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No. 52PROCEDURES AND DATA

Factors Relevant to the Decommissioning of Land-Based Nuclear Reactor Plants

$ INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1980

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From Safety Series No. 46 onwards the various publications in the series aredivided into four categories, as follows:

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FACTORS RELEVANT TO THE DECOMMISSIONING OF LAND-BASED NUCLEAR REACTOR PLANTS


The following States are Members of the International Atomic Energy Agency :

AFGHANISTANALBANIAALGERIAARGENTINAAUSTRALIAAUSTRIABANGLADESHBELGIUMBOLIVIABRAZILBULGARIABURMABYELORUSSIAN SOVIET

SOCIALIST REPUBLIC CANADA CHILE COLOMBIA COSTA RICA CUBA CYPRUSCZECHOSLOVAKIA DEMOCRATIC KAMPUCHEA DEMOCRATIC PEOPLE’S

REPUBLIC OF KOREA DENMARKDOMINICAN REPUBLICECUADOREGYPTEL SALVADORETHIOPIAFINLANDFRANCEGABONGERMAN DEMOCRATIC REPUBLICGERMANY, FEDERAL REPUBLIC OFGHANAGREECEGUATEMALAHAITJ

HOLY SEEHUNGARYICELANDINDIAINDONESIAIRANIRAQIRELANDISRAELITALYIVORY COASTJAMAICAJAPANJORDANKENYAKOREA, REPUBLIC OF KUWAIT LEBANON LIBERIALIBYAN ARAB JAMAHIRIYALIECHTENSTEINLUXEMBOURGMADAGASCARMALAYSIAMALIMAURITIUSMEXICOMONACOMONGOLIAMOROCCONETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAYPAKISTANPANAMAPARAGUAYPERU

PHILIPPINESPOLANDPORTUGALQATARROMANIASAUDI ARABIASENEGALSIERRA LEONESINGAPORESOUTH AFRICASPAINSRI LANKASUDANSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTHAILANDTUNISIATURKEYUGANDAUKRAINIAN SOVIET SOCIALIST

REPUBLIC UNION OF SOVIET SOCIALIST

REPUBLICS UNITED ARAB EMIRATES UNITED KINGDOM OF GREAT

BRITAIN AND NORTHERN IRELAND

UNITED REPUBLIC OF CAMEROON

UNITED REPUBLIC OF TANZANIA

UNITED STATES OF AMERICA URUGUAY VENEZUELA VIET NAM YUGOSLAVIA ZAIRE ZAMBIA

The Agency’s S tatute was approved on 23 October 1956 by the Conference on the S tatute of the IAEA held at United Nations Headquarters, New York; it entered in to force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the contribution o f atomic energy to peace, health and prosperity throughout the world” .

© IAEA, 1980

Permission to reproduce or translate the inform ation contained in this publication may be obtained by writing to the International Atomic Energy Agency, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria.

Printed by the IAEA in Austria August 1980


SAFETY SERIES No.52

FACTORS RELEVANT TO THE DECOMMISSIONING

OF LAND-BASED NUCLEAR REACTOR PLANTS

INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1980


FACTORS RELEVANT TO THE DECOMMISSIONING OF LAND-BASED NUCLEAR REACTOR PLANTS

IAEA, VIENNA, 1980 STI/PUB/541

ISBN 9 2 -0 -6 2 3 0 8 0 -8


FOREWORD

In 1973 the International Atomic Energy Agency, and the Nuclear Energy Agency of the Organization for Economic Co-operation and Development, convened a group of consultants to examine what role the IAEA should play in the decommissioning of nuclear facilities. The consultants advised the IAEA that decommissioning activities should be introduced into its programme, and that it should promote the formulation of guides, recommendations and standards on the subject.

In 1975, and again in 1977, Technical Committees with representatives from Member States and other international organizations met to consider the decommissioning of nuclear facilities. The committees concluded that while there were no known insurmountable technical problems to accomplishing decommissioning, the regulatory aspects, and some other aspects such as policy, planning, timing, cost analysis, waste disposal and safety criteria, needed further development.

Many of the participants of the 1977 Technical Committee also felt that sufficient technical information and experience was available to develop a code and guide for decommissioning nuclear reactors, and recommended that such a document be initiated. They also supported the International Symposium on the Decommissioning of Nuclear Facilities that was held in Vienna in November 1978. The Committees pointed out the advantages of harmonizing principles and rationalizing decommissioning standards on an international basis, and also emphasized the need for criteria for the release of materials and land for general use.

An Advisory Group of experts, convened by the IAEA in April 1978, developed a draft code and guide for the decommissioning of land-based nuclear reactor plants. However, the national authorities of some Member States pointed out that decommissioning experience had so far been confined to research and test reactors and other small nuclear facilities. They felt it would be premature to issue a code and guide on the subject until more experience with decommissioning large nuclear power plants had been gained.

To ensure that the information developed to date is made available to all Member States, it is published here, with a few amplifications, under the present title.


CONTENTS

1. INTRODUCTION...........................,............................................................... 1

1.1. General............................................................................................................ 11.2. Basic stages of decommissioning ............................................................... 3

2. SCOPE ............................................................................................................ 5

3. RESPONSIBILITIES.................................................................................... 6

4. DECOMMISSIONING PLANS ................................................................... 7

4.1. Preliminary decommissioning plan ........................................................... 74.2. Detailed decommissioning p lan s ................................................................ 84.3. Post-decommissioning reports .................................................................... 9

5. RADIATION PROTECTION PROGRAMME ........................................ 10

5.1. Radiation measurements for decommissioning....................................... 105.2. Radiation dose controls and evaluation..................................................... 115.3. Effluents released to the environm ent...................................................... 115.4. Waste m anagem ent....................................................................................... 125.5. Environmental monitoring ......................................................................... 125.6. Post-decommissioning radiological surveillance....................................... 12

6. CRITERIA FOR RELEASE OF MATERIALS, FACILITYOR SITE .......................................................................................................... 13

6.1. Unconditional or unrestricted use ............................................................ 136.2. Conditional or restricted use ................... ................................................. 14


DEFINITIONS......................................................................................................... 17

BIBLIOGRAPHY.................................................................................................... 21

LIST OF PARTICIPANTS .................................................................................... 25

7. Q U A L IT Y A S S U R A N C E ........................................................................................... 14


1. INTRODUCTION

The term ‘decommissioning’ in the nuclear industry is generally agreed to apply to the actions taken at the end of a facility’s useful life in retiring the facility from service with adequate regard to the health and safety of members of the public and the decommissioning workers. These actions can range from merely closing down the facility, with a minimum removal of radioactive material and with continual surveillance and restricted use of the facility, to the removal of radioactive material to the extent that the facility/site becomes available for use without restrictions with regard to the small amounts of residual radionuclides present.

