing on accident prevention, to an emphasis on both prevention and mitigation, and has redoubled its efforts to promote excellence in nuclear safety in each and every plant across the world. All nuclear plants have carefully

Chernobyl and status of nuclear power development in the USSR

International Nuclear Information System (INIS)

Gagarinskii, A.Yu.

1989-01-01

recently concluded agreement on cooperation with the American Nuclear Society, and these problems are also reflected in this agreement. We believe that the IAEA inspections, both being carried out, as, for instance, the recent OSART mission at the Rovno NPP, and those planned, of the Soviet nuclear projects and of the operating NPPs will enable us to make the public confidence in nuclear power come back. At present the IAEA expert inspection of the Gorky NPP is being prepared, which will include both the concept and the NPP design analysis and their practical realization at the plant under construction. But first of all we rely on our own efforts. I believe that soon a new social organization will appear in the USSR - the-Soviet Nuclear Society. In any case, however, the most effective realization of the whole program of works on nuclear power needs a wide international cooperation

Chernobyl and status of nuclear power development in the USSR

Energy Technology Data Exchange (ETDEWEB)

Gagarinskii, A Yu [I.V. Kurchatov Institute of Atomic Energy, Kurchatov Square, 123182 Moscow (Russian Federation)

1989-07-01

recently concluded agreement on cooperation with the American Nuclear Society, and these problems are also reflected in this agreement. We believe that the IAEA inspections, both being carried out, as, for instance, the recent OSART mission at the Rovno NPP, and those planned, of the Soviet nuclear projects and of the operating NPPs will enable us to make the public confidence in nuclear power come back. At present the IAEA expert inspection of the Gorky NPP is being prepared, which will include both the concept and the NPP design analysis and their practical realization at the plant under construction. But first of all we rely on our own efforts. I believe that soon a new social organization will appear in the USSR - the-Soviet Nuclear Society. In any case, however, the most effective realization of the whole program of works on nuclear power needs a wide international cooperation.

Treatment of solutions of fission products - Separation of caesium-137; Traitement des solutions de produits de fission - Separation du cesium-137; Obrabotka rastvorov produktov deleniya - Razdelenie tseziya-137; Tratamiento de soluciones de productos de fision - Separacion del cesio-137

Energy Technology Data Exchange (ETDEWEB)

Stiennon-Bovy, R [Centre d' Etude de l' Energie Nucleaire, Mol (Belgium); Gvion, R [Commission Israelienne de l' Energie Atomique, Tel-Aviv (Israel)

1962-01-15

appreciable de l'activite du cesium, sa realisation a la temperature ordinaire, et la possibilite d'exploitation en regime continu. Par ce procede, la recuperation du cesium peut etre faite avant l'elimination de certains produits de fission. (author) [Spanish] Los autores han adaptado el metodo analitico de determinacion del cesio por medio de la dipierilamina a la recuperacion en escala industrial del cesio-137 contenido en soluciones de productos de fision de elevada actividad. El procedimiento propuesto permite aislar el cesio en forma de cloruro en una sola operacion y recuperar el reactivo de precipitacion con facilidad. Los autores proponen un procedimiento basico. Han estudiado el efecto de las radiaciones sobre la dipierilamina y sus compuestos. Este efecto es practicamente nulo para los compuestos solidos, y despreciable para las soluciones. Ademas, los autores han estudiado el arrastre del cesio por el ion amonico. El procedimiento descrito presenta las ventajas siguientes: elevado grado de descontaminacion del cesio, sencillez del procedimiento y facilidad con que se puede recuperar y volver a emplear el reactivo, elevado rendimiento en la recuperacion del cesio y de la dipierilamina, concentracion apreciable de la actividad del cesio, posibilidad de trabajar a temperatura ambiente, posibilidad de trabajar en regimen continuo. Este procedimiento permite recuperar cesio antes de eliminar ciertos productos de fision. (author) [Russian] Dlya promyshlennogo izvlecheniya tseziya-137 iz rastvorov produktov deleniya avtory primenili analiticheskij sposob dozirovki tseziya pri pomoshchi dipikrilamina v promyshlennom masshtabe i s vysokimi aktivnostyami. Predlagaemyj sposob pozvolyaet odnoj operatsiej izolirovat' tsezij v vide khloristogo soedineniya i legko izvlech' reagent osadka. Avtory predlagayut printsipial'nuyu skhemu. Oni izuchili dejstvie izluchenij na dipikrilamin i ego soedineniya. EHto dejstvie okazyvaetsya prakticheski ravnym nulyu dlya tverdykh soedinenij i

A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers

Energy Technology Data Exchange (ETDEWEB)

