Comprehensive Training on Nuclear Decommissioning Procedures

Module XVIII - Decommissioning

Ferenc

Adorjan

Expert in nuclear safety (

Hungary)

ferencadorjan@gmail.com

Module XVIII - Decommissioning

Module XVIII - Decommissioning

2

Lerning objectives

After completing this Module, the trainee will

be able to:

1.

Define decommissioning.

2.

List the aspects of decommissioning.

3.

List the strategies for decommissioning.

4.

State the main IAEA Standards relating to

decommissioning.

Module XVIII - Decommissioning

3

Contents

1.

Decommissioning Process

2.

Planning of Decommissioning

3.

Conduct of Decommissioning

4.

Completion of Decommissioning

5.

Management

3

Module XVIII - Decommissioning

INTRODUCTION

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Module XVIII - Decommissioning

INTRODUCTION

•

Aspects of decommissioning typically include:

–

Planning for decommissioning

,

–

Conducting decommissioning actions and

–

Terminating the authorization

.

•

Aspects of decommissioning have to be considered

throughout all five major stages of the lifetime of a

nuclear facility (

siting, construction, commissioning,

operation and decommissioning

).

Module XVIII - Decommissioning

INTRODUCTION

•

Decommissioning actions

–

Activities as described in the final decommissioning plan

(decontamination, dismantlement, waste management and

clean-up).

–

Completed when the approved end state has been reached.

–

End state - the release of the facility from regulatory control.

•

Strategies for decommissioning:

–

Immediate dismantling or

–

Deferred dismantling or

–

Entombment

Module XVIII - Decommissioning

IAEA Standards

Decommissioning of Facilities,

IAEA General Safety Requirements No. GSR Part 6

•

Requirements related to:

–

Protection of people and protection of environment,

–

Responsibilities associated with decommissioning,

–

Management of decommissioning,

–

Decommissioning strategy,

–

Financing,

–

Planning of decommissioning during the lifetime of the facility,

–

Conduct of decommissioning actions and

–

Completion of decommissioning actions.

Module XVIII - Decommissioning

IAEA Standards

Safety Guides regarding the decommissioning of specific types of facility:

–

SSG-47 Decommissioning of Nuclear Power Plants, Research

Reactors and Other Nuclear Fuel Cycle Facilities (revision of WS-

G-2.1 and 2.4)

;

–

Decommissioning of Medical, Industrial and Research Facilities,

IAEA Safety Guide WS-G-2.2 (1999. Under revision).

General Safety Requirements and Guides also includes issues on

decommissioning.

Module XVIII - Decommissioning

IAEA Standards

Safety Guides addressing important aspects of

decommissioning, that are of interest of all types of

facilities are:

–

Safety Assessment for the Decommissioning of Facilities Using

Radioactive Material

,

 IAEA Safety Standards Series No. WS-G-5.2;

–

Release of Sites from Regulatory Control on Termination of

Practice

s

, IAEA Safety Standards Series No. WS-G-5.1;

–

Application of the Concepts of Exclusion, Exemption and

Clearance, IAEA Safety Standards Series No. RS-G-1.7.

Module XVIII - Decommissioning

DECOMMISSIONING PROCESS - Learning

objectives

1.

Describe the protection of people and the

environment.

2.

List the responsibilities of the government, the

regulatory body,  the licensee.

3.

Describe the decommissioning option.

4.

Define the immediate and deferred dismantling.

5.

Describe the facilitating decommissioning.

Module XVIII - Decommissioning

DECOMMISSIONING PROCESS

•

Time period of decommissioning  stage may range from a

few years to decades

•

Nuclear installation or its remaining prats may also be

considered decommissioned if incorporated into a new or

existing facility

–

Decommissioning of a nuclear installation on a multifacility site.

•

Radiation protection of both workers and members of the

public should be provided

–

During decommissioning and further use of the site.