Decommissioning of nuclear facilities is not new to the nuclear industry. To date, a total of about 65 nuclear reactors (plus a number of other nuclear facilities) have been or are in the process of being decommissioned. Most of these were demonstration, test or research facilities, but no large power reactors have been involved.

Many more nuclear facilities will require decommissioning in the near future, and their decommissioning will add to the current store of experience. Of the more than 230 nuclear power stations operating in the world today about 150 will be 25 or more years old, and some more than 40 years old, by the year 2000.There will also be a significant number of supporting nuclear facilities of similar ages. Thus, decommissioning is a highly relevant current consideration for the nuclear power industry. It is, therefore, appropriate at this time to issue this document, which contains a consensus of current opinions on considerations for the decommissioning of land-based nuclear reactors.

Technical experts generally agree that nuclear reactors and other facilities can be decommissioned safely, and without unacceptable impacts on man or his environment. In the ultimate case, this includes the dismantlement of a plant and fee restoration of the site to unrestricted use. Much experience has been acquired on decommissioning of small nuclear facilities, and a number of detailed engineering assessments of the requirements and impacts of decommissioning large facilities have been completed in the past few years. Based on this experience and these studies, some governments have developed or are developing guides or regulations that are specific to decommissioning. It is generally believed that improvements in decommissioning technology would be beneficial and will evolve with time as more experience is gained in decommissioning nuclear plants.

At the end of the operational life of a nuclear reactor plant it will be necessary to deal with the plant in the same manner as other non-nuclear commercial plant property no longer useful for its original purpose, namely, to decommission it in a manner that ensures adequate protection - in this case radiological — to those performing the decommissioning task, as well as to members of the public and to the environment. This involves eliminating potentially hazardous conditions,

1.1. G E N E R A L

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recovering whatever remains of value, and making some of the facility resources, including the site itself, available for other applications. Decommissioning does not include refurbishing of the facility for its original or other nuclear purpose.

Some parts of nuclear reactors are essentially similar to other industrial structures in that they can be dismantled by conventional methods. Other parts, which become radioactively contaminated, require additional precautions. Decommissioning of these items, i.e. cleaning, removal of equipment or material, dismantling, must take into account the amount and type of radioactivity that is present.

The primary objective of this report is to provide a checklist of the principles and factors to be considered in order to decommission a land-based nuclear reactor in an orderly and safe manner. This includes the areas of planning (including facilitation of decommissioning at the design step), management, and the carrying out of decommissioning. To the extent feasible, this report takes into consideration past experience to better ensure that the objectives of decommissioning can be met.

It is assumed that the decision on decommissioning is initiated by the owner (or licensee) and approved by the appropriate regulatory bodies. The report covers the direct and major supportive activities during decommissioning, and follow-up activities after decommissioning. Although directed at nuclear reactors, it is also believed that most of the principles outlined are sufficiently generic to enable them to be generally applied to the decommissioning of other types of nuclear facilities.

To initiate the decommissioning of a nuclear reactor plant, the reactor must first be rendered inoperative under any circumstance. This normally requires an orderly shut-down of the reactor, similar to the periodic shut-down required during routine operations. Decommissioning then starts with the removal of all nuclear fuel to ensure the non-operability of the reactor. For practical purposes, this complete defuelling may be conducted in parallel with other decommissioning work. In some cases, a nuclear reactor plant may be decommissioned after an accident has occurred. In this event, special decommissioning procedures may have to be evolved.

In deciding how far a nuclear reactor could or should be decommissioned there is a wide range of schemes, but it is convenient and customary to recognize three basic stages1. Each stage corresponds to a defined physical state of the plant

1 The terra ‘stage’, in the con tex t o f this report, does n o t necessarily im ply a step-wise procedure through various ‘stages’, as indicated by norm al usage of the word. Thus, decommissioning to ‘stage’ 2 does no t necessarily have to be preceded by going through ‘stage’ 1, and ‘stage’ 3 does no t have to be preceded by ‘stages’ 1 and 2. Many Member S tates prefer and /or use o th er term s such as ‘alternative’, ‘level’, ‘o p tio n ’, ‘m ode’, etc. in place of ‘stage’.In addition, at least one Member S tate considers that a nuclear facility is no t com pletely decommissioned un til it can be released fo r unrestricted use. In th is case, ‘stage’ 1 is no t a final decommissioned state; similarly, in m any cases ‘stage’ 2 m ay no t be a final decom m issioned state.

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and, with the exception of the third stage, carries with it the need for continuing surveillance. Depending upon policies of individual countries and conditions at specific reactors, it is possible that those stages requiring continuing surveillance could be considered either the final status or the temporary status, before stage 3 dismantlement. However, in some cases, it may be highly impractical to proceed from an extreme version of stage 2 to stage 3 (see footnote 2).

1.2. BASIC STAGES OF DECOMMISSIONING

The three basic stages are defined as follows:

Stage 1: Storage with surveillance

State o f the plant and equipment

The reactor is completely defuelled and the fuel is shipped away from the reactor.

All heat transport fluids, readily removable contaminated materials, and some highly contaminated materials are removed.

The first contamination barrier, e.g. the reactor vessel, is kept as it was during operation but with all mechanical openings (valves, piping) blocked and sealed.

The containment building is maintained intact in a state appropriate to the remaining hazard.

The atmosphere inside the containment building (and in all areas containing radioactivity) is controlled and the ventilation systems may be operated as required.

Access to the inside of the containment building is controlled by physical barriers and administrative procedures.

Surveillance, inspection and tests

The plant is kept under continuous on-site surveillance, and the equipment necessary for monitoring radiation both inside the plant and in the surrounding

2 An extrem e version of stage 2 (term ed ‘en tom bm ent’ in some M ember States) can involve the encasem ent o f radioactive m aterials in concrete o r o th er structural m aterials sufficiently strong and durable to ensure re ten tion o f the radioactivity. In some M ember States radionuclide re ten tio n m ust persist un til the radionuclides have decayed to levels w hich perm it unrestricted release of the site.

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area is kept operable and used as required. Most ventilation and service systems are kept operational. Surveillance is maintained in accordance with applicable regulatory requirements.

