Inventory of Radioactive Waste

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Inventory of Radioactive Waste

Current Inventory as at

31 December 2014 and Prediction

August 2015

In the event of discrepancies between this translation

and the original German version, the latter shall prevail

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Contents

1.

Introduction ... 5

2.

Summarising evaluation ... 6

2.1 Scope of the data comprised ... 6

2.2 Classification and categorisation of the radioactive waste ... 6

2.3 Inventory of spent fuel and waste from reprocessing... 8

2.4 Inventory of other radioactive waste ... 8

3.

Waste inventories at the different sites ... 10

3.1 Sites in Baden-Württemberg ... 13

3.1.1 Karlsruhe – Central Decontamination Department (Hauptabteilung Dekontaminationsbetriebe – HDB) within the grounds of the Karlsruhe Institute of Technology (KIT) Campus North ... 13

3.1.2 Neckarwestheim nuclear power plant ... 14

3.1.3 Obrigheim nuclear power plant ... 16

3.1.4 Philippsburg nuclear power plant ... 17

3.1.5 Land collecting facility Baden-Württemberg ... 19

3.2 Sites in Bavaria ... 20

3.2.1 Garching – Technische Universität München ... 20

3.2.2 Karlstein – Siemens AG ... 21

3.2.3 Grafenrheinfeld nuclear power plant ... 22

3.2.4 Gundremmingen nuclear power plant ... 23

3.2.5 Isar nuclear power plant ... 25

3.2.6 Mitterteich – Power utilities storage facility ... 27

3.2.7 Mitterteich – Land collecting facility Bavaria... 28

3.3 Sites in Berlin... 29

3.3.1 Berlin – Helmholtz-Zentrum für Materialien und Energie GmbH ... 29

3.3.2 Berlin – Land collecting facility ... 30

3.4 Sites in Brandenburg ... 31

3.4.1 Rheinsberg nuclear power plant ... 31

3.4.2 Land collecting facility Brandenburg ... 32

3.5 Sites in Bremen ... 33

3.5.1 Land collecting facility Bremen ... 33

3.6 Sites in Hamburg ... 34

3.6.1 Land collecting facility Hamburg ... 34

3.7 Sites in Hesse ... 35

3.7.1 Ebsdorfergrund – Land collecting facility Hesse ... 35

3.7.2 Hanau – NUCLEAR CARGO + SERVICE ... 36

3.7.3 Biblis nuclear power plant ... 37

3.8 Sites in Mecklenburg-Western Pomerania ... 39

3.8.1 Greifswald nuclear power plant ... 39

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3.8.3 Rubenow – Zwischenlager Nord storage facility ... 41

3.9 Sites in Lower Saxony ... 43

3.9.1 Braunschweig – Eckert & Ziegler Nuclitec GmbH ... 43

3.9.2 Braunschweig – Research and measuring reactor ... 44

3.9.3 Gorleben – Storage facility ... 45

3.9.4 Emsland nuclear power plant ... 47

3.9.5 Grohnde nuclear power plant ... 48

3.9.6 Lingen nuclear power plant ... 49

3.9.7 Stade nuclear power plant ... 50

3.9.8 Unterweser nuclear power plant ... 51

3.9.9 Land collecting facility Lower Saxony ... 53

3.9.10 Leese – external storage facility for radioactive waste ... 54

3.9.11 Lingen – Fuel fabrication plant ... 55

3.9.12 Munster – central collecting facility of the German Armed Forces (Bundeswehr) ... 56

3.10 Sites in North Rhine-Westphalia ... 57

3.10.1 Ahaus – Transport Cask Storage Facility Ahaus ... 57

3.10.2 Duisburg – Gesellschaft für Nuklearservice mbH ... 58

3.10.3 Gronau – Uranium enrichment plant ... 59

3.10.4 Hamm-Uentrop – High temperature reactor nuclear power plant ... 60

3.10.5 Jülich – Nuclear research reactor ... 61

3.10.6 Jülich – Research centre ... 62

3.10.7 Jülich – Gesellschaft für Nuklear-Service mbH ... 63

3.10.8 Jülich – Land collecting facility North Rhine-Westphalia ... 64

3.10.9 Würgassen nuclear power plant ... 65

3.10.10 Krefeld – Siempelkamp Nukleartechnik GmbH ... 66

3.11 Sites in Rhineland-Palatinate ... 67

3.11.1 Ellweiler – Land collecting facility Rhineland-Palatinate ... 67

3.11.2 Mülheim-Kärlich nuclear power plant ... 68

3.11.3 Mainz – TRIGA Research Reactor Mainz ... 69

3.12 Sites in Saarland ... 70

3.12.1 Elm-Derlen – Land collecting facility Saarland ... 70

3.13 Sites in Saxony ... 71

3.13.1 Rossendorf – Land collecting facility Saxony ... 71

3.13.2 Rossendorf – VKTA – Strahlenschutz, Analytik & Entsorgung Rossendorf e. V. ... 72

3.14 Sites in Saxony-Anhalt ... 73

3.14.1 Land collecting facility Saxony-Anhalt ... 73

3.15 Sites in Schleswig-Holstein ... 74

3.15.1 Geesthacht – Helmholtz-Zentrum Geesthacht – Centre for Materials and Coastal Research GmbH 74 3.15.2 Geesthacht – Land collecting facility ... 75

3.15.3 Brokdorf nuclear power plant ... 76

3.15.4 Brunsbüttel nuclear power plant ... 77

3.15.5 Krümmel nuclear power plant ... 78

3.16 Sites in Thuringia ... 79

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3.17 Sites abroad ... 80

4.

