CELEX: 51988PC0415
Language: en
Date: 1988-07-28
Title: Proposal for a COUNCIL DECISION adopting a research and technological development programme for the European Atomic Energy Community in the field of the decommissioning of nuclear installations (1989-1993) (presented by the Commission)

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 ---pagebreak--- COMMISSION OF THE EUROPEAN COMMUNITIES
                                                         COM ( 88 ) 415 final
                                                         Brussels , 28 July 1988
                                      Proposai for a
                                     COUNCIL DECISION
           adopting a research and technological development programme
                         for the European Atomic Energy Community
          in the field of the decommissioning of nuclear installations
                                           ( 1989-1993 )
                               ( presented by the Commission )
   Av -7' ^r-Tr .- 'no ‘,>^5
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 ---pagebreak---                                                           C &ti - Ÿ o
                                   CONTENTS                           Page
ABSTRACT .                                                               2
1 . INTRODUCTION .                                                       3
2 . UNDERLYING CONSIDERATIONS .                                          3
    2.1 . Objectives of Community R&D in the field of decommis­
          sioning .                                                      3
    2.2 . Advantages of action at Community level .                      4
    2.3 . Past Community activities and achievements .                   4
    2.4 . The need for a further programme .                             6
3 . SCOPE OF THE PROPOSED PROGRAMME .                                    6
    3.1 . Section A - Research and development projects .                6
    3.2 . Section B - Guiding principles .                               7
    3.3 . Section C - Testing of new techniques in practice .            7
4 . IMPLEMENTATION AND MANAGEMENT .                                      9
5 . BUDGET AND STAFF .                                                 10
                                   *        *
                                       *
Annex 1 - The 1984-88 programme on the decommissioning of
            nuclear installations .                                    11
Annex 2 - Description of the proposed research and development
            projects .                                                 17
Annex 3 - Possible pilot dismantling projects .                        22
Annex 4 - Opinion of the Management and Coordination Advisory
            Committee .                                                25
Annex 5 - Opinion of the Scientific and Technical Committee .          26
Annex 6 - Financial record sheets .                                    27
Annex 7 - Proposai for a Council Decision .                            30
                                     - 1 -
 ---pagebreak---                                    ABSTRACT
The present proposal concerns one of the specific programmes through which
the " framework programme for Community activities in the field of research
and technological development ( 1987 to 1991 )" is to he implemented .
The proposed programme is to succeed to :
   the 1979-83 programme of research on the decommissioning of nuclear
   power plants , and
   the 1984-88 programme of research on the decommissioning of nuclear
   installations .
The proposed programme is composed of three Sections with the same subjects
as the current ( 1984-88 ) programme , i.e. :
   Section A - Research and development projects
- Section B - Guiding principles
- Section C - Testing of new techniques in practice .
Section C has been strongly expanded in order to enable the Community to
participate more substantially in selected pilot dismantling projects
undertaken in various Member States .
The proposed programme would require a budget of 31.5 million ECU and a
staff of five . The programme would be implemented mainly through cost-sha¬
ring contracts with competent public organisations or private firms in the
Member States . Tn the carrying out of the programme , the Commission would
again have the assistance of the Management and coordination advisory
committee "Nuclear fission energy - Fuel cycle /processing and storage of
waste ".
                                        2
 ---pagebreak--- 1 . INTRODUCTION
Over the past ten years , since the Community initiated research activities
in the field of the decommissioning of nuclear installations , the situation
in this field has considerably evolved . On the one hand , the technological
basis of decommissioning has been strengthened . On the other hand , the
number of major nuclear installations finally shut down and its rate of
increase , both very small ten years ago , have become substantial .
This evolution had to be taken into account in the formulation of the
present proposal for a new five-year ( 1989-93 ) programme of research on the
decommissioning of nuclear installations . The proposed programme takes up
most of the subjects of the current programme , which terminates on 31 De¬
cember 1988 , but it places greater weight on testing of new decommissioning
techniques in practice .
This orientation is in agreement with the " framework programme for Commu¬
nity activities in the field of research and technological development
( 1987 to 1991 )" which lays down that "work on decommissioning operations
will involve demonstration of relevant technologies".
2 . UNDERLYING CONSIDERATIONS
2.1 . Objectives of Community R&D in the field of decommissioning
Certain parts of nuclear installations inevitably become radioactive during
operation by surface contamination and , in the case of reactors , by direct
activation . Therefore , adequate measures ensuring nuclear safety and
radiation protection must be maintained at the installations finally shut
down , until radioactivity has decayed or radioactive materials have been
removed from the site .
The main objective of the proposed programme of research is to reinforce
the scientific and technical basis necessary to strengthen the safety and
protection aspects of the decommissioning of nuclear installations . This
objective concerns also Member States which might decide to abandon the
production of nuclear energy .
Ten years ago , when the first research programme concerning decommissioning
was proposed , the number of nuclear power plants in the Community that had
been finally shut down was only five . In the meantime , this number has
reached 17 , and by the year 2000 it is expected to run up to about 50 .
Besides nuclear power plants , various other nuclear installations are to be
considered , e.g. nuclear fuel cycle facilities and research reactors .
As decommissioning is still at the outset of becoming a significant indus¬
trial activity , there exists an opportunity for shaping its various fea¬
tures .
                                    - 3 -
 ---pagebreak--- A fundamental feature of decommissioning Is the extent to which radioactive
plant components are stored In situ - in order to take advantage of radio¬
active decay - prior to dismantling and removal from the site . Tt is
generally considered that both immediate dismantling and in-situ storage
over severai decades may be appropriate options , depending on a number of
factors , including the type of plant and the planned use of the site .
However , the decisions of plant owners may be biassed in favour of strate ¬
gies rendering plant sites unavailable for other uses for a long time to
come , unless decommissioning techniques are developed to a high standard .
Besides , the programme will contribute to improve the data basis for
decommissioning cost estimates . Such estimates are needed by installation
owners to accumulate provisions for decommissioning in accordance with
national requirements . Owners of radiochemical installations , in particu ¬
lar , stated important uncertainties in decommissioning costs .
2.2 . Advantages of action at Community level
The intensive exchange of detailed technical information between people
working in the same area , which will again be organised within the frame ¬
work of the proposed programme ( as it has been in the preceding ones ), will
continue to fertilise the individual efforts and make it possible to
integrate research , thereby avoiding unnecessary duplication of work .
Moreover , the Community programme has the potential of catalysing a consen¬
sus on a Community policy in the field of decommissioning and of stimulat ¬
ing the setting up of a regulatory framework within which industrial
activities can develop . An example of an area where common standards are
particularly desirable and further efforts are required , is the release of
steel and other metals from redundant nuclear components , considering that
scrap metal is frequently crossing the borders between Member States .
Besides safety and protection aspects , industrial and economic impacts are
also to be considered , since decommissioning will become a significant new
branch of industrial activity (considering estimates of decommissioning
costs , e.g. for a large Light Water Reactor block , ranging between 150 and
200 million ECU ) . The co-operation at research level of industrial partici ¬
pants from different Member States may stimulate the coming into being of
an efficient decommissioning industry operating on a Community-wide market .
