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<strong>Decommissioning</strong> <strong>and</strong> <strong>dismantlement</strong> <strong>of</strong> <strong>the</strong> <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> plant –<br />

from <strong>nuclear</strong> <strong>power</strong> plant to green fields<br />

<strong>Stade</strong>


Contents<br />

3|The <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station – a short history<br />

4|What does ”decommissioning <strong>and</strong> <strong>dismantlement</strong>”<br />

actually mean?<br />

5|Why is <strong>the</strong> <strong>Stade</strong> plant being decommissioned?<br />

Commercial factors<br />

6|What experience do we have when<br />

it comes to decommissioning <strong>nuclear</strong> <strong>power</strong> stations?<br />

Dismantlement methods<br />

Expertise that’s based on experience<br />

Decommissioned <strong>and</strong> dismantled <strong>nuclear</strong> <strong>power</strong> stations in Germany<br />

Reactor types<br />

The <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station: special features<br />

12 | What, exactly, does <strong>the</strong> dismantling process involve?<br />

From full-load operation to decommissioning:<br />

The transition phase:<br />

Dismantlement Phases I - IV<br />

Conventional dismantling<br />

Timeframe<br />

20 | What does decommissioning mean for <strong>Stade</strong>’s<br />

employees?<br />

Different workforce structures required<br />

Staffing cutbacks<br />

22 | What happens to <strong>the</strong> dismantled parts <strong>and</strong> materials?<br />

Disposal methods<br />

Waste material categories<br />

Mechanical breakdown <strong>of</strong> materials<br />

Decontamination<br />

Safety clearance<br />

Radioactive waste<br />

28 | What happens to <strong>the</strong> vacant site?<br />

Green fields<br />

30 | What is <strong>the</strong> regulatory environment under which<br />

decommissioning is performed?<br />

Statutes <strong>and</strong> regulations<br />

Clearance procedures<br />

Environmental impact analysis<br />

32 | The <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station in brief


The <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station – a short history<br />

July 28, 1967 Nordwestdeutsche Kraftwerke AG applies for a government permit<br />

to build <strong>and</strong> operate a <strong>nuclear</strong> <strong>power</strong> station near <strong>the</strong> German city <strong>of</strong> <strong>Stade</strong><br />

October 1967 Siemens AG is awarded <strong>the</strong> contract to build a turnkey <strong>nuclear</strong> <strong>power</strong> station<br />

November 17, 1967 Permit for earthworks granted; construction works begin<br />

March 1968 Plant operating company Kernkraftwerk <strong>Stade</strong> GmbH established<br />

June 1971 Non-<strong>nuclear</strong> plant <strong>and</strong> equipment commissioned<br />

January 7, 1972 Permit granted for commissioning <strong>of</strong> <strong>nuclear</strong> plant <strong>and</strong> equipment<br />

January 8, 1972 Reactor attains first criticality<br />

January 29, 1972 <strong>Stade</strong> begins to feed electricity into <strong>the</strong> public grid<br />

March 26, 1972 First test at full load<br />

May 19, 1972 Official h<strong>and</strong>-over to Kernkraftwerk <strong>Stade</strong> GmbH <strong>and</strong> start <strong>of</strong> commercial<br />

on-load operation<br />

1984 <strong>Stade</strong> starts cogenerating process heat for a neighboring salt works<br />

Fall 2000 For commercial reasons, E.ON Kernkraft GmbH <strong>and</strong> HEW AG decide to<br />

decommission <strong>and</strong> dismantle <strong>Stade</strong>, starting in <strong>the</strong> fall <strong>of</strong> 2003<br />

July 2001 Application for permit for decommissioning <strong>and</strong> <strong>dismantlement</strong> (Phase I)<br />

Fall 2001 Cumulative volume <strong>of</strong> electric energy generated since commissioning<br />

totals 140,744 million kilowatt-hours<br />

November 14, 2003 Reactor shutdown<br />

2004 to 2008 Fur<strong>the</strong>r applications for <strong>dismantlement</strong> permits (Phases II to IV)<br />

End <strong>of</strong> 2014 <strong>Stade</strong> site released from Germany’s statutory <strong>nuclear</strong> facility<br />

monitoring regime<br />

By end <strong>of</strong> 2015 Conventional demolition <strong>of</strong> remaining building structures<br />

3


<strong>Decommissioning</strong> in <strong>the</strong> broader sense<br />

<strong>Decommissioning</strong> in <strong>the</strong><br />

narrow sense<br />

_ permanent shutdown<br />

<strong>of</strong> reactor<br />

_ permanent shutdown<br />

<strong>of</strong> remaining plant<br />

What does “decommissioning <strong>and</strong><br />

<strong>dismantlement</strong>” actually mean?<br />

Dismantlement<br />

_ disassembly, decontamination,<br />

<strong>and</strong> removal<br />

from site <strong>of</strong> remaining<br />

plant <strong>and</strong> materials<br />

<strong>Decommissioning</strong> a <strong>nuclear</strong> <strong>power</strong> station means<br />

shutting it down permanently.<br />

Once it has been shut down, it is “dismantled,”<br />

meaning it is gradually broken down into its constituent<br />

parts. These parts <strong>the</strong>n undergo different<br />

types <strong>of</strong> treatment, depending on <strong>the</strong> level <strong>of</strong><br />

contamination, after which <strong>the</strong>y are packaged <strong>and</strong><br />

removed from <strong>the</strong> site. Following <strong>dismantlement</strong>,<br />

<strong>the</strong> site is completely cleared <strong>and</strong> made available<br />

for unrestricted use.<br />

The term “decommissioning” is <strong>of</strong>ten used more<br />

loosely to describe everything that happens after<br />

<strong>the</strong> plant is permanently taken <strong>of</strong>fline, including<br />

<strong>the</strong> shut-down <strong>and</strong> <strong>dismantlement</strong> processes.