Parker, K [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

1962-03-15

vklyuchayut mnogogruppovoe transportnoe priblizhenie i polnuyu obrabotku anizotropnogo rasseyaniya, ispol'zuya momenty mnogochlena Lezhandra matritsy peredachi rasseyaniya. Printsipy obrazovaniya gruppovoj postoyannoj obsuzhdayutsya i illyustriruyutsya pri pomoshchi opisaniya sistem gruppovykh postoyannykh, podkhodyashchikh dlya raschetov reaktorov na bystrykh nejtronakh. Obsuzhdayutsya takie prakticheskie problemy, kak ehmpiricheskoe sogla- sovanie gruppovykh postoyannykh dlya vosproizvodstva integral'nykh rezul'tatov i prive-denie mnogogruppovoj sistemy postoyannykh k malogruppovoj sisteme. (author)

The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II

Energy Technology Data Exchange (ETDEWEB)

Loewenstein, W. B. [Argonne National Laboratory, Argonne, IL (United States)

1962-03-15

hexagonal del reactor los datos obtenidos en geometrias simples idealizadas, analiticas o experimentales. Se compara el rendimiento nuclear, incluso el de reproduccion, del reactor real con el del modelo teorico y se describen las variaciones a largo plazo de la reactividad y de la generacion de energia en la envoltura fertil, refiriendolas a los ciclos propuestos para el combustible y la envoltura fertil. La memoria formula consideraciones sobre la seguridad estudiando en particular la introduccion de indices de reactividad normales y anormales y la consecuencia de supuestos efectos de reactividad, que se basan en el comportamiento fisico de la aleacion combustible y de la estructura del reactor, asi como en la extrapolacion al sistema del EBR-II de los experimentos realizados con el conjunto TREAT. Por ultimo, examina el problema de la fusion del cuerpo del reactor EBR-II. (author) [Russian] Vychisleniya statisticheskogo, dinamicheskogo i dlitel'nogo rezhima reaktivnosti ehksperimental'nog o reaktora-razmnozhitel ya EBR-II dayutsya sovmestno s rezul'tatami i analizom ehksperimentov na reaktore EBR-II po dostizheniyu kritichnosti v sukhom sostoyanii i otdel'nykh ehksperimentov na reaktore ZPR-III. Osoboe vnimanie udelyaetsya problemam fizicheskogo rascheta reaktora, kotorye voznikayut posle opredeleniya printsipial'noj skhemy i do sooruzheniya ili vvoda reaktora v ehkspluatatsiyu. Opisyvayutsya analiz bezopasnosti reaktora i soobrazheniya po otsenke opasnostej, a takzheikh vliyanie na raschet reaktora. V doklade opisyvaetsya sposob ispol'zovaniya modeli EBR-II na osnovanii poluchennykh na reaktore ZPR-III dannykh, a takzhe dannykh sukhoj kritichnosti reaktora EBR-II. EHti ehksperimenty, ikh analiz i teoreticheskie vykladki yavlyayutsya osnovoj dlya opredeleniya fizicheskogo povedeniya reaktornoj sistemy. Bolee podrobno issleduyutsya ogranicheniya, prisushchie primeneniyu ehksperimental'nykh dannykh k rassmatrivaemo j ehnergeticheskoj reaktornoj sisteme. Syuda otnosyatsya

IAEA and WANO Sign New Memorandum of Understanding

International Nuclear Information System (INIS)

2012-01-01

Full text: The International Atomic Energy Agency (IAEA) and the World Association of Nuclear Operators (WANO) have signed a new Memorandum of Understanding (MoU) to reflect increased cooperation between the two organisations following the Fukushima Daiichi accident of March 2011. The new agreement enables the two organisations to work more closely together to support the safe and reliable operation of nuclear power plants worldwide, and to enhance information exchange on operating experience and other relevant areas. Through the IAEA's Nuclear Safety Action Plan, IAEA Member States urged the IAEA and WANO to strengthen their MoU to enhance information exchange. WANO member operators also recommended stronger collaboration. Through the new agreement, the two organisations are adopting a more coordinated approach to their respective activities, in order to help prevent further accidents and mitigate the consequences should an accident occur. Plans are now in place to coordinate the timing of IAEA Operational Safety Review Team (OSART) missions and WANO peer reviews, and to arrange periodic meetings of WANO and Agency staff to discuss major safety-related activities. The two organisations will also cooperate and coordinate work on their respective performance indicator programmes and will work towards exchanging information and support in the event of a serious event at a nuclear power plant or fuel cycle facility. In addition to this, the IAEA and WANO will supply staff to each other's review teams when appropriate, and will regularly exchange documents relating to operating experience. Yukiya Amano, Director General of the IAEA, said: ''The IAEA's Action Plan on Nuclear Safety emphasises the importance of working more closely with WANO and other international organisations, so that we can all better address the demands of the future. This agreement is an important step in strengthening that cooperation and enhancing the flow of information on nuclear safety issues

