1. Module 2.5 – Predisposal Management of Radioactive Waste
2017 Advanced Workshop, “School for Drafting Regulations on Radiation Safety” Vienna, Austria 16 – 27 January 2017
Module 2.5 –
Predisposal Management of Radioactive Waste

2. The main sections deal with:
Contents
The main sections deal with:
General approach
Requirements for the responsibilities associated with the predisposal management of radioactive waste
Requirements for the safe development and operation of predisposal radioactive waste management facilities and safe conduct of activities.
Note to the lecturer:
Describe the structure of the lecture.

3. Safety Fundamentals
“The objective of radioactive waste management is to deal with radioactive waste in a manner that protects human health and the environment now and in the future without imposing undue burdens on future generations.”

4. Relevant IAEA publications:
Basis for lecture
Relevant IAEA publications:
Note to the lecturer:
Describe the structure of the lecture.

5. Safety Standards: Predisposal
Classification
Storage
Safety Case
Safety Assessment
Management System
DS 448
DS 447
DS 454
overview of safety standards

6. Requirement 1: Legal and regulatory framework
The government shall provide for an appropriate national legal and regulatory framework within which radioactive waste management activities can be planned and safely carried out. This shall include the clear and unequivocal allocation of responsibilities, the securing of financial and other resources, and the provision of independent regulatory functions. Protection shall also be provided beyond national borders as appropriate and necessary for neighbouring States that may be affected.
The government shall provide national legal and regulatory framework to plan and carry out RWM activities:
Clear allocation of responsibilities;
Securing of financial / other resources;
Provision of independent regulatory functions;
Protection beyond national borders.
The government shall consider:
Legal, technical, financial responsibilities;
Establishing effective and independent regulatory body;
Ensuring continuity of responsibility for safety;
Defining overall process;
Ensure availability of scientific / technical expertise.

7. Requirement 2: National policy and strategy on radioactive waste management
To ensure the effective management and control of radioactive waste, the government shall ensure that a national policy and a strategy for radioactive waste management are established. The policy and strategy shall be appropriate for the nature and the amount of the radioactive waste in the State, shall indicate the regulatory control required, and shall consider relevant societal factors. The policy and strategy shall be compatible with the fundamental safety principles and with international instruments, conventions and codes that have been ratified by the State. The national policy and strategy shall form the basis for decision making with respect to the management of radioactive waste.
To ensure the effective management and control of radioactive waste, the government shall ensure that a national policy and a strategy for radioactive waste management are established.
The policy and strategy shall be appropriate for the nature and the amount of the radioactive waste in the State, shall indicate the regulatory control required, and shall consider relevant societal factors. The policy and strategy shall be compatible with the fundamental safety principles and with international instruments, conventions and codes that have been ratified by the State. The national policy and strategy shall form the basis for decision making with respect to the management of radioactive waste.

8. Requirement 3: Responsibilities of the regulatory body
The regulatory body shall establish the requirements for the development of radioactive waste management facilities and activities and shall set out procedures for meeting the requirements for the various stages of the licensing process. The regulatory body shall review and assess the safety case and the environmental impact assessment for radioactive waste management facilities and activities, as prepared by the operator both prior to authorization and periodically during operation. The regulatory body shall provide for the issuing, amending, suspension or revoking of licenses, subject to any necessary conditions. The regulatory body shall carry out activities to verify that the operator meets these conditions. Enforcement actions shall be taken as necessary by the regulatory body in the event of deviations from, or non-compliance with, requirements and conditions.
The regulatory body shall establish the requirements for the development of radioactive waste management facilities and activities and shall set out procedures for meeting the requirements for the various stages of the licensing process. The regulatory body shall review and assess the safety case and the environmental impact assessment for radioactive waste management facilities and activities, as prepared by the operator both prior to authorization and periodically during operation. The regulatory body shall provide for the issuing, amending, suspension or revoking of licences, subject to any necessary conditions. The regulatory body shall carry out activities to verify that the operator meets these conditions. Enforcement actions shall be taken as necessary by the regulatory body in the event of deviations from, or non-compliance with, requirements and conditions.

9. Responsibilities Regulatory body
Establish appropriate classification scheme
Establish safety requirements and criteria
Handling, transport, storage
Acceptance criteria for disposal
Limits and conditions for removal of controls from material containing radionuclides (clearance), discharges
Ensure relevant documents and records are prepared
Period of preservation, quality
Verify operator meets established conditions;
Take necessary enforcement actions.
Note to the lecturer:
Introduce the lecture using the ideas expressed above.
The regulatory body shall establish the requirements for the development of radioactive waste management facilities and activities and shall set out procedures for meeting the requirements for the various stages of the licensing process. The regulatory body shall review and assess the safety case and the environmental impact assessment for radioactive waste management facilities and activities, as prepared by the operator both prior to authorization and periodically during operation. The regulatory body shall provide for the issuing, amending, suspension or revoking of licences, subject to any necessary conditions. The regulatory body shall carry out activities to verify that the operator meets these conditions. Enforcement actions shall be taken as necessary by the regulatory body in the event of deviations from, or non-compliance with, requirements and conditions.