Why is <strong>the</strong> <strong>Stade</strong> plant being decommissioned?<br />

There are actually no technical reasons for decommissioning <strong>the</strong> <strong>Stade</strong> station at present.<br />

The decision to decommission <strong>the</strong> facility was made exclusively on commercial grounds.<br />

In July 2001, E.ON Kernkraft lodged an application for a permit for <strong>the</strong> initial <strong>dismantlement</strong><br />

phase, residual plant operations, <strong>and</strong> <strong>the</strong> construction <strong>of</strong> a temporary storage facility for <strong>the</strong><br />

radioactive waste from <strong>the</strong> <strong>dismantlement</strong> <strong>of</strong> <strong>the</strong> station’s <strong>nuclear</strong> plant <strong>and</strong> equipment.<br />

Possible reasons for decommission <strong>nuclear</strong> <strong>power</strong> stations<br />

political<br />

_ <strong>nuclear</strong> exit strategy<br />

agreement between <strong>the</strong><br />

German State <strong>and</strong> <strong>the</strong><br />

country’s energy industry<br />

legal<br />

_ Germany’s Atomic<br />

Energy Act (AtG)<br />

_ Germany’s Radiation<br />

Protection Regulations<br />

(StSV)<br />

technical<br />

Commercial factors<br />

_ service life <strong>of</strong> key<br />

components<br />

As a result <strong>of</strong> electricity market liberalization,<br />

Germany’s energy utilities are in <strong>the</strong> process <strong>of</strong><br />

downsizing both <strong>the</strong>ir conventional <strong>and</strong> <strong>nuclear</strong><br />

generation fleets in order to eliminate costly<br />

excess generation capacity.<br />

The <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station is no longer<br />

economic. With a net installed capacity <strong>of</strong> 630 MW,<br />

<strong>the</strong> facility delivers only about half <strong>the</strong> electric output<br />

<strong>of</strong> most o<strong>the</strong>r German <strong>nuclear</strong> <strong>power</strong> stations,<br />

but is equally if not more expensive to operate.<br />

Ano<strong>the</strong>r key factor in <strong>the</strong> decision to decommission<br />

<strong>the</strong> station is <strong>the</strong> levy on water supplies<br />

imposed by <strong>the</strong> government <strong>of</strong> Lower Saxony, <strong>the</strong><br />

German state in which <strong>Stade</strong> is located. The introduction<br />

<strong>of</strong> this levy on water taken from <strong>the</strong> Elbe<br />

River for plant cooling purposes resulted in some<br />

8 million in additional costs for <strong>the</strong> <strong>Stade</strong> facility<br />

per year.<br />

In any event, <strong>the</strong> <strong>Stade</strong> facility would have<br />

exhausted its residual generation quota – set<br />

under Germany’s <strong>nuclear</strong> exit strategy – some time<br />

in 2004. Thus, E.ON Kernkraft’s decision to decommission<br />

<strong>the</strong> plant in 2003 cut short its service life by<br />

only about one year.<br />

commercial<br />

_ excess generation<br />

capacity<br />

_ liberalized energy market<br />

_ government levies on<br />

supplies <strong>of</strong> cooling water<br />

5


What experience do we have when it comes to<br />

decommissioning <strong>nuclear</strong> <strong>power</strong> stations?<br />

Germany’s original decision to use <strong>nuclear</strong> energy<br />

for commercial electric generation came only after<br />

considerable research on radioactive materials <strong>and</strong><br />

testing <strong>of</strong> various types <strong>of</strong> <strong>nuclear</strong> reactor. Dealing<br />

with radioactive buildings, machines, installations,<br />

<strong>and</strong> assemblies is <strong>the</strong>refore nothing new for<br />

Germany’s <strong>nuclear</strong> energy industry.<br />

Several <strong>nuclear</strong> <strong>power</strong> station decommissioning<br />

projects have already been authorized <strong>and</strong> completed<br />

in Germany, allowing <strong>the</strong> relevant energy companies<br />

to trial a wide range <strong>of</strong> methods <strong>and</strong> processes.<br />

The local industry also benefits from <strong>the</strong> decommissioning<br />

expertise ga<strong>the</strong>red by o<strong>the</strong>r countries.


Dismantlement methods<br />

Germany’s <strong>nuclear</strong> <strong>power</strong> station operators carried<br />

out a number <strong>of</strong> conceptual studies on decommissioning<br />

<strong>nuclear</strong> <strong>power</strong> stations as early as <strong>the</strong> mid-<br />

1970’s. These studies developed <strong>and</strong> compared two<br />

decommissioning methods: <strong>dismantlement</strong> after a<br />

period <strong>of</strong> safe enclosure (SAFESTOR) <strong>and</strong> immediate<br />

<strong>dismantlement</strong> (DECON).<br />

The first <strong>of</strong> <strong>the</strong>se two methods involves dismantling<br />

<strong>the</strong> facility after several decades <strong>of</strong> safe enclosure.<br />

The enclosure period allows <strong>the</strong> radioactivity<br />

to decay, so that dismantling can take place under<br />

lower levels <strong>of</strong> radioactive exposure.<br />

As <strong>the</strong> term suggests, immediate <strong>dismantlement</strong><br />

involves dismantling <strong>the</strong> plant as soon as it is taken<br />

out <strong>of</strong> service. The advantage <strong>of</strong> this method is that<br />

<strong>the</strong> plant’s existing technical systems can be used for<br />

pre-<strong>dismantlement</strong> work such as decontamination.<br />

Hybrid <strong>dismantlement</strong> methods can also be used –<br />

such as enclosing only certain parts <strong>of</strong> <strong>the</strong> plant,<br />

while dismantling <strong>the</strong> rest immediately.<br />

<strong>Decommissioning</strong> <strong>nuclear</strong> <strong>power</strong> stations<br />

Implementation <strong>of</strong> safe<br />

enclosure measures<br />

Safe enclosure period<br />

(about 30 years)<br />

Dismantlement<br />

On-load operation<br />

Transition phase<br />

Immediate <strong>dismantlement</strong><br />

7


8<br />

Expertise that’s based on experience<br />

Germany’s <strong>nuclear</strong> energy industry has already permanently decommissioned<br />

several <strong>nuclear</strong> <strong>power</strong> stations, including two where <strong>the</strong> sites have already been<br />

returned to ‘green fields’. The map on <strong>the</strong> page opposite provides an overview<br />

<strong>of</strong> Germany’s <strong>nuclear</strong> station decommissioning <strong>and</strong> <strong>dismantlement</strong> projects.<br />

Facilities that have been fully dismantled are marked in blue.<br />

Dismantling in progress<br />

at <strong>the</strong> Würgassen plant<br />

The Würgassen <strong>dismantlement</strong> project again highlights<br />

<strong>the</strong> fact that <strong>the</strong> immediate <strong>dismantlement</strong><br />

method does not pose any great challenges.<br />

This tried <strong>and</strong> proven process was selected for <strong>the</strong><br />

<strong>Stade</strong> facility because it retains jobs <strong>and</strong> <strong>the</strong>refore<br />

also plant-specific expertise which helps to expedite<br />

<strong>the</strong> <strong>dismantlement</strong> process.<br />

One key difference between <strong>the</strong> Würgassen<br />

<strong>and</strong> <strong>Stade</strong> facilities is that <strong>the</strong> former uses a boiling<br />

water reactor (BWR), whereas <strong>the</strong> latter uses a pressurized<br />

water reactor (PWR). The implications <strong>of</strong> this<br />

in terms <strong>of</strong> <strong>the</strong> <strong>dismantlement</strong> process are explained<br />

on <strong>the</strong> following pages.