Disposed-of radioactive waste... 81

5.

Radioactive waste prediction ... 82

5.1 Predicted amounts of spent fuel and waste from reprocessing ... 82

5.2 Predicted amounts of other radioactive waste ... 82

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1.

Introduction

Residual radioactive material generated during the handling of radioactive material as well

as disassembled or dismantled radioactive components shall be utilised without detrimental

effects or disposed of as radioactive waste in a controlled manner.

In the Federal Republic of Germany, radioactive waste is generated



in connection with the operation of nuclear power plants and experimental,

demonstration and research reactors,



in connection with the decommissioning of nuclear power plants and experimental

and demonstration reactors, of research and training reactors, and of other nuclear

facilities,



in connection with uranium enrichment and the fabrication of fuel assemblies

(nuclear industry),



in connection with basic and applied research,



in connection with the use of radioisotopes in other research institutions,

universities, trade and industry companies, hospitals and medical practices,



in connection with other waste originators, such as e.g. the military sector,



in future in connection with the conditioning of spent fuel intended for direct

disposal.

The

Inventory of Radioactive Waste

provides an overview of the inventory of radioactive

waste and spent fuel assemblies in Germany which have been generated and are to be

disposed of or have already been disposed of as at 31 December 2014 and a prediction of

the expected volume of radioactive waste that will have arisen by the year 2080. It

represents one of the bases for the planning of waste management and for the preparation

of the National Programme. By indicating which radioactive waste is present in which

location, the Federal Ministry for the Environment, Nature Conservation, Building and

Nuclear Safety (

Bundesministerium für Umwelt, Naturschutz, Bau und Reaktorsicherheit

–

BMUB) complies with the required reporting to the EU Commission according to Directive

2011/70/Euratom on behalf of the Federal Republic of Germany.

The inventory of radioactive waste is subject to constant change, which is why the

Inventory

of Radioactive Waste

can only reflect the status at a specific point in time and will therefore

be updated every three years.

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2.

Summarising evaluation

2.1

Scope of the data comprised

The

Inventory of Radioactive Waste

comprises spent fuel and radioactive waste from

reprocessing abroad in Europe that had already been returned by the reference date of

31 December 2014 as well as all types of radioactive waste to be disposed of in the Federal

Republic of Germany.

Radioactive waste from industrial, medical and research applications that has to be delivered

to a

Land

collecting facility rather than directly to a federal disposal facility will only be taken

into account once it has been delivered to a

Land

collecting facility.

2.2

Classification and categorisation of the radioactive waste

For the purpose of representation in the

Inventory of Radioactive

Waste, a general

distinction is made between:



spent fuel and radioactive waste from reprocessing, and



other radioactive waste.

Due to their high level of decay heat, the former count as heat-generating waste and can be

allocated for the largest part to the category of high-level waste according to the IAEA

classification. With a few exceptions, the other radioactive waste belongs to the waste with

negligible heat generation and is classified as low-level and intermediate-level waste

according to the IAEA.

The other radioactive waste (radioactive waste with negligible heat generation) is

categorised

1)

according to its

processing condition

for representation in the

Inventory of

Radioactive Waste

:



Raw waste

is radioactive waste in its form of origin.



Pretreated waste

has been pretreated for better handling or storage. For its disposal,

however, it has to be further conditioned.



Conditioned waste products

are waste in inner containers

(e.g. drums) that have

been conditioned to such an extent that any further treatment will no longer change

its product properties. However, this waste will still have to be packaged in a disposal

cask prior to its disposal.



Disposal Containers

are waste products in a type of container intended for disposal.

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1)

Here, the category system as defined in Appendix X of the German Radiation Protection Ordinance (StrlSchV) using primary waste (R), intermediate product (Z) and conditioned waste (K) for the purpose of inventorying the radioactive waste is replaced by the category system below. The comparison of the category systems is shown in Table 2.1.

For the purpose of inventorying the radioactive waste, the waste is divided according to its state of processing into raw waste (RA), i.e. waste in its original form, and pretreated waste (VA), which e.g. has undergone preconditioning for better handling. For storage, waste will generally be conditioned. The conditioning process normally generates waste products that are usually stored in i.e. drums (as inner containers for future disposal containers) (P1) or already in disposal containers that are intended for the Konrad repository (G1). The product properties of this waste are generally not to be altered until its disposal. In the course of the product control by the Federal Office for Radiation Protection (BfS) it has to be ascertained that the waste product, if it meets the waste acceptance requirements, is suitable for emplacement in the Konrad repository. If this is the case at least for the radiological aspects, a product-controlled waste product (P2) is generated from the waste product of the P1 category. The waste products of the P2 category will then be inserted into Konrad containers for disposal and, if necessary, grouted in concrete (G1). If suitability of the disposal container (G1) for disposal is confirmed by the BfS, it will be categorised as a product-controlled disposal container (G2) which can be enrolled and requested for emplacement in the Konrad repository. A disposal container does not necessarily run through all steps from RA to G2; however, only G2 packages may be disposed of in the Konrad repository.

Table 2.1: Correlation between the former and the more recent category system Raw waste and

pretreated waste Conditioned waste products Disposal containers RA VA P1 P2 G1 G2 Primary waste Intermediate product Conditioned waste X X X X X X X X X

In the Inventory of Radioactive Waste, RA and VA are summarised in one category, P1 and P2 are summarised as waste products, and G1 and G2 as disposal containers for reasons of clarity.

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2.3

Inventory of spent fuel and waste from reprocessing

At the reference date of 31 December 2014, about 8,380 Mg HM

2

had been generated from

the operation of nuclear power plants

3

in the Federal Republic of Germany in the form of

spent fuel assemblies (FA), which will have to be disposed of in Germany.