10. Responsibilities Regulatory body
To facilitate compliance with requirements, the regulatory body has to:
Provide guidance on interpretation of national standards and regulatory requirements;
Encourage/participate in dialogue between operator & other parties;
Establish RW definition/classification , clearance criteria;
Document the procedures (licensing, verification, enforcement);
Establish mechanisms for dissemination of information;
Agree / delineate areas of responsibility / cooperation;
Ensure consideration given to non-radiological hazards.
Carry out verification activities supported by an effective management system and strong safety culture.
To facilitate compliance with regulatory requirements, the regulatory body has to do the following;
Establish a mechanism by means of which information on incidents significant to safety is disseminated to interested parties;
Enter into agreement, where appropriate, with other governmental bodies responsible for regulation in related fields to delineate areas of responsibility or of cooperation;
Ensure that due consideration is given to non-radiological hazards throughout the entire predisposal management of radioactive waste
The regulatory body has to carry out activities that are necessary to verify that requirements for safety and environmental protection are being met by the operator. These activities are required to be supported by an effective management system, including the establishment and maintenance of a strong safety culture.

11. Requirement 4 :Responsibilities of the operator
Operators shall be responsible for the safety of predisposal radioactive waste management facilities or activities. The operator shall carry out safety assessments and shall develop a safety case, and shall ensure that the necessary activities for siting, design, construction, commissioning, operation, shutdown and decommissioning are carried out in compliance with legal and regulatory requirements.

12. Responsibilities
Demonstration of safety by means of the safety case, and for an existing facility or activity by means of periodic safety reviews;
Demonstration of environmental protection by means of an assessment of environmental impacts;
Derivation of operational limits, conditions and controls, including waste acceptance criteria, to assist with ensuring that the predisposal radioactive waste management facility is operated in accordance with the safety case;
Preparation and implementation of appropriate operating procedures, including monitoring;
Application of good engineering practice;
Predisposal management may involve transfer of RW from one operator to another. Waste is often sent from a producer to a central facility. Storage periods can be long and extend over
Note to the lecturer:
Introduce the lecture using the ideas expressed above.

13. Responsibilities
Ensuring that staff are trained, qualified and competent, and, where applicable, licensed by the regulatory body;
Establishment and implementation of a management system ;
Maintenance of records and reporting as required by the regulatory body, including those records and reports necessary to guarantee the accountability for and traceability of radioactive waste throughout the different processes of radioactive waste management;
Establishment and maintenance of a mechanism to provide and ensure adequate financial resources to discharge its responsibilities;
Predisposal management may involve transfer of RW from one operator to another. Waste is often sent from a producer to a central facility. Storage periods can be long and extend over
Note to the lecturer:
Introduce the lecture using the ideas expressed above.

14. INTEGRATED APPROACH TO SAFETY

15. Requirement 5: Security Measures
Measures shall be implemented to ensure an integrated approach to safety and security in the predisposal management of radioactive waste.
The level of security is required to be commensurate with the level of radiological hazard and the nature of the waste.

16. Requirement 6: Interdependencies
Interdependencies among all steps in the generation and management of radioactive waste, as well as the impact of the anticipated disposal option, shall be appropriately taken into account.
COMPATIBILITY (taking actions that facilitate other steps and avoiding taking decisions in one step that detrimentally affect the options available in another step)
OPTIMIZATION (i.e. assessing the overall options for waste management with all the interdependences taken into account).
The use of well managed information of good quality
is key to both aspects.

17. Requirement 7: Management system:
Management systems shall be applied for all steps and elements of the predisposal management of radioactive waste.
GSR Part 2
Features that are important to safe operation, and that are considered in the management system, are to be identified on the basis of the safety case and the assessment of environmental impacts.

18. STEPS IN THE PREDISPOSAL MANAGEMENT OF RADIOACTIVE WASTE
Requirements for the principal approaches to and the elements of the predisposal management of radioactive waste are established in Section 4. In total there are 5 requirements grouped into 4 groups.

19. Waste Management
The principal approaches to the management of radioactive waste are commonly termed ‘delay and decay’, ‘concentrate and contain’ and ‘dilute and disperse’. ‘Delay and decay’ involves holding the waste in storage until the desired reduction in activity has occurred through radioactive decay of the radionuclides contained in the waste. This is effective for many short-lived wastes from radionuclide applications, but can also be used as a minimization approach in the nuclear fuel cycle, e.g. by removing the highest-activity shortest-lived isotopes from the need for further consideration.