Periodic measurements and visual checks are carried out to ensure that contamination control systems, i.e. ventilation systems and contamination barriers, continue to function properly.

Stage 2: Restricted site release



All heat transport fluids, readily removable contaminated materials, and some highly contaminated materials are removed.

Contaminated areas are decontaminated to the extent appropriate, and remaining areas with unacceptable residual radioactivity levels are sealed to prevent unauthorized access. Various containment features generally remain and are augmented where necessary. Contaminated parts that are easily dismantled are removed and transferred off-site or into plant areas that are to be sealed. For example, this sealing may range from using barriers that can be removed without undue effort by man to sealing with a thick overlay of reinforced concrete.

The ventilation, services and other active safety systems are not needed and are deactivated. Some monitoring equipment will likely remain operational, depending on the specific circumstances.

Some parts of the plant or site could be converted to new uses or released, with certain constraints in accordance with appropriate radiological protection requirements, for uses not involving other radioactivity sources.


Surveillance around the restricted areas is required in accordance with regulatory conditions but is less extensive than in stage 1; for example, spot surveys around the barriers are continued as well as surveillance of the environment. An example of maximum surveillance may be the continual monitoring of instrument outputs at a location remote from the site with only periodic on-site inspection and maintenance, plus periodic environmental monitoring. An example o f minimum surveillance — which might

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be used for cases such as the extensive encasement of radioactivity within massive structural materials (e.g. thick concrete or steel) — may be to have access controls as simple warning signs citing laws prohibiting access, and surveillance consisting of periodic inspections and repairs, plus limited periodic environmental monitoring.

Stage 3: Unrestricted site use



All heat transport fluids are removed.

All materials, equipment and structures in which radioactivity levels exist above prescribed limits are removed to an approved storage or disposal site.

In all remaining plant areas the radioactivity levels will have been reduced to those that permit unrestricted use. The site and any remaining equipment and materials may be released for other purposes, without any radiological protection restrictions.


No further surveillance, inspection or tests are necessary.

Variations exist on these three main stages, including decommissioning of different parts of the same facility to different stages.

2. SCOPE

This document applies to all classes of land-based nuclear fission reactors, including those reactors used for the production of electricity or heat, for testing, for research, and for the production of radionuclides.

The document covers the technical and administrative aspects related to the conduct of decommissioning, and to the associated radiation protection of man and his environment both during and after decommissioning.

The document is intended to provide assistance to those responsible for planning or implementing the decommissioning of a land-based nuclear reactor. The user of this report is further encouraged to review past experience gained with nuclear facilities and the published technical data cited in the section entitled Bibliography.

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3. RESPONSIBILITIES

The organization licensed to operate a nuclear reactor (the licensee) is normally responsible for ensuring its safe decommissioning. This implies the fundamental obligation of ensuring that the public interest is upheld in the areas of health, safety and environmental impact as a result of decommissioning. The licensee should be required to demonstrate to the appropriate regulatory bodies that this responsibility has been fulfilled.

To fulfil his responsibilities the licensee should complete the following:

(a) Preparation of the decommissioning plans(b) Preparation of the application and obtaining approval to initiate

decommissioning(c) Provision of qualified staff and appropriate materials and support

services for all aspects of decommissioning(d) Provision of sufficient financial resources to carry out the decommissioning(e) Implementation of the activities described in the decommissioning plans,

including those for surveillance and maintenance activities if required(f) Provision o f radiation monitoring and assurance that radiation

protection is satisfactory during decommissioning(g) Provision of documentation of decommissioning activities and results(h) Submission of the application for change of licence status of the

decommissioned facility and obtaining the licensing change.

The licensee is also responsible for the proper packaging, transport and disposition of radioactive wastes (liquid and solid) arising from the decommissioning. The responsibility for waste disposition can only be transferred to another organization, e.g. radioactive waste storage or disposal licensee, with the prior agreement of the appropriate regulatory bodies.

Following the implementation of the decommissioning plan, the licensee responsibility for that part of the plant remaining on the site continues until the site is released for unrestricted use, or until a legal decision relieves the licensee of this responsibility.

To carry out the decommissioning of the nuclear reactor the licensee may delegate his duties but not his responsibilities to other parties, with the agreement of the appropriate regulatory bodies if required.

The national government has the responsibility to produce and to enforce legislation governing all aspects of decommissioning nuclear facilities.

It is the responsibility of the regulatory bodies to ensure compliance with and adequate monitoring of all requirements for implementation, safety, and environmental protection during the decommissioning of nuclear facilities. In - addition, the national governments ultimately have the responsibility to ensure safety and environmental protection in all cases, whether or not the licensee demonstrates compliance with the licensing requirements.

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4. DECOMMISSIONING PLANS

Plans are required for any industrial activity, including the decommissioning of a nuclear reactor. Preliminary decommissioning plans are recommended to be developed at the time the reactor is in the design stage; where such plans were not developed at that time, as may be the case with plants already in operation, they should be developed as soon as possible thereafter so that, as the time for decommissioning approaches, detailed plans will be available. At the time of decommissioning, these plans must be further augmented to incorporate all the necessary operating details and improved technology.

4.1. PRELIMINARY DECOMMISSIONING PLAN

A preliminary plan for decommissioning should be prepared during the reactor design phase as guidance to both designers and operators, and to provide necessary information to the regulatory bodies. This preliminary plan should establish, in general, feasible decommissioning schemes that can be accomplished without undue risk to the environment. The plan should take into account the provisions for decommissioning that are designed into the plant. The plan must conform to the requirements of the appropriate regulatory bodies. To the maximum extent feasible, this plan should be based on the technical knowledge available at the time of design.

The preliminary plan should include documentation of the following:

(a) A description of the anticipated final status/disposition of the facility and site, and identification of major environmental impacts.

(b) A quantitative estimate of the type, amount and location of important radionuclides and radioactively contaminated materials within the reactor facility at the end of its operating life.

(c) A broad description of the decommissioning techniques that may be used, together with proposals on the management of radioactive waste while it remains within the responsibility of the licensee. This description should demonstrate that such methods are practical and safe for both members of the public and the site personnel.

(d) An estimate of the manpower and materials needed, the anticipated costs, and the bases for these estimates.

(e) The methods used to ensure that adequate financing will be available for decommissioning, if the assurance of decommissioning funds is important to national interests.

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(f) Identification of information required and records that should be maintained during construction and operation of the plant. The information should include the updated design plus files, records and specifications necessary for the detailed planning and execution of decommissioning.