New Instruments and Principles for the Dimensional Measurement and Measurement of Spacing of Reactor Components; Nouveaux Instruments et Procedes de Mesure des Dimensions et de l'Espacement des Elements d'un Reacteur; Novye pribory i printsipy izmereniya razmerov i raspolozheniya komponentov reaktora; Nuevos Instrumentos y Principios para Medir las Dimensiones y la Separacion Entre Componentes de Reactor

Energy Technology Data Exchange (ETDEWEB)

Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

1965-09-15

Full text: The measurement of wall thickness of austenitic and non-ferrous sheets, tubes and containers is presented. Two methods for contactless measurement are discussed: eddy- current method for measuring the thickness of non-ferrous and austenitic sheets and containers by means of transition coils; eddy-current measurement of the wall thickness of tubes by means of feed-through coils. Suitable instruments and their application are shown. Wall-thickness measurement on non-ferrous reactor assemblies by the ''magnetic ball method'' is also discussed. The principle of this new type of measurement is explained, its range of use - especially for spot- measurements - is discussed, and a practical instrument is described. Measurement of non-magnetic coatings on magnetic base materials is discussed. The measurement principles (magnetic DC and AC field methods) are explained and instruments for measurement of nonmagnetic coatings between 3-{mu}m and 20-mm thickness are shown. The special problem of measurement of stellite deposits on ferritic walls of reactor vessels is discussed. The measurement of electrically non-conductive coatings on base materials consisting of non-ferrous metals; and the principle of measurement (eddy currents) are explained. An instrument for this purpose is shown and typical examples of measurements are given. Contactless in-line measurements of physical dimensions of metallic reactor components are given. Various methods for ferrous and non-ferrous metals are explained (magnetic DC and AC field method, eddy-current methods). Instruments and examples for remote measurements of diameter, ovality, distortion etc., of reactor components are described, and methods of measuring the spacing of such components in the ''hot'' zone of the reactor are shown. An instrument for recording the surface profile and for direct reading the roughness values (''Rauhtiefe'', ''Glaettungstiefe'', CLA value and RMS value) is shown. Typical examples of the use of the instrument for reactor components are discussed. Special attention is given to the possibility of using a small and versatile pick-up by means of manipulators in the ''hot'' zones and on ''hot'' materials. The increase of surface roughness with increasing irradiation dose is discussed. (author) [French] Full text: L'auteur presente les problemes de mesure de l'epaisseur de feuilles et des parois de tubes et recipients en aciers austenitiques ou en metaux non ferreux. Deux methodes de mesure des epaisseurs sans contact sont discutees: la mesure, par courants de Foucault, de l'epaisseur de feuilles et des parois de recipients en metaux non ferreux ou en aciers austenitiques, au moyen de bobines se deplacant le long des pieces a examiner: la mesure, par courants de Foucault, de l'epaisseur des parois de tubes, au moyen de bobines dans lesquelles se deplacent les pieces a examiner. L'auteur decrit des instruments appropries et le mode d'utilisation. Il discute egalement la mesure de l'epaisseur des parois de parties constitutives de reacteurs, en metaux non ferreux, par la 'methode de la bille magnetique' et explique le principe de ce nouveau type de mesure et son domaine d'utilisation - notamment pour les mesures par points; il decrit un instrument approprie. L'auteur examine la mesure des revetements non magnetiques de materiaux magnetiques; il explique les principes de mesure (methodes fondees sur les champs magnetiques des courants continus et des courants alternatifs) et decrit des instruments de mesure de revetements non magnetiques dont l'epaisseur varie entre 3 {mu}m et 20 mm. Il expose le probleme special de la mesure des depots de stellite sur les parois en aciers ferritiques des cuves de reacteurs. La mesure des revetements non conducteurs de metaux non ferreux est etudiee. Le memoire explique le principe de mesure (courants de Foucault). Il decrit un instrument approprie et donne des exemples de mesures typiques. L'auteur examine egalement la mesure sans contact, en continu, des dimensions de parties constitutives metalliques de reacteurs et explique diverses methodes de mesure pour les metaux terreux et non terreux (champs magnetiques des courants continus et des courants alternatifs, courants de Foucault). Il decrit des instruments et donne des exemples de mesure telecommandee du diametre, de l'ovalisation, de la distorsion, etc., de diverses pieces; il expose des methodes de mesure de l'espacement des elements de la zone active du reacteur. Le memoire decrit un instrument permettant d'enregistrer le profil de surface et de faire la lecture directe des valeurs de la rugosite (profondeur de rugosite, degre de polissage, direction des irregularites et valeur quadratique moyenne). Il donne des exemples typiques d'emploi de cet instrument pour les pieces d'un