Module XVIII - Decommissioning

Protection of people and environment

Graded approach 

used for all aspects of decommissioning in

determining the scope and level of detail for any particular

facility. In consistency with the magnitude of the possible

radiation risks.

The final decommissioning plan is supported by a 

safety

assessment

 addressing the planned decommissioning

actions and incidents that may occur or situations that may

arise during decommissioning.

Module XVIII - Decommissioning

Responsibilities

Nuclear facility taken out of service → responsibility may be

transferred to a different organization 

(recommended)

Operating organization of the installation undergoing

decommissioning is ultimately responsible for the safety

.

Responsibilities of the government 

– To establish and

maintain a governmental, legal and regulatory framework

for all aspects of decommissioning.

Module XVIII - Decommissioning

Responsibilities

Responsibilities of the regulatory body

•

Authorise and oversight of decommissioning;

–

Needs to establish safety requirements, adopt regulations and

guides, including management of the resulting radioactive waste,

and takes actions to ensure that the regulatory requirements are

met.

Responsibilities of the licensee

•

Implements planning for decommissioning, carries out the

decommissioning actions;

–

The licensee is responsible for all aspects of safety, radiation and

environmental protection during decommissioning.

Module XVIII - Decommissioning

Decommissioning strategy

–

Immediate dismantling

- removal of all radioactive materials

from the site (allowing unrestricted release);

•

Decommissioning actions begin shortly after the permanent shutdown.

•

Equipment, structures, systems and components of a facility containing

radioactive material are removed and/or decontaminated.

–

Deferred dismantling

 - 

when dismantling is postponed;

•

All or part of a facility containing radioactive material is either processed

or placed in such a condition that it can be put in safe storage and the

facility maintained until it is subsequently decontaminated and/or

dismantled.

•

Facility containing radioactive material is either processed or placed in

such a condition that it can be put in safe storage.

Module XVIII - Decommissioning

Decommissioning strategy

Selection of a normal decommissioning strategy is justified

by the licensee 

(legislation, safety, resources, site use,  etc).

Licensee and Regulator should also consider: 

•

Sudden shutdown

– Decommissioning strategy reviewed to

determine of revision of strategy is required.

•

Shutdown caused by an accident

– Before approved

decommissioning plan is implemented, facility needs to be

brought to a safe configuration.

Module XVIII - Decommissioning

Decommissioning strategy

Issues to be considered during the selection process

•

Evaluation of various decommissioning options is

performed with special emphasis on the balance between:

*with regard  decommissioning timeline .

Module XVIII - Decommissioning

Safety

•

Radiological and non-radiological hazards are identified in a formal

safety assessment;

–

To provide appropriate protective measures to ensure safety of workers and

the public and protection of  the environment.

•

Decommissioning may involve operations that may not be normal

during the operation of the installation;

–

Significance of non-radiological hazards may be increased,

–

Problem of ageing of the reactor’s components becomes important when

deferred decommissioning is being considered.

•

Safety assessment helps to ensure safety of the decommissioning

process.

Module XVIII - Decommissioning

Financing

•

Responsibilities in respect of financial provisions for

decommissioning are set out in national legislation.

–

To provide and ensure that adequate financial resources are available when

needed to ensure safe decommissioning.

•

All activities described in the decommissioning plan are included in

the estimation of the cost for decommissioning.

•

The cost estimate is updated on the basis of the periodic update of

the initial or final decommissioning plan.

•

Decommissioned facility is released with restrictions on its future

use – financial resources are available for monitoring, surveillance

and control of the facility throughout the necessary time period.

Module XVIII - Decommissioning

Availability of existing expertise

•

The availability and utilization of facility specific expertise

is highly important for efficient and safe operations during

decommissioning.

•

Expertise could:

–

Decrease the potential for events such as industrial accidents or

overexposures and

–

May help to reduce problems associated with loss of a corporate

memory, and retraining or recruiting of new personnel.

