Sizewell 'B'

International Nuclear Information System (INIS)

1983-01-01

The Nuclear Installations Inspectorate's views on the Central Electricity Generating Board's fuel clad ballooning safety case for the proposed Sizewell B PWR nuclear power station are presented. The Inspectorate's reservations concerning the safety case are discussed and it is emphasised that additional work needs to be done by the CEGB. (U.K.)

Sizewell B

International Nuclear Information System (INIS)

1983-03-01

The safety case relating to protection against the effects of earthquakes is discussed for the proposed Sizewell B nuclear power station. Conclusions on sensitivity studies of events beyond the safe shutdown earthquake (SSE) level, on the level of permissible stresses arising from SSE loads, on the pre-qualification approach to operating basis earthquake or operational shutdown earthquake loads, and on the absence of offshore tectonic features that might influence the seismicity of the Sizewell site are described. Additional work is required on load combinations and the provision of an external hazards trip. (UK)

Sizewell B

International Nuclear Information System (INIS)

1983-07-01

An assessment of human factors topics, which are of significant importance to safety, is discussed with respect to design, construction and operation of the proposed Sizewell B nuclear power station. CEGB expertise in ergonomics and fault studies are described. Outstanding issues are identified and a programme of additional work is discussed. (U.K.)

Radioactivity in the vicinity of Sizewell nuclear power station: marine environmental monitoring, 1983

International Nuclear Information System (INIS)

Hunt, G.J.

1984-01-01

Regular monitoring of radioactivity in the aquatic environment of the British Isles has continued. A report presents the results of this program in relation to the Sizewell nuclear power station for 1983, so as to supplement the most recently available full report which is for 1982. (author)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Arnold, P.J.

1982-11-01

The systems benefits of the selection of the Sizewell site for a PWR power station are dealt with. The transmission modifications which would be needed to provide effective connection of this station to the system are considered. (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Hawes, F.B.

1982-11-01

The biological consequences of using a direct cooled system at the proposed Sizewell B power station are dealt with. Problems caused by the impingement of organisms on the fine-mesh screens through which the water is pumped, by the entrainment of smaller organisms in the flow through the cooling system and by the discharge of warmed chlorinated water into the sea are discussed. The chlorination of cooling water is described. (U.K.)

Sizewell B

International Nuclear Information System (INIS)

1983-03-01

The probability of an aircraft crash on the proposed Sizewell B nuclear power station leading to a significant release of radioactivity is discussed. The aircraft considered are all types of civil and military fixed wing aircraft and helicopters. It is concluded that the general approach to the safety case for aircraft crash is acceptable. Outstanding issues are identified and a programme of additional work is discussed. (UK)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Wilson, A.

1982-11-01

The methods of establishing construction time, capital cost, availability and lifetime of different types of generating plant are described. In volume one assessments are presented for a new coal fired station, for a new AGR station and for a new PWR station - Sizewell B. Volume two, contains all diagrams, tables and appendices presented as evidence. (U.K.)

Steam turbine generators for Sizewell 'B' nuclear power station

International Nuclear Information System (INIS)

Hesketh, J.A.; Muscroft, J.

1990-01-01

The thermodynamic cycle of the modern 3000 r/min steam turbine as applied at Sizewell 'B' is presented. Review is made of the factors affecting thermal efficiency including the special nature of the wet steam cycle and the use of moisture separation and steam reheating. Consideration is given to the optimization of the machine and cycle parameters, including particular attention to reheating and to the provision of feedheating, in order to achieve a high overall level of performance. A modular design approach has made available a family of machines suitable for the output range 600-1300 MW. The constructional features of the 630 MW Sizewell 'B' turbine generators from this range are described in detail. The importance of service experience with wet steam turbines and its influence on the design of modern turbines for pressurized water reactor (PWR) applications is discussed. (author)

The structural integrity safety case for Sizewell B power station

International Nuclear Information System (INIS)

Gerachty, J.E.

1993-01-01

This paper presents the safety case approach adopted for the components of the Sizewell 'B' Power Station for which a high degree of structural integrity is required. Such components include the Reactor Pressure Vessel, Steam Generator and Pressuriser for which Incredibility of Failure is claimed. The two parts of the case involve achievement and demonstration of integrity. This is achieved by extensive measures involving design, manufacture, materials and inspection. The demonstration has required a fracture mechanics approach. The specific role of inspection validation and its relation to critical defect size is described. (author)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Mawer, W.T.

1982-11-01

The cooling water system which would be needed for the proposed Sizewell B power station is described. The possible effects upon public safety, local fishing interests and the existing seabed are examined. Studies of the heat dispersion from outfalls, the location of offshore structures and the control of marine growth in the system are reported. Finally the essential service water system, the reserve ultimate heat sink, the discharge of liquid radioactive waste into the sea and the possible use of waste heat for agricultural and fish farming purposes are discussed. (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Healey, T.; Board, S.J.

1982-11-01

The issue of fuel clad ballooning during a postulated large loss of coolant accident is examined. A summary of the evidence which shows that such an event in the proposed Sizewell B nuclear power plant would not lead to violation of the fuel limits laid down in the United States NRC Code of Federal Regulations, 10 CFR 50, Appendix K. The present status of the computer codes BART and TAPSWEL and the validation evidence to demonstrate their adequacy is outlined. (U.K.)

Radiation monitoring at Sizewell B PWR

International Nuclear Information System (INIS)

Hills, O.C.

1992-01-01

Radiation monitoring in Sizewell-B Power Station most significantly differs from that in existing UK Power Stations in two respects: firstly in the large number of on-line radiation monitors and secondly in the way that the monitors are linked into a fully-integrated, centralised data acquisition and display system, which can be accessed and viewed by the operators. An overview is given of how full process data is transmitted along data links between the Auxiliary Shut-Down Room, Technical Support Centre and Main Control Room, enabling Health Physics and other staff to access information from any radiation monitor. The permanently installed monitors together with the safety category, type and location are listed. As part of the Sizewell-B Process Plant control and instrumentation contract, NEI is to supply the Health Physics Instrumentation (HPI) and Process and Effluent Activity Monitoring System (PEAMS) (excluding the Primary Protection System) plus the Nuclear Sampling System (NSS). This paper concentrates on the HPI, and parts of the PEAMS and NSS for which NEI have the responsibility for system design, detail design, manufacture, site installation and commissioning. Section 2 briefly describes the sources of radiation at Sizewell-B; Sections 3, 4 and 5 describe the PEAMS, HPI and NSS respectively. Section 6 details the design of two of the Sizewell-B PEAMS subsystems. (Author)

Sizing up Sizewell

International Nuclear Information System (INIS)

Woolf, G.

1993-01-01

Sizewell-B nuclear power plant should start to generate electricity in mid-1994. In this article Nuclear Electric makes a case for starting the Sizewell-C project, a 2260 MW twin pressurized water reactor design, before the Sizewell-B project team is disbanded. Sizewell-B has provided a large number of jobs, many for local people, and these will disappear unless Sizewell-C is started. Money would be saved through repeat orders for major plant items and development costs would be spread between the two projects. The capitalized cost of Sizewell-C is estimated at Pound 3.45b with generating costs estimated at 3p/KWh, less than other generating plants. Sizewell-C would also save the carbon dioxide emissions from gas- or coal-fired generating stations. (UK)

Sizewell B

International Nuclear Information System (INIS)

1983-07-01

The design strategy for keeping all exposures of persons to ionising radiations as low as is reasonably practicable (ALARP) is discussed for the proposed Sizewell B nuclear power station. The safety assessment objectives are discussed together with economic factors, choice of primary circuit materials to minimise the formation of crud, operational chemistry, filtration, decontamination, design modifications and radioactive waste management. It is concluded that a significant attempt has been made to quantify design decisions in respect of the ALARP strategy for dose reduction. A programme of additional work is discussed. (U.K.)

Development of operator training programmes for Sizewell B

International Nuclear Information System (INIS)

Birnie, S.

1988-01-01

In accordance with existing practice, it is the Central Electricity Generating Board's (CEGB's) intention that the station manager of Sizewell B and future pressurized water reactor (PWR) stations will be responsible for ensuring that his staff perform their designated duties competently. To assist the station managers in fulfilling these responsibilities, the CEGB ensures that all nuclear training needs are identified, effective training strategies are developed and training programmes provided. The management, operation and development of the CEGB Nuclear Power Training Centre is integrated with nuclear power training activities conducted on site and at other locations. A systematic approach to training must be used so that the training is effective, i.e. that the staff can operate the plant safely and economically. To aid in the systematic production of PWR training programmes in general, but in particular for shift operations engineers, a PWR section was established in 1983 at the CEGB Nuclear Power Training Centre. A condition in the site licence for Sizewell B states that a suitable simulator must be available for training operations staff at least one year before fuel loading commences. The work of this section in operations engineer training is summarized. (author)

Main unit electrical protection at Sizewell 'B' power station

International Nuclear Information System (INIS)

Fischer, A.; Keates, T.

1992-01-01

For any power station, reliable electrical protection of the main generating units (generators plus generator transformers) has important commercial implications. Spurious trips cause loss of generation and consequent loss of revenue, while failure to rapidly isolate a fault leads to unnecessary damage and again, loss of generation and revenue. While these conditions apply equally to Sizewell B there are additional factors to be taken into consideration. A spurious trip of a main generating unit may lead to a trip of the reactor with an associated challenge to the shutdown and core cooling plant. The generator transformers, besides exporting power from the generators to the 400 kV National Grid, also import power from the Grid to the 11 kV Main Electrical System, which in turn is the preferred source of supply to the Essential Electrical System. The Main Unit Protection is designed to clear generator faults leaving this off-site power route intact. Hence failure to operate correctly could affect the integrity of the Essential Electrical Supplies. (Author)

Proof of evidence by National Nuclear Corporation Limited for Sizewell 'B' public inquiry

International Nuclear Information System (INIS)

Franklin, N.L.

1983-02-01

The history, experience and capability of National Nuclear Corporation Limited (NNC) and the requirements for the Sizewell B PWR project are reviewed. A Joint Project Team comprising staff from NNC, Westinghouse, Bechtel and the CEGB has been formed to develop the design of the station and the safety case. It is concluded that Sizewell B will be economic in its own right and will equip NNC with expertise, experience and resources in PWR technology. The construction of Sizewell B will provide the experience on which future PWR projects can proceed with confidence. (U.K.)

Statement for Sizewell 'B' public inquiry

International Nuclear Information System (INIS)

1982-07-01

The formation of National Nuclear Corporation Limited (NNC) is discussed together with its acquisition of staff with nuclear experience, the main contracts which it has performed or is performing, its present corporate structure and the organisation by projects and functions through which it discharges its current obligations. Information concerning NNC's experience in water reactor design and technology; its most recent contribution to assist the Government in making its decisions with respect to the type of reactor upon which the UK nuclear programme should be based; technical agreements it has reached with US organisations; the nature of the work on Sizewell B which is currently being done and the arrangements made for doing it; the implications of building Sizewell B on export prospects and on industry; and NNC's planning to anticipate the possible future requirements for PWR power stations is provided. (U.K.)

Sizewell: proposed site for Britain's first PWR power station

International Nuclear Information System (INIS)

1980-10-01

The pamphlet covers the following points, very briefly: nuclear power - a success story; the Government's nuclear programme; why Sizewell; the PWR (with diagram); the PWR at Sizewell (with aerial view) (location; size; cooling water; road access; fuel transport; construction; employment; environment; screening; the next steps (licensing procedures, etc.); safety; further information). (U.K.)

Load shedding and emergency load sequencing system at Sizewell B power station

International Nuclear Information System (INIS)

Bowcock, S.; Miller, D.

1992-01-01

Sizewell B Nuclear Power Station has a main electrical system that connects together the main turbo-generators, generating at 23.5kV, the 400kV grid and the auxiliary equipment required to operate the station. A separate essential electrical system fed from the main electrical system, supplies all the auxiliaries required to shut-down the nuclear reactor and maintain it in a safe shut-down condition. For safety reasons four similar independent essential electrical systems are provided, each headed by a 3.3kV switchboard and a stand-by 8MW diesel generator. Feeds from the 3.3kV switchboards in turn supply the essential 3.3kV drives and transformer fed 415V essential switchboards. The function of the Load Shedding and Emergency Load Sequencing (LSELS) System is to monitor the condition of the 3.3kV incoming supply from the main electrical system to each essential 3.3kV switchboard and initiate its replacement, with the supply from the associated diesel generator, if it is outside set parameters. In order to achieve this transfer the essential electrical system load must be reduced to a level which the diesel can accommodate as a standing load and then allow the sequenced reconnection of required loads so as not to overload the diesel. The LSELS equipment is categorised as Safety Category 1E and has a significant importance to the safe operation of the power station. Therefore the design of the system must be highly reliable and the purpose of this paper is to detail the design approach used to ensure that a high system reliability is achieved. (Author)

Sizewell 'B' PWR pre-construction safety report

International Nuclear Information System (INIS)

1982-04-01

The Pre-Construction Safety Report (PCSR) for a PWR power station to be constructed as Sizewell 'B' is presented in 13 volumes containing 16 chapters. The PCSR has been submitted to the Nuclear Installations Inspectorate in support of the Central Electricity Generating Board's application for consent to the extension at Sizewell. It describes the design and provides the safety case for the proposed station, which comprises a 4-loop pressurized water reactor with associated generating plant and supporting auxiliary equipment. A general description of the station and its site is given. The strategy for ensuring nuclear safety is set out and the general design aspects of systems and plant outlined. The plant and systems, including their safety design bases and the fault analyses carried out for the design are described. Finally the way in which the plant will be decommissioned at the end of its useful life is outlined. (U.K.)

Sizewell: UK power demand

International Nuclear Information System (INIS)

Anon.

1986-01-01

The Sizewell Inquiry was about whether the next power stations to be built in the UK should be nuclear or coal and, if nuclear, PWRs or AGRs. During the period of the Inquiry forecasts of demand for electricity were low. Now, however, it seems that the forecast demand is much increased. This uncertainty in demand and the wide regional variations are examined in some detail. Facts and figures on electricity sales (area by area) are presented. Also the minutes of supply lost per consumer per year. These show that security of supply is also a problem. It is also shown that the way electricity is used has changed. Whilst electricity generation has been changing to large-scale, centralised power stations the demand patterns may make smaller scale, quickly-constructed units more sensible. The questions considered at the Sizewell Inquiry may, indeed, no longer be the right ones. (UK)

Description of Sizewell B nuclear power plant

International Nuclear Information System (INIS)

Meyer, G.; Stokke, E.

1997-09-01

The intention of this report is to present a condensed technical description of Sizewell B in a language understandable to non-technical personnel. It is unavoidable that some parts will be less precise than the technically initiated would like to see, but hopefully the content still give a realistic picture of Sizewell B. The technical description is based on publicly available material, of which the Sizewell B safety report has been particularly useful. Nearly all figures and drawings found in this description are reproductions of corresponding material in the safety report. To keep the description from becoming too voluminous it has been necessary to condense some background material down to a small volume. Hopefully this has not introduced any errors or inaccuracies, possible oversimplification at certain points must be weighed against the wish to cover most of the topics in the agreed table of contents for these NKS reports. (au)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Jenkin, F.P.

1982-11-01

The CEGB's planning and assessment procedures relating to Sizewell B are explained. The various bases of need for new generating plant capacity are outlined. These are: capacity requirement; provision of economic generating capacity; security of fuel supplies; making provision for future investment options. A detailed case for Sizewell B is then presented, including an assessment of risk and uncertainty. (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Wright, J.K.

1982-11-01

A general description of the nuclear fuel cycle for PWRs and AGRs is given. The details of the fuel cycle for Sizewell B are explained and its cost is analysed against a specific set of background assumptions. Then, in less detail, an evaluation of PWR fuel cycle costs is presented against a wide range of background assumptions. The cost of the AGR fuel cycle is analysed. Finally the uncertainties in the results obtained are considered. (U.K.)

An analysis of the Sizewell B inquiry

International Nuclear Information System (INIS)

Anon.

1986-01-01

The public inquiry into the Central Electricity Generating Board's application to build the first PWR reactor in the United Kingdom (at Sizewell) ranged beyond that particular issue to a more general investigation of the desirability of promoting nuclear power generally. The CEGB's case is presented briefly. The four main arguments are security of electricity supply, diversity of supply, the benefits of PWRs as opposed to AGRs and cost savings. This latter was important to justify not only the need case, but the economic case for Sizewell-B. The economic case included five computed scenarios over a range of the proposed station's capital, fuel and related operating costs, set against three 'no-nuclear', 'medium nuclear' or 'high nuclear' backgrounds. The CEGB figures are compared with those from objectors. The main arguments are outlined. Other political and technical arguments were not examined in depth by the Inquiry. (UK)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Passant, F.H.

1982-11-01

The radioactive wastes expected to arise at the proposed Sizewell B PWR are identified. The plant provided to collect, process, store and dispose of the wastes is described. The quantities and activities of wastes for disposal are derived. The proposed methods of transport and disposal are described. Wastes which would arise from reprocessing and from decommissioning Sizewell B are discussed. Finally some of the radiological aspects of waste disposal are outlined. (U.K.)

Economic issues of the Sizewell B public enquiry

International Nuclear Information System (INIS)

Foster, C.

1987-01-01

The economic arguments and conclusions reached in the Layfield Report of the Sizewell-B public inquiry are restated. The key test for deciding whether Sizewell-B should be built was the net effective cost per kW per annum (the net cost of supplying electricity from a new power station including capital and operating costs) compared with the net avoidable cost (the cost of withdrawing a plant from the generating system). If the net effective cost is less than the net avoidable cost the construction is economically worthwhile. The effective cost calculations are given. The argument in favour not only had to show that nuclear was economically favourable over coal or any other fuel but that the pressurized water reactor design was preferable to the advanced gas-cooled reactor type. The price of coal, (at the time of the Inquiry and in the future) is tabulated. The changed economic situation between the end of the Inquiry and the publication of the Inquiry Report did not invalidate the decision made. There is only a one in seven chance that a coal-fired station will provide new capacity at lower cost than Sizewell-B. The figures used for CEGB's case to the Public Inquiry are given. (UK)

Can the myth be maintained? - understanding the economics of Sizewell B

International Nuclear Information System (INIS)

Harper, M.

1990-01-01

The cost of electricity generated by Sizewell-B is discussed as this has been the model for the economic arguments in favour of the proposed Hinkley Point C pressurised water station. However, since the Energy Select Committee report concluding that electricity from Sizewell-B will be substantially dearer than from coal-fired stations was published public justification is now expressed in terms of benefits to the environment. Reduction of the greenhouse effect, security of supply and maintenance of the nuclear option are now more important. The economic case is examined. (UK)

Electricity consumers' council statement of case to the Sizewell 'B' power station public inquiry

International Nuclear Information System (INIS)

Barnes, M.

1983-01-01

Of the four arguments used in favour of Sizewell, the ECC considers that the economic benefit case is much the most important. Consumers will need to be convinced above all that Sizewell will help to restrain the growth of electricity prices. Of the other three arguments, plant need is not taken very seriously by the Board, making provision for future investment options hardly appears in the Statement of Case, and fuel diversity - while an important objective - can only be examined properly within the context of long-term investment strategy and relates only marginally to Sizewell as a self-standing project. Because a decision about Sizewell can in any case only be fully evaluated within the context of long-term plant strategy, the ECC has also briefly considered the most important long-term issues - the existence or otherwise of a nuclear programme, the questions surrounding technology acquisition and alternative energy investments - against which the Sizewell decision should be viewed. (author)

Remote filter handling machine for Sizewell B

International Nuclear Information System (INIS)

Barker, D.

1993-01-01

Two Filter Handling machines (FHM) have been supplied to Nuclear Electric plc for use at Sizewell B Power Station. These machines have been designed and built following ALARP principles with the functional objective being to remove radioactive filter cartridges from a filter housing and replace them with clean filter cartridges. Operation of the machine is achieved by the prompt of each distinct task via an industrial computer or the prompt of a full cycle using the automatic mode. The design of the machine features many aspects demonstrating ALARP while keeping the machine simple, robust and easy to maintain. (author)

Sizewell 'dirty tricks'

International Nuclear Information System (INIS)

Martin, Steve.

1987-01-01

The pro-nuclear lobby is accused of dubious tactics to promote their case for the Sizewell-B reactor. These include reassessing future electricity demand which, it is claimed, could only be met by nuclear power, claiming that new power stations were needed to avoid blackouts during cold spells, and the reporting of a major design fault in the control rods of the Torness and Heysham AGR stations. The latter is felt to be related to the promotion by the South of Scotland Electricity Board of the AGR case, as opposed to the Central Electricity Generating Board's advocation of a PWR reactor design. The author argues for a series of coal-fired power stations instead, and a major energy conservation programme. (UK)

ECOS: a configurable, multi-terabyte database supporting engineering and technical computing at Sizewell B

International Nuclear Information System (INIS)

Binns, F.; Fish, A.

1992-01-01

One of the three main classes of computing support systems is concerned with the technical and engineering aspects of Sizewell-B power station. These aspects are primarily concerned with engineering means to optimise plant use to maximise power output by increasing availability and efficiency. At Sizewell-B the Engineering Computer system (ECOS) will provide the necessary support facilities, and is described. ECOS is being used by the station commissioning team and for monitoring the state of some plant already in service. (Author)

Ergonomics and its application to Sizewell 'B'

International Nuclear Information System (INIS)

Singleton, W.T.

1986-01-01

The scope of the ergonomics contribution to the design and operation of power stations is described on the basis of current experience in the CEGB and in other countries. The ergonomics questions which arise in relation to Sizewell 'B' are enumerated in detail. Issues which arise from the point of view of station operation and from the complementary point of view of human behaviour are considered. (author)

Sizewell 'B' power station public enquiry: CEGB statement of case. 2 vols and appendices A-G, H, J, L, M

International Nuclear Information System (INIS)

1982-04-01

This statement of case summarises the case which the CEGB intends to put to the public enquiry into building a PWR reactor at Sizewell. The two volumes are divided into chapters covering an introduction, the Electricity Supply Industry and the CEGB, nuclear development on the CEGB system, new generating plant, the need for Sizewell B and various aspects of safety and design. (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Gittus, J.

1982-11-01

In volume one an analysis is presented of degraded core accidents involving the proposed Sizewell B PWR. Consideration is given to their estimated frequency, the course which they take, the release of radioisotopes from the plant and the radiological consequences of such a release. Volume two contains all the figures, tables and appendices presented as evidence. (U.K.)

The effect of fish impingement at Sizewell 'A' Power Station, Suffolk, on North Sea fish stocks

International Nuclear Information System (INIS)

Turnpenny, A.W.H.; Utting, N.J.; Millner, R.S.; Riley, J.D.

1988-04-01

Samples collected from the cooling water intake screens of Sizewell 'A' power station over a 12 month period contained 73 species of fish. Of these, only 20 species were present on more than 50% of sampling dates and only 7 commercially exploited species were caught in quantities of more than a few hundred over the year; namely sprat, herring, cod, whiting, sole, dab and plaice. These species formed the basis of analysis of the impact of the Power Station on commercial species. Commercial species found in the Sizewell area are part of major North Sea stocks. The impact of the losses due to the Power Station is spread over these stocks, hence the effect is minimal. The mortality rate caused by the Power Station is one thousandth to one hundred-thousandth, depending on species, of that caused by commercial fishing and the effect is less than that of a small, inefficient commercial trawler. (author)

Sizewell 'B' PWR reference design

International Nuclear Information System (INIS)

1982-04-01

The reference design for a PWR power station to be constructed as Sizewell 'B' is presented in 3 volumes containing 14 chapters and in a volume of drawings. The report describes the proposed design and provides the basis upon which the safety case and the Pre-Construction Safety Report have been prepared. The station is based on a 3425MWt Westinghouse PWR providing steam to two turbine generators each of 600 MW. The layout and many of the systems are based on the SNUPPS design for Callaway which has been chosen as the US reference plant for the project. (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Gammon, K.M.

1982-11-01

The site selection and site specific aspects of the proposal to build Sizewell B PWR are dealt with. A description of the site and its surroundings is followed by physical and technical details of the proposed development. Consultations with statutory authorities, environmental and other local issues are discussed. Finally population distribution around the site and the way in which this could be controlled are considered. (U.K.)

Hinkley Point 'C' power station public inquiry: proof of evidence on safety criteria

International Nuclear Information System (INIS)

Taylor, R.H.

1988-09-01

A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom. The policy is to replicate the Sizewell ''B'' PWR design which was accepted as safe by an earlier enquiry. In this evidence to the Inquiry, subsequent developments are examined with a view to determining whether these would reverse the Sizewell decision. They are: the possible revision of radiation risk estimates upwards; whether cases of leukaemia occur with greater frequency around nuclear sites than elsewhere; publication of the Health and Safety Executive's consultative document ''The Tolerability of Risk from Nuclear Power Stations''. The overall conclusion is that these developments do not undermine the findings of the Sizewell ''B'' inquiry or the validity of the CEGB's safety criteria. (author)

An exploratory study of the local socio-economic effects of Sizewell B

International Nuclear Information System (INIS)

1982-12-01

This Sizewell B study involved five main tasks: (i) to provide broad estimates of the temporary and permanent accommodation requirements of the proposed Sizewell B workforce and families and the likely level of local supply of accommodation; (ii) to provide broad estimates of the requirements for school places of the accompanied workforce and the likely local supply of such places; (iii) to assess further the wider employment effects of the proposed development on local firms, particularly as potential suppliers of goods and services; (iv) to conduct further studies of the expenditure patterns of power station employees; and (v) to incorporate where relevant the likely effects of a policy of double day shift work (in power station construction) into the predictions. Results of the study are reported. (author)

Electronic document management at Sizewell B

International Nuclear Information System (INIS)

Rippon, Simon.

1996-01-01

Sizewell ''B'', Britain's first PWR, officially opened on March 25 1996, will now rely for its document management on a sophisticated computer-based system. One of the largest single engineering projects ever to be commissioned on one site in Britain, Sizewell ''B'' accommodates more than 300,000 documents, including over 200,000 drawings. The electronic document management system will provide a number of important benefits, including a more direct method of maintaining the station's Configuration Management and hence maintaining high safety standards; improved turnaround in plant modification proposals (PMP); significant time and cost savings in managing vital records; and increased productivity. (Author)

Designing power transformers for Sizewell 'B' as quality products

International Nuclear Information System (INIS)

White, A.; Poole, C.W.

1992-01-01

At the beginning of 1990, Nuclear Electric plc., then a Division of the CEGB, placed a contract with GEC ALSTHOM Transformers Limited of Stafford for the design, supply and installation of the main transformers for the Sizewell B electrical system. The following transformers are being provided under this contract; two Generator Transformers, two Station Transformers, two Unit Transformers and two Fault Limiting Reactors. The main objective of this paper is to describe the quality assurance philosophies applied to the design of these transformers to ensure that the performance requirements were met in full and to describe how these philosophies were converted into a practical working system. The paper does not set out to present a detailed technical appreciation of the transformers themselves but rather, to demonstrate that by addressing quality in the design and design processes, reliable and efficient items of high value, capital equipment result from the partnership in quality between supplier and customer. (Author)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Gregory, A.R.

1982-11-01

The procedure for decommissioning a CEGB nuclear power station is described. Regulatory and licensing procedures in the UK are first listed. The principal sources of radioactivity in the station after final shutdown are classified. The three stages of the decommissioning procedure are then described. Finally the following topics are dealt with briefly: the management of decommissioning wastes, radiological protection during the operation, possible faults arising having radiological significance, design for decommissioning and costs. (U.K.)

Vacuum switchgear for power station auxiliary switchboards

International Nuclear Information System (INIS)

Coombs, P.E.

1992-01-01

Sizewell B is the first UK power station in which vacuum switchgear is used for the auxiliary switchboards. Previously the 3.3kV, 6.6kV or 11kV switchgear has used air-break circuit breakers and fused air-break contactors, known as motor starting devices or fused switching devices (FSD). The use of vacuum interrupters is therefore a new technology in this application, although it has been established in the UK distribution network and in industrial installations from the mid 1970s. Vacuum switchgear was already in use in the USA for power station auxiliary switchgear at the time that it was proposed for Sizewell B. The Sizewell B high voltage auxiliary switchgear comprises eight Unit and Station Auxiliary Switchboards at 3.3kV and 11kV, and four 3.3kV Essential Switchboards for the essential safety related circuits, making a total of 65 circuit breakers plus FSD panels. (Author)

Sizing up Sizewell

International Nuclear Information System (INIS)

Anon.

1983-01-01

The CEGB proposal to build a PWR nuclear power plant at Sizewell, in Suffolk, is discussed under the headings: paying for power (economics of Sizewell); paying for capital (high capital cost of nuclear power plants); paying for delays (effects of construction delays and design changes to meet safety requirements); paying for coal (circumstances in which a fossil-fuel power plant would be less costly than expected); playing for time (advantage argued for postponing Sizewell's construction while pressing on with an energy conservation programme). (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Pepper, R.B.

1982-11-01

The practice of radiological protection within the CEGB is described. Health physics at nuclear power stations is discussed. Radiation exposure of operational staff at a PWR and radiation exposure of members of the public are considered. Finally arrangements for dealing with radiological hazards arising during a site emergency are described. (U.K.)

The future of nuclear power after Sizewell B. 3 v.: v. 1 Economic issues; v. 2 Environmental and safety issues; v. 3 Public perception issues

International Nuclear Information System (INIS)

1987-01-01

The three days of conference proceedings are published in three separate volumes. The first includes 7 papers relating to economic issues - those presented at the Sizewell-B public inquiry and the changes in the economic situation since the inquiry ended. The electricity demand, how this demand is to be met by nuclear and other fuel sources and how energy conservation might be an economic alternative to simply building more generating capacity are all issues discussed. The possible privatisation of the industry is also touched on. Volume two has 8 papers concerned with environmental and safety issues. These include the influence of the Sizewell-B decision on nuclear licensing and reactor safety, the technical and safety aspects of pressurized water reactors (PWR), the roles of British Nuclear Fuels and the United Kingdom Atomic Energy Authority, and radiation protection and effluent discharge control. The six papers in volume 3 look at public perception issues - not only towards nuclear power but towards the public inquiry process. The local authority view, the Friends of the Earth case against the PWR, and technical expertise in the decision process are also topics covered. All the papers are indexed separately. (UK)

Software change control in the Sizewell B ISCO

International Nuclear Information System (INIS)

Johnson, A.

1997-01-01

Central to the control and instrumentation system of the Sizewell B nuclear power plant is a control, data acquisition and control system based on a distributed network of several hundred microprocessors. The system has been integrated into a single functional unity, and software modifications affecting one part of it have an effect on the other parts. The software modification and configuration processes are therefore kept as similar as possible. (A.K.)

The collapse of nuclear power

International Nuclear Information System (INIS)

Jeffery, J.W.

1991-01-01

The decision of the UK government of 9 November 1989, withdrawing all nuclear stations from privatization and cancelling the three PWRs which were to have followed on from Sizewell B, was a shattering blow to the nuclear industry. The reversal (at least temporarily) of decades of government support for nuclear power, and the figures which were becoming available of its relatively high-cost (confirmed by the levy on electricity sales to subsidize nuclear and other non-fossil generation), caused the House of Commons Energy Select Committee to conduct the inquiry culminating in its Report The Cost of Nuclear power. (author)

Torness and Hunterston - as uneconomic as Sizewell B

International Nuclear Information System (INIS)

Jeffery, J.W.