reacteur. L'auteur traite en particulier de la possibilite d'utiliser un petit lecteur polyvalent, a l'aide de manipulateurs, dans les zones actives et pour les matieres 'chaudes'. Il discute l'augmentation de la rugosite de surface en fonction de l'accroissement de l'irradiation. (author) [Spanish] Full text: El autor presenta los problemas de medicion del espesor de hojas y de paredes de tubos y recipientes de material austenftico y no ferroso. Se exponen dos metodos para medir el espesor de paredes sin usar elementos en contacto con las mismas: el metodo de las corrientes de Foucault para medir el espesor de hojas y recipientes de material no ferroso y austenftico, empleando bobinas de transicion, y el empleo de corrientes de Foucault para medir espesores de pared en tubos mediante bobinas anulares extensivas. Se describen los instrumentos adecuados y sus aplicaciones. El autor discute ademas la medicion de espesores de pared en componentes no ferrosos para reactores mediante el 'metodo de la esfera magnetica' y explica el principio de este nuevo procedimiento de medicion, se analiza su alcance, sobre todo para mediciones localizadas, y se describe un instrumento utilizado en la practica. Se examina la medicion de recubrimientos no magneticos aplicados sobre materiales magneticos, se explican los principios de la medicion (metodos de campo magnetico con corriente continua y alterna) y se describen instrumentos para medir recubrimientos no magneticos de espesor comprendido entre 3 {mu}m y 20 mm. Se analiza el problema especial de medir depositos de estelita sobre paredes ferrnicas de recipientes de reactor. Se estudia la medicion de recubrimientos no conductores, aplicados sobre metales no ferrosos. Se explica el principio de medicion (corrientes de Foucault), se describe un instrumento destinado a este fin y se dan ejemplos tfpicos de. mediciones. El autor examina tambien la medicion de dimensiones ffsicas de los componentes metalicos de reactores, sin elementos en contacto con los mismos y describe diversos metodos aplicables a metales ferrosos y no ferrosos (metodo del campo magnetico con corriente continua y alterna, metodo de corrientes de Foucault), Se describen instrumentos y se dan ejemplos de mediciones a distancia del diametro, ovalidad, distorsion, etc., de componentes de reactor. Se exponen metodos para medir la separacion entre tales componentes, en la zona radiactiva del reactor. Se describe un instrumento para registrar perfiles de superficies y para indicacion directa de valores de aspereza ('Rauhtiefe', 'Glaettungstiefe', valor promedio y valor cuadratico medio). Se analizan ejemplos tfpicos del empleo de este instrumento para componentes de reactor. Se presta especial atencion a la posibilidad de usar un captador pequeno y de aplicaciones multiples mediante manipuladores en zonas y en materiales radiactivos. Se analiza el aumento de la aspereza superficial en funcion de la dosis de irradiacion. (author) [Russian] Full text: Rassmatrivaetsja izmerenie tolshhiny listov i tolshhiny stenok trub i kontejnerov iz austenitnyh i cvetnyh metallov. Obsuzhdajutsja dva metoda beskontaktnogo izmerenija tolshhiny stenok: a) metod vihrevyh tokov dlja izmerenija tolshhiny listov i kontejnerov iz cvetnyh i austenitnyh metallov s pomoshh'ju perehodnyh katushek; b) metod vihrevyh tokov dlja izmerenija tolshhiny stenok trub s pomoshh'ju prohodnyh katushek. Opisyvajutsja prigodnye dlja jetogo pribory i ih primenenie. Izmerenie tolshhiny stenok uzlov reaktora iz cvetnyh metallov po 'metodu magnitnogo sharai . Ob'jasnjaetsja princip jetogo novogo vida izmerenij, oblast' ego primenenija (osobenno dlja tochechnyh izmerenij) i opisyvaetsja primenjaemyj na praktike pribor. Izmerenie materialov nemagnitnyh pokrytij na magnitnoj osnove. Ob'jasnjajutsja principy izmerenij (metody magnitnogo polja postojannogo toka i peremennogo toka) i opisyvajutsja pribory dlja izmerenija nemagnitnyh pokrytij tolshhinoj ot 3 mikron do 20 mm. Osobo rassmatrivaetsja problema otlozhenija stellita na ferritnyh stenkah korpusov reaktorov. Izmerenie pokrytij, neprovodjashhih jelektrichestvo,-na materialah iz cvetnyh metallov. Ob'jasnjaetsja princip takogo izmerenija (vihrevye toki). Opisyvaetsja pribor dlja .takih izmerenij i tipichnye primery izmerenij. Privodjatsja beskontaktnye tehnologicheskie izmerenija fizicheskih razmerov metallicheskih komponentov reaktora. Ob{sup j}asnjajutsja razlichnye metody izmerenija chernyh i cvetnyh metallov (metod magnitnogo polja postojannogo toka i peremennogo toka, metody vihrevyh tokov). Opisyvajutsja pribory i primery distancionnogo izmerenija diametra oval'nosti, iskazhenija i t.d. komponentov reaktora. Opisyvajutsja metody opredelenija raspolozhenija takih komponentov v 'gorjachej' zone reaktora. ' Opisyvaetsja pribor dlja registracii profilja poverhnosti i neposredstvennogo opredelenija haraktera nerovnosti (''Rauhtiefe'', ''Glaettungstiefe'', GLA value i RMS value). Rassmatrivajutsja tipichnye primery ispol'zovanija jetogo pribora opredelenija nerovnostej komponentov reaktora. Osoboe vnimanie udeljaetsja vozmozhnosti ispol'zovanija nebol'shogo universal'nogo datchika v ''gorjachih'' zonah i ''gorjachih'' materialah. Rassmatrivaetsja vopros ob uvelichenii nerovnostej poverhnosti pri uvelichenii doz obluchenija. (author)

