<Czech Republic example>

1. National Waste Classification and Policy- Describe national waste classification focusing on the results, no description on the process

(give reference of the process or other relevant materials.

In the Czech Republic, the IAEA waste classification system is incorporated into Regulation No. 307/2002 on radiation protection Coll. of SONS (State Office for Nuclear Safety). Considering disposal options, low level and intermediate level waste are classified into three principal categories: energetical waste, institutional waste containing artificial radionuklides, and institutional waste containing natural radionuclides. Waste classification specified in the legislation is not explicitly bound to disposal options. The principal condition for waste disposal is to meet radioprotection criteria, i. e. 0,25 mSv/yr – limit of effective dose for a member of critical group (normal evolution ecenario and alternative scenarios), and 1 mSv/yr – limit of effective dose for a member of critical group (scenarios with a low probability, e.g. inadvertent intrusion).

Czech Republic legislative frame is presently subject to changes that should come into force in 2015. A new regulation focused on radioactive waste management will be issued. Waste classification should be extended: very low level waste will be added as a new category.

Radioactive waste disposed off in repository sites have to meet acceptance conditions derived using safety assessment. Acceptance conditions specified using the radiation protection criteria are specified as limits of total and/or volume activities. There is no direct relation between waste classification meant above and acceptance conditions derived using waste, repository and site characteristics: radioprotection criteria are the principal parameters determining the choice of the waste management option.

At present, there are operated three disposal facilities:

- repository Dukovany (short lived and low level waste form nuclear powr plants), a subsurface repository

- repository Richard (low level and intermediate level waste of institutional origin, containing artificial radionuclides), a subsurface repository in a former mine

- repository Bratrství (low level and intermediate level waste of institutional origin, containing natural radiouclides), a subsurface repository in a former mine

- one facility (Hostim) has been closed, and post operational monitoring is still in process

Radioactive waste management policy consists of principles specified in Atomic law and in a set of regulations issued by SONS. The principles can be shortly listed as nuclear safety and security, radiation protection, optimization and quality assurance. The government is responsible for developing the policy. Nuclear account is a fund collected from waste producers, designated for financing of activities granted by state through RAWRA (Radioactive Waste Repository Authority), i.e. for siting, development, operation, closure and institutional control of disposal facilities.

2. Approach to managing the ILW

LLW and ILW is disposed off in two of existing facilities, Richard and Bratrství. Both of them are situated in subsurface abandonned mines, with a horizontal access. The thickness of the host structure above the waste disposed is 40 – 60 m and minimum 120 m, respectively.

- Repository Richard is situated in a former limestone mine. Institutional waste containing artificial radionuclides is disposed off to Richard repository. The volume capacity of the repository (10 000 m3) should be spent in several future years. At present, a project of reconstruction of some volumes is prepared to assure new disposal volumes for one or two decades of operation. Possible disposal of institutional waste containing natural radionuclides is considered as well, but re-licensing process would be obligatory.

Schematic figure of repository Richard.

vol-ume

H-3 C-14 Cl-36 Sr-90 Tc-99 I-129 Cs-137

alfa Pu-239

Am-241

0.0010.0020.0030.0040.0050.0060.0070.0080.00

65.98

3.76 10.41 0.90 8.48 4.34 10.63

35.88

5.55

76.20 78.29

Spent volume and limit of total activity [%], Richard repository

Percentage of used volume and used activity limits.

- Repository Bratrství is situated in a former uranium mine. The repository has been operated since 1972. Institutional waste containing natural radionuclides is disposed off to Bratrství repository. The volume capacity of the repository (1 200 m3) should be spent in several years. At present, a project of reconstruction of some volumes is prepared to assure new disposal volumes for five to ten years of operation.

Schematic figure of repository Bratrství.

Percentage of used volume and used activity limits.

3. Details of Existing Disposal Facilities

3.1 Richard repository3.1.1 Disposal option and timescales

Radioactive waste is usually disposed in 200 l drums to disposal chambers adapted for disposal. More than 25 chambers are available, and at present, only four of them contain free volumes. After the chambers are full with waste, they are stabilized in a hydraulic cage system based on application of cement mixture. Disposal started in 1964, and by actually approved plan of closure, it shoud be close in twenty years. But, considering the possibilities of the site, re-construction of other chambers is planned and the intention is to operate the repository at least till 2050.

