Nuclear Issues 

NUCLEAR SAFETY AND THE ENVIRONMENT

Report on the Regulators’ Experience of NDT Qualification for In-service Inspection of Nuclear Components

Report EUR 20819 EN (163K) Published in August 2003

NUCLEAR SAFETY AND THE ENVIRONMENT

30 Years off NRWG activities towards harmonisation of nuclear safety criteria and requirements

Report EUR 20818 EN (204K) Published in November 2002

NUCLEAR SAFETY AND THE ENVIRONMENT

Regulatory Assessment of the Effects of Economic Deregulation of the Nuclear Industry

Report EUR 20431 EN (139K) Published in November 2002

NUCLEAR SAFETY AND THE ENVIRONMENT

Assessment and Upgrading of the Novi Han Monitoring System (Bulgaria)

Report EUR 20656 EN Published in December 2002
cover page (23K)
main report (3,619K!)

The general objectives of this project were:

• Evaluation of the Novi Han site radiological status.

• Review of the Bulgarian legislation in respect to environmental monitoring and comparison to other European and international standards.

• Critical review of the current monitoring practices.

The site assessment has produced the following outputs:

• the Novi Han team undertook the sampling of soils, sediments and vegetation;

• the on-site and laboratory analysis in Belgium have not shown any significant release from the vaults with the exception for ³H that has been detected in significant concentration in water samples collected from boreholes.

The critical analysis of the current monitoring program and the laboratory equipment have revealed some weak points and remedial measures have been proposed where and when required.

An evolutional monitoring program has been defined in accordance with the EC recommendations.

A 2-week training was organised in Belgium for 2 people from Novi Han repository; the training was focused on methods required by the monitoring program.

Four QA analytical procedures have been written by the trainees and have been verified by IRE.

The skeleton of a radiological database has been drafted (realization is beyond the scope of the current project and is strongly linked to the QA system).

The priority equipment needed for the implementation of the monitoring program has been defined in agreement with the Novi Han staff and has been purchased within the limits of budget.

NUCLEAR SAFETY AND THE ENVIRONMENT

Detailed description of a new management system for solid, short-lived low and intermediate level radioactive waste at Ignalina NPP

Report EUR 20655 EN Published in 2002
cover page + description of parts (41K)
Part I (430K)
Part II (1803K)
Part III (194K) - draft only
Part IV (449K)

The objective of this project was to provide a detailed description of a new management system at INPP for solid, short-lived low and intermediate level radioactive waste, from the collection of the waste to the interface with the interim storage facility for the waste.

The results provide a basis for INPP's decision concerning implementation of a new management system.

This project forms part of a wider programme of activities concerning assistance and co-operation between SKB and INPP to help solve the problems of radioactive waste management at the site.

The results cover the following aspects:

• preliminary system description (conceptual);
• detailed system description;
• waste acceptance criteria

In addition, there is an overview, for the benefit of INPP staff, of the treatment of these wastes in Swedish NPPs 

NUCLEAR SAFETY AND THE ENVIRONMENT

Management of Spent Sealed Radioactive Sources in Bulgaria, Latvia, Lithuania, Romania and Slovakia

Report EUR 20654 EN (2870K) January 2003

This study has been performed to consider the situation relating to the regulation and management of spent sealed radioactive sources (SSRS) in five of the central and Eastern European (C&EE) countries that are candidates to join the EU (Bulgaria, Latvia, Lithuania, Romania and Slovakia). See also report EUR19842 dealing with the other five C&EE candidate countries. The general aim of this study has been to acquire a thorough understanding of the management of SSRS in these five countries, in order to recommend improvements in management schemes and to establish whether the application of common disposal criteria would be advantageous.

This report is structured in the same way as report EUR19842.

In general, the management and regulation of SSRS in the five countries is, in view of the particular situation in the different countries, being performed in an acceptable manner. Proposed improvements for management are included in the recommendations in the report. Implementation of these recommendations will serve to further improve the situation.

NUCLEAR SAFETY AND THE ENVIRONMENT

Fifth Situation Report - Radioactive Waste Management in the Enlarged European Union

Report EUR 20653 EN (c. 1200K) February 2003 

This is the fifth in the series of reports on radioactive waste management in the European Union (EU). It presents, in the form of tables, the status in current EU Member States and (for the first time) in Candidate Countries of Central and Eastern Europe at the end of the year 2000. The previous situation report was published in January 1999 (annex to COM(98)799, refer to: Legislation - Commission Communications) and contained an in-depth evaluation of the situation and prospects for radioactive waste management in the Community, including such topics as waste generation, financing, transport, research and social issues. The present report is an interim re-evaluation and concentrates on waste quantities at the end of the year 2000, though it also presents a summary of national strategies and other pertinent information. The report shows that production of waste continues to decline as a result of waste minimisation practices in the low-level categories. The report also shows the quantities of waste (by country and by category) already disposed of (of for which a national disposal route is available) and the quantities of waste in interim storage pending the availability of a disposal route. Most information and data have been supplied by the Member States.

NUCLEAR SAFETY AND THE ENVIRONMENT

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

Report EUR 20311 EN (1349K) Published in 2002

The present project was aimed at providing: a description of the current status of nuclear safety practices during planned outages at nuclear power plants followed in Europe; the criteria for the safety analysis of future reactors at the design stage; proposing a set of recommendations on good practices and criteria leading to the improvement of nuclear safety during those conditions.

The work was organised in 3 phases: Collecting data on current practices; Analysis of questionnaire answers and drawing up of safety good practices references and recommendations; Collecting relevant ideas related to the future reactors at design stage (European Pressurised Water Reactor, European Passive Plant project, European Utilities Requirements and Utilities Requirement Document project).

The key element of the performed work was the detailed questionnaire, based on bibliographical review, expert experience and outage practices available in the working team. Different safety areas and activities were covered: outage context; nuclear safety; outage strategy, organisation and control; operating feedback; use of Probabilistic Safety Assessment.

The questionnaire was answered by 12 European nuclear power plants, representing 9 different European countries and three different types of reactors (Pressurised Water Reactor, Boiling Water Reactor and Water Water Energy Reactor).

Conclusions were drawn under the following headers:

• Organisational survey and generalities
• Organisational effectiveness
• Quality of maintenance
• Quality of operation
• Engineering support, management of modification
• Specific aspects

Each analysed subject includes the following topics:

• Questions background with a summary and the aim of the questions.
• Current status, that describes common practices, as derived from the answers to the questionnaire, and some examples of good specific practices.
• Identified good practices.

NUCLEAR SAFETY AND THE ENVIRONMENT

Remediation of the low-level radioactive waste tailing pond at Kowary, Poland

Report EUR 20312 EN Published in March 2002
cover page (51K)
main report (562K)
enclosure 6 (159K)
enclosure 8 (234K)
enclosure 9 (118K)

The last remaining uranium mining tailing pond in Poland, situated at Kowary, was the subject of the "Kowary Tailing Pond Remediation Programme" financed by Polish public bodies (70%) and by the European Commission (30%) within the framework of its programme of co-operation on radioactive waste issues with candidate countries. The EC-part of the project comprised investigations of the site, project management duties and large-scale civil works following the initial remediation planning performed by the Wroclaw University of Technology (WUT) in 1998-2000. The EC-part was contracted to G.E.O.S. Freiberg Ingenieurgesellschaft mbH following an Open Call for Tender launched by the European Commission in 1999. The following general tasks were performed in close co-operation with WUT, with the construction works subcontracted to local companies:

- review of General Remediation Plan (GRP),
- technical design of the pond cover,
- construction work: internal drainage system, pond cover and site reclamation.

The following aims of remediation were defined:

- minimise the detrimental impact of the tailing pond on the environment,
- provide long-term stability of the slopes surrounding the pond,
- ensure the remediated site is in harmony with the surrounding natural scenery.

Based on the experience gathered in similar projects, which had been running under PHARE or which belonged to the WISMUT-remediation programme in Germany, cost efficient remediation solutions were designed in close co-operation with all involved parties. They were delineated in the detailed planning documents approved in the overall remediation programme managed by WUT. The planned remediation works were prepared and performed successfully according to Polish law and in agreement with the competent local authorities. The aims of remediation were met. Some additional tasks have been recommended in zones adjacent to the tailing pond remediation area.

NUCLEAR SAFETY AND THE ENVIRONMENT

Study on the Development of Methodology for Cost Calculations and Financial Planning of
Decommissioning Operations

Report EUR 20165 EN Published in December 2001
overall approach (126K)
task 1 (491K)
task 2 (926K)
task 3 (617K)
task 4 (76K)

In the current frame of the opening of the European electricity market and of the enlargement process of the European Union, the financial assessment of decommissioning operations has become an important decision driver. Thus there is a crucial need for reliable cost calculation methods and strategies for financial planning of dismantling operations. As to make possible strategy comparisons, these methods have to rely on a transparent basis. They also have to be flexible enough to enable the end-users to adapt it to their own needs.

The main objective of the study was to develop a reliable and transparent methodology for cost assessment and financial planning that is sufficiently precise but without requiring long and in depth investigations and studies. This methodology mainly contains:

• Calculation methods and algorithms for the elaboration of costs items making up the whole decommissioning cost

• Estimated or standard values for the parameters and for the cost factors to be used in the above-mentioned algorithms

• Financial mechanism to be applied as to establish a financial planning

The provided methodology intends to be a generic one that can be adapted to the specific needs of all interested third parties. In order to be of use by a wide variety of organisations, it contains a comprehensive set of values collected on the basis of a world-wide experience.

The work programme consisted of 4 tasks, each reported separately:

Task 1 : Elaboration of the methodology for cost calculation
Task 2 : Collection of the data
Task 3 : Description of financial mechanisms
Task 4 : Drawing up of handbook

NUCLEAR SAFETY AND THE ENVIRONMENT

RIBA PROJECT - Risk-Informed approach for In-Service Inspection of Nuclear Power Plant Components

Report EUR 20164 EN Published in December 2001
summary report (135K)
task 1 (733K)
task 2 (1741K)
task 3 (1614K)

The need for a European review of a Risk-Informed Approach for In-Service Inspection of Nuclear Power Plant Components (RIBA) was identified in 1998. This was as a priority item in the programme of activities conducted in the framework of the Council Resolutions of 22 July 1975 and of 18 June 1992 on the Technological Problems of Nuclear Safety.

The RIBA Project was established in November 1999 as a 24-month Study Contract funded by the European Commission within the frame of the former DG XI WGCS (Working Group on Codes and Standards). The Study Contract was subsequently managed for the EC by DG TREN. The participants in RIBA were Serco Assurance (project co-ordinator), Ringhals AB, EDF, Tecnatom SA and Westinghouse Electric Europe.

The work is presented in a summary report with the detailed results contained in three companion reports as follows:

• Summary report: main conclusions and recommendations

• Task 1 Report: Review of Existing Risk-Informed Methodologies

• Task 2 Report: A Comparative Study of Risk-Informed In-Service Inspection Applications

• Task 3 Report: Conclusions and Recommendations for Risk-Informed In-Service Inspection Methodology Applied to Nuclear Power Plants in Europe

NUCLEAR SAFETY AND THE ENVIRONMENT

TSO Study Project on Development of a Common Safety Approach in the EU for Large Evolutionary Pressurised Water Reactors

Report EUR 20163 EN (1175K) Published in October 2001

In pursuance of the objectives of the Council's Resolutions of 1975 and 1992 on the technological issues of nuclear safety, the European Commission (EC) is seeking to promote a sustained joint in-depth study on possible significant future nuclear power reactor safety cases. To that end the EC decided to support financially a study by the grouping of the European Union's Technical Safety Organisations (TSOG).