Decommissioned <strong>and</strong> dismantled <strong>nuclear</strong> <strong>power</strong> stations in Germany<br />

THTR-300 Hamm-Uentrop<br />

(thorium high<br />

temperature reactor)<br />

Mülheim-Kärlich Nuclear Power Station<br />

(PWR)<br />

Lingen Nuclear Power Station<br />

(BWR)<br />

AVR-Versuchskraftwerk Jülich facility<br />

(experimental high temperature reactor)<br />

Karlsruhe MZFR Multipurpose<br />

Research Reactor<br />

(PWR)<br />

fully dismantled facility<br />

decommissioned facility<br />

<strong>Stade</strong> Nuclear Power Station<br />

(PWR)<br />

Würgassen Nuclear Power Station<br />

(BWR) – owned by E.ON Kernkraft<br />

Kahl Nuclear Power Station<br />

(BWR)<br />

Großwelzheim facility<br />

(superheated steam reactor)<br />

Compact Sodium-Cooled<br />

Nuclear Reactor I/II (KNK), Karlsruhe<br />

Grundremmingen A<br />

Nuclear Power Station<br />

(BWR)<br />

Greifswald Nuclear Power Station<br />

(PWR)<br />

Rheinsberg Nuclear Power Station<br />

(PWR)<br />

Niederaichbach Nuclear Power Station<br />

(heavy water reactor/HWR)<br />

9


10<br />

Reactor types<br />

In PWR <strong>nuclear</strong> <strong>power</strong> stations, <strong>the</strong> reactor heats<br />

water in a fully self-contained circuit known as<br />

<strong>the</strong> primary cooling loop. A heat exchanger transfers<br />

<strong>the</strong> heat energy in <strong>the</strong> primary cooling loop<br />

to a secondary cooling loop, causing <strong>the</strong> water in<br />

<strong>the</strong> secondary loop to evaporate. The steam thus<br />

generated is <strong>the</strong>n ducted to <strong>the</strong> turbines. In this<br />

way, <strong>the</strong> turbines are kept separate from <strong>the</strong> primary<br />

loop, which makes <strong>the</strong>m significantly easier<br />

<strong>and</strong> safer to h<strong>and</strong>le.<br />

In fact, <strong>the</strong> structural design <strong>of</strong> <strong>the</strong> entire<br />

facility was based on <strong>the</strong> principle <strong>of</strong> isolating all<br />

sections which could potentially get exposed to<br />

radioactivity. Only <strong>the</strong> reactor building <strong>and</strong> <strong>the</strong><br />

reactor auxiliary building are located in what is<br />

known as <strong>the</strong> radiation control area; <strong>the</strong> turbine<br />

room, comprising <strong>the</strong> turbines <strong>and</strong> <strong>the</strong> generator,<br />

are located outside <strong>of</strong> this area.<br />

Radiation control areas<br />

PWR plant<br />

BWR plant<br />

Radiation control area<br />

The diagram below fur<strong>the</strong>r illustrates <strong>the</strong> key<br />

differ-ences between pressurized water reactors<br />

(such as <strong>Stade</strong>) <strong>and</strong> boiling water reactors (such<br />

as Würgassen). In BWR plants, <strong>the</strong> radiation control<br />

area encompasses <strong>the</strong> entire block, including <strong>the</strong><br />

turbine room. In PWR plants like <strong>Stade</strong>, on <strong>the</strong> o<strong>the</strong>r<br />

h<strong>and</strong>, <strong>the</strong> reactor building is clearly separated from<br />

<strong>the</strong> turbine room.<br />

1<br />

1 2<br />

2<br />

1 Turbine room<br />

2 Reactor building


The <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station:<br />

special features<br />

<strong>Stade</strong> was Germany’s very first purely commercial<br />

<strong>nuclear</strong> <strong>power</strong> station to use PWR technology. Its installed<br />

capacity is now about half that <strong>of</strong> its more<br />

modern counterparts. However, when it was commissioned<br />

it ranked as Germany’s highest-output PWR<br />

<strong>nuclear</strong> <strong>power</strong> station.<br />

In 1984, <strong>Stade</strong> also became Germany’s first <strong>nuclear</strong><br />

<strong>power</strong> station to cogenerate process heat. The heat,<br />

which is supplied to a neighboring salt works, is generated<br />

via a tertiary cooling loop. Extracting useable<br />

steam in this manner raises <strong>the</strong> overall efficiency<br />

<strong>of</strong> <strong>the</strong> plant.<br />

Pressurized water reactor<br />

1<br />

2<br />

3<br />

1 Reactor pressure vessel<br />

2 Primary coolant pump<br />

3 Steam generator<br />

4 Water separator <strong>and</strong><br />

reheater<br />

1<br />

3<br />

10<br />

4<br />

11<br />

9<br />

10<br />

4<br />

9<br />

5 Turbines<br />

6 Generator<br />

7 Transformer<br />

8 Condenser<br />

9 Heat exchanger<br />

5<br />

8<br />

13<br />

12<br />

10 Feedheater<br />

11 Feedwater pump<br />

12 Cooling-water pump<br />

13 Cooling-water filter<br />

14 Cooling pond<br />

6<br />

7<br />

14<br />

11


What, exactly, does <strong>the</strong> dismantling process involve?<br />

Dismantling a large-scale <strong>nuclear</strong> facility involves<br />

<strong>the</strong> step-by-step removal <strong>of</strong> all plant components <strong>and</strong><br />

thus requires <strong>the</strong> same level <strong>of</strong> precision planning as<br />

building one. The dismantling process also clearly<br />

distinguishes between <strong>nuclear</strong> <strong>and</strong> non-<strong>nuclear</strong> plant<br />

components.