Certain capacity of the repository is used for storage of institutional waste that does not meet acceptance conditions for disposal.

3.1.2 Waste characteristics and volume

Institutional waste containing artificial radionuclides is characterized as follows. More waste forms have been approved for disposal (solidified, non-solidified) and more types of containers (simple drum 200 l, double drum 200 l, MOZAIK container).

Limit Disposed [%] Capacity left

volume [m3] 10249 6762 65,98 3487

H-3

[Bq]

1,00E+15 3,76E+13 3,76 9,62E+14

C-14 1,00E+14 1,04E+13 10,41 8,96E+13

Cl-36 1,00E+12 9,05E+09 0,90 9,91E+11

Sr-90 1,00E+14 8,48E+12 8,48 9,15E+13

Tc-99 1,00E+11 4,34E+09 4,34 9,57E+10

I-129 2,00E+08 2,13E+07 10,63 1,79E+08

Cs-137 1,00E+15 3,59E+14 35,88 6,41E+14

alfa 2,00E+13 1,11E+12 5,55 1,89E+13

Pu-239 5,00E+12 3,81E+12 76,20 1,19E+12

Am-241 1,30E+13 1,02E+13 78,29 2,82E+12

3.1.3 Siting and safety function of natural barriers

Siting was not subject to present legislation. The host structure (limestone) provides a protective layer above repository (40 – 60 m) and about 60 m of unsaturated zone. The environmental host structure is formed by granitic rock. The distance of potential source of water is 3 500 m. The isolation, retention

and dilution capacity of natural barriers provide sufficent protection from potential hazard of waste release.

3.1.4 Disposal facility design including EBS design

EBS system consists of stabilization filling based on cement and hydrualic cage system. The system should protect the near field from advective flow of water for about 5 thousand years.

3.1.5 Facility specific considerations

As it is proposed in safety case, institutional control is planned for 100 yrs. After than, unrestricted release of the facility is assumed, and possibility of intrusion is evaluated. Thanks to application of stabilization matrials, no possibility of retrival is considered.

3.2 Bratrství repository3.2.1 Disposal option and timescales

Radioactive waste is usually disposed in 200 l drums to disposal chambers adapted for disposal. Five chambers are available, at present, only two of them contain free volume for about one hundred drums. After the chambers are full with waste, they are stabilized in a hydraulic cage system based on application of cement mixture. Disposal started in 1972, and by actually approved plan of closure, the operational phase of the repository shoud be closed very early, in approximately five years. Re-construction of other volumes in the repository is planned and the intention is to operate the repository a little bit longer, for another ten years.

3.2.2 Waste characteristics and volume

Institutional waste containing natural radionuclides is characterized as follows. More waste forms have been approved for disposal (solidified, non-solidified) and one principal type of container (simple drum 200 l) is approved.

Limit Disposed [%] Capacity left

volume [m3] 1100 839 76,25 261

Ra-226

[Bq]

5,00E+12 1,35E+12 26,94 3,65E+12

Th-232 3,00E+12 1,37E+08 0,00 3,00E+12

U 2,00E+12 5,30E+11 26,50 1,47E+12

alfa 1,00E+13 1,91E+12 19,14 8,09E+12

3.2.3 Siting and safety function of natural barriers

Siting was not subject to present legislation. The host structure (limestone) provides a protective layer above repository (120 m). The environmental host structure is formed by granitic rock. The isolation, retention and dilution capacity of natural barrier is very limited due to missing non saturated zone and closness of mine water sources and surface water flows.

3.2.4 Disposal facility design including EBS design

EBS system consists of stabilization filling based on cement and hydrualic cage system. The system should protect the near field from advective flow of water for about 5 thousand years.

3.2.5 Facility specific considerations

As it is proposed in safety case, institutional control is planned for 100 yrs. After than, unrestricted release of the facility is assumed, and possibility of intrusion is evaluated. Thanks to application of stabilization matrials, no possibility of retrival is considered.

Reference- Regulation SONS No. 307/2002 Coll., on radiation protection (waste calssification, radiological

limits)- Safety report of Richard repository, RAWRA 2014- Limits and conditions of oparation of Richard repository, RAWRA 2014- Safety report of Bratrství repository, RAWRA 2013- Limits and conditions of oparation of Bratrství repository, RAWRA 2013