The preliminary plan should identify a range of feasible approaches to plant decommissioning. This information should allow the plant designer to consider the introduction of design features that are favourable to decommissioning. Some examples might be:

(1) Provision for adequate materials handling equipment(2) Provisions for separation of attachments from and/or remote maintenance

of highly radioactive components(3) Provisions for effective decontamination or sealing of materials with

radioactive contamination on their surfaces(4) Location and size of access doors to allow for movement of materials(5) Provisions for management of radioactive waste from decommissioning.

4.2. DETAILED DECOMMISSIONING PLANS

A detailed plan for decommissioning should be prepared before the initiation of decommissioning and should be submitted to the appropriate regulatory bodies. The plan should provide sufficient information to all the organizations involved in the decommissioning of the reactor so that they can obtain approval from the regulatory bodies to proceed. This plan should consider all the techniques to be used as well as the safety aspects of the decommissioning programme and of the programme end product, including a radiation protection programme.

The detailed decommissioning plans should include at least the following information:

(a) A clear description of the state of the plant before and after the decommissioning activities

(b) A description of the major activities and schedule of the decommissioning activities

(c) A description of the techniques and procedures to be used in the decommissioning activities, including the use of mock-ups and the special training required

(d) An estimate of the type and quantity of radioactive and non-radioactive wastes to be generated during the decommissioning activities, and the plans for their treatment, transportation and disposal and/or storage

(e) A safety analysis including the environmental impact of decommissioning


(f) A safety analysis, including environmental impact, for the state of the plant to be reached on completion of the decommissioning activities

(g) An estimate of the decommissioning costs and identification of sufficient funding sources to carry out the decommissioning

(h) Identification of the organizations to be involved (including key staff) and the role and responsibilities of each in the decommissioning activities

(i) An estimate of occupational and public radiation exposures from decommissioning

(j) The details of how public and occupational radiation exposures will be controlled. The plan should clearly specify the objectives and procedures for radiation dose management in:

(i) establishing a basis for radiation protection founded on regulatory limits

(ii) establishing a radiation control programme, plans and procedures(iii) ensuring the availability of supporting equipment, instrumentation,

qualified staff and facilities

(k) The quality assurance programme to be used during decommissioning activities

(1) Bases, criteria and the derived working values for radioactivity levels that are acceptable for the release of materials for unrestricted use3

(m) Operational control limits, including those for effluents arising from decommissioning

(n) Plans for emergencies or unexpected occurrences(o) Plans for security control during decommissioning3 (p) Details of records and reports to be developed during decommissioning

and their disposition (q) A description of the environmental monitoring, surveillance, and

maintenance programme that will be implemented after decommissioning, if decommissioning stages 1 or 2 are used.3

4.3. POST-DECOMMISSIONING REPORTS

One or more post-decommissioning reports should be submitted to the appropriate regulatory bodies. These reports should describe the plant in its decommissioned state and provide a summary of decommissioning activities with reference to more detailed reports on this subject. For decommissioning to

3 These plans are in some cases established by or in conjunction w ith the appropriate regulatory bodies.

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stages 1 and 2, the first post-decommissioning report should also specify the safety procedures necessary to maintain the plant within the regulatory requirements.For decommissioning stages 1 and 2, periodic reports should also be submitted which describe the maintenance and surveillance activities and results for each time period.

The reports may also include useful information on an assessment of the effectiveness of the decommissioning techniques used, a description of waste arisings, and costs.

5. RADIATION PROTECTION PROGRAMME

During decommissioning a radiation protection programme must be implemented to ensure that collective radiation doses4 received by the decommissioning personnel and members of the public are optimized, and that individual doses are kept within applicable dose limits required by the regulatory bodies. This radiological protection programme must contain at least the items in the following sub-sections.

5.1. RADIATION MEASUREMENTS FOR DECOMMISSIONING

Radiological measurements are an essential element of a decommissioning operation. These measurements should identify the magnitude and location of both deposited contamination and neutron activation products. For deposited contamination, the identity and quantity of all important radionuclides should be established by a sufficient number of measurements to provide a reasonable estimate o f the average and maximum levels o f contamination on plant facilities and equipment. For both activated materials and deposited contamination, the radiation exposure rates in different areas of the plant should be determined by actual measurements whenever practicable. These measurements should then be used in conjunction with calculated estimates of the amount of radionuclides present to guide decisions and actions for decommissioning.

Radiological measurements for decommissioning should begin before the start of actual decommissioning operations to identify the detailed radiological concerns to be considered in developing detailed decommissioning plans. Continual surveys during decommissioning are required to ensure that adequate radiological

4 The term ‘dose’ m eans ‘dose equivalent’ th roughout the report unless otherwise qualified.

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safety is being practised, to provide radiological information for up-to-date planning of detailed decommissioning procedures, and to assist in monitoring the progress of radioactivity removal. These radiological surveys include radiation measurements and analyses of isotopic composition of both smear samples and airborne radioactivity where necessary. Special surveys may be undertaken for unusual or abnormal conditions. Radiological protection surveillance after decommissioning is also required (see sub-section 5.5).

5.2. RADIATION DOSE CONTROLS AND EVALUATION

The information obtained from radiological measurements should be utilized in the preparation of the final details of the decommissioning plan for controlling and evaluating radiation doses.

This dose control should be an important factor in the contribution made to the total decommissioning plan. Decommissioning should be performed so that individual doses resulting from the decommissioning operation are within prescribed limits.

A personnel monitoring programme must be implemented to ensure that the doses are within the limits set by the regulatory bodies. This programme should include routine external monitoring and monitoring of radionuclides within the bodies of the personnel. Periodic medical examinations should be performed as required by the appropriate regulatory bodies.

Radiation dose controls and surveillance play an important role in the preparation of safe decommissioning work procedures. Their necessity and means of implementation must also be included as an integral part of staff training. Appropriate radiation dose controls should also be applied to all movement of potentially radioactive materials within or outside the facility.

5.3. EFFLUENTS RELEASED TO THE ENVIRONMENT

Discharges of radionuclides via airborne and liquid effluents must be controlled to ensure the protection of the general public.

Authorized limits for release of radionuclides in airborne and liquid effluents are established by the regulatory bodies. The releases should be measured and the results recorded in accordance with regulatory requirements. If releases approach or exceed authorized limits, corrective measures should be taken in conformance with requirements of the respective regulatory bodies.

