1. TM-45865 Technical Meeting on the Disposal of Intermediate Level Waste
IAEA Safety Standards and Activities on the Disposal of Intermediate Level Waste
TM Technical Meeting on the Disposal of Intermediate Level Waste
Yumiko Kumano
Radioactive Waste and Spent Fuel Management Unit
Division of Radiation, Transport and Waste Safety - NSRW

2. Overview
IAEA Safety Standards and previous discussions on ILW disposal
Consultancy in April 2013
Way forward
The presentation will successively go through the problem definition then will explain and give the outcomes of the consultancy we organized and finally will propose the position of the IAEA regarding the issue of intermediate level waste disposal and intermediate depth disposal

3. IAEA Safety Requirements
2010
Under development
Under development
Published in
Published
in 2011
Under development
2009
Under development
2009
Published
in 2011
Under development
Published
in 2012
Under development

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

5. Safety Standards - Disposal
Site Aspects
Design
Construction
Operation
Closure
Post Closure
Safety Assessment
Management System
Near Surface disposal
of RW
DS 356
Specific Safety Guide
Monitoring and Surveillance of Disposal Facilities
DS 357
Specific Safety Guide
overview of safety standards 5

6. Safety Standards - Disposal
SSR-5
Disposal of RW
DS 356
Near Surface Disposal
SSG-23
SC and SA for disposal
SSG-14
Geological Disposal
Near Surface disposal
of RW
DS 356
Specific Safety Guide
LLW
HLW
+ILW? 6

7. Workshop in Korea
Workshop on Intermediate Depth Disposal of Radioactive Waste : the Safety Basis and its Realization (Korea, 2008)
The concept of intermediate depth disposal is not useful - The depth of a geological disposal should be determined by a combination of geological, engineering and safety considerations rather than by an arbitrary standard of what constitutes “intermediate depth” or “deep”
The need for additional guidance for ILW disposal between a few tens to a few hundred meters below ground surface should be further examined
In addition it is important to mention the workshop that took place in Korea in 2008 on intermediate depth disposal of radioactive waste : the safety basis and its realization.
In fact the workshop was organized to address in particular the issue of depth of disposal and the main conclusions of this workshop were that first
The concept of intermediate depth disposal is not useful. The depth of a geological disposal should be determined by a combination of geological, engineering and safety considerations rather than by an arbitrary standard of what constitutes intermediate depth or deep
Second the workshop concluded that there is a need for additional guidance for ILW between a few tens to a few hundred meters below ground surface should be further examined
 This discussion on terminology could not be reflected to GSG-1, while SSR-5 incorporates this conclusion.

8. GSG-1(2009): Classification of RW
WASTE CLASSES
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
As you know as well The IAEA safety guide on the classification published in 2009 defines the different types of radioactive waste and makes links with disposal options.
I am not going to give the definitions of VLLW, VSLW and Exempt waste which are given in the SG but I will just give the definitions of those waste of interest for our issue.
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

9. SSR-5(2009): Disposal of RW DISPOSAL OPTIONS
Near surface disposal: disposal in a facility […] constructed on the ground surface or up to a few tens of metres below ground level. Such a facility may be designated as a disposal facility for low level radioactive waste (LLW)
Disposal of intermediate level waste: […] Disposal could be by emplacement in facilities constructed […] at least a few tens of metres below ground level and up to a few hundred metres below ground level
Geological disposal: disposal in a facility constructed […] in a particular geological formation (e.g. in terms of its long term stability and its hydrogeological properties) at least a few hundred metres below ground level. Such a facility could be designed to receive high level radioactive waste […]. However, with appropriate design, a geological disposal facility could receive all types of radioactive waste.
In terms of disposal the recently published safety requirements on disposal of radioactive waste (SSR5) defines the different disposal options. Near surface disposal is defined as disposal in a facility constructed on the ground surface or up to a few tens of metres below ground level. Such a facility may be designated as a disposal facility for low level radioactive waste (LLW)
The safety requirements publication also indicates that concerning disposal of intermediate level waste, depending on its characteristics, (ILW) can be disposed of in facilities of different types. Disposal could be by emplacement in facilities constructed at least a few tens of metres below ground level and up to a few hundred metres below ground level.
It could include purpose built facilities and facilities developed in or from existing mines. It could also include facilities developed by drift mining into mountainsides or hillsides, in which case the overlying cover could be more than 100 metres deep
Finally geological disposal is defined as disposal in a facility constructed in a particular geological formation (e.g. in terms of its long term stability and its
hydrogeological properties) at least a few hundred metres below ground level. Such a facility could be designed to receive high level radioactive waste . However with appropriate design a geological disposal facility could receive all types of radioactive waste