The general objective of the study programme was to promote, through a collaboration of European Union Technical Safety Organisations (TSOs), common views on technical safety issues related to large evolutionary PWRs in Europe, which could be ready for operation during the next decade. AVN (Belgium) (Technical project leader), AEA Technology (United Kingdom), ANPA (Italy) CIEMAT (Spain), GRS (Germany), IPSN (France), were the TSOs participating in the study which was co-ordinated by RISKAUDIT.

The study focused notably on the EPR project initiated by the French and German utilities and vendors. It also considered relevant projects, even of plants of different size, developed outside the European Union in order to provide elements important for the safety characterisation and which could contribute to the credibility and confidence of EPR. It is expected that this study will constitute a significant step towards the development of a common safety approach in EU countries.

The study constitutes an important step forward in the development of a common approach of the TSOs to the safety of advanced evolutionary pressurised water reactors. This goal was mainly achieved by an in-depth analysis of the key safety issues, taking into account new developments in the national technical safety objectives and in the EPR design. For this reason the Commission has decided to publish at least the present summary report containing the main outcomes of the TSO study. Confidentiality considerations unfortunately prevent the open publication of the full series of reports.

NUCLEAR SAFETY AND THE ENVIRONMENT

Main Characteristics of Nuclear Power Plants in the European Union and Candidate Countries

Report EUR 20056 EN (5193K!!) Published in October 2001

(see EUR 20055) The main objective was to advise the EC on future challenges and opportunities in terms of enhanced co-operation in the area of nuclear safety and harmonisation of safety requirements and practices in an enlarged European Union

Part of this activity was to provide a summary of the plant characteristics of the operating civil nuclear power plants in the EU Member and Candidate Countries. The present report provides these data in three formats:

• A reference table which lists the main characteristics of nuclear power-producing reactors operating in the European Union (EU) and Candidate Countries, as at 31 December 1999. Also included, for the sake of completeness, are data for reactors in the former Soviet Union, such as Russia and the Ukraine. The format adopted follows that in the annual International Atomic Energy Agency (IAEA) reference data report 'Nuclear Power Reactors of the World', from which much of the information was taken;

• A summary table indicating totals by reactor type covering Western and Eastern Europe separately, again from IAEA sources, giving number of plant, total generating capacity and total years in operation. A list of the abbreviations for different reactor types is also provided;

• A set of detailed data sheets giving main plant characteristics for different reactor types ordered by country. These data sheets cover reactors in EU Member and Candidate Countries only.

Details are provided on the origin of the data where these are available, so that further information may be obtained if desired and where permitted by commercial and/or proprietary considerations.

NUCLEAR SAFETY AND THE ENVIRONMENT

25 Years of Community Activities towards Harmonisation of Nuclear Safety Criteria and Requirements
- Achievements and Prospects

Report EUR 20055 EN (1740K) Published in October 2001

The main objective was: To advise the EC on future challenges and opportunities in terms of enhanced co-operation in the area of nuclear safety and harmonisation of safety requirements and practices in an enlarged European Union.

The activities were divided into 3 sub-tasks as follows:

Part A: to prepare an analysis, synthesis and assessment of the main achievements from Community activities related to the Resolutions on the "technological problems of nuclear safety of 1975 and 1992, with due consideration for related research activities;

Part B: to prepare an overview of safety philosophies and practices in EU Member States, taking account of their specific national practices in terms of legal framework, type and age of operating nuclear reactors;

Part C: to provide elements of a strategy for future activities in the frame of the Council Resolutions, with particular attention to the context of enlargement of the EU.

NUCLEAR SAFETY AND THE ENVIRONMENT

Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

Report EUR 20054 EN Published in December 2001
cover page (22K)
main report (183K)
Annex I Safety Assessment (347K)
Annex I Safety Assessment - App. A (71K)
Annex I Safety Assessment - App. B (8K)
Annex I Safety Assessment - App. C (1445K)
Annex I Safety Assessment - App. D (1585K)
Annex I Safety Assessment - App. E (157K)
Annex II EIA (117K)
Annex III Waste Acceptance Criteria (53K)
Annex IV (130K)
Annex V (10K)
Annex VI (5353K!)

The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities:

• Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular

• Development of the short and long-term safety analysis of the Baldone repository, including:
  - The planned increasing of capacity for disposal and long term storage
  - The radiological analysis for the post-closure period

• Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components

• Proposal of recommendations for future updating of radioactive waste acceptance criteria

• Proposal of recommendations for safety upgrades to the facility.

The work programme has been developed in phases and main tasks as follows:

• Phase 0: Project inception

• Phase 1: Establishment of current status, plans and practices
  - Task 1.1: Legislation, regulation and standards
  - Task 1.2: Radioactive waste management
  - Task 1.3: Waste acceptance criteria

• Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements

The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterisation requirements), the design of an engineered cap and strategies for capping.

NUCLEAR SAFETY AND THE ENVIRONMENT

Assessment of the Proposed Design of a New Spent Sealed Radioactive Sources Storage Facility at Novi Han

Report EUR 20053 EN (1193K) Published in September 2001

The NOVI HAN radioactive waste repository (NHRWR) in Bulgaria, built according to a Soviet design, was commissioned in 1964. The State Committee on the Use of Atomic Energy for Peaceful Purposes (CUAEPP) temporarily stopped operations at the repository from October 1994 until measures for improvement of the facility are undertaken. Since 1994, the Spent Sealed Radioactive Sources (SSRS) have been temporarily stored at the facilities at IRT-2000 research reactor of the Bulgarian Academy of Sciences (BAS) in Sofia.

In view of the importance of the radiological risks associated with the present management of the SSRS in Bulgaria, the present study contract has been launched to critically review the proposal to provide a new interim storage facility for SSRS at NHRWR.

A comprehensive critical review was performed of the feasibility study for the construction of a new SSRS facility at Novi Han, carried out by the local consultant engineering company (EQE), and detailed recommendations were made concerning the proposed new development at the site.

The authors think that new concepts and procedures in the management of all categories of SSRS including smoke detectors have to be introduced, taking into account the regulatory framework and the inventories of existing and anticipated SSRS. This should be the basis for the technical specification of the new facilities for conditioning and storage of spent sealed radioactive sources (not only SHARS).

NUCLEAR SAFETY AND THE ENVIRONMENT

Feasibility study of a waste assay system and the possibility of volume reduction at the Püspökszilágy RWTDF

Report EUR 20052 EN (3683K!) Published in May 2001

A review of the types and activities of the waste emplaced at the Püspökszilágy Radioactive Waste Treatment and Disposal Facility (RWTDF) was performed on the basis of the existing operational data. This provided a breakdown of all important parameters of the wastes as well as of the disposal conditions for each disposal unit.

Prior to the detailed review, the behaviour of the compacted wastes, simulating those in the repository, was tested with a view to determine the efficiency of a further supercompaction. Based on the evaluation of market data, the cost of purchasing or renting a supercompactor unit and the resulting unit costs were calculated. A detailed review of the free release strategies and the available equipment was prepared.

To provide an immediate remedy to the shortage of disposal volume, it is suggested to retrieve the old Institutional wastes and the sealed radioactive sources, and use the existing free space for further waste disposal. As an alternative, the use of residual free space in the vaults for further disposal, without waste recovery, is also reviewed.

NUCLEAR SAFETY AND THE ENVIRONMENT

Environmental Impact Assessment for the Decommissioning of Nuclear Installations

Report EUR 20051 (3 Volumes) Published in June 2001
cover page
Vol. 1 (1658K)
Vol. 2 (1060K)
Vol. 3 (918K)
Fig.2-1 (184K)

This Report presents the results of a study concerned with Environmental Impact Assessment (EIA) for the decommissioning of nuclear installations in European Union Member States and in the Applicant Countries in Central and Eastern Europe. The study, undertaken for the Environment Directorate General of the European Commission, took place between January 2000 and March 2001.

The study presents an analysis of the current situation in the European Union and in the Applicant Countries, and develops guidance for applying the relevant Directives for EIA to the specific issue of decommissioning nuclear installations although there is also scope for application to other large or controversial projects.

The first part of the report (Volume 1) describes the current situation in the EU Member States and Applicant Countries. On the basis of this status, the guidance presented in Volume 2 was developed. Draft versions of these volumes were reviewed by an independent review panel and were then subjected to detailed discussion and debate at a Workshop held in Brussels in January 2001. The Workshop was attended by more than 60 representatives of the nuclear industry, nuclear regulators, public interest groups and EIA experts. Some minor changes were made following the Workshop, a record of which can be found in Volume 3.

NUCLEAR SAFETY AND THE ENVIRONMENT

Review and Analysis of Solid Long-lived and High Level Radioactive Waste arising at the Chernobyl Nuclear Power Plant and the Restricted Zone

Report EUR 19897 EN (9399K!!) Published in 2001

The study characterised potential waste arisings in the Exclusion Zone surrounding the Chernobyl Nuclear Power Plant. Studied sites include the Industrial Zone outside the Sarcophagus, three engineered disposal sites (the so-called PZRO), non-engineered near surface trench dumps (PVLRO), contaminated soil and sites of ‘unauthorised’ disposal within the Exclusion Zone.

Analysis of the previous methodology used for waste characterisation and inventory estimates identified a number of errors. A new database was established, which contains the most up-to date information on radwaste in the Exclusion Zone. Based on the analysis of the available information and potential radiological consequences, a judgement was taken regarding the priority of waste retrieval. In a number of cases it is necessary to carry out risk assessment to ensure that in-situ disposal would satisfy the Ukrainian regulations.

Assessments of waste stream volumes for subsequent incineration, encapsulation, storage and disposal in the planned near-surface facilities have been made. It is judged that throughput and capacity of the planned waste management facilities specified by OSAT is, in general, appropriate to the likely waste arisings.

A New Approach to Performance Assessment of Barriers in a Repository

Executive Summary in English (55K)
Main report in German (5052K!)
Technical Annex 1 in German (172K)
Technical Annex 2 in German (174K)
Technical Annex 3 in German (998K)

Abstract:

Multi-barrier systems are accepted as the basic approach for long term environmental safe isolation of radioactive waste in geological repositories. Assessing the performance of natural and engineered barriers is one of the major difficulties in producing evidence of environmental safety for any radioactive waste disposal facility, due to the enormous complexity of scenarios and uncertainties to be considered. This report outlines a new methodological approach originally developed basically for a repository in salt, but that can be transferred with minor modifications to any other host rock formation. The approach is based on the integration of following elements:

1. Implementation of a simple method and efficient criteria to assess and prove the tightness of geological and engineered barriers;

2. Using the method of Partial Safety Factors in order to assess barrier performance at certain reasonable level of confidence;

3. Integration of a diverse geochemical barrier in the near field of waste emplacement limiting systematically the radiological consequences from any radionuclide release in safety investigations; and

4. Risk based approach for the assessment of radionuclide releases.

Indicative calculations performed with extremely conservative assumptions allow to exclude any radiological health consequences from a HLW repository in salt to a reference person with a safety level of 99,9999 % per year.