2.3 . Past Community activities and achievements
The principle of Community action concerning the decommissioning of nuclear
power plants was for the first time approved by the Council in 1977 , within
the framework of the action programme on the environment ( 1 ).
(T )  OJ N° C 139 , 13.6.1977 , p. 1 .
                                       - 4 -
 ---pagebreak--- In 1979 , the Council adopted a 1979-83 programme of research on the decom¬
missioning of nuclear power plants ( 1 ), involving a budget of A. 7 million
ECU . This programme was carried out under 31 research contracts , most of
them cost-sharing , and Its results were extensively published , in particu ¬
lar through :
-    A annual progress reports edited by the Commission ;
-    A3 final reports of individual contracts ;
-    a conference organised by the Commission upon completion of the program¬
     me ( 2 ).
In 198A , the Council adopted a 198A-88 programme of research on the decom¬
missioning of nuclear installations ( 3 ) ( including , e.g. , fuel cycle
facilities and research reactors , in addition to nuclear power plants ),
involving a budget of 12.1 million ECU . This programme is being implemented
through 72 shared-cost contracts , under most of which research is still
continuing . The first results of the programme have been published , so far ,
through annual progress reports , papers contributed to international
conferences and the first final reports of individual contracts . A confe¬
rence will again be organised upon completion of the programme . Further
information on the scope , the implementation and the preliminary results of
this programme is given In Annex 1 .
The Community research has produced numerous scientific and technical
achievements , some of which have already been tested on industrial scale .
The most striking overall impact achieved concerns the reduction of metal
waste arisings . Whereas in 1979 , at the beginning of the Community re¬
search , it was estimated that about 50 to 70% of the radioactive steel
masses of a large Light Water Reactor Plant are to be disposed of as
radioactive waste , this fraction has been reduced to about 20% in a recent
estimate . This reduction results from advances made in various areas , e.g. :
-    development of aggressive decontamination procedures , such as electro¬
     polishing and gel-based methods ;
- development of a new method for regeneration of phosphoric acid (used in
     chemical and electrochemical decontamination ) through which removed
     contaminants can be eliminated in a highly concentrated form ;
- development of melting techniques for low-level radioactive steel scrap ,
     with particular regard to radiation protection aspects and measures ;
- development of a radioactive waste disposal container cast of low-level
     radioactive scrap metal .
All these developments have reached industrial scale . Together , they
involve experience with the treatment of more than 2000 t of low-level
radioactive steel scrap . In parallel to the technological development , the
methodology for evaluating the radiological consequences of the management
of very low-activity material from the dismantling of nuclear installations
has been developed .
(T) Council Decisi on 79 / 3AA /Euratom (OJ N° L 83 , 3 . A. 1979 , p . 19 ).
(?) Decommissioning of Nuclear Power Plants . Proceedings of a European
       Conference held in Luxembourg , 22-2A May 198A . EUR 9A7A .
( 3 ) Council Decision 8A / 60 / Euratom (OJ N° L 36 , 8.2.198A , p . 23 ).
                                        - 5 -
 ---pagebreak--- The Community research activities on decommissioning have been evaluated by
a panel of external experts during the period of January to July 198b . The
recommendations made by the panel have been taken into consideration in the
preparation of the present programme proposal .
2.4 . The need for a further programme
Further research is needed in particular in order to cope with large
components of higher radioactivity level than the components treated so
far . This research should accompany the dismantling of the first nuclear
power plants in the Community , which has been started with the lower-level
radioactive peripheral plant systems and will progressively approach the
higher-level activated reactor block . Accordingly , operations will more and
more rely on remote control .
The need for a further programme of research cn decommissioning has also
been recognised in the framework programme for Community activities in the
field of research and technological development ( 1987 to 1991 ) ( 1 ), where
it Is pointed out that work on decommissioning operations will involve
demonstration of relevant technologies .
The need for a further programme was confirmed by the Management and
coordination advisory committee when it delivered its opinion supporting
the proposed programme ( see Annex 4 ).
3 . SCOPE OF THE PROPOSED PROGRAMME
The proposed programme is composed of three Sections with the same subjects
as the current ( 1984-88 ) programme . Section C has been strongly expanded in
order to enable the Community to participate more substantially in selected
pilot projects undertaken in various Member States .
3.1 . Section A - Research and development projects
Section A of the proposed programme is again composed of a series of
laboratory research activities and assessment studies , as in the current
( 1984-88 ) programme , but the contents of the project areas have been
adapted to the changing needs , account being taken of the obtained results .
Thereby , an important consideration has been that certain techniques being
developed will reach , at the end of the current programme , a stage where
they should be tested in practice , within the framework of Section C , or
where they will not require further Community support .
The proposed programme comprises research and development projects in the
following areas :
1 . Long-term integrity of buildings and systems
2 . Decontamination for decommissioning purposes
3 . Dismantling techniques
(1)   Council Decision 87 / 516 /Euratom , EEC ( OJ N° L 302 , 24.10.1987 , p. I ).
                                          6
 ---pagebreak--- 4 . Treatment of specific waste materials : steel , concrete and graphite
5 . Qualification and adaptation of remote-controlled semi -autonomous
    manipulator systems
f>. Estimation of the quantities of radioactive waste arising from the
    decommissioning of nuclear installations in the Community .
Of that , Project Area N° 5 does not exist in the current programme , whereas
the following Projects of the current programme have not been included in
the above proposal :
- Project N° 5 : Large containers for radioactive waste produced in the
    dismantling of nuclear installations
- Project N° 7 : Influence of installation design features on decommission¬
    ing .
The proposed projects are described in Annex 2 .
3.2 . Section B - Guiding principles
Section B of the proposed programme is concerned with the identification of
guiding principles relating to :
-   the design and operation of nuclear installations with a view to simpli¬
    fying their subsequent decommissioning ;
-   the decommissioning operations with a view to making occupational
    radiation exposures as low as reasonably achievable ;
    the technical elements of a Community policy in this field .
Scientific information produced under the previous research programme on
the decommissioning has already served in the formulation of clearance
levels ( 1 ) for material to be recycled such as steel scrap .
In the proposed programme , the available amount of research and development
results and practical experience , together with an adequate number of
Commission staff , will enable larger progress to be made in the identifica¬
tion of guiding principles .
3.3 . Section C - Testing of new techniques in practice
Section C is again concerned with the testing of new techniques in practi¬
ce , within the framework of large-scale decommissioning operations under¬
taken in Member States .
The testing of new decommissioning techniques in practice has been initiat¬
ed in the 1984-88 programme , with participation of ten nuclear installa¬
tions , i.e. five reactors , four fuel fabrication plants and one waste
vitrification facility .
or Recommendations of a Working Party set up under Art . 31 of the Euratom
     Treaty .
 ---pagebreak---    Mere difficult decommissioning tasks than those already performed are to
   come , for instance , with the dismantling of large neutron-activated reactor
   components . For the first time , nuclear power plants will be completely
   dismantled within the timespan from now to about the year 2000 .