Module XVIII - Decommissioning

Considerations relating to the public

•

Issue of public concerns surrounding decommissioning is

largely centred on the concern of waste disposal.

•

Public opinion is also influenced by other factors like:

–

Local factors, including the anticipated development and use of

land after decommissioning;

–

Local employment considerations after cessation of facility

operation and during decommissioning; and

–

Visual impact and the public attitude.

Module XVIII - Decommissioning

Facilitating decommissioning

Requirements for decommissioning are considered:

I.

At the design stage for a new reactor installation or

II.

As soon as possible for existing installations.

Considerations at the design and construction phase

A baseline background radiological characterization of the site for the

proposed facility and the facility itself need to be undertaken.

Design features that need to be considered for decommissioning:

–

Careful selection of materials and optimization of the

facility’s design, layout and access routes.

Module XVIII - Decommissioning

Facilitating decommissioning

Considerations during facility operation

Accurate and relevant records.

Records are configured so that those relevant to decommissioning may

be readily identified.

–

In addition to drawings and diagrams, photographic records of the

construction and operational phases of the reactor lifetime are kept.

During operations, consideration is given to 

minimizing the extent of

contamination of structures and surfaces, segregation of different

categories of wastes, and avoidance and prompt clean-up of spillages

and leaks

.

Module XVIII - Decommissioning

PLANNING OF DECOMMISSIONING-  Learning

objectives

1.

The planning of decommissioning.

2.

The objectives and steps of a safety

assessment.

3.

The hazards during decommissioning.

4.

The results of regulatory review of a safety

assessment.

Module XVIII - Decommissioning

PLANNING OF DECOMMISSIONING

•

A decommissioning plan

is prepared by licensee for each nuclear

facility.

•

The operating organization plans for adequate financial resources to

ensure the decommissioning of a nuclear facility.

•

Three stages of planning are envisaged: initial, ongoing and final;

–

Degree of detail will increase from the initial to the final decommissioning

plan.

•

Information on type of safety related documents needed are

provided in IAEA Safety Report Standard Format and Content for

Safety Related Decommissioning Documents.

Module XVIII - Decommissioning

Initial planning of decommissioning

Initial decommissioning plan is submitted with the

application for authorization to operate the facility;

–

To demonstrate the feasibility of decommissioning.

Initial plan is updated as necessary with:

–

Operational experience gained,

–

Lessons learned from the decommissioning of similar facilities,

–

New or revised safety requirements, or

–

Technological developments relevant to the selected

decommissioning strategy.

Module XVIII - Decommissioning

Final Planning of decommissioning

Licensee informs regulatory body about planned shutdown,

when time of the permanent shutdown of a facility is

known.

Updates of the final decommissioning plan include:

–

Experience gained in decommissioning,

–

New or revised safety requirements, or

–

New or revised national regulations.

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Module XVIII - Decommissioning

Safety assessment

•

Objectives of safety assessment are:

–

To support the selection of the decommissioning strategy, the development

of a decommissioning plan and associated specific decommissioning

activities;

–

To demonstrate that exposures of workers and of the public are as low as

reasonably achievable (ALARA) and do not exceed the relevant limits or

constraints.

•

Safety assessment:

–

Forms an integral part of the decommissioning plan,

–

Must be commensurate with the complexity and potential hazard of the

installation,

–

Need to be consistent with the decommissioning plan and with other relevant

national and site specific strategies and requirements.

Module XVIII - Decommissioning

Safety assessment - General considerations

In development and review of safety assessment 

graded

approach

 is applied – a process by which the level of

analysis, the documentation and the actions necessary to

comply with the safety requirements and criteria are

commensurate with the following factors:

–

Purpose and scope of the safety assessment;

–

Uncertainty issues, radiological hazards and likelihood of hazards;

–

Complexity, safety requirements and availability of applicable

safety assessment.