NUCLEAR SAFETY AND THE ENVIRONMENT

Support in the development of Regulatory Procedures for licensing Lepse Waste Management Operations

Report EUR 19896 EN (760K) May 2001

This report describes a project intended to assist Gosatomnadzor of Russia develop a set of documents defining the regulatory requirements for information to be submitted to Gosatomnadzor in support of any application for a licence relating to the removal of spent nuclear fuel from the depot ship Lepse. The project resulted in the development of three regulatory documents covering the documentation required in support of a licence application, the requirements for quality assurance arrangements and the safety analysis report.

The working method adopted involved staged development of draft material and review at workshops involving a wide variety of relevant Russian and western organizations. The input and output of the workshops was fully documented to provide an audit trail for the document development and the rationale for what has been included and what is excluded and why.

The availability of the regulatory documents in English should significantly assist in the use of the documents by western partners in the actual industrial project.

Important experience and information was exchanged among participants in the project. The developing understanding is an important element in providing confidence, from a western perspective, that appropriate regulatory supervision can be applied to industrial projects supported by organizations such as the European Commission and national agencies.

The same working methods could be used in the next phase of Lepse regulatory support, i.e., support in development of the procedures for the regulatory review of licence applications, and, subsequently, support in the application of the regulatory inspection process to ensure licence conditions are being complied with. Similarly, these working methods could be used in providing regulatory support for nuclear and radiation safety related to other industrial projects involving radioactive waste management.

The participants in this sub-project described in this report were Norwegian Radiation Protection Authority supported by the Gosatomnadzor Scientific and Engineering Centre (SEC NRS) and western experts from Babcock Rosyth Defence Ltd. (BRDL) and QuantiSci Ltd with the participation in discussions of other experts from Swedish International Project Nuclear Safety (SIP) and the Swedish Radiation Protection Institute (SSI). In addition, there was involvement of other Russian industry and authority organizations, as well as representation from the International Atomic Energy Agency.

NUCLEAR SAFETY AND THE ENVIRONMENT

Nuclear Safety in Central and Eastern Europe April 2001

Report EUR 19895 EN (148K)
Annex 1 (Performance Evaluation Guide) (256K)
Annex 2 (desk-top study - Bulgaria) (702K)
Annex 3 (desk-top study - Czech Rep.) (1175K)
Annex 4 (desk-top study - Hungary) (665K)
Annex 5 (desk-top study - Lithuania) (400K)
Annex 6 (desk-top study - Romania) (337K)
Annex 7 (desk-top study - Slovakia) (553K)
Annex 8 (desk-top study - Slovenia) (682K)
Annex 9-1 (introduction for NIS) (21K)
Annex 9-2 (desk-top study - Armenia) (172K)
Annex 9-3 (desk-top study - Kazakhstan) (129K)
Annex 9-4 (desk-top study - Russian Federation) (642K)
Annex 9-5 (desk-top study - Ukraine) (415K)
Annex 10 (reference list) (477K)

Nuclear safety is one of the critical issues with respect to the enlargement of the European Union towards the countries of Central and Eastern Europe. In the context of the enlargement process, the European Commission's overall strategy on nuclear safety matters has been to bring the general standard of nuclear safety in the pre-accession countries up to a level that would be comparable to the safety levels in the countries of the European Union.

In this context, the primary objective of the project was to develop a common format and general guidance for the evaluation of the current nuclear safety status in countries that operate commercial nuclear power plants. Therefore, one of the project team's first undertakings was to develop an approach that would allow for a consistent and comprehensive overview of the nuclear safety status in the CEEC, enabling an equal treatment of the countries to be evaluated. Such an approach, which did not exist, should also ensure identification of the most important safety issues of the individual nuclear power plants. The efforts resulted in the development of the "Performance Evaluation Guide", which focuses on important nuclear safety issues such as plant design and operation, the practice of performing safety assessments, and nuclear legislation and regulation, in particular the role of the national regulatory body.

Another important aspect of the project was the validation of the Performance Evaluation Guide (PEG) by performing a preliminary evaluation of nuclear safety in the CEEC, namely in Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. The nuclear safety evaluation of each country was performed as a desktop exercise, using solely available documents that had been prepared by various Western institutions and the countries themselves. Therefore, the evaluation is only of a preliminary nature. The project did not intend to re-assess nuclear safety, but to focus on a comprehensive summary of the current status of nuclear safety in the applicant countries, addressing also the impact of recently concluded or ongoing plant modernisation and safety upgrading programmes.

Besides the CEEC, the project includes an overview on the status of nuclear safety in the Newly Independent States (NIS) that operate nuclear power plants (Russian Federation, Ukraine, Armenia and Kazakstan), though on a more general level. As of today, a comprehensive overview on nuclear safety in the NIS does not exist and therefore this work can be considered as an important initiative in view of more detailed investigations that might take place in the future.

The project findings and results are aimed at contributing to the European Commission's opinion on the nuclear safety status in the pre-accession countries. In addition, the exercise was aimed at supporting the decision-making process of the European Commission with respect to the focus, formulation and preparation of future assistance and co-operation projects for the Central and Eastern European region to improve nuclear safety in these countries.

NUCLEAR SAFETY AND THE ENVIRONMENT

Characterisation of Radioactive Waste located at "Shelter" Industrial Site

Report EUR 19844 EN (3896K) April 2001

As a result of the accident at the unit 4 reactor at the Chernobyl Nuclear Power Plant on the 26 April 1986 there was widespread radioactive contamination of the surrounding area. The area immediately surrounding Unit 4, referred to as the Industrial Site, was very heavily contaminated with fuel and core debris ejected from the reactor. Immediate action was undertaken to reduce the local radiation hazard and mitigate the potential of "secondary contamination" of the environment. This action involved (a) the removal and collection of fuel fragments (b) removal of the top layer of soil around unit 4 and (c) preparation of a new surface over the Industrial Site. This new surface is referred to colloquially as the Technogenic Layer.

This report provides an overview of a project undertaken for DG-Environment of European Commission by a Consortium consisting of SGN (France) and AEA Technology (UK) working in collaboration with the Organisation, "National Academy of Sciences of Ukraine; the Interdisciplinary Scientific and Technical Centre ‘Shelter’".

The project consisted of 3 Phases and a total of 14 Tasks. The main purpose of Phase 1 was to review previous work and available information and data on the contamination of the Industrial Site, construction of the Technogenic Layer, Buttress and Pioneer Walls. Phase 2 was directed at additional measurements being carried out on existing boreholes and core samples to improve and/or substantiate existing information and data. Estimation of likely radioactive waste arisings, recovery procedures and a generalised strategy with indicative costs for the management of the waste was also covered by Phase 2. In Phase 3 new boreholes (3 off) were drilled and subsequently investigated. The justification behind Phase 3 was the desire/need to obtain more reliable information on the so-called high-active waste buried in the Industrial Site.

NUCLEAR SAFETY AND THE ENVIRONMENT

Safe management of NPP ageing in the European Union

Report EUR 19843 EN (3165K) May 2001

The objectives of the study covered by this report consist of providing recommendations for the development of a methodology to monitor, control and anticipate the ageing of Nuclear Islands, in order to maintain their level of safety during the whole NPP life cycle.

This is obtained through a synthesis of the potential ageing mechanisms, their potential effects and the available identification and mitigation methods, and an evaluation of the existing ageing management practices in Belgium, France and Spain, using international recommendations as guidance documents.

The aspects covered include, in particular, classification of component priorities, identification of degradation phenomena, surveillance methods and preventive maintenance and repair / replacement programs.

This synthesis comparison work is the basis for the recommendations issued at the end of the study.

NUCLEAR SAFETY AND THE ENVIRONMENT

Management of Spent Sealed Radioactive Sources in Central and Eastern Europe
(Czech Rep., Estonia, Hungary, Poland & Slovenia)

Report EUR 19842 EN (3335K) April 2001

This study has been performed to consider the situation relating to the regulation and management of spent sealed radioactive sources (SSRS) in five central and Eastern European (C&EE) countries currently being considered for admission to the EU: the Czech Republic, Estonia, Hungary, Poland and Slovenia. The general aim of this study has been to acquire a thorough understanding of the management of SSRS in these five countries, in order to recommend improvements in management schemes and to establish whether the application of common disposal criteria would be advantageous.

This report is structured in the following manner; following the Introduction (Section 1), there is description of current and proposed regulatory requirements in the EU, together with a summarised comparison of the regulatory systems in C&EE countries with EU standards in Section 2. Sections 3 to 7 are dedicated to the situation in each of the five countries. Each of these sections is similarly sub-divided to enable country-by-country and topic-by-topic comparison. In each of Sections 3 to 7 there is an overview, description of the sealed source inventory, regulations, current management practices, retrieval of unregistered SSRS, conclusions and a description of possible future technical assistance projects. Section 8 brings together a summary of the situation in each country, with conclusions and both country-specific and generic recommendations.

A common concern in the five countries and also in existing EU member states is the problem of accidental inclusion of SSRS in consignments of scrap-metal. The detection of radioactive material at entrances to scrap metal facilities and at national borders has therefore received considerable attention in recent years. Practical issues regarding the detection of SSRS in scrap metal are described in Appendix A.

None of the five countries considered in this report have any plans to develop regional disposal facilities and no specific common disposal criteria have been developed. All the countries are, however, proceeding with their waste management plans, taking account (to varying degrees) of 'high level' International Standards and practices relating to acceptable dose uptakes, environmental impact, etc. Such a situation is similar to that relating to the EU member states, who also comply with EC Directives, IAEA Safety Series documents, etc., but have not developed specific prescriptive disposal criteria for universal application across all Member States.

The management and regulation of SSRS in the five countries is, in general, performed well and in a similar manner to a number of current EU member states. Many of the proposed improvements for waste management are included in the recommendations in Sections 8.3 and 8.4. Implementation of these recommendations will serve to further improve the situation and provide a long-term safe environment for the management of SSRS.

See also report EUR20654 dealing with the other five C&EE candidate countries.

NUCLEAR SAFETY AND THE ENVIRONMENT

Determination of the in-containment source term for a Large-Break Loss of Coolant Accident

Report EUR 19841 EN (4083K) April 2001

This is the report of a project that focused on one of the most important design basis accidents: the Large Break Loss Of Coolant Accident (LBLOCA) (for pressurised water reactors). The first step in the calculation of the radiological consequences of this accident is the determination of the source term inside the containment. This work deals with this part of the calculation of the LBLOCA radiological consequences for which a previous benchmark (1988) has shown wide variations in the licensing practices adopted by European countries.

The calculation of this source term may naturally be split in several steps (see chapter II), corresponding to several physical stages in the release of fission products: fraction of core failure, release from the damaged fuel, airborne part of the release and the release into the reactor coolant system and the sumps, chemical behaviour of iodine in the aqueous and gas phases, natural and spray removal in the containment atmosphere. A chapter is devoted to each of these topics. In addition, two other chapters deal with the basic assumptions to define the accidental sequence and the nuclides to be considered when computing doses associated with the LBLOCA.