Most plant components <strong>and</strong> systems that are<br />

not exposed to <strong>nuclear</strong> radiation can be dismantled<br />

<strong>and</strong> removed immediately after plant shutdown –<br />

provided <strong>the</strong>y are not required for <strong>the</strong> rest <strong>of</strong> <strong>the</strong><br />

dismantling process.<br />

From full-load operation to<br />

decommissioning: <strong>the</strong> transition phase<br />

The changeover from normal, full-load operation<br />

to <strong>the</strong> <strong>dismantlement</strong> phase requires a number <strong>of</strong><br />

important changes to <strong>the</strong> plant’s operating processes.<br />

To ensure this happens efficiently <strong>and</strong> safely,<br />

<strong>the</strong> <strong>dismantlement</strong> plan allows for a so-called transition<br />

phase <strong>of</strong> about one <strong>and</strong> a half years. During this<br />

period, preparations are made for <strong>the</strong> disassembly<br />

<strong>and</strong> removal <strong>of</strong> plant components <strong>and</strong> systems,<br />

covering <strong>the</strong> following areas in particular:<br />

_ <strong>the</strong> removal <strong>of</strong> spent fuel rods from <strong>the</strong> site<br />

_ system decontamination measures<br />

_ <strong>the</strong> isolation <strong>and</strong> shut-down <strong>of</strong> systems that<br />

are no longer required.<br />

Dismantlement <strong>of</strong> <strong>the</strong> <strong>power</strong> station’s <strong>nuclear</strong> plant<br />

components starts once <strong>the</strong> transition phase has<br />

been completed <strong>and</strong> <strong>the</strong> permit for decommissioning<br />

has been granted. At <strong>Stade</strong>, <strong>the</strong> <strong>dismantlement</strong><br />

process has been divided into four phases. Each <strong>of</strong><br />

<strong>the</strong>se phases is subject to <strong>the</strong> government regulations<br />

applicable at <strong>the</strong> time <strong>and</strong> <strong>the</strong> associated<br />

approval procedures.<br />

13


14<br />

Dismantlement Phase I<br />

1<br />

2<br />

1 Materials air lock <strong>and</strong> air recirculation unit<br />

2 Flood tanks<br />

During <strong>the</strong> first <strong>dismantlement</strong> phase <strong>the</strong> necessary<br />

logistics systems are established within <strong>the</strong> radiation<br />

control area <strong>and</strong> as many non-required <strong>nuclear</strong><br />

systems as possible are removed to create more<br />

space for subsequent dismantling work. The <strong>dismantlement</strong><br />

<strong>of</strong> <strong>the</strong> larger plant components is also<br />

planned at this time.<br />

The diagram above shows some <strong>of</strong> <strong>the</strong> systems<br />

that are dismantled <strong>and</strong> removed during<br />

Dismantlement Phase I:<br />

3<br />

1<br />

4<br />

3 Control rod assembly<br />

4 Pressurized water tanks<br />

_ The flood tanks that feed <strong>the</strong> primary loop<br />

during start-up <strong>and</strong> shut-down.<br />

Dismantling <strong>the</strong>se helps to create extra space<br />

for <strong>the</strong> treatment <strong>and</strong> interim storage <strong>of</strong> waste<br />

materials from <strong>the</strong> <strong>dismantlement</strong> process.<br />

_ The control rod assembly.<br />

The individual components making up this<br />

assembly are also small <strong>and</strong> <strong>the</strong>ir <strong>dismantlement</strong>,<br />

which frees up space in <strong>the</strong> reactor chamber,<br />

is uncomplicated.<br />

_ The pressurized emergency cooling tanks <strong>and</strong><br />

o<strong>the</strong>r <strong>nuclear</strong>-contaminated systems that are no<br />

longer required for <strong>the</strong> subsequent <strong>dismantlement</strong><br />

work.<br />

However, some non-<strong>nuclear</strong> plant components<br />

such as <strong>the</strong> live-steam <strong>and</strong> feedwater systems,<br />

<strong>the</strong> emergency diesel generator set, <strong>and</strong> turbine<br />

<strong>and</strong> generator components are also disassembled<br />

<strong>and</strong> removed during this period.


Dismantlement Phase II<br />

1 Steam generator<br />

2Primary coolant pipe system, including pumps<br />

2<br />

The second <strong>dismantlement</strong> phase focuses on <strong>the</strong><br />

larger <strong>nuclear</strong> plant components <strong>and</strong> involves<br />

preparatory work followed by actual <strong>dismantlement</strong><br />

<strong>and</strong> removal.<br />

The components concerned include <strong>the</strong> primary<br />

coolant pipe system, including:<br />

_ <strong>the</strong> pumps,<br />

_ <strong>the</strong> steam generator.<br />

1<br />

The components shown in <strong>the</strong> diagram are examples<br />

only; o<strong>the</strong>r contaminated components not shown in<br />

<strong>the</strong> diagram are also removed during this phase.<br />

15


16<br />

Dismantlement Phase III<br />

1 Concrete slab<br />

2 Fuel racks<br />

2<br />

1<br />

3<br />

4<br />

3Reactor pressure vessel<br />

4 Concrete shielding<br />

The third <strong>dismantlement</strong> phase involves dismantling<br />

<strong>and</strong> removing <strong>the</strong> most contaminated <strong>nuclear</strong> plant<br />

components. Neutrons escaping from <strong>the</strong> reactor have<br />

made <strong>the</strong>se components radioactive; <strong>the</strong>y can not be<br />

decontaminated. As highlighted in <strong>the</strong> diagram above,<br />

<strong>the</strong>se components include:<br />

_ <strong>the</strong> reactor pressure vessel,<br />

_ <strong>the</strong> concrete shielding that encloses <strong>the</strong> reactor<br />

pressure vessel (known as <strong>the</strong> biological shield),<br />

_ <strong>the</strong> overhead concrete slab that shields <strong>the</strong> reactor<br />

room,<br />

_ <strong>the</strong> fuel racks in <strong>the</strong> former fuel storage tank,<br />

<strong>and</strong> various fixed <strong>and</strong> moveable pressure vessel<br />

components.