1986-01-01

The admission by CEGB that Sizewell B would be uneconomic under conditions postulated in the evidence given by the present author at the Sizewell Inquiry, is used to show that Torness and Hunterston AGRs have almost no chance of being economic, because the large immediate increases in postulated real coal prices required to enable Torness to produce a lifetime surplus, have not materialized. The attempt of SSEB to conceal the fact that it postulated this large increase in real coal prices in order to make Torness appear to be economic, is described and exposed. The joint practice of CEGB and SSEB of discounting long-term nuclear costs so that they make no significant contribution to the final calculated unit cost is described. Finally, the recent document, explaining the SSEB's case for keeping the AGR, is analysed and characterized as 'one of the most misleading documents on the economics of nuclear power to be seriously presented to the public'. (author)

The UK nuclear programme: The Sizewell experience

International Nuclear Information System (INIS)

Salter, W.B.

1990-01-01

The current status of the Sizewell 'B' PWR programme and the effect on it of the proposed privatisation of U.K electricity generation is reviewed. Departures from and additions to the Standard Nuclear Unit Power Plant System (SNUPPS) reference plant design are given. These include Reactor Coolant System overpressure protection and the addition of an Emergency Charging System and an Emergency Boration System. Improvements in monitoring Reactor Coolant System water level during refuelling and maintenance shutdown operations are presented. (author)

Sizewell 'B' public inquiry

International Nuclear Information System (INIS)

Barritt, E.E.

1982-11-01

The report falls under the headings: introduction (need/economics; safety; waste management; local and site specific issues); the Sizewell site - history and planning policies; planning and environmental implications; land use and landscape implications; ecological implications; mineral requirements; highway implications; employment implications; accommodation implications; infrastructure and social/community services; safeguarding restrictions for Sizewell - Nuclear Installations Inspectorate; decommissioning. (U.K.)

Reactor choice - the merits of Sizewell follow-up and longer-term options

International Nuclear Information System (INIS)

Smith, P.

1994-01-01

During 1994 Sizewell B will be completed, a contractor will be selected for the Lungmen Project in Taiwan and the Nuclear Review will hopefully clear the way for continuing PWR construction in the UK. Once the Government has sanctioned the next nuclear station, the choice of plant will fall to Nuclear Electric. Consideration of the available options demonstrates clearly that for the short and medium term only Sizewell C, a twin replica of Sizewell B, provides the low-risk option essential to attracting private finance. The UK has built up the design, manufacturing and construction capability necessary to build the Sizewell C design, both in the UK and overseas. However, there is only a limited window of opportunity to exploit these capabilities since they will decay unless sustained by continuing orders. (author)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Wright, J.K.

1982-11-01

A description is given of the CEGB's current assessment of the potential contribution to electricity generation of those methods considered to be the most significant alternatives to conventional power stations or thermal nuclear reactors for generating electricity. The state of development of the technology, the timescale on which it could be developed, its ability to generate electricity reliably and the cost of generating electricity are some of the matters considered. The following topics are covered: potential developments in coal fired generating plant; combined heat and power generation; energy storage; electricity generation from renewable energy sources; fast reactors and fusion. (U.K.)

The application of the ALARP principle to the design of nuclear power stations

International Nuclear Information System (INIS)

Pugh, I.G.; Eaton, J.R.P.; Dutton, L.M.C.; Youell, F.P.

1987-01-01

A summary is given of the numerical fundamental design criteria specified to ensure nuclear reactor safety; these numerical criteria are compared to ICRP dose limits in order to demonstrate the important role of the criteria in achieving 'ALARP'. The design strategy which has been applied to both AGR and PWR power stations to ensure compliance with the design criteria and guidelines is described. The application of the strategy to Heysham II/ Torness and Sizewell 'B' demonstrates its effectiveness. Details of radiation exposures to operators and the public both in normal operation and following accidents are given including examples of cost-benefit analysis studies. (UK)

A local authority view of the Sizewell B decision and the role of the public enquiry

International Nuclear Information System (INIS)

Ayre, D.

1987-01-01

The background to the Sizewell-B public inquiry is presented. The local authorities are important in this as it was they who first received the Central Electricity Generating Board's request to build Sizewell-B and who triggered the need for a Public Inquiry. The local authorities did not object in principle to the use of the Sizewell site for additional nuclear power generation provided the Government was satisfied that there was a national need for the extra capacity. In future inquiries there might not be acceptance in principle which would change the nature of the Inquiry. The local authority involvement in the public inquiry is discussed under the headings: need and economics, safety and local environment issues. The relevant parts of the Sizewell-B report are considered. The Secretary of State's decision, which follows the Inspector's report, justifies the confidence put in the inquiry process by the local authorities. Concern is expressed, however, that extra financial help is needed to pay for the local authorities expenditure on the Inquiry and also for the consequences of the Sizewell-B project itself. (U.K.)

The industrial impact of Sizewell 'B'

International Nuclear Information System (INIS)

1988-01-01

The paper is a report on the industrial impact of post-Sizewell nuclear reactor policy, as presented by a Working Group set up by the United Kingdom Advisory Council on Applied Research and Development. The primary objective of the Working Group was the quantification of the effects of the introduction of a non-UK design of reactor upon employment, the availability of skilled resources, and on imports and exports. The subject is discussed under the topic headings:-the effect of Sizewell-'B' on UK manufacturing industry, skilled resources, safety, reactor design choice, and replication of the PWR. (U.K.)

Operational experience with the Sizewell B integrated plant computer system

International Nuclear Information System (INIS)

Ladner, J.E.J.; Alexander, N.C.; Fitzpatrick, J.A.

1997-01-01

The Westinghouse Integrated System for Centralised Operation (WISCO) is the primary plant control system at the Sizewell B Power Station. It comprises three subsystems; the High Integrity Control System (HICS), the Process Control System (PCS) and the Distributed Computer system (DCS). The HICS performs the control and data acquisition of nuclear safety significant plant systems. The PCS uses redundant data processing unit pairs. The workstations and servers of the DCS communicate with each other over a standard ethernet. The maintenance requirements for every plant system are covered by a Maintenance Strategy Report. The breakdown of these reports is listed. The WISCO system has performed exceptionally well. Due to the diagnostic information presented by the HICS, problems could normally be resolved within 24 hours. There have been some 200 outstanding modifications to the system. The procedure of modification is briefly described. (A.K.)

Sizewell B nuclear power station: the basis for the decision by the Health and Safety Executive to grant consent to load fuel into the reactor

International Nuclear Information System (INIS)

1994-01-01

The licensing and consent process and the basis for granting a consent for Nuclear Electric to load fuel into the Sizewell B reactor in the United Kingdom are explained. Consent was granted by the UK Nuclear Installations Inspectorate on behalf of the Health and Safety Executive on satisfactory completion of construction and those commissioning stages needed to proceed safely, and the production of a satisfactory safety case. A summary of the assessment of the safety case is appended. It covers the reactor core, coolant system structural integrity, engineered safety features, main and essential electrical system, control and instrumentation, radioactive waste management, radiological protection, fuel storage and handling, civil works and structures, fault analysis, human factors, hazard analysis, quality assurance, and decommissioning. (UK)

Ultimate load model test for Sizewell 'B' primary containment

International Nuclear Information System (INIS)

Crowder, R.

1988-01-01

This paper considers the factors influencing the adoption of an ultimate load factor for the Sizewell 'B' PWR primary containment structure. As part of the validation process for the ultimate load analysis method, a proposal has been made by Nuclear Design Associates to build and test a 1/10th scale model of the containment structure, which would proceed following the granting of section 2 consent for Sizewell 'B'. The modelling principles, construction method and test proposals are examined in some detail. The proposal is currently being considered by the CEGB's Project Management Team. (author)

1994 - Starting a new era for nuclear power in Great Britain

International Nuclear Information System (INIS)

Collier, J.G.

2004-01-01

A gap is opening up between what the world would like to consume in terms of energy and what the world's environment can sustain. To bridge this gap a much greater contribution from nuclear and renewables is needed to limit the emission of CO 2 and other harmful gases. Plans already laid in some Pacific Rim countries recognise this need and nuclear energy is expected to grow rapidly in this region over the next 20-30 years. For Pacific Rim countries without plentiful indigenous fossil fuel resources, nuclear power is the most economic form of electricity generation, minimising the need for expensive imports and strengthening security of energy supply. Nuclear power already makes a significant contribution to reducing emissions in other regions, especially Europe. Well over a third of electricity in Europe comes from nuclear power. In the UK the figure is nearer a quarter and rising. If nuclear power is to fulfil its role as a key part of UK energy supply into the 21st century, we need to maintain our existing capacity as our older plant retires by building further, modern PWRs. Central to our future is Sizewell B power station - the UK's first PWR. Construction is complete and commissioning is well under way. The project is nearing completion - ahead of time and under budget. The success of Sizewell B is the foundation for the future of nuclear power in the UK. Stations based on the Sizewell design will become the workhorses of our utility. Already Nuclear Electric has submitted a planning application to construct Sizewell C. This is a technical replica of Sizewell B in twin reactor form with a net output of around 2600MW. And this design also has strong export potential. Westinghouse and Nuclear Electric have submitted a joint-vender to build a PWR here in Taiwan. Our bid is based on the Sizewell design; an innovative, safe and proven nuclear power plant design for supplying reliable low-cost electricity for the Republic of China's growing economy. The Sizewell

The place of nuclear power on the CEGB system

International Nuclear Information System (INIS)

Jenkin, F.P.

1987-01-01

This paper discusses the developments in the Central Electricity Generating Board's programme of nuclear generation of electricity since the Sizewell-B inquiry. In particular, recent trends in electricity demand growth are discussed. An average growth in both electricity sales and peak demand of over 1.5%pa during the next ten years is predicted, so that by the mid-1990s an additional 5GW capacity will be needed. Energy conservation is one factor taken into consideration when estimating demand. The need for new capacity is illustrated graphically. With the closure of old plant the new generating capacity needed by 2000 is estimated at 13GW with Sizewell-B supplying 1.2GW of this. This demand will be met by construction of both nuclear and coal fired stations. As the demand increase is greater in the south of Britain than in the north, more of this new generating capacity will be built in the south. The CEGB policy is to build four or five Pressurized Water Reactors the same as Sizewell-B. The sites under consideration for new nuclear stations are shown. They are Hinkley Point, Winfrith, Dungeness, Sizewell, Trawsfynnedd, Wylfa and Druridge. (UK)

Sizewell B: the anatomy of an inquiry

International Nuclear Information System (INIS)

O'Riordan, T.; Kemp, R.; Purdue, M.

1987-01-01

The Economic and Social Research Council has studied four major environmental public inquiries, including Sizewell-B. This report summarizes some of the observations of the Sizewell Inquiry Review Project which has been analyzing the context, content and conduct of the Sizewell-B Inquiry. Although public inquiries in Britain have an important function in building public trust in planning decisions where opinions are divided and independent advice is needed, one outcome of the Sizewell-B Inquiry may be a streamlining of the inquiry process, eg by prior examination of policy matters, leaving the Inquiry to consider specifically site-related matters only. (UK)

Nuclear power now and in the future

Energy Technology Data Exchange (ETDEWEB)

Collier, J G [Nuclear Electric (United Kingdom)

1991-08-01

The future of the nuclear industry in the United Kingdom is considered from the perspective of the new public sector utility, Nuclear Electric, set up to retain control of nuclear power stations on the privatization of the rest of the electricity supply industry. Two major objectives are the increased nuclear generation of electricity and the cutting of costs. These are discussed in terms of life extension programmes for the magnox reactors, improved performance of AGR reactors and expectations for the Sizewell B PWR station now under construction; waste management, reactor decommissioning and fuel-cycle costs are also considered. Economic, environmental and political criteria are outlined which need to be addressed in relation to the government's review of nuclear power in 1991. Because of the marginal economic advantages of nuclear power in the United Kingdom, it will be important to quantify the environmental and diversity benefits of this source. (UK).

The training and assessment of operations engineers at Hinkley Point 'B' nuclear power station

International Nuclear Information System (INIS)

Walsey, B.A.; Howard, J.D.

1986-01-01

The Nuclear Power Training Centre at Oldbury-on-Severn was established to provide a common training of staff at all nuclear power stations operated by the Central Electricity Generating Board, following the ''Standard Specification for the Nuclear Training of Staff at CEGB Nuclear Power Stations''. The paper deals with the following aspects of AGR Stations: The Legislation applicable to these stations. The current training requirements for Operations Staff. The development of training for operations staff at Hinkley Point 'B' including training for career progression within the Operations Department. A detailed explanation of the training package developed for Reactor Desk Drivers at Hinkley 'B'. Revision training of Operations staff to ensure that they continue to run the plant in a safe and commercially viable manner. The training of Shift Operations Engineers for their duties under the Station Emergency Plan. (author)

The design and management of cables and supporting steelwork systems for Sizewell 'B'

International Nuclear Information System (INIS)

Kerry, L.P.

1992-01-01

Sizewell B Power Station has over 33,000 cables connecting in excess of 20,000 items of equipment. Over 120 cable types are used. Many cables supply power to, or monitor, safety category 1 equipment essential to the safe operation of the Reactor and supporting systems. Cables must be designed to survive the postulated hazards of Reactor systems fault, earthquake, fire and radiation exposure. The cable network is the nerve system of the station; its role is to distribute electrical power and control indication, metering and protection signals to the various items of plant and equipment under normal and emergency operating conditions. To perform these functions satisfactorily a new range of cable insulations had to be developed and supporting steelwork designed to withstand the effect of an earthquake. The 63 month Sizewell B construction programme means record cable laying and completion rates have to be achieved needing careful and detailed planning from design to installation. As with electrical equipment, cables are designated either essential (to Reactor safety operation) or non-essential. This paper describes the required safety design criteria, how these are achieved and the design approaches to seismically qualified supporting steelwork. Also described are the cable design, scheduling, routing and planning processes which lead to the required installation and commissioning activities being completed in a controlled and timely manner. (Author)

Validation of Sizewell ''B'' ultrasonic inspections -- Messages for performance demonstration

International Nuclear Information System (INIS)

Conroy, P.J.; Leyland, K.S.; Waites, C.

1994-01-01

At the time that the decisions leading to the construction of the Sizewell ''B'' plant were being made, public concern over the potential hazards of nuclear power was increasing. This concern was heightened by the accident at USA's Three Mile Island plant. The result of this and public pressure was that an extensive public inquiry was held in addition to the UK's normal licensing process. Part of the evidence to the inquiry supporting the safety case relied upon the ability of ultrasonic inspections to demonstrate that the Reactor Pressure Vessel (RPV) and other key components were free from defects that could threaten structural integrity. Evidence from a variety of trials designed to investigate the performance capability of ultrasonic inspection revealed that although ultrasonic inspection had the potential to satisfy this requirement its performance in practice was heavily dependent upon the details of application. It was therefore generally recognized that some form of inspection validation was required to provide assurance that the equipment, procedures and operators to be employed were adequate for purpose. The concept of inspection validation was therefore included in the safety case for the licensing of Sizewell ''B''. The UK validation trials covering the ultrasonic inspections of the Sizewell ''B'' PWR Reactor Pressure Vessel are now nearing completion. This paper summarizes the results of the RPV validations and considers some of the implications for ASME 11 Appendix 8 the US code covering performance demonstration

The validation of corrosion inhibitors for ancillary cooling systems at Sizewell B PWR

International Nuclear Information System (INIS)

Allan, S.J.; Garnsey, R.; Lawson, W.F.

1994-01-01

Sizewell B has several low temperature ancillary cooling circuits for removing low grade heat. One of the principal circuits is the Component Cooling Water System (CCWS) primarily constructed from carbon steel pipework but also containing stainless steel, titanium, copper and cupronickel components. Linked to the CCWS is another carbon steel system namely the Reserve Ultimate Heat Sink (RUHS) a system unique to Sizewell B providing an independent heat removal capability for the CCWS as a safety back-up. Both systems utilize demineralized water with the addition of an inhibitor to prevent corrosion. The vendor recommended inhibitor namely potassium chromate is highly toxic to marine life and initial discussions with the regulatory authorities indicated that it would be extremely difficult to obtain a discharge consent to cover leakage or potential system purges and dumps associated with maintenance operations. Thus an alternative was sought. Sodium nitrite (anhydrous NaN0 2 )/borax (Na 2 B 4 0 7 1OH 2 0) inhibitor solutions have been used for many years in the power industry for preservation of carbon steel plant and several proprietary formulations are based on this mixture. There has been extensive test work in the UK on this inhibitor for secondary side boiler storage on gas reactors and therefore it was considered a prime candidate for use at Sizewell B. Starting in 1985 a programme of work sponsored by Nuclear Electric plc has been completed by NNC Ltd to compare nitrite/borax with other suitable inhibitors and validate its use for Sizewell B. (authors). 5 figs., 1 tab

Reviewing nuclear power

International Nuclear Information System (INIS)

Robinson, Colin

1990-01-01

The UK government has proposed a review of the prospects for nuclear power as the Sizewell B pressurized water reactor project nears completion in 1994. However, a delay in the completion of Sizewell B or a change of government could put off the review for some years beyond the mid 1990s. Anticipating, though, that such a review will eventually take place, issues which it should consider are addressed. Three broad categories of possible benefit claimed for nuclear power are examined. These are that nuclear power contributes to the security of energy supply, that it provides protection against long run fossil fuel price increases and that it is a means of mitigating the greenhouse effect. Arguments are presented which cost doubt over the reality of these benefits. Even if these benefits could be demonstrated, they would have to be set against the financial, health and accident costs attendant on nuclear power. It is concluded that the case may be made that nuclear power imposes net costs on society that are not justified by the net benefits conferred. Some comments are made on how a government review, if and when it takes place, should be conducted. (UK)

The local economic and social effects of power station siting: anticipated, demonstrated and perceived

International Nuclear Information System (INIS)

Glasson, J.

1980-01-01

The paper discusses the economic and social effects of power station siting at a local level using material based on the interim research findings from a project commissioned by the Central Electricity Generating Board. The cases for and against power station development are outlined and a review of the actual economic and social effects is presented, drawn from a study of a conventional power station at Drax and a nuclear power station at Sizewell. (U.K.)

Agricultural production data for the Sizewell area

International Nuclear Information System (INIS)

1982-11-01

The proposed site for the Sizewell B nuclear power station is located at the centre of the East Suffolk coastline. The county itself is predominantly agricultural, producing a very wide range of foodstuffs which in the case of one or two particular foodstuffs contribute a significant proportion of the total national production. A general view of the agricultural setting within which the development would be sited and a compendium of more detailed agricultural data relating to the immediate vicinity of the site, which has been drawn on in the Ministry's assessment of the radiological impact of routine atmospheric waste emission, are given. (U.K.)

Why mini Sizewell is safe as houses

International Nuclear Information System (INIS)

Pease, J.

1989-01-01

A one-tenth scale model of the Sizewell-B nuclear power station pressure vessel is under construction. The framework was made from steel, timber and lathe and plaster work. Reinforcement and prestressing can then be fitted. The object is to build a structure that will reflect the behaviour of the real thing. Once completed the vessel will be filled with water (not gas as in the real reactor) and the pressure brought up to 15% overload. 600 measuring instruments will make measurements of the mechanical properties. The model will then be tested to failure. The model will be analysed by computer, then tested, and the results compared. (author)

The Sizewell B inquiry and East Anglia: the legacy of Three Mile Island

International Nuclear Information System (INIS)

Kemp, R.V.

1985-01-01

This paper argues that the great length and cost of the Public Inquiry into the proposed Sizewell-B PWR reactor is due to its investigatory style. This style became necessary because of the complexity of the issues, the difference in resources between the proponents and objectors and because of delays in licensing of the PWR by the Nuclear Installations Inspectorate. The fears about the safety of the PWR type reactors followed the accident at Three Mile Island in 1979, and the Major of Harrisburg was called by the local residents opposed to the siting to give evidence at the Inquiry. The ways in which the Sizewell-B Inquiry has attempted to come to terms with the fears and concerns of local objectors to the project are looked at. The paper considers how these can be properly weighed when the government is committed to nuclear power. The Inquiry is only advisory - the final decision will be taken by the Ministers after Parliamentary debate. The procedures and facilities adopted by the Inquiry are listed and, in particular, the two evening public meetings held in nearby towns to hear the views of local residents outside the formal main hearing are noted. The two main safety aspects of concern were the incidence of leukemia in East Suffolk, and the planning in case of an emergency at Sizewell-B. The experience of the Mayor of Harrisburg was relevant to this point. (U.K.)

The construction of a PWR power station reactor building liner

International Nuclear Information System (INIS)

Skirving, N.; Goulding, J.S.; Gibson, J.A.

1991-01-01

Cleveland Bridge and Engineering Co Ltd (CBE) are constructing the Reactor Building Liner Plate containment of the Sizewell 'B' Power Station for Nuclear Electric Ltd. This has entailed extensive offsite prefabrication of components and their subsequent erection at Sizewell. It has been necessary to engineer temporary supporting mechanisms to enable manufacture and erection to proceed, yet also to withstand wet concrete forces during the progressive construction. The Reactor Building Liner Plate is a safety related system and as such, in addition to strict compliance with the ASME code, the Quality Assurance (QA) requirements of BS 5882 are applicable. A dedicated Project Team was established by CBE to control and direct the work. Equally important as satisfying the rigorous Q.A. requirements has been the need to meet programme and budget. This paper details CBE execution of the Project. (author)

Government observations on the fourth report from the Committee (Session 1989-90) on the cost of nuclear power

International Nuclear Information System (INIS)

1990-01-01

This report consists of the government's response to the Energy Committee's conclusions about the cost of nuclear power generation in the United Kingdom and the practicalities involved in the possible privatisation of the nuclear power industry. The report was published on 5th December 1990. The report covers the process of privatisation criticisms of Kleinwort Benson, arrangements accounting for and calculating costs of nuclear power and the risks associated with nuclear generating capacity, the Fossil Fuel Levy, some issues particular to Scotland and Sizewell B power station. (author)

Showcase or swansong: the dilemma of Sizewell B

International Nuclear Information System (INIS)

Ashmore, Colin.

1996-01-01

The proposal to privatize the United Kingdom's nuclear power generators (Nuclear Electric and Scottish Nuclear, now joined and renamed British Energy) is driven by political rather than rational motives, it is argued. Notwithstanding that nearly one third of the current United Kingdom generating capacity, comes from British Energy, the future looks uncertain, and plans for future nuclear plants at Hinkley Point and Sizewell have been withdrawn, rendering the long-term future of the nuclear fission based industry very unattractive to investors. As gas prices rise, in the long term, the economic balance is likely to change again, with nuclear fusion technology, most likely to benefit. (UK)

German risk study on nuclear power stations. Phase B

International Nuclear Information System (INIS)

1989-11-01

The German Risk Study on Nuclear Power Stations is concerned with investigations of accidents in nuclear facilities and their associated risks. These investigations are undertaken on behalf of the federal Minister of Research and Technology. They have been broken down into two phases (Phase A and Phase B). The results of Phase A were published in 1979 (GRS 79). This report contains a summary of the investigations relating to Phase B. After an introduction setting out the basic principles and aim of the study, a general review will be given of the most important results. The course of the investigations and the results have already been published in a Technical Report (GRS 89). (author)

Sizewell papers

International Nuclear Information System (INIS)

Anon.

1983-01-01

A collection of papers, previously published in the New Scientist between September 1980 and January 1983, dealing with the pressurised water reactor and in particular the proposal by CEGB to build a PWR at Sizewell, Suffolk, is presented. The individual papers are entitled: American reactors are wrong for Britain; Britain's first pressurised-water reactor; a test bed for nuclear safety; the pressure on nuclear safety; Suffolk - a soft touch for PWRs; why Britain needs a PWR; critical time for Sizewell's reactor; why Britain does not need a PWR; a reactor designed for Sizewell; a case not proven; lessons from Three Mile Island; how France went nuclear; an environmentalist's case for the Sizewell PWR. (U.K.)

Special report: Sizewell

International Nuclear Information System (INIS)

Anon.

1985-01-01

Both the UK strategy in choosing a Wistinghouse-type PWR for Sizewell B and the confusion over management structure for Sizewell B are discussed. The role of the NNC (National Nuclear Corporation) is considered. Initially it was implied that NNC would design, sell, and perhaps, even construct PWR reactors. However, this has been reduced gradually and the strategy for obtaining the major components is not clear. It is suggested that the UK should reconsider its commitment to a PWR reactor which may not be the best available. (U.K.)

Local society and nuclear power stations

International Nuclear Information System (INIS)

1984-02-01

This report was made by the expert committee on region investigation, Japan Atomic Industrial Forum Inc., in fiscal years 1981 and 1982 in order to grasp the social economic influence exerted on regions by the location of nuclear power stations and the actual state of the change due to it, and to search for the way the promotion of local community should be. The influence and the effect were measured in the regions around the Fukushima No. 1 Nuclear Power Station of Tokyo Electric Power Co., Inc., the Mihama Power Station of Kansai Electric Power Co., Inc., and the Genkai Nuclear Power Station of Kyushu Electric Power Co., Inc. The fundamental recognition in this discussion, the policy of locating nuclear power stations and the management of regions, the viewpoint and way of thinking in the investigation of the regions where nuclear power stations are located, the actual state of social economic impact due to the location of nuclear power stations, the connected mechanism accompanying the location of nuclear power stations, and the location of nuclear power stations and the acceleration of planning for regional promotion are reported. In order to economically generate electric power, the rationalization in the location of nuclear power stations is necessary, and the concrete concept of building up local community must be decided. (Kako, I.)

Nuclear power: consolidation or change

International Nuclear Information System (INIS)

1986-02-01

Currently about 45% of the electricity consumed in Scotland comes from nuclear sources and when the power station at Torness, near Edinburgh, is fully commissioned it will be about 60%. Torness is an AGR type reactor and the Scottish Electricty Board (SSEB) consider that there is no case for changing to a PWR type design for any future reactor built in the UK. The economics of 'a next AGR' and a PWR reactor are compared. The construction times for the Torness programme, the electrical output, station life, load factor, fuel costs and additional support costs are also considered, and compared with costs estimated by the Central Elecricity Generating Board (CEGB) for the proposed Sizewell-B reactor. Exposure of station staff to radiation, safety, public acceptibility and development potential, impact on industry, job creation and export potential are also discussed briefly. (UK)

Developmental state and perspectives of USSR power stations, espec. nuclear power stations

International Nuclear Information System (INIS)

1983-01-01

According to the resolutions of the 25th and 26th party congresses of the CPSU, the Soviet electric and thermal energy economy envisages as the mainstreams in development: Energy projects based on nuclear fuel, i.e. nuclear power stations (NPS), nuclear heat- and -power stations (NHPS) and nuclear heat stations (NHS); fuel-energy complexes: Ekibastuz, Kansk-Achinsk, West-Siberian complex (Tyumen); power stations utilizing non-conventional regenerative energy sources, i.e. solar, geothermal, MHD power stations. Further down, an overview is given on the developmental perspectives of nuclear-heat and nuclear-power economy and on the development of energy management based on fossil fuels. (orig./UA) [de

Nuclear dewatering

International Nuclear Information System (INIS)

Anon.

1989-01-01

The Sizewell 'B' Nuclear Power Station, the first in a new family of PWR (Pressurised Water Reactor) stations in the UK, is currently under construction on the Suffolk coast. One of the first civil engineering tasks associated with the power station construction was the necessity to lower the water table by 17-18 m over an area of approximately 8 hectares to allow the excavation for the foundations to be carried out in the dry. The way chosen to do this was to construct a diaphragm wall around the site area. This had the least effect on surrounding sites -the Sizewell-A station and various nature reserves and wetlands. The reasons for the choice of method are discussed. Following the construction of the wall the water was pumped out from within the diaphragm wall in January 1988. (author)

Proposed Sizewell 'B' nuclear power station

Energy Technology Data Exchange (ETDEWEB)

1981-10-01

A report by the County Planning Officer is presented. The site history and planning policies, consultations and publicity, environmental impact, safety and national energy policy are considered. Twelve appendices cover various topics, including various representations, and a report on safety by Professor D C Leslie, the Technical Adviser to the Councils. (UK).

Torness: proposed nuclear power station

International Nuclear Information System (INIS)

Anon.

1979-01-01

The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

Operating experience at Scottish Nuclear's power stations

International Nuclear Information System (INIS)

Blackburn, P.

1991-01-01

A brief history is presented of the design and operation of the four Scottish nuclear power stations currently run by Scottish Nuclear, namely Hunterston 'A' and 'B' and the Torness reactors. A design flaw in the Magnox reactor at Hunterston 'A' led to it being operated at lower than optimal temperature and hence producing less power. For Hunterston 'B' reactor the Advanced Gas Cooled design prototype was used. Operating setbacks and successes are noted. The design chosen for Torness embraced all the good points of Hunterston 'B' but sought to eliminate its faults. After 26 years of successful operation Hunterston 'A' is now being decommissioned, while the other three stations continue to generate electricity successfully. (UK)

The development of the Nuclear Electric core performance and fault transient analysis code package in support of Sizewell B

International Nuclear Information System (INIS)

Hall, P.; Hutt, P.

1994-01-01

This paper describes Nuclear Electric's (NE) development of an integrated code package in support of all its reactors including Sizewell B, designed for the provision of fuel management design, core performance studies, operational support and fault transient analysis. The package uses the NE general purpose three-dimensional transient reactor physics code PANTHER with cross-sections derived in the PWR case from the LWRWIMS LWR lattice neutronics code. The package also includes ENIGMA a generic fuel performance code and for PWR application VIPRE-01 a subchannel thermal hydraulics code, RELAP5 the system thermal hydraulics transient code and SCORPIO an on-line surveillance system. The paper describes the capabilities and validation of the elements of this package for PWR, how they are coupled within the package and the way in which they are being applied for Sizewell B to on-line surveillance and fault transient analysis. (Author)

National Nuclear Corporation Limited report and financial statements 31 March 1987

International Nuclear Information System (INIS)

1987-01-01

The paper presents the annual report and audited financial statements of the National Nuclear Corporation Limited, 31 March 1987. The company is engaged in designing and constructing power stations and nuclear power reactors and other related work. A review of the development work carried out on power stations is briefly given, along with the research and development work on reactors. Future prospects concerning the Sizewell-'B' project are briefly outlined. (U.K.)

Nuclear power in crisis

International Nuclear Information System (INIS)

Blowers, Andrew.; Pepper, David.

1987-01-01

Six themes run through this book: nuclear decision making and democratic accountability, nuclear bias and a narrow-based energy policy, scientific discredit and popular expertise, fusing science with social values, managerial competence and the geography of nuclear power. These are covered in thirteen chapters (all indexed separately) grouped into four parts -the political and planning context, nuclear waste, risk and impact - the social dimension and the future of nuclear power. It considers aspects in France, the United States and the United Kingdom with particular references to the Sizewell-B inquiry and the Sellafield reprocessing plant. (UK)

Discharges from nuclear power stations

International Nuclear Information System (INIS)

1991-02-01

HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report contains details of the technologies used at many nuclear power stations to treat and control radioactive discharges and gives, where information was available, details of discharges and authorised discharge limits. (author)

Current training initiatives at Nuclear Electric plc

International Nuclear Information System (INIS)

Fowler, C.D.

1993-01-01

Nuclear Electric, one of the three generating companies to emerge from the demise of the U.K.'s Central Electricity Generating Board (CEGB), owns and operates the commercial nuclear power stations in England and Wales. The U.K. government proscribed further construction beyond Sizewell B, the United Kingdom's first pressurized water reactor (PWR) station, pending the outcome of a review of the future of nuclear power to be held in 1994. The major challenges facing Nuclear Electric at its formation in 1990 were therefore to demonstrate that nuclear power is safe, economical, and environmentally acceptable and to complete the PWR station under construction on time and within budget. A significant number of activities were started that were designed to increase output, reduce costs, and ensure that the previous excellent safety standards were maintained. A major activity was to reduce the numbers of staff employed, with a recognition from the outset that this reduction could only be achieved with a significant human resource development program. Future company staff would have to be competent in more areas and more productive. This paper summarizes some of the initiatives currently being pursued throughout the company and the progress toward ensuring that staff with the required competences are available to commission and operate the Sizewell B program in 1994

Issues regarding transient analysis examined by the Sizewell B Public Inquiry

International Nuclear Information System (INIS)

Farmer, P.R.; Dunnicliffe, C.J.