Table 2.2: Inventory of spent fuel from German nuclear power plants, stored in Germany, as at 31 December 2014

Storage location Containers Fuel

assemblies

Mass

Nuclear power plant storage pools* 14,013 FA 4,258 Mg HM

Dry cask storage in on-site storage facilities 352 9,638 FA 3,444 Mg HM Dry cask storage in the Ahaus and Gorleben storage

facilities and the Zwischenlager Nord storage facility

76 5,343 FA 677 Mg HM Total: 28,994 FA 8,379 Mg HM

*_{including the wet storage facility at the site of the Obrigheim nuclear power plant, which is being}

decommissioned, and the reactor core of the permanently closed down Brunsbüttel nuclear power plant

Radioactive waste that has been returned from reprocessing abroad in Europe and high-level

vitrified waste that has been generated in Germany is stored in the Gorleben and

Zwischenlager Nord storage facilities in the form of 3,164 canisters in 113 casks.

The amount of spent fuel from German experimental and demonstration reactors yet to be

disposed of are in dry storage in 461 casks in the Ahaus storage facility, at the research

centre Forschungszentrum Jülich, and in the Zwischenlager Nord storage facility.

The amount of spent fuel from research reactors is less by several orders of magnitude than

the amount from nuclear power plants and is stored by the research reactors in Berlin,

Garching and Mainz as well as in 18 casks in the Ahaus storage facility.

2.4

Inventory of other radioactive waste

The inventory of other radioactive waste is given in Table 2.3. The distribution of the around

117,000 m³ of conditioned radioactive waste present at the reference date of 31 December

2014 between the groups of waste originators can be taken from Fig. 2.1.

2_{Megagram of heavy metal (Mg HM) is the unit of the mass of heavy metal and hence a measure for the fuel}

content (uranium, plutonium and thorium) of a fuel assembly.

3

Nuclear power plant in this context describes an installation for the fission of nuclear fuel for the commercial generation of electricity.

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Fig. 2.1: Breakdown of the current inventory of other conditioned radioactive waste by groups of waste originators as at 31 December 2014

Table 2.3: Current inventory of other radioactive waste (as at 31 December 2014)4

Processing condition Mass/Volume5

Raw waste and pretreated waste 21,662 Mg

Conditioned waste products 16,908 m3

Disposal Containers 100,288 m3

The volume of raw waste and pretreated waste is given as their mass since the volume of

this waste is usually reduced by conditioning and therefore does not allow any conclusions

as to the volume to be disposed of. The conditioned waste is given as waste volume since in

this case, the expected volume to be disposed of will usually only grow by the packaging of

the waste products in disposal containers, but not by any changes of the waste product

itself.

Before a disposal container can be accepted for emplacement in the Konrad repository, the

product control process has to be concluded. In this process, the disposal container's

compliance with the requirements for disposal is verified.

So far, approx. 3,000 m³ of radioactive waste have been ascertained to comply with the

requirements for disposal in the Konrad repository and hence have been cleared for

enrollment for emplacement in the Konrad repository by the Federal Office for Radiation

Protection (BfS).

4

Differences to other publications are due to the processing of data with the focus on the storage facility site instead of on the waste owners.

5

Including other radioactive waste stored abroad.

Land collecting facilities 3% Nuclear power plants in in post-operational phase or under decommissioning 31% Nuclear power plants in operation 7% Nuclear industry 9% Research institutions 37% Reprocessing in Gemany 13%

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3.

Waste inventories at the different sites

For representation in the

Inventory of Radioactive Waste,

the waste was grouped by the

storage sites on 31 December 2014 as notified by the waste originators. The licence holder

of a facility is not necessarily identical with the originator (owner) of the waste. Since

according to § 78 of the Radiation Protection Ordinance (StrlSchV) storage may be executed

jointly by several waste originators or by third parties, the owner of the waste is not

necessarily the proprietor.

Conditioning facilities that are not clearly physically separated from the storage facilities are

included in the lists of the respective sites, with the amount of waste in the process of being

conditioned not explicitly shown.

In the case of external conditioning facilities, the waste in the process of being conditioned

there is listed. Once conditioning has been completed, the waste is moved to waste storage

facilities.

Fig. 3.1 gives an overview of the sites of the reactors, transport cask storage facilities, waste

storage facilities,

Land

collecting facilities and conditioning facilities in the Federal Republic

of Germany.

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Fig. 3.1:

Sites of the reactors, transport cask storage facilities, waste storage

facilities,

Land

collecting facilities and conditioning facilities for radioactive

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Regarding fuel assemblies, their dimensions and fuel content differ from reactor type to

reactor type. In general, the information on the number of fuel assemblies provided in the

Inventory of Radioactive

Waste represents the corroborated and reliable figures. Since the

associated mass of heavy metal – i.e. a measure for the fuel content (uranium, plutonium

and thorium) – is also of interest in connection with many other issues, this is also indicated.

These data were obtained by calculations. For this purpose, the number of fuel assemblies

was multiplied by an average mass of heavy metal per fuel assembly. It has to be noted in

this context that on the one hand, over the years the mass of heavy metal per fuel assembly

had been subjected to changes during production and on the other hand that it decreases as

a result of burn-up. The calculated masses of heavy metal can therefore only serve as guide

values and are not exactly identical with the actual masses in the spent fuel assemblies. It

has to be noted here that only little amounts of uranium and plutonium are present in the

waste from reprocessing as these were separated and reused.