Module XVIII - Decommissioning

Safety assessment content

Description of the installations/facilities and of the

decommissioning activities

•

Description of the installations/facilities include:

–

Site and local infrastructure 

– dose and/or risk calculations,

–

Installations/facilities

 – safety functions and their associated SSCs,

–

Inventory of radioactive material 

– relevant radionuclides and

calculated and measured activity; the radionuclide distribution and

the dose rate distribution,

–

Operational history

– operational records, post-operational on-site

and off-site

surveys and information from ongoing decommissioning

activities.

Module XVIII - Decommissioning

Safety assessment - Hazards during

decommissioning

All relevant hazards to workers, public and the environment

are included in decommissioning safety assessment:

–

Radiation exposures,

–

Toxic and other dangerous exposures,

–

Industrial hazards.

Initiating events includes those arising 

internally

 from the

decommissioning activities, arising 

externally

and

human

induced

;

–

Initiating event 

– meaning an identified event that leads to

anticipated operational occurrences or accident conditions and

that challenges safety functions.

Module XVIII - Decommissioning

Safety assessment - Defence-in-depth

Defence-in-depth principle used to:

–

Prevent escalation of anticipated operational occurrences and

–

Maintain effectiveness of physical barriers.

This include:

–

Operational limits, controls and conditions to prevent adverse

consequences

;

–

Protective measures which ensure that any accidents will not

result in significant harm to workers, the public or the

environment

;

and

–

Mitigate the consequences of accidents that could occur

.

Module XVIII - Decommissioning

Safety assessment - Safety functions

Safety functions should not be compromised during

decommissioning:

–

Control of reactivity,

–

Cooling of radioactive material,

–

Confinement of radioactive material,

–

Shielding,

–

Radiation detection and actuation of alarms,

–

Fire suppression and ventilation.

Module XVIII - Decommissioning

Safety assessment - Long term safety

Decommissioning should not not impose unacceptable

hazards or undue burdens on future generations.

For deferred dismantling safety assessment demonstrate

that installation/facilities will:

–

Meet relevant safety requirements and criteria in dismantling

period and

–

Can be safely decommissioned in future.

Module XVIII - Decommissioning

Safety assessment – managing of

Uncertainties

All known uncertainties should be taken into account;

–

Quality, reliability and availability of information from the characterization of

the installations/facilities may be limited;

–

Clean-up activities may not be well defined; and

–

Scenarios and the stages in the decommissioning plan may need to be revised

on the basis of knowledge gained from previous stages in the process or from

other similar activities at other facilities or sites.

•

Where uncertainties are significant, the safety assessment considers

applying a phased approach to the safety assessment for

decommissioning.

–

Addressing individual phases and/or stages of the decommissioning plan so as

to reduce the uncertainties as decommissioning progresses.

Module XVIII - Decommissioning

Safety assessment

Results of safety assessments – demonstrate compliance

with regulatory requirements and criteria expressed in terms

of effective dose or in terms of risk.

Safety measures (engineered and procedural) 

must be

commensurate with the likelihood of the occurrence of

accidents and their possible radiological consequences.

Module XVIII - Decommissioning

Regulatory review of the safety assessment

•

The principal 

objectives of regulatory reviews

of safety

assessment are:

–

To consider whether the safety assessment provides an

appropriate basis to support the proposed decommissioning

strategy, plan and activities;

–

To support the authorization process for the decommissioning

strategy, plan and activities by confirming that all relevant safety

requirements and criteria have been met;

–

To identify any regulatory limits and conditions that will need to

be applied during decommissioning or before decommissioning

activities may be commenced; and

–

To provide an input into the process of releasing the site from

regulatory control.

