Safety principles and design criteria for nuclear power stations

International Nuclear Information System (INIS)

Gazit, M.

1982-01-01

The criteria and safety principles for the design of nuclear power stations are presented from the viewpoint of a nuclear engineer. The design, construction and operation of nuclear power stations should be carried out according to these criteria and safety principles to ensure, to a reasonable degree, that the likelihood of release of radioactivity as a result of component failure or human error should be minimized. (author)

Safety criteria for design of nuclear power plants

International Nuclear Information System (INIS)

1997-01-01

In Finland the general safety requirements for nuclear power plants are presented in the Council of State Decision (395/91). In this guide, safety principles which supplement the Council of State Decision and which are to be used in the design of nuclear power plants are defined

Design of concrete structures important to safety of nuclear facilities

International Nuclear Information System (INIS)

2001-10-01

Civil engineering structures in nuclear installations form an important feature having implications to safety performance of these installations. The objective and minimum requirements for the design of civil engineering buildings/structures to be fulfilled to provide adequate assurance for safety of nuclear installations in India (such as pressurised heavy water reactor and related systems) are specified in the Safety standard for civil engineering structures important to safety of nuclear facilities. This standard is written by AERB to specify guidelines for implementation of the above civil engineering safety standard in the design of concrete structures important to safety

Engineering design guidelines for nuclear criticality safety

International Nuclear Information System (INIS)

Waltz, W.R.

1988-08-01

This document provides general engineering design guidelines specific to nuclear criticality safety for a facility where the potential for a criticality accident exists. The guide is applicable to the design of new SRP/SRL facilities and to major modifications Of existing facilities. The document is intended an: A guide for persons actively engaged in the design process. A resource document for persons charged with design review for adequacy relative to criticality safety. A resource document for facility operating personnel. The guide defines six basic criticality safety design objectives and provides information to assist in accomplishing each objective. The guide in intended to supplement the design requirements relating to criticality safety contained in applicable Department of Energy (DOE) documents. The scope of the guide is limited to engineering design guidelines associated with criticality safety and does not include other areas of the design process, such as: criticality safety analytical methods and modeling, nor requirements for control of the design process

General design safety principles for nuclear power plants

International Nuclear Information System (INIS)

1986-01-01

This Safety Guide provides the safety principles and the approach that have been used to implement the Code in the Safety Guides. These safety principles and the approach are tied closely to the safety analyses needed to assist the design process, and are used to verify the adequacy of nuclear power plant designs. This Guide also provides a framework for the use of other design Safety Guides. However, although it explains the principles on which the other Safety Guides are based, the requirements for specific applications of these principles are mostly found in the other Guides

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition); Bezopasnost' atomnykh ehlektrostantsij: proektirovanie. Konkretnye trebovaniya bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Code on the safety of nuclear power plants: Design

International Nuclear Information System (INIS)

1988-01-01

This Code is a compilation of nuclear safety principles aimed at defining the essential requirements necessary to ensure nuclear safety. These requirements are applicable to structures, systems and components, and procedures important to safety in nuclear power plants embodying thermal neutron reactors, with emphasis on what safety requirements shall be met rather than on specifying how these requirements can be met. It forms part of the Agency's programme for establishing Codes and Safety Guides relating to land based stationary thermal neutron power plants. The document should be used by organizations designing, manufacturing, constructing and operating nuclear power plants as well as by regulatory bodies

Nuclear safety

International Nuclear Information System (INIS)

Tarride, Bruno

2015-10-01

The author proposes an overview of methods and concepts used in the nuclear industry, at the design level as well as at the exploitation level, to ensure an acceptable safety level, notably in the case of nuclear reactors. He first addresses the general objectives of nuclear safety and the notion of acceptable risk: definition and organisation of nuclear safety (relationships between safety authorities and operators), notion of acceptable risk, deterministic safety approach and main safety principles (safety functions and confinement barriers, concept of defence in depth). Then, the author addresses the safety approach at the design level: studies of operational situations, studies of internal and external aggressions, safety report, design principles for important-for-safety systems (failure criterion, redundancy, failure prevention, safety classification). The next part addresses safety during exploitation and general exploitation rules: definition of the operation domain and of its limits, periodic controls and tests, management in case of incidents, accidents or aggressions

Radiation protection aspects of design for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Request from nuclear fuel cycle and criticality safety design

International Nuclear Information System (INIS)

Hamasaki, Manabu; Sakashita, Kiichiro; Natsume, Toshihiro

2005-01-01

The quality and reliability of criticality safety design of nuclear fuel cycle systems such as fuel fabrication facilities, fuel reprocessing facilities, storage systems of various forms of nuclear materials or transportation casks have been largely dependent on the quality of criticality safety analyses using qualified criticality calculation code systems and reliable nuclear data sets. In this report, we summarize the characteristics of the nuclear fuel cycle systems and the perspective of the requirements for the nuclear data, with brief comments on the recent issue about spent fuel disposal. (author)

Analysis of effect of safety classification on DCS design in nuclear power plants

International Nuclear Information System (INIS)

Gou Guokai; Li Guomin; Wang Qunfeng

2011-01-01

By analyzing the safety classification for the systems and functions of nuclear power plants based on the general design requirements for nuclear power plants, especially the requirement of availability and reliability of I and C systems, the characteristics of modem DCS technology and I and C products currently applied in nuclear power field are interpreted. According to the requirements on the safety operation of nuclear power plants and the regulations for safety audit, the effect of different safety classifications on DCS design in nuclear power plants is analyzed, by considering the actual design process of different DCS solutions in the nuclear power plants under construction. (authors)

Safety principles and design management of Chashma Nuclear Power Plant

International Nuclear Information System (INIS)

Geng Qirui; Cheng Pingdong

1997-01-01

The basic safety consideration and detailed design principles in the design of Chashma Nuclear Power Plant is elaborated. The management within the frame setting up by 'safety culture' and 'quality culture'

Design characteristics of safety parameter display system for nuclear power plants

International Nuclear Information System (INIS)

Zhang Yuangfang

1992-02-01

The design features of safety parameter display system (SPDS) developed by Tsinghua University is introduced. Some new features have been added into the system functions and they are: (1) hierarchical display structure; (2) human factor in the display format design; (3)automatic diagnosis of safety status of nuclear power plant; (4) extension of SPDS use scope; (5) flexible hardware structure. The new approaches in the design are: (1)adopting the international design standards; (2) selecting safety parameters strictly; (3) developing software under multitask operating system; (4) using a nuclear power plant simulator to verify the SPDS design

Planning and architectural safety considerations in designing nuclear power plants

International Nuclear Information System (INIS)

Konsowa, Ahmed A.

2009-01-01

To achieve optimum safety and to avoid possible hazards in nuclear power plants, considering architectural design fundamentals and all operating precautions is mandatory. There are some planning and architectural precautions should be considered to achieve a high quality design and construction of nuclear power plant with optimum safety. This paper highlights predicted hazards like fire, terrorism, aircraft crash attacks, adversaries, intruders, and earthquakes, proposing protective actions against these hazards that vary from preventing danger to evacuating and sheltering people in-place. For instance; using safeguards program to protect against sabotage, theft, and diversion. Also, site and building well design focusing on escape pathways, emergency exits, and evacuation zones, and the safety procedures such as; evacuation exercises and sheltering processes according to different emergency classifications. In addition, this paper mentions some important codes and regulations that control nuclear power plants design, and assessment methods that evaluate probable risks. (author)

Radiation protection aspects in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Research and design of hanger and support series of nuclear safety class process piping

International Nuclear Information System (INIS)

Mao Chengzhang; Shi Jiemin

1995-12-01

Hangers and supports of nuclear safety class piping are an important part of primary system piping in a nuclear power plant. They will directly affect the reliability of operation, the period at construction and the investment for a nuclear power plant. It is an absolutely necessary job for Pakistan Chashma Nuclear Power Plant Project to research and design a series of piping supports in accordance with ASME-III NF. It is also an important designing for developing nuclear power plant later in China. After working over two years, a series of piping supports of nuclear safety class which have 57 types and more than 2460 specifications have been designed. This series is perfect, and can satisfy the requirements of piping final designing for nuclear power plant. This series of hangers and supports is mainly used in the process piping of nuclear safety class 1,2,3. They can also be used in other piping of nuclear safety class and piping with aseismic requirement of non-nuclear safety class

Tornado-resistance design for the nuclear safety structure of Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Xia Zufeng.

1987-01-01

The primary design consideration of anti-tornado of the nuclear safety structure of Qinshan Nuclear Power Plant is briefly presented. It mainly includes estimating the probability of tornado arising in the site, ascertaining the design requirments of the anti-tornado structures and deciding the tornado load acted on the structures

Design, fabrication and erection of steel structures important to safety of nuclear facilities

International Nuclear Information System (INIS)

2001-10-01

Civil engineering structures in nuclear installations form an important feature having implications to safety performance of these installations. The objective and minimum requirements for the design of civil engineering buildings/structures to be fulfilled to provide adequate assurance for safety of nuclear installations in India (such as pressurised heavy water reactor and related systems) are specified in the Safety Standard for Civil Engineering Structures Important to Safety of Nuclear Facilities. This standard is written by AERB to specify guidelines for implementation of the above civil engineering safety standard in the design, fabrication and erection of steel structures important to safety

Nuclear reactor conceptual design: methodology for cost-effective internalisation of nuclear safety

International Nuclear Information System (INIS)

Gimenez, M.; Grinblat, P.; Schlamp, M.

2002-01-01

A novel and promising methodology to perform nuclear reactor design is presented in this work. It achieves to balance efficiently safety and economics at the conceptual engineering stage. The key to this integral approach is to take into account safety aspects in a design optimisation process where the design variables are balanced in order to obtain a better figure of merit related with reactor economic performance. Design parameter effects on characteristic or critical safety variables, chosen from reactor behaviour during accidents and from its probabilistic safety assessment -safety performance indicators-, are synthesised on Safety Design Maps. These maps allow one to compare these indicators with limit values, which are determined by design criteria or regulations, and to transfer these restrictions to the design parameters. In this way, reactor dynamic response and other safety aspects are integrated in a global optimisation process, by means of additional rules to the neutronic, thermal-hydraulic and mechanical calculations. This methodology turns out to be promising to balance and optimise reactor and safety system design in an early engineering stage, in order to internalise cost-efficiently safety issues. It also allows one to evaluate the incremental costs of implementing higher safety levels. Furthermore, through this methodology, a simplified design can be obtained, compared to the resultant complexity when these concepts are introduced in a later engineering stage. (author)

External Events Excluding Earthquakes in the Design of Nuclear Power Plants. Safety Guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide provides recommendations and guidance on design for the protection of nuclear power plants from the effects of external events (excluding earthquakes), i.e. events that originate either off the site or within the boundaries of the site but from sources that are not directly involved in the operational states of the nuclear power plant units. In addition, it provides recommendations on engineering related matters in order to comply with the safety objectives and requirements established in the IAEA Safety Requirements publication, Safety of Nuclear Power Plants: Design. It is also applicable to the design and safety assessment of items important to the safety of land based stationary nuclear power plants with water cooled reactors. Contents: 1. Introduction; 2. Application of safety criteria to the design; 3. Design basis for external events; 4. Aircraft crash; 5. External fire; 6. Explosions; 7. Asphyxiant and toxic gases; 8. Corrosive and radioactive gases and liquids; 9. Electromagnetic interference; 10. Floods; 11. Extreme winds; 12. Extreme meteorological conditions; 13. Biological phenomena; 14. Volcanism; 15. Collisions of floating bodies with water intakes and UHS components; Annex I: Aircraft crashes; Annex II: Detonation and deflagration; Annex III: Toxicity limits.

Plant designer's view of the operator's role in nuclear plant safety

International Nuclear Information System (INIS)

Corcoran, W.R.; Church, J.F.; Cross, M.T.; Porter, N.J.

1981-01-01

The nuclear plant operator's role supports the design assumptions and equipment with four functional tasks. He must set up th plant for predictable response to disturbances, operate the plant so as to minimize the likelihood and severity of event initiators, assist in accomplishing the safety functions, and feed back operating experiences to reinforce or redefine the safety analyses' assumptions. The latter role enhances the operator effectiveness in the former three roles. The Safety Level Concept offers a different perspective that enables the operator to view his roles in nuclear plant safety. This paper outlines the operator's role in nuclear safety and classifies his tasks using the Safety Level Concept

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. 1.2. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1981), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1986), which are superseded by this new Safety Guide. 1.3. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1981 and 1986, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2000, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included

Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.

2008-01-01

Beside new Ordinance on the control of nuclear material and special equipment ('Official Gazette' No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities ('Official Gazette' No. 74/06) and Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety ('Official Gazette' No. 74/06), based on Nuclear Safety Act ('Official Gazette' No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a licence to perform a nuclear activity. The Ordinance also regulates the content of the forms for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear activities. According to the Nuclear Safety Act, nuclear activities are the production, processing, use, storage, disposal, transport, import, export, possession or other handling of nuclear material or specified equipment. The Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, State Office for Nuclear Safety finalized the text of new Ordinance on conditions for nuclear safety and protection with regard to the siting, design, construction, use and decommissioning of a facility in which a nuclear activity is

Nuclear safety approach for PWRs design and operation

International Nuclear Information System (INIS)

Vignon, D.

1988-01-01

The implementation of France's major nuclear programme - 56 PWR units in service or under construction - has gone hand in hand with the development of an original philosophy in the field of nuclear safety. From an initial core of deterministic safety philosophy current in the seventies, which has been wholly retained and in some instances refined, a range of additions has been made to include consideration of a number of additional situations based on a probabilistic approach. This has resulted in a better coherence for safety and a mitigation of the severe accident probability. Furthermore, the establishment of emergency plans has enabled the Safety Authorities and the operator to adopt a coherent and logical approach to severe accidents with the aim of achieving greater defence in depth, this has resulted in the provision of certain additional measures designed to further reduce the consequences of severe accidents. This paper describes the culmination of this work, as exemplified in the new 1 400MWe - N4 advanced plant series currently under construction, of which the essential elements are also incorporated into all previous units, thereby giving them an equivalent level of safety. This now constitutes the French safety policy with respect to PWR nuclear units

An Axiomatic Design Approach of Nanofluid-Engineered Nuclear Safety Features for Generation III+ React

International Nuclear Information System (INIS)

Bang, In Cheol; Heo, Gyun Young; Jeong, Yong Hoon; Heo, Sun

2009-01-01

A variety of Generation III/III+ reactor designs featuring enhanced safety and improved economics are being proposed by nuclear power industries around the world to solve the future energy supply shortfall. Nanofluid coolants showing an improved thermal performance are being considered as a new key technology to secure nuclear safety and economics. However, it should be noted that there is a lack of comprehensible design works to apply nanofluids to Generation III+ reactor designs. In this work, the review of accident scenarios that consider expected nanofluid mechanisms is carried out to seek detailed application spots. The Axiomatic Design (AD) theory is then applied to systemize the design of nanofluid-engineered nuclear safety systems such as Emergency Core Cooling System (ECCS) and External Reactor Vessel Cooling System (ERVCS). The various couplings between Gen-III/III+ nuclear safety features and nanofluids are investigated and they try to be reduced from the perspective of the AD in terms of prevention/mitigation of severe accidents. This study contributes to the establishment of a standard communication protocol in the design of nanofluid-engineered nuclear safety systems

Nuclear Safety

International Nuclear Information System (INIS)

1978-09-01

In this short paper it has only been possible to deal in a rather general way with the standards of safety used in the UK nuclear industry. The record of the industry extending over at least twenty years is impressive and, indeed, unique. No other industry has been so painstaking in protection of its workers and in its avoidance of damage to the environment. Headings are: introduction; how a nuclear power station works; radiation and its effects (including reference to ICRP, the UK National Radiological Protection Board, and safety standards); typical radiation doses (natural radiation, therapy, nuclear power programme and other sources); safety of nuclear reactors - design; key questions (matters of concern which arise in the public mind); safety of operators; safety of people in the vicinity of a nuclear power station; safety of the general public; safety bodies. (U.K.)

Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1989-01-01

This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

Protection against internal fires and explosions in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. This Safety Guide supplements the requirements established in Safety of Nuclear Power Plants: Design. It supersedes Safety Series No. 50-SG-D2 (Rev. 1), Fire Protection in Nuclear Power Plants: A Safety Guide, issued in 1992.The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice

Nuclear power safety

International Nuclear Information System (INIS)

1991-11-01

This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

Nuclear safety and radiation protection consideration in the design of research and development facility

International Nuclear Information System (INIS)

Akbar, M.R.

2010-01-01

Nuclear safety is a critically important aspect that must be considered in the design of a nuclear facility in order to ensure the protection of the workers, public and environment. This paper looks at the methodology, approach and incorporation of this aspect, specifically into the design of a research and development facility. The Health, Safety and Environmental Basis of Design is an initial analysis of nuclear safety and radiation protection considerations that is performed during the conceptual design phase and sets the baseline for what the design of the facility must conform to. It consists of general nuclear safety design principles, such as defence in depth and optimisation considerations, and a hazard management strategy. Following the Health, Safety and Environmental Basis of Design, a Preliminary Safety Assessment Report is generated during the basic design phase in conjunction with various analyses in order to assess the impact of hazards on the workers and members of the public. This assessment follows a hazard graded approach where the depth of the analysis will be determined by the impact of the worst case accident scenario in the facility. The assessment also includes a waste management strategy which is an essential aspect to be considered in the design in order to minimize the generation of waste. The safety assessment also demonstrates compliance to dose limits and risk criteria for the workers and members of the public set by the regulatory body and supported by a legal framework. Measures are taken to keep risk as low as reasonably achievable and prevent transgression of the risk and dose limits. However, a balance needs to be maintained between 5 reducing these doses further and the cost of such a reduction, which is known as optimization. It is therefore imperative to have nuclear safety specialists analyse the design in order to protect the worker and member of the public from unwarranted exposure to nuclear radiation. (author)

Design aspects of safety critical instrumentation of nuclear installations

Energy Technology Data Exchange (ETDEWEB)

Swaminathan, P. [Electronics Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, Tamil Nadu (India)]. E-mail: swamy@igcar.ernet.in

2005-07-01

Safety critical instrumentation systems ensure safe shutdown/configuration of the nuclear installation when process status exceeds the safety threshold limits. Design requirements for safety critical instrumentation such as functional and electrical independence, fail-safe design, and architecture to ensure the specified unsafe failure rate and safe failure rate, human machine interface (HMI), etc., are explained with examples. Different fault tolerant architectures like 1/2, 2/2, 2/3 hot stand-by are compared for safety critical instrumentation. For embedded systems, software quality assurance is detailed both during design phase and O and M phase. Different software development models such as waterfall model and spiral model are explained with examples. The error distribution in embedded system is detailed. The usage of formal method is outlined to reduce the specification error. The guidelines for coding of application software are outlined. The interface problems of safety critical instrumentation with sensors, actuators, other computer systems, etc., are detailed with examples. Testability and maintainability shall be taken into account during design phase. Online diagnostics for safety critical instrumentation is detailed with examples. Salient details of design guides from Atomic Energy Regulatory Board, International Atomic Energy Agency and standards from IEEE, BIS are given towards the design of safety critical instrumentation systems. (author)

Design aspects of safety critical instrumentation of nuclear installations

International Nuclear Information System (INIS)

Swaminathan, P.

2005-01-01

Safety critical instrumentation systems ensure safe shutdown/configuration of the nuclear installation when process status exceeds the safety threshold limits. Design requirements for safety critical instrumentation such as functional and electrical independence, fail-safe design, and architecture to ensure the specified unsafe failure rate and safe failure rate, human machine interface (HMI), etc., are explained with examples. Different fault tolerant architectures like 1/2, 2/2, 2/3 hot stand-by are compared for safety critical instrumentation. For embedded systems, software quality assurance is detailed both during design phase and O and M phase. Different software development models such as waterfall model and spiral model are explained with examples. The error distribution in embedded system is detailed. The usage of formal method is outlined to reduce the specification error. The guidelines for coding of application software are outlined. The interface problems of safety critical instrumentation with sensors, actuators, other computer systems, etc., are detailed with examples. Testability and maintainability shall be taken into account during design phase. Online diagnostics for safety critical instrumentation is detailed with examples. Salient details of design guides from Atomic Energy Regulatory Board, International Atomic Energy Agency and standards from IEEE, BIS are given towards the design of safety critical instrumentation systems. (author)

New Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.; Cizmek, A.

2008-01-01

Beside new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06), based on Nuclear Safety Act (Official Gazette No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of announcing the intention to perform nuclear activity, submitting an application for the issue of a license to perform nuclear activity, and the procedure for adoption a decision on issuing a nuclear activity license. The Ordinance also regulates the contents of the application form for the announcement of the intention to perform nuclear activity, as well as of the application for the issue of a nuclear activity license and the method of keeping a nuclear activity register. The Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, SONS finalized the text of new Ordinance on nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance regulates nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance defines facilities in which nuclear activity is

A cost-effective methodology to internalize nuclear safety in nuclear reactor conceptual design

International Nuclear Information System (INIS)

Gimenez, M.; Grinblat, P.; Schlamp, M.

2003-01-01

A new methodology to perform nuclear reactor design, balancing safety and economics at the conceptual engineering stage, is presented in this work. The goal of this integral methodology is to take into account safety aspects in an optimization design process where the design variables are balanced in order to obtain a better figure of merit related with reactor economic performance. Design parameter effects on characteristic or critical safety variables, chosen from reactor behavior during accidents (safety performance indicators), are synthesized on Design Maps. These maps allow one to compare the safety indicator with limits, which are determined by design criteria or regulations, and to transfer these restrictions to the design parameters. In this way, reactor dynamic response and other safety aspects are integrated in a global optimization process, by means of additional rules to the neutronic, thermal-hydraulic, and mechanical calculations. An application of the methodology, implemented in Integrated Reactor Evaluation Program 3 (IREP3) code, to optimize safety systems of CAREM prototype is presented. It consists in balancing the designs of the Emergency Injection System (EIS), the Residual Heat Removal System (RHRS), the primary circuit water inventory and the containment height, to cope with loss of coolant and loss of heat sink (LOHS) accidental sequences, taking into account cost and reactor performance. This methodology turns out to be promising to internalize cost-efficiently safety issues. It also allows one to evaluate the incremental costs of implementing higher safety levels

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1982), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1987), which are superseded by this new Safety Guide. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1982 and 1987, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2004, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included.

Differences in safety margins between nuclear and conventional design standards with regards to seismic hazard definition and design criteria

International Nuclear Information System (INIS)

Elgohary, M.; Saudy, A.; Orbovic, N.; Dejan, D.