The raw waste and the pretreated waste is differentiated by its chemical form, based on

Appendix X Part A No. 2 of the Radiation Protection Ordinance (StrlSchV). The conditioned

waste products are differentiated by the type and volume of the package

6)

.

6_{The package volumes indicated are the gross volumes of the packages. The respective typical volumes can be}

taken from the table below.

Container Gross volume Container Gross volume 200-l drum 0.27 m³ Cast-iron container Type III 1.00 m³

280-l drum 0.38 m³ Container Type I 3.90 m³

400-l drum 0.52 m³ Container Type I (Type KfK) 3.80 m³

570-l drum 0.75 m³ Container Type II 4.60 m³

Concrete container Type I 1.20 m³ Container Type III 8.70 m³ Concrete container Type II 1.30 m³ Container Type IV 7.40 m³ Cast-iron container Type I 0.70 m³ Container Type IV (Type KfK) 7.14 m³ Cast-iron container Type II 1.30 m³ Container Type V 10.90 m³ Cast-iron container Type II

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3.1

Sites in Baden-Württemberg

3.1.1

Karlsruhe – Central Decontamination Department (Hauptabteilung

Dekontaminationsbetriebe – HDB) within the grounds of the Karlsruhe Institute of

Technology (KIT) Campus North

Licence holder: WAK GmbH

Name of facility: WAK GmbH

Facility sections:

 Storage facilities

> unlimited licence

 Conditioning facilities

> unlimited licence

Other radioactive waste

Raw waste and pretreated waste Mass

Solid waste, inorganic 2,722.1 Mg

Solid waste, organic 75.6 Mg

Liquid waste, inorganic 64.0 Mg

Liquid waste, organic 2.9 Mg

Mixed waste 115.2 Mg

Radiation sources 5.3 Mg

Total: 2,985.1 Mg

Conditioned waste products Number Volume

200-l drum 6,942 1,874 m³

280-l drum 424 161 m³

400-l drum 421 219 m³

570-l drum 67 50 m³

Concrete container Type II 1 1 m³

Container Type IV (Type KfK) 16 114 m³

Cast-iron container Type II 32 42 m³

Total: 7,903 2,461 m³

Disposal containers Number Volume

Concrete container Type I 7,102 8,522 m³

Container Type IV 9 67 m³

Container Type IV (Type KfK) 6,517 46,546 m³

Cast-iron container Type II (Type KfK) 280 336 m³

Other 274 1,203 m³

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3.1.2

Neckarwestheim nuclear power plant

Licence holder: EnBW Kernkraft GmbH

Name of facility: Neckarwestheim nuclear power plant

Facility sections:

 Unit I

> post-operational phase

 Unit II

> in operation, power operating licence expires on 31 December 2022

 On-site storage facility

> storage limited to 40 years after first emplacement (6 December 2006)

Spent fuel and vitrified waste from reprocessing

Fuel assemblies Net mass

Storage pool 824 FA 385 Mg HM

Storage facility

- 44 Castor® V/19 836 FA 405 Mg HM

Total: 1,660 FA 790 Mg HM

Solid waste, inorganic 103.0 Mg

Mixed waste 6.5 Mg

Radiation source <0.1 Mg

Total: 160.1 Mg

200-l drum 335 90 m³

280-l drum 4 2 m³

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Disposal containers Number Volume

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3.1.3

Obrigheim nuclear power plant

Name of facility: Obrigheim nuclear power plant

Facility sections:

 Nuclear power plant

> under decommissioning

 Wet fuel assembly storage facility

> unlimited licence

Wet fuel assembly storage facility 342 FA 100 Mg HM

Total: 342 FA 100 Mg HM

Raw waste and pretreated waste Mass

Mixed waste 16.9 Mg

Total: 130.2 Mg

200-l drum 1 <1 m³

Other 302 82 m³

Total: 303 82 m³

Container Type II 25 115 m³

Container Type III 3 26 m³

Container Type V 31 338 m³

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3.1.4

Philippsburg nuclear power plant

Name of facility: Philippsburg nuclear power plant

Facility sections:

 Unit 1

 Unit 2

> in operation, power operating licence expires on 31 December 2019

> storage limited to 40 years after first emplacement (19 March 2007)

> unlimited licence

Fuel assemblies Net mass

Storage pool 1,427 FA 448 Mg HM Storage facility - 25 Castor® V/19 - 11 Castor® V/52 475 FA 572 FA 257 Mg HM 100 Mg HM Total: 2,474 FA 805 Mg HM

Mixed waste 31.9 Mg

Total: 168.1 Mg

200-l drum 3,142 848 m³

400-l drum 79 41 m³

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Disposal containers Number Volume

Concrete container Type I 44 53 m³

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3.1.5

Land

collecting facility Baden-Württemberg

The radioactive waste of the Land collecting facility Baden-Württemberg is stored at the site of the WAK Decommissioning and Waste Management Company (Wiederaufarbeitungsanlage Karlsruhe Rückbau- und Entsorgungs-GmbH) in Karlsruhe.