Dismantlement Phase IV<br />

1 Polar crane<br />

2 Fuel transfer platform<br />

2<br />

1<br />

3Ventilation plant<br />

4Water purification plant<br />

In <strong>the</strong> final <strong>nuclear</strong> <strong>dismantlement</strong> phase, all <strong>the</strong><br />

systems remaining in <strong>the</strong> radiation control area are<br />

gradually dismantled <strong>and</strong> removed. The last systems<br />

to be removed are <strong>the</strong> water purification <strong>and</strong> ventilation<br />

plants.<br />

The remaining building structures in <strong>the</strong> control<br />

area are <strong>the</strong>n cleaned <strong>and</strong> decontaminated so that<br />

<strong>the</strong>y meet statutory requirements for safety clearance.<br />

The radiation control area is thus gradually<br />

scaled down <strong>and</strong> eliminated.<br />

3<br />

4<br />

17


18<br />

Elbe River<br />

The final stage involves all such site clearing <strong>and</strong> decontamination<br />

work as is necessary to ensure <strong>the</strong> site meets statutory radiation safety<br />

clearance requirements. Once this has been achieved, <strong>the</strong> site is released<br />

from Germany’s statutory <strong>nuclear</strong> facility control <strong>and</strong> permit regime.<br />

Conventional dismantling<br />

Planned control area elimination process<br />

Step 1<br />

Containment<br />

Step 2<br />

Reactor building<br />

Step 3<br />

Auxiliary services building<br />

Step 4<br />

Entrance to radiation control area,<br />

stack<br />

The final step in dismantling <strong>the</strong> <strong>Stade</strong> plant<br />

involves <strong>the</strong> demolition <strong>and</strong> removal <strong>of</strong> <strong>the</strong> remaining<br />

buildings <strong>and</strong> structures from <strong>the</strong> site. Conventional<br />

demolition methods can be used during this<br />

phase because <strong>the</strong> site is no longer subject to statutory<br />

<strong>nuclear</strong> facility control <strong>and</strong> permit requirements.<br />

The scrap concrete <strong>and</strong> steel generated by <strong>the</strong><br />

demolition process is recycled wherever possible.<br />

The decommissioning <strong>and</strong> dismantling project is<br />

<strong>of</strong>ficially at an end once <strong>the</strong> site has been restored<br />

to green fields.


Timeframe<br />

When <strong>the</strong> <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station was shut<br />

down on November 14, 2003, preparations for <strong>the</strong><br />

plant’s subsequent <strong>dismantlement</strong> were already<br />

well underway.<br />

The current transition phase, which began after<br />

shutdown, involves <strong>the</strong> removal <strong>of</strong> <strong>the</strong> remaining fuel<br />

rods. Once this is done, deconstruction can begin in<br />

accordance with <strong>the</strong> statutory regulations governing<br />

<strong>the</strong> initial <strong>dismantlement</strong> phase. We estimate this<br />

will happen midway through 2005.<br />

The dismantling <strong>of</strong> <strong>the</strong> plant <strong>and</strong> installations<br />

in <strong>the</strong> radiation control area will take place in four<br />

phases, as described earlier. This process is expected<br />

to take almost ten years <strong>and</strong> will <strong>the</strong>refore probably<br />

not be completed until <strong>the</strong> end <strong>of</strong> 2014. The only<br />

task remaining once <strong>the</strong> site has been released<br />

from Germany’s statutory <strong>nuclear</strong> facility control<br />

<strong>and</strong> permit regime is to demolish <strong>the</strong> buildings <strong>and</strong><br />

structures. This is scheduled to take place in 2015.<br />

The phases described above are independent <strong>of</strong><br />

each o<strong>the</strong>r <strong>and</strong> can <strong>the</strong>refore overlap. The permit<br />

application for Phase I was lodged in July 2001.<br />

Permit applications will be lodged in good time for<br />

<strong>the</strong> scheduled start <strong>of</strong> each <strong>of</strong> <strong>the</strong> remaining phases.<br />

<strong>Decommissioning</strong> timetable<br />

2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016<br />

On-load operation<br />

Transition<br />

phase<br />

Construction<br />

Residual operation (immediate <strong>dismantlement</strong>)<br />

Dismantlement <strong>of</strong> non-<strong>nuclear</strong> components<br />

Dismantlement <strong>of</strong> <strong>nuclear</strong> components<br />

Phase I<br />

Operation<br />

Phase II<br />

Phase III<br />

Storage facility for radioactive waste<br />

Phase IV<br />

Building<br />

demolition<br />

19


What does decommissioning mean for <strong>Stade</strong>’s employees?


Different workforce structures required<br />

Compared to daily production operations, plant<br />

decommissioning involves fundamentally different<br />

work processes. This has important implications for<br />

<strong>the</strong> plant’s organizational structures as well as <strong>the</strong><br />

makeup <strong>and</strong> size <strong>of</strong> its workforce.<br />

The primary focus during <strong>the</strong> <strong>Stade</strong> facility’s<br />

service life was on ensuring safe, reliable plant operation.<br />

Now that <strong>the</strong> facility is being decommissioned,<br />

its safety systems <strong>and</strong> installations will gradually be<br />

taken out <strong>of</strong> service. Naturally, this will also impact<br />

<strong>the</strong> employees who are working in this area.<br />

However, decommissioning also brings with it new<br />

task areas <strong>and</strong> responsibilities. For example, it will<br />

create opportunities for employees who are skilled<br />

in <strong>the</strong> use <strong>of</strong> <strong>the</strong> dismantling equipment. We will<br />

also need additional radiation protection specialists.<br />

However, over <strong>the</strong> long term <strong>the</strong>re will be a net<br />

decline in employee numbers.<br />

Staffing cutbacks<br />

E.ON Kernkraft GmbH has a tw<strong>of</strong>old strategy for<br />

minimizing <strong>the</strong> impact <strong>of</strong> anticipated job losses.<br />

Our older employees, including those who reach<br />

<strong>the</strong> required age before <strong>the</strong> end <strong>of</strong> <strong>the</strong> dismantling<br />

project, have <strong>the</strong> opportunity to participate in a<br />

special early retirement program. Exempt from this<br />

are those older staff members who possess skills<br />

that are essential for <strong>the</strong> dismantling project.<br />

The second strategy relates to <strong>the</strong> redeployment<br />

<strong>of</strong> personnel to o<strong>the</strong>r E.ON Kernkraft locations. Those<br />

affected will need to relocate <strong>and</strong>, in all probability,<br />

retrain. This option will most likely be more attractive<br />

to <strong>the</strong> company’s younger employees.<br />

21


What happens to <strong>the</strong> dismantled parts <strong>and</strong> materials?<br />

Waste material<br />

from <strong>the</strong> radiation<br />

control area<br />

Various measurements, tests, <strong>and</strong> treatment processes<br />

Safety clearance<br />

as re-usable/recyclable<br />

waste or conventionalnon-recyclable<br />

waste<br />

Controlled re-use Radioactive waste<br />

By far most <strong>of</strong> <strong>the</strong> material resulting from <strong>the</strong><br />

<strong>dismantlement</strong> process is not radioactively contaminated<br />

<strong>and</strong> can <strong>the</strong>refore be treated like normal concrete<br />