2006-01-01

With the surging interest in new build nuclear all over the world and a permanent interest in earthquake resistance of nuclear plants, there is a need to quantify the safety margins in nuclear buildings design in comparison to conventional buildings in order to increase the public confidence in the safety of nuclear power plants. Nuclear (CAN3-N289 series) and conventional (NBCC 2005) seismic standards have different approaches regarding the design of civil structures. The origin of the differences lays in the safety philosophy behind the seismic nuclear and conventional standards. Conventional seismic codes contain the minimal requirement destined primarily to safeguard against major structural failure and loss of life. It doesn't limit damage to a certain acceptable degree or maintain function. Nuclear seismic code requires that structures, systems and components important to safety, withstand the effects of earthquakes. The requirement states that for equipment important to safety, both integrity and functionality should be ascertained. The seismic hazard is generally defined on the basis of the annual probability of exceedence (return period). There is a major difference on the return period and the confidence level for design earthquakes between the conventional and the nuclear seismic standards. The seismic design criteria of conventional structures are based on the use of Force Modification Factors to take into account the energy dissipation by incursion in non-elastic domain and the reserve of strength. The use of such factors to lower intentionally the seismic input is consistent with the safety philosophy of the conventional seismic standard which is the 'non collapse' rather than the integrity and/or the operability of the structures or components. Nuclear seismic standard requires that the structure remain in the elastic domain; energy dissipation by incursion in non-elastic domain is not allowed for design basis earthquake conditions. This is

Safety of nuclear installations: Future direction

International Nuclear Information System (INIS)

1990-04-01

The Workshop presentations were divided into sessions devoted to the following topics: Environmental impact of fossil fuel energy technologies (5 papers), Future needs for nuclear power (7 papers), Safety objectives (10 papers), Safety aspects of the next generation of current-type nuclear power plants (8 papers), Safety aspects of new designs and concepts for nuclear power plants (6 papers), Special safety issues: Safety aspects of new designs and concepts for nuclear power plants (5 papers), Safety aspects of new designs and processes for the nuclear fuel cycle (5 papers), Closing panel (3 papers), 12 poster presentations and a Summary of the Workshop. A separate abstract was prepared for each of these papers. Refs, figs and tabs

Research on conceptual design of simplified nuclear safety instrument and control system

International Nuclear Information System (INIS)

Huang Jie

2015-01-01

The Nuclear safety instrument and control system is directly related to the safety of the reactor. So redundant and diversity design is used to ensure the system's security and reliability. This make the traditional safety system large, more cabinets and wiring complexity. To solve these problem, we can adopt new technology to make the design more simple. The simplify conceptual design can make the system less cabinets, less wiring, but high security, strong reliability. (author)

Nuclear safety culture and nuclear safety supervision

International Nuclear Information System (INIS)

Chai Jianshe

2013-01-01

In this paper, the author reviews systematically and summarizes up the development process and stage characteristics of nuclear safety culture, analysis the connotation and characteristics of nuclear safety culture, sums up the achievements of our country's nuclear safety supervision, dissects the challenges and problems of nuclear safety supervision. This thesis focused on the relationship between nuclear safety culture and nuclear safety supervision, they are essential differences, but there is a close relationship. Nuclear safety supervision needs to introduce some concepts of nuclear safety culture, lays emphasis on humanistic care and improves its level and efficiency. Nuclear safety supervision authorities must strengthen nuclear safety culture training, conduct the development of nuclear safety culture, make sure that nuclear safety culture can play significant roles. (author)

Second ANS workshop on the safety of Soviet-designed nuclear power plants. Summary report

International Nuclear Information System (INIS)

Bari, R.A.

1995-03-01

The Second American Nuclear Society Workshop on the Safety of Soviet-Designed Nuclear Power Plants was held in Washington, DC, in November, 1994. The Workshop consisted of both plenary sessions and working sessions with three hundred participants overall. All countries with operating Soviet-Designed nuclear power plants were represented and representatives from several other countries also participated. In addition to the status and plans related to technical issues, the Workshop also included discussions of economic, political, legal, and social issues as they relate to the safety of these nuclear power plants

Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)

International Nuclear Information System (INIS)

VINCENT, Andrew

2005-01-01

software. The discussion provided herein illustrates benefits of applying the Safety Software Guide to work activities dependent on software applications and directed toward the design of new nuclear facilities. In particular, the Guide-based systematic approach with software enables design processes to effectively proceed and reduce the likelihood of rework activities. Several application examples are provided for the new facility

Safety investigation of 'Mutsu', the first nuclear ship in Japan (the correspondence to the guideline of safety design examination, etc.)

International Nuclear Information System (INIS)

1981-01-01

Japan Nuclear Ship Development Agency had made previously application for the permission of the alteration of the reactor installation in the nuclear ship Mutsu (the first of this kind in Japan), based on the overall safety investigation of the ship made by JNDA. Taking the opportunity of the governmental safety examination concerning the permission, the correspondence of the safety aspects of the n.s. Mutsu to the existing guidelines for the safety of nuclear reactor facilities was examined. These results to further enhance the safety of the n.s. Mutsu are described concerning the following matters: the safety design examination guideline for power-generating LWR facilities (58 items); the safety evaluation guideline for power-generating LWR facilities (the analysis of abnormal transients during operation and accidents); the safety countermeasures to be adopted in the reactor plant of the n.s. Mutsu from the situation of the TMI nuclear accident in U.S. (7 in design and 10 in operation management); the analysis simulating the TMI accident. (J.P.N.)

The design features and safety concepts of the nuclear heating reactor developed in China

International Nuclear Information System (INIS)

Zheng Wenxiang; Wang Dazhong

1995-01-01

Based on the specific conditions of the nuclear heat applications and the development objectives of the advanced reactors, the nuclear heating reactor (NHR) exploited in China has adhered to the new safety concepts and been designed with a number of advanced features, including the integrated arrangement, full power natural circulation capacity, self-pressurized performance, dynamically-hydraulic control rod drive and passive safety systems, so that higher standard of safety as well as simplification in the plant systems and improvement in economic viability has been achieved. This paper describes the special consideration in the design as well as the main design features and safety concepts of the NHR. Some experimental and analytical results are also presented to demonstrate the NHR safety features

Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island design, Docket No. 50-447

International Nuclear Information System (INIS)

1983-04-01

The Safety Evaluation Report for the application filed by General Electric Company for the Final Design Approval for the General Electric Standard Safety Analysis Report (GESSAR II FSAR) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report summarizes the results of the staff's safety review of the GESSAR II BWR/6 Nuclear Island Design. Subject to favorable resolution of items discussed in the Safety Evaluation Report, the staff concludes that the facilities referencing GESSAR II, subject to approval of the balance-of-plant design, can conform with the provisions of the Act and the regulations of the Nuclear Regulatory Commission

Development of nuclear safety issues program

Energy Technology Data Exchange (ETDEWEB)

Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K

2006-12-15

The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants.

Development of nuclear safety issues program

International Nuclear Information System (INIS)

Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K.

2006-12-01

The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants

Safety and security aspects in design of digital safety I and C in nuclear power plants

International Nuclear Information System (INIS)

Ding, Yongjian; Waedt, Karl

2016-01-01

The paper describes a safety objective oriented systematic design approach of digital (computerized) safety I and C in modern nuclear power plants which considers the plant safety requirements as well as cybersecurity needs. The defence in depth philosophy is applied by using different defence lines in the I and C architecture and protection zones in the plant IT environment.

Safety and security aspects in design of digital safety I and C in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Ding, Yongjian [University of Applied Sciences Magdeburg-Stendal, Magdeburg (Germany). Inst. of Electrical Engineering; Waedt, Karl [Areva GmbH, Erlangen (Germany). PEAS-G

2016-05-15

The paper describes a safety objective oriented systematic design approach of digital (computerized) safety I and C in modern nuclear power plants which considers the plant safety requirements as well as cybersecurity needs. The defence in depth philosophy is applied by using different defence lines in the I and C architecture and protection zones in the plant IT environment.

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

Seismic design and performance of nuclear safety related RC structures based on new seismic design principle

International Nuclear Information System (INIS)

Murugan, R.; Sivathanu Pillai, C.; Chattopadhyaya, S.; Sundaramurthy, C.

2011-01-01

Full text: Seismic design of safety related Reinforced Concrete (RC) structures of Nuclear power plants (NPP) in India as per the present AERB codal procedures tries to ensure predominantly elastic behaviour under OBE so that the features of Nuclear Power Plant (NPP) necessary for continued safe operation are designed to remain functional and prevent accident (collapse) of NPP under SSE for which certain Structures, Systems and Components (SSCs) those are necessary to ensure the capability to shut down the reactor safely, are designed to remain functional. While the seismic design principles of non safety related structures as per Indian code (IS 1893-2002) are ensuring elastic behaviour under DBE and inelastic behaviour under MCE by utilizing ductility and energy dissipation capacity of the structure effectively. The design principle of AERB code is ensuring elastic behaviour under OBE and is not enlightening much inference about the overall structural behaviour under SSE (only ensuring the capability of certain SSCs required for safe shutdown of reactor). Various buildings and structures of Indian Nuclear power plant are classified from the basis of associated safety functions in a descending order in according with their roles in preventions and mitigation of an accident or support functions for prevention. This paper covers a comprehensive seismic analysis and design methodology based on the AERB codal provisions followed for safety related RC structure taking Diesel Generator Building of PFBR as a case study and study and investigates its performance under OBE and SSE by carrying out Non-linear static Pushover analysis. Based on the analysis, observed variations, recommendations are given for getting the desired performance level so as to implement performance based design in the future NPP design

Nuclear safety research collaborations between the US and Russian Federation international nuclear safety centers

International Nuclear Information System (INIS)

Hill, D.J; Braun, J.C; Klickman, A.E.; Bugaenko, S.E; Kabanov, L.P; Kraev, A.G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the U.S. Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the U. S. Center at Argonne National Laboratory in October 1995. MINATOM established the Russian Center at the Research and Development Institute of Power Engineering in Moscow in July 1996. In April 1998 the Russian center became an independent, autonomous organization under MINATOM. The goals of the centers are to: cooperate in the development of technologies associated with nuclear safety in nuclear power engineering. be international centers for the collection of information important for safety and technical improvements in nuclear power engineering. maintain a base for fundamental knowledge needed to design nuclear reactors.The strategic approach that is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors

Nuclear power: Siting and safety

International Nuclear Information System (INIS)

Openshaw, S.

1986-01-01

By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

Requirement and prospect of nuclear data activities for nuclear safety

International Nuclear Information System (INIS)

Kimura, Itsuro

2000-01-01

Owing to continuous efforts by the members of JNDC (Japanese Nuclear Data Committee) and Nuclear Data Center in JAERI (Japan Atomic Energy Research Institute), several superb evaluated nuclear data files, such as JENDL, FP (fission product) yields and decay heat, have been compiled in Japan and opened to the world. However, they are seldom adopted in safety design and safety evaluation of light water reactors and are hardly found in related safety regulatory guidelines and standards except the decay heat. In this report, shown are a few examples of presently used nuclear data in the safety design and the safety evaluation of PWRs (pressurized water reactors) and so forth. And then, several procedures are recommended in order to enhance more utilization of Japanese evaluated nuclear data files for nuclear safety. (author)

A new design concept for offshore nuclear power plants with enhanced safety features

International Nuclear Information System (INIS)

Lee, Kihwan; Lee, Kang-Heon; Lee, Jeong Ik; Jeong, Yong Hoon; Lee, Phill-Seung

2013-01-01

Highlights: ► A new design concept for offshore nuclear power plants is proposed. ► The total general arrangement for the concept is suggested. ► A new emergency passive containment cooling system (EPCCS) is proposed. ► A new emergency passive reactor-vessel cooling system (EPRVCS) is proposed. ► Safety features against earthquakes, tsunamis, and storms are discussed. - Abstract: In this paper, we present a new concept for offshore nuclear power plants (ONPP) with enhanced safety features. The design concept of a nuclear power plant (NPP) mounted on gravity-based structures (GBSs), which are widely used offshore structures, is proposed first. To demonstrate the feasibility of the concept, a large-scale land-based nuclear power plant model APR1400, which is the most recent NPP model in the Republic of Korea, is mounted on a GBS while minimizing modification to the original features of APR1400. A new total general arrangement (GA) and basic design principles are proposed and can be directly applied to any existing land based large scale NPPs. The proposed concept will enhance the safety of a NPP due to several aspects. A new emergency passive containment cooling system (EPCCS) and emergency passive reactor-vessel cooling system (EPRVCS) are proposed; their features of using seawater as coolant and safety features against earthquakes, Tsunamis, storms, and marine collisions are also described. We believe that the proposed offshore nuclear power plant is more robust than conventional land-based nuclear power plants and it has strong potential to provide great opportunities in nuclear power industries by decoupling the site of construction and that of installation.

Selecting of key safety parameters in reactor nuclear safety supervision

International Nuclear Information System (INIS)

He Fan; Yu Hong

2014-01-01

The safety parameters indicate the operational states and safety of research reactor are the basis of nuclear safety supervision institution to carry out effective supervision to nuclear facilities. In this paper, the selecting of key safety parameters presented by the research reactor operating unit to National Nuclear Safety Administration that can express the research reactor operational states and safety when operational occurrence or nuclear accident happens, and the interrelationship between them are discussed. Analysis shows that, the key parameters to nuclear safety supervision of research reactor including design limits, operational limits and conditions, safety system settings, safety limits, acceptable limits and emergency action level etc. (authors)

Software Quality Assurance for Nuclear Safety Systems

International Nuclear Information System (INIS)

Sparkman, D R; Lagdon, R

2004-01-01

The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: (sm b ullet) Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe (sm b ullet) Considers the larger system that uses the software and its impacts (sm b ullet) Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety

Nuclear law - Nuclear safety

International Nuclear Information System (INIS)

Pontier, Jean-Marie; Roux, Emmanuel; Leger, Marc; Deguergue, Maryse; Vallar, Christian; Pissaloux, Jean-Luc; Bernie-Boissard, Catherine; Thireau, Veronique; Takahashi, Nobuyuki; Spencer, Mary; Zhang, Li; Park, Kyun Sung; Artus, J.C.

2012-01-01

This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

Safety provisions of nuclear power plants

International Nuclear Information System (INIS)

Niehaus, F.

1994-01-01

Safety of nuclear power plants is determined by a deterministic approach complemented by probabilistic considerations. Much use has been made of the wealth of information from more than 6000 years of reactor operation. Design, construction and operation is governed by national and international safety standards and practices. The IAEA has prepared a set of Nuclear Safety Standards as recommendations to its Member States, covering the areas of siting, design, operations, quality assurance, and governmental organisations. In 1988 the IAEA published a report by the International Nuclear Safety Advisory Group on Basic Safety Principles for Nuclear Power Plants, summarizing the underlying objectives and principles of excellence in nuclear safety and the way in which its aspects are interrelated. The paper will summarize some of the key safety principles and provisions, and results and uses of Probabilistic Safety Assessments. Some comments will be made on the safety of WWER 440/230 and WWER-1000 reactors which are operated on Bulgaria. 8 figs

Nuclear power and safety

International Nuclear Information System (INIS)

Chidambaram, R.

1992-01-01

Some aspects of safety of nuclear power with special reference to Indian nuclear power programme are discussed. India must develop technology to protect herself from the adverse economic impact arising out of the restrictive regime which is being created through globalization of safety and environmental issues. Though the studies done and experience gained so far have shown that the PHWR system adopted by India has a number of superior safety features, research work is needed in the field of operation and maintenance of reactors and also in the field of reactor life extension through delaying of ageing effects. Public relations work must be pursued to convince the public at large of the safety of nuclear power programme. The new reactor designs in the second stage of evolution are based on either further improvement of existing well-proven designs or adoptions of more innovative ideas based on physical principles to ensure a higher level of safety. The development of Indian nuclear power programme is characterised by a balanced approach in the matter of assuring safety. Safety enforcement is not just looked upon as a pure administrative matter, but experts with independent minds are also involved in safety related matters. (M.G.B.)

Nuclear Safety Review 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-15

The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis.

Nuclear Safety Review 2013

International Nuclear Information System (INIS)

2013-07-01

The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis

Small nuclear reactor safety design requirements for autonomous operation

International Nuclear Information System (INIS)

Kozier, K.S.; Kupca, S.

1997-01-01

Small nuclear power reactors offer compelling safety advantages in terms of the limited consequences that can arise from major accident events and the enhanced ability to use reliable, passive means to eliminate their occurrence by design. Accordingly, for some small reactor designs featuring a high degree of safety autonomy, it may be-possible to delineate a ''safety envelope'' for a given set of reactor circumstances within which safe reactor operation can be guaranteed without outside intervention for time periods of practical significance (i.e., days or weeks). The capability to operate a small reactor without the need for highly skilled technical staff permanently present, but with continuous remote monitoring, would aid the economic case for small reactors, simplify their use in remote regions and enhance safety by limiting the potential for accidents initiated by inappropriate operator action. This paper considers some of the technical design options and issues associated with the use of small power reactors in an autonomous mode for limited periods. The focus is on systems that are suitable for a variety of applications, producing steam for electricity generation, district heating, water desalination and/or marine propulsion. Near-term prospects at low power levels favour the use of pressurized, light-water-cooled reactor designs, among which those having an integral core arrangement appear to offer cost and passive-safety advantages. Small integral pressurized water reactors have been studied in many countries, including the test operation of prototype systems. (author)

Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants

International Nuclear Information System (INIS)

Chang, Soon Heung; Kim, Sang Ho; Choi, Jae Young

2013-01-01

Highlights: • We newly propose the design concept of integrated passive safety system (IPSS). • It has five safety functions for decay heat removal and severe accident mitigation. • Simulations for IPSS show that core melt does not occur in accidents with SBO. • IPSS can achieve the passive in-vessel retention and ex-vessel cooling strategy. • The applicability of IPSS is high due to the installation outside the containment. -- Abstract: The design concept of integrated passive safety system (IPSS) which can perform various passive safety functions is proposed in this paper. It has the various functions of passive decay heat removal system, passive safety injection system, passive containment cooling system, passive in-vessel retention and cavity flooding system, and filtered venting system with containment pressure control. The objectives of this paper are to propose the conceptual design of an IPSS and to estimate the design characters of the IPSS with accident simulations using MARS code. Some functions of the IPSS are newly proposed and the other functions are reviewed with the integration of the functions. Consequently, all of the functions are modified and integrated for simplicity of the design in preparation for beyond design based accidents (BDBAs) focused on a station black out (SBO). The simulation results with the IPSS show that the decay heat can be sufficiently removed in accidents that occur with a SBO. Also, the molten core can be retained in a vessel via the passive in-vessel retention strategy of the IPSS. The actual application potential of the IPSS is high, as numerous strong design characters are evaluated. The installation of the IPSS into the original design of a nuclear power plant requires minimal design change using the current penetrations of the containment. The functions are integrated in one or two large tanks outside the containment. Furthermore, the operation time of the IPSS can be increased by refilling coolant from the

Nuclear power and safety

International Nuclear Information System (INIS)

Saunders, P.; Tasker, A.

1991-01-01

Nuclear power currently provides about a fifth of both Britain's and the world's electricity. It is the largest single source of electricity in Western Europe; in France three quarters of electricity is generated by nuclear power stations. This booklet is about the safety of those plants. It approaches the subject by outlining the basic principles and approaches behind nuclear safety, describing the protective barriers and safety systems that are designed to prevent the escape of radioactive material, and summarising the regulations that govern the construction and operation of nuclear power stations. The aim is to provide a general understanding of the subject by explaining the general principles of the Advanced Gas Cooled Reactor and setting out the UKAEA strategy for nuclear safety, the objective being always to minimize risk. (author)

Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

Advanced nuclear reactor safety design technology research in NPIC

International Nuclear Information System (INIS)

Yu, H.

2014-01-01

After the Fukushima accident happen, Nuclear Power Plants (NPPs) construction has been suspended in China for a time. Now the new regulatory rule has been proposed that the most advanced safety standard must be adopted for the new NPPs and practical elimination of large fission product release by design during the next five plans period. So the advanced reactor research is developing in China. NPIC is engaging on the ACP1000 and ACP100 (Small Module Reactor) design. The main design character will be introduced in this paper. The Passive Combined with Active (PCWA) design was adopted during the ACP1000 design to reduce the core damage frequency (CDF); the Cavity Injection System (CIS) is design to mitigation the consequence of the severe accident. Advance passive safety system was designed to ensure the long term residual heat removal during the Small Module Reactor (SMR). The SMR will be utilized to be the floating reactors, district heating reactor and so on. Besides, the Science and Technology on Reactor System Design Technology Laboratory (LRSDT) also engaged on the fundamental thermal-hydraulic characteristic research in support of the system validation. (author)

Nuclear power plant safety

International Nuclear Information System (INIS)

Otway, H.J.

1974-01-01

Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

East/West cooperation on the safety of USSR-designed nuclear power stations

International Nuclear Information System (INIS)

Spencer, P.H.

1991-01-01

In the aftermath of the accident at the Chernobyl nuclear power station in the Soviet Union, nuclear power plant operators throughout the world came together in May 1989 to form the World Association of Nuclear Operators (WANO). When it became clear that the operators of plants of an early design supplied by the USSR needed assistance in the upgrading of the safety of these units, WANO was uniquely placed to assist and facilitate in this. In July 1990, WANO took the decision to form a special project to assist the operators of the VVER 440/230 plants in their efforts to increase the safety standards for these units. The work performed by this special project team is described

Nuclear safety policy working group recommendations on nuclear propulsion safety for the space exploration initiative

Science.gov (United States)

Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J. Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W.

1993-01-01

An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

Nuclear safety in France

International Nuclear Information System (INIS)

Tanguy, P.

1979-01-01

A brief description of the main safety aspects of the French nuclear energy programme and of the general safety organization is followed by a discussion on the current thinking in CEA on some important safety issues. As far as methodology is concerned, the use of probabilistic analysis in the licensing procedure is being extensively developed. Reactor safety research is aimed at a better knowledge of the safety margins involved in the present designs of both PWRs and LMFBRs. A greater emphasis should be put during the next years in the safety of the nuclear fuel cycle installations, including waste disposals. Finally, it is suggested that further international cooperation in the field of nuclear safety should be developed in order to insure for all countries the very high safety level which has been achieved up till now. (author)

Recent developments in the IAEA safety standards: design and operation of nuclear power plants

International Nuclear Information System (INIS)

Saito, Takehiko

2004-01-01

The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

Design and safety features of commercial nuclear power plants in Japan, 1976 edition

International Nuclear Information System (INIS)

Izumi, Fumio; Harayama, Yasuo

1976-10-01

The December 1975 edition (JAERI-M 5959) contained design particulars and safety features of 20 commercial nuclear power plants in Japan as of December 1974. Subsequently new plants have been put into operation and some plants under construction have undergone design modifications. The present edition presents similar data of the commercial nuclear power plants in Japan up to June 1976, compiled by computer processing. (auth.)

Effort on Nuclear Power Plants safety

International Nuclear Information System (INIS)

Prayoto.

1979-01-01

Prospects of nuclear power plant on designing, building and operation covering natural safety, technical safety, and emergency safety are discussed. Several problems and their solutions and nuclear energy operation in developing countries especially control and permission are also discussed. (author tr.)

Promoting safety in nuclear installations. The IAEA has established safety standards for nuclear reactors and provides expert review and safety services to assist Member States in their application

International Nuclear Information System (INIS)

2002-01-01

More than 430 nuclear power plants (NPPs) are currently operating in 30 countries around the world. The nuclear share of total electricity production ranges from about 20 percent in the Czech Republic and United States to nearly 78 percent in France and Lithuania. Worldwide, nuclear power generates about 16% of the total electricity. The safety of such nuclear installations is fundamental. Every aspect of a power plant must be closely supervised and scrutinized by national regulatory bodies to ensure safety at every phase. These aspects include design, construction, commissioning, trial operation, commercial operation, repair and maintenance, plant upgrades, radiation doses to workers, radioactive waste management and, ultimately, plant decommissioning. Safety fundamentals comprise defence-in-depth, which means having in place multiple levels of protection. nuclear facilities; regulatory responsibility; communicating with the public; adoption of the international convention on nuclear safety including implementation of IAEA nuclear safety standards. This publication covers topics of designing for safety (including safety concepts, design principles, and human factors); operating safety (including safety culture and advance in operational safety); risk assessment and management

International Aspects of Nuclear Safety

International Nuclear Information System (INIS)

Lash, T.R.