Retention of knowledge and experience from experts in near-term operating plants

International Nuclear Information System (INIS)

Jiang, H.

2007-01-01

safety and quality of nuclear power plants. For example, documentation/procedure system can have a big effect on the knowledge management. In order to keep complete information of the procedures and their change, not only should the change be documented, but also the cause and effect of the change should be formally documented. Human resource is essential support for successful knowledge management. It is well know in the industry that the implementation of SAT is very resource-consuming labour, especially for human resource. And well-kept information manage system need not just experts in archive and computer technology, but also expertise in operation, maintenance, etc. to fulfill the function in data collecting, analyzing, keeping, organizing, and utilizing. Furthermore, there should be additional personnel deployed in operating, maintenance departments to support the function of knowledge management. And to make the matter worse, strain of human resource on knowledge management is a chick and egg situation. Above all, managers' recognition of the significance and impact of knowledge management is the decisive factor and of paramount importance. Therefore, to spur the successful application of knowledge management, it is not enough to call on the training and information management experts to focus on knowledge management by TECDOC or conference. More intense measure should be taken to attract the attention of higher management, as high as possible, by items in safety standards, performance objectives and criteria, or OSART Guidelines. And the transfer of good-practice and experience should be extensive by many and various ways, e.g. workshop, document and experts exchange, so as to cover all important elements in knowledge management and narrow the gap between newly operating organizations and well-developed organizations. (author)

Efficiency of the Shut-Down and Safety Equipment and the Kinetic Characteristics of the G2 and G3 Reactors; Efficacite des dispositifs de secours et de securite et caracteristiques cinetiques des piles G2 et G3; Ehffektivnost' sistem avarijnoj zashchity reaktorov G.2 i G.3 i kineticheskie kharakteristiki ehtikh sistem; Caracteristicas cineticas y eficacia de los dispositivos de auxilio y de seguridad de los reactores G2 y G3

Energy Technology Data Exchange (ETDEWEB)

Henri, C.; Plisson, J.; Teste duBailler, A. [Centre d' Etudes Nucleaires de Saclay (France)

1963-10-15

dispositivos de seguridad instalados. (author) [Russian] Opyt, priobretennyj v techenie neskol'kikh let ehkspluatatsii reaktorov G.2 i G.3, daet vozmozhnost' podtverdit' vysokuyu stepen' bezopasnosti raboty semejstva reaktorov na prirodnom urane, grafite i gaze. Opisyvayutsya ustanovki avarijnoj zashity, kotorye pozvolyaet predotvrashchat', s odnoj storony, takie avarii kak prekrashchenie postupleniya ehlektroehnergii v raspredelitel'nuyu set', ostanovka tsirkulyatsii gaza, prekrashchenie podachi vody i t.d., i, s drugoj storony, takie avarii, kak razrushenie obolochki, mestnye peregrevy, poterya zhidkogo teplonositelya i t.d. Printsipial'nye skhemy dayut ob{sup y}asnenie rabote ehtikh ustanovok. Izuchaetsya, glavnym obrazom, ehlektrosnabzhenie i ''kontrol''' pri avarijnykh situatsiyakh, avarijnoe snabzhenie vodoj i tsepochka avarijnoj zashchity. Ukazyvayutsya posledovatel'nye izmeneniya i uluchsheniya ehtikh ustanovok S pomoshch'yu ehksperimental'nogo issledovaniya povedeniya reaktorov na nestatsionarnom rezhime vyyavlyayutsya vnutrenne prisushchie ehtim reaktoram kharakteristiki zashchity. Issledovaniya pozvolyayut podttverdit' prigodnost' raschetnogo metoda. (author)