20. Principal approaches to waste management
Delay and decay - (processing), storage, authorized discharge
Concentrate and contain - processing, storage, disposal
Dilute and disperse - authorized discharge
Radionuclides have a property that is useful if waste management: they decay, meaning that their activity - orradiological hazard associated waste is recuced in time. This is put in use in the approaches to waste management.
The principal approaches to the management of radioactive waste are commonly termed ‘delay and decay’, ‘concentrate and contain’ and ‘dilute and disperse’.
‘Delay and decay’ involves holding the waste in storage until the desired reduction in activity has occurred through radioactive decay of the radionuclides contained in the waste.
‘Concentrate and contain’ means reduction of volume and confinement of the radionuclide contents by means of a conditioning process to prevent dispersion in the
environment.
‘Dilute and disperse’ means discharging waste to the environment in such a way that environmental conditions and processes ensure that the concentrations of the radionuclides are reduced to such levels that the radiological impact of the released material is acceptable.
In establishing policies in this area, consideration has to be given to the radiological impacts of the different management options. From a radiological protection perspective, a balance has to be struck between the present exposures resulting from the dispersal of radionuclides in the environment and potential future exposures which could result as a consequence of radioactive waste disposal
The first two approaches (‘delay and decay’, ‘concentrate and contain’) require
that radioactive waste be held in storage for varying lengths of time or placed in a disposal facility with a view to preventing its release to the environment. Radioactive
waste must therefore be processed, as necessary, in such a way that it can be safely placed and held in a storage or disposal facility.
The third approach (‘dilute and disperse’) is a legitimate practice in the management of radioactive waste and has to be carried out within authorized limits
established by the regulatory body

21. Selection of Management Options
Protection of Health (Future Generations) and Environment
Inventory and classes/categories of RAW
Storage capacity for RAW
Safety and Security considerations related to LTS
Technical Infrastructure & Financial Resources Available
Public Consultation
Social and Political Conditions
Interdependencies with other predisposal and final disposal options
Selected options must be consistent with National policies for waste management
National policies for radioactive waste management will be a critical factor when selecting options for predisposal waste management. The presence or absence of regulations for clearance is one example of a predetermined option. In many cases, selected types of predisposal waste management facilities will be available, thus, options may already be identified. For example, incineration may be identified as the chosen alternative for volume reduction of combustible waste.
Interdependencies (or constraints) imposed by decisions already made in other steps of the waste management lifecycle must be clearly identified early in the process of selecting options.
As many choices between options will depend on the characteristics of the waste, it is critical to have an effective waste characterization program in place.

22. Requirement 8: Radioactive waste generation and control
All radioactive waste shall be identified and controlled. Radioactive waste arising shall be kept to the minimum practicable.
France

23. Requirement 8: Radioactive waste generation and control (cont)
Reduce waste generation - volume and radioactivity content has to be considered before the construction of a facility, beginning with the design phase, and throughout the lifetime of the facility;
Reuse and recycling;
Authorized discharge of effluent, clearance of materials in compliance with conditions and criteria established by the regulatory body;
Ensure due consideration to non-radiological hazards.
The control measures are generally applied in the following order: reduce waste generation, reuse items as originally intended, recycle materials and, finally, consider disposal as waste.
The reuse and recycling of materials has to be applied to keep the generation of radioactive waste to the minimum practicable, provided that protection objectives are met.
The authorized discharge of effluent and clearance of materials from regulatory control, after some appropriate processing and/or a sufficiently long period of storage, together with reuse and recycling of material, can be effective in reducing the amount of radioactive waste that needs further processing or storage.
The regulatory body also has to ensure that the operator gives due consideration to non-radiological hazards in applying such options.

24. Requirement 9: Characterization and classification of radioactive waste
At various stages in the process of management of radioactive waste, the radioactive waste shall be classified and characterized in accordance with the requirements established or approved by the Regulatory Body.

25. Waste Properties Origin/Source Biological properties:
Criticality
Radiological Properties
Half-lives of radionuclides
Heat generation
Intensity of penetrating radiation
Activity concentration of radionuclides
Surface contamination
Dose factors of relevant radionuclides
Decay products
Biological properties:
Potential biological hazards
Bio-accumulation
Other Factors
Volume
Amount arising per unit of time
Physical distribution
As this list demonstrates, there is a wide range of properties that must be considered when managing and processing radioactive wastes, most of which also impact directly upon safety.
For purposes of waste classification, a subset of these properties needs to be selected as the primary basis for classification. For example, the half-life, intensity of radiation and heat-generating properties of the waste might be the focus of a classification system.

26. Waste Properties Chemical Properties Phisycal Properties
Chemical composition
Solubility and chelating agents
Potential chemical hazard
Corrosion resistance/corrosiveness
Organic content
Combustibility and flammability
Chemical reactivity and swelling potential
Gas generation
Sorption of radionuclides
Phisycal Properties
Physical state (solid, liquid or gaseous)
Size and weight
Compactibility
Dispersibility
Volatility
Miscibility
Free liquid content
As this list demonstrates, there is a wide range of properties that must be considered when managing and processing radioactive wastes, most of which also impact directly upon safety.
For purposes of waste classification, a subset of these properties needs to be selected as the primary basis for classification. For example, the half-life, intensity of radiation and heat-generating properties of the waste might be the focus of a classification system.