   The Commission , through shared-cost participation in specific parts of such
   projects , intends promoting the use of advanced techniques and the perform¬
   ance of collateral investigations , in order to enhance the production of
   useful knowledge and experience to serve in subsequent decommissioning
   tasks . The Commission would also like to promote the testing of techniques
   developed in other Member countries , having no suitable dismantling pro ¬
   ject . Resides , dismantling projects will contribute to improve the data
   basis for decommissioning cost estimates .
   It is proposed to focus Section C mainly cn a few outstanding decommission ¬
   ing projects performed or planned in various Member States , which could he
   namely :
   - the Windscale Advanced Gas-cooled Reactor ( WAGR)
   - the Gunaremmingen Boiling Water Reactor (KRB-A )
       the BR-3 Pressurised Water Reactor
       the AT-1 fuel reprocessing plant .
   Some important characteristics of these projects are given in Table I.
                        TABLE I - PILOT DISMANTLING PROJECTS
Instai 1 at ion  WAGR              KRB-A           BR-3           AT-1
Location         Sellai ield ,     Gundremmingen , Mol ,          La Hague ,
                 United Kingdom    Germany         Belgium        France
Type             Advanced Gas -    Boiling Water   Pressurised    FBR fuel
                 cooled Reactor    Reactor         Water Reactor  reprocessing
                                                                  plant
Production       33 MWe            250 MWe         11 MWe         2 kg / d
capacity
Production       1962-81           1966-77         1962-87        1969-79
period
Decommission ¬   1981-96           1982-99         1989-          1981-93
ing period
                                         - 8 -
 ---pagebreak--- The proposed pilot projects represent complementary types of installation
which , considered together , cover the large majority of nuclear installa¬
tions involving difficult decommissioning tasks . All projects , with the
exception of. the BR-3 project , include the complete removal of the radio¬
active materials from the installation . ( The BR-3 plant was finally shut
down only recently , so that a complete decommissioning plan has not yet
been set up ). It is therefore proposed to consider in the first instance
only the four above-mentioned projects as pilot projects for the Community
programme . However , if satisfactory terms of Community participation could
not be reached on a project , or if a project would be abandoned cr unduely
delayed or modified , it should be replaced by the most suitable substitute
project .
Further information on the four projects is given in Annex 3 . This informa¬
tion includes possible subjects for cost-sharing Community participation ,
from which the most interesting ones are to be selected .
In addition to the above-mentioned pilot projects , other nuclear installa¬
tions being dismantled in Member States should be selected at the initial
stage of the proposed programme , for alternative tests .
The Commission would promote the secondment of staff from other member
countries to the pilot dismantling projects , for participation in the re ¬
search activities .
4 . IMPLEMENTATION AND MANAGEMENT
The proposed programme will be implemented mainly through shared-cost
contracts with competent public organisations or private firms established
in the Member States . The Community contribution will not normally exceed
50% of the total expenditure . In respect of universities , the Community may
assume up to 100% of the additional expenditure (marginal cost ) .
In particular cases , where an opportunity for a large co-operation involv¬
ing different countries exists , reinforced concerted action will be appli¬
ed . This concerns in particular the pilot dismantling projects considered
in Section C of the proposed programme , where the Community would partici¬
pate through shared-cost contracts in specific parts of the projects , and
organise by means cf concerted action an exchange of information relating
to the other parts .
In the selection of research proposals , the Commission will give priority
to joint proposals from bodies of different Member States . Moreover , the
Commission will incite proposers of related research to co-operation . An
intensive exchange of detailed technical information between people working
in the same area will again be organised .
                                          9
 ---pagebreak--- In the- carrying out of the programme , the Commission will again have the
assistance of the Management and coordination advisory committee " Nuclear
fission energy - Fuel cycle /processing and storage of waste " ( CGC6 ) ( 1 ).
The Commission will continue to participate in the relevant activities in
the field of decommissioning , initiated by the International Atomic Energy
Agency and the OECD Nuclear Energy Agency .
5 . BUDGET AND STAFF
The proposed programme would require a Community funding of 31.5 million
ECU and a staff of five . Table TI gives a breakdown of the costs .
                         TABLE II - BREAKDOWN OF COSTS
(Over five years )
    Item                                                                    MECU
    A. Research and development projects :
                                               - Area  N°  1                 0.3
                                               - Area  N°  2                 0.7
                                               - Area  N°  3                 2.0
                                               - Area  N°  4                 1.5
                                               - Area  N°  5                 1.8
                                               - Area  N°  6                 0.9
                                               - Total Section A .           7.2
    B. Identification of guiding principles .                                0.3
    C. Testing of new techniques in practice :
                                               - Pilot projects . 16.0
                                               - Alternative tests . 4.0
                                               - Staff secondment .          1 .0
                                               - Total Section G . 21.0
    Commission staff ( 3A + IB 4 IC ) .                                      2.3
    Administrative expenses . .             .                                0.7
    Total . 31.5
                                            *
(1)    Council Decision 84 / 338 / Euratom , ECSC , FEC ( OJ N° L 177 , 4.7.1984 ,
       p. 25 ).
                                              10 -
 ---pagebreak---                                       ANNEX 1
   THE 1984-88 PROGRAMME ON THE DECOMMISSIONING OF NUCLEAR INSTALLATIONS
1 . Scope
By its Decision of 31 January 1984 ( 1 ), the Council adopted a 12.1 MECU
programme , which is a follow-up of the first research programme on the
decommissioning of nuclear power plants ( 1979-83 ) ( 2 ) for the five-year
period from 1 January 1984 to 31 December 1988 , differing from the first
one in the respect that investigations are extended to nuclear installa¬
tions , such as reprocessing plants and fuel fabrication plants , in addition
to nuclear power plants .
The programme is divided into three sections , A , B and C.
Section A   relates to research and development projects as follows :
- Project   N°l : Long-term integrity of buildings and systems ;
- Project   N°2 : Decontamination for decommissioning purposes ;
- Project   N°3 : Dismantling techniques ;
- Project   N°4 : Treatment of specific waste materials : steel , concrete and
                  graphite ;
- Project N°5 : Large containers      for radioactive waste produced in the
                  dismantling of nuclear installations ;
- Project N°6 : Estimation of the quantities of radioactive waste arising
                  from decommissioning of nuclear installations in the Commu¬
                  nity ;
- Project N°7 : Influence of installation design features on decommission­
                  ing .
Section B concerns the identification of guiding principles , namely :
    certain guiding principles in the design and operation of nuclear
    installations with a view to simplifying their subsequent decommission¬
    ing ;
- guiding principles in the decommissioning of nuclear installations ,
    which could form the initial elements of a Community policy in this
    field .
Section C - testing of new techniques under real conditions , within the
framework of large-scale decommissioning operations undertaken in Member
States - has been added to the programme in order to improve these techni¬
ques in particular in the presence of radioactivity .
2 . Management
This programme is carried out on the Commission 's responsibility by means
of cost-sharing contracts with public organisations and private firms
within the EC Member States having competence in nuclear research .
(1)   OJ N° L 36 , 8.2.1984 , p. 23 .
(2)   OJ N° L 83 , 3.4.1979 , p. 19 .
                                           11
 ---pagebreak--- The Commission has set up three working groups for the various research
areas of the programme , to provide specialised scientific support for the
Commission in handling the technical aspects of the programme and to
ensure , at operational level , frequent exchanges of information and views
on the latest progress of the research . The groups meet twice a year .