Accurate, up-to-date records should be kept of all airborne and liquid effluent releases. Summary reports of this information should be issued routinely by the licensee to the appropriate authorities.

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Large quantities of radioactive wastes typically arise from decommissioning, and the forms of these wastes can be different from those arising during normal plant operation. Because of these circumstances, special treatments and handling techniques may be needed. The large quantity of radioactive waste will also place an added burden on the existing waste management facilities at the plant. Thus, special provisions may be required for waste management.

5.4. WASTE MANAGEMENT

Removal from the site and subsequent storage or disposal of radioactive solid wastes should adhere to national regulations and international guides for the safe transport and disposition of radioactive materials. Accurate, up-to-date records should be kept of all waste movements. Summary reports of this information should be issued by the licensee to the regulatory bodies.

5.5. ENVIRONMENTAL MONITORING

Radiation monitoring of the environment in the area surrounding the plant site should be performed during decommissioning and during the maintenance and surveillance periods following decommissioning to stages 1 and 2 until approval to discontinue is obtained from the regulatory bodies. This monitoring is done at selected locations and times to check the adequacy of the control of radioactive materials released into the environment, and to obtain a more direct assessment of radionuclide concentrations in the surroundings and the resulting radiation dose rates to the population.

Guidance for the regulatory bodies and the licensee for determining requirements for environmental monitoring associated with a decommissioning procedure can be found in the IAEA Safety Series Nos 41, 45 and 46. The principles therein should be applied to decommissioning of nuclear reactors to the extent possible.

5.6. POST-DECOMMISSIONING RADIOLOGICAL SURVEILLANCE

A detailed post-decommissioning radiological survey should be made to delineate the level and extent of the residual radioactivity within the facilities and on the plant site. This survey is needed to demonstrate compliance with the criteria for acceptable residual contamination levels established by the regulatory bodies for the specific condition in which the site and facility are being released.

Following decommissioning to stages 1 or 2, post-decommissioning surveillance should include a continuing programme of facility and site monitoring

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to ensure that the radionuclides released to the environment are within acceptable levels. The results of these surveys should be included in periodic postdecommissioning reports. The competent national authorities should review the monitoring programme and its results at regular intervals.

6. CRITERIA FOR RELEASE OF MATERIALS, FACILITY OR SITE

The decommissioning of nuclear facilities will result in materials and components that may be reused and those that may be considered as waste. If the radioactivity levels of materials or components exceed those prescribed, the items must be handled in accordance with appropriate radiological protection and control requirements. Similarly, materials recovered during decommissioning with radioactivity content so high as to prohibit their reuse must be considered as radioactive wastes. These materials must be processed and/or disposed of in accordance with appropriate radioactive waste management procedures and regulations. Materials with radioactivity levels below prescribed levels may be treated and managed in the same manner as other non-radioactive materials.

The various stages of decommissioning can result in a condition whereby all or part of the site, premises, materials and equipment can be released for unrestricted use with regard to their radioactivity levels. In this case, the levels of residual radioactivity on or within the unconditionally released site, premises, material, equipment and waste must be low enough to ensure that without any control or surveillance potential radiation exposure to people by any exposure pathway, either individually or collectively, will not be in excess of appropriately established dose limits.

The disposition of the radioactive materials from decommissioning, whether they are to be used for some further purpose or regarded as waste, generally does not require special regulations or treatments. The existing regulations and methodologies for dealing with similar materials generated during the course of a nuclear plant’s operating life will usually be applicable to the decommissioning programme, although special consideration may be needed because of the large volumes of material involved. Hence, the management of radioactive wastes arising from the decommissioning of nuclear reactors and their associated auxiliaries should be carried out in accordance with the relevant national radiological protection and waste management regulations.

All waste considered to have radioactivity levels acceptably low for unrestricted release can be dealt with as industrial waste. However, development of criteria for and establishment of these acceptable levels should be done by the appropriate regulatory bodies.

13


The methodologies that may be used in determining the classification of materials from decommissioning should take the following factors into account:

The amount and type of significant contamination from radionuclides

The amount and type of radioactivity with activated materials

The change in characteristics of residual radioactivity levels as a function of time

The potential of all residual radioactive sources to become a radiation hazard; this should be done taking into account all known pathways, including the direct exposure pathways of inhalation and ingestion, and indirect pathways through the air, water, food chains, and by reuse of materials.

6.1. UNCONDITIONAL OR UNRESTRICTED USE

Release for unconditional use or reuse of sites, premises, equipment or materials has as its objective the continued use or reuse without any regulatory control or monitoring for radiation protection. Hence, the methods used to determine acceptable residual radioactivity levels to enable premises, equipment, material, or sites to be used unconditionally should ensure that this objective can be achieved and continuously maintained without further assessment. The levels to be achieved will need to be defined and administered by the appropriate regulatory body.

6.2. CONDITIONAL OR RESTRICTED USE

When release on an unconditional basis is either not achievable or necessary the radiation control and monitoring requirements to be applied will remain within the established licensing control framework and limiting criteria of the regulatory body. In this regard it could be foreseen that a reactor may be only partially dismantled, that further development for nuclear purposes may take place at the same site, and that the remaining responsibility for the decommissioned plant would be incorporated in revised regulatory conditions. Similarly, plant items (materials and equipment) may be reused in other facilities, subject to appropriate radiological control and licensing conditions.

7. QUALITY ASSURANCE

As with most other nuclear activities, a strict quality assurance programme should be planned and initiated by the licensee before the decommissioning of a

14


nuclear reactor commences. The decommissioning quality assurance programme should be in accordance with the general quality assurance criteria and requirements adopted for the various phases of nuclear reactor design, construction and operation.

The objectives of the quality assurance programme are to ensure that all decommissioning activities are achieved satisfactorily, and that these achievements are accomplished in accordance with planned written procedures and instructions that have been reviewed and approved by appropriate experts and responsible personnel.

An appropriate staff that has responsibility for quality assurance should be established by the licensee in accordance with national practice. This staff should have the authority and responsibility to develop quality assurance requirements and to compare quality assurance performance with these requirements.

The duties and responsibilities of all decommissioning personnel (and organizations) involved and their lines of communication, approvals and authorities should be clearly defined in the quality assurance plan. The appropriate regulatory bodies should check and record, according to their own policies and regulations, the adequacy of the quality assurance and the other decommissioning units, and the competence of personnel engaged in decommissioning work.