27. Methods of waste classification
Classification schemes for radioactive waste may be developed from different bases, such as safety or regulatory related aspects or process engineering demands
Radioactive waste classification schemes can be set up at different levels and for various purposes. A classification scheme may be defined at the international level, at the national level or at the operator level. Its perspective and purpose will differ accordingly, addressing, for example, safety related aspects, the origin and characteristics of the waste, engineering demands or regulatory control
The approach to classification will depend on the purpose of the radioactive waste classification scheme
A clear distinction has to be made between a classification scheme and a set of regulatory limits
Classification schemes for radioactive waste may be developed from different bases, such as safety or regulatory related aspects or process engineering demands. The Annex II provides a discussion of the various purposes of and approaches to classification schemes for radioactive waste.
The approach to classification will depend on the purpose of the radioactive waste classification scheme. One basic approach to classification is a straightforward qualitative description of the individual classes, whereby the general characteristics of the radioactive waste are used as the main criteria for the classification. Nevertheless, even for this qualitative approach to classifying, numerical values to characterize broad bands or orders of magnitude may also be helpful. Another basic approach to classification is by the use of quantitative criteria, whereby numerical values are specified for the definition of waste classes. A clear distinction has to be made between a classification scheme and a set of regulatory limits. The purpose of classification is to ensure that waste is managed in a safe and economic manner within the framework of a national
strategy and to facilitate communication, while the purpose of regulatory limitation is to ensure the safety of each licensed facility and activity. Therefore, the development of precise limits has to be carried out within the regulatory
framework of licensing or authorizing specific radioactive waste management activities and facilities. The regulatory body of a State will establish actual limits on quantities or concentrations for the classification of radioactive waste.

28. Possible ways to classify
Some of the possible ways to classify waste:
Classification by origin
Nuclear fuel cycle, isotope production, NORM..
Classification by physical state
Solid, liquid, gaseous
Classification by activity concentration
Very low, low, intermediate, high activity level waste
Classification by half-life
Very short-lived, short-lived, long-lived waste
Some of the possible ways to classify waste are based on the most obvious and important properties of the waste: physical state, activity concentration and half-life. These attributes are directly related to safety and hazard assessment, and therefore classification based on them aids planning for safety of waste management.
Some other possible choices, such as classification by origin, are less directly related to safety or to other technical requirements for management, and may be based instead on more administrative concerns such as determining who is financially responsible for their management. However, a system based on such a choice can obscure the safety issues which are most important in the long term, and thus make development of a comprehensive strategy more difficult.

29. Waste classification - System
Ideal classification system should:
Cover all RAW types
Address all stages of RAW management
Relate RAW classes to potential hazard
Be flexible
Not change accepted terminology
Be simple, easy to understand
Be universally applicable
No such system exists!
In order to meet the purposes described earlier, a waste classification system should ideally have the properties listed on this slide.
It should come as no surprise that no such ideal system exists; this is no doubt one of the reasons behind the variety of national systems still in use.

30. Classification of radioactive waste GSG-1 (2009)
In complement It is necessary to summarize the situation with regards to ILW and Intermediate depth disposal.
The classification of raw makes the link between types of radioactive waste and disposal options. In particular the classification gives this graph and we often have feedback on it that it could be perceived that there is a direct link between intermediate level waste and intermediate depth disposal, in particular if this graph is taken alone without reading the document.

31. Classification of radioactive waste GSG-1 (2009)
EW: Meets the criteria for clearance, exemption or exclusion from regulatory control for radiation protection purposes
VSLW: Can be stored for decay over a limited period of up to a few years and subsequently cleared from regulatory control according to arrangements approved by the regulatory body, for uncontrolled disposal, use or discharge
VLLW: Does not necessarily meet the criteria of EW, but that does not need a high level of containment and isolation and, therefore, is suitable for disposal in near surface landfill type facilities with limited regulatory control
The IAEA safety guide on the classification published in 2009 defines the different types of radioactive waste and makes links with disposal options.
Exempt waste (EW) contains such small concentrations of radionuclides that it does not require provisions for radiation protection, irrespective of whether the waste is disposed of in conventional landfills or recycled VSLV - Very short lived waste contains only radionuclides of very short half-life with activity concentrations above the clearance levels. Such waste can be stored until the activity has fallen beneath the levels for clearance, allowing for the cleared waste to be managed as conventional waste. Through radioactive decay, VSLW will move into the class of exempt waste VLLW - waste with such a limited hazard, which is nevertheless above or close to the levels for exempt waste. Substantial amounts of waste arise from the operation and decommissioning of nuclear facilities with levels of activity concentration in the region of or slightly above the levels specified for the clearance of material from regulatory control. An adequate level of safety for VLLW may be achieved by its disposal in engineered surface landfill type facilities LLW are defined as waste which are above clearance level, with limited amounts of long lived Rn. These waste requires robust isolation and containment for periods up to a few hundred years . They are suitable for disposal in engineered near surface facilities typically from the surface to 30 m
ILW: are defined as waste with a content in long lived radionuclides which implies the need for a greater degree of containment and isolation than that provided by near surface disposal facilities, which is provided by disposal at greater depth than that of near surface disposal facilities i.e. in the order of tens of meters to a few hundred meters
High levek waste are defined in the classification as waste with high levels of activity concentrations, which generates heat by radioactive decay or waste with large amounts of long lived radioanuclides. Because of these characteristics these waste should be disposed of in deep stable geological formations of several hundred meters or more below the surface
In addition to these definitions one very important element which is given in the classification is that the suitability of waste in a particular disposla facility is required to be demonstrated by the safety case and supporting safety assessment for that facility
EW, VSLW, VLLW
This new classification applies to all types of radioactive waste. It is based primarily on long term safety. It is meant to facilitate communication and information exchange within and among states. In order to take into account comments made on the previous classification, a generic linkage has been made between the classes of waste and potential disposal options but one essential element which is mentioned in the classification is that the suitability of waste for disposal in a particular disposal facaility is required to be demonstrated by the safety case and supporting safety assessment for that facility