1988-01-01

Issues on PWR safety transient analysis that were discussed at the Sizewell B Public Inquiry are presented. The Public Inquiry was set up by the UK Government under an Inspector, Sir Frank Layfield, to examine all aspects of the construction, safety and operation of a 1200 MW(e) PWR on the Sizewell site. The terms of reference were broad ranging, and the constitution of the Inquiry was to make a recommendation under three Acts of Parliament which apply to the construction and operation of nuclear electrical plant. The Inquiry also covered local planning aspects, which are the responsibility of the Local Authority - in this case the Suffolk County Council. The Inspector examined and made recommendations on the safety of the Station, but consideration by Public Inquiry is outside the formal safety and licensing process, which is the business of the Utility (the CEGB) and the Nuclear Installations Inspectorate (the NII). The paper therefore takes a broader look at the question of safety, dealing with the licensing process, the requirements of the safety case and the forward strategies adopted by the CEGB in terms of research and development. This is considered for transient analysis, and the aim is to set the discussions and conclusions of the Public Inquiry into their proper context with regard to nuclear safety in the UK. The Inquiry went into some depth on the topic of LOCA, as an example of safety analysis. In the summary of the evidence and cross-examination the Inspector accepted the adequacy of the LOCA safety case without major reservations, and was satisfied further work in progress would resolve any residual criticisms. In particular support was given for the CEGB commitment to the development and use of more physically realistic calculational methods

The power of British Energy

International Nuclear Information System (INIS)

Hawley, R.

1997-01-01

When the power industry in Britain was privatized, British Energy plc (BE), whose head office is in Edingburgh, Scotland, was founded in July 1996. It is the only power utility in the world exclusively operating nuclear power stations. Operative business has remained the responsibility of the two regional supply companies, Nuclear Electric (NE) and Scottish Nuclear (SN) which, in addition to the modern PWR nuclear generating unit of Sizewell B, have included in the new holding company their advanced gas-cooled and gas-moderated reactor (AGR) units. The older gas-graphite reactor (GGR) plants were combined in the new Magnox Electric plc, Berkeley; at some later date, this company is to be merged with another nuclear power plant operator, British Nuclear Fuels plc (BNFL). Sizewell B, which was commissioned in 1995, is the last nuclear generating unit to be started up in the United Kingdom, for the time being. In times of low raw material prices and the need for a quick return on invested capital, BE is reluctant to run the risk associated with tying up capital for a long time. Instead, the company has backfitted its plants so that the production of electricity from nuclear power in Britain in 1996 of 92,476 GWh was increased by almost 10% over the 1995 level of 84,174 GWh. In addition to modernization and rationalization at home, BE together with Sizewell B vendor Westinghouse is engaged worldwide in the development and commercialization of future advanced reactors. This ensures that the know-how accumulated will be preserved and will be available for new nuclear power plants to be built in Britain in the next century. (orig.)

The UK nuclear power industry

International Nuclear Information System (INIS)

Collier, J. G.

1995-01-01

In the United Kingdom, nuclear power plants are operated by three companies: Nuclear Electric (NE), Scottish Nuclear (SN), and British Nuclear Fuels plc (BNFL). The state-operated power industry was privatized in 1989 with the exception of nuclear power generation activities, which were made part of the newly founded (state-owned) NE and SN. At the same time, a moratorium on the construction of new nuclear power plants was agreed. Only Sizewell B, the first plant in the UK to be equipped with a pressurized water reactor, was to be completed. That unit was first synchronized with the power grid on February 14, 1995. Another decision in 1989 provided for a review to be conducted in 1994 of the future of the peaceful uses of nuclear power in the country. The results of the review were presented by the government in a white paper on May 9, 1995. Accordingly, NE and SN will be merged and privatized in 1996; the headquarters of the new holding company will be in Scotland. The review does not foresee the construction of more nuclear power plants. However, NE hopes to gain a competitive edge over other sources of primary energy as a result of this privatization, and advocates construction of a dual-unit plant identical with Sizewell B so as to avoid recurrent design and development costs. Outside the UK, the company plans to act jointly with the reactor vendor, Westinghouse, especially in the Pacific region; a bid submitted by the consortium has been shortisted by the future operator of the Lungmen nuclear power plant project in Taiwan. In upgrading the safety of nuclear power plants in Eastern Europe, the new company will be able to work through existing contacts of SN. (orig.) [de

Sizewell 'B' public inquiry. Proof of evidence on local environmental issues

Energy Technology Data Exchange (ETDEWEB)

Barritt, E E

1982-11-01

The report falls under the headings: introduction (need/economics; safety; waste management; local and site specific issues); the Sizewell site - history and planning policies; planning and environmental implications; land use and landscape implications; ecological implications; mineral requirements; highway implications; employment implications; accommodation implications; infrastructure and social/community services; safeguarding restrictions for Sizewell - Nuclear Installations Inspectorate; decommissioning.

Managing nuclear power stations for success

International Nuclear Information System (INIS)

Smith, G.

2006-01-01

Ontario Power Generation's (OPG) top operational priority is to manage its nuclear assets to ensure they operate as safely, efficiently and cost effectively as possible. In meeting these objectives, the company is focused on continuously improving its nuclear performance and benchmarking that performance against the best in North America. This presentation explores how OPG is improving its nuclear performance and the steps it is taking to sustain performance success going forward. Topics to be discussed include the measures OPG is taking to enhance human performance and station reliability as well as the company's preparations to determine if a business case exists for extending the lives of the Pickering B and eventually the Darlington nuclear stations. (author)

TEPCO plans to construct Higashidori Nuclear Power Station

International Nuclear Information System (INIS)

Tsuruta, Atsushi

2008-01-01

In 2006, TEPCO submitted to the government plans for the construction of Higashidori Nuclear Power Station. The application was filed 41 years after the project approved by the Higashidori Village Assembly. This nuclear power station will be the first new nuclear power plant constructed by TEPCO since the construction of Units No.6 and 7 at the Kashiwazaki Kariwa Nuclear Power Station 18 years ago. Higashidori Nuclear Power Station is to be constructed at a completely new site, which will become the fourth TEPCO nuclear power station. Higashidori Nuclear Power Station Unit No.1 will be TEPCO's 18th nuclear reactor. Unit No.1 will be an advanced boiling water reactor (ABWR), a reactor-type with a proven track record. It will be TEPCO's third ABWR. Alongside incorporating the latest technology, in Higashidori Nuclear Power Station Unit No.1, the most important requirement is for TEPCO to reflect in the new unit information and experience acquired from the operation of other reactors (information and experience acquired through the experience of operating TEPCO's 17 units at Fukushima Daiichi Nuclear Power Station, Fukushima Daini Nuclear Power Station and Kashiwazaki Kashiwa Nuclear Power Station in addition to information on non-conformities at nuclear power stations in Japan and around the world). Higashidori Nuclear Power Station is located in Higashidori-Village (Aomori Prefecture) and the selected site includes a rich natural environment. From an environmental perspective, we will implement the construction with due consideration for the land and sea environment, aiming to ensure that the plant can co-exist with its natural surroundings. The construction plans are currently being reviewed by the Nuclear and Industrial Safety Agency. We are committed to making progress in the project for the start of construction and subsequent commercial operation. (author)

Probabilistic safety analysis for Sizewell B - proof of evidence, established on behalf of the Friends of the Earth, London, within the framework of the Sizewell B power station public inquiry

International Nuclear Information System (INIS)

Hahn, L.

1985-01-01

The conclusions drawn in the study presented by the Oeko-Institut, Freiburg, state that there are indeed advantages in the design of the PWR-type Sizewell-B reactor over other types with regard to certain event sequences, but that on the whole, with regard to overall accident probability, there is no significant progress detectable, or even provable. The main results of the analysis in hand undoubtedly are that the unrealistically favourable data presented in the other two Sizewell studies are brought about not by the design features, but by the assumptions, methods and data applied in the studies, so that certain weak points in the methodological approach common to both studies inevitably lead to similar results. The authors of the study in hand explain some of the weak points of the Westinghouse Study and of the CEGB Study to be as follows: - Lack of error bands of results. - Lack of a quantitative analysis of in-plant fire accidents. - Lack of quantitative analysis of external impacts. - Lack of (CEGB) or unsatisfactory (Westinghouse) evaluation of the measuring, control, and drive systems. - Lack of (CEGB) or unsatisfatory (Westinghouse) evaluation of the human factors. - Completely unsatisfactory evaluation of common-mode failures (i.e. multiple failures due to common cause, undiscovered systems interactions, etc.). - Unacceptable handling and use of available data (using data assessments made by experts, instead of data available from experience). (orig./HSCH) [de

Nuclear safeguards control in nuclear power stations

International Nuclear Information System (INIS)

Boedege, R.; Braatz, U.; Heger, H.

1976-01-01

The execution of the Non-Proliferation Treaty (NPT) has initiated a third phase in the efforts taken to ensure peace by limiting the number of atomic powers. In this phase it is important, above all, to turn into workable systems the conditions imposed upon technology by the different provisions of the Verification Agreement of the NPT. This is achieved mainly by elaborating annexes to the Agreement specifically geared to certain model plants, typical representatives selected for LWR power stations being the plants at Garigliano, Italy (BWR), and Stade, Federal Republic of Germany (PWR). The surveillance measures taken to prevent any diversion of special nuclear material for purposes of nuclear weapons manufacture must be effective in achieving their specific objective and must not impede the circumspect management of operations of the plants concerned. A VDEW working party has studied the technical details of the planned surveillance measures in nuclear power stations in the Federal Republic of Germany and now presents a concept of material balancing by units which meets the conditions imposed by the inspection authority and could also be accepted by the operators of nuclear power stations. The concept provides for uninterrupted control of the material balance areas of the nuclear power stations concerned, allows continuous control of the whole nuclear fuel cycle, is based exclusively on existing methods and facilities, and can be implemented at low cost. (orig.) [de

Virginia power nuclear power station engineer training program

International Nuclear Information System (INIS)

Williams, T.M.; Haberstroh-Timpano, S.

1987-01-01

In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

Periodical inspection in nuclear power stations

International Nuclear Information System (INIS)

1986-01-01

Periodical inspection is presently being made of eight nuclear power plants in nuclear power stations. Up to the present time, in three of them, failures as follows have been observed. (1) Unit 3 (PWR) of the Mihama Power Station in The Kansai Electric Power Co., Inc. Nineteen heat-transfer tubes of the steam generators were plugged up due to failure. A fuel assembly with a failed spring fixture and in another the control-rod cluster with a failed control rod fixture were replaced. (2) Unit 2 (PWR) of the Oi Power Station in The Kansai Electric Power Co., Inc. Eight heat-transfer tubes of the heat exchangers were plugged up due to failure. (3) Unit 6 (BWR) of the Fukushima Nuclear Power Station I in The Tokyo Electric Power Co., Inc. A fuel assembly with leakage was replaced. (Mori, K.)

Islands for nuclear power stations

International Nuclear Information System (INIS)

Usher, E.F.F.W.; Fraser, A.P.

1981-01-01

The safety principles, design criteria and types of artificial island for an offshore nuclear power station are discussed with particular reference to siting adjacent to an industrial island. The paper concludes that the engineering problems are soluble and that offshore nuclear power stations will eventually be built but that much fundamental work is still required. (author)

Studying dynamics of indicators of nuclear power stations exploitation (the case of US nuclear power stations)

OpenAIRE

Varshavsky, Leonid

2013-01-01

Analysis of external and internal factors influencing significant improvement of economic indicators of US nuclear power stations in the 1990s is carried out. Approaches to modeling dynamics of capacity factors of nuclear power stations are proposed. Comparative analysis of dynamics of capacity factors and occupational radiation exposure for various generations of US nuclear power plants is carried out. Dynamical characteristics of «learning by doing» effects for analyzed indicators are measu...

The use of probabilistic safety analysis in design and operation -- Lessons learned from Sizewell B. Annex 14

International Nuclear Information System (INIS)

Buttery, N.E.

2002-01-01

Probabilistic Safety Assessments (PSAs) have been used extensively in the design and licensing of Sizewell B. This paper outlines the role of PSA in the UK licensing process and describes how it has been applied to Sizewell B during both the pre-construction and pre-operational phases. From this experience a 'Living PSA' has been formulated which continues be used to support operation. The application of PSA to Sizewell B has demonstrated that it is a powerful tool with potential for future use. Its strengths and limitations as a tool need to recognised by both users and regulators. It is not a fully mechanistic means of ensuring design safety, but is an important aid to decision making. It also has the potential to allow risk judgements to be taken in conjunction with commercial and environmental issues. (author)

Sizewell and the people: what the community thinks

International Nuclear Information System (INIS)

Chappell, H.

1983-01-01

Some 15 or so of the people who live in Leiston, the town (pop. 4000) nearest the proposed Sizewell-B site, give their views about the building of the PWR station. The points raised include the possibility of employment, the disruption to the town during the actual building of the reactor and the safety record of PWRs. It is an issue which divides families and where young and old are found on both sides of the argument. The public inquiry is felt to be a formality only and the building of Sizewell-B to be inevitable. (U.K.)

Construction work management for nuclear power stations

International Nuclear Information System (INIS)

Yoshikawa, Yuichiro

1982-01-01

Nuclear power generation is positioned as the nucleus of petroleum substitution. In the Kansai Electric Power Co., efforts have been made constantly to operate its nuclear power plants in high stability and safety. At present, Kansai Electric Power Co. is constructing Units 3 and 4 in the Takahama Nuclear Power Station in Fukui Prefecture. Under the application of the management of construction works described here, both the nuclear power plants will start operation in 1985. The activities of Kansai Electric Power Co. in the area of this management are described: an outline of the construction works for nuclear power stations, the management of the construction works in nuclear power stations (the stages of design, manufacturing, installation and test operation, respectively), quality assurance activities for the construction works of nuclear power plants, important points in the construction work management (including the aspects of quality control). (J.P.N.)

Reliability study of nuclear power stations

International Nuclear Information System (INIS)

Nemec, J.; Sedlacek, J.

1975-01-01

The paper considers the physical and mathematical bases underlying nuclear power station reliability from the standpoints of material fatigue, thermal yield and ageing. The risk of failure of nuclear power station components is determined by means of the Markov stochastic process

Pumps for nuclear power stations

International Nuclear Information System (INIS)

Ogura, Shiro

1979-01-01

16 nuclear power plants are in commercial operation in Japan, and nuclear power generation holds the most important position among various substitute energies. Hereafter also, it is expected that the construction of nuclear power stations will continue because other advantageous energy sources are not found. In this paper, the outline of the pumps used for BWR plants is described. Nuclear power stations tend to be large scale to reduce the construction cost per unit power output, therefore the pumps used are those of large capacity. The conditions to be taken in consideration are high temperature, high pressure, radioactive fluids, high reliability, hydrodynamic performances, aseismatic design, relevant laws and regulations, and quality assurance. Pumps are used for reactor recirculation system, control rod driving hydraulic system, boric acid solution injecting system, reactor coolant purifying system, fuel pool cooling and purifying system, residual heat removing system, low pressure and high pressure core spraying systems, and reactor isolation cooling system, for condensate, feed water, drain and circulating water systems of turbines, for fresh water, sea water, make-up water and fire fighting services, and for radioactive waste treating system. The problems of the pumps used for nuclear power stations are described, for example, the requirement of high reliability, the measures to radioactivity and the aseismatic design. (Kako, I.)

Safety aspects of nuclear power stations

International Nuclear Information System (INIS)

Binner, W.

1980-01-01

Psychological aspects of the fear of nuclear power are discussed, cancer deaths due to a nuclear accident are predicted and the need for nuclear accident prevention is stressed. A simplified analysis of the safety precautions in a generalised nuclear power station is offered, with reference to loss-of-coolant incidents, and developments in reactor design for fail-safe modes are explained. The importance of learning from the Three Mile Island incident is noted and failure statistics are presented. Tasks to be undertaken at the Austrian Zwentendorf nuclear power station are listed, including improved quality control and acoustic detectors. Precautions against earthquakes are also discussed and it is stated that safe operation of the Zwentendorf station will be achieved. (G.M.E.)

Tokai earthquakes and Hamaoka Nuclear Power Station

International Nuclear Information System (INIS)

Komura, Hiroo

1981-01-01

Kanto district and Shizuoka Prefecture are designated as ''Observation strengthening districts'', where the possibility of earthquake occurrence is high. Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., is at the center of this district. Nuclear power stations are vulnerable to earthquakes, and if damages are caused by earthquakes in nuclear power plants, the most dreadful accidents may occur. The Chubu Electric Power Co. underestimates the possibility and scale of earthquakes and the estimate of damages, and has kept on talking that the rock bed of the power station site is strong, and there is not the fear of accidents. However the actual situation is totally different from this. The description about earthquakes and the rock bed in the application of the installation of No.3 plant was totally rewritten after two years safety examination, and the Ministry of International Trade and Industry approved the application in less than two weeks thereafter. The rock bed is geologically evaluated in this paper, and many doubtful points in the application are pointed out. In addition, there are eight active faults near the power station site. The aseismatic design of the Hamaoka Nuclear Power Station assumes the acceleration up to 400 gal, but it may not be enough. The Hamaoka Nuclear Power Station is intentionally neglected in the estimate of damages in Shizuoka Prefecture. (Kako, I.)

Hinkley Point 'C' power station public inquiry: proof of evidence on design and safety

International Nuclear Information System (INIS)

George, B.V.

1988-09-01

A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom. The policy is to replicate the Sizewell ''B'' PWR design. The Hinkley Point ''C'' design is described indicating where changes in the Sizewell ''B'' design have been made to accommodate site differences. These are associated with the civil engineering construction and some of the electrical systems and do not affect the safety case. External hazards differ from site to site and the effect on the safety case of those specific to Hinkley Point are examined. The Chernobyl accident and the assessment of the United Kingdom PWR which was carried out subsequently are reviewed. The assessment indicated that no changes in the Sizewell ''B'' design and safety case were called for as a result of this accident; accident management developments are also reviewed, however. The CEGB's approach to minimizing occupational radiation doses is described. (UK)

Nuclear privatization

International Nuclear Information System (INIS)

Jeffs, E.

1995-01-01

The United Kingdom government announced in May 1995 plans to privatize the country's two nuclear generating companies, Nuclear Electric and Scottish Nuclear. Under the plan, the two companies will become operating divisions of a unified holding company, to be called British Electric, with headquarters in Scotland. Britain's nuclear plants were left out of the initial privatization in 1989 because the government believed the financial community would be unwilling to accept the open-ended liability of decommissioning the original nine stations based on the Magnox gas-cooled reactor. Six years later, the government has found a way around this by retaining these power stations in state ownership, leaving the new nuclear company with the eight Advanced Gas-cooled Reactor (AGR) stations and the recently completed Sizewell B PWR stations. The operating Magnox stations are to be transferred to BNFL, which operates two Magnox stations of their own at Calder Hall and Chapelcross

Safety planning for nuclear power stations

International Nuclear Information System (INIS)

Tadmor, J.

1979-01-01

The article shows that compared to the many industries and other human activities, nuclear power stations are among the safest. A short description of the measures taken to prevent accidents and of the additional safety means entering into action if an accident does occur is presented. It is shown that in nuclear plants the death frequency following malfunctioning is 1 death in 100.000 years whereas deaths following other human activities is 1 in 2 to 100 years and following natural calamities like earthquakes and floods is 1 in 10 years. As an example it is shown that for a population of 15.000.000 living in a radius of 40 km around 100 power stations the average number of deaths will be of 2 per year as compared to 4200 from road accidents with the corresponding number of injuries of 20 and 375.000 respectively. (B.G.)

The Paks Nuclear Power Station

International Nuclear Information System (INIS)

Erdosi, N.; Szabo, L.

1978-01-01

As the first stage in the construction of the Paks Nuclear Power Station, two units of 440 MW(e) each will be built. They are operated with two coolant loops each. The reactor units are VVER 440 type water-moderated PWR type heterogeneous power reactors designed in the Soviet Union and manufactured in Czechoslovakia. Each unit operates two Soviet-made K-220-44 steam turbines and Hungarian-made generators of an effective output of 220 MW. The output of the transformer units - also of Hungarian made - is 270 MVA. The radiation protection system of the nuclear power station is described. Protection against system failures is accomplished by specially designed equipment and security measures especially within the primary circuit. Some data on the power station under construction are given. (R.P.)

Extension of life of nuclear power stations

International Nuclear Information System (INIS)

Takahashi, Hideaki

1991-01-01

At the time of designing nuclear power stations, as their service life, generally 40 years are taken, and the basic design specifications of machinery and equipment are determined. In USA where atomic energy has been developed, the new construction of nuclear power stations is cased for a while, however, if this situation continues as it is, since old power stations reach the service life of 40 years and are retired in near future, it is feared that the circumstance of the total amount of power generation becoming short will occur. As one of the countermeasures to this, the research on the extension of life of nuclear power stations has been carried out in many fields in USA, and it is expected that the application for extending the life for the power stations constructed in the initial period of development is submitted in 1991. The researches that have been carried out for solving the technical problems in this extension of life and the situation in Japan are reported. The NEC of USA decided that the operation period of nuclear power stations in USA, which is considered to be 40 years so far, can be extended up to the limit of 20 years. The background and circumstances of this problem in USA, Nuclear Plant Aging Research Program, Plant Life Extension Program and so on are reported. (K.I.)

The nuclear power station

International Nuclear Information System (INIS)

Plettner, B.

1987-04-01

The processes taking place in a nuclear power plant and the dangers arising from a nuclear power station are described. The means and methods of controlling, monitoring, and protecting the plant and things that can go wrong are presented. There is also a short discourse on the research carried out in the USA and Germany, aimed at assessing the risks of utilising nuclear energy by means of the incident tree analysis and probability calculations. (DG) [de

Nuclear power station achievement 1968-1980

International Nuclear Information System (INIS)

Howles, L.R.

This report reviews and gives an analysis of the achievement of operating nuclear power stations in the Western world on three relevant bases: (1) both annual and cumulative achievement of all nuclear power stations at a particular time; (2) cumulative achievement of all nuclear power stations at the end of the first and subsequent years of their lives to show trends with age; (3) achievement based on refuelling period considerations. Nowhere in the report are any operating details ignored, omitted or eliminated in the method of analysis. Summarising the results of the reviews shows: an improvement with time from initial electricity generation on all bases; that initially, larger sizes of reactor/turbine operate less well than smaller sizes (except for PHWR's); that after an initial number of years, the largest size units operate as well as the intermediate and smaller sizes, or better in the PHWR case; that a 75 per cent cumulative load factor achievement in the middle years of a reactor/turbines life can be expected on the refuelling period considerations base; that at June 1980, 35 nuclear power stations achieved an annual load factor over 75 per cent; that the above achievement was possible despite the repercussions following the Three Mile Island 'accident' and the shutdowns in the USA for piping system seismic adequacy checks required by the Nuclear Regulatory Commission for five nuclear power stations; and that even when reactors/turbines are reaching towards the end of their design life, there is no rapid deterioration in their achievements. (author)

Diaphragm walling for Sizewell B sets records

International Nuclear Information System (INIS)

Anon.

1988-01-01

The first phase of construction of the Sizewell-B nuclear reactor has been completed. This was the building of a diaphragm wall around the site. It is one of the largest and deepest diaphragm walls to be installed in Europe. The site can be pumped dry of groundwater and the foundations constructed in the dry. The specifications of the wall and its construction, using two Hydrofraise excavation rigs, are described. The excavated material is brought up as a slurry and the (bentonite) slurry is cleaned and desanded. Most of the wall has been formed using a plastic concrete but reinforced concrete has been used for some stretches. The diaphragm wall, which is 1258m long and 55m deep on average, was built in 19 weeks. (U.K.)

Electricity supplies in a French nuclear power station

International Nuclear Information System (INIS)

2011-01-01

As the operation of a nuclear power station requires a power supply system enabling this operation as well as the installation safety, this document describes how such systems are designed in the different French nuclear power stations to meet the requirements during a normal operation (when the station produces electricity) or when it is stopped, but also to ensure power supply to equipment ensuring safety functions during an incident or an accident occurring on the installation. More precisely, these safety functions are provided by two independent systems in the French nuclear power stations. Their operation is briefly described. Two different types of nuclear reactors are addressed: pressurised water reactors (PWR) of second generation, EPR (or PWR of third generation)

Communication on energy: who pays for the long-term costs of nuclear power

International Nuclear Information System (INIS)

Jeffery, J.W.

1987-01-01

The question in the title arises in making a fair comparison between a coal-fired station, which has no long-term costs, and a nuclear station, whose large long-term costs are discounted into insignificance by the present method of calculation. This problem was raised by the present author in his evidence to the Sizewell Inquiry, and has recently been discussed by the House of Commons Select Committee on Energy, who expressed grave disquiet that 'the costs of decommissioning become almost irrelevant to the current economics of nuclear power'. The present article analyses the bizarre effects of long-term discounting, and suggests a method of making a fair and symmetrical comparison between coal-fired and nuclear stations. (author)

Physics and nuclear power

International Nuclear Information System (INIS)

Buttery, N E

2008-01-01

Nuclear power owes its origin to physicists. Fission was demonstrated by physicists and chemists and the first nuclear reactor project was led by physicists. However as nuclear power was harnessed to produce electricity the role of the engineer became stronger. Modern nuclear power reactors bring together the skills of physicists, chemists, chemical engineers, electrical engineers, mechanical engineers and civil engineers. The paper illustrates this by considering the Sizewell B project and the role played by physicists in this. This covers not only the roles in design and analysis but in problem solving during the commissioning of first of a kind plant. Looking forward to the challenges to provide sustainable and environmentally acceptable energy sources for the future illustrates the need for a continuing synergy between physics and engineering. This will be discussed in the context of the challenges posed by Generation IV reactors

An examination of the proposals for the off-site electrical power sources at the Sizewell B PWR

Energy Technology Data Exchange (ETDEWEB)

Woodhouse, P. A. [HM Nuclear Installations Inspectorate, London (United Kingdom)

1986-02-15

Over the past few years there has been an increase in the attention being given to the adequacy and reliability of alternative sources of power provided to supply safety equipment should off-site electrical sources fail. This paper discusses the rationale of HM Nuclear Installations Inspectorates assessment of the electrical systems proposed for the UK's first Pressurized water Reactor, Sizewell 3. The requirements for on-site sources are given, and a discussion is provided of the NII's Assessment Principles including common mode failure, single failure criterion and reliability targets. Where the assessment has resulted in notifications to the original design the reasons are given. The UK's large interconnected Grid System makes complete losses of off-site power comparatively rare. The potential exists however and this paper shows how the current approach ensures that not only are adequate on-site sources available but also that their siting, maintenance and testing are such that loss of off-site power will not cause an unacceptable risk to the public. (author)

Process instrumentation for nuclear power station

International Nuclear Information System (INIS)

Yanai, Katsuya; Shinohara, Katsuhiko

1978-01-01

Nuclear power stations are the large scale compound system composed of many process systems. Accordingly, for the safe and high reliability operation of the plants, it is necessary to grasp the conditions of respective processes exactly and control the operation correctly. For this purpose, the process instrumentation undertakes the important function to monitor the plant operation. Hitachi Ltd. has exerted ceaseless efforts since long before to establish the basic technology for the process instrumentation in nuclear power stations, to develop and improve hardwares of high reliability, and to establish the quality control system. As for the features of the process instrumentation in nuclear power stations, the enormous quantity of measurement, the diversity of measured variables, the remote measurement and monitoring method, and the ensuring of high reliability are enumerated. Also the hardwares must withstand earthquakes, loss of coolant accidents, radiations, leaks and fires. Hitachi Unitrol Sigma Series is the measurement system which is suitable to the general process instrumentation in nuclear power stations, and satisfies sufficiently the basic requirements described above. It has various features as the nuclear energy system, such as high reliability by the use of ICs, the methods of calculation and transmission considering signal linkage, loop controller system and small size. HIACS-1000 Series is the analog controller of high reliability for water control. (Kako, I.)

Monitoring of nuclear power stations

International Nuclear Information System (INIS)

Ull, E.; Labudda, H.J.

1987-01-01

The purpose of the invention is to create a process for undelayed automated detection and monitoring of accidents in the operation of nuclear power stations. According to the invention, this problem is solved by the relevant local measurements, such as radiation dose, components and type of radiation and additional relevant meteorological parameters being collected by means of wellknown data collection platforms, these being transmitted via transmission channels by means of satellites to suitable worldwide situated receiving stations on the ground, being processed there and being evaluated to recognise accidents. The local data collection platforms are used in the immediate vicinity of the nuclear power station. The use of aircraft, ships and balloons as data collection systems is also intended. (HWJ)

Principles of nuclear power station control

International Nuclear Information System (INIS)

Knowles, J.B.

1975-12-01

This memorandum represents lecture notes first distributed as part of a UKAEA introductory course on Reactor Technology held during November 1975. A nuclear power station is only one element of a dispersed interconnected arrangement of other nuclear and fossil-fired units which together constitute the national 'grid'. Thus the control of any one station must relate to the objectives of the grid network as a whole. A precise control of the supply frequency of the grid is achieved by regulating the output power of individual stations, and it is necessary for each station to be stable when operating in isolation with a variable load. As regards individual stations, several special control problems concerned with individual plant items are discussed, such as: controlled reactivity insertions, temperature reactivity time constants and flow instability. A simplified analysis establishes a fundamental relationship between the stored thermal energy of a boiler unit (a function of mechanical construction) and the flexibility of the heat source (nuclear or fossil-fired) if the station is to cope satisfactorily with demands arising from unscheduled losses of other generating sets or transmission capacity. Two basic control schemes for power station operation are described known as 'coupled' and 'decoupled control'. Each of the control modes has its own merits, which depend on the proposed station operating strategy (base load or load following) and the nature of the heat source. (U.K.)

Inpile honing of Sizewell primary selector valve housings

International Nuclear Information System (INIS)

Grindrod, A.; Ward, R.G.

1976-03-01

Difficulties have been experienced at Sizewell power station with the removal and replacement of several of the primary selector valves fitted in the reactors, during the annual maintenance programme. An inpile honing device is described which was specifically designed and developed to facilitate the restoration of the inner sealing faces of the valve housings. (author)

Services for nuclear power stations

International Nuclear Information System (INIS)

Fremann, M.; Ryckelynck

1987-01-01

This article gives an information as complete as possible about the activities of the french nuclear industry on the export-market. It describes the equipment and services available in the field of services for nuclear power stations [fr

Evaluating the nation's risk assessors: nuclear power and the 'value of life'

International Nuclear Information System (INIS)

Marin, Alan

1986-01-01

The inquiry into the proposed Sizewell nuclear power station has also brought into question the way in which risk is assessed. In the United Kingdom the Nuclear Installations Inspectorate (NII) ensures the safe operation of nuclear power plants and decides how much money needs to be spent on reducing the risk of fatal accidents. The two methods of assessing a value for a life are explained and their relative merits discussed. The Health and Safety Executive (of which the NII is part) uses a human capital approach. The Nuclear Radiological Protection Board uses a risk-reduction method which gives a much higher figure. It is suggested that a common basis for assessing risk should be adopted. (UK)

Socioeconomic impacts: nuclear power station siting

International Nuclear Information System (INIS)

1977-06-01

The rural industrial development literature is used to gain insights on the socioeconomic effects of nuclear power stations. Previous studies of large industrial facilities in small towns have important implications for attempts to understand and anticipate the impacts of nuclear stations. Even a cursory review of the nuclear development literature, however, reveals that industrialization research in rural sociology, economic geography and agricultural economics has been largely ignored

Report of NII investigation into allegations of faulty welding at Hinkley 'B' nuclear power station

International Nuclear Information System (INIS)

1987-01-01

This reports the procedure and findings of the Nuclear Installations Inspectorate's investigation into allegations of welding and radiography malpractice at Hinkley Point-B power station. These concerned welds and their radiographic testing made on pipework carrying water or steam associated with one of the main electricity turbo generators, during construction in 1971. The water or steam is not radioactive and pipe failure would have no nuclear safety significance. Both the Central Electricity Generating Board and the NII investigated the allegations. Both investigations concluded that there was no evidence to support the allegations. (U.K.)