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3.2

Sites in Bavaria

3.2.1

Garching – Technische Universität München

Licence holder: Technische Universität München

Name of facility: Technische Universität München

Facility sections:

 Research Reactor Munich

 FRM II (Forschungs-Neutronenquelle Heinz Maier-Leibnitz) (in operation)

> unlimited licence

 Institute of Radiochemistry

> unlimited licence

Rack in the set-down pool of the FRM II 35 FA 243.5 kg

uranium

Total: 35 FA 243.5 kg

uranium

Mixed waste 0.7 Mg

Total: 33.5 Mg

200-l drum 4 1 m³

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3.2.2

Karlstein – Siemens AG

Licence holder: Siemens AG, Energy Sector

Name of facility: Siemens AG

Facility sections:

 Nuclear energy experimental facility and service centre

> unlimited licence

 Storage facilities

> unlimited licence

Total: 29.2 Mg

200-l drum 4 1 m³

280-l drum 1 <1 m³

400-l drum 1 1 m³

Total: 10 7 m³

Container Type VI 236 1,274 m³

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3.2.3

Grafenrheinfeld nuclear power plant

Licence holder: E.ON Kernkraft GmbH

Name of facility: Grafenrheinfeld nuclear power plant

Facility sections:

> in operation, power operation licence expires on 31 December 2015

> storage limited to 40 years after first emplacement (27 February 2006)

Storage pool 404 FA 217 Mg HM Storage facility - 21 Castor® V/19 399 FA 214 Mg HM Total: 803 FA 431 Mg HM

Other radioactive waste

Total: 29.0 Mg

200-l drum 47 13 m³

Total: 47 13 m³

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3.2.4

Gundremmingen nuclear power plant

Licence holder: RWE Power AG

Name of facility: Gundremmingen nuclear power plant

Facility sections:

 Unit A

 Unit B

 Unit C

> storage limited to 40 years after first emplacement (25 August 2006)

> unlimited licence

Fuel assemblies Net mass

Storage pool 4,410 FA 767 Mg HM Storage facility - 42 Castor® V/52 2,184 FA 380 Mg HM Total: 6,594 FA 1,147 Mg HM

Mixed waste 19.4 Mg

Total: 74.2 Mg

200-l drum 667 180 m³

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Disposal containers Number Volume

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3.2.5

Isar nuclear power plant

Name of facility: Isar nuclear power plant

Facility sections:

 Isar 1

 Isar 2

> storage limited to 40 years after first emplacement (12 March 2007)

Storage pool 2,172 FA 536 Mg HM Storage facility - 25 Castor® V/19 - 9 Castor® V/52 475 FA 468 FA 254 Mg HM 81 Mg HM Total: 3,115 FA 871 Mg HM

Other radioactive waste

Mixed waste < 1 Mg

Total: 135.2 Mg

200-l drum 414 112 m³

280-l drum 17 6 m³

400-l drum 21 11 m³

570-l drum 5 4 m³

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Cast-iron container Type I 2 1 m³

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3.2.6

Mitterteich – Power utilities storage facility

Licence holder: GRB Sammelstelle Bayern für radioaktive Stoffe GmbH Name of facility: Power utilities storage facility Mitterteich _>

Licence limited until 31 December 2028

Other radioactive waste

200-l drum 11,899 3,213 m³ 280-l drum 287 109 m³ 400-l drum 106 55 m³ 570-l drum 26 20 m³ Other 5 14 m³ Total: 12,323 3,411 m³

Container Type I 6 23 m³

Container Type IV 164 1,214 m³

Cast-iron container Type II 1,993 2,591 m³

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3.2.7

Mitterteich –

Land

collecting facility Bavaria

Licence holder: GRB Sammelstelle Bayern für radioaktive Stoffe GmbH Name of facility: Land collecting facility Bavaria _>

Licence limited until 31 December 2028 Note: Raw waste is also accepted at the Neuherberg outpost.

Other radioactive waste

Mixed waste 7.2 Mg

Radiation sources <0.1 Mg

Total: 7.2 Mg

200-l drum 777 210 m³

280-l drum 6 2 m³

400-l drum 10 5 m³

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3.3

Sites in Berlin

3.3.1

Berlin – Helmholtz-Zentrum für Materialien und Energie GmbH

Licence holder: Helmholtz-Zentrum für Materialien und Energie GmbH Name of facility: Berliner-Experimentier-Reaktor II _>

Operation will cease on 31 December 2019

Spent fuel and vitrified waste from reprocessing

Set-down racks 57 FA 77.4 kg SM

Total: 57 FA 77.4 kg SM

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3.3.2

Berlin –

Land

collecting facility

Licence holder: Helmholtz-Zentrum für Materialien und Energie GmbH Name of facility: Land collecting facility Berlin

Facility sections:

 Land collecting facility

> unlimited licence

Gaseous waste <0.1 Mg

Mixed waste 27.9 Mg

Total: 230.1 Mg

200-l drum 287 78 m³

400-l drum 12 6 m³

Total: 298 83 m³

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3.4

Sites in Brandenburg

3.4.1

Rheinsberg nuclear power plant

Licence holder: EWN GmbH

Name of facility: Rheinsberg nuclear power plant

Facility sections:

> unlimited licence

Mixed waste 40.5 Mg

Total: 200.5 Mg

200-l drum 477 129 m³

570-l drum 1 1 m³

Total: 478 130 m³

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3.4.2

Land

collecting facility Brandenburg

The radioactive waste of the Land collecting facility is stored together with the waste of the Land

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3.5

Sites in Bremen

3.5.1

Land

collecting facility Bremen

collecting facilities Hamburg, Lower Saxony and Schleswig-Holstein at the Helmholtz-Zentrum Geesthacht – Centre for Materials and Coastal Research GmbH in Geesthacht.

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3.6

Sites in Hamburg

3.6.1

Land

collecting facility Hamburg

collecting facilities Bremen, Lower Saxony and Schleswig-Holstein at the Helmholtz-Zentrum Geesthacht – Centre for Materials and Coastal Research GmbH in Geesthacht.