32. Classification of radioactive waste GSG-1 (2009)
LLW: Above the clearance level, limited amounts of long lived Rn. Requires robust isolation and containment for periods up to a few hundred years. Suitable for disposal in engineered near surface facilities typically from the surface to 30 m depth
ILW: content in long lived Rn → greater degree of containment and isolation than that provided by NS disposal facilities. Disposal at greater depth than that of NS disposal facilities i.e. order of tens of m to a few hundred m (intermediate depth disposal)
HLW: high levels of activity concentrations, heat generation by radioactive decay or waste with large amounts of long lived Rn. Disposal in deep, stable geological formations of several hundred meters depth or more below the surface
The suitability of waste for disposal in a particular disposal facility is required to be demonstrated by the safety case and supporting safety assessment for that facility
The IAEA safety guide on the classification published in 2009 defines the different types of radioactive waste and makes links with disposal options.
Exempt waste (EW) contains such small concentrations of radionuclides that it does not require provisions for radiation protection, irrespective of whether the waste is disposed of in conventional landfills or recycled VSLV - Very short lived waste contains only radionuclides of very short half-life with activity concentrations above the clearance levels. Such waste can be stored until the activity has fallen beneath the levels for clearance, allowing for the cleared waste to be managed as conventional waste. Through radioactive decay, VSLW will move into the class of exempt waste VLLW - waste with such a limited hazard, which is nevertheless above or close to the levels for exempt waste. Substantial amounts of waste arise from the operation and decommissioning of nuclear facilities with levels of activity concentration in the region of or slightly above the levels specified for the clearance of material from regulatory control. An adequate level of safety for VLLW may be achieved by its disposal in engineered surface landfill type facilities LLW are defined as waste which are above clearance level, with limited amounts of long lived Rn. These waste requires robust isolation and containment for periods up to a few hundred years . They are suitable for disposal in engineered near surface facilities typically from the surface to 30 m
ILW: are defined as waste with a content in long lived radionuclides which implies the need for a greater degree of containment and isolation than that provided by near surface disposal facilities, which is provided by disposal at greater depth than that of near surface disposal facilities i.e. in the order of tens of meters to a few hundred meters
High levek waste are defined in the classification as waste with high levels of activity concentrations, which generates heat by radioactive decay or waste with large amounts of long lived radioanuclides. Because of these characteristics these waste should be disposed of in deep stable geological formations of several hundred meters or more below the surface
In addition to these definitions one very important element which is given in the classification is that the suitability of waste in a particular disposla facility is required to be demonstrated by the safety case and supporting safety assessment for that facility
EW, VSLW, VLLW
This new classification applies to all types of radioactive waste. It is based primarily on long term safety. It is meant to facilitate communication and information exchange within and among states. In order to take into account comments made on the previous classification, a generic linkage has been made between the classes of waste and potential disposal options but one essential element which is mentioned in the classification is that the suitability of waste for disposal in a particular disposal facaility is required to be demonstrated by the safety case and supporting safety assessment for that facility

33. Waste Classification Systems versus Waste Acceptance Criteria
Difference between waste acceptance criteria (WAC) and a waste classification system?
Waste classification systems – provide a national system of classification for managing all types of radioactive waste. Do not specify criteria for individual facilities
WAC – are specific to a particular storage or disposal facility
WAC provide detailed specifications - as per waste properties - for waste to meet before it can be accepted at a particular storage or disposal facility
It should be noted that a classification system is not the same as the waste acceptance criteria used by individual facilities or repositories to perform triage on incoming material. WAC are by their nature specific to a particular facility, and often include detailed requirements and specifications related to a wide range of properties as discussed earlier. While this serves the purpose of safe operation of the individual facility, it does not respond to the need for a broader classification system for strategic planning and communication.

34. Requirement 10: Processing of radioactive waste
Radioactive material for which no further use is foreseen, and with characteristics that make it unsuitable for authorized discharge, authorized use or clearance from regulatory control, shall be processed as radioactive waste. The processing of radioactive waste shall be based on appropriate consideration of the characteristics of the waste and of the demands imposed by the different steps in its management (pretreatment, treatment, conditioning, transport, storage and disposal). Waste packages shall be designed and produced so that the radioactive material is appropriately contained both during normal operation and in accident conditions that could occur in the handling, storage, transport and disposal of waste.