10. The classification of radioactive waste
In complement It is necessary to summarize the situation with regards to ILW and Intermediate depth disposal.
The classification of rw 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.

11. Consultancy on the need for a specific safety guide – March 2011
Consultancy organized in March 2011
Study and analyze the potential differences in terms of safety to expect between disposal of ILW at depths ranging from a few tens to a few hundred meters, geological disposal for HLW and near surface disposal
Conclusions
Term “Intermediate depth disposal” should be avoided/not useful
No specific SG for ILW disposal – already covered by SSG-14
Develop a safety report to address specific issues of ILW disposal
As a consequence and in order to try to finally address the issue a consultancy has been set up on the need of a specific safety guide on intermediate depth disposal or rather specific safety guide for Intermediate level waste.
The consultancy, which took place in Vienna in March 2011 aimed at studying and analyzing the potential differences in terms of safety to expect between disposal of ILW at depths ranging from a few tens to a few hundred meters, geological disposal for HLW and near surface disposal
3 experts took part of the consultancy:
Bengt hedberg from SSM sweden and who is as well the WASSC representative
Christophe serres form the French TSO IRSN
And Hirito KAWAKAMI from the japanese TSO

12. Consultancy to draft a technical document on disposal facilities for ILW – April 2013
Objectives
To discuss previous discussions and up-to-date information
To discuss contents of a new technical document
To prepare an draft document
To discuss work plan
Consultants
Don Howard (CNSC, Canada) : Chair
Jean-Michel Hoorelbeke (ANDRA, France)
Juergen Wollrath (BfS, Germany)
Fredrik Vahlund (SKB, Sweden)

13. Consultancy to draft a technical document on disposal facilities for ILW – April 2013
Outcome
Draft document on “SAFETY-RELATED ISSUES FOR THE DISPOSAL OF ILW”
Issues related to ILW disposal
Waste characteristics
Half-life and activity / Chemotoxicity / Waste volume /
Waste form properties and waste conditioning /
Properties related to the operational safety
Depth-related characteristics
Geological properties / Erosion /
Permafrost and glaciation /
Human intrusion / Redox
Design consideration for long-term isolation
Operational issues

14. This week
Objectives
Information sharing on various national activities
Discussion on common issues / Topics to be addressed in the Safety Report
Drafting of the Safety Report
Expected Outcome
Updated draft Safety Report
Preparation of Project Plan

15. International and Harmonization Projects in relation to Waste Management
CRAFT (successor to SADRWMS)
Application of GSG-3, SADRWMS methodology & SAFRAN Tool
Illustrative examples to complement SG (DS284)
PRISM
Safety case development / implementation for near-surface disposal
Barrier performance
Uncertainty
GEOSAF I / II
Safety on geological disposal
Regulatory expectations throughout development and operation
Assessment – engineering, site, radiological impact, integration
Working Group for the Dual Use Cask for Spent Nuclear Fuel
Safety case covering both transportation / storage
Extended periods of storage and meeting transport requirements
HIDRA
Human intrusion for both geological / near-surface disposal facilities
Relationship with siting/ designing/ waste acceptance criteria

16. Thank You