Achievement of decommissioning objectives can be aided significantly by employing a thorough quality assurance analysis of the tasks to be performed.This analysis includes the identification of the skills required, the selection and training of personnel, the design, specifications, procurement and use of appropriate equipment, the employment of proper techniques, the determination of the standards or codes to be adopted, and the provision of the necessary verification and control activities.

Quality assurance control measures should be established to ensure that:

(a) Applicable regulatory requirements, criteria and limits are properly recognized and operations are measured for conformance

(b) Plant materials are properly handled, identified and controlled(c) Plant equipment is correctly functional, operated and transported(d) Decommissioning plans and technical documents and their modifications,

and decommissioning activities are properly reviewed and duly approved(e) Important systems, structures and components are regularly inspected(f) The measurements and tests carried out are appropriate to the condition

of the installation, and their interpretation is properly done(g) All important information relevant to decommissioning is adequately

documented, stored, and made retrievable to allow for future needs of the information.

15


DEFINITIONS

The following definitions are used in this report. These definitions agree with others used by the IAEA, with some minor exceptions, but may not necessarily conform to definitions adopted elsewhere fo r international use.

Acceptable Limits

Acceptable Contamination Levels for Unrestricted Use

Basic Radiation Dose Limit

Competent Authority

Contamination

Decommissioning

Decommissioning Stage

Decontamination

Limits acceptable to the regulatory body (also called authorized or regulatory limits).

Levels of radioactivity that meet specified levels for any use of the material without restrictions regarding radioactivity.

An upper limit of allowable radiation exposure as established by the regulatory body. (Dose limits are expressed in terms of dose equivalent, of which the unit is the sievert (Sv), lSv= U/kg = 100 rem).

A national authority designated or otherwise recognized as such by the Member State for a specific purpose (see Regulatory Body).

Undesired radioactive m atter or radionuclides that have been deposited on solid surfaces, or are present in solids, liquids or gases.

The work required for the planned permanent retirement of a nuclear facility from active service to bring it to the planned status. Thereafter the plant will be in a new regulatory situation. (Some Member States feel that a plant is not decommissioned until it is suitable for unrestricted use.)

The extent of decommissioning and the status of a facility after decommissioning. Three basic stages are proposed by the IAEA: storage with surveillance; restricted site release; unrestricted site release. Conditions for each of these stages are presented in the text.

The removal of radioactive contaminants with the objective of reducing the residual radioactivity level in or on materials within a nuclear facility or site.

17


Dismantlement or Dismantling

Facility

Induced Radioactivity

Licensee

Monitoring

Nuclear Reactor Plant

Off-site

Operating Organization

Owner

18

The planned removal of major structures, systems and components. In decommissioning, this involves removal of radioactive or contaminated material from the facility and site, to the extent of permitting release of the property for unrestricted use.

The physical complex of buildings and equipment within a site.

Radioactivity of the radionuclides produced within materials by neutron irradiation (also called activation).

The holder of a licence issued by the regulatory body to perform specific activities related to the siting, construction, commissioning, operation or decommissioning of a nuclear power plant.

The periodic or continuous measurement of radiation or radioactive contamination levels for purposes related to the assessment or control of radiation exposure in man and his environment.

A nuclear fission reactor or reactors together with all structures, systems and components necessary for safety and

for the production of heat or electricity or irradiation fluxes. This report relates to all classes of land-based thermal neutron reactors, including their radioactive ancillary plant and equipment.

Refers to any area outside the boundary line marking the limits of the plant site.

The organization authorized by the regulatory body to operate the plant or facility.

The organization that possesses (or holds title to) the facility and site.


Prescribed Limits Limits established or accepted by the regulatory body.

Public (or Population) Those persons who occupy areas beyondthe plant site.

Quality Assurance Planned and systematic actions necessary toprovide adequate confidence that an item or facility will perform satisfactorily in service.

Radiation Exposure Pathways The routes by which radioactive materialscan reach and/or irradiate man. These include carrying of radioactive materials to man by air or water followed by inhalation or ingestion; carrying of radioactive materials through foods or animals that absorb the materials; or by direct radiation from sources external to the body.

Radioactive Waste Any material containing or contaminatedwith radionuclides at concentrations or radioactivities greater than exempt quantities established by the competent authorities, and for which there is no foreseen use.

Radioactive Waste Management All activities, administrative and operational,that are involved in the handling, treatment, conditioning, transportation, storage and disposal of radioactive waste.

Radiological Safety

Regulatory Body

Protection of all persons from undue radiological hazards.

A national authority or a system of authorities designated by a Member State, assisted by technical and other advisory bodies, and having the legal authority for conducting the licensing process, for issuing licences and thereby for regulating nuclear power plant siting, design, construction, commissioning, operation, shut-down and decommissioning or specific aspects thereof.1

This national au tho rity could be either the governm ent itself, o r one o r m ore departm ents o f the governm ent, o r a body or bodies specially vested w ith appropriate legal authority .

19


Restricted Use The use of materials or a facility is restricted by a regulatory process because of its potential hazards.

Site

Site Personnel

Stage

Surveillance

Survey

The area containing the plant, defined by a boundary and under effective control of the operating organization.

All persons working on the site, either permanently or temporarily.

See Decommissioning Stage.

Those activities necessary to ensure that the facility and site remain in a safe condition (including inspection and monitoring of the site, maintenance of barriers to limit access to radioactive materials left on the site, and prevention of activities on the site that might impair these barriers).

A systematic investigation and measurement of radiation and/or radionuclide levels and radioactive contamination levels. The results are usually followed by an evaluation of the radiation hazards from the radioactive materials present.

20


BIBLIOGRAPHY

BAINBRIDGE, G .R ., et al., Decommissioning of Nuclear Facilities: A Review Status, At. Energy Rev. 1 2 (1 9 7 4 ) 145.

BRIDENBAUGH, D.G., TURNER, R.L., LLOYD, G.B., “ M aintenance and in-service inspection experience at large nuclear pow er plants” , Experience from Operating and Fuelling Nuclear Power Plants (Proc. Symp. Vienna, 1974), IAEA, Vienna (1974) 317.

COMMISSION OF THE EUROPEAN COMMUNITIES, Decommissioning of LWR Nuclear Power Plants, prepared by Nuklear-Ingenieur Service GmbH., Hanau (FR G ), Rep. EUP 5728 d (1976).

DETILLEUX, E.J., “ Status of the decommissioning program m e of the Eurochem ic reprocessing p lan t” , Management o f Wastes from the LWR Fuel Cycle (Proc. Int. Symp. Denver, 1976), USAEC Technical Inform ation Center, Oak Ridge, TN, CONF-76-0701 (1976).