Introductory Statement to Board of Governors, 4 March 2013, Vienna, Austria

International Nuclear Information System (INIS)

Amano, Y.

2013-01-01

major undertaking and I would be grateful for the active support of all Member States. The IAEA Action Plan on Nuclear Safety calls for Member States to make more use of IAEA peer reviews. Many have done so. However, not all Member States with nuclear power have requested operational safety review - OSART - missions in line with the Action Plan. I encourage all countries to do so. This would help to achieve a high level of safety nuclear power plants, including adequate preparedness to manage severe accidents. Of course, nuclear safety is not just about nuclear power plants and fuel cycle facilities. It is also important to protect the public and the environment from exposure to radioactive sources, and to protect medical staff and patients from unnecessary and unintended exposure to radiation. These are issues for all countries. In December, the Agency organized an international conference in Bonn, Germany on Radiation Protection in Medicine. The Conference agreed the Bonn Call for Action, which recommended practical measures to improve protection for patients and health workers against over-exposure to ionizing radiation. In October this year, an International Conference on the Safety and Security of Radioactive Sources will be held in Abu Dhabi, United Arab Emirates. I encourage all Member States to participate. Preparations for the IAEA International Conference on Nuclear Security in July are progressing. I am grateful to the Minister of Foreign Affairs of Hungary, His Excellency Mr. Janos Martonyi, for agreeing to serve as President of this Conference. I encourage all countries to participate at ministerial level. The Ambassador of Hungary will take the lead in coordinating open-ended consultations among Member States. The Ambassador of Brazil, who has been acting as Chairman of the Programme Committee for this Conference, will act as Co-Chair. I thank Ambassadors Csuday and Vinhas for their willingness to take on these important roles.

Advanced epithermal thorium reactor (AETR) physics; Physique d'un reacteur au thorium, a neutrons epithermiques, de type perfectionne (AETR); Fizika usovershenstvovannog o nadteplovogo torievogo reaktora; Fisica del reactor epitermico de tipo avanzado, alimentado con torio (AETR)

Energy Technology Data Exchange (ETDEWEB)

Campise, A. V. [Atomics International, Canoga Park, CA (United States)

1962-03-15

del {sup 233}Pa y de isotopos del uranio sobre el balance neutronico relativo y se evalua la probable razon de reproduccion y las caracteristicas de combustion teniendo en cuenta la imprecision en el conocimiento de las secciones eficaces nucleares. (author) [Russian] Rassmatrivayuts ya printsipy konstruirovani ya usovershenstvovannog o nadteplovogo torievogo reaktora s uchetom sushchestvuyushchej teorii yadernykh parametrov i potentsial'nogo poleznogo ispol'zovaniya nejtronov. Byl izuchen ehffekt rezonansnogo zakhvata toriya v sistemakhs grafitovym zamedlitelem dlya nejtronov s ehnergiyami ot 0,10 do 100 kehv. Ispol'zuyutsya formuly uzkogo rezonansa i shirokogo rezonansa v tselyakh polucheniya zavisimogo ot temperatury ehffektivnogo rezo- nansnogo integrala torievogo sterzhnya, kotoryj vyrazhaetsya v vide ehkvivalentnykh mnogogruppovykh sechenij. Neobkhodimost' v poluchenii yadernykh dannykh v oblasti promezhutochnykh ehnergij privela k sozdaniyu proekta i konstruktsii kriticheskoj sborki. Yadernyj proekt ehtoj sborki podcherkivaet vazhnost' dannykh poperechnykh sechenij i teoreticheskoj interpretatsii ehksperimental'nykh rezul'tatov, imeyushchikh otnoshenie k usovershenstvovannom u nadteplovomu torievomu reaktoru. Tochnost' analiticheskikh metodov byla podtverzhdena pri analize ehksperimental'nykh rezul'tatov, poluchennykh na reaktore nulevoj moshchnosti ZPR-III. Provodyatsya sravneniya trekh konfiguratsij teploperedachi s ispol'zovaniem udvoennogo vremeni v kachestve optimal'nogo parametra. EHffekt proizvodstva izotopa protaktiniya-233 i urana pri otnositel'no poleznom ispol'zovanii nejtronov, vozmozhnye koehffitsienty vosproizvodstva i kharakteristiki vygoraniya otsenivayutsya v svyazi s netochnostyami v yadernykh poperechnykh secheniyakh. (author)