Sizewell integrated system for centralized operations: getting it all together

International Nuclear Information System (INIS)

Cook, B.M.; Robinson, D.E.P.

1992-01-01

In June 1991, Westinghouse was awarded a contract by Nuclear Electric to supply the Integrated System for Centralized Operations (ISCO) for the Sizewell B nuclear power plant under construction in Suffolk. This system is a large scale distributed control and instrumentation system that will perform safety and control functions for the primary and secondary systems for the plant. Combined with the control and instrumentation equipment that was already being supplied for the plant by Westinghouse, this will be the most extensive integration of modern digital control equipment on a nuclear power plant to date. The ISCO architecture, consisting of 3 major segments -high integrity control, process control and the distributed computer system - is described. The history of the ISCO development is explained. (Author)

The Heysham 2 and Torness nuclear power station projects

International Nuclear Information System (INIS)

Cameron, P.J.

1989-01-01

At the beginning of the design of the Heysham 2 and Torness Nuclear Power Stations in the UK, it was agreed that the Hinkley Point B/Hunterston B Advanced Gas Cooled reactor design would be repeated. However, the Hinkley Point B/Hunterston B designs dated from 1964, and inevitably safety requirements had escalated in the intervening years. Furthermore, operating experience gained from Hinkley Point B/Hunterston B showed that it was desirable to make changes to particular features. Design changes were therefore included where it was considered essential to improve performance, to improve safety and to improve engineering. The resulting station designs are described. (author)

Design and safety of the Sizewell pressurized water reactor

International Nuclear Information System (INIS)

Marshall, W.

1983-01-01

The Central Electricity Generating Board propose to build a pressurized water reactor at Sizewell in Suffolk. The PWR Task Force was set up in June 1981 to provide a communications centre for developing firm design proposals for this reactor. These were to follow the Standardized Nuclear Unit Power Plant System designed by Bechtel for the Westinghouse nuclear steam supply system for reactors built in the United States. Changes were required to the design to accommodate, for example, the use of two turbine generators and to satisfy British safety requirements. Differences exist between the British and American licensing procedures. In the UK the statutory responsibility for the safety of a nuclear power station rests unambiguously with the Generating Boards. In the U.S.A. the Nuclear Regulatory Commission issues detailed written instructions, which must be followed precisely. Much of the debate on the safety of nuclear power focuses on the risks of big nuclear accidents. It is necessary to explain to the public what, in a balanced perspective, the risks of accidents actually are. The long-term consequences can be presented in terms of reduction in life expectancy, increased chance of cancer or the equivalent pattern of compulsory cigarette smoking. (author)

Quality control of Ling'ao nuclear power station civil construction

International Nuclear Information System (INIS)

Lu Buliang; Ye Changyuan

2001-01-01

Based on the quality control model adopted during Ling'ao Nuclear Power Station construction, the author briefly introduces quality control process of some main civil construction activities (reinforced concrete, steel liner, steel works and prestressing force) of nuclear power station, and makes some descriptions on non-conformance control of civil works. These quality control processes described come from the concrete practice during civil construction of Ling'ao Nuclear Power Station, and are based on Daya Bay Nuclear Power Station construction experience

On the development of small nuclear power stations

International Nuclear Information System (INIS)

Goetzmann, C.A.

1989-01-01

There are weighty reasons for and against the building of small nuclear power stations. Factors such as specific investment costs, opportunities for and areas of application, geographical conditions as well as those relating to infrastructure, security and availability play an important role in the planning, construction and running of a nuclear power station. For the usual large power stations, the comparatively low specific investment costs and a proven technology are favorable factors which minimize the investment risk. The article presents an overview of reasons for using small power stations and also considers the difficulties which would arise in practice. (orig.) [de

Simulation of a pressurized-water nuclear power station

International Nuclear Information System (INIS)

Larminaux, Robert; Ourmann, Michel

1978-01-01

Faced with the large programme of fitting out PWR nuclear power stations, Electricite de France have undertaken a series of studies with a view to ensuring the best possible adaptation of the secondary part -particularly the feed water heating section- to the nuclear boiler. In order to undertake such studies it has been necessary to finalize simulation models of the entire power station. So as to verify the validity of the models, experiment-calculation comparisons were made during transient operating states recorded at the Ardennes power station as well as during starting up trials at the Tihange I power station [fr

Nuclear power and public acceptance in the UK

International Nuclear Information System (INIS)

Baker, J.W.

1985-01-01

The subject is covered in sections: introduction; UK nuclear experience (experience of the Central Electricity Generating Board; impartial assessment); Sizewell inquiry (into proposal to construct a PWR based plant as Sizewell B; inquiry process; ground covered; economics and safety; project management); public acceptance (sociological studies); long-term programme. (U.K.)

Organisation of radiation protection at Sizewell Nuclear Power Plant in the UK. Report n. 290

International Nuclear Information System (INIS)

Crouail, P.; Jeannin, B.; Lefaure, C.; Panisset, L.

2004-01-01

This report first describes the organisation and management of radiation protection at Sizewell Nuclear Power Plant (UK): general organisation, organisation of the radiation protection department, goals of radiation protection at plant and corporate levels, measurement of radiation protection performance, presence of health physicists in the plant, national and international comparisons. Then, it addresses the training of workers and radiation protection specialists with respect to radiation protection, the management of zoning and surveillance (action to address the radiation risk and the contamination risk). It describes the relationships of Health physicists with contractors and other workers teams, and the relationships with safety authorities. It indicates the different outages of this organisation: general planning, information sheets, physicists work planning, reviews and meetings. It describes the management of personal dosimetry with radiation work permits and actions aimed at the reduction of doses during various operations. The last part proposes a feedback experience report and evokes the generated database, and addresses events reporting

NDE fo Sizewell B

International Nuclear Information System (INIS)

Baborovsky, V.M.; Whittle, M.J.

1988-01-01

A key feature of the safety case for Sizewell B is the extensive NDE proposed for all primary circuit components whose failure must be demonstrated to be incredible. These incredibility of failure components include the reactor pressure vessel, the pressurizer, steam generator shells and reactor coolant pump casings. All of them are to be inspected by repeated, independent inspections using diverse techniques to ensure the highest reliability. The inspections themselves are checked by an independent inspection validation center. This paper reviews the progress made in implementing the above proposals. A number of components have already been inspected, other inspections are imminent. The work has required major technical and administrative innovations and these are described

Station black out of Fukushima Daiichi Nuclear Power Station Unit 1 was not caused by tsunamis

International Nuclear Information System (INIS)

Ito, Yoshinori

2013-01-01

Station black out (SBO) of Fukushima Daiichi Nuclear Power Station Unit 1 would be concluded to be caused before 15:37 on March 11, 2011 because losses of emergency ac power A system was in 15:36 and ac losses of B system in 15:37 according to the data published by Tokyo Electric Power Co. (TEPCO) in May 10, 2013. Tsunami attacked the site of Fukushima Daiichi Nuclear Power Station passed through the position of wave amplitude meter installed at 1.5 km off the coast after 15:35 and it was also recognized tsunami arrived at the coast of Unit 4 sea side area around in 15:37 judging from a series of photographs taken from the south side of the site and general knowledge of wave propagation. From a series of photographs and witness testimony, tsunami didn't attack Fukushima Daiichi Nuclear Power Station uniformly and tsunami's arrival time at the site of Unit 1 would be far later than arrival time at the coast of Unit 4 sea side area, which suggested it would be around in 15:39. TEPCO insisted tsunami passed through 1.5 km off the coast around in 15:33 and clock of wave amplitude meter was incorrect, which might be wrong. Thus SBO of Fukushima Daiichi Nuclear Power Station Unit 1 occurred before tsunami's arrival at the site of Unit 1 and was not caused by tsunami. (T. Tanaka)

Decommissioning of nuclear power stations

International Nuclear Information System (INIS)

Gregory, A.R.

1988-01-01

In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

Development and construction of nuclear power and nuclear heating stations in the USSR

International Nuclear Information System (INIS)

Schmidt, G.; Kirmse, B.

1983-01-01

The state-of-the-art of nuclear power technology in the USSR is reviewed by presenting characteristic data on design and construction. The review takes into consideration the following types of facilities: Nuclear power stations with 1000 MWe pressurized water reactors, with 1000 MWe pressure tube boiling water reactors, and with 600 MWe fast breeder reactors; nuclear heating power stations with 1000 MWe reactors and nuclear heating stations with 500 MWth boiling water reactors

Democracy and the Sizewell inquiry

International Nuclear Information System (INIS)

Armstrong, J.

1987-01-01

In this paper the brief summary of selected procedural aspects of the Sizewell Inquiry indicates that the way in which major and controversial planning proposals are subject to public debate is in need of urgent review. The Sizewell Inquiry fell short of public expectation, and indeed of Government promises, on two major counts; it did not provide a forum for the debate of certain questions which are clearly of utmost importance and concern to the nuclear issue, while its semi-judicial format and unbalanced funding effectively discouraged and often prevented the level of participation which many objecting parties sought. The Government's assurance of a 'full and fair' debate proved to be hollow and in some quarters this has served to increase scepticism of the stated desire for public involvement in nuclear decision-making. Of the major controversies which have been in the subject of public inquiries in recent years, nuclear power is clearly one of the most challenging. It brings together an extremely varied band of objectors which, in the light of recent radioactive leakages from Windscale, future plans for waste storage facilities and the proposed plutonium reprocessing plant at Dounreay, promises only to grow

Nuclear power stations in August: information and commentary

International Nuclear Information System (INIS)

Rogozhin, Yu.

1989-01-01

A summary of events at nuclear power stations in the USSR in August 1989 is given. There were 44 nuclear power units in service which had 9 unplanned shutdowns and 13 unsanctioned power reductions. Gosatomenergonadzor SSSR is also responsible for all research and marine reactors. It is reported that there are currently (1989) six nuclear vessels in the USSR and no major accidents or damage to nuclear steam-generating units on these were reported. On-site inspectors maintain a constant presence at nuclear power stations to supervise operation and make sure safety requirements are enforced. Glasnost is opening up previously forbidden areas to the public to enable it to obtain information to allow objective assessment to be made. (author)

Review of radioactive discharges from nuclear power stations

International Nuclear Information System (INIS)

1991-02-01

HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report is a review of the arisings and concludes that suitable technologies exist, which if applied, could reduce discharges from nuclear power plants in England and Wales in line with the rest of Europe. (author)

Hinkley Point 'C' power station public inquiry: proof of evidence on emergency planning

International Nuclear Information System (INIS)

Western, D.J.

1988-09-01

A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom, adjacent to an existing nuclear power station incorporating Magnox and Advanced Gas Cooled reactors. The CEGB evidence to the Inquiry presented here introduces the concept of the Reference Accident as the basis for emergency arrangements. The description which follows of the emergency arrangements at the Hinkley Point site include: the respective responsibilities and their co-ordination of bodies such as the CEGB, external emergency services and government departments; the site emergency organization; practical aspects of the emergency arrangements; and consideration of the extension of the arrangements to a PWR on the same site. Recent developments in emergency planning, such as those arising out of post Chernobyl reviews and the Sizewell ''B'' PWR Inquiry, are taken into account. The conclusion is reached that soundly based emergency arrangements already exist at Hinkley Point which would require relatively minor changes should the proposed PWR be constructed. (UK)

Environmental radiation monitoring system in nuclear power station

International Nuclear Information System (INIS)

Matsuoka, Sadazumi; Tadachi, Katsuo; Endo, Mamoru; Yuya, Hiroshi

1983-01-01

At the time of the construction of nuclear power stations, prior to their start of operation, the state of environmental radiation must be grasped. After the start of the power stations, based on those data, the system of environmental radiation monitoring is established. Along with the construction of Kashiwazaki-Kariwa Nuclear Power Station, The Tokyo Electric Power Co., Inc. jointly with Fujitsu Ltd. has developed a high-reliability, environmental radiation monitoring system, and adopted ''optical data highways'' using optical fiber cables for communication. It consists of a central monitoring station and 11 telemeter observation points, for collecting both radiation and meteorological data. The data sent to the central station through the highways are then outputted on a monitoring panel. They are analyzed with a central processor, and the results are printed out. (Mori, K.)

Validated automated ultrasonic inspections of the Sizewell 'B' reactor pressure vessel

International Nuclear Information System (INIS)

Dikstra, B.J.; Farley, J.M.

1992-01-01

Automated ultrasonic inspection was applied extensively during manufacture of the RPV for Sizewell 'B'. This was an important element of the safety case presented at the Sizewell 'B' public enquiry. This requirement reflected concern in the United Kingdom as to the effectiveness and reliability of ultrasonic inspections. By applying automated inspections in addition to the manual ultrasonic inspection carried out by the vessel manufacturer, the overall reliability of the inspection of the vessel would be considerably enhanced. The automated inspections carried out in the manufacturer's workshops were termed 'automated shop inspections' (ASIs). The ASIs were carried out in two contracts: the first to inspect the component forgings of the RPV, the second to inspect the pressure retaining welds. (author)

The legal framework for nuclear power stations in the Federal Republic of Germany

International Nuclear Information System (INIS)

Schmidt-Preuss, M.

2008-01-01

Within the range of the power generation the part of nuclear energy amounts 22 % in Germany in the year 2007. The author of the contribution under consideration describes the legal framework for nuclear power stations in the Federal Republic of Germany. The following aspects are described: (a) The atomic law and the completion of the power generation from nuclear energy; (b) The disposal of nuclear wastes; (c) The Euratom contract; (d) The institutional framework for the execution of the atomic energy law; (e) Legal protection opposite atom legal sovereignty documents; (f) future of the atomic law; (g) European Union-Russian partnership agreement and cooperation agreement. In order to guarantee a sustainable power supply for the production of goods and services in a national economy, also the legal framework for nuclear power stations in Germany must be realized

Present status of maintenance in nuclear power stations

International Nuclear Information System (INIS)

Fueki, Kensuke

1982-01-01

For nuclear power stations, the improvement of the rate of facility utilization is indispensable. As its means, the shortening of regular inspection period, the adoption of long term cycle operation, the shortening of plant shutdown period by the improvement of the reliability of installed equipment and so on are conceivable. In this paper, the maintenance techniques in nuclear power stations which constitute the basis of reliability improvement are explained. In nuclear power stations, the use of nuclear fuel, accordingly the existence of radioactivity are the remarkable features. At the time of an accident, the nuclear reaction in a reactor must be stopped, and the excessive heat must be removed. The radioactivity in nuclear fuel must not be released outside. The regular inspection of once a year is provided by the law, and routine tests are performed during normal operation. The check-up by operators also is a part of the safety measures. For the early detection of abnormality, the diagnosis system is developed, and the maintenance techniques during operation are examined for being taken into the safety test and standard. The improvement of reliability is attempted by the redundancy of systems. The activity of quality assurance, the organization for the maintenance of nuclear power stations and maintenance works, and the measures to raise the rate of operation are reported. (Kako, I.)

Coal price prospects and availability of coal in the U.K. power generation market

International Nuclear Information System (INIS)

Parker, M.J.

1983-02-01

The availability and cost of National Coal Board coal is discussed with respect to the CEGB's economic case for Sizewell B nuclear power station. It is concluded that an investment which depended for its viability on an early or rapid escalation in international coal prices, or upon this escalation continuing indefinitely into the future, would not be sound. (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Matthews, R.R.

1982-11-01

Descriptions are given of the CEGB's organizational structure and the policies and practices developed within the Board to achieve safety in its nuclear plants. The division of nuclear safety responsibilities within the CEGB and between the various UK nuclear organizations is outlined. The achievement of nuclear safety and radiological protection in design and in operation is discussed. (U.K.)

Emergency protection and nuclear power station remote monitoring

International Nuclear Information System (INIS)

Nowak, K.; Wolf, H.

1986-01-01

The States of the Federal Republic of Germany are planning emergency protection measures for the environment of nuclear power stations based on their statutory duty of care. In this connection the paper explains to what extent remote monitoring of nuclear power stations practised by the Federal Supervisory Authorities may support the design and implementation of emergency protection measures. (orig.) [de

Massive use of pulverized fuel ash in concrete for the construction of a U.K. power station

International Nuclear Information System (INIS)

Davies, D.R.; Kitchener, J.N.

1996-01-01

This paper describes the incorporation and benefits of pulverized fuel ash (PFA) in nearly 620,000 m 2 of concrete used in the construction of the UK's first commercial pressurized light water nuclear reactor power station, Sizewell B, Suffolk. Overall nearly 100,000 t of PFA, 1,300 t of sintered fly ash lightweight aggregate, and nearly 137,000 t of Ordinary Portland Cement (OPC) were used in the works. Generally in the construction of the main power station buildings, structural concrete with a characteristic strength of 45 N/mm 2 was placed and included fly ash as 40% of the cementitious component. Also, concrete with fly ash as 50% of the cementitious component was placed as mass fill. The program of research is reported, including sulfate resistance, heat of hydration,elastic properties, alkali-silica reaction, and long-term strength test results. Test and field results are presented and discussed. Strict quality assurance procedures were enforced and statistical summaries are offered to give an insight into the quality of control exercised. Test work and long-term results are also outlined

Remerschen nuclear power station with BBR pressurized water reactor

International Nuclear Information System (INIS)

Hoffmann, J.P.

1975-01-01

On the basis of many decades of successful cooperation in the electricity supply sector with the German RWE utility, the Grand Duchy of Luxemburg and RWE jointly founded Societe Luxembourgeoise d'Energie Nucleaire S.A. (SENU) in 1974 in which each of the partners holds a fifty percent interest. SENU is responsible for planning, building and operating this nuclear power station. Following an international invitation for bids on the delivery and turnkey construction of a nuclear power station, the consortium of the German companies of Brown, Boveri and Cie. AG (BBC), Babcock - Brown Boveri Reaktor GmbH (BBR) and Hochtief AG (HT) received a letter of intent for the purchase of a 1,300 MW nuclear power station equipped with a pressurized water reactor. The 1,300 MW station of Remerschen will be largely identical with the Muelheim-Kaerlich plant under construction by the same consortium near Coblence on the River Rhine since early 1975. According to present scheduling, the Remerschen nuclear power station could start operation in 1981. (orig.) [de

Experience gained in the operation of the Beznau nuclear power station

International Nuclear Information System (INIS)

Kueffer, K. von.

1976-01-01

The 24th December 1969, when the Beznau 1 nuclear power station was placed in commercial operation, marked the beginning of electricity production from nuclear energy in Switzerland. Beznau 2 followed on the 15th March 1972. Together with the Muehleberg nuclear power station, nuclear energy accounts for approximately 20 percent of the total electricity production in Switzerland. Until the end of 1975, Switzerland's three nuclear power stations had a mean energy utilisation factor of 71.3 percent which, as compared with a mean energy utilization factor of 60.5 percent for all the nuclear power stations in the West, suggests fairly good operational results. Problems that arose during operation are discussed in detail. By way of summary it is stated that the operation of the Beznau nuclear power station has so far proved a success. The production of electrical energy has always remained within the limits imposed by the law and by the safety aspects. (Auth.)

Human reliability analysis of Lingao Nuclear Power Station

International Nuclear Information System (INIS)

Zhang Li; Huang Shudong; Yang Hong; He Aiwu; Huang Xiangrui; Zheng Tao; Su Shengbing; Xi Haiying

2001-01-01

The necessity of human reliability analysis (HRA) of Lingao Nuclear Power Station are analyzed, and the method and operation procedures of HRA is briefed. One of the human factors events (HFE) is analyzed in detail and some questions of HRA are discussed. The authors present the analytical results of 61 HFEs, and make a brief introduction of HRA contribution to Lingao Nuclear Power Station

On the troubles happened in nuclear power stations, 1995

International Nuclear Information System (INIS)

1996-01-01

The troubles which happened at the nuclear power stations of Japan in the fiscal year of 1995 are described in this report. The number of troubles in those power stations reported from the corporations of electric industry to Nuclear Safety Commission according to The Law for Regulation of Nuclear Fertile Material, Nuclear Fuel Material and Reactors and Utility Industry Law were 14 in the year and so, the number per reactor was 0.3. The details of the trouble cases were as follows; one and nine cases for automatic and manual shutdowns in operation, respectively and 4 cases found during a down-time of the reactor. But, there was no influence on the environment surrounding those nuclear power stations by the radioactive materials in either of the cases. (M.N.)

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)

National Nuclear Corporation Limited report and financial statements 31 March 1988

International Nuclear Information System (INIS)

1988-01-01

The Group is engaged in designing and constructing power stations and nuclear power reactors and other related work and in associated research and development. Work on the Advanced Gas Cooled Reactor Power Stations at Heysham II and Torness has continued during the year. A variety of work continues to be undertaken on completed stations at Hinkley Point 'B', Heysham I, Hartlepool and Dungeness 'B' through the company's Operational Support Unit which was formed during the year. The Unit is pursuing work on other nuclear stations. Work on the Sizewell 'B' PWR under the Central Electricity Generating Board's Project Management Team is proceeding well. In June 1988 the company was awarded a contract to assist the Ministry of Defence in the management of several major projects. The accounts are presented. It is shown that the profit available to the shareholders for the year ended 31 March 1988 is Pound 4,219,000. Research and development has been undertaken on AGRs, PWRs and fast reactors. Its technologies cover chemistry, materials, heat transfer, fluid flow, mechanical engineering and instrumentation. (author)

Plant computer system in nuclear power station

International Nuclear Information System (INIS)

Kato, Shinji; Fukuchi, Hiroshi

1991-01-01

In nuclear power stations, centrally concentrated monitoring system has been adopted, and in central control rooms, large quantity of information and operational equipments concentrate, therefore, those become the important place of communication between plants and operators. Further recently, due to the increase of the unit capacity, the strengthening of safety, the problems of man-machine interface and so on, it has become important to concentrate information, to automate machinery and equipment and to simplify them for improving the operational environment, reliability and so on. On the relation of nuclear power stations and computer system, to which attention has been paid recently as the man-machine interface, the example in Tsuruga Power Station, Japan Atomic Power Co. is shown. No.2 plant in the Tsuruga Power Station is a PWR plant with 1160 MWe output, which is a home built standardized plant, accordingly the computer system adopted here is explained. The fundamental concept of the central control board, the process computer system, the design policy, basic system configuration, reliability and maintenance, CRT display, and the computer system for No.1 BWR 357 MW plant are reported. (K.I.)

Energy analysis of nuclear power stations

International Nuclear Information System (INIS)

Lindhout, A.H.

1975-01-01

A study based on a 1000MWe light water reactor power station was carried out to determine the total energy input and output of the power station. The calculations took into account the mining and processing of the ore, enrichment of the uranium, treatment of used nuclear fuel, investment in land, buildings, machinery, and transport. 144 tons of natural uranium produce 6100 million kWh (electric) and 340 million kWh (thermal) per annum. (J.S.)

Annual report of operation management in nuclear power stations, fiscal year 1985

International Nuclear Information System (INIS)

1986-09-01

Twenty years have elapsed since the first practical nuclear reactor in Japan started the operation. In the generated power in fiscal year 1985, that of nuclear power stations for the first time overtook that of thermal power stations, and now the age of nuclear power as the main and oil power as the subordinate has begun. As of the end of fiscal year 1985, there were 32 nuclear power plants in operation, having total output capacity of 24.521 million kW. In fiscal year 1985, nuclear power plants generated about 159 billion kWh, which is about 26 % of electric power supply. As to the capacity factor, 76 % was attained in fiscal year 1985, and this is ranked in the top group of LWR-operating countries in the world. It showed that the Japanese technology of nuclear power generation is at the top level in the world. However, in order to increase nuclear power generation and to accomplish the role of main electric power source hereafter, it is necessary to further increase the reliability and economical efficiency. The list of nuclear power stations in Japan, the state of operation of nuclear power stations, the state of accidents and troubles, the state of regular inspection, the management of radioactive wastes and the radiation exposure of workers in nuclear power stations, the operational management and others are reported. (Kako, I.)

Argentinian experience in selecting sites for nuclear power stations

International Nuclear Information System (INIS)

Csik, B.J.

1975-01-01

One nuclear power station is in operation in the Republic of Argentina, a second is under construction, and the decision to build a third has been taken. According to existing plans, about ten nuclear power stations should go into operation during the next decade. The present paper analyses the experience acquired in selecting sites for the first units, commenting on the criteria and methods applied, the studies that were carried out, the specific problems encountered and the solutions adopted, as well as on the question of acceptance of the chosen sites by the public. It goes on to describe the current programme of selection and study of sites for future nuclear power stations

Aseismic foundation system for nuclear power stations

International Nuclear Information System (INIS)

Jolivet, F.; Richli, M.

1977-01-01

The aseismic foundation system, as described in this paper, is a new development, which makes it possible to build standard nuclear power stations in areas exposed to strong earthquakes. By adopting proven engineering concepts in design and construction of components, great advantages are achieved in the following areas: safety and reliability; efficiency; design schedule; cost. The need for an aseismic foundation system will arise more and more, as a large part of nuclear power station sites are located in highly seismic zones or must meet high intensity earthquake criteria due to the lack of historic data. (Auth.)

Planning and preparedness for radiological emergencies at nuclear power stations

International Nuclear Information System (INIS)

Thomson, R.; Muzzarelli, J.

1996-01-01

The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

Costs of producing electricity from nuclear, coal-fired and oil-fired power stations

International Nuclear Information System (INIS)

1980-07-01

The Board publishes generation costs per kW h incurred at recently commissioned power stations so that the costs and performance of nuclear and conventional stations of roughly the same date of construction can be compared. The term 'conventional power station' is used to describe coal-fired and oil-fired steam power stations. The Board has now decided: (A) to supplement the past method of calculating costs at main stations commissioned between 1965 and 1977 by giving the associated figures for interest during construction, for research, and for training; (B) to give similar figures for the contemporary stations Hinkley Point B and the first half of Drax, (C) to provide estimates of generating costs of stations under construction; (D) to set out explicitly the relationship of this method of calculation to that employed in taking investment decisions on future stations. In this way the figures for stations in commission and under construction are arrived at more in line with the general principles of evaluating investment proposals. The present document provides this information. (author)

Core power distribution measurement and data processing in Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Zhang Hong

1997-01-01

For the first time in China, Daya Bay Nuclear Power Station applied the advanced technology of worldwide commercial pressurized reactors to the in-core detectors, the leading excore six-chamber instrumentation for precise axial power distribution, and the related data processing. Described in this article are the neutron flux measurement in Daya Bay Nuclear Power Station, and the detailed data processing

The decommissioning of nuclear power stations

International Nuclear Information System (INIS)

Barker, F.

1992-01-01

This report has been commissioned by the National Steering Committee of Nuclear Free Local Authorities to provide: a comprehensive introduction to the technical, social, political, environmental and economic dimensions to nuclear power station decommissioning; an independent analysis of Nuclear Electric's recent change of decommissioning strategy; the case for wider public involvement in decision making about decommissioning; and a preliminary assessment of the potential mechanisms for achieving that essential wider public involvement

Validation gets underway on Sizewell ''Incredibility of Failure'' components

International Nuclear Information System (INIS)

Anon.

1992-01-01

The Inspection Validation Centre (IVC) of AEA Reactor Services in the UK has begun an eighteen month programme to validate the procedures and personnel of OIS plc, the inspection agents chosen by Nuclear Electric to carry out the pre-service ultrasonic inspection of the Sizewell B Pressurized Water Reactor components assigned to the ''Incredibility of Failure'' (IoF) category. The work involves several Sizewell B primary circuit components - the steam generators, pressurizer, and primary pumps - and will consider the inspections to be applied to the circumferential and nozzle-to-shell welds, nozzle inner radii and the pump fly-wheel forging. The validation will provide independent confirmation that OIS personnel are capable of using manual and automated methods to find and size any flaws of structural concern in these components. (author)

Hinkley Point 'C' power station public inquiry: proof of evidence on potential off-site effects of radiation

International Nuclear Information System (INIS)

Western, D.J.

1988-09-01

A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom. This evidence to the Inquiry is concerned with the potential of the proposed Hinkely Point ''C'' PWR to increase the exposure of members of the public offsite to radiation. The policy is to replicate the design of the Sizewell ''B'' reactor. The evidence examined in great detail at the Sizewell ''B'' Public Inquiry where the Inspector concluded that the risk would be very small. The purpose of this evidence is to provide an explicit account of the potential off-site effects of radiation at the Hinkley Point site, so that it can be seen that there is nothing specific to this location that could lead to a different conclusion. (author)

Research on application of knowledge engineering to nuclear power stations

International Nuclear Information System (INIS)

Umeda, Takeo; Kiyohashi, Satoshi

1990-01-01

Recently, the research on the software and hardware regarding knowledge engineering has been advanced eagerly. Especially the applicability of expert systems is high. When expert systems are introduced into nuclear power stations, it is necessary to make the plan for introduction based on the detailed knowledge on the works in nuclear power stations, and to improve the system repeatedly by adopting the opinion and request of those in charge upon the trial use. Tohoku Electric Power Co. was able to develop the expert system of practically usable scale 'Supporting system for deciding fuel movement procedure'. The survey and analysis of the works in nuclear power stations, the selection of the system to be developed and so on are reported. In No. 1 plant of Onagawa Nuclear Power Station of BWR type, up to 1/3 of the fuel is replaced at the time of the regular inspection. Some fuel must be taken to outside for ensuring the working space. The works of deciding fuel movement procedure, the development of the system and its evaluation are described. (K.I.)

Experience in safeguarding nuclear material at the Rheinsberg nuclear power station

International Nuclear Information System (INIS)

Winkler, R.

1976-01-01

The three years' experience that has been gained in application of the Safeguards Agreement shows that the carrying out of inspections at the nuclear power plant has virtually no effect on operating conditions. In future it will be possible to reduce this effect even further and still maintain the operational reliability of the station. Verification of the transfer of nuclear material and detection of possible violations have proved relatively simple. The labour requirement of each unit at the station for the performance of inspections is not more that thirty man-days. Constructive collaboration between power station staff and inspectors is of great importance in improving the safeguards procedures. (author)

Computer based training simulator for Hunterston Nuclear Power Station

International Nuclear Information System (INIS)

Bowden, R.S.M.; Hacking, D.

1978-01-01

For reasons which are stated, the Hunterston-B nuclear power station automatic control system includes a manual over-ride facility. It is therefore essential for the station engineers to be trained to recognise and control all feasible modes of plant and logic malfunction. A training simulator has been built which consists of a replica of the shutdown monitoring panel in the Central Control Room and is controlled by a mini-computer. This paper highlights the computer aspects of the simulator and relevant derived experience, under the following headings: engineering background; shutdown sequence equipment; simulator equipment; features; software; testing; maintenance. (U.K.)

Reviewing nuclear power station achievement

International Nuclear Information System (INIS)

Howles, L.R.

1976-01-01

For measurement of nuclear power station achievement against original purchase the usual gross output figures are of little value since the term loosely covers many different definitions. An authentically designed output figure has been established which relates to net design output plus house load at full load. Based on these figures both cumulative and moving annual load factors are measured, the latter measuring the achievement over the last year, thus showing trends with time. Calculations have been carried out for all nuclear stations in the Western World with 150 MW(e) gross design output and above. From these are shown: moving annual load factor indicating relative station achievements for all the plants; cumulative load factors from which return of investment can be calculated; average moving annual load factors for the four types of system Magnox, PWR, HWR, and BWR; and a relative comparison of achievement by country in a few cases. (U.K.)