<strong>and</strong> steel demolition waste. This includes <strong>the</strong><br />

material removed from <strong>the</strong> radioactive control area.<br />

However, because <strong>of</strong> <strong>the</strong> risk that material from <strong>the</strong><br />

control area may be contaminated, all components<br />

from this area need to undergo rigorous testing.<br />

Once testing is complete, <strong>the</strong> disposal technicians<br />

individually determine how each component is to<br />

be disposed <strong>of</strong>.<br />

Material that is nei<strong>the</strong>r contaminated nor radioactive<br />

may be suitable for immediate re-use or recycling<br />

in o<strong>the</strong>r areas. For example, <strong>the</strong> waste concrete<br />

from <strong>the</strong> building demolition process counts is st<strong>and</strong>ard<br />

building rubble <strong>and</strong> can be re-used in <strong>the</strong> construction<br />

industry. Most <strong>of</strong> <strong>the</strong> metal components are<br />

recyclable scrap metal. The diagram below shows <strong>the</strong><br />

main disposal methods for <strong>the</strong> waste material from<br />

<strong>the</strong> radiation control area.


Disposal methods<br />

There are a range <strong>of</strong> disposal methods for <strong>the</strong><br />

waste material from <strong>the</strong> radiation control area.<br />

These include:<br />

_ unrestricted safety clearance for re-use or<br />

recycling<br />

_ scrap metal: safety clearance for recycling subject<br />

to certain conditions<br />

_ safety clearance for disposal as conventional,<br />

non-recyclable waste (for l<strong>and</strong>fills)<br />

_ controlled re-use by <strong>the</strong> <strong>nuclear</strong> industry<br />

_ safe disposal as radioactive waste<br />

The materials are classified into <strong>the</strong> above clearance<br />

categories in accordance with <strong>the</strong> rules <strong>and</strong><br />

radiation exposure limit values laid down in<br />

Germany’s Radiation Protection Regulations (StSV).<br />

Each control area component is tested to determine<br />

its contamination or radioactivity status, classified,<br />

<strong>and</strong> assigned an appropriate disposal method.<br />

Each component is <strong>the</strong>n disassembled <strong>and</strong>/or broken<br />

down <strong>and</strong>, where applicable, decontaminated so that<br />

it meets <strong>the</strong> requirements <strong>of</strong> <strong>the</strong> selected disposal<br />

method.<br />

Dismantling work in progress at<br />

<strong>the</strong> Würgassen NPP<br />

23


24<br />

Plant <strong>dismantlement</strong>:<br />

waste material categories<br />

Based on its experience <strong>of</strong> past decommissioning<br />

projects <strong>and</strong> its intimate knowledge <strong>of</strong> <strong>the</strong> <strong>Stade</strong><br />

facility, E.ON Kernkraft GmbH is able to estimate<br />

with considerable accuracy <strong>the</strong> volume <strong>and</strong> percentages<br />

<strong>of</strong> materials that will be allocated to each<br />

clearance category, as shown in <strong>the</strong> chart below.<br />

Materials categories: percentages <strong>and</strong> volumes<br />

Area<br />

in Mg (megagrams)<br />

Clearance<br />

(restricted <strong>and</strong><br />

unrestricted)<br />

272,100 Mg<br />

Non-<strong>nuclear</strong><br />

area<br />

127,540 Mg<br />

Nuclear<br />

area<br />

Controlled<br />

re-use<br />

Detailed view:<br />

Nuclear area<br />

Radioactive<br />

waste<br />

97,2 % Safety<br />

clearance<br />

0,4 % Controlled<br />

re-use<br />

2,4 % Radioactive<br />

waste<br />

Nuclear area 124,005 (97.2 %) 545 (0.4 %) 2,990 (2.4 %) 127,540 (100 %)<br />

Non-<strong>nuclear</strong> area 272,100 - - 272,100<br />

Total 396,105 545 2,990 399,640<br />

Total


Mechanical breakdown <strong>of</strong> materials<br />

During <strong>the</strong> <strong>dismantlement</strong> process large plant<br />

components need to be cut up into smaller sections.<br />

Conventional tools such as large blade saws, hydraulic<br />

shears, cutting torches, <strong>and</strong> metal shredders are<br />

used for this purpose. Slow-running machinery is<br />

employed wherever possible to prevent <strong>the</strong> creation<br />

<strong>of</strong> aerosols.<br />

The tools <strong>and</strong> equipment are set up in <strong>the</strong><br />

necessary configuration in <strong>the</strong> areas designated for<br />

dismantling/cutting, decontamination, <strong>and</strong> waste<br />

treatment. Minimizing <strong>the</strong> decommissioning personnel’s<br />

exposure to radiation is <strong>the</strong> paramount criterion<br />

for selecting which tools <strong>and</strong> methods to use.<br />

The work processes are also designed to prevent<br />

<strong>the</strong> buildup <strong>of</strong> dust <strong>and</strong> grime. Certain processes are<br />

even performed in sealed areas with <strong>the</strong>ir own, separate<br />

air h<strong>and</strong>ling systems or in containers. In <strong>the</strong>se<br />

areas, <strong>the</strong> air is extracted <strong>and</strong> filtered, <strong>the</strong>reby preventing<br />

<strong>the</strong> spread <strong>of</strong> radioactivity within <strong>the</strong> plant<br />

<strong>and</strong> protecting <strong>the</strong> environment from radioactive<br />

emissions.<br />

Wherever possible, <strong>the</strong> plant components are<br />

broken down into pieces small enough to fit into<br />

special containers, which are <strong>the</strong>n transported to<br />

fur<strong>the</strong>r treatment stations. After disassembly <strong>and</strong><br />

cutting, each item is thoroughly cleaned. Extremely<br />

sensitive measuring instruments are <strong>the</strong>n used to<br />

determine each item’s level <strong>of</strong> radioactivity or surface<br />

contamination. Depending on <strong>the</strong> outcome <strong>of</strong> <strong>the</strong>se<br />

measurements, each item is ei<strong>the</strong>r submitted for<br />

final clearance testing or is first decontaminated<br />

<strong>and</strong> <strong>the</strong>n submitted for final clearance testing.<br />