IAEA Completes Expert Mission to Kori 1 Nuclear Power Plant in the Republic of Korea

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) has completed a review of safety practices at the Kori 1 Nuclear Power Plant (NPP) near Busan in the Republic of Korea. The IAEA assembled the team at the request of Korea Hydro and Nuclear Power Co., Ltd. (KHNP) following a station blackout event on 9 February 2012. The team - comprised of experts from Belgium, France, Sweden, United Kingdom and the IAEA - conducted its mission from 4 to 11 June 2012 under the leadership of the IAEA's Division of Nuclear Installation Safety. The expert mission applied the methodology of the IAEA's Operational Safety Review (OSART) missions and covered the areas of Management, Organization and Administration; Operations; Maintenance and Operating Experience. The conclusions of the review are based on the IAEA's Safety Standards, which are developed by the Agency to help nations improve their nuclear safety practices, which are the responsibility of every nation that undertakes nuclear-related activities. Throughout the review, the exchange of information between the experts and plant personnel was very open, professional and productive. Prior to the mission, Korea's Nuclear Safety and Security Commission completed an interim investigation, and it continues to perform additional investigations and technical reviews. The Commission identified corrective actions for the plant concerning reinforcing safety culture, emergency diesel generator reliability, configuration control and risk management during refueling outage, test and maintenance procedures and emergency action level declaration. The expert mission confirmed that some corrective actions have already been completed and others are in progress. The expert mission found the management and staff of Kori 1 NPP to be committed and working hard to complete all improvements. The root cause analysis of the event at Kori 1 NPP is still in progress and is expected to lead to

Radioactive apparatus for measuring the thickness of hot sheet-metal; Jauge d'epaisseur radioactive pour la mesure a chaud de plaques metalliques; Radioaktivnyj izmeritel' tolshchiny goryachego listovogo prokata; Calibrador radiactivo para la medicion en caliente de chapas

Energy Technology Data Exchange (ETDEWEB)

Vasichev, B N; Latyshev, V K; Pliskin, Yu S; Felinger, A K

1962-01-15

}Cs de actividad equivalente a la de 9,2 g de radio, es posible medir el espesor de chapas calientes del espesor mencionado con un margen de aproximacion de {+-} 0,1 mm. El aparato efectua las mediciones a razon de una por segundo y funciona satisfactoriamente en las condiciones que exigen las operaciones de laminado. (author) [Russian] Dlya polucheniya vysokoj tochnosti izmerenij v usloviyakh prokatnogo proizvodstva vybran dinamicheskij metod kompensatsii, pri kotorom parametr sravneniya prokhodit vse znacheniya v izmeryaemoj oblasti, a nul'-organ otmechaet lish' moment ravenstva izmeryaemogo parametra i parametra sravneniya. Ispol'zovanie ehtogo metoda dalo vozmozhnost' osvobodit'sya ot mekhanicheskikh obratnykh svyazej i peremennykh po svoemu kharakteru peremeshchenij, svojstvennykh metodu staticheskoj kompensatsii, i sozdat' pribor, udovletvoryayushchij kak trebovaniyam tochnosti, tak i bystrodejstviya v slozhnykh usloviyakh prokatnogo proizvodstva. V doklade izlagaetsya printsipial'naya skhema pribora dlya kontrolya tolshchiny lista v protsesse prokatki, rassmatrivayutsya faktory, vliyayushchie na tochnost' izmereniya tolshchiny goryachego lista (temperatura, volnistost', nalichie vody na poverkhnosti lista, material lista i ego polozhenie na rol'gange). Opisyvaetsya konstruktivnoe vypolnenie opytno-promyshlennogo obraztsa pribora na diapazone tolshchin ot 14 mm do 44 mm. Promyshlennye ispytaniya pribora pokazali, chto pri istochnike izlucheniya Cs{sup 137} aktivnost'yu 9,2 g-ehkv. radiya tochnost' izmereniya tolshchiny goryachego lista v ukazannom vyshe diapazone sostavlyaet {+-}0,1 mm. Bystrodejstvie pribora - odno izmerenie v sekundu. Pribor nadezhno rabotaet v usloviyakh prokatnogo tsekha. (author)

Implementing and measuring safety goals and safety culture. 4. Utility's Activities for Better Safety Culture After the JCO Accident

International Nuclear Information System (INIS)