2000-01-01

Even though not all the world's nations have developed a nuclear power industry, nuclear safety is unquestionably an international issue. Perhaps the most compelling proof is the 1986 accident at Chornobyl nuclear power plant in what is now Ukraine. The U.S. Department of Energy conducts a comprehensive, cooperative effort to reduce risks at Soviet-designed nuclear power plants. In the host countries : Armenia, Ukraine, Russia, Bulgaria, the Czech Republic, Hungary, Lithuania, Slovakia, and Kazakhstan joint projects are correcting major safety deficiencies and establishing nuclear safety infrastructures that will be self-sustaining.The U.S. effort has six primary goals: 1. Operational Safety - Implement the basic elements of operational safety consistent with internationally accepted practices. 2. Training - Improve operator training to internationally accepted standards. 3. Safety Maintenance - Help establish technically effective maintenance programs that can ensure the reliability of safety-related equipment. 4. Safety Systems - Implement safety system improvements consistent with remaining plant lifetimes. 5. Safety Evaluations - Transfer the capability to conduct in-depth plant safety evaluations using internationally accepted methods. 6. Legal and Regulatory Capabilities - Facilitate host-country implementation of necessary laws and regulatory policies consistent with their international treaty obligations governing the safe use of nuclear power

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear installations

International Nuclear Information System (INIS)

1991-01-01

In accordance with the Nuclear Energy Act, a Licence may only be issued if the precautions required by the state of the art have been taken to prevent damage resulting from the construction and operation of the installation. The maximum admissible body doses in the area around the installation which must be observed in planning constructional and other technical protective measures to counter accidents in or at a nuclear power station (accident planning values, are established). According to the Radiological Protection Ordinance the Licensing Authority can consider these precautions to have been taken if, in designing the installation against accidents, the applicant has assumed the accidents which, according to the Safety Criteria and Guidelines for Nuclear Power Stations published in the Federal Register by the Federal Minister of the Interior after hearing the competent senior state authorities, must determine the design of a nuclear power station. On the basis of previous experience from safety analysis, assessment and operation of nuclear power stations, the accident guidelines published here define which accidents are determinative for the safety-related design of PWR power stations and what verification -particularly with regard to compliance with the accident planning values of the Radiological Protection Ordinance -must be provided by the applicant. (author)

System Design and the Safety Basis

International Nuclear Information System (INIS)

Ellingson, Darrel

2008-01-01

The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination and decommissioning (D and D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities

Maintaining the design integrity of nuclear installations throughout their operating life. INSAG-19. A report by the International Nuclear Safety Advisory Group

International Nuclear Information System (INIS)

2003-01-01

A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. this INSAG report discusses the problem of maintaining the integrity of design of a nuclear power plant over its entire lifetime in order to achieve a continuous high level of safety. A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's operating lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. The purpose of this report is to identify the issues and some of the principles that should be addressed, discuss some of the solutions to the problem, and highlight the specific responsibilities of designers, operators and regulators. The issues and principles discussed here are also applicable to other nuclear installations (for example, research reactors and fuel cycle facilities). This INSAG report is directed at senior executives who are responsible for: the overall safety of nuclear installations; the operation, maintenance and

Instrumentation and control systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. It supplements Safety Standards Series No. NS-R-1: Safety of Nuclear Power Plants: Design (the Requirements for Design), which establishes the design requirements for ensuring the safety of nuclear power plants. This Safety Guide describes how the requirements should be met for instrumentation and control (I and C) systems important to safety. This publication is a revision and combination of two previous Safety Guides: Safety Series Nos 50-SG-D3 and 50-SG-D8, which are superseded by this new Safety Guide. The revision takes account of developments in I and C systems important to safety since the earlier Safety Guides were published in 1980 and 1984, respectively. The objective of this Safety Guide is to provide guidance on the design of I and C systems important to safety in nuclear power plants, including all I and C components, from the sensors allocated to the mechanical systems to the actuated equipment, operator interfaces and auxiliary equipment. This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety. It expands on paragraphs of Ref in the area of I and C systems important to safety. This publication is intended for use primarily by designers of nuclear power plants and also by owners and/or operators and regulators of nuclear power plants. This Safety Guide provides general guidance on I and C systems important to safety which is broadly applicable to many nuclear power plants. More detailed requirements and limitations for safe operation specific to a particular plant type should be established as part of the design process. The present guidance is focused on the design principles for systems important to safety that warrant particular attention, and should be applied to both the design of new I and C systems and the modernization of existing systems. Guidance is provided on how design

Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants

International Nuclear Information System (INIS)

2016-05-01

Revised to take into consideration findings from the Fukushima Daiichi nuclear power plant accident, IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, has introduced some new concepts with respect to the earlier safety standard published in the year 2000. The preparation of SSR-2/1 (Rev. 1) was carried out with constant and intense involvement of IAEA Member States, but some new requirements, because of the novelty of the concepts introduced and the complexity of the issues, are not always interpreted in a unique way. The IAEA is confident that a complete clarification and a full understanding of the new requirements will be available when the supporting safety guides for design and safety assessment of nuclear power plants are prepared. The IAEA expects that the effort devoted to the preparation of this publication, which received input and comments from several Member States and experts, will also facilitate and harmonize the preparation or revision of these supporting standards

The current CEA/DRN safety approach for the design and the assessment of non-electrical applications of nuclear heat

International Nuclear Information System (INIS)

Fiorini, G.L.; Costa, M.

2000-01-01

This paper presents the basis of the safety approach currently implemented by the Commissariat a l'Energie Atomique - Nuclear Reactor Directorate (CEA/DRN), both for the design and the assessment of innovative systems and future nuclear installations. It is considered that the described approach is applicable to the plants built for non-electrical applications of nuclear heat. This is typically the case of Nuclear Desalination Installations. This approach is the result of the experience maturated, within the context of the CEA/DRN Innovative Programme, through practical applications over several future concepts (both fission and fusion plants). The background of this experience is structured coherently with the European Safety Authorities recommendations, the European Utilities Requirements (EUR) and the ''fundamental safety objectives'' defined by the IAEA. The Defence In Depth principle and its application, by means, among others, of the barrier concept, remains the basis of the safety design process of future nuclear installations. Its adequacy is checked through the safety assessment. The methodology for Lines of Defence (LOD) implementation as well as the one for the LOD architecture assessment is shown and motivated. The document shows that the clear and unambiguous definition of the safety approach provides an essential base for the organisation of the design tasks, being sure that the safety aspects are correctly taken into account and implemented, and for an adequate safety assessment of the final design, both from qualitative point of view as well as for the quantitative safety analysis. (author)

Design data and safety features of commerical nuclear power plant

International Nuclear Information System (INIS)

Heddleson, F.A.

1976-06-01

Design data, safety features, and site characteristics are summarized for 34 nuclear power units in 17 power stations in the United States. Six pages of data are presented for each plant, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. This volume covers Light Water Reactors (LWRs) with dockets 50-508 through 50-549, four HTGRs--50-171, 50-267, 50-450/451, 50-463/464, the Atlantic Floating Station 50-477/478, and the Clinch River Breeder 50-537

Regulatory Safety Requirements for Operating Nuclear Installations

International Nuclear Information System (INIS)

Gubela, W.

2017-01-01

The National Nuclear Regulator (NNR) is established in terms of the National Nuclear Regulator Act (Act No 47 of 1999) and its mandate and authority are conferred through sections 5 and 7 of this Act, setting out the NNR's objectives and functions, which include exercising regulatory control over siting, design, construction etc of nuclear installations through the granting of nuclear authorisations. The NNR's responsibilities embrace all those actions aimed at providing the public with confidence and assurance that the risks arising from the production of nuclear energy remain within acceptable safety limits -> Therefore: Set fundamental safety standards, conducting pro-active safety assessments, determining licence conditions and obtaining assurance of compliance. The promotional aspects of nuclear activities in South Africa are legislated by the Nuclear Energy Act (Act No 46 of 1999). The NNR approach to regulations of nuclear safety and security take into consideration, amongst others, the potential hazards associated with the facility or activity, safety related programmes, the importance of the authorisation holder's safety related processes as well as the need to exercise regulatory control over the technical aspects such as of the design and operation of a nuclear facility in ensuring nuclear safety and security. South Africa does not have national nuclear industry codes and standards. The NNR is therefore non-prescriptive as it comes to the use of industry codes and standards. Regulatory framework (current) provide for the protection of persons, property, and environment against nuclear damage, through Licensing Process: Safety standards; Safety assessment; Authorisation and conditions of authorisation; Public participation process; Compliance assurance; Enforcement

NPP Mochovce nuclear safety enhancement program

International Nuclear Information System (INIS)

Cech, J.; Baumester, P.

1997-01-01

Nuclear power plant Mochovce is currently under construction and an extensive nuclear safety enhancement programme is under way. The upgrading and modifications are based on IAEA documents and on those of the Nuclear Regulatory Authority of the Slovak Republic. Based on a contract concluded with Riskaudit from the CEC, safety examinations of the Mochovce design were performed. An extensive list of technical specifications of safety measures is given. (M.D.)

Strengthening the Global Nuclear Safety Regime. INSAG-21. A report by the International Nuclear Safety Group

International Nuclear Information System (INIS)

2014-01-01

The Global Nuclear Safety Regime is the framework for achieving the worldwide implementation of a high level of safety at nuclear installations. Its core is the activities undertaken by each country to ensure the safety and security of the nuclear installations within its jurisdiction. But national efforts are and should be augmented by the activities of a variety of international enterprises that facilitate nuclear safety - intergovernmental organizations, multinational networks among operators, multinational networks among regulators, the international nuclear industry, multinational networks among scientists, international standards setting organizations and other stakeholders such as the public, news media and non-governmental organizations (NGOs) that are engaged in nuclear safety. All of these efforts should be harnessed to enhance the achievement of safety. The existing Global Nuclear Safety Regime is functioning at an effective level today. But its impact on improving safety could be enhanced by pursuing some measured change. This report recommends action in the following areas: - Enhanced use of the review meetings of the Convention on Nuclear Safety as a vehicle for open and critical peer review and a source for learning about the best safety practices of others; - Enhanced utilization of IAEA Safety Standards for the harmonization of national safety regulations, to the extent feasible; - Enhanced exchange of operating experience for improving operating and regulatory practices; and - Multinational cooperation in the safety review of new nuclear power plant designs. These actions, which are described more fully in this report, should serve to enhance the effectiveness of the Global Nuclear Safety Regime

Managing nuclear safety at Point Lepreau

Energy Technology Data Exchange (ETDEWEB)

Paciga, J [New Brunswick Power, Point Lepreau NGS, PQ (Canada)

1997-12-01

Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance).

Managing nuclear safety at Point Lepreau

International Nuclear Information System (INIS)

Paciga, J.

1997-01-01

Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance)

The current CEA/DRN safety approach for the design and the assessment of future nuclear installations

International Nuclear Information System (INIS)

Fiorini, G.L.; Pinto, P.L.; Costa, M.

1999-01-01

The purpose of the document is to present the basis of the safety approach currently implemented by the CEA/DRN, both for the design and the assessment of innovative systems and future nuclear installations. This approach is the result of the experience maturated, within the context of the CEA/DRN Innovative Programme through practical applications over several future concepts, both for fission and fusion reactors, as well as for waste disposal. The background of this experience is structured coherently with the European Safety Authorities recommendations and the European Utilities Requirements (EUR). The Defence In Depth principle and its application, by means, among others, of the barrier concept, remains the basis of the safety design process of future nuclear installations. Its adequacy is checked through the safety assessment. The methodology for Lines Of Defence (LOD) implementation as well as the one for the LOD architecture assessment is shown and motivated. The document shows that the clear and unambiguous definition of the safety approach provides an essential base for the organisation of the design tasks, being sure that the safety aspects are correctly taken into account and implemented, and for an adequate safety assessment of the final design, both from qualitative point of view as well as for the quantitative safety analysis. (author)

International Nuclear Safety Center (INSC) database

International Nuclear Information System (INIS)

Sofu, T.; Ley, H.; Turski, R.B.

1997-01-01

As an integral part of DOE's International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world's nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world's nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables

Nuclear safety chains

International Nuclear Information System (INIS)

Robbins, M.C.; Eames, G.F.; Mayell, J.R.

1981-01-01

An original scheme has been developed for expressing the complex interrelationships associated with the engineered safeguards provided for a nuclear power station. This management tool, based upon network diagrams called Nuclear Safety Chains, looks at the function required of a particular item of safety plant, defines all of the vital supplies and support features necessary for successful operation, and expresses them in visual form, to facilitate analysis and optimisation for operations and maintenance staff. The safety chains are confined to manual schemes at present, although they are designed to be compatible with modern computer techniques. Their usefulness with any routine maintenance planning application on high technology plant is already being appreciated. (author)

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

Energy Technology Data Exchange (ETDEWEB)

RYAN GW

2007-09-24

'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

International Nuclear Information System (INIS)

RYAN GW

2007-01-01

'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents

IAEA activity related to safety of nuclear desalination

International Nuclear Information System (INIS)

Gasparini, M.

2000-01-01

The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. The current safety approach, based on the achievement of the fundamental safety functions and defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

China's nuclear safety regulatory body: The national nuclear safety administration

International Nuclear Information System (INIS)

Zhang Shiguan

1991-04-01

The establishment of an independent nuclear safety regulatory body is necessary for ensuring the safety of nuclear installations and nuclear fuel. Therefore the National Nuclear Safety Administration was established by the state. The aim, purpose, organization structure and main tasks of the Administration are presented. At the same time the practical examples, such as nuclear safety regulation on the Qinshan Nuclear Power Plant, safety review and inspections for the Daya Bay Nuclear Power Plant during the construction, and nuclear material accounting and management system in the nuclear fuel fabrication plant in China, are given in order to demonstrate the important roles having been played on nuclear safety by the Administration after its founding

Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2007-10-01

The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

Safety of nuclear ships

International Nuclear Information System (INIS)

1978-01-01

Interest in the utilization of nuclear steam supply systems for merchant ships and icebreakers has recently increased considerably due to the sharp rise in oil prices and the continuing trend towards larger and faster merchant ships. Canada, for example, is considering construction of an icebreaker in the near future. On the other hand, an accident which could result in serious damage to or the sinking of a nuclear ship is potentially far more dangerous to the general public than a similar accident with a conventional ship. Therefore, it was very important to evaluate in an international forum the safety of nuclear ships in the light of our contemporary safety philosophy, taking into account the results of cumulative operating experience with nuclear ships in operation. The philosophy and safety requirement for land-based nuclear installations were outlined because of many common features for both land-based nuclear installations and nuclear ships. Nevertheless, essential specific safety requirements for nuclear ships must always be considered, and the work on safety problems for nuclear ships sponsored by the NEA was regarded as an important step towards developing an international code of practice by IMCO on the safety of nuclear merchant ships. One session was devoted to the quantitative assessment of nuclear ship safety. The probability technique of an accident risk assessment for nuclear power plants is well known and widely used. Its modification, to make it applicable to nuclear propelled merchant ships, was discussed in some papers. Mathematical models for describing various postulated accidents with nuclear ships were developed and reported by several speakers. Several papers discussed a loss-of-coolant accident (LOCA) with nuclear steam supply systems of nuclear ships and engineering design features to prevent a radioactive effluence after LOCA. Other types of postulated accidents with reactors and systems in static and dynamic conditions were also

Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island Design (Docket No. 50-447). Supplement No. 3

International Nuclear Information System (INIS)

1985-01-01

Supplement 3 to the Safety Evaluation Report (SER) for the application filed by General Electric Company for the final design approval for the GE BWR/6 nuclear island design has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

The role of probabilistic safety assessment and probabilistic safety criteria in nuclear power plant safety

International Nuclear Information System (INIS)

1992-01-01

The purpose of this Safety Report is to provide guidelines on the role of probabilistic safety assessment (PSA) and a range of associated reference points, collectively referred to as probabilistic safety criteria (PSC), in nuclear safety. The application of this Safety Report and the supporting Safety Practice publication should help to ensure that PSA methodology is used appropriately to assess and enhance the safety of nuclear power plants. The guidelines are intended for use by nuclear power plant designers, operators and regulators. While these guidelines have been prepared with nuclear power plants in mind, the principles involved have wide application to other nuclear and non-nuclear facilities. In Section 2 of this Safety Report guidelines are established on the role PSA can play as part of an overall safety assurance programme. Section 3 summarizes guidelines for the conduct of PSAs, and in Section 4 a PSC framework is recommended and guidance is provided for the establishment of PSC values

Tutorial on nuclear thermal propulsion safety for Mars

International Nuclear Information System (INIS)

Buden, D.

1992-01-01

Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments

Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

Energy Technology Data Exchange (ETDEWEB)

Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott F [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-01-06

Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the

Safety systems and safety analysis of the Qinshan phase III CANDU nuclear power plant

International Nuclear Information System (INIS)

Cai Jianping; Shen Sen; Barkman, N.

1999-01-01

The author introduces the Canadian nuclear reactor safety philosophy and the Qinshan Phase III CANDU NPP safety systems and safety analysis, which are designed and performed according to this philosophy. The concept of 'defence-in-depth' is a key element of the Canadian nuclear reactor safety philosophy. The design concepts of redundancy, diversity, separation, equipment qualification, quality assurance, and use of appropriate design codes and standards are adopted in the design. Four special safety systems as well as a set of reliable safety support systems are incorporated in the design of Qinshan phase III CANDU for accident mitigation. The assessment results for safety systems performance show that the fundamental safety criteria for public dose, and integrity of fuel, channels and the reactor building, are satisfied

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

culture and achieve good performance in terms of safety. This publication identifies the main safety objectives and responsibilities of management with respect to the safe operation of nuclear power plants and associated corporate roles of the operating organization. This Safety Guide discusses the factors to be considered in (a) structuring the operating organization to meet these main safety objectives, (b) setting up management programmes that ensure that the safety tasks are performed, (c) establishing services and facilities that are intended to meet the above requirements and (d) maintaining a strong safety culture within the organization. This Safety Guide primarily addresses safety matters directly related to the operation of nuclear power plants. It assumes that the safety aspects of siting, design, manufacturing and construction have been resolved. It also covers the internal interrelationships between operations and design, construction and commissioning and other organizational units, and deals with the involvement of the operating organization in reviews of safety issues, bearing in mind future operation. Finally, this publication discusses the relationship between the operating organization, the regulatory body and the general public. Section 2 focuses on the operating organization and its structure. Section 3 discusses the functions, responsibilities, goals and objectives of the operating organization that ensure the safe operation of nuclear power plants. Section 4 gives guidance on the interface between the operating organization and external organizations. Section 5 covers safety management aspects. Section 6 provides guidance on the major management programmes that should be established to ensure the safe operation of a nuclear power plant. Section 7 discusses additional services that are needed to support the functioning of plant operation management programmes. Section 8 provides general guidance on the communication and liaison matters that are

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

culture and achieve good performance in terms of safety. This publication identifies the main safety objectives and responsibilities of management with respect to the safe operation of nuclear power plants and associated corporate roles of the operating organization. This Safety Guide discusses the factors to be considered in (a) structuring the operating organization to meet these main safety objectives, (b) setting up management programmes that ensure that the safety tasks are performed, (c) establishing services and facilities that are intended to meet the above requirements and (d) maintaining a strong safety culture within the organization. This Safety Guide primarily addresses safety matters directly related to the operation of nuclear power plants. It assumes that the safety aspects of siting, design, manufacturing and construction have been resolved. It also covers the internal interrelationships between operations and design, construction and commissioning and other organizational units, and deals with the involvement of the operating organization in reviews of safety issues, bearing in mind future operation. Finally, this publication discusses the relationship between the operating organization, the regulatory body and the general public. Section 2 focuses on the operating organization and its structure. Section 3 discusses the functions, responsibilities, goals and objectives of the operating organization that ensure the safe operation of nuclear power plants. Section 4 gives guidance on the interface between the operating organization and external organizations. Section 5 covers safety management aspects. Section 6 provides guidance on the major management programmes that should be established to ensure the safe operation of a nuclear power plant. Section 7 discusses additional services that are needed to support the functioning of plant operation management programmes. Section 8 provides general guidance on the communication and liaison matters that are

Safety strategy and safety analysis of nuclear power plants

International Nuclear Information System (INIS)

Franzen, L.F.

1976-01-01

The safety strategy for nuclear power plants is characterized by the fact that the high level of safety was attained not as a result of experience, but on the basis of preventive accident analyses and the finding derived from such analyses. Although, in these accident analyses, the deterministic approach is predominant, it is supplemented by reliability analyses. The accidents analyzed in nuclear licensing procedures cover a wide spectrum from minor incidents to the design basis accidents which determine the design of the safety devices. The initial and boundary conditions, which are essentail for accident analyses, and the determination of the loads occurring in various states during regular operation and in accidents flow into the design of the individual systems and components. The inevitable residual risk and its origins are discussed. (orig.) [de

Complementary safety assessments - Report by the French Nuclear Safety Authority

International Nuclear Information System (INIS)

2011-12-01

As an immediate consequence of the Fukushima accident, the French Authority of Nuclear Safety (ASN) launched a campaign of on-site inspections and asked operators (mainly EDF, AREVA and CEA) to make complementary assessments of the safety of the nuclear facilities they manage. The approach defined by ASN for the complementary safety assessments (CSA) is to study the behaviour of nuclear facilities in severe accidents situations caused by an off-site natural hazard according to accident scenarios exceeding the current baseline safety requirements. This approach can be broken into 2 phases: first conformity to current design and secondly an approach to the beyond design-basis scenarios built around the principle of defence in depth. 38 inspections were performed on issues linked to the causes of the Fukushima crisis. It appears that some sites have to reinforce the robustness of the heat sink. The CSA confirmed that the processes put into place at EDF to detect non-conformities were satisfactory. The complementary safety assessments demonstrated that the current seismic margins on the EDF nuclear reactors are satisfactory. With regard to flooding, the complementary safety assessments show that the complete reassessment carried out following the flooding of the Le Blayais nuclear power plant in 1999 offers the installations a high level of protection against the risk of flooding. Concerning the loss of electrical power supplies and the loss of cooling systems, the analysis of EDF's CSA reports showed that certain heat sink and electrical power supply loss scenarios can, if nothing is done, lead to core melt in just a few hours in the most unfavourable circumstances. As for nuclear facilities that are not power or experimental reactors, some difficulties have appeared to implement the CSA approach that was initially devised for reactors. Generally speaking, ASN considers that the safety of nuclear facilities must be made more robust to improbable risks which are not

Nuclear Safety Bureau: safety objectives and principles for the proposed ANSTO reactor

International Nuclear Information System (INIS)

Westall, D.

1993-01-01

Siting criteria and safety assessment principles were previously promulgated by the Australian Atomic Energy Commission (AAEC), and have been applied by ANSTO and the Nuclear Safety Bureau (NSB). The NSB is revising these criteria and principles to take account of evolving nuclear safety standards and practices. The NSB Safety and Siting Assessment Principles (SSAP) are presented and it is estimated that it will provide a comprehensive basis for the safety assessment of research reactors in Australia, and be applicable to all stages of a reactor project: siting: design and construction; operation; modification; and decommissioning. The SSAP are similar to the principles promulgated by the AAEC, in that probabilistic safety criteria are set for assessment of design, however these criteria are complimentary to a deterministic design basis approach. This is a similar approach to that recently published by the UK Nuclear Installations Inspectorate 4 . Siting principles are now also included, where they were previously separate, and require a consideration of the consequences of severe accidents which are an extension of accidents catered for by the design of the plant. Criteria for radiation doses due to normal operations and design basis accidents are included in the principles for safety assessment. 9 refs

Nuclear Safety Review for 2014

International Nuclear Information System (INIS)

2014-07-01

The Nuclear Safety Review 2014 focuses on the dominant nuclear safety trends, issues and challenges in 2013. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: strengthening safety in nuclear installations; improving radiation, transport and waste safety; enhancing emergency preparedness and response (EPR); improving regulatory infrastructure and effectiveness; and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards, and activities relevant to the Agency’s safety standards. The global nuclear community has made steady and continuous progress in strengthening nuclear safety in 2013, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”) and reported in Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2013/8-GC(57)/INF/5), and the Supplementary Information to that report and Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2014/2). • Significant progress continues to be made in several key areas, such as assessments of safety vulnerabilities of nuclear power plants (NPPs), strengthening of the Agency’s peer review services, improvements in EPR capabilities, strengthening and maintaining capacity building, and protecting people and the environment from ionizing radiation. The progress that has been made in these and other areas has contributed to the enhancement of the global nuclear safety framework. • Significant progress has also been made in reviewing the Agency’s safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on vitally important areas such as design and operation of NPPs, protection of NPPs against severe accidents, and EPR. • The Agency continued to

Advancements in the design of safety-related systems and components of the MARS nuclear plant

International Nuclear Information System (INIS)

Caira, M.; Caruso, G.; Naviglio, A.; Sorabella, L.; Farello, C.E.