After the programme had been adopted by the Council on 31 January 1984 , the
research proposals were called for ( 1 ). As for the foregoing 1979-83 pro¬
gramme , the research proposals received were examined and evaluated in
detail by ad-hoc groups composed of experts of various Member States and
the Commission staff . The most appropriate proposals were chosen and
detailed work programmes defined . The exchange of views between experts was
found to be of great value and a help for a better understanding of the
problems posed . The majority of the research contracts were negotiated
between mid-1984 and end of 1985 . By the end of May 1988 , a total of 72
contracts had been awarded . Most of them will end during the second 1988
semester .
3 . Progress and results
Project N°l : Investigations being performed on the implications of main¬
taining shut-down nuclear installations for long periods before dismant ¬
ling , in order to benefit from the natural decrease of radioactivity , will
serve to assist the choice of the best timing for dismantling . This choice
is one of the basic decisions that have to be taken in the decommissioning
of any nuclear installation : work in this project started rather late ,
hence no essential results are yet available .
Project N°2 : The characterisation of the radioactive surface contamination
in nuclear installations and the development of efficient decontamination
techniques is another important project in the current programme . Essential
results obtained up to now are as follows :
The Lingen decontamination procedure was tested on a primary system stain¬
less steel pipe of the Lingen Boiling Water Reactor . The procedure is based
on oxide layer removal using the LOMI ( Low Oxydation Metal Ions ) process ,
followed by a dilute mixture of hydrochloric acid and nitric acid . The
tests are aimed at demonstrating the possibility of reducing the contamina¬
tion to a level below the limit for unrestricted release ( 0.37 Bq / cm2 ) and
this objective has been attained .
Decontamination procedures on small valves (1 to 2 inch nominal size ) from
the Garigliano Boiling Water Reactor were tested using two aggressive
chemical decontaminants , i.e. hydrochloric acid and a mixture of nitric
acid and hydrofluoric acid : whereas the treatments were highly effective on
the surface areas that were well accessible to the decontaminant , contami¬
nation deposited between fitted parts , e.g. threads or pipe joints , could
not be removed completely .
Promising results on laboratory scale have been obtained with applications
of electrochemical techniques , in particular with electrolytes other than
phosphoric acid .
(1)   OJ N° C 68 , 9.3.1984 , p. 2 .
                                        12
 ---pagebreak--- A remote electrochemical decontamination method for hot cell applications ,
with special regard to plutonium-contaminated stainless steel surfaces is
under development at laboratory scale . Two types of application are being
considered , i.e. tank immersion for small items and in-situ electropoli¬
shing of 5 cm squares , using a light , vacuum-sealed head , to remove hot
spots from large surface areas . Nitric acid has been chosen as electrolyte .
An advantage with this electrolyte is , that metal dissolution is achieved
also in recesses and cavities .
A decontamination method by spraying a chemical gel was developed on
laboratory scale and applied to a cooling circuit of the French gas-gra¬
phite reactor G2 , before dismantling , with the following sequence : basic
gel spraying ( NaOH) ; rinsing ; acid gel spraying ; rinsing . Good results at
larger in-situ tests have been obtained : the initial activity of 100 Bq / cm2
has been reduced to 0.2 Bq / cm2 .
Project N°3 : About half of all 20 contracts concluded are dealing with the
optimisation of thermal cutting in air and under water and/ or the charac¬
terisation of the cutting effluents as well as the assessment of useful
filter systems . Aerosol measurements are made in close cooperation between
contractors , by using the same measuring technique , facilitating the
comparison of generated data . Presently , a considerable amount of data on
effluents generated by cutting of different types of steel in air and under
water with various cutting tools ( e.g. plasma arc , oxy-propane , oxy-acety-
lene ) are available . Cooperation has been established on pre-filter assess¬
ment , making use of the Hero facility for optimising dismantling procedures
for the Windscale Advanced Gas Cooled Reactor . The assessed pre-filters , as
protection of High Efficiency Particulate Air (HEPA) filters , include an
electrocyclone , an electrostatic precipitator and bag filters : with oxy-
propane cutting , filter efficiencies were 60 , 98 and 99% , respectively . Rut
only the availability of appropriate cleaning and maintenance procedures ,
being under development , will allow the choice of pre-filters for given
cutting problems .
Laser cutting of metallic components is developed by means of a robot arm
with 5 articulations for the transmission of a 3-5 kW laser beam into a hot
cell . The system , including the software package , is ready for cutting
tests .
Extensive studies on the dismantling of thick-walled reinforced concrete
structures ( such as biological shields ) by controlled blasting with explo¬
sives have been undertaken in two contracts with a common work programme .
They have resulted in optimised procedures for initiation mode , type and
distribution of charges , as well as for dust control , and the assessment of
blast effects on the remaining containment and other installations which
are to be preserved .
Project N°4 : Essential progress has been achieved in the treatment of
radioactively contaminated steel waste by melting (more than 1000 Mg) and
in the recycling and reuse of those waste : melting was demonstrated to be
an efficient procedure for the release measurements which can be done in a
safe and fast way because of the perfect homogenisation of the radioactivi¬
ty in the ingot retaining the bulk of the Co–60 activity ; the volatile
cesium activity is retained in slag and filters . Melting of non-ferrous
                                         13 -
 ---pagebreak--- metal waste from refurbishing / dismantling nuclear Installations ( galvanised
zink sheets , copper , aluminium , brass ) as well as scrap contaminated with
radionuclides that are difficult to measure ( e.g. Fe-55 , Ni-63 , Sr-90 ) has
been initiated . Work concentrates on tbe radiological impact of this
technique and the long-term behaviour of the melting device , aiming at
protecting work force and the surrounding area efficiently .
Significant progress has also been made with fixing of contamination on
large concrete and metal parts by coating with polymers . A strongly gamma-
radioactive steel component was successfully coated by a teleoperated
mobile projection apparatus developed in this aim .
Work on treatment of contaminated concrete and radioactive graphite started
late , but important progress has been made in the development of a sampling
technique of the French G2-core graphite , allowing the obtention of 80 x 80
mm cylindrical graphite samples suitable for precise characterisation work
on radioactive graphite .
Project N°5 : Research work under way relates to design and evaluation of
large containers for reactor decommissioning waste , large waste containers
made of fibre-reinforced cement and of low-level radioactive metal scrap .
Essential progress has been achieved in the development of a prototype
container for disposal in the Konrad mine ( loading capacity 14 Mg , 5.4 m3 )
cast of low-radioactive metal scrap (< 10 Bq / g ). This container is present ¬
ly tested in the frame of the licensing procedure .
Project N°6 : Research is in progress in the following main areas :
-    optimisation measurement techniques of low-level radioactive material
     for large land areas , and of methods aiming at the establishment of the
     curie content of Windscale AGR under dismantling ;
-    methodology study for assessing suitable systems for management of
     reactor decommissioning waste and development of systems for contamina¬
     tion measurements on curved surfaces ;
-    estimation of wastes arising from the dismantling of a commercial fast
     breeder reactor ;
-    radiological evaluation of releasing very low-level radioactive copper
     and aluminium .