Insurance of nuclear power stations

International Nuclear Information System (INIS)

Debaets, M.

1992-01-01

Electrical utility companies have invested large sums in the establishment of nuclear facilities. For this reason it is normal for these companies to attempt to protect their investments as much as possible. One of the methods of protection is recourse to insurance. For a variety of reasons traditional insurance markets are unable to function normally for a number of reasons including, the insufficient number of risks, an absence of meaningful accident statistics, the enormous sums involved and a lack of familiarity with nuclear risks on the part of insurers, resulting in a reluctance or even refusal to accept such risks. Insurers have, in response to requests for coverage from nuclear power station operators, established an alternative system of coverage - insurance through a system of insurance pools. Insurers in every country unite in a pool, providing a net capacity for every risk which is a capacity covered by their own funds, and consequently without reinsurance. All pools exchange capacity. The inconvenience of this system, for the operators in particular, is that it involves a monopolistic system in which there are consequently few possibilities for the negotiation of premiums and conditions of coverage. The system does not permit the establishment of reserves which could, over time, reduce the need for insurance on the part of nuclear power station operators. Thus the cost of nuclear insurance remains high. Alternatives to the poor system of insurance are explored in this article. (author)

Nuclear power stations. Information paper no. 1. Controls on the building and running of nuclear power stations

Energy Technology Data Exchange (ETDEWEB)

1981-09-01

Controls and constraints which govern the development and running of nuclear power stations are briefly examined. Government policy, permission to build, authority to start building, site acquisition building, running and public opinion are briefly discussed.

Validation results of the pre-service ultrasonic inspections of the Sizewell B pressurizer and steam generators and reactor coolant pump flywheels

International Nuclear Information System (INIS)

Conroy, P.J.; Leyland, K.S.

1995-01-01

In the UK, concern over the safety issues associated with nuclear power generation resulted in a demand for a public inquiry into the construction and operation of Sizewell ''B'', Britain's first PWR. This public inquiry was additional to the UK's normal licensing process. The onus was placed upon the UK utility, CEGB (now Nuclear Electric plc) to provide evidence to the inquiry to support the case that the plant would be constructed and operated to a sufficiently high standard of safety. Part of the evidence to the inquiry (1) relied upon the ability of ultrasonic inspections to verify that the reactor pressure vessel and other safety critical components (collectively known as IoF components), were free from defects that could threaten structural integrity. At that time, the body of evidence showed that although ultrasonic inspection had the potential to satisfy this requirement, it would be necessary to validate the procedures and key operators used in order to provide assurance that they were adequate. Inspection validation therefore became an integral part of the UK PWR nuclear power program

Standard concerning the design of nuclear power stations in earthquake-prone districts

International Nuclear Information System (INIS)

Kirillov, A.P.; Anbriashivili, Y.K.; Suvilova, A.V.

1980-01-01

The measures of security assurance against the effect of radioactive contamination has become more and more complex due to the construction of nuclear power stations of diverse types. The aseismatic measures for the nuclear power stations built in the districts where earthquakes of different intensity occur are important problems. All main machinery and equipments and emergency systems in power stations must be protected from earthquakes, and this makes the solution of problems difficult. At present in USSR, the provisional standard concerning the design of atomic energy facilities built in earthquake-prone districts is completed. The basic philosophy of the standard is to decide the general requirements as the conditions for the design of nuclear power stations built in earthquake-prone districts. The lowest earthquake activity in the construction districts is considered as magnitude 4, and in the districts where earthquake activity is magnitude 9 or more, the construction of nuclear power stations is prohibited. Two levels of earthquake action are specified for the design: design earthquake and the largest design earthquake. The construction sites of nuclear power stations must be 15 to 150 km distant from the potential sources of earthquakes. Nuclear power stations are regarded as the aseismatically guaranteed type when the safety of reactors is secured under the application of the standard. The buildings and installations are classified into three classes regarding the aseismatic properties. (Kako, I.)

Inspecting Sizewell B Class 1 and IoF components

International Nuclear Information System (INIS)

McNulty, T.

1990-01-01

Class 1 and ''incredibility of failure'' (IoF) pre-service inspections for Sizewell B cover steam generator and pressurizer welds and nozzles, welds on the emergency boration system, accumulators and reactor coolant loop, and the whole of the Class 1 piping. The contractor for this work has recently been selected. The scope of the work and the techniques and equipment to be used are outlined. (author)

The Spanish Nuclear Safety Council and nuclear power stations in operation in Spain

International Nuclear Information System (INIS)

Perello, M.

1984-01-01

On 20 April 1980 the Spanish Congress of Deputies passed an Act setting up the Nuclear Safety Council (CSN) as the sole organization responsible for nuclear safety and radiation protection. In this paper it is stated that that date marked the beginning of a new nuclear safety policy in Spain. As one of its objectives, this policy is aimed at the monitoring and testing of operating nuclear installations. A detailed description is given of the Operating Nuclear Installation Service (SINE), including its basic structure, its functions and the technical and manpower resources available to it. The maintenance of close relations with other organs of the CSN is considered of paramount importance in order for the tasks allotted to SINE to be fulfilled. International co-operation and outside contracting greatly assist importing countries which have limited manpower resources. A description is then given of the present state of the nuclear power stations in operation in Spain together with an account of the most important initiatives which have been taken so far. The year 1968 saw the beginning of commercial operation of the Jose Cabrera nuclear power station, which has the only single-loop PWR reactor in the world. At present, it is being subjected to the Systematic Evaluation Programme (SEP). The Santa Maria de Garona nuclear power station has been operating for over twelve years and is also being subjected to the SEP although design modifications derived from operating experience have already been introduced. The Vandellos I station was the last of the first generation and has also benefited from the operating experience of similar French plants. Unit 1 of the Almaraz power station opens the door to the second generation and the generic problem which has occurred with the steam generators is in process of being solved. Lastly, some general conclusions are presented about the organization of and experience acquired with operating nuclear power stations. (author)

Stade nuclear power station (KKS): four giants on tour

International Nuclear Information System (INIS)

Beverungen, M.; Viermann, J.

2008-01-01

The Stade nuclear power station was the first nuclear power plant in the Federal Republic of Germany to deliver heat in addition to electricity. Since 1984, district heat was distributed to a saltworks nearby. The power plant, which is situated on the banks of the river Elbe, was commissioned in 1972 after approximately 4 years of construction. Together with the Wuergassen plant, it was among the first commercial nuclear power plants in this country. E.ON Kernkraft holds a 2/3 interest, Vattenfall Europe a 1/3 interest in the nuclear power plant. The Stade nuclear power station was decommissioned on November 14, 2003 for economic reasons which, in part, were also politically motivated. In September 2005, the permit for demolition of the nuclear part was granted. The release from supervision under the Atomic Energy Act is expected for 2014. In the course of demolition, the 4 steam generators of the Stade nuclear power station were removed. These components, which have an aggregate weight of approx. 660 tons, are to be safely re-used in Sweden. In September 2007, the steam generators were loaded on board the Swedish special vessel, MS Sigyn, by means of a floating crane. After shipment to Sweden, heavy-duty trucks carried the components to the processing hall of Studsvik AB for further treatment. After 6 months of treatment, the contaminated inner surfaces of the tube bundles of the steam generators have been decontaminated successfully, among other items. This has increased the volume of material available for recycling and thus decreased the volume of residues. (orig.)

The crumbling case for nuclear power

International Nuclear Information System (INIS)

Bunyard, P.

1983-01-01

In connection with the Public Inquiry into the CEGB proposal to build a pressurised water reactor at Sizewell in Suffolk, the case for nuclear power is examined under the headings: the economics of nuclear power - how they would like them to be; systems analysis - net effective cost; CEGB prejudices the results (comparison with coal-fired plants; forecasting on various assumptions); discounting future costs; back-end costs soar (reprocessing); real reprocessing costs; AGR costs balloon. (U.K.)

Radiation protection in the design and operation of Sizewell B

International Nuclear Information System (INIS)

Oldfield, M.

1989-01-01

This paper raises Health Physics operational issues specific to PWR or not previously encountered by the CEGB, which need to be resolved before the operation of Sizewell B and its replica successors. Staffing, access to contamination areas, training, temporary scaffolding and temporary lead shielding are discussed and the author makes some observations and suggestions. (author)

Economic and financial benefits as a compensation for living near a nuclear power station. A case study of Kashiwazaki-Kariwa Nuclear Power Station

International Nuclear Information System (INIS)

Kato, Takaaki; Hatta, Masahisa; Matsumoto, Shiro; Nishikawa, Masashi

2007-01-01

Although dwellers living near a nuclear power station are entitled to economic/financial benefits such as increased job opportunities and local tax revenues pertaining to the power station, it is not clear whether such benefits are appreciated by the dwellers. Two findings of this study based upon a social survey of local dwellers living near the Kashiwazaki-Kariwa Nuclear Power Station are summarized as follows. First, an increase in the per capita sizes of the local tax revenue and national subsidies resulted in a larger share of respondents who thought that those revenues are beneficial. Therefore, local dwellers are aware of the sizes of economic/financial benefits. Second, given the same risk level of nuclear disaster, a larger per capita financial benefit resulted in a larger share of respondents who felt compensated for the nuclear risk. However, this increase in the number of compensated respondents is low relative to the increase in the amount of financial benefits. (author)

Reload Startup Physics Tests for Tianwan Nuclear Power station

International Nuclear Information System (INIS)

Yang Xiaoqiang; Li Wenshuang; Li Youyi; Yao Jinguo; Li Zaipeng Jiangsu

2010-01-01

This paper briefly describes the test purposes, test items, test schedules and test equipment's for reload startup physics test's on Unit 1 and 2 of Tianwan Nuclear Power station. Then, an overview of the previous thrice tests and evaluations on the tests results are presented. In the end, the paper shows the development and work direction of optimization project for reload startup physics tests on Unit 1 and 2 of Tianwan Nuclear Power station. (Authors)

The management of interfaces between organizations involved with the construction of Sizewell 'B'

International Nuclear Information System (INIS)

Butler, P.H.; Salmons, B.H.

1990-01-01

The overall organisation for the design, construction and commissioning of Sizewell 'B' is described, together with the specific responsibilities of the organisations involved. The paper describes how the parameters for each interface are identified, and how the formal arrangements for controlling transmission of information and material are handled. Whilst each organisation will perceive quality achievement as the ultimate objective, the specific individual responsibilities may dictate different, and sometimes opposing mechanisms for implementation, due to different perceptions of priority. The PWR Project Group has the ultimate responsibility for building Sizewell 'B' to cost and schedule and to the specified quality, and the paper describes, with some examples, how the different perceptions are addressed in order to achieve the ultimate objective. (author)

Impact studies and nuclear power stations

International Nuclear Information System (INIS)

Chambolle, Thierry

1981-01-01

Impact studies form an essential part of environmental protection. The impact study discipline has enabled the EDF to have a better understanding of the effects of nuclear power stations on the environment and to remedy them at the project design stage [fr

Principle simulator for a PWR nuclear power station

International Nuclear Information System (INIS)

Wahlstroem, B.

1975-05-01

A report is given on a simulator developed for the training of operational and planning staff for the Lovisa nuclear power station in Finland. All main components of the power station are illustrated and trainees can operate the simulator in the power range 3-100 %. The model was originally developed for planning the control system of Lovisa I, for which reason the simulator project could be carried out on a relatively limited budget. (author)

Industrial relations and site management proposals for Sizewell 'B'

International Nuclear Information System (INIS)

Burbridge, R.N.

1986-01-01

The vendor assessment and general contract strategy for the proposed Sizewell 'B' PWR are reviewed with particular reference to a 'Key Date' procedure. The family of programmes used in constructing CEGB projects is indicated and the intended site labour strategy for the project is outlined. To exemplify the current success of these policies, the paper concludes with a brief review of their application to the CEGB's Drax Completion Project. (author)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Womack, G.J.

1982-11-01

The safe transport of irradiated fuel is discussed. Firstly the amount of fuel to be handled, the storage of irradiated fuel at the station, the design of the flask to be used and its cost, and the operations and maintenance involved in operating a flask are considered. The regulations for the safe transport of radioactive material are then described. Possible accident situations and their radiological consequences are discussed. It is concluded that the risk to the population and the environment is very small. (U.K.)

Annual report on operational management of nuclear power stations, 1979-1980

International Nuclear Information System (INIS)

1981-04-01

This report was compiled by the Agency of Natural Resoures and Energy. The commercial nuclear power stations in Japan started the operation in 1966 for the first time, and as of the end of March, 1981, 22 plants with more than 15.5 million kW capacity were in operation. Nuclear power generation is regarded as the top-rated substitute energy for petroleum, and the target of its development in 1990 is about 52 million kW. The government and the people are exerting utmost efforts to attain the target. The result of the rate of operation of nuclear power stations reached 60.8% in 1980, but it is important to maintain the good, stable state of operation by perfecting the operational management hereafter in order to establish the position of LWRs. At present, the operational management officers of the government stay in nationwide power stations, and supervise the state of operations, thus the system of operational management was strengthened after the Three Mile Island accident in the U.S., and the improvement in the rate of operation is expected. A table shows the nuclear power stations in operation and under construction. The state of operations of individual nuclear power plants in 1979 and 1980, the accidents and failures occurred in nuclear power plants from 1966 to 1980, the minor troubles, the conditions in the regular inspections of individual nuclear power plants, radioactive waste management and the radiation exposure of workers are reported. (Kako, I.)

Rising to the challenge - the changing face of Nuclear Electric

International Nuclear Information System (INIS)

Hawley, R.

1994-01-01

When the electricity generation industry in the United Kingdom was privatised in 1989, the Government decided to withdraw the nuclear generating capacity from the programme. Nuclear power's poor track record on construction, operating and production costs and apparently crippling liabilities for decommissioning and radioactive waste management made it an unlikely success on the financial markets. Nuclear Electric was then formed, a public limited company, wholly owned by the Government to run England's and Wales' nuclear power industry. In four years since then the management and staff of Nuclear Electric have worked hard to improve performance; output has risen, costs are down and productivity has doubled. The Sizewell B power station has been completed remarkably ahead of time and within budget. It is argued that, with further improvements, Nuclear Electric may also be profitably privatised in the future should the Government wish it. (UK)

Contamination awareness at the Dresden Nuclear Power Station

International Nuclear Information System (INIS)

Pagel, D.J.; Rath, W.C.

1986-01-01

Dresden Nuclear Power Station, which is located ∼ 60 miles southwest of Chicago near Morris, Illinois, has been generating electricity since 1960. Owned by Commonwealth Edison, Dresden was the nation's first privately financed nuclear station. On its site are three boiling water reactors (BWRs). Due to the contamination potential inherent with a reactor, a contamination trending program was created at the station. Studies had indicated a rise in contamination events during refueling outages. Further increases were due to specific work projects such as hydrolyzing operations. The investigations suggested that contract personnel also increased the number of events. In 1983, a contamination awareness program was created. The 1984 contamination awareness program was comprised of the following: (1) a statistical review in which trended contamination events were discussed. (2) A demonstration of protective clothing removal by an individual making various mistakes. (3) Scenarios were developed for use in mock work areas. (4) Upper management involvement. Because of the 1984 program, favorable attention has been focused on Dresden from the US Nuclear Regulatory Commission and the Institute of Nuclear Power Operations

Reload shutdown for Nuclear Power Stations in spain in 2003

International Nuclear Information System (INIS)

2004-01-01

Regarding time reductions in fuel reloading at Spanish nuclear power stations, the Spanish Nuclear Security Council (CSN), at the request of the Spanish Finance and Treasury Department of the Chamber of Deputies, delivered an instruction, by which power station's owners were urged to establish a detailed planning of reload operations. This article includes the results of this instruction. (Author) 6 refs

Distributed systems for protecting nuclear power stations

International Nuclear Information System (INIS)

Jover, P.

1980-05-01

The advantages of distributed control systems for the control of nuclear power stations are obviously of great interest. Some years ago, EPRI, (Electric Power Research Institute) showed that multiplexing the signals is technically feasible, that it enables the availability specifications to be met and costs to be reduced. Since then, many distributed control systems have been proposed by the manufacturers. This note offers some comments on the application of the distribution concept to protection systems -what should be distributed- and ends with a brief description of a protection system based on microprocessors for the pressurized power stations now being built in France [fr

Incinerators for radioactive wastes in Japanese nuclear power stations

International Nuclear Information System (INIS)

Karita, Yoichi

1983-01-01

As the measures of treatment and disposal of radioactive wastes in nuclear power stations, the development of the techniques to decrease wastes, to reduce the volume of wastes, to treat wastes by solidification and to dispose wastes has been advanced energetically. In particular, efforts have been exerted on the volume reduction treatment from the viewpoint of the improvement of storage efficiency and the reduction of transport and disposal costs. Incineration as one of the volume reduction techniques has been regarded as the most effective method with large reduction ratio, but it was not included in waste treatment system. NGK Insulators Ltd. developed NGK type miscellaneous solid incinerators, and seven incinerators were installed in nuclear power stations. These incinerators have been operated smoothly, and the construction is in progress in six more plants. The necessity of incinerators in nuclear power stations and the problems in their adoption, the circumstance of the development of NGK type miscellaneous solid incinerators, the outline of the incinerator of Karlsruhe nuclear power station and the problems, the contents of the technical development in NGK, the outline of NGK type incinerators and the features, the outline of the pretreatment system, incinerator system, exhaust gas treatment system, ash taking out system and accessory equipment, the operational results and the performance are described. (Kako, I.)

Nuclear Electric: the misuse of the subsidy and the case for the immediate closure of Magnox

International Nuclear Information System (INIS)

1992-11-01

The nature and purpose of fossil fuel levy which creates a subsidy for the nuclear industry is discussed. It is claimed that without the subsidy the operation of Magnox and AGR stations generates electricity at a loss. This means that most of the fossil fuel levy is being used to make up Nuclear Electric's losses. The rest is mostly being used to build the Sizewell-B power plant. This is in contrast to the popular belief and understanding that the subsidy is for decommissioning old plants, and cleaning up accumulated spent fuels and other wastes. The economics of the Magnox stations are discussed and Nuclear Electric's claim that closing them would not stop the losses is challenged. (U.K.)

76 FR 50274 - Terrestrial Environmental Studies for Nuclear Power Stations

Science.gov (United States)

2011-08-12

... Draft Regulatory Guides in the ``Regulatory Guides'' collection of the NRC's Library at http://www.nrc... Stations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment... draft regulatory guide (DG), DG-4016, ``Terrestrial Environmental Studies for Nuclear Power Stations...

Nuclear awaits 1994

International Nuclear Information System (INIS)

Collier, J.G.

1992-01-01

When the UK electricity industry was privatised, the Government stated that in 1994 it would undertake a review of the prospects for nuclear power. The future role of nuclear power will be viewed against the improved performance of the nuclear utilities; the success being achieved on the construction of Sizewell B; and the economics taking into account environmental benefits. The chairman of Nuclear Electric reviews the current position of Nuclear Power in Britain and puts the case for nuclear power in the future. (author)

Regulatory experience in nuclear power station decommissioning

International Nuclear Information System (INIS)

Ross, W.M.; Waters, R.E.; Taylor, F.E.; Burrows, P.I.

1995-01-01

In the UK, decommissioning on a licensed nuclear site is regulated and controlled by HM Nuclear Installations Inspectorate on behalf of the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to decommissioning activities and provides a continuous but flexible safety regime until there is no danger from ionising radiations. The regulatory strategy is discussed, taking into account Government policy and international guidance for decommissioning and the implications of the recent white paper reviewing radioactive waste management policy. Although each site is treated on a case by case basis as regulatory experience is gained from decommissioning commercial nuclear power stations in the UK, generic issues have been identified and current regulatory thinking on them is indicated. Overall it is concluded that decommissioning is an evolving process where dismantling and waste disposal should be carried out as soon as reasonably practicable. Waste stored on site should, where it is practical and cost effective, be in a state of passive safety. (Author)

Valves and fittings for nuclear power stations

International Nuclear Information System (INIS)

1976-01-01

The standard specifies technical requirements for valves and pipe fittings in nuclear power stations with PWR type reactors. Details of appropriate materials, welding, surface treatment for corrosion protection, painting, and complementary supply are given

Algological studies on the site of the Fessenheim nuclear power station

International Nuclear Information System (INIS)

Pierre, J.F.

1980-01-01

Systematic study of the algal flora at five stations situated on both sides of the nuclear power station at Fessenheim (department of Haut-Rhin, France). The analysis of the diatomaceae populations in 1977 and 1978, i.e. before and after the start of the reactors, does not indicate, in the composition and abundance of algae, any modifications susceptible to be directly connected to the implantation of the nuclear power station [fr

For sale: 7 AGR stations and a brand new PWR

International Nuclear Information System (INIS)

Anon.

1995-01-01

Britain's seven AGR stations and the Sizewell B PWR will pass to private ownership under the UK government's plan to privatise the two nuclear generators, Nuclear Electric and Scottish Nuclear, sometime next year. Under the new set-up, the two generators will become operating subsidiaries of a holding company which will be headquartered in Scotland. The companies' ageing Magnox gas-cooled reactors will remain in a separate public sector company before being transferred to British Nuclear Fuels (BNFL) at the time of privatisation. (author)

Application of the minicomputer at Genkai Nuclear Power Station

Energy Technology Data Exchange (ETDEWEB)

Kitamura, H [Kyushu Electric Power Co., Inc., Fukuoka (Japan)

1977-03-01

Genkai Nuclear Power Station introduced a minicomputer system for the data control purpose in addition to a process control computer introduced in the same manner as other PWR nuclear power stations. This system employs two computers; the one for on-line data aquisition, and another for data processing. The control system introduced includes four systems amoung various data control businesses in the nuclear power station. The language used is mainly an assembler language. The first is the meteorological control system which collects, edits and transmits the weather data sent from the observation instruments around the power station. The second is the personal radiation exposure control system which is designed to realize the labor-saving in book-keeping, the speed-up and the improvement of accuracy in the preparation of the reports to the authorities and the head office and the data for exposure control, and the unification of data processing. The third is the waste control system composed of three subsystems of gas, liquid and solid waste control. The fourth is the maintenance and repair control system which gives inputs to the computer according to the classification written in the slips for maintenance and repair, and prepares a number of statistical tables for maintenance control.

Expansion potential for existing nuclear power station sites

Energy Technology Data Exchange (ETDEWEB)

Cope, D. F.; Bauman, H. F.

1977-09-26

This report is a preliminary analysis of the expansion potential of the existing nuclear power sites, in particular their potential for development into nuclear energy centers (NECs) of 10 (GW(e) or greater. The analysis is based primarily on matching the most important physical characteristics of a site against the dominating site criteria. Sites reviewed consist mainly of those in the 1974 through 1976 ERDA Nuclear Power Stations listings without regard to the present status of reactor construction plans. Also a small number of potential NEC sites that are not associated with existing power stations were reviewed. Each site was categorized in terms of its potential as: a dispersed site of 5 GW(e) or less; a mini-NEC of 5 to 10 GW(e); NECs of 10 to 20 GW(e); and large NECs of more than 20 GW(e). The sites were categorized on their ultimate potential without regard to political considerations that might restrain their development. The analysis indicates that nearly 40 percent of existing sites have potential for expansion to nuclear energy centers.

Expansion potential for existing nuclear power station sites

International Nuclear Information System (INIS)

Cope, D.F.; Bauman, H.F.

1977-01-01

This report is a preliminary analysis of the expansion potential of the existing nuclear power sites, in particular their potential for development into nuclear energy centers (NECs) of 10 (GW(e) or greater. The analysis is based primarily on matching the most important physical characteristics of a site against the dominating site criteria. Sites reviewed consist mainly of those in the 1974 through 1976 ERDA Nuclear Power Stations listings without regard to the present status of reactor construction plans. Also a small number of potential NEC sites that are not associated with existing power stations were reviewed. Each site was categorized in terms of its potential as: a dispersed site of 5 GW(e) or less; a mini-NEC of 5 to 10 GW(e); NECs of 10 to 20 GW(e); and large NECs of more than 20 GW(e). The sites were categorized on their ultimate potential without regard to political considerations that might restrain their development. The analysis indicates that nearly 40 percent of existing sites have potential for expansion to nuclear energy centers

Loss of cooling accident simulation of nuclear power station spent-fuel pool

Energy Technology Data Exchange (ETDEWEB)

Lee, M.; Liang, K-S., E-mail: mlee@ess.nthu.edu.tw, E-mail: ksliang_1@hotmail.com [National Tsing Hua Univ., Hsinchu, Taiwan (China); Lin, K-Y., E-mail: syrup760914@gmail.com [Taiwan Power Company, Taiwan (China)

2014-07-01

The core melt down accident of Fukushima Nuclear Power Station on March 11th, 2011 alerted nuclear industry that the long term loss of cooling of spent fuel pool may need some attention. The target plant analyzed is the Chinshan Nuclear Power Station of Taiwan Power Company. The 3-Dimensional RELAP5 input deck of the spent fuel pool of the station is built. The results indicate that spent fuel of Chinshan Nuclear Power Station is uncovered at 6.75 days after an accident of loss cooling takes place and cladding temperature rises above 2,200{sup o}F around 8 days. The time is about 13 hours earlier than the results predicted using simple energy balance method. The results also show that the impact of Counter Current Flow Limitation (CCFL) and radiation heat transfer model is marginal. (author)

Dosimetry systems in nuclear power stations

International Nuclear Information System (INIS)

Weidmann, U.

1992-01-01

In the following paper the necessity of the use of electronic dosimetry systems in nuclear power stations is presented, also encompassing the tasks which this type of systems has to fulfill. Based on examples the construction principles and the application possibilities of a PC supported system are described. 5 figs

Design Provisions for Withstanding Station Blackout at Nuclear Power Plants

International Nuclear Information System (INIS)

2015-08-01

International operating experience has shown that the loss of off-site power supply concurrent with a turbine trip and unavailability of the standby alternating current power system is a credible event. Lessons learned from the past and recent station blackout events, as well as the analysis of the safety margins performed as part of the ‘stress tests’ conducted on European nuclear power plants in response to the Fukushima Daiichi accident, have identified the station blackout event as a limiting case for most nuclear power plants. The magnitude 9.0 earthquake and consequential tsunami which occurred in Fukushima, Japan, in March 2011, led to a common cause failure of on-site alternating current electrical power supply systems at the Fukushima Daiichi nuclear power plant as well as the off-site power grid. In addition, the resultant flooding caused the loss of direct current power supply, which further exacerbated an already critical situation at the plant. The loss of electrical power resulted in the meltdown of the core in three reactors on the site and severely restricted heat removal from the spent fuel pools for an extended period of time. The plant was left without essential instrumentation and controls, and this made accident management very challenging for the plant operators. The operators attempted to bring and maintain the reactors in a safe state without information on the vital plant parameters until the power supply was eventually restored after several days. Although the Fukushima Daiichi accident progressed well beyond the expected consequences of a station blackout, which is the complete loss of all alternating current power supplies, many of the lessons learned from the accident are valid. A failure of the plant power supply system such as the one that occurred at Fukushima Daiichi represents a design extension condition that requires management with predesigned contingency planning and operator training. The extended loss of all power at a

Innovations in PHWR design, integration of nuclear power stations into power systems and role of small size nuclear power plants in a developing country

International Nuclear Information System (INIS)

Mehta, S.K.; Kakodkar, A.; Balakrishnan, M.R.; Ray, R.N.; Murthy, L.G.K.; Chamany, B.F.; Kati, S.L.

1977-01-01

PHWR concept of thermal reactors has been considered with a view to exploiting the limited resources of natural uranium and keeping in mind the projected nuclear power programme covering fast breeder reactors. Experience in engineering of current PHWR units in India, gradual build up of necessary infrastructure and operational experience with one unit, have helped in building up design and technological capability in the country. The R and D facilities have been so planned that additional data required for the design of bigger reactor units (i.e.500/600 MWe) could be generated with minimal augmentation. Satisfactory operation of a nuclear power station demands certain prerequisites from the connected power system. The grid should have load patterns suitable for base load operation of these stations, should be stiff so far as voltage and frequency fluctuations are concerned and should have high reliability. A typical power grid in this country is characterised by heavy loads during peak hours and very light loads during night. Regional grids are of small size and the few interconnections existing between the regional grids consist of weak tie lines. Amongst all types of the power stations, it is the nuclear system which undergoes maximum strain and economic penalty while operating when connected to such a power system. Consistent with the above, phase installation of small-size power reactor units of about 200 MWe capacity may facilitate setting up of larger unit sizes at a later date. The effect of any possible reduction in the capital cost of a larger unit power station will enable the power station to partially meet the demand of the more productive types of loads. This paper deals with some of the major design changes that are being incorporated in the PHWR type power reactors currently being set up and the research and development back-up required for the purpose. Since the unit sizes of the power reactors presently contemplated are small compared to nuclear

Electricity Generation Through the Koeberg Nuclear Power Station of Eskom in South Africa

International Nuclear Information System (INIS)

Dladla, G.; Joubert, J.

2015-01-01

The poster provides information on the process of nuclear energy generation in a nuclear power plant in order to produce electricity. Nuclear energy currently provides approximately 11% of the world’s electricity needs, with Koeberg Nuclear Power Station situated in the Western Cape providing 4.4% of South Africa’s electricity needs. As Africa’s first nuclear power station, Koeberg has an installed capacity of 1910 MW of power. Koeberg’ s total net output is 1860 MW. While there are significant differences, there are many similarities between nuclear power plants and other electrical generating facilities. Uranium is used for fuel in nuclear power plants to make electricity. With the exception of solar, wind, and hydroelectric plants, all others including nuclear plants convert water to steam that spins the propeller-like blades of a turbine that spins the shaft of a generator. Inside the generator coils of wire and magnetic fields interact to create electricity. The energy needed to boil water into steam is produced in one of two ways: by burning coal, oil, or gas (fossil fuels) in a furnace or by splitting certain atoms of uranium in a nuclear energy plant. The uranium fuel generates heat through a controlled fission process fission, which is described in this poster presentation. The Koeberg Nuclear Power Station is a Pressurised water reactor (PWR). The operating method and the components of the Koeberg Power Station are also described. The nuclear waste generated at a nuclear power station is described under three headings— low-level waste, intermediate-level waste and used or spent fuel, which can be solid, liquid or gaseous. (author)

Heating of water by nuclear power stations

International Nuclear Information System (INIS)

1974-01-01

The aim of this note is to examine: the thermal conditions of the Rhone in its present state; heating caused by the building of nuclear power stations; the main hydrobiological and ecological characteristics of the Rhone [fr

Full scale model studies of nuclear power stations for earthquake resistance

International Nuclear Information System (INIS)

Kirillov, A.P.; Ambriashvili, Ju. K.; Kozlov, A.V.

Behaviour of nuclear power plants and its equipments under seismic action is not well understood. In the absence of well established method for aseismic deisgn of nuclear power plants and its equipments, it is necessary to carry out experimental investigations on models, fragments and full scale structures. The present study includes experimental investigations of different scale models and on existing nuclear power stations under impulse and explosion effects simulating seismic loads. The experimental work was aimed to develop on model test procedure for nuclear power station and the evaluation of the possible range of dynamic stresses in structures and pipe lines. The results of full-scale investigations of the nuclear reactor show a good agreement of dynamic characteristics of the model and the prototype. The study confirms the feasibility of simulation of model for nuclear power plants. (auth.)

Public relations activities of the Service Hall for Kashiwazaki-Kariwa Nuclear Power Station

International Nuclear Information System (INIS)

Kono, T.