DETILLEUX, E., LENNEMANN, W.L., “ Criteria, standards and policies regarding decommissioning of nuclear facilities” , Nuclear Power and its Fuel Cycle (Proc. Int. Conf. Salzburg, 1977), IAEA, Vienna 4 (1977) 807.

ENERGY RESEARCH AND DEVELOPMENT ADMINISTRATION, Radiological Surveillance at ERDA Installations, Rep. USERDA 77-24 (1976).

INTERNATIONAL ATOMIC ENERGY AGENCY, Decommissioning o f Nuclear Facilities (Proc. Int. Symp. Vienna, 1978), IAEA, Vienna (1979).

INTERNATIONAL ATOMIC ENERGY AGENCY, Decommissioning of Nuclear Facilities, Technical D ocum ent IAEA-179, Vienna (1975).

INTERNATIONAL ATOMIC ENERGY AGENCY, Decommissioning of Nuclear Facilities, Technical D ocum ent IAEA-205, Vienna (1977).

INTERNATIONAL ATOMIC ENERGY AGENCY, Objectives and Design of Environm ental M onitoring Programmes fo r Radioactive C ontam inants, Safety Series No. 41, IAEA, V ienna(1975).

INTERNATIONAL ATOMIC ENERGY AGENCY, Principles for Establishing L im its fo r the Release o f Radioactive Materials in to the Environm ent, Safety Series N o.45, IAEA, Vienna (1978).

INTERNATIONAL ATOMIC ENERGY AGENCY, M onitoring o f A irborne and Liquid Radioactive Releases from Nuclear Facilities to the Environm ent, Safety Series N o.46,IAEA, Vienna (1978).

INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for Safe T ransport o f R adioactive Materials 1973 Revised Edition (As Am ended), Safety Series N o.6, IAEA, V ienna (1979).

INTERNATIONAL ATOMIC ENERGY AGENCY, Safe Handling of Radionuclides 1973 Edition, Safety Series N o .l , IAEA, Vienna (1973).

INTERNATIONAL ATOMIC ENERGY AGENCY, Safety in Nuclear Pow er P lant O peration, including Commissioning and Decommissioning, A Code of Practice, Safety Series N o.50-C-0, IAEA, Vienna (1978).

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Principles o f Environm ental M onitoring Related to the Handling of Radioactive Materials, ICRP No.7 (1966).

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INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, R ecom m endations o f the In ternational Commission on Radiological P rotection, Publication 26, Pergam on Press, L ondon (1977).

JENKINS, C.E., e t al., Technology, Safety and Costs o f Decommissioning a Reference Small Mixed Oxide Fuel Fabrication Plant, B attelle Pacific Northw est Labs., Richland, WA, R eport fo r the US Nuclear R egulatory Commission, NUREG/CR-129 (Feb. 1979).

KAERNBRAENSLESAEKERHET, Technology and Costs for Dismantling a Swedish Nuclear Power Plant, Rep. KBS-TR-79-22 (Oct. 1979).

KONZEK, G .J., SAMPLE, C.R., Decommissioning of Nuclear Facilities — An A nnotated Bibliography, Battelle Pacific N orthw est Labs., Richland, WA, R eport for the US Nuclear Regulatory Commission, NUREG/CR-0131 (Oct. 1978).

MANION, W.J., LAGUARDIA, T.S., An Engineering Evaluation o f Nuclear Power R eactor Decommissioning Alternatives, A tom ic Industrial Forum , Inc., Rep. AIF/NESP-009 (Nov. 1976).

MARTIN, A., et al., A Prelim inary S tudy of the Decommissioning of Nuclear R eactor Installations, Associated Nuclear Services, London, Rep. No.155 (Ju ly 1977).

MOORE, E.B., et al., Decommissioning Nuclear Facilities: A Review and Analysis o f C urrent Regulations, B attelle Pacific Northw est Labs., Richland, WA, R eport for the US Nuclear Regulatory Commission, NUREG/CR-0671 (Aug. 1979).

MOORE, E.B., et al., Facilitation of Decommissioning Light W ater Reactors, B attelle Pacific Northw est Labs., Richland, WA, R eport fo r the US Nuclear Regulatory Commission, N U REG /CR-0569 (Dec. 1979).

NUCLEAR REGULATORY COMMISSION, S tate W orkshops fo r Review of the Nuclear Regulatory Com mission’s Decommissioning Policy (Proc. Confs Philadelphia, A tlanta, A lbuquerque, Sept. 1978), Office o f Standards Developm ent, W ashington, DC, Rep. NUREG/ CP-0003 (Dec. 1978).

NUCLEAR REGULATORY COMMISSION, S tate W orkshops fo r Review of the Nuclear Regulatory Com mission’s Decommissioning Policy (Proc. Conf. Sept. 1979), Office o f Standards Developm ent, W ashington, DC, Rep. NUREG/CP-0008 (Dec. 1979).

O’DONNEL, F.R ., e t al., Potential R adiation Dose to Man from Recycle o f Metals Reclaimed from a Decom m issioned Nuclear Power Plant, Oak Ridge National Lab., TN, R eport fo r the US Nuclear R egulatory Commission, NUREG/CR-0134 (Dec. 1978).

Saxton Decommissioning Plan and Safety Analysis R eport, Saxton Nuclear Experim ental Corp., Reading, PA (April 1972).

SCHNEIDER, K .J., e t al., Technology, Safety and Costs of Decommissioning a Reference Fuel Reprocessing Plant, B attelle Pacific N orthw est Labs., Richland, WA, R eport for the US Nuclear Regulatory Commission, NUREG-0278 (Oct. 1977).

SMITH, R .I., e t al., Technology, Safety and Costs of Decommissioning a Reference Pressurized R eactor Pow er S tation, B attelle Pacific N orthw est Labs., Richland, WA, R eport fo r the US Nuclear R egulatory Commission, NUREG/CR-0130 A ddendum (Aug. 1979).

SMITH, R .I., et al., Technology, Safety and Costs o f Decommissioning a Reference Low Level Waste Burial G round, B attelle Pacific N orthw est Labs., Richland, WA, R eport fo r the US Nuclear Regulatory Commission, NUREG/CR-0570, Vols 1 and 2 (Feb. 1980).