Module XVIII - Decommissioning

Regulatory review of the safety assessment

The 

results of the review

of the safety assessment demonstrate:

–

The safety assessment is consistent with the decommissioning plan and other

related safety assessments;

–

Decommissioning activities are optimized with due regard to dose and risk

constraints for planned activities;

–

Suitable and sufficient safety measures (procedural measures and engineered

safety features) will be in place so that the decommissioning activities can be

carried out safely and in accordance with all relevant safety requirements and

criteria, and in an optimized manner;

–

Surveillance measures and maintenance measures are adequate to ensure

safety;

–

Emergency planning and preparedness during decommissioning are adequate;

and

–

Good engineering practice has been used in developing the proposals for

decommissioning.

Module XVIII - Decommissioning

CONDUCT OF DECOMMISSIONING - Learning

objectives

1.

 Critical tasks of decommissioning.

2.

State the concerns with fuel removal.

3.

The importance of containment regarding

the decommissioning.

4.

The decontamination.

5.

The final radiological survey.

Module XVIII - Decommissioning

CONDUCT OF DECOMMISSIONING

•

Decommissioning techniques shall be selected such that:

–

Protection of workers, the public and the environment are optimized,

–

Generation of waste is minimized, and

–

Potential negative impact on storage and disposal of waste is minimized.

•

As decommissioning actions progress (decontamination, cutting and

handling of large components) new hazards may arise.

–

Impact of these actions on safety shall be assessed and managed.

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Module XVIII - Decommissioning

Critical tasks of decommissioning

Initial characterization of decommissioning

Survey of radiological an non-radiological hazards:

–

Important input for safety assessment,

–

Input for implementing a safe approach during the work,

–

Conducted to identify the inventory and location of radioactive and other

hazardous materials.

Radiation and contamination maps are prepared with adequate

number of radiation and contamination surveys.

Inventory of all hazardous chemicals present in the installation should

be conducted.

Module XVIII - Decommissioning

Critical tasks of decommissioning

Fuel removal from reactors

Fuel should be removed prior to conduct of decommissioning actions;

–

Spent fuel removal from reactor at the end of its operational lifetime is part of

operation.

Procedures for the removal, storage and shipment of fuel are the same

as those used during normal operation.

On-site interim storage facilities for spent fuel – care is taken with

respect to possible interference with future decommissioning activities

at the reactor installation.

Module XVIII - Decommissioning

Critical tasks of decommissioning

Containment maintenance and modification

Containment systems should be retain as long as necessary and

feasible;

–

Containment is important element of defence-in-depth to prevent the

movement of residual radionuclides.

Adequate containment is planned and demonstrated when the

airborne contamination may be raised:

–

Containment related barriers or devices are removed or altered,

–

Cutting and dismantling operations are carried out.

Module XVIII - Decommissioning

Critical tasks of decommissioning

Decontamination

Decontamination are 

activities directed to the removal or reduction of

radioactive contamination

.

Decontamination may be applied to:

–

Internal or external surfaces of components and systems,

–

Structural surfaces, and

–

Tools employed in decommissioning.

Decontamination can be conducted before, during or after dismantling.

Module XVIII - Decommissioning

Critical tasks of decommissioning

Decontamination

The objectives of decontamination include:

–

Reduction of exposures during decommissioning activities;

–

Minimization of the volume of the categories of material to be classified or

disposed of as solid radioactive waste; and

–

Increase of the possibility of recycle and reuse of equipment, materials or

premises.

Important to exchange information and experience;

–

Especially for smaller facilities, where development of new and optimised

techniques is less feasible.

Module XVIII - Decommissioning

Critical tasks of decommissioning

Dismantling

•

Special tools and devices may be needed during dismantling – tools

and devices should be tested before their use.

•

Considerations for determining most effective and safe dismantling:

–

Equipment is simple to operate, decontaminate and maintain;

–

Effective methods for controlling airborne radionuclides implemented;

–

Effective control of discharges to the environment;

–

Underwater dismantling and cutting – water processing to ensure good visibility

and assist in effluent treatment;

–

Effect of each task on adjacent systems and structures are evaluated;

–

Waste containers, handling systems and routes are defined in advance.