1992-01-01

In the paper, the advancements in the design of safety-related systems and components of the MARS nuclear plant, equipped with a 600 MW th PWR, are described. These advancements are due to the special safety features of this plant, which relies completely on inherent and passive safety. In particular, the new steps of the design of the innovative, completely passive, and with an unlimited autonomy Emergency core Cooling System are described, together with the characteristics of the last version of the steam generator, developed in a new design involving disconnecting components, for a fast erection and an easy maintenance. (author)

Safety assessment principles for nuclear plants

International Nuclear Information System (INIS)

1992-01-01

The present Safety Assessment Principles result from the revision of those which were drawn up following a recommendation arising from the Sizewell-B enquiry. The principles presented here relate only to nuclear safety; there is a section on risks from normal operation and accident conditions and the standards against which those risks are assessed. A major part of the document deals with the principles that cover the design of nuclear plants. The revised Safety assessment principles are aimed primarily at the safety assessment of new nuclear plants but they will also be used in assessing existing plants. (UK)

Nuclear Safety Review for 2015

International Nuclear Information System (INIS)

2015-06-01

The Nuclear Safety Review 2015 focuses on the dominant nuclear safety trends, issues and challenges in 2014. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: improving radiation, transport and waste safety; strengthening safety in nuclear installations; enhancing emergency preparedness and response (EPR); and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the Agency’s safety standards. The global nuclear community continued to make steady progress in improving nuclear safety throughout the world in 2014; and, the Agency and its Member States continued to implement the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”), which was endorsed by the General Conference in 2011 after the Fukushima Daiichi accident in March 2011. • Significant progress has been made in reviewing and revising various Agency’s safety standards in areas such as management of radioactive waste, design basis hazard levels, protection of nuclear power plants (NPPs) against severe accidents, design margins to avoid cliff edge effects, multiple facilities at one site, and strengthening the prevention of unacceptable radiological consequences to the public and the environment, communications and EPR. In addition, the Guidelines for Drafting IAEA Safety Standards and Nuclear Security Series Publications was issued in July 2014.• The Agency continued to analyse the relevant technical aspects of the Fukushima Daiichi accident and to share and disseminate lessons learned to the wider nuclear community. In 2014, the Agency organized two international experts’ meetings (IEMs), one on radiation protection and one on severe accident management. Reports from previous IEMs were also published in 2014: IAEA Report on Human and Organizational Factors in Nuclear

Nuclear safety research in France

International Nuclear Information System (INIS)

Tanguy, P.

1976-01-01

As a consequence of the decision of choosing light water reactors (PWR) for the French nuclear plants of the next ten years, a large safety program has been launched referring to three physical barriers against fission product release: the fuel element cladding, main primary system boundary and the containment. The parallel development of French-designed fast breeder reactors involved safety studies on: sodium boiling, accidental fuel behavior, molten fuel-sodium interaction, core accident and protection, and external containment. The rapid development of nuclear energy resulted in a corresponding development of safety studies relating to nuclear fuel facilities. French regulations also required a special program to be developed for the realistic evaluation of the consequences of external agressions, the French cooperation to multinational safety research being also intensive

Nuclear safety: an international approach: the convention on nuclear safety

International Nuclear Information System (INIS)

Rosen, M.

1994-01-01

This paper is a general presentation of the IAEA Convention on Nuclear Safety which has already be signed by 50 countries and which is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The paper gives a review of its development and some key provisions for a better understanding of how this agreement will operate in practice. The Convention consists of an introductory preamble and four chapters consisting of 35 articles dealing with: the principal objectives, definitions and scope of application; the various obligations (general provisions, legislation, responsibility and regulation, general safety considerations taking into account: the financial and human resources, the human factors, the quality assurance, the assessment and verification of safety, the radiation protection and the emergency preparedness; the safety of installations: sitting, design and construction, operation); the periodic meetings of the contracting parties to review national reports on the measures taken to implement each of the obligations, and the final clauses and other judicial provisions common to international agreements. (J.S.). 1 append

Nuclear accidents and safety measures of domestic nuclear power plants

International Nuclear Information System (INIS)

Song Zurong; Che Shuwei; Pan Xiang

2012-01-01

Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

1998-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

Application of project management methodology in design management of nuclear safety related structure

International Nuclear Information System (INIS)

Chen Mao

2004-01-01

This paper focuses on the application of project management methodology in the design management of Nuclear Safety Related Structure (NSRS), considering the design management features of its civil construction. Based on the experiences from the management of several projects, the project management triangle is proposed to be used in the management, to well treat the position of design interface in the project management. Some other management methods are also proposed

Evaluation of the Ventilation and Air Cleaning System Design Concepts for Safety Requirements during Fire Conditions in Nuclear Applications

International Nuclear Information System (INIS)

Rashad, S.; El-Fawal, M.; Kandil, M.

2013-01-01

The ventilation and air cleaning system in the nuclear or radiological installations is one of the essential nuclear safety concerns. It is responsible for confining the radioactive materials involved behind suitable barriers during normal and abnormal conditions. It must be designed to prevent the release of harmful products (radioactive gases, or airborne radioactive materials) from the system or facility, impacting the public or workers, and doing environmental damage. There are two important safety functions common to all ventilation and air cleaning system in nuclear facilities. They are: a) the requirements to maintain the pressure of the ventilated volume below that of surrounding, relatively non-active areas, in order to inhibit the spread of contamination during normal and abnormal conditions, and b) the need to treat the ventilated gas so as to minimize the release of any radioactive or toxic materials. Keeping the two important safety functions is achieved by applying the fire protection for the ventilation system to achieve safety and adequate protection in nuclear applications facilities during fire and accidental criticality conditions.The main purpose of this research is to assist ventilation engineers and experts in nuclear installations for safe operation and maintaining ventilation and air cleaning system during fire accident in nuclear facilities. The research focuses on fire prevention and protection of the ventilation systems in nuclear facilities. High-Efficiency particulate air (HEPA) filters are extremely susceptible to damage when exposed to the effects of fire, smoke, and water; it is the intent of this research to provide the designer with the experience gained over the years from hard lessons learned in protecting HEPA filters from fire. It describes briefly and evaluates the design safety features, constituents and working conditions of ventilation and air cleaning system in nuclear and radioactive industry.This paper provides and

Technical regulations on the general design and safety criteria for design and construction of nuclear reactors of May 1975

International Nuclear Information System (INIS)

1975-05-01

These Technical Regulations published on 5th September 1975 were made in implementation of Section 33 of Decree No 7/9141 on the procedure for the licensing of nuclear installations. They serve as a guide to licensing authorities, project designers and operators in the nuclear field and therefore provide general criteria for safety standards, engineering codes, siting considerations, design bases for overall environmental radiation protection, and also deal with reactor core design, instrumentation, control, alarm systems, including an emergency core cooling system. Finally, the safe design of fuel elements must be ensured and fuel storage and handling techniques complied with. (NEA) [fr

Guidelines for nuclear reactor equipments safety-analysis

International Nuclear Information System (INIS)

1978-01-01

The safety analysis in approving the applications for nuclear reactor constructions (or alterations) is performed by the Committee on Examination of Reactor Safety in accordance with various guidelines prescribed by the Atomic Energy Commission. In addition, the above Committee set forth its own regulations for the safety analysis on common problems among various types of nuclear reactors. This book has collected and edited those guidelines and regulations. It has two parts: Part I includes the guidelines issued to date by the Atomic Energy Commission: and Part II - regulations of the Committee. Part I has collected 8 categories of guidelines which relate to following matters: nuclear reactor sites analysis guidelines and standards for their applications; standard exposure dose of plutonium; nuclear ship operation guidelines; safety design analysis guidelines for light-water type, electricity generating nuclear reactor equipments; safety evaluation guidelines for emergency reactor core cooling system of light-water type power reactors; guidelines for exposure dose target values around light-water type electricity generating nuclear reactor equipments, and guidelines for evaluation of above target values; and meteorological guidelines for the safety analysis of electricity generating nuclear reactor equipments. Part II includes regulations of the Committee concerning - the fuel assembly used in boiling-water type and in pressurized-water type reactors; techniques of reactor core heat designs, etc. in boiling-water reactors; and others

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2007-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

The safety of nuclear installations

International Nuclear Information System (INIS)

1993-01-01

This Safety Fundamental publication sets out basic objectives, concepts and principles for ensuring safety that can be used both by the IAEA in its international assistance operations and by Member States in their national nuclear programmes. These Safety Fundamentals apply primarily to those nuclear installations in which the stored energy developed in certain situations could potentially results in the release of radioactive material from its designated location with the consequent risk of radiation exposure of people. These principles are applicable to a broad range of nuclear installations, but their detailed application will depend on the particular technology and the risks posed by it. In addition to nuclear power plants, such installations may include: research reactors and facilities, fuel enrichment, manufacturing and reprocessing plants; and certain facilities for radioactive waste treatment and storage

Development of the Advanced Nuclear Safety Information Management (ANSIM) System

Energy Technology Data Exchange (ETDEWEB)

Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

Design of Instrumentation and Control Systems for Nuclear Power Plants. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This publication is a revision and combination of two Safety Guides, IAEA Safety Standards Series No. NS-G-1.1 and No. NS-G-1.3. The revision takes into account developments in instrumentation and control (I&C) systems since the publication of the earlier Safety Guides. The main changes relate to the continuing development of computer applications and the evolution of the methods necessary for their safe, secure and practical use. In addition, account is taken of developments in human factors engineering and the need for computer security. This Safety Guide references and takes into account other IAEA Safety Standards and Nuclear Security Series publications that provide guidance relating to I&C design

Applicability of trends in nuclear safety analysis to space nuclear power systems

International Nuclear Information System (INIS)

Bari, R.A.

1992-01-01

A survey is presented of some current trends in nuclear safety analysis that may be relevant to space nuclear power systems. This includes: lessons learned from operating power reactor safety and licensing; approaches to the safety design of advanced and novel reactors and facilities; the roles of risk assessment, extremely unlikely accidents, safety goals/targets; and risk-benefit analysis and communication

Safety consideration and economic advantage of a new underground nuclear power plant design

International Nuclear Information System (INIS)

Lyczkowski, R.W.; Ching, J.T.

1979-01-01

A conceptual design of an underground nuclear power plant is proposed to make undergrounding of nuclear reactors not only environmentally desirable but also economically feasible. Expedient to the underground environment, this design capitalizes on the pressure-containing and radiation filtering characteristics of the new underground boundary conditions. Design emphasis is on the containment of a catastrophic accident - that of a reactor vessel rupture caused by external means. The High Capacity Rapid Energy Dissipation Underground Containment (HiC-REDUCE) system which efficiently contains loss-of-coolant accidents (LOCAs) and small break conditions is described. The end product is a radiation-release-proof plant which, in effect, divorces the public from the safety of the reactor. (Auth.)

Nuclear power reactor safety research activities in CIAE

International Nuclear Information System (INIS)

Pu Shendi; Huang Yucai; Xu Hanming; Zhang Zhongyue

1994-01-01

The power reactor safety research activities in CIAE are briefly reviewed. The research work performed in 1980's and 1990's is mainly emphasised, which is closely related to the design, construction and licensing review of Qinshan Nuclear Power Plant and the safety review of Guangdong Nuclear Power Station. Major achievements in the area of thermohydraulics, nuclear fuel, probabilistic safety assessment and severe accident researches are summarized. The foreseeable research plan for the near future, relating to the design and construction of 600 MWe PWR NPP at Qinshan Site (phase II development) is outlined

Maintaining the design Integrity of nuclear installations throughout their operating life. INSAG-19. A report by the International Nuclear Safety Advisory Group (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. this INSAG report discusses the problem of maintaining the integrity of design of a nuclear power plant over its entire lifetime in order to achieve a continuous high level of safety. A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's operating lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. The purpose of this report is to identify the issues and some of the principles that should be addressed, discuss some of the solutions to the problem, and highlight the specific responsibilities of designers, operators and regulators. The issues and principles discussed here are also applicable to other nuclear installations (for example, research reactors and fuel cycle facilities). This INSAG report is directed at senior executives who are responsible for: the overall safety of nuclear installations; the operation

Nuclear safety regulations in the Republic of Croatia

International Nuclear Information System (INIS)

Cizmek, A.; Horvatic, M.; Ilijas, B.; Medakovic, S.

2009-01-01

Based on Nuclear Safety Act (Official Gazette No. 173/03) in 2006 State Office for Nuclear Safety (SONS) adopted beside Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06) the new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08) and Ordinance on conditions for nuclear safety and protection with regard to the sitting, design, construction, use and decommissioning of a facility in which a nuclear activity is to be performed (Official Gazette No. 71/08). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a license to perform nuclear activity. The Ordinance also regulates the content of the form for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear conditions, whereas compliance is established by the decision passed by SONS. Ordinance on special conditions (requirements) for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned activities Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a licence to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance

Enhancement of nuclear safety culture

International Nuclear Information System (INIS)

Anderson, Stanley J.

1996-01-01

Throughout the 40-year history of the commercial nuclear power industry, improvements have continually been made in the design of nuclear power plants and the equipment in them. In one sense, we have reached an enviable point -- in most plants, equipment failures have become relatively rare. Yet events continue to occur. Regardless of how much the plants are improved, that equipment is operated by people -- highly motivated, well-trained people -- but people nonetheless. And people occasionally make mistakes. By setting the right climate and by setting high standards, good plant management can reduce the number of mistakes made ? and also reduce their potential consequences. Another way to say this is that the proper safety culture must be established and continually improved upon in our nuclear plants. Safety culture is defined by the International Atomic Energy Agency as 'that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance.' In short, we must make safety our top priority

Nuclear safety and regulation

International Nuclear Information System (INIS)

Kim, Hho Jung

2000-03-01

This book contains 12 chapters, which are atom and radiation, nuclear reactor and kinds of nuclear power plant, safeguard actuation system and stability evaluation for rock foundation of nuclear power plant, nuclear safety and principle, safety analysis and classification of incident, probabilistic safety assessment and major incident, nuclear safety regulation, system of nuclear safety regulation, main function and subject of safety regulation in nuclear facilities, regulation of fuel cycle and a nuclear dump site, protection of radiation and, safety supervision and, safety supervision and measurement of environmental radioactivity.

Advanced nuclear power systems: Design, technology, safety and strategies for their deployment

International Nuclear Information System (INIS)

1994-01-01

The objectives of the symposium were to provide high level decision makers with an overview of the discussion concerning the need for nuclear power and salient features of advanced nuclear power systems; a forum for discussing the design objectives and safety approaches for such systems and the views of regulatory bodies; a forum for identifying barriers to the deployment of these systems and for reviewing strategies to overcome these barriers; and a forum for reviewing options for international cooperation in the development and deployment of such systems. Refs, figs and tabs

Redefining interrelationship between nuclear safety, nuclear security and safeguards

International Nuclear Information System (INIS)

Irie, Kazutomo

2011-01-01

Since the beginning of this century, the so-called 3Ss (Nuclear Safety, Nuclear Security and Safeguards) have become major regulatory areas for peaceful uses of nuclear energy. The importance of the 3Ss is now emphasized to countries which are newly introducing nuclear power generation. However, as role models for those newcomers, existing nuclear power countries are also required to strengthen their regulatory infrastructure for the 3Ss. In order to rationalize the allocation of regulatory resources, interrelationship of the 3Ss should be investigated. From the viewpoint of the number of the parties concerned in regulation, nuclear security is peculiar with having 'aggressors' as the third party. From the viewpoint of final goal of regulation, nuclear security in general and safeguards share the goal of preventing non-peaceful uses of nuclear energy, though the goal of anti-sabotage within nuclear security is rather similar to nuclear safety. As often recognized, safeguards are representative of various policy tools for nuclear non-proliferation. Strictly speaking, it is not safeguards as a policy tool but nuclear non-proliferation as a policy purpose that should be parallel to other policy purposes (nuclear safety and nuclear security). That suggests 'SSN' which stands for Safety, Security and Non-proliferation is a better abbreviation rather than 3Ss. Safeguards as a policy tool should be enumerated along with nuclear safety regulation, nuclear security measures and trade controls on nuclear-related items. Trade controls have been playing an important role for nuclear non-proliferation. These policy tools can be called 'SSST' in which Trade controls are also emphasized along with Safety regulation, Security measures and Safeguards. Recently, it becomes quite difficult to clearly demarcate these policy tools. As nuclear security concept is expanding, the denotation of nuclear security measures is also expanding. Nuclear security measures are more and more

PA activity by using nuclear power plant safety demonstration and analysis

International Nuclear Information System (INIS)

Tsuchiya, Mitsuo; Kamimae, Rie

1999-01-01

INS/NUPEC presents one of Public acceptance (PA) methods for nuclear power in Japan, 'PA activity by using Nuclear Power Plant Safety Demonstration and Analysis', by using one of videos which is explained and analyzed accident events (Loss of Coolant Accident). Safety regulations of The National Government are strictly implemented in licensing at each of basic design and detailed design. To support safety regulation activities conducted by the National Government, INS/NLTPEC continuously implement Safety demonstration and analysis. With safety demonstration and analysis, made by assuming some abnormal conditions, what impacts could be produced by the assumed conditions are forecast based on specific design data on a given nuclear power plants. When analysis results compared with relevant decision criteria, the safety of nuclear power plants is confirmed. The decision criteria are designed to help judge if or not safety design of nuclear power plants is properly made. The decision criteria are set in the safety examination guidelines by taking sufficient safety allowance based on the latest technical knowledge obtained from a wide range of tests and safety studies. Safety demonstration and analysis is made by taking the procedure which are summarized in this presentation. In Japan, various PA (Public Acceptance) pamphlets and videos on nuclear energy have been published. But many of them focused on such topics as necessity or importance of nuclear energy, basic principles of nuclear power generation, etc., and a few described safety evaluation particularly of abnormal and accident events in accordance with the regulatory requirements. In this background, INS/NUPEC has been making efforts to prepare PA pamphlets and videos to explain the safety of nuclear power plants, to be simple and concrete enough, using various analytical computations for abnormal and accident events. In results, PA activity of INS/NUPEC is evaluated highly by the people

Nuclear criticality safety program at the Fuel Cycle Facility

International Nuclear Information System (INIS)

Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

1994-01-01

The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

Development of a nuclear ship safety philosophy

International Nuclear Information System (INIS)

Thompson, T.E.

1978-01-01

A unique safety philosophy must be recognized and accepted as an integral part of the design and operation of a nuclear ship. For the nuclear powered ship, the ultimate safety of the reactor and therefore the crew and the environment lies with the safety of the ship itself. The basis for ship safety is its ability to navigate and survive the conditions or the environment in which it may find itself. The subject of traditional ship safety is examined along with its implication for reactor protection and safety. Concepts of reactor safety are also examined. These two philosophies are combined in a manner so as to provide a sound philosophy for the safety of nuclear ships, their crews, and the environment

Human factor as nuclear safety element

International Nuclear Information System (INIS)

Valeca, S.C.; Preda, M.; Valeca, M.; Ana, E. M.; Popescu, D.

2008-01-01

National nuclear power system is based on western technology, it covers almost 20% from national need and could be briefly described by: - Safety and economic performances of Cernavoda NPP Unit 1; - Reduced influence on environment, population and workers; - Excellent ranking (place 4) among CANDU units from all over the world. Also, the national nuclear power system plays a major role in Romanian power policy accomplishment: - Energy safety and independence assurance; - Decrease of production of greenhouse effect gases; - Preserve the stability and adequacy of energy cost. 'Nuclear Safety' concept covers all the activities resulting from nuclear fuel cycle. By taking into account the international experience, the related activities are estimated to last around 70 years in Romania: - 10 years for site description and selection, design, manufacturing and commissioning activities; - 40 years for Nuclear Power Plant operation, maintenance and modernization activities; - 20 years for preservation and decommissioning activities. The above mentioned activities requires human resources, qualified and specialized in the following areas: - research and development; - equipment design, manufacturing and operation; - components construction and assembly, operation and maintenance. (authors)

Nuclear safety

International Nuclear Information System (INIS)

1991-02-01

This book reviews the accomplishments, operations, and problems faced by the defense Nuclear Facilities Safety Board. Specifically, it discusses the recommendations that the Safety Board made to improve safety and health conditions at the Department of Energy's defense nuclear facilities, problems the Safety Board has encountered in hiring technical staff, and management problems that could affect the Safety Board's independence and credibility

Code of safety for nuclear merchant ships

International Nuclear Information System (INIS)

1982-01-01

The Code is in chapters, entitled: general (including general safety principles and principles of risk acceptance); design criteria and conditions; ship design, construction and equipment; nuclear steam supply system; machinery and electrical installations; radiation safety (including radiological protection design; protection of persons; dosimetry; radioactive waste management); operation (including emergency operation procedures); surveys. Appendices cover: sinking velocity calculations; seaway loads depending on service periods; safety assessment; limiting dose-equivalent rates for different areas and spaces; quality assurance programme; application of single failure criterion. Initial application of the Code is restricted to conventional types of ships propelled by nuclear propulsion plants with pressurized light water type reactors. (U.K.)

Hualong One's nuclear reactor core design and relative safety issues research

Energy Technology Data Exchange (ETDEWEB)

Yu, H., E-mail: yuhong_xing@126.com [Nuclear Power Inst. of China, Design and Research Sub-Inst., Chengdu, Sichuan (China)

2015-07-01

'Full text:' Hualong One, a third generation 1000MWe-class pressurized water reactor, is developed by China National Nuclear Cooperation (CNNC), based on the self-reliant technologies and experiences from China 40 years designing, construction, operation and maintenance of NPPs. In China, it has been approved to construct at Fuqing 5&6 and Fangchenggang 3&4. The Hualong One adopts advanced design features to dramatically enhance plant safety, economic efficiency and convenience of operation and maintenance. It consists of three loops with nominal thermal power output 3060 MWt and a 60-year design life. Its reactor core has 177 fuel assemblies, 18 month refueling interval (after initial cycle), and more than 15% thermal margin. It adopts low leakage loading pattern which can achieve better economy of the neutron, higher reactivity and lower radiation damage of pressure vessel. For the safety design, incorporating the feedback of Fukushima accident, the Hualong One has a combination of active and passive safety systems, a single station layout, double containment structure, and comprehensive implementation of defence-in-depth design principles. The new design features has been successfully evaluated to ensure that they enhance the performance and safety of Hualong One. Several experimental activates have been conducted, such as cavity injection and cooling system testing, passive containment heat removal system testing, and passive residual heat removal system of secondary side testing. The future improvements of Hualong reactor will focus on better economic core design and more reliable safety system. (author)

Nuclear safety infrastructure

International Nuclear Information System (INIS)

Moffitt, R.L.