The report describes where there is agreement between the partner organisations and where there are still differences in approach. For example, there is agreement concerning the percentage of failed fuel which could be used in future licensing assessments (however this subject is still under discussion in France, a lower value is thinkable). For existing plants, AVN (Belgium) wishes to keep the initial licensing assumptions. For the release from damaged fuel, there is not complete agreement: AVN (Belgium) wishes to maintain its present approach. IPSN (France), GRS (Germany) and NNC (UK) prefer to use their own methodologies that result in slightly different values to the proposed values for a common position. There are presently no recommendations of the release of fuel particulates. An agreement has been reached on the fact that no retention in the RCS is to be accounted for, and on the release part going to the containment atmosphere. For the retention in the containment (chemistry of iodine and spray/natural removal of iodine and aerosols), the partners agree with the recommendation to use a code allowing an accurate modelling of the phenomena. However, such codes may not be available for everybody or are still subject to some validation problems. In that case, simple conservative models are proposed. The problem of organic iodine formation is still a controversial subject but a value of 0.2% of the release to the containment atmosphere seems to be acceptable.

NUCLEAR SAFETY AND THE ENVIRONMENT

Proceedings of the workshop on restoration strategies of contaminated territories resulting from the Chernobyl accident

Report EUR 18193 EN (2969K) Published in November 2000

On 29/30 June 1998 a workshop took place in Brussels on remediation strategies for the contaminated territories that have resulted from the Chernobyl accident.

The goal of the workshop was to get an objective understanding of the problems still posed by the existence of contaminated territories. To this end, a number of Western and CIS decision-makers in charge of remediation activities - sometimes at the Minister level, participated in the workshop. Some Members of the European Parliament also contributed to the discussions.

The workshop raised several important issues. The most important dealt with the consensus between the participants that co-operation between CIS and Western Countries on the identification of specific criteria for defining contaminated territories would be highly desirable. These criteria are enormously important to the CIS countries for political, social and economic reasons. They help to determine which category of people living in contaminated territories should receive some financial compensation for the risks taken and influence when this compensation should stop being paid and if people should or could be "re-located". Given the need of the CIS countries to start reducing the large amounts of money that they are paying out in compensation, they would like to get EU endorsement of the criteria to be applied. Therefore, the EU has a major role to play in assisting the CIS countries in this area.

But even if criteria for rehabilitation of contaminated territories can be harmonised between the EU and the CIS countries, this does not mean that the population living in these territories will accept them. Therefore, a number of social aspects must be resolved before a contaminated territory can become fully rehabilitated.

Another important outcome of the workshop was the identification of potential topics that could be proposed for international collaboration. One of these projects was supported by DG-Environment and dealt with the dissemination of the ETHOS research project, while the other was focussed on the completion of cost-benefit analysis for optimising remediation strategies. Some of the other topics were addressed in the research programme of the EU on nuclear fission and generic research on radiological protection that have been launched within the activities of the 5^th Framework Programme for Research and Technological Development (Preserving the Ecosystem).

NUCLEAR SAFETY AND THE ENVIRONMENT

Common position of European nuclear regulators for the licensing of safety critical software for nuclear reactors

Report EUR 19265 EN (307K) Published in May 2000

It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the assessment of these factors. An undesirable consequence of this situation is that the licensing approaches taken by nuclear safety authorities and by technical support organisations are determined independently and with only limited informal technical co-ordination and exchanges. It is notable that several software implementations of nuclear safety systems have been marred by costly delays caused by difficulties in co-ordinating the development and the qualification process.

This report contains the conclusions reached by a task force convened under the Nuclear Regulator Working Group (NRWG) and of the Reactor Safety Working Group (RSWG) of the European Commission Directorate General for Environment. In a first stage off investigation, the task force identified what were believed to be, from a regulatory viewpoint, some of the most important and practical issue areas raised by the licensing of software important to safety. In the second stage of the investigation, for each issue area, the task force strove for and reached: (1) a Common Position on the basis for licensing and minimal evidence which should be sought, (2) consensus on best design and licensing Recommended Practices, and (3) agreement on certain alternatives which could be acceptable.

NUCLEAR SAFETY AND THE ENVIRONMENT

Natural radionuclide concentrations in materials processed in the chemical industry and the related radiological impact

Report EUR 19264 EN (326K) Published in August 2000

The subject of this study is the potential radiation risk that can result from the presence of naturally occurring radioactive materials in raw materials usually considered as not radioactive and used in the manufacturing of chemical products.

In a review concerning such raw materials (phosphate ores, Zirconium, various metal ores) basic information on major companies involved, quantities produced, range of radionuclide concentration, chemical processes, products and by-products has been compiled for EU member states.

Typical radiation exposure scenarios such as radiation exposure of staff due to direct radiation, dust inhalation and dumping of various materials as well as the exposure of the public due to dumping and use of products have been investigated. The results show that the inhalation of dust is the major source of dose uptake which may require limiting dust concentrations.

In a survey concerning the current legislation in the European Union and its member states the problems radon at workplaces, testing and remedying existing workplaces, controlled and supervised areas and protection against exposure from natural sources are discussed. Regarding the regulation and classification schemes identified and taking into consideration the exposure estimates derived, it can be concluded that the dust inhalation situation of staff should be carefully and specifically re-considered before any additional regulatory measures are taken.

NUCLEAR SAFETY AND THE ENVIRONMENT

Use of the existing buildings of the Püspökszilàgy radioactive waste treatment and disposal facility for temporary storage of radioactive wastes (Hungary)

Report EUR 19260 EN (452K) June 2000

The NATIONAL INSTITUTE FOR RADIOELEMENTS – IRE – in close collaboration with BELGATOM S.A. and TS ENERCON Kft have carried out a feasibility study for the conversion of an existing building of the Püspökszilágy Radioactive Waste Treatment and Disposal Facility into a centralised interim store for radioactive waste.

The first part of the study dealt with the assessment of the constraints project related to the regulatory requirements, to the physical state of the building and to the current operating procedures. According to this assessment and to the State of the Art in this field, a critical review of the potential designs under investigation was carried out.

All the aspects reviewed and analysed in the first part of the study were taken into account for defining functional specifications of a new basic design for the temporary storage. The conceptual building layout proposed by IRE and partners introduces new concepts in the operating procedure such as minimisation and segregation in order to reduce the waste volume. Both concepts involve enhancing the check on site by performing a stringent characterisation of waste drums on receipt.

The design suggested for an operation period of at least 10 years, could be used to store 840 LILW drums placed in racks. A cost estimate for the main items of investment and operating costs is presented.

NUCLEAR SAFETY AND THE ENVIRONMENT

Contact Expert Group: Working Group on Russian Strategy on Management of Radwaste & SNF

Report EUR 19263 EN (408K) June 2000

see also separate Executive Summary (57K) January 2001

NUCLEAR SAFETY AND THE ENVIRONMENT

European safety practices on the application of the Leak Before Break (LBB) concept

Report EUR 18549 EN (307K) Jan 2000

NUCLEAR SAFETY AND THE ENVIRONMENT

Current situation concerning radioactive waste management and restoration of contaminated territories in and around the Mayak site

Report EUR 18190 EN (nnnK) nnn 200n

NUCLEAR SAFETY AND THE ENVIRONMENT

Assessment of situation and disposal concepts for radioactive waste arisings from reprocessing operations in Chelyabinsk-65 (Mayak)

Report EUR 19262 EN (nnnK) nnn 200n

NUCLEAR SAFETY AND THE ENVIRONMENT

Preliminary study for an EIA for defuelling Russian submarines at Zvezdochka (NW Russia)

Report EUR 19261 EN (403K) March 2000

NUCLEAR SAFETY AND THE ENVIRONMENT

Report on the Magurele Radioactive Waste Treatment Plant (Romania)

Report EUR 19259 EN (249K) May 2000

BNFL Engineering Ltd (BE Ltd), working closely with the Romanian National Institute of Physics and Nuclear Engineering (IFIN-HH), have undertaken an investigation of the Magurele Radioactive Waste Treatment Plant (RWTP). The present report is the output from this investigation

In the short term the Magurele RWTP has sufficient capacity to process the routine forecast arisings. In the longer term, decommissioning of the Magurele research reactor could challenge the available capacity unless this is taken into account during planning.

Twenty-Four short-term improvements are recommended along with nine medium term improvements. Key short-term improvements relate to the radiation dose rates received by the operators of the plant. Currently they are receiving on average 20mSv per year. This dose will become the new statutory limit and as such improvements to control and reduce their dose are needed. The main improvements that would assist in this area are:

• Repair or replace evaporator instrumentation and steam pressure regulator.

• Repair or replace Vaqua Blast Unit

• Provision of alarmed dosimeters and change room monitoring equipment.

• Ensure adequate supply of operating spares especially glovebox gloves

• Review of operating and maintenance procedures

Improvements to industrial safety have also been identified which would assist in better operation of the facility.

NUCLEAR SAFETY AND THE ENVIRONMENT

Preliminary evaluation of spent fuel storage at Magurele Romania

Report EUR 19258 EN (413K) March 2000

This study provides information relating to spent fuel storage at the Institute of Nuclear Physics and Engineering (IFIN-HH) VVR-S research reactor site at Magurele near Bucharest in Romania. The fuel is currently stored in an at-reactor pond and in an away-from-reactor pond on the reactor site. The reactor at Magurele is currently shut down. The regulator has stated that it will not have a licence to decommission until alternative arrangements are made for the storage of its spent fuel.

A recent PHARE project (ref. PH4.01/94 – Regional Study of Soviet Designed Research Reactors) concluded that a deferral option of dry storage of the fuel would be the best short term policy, and that a detailed study of cask storage should be undertaken. However, there is a certain amount of preliminary information that needs to be obtained prior to such a study, and this report addresses this need. This report provides the best available information on the quantity and state of the fuel, the physical conditions around the Magurele site, and the current licensing position for spent fuel storage. The study has been carried out with the assistance of Romanian experts and a visit by the authors to discuss the situation with these experts, the Romanian nuclear regulator, and the plant management.

There are 152 EK-10 and 74 S-36 fuel assemblies on site, currently in wet storage ponds. There is evidence that some of this fuel is corroding. Any dry storage of the fuel would need to take into account the high seismicity of the area, the large range of ambient conditions and the relatively high water table. Details of these and other physical conditions have been obtained. Over the next year the regulators are planning on providing spent fuel requirements, but these are likely not to be overly prescriptive, and will be based on current IAEA guidance documents. Details such as the number of barriers needed to avoid fission product release are therefore unlikely to be prescribed provided overall safety requirements are met.