Decontamination<br />

In most cases, radioactivity is confined to mere<br />

surface contamination. When <strong>the</strong> <strong>Stade</strong> plant was<br />

built, many <strong>of</strong> <strong>the</strong> components used were coated<br />

with a special sealant designed to facilitate decontamination.<br />

These types <strong>of</strong> components can in most<br />

cases be completely decontaminated by thorough<br />

washing or abrasion. Where contamination has penetrated<br />

deep into <strong>the</strong> material via cracks <strong>and</strong> pores it<br />

is removed by mechanical or chemical means.<br />

The following decontamination methods are used:<br />

_ steel grit blasting,<br />

_ water blasting, <strong>and</strong><br />

_ chemical flushing.<br />

Dry steel grit blasting is a highly effective decontamination<br />

method for disassembled <strong>and</strong> cut-up components<br />

with readily accessible surfaces. It involves<br />

grinding <strong>the</strong> surface <strong>of</strong>f <strong>the</strong> components by bombarding<br />

<strong>the</strong>m with a jet <strong>of</strong> pin-head-sized steel<br />

grains traveling at nearly <strong>the</strong> speed <strong>of</strong> sound.<br />

Chemical flushing, on <strong>the</strong> o<strong>the</strong>r h<strong>and</strong>, is used for<br />

decontaminating whole systems <strong>and</strong> assemblies prior<br />

to disassembly. The final decontamination step is a<br />

simple matter <strong>of</strong> isolating <strong>the</strong> contaminated particles<br />

from <strong>the</strong> steel grit or chemical solution.<br />

Decontamination keeps <strong>the</strong> volume <strong>of</strong> secondary<br />

radioactive waste to an absolute minimum <strong>and</strong> significantly<br />

reduces <strong>the</strong> amount <strong>of</strong> radiation to which<br />

<strong>the</strong> plant’s personnel are exposed during subsequent<br />

dismantling work. The decontamination methods<br />

used are specially tailored to <strong>the</strong> method <strong>of</strong> disposal.<br />

25


26<br />

Safety clearance<br />

The material from <strong>the</strong> <strong>dismantlement</strong> process must<br />

meet extremely stringent st<strong>and</strong>ards to qualify for<br />

unrestricted clearance for conventional recycling or<br />

re-use. This involves subjecting it to a series <strong>of</strong> tests:<br />

Following preliminary testing for <strong>the</strong> presence <strong>of</strong><br />

radioactivity, disassembly <strong>and</strong> dismembering, <strong>and</strong><br />

decontamination, <strong>the</strong> material is subjected to socalled<br />

orientation testing. This entails direct measurements<br />

<strong>of</strong> surface contamination, <strong>the</strong> primary aim <strong>of</strong><br />

which is to determine <strong>the</strong> distribution <strong>of</strong> radioactivity<br />

across <strong>the</strong> surfaces.<br />

Final clearance testing is designed to determine<br />

whe<strong>the</strong>r <strong>the</strong> material meets statutory requirements<br />

for clearance. It involves a range <strong>of</strong> different measurement<br />

<strong>and</strong> testing methods, which are also subject<br />

to differing requirements in terms <strong>of</strong> radioactivity<br />

distribution <strong>and</strong> are thus closely associated with<br />

orientation testing.<br />

Under certain conditions <strong>the</strong> <strong>power</strong> plant operator<br />

will also conduct so-called control measurements.<br />

These involve both direct measurements <strong>and</strong> <strong>the</strong><br />

taking <strong>of</strong> samples for laboratory analysis.<br />

Once all <strong>the</strong> tests <strong>and</strong> measurements have been<br />

performed, <strong>the</strong> complete set <strong>of</strong> clearance documents<br />

is submitted to <strong>the</strong> competent statutory atomic energy<br />

regulatory body. The material can only be removed<br />

from <strong>the</strong> plant site after this body has given its<br />

approval <strong>and</strong> <strong>the</strong> plant’s designated radiation protection<br />

<strong>of</strong>ficer has issued final safety clearance.<br />

The clearance process<br />

Disassembly, dismembering<br />

Decontamination<br />

Preliminary/<br />

orientation testing<br />

Final clearance testing<br />

Control testing<br />

Final clearance


Radioactive waste<br />

E.ON Kernkraft plans to construct a storage facility<br />

for radioactive waste during <strong>the</strong> post-shutdown transitional<br />

phase. The facility will be located adjacent to<br />

<strong>the</strong> <strong>Stade</strong> site <strong>and</strong> will be used exclusively to house<br />

radioactive waste from <strong>the</strong> operation <strong>and</strong> <strong>dismantlement</strong><br />

<strong>of</strong> <strong>the</strong> <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station. Only low<br />

<strong>and</strong> medium-level radioactive waste will be stored<br />

in <strong>the</strong> facility; <strong>the</strong> fuel elements will be transported<br />

<strong>of</strong>f-site prior to <strong>the</strong> start <strong>of</strong> dismantling work.<br />

The storage facility will have a service life <strong>of</strong><br />

40 years, <strong>and</strong> is intended for temporary storage until<br />

Germany’s federal government provides a final storage<br />

facility. However, <strong>the</strong> waste will be placed in <strong>the</strong><br />

temporary facility in a form suitable for final storage.<br />

11<br />

2<br />

4<br />

5<br />

Elbe River<br />

1<br />

10<br />

8<br />

9<br />

6<br />

3<br />

7<br />

1 Reactor building<br />

2 Reactor auxiliary building<br />

<strong>and</strong> annexes<br />

3 Aftercooling system building<br />

4 Switchgear building<br />

5 Turbine room<br />

6 Control building<br />

7 Office <strong>and</strong> employee services<br />

building<br />

8 Workshop <strong>and</strong> storage area<br />

9 Emergency diesel generating<br />

sets<br />

10 Transformers<br />

11 Planned temporary storage<br />

facility for radioactive waste<br />

27


What happens to <strong>the</strong> vacant site?


Green fields<br />

In Germany two <strong>nuclear</strong> <strong>power</strong> station sites have<br />

already been returned to ‘green fields.’ Broadly<br />

speaking, <strong>the</strong> l<strong>and</strong> on which <strong>the</strong> <strong>power</strong> plants were<br />

once located has been returned to nature: it has<br />

been replanted <strong>and</strong> is now lying fellow. The <strong>Stade</strong><br />

site will also be restored to green fields. At this<br />

stage it has not been decided if <strong>and</strong> to what extent<br />

<strong>the</strong> l<strong>and</strong> will be put to o<strong>the</strong>r industrial uses.<br />

29


What is <strong>the</strong> regulatory environment under which<br />

decommissioning is performed?<br />

Statues <strong>and</strong> regulations<br />

In Germany <strong>the</strong> construction, operation, <strong>and</strong> decommissioning<br />

<strong>of</strong> <strong>nuclear</strong> <strong>power</strong> stations is governed by<br />

<strong>the</strong> Atomic Energy Act (AtG). The decommissioning<br />

<strong>and</strong> <strong>dismantlement</strong> <strong>of</strong> <strong>nuclear</strong> facilities is also subject<br />

to numerous statutory <strong>and</strong> administrative regulations.<br />

The regulatory framework includes <strong>the</strong> Radiation<br />

Protection Regulations (StSV), <strong>the</strong> Recycling <strong>and</strong><br />

Waste Management Act (KrW-/AbfG ), <strong>the</strong> Hazardous<br />

Substances Regulations (GefSt<strong>of</strong>fV), <strong>and</strong> <strong>the</strong> Federal<br />

Pollution Control Act (BimSchG).