Concluding results are obtained in the establishment of a computer-assisted
measuring technique for low-gamma activities showing that a peak-fitting
method may save up to 50% of time-related costs compared with the tradi¬
tional gross-counting method .
An integrated portable measuring device composed by a series of round and
flat gas flow detectors suitable for contamination measurements on curved
surfaces ( e.g. inside tubes > 22 mm at distances up to 6 m) was developed
and should now be tested under real conditions .
Project N°7 : Some of the subjects studied under the first programme needed
to be continued , whereas the design features of fuel cycle installations
( e.g. reprocessing plants ) are newly added . Research work under way relates
to :
-    decontamination and remote dismantling tests in a reprocessing pilot
     plant and testing of cobalt-free valves seatings ;
                                          14 -
 ---pagebreak--- -  pre-stressed concrete reactor vessels with weakness planes and in-situ
    sealing of concrete surface by Impregnation with polymers ;
-  design features for decommissioning of a large commercial, fast breeder
    reactor .
Essential progress is obtained for the decontamination and dismantling of
the reprocessing plant at Trisaia ( Italy): the decontamination of a modular
unit , using concentrated ( 12 M) nitric acid and successively less concen¬
trated solutions till a final washing with demineralised water , has been
performed and the manufacture of the cutting equipment achieved .
Progress has also been made for the optimisation of the in-situ sealing of
concrete surfaces by polymer impregnation showing useful for normal opera¬
tion as well as for the long-term integrity ; the development and testing of
appropriate impregnation devices has been successfully achieved .
Section C : Large-scale investigations in this programme are associated to
work on the decommissioning of nuclear reactors such as Garigliano BWR ,
KRB-A Gundremmingen BWR , Windscale AGR , Rapsodie FBR and to some fuel
fabrication and waste treating plants :
A major advance in efficient decontamination with minimum quantities of
secondary waste is the new process for regeneration of phosphoric acid
which was developed and demonstrated on a large scale at KRB-A Gundremmin¬
gen . Phosphoric acid , used for chemical and electro-chemical decontamina¬
tion , is mixed with oxalic acid , whereby iron oxalate is formed , which
precipitates and is removed as a sediment containing most of the radioacti¬
vity . The decontamination of 500 Mg of steel scrap from dismantling the
turbine house components of the Gundremmingen BWR produced 18 t of iron
oxalate which will be pyrolytically decomposed to 8 Mg of iron oxide ,
representing 1.6 wt % of the scrap treated .
The development and manufacturing of the prototype for a multi-purpose
automatic measuring system for low-level activity intended for the free-
release sorting of decommissioning waste , is well advanced and will be
tested on large scale ( 1000 Mg ) in the frame of the decommissioning of the
KKN reactor .
Five large glove boxes of mixed-oxide fuel fabrication plant had to be
decommissioned with their internal equipment . The boxes were up to 4.1 m
high , had 10 m3 and a weight , including the equipment , up to 2 Mg . After
specific conditioning , the boxes were moved to the Mol Nuclear Research
Centre for dismantling (5 km on public road ).
The removal of internals and the cleaning of the PIVER I cell at Marcoule ,
the first French demonstration facility for the vitrification of high-level
liquid waste from reprocessing gas-cooled and fast–breeder reactor fuel ,
has been undertaken . Further work relates to the estimation of the radio¬
active inventory associated to radiation dose rates up to several hundred
rad /h and to the installation of remote-controlled manipulators and robots .
                                        15
 ---pagebreak--- Section B : Results which will be obtained from several research contracts
being carried out within the frame of Section A ( e.g. : long-term stability
and leak-tightness of reactor containments , consequences of suppression of
negative pressure in the German I.ingen reactor , methodology for assessing
suitable systems for management of reactor decommissioning wastes ) could
serve as a basis for guiding principles in the field of decommissioning and
may allow one day to decommission nuclear installations not only on a case-
by-case basis . To reach that goal and with respect to the coming 1992
internal market , specific technical regulations on decommissioning , as well
as Community criteria for distinguishing non-radioactive material from
radioactive material , should be established .
4 . Exchange and dissemination of results
A direct exchange of detailed information on the work progress is ensured
at operational level by the working groups referred to in paragraph 2 and
by semestrial reports ; this exchange is restricted . The results of each
research contract appear in final reports which are prepared by the con¬
tractors and which are either published with the agreement of the contrac ¬
tors ,   or " communicated " to  the bodies    concerned in the Member States
("Article 13 of the Euratom Treaty ) . The Commission also publishes annual
progress reports on the programme ( 1 ). Publications in scientific journals
and contributions to international conferences supplement this exchange of
information .
A public conference is planned after the completion of the programme , in
order to present the results of the 1984-88 programme to the international
scientific community .
Finally , the programme staff is participating in working parties and
technical committees on the decommissioning of nuclear installations , which
are organised within the framework of the international organisations
( IAEA , OECD / NEA).
(1)    First report (year 1985 ): EUR 10740 ;
       Second report (year 1986 ): EUR 11112 .
       Third report (year 1987 ): in print .
                                           16 -
 ---pagebreak---                                                     ANNEX 2
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                                       [) ΕνΕΙΟΡΜΚΝΤ ΡΚϋ^)ΕϋΤ3
Area N°1
Long-term integrity of buildings and systems
A. Objective
It has been proposed that the dismantling of nuclear Installations be
delayed for periods ranging from several decades to about a hundred years .
Thereupon , the radioactivity having largely died away , dismantling would be
easier and the radiation exposure of the dismantling personnel would be
less . The objective of this area is to determine the measures required for
maintaining shut-down plants in a safe condition and to assess the radiolo¬
gical consequences and costs .
B. Research performed
The research work has been focused on the following main subjects :
   inspection of selected nuclear power plants and examination of materials
   as they exist therein , in order to determine the mode and pace of
   degradation ;
- methodology studies of the measures necessary for maintaining plants in
   safe condition and for keeping the necessary ancillary equipment oper¬
   able .
C. Propos ed p rogramme 1SS9-93
Research in this area should be pursued with a constant moderate effort ,
enlarging the data base ar.d exploiting the growing experience , in order to
establish confidence in long-term forecasts . This involves in particular :
- collection of additional experimental data , e.g. repetition of past
   examinations after a time interval of about five years , in order to
   determine the rate of degradation and derive or check forecasting rules ;
- comparison of confinement methods applied at specific shut-down nuclear
   installations in Member States ;
-  assessment of the merits of the Safe Storage option in the decommis ¬
   sioning of nuclear installations other than reactors .
Area N°2
Decontamination for decomm i ssioning purposes
A. Objective
The objective of this research is to develop and assess techniques for
decontaminating surfaces of components and structures of nuclear installa¬
tions that are past use . The main purpose of decontamination would be
reduction of the occupational radiation exposure during dismantling of the
contaminated item and / or reduction of the volume of radioactive waste .
                                                         17
 ---pagebreak--- B. Research performed
The following, decontamination techniques have been developed and assessed :
    techniques using aggressive agents in liquid and gel-like form ;
    electrochemical techniques using various electrolytes ;
- hydromechanical techniques (high-pressure water lance , ultrasound );
- decontamination of concrète surfaces hy fl&me jetting .