1998-01-01

This article includes information of the Service Hall for Kashiwazaki-Kariwa Nuclear Power Station. About 30% of the total electricity production in Japan is due to 16 power stations and 52 reactors. The service hall is a kind of atomic power pavilion for public relations. In Japan, each nuclear power station has such a pavilion, which acts a a center of public relations activities for the atomic power. (S. Grainger)

Operating Experience at the Aagesta Nuclear Power Station

Energy Technology Data Exchange (ETDEWEB)

Sandstroem, S [ed.

1966-09-15

Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965.

Operating Experience at the Aagesta Nuclear Power Station

International Nuclear Information System (INIS)

Sandstroem, S.

1966-09-01

Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW t ) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965

Operating Experience at the Aagesta Nuclear Power Station

Energy Technology Data Exchange (ETDEWEB)

Sandstroem, S. (ed.)

1966-09-15

Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965.

The regional income and employment impacts of nuclear power stations

International Nuclear Information System (INIS)

McGuire, A.

1982-01-01

This paper attempts quantitatively to assess the income and employment impacts associated with two nuclear establishments in Scotland: the United Kingdom Atomic Energy Authority (U.K.A.E.A.) nuclear power establishment at Dounreay in Caithness and the South of Scotland Electricity Board (S.S.E.B.) nuclear power station presently under construction at Torness in the Lothian region. The model used is a basic Keynesian income multiplier model refined to allow detailed analysis of income and employment impacts at a local level. As used in this study it allows the identification of the increase in income and the associated increase in employment relating to the siting of a nuclear power plant in a particular locality. Results are given. The employment multipliers are estimated to be in the range 1.236 to 1.535 for Dounreay and 1.294 to 1.675 for the operational phase of the Torness plant. It is concluded that although the absolute income increases in the respective subregions are significant, compared to the total annual expenditure of the establishments these figures indicate high leakage from the subregions. (UK)

Experiences of operation for Ikata Nuclear Power Station

International Nuclear Information System (INIS)

Kashimoto, Shigeyuki

1979-01-01

No. 1 plant in the Ikata Nuclear Power Station, Shikoku Electric Power Co., Inc., is a two-loop PWR unit with electric output of 566 MW, and it began the commercial operation on September 30, 1977, as the first nuclear power station in Shikoku. It is the 13th LWR and 7th PWR in Japan. The period of construction was 52 months since it had been started in June, 1973. During the period, it became the object of the first administrative litigation to seek the cancellation of permission to install the reactor, and it was subjected to the influence of the violent economical variation due to the oil shock, but it was completed as scheduled. After the start of operation, it continued the satisfactory operation, and generated about 2.35 billion KWh for 4300 operation hours. It achieved the rate of utilization of 96.7%. Since March 28, 1978, the first periodical inspection was carried out, and abnormality was not found in the reactor, the steam generator and the fuel at all. The period of inspection was 79 days and shorter than expected. The commercial operation was started again on June 14. The outline of the Ikata Nuclear Power Station, its state of operation, and the periodical inspection are reported. Very good results were able to be reported on the operation for one year, thanks to the valuable experiences offered by other electric power companies. (Kako, I.)

Improvement and optimization for in-service inspection of M310 nuclear power station

International Nuclear Information System (INIS)

Wang Chen; Sun Haitao; Gao Chen; Deng Dong

2015-01-01

In-service inspection (ISI) is an important method to ensure the safety of the mechanical equipment in nuclear power stations. According to the in-service inspection experience feedback from the domestic nuclear power stations, the reasonableness of some provisions in the RSE-M code are discussed and the applications of risk-informed in-service inspection (RI-ISI) are introduced, and the advices for the optimization of the ISI of the domestic M310 nuclear power stations are proposed. (authors)

A survey on the history of developing nuclear power station in Hunan Province

International Nuclear Information System (INIS)

Ren Dexi

1993-01-01

Sixteen years ago it was suggested that a nuclear power station should be built in Hunan Province, and a special document was reported to the State Council. Up to now, the idea has still been under consideration. The author discusses the development of nuclear power station in Hunan province. It mainly consists of four parts: the history, the necessity the barriers met in the course and the feasible way of developing nuclear power station in Hunan Province

Anticorrosional protection in nuclear power station objects

International Nuclear Information System (INIS)

Czarnocki, A.; Kwiatkowski, A.

1976-01-01

The distribution and qualities of chemical protection and demands concerning preparation of the bottom for protecting coats in nuclear power station objects are discussed. The solutions of protections applied abroad and in the objects of ''MARIA'' reactor are presented. (author)

Sizewell B cycle 5 core design with Framatome ANP's CASCADE-3D and British Energy's PANTHER

International Nuclear Information System (INIS)

Attale, F.; Koegl, J.; Knight, M.; Bryce, P.

2001-01-01

Sizewell B Cycle 5 is the first cycle, after 4 cycles with BNFL fuel, with a reload consisting of Framatome ANP HTP (high thermal performance) fuel assemblies. The impact of this fuel vendor change on the Nuclear Design area is that, according to British energy's (BE) practice, the Framatome ANP's nuclear design code system CASCADE-3D is used for the majority of the cycle specific safety case calculations. However, other parts of the safety submission (e.g. 3D transient analyses) are made by using the BE code PANTHER. Before using in parallel two different code systems for reload core licensing extensive comparisons of applied methodologies and obtained results were required to ensure an acceptable level of agreement. (orig.)

Nuclear power stations licensing

International Nuclear Information System (INIS)

Solito, J.

1978-04-01

The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt

The legal framework for nuclear development

International Nuclear Information System (INIS)

Baker, J.

1982-01-01

A summary is presented of the legal framework within which civil nuclear power operations are conducted in Britain. The planning procedures are illustrated by reference to the consents history of one of the CEGB existing power stations - Sizewell 'A'. The process is traced through the stages of defining the need, identifying a site, making a formal application to build, Public Enquiry, site licensing and operational control. (U.K.)

Risk of loss power for ATWT in Daya Bay and Ling'ao nuclear power stations

International Nuclear Information System (INIS)

Guo Cheng

2010-01-01

In order to analyze the differences between the Anticipated Transient Without Reactor Trip (ATWT) and other reactor protection methods, this paper analyzes in detail the realizing means of ATWT and the effect of lost of power supply on the units based on Daya Bay and Ling'ao Nuclear Power Stations by system wiring diagram. Based on the comprehensive analysis,this paper proposes the sequence for powering when recovering the power source after ATWT power supply (LCC/LNE) loss for Daya Bay and Ling'ao Nuclear Power Stations. (authors)

Nuclear economics and privatisation

International Nuclear Information System (INIS)

Evans, N.L.

1987-01-01

In this paper the compatibility of the British government's two policies of privatisation of the electricity supply industry and the development of nuclear power is considered. The structures that a privatised electricity supply industry might have looked at, especially those which might have greatest effect on the position of nuclear power. Only three alternatives for Sizewell-B - a pressurized water reactor, an advanced gas-cooled reactor or a large coal-fired power station were considered. The economic case was made using a discount rate o 5% -lower than would be taken by private sector companies. This has an important effect on the economic advantage of one fuel over another. Changes in the electricity supply industry with privatisation are discussed. These might lead to consideration of a greater range of options for meeting demand (eg renewable energy sources) as the emphasis would be on profitability. (UK)

High system-safety level of nuclear power stations

International Nuclear Information System (INIS)

Lutz, H.R.

1976-01-01

A bluntly worded disquisition contrasting the incidence of death and harm to persons in the chemical industry with the low hazards in nuclear power stations. Quotes conclusions from a U.S. accident study that the risk from 100 large power stations is 100 times smaller than from chlorine manufacture and transport. The enclosure of a reactor in a safety container, the well understood effects of radioactivity on man, and the ease of measuring leakage well below safe limits, are safety features which he considers were not matched in the products and plant of the Seveso factory which suffered disaster. Questions the usefulness of warnings about nuclear dangers when chemical dangers are much greater and road dangers very much greater still. (R.W.S.)

Axial power deviation control strategy and computer simulation for Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Liao Yehong; Zhou Xiaoling, Xiao Min

2004-01-01

Daya Bay Nuclear Power Station has very tight operation diagram especially at its right side. Therefore the successful control of axial power deviation for PWR is crucial to nuclear safety. After analyzing various core characters' effect on axial power distribution, several axial power deviation control strategies has been proposed to comply with different power varying operation scenario. Application and computer simulation of the strategies has shown that our prediction of axial power deviation evolution are comparable to the measurement values, and that our control strategies are effective. Engineering experience shows that the application of our methodology can predict accurately the transient of axial power deviation, and therefore has become a useful tool for reactor operation and safety control. This paper presents the axial power control characteristics, reactor operation strategy research, computer simulation, and comparison to measurement results in Daya Bay Nuclear Power Station. (author)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Flowers, R.

1982-11-01

The role of NIREX (the Nuclear Industry Radioactive Waste Executive) in planning for the disposal of intermediate level waste and low level waste is explained. An inventory of such wastes in the UK is given and future arisings are estimated. Radioactive waste disposal routes currently available in the UK are described. The need for NIREX to increase these disposal facilities and plans for future operations are discussed. (U.K.)

Valves for condenser-cooling-water circulating piping in thermal power station and nuclear power station

International Nuclear Information System (INIS)

Kondo, Sumio

1977-01-01

Sea water is mostly used as condenser cooling water in thermal and nuclear power stations in Japan. The quantity of cooling water is 6 to 7 t/sec per 100,000 kW output in nuclear power stations, and 3 to 4 t/sec in thermal power stations. The pipe diameter is 900 to 2,700 mm for the power output of 75,000 to 1,100,000 kW. The valves used are mostly butterfly valves, and the reliability, economy and maintainability must be examined sufficiently because of their important role. The construction, number and arrangement of the valves around a condenser are different according to the types of a turbine and the condenser and reverse flow washing method. Three types are illustrated. The valves for sea water are subjected to the electrochemical corrosion due to sea water, the local corrosion due to stagnant water, the fouling by marine organisms, the cavitation due to valve operation, and the erosion by earth and sand. The fundamental construction, use and features of butterfly valves are described. The cases of the failure and repair of the valves after their delivery are shown, and they are the corrosion of valve bodies and valve seats, and the separation of coating and lining. The newly developed butterfly valve with overall water-tight rubber lining is introduced. (Kako, I.)

Multivariable control in nuclear power stations

International Nuclear Information System (INIS)

Parent, M.; McMorran, P.D.

1982-11-01

Multivariable methods have the potential to improve the control of large systems such as nuclear power stations. Linear-quadratic optimal control is a multivariable method based on the minimization of a cost function. A related technique leads to the Kalman filter for estimation of plant state from noisy measurements. A design program for optimal control and Kalman filtering has been developed as part of a computer-aided design package for multivariable control systems. The method is demonstrated on a model of a nuclear steam generator, and simulated results are presented

Exploration and practice on contract management of Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Wang Yonggang

2002-01-01

In the market economy, Daya Bay Nuclear Power Station needs to out source or allow to suppliers among industries, while concentrating its core competitive capability, for safely and stable operation. By evaluating the features of contract management in Daya Bay Nuclear Power Station, set up the organization and process of the supply management

Construction of a nuclear power station in one's locality: attitudes and salience

NARCIS (Netherlands)

van der Pligt, J.; Eiser, J.R.; Spears, R.

1986-01-01

Examined the attitudes toward the building of a nuclear power station in one's locality by surveying 290 residents (mean age 47.5 yrs) of 3 small rural communities that were listed as possible locations for a new nuclear power station. Results show that a large majority of Ss opposed the building of

Effectiveness for public acceptance of nuclear energy. Analysis of questionnaire distributed at organized visits to Nuclear Power Stations

International Nuclear Information System (INIS)

1996-01-01

In First Atomic Power Industry Group, as a part of the public acceptance activities for nuclear power, the visit to nuclear power stations for the inspection have been held. This aims at acquiring the correct knowledge on nuclear power by seeing the various facilities of nuclear power stations actually by own eyes. In the execution of the visits, mainly female employees were asked to participate, calling to the various companies in the group. On November 16 and 17, 1995, the visit to Kashiwazaki-Kariwa nuclear power station of Tokyo Electric Power Co. was held. In this study, the impression and opinion that all the participants possess through the visit and the seminar held beforehand were collected and analyzed by the questionnaire. The schedule of the visit, and the contents of the questionnaire are shown. As the feature of the questionnaire, the same questions were made before and after the inspection, and the change of opinion was examined. The results are summarized. The participants who trust the safety of nuclear power stations were 37% before the inspection and increased to 84% after the inspection. (K.I.)

Cultivation of nuclear safety culture in Guangdong Nuclear Power Station (GNPS)

International Nuclear Information System (INIS)

Lu Wei; Tang Yanzhao

2004-01-01

Probed into the concept and developing phases of safety couture in the management of nuclear power station, especially analyzed the background and the road of cultivating nuclear safety culture in GNPS, highlighted the core concept of GNPS nuclear safety culture, presented GNPS safety culture indicators, summarized the major measures taken by GNPS, depicted the propagandizing process of transparency in GNPS, and systematically appraised the effect of GNPS in implementing nuclear safety culture. (authors)

Occupational radiation exposures at Canadian CANDU nuclear power stations

International Nuclear Information System (INIS)

LeSurf, J.E.; Taylor, G.F.

1982-09-01

In Canada, methods to reduce the radiation exposure to workers at nuclear power reactors have been studied and implemented since the early days of the CANDU reactor program. Close collaboration between the designers, the operators, and the manufacturers has reduced the total exposure at each station, the dose requirement to operate and maintain each successive station compared with earlier stations, and the average annual exposure per worker. Specific methods developed to achieve dose reduction include water chemistry; corrosion resistant materials; low cobalt materials; decontamination; hot filtration, improved equipment reliability, maintainability, and accessibility; improved shielding design and location; planning of work for low exposure; improved operating and maintenance procedures; removal of tritium from D 2 O systems and work environments; improved protective clothing; on-power refuelling; worker awareness and training; and many other small improvements. The 1981 occupational dose productivity factors for Pickering A and Bruce A nuclear generating stations were respectively 0.43 and 0.2 rem/MW(e).a

Civil engineering in nuclear power stations: design of the turbine building and nuclear auxiliary building

International Nuclear Information System (INIS)

Lacroix, R.

1985-01-01

After enumerating the specific features of civil engineering in nuclear power stations. One goes on to examine the principal deliberations undertaken with the aim of optimising projects for transition from the P4 to P'4 and then N4 generations of nuclear power stations. The courses of action decided with respect to the design of the machine room and auxiliary equipment building are described [fr

Procedures for permission of installation of nuclear power stations

International Nuclear Information System (INIS)

Narita, Yoriaki

1980-01-01

The locations of atomic power stations are first selected by electric power enterprises in consultation with the Ministry of International Trade and Industry or under the guidance of authorities concerned. The surveys of the climate, topography, water and plants in the planned sites and the influences of nuclear power generation to the surrounding areas are made by the enterprisers under the administrative guidance of the MITI. Secondly, the basic project shall be submitted to and decided by the Power Resource Development Council headed by the Prime Minister (Article 10, the Power Resource Development Law). The Council shall, if necessary, call for the attendance of the governors of prefectures concerned and hear their opinions (Article 11, the Law). As the third and most complicated phase, various procedures include; (a) permission of the changes of electrical facilities under the Electricity Enterprises Act; (b) authorization of the installation of reactors under the Nuclear Reactor Regulation Law; (c) permission or authorization under other regulations including the Agricultural Land Act, etc.; (d) additional procedures related to the indemnification to fishery and so forth. Finally the reactors are to be operated after receiving the certificates of the Minister of ITI on the inspections of construction works, nuclear fuel materials used for the reactors and welding processes of reactor containment vessels, boilers, turbines, etc. (Okada, K.)

75 FR 10517 - Nebraska Public Power District, Cooper Nuclear Station; Exemption

Science.gov (United States)

2010-03-08

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-298; NRC-2010-0061] Nebraska Public Power District, Cooper Nuclear Station; Exemption 1.0 Background Nebraska Public Power District (NPPD or the licensee) is the holder of Facility Operating License No. DPR-46 which authorizes operation of the Cooper Nuclear...

Efforts toward enhancing seismic safety at Kashiwazaki Kariwa nuclear power station

Energy Technology Data Exchange (ETDEWEB)

Yamashita, Kazuhiko

2010-09-15

Kashiwazaki-Kariwa Nuclear Power Station, 8212MW, was struck by M6.8 quakes in July 2007. TEPCO has steadily been conducting restoration and post-earthquake equipment integrity assessment, aiming to make it a disaster-resistant power station. 2 units among 7 resumed commercial operation by June 2010. This earthquake has provided a great deal of knowledge and information useful for nuclear safety improvement. It has also served as a valuable reference for the IAEA in developing earthquake-related guidelines. TEPCO would like to share the knowledge and information thereby contributing to improving the safety of nuclear power generation. We will introduce some of our activities.

Improved monolithic reinforced concrete construction for nuclear power stations

International Nuclear Information System (INIS)

Guenther, P.; Fischer, K.

1983-01-01

Experience has shown that in applying monolithic reinforced concrete in nuclear power plant construction the following auxiliary means are useful: measuring sheets in assembling, welding gauges for reaching high tolerance accuracies of prefabricated reinforced concrete members, suitable lining materials, formwork anchorage and formwork release agents, concrete workability agents, mechanized procedures for finishing and assembling. These means were successfully tested in constructing the Greifswald nuclear power station

Port construction works in the Sendai Nuclear Power Station

International Nuclear Information System (INIS)

Narahara, Akio; Minamata, Hisashi; Harada, Kensaku

1982-01-01

Sendai Nuclear Power Station is the second nuclear power station of Kyushu Electric Power Co., Inc., with two PWR plants of 890 MW each, and the operation of No.1 plant will be started in July, 1984, and that of No.2 plant in March, 1986. The civil engineering works for both plants were started in June, 1978, and March, 1981, respectively, and the rate of progress as of the end of September, 1982, was 97 % and 66 %, respectively. In the construction of this power station, the port facility was provided for the transport of construction materials and spent fuel, and for the intake of condenser cooling water. In order to make the construction by dry work, the double cofferdam structures with steel sheet piles were made offshore. The use of the wharf was started in March, 1980, though typhoons hit the area several times, and the dredging in the port was completed in May, 1982. The outline of the plan of this power station, the state of affairs before the start of construction, the outline of the port construction works, the topography, geological features and sea conditions, the design of the port such as breakwaters, unloading wharf and water intake, the manufacture and installation of caissons, dredging, and the temporary cofferdam works for water intake are described. (author)

Protection and safety of nuclear power stations

International Nuclear Information System (INIS)

Anon.

1976-01-01

The extreme requirements for the safety of nuclear power stations set tasks to the civil engineer which, resulting from dynamic load assumptions, among other things also demand the development of novel special concrete steels with a high elastic limit (here: DYWIDAG thread tie rod) for singly reinforced members. (orig.) [de

Lippe-Ems GmbH nuclear power stations. Annual report 1992

International Nuclear Information System (INIS)

1993-01-01

The Nuclear power company Lippe-Ems GmbH (KLE) runs the Emsland Nuclear Power Station (KKE) in Lingen (Ems) with a 1300 MW pressurized Water reactor. Partners of KLE are VEW and Elektromark. This 1992 annual report reveals numerous financial data of the operator (balance sheet, profit and loss account.) (orig./UA) [de

Assessment of options for the treatment of Sizewell PWR liquid effluent

International Nuclear Information System (INIS)

Hornby, J.; Allam, J.; Knibbs, R.H.

1992-01-01

This report describes the origins of PWR liquid waste streams, their composition and rates of arising. Data has been collected from operational PWRs and estimates obtained for Sizewell B PWR liquid waste streams. Current liquid waste treatment practices are reviewed and assessments made of established and novel treatment techniques which could be applicable to Sizewell B. A short list of treatment options is given and recommendations are made relating to established treatment technologies suitable for Sizewell B and also to development work on more novel treatments which could lead to a reduction in waste disposal volumes. (author)

Safety aspects of station blackout at nuclear power plants

International Nuclear Information System (INIS)

1985-03-01

The principal focus of this report is on existing light water reactor nuclear power plants. However, many of the considerations discussed herein can be equally applied to new plants, i.e. those not yet in construction. This report is organized to provide a description of design and procedural factors which safety assessments and reviews of operating experience have shown to be important. These are divided into the off-site power system, the on-site AC power systems and alternate (or nearby) sources of power. The latter may be used in the unlikely event that both normal off-site and on-site sources fail. It must be emphasized that first priority should be placed on designing and maintaining high reliability of both the off-site and on-site AC power systems. This basic concept also applies to the capabilities for restoring power sources which failed and making use of all available alternative and nearby power sources during an emergency, to restore AC power in a prompt manner. Discussions on these aspects are provided in chapters 2 and 3 of this report. Because the expected event frequency and associated confidence in such estimations of station blackout are uncertain, preparations should be made to deal with a station blackout. The nature of those preparations, whether they be optimizing emergency procedures to use existing equipment, modifying this equipment to enhance capabilities, or adding new components or systems to cope with station blackout, must be made in light of plant-specific assessments and regulatory safety philosophies/requirements. Discussions on these matters are provided in chapter 4. General and specific conclusions and recommendations are provided in chapter 5. Appendix A provides a description of several case studies on station blackout and loss of off-site power. Abstracts of papers and presentations are provided in Appendix B with authors and affiliations identified to facilitate personal contact. The References and Bibliography contain a

Trends in digital I and C for nuclear power plants

International Nuclear Information System (INIS)

Cook, B.M.

2000-01-01

Over the past decade, large-scale digital I and C systems have been installed on nuclear power plants as the original systems for plant operations. Examples of these include Sizewell B in the United Kingdom and Temelin NPP in the Czech Republic. Now, this digital technology is being used for replacement and upgrade systems such as those for Ringhals Unit 2 in Sweden and the Kewaunee plant in the United States. Such a digital upgrade is being planned for the Dukovany NPP in the Czech Republic. As the experience base grows with this digital technology on nuclear power plants, certain trends are developing in the application practices and licensing of these systems. This paper discusses these trends and suggests adaptations that may become necessary in the classical roles of vendors, regulators and plant operators. (author)

Bradwell Nuclear Power Station

International Nuclear Information System (INIS)

1987-01-01

When built, the Magnox reactors were expected to have operating lifetimes of 20-25 years. In order to satisfy the licensing authorities of their continued safety, long term safety reviews (LTSRs) are being carried out as the reactors reach 20 years of operation. This is the Nuclear Installations Inspectorate's (NII) summary report on Bradwell nuclear power station. The objectives of the LTSR are stated. A description of the plant is followed by an explanation of the statutory position on licensing. The responsibilities of the Central Electricity Generating Board (CEGB) and the NII are defined. From the examination of the CEGB's LTSR it is concluded that this generally confirms the validity of the existing safety case for present operation. However, some recommendations are made as to work required for reactor operation up to 1992. A summary of the NII findings is presented. This includes the reactor pressure circuit integrity, effects of ageing and in-service wear and radiation doses. (U.K.)

Heavy density concrete for nuclear radiation shielding and power stations: [Part]2

International Nuclear Information System (INIS)

Singha Roy, P.K.

1987-01-01

This article is the second part of the paper entitled 'Heavy density concrete for nuclear radiation shielding and power stations'. In this part, some of the important properties of heavy density concrete are discussed. They include density, water retentivity, air content, permeability with special reference to concrete mixes used in India's nuclear power reactors. All these properties are affected to various extents by heating. Indian shield concrete is rarely subjected to temperatures above 60degC during its life, because of thermal shield protection. During placement, the maximum anticipated rise in temperature due to heat of hydration is restricted to around 45degC by chilling, if necessary to reduce shrinkage stresses and cracks. (M.G.B.)

Front against the Temelin nuclear power station

International Nuclear Information System (INIS)

Anon.

1990-01-01

Though the main concern of the author is the Czechoslovakian Temelin power station, the main target of his attacks are the Austrian proponents of nuclear energy i.e. the Reactor Safty Commission and the Austrian Chancellor. The newly opened possibility of anti-nuclear propaganda in the CSFR, by Greenpeace and the author's organisation is welcomed. The number of signatures collected against Temelin is given as 350.000. 815 signatures come from Japan: a facsimile of some Japanese signatures is presented

Development of the fuel-cycle costs in nuclear power stations with light-water reactors

International Nuclear Information System (INIS)

Brosch, R.; Moraw, G.; Musil, G.; Schneeberger, M.

1976-01-01

The authors investigate the fuel-cycle costs in nuclear power stations with light-water reactors in the Federal Republic of Germany in the years 1966 to 1976. They determine the effect of the price development for the individual components of the nuclear fuel cycle on the fuel-cycle costs averaged over the whole power station life. Here account is taken also of inflation rates and the change in the DM/US $ parity. In addition they give the percentage apportionment of the fuel-cycle costs. The authors show that real fuel-cycle costs for nuclear power stations with light-water reactors in the Federal Republic of Germany have risen by 11% between 1966 and 1976. This contradicts the often repeated reproach that fuel costs in nuclear power stations are rising very steeply and are no longer competitive. (orig.) [de

Notes on organization of nuclear power station construction

International Nuclear Information System (INIS)

Marsicanin, B.

1977-01-01

After a visite to some european nuclear power stations under construction and in operation, in this report a short general view on this subject is given. The progress in this in large, industrialised countries is considered as well as the relevant experience in developing countries. The new role of nuclear research institutes during construction and operation is pointed out and prospects of this cooperation evaluated. (author)

Dynamics and control in nuclear power stations

International Nuclear Information System (INIS)

Butterfield, M.H.

1992-01-01

This volume presents a wide view of aspects of control of nuclear power stations by taking into consideration the plant as a whole and the protection systems employed therein. Authors with worldwide experience consider all aspects of dynamics and control in the context of both fast and thermal power stations. The topics discussed include the methods of development and applications within the analysis of plant behaviour, the validation of mathematical models, plant testing, and the design and implementation of controls. There are 27 papers all of which are indexed separately; steady states and model evolution (5 papers), control and protection systems (5 papers), transients (7 papers), testing and data (3 papers), model validation (6 papers) and commissioning and operation (1 paper). (author)

Obrigheim nuclear power station. Annual report 1987

International Nuclear Information System (INIS)

Koerner, C.

1988-01-01

The Obrigheim nuclear power station was operated at full load during the year 1987; 7.351 operating hours procuded electrical energy of 2.607 GWh. This is the fifth best annual result during Obrigheim's operating period. Since commissioning in October 1968, 139.310 hours of operation have generated 46.681 GWh (gross) and from test operation in March 1969 until the end of 1987, 138.530 hours of operation have generated 46.569 GWh. This is an availability of power of 81.6% in this period and a time availability of 83.9%. In 1987, the plant was shut down for 1.222 hours for the 18th refueling including testing, inspection and repair work. Apart from refueling, the plant had a good time availability and therefore contributed 5% to the safe, economical and environmentally acceptable electricity supply of the Land Baden-Wuerttemberg. The power station is of great significance to the region, both in terms of power supply and the economy. (orig./HP) [de

Great Britain 1994: Starting a new era for nuclear power

International Nuclear Information System (INIS)

Collier, J.G.

1994-01-01

In the course of the British program of privatization of the state-owned electricity generating industry the nuclear power plants in England and Wales were incorporated into the newly founded (and state-owned) NE in 1989. In addition, the government decided in favor of a moratorium in the construction of more nuclear power plants. Only Sizewell B, Britain's first pressurized water reactor (PWR), was to be completed. At that point in time, three other PWRs were in the planning stage. The government decision included a review of the future of nuclear technology to be held in 1994. At the beginning of 1994, the nuclear future of Britain appears in a much more positive light than had been thought possible in 1989. When founding NE, the British government endowed it with a startup capital and also instituted a tax levied on fossil energy sources, the revenue from which is being made available to NE in compensation for the old liabilities NE had to assume. (orig./UA) [de

76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations

Science.gov (United States)

2011-12-30

... guidelines in identifying suitable candidate sites for nuclear power stations. The decision that a station... combination and a cost-benefit analysis comparing it with alternative site-plant combinations, as discussed in...

Evaluation of Shoreham Nuclear Power Station, Unit 1 technical specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-08-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Shoreham Nuclear Power Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Shoreham T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Shoreham Nuclear Power Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Living near a nuclear power station

International Nuclear Information System (INIS)

Marcan, P.; Slovak, K.

2007-01-01

The need to expand nuclear power and its advantages are discussed publicly nearly each week. According to politicians and the nuclear lobby investing tens of billions Sk at Mochovce will bring Slovakia the often cited 'independence and energy self-sufficiency'. It will also mean profit for Slovenske elektrarne and the company's shareholders - the state and Italian company, Enel. In addition to the lively discussion on the pros and cons of nuclear energy, TREND was also interested in the living conditions around the concrete and strictly guarded, potentially dangerous plants and in the opinion of the people most affected by Mochovce and Jaslovske Bohunice on expansion of the existing and the building of new nuclear power plants. The construction of nuclear powers stations in these regions was not only about new jobs. The state 'prescribed' iodine pills and did not allow any construction in the region and, in the case of Mochovce, ordered the complete demolition of a village. The only thing that remained from Mochovce village was the church. 'And when it was found that the power plant would not reach it, it was even given a new roof. Former inhabitants, especially the older ones that had problems accepting the evacuation, used to visit it often,' explained Jan Foldy, the head of the local municipality in Kalna nad Hronom. After many years, life in the neighbouring villages is not bad. Their budgets are overflowing and so they can afford to spoil their inhabitants with free cable TV and high standard sport facilities, which should partly compensate for the fact that the people are living so close to a nuclear facility. (authors)

The appliction of project management in operations preparation of nuclear power station

International Nuclear Information System (INIS)

Tang Zhengrong; Zhang Zhixiong

2001-01-01

Concept, history, characteristics of the project management is introduced. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers our study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

How has severe accident analysis contributed to sizewell B and how can it continue to contribute in the future

International Nuclear Information System (INIS)

Harrison, J.R.; Western, D.J.

1987-01-01

Sizewell B is a proposed 1100 MWe PWR which is a UK development of the US SNUPPS design. The UK reference design document for the plant was first issued in 1981 and the Pre-Construction Safety Report (PCSR) was submitted to the Nuclear Installations Inspectorate (NII), the UK licensing authority, in 1982. A major public inquiry into the proposal took place between January 1983 and March 1985. This paper is concerned with the analysis of severe accidents. This means all the analysis that is concerned with those fault sequences that are outside the design basis of the plant and which may lead to severe consequences - either in terms of plant damage or release of radioactivity. This analysis comprises probabilistic assessments of the frequency of such sequences, transient analysis of the way such sequences develop and radiological release analysis. Part one of this paper examines how the severe accident analysis carried out for Sizewell B has contributed to the judgement that the design is sound and that the construction phase should proceed. The second part of the paper looks to the future and asks ''Can severe accident analysis make any further contribution during the period from licensing up until operation commences

The term 'availability' as used in connection with nuclear power stations

International Nuclear Information System (INIS)

Fehndrich, W.; Kutsch, W.

1975-01-01

The increase in the nuclear generating capacity installed has resulted in a general discussion about the availability to be expected from nuclear power stations. Comparisons of statistical data on nuclear power plant operation frequently show that data on availability and plant factors of nuclear power stations may differ widely in some cases. Aside from errors, these discrepancies are due mainly to the different terms and definitions used by the institutions compiling these reports. In this contribution, first of all these institutions are listed and then the different terms and their definitions are given. It is seen that translations which are correct linguistically give rise to discrepancies because a term used is defined differently by different agencies. Because of these difficulties of definition, the applicability of the term 'Arbeitsverfuegbarkeit' (availability in terms of work) as mentioned in many publications is greatly restricted. A comparison of the availability and plant factor data quoted by various organizations for several nuclear power plants indicates that there may be major differences even in those cases in which the same terms are used for the same parameters. (orig.) [de

A RETRAN-02 model of the Sizewell B PCSR design - the Winfrith one-loop model, version 3.0

International Nuclear Information System (INIS)

Kinnersly, S.R.