2010-01-01

The introduction of nuclear power in any country requires the early establishment of a long term nuclear safety infrastructure. This is necessary to ensure that the siting, design, construction, commissioning, operation and dismantling of the nuclear power plant and any other related installations, as well as the long term management of radioactive waste and spent fuel, are conducted in a safe and secure manner. The decision to undertake a nuclear power program is a major commitment requiring strict attention to nuclear safety. This commitment is a responsibility to not only the citizens of the country developing such a program, but also a responsibility to the international community. Nobody can take on this responsibility or make the critical decisions except the host country. It is important to make sure that the decision making process and the development activities are done in as open a manner as possible allowing interested stakeholders the opportunity to review and comment on the actions and plans. It cannot be overemphasized that everyone involved in a program to develop nuclear power carries a responsibility for ensuring safety. While it is clear that the key decisions and activities are the responsibility of the host country, it is also very important to recognize that help is available. The IAEA, OECD-NEA, WANO and other international organizations along with countries with established nuclear power programs are available to provide information and assistance. In particular, the IAEA and OECD-NEA have published several documents regarding the development of a nuclear power program and they have been and continue to support many meetings and seminars regarding the development of nuclear power programs

Nuclear Electric flask design and safety case development during the last ten years

International Nuclear Information System (INIS)

Dougall, I.; Jones, D.K.

1994-01-01

The scope of Nuclear Electric's (NE) requirements for irradiated fuel transport and the relevant safety and regulatory compliance standards are outlined. To illustrate NE's approach to demonstrating package design compliance the basis of the safety case for unbottled Magnox fuel transport in the Mk M2 Magnox flask is described. The considerations which lay behind the development of the Mk A2 AGR Flask are indicated and a description is given of the main design features of this flask. Finally there is a summary of progress in obtaining Type B(M) approvals, based on the 1985 IAEA Regulations, for the requisite range of flask contents. (author)

Approaches to nuclear safety

International Nuclear Information System (INIS)

Watkins, J.D.

1990-01-01

This article examines the factors which affect the safe operation of a nuclear power plant. Some of these are an organizational and individual dedication to safety and excellence in every aspect of plant functions, international cooperation, and advanced reactor design. These are in addition to excellence in management of nuclear plants and the training of key operations personnel. The author feels all of these are necessary to restore public confidence in nuclear power

Main design and safety features of a 200MW nuclear heating reactor

International Nuclear Information System (INIS)

Zheng, Wenxiang; Gao, Zuying; Wang, Dazhong

1992-01-01

Inept has been in charge of the development of a nuclear heating reactor since 1980s, which is one of the national key R and D Programs in China. A 5MWt experimental NCR was completed at Inept in 1989 and has operated successfully for space heating since then. In order to realize the commercialization of the NCR, it has been decided to construct a 200MW demonstration NCR in 1993. A number of advanced features, including natural circulation, integrated arrangement, self-pressurized performance, dual vessel structure, hydraulic control rod drive and passive safety systems, have been incorporated into the NCR-200 to achieve its safety goal and economic viability. This makes the NCR safe, simple, reliable, easy-constructed and maintained. At present, the design work of the NCR-200 have shown that its safety characteristics are excellent. The NCR could play an important role in resolving future energy and environmental problems in China. The paper will mainly cover the key design considerations, main technical features and safety analysis results of the NCR-200

Nuclear safety. Seguranca nuclear

Energy Technology Data Exchange (ETDEWEB)

Aveline, A [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica

1981-01-01

What is nuclear safety Is there any technical way to reduce risks Is it possible to put them at reasonable levels Are there competitiveness and economic reliability to employ the nuclear energy by means of safety technics Looking for answers to these questions the author describes the sources of potential risks to nuclear reactors and tries to apply the answers to the Brazilian Nuclear Programme. (author).

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide (Spanish Edition); Diseno del sistema de refrigeracion del reactor y los sistemas asociados en las centrales nucleares. Guia de seguridad

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-15

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1982), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1987), which are superseded by this new Safety Guide. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1982 and 1987, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2004, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included.

Cost reduction and safety design features of new nuclear power plants in India. Annex 13

International Nuclear Information System (INIS)

Sharma, V.K.

2002-01-01

Indian Nuclear Power Programme is designed to exploit limited reserves of uranium and extensive resource of thorium. Pressurised heavy water reactors are found most suitable and form the main stay of the first stage of the programme. Thorium utilisation is achieved in the second and third stages. Today India has total installed capacity of 2720 MWe of PHWRs which are operating with high plant load factors of over 80%. Rich experience of construction and operation of over 150 reactor years is being utilised in effecting cost reduction and safety improvements. Standardisation and reduction in gestation period by preproject activities, advance procurement and work packages of engineer, procure, construct and commission are some of the techniques being adopted for cost reduction in the new projects. But the cost of safety is rising. Design basis event of double ended guillotine rupture of primary pressure boundary needs a relook based on current knowledge of material behaviour. This event appears improbable. Similarly some of the safety related systems like closed loop cooling water operating at low temperature and pressure, and low usage factors may be designed as per standard codes without invoking special nuclear requirements. The paper will address these issues and highlight the possible areas for cost reduction both in operating and safety systems. Modern construction and project management techniques are being employed. Gestation period of 5 years and cost of less than US $1400 per KWe are the present targets. In Indian environment nuclear power is found to be competitive with thermal power plants at distances of about 800 Kms from the coal mines. (author)

A comparison of the difference of requirements between functional safety and nuclear safety controllers

Energy Technology Data Exchange (ETDEWEB)

Chen, C.K.; Lee, C.L.; Shyu, S.S. [Inst. of Nuclear Energy Research, Taoyuan, Taiwan (China)

2014-07-01

In order to establish self-reliant capabilities of nuclear I&C systems in Taiwan, Taiwan's Nuclear I&C System (TNICS) project had been established by Institute of Nuclear Energy Research (INER). A Triple Modular Redundant (TMR) safety controller (SCS-2000) has been completed and gone through the IEC 61508 Safety Integrity Level 3 (SIL3) certification of Functional Safety for industries. Based on the certification processes, the difference of requirements between Functional Safety and Nuclear Safety controllers in term of hardware and software are addressed in this study. Besides, the measures used to determine and verify the reliability of the safety control system design are presented. (author)

Basis for the safety approach for design and assessment of Generation IV nuclear systems

International Nuclear Information System (INIS)

Fiorini, G.L.; Leahy, T.

2009-01-01

The primary objective of the RSWG is the implementation of a harmonized approach on long-term safety, and to address risk and regulatory issues in development of the next generation of nuclear systems. To this end, the group is proposing safety goals and evaluation methodology applicable for the design and assessment of future systems. The paper resumes the content of the first RSWG report which provides insights for the safety approach and assists the GIF Systems Steering Committee as well as the GIF Experts Group and the GIF Policy Group for the definition of the most adequate safety related Gen IV R and D. The document is also an essential contributor to help identifying the needed supportive crosscut R and D effort (i.e. applicable to all the innovative nuclear technologies). Although the report presents a number of thoughts and recommendations, it really represents only the start of the efforts for the RSWG. (author)

Nuclear Safety: Technical progress review, January--March 1989

Energy Technology Data Exchange (ETDEWEB)

Silver, E. G. [ed.

1989-01-01

This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

Nuclear Safety: Technical progress review, January-March 1988

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1988-01-01

This journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

The design study of the JT-60SU device. No.8. Nuclear shielding and safety design

Energy Technology Data Exchange (ETDEWEB)

Miya, Naoyuki; Kikuchi, Mitsuru; Ushigusa, Kenkichi [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment] [and others

1998-03-01

Results of nuclear shielding design study and safety analysis for the steady-state tokamak device JT-60SU are described. D-T operation (option) for two years is adopted in addition to ten years operation using deuterium. Design work has been done in accordance with general laws for radioisotopes handling in Japan as a guideline of safety evaluation, which is applied to the operation of present JT-60U device. Optimization of the shielding design for the device structure including vacuum vessel has been presented to meet with allowable limits of biological shielding determined in advance. It is shown that JT-60SU can be operated safely in the present JT-60 experimental building. It is planed to use 100g/year of tritium in D-T operation phase. A concept of multiple -barrier system is applied to the facility design to prevent propagation of tritium, in which the torus hall and the tritium removal room provide the tertiary confinement. From the design of atmosphere detritiation system for accidental tritium release, it is shown that tritium concentration level can be reduced to the allowable level after two weeks with reasonable compact size components. Safety assessment related to activation of coolant/air, and atmospheric tritium effluents are discussed. (author)

IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1980-01-01

This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

US nuclear safety. Review and experience

International Nuclear Information System (INIS)

Hanauer, S.H.

1977-01-01

The paper deals with the evolution of reactor safety principles, design bases, regulatory requirements, and experience in the United States. Safety concerns have evolved over the years, from reactivity transients and shut-down systems, to blowdowns and containment, to severe design basis accidents and mitigating systems, to the performance of actual materials, systems and humans. The primary safety concerns of one epoch have been superseded in considerable measure by those of later times. Successive plateaus of technical understanding are achieved by solutions being found to earlier problems. Design studies, research, operating experience and regulatory imperatives all contribute to the increased understanding and thus to the safety improvements adopted and accepted. The improvement of safety with time, and the ability of existing reactors to operate safely in the face of new concerns, has confirmed the correctness and usefulness of the defence-in-depth approach and safety margins used in safety design in the United States of America. A regulatory programme such as the one in the United States justifies its great cost by its important contributions to safety. Yet only the designers, constructors and operators of nuclear power plants can actually achieve public safety. The regulatory programme audits, assesses and spot-checks the actual work. Since neither materials nor human beings are flawless, mistakes will be made; that is why defence-in-depth and safety margins are provided. The regulatory programme should enhance safety by decreasing the frequency of uncorrected mistakes. Maintenance of public safety also requires technical and managerial competence and attention in the organizations responsible for nuclear plants as well as regulatory organizations. (author)

The impact of safety standards updating for design purposes in nuclear power plants licensing

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2009-01-01

The Brazilian experience of nuclear power plants licensing was consolidated by the use of the Brazilian, American, German and IAEA standards. Independently of the set of norms, standards or guides to be used, this set should be in consonance with the state-of-art or the current state of knowledge in science and technology. In the general design criteria of US NRC or German BMI, or in the Brazilian norms (CNEN) or even, in the IAEA standards, this aspect is always emphasized. On the other hand, the international operational experience of nuclear reactors (for example, TMI accident) also contributes to the updating of norms and standards. The use of new technologies (for example, digital technology) impels the norms and standards to adopt new design criteria related to the new technological context. Moreover, we must add the particular vision that each country can have concerning to specific topics in nuclear safety. This work discusses how the norms, standards and guides used in the nuclear licensing are being reviewed to cope with the requirement of the state-of-art. In order to accomplish this aim we took some general design criteria to exemplify how they are fulfilled, mainly those related directly with the protection of the defense-in-depth barriers: primary coolant system, containment vessel and containment systems, including external events and severe accidents. In complement to the deterministic analysis, it is also discussed the design criteria related to the human factors engineering and probabilistic safety analysis, including severe accidents aspects. (author)

Nuclear Safety: Volume 29, No. 3: Technical progress review

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1988-07-01

Nuclear Safety is a review journal that covers significant development in the field of nuclear safety. Its scope included the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated. Individual papers have been cataloged separately.

Nuclear safety in France

International Nuclear Information System (INIS)

Laverie, M.

1981-02-01

The principles and rules governing the safety of nuclear installations are defined as from three fundamental principles and three practical rules as follows: First principle: the operator is responsible and of the highest order. Second principle: the public authorities exercise their control responsibility with respect to the design, construction and running of the installations. Third principle: nuclear safety, this is to accept that man and his technique are not infallible and that one must be prepared to control the unpredictable. First rule: the installations must include several 'lines of defence' in succession and to the extent where this is possible these must be independent of each other. Second rule: procedures are required and supervised by the Government Departments. Third rule: nuclear safety requires that any incident or anomaly must undergo an analysis in depth and is also based on a standing 'clinical' examination of the installations. The definition is given as to how the public authorities exercise their intervention: terms and conditions of the intervention by the safety authorities, authorization procedures, surveillance of the installations, general technical regulations. Two specific subjects are presented in the addendum, (a) the choice of nuclear power station sites in France and (b) the storage of radioactive wastes [fr

Report on nuclear safety on the operation of nuclear facilities in 1989

International Nuclear Information System (INIS)

Gregoric, M.; Levstek, M. F.; Horvat, D.; Kocuvan, M.; Cresnar, N.

1990-01-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1989.

Report on nuclear safety on the operation of nuclear facilities in 1990

International Nuclear Information System (INIS)

Gregoric, M.; Grlicarev, I.; Horvat, D.; Levstek, M.F.; Lukacs, E.; Kocuvan, M.; Skraban, A.

1991-06-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1990.

National report of Brazil. Nuclear Safety Convention

International Nuclear Information System (INIS)

1998-09-01

This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Implementing national nuclear safety plan at the preliminary stage of nuclear power project development

International Nuclear Information System (INIS)

Xue Yabin; Cui Shaozhang; Pan Fengguo; Zhang Lizhen; Shi Yonggang

2014-01-01

This study discusses the importance of nuclear power project design and engineering methods at the preliminary stage of its development on nuclear power plant's operational safety from the professional view. Specifically, we share our understanding of national nuclear safety plan's requirement on new reactor accident probability, technology, site selection, as well as building and improving nuclear safety culture and strengthening public participation, with a focus on plan's implications on preliminary stage of nuclear power project development. Last, we introduce China Huaneng Group's work on nuclear power project preliminary development and the experience accumulated during the process. By analyzing the siting philosophy of nuclear power plant and the necessity of building nuclear safety culture at the preliminary stage of nuclear power project development, this study explicates how to fully implement the nuclear safety plan's requirements at the preliminary stage of nuclear power project development. (authors)

Safety guide on fire protection in nuclear power plants

International Nuclear Information System (INIS)

1976-01-01

The purpose of the Safety Guide is to give specific design and operational guidance for protection from fire and explosion in nuclear power plants, based on the general guidance given in the relevant sections of the 'Safety Code of Practice - Design' and the 'Safety Code of Practice - Operation' of the International Atomic Energy Agency. The guide will confine itself to fire protection of safety systems and items important to safety, leaving the non-safety matters of fire protection in nuclear power plants to be decided upon the basis of the various available national and international practices and regulations. (HP) [de

Panel 1: Safety design criteria

International Nuclear Information System (INIS)

Yllera, Javier

2013-01-01

There is general consensus in the nuclear community, and more after the Fukushima accident, that the deployment of nuclear energy has to be done at the highest levels of nuclear safety and that safety cannot be compromised by other factors. It is well understood that reactors that are being licensed and the new generations of reactors that will be constructed in the future will need to reach higher safety levels than the existing ones. Several countries and international organizations or international groups are launching initiatives to harmonise safety goals, safety requirements, safety objectives, regulations, criteria or safety reference levels. There are differences in the meanings of these terms and the working approaches, but the overall purpose is the same: to specify how new plants can be safer. In this context, the IAEA has an statutory function for developing international nuclear safety standards. The IAEA safety standards are per se not mandatory for IAEA Member States. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA’s standards for use in their national regulations in different ways. The IAEA Safety Standards represent international consensus on what must constitute a high level of safety for nuclear installations. In the area of NPP design, IAEA safety standards that are published are intended to apply primarily to new plants. It might not be practicable to apply all the requirements to plants that are already in operation. In addition, the focus is primarily on plants with water cooled reactors

National Nuclear Safety Report 2001. Convention on Nuclear Safety

International Nuclear Information System (INIS)

2001-01-01

The First National Nuclear Safety Report was presented at the first review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This second National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the first review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex 1. In general, the information contained in this Report has been updated since March 31, 1998 to March 31, 2001. Those aspects that remain unchanged were not addressed in this second report with the objective of avoiding repetitions and in order to carry out a detailed analysis considering article by article. As a result of the above mentioned detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention

National nuclear safety report 2004. Convention on nuclear safety

International Nuclear Information System (INIS)

2004-01-01

The second National Nuclear Safety Report was presented at the second review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This third National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the second review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex I and those belonging to the second review meeting are included as Annex II. In general, the information contained in this Report has been updated since March 31, 2001 to April 30, 2004. Those aspects that remain unchanged were not addressed in this third report. As a result of the detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention. The questions and answers originated at the Second Review Meeting are included as Annex III

Safety program considerations for space nuclear reactor systems

International Nuclear Information System (INIS)

Cropp, L.O.

1984-08-01

This report discusses the necessity for in-depth safety program planning for space nuclear reactor systems. The objectives of the safety program and a proposed task structure is presented for meeting those objectives. A proposed working relationship between the design and independent safety groups is suggested. Examples of safety-related design philosophies are given

Nuclear safety considerations in the conceptual design of a fast reactor for space electric power and propulsion

Science.gov (United States)

Hsieh, T.-M.; Koenig, D. R.

1977-01-01

Some nuclear safety aspects of a 3.2 mWt heat pipe cooled fast reactor with out-of-core thermionic converters are discussed. Safety related characteristics of the design including a thin layer of B4C surrounding the core, the use of heat pipes and BeO reflector assembly, the elimination of fuel element bowing, etc., are highlighted. Potential supercriticality hazards and countermeasures are considered. Impacts of some safety guidelines of space transportation system are also briefly discussed, since the currently developing space shuttle would be used as the primary launch vehicle for the nuclear electric propulsion spacecraft.

Independent assessment for new nuclear reactor safety

Directory of Open Access Journals (Sweden)

D'Auria Francesco

2017-01-01

Full Text Available A rigorous framework for safety assessment is established in all countries where nuclear technology is used for the production of electricity. On the one side, industry, i.e. reactor designers, vendors and utilities perform safety analysis and demonstrate consistency between results of safety analyses and requirements. On the other side, regulatory authorities perform independent assessment of safety and confirm the acceptability of safety of individual reactor units. The process of comparing results from analyses by reactor utilities and regulators is very complex. The process is also highly dependent upon mandatory approaches pursued for the analysis and from very many details which required the knowledge of sensitive proprietary data (e.g. spacer designs. Furthermore, all data available for the design, construction and operation of reactors produced by the nuclear industry are available to regulators. Two areas for improving the process of safety assessment for individual Nuclear Power Plant Units are identified: New details introduced by industry are not always and systematically requested by regulators for the independent assessment; New analytical techniques and capabilities are not necessarily used in the analyses by regulators (and by the industry. The established concept of independent assessment constitutes the way for improving the process of safety assessment. This is possible, or is largely facilitated, by the recent availability of the so-called Best Estimate Plus Uncertainty approach.

Independent assessment for new nuclear reactor safety

International Nuclear Information System (INIS)

D'Auria, F.; Glaeser, H.; Debrecin, N.

2017-01-01

A rigorous framework for safety assessment is established in all countries where nuclear technology is used for the production of electricity. On one side, industry, i.e. reactor designers, vendors and utilities perform safety analysis and demonstrate consistency between results of safety analyses and requirements. On the other side, regulatory authorities perform independent assessment of safety and confirm the acceptability of safety of individual reactor units. The process of comparing results from analyses by reactor utilities and regulators is very complex. The process is also highly dependent upon mandatory approaches pursued for the analysis and from very many details which required the knowledge of sensitive proprietary data (e.g. spacer designs). Furthermore, all data available for the design, construction and operation of reactors produced by the nuclear industry are available to regulators. Two areas for improving the process of safety assessment for individual Nuclear Power Plant Units are identified: New details introduced by industry are not always and systematically requested by regulators for the independent assessment; New analytical techniques and capabilities are not necessarily used in the analyses by regulators (and by the industry). The established concept of independent assessment constitutes the way for improving the process of safety assessment. This is possible, or is largely facilitated, by the recent availability of the so-called Best Estimate Plus Uncertainty (BEPU) approach. (authors)

Safety of nuclear installations in Slovakia

International Nuclear Information System (INIS)

1998-01-01

In this part next aspects are described: (1) Site selection (Legislation related to site selection; Meeting criteria at Bohunice and Mochovce sites; International agreements); (2) Design preparation and construction (Designing and construction-relevant legislation; Nuclear installation project preparation of nuclear installation at Mochovce site); (3) Operation (Operator licensing procedure; Operation limits and conditions; Maintenance testing and control documentation for management and operation; Technical support of operation; Analysis of events at nuclear installations and Radioactive waste production); (4) Planned safety upgrading activities at nuclear installations

Lightning protection design of nuclear power plants. KTA safety code, version 6/99

International Nuclear Information System (INIS)

1999-06-01

This KTA safety code does not cover calculation methods for determination of lightning-induced voltage inputs to control room systems within the reactor building, as the literature presents a variety of applicable methods, which however cannot be directly applied to any power plant, due to the great diversity of geometries of the electrical systems and control room systems in nuclear power plants. Compliance with the design requirements of this safety code for shielding of buildings, and installation and shielding of cables, can be considered to offer the appropriate protection. (orig./CB) [de

Nuclear health and safety

International Nuclear Information System (INIS)

1991-08-01

This paper is a review of environmental and safety programs at facilities in the Naval Reactors Program which shows no basis for allegations that unsafe conditions exist there or that the environment is being harmed by activities conducted there. The prototype reactor design provides safety measures that are consistent with commercial nuclear power plants. Minor incidents affecting safety and the environment have occurred, however, and dents affecting safety and the environment have occurred, however, and as with other nuclear facilities, past activities have caused environmental problems that require ongoing monitoring and vigilance. While the program has historically been exempt from most oversight, some federal and state environmental oversight agencies have recently been permitted access to Naval Reactors facilities for oversight purposes. The program voluntarily cooperates with the Nuclear Regulatory Commission regarding reactor modifications, safety improvements, and component reliability. In addition, the program and its contractors have established an extensive internal oversight program that is geared toward reporting the slightest deviations from requirements or procedures. Given the program's classification policies and requirements, it does not appear that the program routinely overclassifies information to prevent its release to the public or to avoid embarrassment. However, GAO did not some instances in which documents were improperly classified

Safety philosophy and design principles for systems and components of nuclear power plant: external event

International Nuclear Information System (INIS)

Lopes, J.P.G.

1986-01-01

In nuclear power plants, some systems and components are designed to withstand external impacts. Such systems and components are those which have to perform their functions even during and after the occurrences of an earthquake, for example, fulfilling the safety objectives and avoiding the release of radioactive material to the environment. The aim of this report is to introduce the safety philosophy and design principles for systems/components to perform their functions during and after the occurrence of an earthquake, as applied by NUCLEN for Angra 2 and 3. (Author) [pt

Enhancing operational nuclear safety

International Nuclear Information System (INIS)

Sengoku, Katsuhisa

2008-01-01

Since Chernobyl, the dictum A n accident anywhere is an accident everywhere i s a globally shared perception. The paper presents challenges to the international nuclear community: globalization, sustainable and dynamic development, secure, safe and clean energy supply, nuclear r enaissance , public concern for nuclear safety, nuclear security, and technology and management. Strong national safety infrastructures and international cooperation are required to maintain a high level of nuclear safety and security worldwide. There is an increasing number of countries thinking of going nuclear: Morocco, Indonesia, Iran, Poland, Turkey, Bangladesh, Egypt, Vietnam, Chile, Nigeria, Malaysia, Thailand, Uruguay, Tunisia, Algeria. Another serious incident will jeopardize the prospect of nuclear renaissance. Safety and security are preconditions for countries newly introducing NPP as well as for those with mature nuclear programmes. The Global Nuclear Safety Regime (GNSR) is referred to as the institutional, legal and technical framework to achieve worldwide implementation of the safety of nuclear installations. At the top of the framework is the Convention on Nuclear Safety which covers the nuclear power plants. The convention has 56 contracting parties which meet triennially where national reports are presented and subject to the review of peers. The International Atomic Energy Agency (IAEA) undertakes a programme to foster the GNSR through the establishment of IAEA safety standards and related publications. The programme provides for the application of standards for the (1) safety of nuclear installations, (2) safety of radioactive sources, (3) safe transport of radioactive material and (4) management of radioactive waste. It also provides for the security of nuclear installations, nuclear material and radioactive material. The safety standards hierarchy is as follows: safety fundamental, safety requirements and safety guides. The safety fundamentals are the bases for IAEA

Nuclear power safety

International Nuclear Information System (INIS)

1988-01-01

The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

Innovation in the Safety of nuclear systems: fundamental aspects

International Nuclear Information System (INIS)

Herranz, L. E.