NUCLEAR SAFETY AND THE ENVIRONMENT

Comparative cost assessment of locally installed versus centralised facilities for radioactive wastes thermal treatment systems

Report EUR 19257 EN (279K) Year 2000

NUCLEAR SAFETY AND THE ENVIRONMENT

Fuel cladding failure criteria

Report EUR 19256 EN (1561K) Year 2000

NUCLEAR SAFETY AND THE ENVIRONMENT

Radiological impact due to wastes containing radionuclides from use and treatment of water

Report EUR 19255 EN (274K) Published in May 2000

All natural waters contain certain concentrations of naturally occurring radionuclides. With the required treatment of the water, some of the radionuclides are enriched in the waste (mainly filter sludge) and may cause a radiation risk to operating personnel and public during handling, transportation and disposal of this waste. The present report present the results of a survey performed concerning the use and treatment of

• general water (tap water),

• mineral water used in spas, and

• mineral water in the bottled water industry

in various countries of the European Union.

NUCLEAR SAFETY AND THE ENVIRONMENT

Managment of radioactive waste arising from medical establishments in the European Union
(proceedings of a workshop)

Report EUR 19254 EN (479K) Published in 2000

Concern has been expressed regarding management of radioactive waste in medical establishments. The importance of this subject is also reflected in the activities being supported by international organisations, like the IAEA, through the preparation of technical reports and recommendations.

In order to better understand how this kind of radioactive waste is currently managed in medical establishments in Member States (MS) of the European Union, the Directorate-General for Environment of the European Commission decided to launch a pilot study focussing on the situation existing in one Member State, namely Belgium. This study was awarded to the Belgian company BUGECO, represented by Mr. Jean Delhove, a highly recognised expert in this field. The study was completed in late 1998, and the report entitled "Management of radioactive waste in medical establishments" was published as EUR18861. The results of the study were then used as a background for exchanging information with the other MS on management of radioactive waste in medical establishments. In practice, each MS representative was asked to describe in writing the situation prevailing in his country according to a format complying with the structure of the pilot study.

Discussion of the different national situations took place within the framework of a workshop organised by DG-Environment on 16/17 February 1999 in Brussels. Representatives of 13 MS attended the workshop.

The workshop focused on the following four topics:

• presentation and discussion of the main results of the pilot survey conducted on the Belgian situation;

• brief description of the regulatory framework and the management practices applied in each of the represented MS (all the States of the Union, except Austria and Luxembourg), based on the structure of the pilot survey;

• discussion of all the results presented;

• identification of future lines of action, including those to be conducted at the EU level.

The proceedings of this workshop are the subject of the present report. A list of workshop participants is included.

NUCLEAR SAFETY AND THE ENVIRONMENT

Report on risk-informed in-service inspection and in-service testing

Report EUR 19153 EN (230K) Published in 1999/2000

Risk Informed In-Service Inspection (ISI) has been considered a priority area within the multi-annual programme (1996-2000) of the Nuclear Regulators Working Group (NRWG) of the European Commission.

During its meeting in November 1996 the NRWG decided to set up a Task Force (TF) to agree on the philosophy and principles governing risk-informed in-service inspection and testing of mechanical components of Nuclear Power Plants (NPPs), in order to maintain sufficient margins against leakages and failure, considering dose exposures to the public.

The TF was made up of representatives from AVN (Belgium), HSK (Switzerland), BfS (Germany), CSN (Spain), SKI (Sweden), STUK (Finland) and SONS (Czech Republic), the latter participating in some TF meetings only. The Chairman was the representative from SKI and the "Unit of Safety of Nuclear Installations" (DG XI.C.2) of the European Commission provided the TF with the corresponding Technical Secretary services.

The first task of the TF was the preparation of a questionnaire as a basis for the analysis of national and international activities in the field of risk-informed ISI. The questionnaire was sent to the members of the NRWG and responses from the participating countries and HSE (The United Kingdom) and SZW (The Netherlands) were received. Appendix A of this document contains a summary of these responses along with the corresponding analysis and conclusions.

The TF held six meetings and information on the progress was reported to the NRWG at its plenary sessions.

The present report represents the work product of the activities conducted by the TF. These activities were primarily focused on ISI and relevant aspects of In-Service Testing (IST) were also considered as appropriate. As a consequence of the rather limited insights in this field available in Europe the TF agreed early in its work that it would be premature to propose a document describing good practices. Instead the intention is to point out important factors to be considered in applying PSA results to ISI/IST.

A current practices document results from a review and inventory of current practices in different countries.

The documents published by the European Commission which relate to the implementation of the Council Resolutions of 22 July 1975 and 18 June 1992 on the Technological Problems on Nuclear Safety may fall into one of the following categories: current practices, good practices or consensus document.

Current practices document:

A current practices document results from a review and inventory of current practices in different countries.

Good practices document:

A good practices document presents one or more different approaches to reach safety objectives.

Consensus document:

A consensus document stresses the degree of harmonisation achieved between practices and sets out the consensus reached in NRWG.

The present document "Report on Risk-Informed In-Service Inspection and In-Service Testing" falls underthe category "Current Practices Document" according to the advice of the NRWG.

For more information use the contact request form (link in banner at top of page).

NUCLEAR SAFETY AND THE ENVIRONMENT

Management and disposal of disused sealed radioactive sources in the European Union

Report EUR 18186 EN (678K) Published in 2000

Sealed radiation sources are widely used in industry, medicine and research. All Member states of the European Union (EU) have been using sealed sources for many decades. Although most Member States have laid down a regulatory framework to control sealed sources, there are still a number of uncertainties concerning management of historical Ra-226 alpha sources, and the possibility of retrieving non-registered sources which may both represent high radiological risks for the population. In addition, management schemes and practices currently implemented in Member states may be somewhat conflicting and create problems for storage and disposal.

The general aim of the current study was to propose improved management schemes for disused sealed radioactive sources in the European Union, with the view to approximating policies of the Member States in this particular area.

The work has covered the following activities:

• Review of the different regulatory frameworks laid down in each of the Member states.

• Analysis of the management practices employed for the management of sealed sources throughout the European Union, with the view to identifying possible gaps and contradictions. Particular attention has been paid to management of historical Ra-226 sources.

• Generating proposals on how to retrieve non-registered disused sealed sources.

• Making recommendations for an improved management system at the European level with the view to develop EU policy actions in this area.

NUCLEAR SAFETY AND THE ENVIRONMENT

Schemes for financing radioactive waste storage and disposal (annex covering Central and East European Countries and workshop held 22/4/99)

Report EUR 18185 EN (Annex) (229K) Published in 2000

In an earlier study, information was assembled on financing schemes for radioactive waste management in operation in ten European Union countries and in the USA and Canada. The Final Report of that study was issued in October 1998 and published as EUR 18185. The study has now been extended to encompass ten of the so-called EU applicant countries of central and eastern Europe and this report forms an annex to the earlier report. There are wide variations between applicant countries, as there are between EU countries, in the scale of nuclear power generation and hence in the volumes of radioactive waste produced and the costs of managing them. In addition, however, there are major differences in the institutional arrangements and in the levels of development of financing arrangements for radioactive waste management. These differences, and their implications, are discussed in Section 11.

The majority of the information in this report was drawn from responses to a questionnaire identical to the one used for the earlier study. For consistency with the main report, it is grouped (Sections 2 to 10) for each country under the following headings:

• Overview of the institutional framework;

• Responsibilities of the Waste Management Organisation (WMO);

• Facilities in existence;

• Costs of waste management;

• Financial mechanism.

This report also contains the report of the Workshop held in Brussels in April 1999 to discuss the financing of radioactive waste storage and disposal in the light of the main study and this extension.

NUCLEAR SAFETY AND THE ENVIRONMENT

General overview of existing and future requirements for decommissioning nuclear facilities in Hungary, Poland, Slovenia, Slovak and Czech Republics

Report EUR 19155 EN (2607K!). Published in 1999

This report collects and summarises important data for the decommissioning of power plants and research reactors in the five following Eastern Countries: Czech and Slovak Republics, Hungary, Poland and Slovenia. These data mainly concern characteristics and inventory of radioactive materials expected to be produced from decommissioning of typical reactors operating in the five countries concerned.

Finally, basic requirements for decommissioning were established, analysed and reviewed with Local Experts from each of the countries concerned, in order to determine needs in the decommissioning field for the future.

NUCLEAR SAFETY AND THE ENVIRONMENT

Radioactive Waste Management in the Central and East European Countries

Full report EUR 19154 EN (375K) July 1999

Ten countries from Central and Eastern Europe have applied to join the European Union. However, the current level of safety in the nuclear sector in the majority of these applicant countries is not considered to be as high as that in the present EU Member States, and nuclear safety in general has therefore become one of the priority issues in the enlargement process. This report presents the current situation concerning the management of radioactive waste in the region, including such aspects as spent nuclear fuel from power and research reactors, quantities of radioactive waste from all sources, legislative reform and status of international assistance projects. Most data have been supplied by national sources. An executive summary reviews and interprets the information presented in the different country chapters. The report represents an important step in assessing the radioactive waste problems in these countries, and will help formulate future Commission strategy in this field during the enlargement process. The report also provides a benchmark by which to judge subsequent developments in this field.

NUCLEAR SAFETY AND THE ENVIRONMENT

Environmental Impact Assessments and Geological Repositories for Radioactive Waste

Report EUR 19152 EN Vol. 1 (487K), Vol. 2 (4357K!), Vol. 3 (442K) Vol. 4 (314K) October 1999

In the EU, an environmental impact assessment (EIA) is a necessary and important part of the development of a case for a geological repository for the long-term or final storage of radioactive waste. Under Directive 85/337/EEC, EIA is a mandatory requirement for all installations "solely designed for the permanent storage of the final disposal of radioactive waste." Under the amending Directive 97/11/EC, this requirement is extended to "installations designed … solely for the storage (planned for more then 10 years) of … radioactive waste in a different site than the production site."

Directive 85/337/EEC establishes basic principles and procedural requirements for EIA, allowing Member States considerable discretion in the details of implementation into domestic legislation, particularly as regards the specific impacts to be addressed an the nature of the public involvement in the assessment process.

The present report presents the findings of a 15-month study that examined the following aspects of EIA in relation to geological repositories for radioactive waste:

• National requirements for EIA (EU Member States, EU applicant countries, Canada, Switzerland, USA), and implementation of Directive 85/337/EEC and its amendment (97/11/EC) in the EU Member States and their adoption in EU applicant countries;
• involvement of the public in the EIA process;
• role of safety indicators and implications for EIA;
• an idealised EIA process in the context of the development of a waste disposal or long-lived storage facility;
• scope and content of an EIA report;
• impact on the EIA of retrievability of waste.

The report is in four separate volumes:

Volume 1 - Main Report
Volume 2 - Main Report - Appendices
Volume 3 - Central and East European Countries
Volume 4 - Workshop Report [workshop held in Brussels 20-21 April 1999]

A study of different quantities of waste types relative to radioactive wastes

Download report (109K) only available in electronic version

This report provides an overview of waste quantities in Europe with reference to the situations in France, Germany and the UK, with specific consideration of toxic wastes. The report is divided into three parts, one for each country. Information has been gathered on regulations, waste production, eventually location of residues and, when possible, indications on the various authorised treatment. The production and management of radioactive waste has already been extensively studied and reported on, and for this reason has not been included in the present study, though the intention is that comparisons should be drawn between the different waste categories.