Module XVIII - Decommissioning

Critical tasks of decommissioning

Final radiological survey

Survey of the residual radionuclides at the facility site must be

performed after completion of decommissioning;

–

To demonstrate that the residual activity complies with the criteria set by the

national regulatory authority and the decommissioning objectives have been

fulfilled.

Final survey report includes:

–

Criteria used;

–

Methods and procedures to ensure that the criteria were met; and

–

Measurement data, including appropriate statistical analysis and systematic

approaches used.

Module XVIII - Decommissioning

Additional aspects of decommissioning

actions

Radiation protection

The radiation protection programme ensures that 

radiation protection

is optimized and that doses are kept within appropriate limits

.

During decommissioning special situations may need to be considered,

which may require:

–

Use of specialized equipment and

–

Implementation of certain non-routine procedures.

Module XVIII - Decommissioning

Radiation protection

The radiation protection programme should be clearly set

out in the decommissioning plan.

–

Involved in its execution properly trained and have access to

appropriate equipment for carrying out radiation surveys.

Decommissioning work should be planned and carried out

using work order procedures and radiation work permits,

with adequate involvement of radiation protection

expertise.

Additional aspects of decommissioning

actions

Module XVIII - Decommissioning

Additional aspects of decommissioning

actions

Material management

Material management is considered in the decommissioning plan and

the safety assessment to ensure radiological protection.

Radiological consequences are assessed from:

–

The management of material arising from decommissioning, including metal,

building rubble, liquids and other material destined for release from

regulatory control; and

–

The management of radioactive waste on the site, including any processing,

handling and storage of the waste.

The safety assessment for decommissioning need to be consistent with

relevant site and national strategies and regulatory requirements for

the management of material and radioactive waste.

Module XVIII - Decommissioning

Additional aspects of decommissioning

actions

Waste management

A waste management plan – considers the different categories of

waste produced during decommissioning and aim at the safe

management of such wastes.

Optimizing waste management and minimizing cross-contamination

and secondary waste generation.

Reductions in volumes of radioactive waste can be achieved through:

–

Decontamination programmes

–

Controlled dismantling techniques

–

Contamination control

Module XVIII - Decommissioning

Additional aspects of decommissioning

actions

Waste management

•

Sorting of waste materials,

•

Effective processing,

•

Reuse and recycle strategies, and

•

Release of low activity materials from regulatory control.

Integrated approach to balance waste minimization goals and radiation

exposures as low as reasonably achievable.

Considered disposal with no suitable waste disposal sites available:

–

Preparing and maintaining the installation in safe enclosure;

–

Dismantling the installation and storing the generated waste in appropriate

temporary waste storage facilities

Module XVIII - Decommissioning

Additional aspects of decommissioning

actions

Emergency planning

Develop, implement and maintain procedures to cope with abnormal

occurrences.

–

Personnel must be trained in contingency procedures.

Physical protection and safeguards

Physical protection and surveillance of the reactor site must be

maintained during decommissioning.

Module XVIII - Decommissioning

COMPLETITION OF DECOMMISSIONING

Licensee

 - A final decommissioning report - to demonstrate

that the end state of the facility as specified in the

approved final decommissioning plan has been met.

Regulatory body reviews final decommissioning report and evaluate

the end state - to ensure that the all regulatory requirements and end

state criteria have been met.

Regulatory body -

 decides on the termination of the

facility’s authorization and on its release from regulatory

control.

Module XVIII - Decommissioning

COMPLETITION OF DECOMMISSIONING

Approved end state is termination of decommissioning

authorization with restrictions on future use of the

remaining structures;

–

Controls and programmes for monitoring and surveillance should

be maintained to ensure optimization of protection and safety.

Separate authorization should be issued:

–

When radioactive waste is stored on the site and

–

For partial release of the site.

Module XVIII - Decommissioning

MANAGEMENT - Learning objectives

1.

Describe staffing and training for decommissioning.

2.