2009-01-01

Safety commercial nuclear reactors has been an indispensable condition for future enlargement of power generation based on nuclear technology. Its fundamental principle, defence in depth, far from being outdated, is still adopted as a key foundation in the advanced nuclear system (generations III and IV). Nevertheless, the cumulative experience gained in the operation and maintenance of nuclear reactors, the development of methodologies like the probabilistic safety analysis, the use of passive safety systems and, even, the inherent characteristics of some new design (which exclude accident scenarios), allow estimating safety figures of merit even more outstanding that those achieved in the second generation of nuclear reactors. This safety innovation of upcoming nuclear reactors has entailed a huge investigation program (generation III) that will be focused on optimizing and demonstrating the postulated safety of future nuclear systems (Generation IV). (Author)

Safety management in nuclear technology. Proceedings

International Nuclear Information System (INIS)

2008-01-01

At the symposium of TueV Sued AG (Munich, Federal Republic of Germany) held in Munich on 28 and 29 October 2008, the following lectures were held: (1) Fundamental requirements of the management system in nuclear technology - Experiences from the international developments at IAEA and WENRA (M. Herttrich); (2) Information from a comparison of requirements of safety management systems (B. Kallenbach-Herbert); (3) Requirements of a modern management system in German nuclear power plants from the view of nuclear safety (D. Majer); (4) Requirements on safety management in module 8 of the regulations project (M. Maqua); (5) Requirements on the management system in nuclear power plants according to GRS-229 and developments at the KTA 1402 ''Integrated management system for safe operation of nuclear power plants (in progress)'' (C. Verstegen); (6) Experiences from the development and implementation of safety management systems in connection with the works management of a nuclear power plant (K. Ramler); (7) Design of a safety management system of a nuclear power plant in consideration of existing management systems (U. Naumann); (8) Experiences in the utilization and evaluation of a safety management system (J. Ritter); (9) Aspects of leadership of safety management systems (S. Seitz); (10) Management of safety or safety management system? Prevailing or administration? (A. Frischknecht); (11) Change management - strategies for successful transfer of new projects: How can I motivate co-workers for a further development of the safety management system? (U. Schnabel); (12) Requirements concerning indicators in integrated management systems and safety management systems (J. Stiller); (13) Integration of proactive and reactive indicators in the safety management system (B. Fahlbruch); (14) What do indicators show? About the use of indicators by regulatory authorities (A. Kern); (15) Safety management and radiation protection in nuclear technology (K. Grantner); (16) Any more

Safety of nuclear power reactors

International Nuclear Information System (INIS)

MacPherson, H.G.

1982-01-01

Safety is the major public issue to be resolved or accommodated if nuclear power is to have a future. Probabilistic Risk Analysis (PRA) of accidental releases of low-level radiation, the spread and activity of radiation in populated areas, and the impacts on public health from exposure evolved from the earlier Rasmussen Reactor Safety Study. Applications of the PRA technique have identified design peculiarities in specific reactors, thus increasing reactor safety and establishing a quide for evaluating reactor regulations. The Nuclear Regulatory Commission and reactor vendors must share with utilities the responsibility for reactor safety in the US and for providing reasonable assurance to the public. This entails persuasive public education and information that with safety a top priority, changes now being made in light water reactor hardware and operations will be adequate. 17 references, 2 figures, 2 tables

Integrating Safeguards and Security with Safety into Design

International Nuclear Information System (INIS)

Bean, Robert S.; Hockert, John W.; Hebditch, David J.

2009-01-01

There is a need to minimize security risks, proliferation hazards, and safety risks in the design of new nuclear facilities in a global environment of nuclear power expansion, while improving the synergy of major design features and raising operational efficiency. In 2008, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) launched the Next Generation Safeguards Initiative (NGSI) covering many safeguards areas. One of these, launched by NNSA with support of the DOE Office of Nuclear Energy, was a multi-laboratory project, led by the Idaho National Laboratory (INL), to develop safeguards by design. The proposed Safeguards-by-Design (SBD) process has been developed as a structured approach to ensure the timely, efficient, and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical security, and safety objectives into the overall design process for the nuclear facility lifecycle. A graded, iterative process was developed to integrate these areas throughout the project phases. It identified activities, deliverables, interfaces, and hold points covering both domestic regulatory requirements and international safeguards using the DOE regulatory environment as exemplar to provide a framework and guidance for project management and integration of safety with security during design. Further work, reported in this paper, created a generalized SBD process which could also be employed within the licensed nuclear industry and internationally for design of new facilities. Several tools for integrating safeguards, safety, and security into design are discussed here. SBD appears complementary to the EFCOG TROSSI process for security and safety integration created in 2006, which focuses on standardized upgrades to enable existing DOE facilities to meet a more severe design basis threat. A collaborative approach is suggested.

Safety policy for nuclear power development

International Nuclear Information System (INIS)

Uchida, Hideo

1987-01-01

The report discusses various aspects of the safety policy for nuclear power development in Japan. Nuclear power development over three decades in Japan has led to operating performance which is highly safe and reliable. This has been appreciated internationally. Discussed here is the Japanese basic safety policy for nuclear power development that is essential first to design, manufacture and construction using high technology. The current careful quality assurance and reliable operation management by skilled operators are relied upon, on the basis of the fact that measures to prevent abnormal events are given first priority rather than those to mitigate consequences of abnormal events or accidents. Lessons learned from accidents and failures within or outside Japan such as the TMI accident and Chernobyl accident have been reflected in the improvement of safety through careful and thorough examinations of them. For further improvement in nuclear safety, deliberate studies and investigations on severe accidents and probabilistic safety assessment are considered to be important. Such efforts are currently being promoted. For this purpose, it is important to advance international cooperation and continue technical exchanges, based on operation experience in nuclear power stations in Japan. (Nogami, K.)

Nuclear Fuel Safety Criteria Technical Review - Second edition

International Nuclear Information System (INIS)

Beck, Winfried; Blanpain, Patrick; Fuketa, Toyoshi; Gorzel, Andreas; Hozer, Zoltan; Kamimura, Katsuichiro; Koo, Yang-Hyun; Maertens, Dietmar; Nechaeva, Olga; Petit, Marc; Rehacek, Radomir; Rey-Gayo, Jose Maria; Sairanen, Risto; Sonnenburg, Heinz-Guenther; Valach, Mojmir; Waeckel, Nicolas; Yueh, Ken; Zhang, Jinzhao; Voglewede, John

2012-01-01

Most of the current nuclear fuel safety criteria were established during the 1960's and early 1970's. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits. In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities)

Safety Design Approach for the Development of Safety Requirements for Design of Commercial HTGR

International Nuclear Information System (INIS)

Ohashi, Hirofumi; Sato, Hiroyuki; Nakagawa, Shigeaki; Tachibana, Yukio; Nishihara, Tetsuo; Yan, Xing; Sakaba, Nariaki; Kunitomi, Kazuhiko

2014-01-01

The research committee on “Safety requirements for HTGR design” was established in 2013 under the Atomic Energy Society of Japan to develop the draft safety requirements for the design of commercial High Temperature Gas-cooled Reactors (HTGRs), which incorporate the HTGR safety features demonstrated using the High Temperature Engineering Test Reactor (HTTR), lessons learned from the accident of Fukushima Daiichi Nuclear Power Station and requirements for the integration of the hydrogen production plants. The safety design approach for the commercial HTGRs which is a basement of the safety requirements is determined prior to the development of the safety requirements. The safety design approaches for the commercial HTGRs are to confine the radioactive materials within the coated fuel particles not only during normal operation but also during accident conditions, and the integrity of the coated fuel particles and other requiring physical barriers are protected by the inherent and passive safety features. This paper describes the main topics of the research committee, the safety design approaches and the safety functions of the commercial HTGRs determined in the research committee. (author)

Improving the rationality of nuclear safety regulations

International Nuclear Information System (INIS)

Choi, Byung Sun; Choi, Y. G.; Mun, G. H.

2005-03-01

This study focuses on human nature and institutions around the risk management in Korean Nuclear Installations. Nuclear safety regulatory system in Korea has had a tendency to overvalue the technical or engineering areas. But just like other risk management system, the knowledge of social science is also required to design more valid safety regulatory system. As a result of analysis, this study suggest that performance regulation need to be introduced to current nuclear safety regulation system. In this advanced regulatory system, each nuclear generation unit have to be evaluated by performance of its own regulatory implementation and would be treated differently by the performance. Additionally, self-regulation could be very effective was to guarantee nuclear safety. Because KHNP could be judged to have an considerable capabilities to manage its own regulatory procedures. To make self-regulatory system established successfully, it is also important to arrange the appropriate incentive and compensate structures

Aseismatic design and safety of nuclear power generation facilities. On aseismatic capability of commercial nuclear power stations

International Nuclear Information System (INIS)

Kato, Muneaki

1995-01-01

In view of the great Hanshin earthquake, the aseismatic safety of the important facilities in nuclear power stations is ensured by the location direct on base rocks, the design with the earthquake force at least three times as large as that in the building standard, and the consideration of the earthquakes due to active faults as design earthquake. The basic policy of the aseismatic design of nuclear power stations is described. The determination of the earthquake motions due to strongest earthquake and utmost limit earthquake for design, the survey of the geological features and ground of the sites and so on are explained. In the aseismatic design of buildings and structures, structural planning, the modeling for the aseismatic analysis of buildings, the analysis of time historical response and so on are carried out. In the aseismatic design of equipment and piping systems, the planning of aseismatic support structures, the aseismatic design and the analysis of time historical response, the spectral modal analysis for other systems such as multiple material point system and so on are described. The tests and researches related to the aseismatic design are reported. (K.I.)

Meteorological events in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide provides recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. It is of interest to safety assessors and regulators involved in the licensing process as well as to designers of nuclear power plants. This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It supplements the IAEA Safety Requirements publication on Site Evaluation for Nuclear Facilities which is to supersede the Code on the Safety of Nuclear Power Plants: Siting, Safety Series No. 50-C-S (Rev. 1), IAEA, Vienna (1988). The present Safety Guide supersedes two earlier Safety Guides: Safety Series No. 50-SG-S11A (1981) on Extreme Meteorological Events in Nuclear Power Plant Siting, Excluding Tropical Cyclones and Safety Series No. 50-SG-S11B (1984) on Design Basis Tropical Cyclone for Nuclear Power Plants. The purpose of this Safety Guide is to provide recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. This Safety Guide provides interpretation of the Safety Requirements publication on Site Evaluation for Nuclear Facilities and guidance on how to fulfil these requirements. It is aimed at safety assessors or regulators involved in the licensing process as well as designers of nuclear power plants, and provides them with guidance on the methods and procedures for analyses that support the assessment of the hazards associated with extreme and rare meteorological events. This Safety Guide discusses the extreme values of meteorological variables and rare meteorological phenomena, as well as their rates of occurrence, according to the following definitions: (a) Extreme values of meteorological variables such as air temperature and wind speed characterize the meteorological or climatological environment. And (b) Rare meteorological phenomena

Revision of nuclear power plants safety systems' routine testing assigned periodicity during the design extension period

International Nuclear Information System (INIS)

Skalozubov, V.I.; Kozlov, Yi.L.; Chulkyin, O.O.

2017-01-01

When nuclear power plants safety systems thermal equipment operation extending, a necessary requirement shall rely on revising the scheduled equipment tests frequency to optimize those tests schedule taking into account the equipment remained lifespan. On the one hand, there exists a need for tests frequency increase to detect ''hidden'' failures, and on the another, frequent tests cause a premature wear of the equipment. Proposed is an original method for optimizing the frequency of NPPs safety systems thermal engineering equipment testing. Essential in the proposed method is the optimization criterion chosen: index of security system failure probability non-exceedance during the beyond-design operating period as referred to the failure probability expected considering the equipment residual resource during the design operating period. The developed method implementation when applied to NPPs safety systems operated beyond the design service life at nuclear power plants with WWER-1000 series reactors, allowed to establish that the optimal tests frequency makes half the designed one when the equipment service life is extended by five years and three times less that the designed frequency when subject lifespan extended by 10 years.

Licensee responsibility for nuclear power plant safety

International Nuclear Information System (INIS)

Schneider, Horst

2010-01-01

Simple sentences easy to grasp are desirable in regulations and bans. However, in a legal system, their meaning must be unambiguous. Article 6, Paragraph 1 of the EURATOM Directive on a community framework for the nuclear safety of nuclear facilities of June 2009 states that 'responsibility for the nuclear safety of a nuclear facility is incumbent primarily on the licensee.' The draft 'Safety Criteria for Nuclear Power Plants, Revision D, April 2009' of the German Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU) (A Module 1, 'Safety Criteria for Nuclear Power Plants: Basic Safety Criteria' / '0 Principles' Paragraph 2) reads: 'Responsibility for ensuring safety rests with the licensee. He shall give priority to compliance with the safety goal over the achievement of other operational objectives.' In addition, the existing rules and regulations, whose rank is equivalent to that of international regulations, assign priority to the safety goal to be pursued by the licensee over all other objectives of the company. The operator's responsibility for nuclear safety can be required and achieved only on the basis of permits granted, which must meet legal requirements. The operator's proximity to plant operation is the reason for his 'primary responsibility.' Consequently, verbatim incorporation of Article 6, Paragraph 1 of the EURATOM Directive would only be a superscript added to existing obligations of the operator - inclusive of a safety culture designed as an incentive to further 'the spirit of safety-related actions' - without any new legal contents and consequences. In the reasons of the regulation, this would have to be clarified in addition to the cryptic wording of 'responsibility.. primarily,' at the same time expressing that operators and authorities work together in a spirit of openness and trust. (orig.)

Nuclear power plants: a unique challenge to fire safety

International Nuclear Information System (INIS)

Nowlen, S.P.

1992-01-01

The evaluation of fire safety in a nuclear power plant must include the consideration of the impact of a fire on the operability of plant safety equipment and systems. This issue is not typical of the life safety and property protection issues which dominate traditional fire safety concerns. This paper provides a general discussion of the issue of nuclear power plant fire safety as it currently exists in the USA. Included is a discussion of the past history of nuclear power plant fire events, the development of nuclear industry specific fire safety guidelines, the adverse experience associated with the inadvertent operation of fire suppression systems, and the anticipated direction of fire safety requirements for future reactor designs in the USA. (Author)

IR-360 nuclear power plant safety functions and component classification

International Nuclear Information System (INIS)

Yousefpour, F.; Shokri, F.; Soltani, H.

2010-01-01

The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.

IR-360 nuclear power plant safety functions and component classification

Energy Technology Data Exchange (ETDEWEB)

Yousefpour, F., E-mail: fyousefpour@snira.co [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of); Shokri, F.; Soltani, H. [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of)

2010-10-15

The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.

Canadian approach to nuclear power safety

International Nuclear Information System (INIS)

Atchison, R.J.; Boyd, F.C.; Domaratzki, Z.

1983-01-01

The development of the Canadian nuclear power safety philosophy and practice is traced from its early roots at the Chalk River Nuclear Laboratories to the licensing of the current generation of power reactors. Basic to the philosophy is a recognition that the licensee is primarily responsible for achieving a high standard safety. As a consequence, regulatory requirements have emphasized numerical safety goals and objectives and minimized specific design or operating rules. In this article the Canadian licensing process is described with a discussion of some of the difficulties encountered. Examples of specific licensing considerations for each phase of a project are included

Philosophy and safety requirements for land-based nuclear installations

International Nuclear Information System (INIS)

Kellermann, Otto

1978-01-01

The main ideas of safety philosophy for land-based nuclear installations are presented together with their background of protection goals. Today's requirements for design and quality assurance are deductively shown. Finally a proposition is made for a new balancing of safety philosophy according to the high safety level that nuclear installations have reached

Safety aspects of the desalination of sea water using nuclear energy

International Nuclear Information System (INIS)

Carnino, A.; Gasparini, N.

2001-01-01

The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. Some specific characteristics of desalination plants such as siting and coupling require particular consideration from a safety point of view, and further safety studies will be needed when the type and size of the reactor are determined. The current safety approach, based on the defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

Civil design aspects for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Bhalerao, Sandip; Subramanyam, P.; Sharma, Sudin; Bhargava, Kapilesh; Agarwal, Kailash; Rao, D.A.S.; Roy, Amitava; Basu, S.

2015-01-01

The civil design requirements of safety related nuclear structures are much more stringent and conservative as compared to that for conventional and industrial structures. Due to the importance of safety and desired reliability in the civil design of nuclear structures, International Atomic Energy Agency (IAEA) and Atomic Energy Regulatory Board (AERB) have provided various safety guides for their safe design. There has been advancement in theoretical and experimental knowledge pertaining to the design, construction, installation, maintenance, testing and inspection of structures, systems, and components (SSCs) of nuclear power plants (NPPs), such that, their quality and reliability is commensurate with safety functions. The well established procedures are available in the form of different codes, standards, guidelines and well proven research work for NPPs. However, such procedures are somewhat limited in nature for design of civil structures in nuclear fuel cycle facilities (NFCF), and till date no separate codes or standards have been published by regulatory authorities in India that cover civil design aspects for NFCF. Hence, design of civil structures of NFCF in India is performed by using different national and international standards, and the recommendations provided by BARC Safety Council (BSC). Present paper focuses civil design aspects for NFCF in India. (author)

Economic consideration of nuclear safety and cost benefit analysis in nuclear safety regulation

International Nuclear Information System (INIS)

Choi, Y. S.; Choi, K. S.; Choi, K. W.; Song, I. J.; Park, D. K.

2001-01-01

For the optimization of nuclear safety regulation, understanding of economic aspects of it becomes increasingly important together with the technical approach used so far to secure nuclear safety. Relevant economic theories on private and public goods were reviewed to re-illuminate nuclear safety from the economic perspective. The characteristics of nuclear safety as a public good was reviewed and discussed in comparison with the car safety as a private safety good. It was shown that the change of social welfare resulted from the policy change induced can be calculated by the summation of compensating variation(CV) of individuals. It was shown that the value of nuclear safety could be determined in monetary term by this approach. The theoretical background and history of cost benefit analysis of nuclear safety regulation were presented and topics for future study were suggested

Safety related requirements on future nuclear power plants

International Nuclear Information System (INIS)

Niehaus, F.

1991-01-01

Nuclear power has the potential to significantly contribute to the future energy supply. However, this requires continuous improvements in nuclear safety. Technological advancements and implementation of safety culture will achieve a safety level for future reactors of the present generation of a probability of core-melt of less than 10 -5 per year, and less than 10 -6 per year for large releases of radioactive materials. There are older reactors which do not comply with present safety thinking. The paper reviews findings of a recent design review of WWER 440/230 plants. Advanced evolutionary designs might be capable of reducing the probability of significant off-site releases to less than 10 -7 per year. For such reactors there are inherent limitations to increase safety further due to the human element, complexity of design and capability of the containment function. Therefore, revolutionary designs are being explored with the aim of eliminating the potential for off-site releases. In this context it seems to be advisable to explore concepts where the ultimate safety barrier is the fuel itself. (orig.) [de

Regulatory control of nuclear safety in Finland. Annual report 2008

International Nuclear Information System (INIS)

Kainulainen, E.

2009-06-01

This report covers the regulatory control of nuclear safety in 2008, including the design, construction and operation of nuclear facilities, as well as nuclear waste management and nuclear materials. The control of nuclear facilities and nuclear waste management, as well as nuclear non-proliferation, concern two STUK departments: Nuclear Reactor Regulation and Nuclear Waste and Material Regulation. It constitutes the report on regulatory control in the field of nuclear energy, which the Radiation and Nuclear Safety Authority (STUK) is required to submit to the Ministry of Employment and the Economy pursuant to section 121 of the Finnish Nuclear Energy Decree. The first parts of the report explain the basics of the nuclear safety regulation included as part of STUK's responsibilities, as well as the objectives of the operations, and briefly introduce the objects of regulation. The chapter concerning the development and implementation of legislation and regulations describes changes in nuclear legislation, as well as the progress of STUK's YVL Guide revision. The chapter also includes a summary of the application of the updated YVL Guides to nuclear facilities. The section concerning the regulation of nuclear facilities contains a complete safety assessment of the nuclear facilities currently in operation or under construction. For the nuclear facilities in operation, the section describes plant operation, events during operation, annual maintenance, development of the plants and their safety, and observations made during monitoring. Data and observations gained during regulatory activities are reviewed with a focus on ensuring the safety functions of nuclear facilities and the integrity of structures and components. The report also includes a description of the oversight of the operations and quality management of organisations, oversight of operational experience feedback activities, and the results of these oversight activities. The radiation safety of nuclear

The safety of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

Do nuclear power plants present an unjustifiable risk Can there be confidence in their safety The Uranium Institute invited a group of senior safety experts from eight different Western countries operating different types of reactors to provide an authoritative explanation for non-specialists of the basic principles of reactor safety, their application and their implications. The report presents the group's opinion on the level of safety achieved in the Western nuclear power plants with which the authors are directly familiar. Although many of the points made may well also be true for non-Western reactors, the report does not cover them except where specifically stated. It does describe and discuss the causes of the Chernobyl disaster. It does not compare nuclear power with other fuels, nor does it deal with its benefits, since however great the benefits from the peaceful use of nuclear power, and its own advantages over other fuels, they could not compensate for lack of safety. The conclusion reached is that the risk associated with electricity production at nuclear power plants can be kept very low. Proper use of the extensive knowledge available today can guarantee operation of nuclear power plants at very high safety levels, carrying very low risks, both to health and of contamination of the environment: risks that are continually lowered by upgrading existing plants and their operation, and by the design of future power plants. (author).

The European community and nuclear safety

International Nuclear Information System (INIS)

Brinkhorst, L.J.

1992-01-01

Full text: Since the inception of the EURATOM Treaty (1957) the use of nuclear power has made an enormous progress. The nuclear sector has become a very important component of the production of energy. Prisoner of its success further development of the use of nuclear energy is confronted with the challenge of ensuring its integration within the framework of modern environment protection concepts. The link between the radiation protection objective and the responsibilities of the State's Authorities in the control of the design and operation of nuclear industrial facilities has become evident. On the other hand, the evolution in the perception of the transfrontier character of the nuclear risk by the population and. the drive for the political integration of Europe have led the Community Member States to an increasing concentration between their nuclear policy-making organs and in particular between their Nuclear Safety Authorities It is quite natural that the Community institutions, the Council of Ministers and the Commission and more recently the European Parliament have become active hosts and catalysts of the concentration of the Member States on the nuclear safety objectives which are at the source of the protection of the population and of the environment. The joint efforts of the Member States and the Commission have led to a reinforcement of the process of harmonisation of safety requirements for nuclear installations at Community level. A parallel concentration effort has been done by Community Member States concerning the back-end of the fuel cycle, in particular radioactive waste management. The European Community meets the conditions to become a key driving force for nuclear safety progress beyond its region because of the advanced stage of nuclear safety in the Community which includes the flexibility and completeness of its fuel cycle and the long experience of Community institutions in the promotion of harmonisation of safety objectives, criteria and

Feasibility study on floating nuclear power plant (2). Safety design study of FNPP. Contract research

Energy Technology Data Exchange (ETDEWEB)

Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Masao [Niigata Engineering Co. Ltd., Tokyo (Japan); Nakazawa, Toshio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Sato, Kazuo [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

2001-02-01

In the previous report of 'Conceptual Design Study of FNPP (Floating Nuclear Power Plant)', a design study on a concept for FNPP, which is sited off the sea coast on the open sea with water depth of 20m and it is moored on protected sea by the breakwater was conducted and the floating platform guarded by the breakwater was found to be stable enough to install the nuclear power plant from analysis simulating the movement of the platform due to sea wave or wind. In this report, studies on a basic safety design concept of the FNPP, setting natural phenomena for design condition, required safety functions and a review on dynamic analysis of the large floating structure are presented. The studies revealed that the stability of the floating platform is an essential issue for the FNPP soundness, and the design base natural phenomena such as S1 and S2-class storm including S1 and S2-class earthquake should be considered in evaluation of the stability of the floating platform, and it is one of key technical subjects how to set the magnitude of these storm in application of design evaluation on each FNPP case. (J.P.N.)