Omoto, Akira

2001-01-01

The criticality accident at the JCO plant prompted the Government to enact a law for nuclear emergency preparedness. The nuclear industry established NSnet to facilitate opportunities for peer review among its members. This paper describes the activities by NSnet and TEPCO's Kashiwazaki-Kariwa nuclear power station (NPS) for a better safety culture. Created as a voluntary organization by the nuclear industry in 1999, NSnet has 35 members and is assisted by CRIEPI and NUPEC for its activities relevant to human factors. Given the fact that nuclear facility operators not belonging to WANO had no institutional system available for exchange of experiences and good practices for better safety among themselves, NSnet's activities focus on peer review by member organizations and onsite seminars. Starting April 2000 with visits to three fuel fabricators, NSnet intends to have 23 peer-review visits in 2 yr (Ref. 1). The six-member review team stays on-site for 4 days, during which time they review-using guidelines available from WANO and IAEA-OSART-six areas: organization/management, emergency preparedness, education/training, operation/ maintenance, protection against occupational radiation exposure, and prevention of accidents. A series of on-site seminars is held at members' nuclear facilities, to which NSnet dispatches experts for lectures. NSnet plans to hold such seminars twice per month. Other activities include information-sharing through a newsletter, a Web site (www. nsnet.gr.jp), and others. Although considerable differences exist in the design and the practices in operation/maintenance between power reactors and JCO, utilities can extract lessons from the accident that will be worth consideration for their own facilities in the areas of safety culture, education and training, and interface between design and operation. This thinking prompted the Nuclear Safety Promotion Center at Kashiwazaki-Kariwa NPS, to which the author belonged at that time, to launch the

Conclusions and Recommendations of the IAEA International Conference on Topical Issues in Nuclear Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

Main Conclusions and Recommendations of International Conference on Topical Issues in Nuclear Installation Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

Radiation Synthesis of Stannous Dibromodibutyl; Synthese radiochimique de l'etain dibromopibutyle; Radiatsionno-khimicheskij sintez dibromdibutilolova; Sintesis radioquimica del dffiromodibutilestano

Energy Technology Data Exchange (ETDEWEB)

Abramova, L. V.; Vereshchinskij, I. V.; Kocheshkov, K. A.; Miretskij, V. Yu.; Pozdneev, V. V.; Ryabukhin, Yu. S.; Sheverdina, N. I.

1963-11-15

dosimetro de sulfato de hierro es de {approx}50 rad/s. Se utilizaron diversas proporciones de estafio metalico en polvo y bromuro de butilo de distintos grados de pureza. Se comprobo que en tales condiciones se desarrolla una reaccion radioquimica orientada en virtud de la cual se produce basicamente dibromodibutilestaflo con elevado rendimiento. Se demostro que el proceso tiene un periodo de induccion cuya duracion depende de la pureza del bromuro de butilo inicial. Este mismo factor influye tambien notablemente en la velocidad de formacion del producto final. Se comprobo que el estafio que no interviene en la reaccion puede volver a utilizarse para obtener dibromodibutilestaflo, pero en ese caso se anula por completo el periodo de induccion. Estas propiedades satisfacen los requisitos para la realizacion de un proceso continuo. Los autores proponen un mecanismo de reaccion, para explicar las leyes de este proceso que se desarrolla con un elevado rendimiento radioquimico. (author) [Russian] Printsipial'naya vozmozhnost' sinteza olovoorganicheskikh soedinenij pri dejstvii {gamma}-izlucheniya Co{sup 60} na smesi metallicheskogo olova i sootvetstvuyushchikh galoidalkilov vpervye byla ustanovlena Abramovoj, Kocheshkovym i SHeverdinoj v 1956 g. Usloviya provedeniya opytov v steklyannoj apparature bez peremeshivaniya ne pozvolyali vyyavit' kineticheskie zakonomernosti obrazovaniya ehtogo klassa metalloorganicheskikh soedinenij. Nastoyashchaya rabota byla postavlena dlya vyyasneniya vliyaniya ryada faktorov na skorost' radiatsionno-khimicheskogo sinteza olovoorganicheskikh soedinenij na primere dibromdibutilolova. S ehtoj tsel'yu byla skonstruirovana i izgotovlena spetsial'naya ustanovka s periodicheskoj zagruzkoj komponentov i vygruzkoj produktov reaktsii. Otlichitel'nymi osobennostyami ustanovki yavlyalis' vozmozhnost' ee termostatirovaniya, osushchestvlenie ehffektivnogo peremeshivaniya i periodicheskogo otbora prob dlya analizov. Osnovnoj uzel ustanovki (reaktsionnyj sosud iz