 

NUCLEAR SAFETY AND THE ENVIRONMENT

Evaluation of the radiological and economic consequences of decommissioning particle accelerators

Report EUR 19151 EN (2403K!). Published in 1999

For biologic protection, accelerators are housed in thick-walled concrete buildings, which become slightly radioactive during the operational lifetime of the accelerator. At decommissioning, considerable amounts of low level (up to over 50 times the proposed clearance levels) solid radioactive waste have to be taken into account.

To assess the radiological and economic consequences of dismantling the EU accelerators, a selection of three representative cases was made, which were analysed in detail with respect to activation of concrete and metal parts. The results of this inventory (with 3-D mapping of the activity) were used for a full-scale waste volume and decommissioning cost evaluation for the three selected cases in different dismantling and decommissioning scenarios. It can be concluded that the total decommissioning costs could easily represent up to four times the purchase costs.

NUCLEAR SAFETY AND THE ENVIRONMENT

Radiological impact, through the drinking water pathway, of the nuclear tests performed on the Balapan test site, Kazakhstan

Report "EUR 17632 EN"  Published in 1999

In Kazakhstan, in the Balapan zone situated in the Semipalatinsk test site, over the years between 1965 and 1989, about 110 underground nuclear tests were performed. In most cases, these tests were performed at an average depth of between 450 and 600 metres. The aim of this study is to assess the radiological impact on the population which might result from the consumption of contaminated water extracted from wells and rivers and from the operation of the open-pit coal mine of Karajera situated in the close vicinity of the test site. The results show that beyond 1 km from the zone of boreholes used for the tests, the radiological consequences are minimal and, thereby, do not justify the implementation of underground remedial actions. However, the continued exploitation of the Karajera coal-mine might lead to significant radiation exposure of the workers if workings continue towards the south-east. Further investigations are needed to examine these uncertainties.

NUCLEAR SAFETY AND THE ENVIRONMENT

Feasibility study for an underground repository for long-lived non-heat-generating radioactive waste in Ukraine

Report "EUR 17631 EN"  Published in July 1999

The general objective of this study was to assess several disposal options for long-lived non-heat-generating radioactive waste in disused mines of Ukraine. The investigations fell into the following  fields: familiarisation with the Ukrainian regulatory framework concerning radioactive waste disposal, review of potential disused mines, selection of the most relevant sites for long-lived radioactive wastes, and preliminary performance assessment for the selected disused mines.

NUCLEAR SAFETY AND THE ENVIRONMENT

Management of sealed radioactive sources produced and sold in the Russian Federation

Report "EUR 18191 EN". Published in 1999

As a result of past and present civil nuclear activities (medicine, industry, research etc.), about 2 x 10⁶ Ci of spent sealed sources has been accumulated in the 16 RADON enterprises. Various manufacturers, e.g. MAYAK-Cheliabinsk, NIAR-Dimitrovgrad and FEI-Obninsk, are involved in the large-scale production of sealed radioactive sources.

In view of the importance of the radiological risks associated with the actual management of spent sealed radioactive sources in the Russian Federation, especially when these sources are not subject to any form of regulatory control (so-called non-registered sources), the present study contract has been launched to examine the regulations laid down by the Russian Authorities as well as the various management practices used to improve the safety level at a reasonable cost.

This report provides a description and an analysis of the situation in Russia regarding the management of sealed radioactive sources from fabrication to final waste disposal.

The object of the study is to establish the basis for a comparison between the situation and practice in Russia and that existing in the European Union with the purpose of identifying possible improvements which could become the subject of future collaboration projects.

NUCLEAR SAFETY AND THE ENVIRONMENT

Evaluation of the radiological impact resulting from injection operations in Tomsk-7 and Krasnoyarsk-26

Report "EUR 18189 EN". Published in 1999

For about 30 years, the disposal of radioactive liquid waste arising from the operation of nuclear facilities situated in Dimitrovgrad, Tomsk and Krasnoyarsk in the Russian Federation has been carried out by deep-well injection. The use of this disposal mode for this waste type – which is unique in the world – is raising a number of objections from local authorities as well as from the public. In the European Union, the relevance and safety of this disposal mode - although forbidden – is also being questioned.

This study was conducted by a team of experienced scientists, including local Russian experts, experienced in the field of radioactive waste disposal. Three main topics were investigated;

- Data collection and analysis;

- Comparison of the Russian and the West European methodologies to assess the radiological consequences;

- Assessment of the radiological consequences

NUCLEAR SAFETY AND THE ENVIRONMENT

Review of existing and future requirements for decommissioning nuclear facilities in the CIS

Report EUR 18945 EN (3034K!). Published in July 1999

The countries that form the Commonwealth of Independent States (CIS) have inherited a significant legacy of nuclear facilities from the former Soviet Union. Many of these facilities have now reached or are close to reaching their design lifetime. The report provides an overview of the current state in CIS countries concerning the technical conditions and requirements for decommissioning of nuclear facilities.

NUCLEAR SAFETY AND THE ENVIRONMENT

Assessment of the consequences of the presence of toxic elements in some common radioactive waste streams

Report EUR 18211 EN (8037K!!) Published in July 1999.

In 1995 a study was carried out to investigate the application of procedures and disposal criteria developed in the nuclear industry for the assessment of non-radioactive contaminants found in low level and exemptible radioactive waste streams. The work is reported as EUR 16745. The aim of this follow-up study is to undertake more detailed waste and facility specific calculations.  The principal outcome of the current study is the assessment of the impacts arising from the disposal of non-radioactive contaminants in selected waste streams for a range of near-surface facilities. The results are compared with the generic levels obtained from the previous study and conclusions concerning the robustness of the generic levels are drawn. Secondary outputs are: the comparison of the impacts of non-radioactive and radioactive contaminents in the waste streams; the demonstration of how a second iteration of the SACO methodolgy can be used to undertake more detailed waste and disposal system specific calculations; and the collation of further data concerning inventories, health risks and the behaviour of organic contaminents in the environment.

NUCLEAR SAFETY AND THE ENVIRONMENT

Management of radioactive waste in medical establishments

Report "EUR 18861 EN" Published in May 1999.

This study has been prepared to describe the current management of radioactive waste produced in the medical sector in Belgium, to analyse the generated inconveniences and when needed, to suggest improvements to the current situation. The scope is limited to the utilisation of unsealed radioactive materials in hospitals. It covers neither the production and distribution of radio-isotopes nor the medical research applications.

NUCLEAR SAFETY AND THE ENVIRONMENT

Decommissioning of nuclear installations in the European Union. Supporting document for the preparation of an EC communication on the subject of decommissioning nuclear installations in the EU

Report EUR 18860 EN (242K). Published in May 1999

This document has been created and used as a support for an EC Communication on the subject of decommissioning nuclear installations in the EU. The Communication will aim at addressing the emphasis that the European Commission has placed on co-operation between the Member States in this field. This supporting document has been formulated together with a Group of invited Experts on the basis of Terms and References establishing the main focus of the Communication. It is constituted by an Introduction, the terms of References and the Supporting Positions and Observations from the Group of Experts on the various items developed from the Terms of References.

NUCLEAR SAFETY AND THE ENVIRONMENT

Schemes for financing radioactive waste storage and disposal

Report EUR 18185 EN (646K) Published in March 1999.

The study is based on the information collected from 10 Member States of the EU, the USA and Canada; it focuses on the application of the "polluter pays" principle to the management of radioactive waste from all producers, large and small. Schemes in the non-nuclear sectors have also been analysed where there are financial analogies with the nuclear sector. The schemes are analysed against three criteria: financeability, fairness and efficiency.

NUCLEAR SAFETY AND THE ENVIRONMENT

Evaluation of the suitability of the sites and facilities at Degelen and Azgir in the Republic of Kazakhstan as a final repository for radioactive waste

Report "EUR 17633 EN"

This report provides a preliminary assessment of the suitability of both sites (Degelen and Azgir) for disposal of radioactive  waste, and to identify which site, if any, could merit further investigations.

NUCLEAR SAFETY AND THE ENVIRONMENT

Safety case for geological disposal of high-level radioactive waste -follow-up to the 'desk simulation' licence application studies. Proceedings of the Mol workshop 27 and 28 November 1997

Report "EUR 18187 EN"

This report is a summary of the proceedings of the workshop which presented the two studies launched by the European Commission : 'Building the safety case for a hypothetical underground repository in clay'  and 'Building the safety case for a hypothetical underground repository in crystalline rock'.

NUCLEAR SAFETY AND THE ENVIRONMENT

Minimisation of waste in the field of common home and industrial products with a significant radionuclide content

Report "EUR 18213 EN"

The purpose of this study is to identify alternative technologies for products routinely used in the home and industry, having a significant radionuclide content.

NUCLEAR SAFETY AND THE ENVIRONMENT

Handbook on measurement methods and strategies at very low levels and activities

Report EUR 17624 EN (417K)

This handbook suggests methods which can be used to assess the levels of radioactive contamination and neutron activation in materials which have the potential for free release, that is, those which are only, at worst, contaminated or activated to a low level.

NUCLEAR SAFETY AND THE ENVIRONMENT

Recycling and reuse of radioactive material in the controlled nuclear sector

Report EUR 18041 EN (1113K)

This review contains estimates of the amounts of low-level waste materials which may arise from nuclear facilities around the EU up to 2050. The study concludes that the most promising materials for recycling in the controlled nuclear sector are those of steels and concrete.

NUCLEAR SAFETY AND THE ENVIRONMENT

Analysis of the medium and long term environmental and radiological consequences of the migration of radionuclides from the Karachay Lake in the Southern Urals (Russian Federation) - Parts 1 & 2: Identification of possible countermeasures

Report "EUR 17630 EN"

The study contract aimed at analysing the medium and long term environmental and radiological consequences of the migration of radionuclides from the Karachay Lake and identifying possible countermeasures. The study was split into four main tasks:

(i) Analysis and collation of currently available data regarding the environmental and radiological consequences of radionuclide migration from the Karachay Lake;

(ii) forecasts of radionuclide migration over the next 300 years through groundwater flow and contaminant transport modelling;

(iii) assessments of the radiological impact of radionuclide migration from the Karachay Lake in terms of dose uptake by critical groups of the population;

(iv) identification and costing of additional countermeasures to reduce the radiological impact to the population.

These tasks have been carried out within a collaborative programme between BNFL, PA Mayak, Hydrospetzgeologiya, the Obninsk Institute of Physics and Energy, and Westlakes Scientific Consulting Ltd.

The report also contains a summary record of a workshop that was organised by the European Commission together with the Russian Federation (Moscow, January 1998) on the Karachay Lake issue.

NUCLEAR SAFETY AND THE ENVIRONMENT

Radioactive waste categories-Current position (1998) in the EU Member States and in the Baltic and central European countries

Report EUR 18324 EN (121K) Published in 1998

This document includes the definition of radioactive waste, the legal basis of the classification system, the details of the system in use, the target group for the classification system and brief details of the waste management system in each country including other waste categories where applicable.

NUCLEAR SAFETY AND THE ENVIRONMENT

Materials containing natural radionuclides in enhanced concentrations

Report "EUR 17625 EN".1997

The report presents a review and collation of information on materials containing natural radionuclides in enhanced concentrations. Particular emphasis is given to situations in which the level of radiation exposure to workers or the public from waste materials or by-products is enhanced as a result of processing. The industrial activities or processes covered by the report are power production from coal, phosphate production, oil and gas production, rare earth and zirconium processing, metal smelting, processing of copper ores, production of building materials, and a number of minor processes.