Life Management and Safety of Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Fabbri, S.; Diluch, A.; Vega, G., E-mail: fabbri@cnea.gov.ar [Comisión Nacional de Energía Atómica, Buenos Aires (Argentina)

2014-10-15

The nuclear programme in Argentina includes: nuclear power and related supplies, medical and industrial applications, waste management, research and development and human training. Nuclear facilities require life management programs that allow a safe operation. Safety is the first priority for designers and operators. This can be attained with defence in depth: regular inspections and maintenance procedures to minimize failure risks. CNEA objectives in this area are to possess the necessary capability to give safe and fast technical support. Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to the nuclear plants and research reactors. As a consequence of an increasing concern about safety and ageing a Life Management Department for safe operation was created to take care of these subjects. The goal is to elaborate a Safety Evaluation Process for the critical components of nuclear plants and other facilities. The overall objectives of a safety process are to ensure a continuous safe, reliable and effective operation of nuclear facilities and it means the implementation of the defence in deep concept to enhance safety for the protection of the public, the workers and the environment. (author)

Radiological safety of nuclear power plants in India

International Nuclear Information System (INIS)

Sathish, A.V.

2015-01-01

Safety in nuclear power plants (NPPs) is often less understood and more talked about, thus the author wanted to share the facts to clear the myths. Safety is accorded overriding priority in all the activities. All nuclear facilities are sited, designed, constructed, commissioned and operated in accordance with strict quality and safety standards. Principles of defence in depth, redundancy and diversity are followed in the design of all nuclear facilities and their systems/components. PPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, approved standard operating and maintenance procedures, a well-defined waste management methodology, periodically rehearsed emergency preparedness and disaster management plans. The regulatory framework in the country is robust, with the independent Atomic Energy Regulatory Board (AERB) having powers to frame the policies, laying down safety standards, monitoring and enforcing all the safety provisions. As a result, India's safety record has been excellent in over 400 reactor years of operation of power reactors

The Nuclear Energy Agency: Strengthening Nuclear Safety Technology and Regulation Through Effective International Cooperation

International Nuclear Information System (INIS)

Nieh, H.

2016-01-01

The NEA provides an effective forum for international co-operation on nuclear safety and regulatory issues in its specific task groups, working parties and expert groups, as well as through joint international safety research projects. In these activities, NEA member countries work together to share and analyse data and experiences, gain consensus and develop approaches that can be applied within each country’s governmental processes. Through effective international co-operation, NEA member countries have worked together to develop actions for improving their regulatory frameworks and nuclear installation safety. As a result of these efforts, safety improvements and further harmonisation have been realized in the areas operating reactors, new reactors, human and organisational factors and nuclear safety research. At the NEA, technical and programmatic work under the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI), joint safety research projects and the Multinational Design Evaluation Programme (MDEP) have helped NEA member countries to ensure a high standard for nuclear safety and to further develop the technical knowledge base. (author)

Advanced nuclear reactor safety issues and research needs

International Nuclear Information System (INIS)

2002-01-01

On 18-20 February 2002, the OECD Nuclear Energy Agency (NEA) organised, with the co-sponsorship of the International Atomic Energy Agency (IAEA) and in collaboration with the European Commission (EC), a Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Currently, advanced nuclear reactor projects range from the development of evolutionary and advanced light water reactor (LWR) designs to initial work to develop even further advanced designs which go beyond LWR technology (e.g. high-temperature gas-cooled reactors and liquid metal-cooled reactors). These advanced designs include a greater use of advanced technology and safety features than those employed in currently operating plants or approved designs. The objectives of the workshop were to: - facilitate early identification and resolution of safety issues by developing a consensus among participating countries on the identification of safety issues, the scope of research needed to address these issues and a potential approach to their resolution; - promote the preservation of knowledge and expertise on advanced reactor technology; - provide input to the Generation IV International Forum Technology Road-map. In addition, the workshop tried to link advancement of knowledge and understanding of advanced designs to the regulatory process, with emphasis on building public confidence. It also helped to document current views on advanced reactor safety and technology, thereby contributing to preserving knowledge and expertise before it is lost. (author)

Importance of human factors on nuclear installations safety

International Nuclear Information System (INIS)

Caruso, G.J.

1990-01-01

Actually, installations safety and, in particular the nuclear installations infer a strong incidence in human factors related to the design and operation of such installations. In general, the experience aims to that the most important accidents have happened as result of the components' failures combination and human failures in the operation of safety systems. Human factors in the nuclear installations may be divided into two areas: economy and human reliability. Human factors treatments for the safety evaluation of the nuclear installations allow to diagnose the weak points of man-machine interaction. (Author) [es

Bowtie Risk Management methodology and Modern Nuclear Safety Reports

International Nuclear Information System (INIS)

Ilizastigui Pérez, F.

2016-01-01

The Safety Report (SR) plays a crucial role within the nuclear licensing regime as the principal means for demonstrating the adequacy of safety analysis for a nuclear facility to ensure that it can be constructed, operated, maintained, shut down, and decommissioned safely and in compliance with applicable laws and regulations. It serves as the basis for granting authorizations for the commencement of the main stages of the facility’s life cycle as well as decision-making processes related to safety. Historically, the majority of nuclear safety reports have operated under rather prescriptive regimes, with emphasis placed on demonstrations of the robustness of the facility’s design (design safety) against prescriptive technical requirements set by the regulatory body, and less attention paid to demonstrating the adequacy and effectiveness of Operator’s management system for managing risks to daily operation.

IAEA safety fundamentals: the safety of nuclear installations and the defence in depth concept

International Nuclear Information System (INIS)

Aro, I.

2005-01-01

This presentation is a replica of the similar presentation provided by the IAEA Basic Professional Training Course on Nuclear Safety. The presentation utilizes the IAEA Safety Series document No. 110, Safety Fundamentals: the Safety of Nuclear Installations. The objective of the presentation is to provide the basic rationale for actions in provision of nuclear safety. The presentation also provides basis to understand national nuclear safety requirements. There are three Safety Fundamentals documents in the IAEA Safety Series: one for nuclear safety, one for radiation safety and one for waste safety. The IAEA is currently revising its Safety Fundamentals by combining them into one general Safety Fundamentals document. The IAEA Safety Fundamentals are not binding requirements to the Member States. But, a very similar text has been provided in the Convention on Nuclear Safety which is legally binding for the Member State after ratification by the Parliament. This presentation concentrates on nuclear safety. The Safety Fundamentals documents are the 'policy documents' of the IAEA Safety Standards Series. They state the basic objectives, concepts and principles involved in ensuring protection and safety in the development and application of atomic energy for peaceful purposes. They will state - without providing technical details and without going into the application of principles - the rationale for actions necessary in meeting Safety Requirements. Chapter 7 of this presentation describes the basic features of defence in depth concept which is referred to in the Safety Fundamentals document. The defence in depth concept is a key issue in reaching high level of safety specifically at the design stage but as the reader can see the extended concept also refers to the operational stage. The appendix has been taken directly from the IAEA Basic Professional Training Course on Nuclear Safety and applied to the Finnish conditions. The text originates from the references

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

experience and harmonising safety approaches among Member States. However there is still a need to build on international cooperation in order to promote sharing of experience and knowledge for practical enhancement of nuclear safety. 3. Countries embarking on nuclear power programmes assume very important safety responsibilities that cannot and must not be delegated. Therefore, the establishment of a sustainable national safety infrastructure is an essential foundation for ensuring safe design, construction, operation and decommissioning of nuclear power plants. The process involves the development of a strong governmental, legal and regulatory framework as well as the necessary education and training, technical capacity building and integrated approach to safety, and safety management for all nuclear stakeholders. Vendor countries (vendors and regulators) that are supplying nuclear technology, materials and equipment to the new entrants have moral responsibility and common interest towards these countries and as such should contribute to the creation of strong safety infrastructures in the recipient countries. IAEA should support this process. Specific IAEA safety guides for countries embarking on nuclear power should be enhanced or developed and tailored safety reviews should be prerequisite at different stages of newcomer programme development. IAEA should also develop and provide to the newcomers appropriate training programmes to assure development of safety capacity. Other countries could also provide useful input particularly if they are involved in similar projects. 4. Operating Experience Feedback is an important element of the continuous safety improvement process for nuclear power plants. OEF databases should be analyzed and used more extensively and the lessons learned disseminated and applied among the Member States. All Member States, through their regulatory bodies, have the joint responsibility to adopt the OEF lessons learned in their respective nuclear

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

experience and harmonising safety approaches among Member States. However there is still a need to build on international cooperation in order to promote sharing of experience and knowledge for practical enhancement of nuclear safety. 3. Countries embarking on nuclear power programmes assume very important safety responsibilities that cannot and must not be delegated. Therefore, the establishment of a sustainable national safety infrastructure is an essential foundation for ensuring safe design, construction, operation and decommissioning of nuclear power plants. The process involves the development of a strong governmental, legal and regulatory framework as well as the necessary education and training, technical capacity building and integrated approach to safety, and safety management for all nuclear stakeholders. Vendor countries (vendors and regulators) that are supplying nuclear technology, materials and equipment to the new entrants have moral responsibility and common interest towards these countries and as such should contribute to the creation of strong safety infrastructures in the recipient countries. IAEA should support this process. Specific IAEA safety guides for countries embarking on nuclear power should be enhanced or developed and tailored safety reviews should be prerequisite at different stages of newcomer programme development. IAEA should also develop and provide to the newcomers appropriate training programmes to assure development of safety capacity. Other countries could also provide useful input particularly if they are involved in similar projects. 4. Operating Experience Feedback is an important element of the continuous safety improvement process for nuclear power plants. OEF databases should be analyzed and used more extensively and the lessons learned disseminated and applied among the Member States. All Member States, through their regulatory bodies, have the joint responsibility to adopt the OEF lessons learned in their respective nuclear

Construction for Nuclear Installations. Specific Safety Guide

International Nuclear Information System (INIS)

2015-01-01

This Safety Guide provides recommendations and guidance based on international good practices in the construction of nuclear installations, which will enable construction to proceed with high quality. It can be applied to support the development, implementation and assessment of construction methods and procedures and the identification of good practices for ensuring the quality of the construction to meet the design intent and ensure safety. It will be a useful tool for regulatory bodies, licensees and new entrant countries for nuclear power plants and other nuclear installations

Safety of WWER type nuclear power plants - viewing from Hungary

International Nuclear Information System (INIS)

Voeroess, L.

1991-01-01

An evaluation of WWER type nuclear power plants operating in Hungary is given, relative to the safety requirements accepted internationally; how safe can they be regarded and what can be done to assure a high level of safety in all case. After an overview of general safety criteria, an overall description of WWER-440 type nuclear reactors is presented. Design safety, operational safety issues are treated in detail. Safety inspection and safety-related research and development is discussed. Regarding the future, five different issues associated with nuclear reactor safety should be considered. (R.P.) 20 refs.; 12 figs.; 3 tabs

Nuclear Safety in Central and Eastern Europe

International Nuclear Information System (INIS)

2001-04-01

Nuclear safety is one of the critical issues with respect to the enlargement of the European Union towards the countries of Central and Eastern Europe. In the context of the enlargement process, the European Commission overall strategy on nuclear safety matters has been to bring the general standard of nuclear safety in the pre-accession countries up to a level that would be comparable to the safety levels in the countries of the European Union. In this context, the primary objective of the project was to develop a common format and general guidance for the evaluation of the current nuclear safety status in countries that operate commercial nuclear power plants. Therefore, one of the project team first undertakings was to develop an approach that would allow for a consistent and comprehensive overview of the nuclear safety status in the CEEC, enabling an equal treatment of the countries to be evaluated. Such an approach, which did not exist, should also ensure identification of the most important safety issues of the individual nuclear power plants. The efforts resulted in the development of the ''Performance Evaluation Guide'', which focuses on important nuclear safety issues such as plant design and operation, the practice of performing safety assessments, and nuclear legislation and regulation, in particular the role of the national regulatory body. Another important aspect of the project was the validation of the Performance Evaluation Guide (PEG) by performing a preliminary evaluation of nuclear safety in the CEEC, namely in Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. The nuclear safety evaluation of each country was performed as a desktop exercise, using solely available documents that had been prepared by various Western institutions and the countries themselves. Therefore, the evaluation is only of a preliminary nature. The project did not intend to re-assess nuclear safety, but to focus on a comprehensive summary

NSPWG-recommended safety requirements and guidelines for SEI nuclear propulsion

International Nuclear Information System (INIS)

Marshall, A.C.; Lee, J.H.; McCulloch, W.H.; Sawyer, J.C. Jr.; Bari, R.A.; Brown, N.W.; Cullingford, H.S.; Hardy, A.C.; Remp, K.; Sholtis, J.A.

1992-01-01

An Interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top- level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition the NSPWG reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. Safety requirements were developed for reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, and safeguards. Guidelines were recommended for risk/reliability, operational safety, flight trajectory and mission abort, space debris and meteoroids, and ground test safety. In this paper the specific requirements and guidelines will be discussed

Nuclear safety regulations

International Nuclear Information System (INIS)

1998-01-01

The Departmental Rules and The Safety Guides were issued by the NNSA in 1998. The NNSA performed the activities of propagation and implementation of nuclear safety regulations at QTNPP in order to improve the nuclear safety culture of operating organization and construct and contract organizations

Nuclear Safety. 1997

International Nuclear Information System (INIS)

1998-01-01

A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs

Nuclear safety in all-European collaboration

International Nuclear Information System (INIS)

Toepfer, K.

1992-01-01

The importance of international cooperation in the field of nuclear safety is shown by the fact that there are more than 400 nuclear powerstations of different designs, different ages and in different legal, economic and social systems worldwide. The German Federal Government therefore supports the regulations of the IAEA Safety Standard, the so called NUSS codes. In the bilateral field, agreements have already been made with many countries, which provide for collaboration to protect against the dangers of nuclear energy. The effects of the Chernobyl accident reinforce the necessity of making this more intensive and extending it to the countries of the former Eastern block. (DG) [de

Global nuclear safety culture

International Nuclear Information System (INIS)

1997-01-01

As stated in the Nuclear Safety Review 1996, three components characterize the global nuclear safety culture infrastructure: (i) legally binding international agreements; (ii) non-binding common safety standards; and (iii) the application of safety standards. The IAEA has continued to foster the global nuclear safety culture by supporting intergovernmental collaborative efforts; it has facilitated extensive information exchange, promoted the drafting of international legal agreements and the development of common safety standards, and provided for the application of safety standards by organizing a wide variety of expert services

Nuclear safety after Three Mile Island and Chernobyl

International Nuclear Information System (INIS)

Ballard, G.M.

1988-01-01

This book contains the proceedings on nuclear safety after Three Mile island and Chernobyl. Topics covered include: Design for safety; Man-machine interaction; Source terms and consequence; and accident response

The role of nuclear law in nuclear safety after Fukushima

International Nuclear Information System (INIS)

Cardozo, Diva E. Puig

2013-01-01

The paper contains the following topics: nuclear law, origin and evolution, role of the legal instruments on nuclear safety, nuclear safety the impact of major nuclear accidents: Chernobyl and Fukushima. The response of the nuclear law post Fukushima. Safety and security. International framework for nuclear safety: nuclear convention joint convention on safety on spent fuel management and on the safety of radioactive waste management. The Fukushima World Conference on Nuclear Safety. Convention on Prompt Notification and Assistance in case of a Nuclear Accident or Radiological Emergency. Plan of Action for Nuclear Safety. IAEA recommendations for the safety transport of radioactive material. International framework for nuclear security. Convention on the Physical Protection of Nuclear Materials. International Convention for the Suppression of Acts Against Nuclear Terrorism. Resolution No. 1540 of the Security Council of United Nations (2004). Measures to strengthen international safety. Code of conduct on the safety research reactor

Nuclear reactor design

CERN Document Server

2014-01-01

This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

Technical Guidance from the International Safety Framework for Nuclear Power Source Applications in Outer Space for Design and Development Phases

Science.gov (United States)

Summerer, Leopold

2014-08-01

In 2009, the International Safety Framework for Nuclear Power Source Applications in Outer Space [1] has been adopted, following a multi-year process that involved all major space faring nations in the frame of the International Atomic Energy Agency and the UN Committee on the Peaceful Uses of Outer Space. The safety framework reflects an international consensus on best practices. After the older 1992 Principles Relevant to the Use of Nuclear Power Sources in Outer Space, it is the second document at UN level dedicated entirely to space nuclear power sources.This paper analyses aspects of the safety framework relevant for the design and development phases of space nuclear power sources. While early publications have started analysing the legal aspects of the safety framework, its technical guidance has not yet been subject to scholarly articles. The present paper therefore focuses on the technical guidance provided in the safety framework, in an attempt to assist engineers and practitioners to benefit from these.

Fundamentals for the safety-relevant design of rotational shiftplans in nuclear power plants

International Nuclear Information System (INIS)

Preuss, W.; Herbert, K.W.; Reinartz, G.; Saniter, R.

1984-01-01

The investigation was concerned with the influence of rotational shiftwork on operator performance, particularly in the nuclear power industry. In an analysis of the literature, the fundamental chronobiological knowledge was reviewed. Work physiological criteria for the design of shiftplans were assembled and their relevance to this industry was assessed. In addition, interviews were held with representatives from nuclear power utilities in the Federal Republic of Germany and also in Switzerland and the Netherlands. Characteristics of the shiftplans in current use were recorded and the basic operating principles of the shift systems were ascertained. The alternative designs were discussed and assessed from the point of view of operator performance and their significance to safety. The results of the analysis of the literature and of the interviews with the utilities are presented in two separate volumes of the report. (orig.) [de

New reactor technology: safety improvements in nuclear power systems.

Science.gov (United States)

Corradini, M L

2007-11-01

Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

Organization and Nuclear Safety: Safety culture

International Nuclear Information System (INIS)

Martin Marquinez, A.

1998-01-01

This book presents the experience in nuclear safety and its influence in the exploitation on nuclear power plants. The safety organization and quality management before and after Chernobylsk and three mile island accidents

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Nuclear power and nuclear safety 2009

International Nuclear Information System (INIS)

Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.; Nystrup, P.E.; Thorlaksen, B.

2010-05-01

The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

Problems of structural mechanics in nuclear design

International Nuclear Information System (INIS)

Patwardhan, V.M.; Kakodkar, Anil

1975-01-01

A very careful and detailed stress analysis of nuclear presure vessels and components is essential for ensuring the safety and integrity of nuclear power plants. The nuclear designer, therefore, relies heavily on structural mechanics for application of the most advanced stress analysis techniques to practical design problems. The paper reviews the inter-relation between structural mechanics and nuclear design and discusses a few of the specific structural mechanics problems faced by the nuclear designers in the Department of Atomic Energy, India. (author)

The way to solve the safety problems of nuclear power

International Nuclear Information System (INIS)

Qian Jihui; Zhang Senru

1991-01-01

Based on the safety problems that the current water cooled reactor nuclear power plants have the potential danger of core melt, the paper comments upon the safety behaviors of the advanced reactors (AP-600, SIR) and passive safety reactors (PIUS, MHTGR). According to design and user's requirements for next generation water cooled reactor, the paper put forward a new concept about self safety U-ZrH reactor (SUR) which is able to solve the safety problems for water cooled reactor nuclear power plant and become a development direction for world water cooled reactor nuclear power plants. This type of reactor has been studied in NPIC (Nuclear Power Institute of China)

Industrial Personal Computer based Display for Nuclear Safety System

International Nuclear Information System (INIS)

Kim, Ji Hyeon; Kim, Aram; Jo, Jung Hee; Kim, Ki Beom; Cheon, Sung Hyun; Cho, Joo Hyun; Sohn, Se Do; Baek, Seung Min

2014-01-01

The safety display of nuclear system has been classified as important to safety (SIL:Safety Integrity Level 3). These days the regulatory agencies are imposing more strict safety requirements for digital safety display system. To satisfy these requirements, it is necessary to develop a safety-critical (SIL 4) grade safety display system. This paper proposes industrial personal computer based safety display system with safety grade operating system and safety grade display methods. The description consists of three parts, the background, the safety requirements and the proposed safety display system design. The hardware platform is designed using commercially available off-the-shelf processor board with back plane bus. The operating system is customized for nuclear safety display application. The display unit is designed adopting two improvement features, i.e., one is to provide two separate processors for main computer and display device using serial communication, and the other is to use Digital Visual Interface between main computer and display device. In this case the main computer uses minimized graphic functions for safety display. The display design is at the conceptual phase, and there are several open areas to be concreted for a solid system. The main purpose of this paper is to describe and suggest a methodology to develop a safety-critical display system and the descriptions are focused on the safety requirement point of view

Industrial Personal Computer based Display for Nuclear Safety System

Energy Technology Data Exchange (ETDEWEB)

Kim, Ji Hyeon; Kim, Aram; Jo, Jung Hee; Kim, Ki Beom; Cheon, Sung Hyun; Cho, Joo Hyun; Sohn, Se Do; Baek, Seung Min [KEPCO, Youngin (Korea, Republic of)

2014-08-15

The safety display of nuclear system has been classified as important to safety (SIL:Safety Integrity Level 3). These days the regulatory agencies are imposing more strict safety requirements for digital safety display system. To satisfy these requirements, it is necessary to develop a safety-critical (SIL 4) grade safety display system. This paper proposes industrial personal computer based safety display system with safety grade operating system and safety grade display methods. The description consists of three parts, the background, the safety requirements and the proposed safety display system design. The hardware platform is designed using commercially available off-the-shelf processor board with back plane bus. The operating system is customized for nuclear safety display application. The display unit is designed adopting two improvement features, i.e., one is to provide two separate processors for main computer and display device using serial communication, and the other is to use Digital Visual Interface between main computer and display device. In this case the main computer uses minimized graphic functions for safety display. The display design is at the conceptual phase, and there are several open areas to be concreted for a solid system. The main purpose of this paper is to describe and suggest a methodology to develop a safety-critical display system and the descriptions are focused on the safety requirement point of view.

National nuclear safety report 1998. Convention on nuclear safety

International Nuclear Information System (INIS)

1998-01-01

The Argentine Republic subscribed the Convention on Nuclear Safety, approved by a Diplomatic Conference in Vienna, Austria, in June 17th, 1994. According to the provisions in Section 5th of the Convention, each Contracting Party shall submit for its examination a National Nuclear Safety Report about the measures adopted to comply with the corresponding obligations. This Report describes the actions that the Argentine Republic is carrying on since the beginning of its nuclear activities, showing that it complies with the obligations derived from the Convention, in accordance with the provisions of its Article 4. The analysis of the compliance with such obligations is based on the legislation in force, the applicable regulatory standards and procedures, the issued licenses, and other regulatory decisions. The corresponding information is described in the analysis of each of the Convention Articles constituting this Report. The present National Report has been performed in order to comply with Article 5 of the Convention on Nuclear Safety, and has been prepared as much as possible following the Guidelines Regarding National Reports under the Convention on Nuclear Safety, approved in the Preparatory Meeting of the Contracting Parties, held in Vienna in April 1997. This means that the Report has been ordered according to the Articles of the Convention on Nuclear Safety and the contents indicated in the guidelines. The information contained in the articles, which are part of the Report shows the compliance of the Argentine Republic, as a contracting party of such Convention, with the obligations assumed

Study on European Nuclear Safety Practices during Planned Outages at Nuclear Power Plants

International Nuclear Information System (INIS)

2001-12-01

The present project was aimed at providing: a description of the current status of nuclear safety practices during planned outages at nuclear power plants followed in Europe; the criteria for the safety analysis of future reactors at the design stage; proposing a set of recommendations on good practices and criteria leading to the improvement of nuclear safety during those conditions. The work was organised in 3 phases: Collecting data on current practices; Analysis of questionnaire answers and drawing up of safety good practices references and recommendations; Collecting relevant ideas related to the future reactors at design stage (European Pressurised Water Reactor, European Passive Plant project, European Utilities Requirements and Utilities Requirement Document project). The key element of the performed work was the detailed questionnaire, based on bibliographical review, expert experience and outage practices available in the working team. Different safety areas and activities were covered: outage context; nuclear safety; outage strategy, organisation and control; operating feedback; use of Probabilistic Safety Assessment. The questionnaire was answered by 12 European nuclear power plants, representing 9 different European countries and three different types of reactors (Pressurised Water Reactor, Boiling Water Reactor and Water Water Energy Reactor). Conclusions were drawn under the following headers: Organisational survey and generalities Organisational effectiveness Quality of maintenance Quality of operation Engineering support, management of modification Specific aspects Each analysed subject includes the following topics: Questions background with a summary and the aim of the questions. Current status, that describes common practices, as derived from the answers to the questionnaire, and some examples of good specific practices. Identified good practices. (author)

Holistic safety analysis for advanced nuclear power plants

International Nuclear Information System (INIS)

Alvarenga, M.A.B.; Guimaraes, A.C.F.