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3.7

Sites in Hesse

3.7.1

Ebsdorfergrund –

Land

collecting facility Hesse

Licence holder: Hessian Agency for the Environment and Geology Name of facility: Land_ collecting facility Hesse

unlimited licence

Other radioactive waste

Total: 114.9 Mg

200-l drum 303 82 m³

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3.7.2

Hanau – NUCLEAR CARGO + SERVICE

Licence holder: NUCLEAR CARGO + SERVICE GmbH

Name of facility: NUCLEAR CARGO + SERVICE GmbH

Facility sections:  two storage facilities _> unlimited licence

Other radioactive waste

Total: 0.4 Mg

200-l drum 38 10 m³

280-l drum 2 1 m³

400-l drum 39 20 m³

570-l drum 5 4 m³

Total: 84 35 m³

Container Type IV (Type KfK) 278 1,985 m³

Container Type VI 954 5,152 m³

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3.7.3

Biblis nuclear power plant

Name of facility: Biblis nuclear power plant

Facility sections:

 Unit A and B

 Waste storage depot (LAW storage)

> unlimited licence

> storage limited to 40 years after first emplacement (18 May 2006)

> since the 3rd modification licence of 16 June 2014, the mixed storage of transport and storage casks and up to 252 Mosaik containers has been possible in storage hall No. 2

Spent fueland vitrified waste from reprocessing

Storage pool 946 FA 506 Mg HM Storage facility - 51 Castor® V/19 969 FA 519 Mg HM Total: 1,915 FA 1,025 Mg HM

Mixed waste 8.8 Mg

Total: 117.9 Mg

Conditioned waste products Number Volume

200-l drum 89 24 m³

280-l drum 24 9 m³

400-l drum 36 19 m³

570-l drum 3 2 m³

(38)

38

Cast-iron container Type III 674 674 m³

(39)

39

3.8

Sites in Mecklenburg-Western Pomerania

3.8.1

Greifswald nuclear power plant

Licence holder: Energiewerke Nord GmbH

Name of facility: Greifswald nuclear power plant

Facility sections:

 Nuclear power plant Units 1-6

> unlimited licence

Total: 586.2 Mg

200-l drum 200 54 m³

(40)

40

3.8.2

Rubenow –

Land

collecting facility Mecklenburg-Western Pomerania

Licence holder: ZLN GmbH and EWN GmbH

Name of facility:

Land collecting facility for radioactive waste of the Land of Mecklenburg-Western Pomerania

> unlimited licence

Note: The waste of the Land collecting facility for radioactive waste of the Land of Mecklenburg-Western Pomerania is stored together with the waste of the Land collecting facility of the Land of Brandenburg in the Zwischenlager Nord storage facility.

Raw waste and pretreated waste Mass

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41

3.8.3

Rubenow – Zwischenlager Nord storage facility

Licence holder: EWN GmbH, ZLN GmbH

Name of facility: Zwischenlager Nord

Facility sections:

 Storage for radioactive waste

> unlimited licence

 Storage facility

> Storage limited until 31 October 2039

> unlimited licence

Fuel assemblies and

canisters Net mass

Storage facility

- 62 Castor® 440/84 and 3 Castor® KRB-MOX - 4 Castor® KNK

- 5 Castor® HAW 20/28 CG with vitrified fission product solutions 5.048 FA 2,413 fuel rods 140 canisters 584 Mg HM 0.5 Mg HM Total: 5,048 FA 2,413 fuel rods 140 canisters 584.5 Mg HM

Other radioactive waste

Mixed waste 8.6 Mg

Total: 3,781.1 Mg

200-l drum 10,614 2,866 m³

280-l drum 34 13 m³

400-l drum 114 59 m³

570-l drum 18 14 m³

(42)

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Container Type IV (Type KfK) 477 3,406 m³

(43)

43

3.9

Sites in Lower Saxony

3.9.1

Braunschweig – Eckert & Ziegler Nuclitec GmbH

Licence holder: Eckert & Ziegler Nuclitec GmbH Name of facility: Conditioning facilities _>

unlimited licence

Other radioactive waste

Mixed waste 31.4 Mg

(44)

44

3.9.2

Braunschweig – Research and measuring reactor

Licence holder: Physikalisch-Technische Bundesanstalt

Name of facility: Research and measuring reactor Braunschweig

Facility sections:

 Research reactor

> dismantled, released from nuclear supervision with the exception of the storage facility

> licence limited until emplacement in a federal disposal facility is possible, with additional adequate time for work related to the delivery to the disposal facility

Conditioned waste products Number Volume

200-l drum 84 23 m³

400-l drum 32 17 m³

570-l drum 2 2 m³

Total: 118 42 m³

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3.9.3

Gorleben – Storage facility

Licence holder: BLG Brennelementlager Gorleben GmbH,

GNS Gesellschaft für Nuklear-Service mbH Name of facility: Storage facility Gorleben

Facility sections:

 Gorleben waste storage facility

> unlimited handling licence

 Transport cask storage facility

> storage licence limited until 31 December 2034

Spent fueland vitrified waste from reprocessing

Fuel assemblies and

canisters Net mass

Storage facility - 3 Castor® V/19 - 1 Castor® Ic - 1 Castor® IIa

- 74 Castor® HAW 20/28 CG with vitrified fission product solutions

- 12 TN® 85 with vitrified fission product solutions - 1 TS® 28 V with vitrified fission product solutions - 21 Castor® HAW28M with vitrified fission product

solutions 57 FA 16 FA 9 FA 2,072 canisters 336 canisters 28 canisters 588 canisters 30 Mg HM 3 Mg HM 5 Mg HM Total: 82 FA 3,024 canisters 38 Mg HM

Other radioactive waste

200-l drum 1,020 275 m³

280-l drum 216 82 m³

400-l drum 296 154 m³

(46)