35. Basic Steps of Waste Processing
Pre-Treatment
Reuse/recycle
(radioactive material)
Clearance
Treatment
Effective management of radioactive waste considers the basic steps (shown schematically in Figure) in the radioactive waste management process as parts of a total system, from generation through disposal.
Pretreatment Pretreatment of waste is the initial step in waste management that occurs after waste generation. It consists of, for example, collection, segregation, chemical adjustment and decontamination and may include a period of interim storage.
Treatment Treatment of radioactive waste includes those operations intended to improve safety or economy by changing the characteristics of the radioactive waste. The basic treatment concepts are volume reduction, radionuclide removal and change of composition.
Conditioning Conditioning of radioactive waste involves those operations that transform radioactive waste into a form suitable for handling, transportation, storage and disposal. The operations may include immobilization of radioactive waste, placing the waste into containers and providing additional packaging.
Disposal Disposal is the final step in the radioactive waste management system. It consists mainly of the emplacement of radioactive waste in a disposal facility with reasonable assurance for safety, without the intention of retrieval and without reliance on long term surveillance and maintenance.
(SS No.111-F Annex p13)
Characterization, as early as possible, is utterly important
Conditioning
Characterization
Storage
Transport
Disposal

36. Requirement 10: Processing of radioactive waste (cont)
Main purpose of processing is to enhance safety by producing a waste form that fulfills the acceptance criteria for safe processing, transport, storage and disposal;
Safety is ensured during normal operation, measures are taken to prevent occurrence of incidents or accidents, and provisions are made to mitigate consequences of accidents;
Consistency with the waste type, possible storage, anticipated disposal option and limits, conditions, and controls is established in the safety case and assessment of environmental impact.

37. Requirement 11: Storage of radioactive waste
Waste shall be stored in such a manner that it can be inspected, monitored, retrieved and preserved in a condition suitable for its subsequent management. Due account shall be taken of the expected period of storage, and, to the extent possible, passive safety features shall be applied. For long term storage in particular, measures shall be taken to prevent degradation of the waste containment.
Storage is by definition an interim measure, but it can last for several decades. The intention in storing waste is that the waste can be retrieved for clearance, processing and/or disposal at a later time, or, in the case of effluent, for authorized discharge.
May take place between and within basic waste management steps;
May be used to facilitate subsequent step:
Act as a buffer between / within steps;
Allow time for decay prior to clearance or authorized discharge;
Hold waste generated in emergency situations pending decision on its future management.

38. Requirement 11: Storage of radioactive waste (cont)
Design depends on the type of RW, its characteristics and associated hazards, radioactive inventory, and anticipated period of storage;
Regular monitoring, inspection and maintenance of the waste and of the storage facility is required to ensure their continued integrity;
Adequacy of the storage capacity has to be periodically reviewed (prediction in waste arising, availability of disposal options).
Storage is by definition an interim measure, but it can last for several decades. The intention in storing waste is that the waste can be retrieved for clearance, processing and/or disposal at a later time, or, in the case of effluent, for authorized discharge.
May take place between and within basic waste management steps;
May be used to facilitate subsequent step:
Act as a buffer between / within steps;
Allow time for decay prior to clearance or authorized discharge;
Hold waste generated in emergency situations pending decision on its future management.

39. need for inspection, retrievability
Storage
Defined as the holding of RAW in a facility that provides for their/its containment, with the intention of retrieval
Intermediate step requiring retrieval for later re-use or disposal
Time scales are at most a few tens of years
Storage of RAW, including LTS, is an interim solution, not an alternative to disposal
In the longer term, only disposal with its inherent passive safety can guarantee protection against all potential hazards
need for inspection, retrievability
passive safety
Storage options include wet storage in some form of storage pool or dry storage in a facility or casks built solely for this purpose; another option for dry storage is to place the spent fuel in casks designed for both storage and transport, which is defined as a Dual Purpose Cask. Although evidence confirms that storage under designed conditions is safe and secure, it has to be recognized that such storage represents only an interim stage in any spent fuel management strategy. While in countries like France, Russia, Japan, India and others there are ongoing programmes to recycle spent fuel, there is an urgent need to move on towards final disposal options. The delay has been caused, for the most part, by the slow rate of development of geological disposal facilities for spent fuel. Fortunately, geological disposal projects in Finland, Sweden and France are moving towards the licensing stage.

40. Long Term Storage Challenges
Safety of Long Term (100 yr) Storage Periods
RAW, container and facility degradation
Storage Capacity
(user premises, centralized Storage)
Inadequate legal or regulatory framework
Laws against import of RAW of foreign origin
Availability of resources (financial, human, technical)
Societal and economic instability
Public acceptance
Safety. In general, it is more difficult to ensure the safety of spent fuel storage using storage pools than dry stores, and it is expected that there will be a transition from wet to dry storage.
Storage Capacity. Projections on storage capacities indicate that by ~2030, spent fuel storage capacity may be running out.
Centralised storage It may be no easier to site, construct and licence centralised storage facilities than geological disposal facilities, particularly if new storage arrangements require increased waste transportation, which is often a focus of public objections. However, it add flexibility to the overall waste management system because it does away with the need to maintain stores at each NPP and allows the NPPS to be decommissioned.
Political and societal stability. some countries are experiencing a relatively high risk of instability, including changes to governments and wars. This can be a driver to implement a disposal solution, not to store wastes on the surface.
Acceptability of extended storage periods. Communities often do not accept interim waste stores unless there was seen to be planning for, and steps towards, the implementation of waste disposal. Waste management organisations and governments should be open and transparent regarding intentions for the period of waste storage and plans for waste disposal.