The permit process<br />

Permit application<br />

Permitting authority<br />

(highest competent<br />

authority at state level)<br />

Decision<br />

Clearance procedures<br />

Permanent <strong>nuclear</strong> <strong>power</strong> station decommissioning<br />

<strong>and</strong> safe enclosure require permits issued in accordance<br />

with <strong>the</strong> Atomic Energy Act (AtG) by <strong>the</strong> highest<br />

competent state-level authority. Accordingly,<br />

E.ON Kernkraft GmbH has applied to Germany’s<br />

Lower Saxony State Ministry for <strong>the</strong> Environment<br />

for a permit to decommission <strong>and</strong> dismantle <strong>the</strong><br />

<strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station.<br />

The diagram above shows <strong>the</strong> role <strong>of</strong> <strong>the</strong> various<br />

government bodies <strong>and</strong> institutions in <strong>the</strong> permit<br />

process.<br />

Additional reports<br />

Participating government agencies<br />

General public<br />

Expert report<br />

Federal Ministry for <strong>the</strong> Environment,<br />

Conservation <strong>and</strong> Reactor Safety (BMU)<br />

Participating federal<br />

agencies<br />

Environmental impact analysis<br />

An environmental impact analysis must be performed<br />

before <strong>the</strong> <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station decommissioning<br />

project can proceed. The analysis must cover<br />

all aspects <strong>of</strong> <strong>the</strong> project, including <strong>the</strong> proposed construction<br />

<strong>of</strong> a temporary storage facility for radioactive<br />

waste from <strong>the</strong> operation <strong>and</strong> <strong>dismantlement</strong> <strong>of</strong><br />

<strong>the</strong> plant. Its purpose is to ascertain <strong>and</strong> assess <strong>the</strong><br />

project’s environmental impacts. The environmental<br />

impact analysis is thus an integral part <strong>of</strong> <strong>the</strong> permit<br />

process.<br />

31<br />

Reactor Safety Commission<br />

Radiation Protection Commission


32<br />

The <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station in brief<br />

<strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station<br />

Technical data<br />

Reactor type BWR<br />

Net installed capacity 630 MW<br />

Start <strong>of</strong> commercial on-load operation May 19, 1972<br />

Nuclear plant<br />

Reactor pressure vessel<br />

Rated pressure (positive) 175 bar<br />

Internal diameter 4,080 mm<br />

Overall height 10,400 mm<br />

Cylinder section wall thickness plus plating 192 + 7 mm<br />

Total weight 270 t<br />

Reactor core<br />

Number <strong>of</strong> fuel elements 157<br />

Total uranium weight 56 t<br />

Number <strong>of</strong> control rods 49<br />

Steam generators<br />

Number 4<br />

Steam output per unit 898.1 t/h<br />

Output steam pressure 52 bar<br />

Output steam temperature 265 °C<br />

Reactor cooling system<br />

Number <strong>of</strong> coolant pumps 4<br />

Average coolant temperature 298 °C<br />

Containment<br />

Ball diameter 48 m<br />

Rated pressure (positive) 3.8 bar<br />

Wall thickness 25-35 mm<br />

Turbine room systems<br />

Turbines <strong>and</strong> condenser<br />

High-pressure turbine 1<br />

Low pressure turbine 2<br />

Speed 1,500 min –1<br />

Heat rise <strong>of</strong> cooling water in condenser 9 K<br />

Generator<br />

Output 780 MVA<br />

Transformer voltage 21 kV<br />

Power factor (cos phi) 0.85<br />

Unit transformers<br />

Number 2<br />

Output per unit 380 MVA<br />

Frequency 50 Hz<br />

Cogeneration system<br />

Tertiary loop steam volume 60 t/h, corresp. to 7.7 MW<br />

Steam pressure 10 bar<br />

Steam temperature 190°C<br />

Condensate pipeline 1.5 km to salt works<br />

Located on <strong>the</strong> banks <strong>of</strong> <strong>the</strong> Elbe River,<br />

<strong>the</strong> <strong>Stade</strong> <strong>nuclear</strong> <strong>power</strong> station was commissioned<br />

in 1972. It has been cogenerating<br />

process heat for a neighboring salt<br />

works since 1984.<br />

The <strong>Stade</strong> plant is two-thirds owned<br />

by E.ON Kernkraft GmbH. The remaining<br />

one-third stake is owned by Vattenfall<br />

Europe AG.


Publisher<br />

E.ON Kernkraft GmbH<br />

Corporate Communications<br />

Tresckowstraße 5<br />

30457 Hannover<br />

Germany<br />

Editor<br />

Kernkraftwerk <strong>Stade</strong><br />

Public Relations<br />

Photographs<br />

Peter Hamel<br />

Volkmar Gawehn, Isernhagen (page 2)<br />

Zefa, Hamburg (page 29)<br />

Archivberlin, Berlin (page 30)<br />

Translation<br />

Anglobe Business Services,<br />

Hamburg<br />

Design<br />

Maurer Werbeagentur,<br />

Hannover<br />

Printer<br />

Gesellschaft für Digital- und<br />

Printmedien mbH, Hannover<br />

Edition 6/2004<br />

All rights reserved. No part <strong>of</strong><br />

this document may be reproduced<br />

without <strong>the</strong> Editor’s permission.


E.ON Kernkraft GmbH PO Box 4849 30048 Hannover Germany<br />

Tresckowstraße 5 30457 Hannover Germany<br />

T +49 (0)5 11-4 39 03 F +49 (0)5 11-4 39 23 75<br />

www.eon-kernkraft.com www.eon.com<br />

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T +49 (0)41 41-77 23 91 F +49 (0)41 41-79 93 04<br />

E.ON Kernkraft GmbH Corporate Communications

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