46

Container Type V 301 3,281 m³

Container Type VI 65 351 m³

Cast-iron container Type II 1,015 1,320 m³

Cast-iron container Type III 113 113 m³

(47)

47

3.9.4

Emsland nuclear power plant

Licence holder: Kernkraftwerke Lippe-Ems GmbH

Name of facility: Emsland nuclear power plant

Facility sections:

> in operation, power operation licence expires on 31. December 2022

> storage limited to 40 years after first emplacement (10 December 2002)

Storage pool 510 FA 274 Mg HM Storage facility - 32 Castor® V/19 608 FA 327 Mg HM Total: 1,118 FA 601 Mg HM

Other radioactive waste

Total: 24.7 Mg

200-l drum 58 16 m³

Total: 58 16 m³

(48)

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3.9.5

Grohnde nuclear power plant

Name of facility: Grohnde nuclear power plant

Facility sections:

> storage limited to 40 years after first emplacement (27 April 2006)

Other radioactive waste

Mixed waste 17.0 Mg

Total: 56.1 Mg

200-l drum 323 87 m³

400-l drum 5 3 m³

Total: 328 90 m³

(49)

49

3.9.6

Lingen nuclear power plant

Licence holder: Kernkraftwerk Lingen GmbH

Name of facility: Lingen nuclear power plant _>

in safe enclosure, transition to dismantling

Other radioactive waste

Mixed waste 19.3 Mg

Total: 146.8 Mg

200-l drum 579 156 m³

280-l drum 26 10 m³

Total: 605 166 m³

(50)

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3.9.7

Stade nuclear power plant

Name of facility: Stade nuclear power plant

Facility sections:

 Storage for radioactive waste (LarA)

> to be cleared out once the Konrad repository is in operation, therefore limited to a maximum of 40 years from date of commissioning (July 2007)

Mixed waste 6.0 Mg

Total: 585.2 Mg

200-l drum 649 175 m³

280-l drum 9 3 m³

Total: 658 178 m³

Container Type IV 183 1,354 m³

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3.9.8

Unterweser nuclear power plant

Name of facility: Unterweser nuclear power plant

Facility sections:

 Storage facility Unterweser

> unlimited licence

> storage limited to 40 years after first emplacement (18 June 2007)

Other radioactive waste

Mixed waste 0.4 Mg

Total: 44.1 Mg

200-l drum 1,375 371 m³

280-l drum 79 30 m³

400-l drum 63 33 m³

570-l drum 78 59 m³

(52)

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(53)

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3.9.9

Land

collecting facility Lower Saxony

Since 2002, the Land collecting facility Lower Saxony has been operated by Gesellschaft für Nuklear-Service (GNS). GNS accepts the raw waste intended for the Land collecting facility Lower Saxony and conditions it at its facility within the grounds of the research centre Forschungszentrum Jülich. After conditioning and packaging in line with the requirements for disposal, the waste is transported to the storage facility of the Eckert & Ziegler Nuclitec company in Leese and emplaced there. In addition, there are 4,885 200-liter drums in the Leese storage facility which were accepted by the Land

collecting facility Lower Saxony prior to 2002.

Old waste of the Land collecting facility Lower Saxony is furthermore stored together with waste of the Land collecting facilities of Bremen, Hamburg and Schleswig-Holstein at the Helmholtz-Zentrum Geesthacht – Centre for Materials and Coastal Research GmbH in Geesthacht.

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3.9.10 Leese – external storage facility for radioactive waste

Licence holder: Eckert & Ziegler Nuclitec GmbH

Name of facility: Leese external storage facility for radioactive waste _> unlimited licence

Other radioactive waste

200-l drum 4,885 1,319 m³

Total: 4,885 1,319 m³

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3.9.11 Lingen – Fuel fabrication plant

Licence holder: Advanced Nuclear Fuels GmbH

Name of facility: Fuel fabrication plant

Facility sections:  Fabrication plant for fuel assemblies _> unlimited licence

Other radioactive waste

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3.9.12 Munster – central collecting facility of the German Armed Forces (Bundeswehr)

Licence holder: Bundeswehr Research Institute for Protective Technologies and NBC Protection (WIS) in Munster

Name of facility: Central Collecting Point for Bundeswehr radioactive waste _> unlimited licence

Other radioactive waste

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3.10 Sites in North Rhine-Westphalia

3.10.1 Ahaus – Transport Cask Storage Facility Ahaus

Licence holder: GNS Gesellschaft für Nuklear-Service mbH, Brennelement-Zwischenlager Ahaus GmbH

Name of facility: Transport Cask Storage Facility Ahaus

 Storage limited until 31 December 2036, storage licence according to §7 StrlSchV limited to 10 years after first emplacement (21 July 2010)

Spent fuel and vitrified waste from reprocessing

Storage facility - 3 Castor® V/19 - 3 Castor® V/52 - 305 Castor® THTR/AVR - 18 Castor® MTR 2 57 FA 156 FA 617,606 FA spheres 951 FA 29 Mg HM 26 Mg HM 7 Mg HM 2 Mg* Total: 1,164 FA and 617,606 FA spheres 62 Mg HM 2 Mg* *

Gross mass of fuel assemblies at the time of allocation for disposal. Apart from the total mass of the fuel, it also comprises the mass of non-separable cladding and construction materials. The separable top and bottom end pieces are not considered here.