Describe the organization and administrative control

of decommissioning.

3.

Describe the integrated management system for

decommissioning.

Module XVIII - Decommissioning

MANAGEMENT

•

Prime 

responsibility for safety remains with the licensee

.

•

Individuals made responsible for performing

decommissioning actions;

–

Need to

have the necessary skills, expertise and training to

perform decommissioning safely

;

–

Have the 

responsibility to inform the decommissioning

management of any concerns about safety

.

•

Decommissioning must be controlled through the use of

written procedures.

Module XVIII - Decommissioning

Staffing and training

•

The operating organization should have 

competent staff

and specialized expertise

(where needed).

•

Contractors may be used to carry out all or some aspects

of decommissioning – 

appropriate level of control,

supervision and training need to be provided to ensure

safety

.

•

Persons involved in decommissioning activities:

–

Are familiar with facility and safety procedures,

–

Have specialized trainings,

–

Use of mock-up and models in training.

Module XVIII - Decommissioning

Organization and administrative control

•

Organizational structure – clear delineation of authorities

and responsibilities among various units.

•

Operational administrative measures may be relevant during

decommissioning;

–

Reviewed and modified to be appropriate to the decommissioning;

–

Administrative control measures must be endorsed by the regulatory body.

•

Decommissioning specialist and appropriate site personnel manage

the decommissioning plan;

–

New competence may be required;

–

Retention of key personnel, familiar with installation during its operation.

Module XVIII - Decommissioning

Integrated management system

•

Should be 

applied throughout the entire process of

decommissioning 

until the final decision is made on

compliance with the release criteria.

•

The aim is to ensure integration of all aspect of managing facility

and decommissioning activities.

•

System for archiving, retrieving and amending records should be

maintained to document the decommissioning activities.

•

This system should be commensurate with the size, complexity and

hazard potential of the site to be released from regulatory control.

Module XVIII - Decommissioning

Module XVIII - Decommissioning

REFERENCES

–

GSR Part 5 Predisposal Management of Radioactive Waste (2009)

–

GSR Part 6 Decommissioning of Facilities (2014)

–

SSG-47 Decommissioning of Nuclear Power Plants, Research Reactors and

Other Nuclear Fuel Cycle Facilities (revision of WS-G-2.1 and 2.4);

–

Decommissioning of Medical, Industrial and Research Facilities, IAEA Safety

Guide WS-G-2.2 (1999. Under revision).

–

Decommissioning strategies for facilities using radioactive material. Safety

Reports Series No. 50, IAEA, Vienna (2007).

–

 Standard Format and Content for Safety Related Decommissioning Documents,

Safety Reports Series No. 45, IAEA, Vienna (2005).

–

Radiological characterization of shut down nuclear reactors for

decommissioning purposes, Technical Reports Series No. 389, IAEA, Vienna

(1998).

–

State-of-the-art Technology for Decontamination and Dismantling of Nuclear

Facilities, Technical Reports Series No. 395, IAEA, Vienna (1999).

–

Innovative and Adaptive Technologies in Decommissioning Of Nuclear Facilities,

IAEA-TECDOC-1602, IAEA, Vienna (2008).

–

Selection of Decommissioning Strategies: Issues and Factors, IAEA-TECDOC-

1478, IAEA, Vienna (2005).

Module XVIII - Decommissioning

Module XVIII - Decommissioning

62

Summary

The following issues were discussed

1.

Content of decommissioning actions

2.

Responsibility for decommissioning

3.

Safety aspects of decommissioning.

4.

Strategies for decommissioning.

5.

IAEA standards on decommissioning.

Module XVIII - Decommissioning

Module XVIII - Decommissioning

63

•

Decommission as a part of a life cycle should be

considered at feasibility study stage.

•

A decommissioning strategy and draft plan should be

developed at the constriction stage

•

Availability of resources for decommissioning should

be concerned with regard the long term of the process

63

Key points

Thank you!