1983-11-01

A one-loop RETRAN-02 model of the Sizewell B Pre Construction Safety Report (PCSR) design, set up at Winfrith, is described and documented. The model is suitable for symmetrical pressurised transients. Comparison with data from the Sizewell B PCSR shows that the model is a good representation of that design. Known errors, limitations and deficiencies are described. The mode of storage and maintenance at Winfrith using PROMUS (Program Maintenance and Update System) is noted. It is recommended that users modify the standard data by adding replacement cards to the end so as to aid in identification, use and maintenance of local versions. (author)

Monitoring of radioactivity in the environs of Finnish nuclear power stations in 1986

International Nuclear Information System (INIS)

Ilus, E.; Sjoeblom, K.L.; Aaltonen, H.; Klemola, S.; Arvela, H.

1987-06-01

Results of the environmental programmes monitoring radioactivity around the Finnish nuclear power stations in 1986 are reported. After the end of April the fallout nuclides from the Chernobyl accident predominated in all samples taken from the environs of the two power stations Loviisa and Olkiluoto. Radionuclides originating from the Finnish power stations were detected mainly in samples taken from the aquatic environment. The concentrations of the locally discharged nuclides were very low in comparison with the fallout nuclides and their impact on the radiation doses of the population was insignificant. Both nuclear power stations are situated in the main fallout area in Finland. The results of these large monitoring programmes give a good picture of the behaviour of the Chernobyl fallout in the specific areas in Finland

End of the nuclear dream. The UKAEA and its role in nuclear research and development

Energy Technology Data Exchange (ETDEWEB)

Flood, M

1988-01-01

The study sets out to assess the performance of the United Kingdom Atomic Energy Authority (UKAEA) and to make recommendations for its role in the future within the overall energy needs of the United Kingdom. It assumes that the Magnox stations will be phased out after 20-25 years service, that the Advanced Gas-Cooled reactors will be shut down after 20-25 years service and no more built and that perhaps five or so Pressurized Water reactors will be built by the year 2000, including the Sizewell-B station. The first part of the report traces the institutional changes that have taken place in the UKAEA from its formation in 1954 up to the late 1980s. The current structure of the UKAEA is described in part 2. Questions of accountability are raised and its dual role of assessor and promoter of nuclear power is questioned. Part three looks at the UKAEA's role in developing nuclear power, especially the economic implications. In part four fundamental errors of judgement by the UKAEA are blamed for the failure of the UK nuclear industry to provide cheap, abundant, electricity. Practical recommendations for a major restructuring of the Authority are made.

Nuclear weapons and nuclear power stations: what is the connection

International Nuclear Information System (INIS)

Spencer, K.

1985-01-01

From the start of the nuclear age with the dropping of two atom bombs on Japan in 1945 it has been known that this new source of primary energy could be exploited for weapons or for replacing coal or oil in electricity-generating stations. Nuclear energy is made from two elements: naturally occurring uranium and man-made plutonium. Their processing differs according to the intended end-use. Great efforts have been and still are made to disguise the close connection between nuclear energy for war and for power stations. Two reasons are suggested for this: political conveniences in avoiding additional informed protests against nuclear weapon production and industrial convenience in carrying on without public protest what has become a very profitable industry. It is argued that medical doctors, because of their professional prestige, can speak and be listened to on the risks of continuing to exploit this newly discovered form of energy. Furthermore, this industry is uniquely hazardous to the health of its workers, to the public generally and possibly to the procreation and genetic health of future generations. (author)

Sizewell B - analysis of British application of US PWR technology

International Nuclear Information System (INIS)

1983-05-01

This report provides information on the staff's evaluation of major design differences and issues developed by the British in their application (Sizewell B) of US PWR technology. One design change, the addition of steam-driven charging pumps, was assessed to have a relatively high value compared to the other changes. However, the assessment is based on a number of assumptions for which inadequate data exist to make an unqualified judgment. Other changes to the US design (as typified by the SNUPPS design) were found to have relatively low or moderate safety benefits for US application

The risks at nuclear power stations and their insurance

International Nuclear Information System (INIS)

Schludi, H.N.

1994-01-01

Insurance can offer an uninterrupted insurance cover from start-up-to shut-down of a nuclear power station. This is assured by the insurance for the erection, for the nuclear liability, for the nuclear/fire, for the engines, for operational interruptions and for the transport. For each of the above mentioned insurance branches, essential characteristic features, such as risk carrier, protection range and insurance costs, are given. (orig.) [de

The glass model of Muelheim-Kaerlich nuclear power station

International Nuclear Information System (INIS)

Kuttruf, H.; Lemke, W.

1986-01-01

The glass model represents the nuclear steam generator system of Muelheim-Kaerlich nuclear power station on a scale of 1:25 and in simplified form, so that the thermohydraulic behaviour in both normal operational and fault conditions can be represented. A set-up time of about one hour results in a helpful aid to instruction. (orig.) [de

Daya Bay Nuclear Power Station five-year business plan and operating results

International Nuclear Information System (INIS)

Zhang Shanming

2000-01-01

Guangdong Nuclear Power Joint Venture Company, Ltd. first 5-Year Business Plan (hereinafter referred to as 5-Year Business Plan) serves as guidance of both the operations and management of the company. Continuous performance improvement of the nuclear power station has been achieved through the fulfillment of goals and improvement plan defined by the 5-Year Business Plan, and through standard and systematic management. Daya Bay Nuclear Power Station (GNPS) has made great contributions to sustainable economic developments of both Guangdong and Hong Kong since its commercial operation in 1994. As of the end of 1999, the cumulative off-take electricity generated by GNPS had reached 69.9 billion kWh. Of the WANO indicators universally applied by nuclear power industry throughout the world, 6 indicators of Daya Bay performance entered the world top quartile while 9 the medium level

Capacity factor of nuclear power stations in Japan in fiscal year 1984

International Nuclear Information System (INIS)

Agawa, Takashi

1985-01-01

In Japan presently a total of 28 nuclear power plants are in operation with aggregate capacity 20,561 MW, 22 % of the total power generation. Around 1975 there occurred such as stress corrosion cracking and to repair them much time was consumed, leading to the low capacity factor. With such troubles removed, in fiscal 1984, the capacity factor on average of the nuclear power stations is 73.9 %, the highest so far. Contributing to this are long period of the continuous operation, short period of the periodical inspection and increase in the in-operation capacity factor. Contents are the following : construction state of nuclear power stations, operation state in fiscal 1984, causes leading to the high capacity factor, future directions. (Mori, K.)

77 FR 50533 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 3

Science.gov (United States)

2012-08-21

....; Millstone Power Station, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Environmental assessment and... search, select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems... Optimized ZIRLO\\TM\\ fuel rod cladding in future core reload applications for Millstone Power Station, Unit 3...

Education and training of operators and maintenance staff at Hamaoka Nuclear Power Stations

International Nuclear Information System (INIS)

Makido, Hideki; Hayashi, Haruhisa

1999-01-01

At Hamaoka Nuclear Power Station, in order to ensure higher safety and reliability of plant operation, education and training is provided consistently, on a comprehensive basis, for all operating, maintenance and other technical staff, aimed at developing more capable human resources in the nuclear power division. To this end, Hamaoka Nuclear Power Station has the 'Nuclear Training Center' on its site. The training center provides the technical personnel including operators and maintenance personnel with practical training, utilizing simulators for operation training and the identical facilities with those at the real plant. Thus, it plays a central role in promoting comprehensive education and training concerning nuclear power generation. Our education system covers knowledge and skills necessary for the safe and stable operation of nuclear power plant, targeting new employees to managerial personnel. It is also organized systematically in accordance with experience and job level. We will report the present education and training of operators and maintenance personnel at Hamaoka Nuclear Training Center. (author)

Cause trending analysis for licensing operational events in Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Wang Dewei

2005-01-01

The human causal factors for all human error licensing operational events on Daya Bay nuclear power station since 1993 to 2003 are categorized, the trend of these causal factors is analyzed. The emphasis is placed on analyzing the deficiencies on complying with and executing regulations and procedures. The results provide directional reference for nuclear power station to improve human performance. (author)

Decommissioning situation and research and development for the decommissioning of the commercial nuclear power station in Japan

International Nuclear Information System (INIS)

Yamamoto, Tatsumi.

1996-01-01

There are 48 commercial nuclear power stations in operation in Japan as of January 1, 1995, which supplies about 28% (2.2 x 10 8 MWh) of total annual electricity generation in FY 1992. Accordingly, as the nuclear power contributes so much in electricity generation, there is a growing concern in the public toward the safety on decommissioning nuclear power station. It is gravely important to secure the safety throughout the decommissioning. This paper discusses: the decommissioning situation in Japan; the Japanese national policy for decommissioning of commercial nuclear power stations; R and D for decommissioning of commercial nuclear power stations in Japan; and the present conditions of low-level radioactive wastes disposal in Japan

Forecasting Canadian nuclear power station construction costs

International Nuclear Information System (INIS)

Keng, C.W.K.

1985-01-01

Because of the huge volume of capital required to construct a modern electric power generating station, investment decisions have to be made with as complete an understanding of the consequences of the decision as possible. This understanding must be provided by the evaluation of future situations. A key consideration in an evaluation is the financial component. This paper attempts to use an econometric method to forecast the construction costs escalation of a standard Canadian nuclear generating station (NGS). A brief review of the history of Canadian nuclear electric power is provided. The major components of the construction costs of a Canadian NGS are studied and summarized. A database is built and indexes are prepared. Based on these indexes, an econometric forecasting model is constructed using an apparently new econometric methodology of forecasting modelling. Forecasts for a period of 40 years are generated and applications (such as alternative scenario forecasts and range forecasts) to uncertainty assessment and/or decision-making are demonstrated. The indexes, the model, and the forecasts and their applications, to the best of the author's knowledge, are the first for Canadian NGS constructions. (author)

The application of project management in operations preparation of nuclear power station

International Nuclear Information System (INIS)

Zhang Zhixiong; Tang Zhengrong

2000-01-01

The author first presents a brief introduction of the concept, history, characteristics of project management. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers authors' study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

Ballooning analysis for the Sizewell B PWR using symmetric MABEL calculations

International Nuclear Information System (INIS)

Sweet, D.W.; Gibson, I.H.; Fell, J.

1982-12-01

An analysis of the fuel clad ballooning potential associated with the Sizewell B PWR following a design basis large break cold leg LOCA is described. Calculations employ MABEL-2C code. No allowance has been made for asymmetries in power or geometry, thus precluding any amelioration offered by early clad rupture. Thermal hydraulic data were derived from a TRAC-PD2 best estimate analysis of the LOCA and the work includes a detailed sensitivity study which leads to a correlation between peak clad temperature and clad strain. For the best estimate start of cycle 1 peak rod rating, no loss of coolability is expected within 95 percent confidence limits on peak clad temperature. No loss of coolability is expected either for rods at the design basis peak rod rating. The temperature does not have to be much higher than the 95 percent confidence limit on the best estimate rating or much beyond that of the design basis rating for rod contact and severe blockage to follow. This indicates that to establish a complete safety case the added complexity of pellet eccentricity and rod to rod power variations must be considered. (U.K.)

Structural integrity of Sizewell B - the way forward

International Nuclear Information System (INIS)

Geraghty, J.E.

1996-01-01

The Incredibility of Failure (IOF) approach has been used on Sizewell B. This involves demonstrating that under all conditions, the failure of certain components is so remote as to be considered incredible. It means that the integrity of these components is such that they must remain intact assuming other plant items do fail. For example, a complete failure of the main loop pipework must be withstood by the RPV and steam generator shell. The IOF components are mainly those of the reactor coolant circuit and the purpose of this paper is to describe the approach adopted for the RPV, the steam generator shell, pressurizer and reactor coolant pump casing. The two arms of the safety case are achievement and demonstration of integrity. (author)

The Importance of Reliable Nuclear Power For Energy Supply

International Nuclear Information System (INIS)

Blix, Hans

1989-01-01

The severe accident at Chernobyl in 1986 caused a setback in public acceptance of nuclear power practically everywhere in the world. In some countries, the media even give the impression that nuclear power is on the way out worldwide, because of concerns about safety, radioactive waste disposal, and the risk of proliferation of nuclear weapons. Let me give you a more accurate picture of the situation. At the beginning of this year there were about 430 nuclear power reactors in operation in 26 countries around the world and they produced more than 16% of the world's electric energy. That amount of electricity is equal to the total amount of electric energy that was produced in the world in 1956. I mention this because, when we concentrate on the problems which nuclear power is facing, we tend to forget that among all the major energy sources? coal, oil, gas, hydro and nuclear- it is nuclear which has experienced the fastest rise in relative importance for the global energy supply. Its contribution to global energy supply has increased from just under 1% in 1974 to about 5% in 1987. On the positive side we can note the continuation of strong nuclear power programmes with construction starts in France and Japan, the start of construction at Sizewell B, which marks a new departure for nuclear power in the United Kingdom, and the orders for the Korean units 11 and 12

Nuclear power. Its development in the United Kingdom

International Nuclear Information System (INIS)

Pocock, R.F.

1977-01-01

The subject is covered chronologically in chapters, entitled: from war to peace; the Atomic Energy Authority and the first nuclear power station; a civil power programme; Windscale - the need for caution; research for the future; the new (Magnox) power stations; revision of the nuclear power programme; supply of nuclear fuels; nuclear power for ship propulsion; completion of first programme; Dungeness B and second programme, political assessment of (nuclear) industry's structure; reorganization of the industry; nuclear power in the environment; completion of second programme; the energy crisis; decision on third programme. (U.K.)

Requirement profile for nuclear power station personnel

International Nuclear Information System (INIS)

Roeglin, H.C.

1984-01-01

The starting point in deriving the requirement profile for the shift personnel in the control rooms of nuclear power stations is information of a technical, organisational and ergonomic kind. The technique used, the distribution of work to different work areas and the configuration of the workplace is determined by the tasks and the environmental conditions in which they have to be done. (orig./DG) [de

Iodine filters in nuclear power stations

International Nuclear Information System (INIS)

Wilhelm, J.G.

1977-04-01

On the basis of calculated and recorded release rates of nuclear power plants, the significance of iodine releases in the invironmental impact relative to other nuclides is discussed. The release pathways for iodine in LWR-type reactors and the efficiency of various methods to lower the activity release are given. The airborne species of iodine are discussed with regard to their removal in iodine sorption filters and environmental impact. The technical status of iodine removal by means of iodine sorption filters is studied for normal operation and accident conditions in nuclear power stations on the basis of the data given in the relevant literature for the efficiency of a number of iodine sorption materials. The applicability of concepts for ventilation and containment and their influence on iodine filter systems are discussed. Design, structure, and testing of iodine sorption filters are treated in detail; recommendations for design are given, and failure sources are mentioned. (orig.) [de

Nuclear power and the economic interests of consumers

International Nuclear Information System (INIS)

MacKerron, G.

1982-06-01

This study examines the main economic issues surrounding the use of nuclear power from a broadly consumer perspective. It sets out to answer four related questions: has nuclear investment been good value in the past; are current plans for nuclear investment (especially at Heysham II and beyond) likely to be good value in the future; what are the likely economic consequences if there is an explicit or de facto moratorium on the building of more nuclear power plants; and what strategic factors influence decision-making about nuclear investment and what are their consequences for consumers. (It should be noted that the CEGB's 'Statement of Case' for a PWR at Sizewell was published too late to be taken into account in this report). (author)

Hygienic situation in the site of nuclear power stations in Fukushima Prefecture

International Nuclear Information System (INIS)

Sakka, Masatoshi

1984-01-01

In the Fukushima No. 1 Nuclear Power Station in Fukushima Prefecture, the hygienic statistics for ten years each before and after the start of the power station were compared between the surrounding radiation monitoring area and the reference area without such monitoring, both areas containing populations. There was no difference at all between the two areas. It was thus shown that the nuclear power generation had no adverse effect on the health of the people. The following statistics in both areas concerning the health of the populations are described: external exposure dose, internal exposure sources, whole-body exposure dose, the change of the hygienic state around the power station, the number of deaths and mortality in the areas, the deaths from cancer in the areas, the health of children, the causes of deaths in Fukushima Prefecture. (Mori, K.)

Measurement uncertainty recapture (MUR) power uprates operation at Kuosheng Nuclear Power Station

International Nuclear Information System (INIS)

Chang Chinjang; Wang Tunglu; Lin Chihpao

2009-01-01

Measurement Uncertainty Recapture PowerUprates (MUR PU) are achieved through the use of state-of-the-art feedwater flow measurement devices, i.e., ultrasonic flow meters (UFMs), that reduce the degree of uncertainty associated with feedwater flow measurement and in turn provide for a more accurate calculation of thermal power. The Institute of Nuclear Energy Research (INER) teamed with Sargent and Lundy, LLC (S and L), Pacific Engineers and Constructors, Ltd (PECL), and AREVA to develop a program and plan for the Kuosheng Nuclear Power Station (KNPS) MUR PU Engineering Service Project and for the assistance to Kuosheng MUR PU operation. After regulator's approval of the licensing requests, KSNPS conducted the power ascension test and switchover to the new rated thermal power for Unit 2 and Unit 1 on 7/7/2007 and 11/30/2007, respectively. From then on, KNPS became the first nuclear power plant implementing MUR PU operation in Taiwan and in Asia. (author)

Radiation protection organization in Guangdong Nuclear Power Station (GNPS)

International Nuclear Information System (INIS)

Yang Maochun

1993-01-01

The French way of radiation protection management has been adopted by Guangdong Nuclear Power Station (GNPS) but there are some differences. In this paper author describes radiation protection organization in GNPS, special measures having been taken and the present status

75 FR 76055 - Nebraska Public Power District Cooper Nuclear Station; Notice of Issuance of Renewed Facility...

Science.gov (United States)

2010-12-07

... NUCLEAR REGULATORY COMMISSION Docket No. 50-298; NRC-2008-0617] Nebraska Public Power District Cooper Nuclear Station; Notice of Issuance of Renewed Facility Operating License No. DPR-46 for an... Power District (NPPD), the operator of the Cooper Nuclear Station (CNS). Renewed facility operating...

Daya Bay Nuclear Power Station equipment reliability management system innovation

International Nuclear Information System (INIS)

Gao Ligang; Wang Zongjun

2006-01-01

Daya Bay Nuclear Power Station has achieved good performance since its commercial operation in 1994. The equipment reliability management system that features Daya Bay characteristics has been established through constant technology introduction, digestion and innovation. It is also based on the success of operational system, equipment maintenance system and technical support system. The system lays a solid foundation for the long-term safe operation of power station. This article emphasizes on the innovation part of equipment reliability management system in Daya Bay. (authors)

Development of heavy load carrying vehicle for nuclear power station

International Nuclear Information System (INIS)

Terabayashi, Yasuharu; Oono, Hiroo; Aizu, Takao; Kawaguchi, Kaname; Yamanaka, Masayuki; Hirobe, Tamio; Inagaki, Yoshiaki.

1985-01-01

In nuclear power stations, in order to carry out sound and stable operation, the routine inspection and regular inspection of machinery and equipment are performed, therefore, the transportation of heavy things is frequently carried out. Especially, the transportation of heavy things over the steps of passages and stairs requires much labor. Therefore, Chubu Electric Power Co., Inc. and Chubu Plant Service Co., Ltd. carried out the research on the development of a vehicle for transporting heavy components of nuclear power plants. In this research, it was aimed at developing a vehicle which can carry heavy components and get over a step, climb and descend stairs, and run through a narrow passage having many curves as well as running on flat ground. For this purpose, the actual state of the transportation of heavy things was investigated during the regular inspection of a nuclear power station, and on the basis of this results, a prototype vehicle was made and tested. Thereafter, a transporting vehicle of actual scale was made and tested. The investigation of actual state and the examination of the fundamental concept, the design, trial manufacture and verifying test are reported. (Kako, I.)

Noise test system of rotating machinery in nuclear power station based on microphone array

Science.gov (United States)

Chang, Xincai; Guan, Jishi; Qi, Liangcai

2017-12-01

Rotating machinery plays an important role in all walks of life. Once the equipment fails, equipment maintenance and shutdown will cause great social harm and economic losses. Equipment safety operations at nuclear power stations have always been of top priority. It is prone to noise when the equipment is out of order or aging. Failure to find or develop equipment at the initial stage of equipment failure or ageing will pose a serious threat to the safety of the plant’s equipment. In this paper, sound imaging diagnosis technology is applied as a supplementary method to the condition monitoring and diagnosis system of rotating machinery in nuclear power stations. It provides a powerful guarantee for the condition monitoring and fault diagnosis of rotating machinery in nuclear power stations.

Ranking French nuclear industry on international market

International Nuclear Information System (INIS)

Labbe, B.

1987-01-01

Based on the success of its own ambitious nuclear power station program, France has been able to export its technology to many parts of the world, providing everything from individual components to complete power stations on a turnkey basis. Industrial partners who regurarly work together have set up the necessary structures to ensure the dovetailing of their activities during joint operations on the foreign market. These structures are matched to the needs of individual clients, and can be dispensed with completely in cases where a sole supplier is involved. Not one single unit under construction has been halted and no contract cancelled after the Chernobyl accident. France, like Japan and the USSR, is pressing on with its nuclear power program. China has ordered two PWR units for Daya Bay, while Britain has decided to construct its first PWR at Sizewell. Although a number of countries have deferred decisions in this field, this has been mainly on financial grounds. The French nuclear power industry has demonstrated its mastery of the technology, which can now be placed at the disposal of countries wishing to build nuclear power units, to improve their existing nuclear capacity, to develop parts of this future-oriented industry, or to supply their power stations with advanced nuclear fuel

The tolerability of risk from nuclear power stations: a discussion of the HSE's guidelines

International Nuclear Information System (INIS)

Ryder, E.A.; Woods, P.B.

1989-01-01

The Health and Safety Executive's discussion document, ''The Tolerability of risk from nuclear power stations'', published just a year ago considers the concept of risk and the broad principles of risk assessment and proposes guidelines on the tolerable levels of individual and societal risks from normal operation and from accidents at nuclear power stations. This paper discusses how these guidelines might be applied in safety assessments so as to ensure an acceptable level of safety and considers some of the problems inherent in the estimation of risk from nuclear power stations. It shows how the tolerable risk levels of the Health and Safety Executive's document are related to the standards used by HM Nuclear Installations Inspectorate when licensing nuclear installations. Some of the uncertainties in the estimation of acceptable risk are discussed as are the acceptance criteria used by the Inspectorate in its assessments of both normal and accident situations. (author)

Economical dismantling of nuclear power stations

International Nuclear Information System (INIS)

Mallok, J.; Andermann, H.

1999-01-01

The dismantling of nuclear power stations requires a high degree of security and economic efficiency due to the strong contamination of components and the close spatial conditions. In order to protect involved staff from radiation, modern remote-controlled technology is applied in sectors with heavy radioactive contamination such as reactor pressure vessels. The article shows, that the dismantling of reactor pressure vessels using a remote-controlled milling machine developed by the Siemens subsidiary Mechanik Center Erlangen GmbH, can be done in a secure and efficient way. (orig.) [de

FAPIG's activities for public acceptance of nuclear energy. Analytical results of questionnaire executed at organized visits to nuclear power stations

International Nuclear Information System (INIS)

Yoneda, Masaaki

2010-01-01

The First Atomic Power Industry Group (FAPIG) organized eighteenth visit of woman employees to nuclear power stations. They would have few chance of such a visit and to unfamiliar with mechanism of nuclear power generation as well as radiation and radioactivity. Participants were required to have a lecture on energy in general and basic understanding of nuclear energy and then had a visit to nuclear power stations to learn nuclear energy as correct knowledge. They also filled out the same questionnaire before the lecture and after the visit to express their ideas or comments on nuclear energy. This paper described analytical results of the questionnaire and significance of the organized visit for public acceptance of nuclear energy. (T. Tanaka)

Siting technology of underground nuclear power station

International Nuclear Information System (INIS)

Motojima, M.; Hibino, S.

1989-01-01

For the site of a nuclear power station, it may be possible to select a seaside mountain area, if the condition is suitable to excavate large rock caverns in which a reactor and other equipments are installed. As the case study on the siting technology for an underground nuclear power station, the following example was investigated. The site is a seaside steep mountain area, and almost all the equipments are installed in plural tunnel type caverns. The depth from the ground surface to the top of the reactor cavern is about 150 m, and the thickness of the rock pillar between the reactor cavern of 33 m W x 82 mH x 79 mD and the neighboring turbine cavern is 60 m. In this paper, the stability of rock caverns in this example, evaluated by numerical analysis, is described. The numerical analysis was carried out on the central cross section of the reactor cavern, taking the turbine cavern, geostress, the mechanical properties of rock mass and the process of excavation works in consideration. By the analysis, the underground caverns in this example were evaluated as stable, if the rock quality is equivalent to C H class or better according to the CRIEPI rock classification. (K.I.)

L.V. switchgear - design and development

International Nuclear Information System (INIS)

Armes, D.S.; Brown, R.D.

1992-01-01

This work describes the methods employed in the design and development of L.V. switchgear to meet the prospective conditions and operational requirements imposed on equipment at sites of PWR power stations. The work concentrates on the aspects of design, manufacture, qualification work and quality assurance particular to the range of L.V. switchgear distribution boards manufactured by Laurence, Scott and Electromotors Ltd. for Sizewell B Power Station and contrasts this equipment with other equipment for conventional (i.e. non-nuclear) power station purposes. (Author)

Computerized training program usage at the Fort Calhoun Nuclear Power Station

International Nuclear Information System (INIS)

Ruzic, D.H.; Reed, W.H.; Lawton, R.K.; Fluehr, J.J.

1987-01-01

The increased US Nuclear Regulatory Commission and Institute of Nuclear Power Operations (INPO) interest in the nuclear power industry training programs resulted in the Omaha Public Power District staff at the Fort Calhoun Nuclear Power Station investigating the potential for computerizing their recently accredited training records, student training requirements, and the process of determining student certification status. Additional areas that were desirable were a computerized question data bank with random test generation, maintaining history of question usage, and tracking of the job task analysis process and course objectives. SCI Software's online personnel training information management system (OPTIM) was selected, subsequent to a bid evaluation, to provide these features while operating on the existing corporate IBM mainframe

Fundamentals of asset management in an ageing nuclear power station

International Nuclear Information System (INIS)

Crook, B.

2014-01-01

In an ageing nuclear power station there are many challenges associated with implementing and refining an asset management program. Ageing nuclear power stations are faced with the formidable task of replacing and refurbishing major Structures, Systems, and Components (SSCs) in a managed and cost-effective way. This paper provides a brief background on equipment reliability and asset management, covers Bruce Power's methodology for implementing this complex and all-encompassing program, and describes one of the key challenges faced by Bruce Power and the industry. The effective scoping and identification of critical components is an on-going challenge which can affect the integrity of many processes built upon it. This is a fundamental building block to nearly all processes at Bruce Power and one that is at the centre of many improvement initiatives and projects. The consequences from lacking this baseline data, or worse relying upon incorrect data, can permeate the asset management process and hinder the organization's ability to assess risk properly and take the necessary steps to mitigate this risk in the short and long term. (author)

Sizewell B cycle 5 core design with Framatome ANP's CASCADE-3D and British Energy's PANTHER

Energy Technology Data Exchange (ETDEWEB)

Attale, F.; Koegl, J. [Framatome ANP GmbH, Nuclear Fuel Cycle, Erlangen (Germany); Knight, M.; Bryce, P. [British Energy, Nuclear Technology Branch, Gloucester (United Kingdom)

2001-07-01

Sizewell B Cycle 5 is the first cycle, after 4 cycles with BNFL fuel, with a reload consisting of Framatome ANP HTP (high thermal performance) fuel assemblies. The impact of this fuel vendor change on the Nuclear Design area is that, according to British energy's (BE) practice, the Framatome ANP's nuclear design code system CASCADE-3D is used for the majority of the cycle specific safety case calculations. However, other parts of the safety submission (e.g. 3D transient analyses) are made by using the BE code PANTHER. Before using in parallel two different code systems for reload core licensing extensive comparisons of applied methodologies and obtained results were required to ensure an acceptable level of agreement. (orig.)

Air quality assessment in the vicinity of nuclear and thermal power stations

International Nuclear Information System (INIS)

Sivaramasundaram, K.; Vijay Bhaskar, B.; Muthusubramanian, P.; Rajan, M.P.; Hegde, A.G.

2007-01-01

The status and ranking of any country, in the context of globalisation, is decided by its economic progress, which is directly linked into power generation. The power is generated by many routes and the nuclear and thermal routes are noteworthy among them. As the power production and its associated activities may cause qualitative deterioration, it is essential to study the impact of power production on atmospheric environment. In this connection, a comparative study has been carried out to assess the air quality with special reference to criteria pollutants in the vicinity of nuclear and thermal power stations. In the present investigation, the air samples are collected on weekly basis and the pollutants such as sulphur dioxide (SO 2 ), nitrogen oxides (NOx), carbon monoxide (CO), suspended particulate matter (SPM) and respirable particulate matter (RPM) are estimated by adopting standard procedures set by United States-Environmental Protection Agency (US-EPA) and Central Pollution Control Board (CPCB). As the micro meteorological parameters influence on the status of air quality, simultaneous measurements of these parameters are also carried, out during sampling. It is studied that estimated concentrations of all criteria pollutants in the vicinity of these power stations are within the permissible limits set by CPCB. On the basis of the generated database pertaining to the concentrations of criteria air pollutants in the vicinity of nuclear and thermal power stations, it is concluded that nuclear power production may be considered as a viable option in terms of environmental protection in our country. (author)

Childhood cancer mortality in relation to the St Lucie nuclear power station

International Nuclear Information System (INIS)

Boice, John D Jr; Mumma, Michael T; Blot, William J; Heath, Clark W Jr

2005-01-01

An unusual county-wide excess of childhood cancers of brain and other nervous tissue in the late 1990s in St Lucie County, Florida, prompted the Florida Department of Health to conduct a case-control study within the county assessing residential chemical exposures. No clear associations were found, but claims were then made that the release of radioactive substances such as strontium 90 from the St Lucie nuclear power station, which began operating in 1976, might have played a role. To test the plausibility of this hypothesis, we extended by 17 years a previous study of county mortality conducted by the National Cancer Institute. Rates of total cancer, leukaemia and cancer of brain and other nervous tissue in children and across all ages in St Lucie County were evaluated with respect to the years before and after the nuclear power station began operation and contrasted with rates in two similar counties in Florida (Polk and Volusia). Over the prolonged period 1950-2000, no unusual patterns of childhood cancer mortality were found for St Lucie County as a whole. In particular, no unusual patterns of childhood cancer mortality were seen in relation to the start-up of the St Lucie nuclear power station in 1976. Further, there were no significant differences in mortality between the study and comparison counties for any cancer in the time period after the power station was in operation. Relative rates for all childhood cancers and for childhood leukaemia were higher before the nuclear facility began operating than after, while rates of brain and other nervous tissue cancer were slightly lower in St Lucie County than in the two comparison counties for both time periods. Although definitive conclusions cannot be drawn from descriptive studies, these data provide no support for the hypothesis that the operation of the St Lucie nuclear power station has adversely affected the cancer mortality experience of county residents

78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

Science.gov (United States)

2013-04-15

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-320; NRC-2013-0065] GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain Security Requirements AGENCY: Nuclear... and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission...