41. Requirement 12: Radioactive waste acceptance criteria
Waste packages and unpackaged waste accepted for processing, storage and/or disposal shall conform to criteria consistent with the approved safety case

42. Waste Acceptance Criteria (WAC)
Radioactive waste destined for disposal shall be processed to meet the acceptance criteria for disposal established with the approval of the regulatory body.
Define the radiological, mechanical, physical, chemical and biological properties of the waste package and unpackaged waste.
WAC are essential for the safe handling and storage of waste during normal operation, ensuring safety during possible accidents, and long term safety during subsequent disposal;
(WS-R-2 p 8)

43. Waste Acceptance Criteria (WAC) Example of Japanese Technical Criteria for homogenous solidified low level waste packages.
Label to Indicate Radioactive
Colored Band
(Regarded to Dose Rate)
LABEL
WASTE PACKAGE
Not to be Seriously Damaged
CONTAINER INTEGRITY
放 射 性
C - 0 0
○ ○ 電
△ △ 発
Not to Remain Large Voids
VOIDAGE
Identification Number
IDENTIFICATION
Cement : JIS R 5210,5211 Quality
Asphalt : JIS K 227 Quality & Penetration < 100
Plastic : Unsaturated Polyester Resin
SOLIDIFYING MATERIAL
Metallic container Prescribed in JIS Z 1600
TYPE OF CONTAINER
β/γ emitter : < 4 Bq / cm2
α emitter : < 0.4 Bq / cm2
SURFACE CONTAMINATION
This figure shows about the technical criteria for waste packages, there are 10 items in the technical criteria for homogenous solidified waste package.
These criteria consist 2 categories, one is shown by orange boxes, these criteria concerning manufacturing of waste package such as material, condition of mixing and strength.
The other is shown by green box, these criteria concerning the waste package such as limit of contamination, radioactivity and identification Number & label.
Cement : Compressive Strength ≧ 15 kg / cm2
Plastic : Durometer Hardness ≧ 25
To withstand the load is received when buried
STRENGTH OF WASTE
Solidified Homogeneously
Asphalt : Waste Weight / Package Weight ≦ 50%
Plastic : Waste Weight / Package Weight ≦ 70%
Not be Contained Substances Which Threaten to Damage
WASTE FORM
Not to Exceed the Maximum Concentration of Radioactivity
RADIOACTIVITY

44. DEVELOPMENT AND OPERATION OF PREDISPOSAL RADIOACTIVE WASTE MANAGEMENT FACILITIES AND ACTIVITIES
Section 5 establishes requirements for the safe development and operation of predisposal radioactive waste management facilities and safe conduct of activities. It includes 10 requirements grouped into 3 groups.

45. Requirement 13: Preparation of the safety case and supporting safety assessment
The operator shall prepare a safety case and a supporting safety assessment. In the case of a step by step development, or in the event of modification of the facility or activity, the safety case and its supporting safety assessment shall be reviewed and updated as necessary.
SC has to be prepared early in the development of the facility as a basis for regulatory decision making and approval;
SC has to be progressively developed and refined as the project proceeds;
It is the operator’s is responsibility to compile the SA in accordance with the requirements of the regulatory body.

46. Requirement 13: Preparation of the safety case and supporting safety assessment (cont)
In the case of a step by step development, or in the event of modification of the facility or activity, the safety case and its supporting safety assessment shall be reviewed and updated as necessary.
That ensures quality of technical programme and the associated decision making and;
Provides a framework in which confidence in the technical feasibility and safety of the facility can be established at each stage of its development.
SC has to be prepared early in the development of the facility as a basis for regulatory decision making and approval;
SC has to be progressively developed and refined as the project proceeds;
It is the operator’s is responsibility to compile the SA in accordance with the requirements of the regulatory body.

47. Requirement 14: Scope of the safety case and supporting safety assessment
The safety case for a predisposal radioactive waste management facility shall include a description of how all the safety aspects of the site, the design, operation, shutdown and decommissioning of the facility, and the managerial controls satisfy the regulatory requirements. The safety case and its supporting safety assessment shall demonstrate the level of protection provided and shall provide assurance to the regulatory body that safety requirements will be met.
The safety case for a predisposal radioactive waste management facility shall include a description of how all the safety aspects of the site, the design, operation, shutdown and decommissioning of the facility, and the managerial controls satisfy the regulatory requirements.