C , Propcsed programme 1989-93
Research in Area N° 2 should be pursued with a reduced effort focused on
selected techniques . As a new subject , the use of liquid chemical agents
carried by a large volume of air , in the form of foam or fog , should be
developed with a view to decontaminating large-volume systems . Thermal
techniques for removal of concrete surface layers should be investigated
from a more general and fundamental view than in the past .
Area N° 3
Dismantling techniques
A.   Objective
The objective of this research is the development of the special techniques
needed for dismantling the large steel components (e.g. reactor pressure
vessel ) and reinforced-concrete structures (e.g. reactor shielding ) of
redundant nuclear installations , account being taken of the particular
requirements due to radioactivity .
B.   Research performed                                            _
The following techniques are being tested and developed :
- thermal techniques such as plasma-arc and oxygen cutting and cutting by
    laser beam ;
-   mechanical techniques such as abrasive water jet cutting ;
    explosive techniques for the dismantling of concrete structures .
C.   Froposed programme 1989-93
Research in this Area should be pursued vigorously . The following develop ¬
ment needs have already been identified :
-   development of the arc-saw technique for cutting thick-walled steel
    components ;
-   further development of the electrolytic technique for segmenting thick
    steel sections ;
-   comparative assessment of various segmenting techniques with reference
    to standard cutting tasks ;
-   full-scale testing of controlled explosive techniques for dismantling of
    concrete structures .
                                        18 -
 ---pagebreak--- Area N° 4
Treatment of specific waste materials : steel , concrete and graphite
A. Objective
In the dismantling of nuclear installations , large amounts of radioactive
steel , concrete and - in the case of gas-cooled reactors - graphite will
arise . This waste must be suitably conditioned for disposal or recycling .
This Area has been strictly delimited to preclude overlapping with the
Community research programme on radioactive waste management .
B. Research performed
The following research work has been performed :
- experiments on the melting of radioactive steel scrap including large
   melting series ;
   development and assessment of techniques for coating metal , concrete and
   graphite parts in order to immobilise the radioactivity ;
   immobilisation of concrete dust and separation of radioactive and
   non-radioactive constituents of concrete ;
   assessment of various management modes for radioactive graphite waste .
C. Proposed programme 1989-93
Melting of very low-level radioactive steel scrap from Light Water Reactor
components , to produce new nuclear components , is already becoming indus ¬
trial. practice and is not expected to need further research . Further work
is required , however , in relation to steel scrap originating from other
types   of  nuclear  installation , e.g.    alpha-contaminated material , and
non-ferrous scrap .
The further development needs relating to concrete and graphite v'aste will
be determined after completion of the current work .
Area N° 5
Qualification and adap tation of remote-controlled semi-autonomous manipula-
tor svstems
A. Objective
Because of radiation fields , certain decommissioning tasks must be per¬
formed with remote control , and others are preferably performed therewith
in order to minimise occupational exposure . This requirement forms a major
technical challenge in decommissioning .
The objective of this research is to qualify and adapt remote-controlled
semi–autonomous systems for manipulation of decommissioning tools and
instruments .
                                         19
 ---pagebreak--- B. Research performed
Remote-controlled manipulation         systems    did not     form the    subject of n
Project Area of Its own , so fnr , hot limited activities In this field have
been per I 01 med under Pro let t. N*’    ( heron taw Inn lion ) and N " T ( l > I stiuuit I Inn
techniques ) .
C. Propoeed programme 1 98 9-93
Remote-controlled semi-autonomous manipulators should be tested and adapt ¬
ed , in order to qualify and improve their performances with typical decom¬
missioning tasks and tools . For this purpose , existing components and
sub-systems should be used and adapted as far as feasible . This concerns in
particular sensing systems and computer programmes for semi-autonomous
process control , which form important aspects of this research . Special
attention should be paid to highly repetitive time-consuming operations ,
e.g. decontamination and clearance measurements of large surface areas of
premises .
Area N°6
Estimation of the quantities of radioactive waste arising from decommis ¬
sioning of nuclear Installations in the Communl tv
A. Obiective
The low-level radioactive waste produced in the dismantling of nuclear
installations will ultimately constitute a substantial part of the overall
volume of radioactive waste generated by nuclear industry . The objective of
this research is to estimate the quantities of various categories of radio ¬
active waste that will arise from the decommissioning of nuclear installa¬
tions in the Community . This involves the definition of reference strate¬
gies for decommissioning and is therefore to be regarded as a long-term
task .
B. Research performed
The following research work has been performed :
- determination of the long-lived radionuclide content of neutron-acti ¬
    vated steel , concrete and graphite ;
    preparation of a methodology for evaluating the radiological consequen¬
    ces of the management of very low-level waste produced in the dismantl ¬
    ing of nuclear installations ; evaluation of residual activity levels
    below which materials could be re-used ;
    development of measurement techniques required for the purpose of
    deciding whether or not material from the dismantling of nuclear instal ¬
    lations is radioactive .
                                               20 -
 ---pagebreak--- C. TropoFed programme 1989-93
Radioactivity measuring techniques should be further developed with parti¬
cular regard to clearance procedures for materials , buildings and sites ,
Including the cate ol mixtures of alpha , beta and gamma emitters . The
quality assurance of clearance procedures should also he considered .
Strategies for the decommissioning of nuclear installations and for the
management of the radioactive waste arising therefrom should be studied ,
account being taken of the waste disposal facilities existing or planned in
various member countries . Safety being one of the aspects to be considered ,
a methodology for evaluating the risk of decommissioning operations should
be developed .
The evaluation of residual activity levels below which materials could be
 reused should be pursued , including consideration of statistical aspects .
                                         21
 ---pagebreak---                                         ANNEX 3
                        POSSIBLE PILOT DISMANTLING PROJECTS
1 . Windscale Advanced Gas-cooled Reactor (WAGR )
A. Specific contribution to the programme
The WAGR dismantling project provides opportunities for testing decommis¬
sioning techniques against the specific requirements of gas-cooled react ¬
ors , e.g. requirements relating to large-volume systems . Gas-cooled react ¬
ors represent the majority of first-generation nuclear power reactors ,
which    are to be    decommissioned   in  the   near future : of about 50 nuclear
power reactors in the Community which will be finally shut down by the year
2000 , about two thirds will be of the gas-cooled types .
B. State of the project
The WAGR dismantling project is already in the implementation phase . Major
activities performed have been , e.g. construction of a waste packaging
building and design of a remote dismantling machine . Dismantling of the
most radioactive part of the reactor is planned for the period 1991-95 .
Several activities of the current ( 1984-88 ) research programme of the
Community have been carried out in the framework of the WAGR project . These
activities concern the following subjects :
- ventilation and filtration techniques for thermal cutting operations
    ( joint UK / French experiments ),
-   methods to establish the radionuclide content of waste ,
-   development of techniques to dispose of the heat exchangers .
C. Possible subjects for Community participation ( shared-cost contracts )
-   Dismantling of reactor top biological shield , refuelling branches and
    reactor pressure vessel top dome .
-   Inactive trials of the remote dismantling machine .