Disposal Containers Number Volume

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3.10.2 Duisburg – Gesellschaft für Nuklearservice mbH

Licence holder: GNS Gesellschaft für Nuklear-Service mbH Name of facility: Conditioning facilities

> Licence limited until 31 December 2022

Other radioactive waste

Total: 389.2 Mg

200-l drum 971 262 m³

(59)

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3.10.3 Gronau – Uranium enrichment plant

Licence holder: URENCO Deutschland GmbH

Name of facility: Uranium enrichment plant

Facility sections:

 Plant

> unlimited licence

Liquid waste, inorganic < 0.1 Mg

Liquid waste, organic < 0.1 Mg

Total: 6.6 Mg

200-l drum 54 15 m³

Total: 54 15 m³

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3.10.4 Hamm-Uentrop – High temperature reactor nuclear power plant

Licence holder: Hochtemperatur Kernkraftwerk GmbH (HKG)

Name of facility: Thorium High Temperature Reactor (THTR) _> in safe enclosure

Other radioactive waste

Total: 278.1 Mg

200-l drum 60 16 m³

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3.10.5 Jülich – Nuclear research reactor

Licence holder: Arbeitsgemeinschaft Versuchsreaktor GmbH Name of facility: Jülich nuclear research reactor

Facility sections:  Research reactor _>

under decommissioning

Other radioactive waste

Mixed waste 15.5 Mg

Total: 709.6 Mg

200-l drum 97 26 m³

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3.10.6 Jülich – Research centre

Licence holder: Forschungszentrum Jülich GmbH

Name of facility: Forschungszentrum Jülich

Facility sections:

 Research reactor 2

 Storage facility

> Clear-out ordered

 Waste storage facility

> unlimited licence

Fuel assemblies Net mass Storage facility

- 152 Castor® THTR/AVR approx. 290,000

AVR FA spheres 2 Mg HM Total: approx. 290,000 AVR FA spheres 2 Mg HM

Other radioactive waste

Mixed waste 4,226.9 Mg

Total: 4,437.2 Mg

200-l drum 618 167 m³

Total: 618 167 m³

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3.10.7 Jülich – Gesellschaft für Nuklear-Service mbH

Licence holder: GNS Gesellschaft für Nuklear-Service mbH Name of facility: Conditioning facilities _>

unlimited licence

Other radioactive waste

Mixed waste 7.4 Mg

Radiation source 1.4 Mg

Total: 182.0 Mg

200-l drum 1,386 374 m³

280-l drum 2 1 m³

400-l drum 5 3 m³

Other 3 2 m³

Total: 1,396 380 m³

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3.10.8 Jülich –

Land

collecting facility North Rhine-Westphalia

Licence holder: Cologne district government

Name of facility: Land collecting facility North Rhine-Westphalia _> unlimited licence

Other radioactive waste

Total: 1.2 Mg

200-l drum 875 236 m³

280-l drum 676 257 m³

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3.10.9 Würgassen nuclear power plant

Name of facility: Würgassen nuclear power plant

Facility sections:

> under decommissioning  UNS storage facility

> in §7 AtG licence of the nuclear power plant included, albeit limited until 31 December 2033

 Transport preparation hall

> limited licence until 31 December 2045

Mixed waste 47.0 Mg

Total: 75.1 Mg

200-l drum 1,170 316 m³

280-l drum 1,508 573 m³

Total: 2,678 889 m³

Container Type II 19 87 m³

Container Type III 136 1,183 m³

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3.10.10 Krefeld – Siempelkamp Nukleartechnik GmbH

Licence holder: Siempelkamp Nukleartechnik GmbH

Name of facility: CARLA – melting facility _>

Licence limited until 31 December 2015

Other radioactive waste

Mixed waste 5.8 Mg

Total: 2,154.7 Mg

200-l drum 270 73 m³

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3.11 Sites in Rhineland-Palatinate

3.11.1 Ellweiler –

Land

collecting facility Rhineland-Palatinate

Licence holder: Landesamt für Umwelt, Wasserwirtschaft und Gewerbeaufsicht Rheinland-Pfalz

Name of facility: Land_ collecting facility Rhineland-Palatinate unlimited licence

Other radioactive waste

Raw waste and pretreated waste

Mass

Total: 155.2 Mg

200-l drum 35 9 m³

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3.11.2 Mülheim-Kärlich nuclear power plant

Name of facility: Mülheim-Kärlich nuclear power plant _> under decommissioning

Other radioactive waste

(69)

69

3.11.3 Mainz – TRIGA Research Reactor Mainz

Licence holder: Mainz University

Name of facility: TRIGA Research Reactor Mainz _> in operation, unlimited licence

Spent fuel and vitrified waste from reprocessing

Wet/dry storage facility 4 FA 764 g uranium

(70)

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3.12 Sites in Saarland

3.12.1 Elm-Derlen –

Land

collecting facility Saarland

Licence holder: Ministry of Environment and Consumer Protection Name of facility: Land_ collecting facility Saarland

unlimited licence

The waste of the Land collecting facility Saarland is currently being conditioned in compliance with the requirements for disposal by Eckert & Ziegler Nuclitec GmbH.

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3.13 Sites in Saxony

3.13.1 Rossendorf –

Land

collecting facility Saxony

Licence holder: VKTA – Strahlenschutz, Analytik & Entsorgung Rossendorf e.V. Name of facility:

Land collecting facility of the Free State of Saxony for radioactive waste

> unlimited licence

Other radioactive waste

Mixed waste 76.0 Mg

Total: 78.4 Mg

200-l drum 17 5 m³

280-l drum 11 4 m³

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3.13.2 Rossendorf – VKTA – Strahlenschutz, Analytik & Entsorgung Rossendorf e. V.

Licence holder: VKTA – Strahlenschutz, Analytik & Entsorgung Rossendorf e. V.

Name of facility: Research centre

Facility sections:

 Research centr