Some issues on radiological consequences analysis in site selection for nuclear power stations

International Nuclear Information System (INIS)

Chen Xiaoqiu; Yue Huiguo

2006-01-01

The three considerations, Site safety and environmental protection and emergency preparedness, are the focus of attention in the evaluation of the suitability of a site for nuclear power station. This paper summarized the basic regulatory requirements for the siting of nuclear power station, described the existing problems on radiological consequences analyses during the siting stage and discussed the is- sues that need to concern in the reviewing of the radiological consequences analyses in the siting appraisal stage. (authors)

FAPIG's activities for public acceptance of nuclear energy. Analytical results of questionnaire executed at organized visits to nuclear power stations

International Nuclear Information System (INIS)

Mizoguchi, Tadao

1999-01-01

FAPIG organizes a visit to nuclear power station in every November. It is an object that visitors acquire the correct knowledge of nuclear power by looking at the various facilities in the nuclear power stations. The paper showed the analytical results of questionnaire executed at organized visits to the Kashiwazaki-Kariwa nuclear power station. The visitors were 18 women. The questionnaire was carried out by the same problems before and after seminar and a conducted tour. Their impressions and opinions and the changes are analyzed. The speakers used easy words, video, OHP, pamphlet and experimental equipment. These means showed very good results to visitors. The seminar had very large effect on just recognition of safety and need of it. The change of answer proved from 3 to 6 of need and from 0 to 7 of safety of it. Nine members indicated good understanding of seminar content. The interested items in the seminar were measurement of radiation, effects of radiation, reason of decreasing average life, Chernobyl accident, difference between nuclear power and atomic bomb and nuclear power dose not generate carbon dioxide and recycle plutonium after nuclear fission of uranium. (S.Y.)

Safety of Ikata Nuclear Power Station from the accident of Three Mile Island

International Nuclear Information System (INIS)

Nonaka, Hiroshi

1979-01-01

The leak of radioactive substances occurred on March 28, 1979, in the No. 2 plant of Three Mile Island Nuclear Power Station, and this accident must be put to use to prevent similar accidents and to secure safety hereafter in the nuclear power stations being operated in Japan. In the TMI accident, too many problems concerning the operation management seemed to exist in a series of events. In this paper, a few matters related to the TMI accident among the aspects of the operation management in Ikata Nuclear Power Station are reported. As the problems of operation management, it is considered that the operation of the TMI plant was continued as the exit valve of auxiliary feed line was closed, that it took long time to close the root valve for a pressurizer relief valve manually, and that the ECCS was stopped manually. In TMI, the abnormal phenomenon of losing main feed water has occurred 6 times since the attainment of criticality in March, 1978, and the opening and sticking of pressurizer relief valves occurred at least twice in about 150 times of their actuation in the nuclear reactors designed by Babcock and Wilcox Co. In Ikata Nuclear Power Station, these problems are detected early and the suitable measures are taken immediately, therefore it never happens to continue the operation as the problems are left as they are. It is not conceivable that similar troubles occur many times. (Kako, I.)

Study on temperature field airborne remote sensing survey along shore nuclear power station in different tide status

International Nuclear Information System (INIS)

Liang Chunli; Li Mingsong

2010-01-01

Nuclear Power Station needs to let large quantity of cooling water to the near sea area when it is running. Whether the cooling water has effect to surrounding environment and the running of Nuclear Power Station needs further research. Temperature Drainage Mathematic Model and Physical Analogue Model need to acquire the distribution characteristic of near Station sea surface temperature field in different seasons and different tide status. Airborne Remote Sending Technique has a advantage in gaining high resolution sea surface temperature in different tide status, and any other manual method with discrete point survey can not reach it. After a successful implementation of airborne remote sensing survey to gain the near-shore temperature drainage information in Qinshan Nuclear Power Station, it provides the reference methods and ideas for temperature drainage remote sensing survey of Nuclear Power Station. (authors)

Organization of radiation protection in German nuclear power stations

International Nuclear Information System (INIS)

1989-01-01

Using the operating handbooks of the nuclear power stations in West Germany, an examination was carried out of how far the existing organisational structure for radiation protection fulfils the requirements for protection and whether a standardisation of the organisation would provide improvements for the protection of the personnel and for the practicability of the radiation protection organisation. In particular, the parts 'Personnel operating organisation', 'Radiation protection order' and 'Maintenance order' of the operating handbook were evaluated and an audit was made of the radiation protection organisation. In general, the result of the assessment is that the organisation of radiation protection does not contradict the orders, guidelines and regulations in any of the nuclear power stations examined. Corresponding to the possibilities of regulating details of the radiation protection organisation within the undertaking, the target of 'protection of the personnel against radioactive irradiation' is achieved by the various organisation structures which are largely equal to the given example. (orig./HP) [de

Radioecological investigations of the Bilibino Nuclear Power Station area

Energy Technology Data Exchange (ETDEWEB)

Emelyanova, L.; Neretin, L. [Moscow State Univ. (Russian Federation). Geographical Faculty]|[Russian Academy of Sciences, Moscow (Russian Federation). P.P. Shirshov Inst. of Oceanology

1995-12-31

The landscape structure of the territory and the current radioactive state of ecosystems in the vicinity of Bilibino Nuclear Power Station (Western Chukotka Peninsula) within the area of its potential influence on the environment were studied in 1989--1990. Accumulation of strontium-90 and cesium-137 radionuclides in several key biological members of the ecosystems has been analyzed. Maximal weighted content of cesium-137 was revealed in mountain pine cones (Pinus pumila) -- 9,200 Bq/kg.d.w., cowberry fruits have demonstrated considerable contamination by strontium and cesium isotopes. The purification of first two components of food chain ``lichen-reindeer-man`` was pointed out in the investigated area. Besides the chemical characteristics, visual biological anomalies of biocomponents nearby the Bilibino NPS ecosystems are observed. On the basis of field radioecological investigations and future work, programs were developed for the conditions of the Bilibino Nuclear Power Station area. This experience could be applied to the researches of radioactive contamination in ecosystems of other northern territories.

Examination policy concerning the additional installation of No. 3 and No. 4 reactors in Takahama Nuclear Power Station and No. 3 and No. 4 reactors in Fukushima No. 2 Nuclear Power Station

International Nuclear Information System (INIS)

1980-01-01

The Nuclear Safety Commission decided the annual examination policy on the modification of reactor installation in Takahama Nuclear Power Station to construct No. 3 and No. 4 reactors inquired under date of November 26, 1979, by the Minister of International Trade and Industry, so that the examination results of the accident in Three Mile Island nuclear power station are reflected to the examination for the purpose of improving reactor safety. The examination results of the accident in Three Mile Island power station are being investigated by the Committee on Examination of Reactor Safety, based on the policy shown in ''On the second report of the special committee examining the accident in a nuclear power station in the U.S.'' determined by the Nuclear Safety Commission under date of September 13, 1979. Though the Committee will further clarify the past guideline about the items concerning the criteria, design and operation management, the Committee decided the tentative policy to reflect it to safety examination. Further, a table is attached, in which 52 items to be reflected to the security measures are classified from the viewpoint of necessity to reflect them to the final examination. This table includes 13 items of criteria and examination, 7 items related to design, 10 items related to operation management, 10 antidisaster items, and 12 items related to safety research. (Wakatsuki, Y.)

Comparison and evaluation of nuclear power plant options for geosynchronous power stations

International Nuclear Information System (INIS)

Williams, J.R.

1975-01-01

A solution to the safety, safeguards, and radwaste disposal problems of nuclear power is to locate the breeder reactor power plants far out in geosynchronous orbit and beam the power to earth with microwaves. The generation of nuclear power in space is technologically feasible and has already been demonstrated on a small scale. It has also been shown that high efficiency microwave transmission of power from synchronous orbit to earth is feasible and is not hazardous. The reactor safety problem would be virtually eliminated because of the remoteness of the satellite power station in geosynchronous orbit. The worst possible accident at such a plant would have negligible effect on the earth, certainly less than the high altitude nuclear explosions which have been conducted in the past. Accidental re-entry from geosynchronous orbit could not occur because of the very large velocity change required. The safeguards problem can be virtually eliminated by adopting the following procedures: 1) The plant is initially started up using U-235 fuel or bred plutonium or U-233 from another geosynchronous power plant, 2) Once the plant is operating, only nonhazardous fertile materials (thorium or depleted uranium) are shipped up from earth, 3) The fissile fuel is bred and used in space, and none of this highly toxic fissile material is ever returned to earth. The radioactive waste could be concentrated and ejected in canisters into deep space away from the earth. The geosynchronous nuclear power plant offers unlimited nuclear power without nuclear hazards or nuclear pollution, but at somewhat higher cost. Whether or not society will be willing to pay these higher costs of nuclear power from space, or whether new energy resources such as nuclear fusion or solar power become feasible, remains to be seen. A prudent course to follow would be to give careful consideration to all future options for large scale energy generation, including the option of nuclear power from space

Technological development of Guangdong nuclear power station

International Nuclear Information System (INIS)

Huang Shiqiang

2000-01-01

After over 5 years of operations, the Guangdong Nuclear Power Station (GNPS) has achieved good results both economically and in operational safety performance. The main attributes to the success of the plant operational performances include the equipment reliability, the technical capability and management efficiency. To that the key strategy has been to adopt know-how and technological transfer and encourage self-innovation, aiming to strive for the long-term self-reliance in design, manufacturing and operating the plant. (author)

The effects of the nuclear disaster at Fukushima Daiichi Nuclear Power Station on local governments

International Nuclear Information System (INIS)

Nakamura, Makoto; Dake, Kinji

2012-01-01

All Japan council of local governments with atomic power stations consisted of 24 reactor site and 6 neighboring local governments to solve reactor site related problems. Nuclear disaster at Fukushima Daiichi Nuclear Power Station affected member local governments to be forced in severe conditions such as 'removal of administrative function' or 'refuge over a wide district beyond local government area', not imagined before. The council set up working group for thirteen local governments themselves to investigate this disaster and find safety and prevention of disaster measures to be deployed in nuclear administration, which published report in March 2012. This article described outline of investigation and derived problems and direction of their solution. Main items were related with communication, resident evacuation, prevention of disaster system, and management of refuge site. (T. Tanaka)

Service hall in Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc

International Nuclear Information System (INIS)

Tawara, Shigesuke

1979-01-01

There are six BWR type nuclear power plants in the Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc. The service hall of the station is located near the entrance of the station. In the center of this service hall, there is the model of a nuclear reactor of full scale. This mock-up shows the core region in the reactor pressure vessel for the number one plant. The diameter and the thickness of the pressure vessel are about 5 m and 16 cm, respectively. The fuel assemblies and control rods are set just like the actual reactor, and the start-up operation of the reactor is shown colorfully and dynamically by pushing a button. When the control rods are pulled out, the boiling of water is demonstrated. The 1/50 scale model of the sixth plant with the power generating capacity of 1100 MWe is set, and this model is linked to the mock-up of reactor written above. The operations of a recirculating loop, a turbine and a condenser are shown by switching on and off lamps. The other exhibitions are shielding concrete wall, ECCS model, and many kinds of panels and models. This service hall is incorporated in the course of study and observation of civics. The good environmental effects to fishes and shells are explained in this service hall. Official buildings and schools are built near the service hall utilizing the tax and grant concerning power generation. This service hall contributes to give much freedom from anxiety to the public by the tour. (Nakai, Y.)

Circulating water pumps for nuclear power stations

International Nuclear Information System (INIS)

Satoh, Hiroshi; Ohmori, Tsuneaki

1979-01-01

Shortly, the nuclear power station with unit power output of 1100 MW will begin the operation, and the circulating water pumps manufactured recently are those of 2.4 to 4 m bore, 840 to 2170 m 3 /min discharge and 2100 to 5100 kW driving power. The circulating water pumps are one of important auxiliary machines, because if they fail, power generation capacity lowers immediately. Enormous quantity of cooling water is required to cool condensers, therefore in Japan, sea water is usually used. As siphon is formed in circulating water pipes, the total head of the pumps is not very high. The discharge of the pumps is determined so as to keep the temperature rise of discharged water lower than 7 deg. C. The quantity of cooling water for nuclear power generation is about 50% more as compared with thermal power generation because of the difference in steam conditions. The total head of the pumps is normally from 8 to 15 m. The circulating water pumps rarely stop after they started the operation, therefore it is economical to determine the motor power so that it can withstand 10% overload for a short period, instead of large power. At present, vertical shaft, oblique flow circulating water pumps are usually employed. Recently, movable blade pumps are adopted. The installation, construction and materials of the pumps and the problems are described. (Kako, I.)

Phytotoxicology section investigation in the vicinity of the Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the Darlington Nuclear Generating Station, in October, 1989

International Nuclear Information System (INIS)

1991-02-01

The Phytotoxicology Section, Air Resources Branch is a participant in the Pickering and Bruce Nuclear Contingency Plans. The Phytotoxicology Emergency Response Team is responsible for collecting vegetation samples in the event of a nuclear emergency at any of the nuclear generating stations in the province. As part of its responsibility the Phytotoxicology Section collects samples around the nuclear generating stations for comparison purposes in the event of an emergency. Because of the limited frequency of sampling, the data from the surveys are not intended to be used as part of a regulatory monitoring program. These data represent an effort by the MOE to begin to establish a data base of tritium concentrations in vegetation. The Phytotoxicology Section has carried out seven surveys in the vicinity of Ontario Hydro nuclear generating stations since 1981. Surveys were conducted for tritium in snow in the vicinity of Bruce Nuclear Power Development (BNPD), February, 1981; tritium in cell-free water of white ash in the vicinity of BNPD, September, 1981; tritium in snow in the vicinity of BNPD, March, 1982; tritium in tree sap in the vicinity of BNPD, April, 1982; tritium in tree sap in the vicinity of BNPD, April, 1984, tritium in the cell-free water of white ash in the vicinity of BNPD, September, 1985; and, tritium in cell-free water of grass in the vicinity of Pickering Nuclear Generation Station (PNGS), October 1986. In all cases a pattern of decreasing tritium levels with increasing distance from the stations was observed. In October, 1989, assessment surveys were conducted around Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the new Darlington Nuclear Generating Station (DNGS). The purpose of these surveys was to provide baseline data for tritium in cell-free water of grass at all three locations at the same time of year. As none of the reactor units at DNGS had been brought on line at the time of the survey, this data was to be

Implications of Extension of Station Blackout Cooping Capability on Nuclear Power Plant Safety

International Nuclear Information System (INIS)

Volkanovski, Andrija

2015-01-01

The safety of the nuclear power plant depends on the availability of the continuous and reliable sources of electrical energy during all modes of operation of the plant. The station blackout corresponds to a total loss of all alternate current (AC) power as a result of complete failure of both offsite and on-site AC power sources. The electricity for the essential systems during station blackout is provided from the batteries installed in the nuclear power plant. The results of the probabilistic safety assessment show that station blackout is one of the main and frequently the dominant contributor to the core damage frequency. Results of the analysis of the implications of the strengthening of the SBO mitigation capability on safety of the NPP will be presented. The assessment is done with state-of-art deterministic and probabilistic methods and tolls with application on reference models of nuclear power plants. The safety analysis is done on reference model of the nuclear power plant. Obtained results show large decrease of the core damage frequency with strengthening of the station blackout mitigation capability. The time extension of blackout coping capability results in the delay of the core heat up for at least the extension time interval. Availability and operation of the steam driven auxiliary feedwater system maintains core integrity up to 72 h after the successful shutdown, even in the presence of the reactor coolant pumps seal leakage. The largest weighted decrease of the core damage frequency considering the costs for the modification is obtained for the modification resulting in extension of the station blackout coping capability. The importance of the common cause failures of the emergency diesel generators for the obtained decrease of the core damage frequency and overall safety of the plant is identified in the obtained results. (authors)

U.S. Central Station Nuclear Power Plants: operating history

International Nuclear Information System (INIS)

1976-01-01

The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission

Fire protection devices in the controlled region of GKN nuclear power station

International Nuclear Information System (INIS)

Bernhardt, S.; Grauf, E.

1976-01-01

In the GKN nuclear power station ('Neckar reactor'), an 805 MW PWR reactor whose start-up is scheduled for the near future, fire protection measures have been realized that go far beyond those realized in other German nuclear power stations until now. One of the main reasons is that the authorities have been sensibilized by a fire in the refuelling cavity during construction and by the Browns Ferry fire and are therefore extremely thorough in their examination. Further subsections have been added to the fire prevention sections in order to provide better quenching devices for potential fire sites. (orig./AK) [de

Challenges to fire protection measures at Hamaoka Nuclear Power Station

International Nuclear Information System (INIS)

Narama, Takeshi

2015-01-01

New regulatory standards for fire protection at nuclear power plants have been established by the Nuclear Regulation Authority. This paper introduces the measures taken by the Hamaoka Nuclear Power Station for the following four items, which were especially big changes. (1) To install a combination of sensors of different types or instruments with equivalent functions so as to be able to emit unique signals to inform a fire in the early stage. (2) To conduct 'UL vertical burn test' as the demonstration test for self-extinguishing performance as the condition for flame-retardant cable. (3) To install automatic fire-extinguishers or fixed fire-extinguishing devices of manual type at the spots where fire-fighting is difficult due to the filling of smoke in a fire or the effect of radiation. (4) To separate the system for purpose of ensuring safety function to attain the high-temperature shutdown and cold-temperature shutdown of a reactor whatever fire may happen at the nuclear facilities. The examples of the installation of fire-extinguishers as the measures for the above Item (3) are as follows; (A) as for the devices containing oil, a foam-extinguishing agent is released against each target device from the nozzle, and (B) for large vertical pump motors indoors and relatively small pump motors, IA type automatic foam extinguishing systems are installed. (A.O.)

Power station impacts: socio-economic impact assessment

International Nuclear Information System (INIS)

Glasson, John; Elson, Martin; Barrett, Brendan; Wee, D. Van der

1987-01-01

The aim of this study is to assess the local social and economic impacts of a proposed nuclear power station development at Hinkley Point in Somerset. The proposed development, Hinkley Point C, would be an addition to the existing Hinkley Point A Magnox station, commissioned in 1965, and the Hinkley Point B Advanced Gas Cooled Reactor (AGR) station, commissioned in 1976. It is hoped that the study will be of assistance to the CEGB, the Somerset County and District Councils and other agencies in their studies of the proposed development. In addition, the study seeks to apply and further develop the methodology and results from previous studies by the Power Station Impacts (PSI) team for predicting the social and economic effects of proposed power station developments on their localities. (author)

A list of abnormal occurences at Swedish nuclear power stations

International Nuclear Information System (INIS)

McHugh, B.

1974-08-01

This report consists of a list of extracts from documents belonging to Statens Kaernkraftinspektion (SKI) in Sweden. It deals with non-routine occurrences at the Swedish nuclear power stations which are in operation or where test operations of components and systems have started. The investigation has included matter about the following nuclear power plants: Barsebaeck-1, Oskarshamn-1, Oskarshamn-2, Ringhals-1, Ringhals-2, Aagesta. In all cases from the start of the test operations up to latest the 1st of June 1974. (M.S.)

ALARA organization in nuclear power stations

International Nuclear Information System (INIS)

Dollo, R.

1997-01-01

EDF's nuclear power stations were built with provisions being made, as from the design stage, to limit radiation sources and the results observed over the first ten years (annual collective dose and dose per unit of less than 2 man.Sv) were considered to be very good. However, these results began to deteriorate from 1988 onwards. At the same time, considerable progress was being made by other generators of electricity, who were achieving results which were better than those achieved by our later units. Furthermore, radiological protection standards are being revised and personal dose limits will soon be lowered. (authors)

Electrical and control aspects of the Sizewell B PWR

International Nuclear Information System (INIS)

1992-01-01

The pressurized water reactor, Sizewell-B, which is being built in Suffolk is well on in its construction schedule. This conference looked at the electrical and control aspects of the first PWR to be built in the United Kingdom. Although based on the standard Westinghouse PWR design, modifications have been made to meet the particular requirements of the site and the UK licensing regulations. There are 11 papers on all aspects of the electrical systems, 5 papers on the cables and cable installation, 5 on the main control rooms and auxiliary shutdown room, 5 on the integrated system and centralised operation, 6 on the monitoring and protection systems and 9 on the reactor protection systems. All 41 are indexed separately. (UK)

Ten-yearly report on operations at the Garigliano nuclear power station

International Nuclear Information System (INIS)

1977-01-01

This document is the final report on operation of the Garigliano Nuclear Power Station as required under the participation contract between Enel and Euratom and refers to the first ten years of commercial operation (1 May 1964-31 December 1973) of the power station. In the decade in question the Garigliano Power Station has assumed an important position in the world spectrum of nuclear energy since it was the first thermal-power reactor in the world to have irradiated considerable quantities of plutonium as a fuel in its own core for the production of energy. An experimental programme on this was started in 1966 with theoretical study of plutonium recycling and was followed by the charging of the Garigliano reactor with some mixed oxide elements (PuO 2 -UO 2 ) in 1968 and 1970. The excellent performance of these prototype elements, which among other things were examined in detail at the end of each radiation cycle, prompted Enel to decide in favour of the use of entire batches of recycled fuel elements of the PuO 2 -UO 2 type in the reactor from 1975 onwards

Report from investigation committee on the accident at the Fukushima Nuclear Power Stations of Tokyo Electric Power Company

International Nuclear Information System (INIS)

Koshizuka, Seiichi

2012-01-01

Government's Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company published its final report on July 23, 2012. Results of investigation combined final report and interim report published on December 26, 2011. The author was head of accident accuse investigation team mostly in charge of site response, prior measure and plant behavior. This article reported author related technical investigation results focusing on site response and prior measures against tsunamis of units 1-3 of Fukushima Nuclear Power Stations. Misunderstanding of working state of isolation condenser of unit 1, unsuitability of alternative water injection at manual stop of high-pressure coolant injection (HPCI) system of unit 3 and improper prior measure against tsunami and severe accident were pointed out in interim report. Improper monitoring of suppression chamber of unit 2 and again unsuitable work for HPCI system of unit 3 were reported in final report. Thorough technical investigation was more encouraged to update safety measures of nuclear power stations. (T. Tanaka)

Quality assurance in the structural installations of nuclear power stations

International Nuclear Information System (INIS)

Schnellenbach, G.; Wrage, S.

1985-01-01

The concept of quality assurance distinguishes between self-monitoring of the design, manufacturing and executing firms and external monitoring by state institutions or by experts commissioned by them. The long-term control of structures is within the area of responsibility of the owner. This quality assurance concept is controlled in detail by statutes, which clearly define responsibilities. This structural engineering quality assurance system also forms the basis for the design, construction and utilization of structural installations of nuclear power stations; requirements emanating from the Atomic Energy Acts for the structural installations demand, however, to some extent a sharpening of self- and external monitoring. Therefore, today a quality concept has been developed for the important engineering safety-related buildings of nuclear power stations. This concept takes account of the strict requirements imposed and fulfils the requirement of KTA 1401. (orig.) [de

Efforts toward enhancing seismic safety at Kashiwazaki Kariwa Nuclear Power Station

International Nuclear Information System (INIS)

Yamashita, Kazuhiko

2009-01-01

It has been two years since the Niigata-ken Chuetsu-oki Earthquake (NCOE) occurred in 2007. The earthquake brought a major disaster for Kashiwazaki, Kariwa, and the neighboring areas. First of all, we would like to give condolences to people in the devastated area and to pray for the immediate recovery. Our Kashiwazaki Kariwa Nuclear Power Station located in the same area was naturally caught up in the earthquake. The station was hit by a big tremor more than its intensity assumed to be valid at the station design stage. In spite of unexpected tremor, preventive functions for the station safety worked as expected as it designed. Critical facilities designed as high seismic class were not damaged, though considerable damages were seen in outside-facilities designed as low seismic class. We currently make efforts to inspect and recover damages. While we carefully carry out inspection and assessment to make sure the station integrity, we are also going forward restoration as well as construction for seismic safety enhancement in turn. This report introduces details of the following accounts, these are an outline of guidelines for seismic design evaluation that was revised in 2006, a situation at Kashiwazaki Kariwa Nuclear Power Station in the aftermath of the earthquake, and efforts toward enhancing seismic safety that the Tokyo Electric Power Company (TEPCO) has made since the seismic disaster, and our approach to evaluation of facility integrity. (author)

A survey of the development of Nuclear Power Stations in Asia

International Nuclear Information System (INIS)

Javan, A.

2000-01-01

Thanks to its direct correlation with economic development, the power industry has got a boost in the Asian countries. The development of the power industry in Asia hinges predominantly on the construction of nuclear power stations. The capacity of nuclear plants is expected to reach to 51-67 gigawatts in 2010, compared with 22.5 gigawatts in 1999. As the nuclear technology is supplied by the Western economies especially the US, Canada and France, the construction of new nuclear plants would make the Asian states even more dependant on the Western nations. It seems the willingness of the western countries in providing nuclear power technology to the Asian states, among other factors stems from their ambition of controlling price and supply of oil and gas in the region. This is actually a threat to the fossil fuel holders

Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

OpenAIRE

TANAKA, Shun-ichi

2012-01-01

The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety o...

Isar-2 nuclear power station twenty-five years

International Nuclear Information System (INIS)

Fischer, Erwin; Luginger, Markus

2013-01-01

The Isar-2 nuclear power station (KKI 2) began commercial power operation on April 9, 1988. In these past 25 years the plant generated a total of approx. 285 billion kWh of electricity. The annual electricity production of KKI 2 of approx. 12 billion kWh corresponds to a share of approx. 15 % in the cumulated Bavarian electricity production. This amount of electricity, theoretically, could supply some 3 million three person households, or meet two thirds of the electricity requirement of the Bavarian industry, for one year. In its 25 years of power operation the Isar-2 nuclear power plant has recorded the highest annual gross electricity production of all nuclear power plants in the world nine times so far. A plant performance as impressive as this necessitates a plant availability far above the average. This, in turn, is based on short revision times and faultfree plant operation. However, high plant safety and availability must not be taken for granted, but are the result of responsible, safety-minded plant operation combined with continuous plant optimization and permanent execution of comprehensive checks, inspections, and maintenance measures. Besides plant technology also organization and administration were permanently advanced and adapted to changing requirements so as to safeguard reliable, safe, and non-polluting plant operation.

Simulators of nuclear power stations

International Nuclear Information System (INIS)

Zanobetti, D.

1984-01-01

The report deals with the simulators of nuclear power stations used for the training of operators and for the analysis of operations. It reviews the development of analogical, hybrid and digital simulators up to the present, indicating the impact resulting from the TMI-2 accident. It indicates, the components of simulators and the present accepted terminology for a classification of the various types of simulators. It reviews the present state of the art of the technology: how a basic mathematical model of a nuclear power system is worked out and what are the technical problems associated with more accurate models. Examples of elaborate models are given: for a PWR pressurizer, for an AGR steam generator. It also discusses certain problems of hardware technology. Characteristics of present replica simulators are given with certain details: simulated transient evolutions and malfunctions, accuracy of simulation. The work concerning the assessment of the validity of certain simulators is reported. A list of simulator manufacturers and a survey of the principal simulators in operation in the countries of the European Community, in the United States, and in certain other countries are presented. Problem associated with the use of simulators as training facilities, and their use as operational devices are discussed. Studies and research in progress for the expected future development of simulators are reviewed

AECB staff annual assessment of the Bruce B Nuclear Generating Station for the year 1996

International Nuclear Information System (INIS)

1997-06-01

The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Bruce Nuclear Generating Station B for 1996. It was concluded that Ontario Hydro operated Bruce B safely in 1996. Although the Bruce B plant is safe,it was noted that the number of outages and the number of secondary and tertiary equipment failures during reactor unit upsets increased. Ontario Hydro needs to pay special attention to prevent such a decrease in the safety performance at Bruce B

Annual report of operation management in nuclear power stations, fiscal year 1985. Showa 60 nendo genshiryoku hatsudensho unten kanri nenpo

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

Twenty years have elapsed since the first practical nuclear reactor in Japan started the operation. In the generated power in fiscal year 1985, that of nuclear power stations for the first time overtook that of thermal power stations, and now the age of nuclear power as the main and oil power as the subordinate has begun. As of the end of fiscal year 1985, there were 32 nuclear power plants in operation, having total output capacity of 24.521 million kW. In fiscal year 1985, nuclear power plants generated about 159 billion kWh, which is about 2 % of electric power supply. As to the capacity factor, 76% was attained in fiscal year 1985, and this is ranked in the top group of LWR-operating countries in the world. It showed that the Japanese technology of nuclear power generation is at the top level in the world. However, in order to increase nuclear power generation and to accomplish the role of main electric power source hereafter, it is necessary to further increase the reliability and economical efficiency. The list of nuclear power stations in Japan, the state of operation of nuclear power stations, the state of accidents and troubles, the state of regular inspection, the management of radioactive wastes and the radiation exposure of workers in nuclear power stations, the operational management and others are reported.

Concrete works in Igata Nuclear Power Station Unit-2

International Nuclear Information System (INIS)

Yanase, Hidemasa

1981-01-01

The construction of Igata Nuclear Power Station Unit-2 was started in February, 1978, and is scheduled to start the commercial operation in March, 1982. Construction works are to be finished by August, 1981. The buildings of Igata Nuclear Power Station are composed of large cross section concrete for the purpose of shielding and the resistance to earth quakes. In response to this, moderate heat Portland cement has been employed, and in particular, the heat of hydration has been controlled. In this report, also fine and coarse aggregates, admixtures and chemical admixtures, and further, the techniques to improve the quality are described. Concrete preparation plant was installed in the power station site. Fresh concrete was carried with agitator body trucks from the preparation plant to the unloading point, and from there with pump trucks. Placing of concrete was carried out, striving to obtain homogeneous and dense concrete by using rod type vibrators. Further, concrete was placed in low slump (8 - 15 cm) to reduce water per unit volume, and its temperature was also carefully controlled, e.g., cold water (temperature of mixing water was about 10 deg C) was used in summer season (end of June to end of September). As a result, the control target was almost satisfied. As for testing and inspection, visual appearance test was done as well as material testing in compliance with JIS and other standards. (Wakatsuki, Y.)

Report and accounts 1989/90

International Nuclear Information System (INIS)

1991-01-01

Nuclear Electric was set up to run all the Magnox and AGR nuclear power stations and nuclear-related assets of the Central Electricity Generating Board. It is also to be responsible for the construction and operation of the PWR station at Sizewell-B in Suffolk. The decision not to privatise the nuclear section of the electricity supply industry in England but to retain it in government ownership came quite late on so the handover to Nuclear Electric was set up in 20 weeks, so that the new company could start operating on 31st march 1990. This report sets out the first year's progress and reviews the operation of the Magnox and AGR reactors and the construction of Sizewell-B including a revised cost estimation. Health and Safety is an important objective of the company and its committment to this and to environmental protection is stated. The Directors Report and company accounts presented. The accounts show an operating profit but an overall loss for the financial year 1989/90. (UK)

Research on applicability of optical and digital technologies to nuclear power stations

International Nuclear Information System (INIS)

Emoto, Motonori

1990-01-01

Recently, the development of electronic technology represented by optical multiple transmission technology and digital technology is remarkable, and it is expected that this tendency advances further hereafter. The improvement of the reliability, operational performance and maintainability of nuclear power stations by applying these most advanced technologies to them has been desired. In this research, it was found that by the application of optical multiple transmission and digital technology to nuclear power stations, their operation by a small number of operators, the automation of work management and so on can be realized. Besides, it was found that as the major technologies of hereafter, the advance of artificial intelligence technology, rapid and large capacity information processing, the network of the computers of different types and others is necessary. Further, if these technologies are completed, the clarification of the requirement when those are actually applied to nuclear power stations is necessary, and it was found also that as the matters to be considered at that time, the extent of improvement of reliability, the reduction of risk at the time of the troubles of equipment and other fundamental matters must be clarified hereafter. (K.I.)