-   Decontamination and dismantling of three heat exchangers .
-   Remotely controlled dismantling of the reactor hot box .
    Remotely controlled dismantling of the reactor neutron shield ( upper
    axial shield ).
-   Remotely controlled dismantling of reactor core graphite .
-   Remote packaging of intermediate level waste .
-   Melter for installation in the turbine hall .
                                              22
 ---pagebreak--- 2 . Gundremmingen-A Boiling Water Reactor
A. Specific contribution to the programme
The Gundremmingen-A plant belongs to the light-water reactors , which
represent the large majority of more recent nuclear power plants in the
Community . It would be the first nuclear power plant in the world with a
capacity of several hundreds of MWe , to be removed completely . Particular
attention in the implementation of this project is being paid to reduction
of waste arisings .
B. State of the project
The Gundremmingen-A dismantling project was started with decontamination
and demolition of the radioactive waste store and with dismantling of the
turbine building equipment . Over the next five-year period ( 1989-93 ),
higher level contaminated equipment from the reactor building will be
removed .   Dismantling of neutron-activated equipment ,     e.g. the reactor
vessel , is planned for 1994 / 95 .
Several activities of the previous ( 1979-83 ) and current ( 1984-88 ) research
programmes of the Community have been carried out in the framework of the
Gundremmingen-A project . These concern in particular the following sub ¬
jects :
- distribution of activation products in the biological shield ,
- development and large-scale application of decontamination techniques ,
- large-scale application of segmenting techniques ,
- steel melting as a radioactive waste conditioning method .
C. Possible subjects for Community participation ( shared-cost contracts )
     Assessment of system decontamination techniques and comparison with
     other radiation protection methods .
     Segmenting of higher-level contaminated components , e.g. secondary steam
     generators .
     Thermal and mechanical techniques for underwater segmenting of activated
     components , i.e. reactor pressure vessel internals .
     Development of a dismantling manipulator for segmenting of the reactor
     pressure vessel and its internals .
     Optimised system for reuse of scrap material and for volume reduction of
     radioactive residues .
 3 . BR-3 Pressurised Water Reactor
A. Specific contribution to the programme
Pressurised Water Reactors are the reactor type most frequently used in the
 Community , and the BR-3 was the first plant of this type operating in
Western Europe . The BR-3 project involves dismantling of highly radiating
 steel components of significant dimensions .
                                         - 23 -
 ---pagebreak--- B. State of the nroject
The BR-3 plant has been finally shut down only recently . Following prepara¬
tory activities , decontamination of the primary circuit is planned for 1990
and dismantling of the reactor internals is planned for 1991-93 . No further
dismantling activities , for years later than 1993 , are planned so far .
C. Possible subjects for Community participation ( shared-cost contracts )
     Chemical decontamination of the primary circuit .
     Remote-controlled underwater segmenting of the reactor internals .
4 . AT-1 fuel reprocessing plant
A. Specific contribution to the programme
Installations from the backend of the nuclear fuel cycle pose special
problems due to the presence of alpha emitters . One important task is to
prove compliance with the low exemption limits for alpha emitters on large
amounts of decontaminated material or on surface areas of premises . Dis ¬
mantling of mixed-oxide (UO^-PuC^) fuel facilities has already been demons¬
trated within the framework of the current ( 1984-88 ) research programme .
Reprocessing plants , containing mixtures of alpha , beta and gamma emitters ,
require additionally that decommissioning operations be controlled remote-
iy .
B. State of the project
The AT-1 dismantling project is already in the phase of implementation . The
activities performed so far concern mainly the dismantling of components
contaminated only by alpha emitters , and development of a computer-assisted
telemanipulator to be used from 1990 to 93 for dismantling of the other
components . The AT-1 project would be completed by the end of 1993 .
C. Possible subjects for Community participation ( shared-cost contracts )
-    Management of alpha-beta-gamma wastes , in particular :
     . counting system for sorting of waste items and segments ,
     . system for waste transfer without breach of confinement ,
     . prototype facility for decontamination of alpha wastes ,
     . facility for alpha and beta-gamma counting of waste packages .
-    Remote-controlled dismantling of high-activity cells , in particular :
     . development of an electronic telemanipulator ,
     . adaptation and optimisation of operating procedures for various remote
       handling systems and cutting tools ,
     . automation of operations .
                                       - 24 -
 ---pagebreak---                                     ANNEX 4
       OPINION OF THE MANAGEMENT AND COORDINATION ADVISORY COMMITTEE
   "NUCLEAR FISSION ENERGY - FUEL CYCLE /PROCESSING AND STORAGE OF WASTE "
The Management and Coordination Advisory Committee "Nuclear fission energy
- Fuel cycle /processing end storage of waste " ( CGC 6 ), on its meeting of
12 April 1988 , examined a proposal for a 1989-93 programme of research cn
the decommissioning of nuclear installations ( document CGC 6 / 88-7 ).
The proposed programme is composed of three Sections with the same subjects
as the current ( 1984-88 ) programme , i.e. : Section A , Research and develop¬
ment projects ; Section B , Guiding principles ; Section C , Testing of new
techniques ir. practice . Section C has been strongly expanded in order to
enable the Community to participate more substantially ir. selected pilot
dismantling projects in various Member States .
The proposed programme would require a budget of 31.5 million ECU and a
staff of five . The programme would be implemented through cost-sharing
contracts with competent public organisations or private firms in the
Member States .
The Committee considers that the three Sections of the programme provide a
suitable basis for a well balanced activity comprising laboratory research ,
identification of guiding principles and pilot operations . The Committee
welcomes the increased effort on the testing of new techniques in practice
and recommends to take a flexible approach in the implementation of Sec¬
tion C. In this context , the Committee notes with satisfaction the possibi ¬
lity of alternative tests . The Committee agrees with the Commission that it
should be verified at the beginning of each contract that the licensing
authorisations and balancing national funding are reasonably assured .
As a conclusion , the Committee supports unanimously the programme proposed
by the Commission services , both for its technical content and the amount
of funding .
Brussels , 12 April 1988                               J. LEFEVRE
                                              Chair-man of the Committee
 ---pagebreak---                                       ANNEX 5
                 OPINION OF THE SCIENTIFIC AND TECHNICAL COMMITTEE
The Scientific and Technical Committee , at its 19th July 1988 meeting ,
examined a proposal for a third , five-year , cost-sharing research programme
( 1989-93 ) on the decommissioning of nuclear installations ( document
DEC-88 / 3 ) , drawn up by the Commission to follow the current 1984-88 re ¬
search programme . The proposed programme requires a Community contribution
of 31.5 million ECU . Having examined the proposal , the Scientific and
Technical Committee gives the following opinion .
The Committee considers that it is essential for the Community to continue
developing techniques for decommissioning the various types of full-size
nuclear power reactors and other facilities of the nuclear fuel cycle in
the EC . Strong emphasis should be given to optimising decontamination and
dismantling techniques with the aim of minimising the quantity of radio ¬
active waste needing final disposal , the generation of secondary waste , and
the radiation exposure to workers carrying out decommissioning . In addi ¬
tion , the Committee recommends that the programme includes evaluation of
the economics of various decommissioning techniques .