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SMITH, R .I., KONZEK, G J . , KENNEDY, W.E., Technology, Safety and Costs of Decommissioning a Reference Pressurized W ater R eactor Power Station, Battelle Pacific Northw est Labs., Richland, WA, R eport for the US Nuclear Regulatory Commission, NUREG/ CR -0130 (June 1978).

UNITED NATIONS, Sources and Effects o f Ionizing Radiation, United Nations Scientific Com m ittee on the E ffects o f A tom ic Radiation 1977 report to the General Assembly, w ith annexes, U nited Nations sales publication E.77, IX 1, New York (1977).

UNITED POWER ASSOCIATION, Final Elk River R eactor Program Report, USAEC Chicago O perations Office, Rep. C OO -651-93 Revised (Nov. 1974).

UNITED STATES ATOMIC ENERGY COMMISSION, T erm ination o f O perating Licenses for Nuclear Reactors, R egulatory G uide 1.86, USAEC D irectorate o f Regulatory Standards, W ashington, DC (June 1974).

USAEC TECHNICAL INFORMATION CENTER, OAK RIDGE, D econtam ination and Decommissioning (D and D) o f ERDA Facilities (Proc. 1st Conf. Idaho Falls, 1975), CONF-750827 (Sept. 1975).

UNITED STATES NUCLEAR REGULATORY COMMISSION, Inform ation Relevant to Ensuring th a t Occupational R adiation Exposures at Nuclear Power S tations will be As Low As is Reasonably Achievable, Regulatory Guide 8.8, W ashington, DC (1977).

UNITED STATES NUCLEAR REGULATORY COMMISSION, Plan for Reevaluation o f NRC Policy on Decommissioning Nuclear Facilities, Office o f Standards Developm ent, W ashington, DC, Rep. NUREG-0436, R ev.l (Dec. 1978).

UNSWORTH, G.N., Decommissioning of the Candu-PHW Reactor, A tom ic Energy of Canada L td., Pinawa, M anitoba, W hiteshell Nuclear Research Establishm ent, Rep. AECL-5687.

23


LIST OF PARTICIPANTS

BELGIUM

Baekelandt, L.

de Clercq, H.

Dozinel, P.

Ministere de la Sante publique et de la famille, Service des nuisances,

Cite administrative de l’Etat, Quartier Vesale, B-1010 Brussels

Institut d’hygifene et d’epidemiologie,Rue Juliette Wytsman 14,B-1050 Brussels

SociSte de traction et d’61ectricit6,Rue de la Science 31,B-1040 Brussels

CANADA

Unsworth, G.N. Atomic Energy of Canada, Ltd.,Whiteshell Nuclear Research Establishment, Pinawa, Manitoba ROE ILO

FRANCE

Cregut, A.

Jacquemin, M.

Lurie, R.

CEA, Centre de Marcoule,Institut de protection et de surete nucleaire (IPSN), BP 170F-30200 Bagnols-sur-Ceze

CEA, Institut de protection et de surete nucleaire (IPSN),

BP 6,F-92260 Fontenay-aux-Roses

CEA, Centre de Marcoule,Institut de protection et de surete nucleaire (IPSN), BP 170,F-30200 Bagnols-sur-Ceze

GERMANY, FEDERAL REPUBLIC OF

Broecker, B. Nordwestdeutsche Kraftwerke AG., Schone Aussicht 14,D-2000 Hamburg 76

25


INDIA

Sharma, S.K.

ITALY

Buono, A.

Cigna, A.

Saponaro, G.

SWEDEN

Forsstrom, H.

Mandahl, B.

Pettersson, B.G.

SWITZERLAND

Aeppli, J.

Perotto, C.

UNITED KINGDOM

Lunning, W.H. (Chairman)

Bhabha Atomic Research Centre, Trombay,Bombay 400085

Ente Nazionale per l’Energia Elettrica,Via G.B. Martini 3,1-00198 Rome

Comitato Nazionale per l’Energia Nucleare (CNEN)-Casaccia,

C.P. 2400 1-00100 Rome

Comitato Nazionale per l’Energia Nucleare (CNEN), Viale Regina Margherita 125,1-00198 Rome

Statens Vattenfallsverk,Fack, S-162 87 VaUingby

Oskarshamnsverkets Kraftgrupp AB., P.O. Box 1746,S-l 11 87 Stockholm

Statens Vattenfallsverk,Fack, S-l62 87 Vallingby

Division pour la securite des installations nucleaires, CH-5303 Wiirenlingen

Centrale nucleaire de Muhleberg,CH-3202 Muhleberg

United Kingdom Atomic Energy Authority, Risley, Warrington,Cheshire WA3 6AT

26


Gregory, A.R. Central Electricity Generating Board, Barnwood,Gloucester GL4 7RS

Kewley, S.J. South of Scotland Electricity Board, Cathcart House,Inverlair Avenue,Glasgow

Regan, J.D. Nuclear Power Company Ltd., Booths Hall,Risley, Warrington,Cheshire WA3 6BZ

Saddington, K. United Kingdom Atomic Energy Authority, Risley, Warrington,Cheshire WA3 6B2

UNITED STATES OF AMERICA

Conti, E. United States Nuclear Regulatory Commission,Washington, DC 20555

Manion, W.J. Nuclear Energy Services Inc.,Shelter Rock Road,Danbury, Connecticut 06810

ORGANIZATIONS

COMMISSION OF EUROPEAN COMMUNITIES (CEC)

Benco, A. C.C.R. Ispra,1-21020 Ispra, Italy

Huber, B. Rue de la Loi 200,B-1049 Brussels, Belgium

INTERNATIONAL UNION OF ELECTRICAL ENERGY PRODUCERS AND DISTRIBUTORS/UNION INTERNATIONALE DES PRODUCTEURS ET DISTRIBUTEURS D’ENERGIE ELECTRIQUE (UNIPEDE)

Weeks, R.J. Central Electricity Generating Board,Beckwith Knowle,Otley Road, Harrogate,Yorkshire HG3 IPS,United Kingdom

27


NUCLEAR ENERGY AGENCY OF THE OECD

Maestas, E. 38 Boulevard Suchet,F-75016 Paris, France

SCIENTIFIC SECRETAR Y

Lanni, L. Division of Nuclear Safety and EnvironmentalProtection,

IAEA, P.O. Box 100,A-1400 Vienna, Austria

COMPILA TION OF REPOR T

Schneider, K.J. Division of Nuclear Safety and Environmental Protection,

IAEA, P.O. Box 100,A-1400 Vienna, Austria

28


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