NUCLEAR  SCIENCE AND TECHNOLOGY

Optimal Management routes for the restoration of territories contaminated during and after the Chernobyl accident

Report "EUR 17627 EN".1997

This report identifies optimised restoration strategies for contaminated territories (actually private agricultural lands and forests) in Ukraine, Belarus and the Russian Federation resulting from the Chernobyl accident. The evaluation of restoration strategies is based on economic and radiological criteria. For this purpose a methodology involving the subdivision of the territories into categories based on doses was developed. Remediation strategies for agricultural lands involves many options; for example, extensive resettlement, supply of clean milk, radical improvement of land, etc. For contaminated forests the potential radiological impact resulting from a selection of countermeasures like incineration of contaminated wood has been thoroughly evaluated.

NUCLEAR  SCIENCE AND TECHNOLOGY

Measurements, modelling of migration and possible radiological consequences at deep-well injection sites for liquid radioactive waste in Russia

Report "EUR 17626 EN".1997

In the former Soviet Union deep borehole injection of liquid radioactive waste has been established practice at least since 1963. The liquid is injected into sandy or other formations with high porosity, which are isolated by water-tight layers. This technique has also been used elsewhere for toxic liquid waste and residues from mining operations.

In this study a methodology is developed to assess deep-well injection sites. It is applied to one of the existing deep-well repositories, that of the Research Institute for Nuclear Reactors (NIIAR) in Dimitrovgrad.

NIIAR’s use of the repository is special in the sense that the radionuclides disposed of are all short-lived. Had the aim of the study been just to assess the NIIAR repository, a simpler methodology would have sufficed.

In order to show that the methodology is applicable to the disposal of long-lived radionuclides, as is practised in the deep-well injection repositories in Tomsk and Krasnoyarsk, the methodology is applied to some fictitious inventories using the NIIAR repository circumstances. It must be stressed that the aim is to demonstrate the applicability of the methodology, and that the results must not be interpreted as directly applicable to either of the other repositories (since they have very different geometries, layer structures and hydrology), nor as an assessment of the performance of the NIIAR repository for any proposed disposal of long-lived radioactive waste. The inventories are completely fictitious and based on the experience of one of the partners with nuclides important for the assessment of waste disposal facilities.

Subject to the limitations discussed in the main report and the data provided, the calculations demonstrated that deep-well disposal of low level, short-lived, radioactive waste, using the methodology applied in Dimitrovgrad, is acceptably safe within the regulatory requirements applicable in Russia.

Though all three existing sites are still in use, the Russian authorities are not planning to continue to exploit them in the long term, and are carrying out investigations to store waste in solid form.

NUCLEAR  SCIENCE AND TECHNOLOGY

Evolution of the radiological situation around the nuclear reactors with spent fuel which have been scuttled in the Kara Sea

Report "EUR 17634 EN".1997

This report presents an evaluation of the radiological consequences to man as a result of the nuclear reactors and their associated reactor compartments (six in total) that were scuttled in the Kara Sea from 1965 to 1981. Based on radionuclide inventories - which were found to be in good agreement with those estimated in other international projects - and considering several plausible release scenarios from the fuel, the radiological impact to man was calculated using short- and long-range dispersion models. In all cases, the best estimated maximum dose to members of critical groups as well as the collective dose integrated over long periods were shown to be below the values considered to be of regulatory concern. Therefore the study concluded that the radiological consequences related to the scuttled reactors are negligible and that there is no need to retrieve them from the bottom of the Kara Sea. The project has been implemented by a joint team of West European and CIS scientists within the framework of the EC/CIS collaborative programme on radioactive waste management and site restoration supported by the Directorate-General for Environment, Nuclear Safety and Civil Protection of the European Commission.

NUCLEAR  SCIENCE AND TECHNOLOGY

Current practice of dealing with natural radioactivity from oil and gas production in EU Member States

Report "EUR 17621 EN".1997

The production process of oil and gas mobilises naturally occurring radionuclides from deep underground reservoir rock, which are either deposited as naturally occurring radioactive material (NORM) in production, treatment and transport facilities or appear in produced effluents.

The present report reflects information pertaining to the current status of management of NORM in Norway, the United Kingdom and the Netherlands, and on less extensive information obtained from Germany.

Solid waste containing NORM is generated at the production installations as sludges and as scale debris from on-site decontamination of vessels and components. Additional NORM containing waste is produced at onshore decontamination facilities for components.

In the forthcoming decommissioning of large numbers of oil and gas production and transport installations the presence of NORM in a significant mass of steel to be recycled or re-used will have to be taken into account.

NUCLEAR  SCIENCE AND TECHNOLOGY

Elements for assessing the equivalence between radioactive waste materials

Report EUR 17241 EN (1081K) August 1996

This report describes the assessment of methods for determining equivalence between low, intermediate and high level radioactive wastes. Simple indicators based on impacts such as individual and collective doses and costs were used to estimate the amount of each waste considered equivalent. A method for determining equivalence using multi-attribute utility analysis to balance all the relevant impacts was developed, and the key factors identified. The best performing simple indicators of equivalence were identified, and a PC program was developed to calculate equivalent amounts of low, intermediate and high-level wastes.

NUCLEAR  SCIENCE AND TECHNOLOGY

Criteria for establishing harmonised categories of waste based on the storage and disposal route

Report EUR 17240 EN (1233K) 1996

The task was to evaluate possible ways to establish criteria for radioactive waste classification and categorisation, and to propose one or more possible schemes for categorisation of wastes based on radioactive risk and the storage and disposal route. To do this, the radiological impact of combinations of wastes and waste forms allocated to different storage and disposal methods were explored. Comparison of these impacts with risk criteria, together with other considerations such as heat generation, were used to allocate wastes to appropriate storage and disposal methods, thereby classifying them.

The main outcome is that it is possible to categorise waste to a particular type of facility using a new method of estimating risk from information about the radionuclide content of the waste, waste form, packaging and time factors using a multi-entry decision system based on dose modifying factors.

NUCLEAR  SCIENCE AND TECHNOLOGY

The situation of spent fuel storage in nuclear reactors in the CIS and Central and Eastern Europe

Report "EUR 16998 EN".1996/7

The analysis of the situation of spent fuel storage at reactor site for power-producing reactors in 10 formerly Socialist countries has been performed. The report includes short descriptions of the nuclear fuel used in Soviet-designed reactors, and provides information on national spent fuel management policy.

Tables list by reactor site pond occupation and data on future management as supplied by the plant operators.

NUCLEAR  SCIENCE AND TECHNOLOGY

Management of spent radiation sources in the European Union: quantities, storage, recycling and disposal

Report "EUR 16960 EN".1996

This report considers the management of spent sealed sources in the European Union. It identifies the quantities of sealed sources entering the European markets annually and considers how Member States currently regulate these sources. In particular, the report considers the waste management systems currently applied to spent sealed sources. The report then moves on to investigate the risks associated with types of sources, disposal practices and identifies an appropriate waste management system based on the risks associated with sources. It concludes with a number of recommendations for further consideration.

The information collected on the use of sources within Europe enabled 10 key sources to be selected either on the basis of high initial activity or high sales volumes. Radium was also selected on the basis of its widespread historical use. These sources were then subjected to a semi-quantitative risk assessment that identified the risks associated with the different sources and discussed the disposal of these sources.

The report considers how the waste management systems across Europe could be improved. It concluded that a multi-tier approach determined by the risk presented by a source throughout its life would be appropriate. This could be made up of a combination of consumer-based systems for low and medium-risk sources and a producer-based system to control high-risk sources.

NUCLEAR  SCIENCE AND TECHNOLOGY

Approaches for regulating management of large volumes of waste containing natural radionuclides in enhanced concentrations

Report "EUR 16956 EN".1996

The findings of a project for developing approaches for management of large volumes of waste containing natural radioactivity in enhanced concentrations are presented. There are descriptions of regulations in Member States of the European Union, an inventory of volumes involved and pragmatic approaches for handling radioactive waste from the non-nuclear industry.

An overview is given of existing EU regulations and regulations in Member States and trends in future regulations within the EU Member States are indicated. Information is gathered from literature studies and from companies in different branches of industry about radiological problems inside the plants and about waste management problems.

Recommendations and practical approaches are given which can be used to regulate practises in the industrial branches concerned. In general it is not necessary to prescribe for natural radioactivity the same stringent regulations as for anthropogenic radioactivity.

NUCLEAR  SCIENCE AND TECHNOLOGY

Inventory of radioactive waste and spent fuel at the Kola Peninsula region of north-west Russia

Report "EUR 16916 EN".1996

The Murmansk and Arkhangelsk regions of north-west Russia have accumulated significant amounts of spent nuclear fuel and radioactive waste which resulted from operating the kola nuclear power plant, nuclear-powered icebreakers and a container ship of the merchant marine, nuclear-powered submarines and cruisers of the Navy, and from industrial and medical use of radionuclides. Most of these materials are now in interim storage awaiting a permanent solution. In order to soundly plan and later install a state-of-the-art spent fuel and waste management system, an analysis of the present situation is needed, including an inventory of materials currently in storage and of expected arisings. This report provides a detailed spent fuel and radioactive waste inventory and suggests a management plan in order to improve the present situation.

NUCLEAR  SCIENCE AND TECHNOLOGY

Analysis of radioactive waste vitrification practices in the Commonwealth of Independent States

Report "EUR 16945 EN".1996

Vitrification of radioactive waste has been developed in Russia since 1960, and has been applied at industrial scale to vitrify liquid high-level waste from reprocessing of spent fuel.

The State of vitrification practice has been analysed starting with a description of the reprocessing plants and their products. The research and development activities were focused on investigations of silicate and phosphate glasses.

After operating some experimental melters, the first industrial-scale melter EP-500 was built at the Mayak reprocessing plant. This plant was decommissioned after 13 months of operation, and a new melter was built in 1990, which has been in active operation since 1991.

Flowsheets, feed compositions and sketches of installations are included in the report, which also briefly addresses vitrification processes under development for solidifying low-level waste.

NUCLEAR  SCIENCE AND TECHNOLOGY

Application of procedures and disposal criteria developed for nuclear waste packages to cases involving chemical toxicity

Report "EUR 16745 EN".1996

Radioactive waste may include chemically toxic elements such as heavy metals, which may present a risk to man and the environment even after the decay of the radioactive content of the waste. The work described in this report demonstrates how limiting values for chemically toxic components may be derived to support decisions concerning appropriate disposal options for radioactive waste streams. Only solid low level and exemptible wastes are considered here.

The safety assessment comparison (SACO) methodology, developed under the European Commission’s R&D programme on management and storage of radioactive waste (1990-94) was used to provide a thorough and quantitative assessment of risks. The disposal of eight representative waste streams in five representative facilities was considered leading to the derivation of maximum acceptable limits for toxic element concentrations.

In comparing these derived threshold values to the concentrations of toxic elements in various real waste streams, it is concluded that many of the waste for shallow disposal. However, it should be borne in mind that the disposal limits have been derived using generic data and are not directly applicable to specific sites. It is expected that more detailed, facility specific calculations would show that shallow disposal is acceptable in all but a few cases.