1992-01-01

This paper reviews the basic methodology of safety analysis used in the ANGRA-I and ANGRA-II nuclear power plants, its weaknesses, the problems with public acceptance of the risks, the future of the nuclear energy in Brazil, as well as recommends a new methodology, HOLISTIC SAFETY ANALYSIS, to be used both in the design and licensing phases, for advanced reactors. (author)

Safety issues of nuclear production of hydrogen

International Nuclear Information System (INIS)

Piera, Mireia; Martinez-Val, Jose M.; Jose Montes, Ma

2006-01-01

Hydrogen is not an uncommon issue in Nuclear Safety analysis, particularly in relation to severe accidents. On the other hand, hydrogen is a household name in the chemical industry, particularly in oil refineries, and is also a well known chemical element currently produced by steam reforming of natural gas, and other methods (such as coal gasification). In the not-too-distant future, hydrogen will have to be produced (by chemical reduction of water) using renewable and nuclear energy sources. In particular, nuclear fission seems to offer the cheapest way to provide the primary energy in the medium-term. Safety principles are fundamental guidelines in the design, construction and operation both of hydrogen facilities and nuclear power plants. When these two technologies are integrated, a complete safety analysis must consider not only the safety practices of each industry, but any interaction that could be established between them. In particular, any accident involving a sudden energy release from one of the facilities can affect the other. Release of dangerous substances (chemicals, radiotoxic effluents) can also pose safety problems. Although nuclear-produced hydrogen facilities will need specific approaches and detailed analysis on their safety features, a preliminary approach is presented in this paper. No significant roadblocks are identified that could hamper the deployment of this new industry, but some of the hydrogen production methods will involve very demanding safety standards

The case for nuclear energy. Chapter 2. Nuclear safety and energy security

International Nuclear Information System (INIS)

Trosman, G.

2010-01-01

The U.S. nuclear safety assistance activities have had a direct and substantial impact on improving safe operations of 67 Soviet-designed commercial nuclear power plants in Armenia, Bulgaria, Czech Republic, Hungary, Kazakhstan, Lithuania, Russia, Slovakia, and Ukraine. The U.S. Department of Energy worked with these host countries both to improve safe nuclear operations and in some cases assist in plant shutdown. Independent international safety reviews have identified significant progress in the Eastern European countries to improve the safety of their nuclear power plants since the early 1990s. In addition, all of the probabilistic risk assessments conducted at these plants show a major reduction in the frequency of core damage accidents since U.S. assistance to improve safety at these reactors began. Improved operational safety follows from the combined efforts to improve operator performance. These efforts include providing simulators for operators to practice handling emergency scenarios, developing emergency operating instructions that guide operators calmly through emergencies, providing safety parameter display systems that give operators immediate graphical information on the status of plant systems and training the operators on the safety basis for the plants they operate

An international nuclear safety regime

International Nuclear Information System (INIS)

Rosen, M.

1995-01-01

For all the parties involved with safe use of nuclear energy, the opening for signature of the 'Convention on Nuclear Safety' (signed by 60 countries) and the ongoing work to prepare a 'Convention on Radioactive Waste Safety' are particularly important milestones. 'Convention on Nuclear Safety' is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The two conventions are only one facet of international cooperation to enhance safety. A review of some cooperative efforts of the past decades, and some key provisions of the new safety conventions, presented in this paper, show how international cooperation is increasing nuclear safety worldwide. The safety philosophy and practices involved with legal framework for the safe use of nuclear power will foster a collective international involvement and commitment. It will be a positive step towards increasing public confidence in nuclear power

Design requirements for new nuclear reactor facilities in Canada

International Nuclear Information System (INIS)

Shim, S.; Ohn, M.; Harwood, C.

2012-01-01

The Canadian Nuclear Safety Commission (CNSC) has been establishing the regulatory framework for the efficient and effective licensing of new nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of new nuclear reactor facilities, regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants; and 2. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities. These regulatory documents have been modernized to document past practices and experience and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper highlights two particular aspects of these regulatory documents: The use of a graded approach to make the documents applicable for a wide variety of nuclear reactor facilities including nuclear power plants (NPPs) and small reactor facilities; and, Design requirements that are new and different from past Canadian practices. Finally, this paper presents some of the proposed changes in RD-337 to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were not needed as the 2008 version of RD-337 already contained requirements to address most of the lessons learned from the Fukushima event of March 2011. (author)

IAEA activities in nuclear safety: future perspectives. Spanish Nuclear Safety Council, Madrid, 28 May 1998

International Nuclear Information System (INIS)

ElBaradei, M.

1998-01-01

The document represents the conference given by the Director General of the IAEA at the Spanish Nuclear Safety Council in Madrid, on 28 May 1998, on Agency's activities in nuclear safety. The following aspects are emphasized: Agency's role in creating a legally binding nuclear safety regime, non-binding safety standards, services provided by the Agency to assist its Member States in the Application of safety standards, Agency's nuclear safety strategy, and future perspective concerning safety aspects related to radioactive wastes, residues of past nuclear activities, and security of radiological sources

Research on integrated managing system based on CIMS for nuclear power plant safety

International Nuclear Information System (INIS)

Zhou Gang

2006-01-01

In order to improve safety, economy and reliability of operation for nuclear power plant (NPP), a novel integrated managing method was proposed based on the ideas of computer and contemporary integrated manufacturing system (CIMS). The application of CIMS to nuclear power plant safety management was researched. In order to design an integrated managing system to meet the needs of NPP safety management, all work related to nuclear safety is divided into different category according to its characters. On basis of this work, general integrated managing system was designed at first. Then subsystems were designed and every subsystem implements a category of nuclear safety management work. All subsystems are independent relatively on the one hand and are interrelated on other hand by global information system. (authors)

Nuclear Safety Culture

International Nuclear Information System (INIS)

2017-01-01

Ethics is caring about people and Safety is caring that no physical harm comes to people.Therefore Safety is a type of Ethical Behavior. Culture: is The Way We Do Things Here.Safety Culture is mixture of organization traditions, values, attitudes and behaviors modeled by Its leaders and internalized by its members that serve to make nuclear safety the overriding priority. Safety Culture is that assembly of characteristics and attitudes in Organisations and individuals which established that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance

Operational safety enhancement of Soviet-designed nuclear reactors via development of nuclear power plant simulators and transfer of related technology

International Nuclear Information System (INIS)

Kohut, P.; Epel, L.G.; Tutu, N.K.

1998-01-01

The US Department of Energy (DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper

Design of nuclear power plants

International Nuclear Information System (INIS)

Lobo, C.G.

1987-01-01

The criteria of design and safety, applied internationally to systems and components of PWR type reactors, are described. The main criteria of the design analysed are: thermohydraulic optimization; optimized arrangement of buildings and components; low costs of energy generation; high level of standardization; application of specific safety criteria for nuclear power plants. The safety criteria aim to: assure the safe reactor shutdown; remove the residual heat and; avoid the release of radioactive elements for environment. Some exemples of safety criteria are given for Angra-2 and Angra-3 reactors. (M.C.K.) [pt

Framework of nuclear safety and safety assessment

International Nuclear Information System (INIS)

Furuta, Kazuo

2007-01-01

Since enormous energy is released by nuclear chain reaction mainly as a form of radiation, a great potential risk accompanies utilization of nuclear energy. Safety has been continuously a critical issue therefore from the very beginning of its development. Though the framework of nuclear safety that has been established at an early developmental stage of nuclear engineering is still valid, more comprehensive approaches are required having experienced several events such as Three Mile Island, Chernobyl, and JCO. This article gives a brief view of the most basic principles how nuclear safety is achieved, which were introduced and sophisticated in nuclear engineering but applicable also to other engineering domains in general. (author)

Safety culture in nuclear installations. Management of safety and safety culture in Indian NPPs

International Nuclear Information System (INIS)

Rawal, S.C.

2002-01-01

Nuclear Power Corporation Of India Ltd. (NPCIL) is a company owned by Government of India and is responsible for Design, Construction, Commissioning, Operation and Decommissioning of Nuclear Power plants in India. Presently, a total of 13 Nuclear power Stations are in operation with an installed capacity of 2620 MWe and 2 VVR type PWR Units of 1000 MWe capacity each, 2 PHWR type units of 500 MWe capacity each and 4 PHWR type 220 MWe capacity each are under construction. NPPs generation capacity has been increased from 70% to 85% in the span Of last 7 years with high level of safety standards. This could be achieved through Management commitment towards building a strong Safety Culture. Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The two attributes of safety culture are built in and upgraded in each individuals through special training at the time of entry in the organisation and later through in built procedures in the work practices, motivation and encouragement for free participation of each individuals. Individuals are encouraged to participate in Quality circle teams at the sectional level and review of safety proposal originated by individuals in Station operation Review Committee at Station level, in addition to this to continuously enhance the safety culture, refresher training courses are being organised at regular intervals. The safety related proposals are categorised in to two namely: Proposals from Operating Plants, and Proposals from projects and Design. The concept of safety

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2003-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures. Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

Nuclear safety. Volume 36, Number 2, July--December 1995

Energy Technology Data Exchange (ETDEWEB)

None

1995-12-01

The primary scope of the journal is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. The following subjects are covered here: (1) the Chernobyl accident; (2) general safety considerations; (3) accident analysis; (4) design features; (5) environmental effects; (6) operating experiences; (7) US NRC information and analyses; and (8) recent developments. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Assessment of safety of the nuclear installations of the world

International Nuclear Information System (INIS)

Thomas, B.A.; Pozniakov, N.; Banga, U.

1992-01-01

Incidents and accidents periodically remind us that preventive measures at nuclear installations are not fully reliable. Although sound design is widely recognized to be prerequisite for safe operation, it is not sufficient. An active management that compensates for the weak aspects of the installations design by redundant operational provisions, is the key factor to ensure safe operation. Safety of nuclear installations cannot be assessed on an emotional basis. Since 1986, accurate safety assessment techniques based on an integrated approach to operational safety have been made available by the ASSET services and are applicable to any industrial process dealing with nuclear materials. The ASSET methodology enables to eliminate in advance the Root Causes of the future accidents by introducing practical safety culture principles in the current managerial practices

Safety culture of nuclear power plant

International Nuclear Information System (INIS)

Zheng Beixin

2008-01-01

This paper is a summary on the basis of DNMC safety culture training material for managerial personnel. It intends to explain the basic contents of safety, design, management, enterprise culture, safety culture of nuclear power plant and the relationship among them. It explains especially the constituent elements of safety culture system, the basic requirements for the three levels of commitments: policy level, management level and employee level. It also makes some analyses and judgments for some typical safety culture cases, for example, transparent culture and habitual violation of procedure. (authors)

Safety related terms for advanced nuclear plants

International Nuclear Information System (INIS)

1995-12-01

The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

Safety related terms for advanced nuclear plants

International Nuclear Information System (INIS)

1991-09-01

The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

culture and achieve good performance in terms of safety. This publication identifies the main safety objectives and responsibilities of management with respect to the safe operation of nuclear power plants and associated corporate roles of the operating organization. This Safety Guide discusses the factors to be considered in (a) structuring the operating organization to meet these main safety objectives, (b) setting up management programmes that ensure that the safety tasks are performed, (c) establishing services and facilities that are intended to meet the above requirements and (d) maintaining a strong safety culture within the organization. This Safety Guide primarily addresses safety matters directly related to the operation of nuclear power plants. It assumes that the safety aspects of siting, design, manufacturing and construction have been resolved. It also covers the internal interrelationships between operations and design, construction and commissioning and other organizational units, and deals with the involvement of the operating organization in reviews of safety issues, bearing in mind future operation. Finally, this publication discusses the relationship between the operating organization, the regulatory body and the general public. Section 2 focuses on the operating organization and its structure. Section 3 discusses the functions, responsibilities, goals and objectives of the operating organization that ensure the safe operation of nuclear power plants. Section 4 gives guidance on the interface between the operating organization and external organizations. Section 5 covers safety management aspects. Section 6 provides guidance on the major management programmes that should be established to ensure the safe operation of a nuclear power plant. Section 7 discusses additional services that are needed to support the functioning of plant operation management programmes. Section 8 provides general guidance on the communication and liaison matters that are

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

culture and achieve good performance in terms of safety. This publication identifies the main safety objectives and responsibilities of management with respect to the safe operation of nuclear power plants and associated corporate roles of the operating organization. This Safety Guide discusses the factors to be considered in (a) structuring the operating organization to meet these main safety objectives, (b) setting up management programmes that ensure that the safety tasks are performed, (c) establishing services and facilities that are intended to meet the above requirements and (d) maintaining a strong safety culture within the organization. This Safety Guide primarily addresses safety matters directly related to the operation of nuclear power plants. It assumes that the safety aspects of siting, design, manufacturing and construction have been resolved. It also covers the internal interrelationships between operations and design, construction and commissioning and other organizational units, and deals with the involvement of the operating organization in reviews of safety issues, bearing in mind future operation. Finally, this publication discusses the relationship between the operating organization, the regulatory body and the general public. Section 2 focuses on the operating organization and its structure. Section 3 discusses the functions, responsibilities, goals and objectives of the operating organization that ensure the safe operation of nuclear power plants. Section 4 gives guidance on the interface between the operating organization and external organizations. Section 5 covers safety management aspects. Section 6 provides guidance on the major management programmes that should be established to ensure the safe operation of a nuclear power plant. Section 7 discusses additional services that are needed to support the functioning of plant operation management programmes. Section 8 provides general guidance on the communication and liaison matters that are

Documents pertaining to safety control of nuclear facilities

International Nuclear Information System (INIS)

1998-01-01

The Finnish Radiation and Nuclear Safety Authority (STUK) controls the safety of nuclear facilities in Finland. This control encompasses on one hand the evaluation of plant safety on the basis of plans and analyses pertaining to the plant and on the other hand the inspection of plant structures, systems and components as well as of operational activity. STUK also monitors plants operational experience feedback and technical developments in the field, as well as the development of safety research and takes the necessary measures on their basis. Guide YVL 1.1 describes how STUK controls the design, construction and operation of nuclear power plants. The documents to be submitted to STUK are described in the nuclear energy legislation and YVL guides. This guide presents the mode of delivery, quality, contents and number of documents to be submitted to STUK

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

culture and achieve good performance in terms of safety. This publication identifies the main safety objectives and responsibilities of management with respect to the safe operation of nuclear power plants and associated corporate roles of the operating organization. This Safety Guide discusses the factors to be considered in (a) structuring the operating organization to meet these main safety objectives, (b) setting up management programmes that ensure that the safety tasks are performed, (c) establishing services and facilities that are intended to meet the above requirements and (d) maintaining a strong safety culture within the organization. This Safety Guide primarily addresses safety matters directly related to the operation of nuclear power plants. It assumes that the safety aspects of siting, design, manufacturing and construction have been resolved. It also covers the internal interrelationships between operations and design, construction and commissioning and other organizational units, and deals with the involvement of the operating organization in reviews of safety issues, bearing in mind future operation. Finally, this publication discusses the relationship between the operating organization, the regulatory body and the general public. Section 2 focuses on the operating organization and its structure. Section 3 discusses the functions, responsibilities, goals and objectives of the operating organization that ensure the safe operation of nuclear power plants. Section 4 gives guidance on the interface between the operating organization and external organizations. Section 5 covers safety management aspects. Section 6 provides guidance on the major management programmes that should be established to ensure the safe operation of a nuclear power plant. Section 7 discusses additional services that are needed to support the functioning of plant operation management programmes. Section 8 provides general guidance on the communication and liaison matters that are

The Canadian approach to nuclear power safety

International Nuclear Information System (INIS)

Atchison, R.J.; Boyd, F.C.; Domaratski, Z.

1983-07-01

The development of the Canadian nuclear power safety philosophy and practice is traced from its early roots at the Chalk River Nuclear Laboratory to the licensing of the current generation of power reactors. Basic to the philosophy is a recognition that the primary responsibility for achieving a high standard of safety resides with the licensee. As a consequence, regulatory requirements have emphasized numerical safety goals and objectives and minimized specific design or operating rules. The Canadian licensing process is described along with a discussion of some of the difficulties encountered. Examples of specific licensing considerations for each phase of a project are included

The Management System for Nuclear Installations Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

Nuclear safety policy statement in korea

International Nuclear Information System (INIS)

Kim, W.S.; Kim, H.J.; Choi, K.S.; Choi, Y.S.; Park, D.K.

2006-01-01

Full text: Wide varieties of programs to enhance nuclear safety have been established and implemented by the Korean government in accordance with the Nuclear Safety Policy Statement announced in September 1994. The policy statement was intended to set the long-term policy goals for maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It has been recognized as very effective in developing safety culture in nuclear-related organizations and also enhancing nuclear safety in Korea. However, ageing of operating nuclear power plants and increasing of new nuclear facilities have demanded a new comprehensive national safety policy to cover the coming decade, taking the implementation results of the policy statement of 1994 and the changing environment of nuclear industries into consideration. Therefore, the results of safety policy implementation have been reviewed and, considering changing environment and future prospects, a new nuclear safety policy statement as a highest level national policy has been developed. The implementation results of 11 regulatory policy directions such as the use of Probabilistic Safety Assessment, introduction of Periodic Safety Review, strengthening of safety research, introduction of Risk Based Regulation stipulated in the safety policy statement of 1994 were reviewed and measures taken after various symposia on nuclear safety held in Nuclear Safety Days since 1995 were evaluated. The changing international and domestic environment of nuclear industry were analysed and future prospects were explored. Based on the analysis and review results, a draft of new nuclear safety policy statement was developed. The draft was finalized after the review of many prominent experts in Korea. Considering changing environment and future prospects, new policy statement that will show government's persistent will for nuclear safety has been

EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

Energy Technology Data Exchange (ETDEWEB)

Erven, Ulrich (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard (ed.) [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De (ed.) [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

2005-07-01

The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

Energy Technology Data Exchange (ETDEWEB)

Erven, Ulrich [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

2005-07-01

The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

Human factors in nuclear safety oversight

International Nuclear Information System (INIS)

Taylor, K.

1989-01-01

The mission of the nuclear safety oversight function at the Savannah River Plant is to enhance the process and nuclear safety of site facilities. One of the major goals surrounding this mission is the reduction of human error. It is for this reason that several human factors engineers are assigned to the Operations assessment Group of the Facility Safety Evaluation Section (FSES). The initial task of the human factors contingent was the design and implementation of a site wide root cause analysis program. The intent of this system is to determine the most prevalent sources of human error in facility operations and to assist in determining where the limited human factors resources should be focused. In this paper the strategy used to educate the organization about the field of human factors is described. Creating an awareness of the importance of human factors engineering in all facets of design, operation, and maintenance is considered to be an important step in reducing the rate of human error

Proceedings of the specialist meeting on nuclear fuel and control rods: operating experience, design evolution and safety aspects

International Nuclear Information System (INIS)

1997-01-01

Design and management of nuclear fuel has undergone a strong evolution process during past years. The increase of the operating cycle length and of the discharge burnup has led to the use of more advanced fuel designs, as well as to the adoption of fuel efficient operational strategies. The analysis of recent operational experience highlighted a number of issues related to nuclear fuel and control rod events raising concerns about the safety aspects of these new designs and operational strategies, which led to the organisation of this Specialists Meeting on fuel and control rod issues. The meeting was intended to provide a forum for the exchange of information on lessons learned and safety concern related to operating experience with fuel and control rods (degradation, reliability, experience with high burnup fuel, and others). After an opening session 6 papers), this meeting was subdivided into four sessions: Operating experience and safety concern (technical session I - 6 papers), Fuel performance and operational issues (technical session II - 7 papers), Control rod issues (technical session III - 9 papers), Improvement of fuel design (technical session IV.A - 4 papers), Improvement on fuel fabrication and core management (technical session IV.B - 6 papers)

Some considerations on the safety of nuclear ships

International Nuclear Information System (INIS)

Kuramoto, Masaaki

1978-01-01

For realizing the practical utilization of nuclear merchant ships, it is essential to gain their acceptance by maritime countries on an equal footing with conventional vessels, and to have the administrative procedures for their admission simplified. This, however cannot be expected to be attained overnight, and progressive measures will have to be adopted, to approach the ultimate goal step by step. The first step should be to demonstrate the safety of nuclear propulsion, for which nuclear ships must accumulate their mileages of safe service. The second important step is to simplify the procedures demanded of nuclear ships for access to ports, through the establishment of international safety standards and design criteria, the enforcement of safety measures covering the entrance of nuclear ships into ports, and the assurance of safety in he repair, inspection and refuelling operations of these ships. Among these measures, the considerations relevant to port entry are the subject of vital interest to both ship operators and port authorities

Safety of light water reactors. Risks of nuclear technology

International Nuclear Information System (INIS)

Veser, Anke; Schlueter, Franz-Hermann; Raskob, Wolfgang; Landman, Claudia; Paesler-Sauer, Juergen; Kessler, Guenter

2012-01-01

The book on the safety of light-water reactors includes the following chapters: Part I: Physical and technical safety concept of actual German and future European light-water reactors: (1) Worldwide operated nuclear power plants in 2011, (2) Some reactor physical fundamentals. (3) Nuclear power plants in Germany. (4) Radioactive exposure due to nuclear power plants. (5) Safety concept of light-water reactors. (6) Probabilistic analyses and risk studies. (7) Design of light-water reactors against external incidents. (8) Risk comparison of nuclear power plants and other energy systems. (9) Evaluation of risk studies using the improved (new) safety concept for LWR. (19) The severe reactor accidents of Three Mile Island, Chernobyl and Fukushima. Part II: Safety of German LWR in case of a postulated aircraft impact. (11) Literature. (12) Review of requirements and actual design. (13) Incident scenarios. (14) Load approach for aircraft impact. (15) Demonstration of the structural behavior in case of aircraft impact. (16) Special considerations. (17) Evaluation of the safety state of German and foreign nuclear power plants. Part III: ROSOS as example for a computer-based decision making support system for the severe accident management. (19) Literature. (20) Radiological fundamentals, accident management, modeling of the radiological situation. (21) The decision making support system RODOS. (22) RODOS and the Fukushima accident. (23) Recent developments in the radiological emergency management in the European frame.

Autoclave nuclear criticality safety analysis

Energy Technology Data Exchange (ETDEWEB)

D`Aquila, D.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Tayloe, R.W. Jr. [Battelle, Columbus, OH (United States)

1991-12-31

Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

Status report of the US Department of Energy's International Nuclear Safety Program

International Nuclear Information System (INIS)