[en] According to the basic safety standards the undertaking shall inform exposed workers about the health risks involved in their work, general radiation protection procedures and precautions to be taken in the controlled area. Using available information and knowledge based on international recommendations related to radiation protection, nuclear energy and specific plant design and procedures, the topics of interest have been selected and prepared for computer presentation or film. The paper presents the requirements, suggestions and facts included in this information, such as radiation protection practice in general and nuclear power plant specific information. The presentation will provide a useful example on how to inform and train periodically radiation workers from outside undertakings. (author)

[en] In 2001 a modernization of the Accident Localization System (ALS) on unit 4 was accomplished. The outage duration was longer then usually and special dose budget was elaborated. All ALS work was performed by external organization. An ALARA implementation was recognized priority. The really accumulated collective doses were analyzed and conclusions drawn. A short film on CD was prepared. Two conclusions are drawn: 1. Good work management and a first attempt of effective empowerment of the workers gave satisfactory results; 2. Although the work was not typical, and performed for a first time, the ALARA implementation reduced the projected collective dose with 19%

[en] The Thermo (Siemens) Electronic Dosemeter EPD-1.2D is the Approved dosimetry system for British Energy (BE). It has been in use for a number of years firstly as a control dosemeter and latterly as a legal dosemeter. This paper reviews its performance from a corporate perspective and considers issues such as maintenance strategy, sharing of dosemeters across a number of sites and common user problems encountered across sites. In conclusion the introduction of electronic dosemeters for legal use within BE has been successful. The main issues that require attention with electronic dosimetry are: - the reliability and ruggedness of the dosemeter; - the arrangements for the computing support of the system; - obsolescence and updates of components and software

[en] French regulations originally required film to be used as a passive dosimeter. This ruling was changed with the publication of the decision dated 23 March, 'stipulating the rules concerning external dosimetry for workers assigned to tasks involving exposure to radiation'. This decision lays down certain obligations in terms of results, but does not impose any particular technology. Moreover, technological advances have made the future of silver film uncertain, for both photographic and dosimetry purposes. Consequently, in early 2001 the Management at the EDF Group's Nuclear Generation Division (DPN) decided to undertake a study, looking at the feasibility and potential benefits of adopting a new passive dosimeter technology. (author)

[en] Nuclear plant decommissioning presents several challenges in radiation protection. The plant demolition must consider radiation protection for workers, protection of the public, and careful material management. Decommissioning of the San Onofre Nuclear Generating Station (SONGS) Unit 1 presented some additional challenges. Including complete removal of above ground structures this can be accomplished safely and efficiently. None of the low-level radioactive waste is unique to decommissioning although transportation of large components can be a significant challenge. Proven techniques are available to handle Greater than Class C waste (highly activated reactor internals) and spent fuel. A considerable challenge is the disposing of the very large volume of potentially clean material. There is a high cost to survey and decontaminate materials. Moreover, in the US today there are no standards for the clearance of potentially contaminated volumetric materials. Careful planning is necessary to determine the most cost-effective means for waste management, whether it includes decontamination and surveys or simple disposal. Lastly, existing ALARA programs with some minor modifications provide sufficient worker and public protection from radiation

[en] In this paper we present a method of combining results from gamma scanning equipment with a 3D dose simulation tool with the aim to achieve a reliable dose characterisation of the work site in order to perform dose assessment and optimisation for work planned in the area. A first step in any ALARA pre-job study is the radiological characterisation of the work site. Traditionally this is done based on 4 π dose measurement and spectral analysis of sweeps or samples taken from the site. This method can be very tedious and dose intensive especially in complex geometries. In recent years equipment such as gamma cameras and gamma scanners started to appear on the market enabling a remote localisation of source positions and geometry. We will show how the data of the gamma scanning can be analysed with a 3D dose assessment tool in order to achieve a reliable source model for the work environment and how the source and geometry modelling information can be used in the dose optimisation problems. (author)

[en] Information sharing through ISOE system has known to be an effective tool to support for decision-making process. The ISOEDAT distributed to the member states since 1995 has never been operated in Korea because of operational conflicts with computer environment in Asian region. In this regard, both the CEPN and the KINS devoted to recognize the sources of conflicts that were eliminated recently. In parallel, the database and task allocation of radiation works during outages has been modified to adopt the formula of task groups described in the ISOEDAT. Various efforts are being devoted to implement the new actions for management. Concerns and lessons learned obtained from these modifications will be presented in this paper as well as the pilot test results for grouping radiation work assignments during the outage. (authors)

[en] Teollisuuden Voima Oy (TVO) is a private own company, which operates two ASEA Atom designed BWR units in Olkiluoto island in the west coast of Finland. TVO is founded in 1969 and the commercial operation of units OL1 and OL2 started in 1979 and 1982 respectively. After two power increase projects the current net power of 840 MWe per unit (corresponds to 2500 MW thermal power) was achieved in 1998. The company produces electricity to its shareholders at cost. During the year 2003 over 25 % of the electricity in Finland was produced by nuclear power, meanwhile the share of import was 5.7 %. Other notable manners of electricity production are hydropower, co-generation (district heating and industry) and condensing power (fossil fuel). Up to the year 2015 the annual electricity demands are estimated to increase with 25 - 30 TWh. This is due to the consumption increase, estimated decrease of import and reduction of old capacity. The paper addresses the following items: - overall view on the nuclear power licensing and procurement procedures; - bid evaluation phase - radiation protection aspects; - main activities during the execution phase and conduct operation

[en] The radiation protection of itinerant (called 'outside' in EU directive and 'external' in the Czech legislation) workers in the light of the new legislation adopted after the harmonization with the EU directives in last two years in the Czech Republic is described. With respect to new legislation being in force from 2002, SUJB is authorized to issue and register radiation passports. Forms of these passports, rules of the forms filling and verification of registered data are laid down in new special Decree of SONS No.419/2002 Coll. on personal radiation passports. The radiation passport consists of two parts, one part is permanent with the possibility of ten years dosimetric results registration and second part with detailed registration of annual doses will be changed every year. During 2003 SUJB has issued 2 050 personal radiation passports. The licensing process and requirements for undertakings and operators are described and the actual problems which raised during the implementation process are also identified. The recent status of the international recommendations as well as the necessity of the unified and clear approach on this field is also discussed. (authors)

[en] The optimisation of the operation of a nuclear power plant (NPP) is a challenging issue due to the fact that besides general management issues, a risk associated to nuclear facilities should be included. In order to optimise the radiation protection programmes in around 440 reactors in operation with more than 500 000 monitored workers each year, the 1.y words: rad-exchange of performance indicators (PI) related to radiation protection issues seems to be essential. Those indicators are a function of a type of a reactor as well as the age and the quality of the management of the reactor. In general three main types of radiation protection PI could be recognised. These are: occupational exposure of workers, public exposure and management of PI related to radioactive waste. The occupational exposure could be efficiently studied using ISOE database. The dependence of occupational exposure on different types of reactors, e.g. PWR and BWR are given, analysed and compared. (authors)