NUCLEAR  SCIENCE AND TECHNOLOGY

Benchmark exercise on the probabilistic safety assessment of steam generator tube rupture radiological releases

Report "EUR 18550 EN". Published in May 1999

This synthesis report describes a collaborative benchmark exercise in which PSA, thermal hydraulic and radiological analyses were performed with a view to identifying the non-core damage steam generator tube rupture consequences which contribute most to risk. These sequences have the potential to lead to appreciable releases of radioactivity to the environment.The analysis of sequences which result in core damage, which are important contributors to overall risk, was not within the scope of the study performed.

NUCLEAR SCIENCE AND TECHNOLOGY

Demonstrating compliance with clearance levels in dismantling nuclear installations (and application to the WAK reprocessing plant)

Report "EUR 17623 EN". Published in 1997.

The investigation has been concerned with characterisation of waste materials arising from building demolition associated with the decommissioning of a reprocessing plant. As an example for data collection, the reprocessing plant Karlsruhe was chosen which dealt with a wide variety of fuels for reprocessing.

The information which has been available to date was based largely on theoretical considerations. The data which are becoming available on the inventories of the low-level wastes are used to discuss routing options within the decommissioning programme. The methodology developed for the study allows the radiological consequences of waste management options to be determined as a function of the numerical value of clearance criteria in terms of limits on activity concentration. Nuclide spectra for different process areas are evaluated so that the methodology permits the quantification of the widest possible range of radiological impacts arising from any specified management option, whether it involves recycling, re-use or disposal.

NUCLEAR SCIENCE AND TECHNOLOGY

A review of the situation of decommissioning of nuclear installations in Europe

Report EUR 17622 EN (239K). Published in 1997.

A considerable number of nuclear power plants have been built in the European Community since the 1950s, ranging from low power materials test reactors, through various medium power prototype/experimental reactors, up to high power commercial stations. In addition, there are a number of fuel fabrication and reprocessing plants associated with the nuclear fuel cycle. Many of these facilities have reached the end of their operating lives and gave therefore been withdrawn from service.

A study has been carried out on nuclear facilities being decommissioned in five member countries, namely France, Germany, Italy, Spain and the United Kingdom. The purpose of the study has been to:

(i) Provide a list of nuclear installations shut down in the named countries between 1993 and 1995.

(ii) Provide information on the decommissioning stage attained at each installation covered and its planned future state. This includes whether or not the facility has been defuelled, what operational wastes remain and what the extent of the radiologically controlled area(s).

(iii) Identify the monitoring and inspection proposals/experience for these installations, including where possible the effort involved.

(iv) Identify relevant codes and standards applicable to decommissioning in Member States and to identify where available the relevant licensing requirements.

NUCLEAR SCIENCE AND TECHNOLOGY

Radioactive Waste Equivalence
- Euradwaste series No. 3 -
(Report of a working group set up in the frame of the "Community Plan of Action in the Field of Radioactive Waste)

Report EUR 12879 EN (980K). Published in 1990.

The present report, drafted by a working group set up within the framework of the Community's Plan of Action in the field of radioactive waste, reviews possible situations in which an equivalence concept for radioactive waste may be used, analyses the various factors involved, and suggests guidelines for the introduction of such a concept.

NUCLEAR SCIENCE AND TECHNOLOGY

Objectives, standards and criteria for radioactive waste disposal in the European Community
- Euradwaste series No. 1 -
(Report of a working group on 'joint elaboration of radioactive waste-management policies')

Report "EUR 12570 EN". Published in 1990.

The present report, proposed by a working group within the framework of the European Commission's research programme on radioactive waste management and disposal, reviews the objectives, standards and criteria for radioactive waste disposal in the European Community with the view to identifying common features and differences in the regulatory frameworks of its Member States. Suggestions for possible harmonisation are made.

A few common general principles are the basis for legal and regulatory measures. These principles apply to and are discussed for the following: radiation protection (with the systems of dose limitation and control), ethical and sociological questions, environmental and natural resources protection, and nuclear safeguards.

A description is given of the implementation of common principles, standards and requirements at Community level, in line with requirements laid down in the European Community Treaties, and in international Conventions and recommendations. This is followed by a review of the implementation of basic criteria by national safety authorities. Regulatory measures and national policies, and the approaches used in devising criteria are discussed for both near surface disposal of low-level waste, and for deep geological disposal of waste in continental geological formations.

Finally, the roles and duties of the operators of radioactive waste facilities are reported.

More detailed information on particular aspects is presented in the annexes: waste classification in the European Community Member States; financial provisions for waste management activities; regional Conventions on pollution prevention; and radioactive waste management policies. As examples of the implementation of a regulatory framework the situation for the operating repositories at Drigg (UK), Centre de la Manche (F) and Dounreay (UK) is described, as well as the intended criteria and limits for Konrad (FRG), Gorleben (FRG), Centre de l'Aube (F) and El Cabril (E).

NUCLEAR SCIENCE AND TECHNOLOGY

Leak before break assessment of pressurised components

Report "EUR 17574 EN"

The report presents the results of an AEA Technology led CEC contract, which has been undertaken to compare leak before break (LBB) methodologies in EU countries.

NUCLEAR SCIENCE AND TECHNOLOGY

European Nuclear Regulators' Current Requirements and Practices for the Licensing of Safety Critical Software for Nuclear Reactors. European Commission's Advisory Experts Group Nuclear Regulators Working Group, Draft Report Revision 8

Report EUR 18158 EN

The report contains the conclusions of experts from nuclear safety institutes about the computer-based systems used in nuclear power plants for safety functions.

NUCLEAR SCIENCE AND TECHNOLOGY

Guideline for the Evaluation of European Practices on the Harsh Environment Qualification of Electrical and I&C Equipment. Prepared for the European Commission's Reactor Safety Working Group

Report EUR 17563 EN

The report presents the principal results of the work carried out in 1993-96 by the working group. The group worked out a guideline for the evaluation of electrical, instrumentation and control equipment. Only the qualification for harsh environment within design basis was considered.

NUCLEAR SCIENCE AND TECHNOLOGY

Current Status of Probabilistic Safety Assessments for Soviet Designed Reactors

Full report EUR 17567 EN (340K).

The European Commission has funded a project called " Current Status of Probabilistic Safety Assessment for Soviet Designed Reactors". The project was undertaken by ENCONET Consulting (Austria).

The political changes in Central and Eastern Europe have led to an increased interest in the safety of nuclear reactors in the region. Many of the operating reactors were found to have significant safety deficiencies, both in design and operating practices. Moreover, the scope of safety analysis performed for these reactors was insufficient compared to the standards applied in countries of the European Union. One of the major deficiencies that was found was a lack of any comprehensive Probabilistic Safety Assessment (PSA) analysis.

In countries where Soviet designed reactors are operating, numerous PSA-related activities were undertaken. These activities, however, did not produce a single complete study comparable to Western requirements. Therefore, one of the most important areas of international assistance provided was related to PSA.

Since the political changes, the number of PSA activities performed in the countries with Soviet designed reactors has significantly increased. In the mid-nineties there were more than 25 plant-specific projects for reactors that were either operating, or under construction.

At present, there is a PSA project completed or at least on-going for most Soviet designed reactors. Recognising the variability in quality and comprehensiveness of the PSAs performed for Soviet designed reactors, and possible misinterpretations that might occur if those PSAs were used for safety arguments, the Environment Directorate- General of the European Commission initiated a project aimed at collecting information on any available PSA studies for Soviet designed reactors.

The report contains the following sections:

The concept of PSA:

• Validation of the PSA model
• Quality factors of PSA
• Interaction between probabilistic & deterministic approaches
• Consideration of uncertainties

Overview of the Soviet designed reactors:

• WWER type reactors
• RBMK type reactors

Graphical representation of the PSA results

Final conclusions

References

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NUCLEAR SCIENCE AND TECHNOLOGY

Common position of European regulators on qualification of NDT systems for pre- and in-service inspection of light water reactor components

Report EUR 16802 EN

The need to qualify non-destructive testing (NDT) systems for pre-and in-service inspection has been recognized to a greater or lesser extent for many years in many of the European countries engaged in nuclear power generation. A recent modification to Section XI of the ASME code to include formal requirements for what it terms performance demonstration has resulted in a large programme by the licensees in the USA to provide the appropriate procedures, facilities and infrastructures. This programme is known as the performance demonstration initiative (PDI). This, as well as the results from the large international PISC programme, has promoted European licensees and inspection companies to cooperate and consider a similar initiative. The organisation which has been set up to do this is know as the European Network for Inspection Qualification (ENIQ).

Consequently, it has also been recognized that a common basis for this further development of NDT qualification programmes in the European countries is needed and that the development of such a basis should be guided by the views of the regulatory bodies on essential aspects of the qualification process.

In November 1992, the Nuclear Regulators Working Group (NRWG) therefore established a task force with the purpose of establishing a platform for the further development of NDT qualification programmes in the different European countries.

This platform deals with the objective and role of NDT qualification, principles for the derivation of basic qualification requirements, and qualification methodologies as well as the way to organize the process of NDT qualification, which depends on the legal framework within the various countries.

The views expressed in this document are based on the common position of the regulatory bodies, but taking into account those verying needs and legal situations that exist.

Preparatory work for an indicative program related to ageing issues

DOWNLOAD REPORT (260K) only available in electronic version

The European Commission has funded a project called "Preparatory work for an indicative programme related to ageing issues". The project was undertaken by TECNATOM S.A. (Spain), with the collaboration of MITSUI BABCOCK ENERGY Ltd (United Kingdom).

This study is directed to give an account of either recent or ongoing programmes on ageing of components and parts of NPP's. Ageing issues of NPPs (Nuclear Power Plants) have been in the agenda of regulators, utilities, designers and R and D laboratories due to their impact on the safe life of operating plants and their economical aspects. On the other side, there are no well established provisions for mitigating ageing effects of components since phenomena which are involved in, are complex and, in many cases, there is a main difficulty for anticipating them in the stages of the components design.

The Commission Working Group for Codes & Standards (WGCS) stated in 1995 that a programme on ageing for codes could not be handled in a large manner in the frame of the group without an accurate view of ongoing programmes; moreover, there was a need for working out a synthesis of the ongoing work for avoiding redundancies with other programmes.

Finally, the authors of the report produced an extensive overview with a useful list of references of available reports from ageing programmes encompassing international organisations, owners groups, some EU countries and a short description of European networks and groups with interest for the subject. In addition, the report states general recommendations for a future programme of the WGCS. Some of these recommendations have been already taken into account in inputs of the 1996 and 1997 programmes, however, several of these recommendations might be included in the next research programme of the Commission. Although the report focus on LWR (Light Water Reactor) type reactor since it was the first objective, the material encompassed by the report is useful for other types of reactor in specific systems. The VVER reactors are not addressed specifically in this context.

The report contains the following sections:

• Ageing research programs status (List of institutions: International organizations, USA, European Union, other countries and utilities and owners groups);
• Ageing ongoing programs (List of institutions);
• Strategies and future developments;
• Conclusions;
• References.

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