48. Requirement 14: Scope of the safety case and supporting safety assessment (cont)
The SC/SA shall demonstrate the level of protection provided and shall provide assurance to the regulatory body that safety requirements will be met.
Primary aim is to ensure safety objectives and criteria set by regulatory body are met;
Address operational safety and all safety aspects of the facility and activities;
Include consideration for reducing hazards to workers, public and environment during normal operations and possible accident conditions;
Extent and detail are commensurate with complexity of the operations and the magnitude of the hazards.
The safety case for a predisposal radioactive waste management facility shall include a description of how all the safety aspects of the site, the design, operation, shutdown and decommissioning of the facility, and the managerial controls satisfy the regulatory requirements.

49. Requirement 15: Documentation of the safety case and supporting safety assessment
The safety case and its supporting safety assessment shall be documented at a level of detail and to a quality sufficient to demonstrate safety, to support the decision at each stage and to allow for the independent review and approval of the safety case and safety assessment. The documentation shall be clearly written and shall include arguments justifying the approaches taken in the safety case on the basis of information that is traceable.

50. Requirement 15: Documentation of the safety case and supporting safety assessment (cont)
Justification:
explaining choices, stating arguments for/against decisions made (especially main approaches taken in SC);
Traceability:
ability to follow information that is provided in the documentation and used in developing the SC;
Clarity:
good structure, presentation allows for understanding of the safety arguments and their bases.

51. Requirement 16: Periodic safety reviews
The operator shall carry out periodic safety reviews and shall implement any safety upgrades required by the regulatory body following this review. The results of the periodic safety review shall be reflected in the updated version of the safety case for the facility.
Confirm input assumptions to be complied with remain adequately controlled;
Periodicity depends on requirements of regulatory body, and:
Significant changes to facility/activity;
Significant developments in knowledge (research, feedback);
Emerging safety issue due to incident or regulatory body concern;
Significant improvements in assessment techniques (i.e., computer codes, input data).

52. DEVELOPMENT OF PREDISPOSAL RADIOACTIVE WASTE MANAGEMENT FACILITIES

53. Requirement 17: Location and design of facilities
Predisposal radioactive waste management facilities shall be located and designed so as to ensure safety for the expected operating lifetime under both normal and possible accident conditions, and for their decommissioning.

54. Requirement 18: Construction and commissioning of the facilities
Predisposal radioactive waste management facilities shall be constructed in accordance with the design as described in the safety case and approved by the regulatory body. Commissioning of the facility shall be carried out to verify that the equipment, structures, systems and components, and the facility as a whole, perform as planned.
While operator is responsible for constructing the facilities, the regulatory body is responsible for oversight of construction and verification activities;
Depending on size/complexity of the facilities, commissioning may be carried out in stages – facility construction, equipment installation, demonstration of performance, and non-active and active commissioning

55. Requirement 19: Facility operation
Predisposal radioactive waste management facilities shall be operated in accordance with national regulations and with the conditions imposed by the regulatory body. Operations shall be based on documented procedures. Due consideration shall be given to the maintenance of the facility to ensure its safe performance. Emergency preparedness and response plans, if developed by the operator, are subject to the approval of the regulatory body.

56. Requirement 19: Facility operation (cont)
Operational limits, conditions and controls may be provided in the authorization documents, or may be in a separate document (technical specifications);
All operations and activities important to safety have to be subject to documented limits, conditions and controls, and have to be carried out by trained, qualified and competent personnel;
All safety related criteria and documented operating procedures required by the regulatory body have to be submitted to the regulatory body for approval;

57. Requirement 20: Shutdown and decommissioning of facilities
The operator shall develop, in the design stage, an initial plan for the shutdown and decommissioning of the predisposal radioactive waste management facility and shall periodically update it throughout the operational period. The decommissioning of the facility shall be carried out on the basis of the final decommissioning plan, as approved by the regulatory body. In addition, assurance shall be provided that sufficient funds will be available to carry out shutdown and decommissioning
Objective is to limit occupational exposures, waste generated, and potential for accidents during decommissioning;
Time periods between updates will be dependent on the type of facility, operational history, and have to be agreed by the regulatory body.
The objective is to facilitate the future dismantling activities by reducing occupational exposures, minimizing the generation of waste and reducing the potential for accidents during decommissioning;
Particular consideration has to be given to any transfer of responsibility for the facility that may occur at this stage;

58. OTHER PROVISIONS

59. Requirement 21: System of accounting for and control of nuclear material
For facilities subject to agreements on nuclear material accounting, in the design and operation of predisposal radioactive waste management facilities the system of accounting for and control of nuclear material shall be implemented in such a way as not to compromise the safety of the facility

60. Requirement 22: Existing facilities
The safety at existing facilities shall be reviewed to verify compliance with requirements. Safety related upgrades shall be made by the operator in line with national policies and as required by the regulatory body.

61. Summary
Safety in predisposal RW management is based on broad spectrum of safety requirements, which are governed by the objective and principles of the Safety Fundamentals;
Safety requirements must be met to ensure the protection of people and the environment, both now and in the future;
All safety requirements are important, non of them has to be ignored.
Safety requirements are reviewed and updated. Checking and updating of your knowledge is important.

62. Thank you!
Thank you!