The Committee welcomes the emphasis given in Section C of the new programme
in focussing effort on four representative and complementary pilot pro ¬
jects . The Committee stresses the importance of access to these projects
for interested organisations and industries within the EC .
In order also to improve public understanding of decommissioning , the
Commission should give the widest possible dissemination of both results
from its own programme and , as far it can do so , the other programmes being
carried out by Member States .
The Committee considers that the proposed programme is appropriate to its
objective and therefore strongly supports the proposal , although it consi ¬
ders that the resources allocated could usefully be increased .
                                           26
 ---pagebreak---                                      ANNEX 6
                             FINANCIAL RECORD SHEETS
1 . Budget Heading
- Code N° : 7316 ( 1988 ); 7352 ( 1989 ).
- Title : Decommissioning of nuclear installations
2 . Legal basis
Article 7 of the Treaty establishing the EAEC .
3 . Description and objective of the action
This action concerns a five-year ( 1989-93 ) shared-cost research programme ,
which is a follow-up of the programme ending in 1988 that was adopted by
Council Decision 84 / 60 /Euratom of 31 January 1984 ( OJ N° L 36 , 8.2.1984 ,
p. 23 ) . The present programme is one of the components of the "Framework
programme for Community activities in the field of research and technolo¬
gical development ( 1987 to 1991 )" concerned by Council Decision 87 / 516 /Eu-
ratom , EEC of 28 September 1987 (OJ N° L 302 , 24.10.1987 , p. 1 ).
The programme includes the following subjects :
- research and development projects concerning specialised techniques and
    basic information ;
-   identification of guiding principles ;
-   testing of new techniques in practice , within the framework of large -
    scale decommissioning operations .
The objective of the programme is to reinforce the scientific and technical
basis necessary to strengthen the safety and protection aspects of the
decommissioning of nuclear installations .
The action concerns in particular :
-   authorities responsible for nuclear safety and radiation protection ;
    licensees of nuclear installations ;
- public organisations and private firms with competence in nuclear
    research , concerned as potential contractors .
4 . Justification of the action
The action is necessary to attain the objective given under item 3 above .
Since decommissioning is still at the outset of becoming a major industrial
activity , the programme period is propitious for shaping decommissioning
procedures .
Action at Community level makes for economy of work through the exchange of
information .
                                          27
 ---pagebreak--- The need for Community action in this field was repeatedly recognised by
the Council , namely in the two Decisions mentioned under item 3 above .
5 . Financial implications of the action in respect of expenditures
5.1 . Total cost over the whole duration : approx . 60 MioECU .
5.2   Breakdown of financing :
       - Community budget : approx . 53%
       - National budgets )             47%
       - Contractors        ) aPProx *
5.3 . Multiannual timetable of appropriations
                     Appropriations for commitment (MioECU)
                       1989     1990      1991      1992    1993    1994    1989-93
   Staff               0.397    0.453     0.478     0.498   0.519     -
                                                                              2.345
   Administration      0.138    0.139     0.140     0.141   0.142     -
                                                                              0.700
   Contracts           7.465   11.908     5.282     3.761   0.039     -
                                                                             28.455
   Total               8.000   12.500     5.900     4.400   0.700     -
                                                                             31.500
                       Appropriations for payment (MioECU)
                       1989     1990      1991      1992    1993    1994    1989-93
   Staff               0.397    0.453     0.478     0.498   0.519     -
                                                                              2.345
   Administration      0.138    0.139     0.140     0.141   0.142     -
                                                                              0.700
   Contracts           1.465    4.908     6.882     6.661   5.339   3.200    28.455
   Total               2.000    5.500     7.500     7.300   6.000   3.200    31.500
5.4 . Method of calculation
5.4.1 . Staff expenditure
The appropriations were evaluated on the basis of the following staff :
    3 category A officials ( already assigned to the 1984-88 programme on the
    decommissioning of nuclear installations );
    1 category B official ( from mid-1989 );
    1 category C official ( from 1.1.1990 ).
The   calculations   are based   on   the   data  established  for the   Provisional
Draft Budget for 1989 ( i.e. : A : 93,000 ECU ; B : 58,000 ECU ; C : 37,000 ECU)
and on an annual increase rate of 4% to take into account the trend in the
general level of prices in the Community .
Appropriations for staff also cover expenses for missions and auxiliary
staff .
                                              28 -
 ---pagebreak--- 5.4.2 . Administrative expenditure
Administrative expenditure covers :
    organisation of working group meetings ;
-   use cf data processing and télécommunication facilities ;
-   supporting coordination activities ;
-   programme évaluation .
The calculations are based on average requirements and experience made with
the 1984-88 programme .
5.4.3 . Contract expenditure
The appropriations cover the financial contribution of the Community
( typically 50% ) to the expenditures incurred by contractors in performing
research and development work under the programme .
6 . Financing of expenditures
The appropriations required to cover the financial participation of the
Community in this action will be entered into the future Community budgets .
7 . Control System to be applied
Administrative control by the Directorate General for Financial Control and
by the Contract Division of the Directorate General for Science , Research
and Development , as regards the implementation of the budget and regularity
of expenditures .
Scientific Control by the competent Management and Coordination Advisory
Committee (CGC1) and by responsible officials in the Directorate General for
Science , Research and Development .
Evaluation in accordance with the " Community plan of action relating to the
evaluation of Community research and development activities for the years
1987 to 1991 " ( COM(86 ) 660 final ).
                                         29 -
 ---pagebreak---                                        ANNEX 7
                        PROPOSAL FOR A COUNCIL DECISION
         ADOPTING A RESEARCH AND TECHNOLOGICAL DEVELOPMENT PROGRAMME
                   FOR THE EUROPEAN ATOMIC ENERGY COMMUNITY
        IN THE FIELD OF THE DECOMMISSIONING OF NUCLEAR INSTALLATIONS
                                      ( 1989-93 )
THE COUNCIL OF THE EUROPEAN COMMUNITIES ,
Having regard to the Treaty establishing the European Atomic Energy Commu¬
nity , and in particular Article 7 thereof ,
Having regard to the proposal from the Commission , submitted after consult ¬
ing the Scientific and Technical Committee ( 1 ),
Having regard to the opinion of the European Parliament ( 2 ),
Having regard to the opinion of the Economic and Social Committee ( 3 ) ,
Whereas certain parts of nuclear installations inevitably become radio ¬
active during operation ; whereas it is therefore essential to find effect ¬
ive solutions which are capable of ensuring the safety and protection of
both mankind and the environment against the potential hazards involved in
the decommissioning of these installations ;
Whereas the research programme concerning the decommissioning of nuclear
installations , adopted by Decision 84 / 60 /Euratom ( 4 ), has yielded positive
results and opened up encouraging prospects ;
Whereas the scientific and technical basis necessary to strengthen the
safety and protection aspects of decommissioning should be further reinfor¬
ced , namely by demonstration of relevant techniques ;
Whereas the Council , by adopting the framework programme of Community
research and technological development ( 1987-91 ) ( 5 ), acknowledges the need
for a further action on the decommissioning of nuclear installations ,
HAS ADOPTED THIS DECISION :
                                      Article 1
A research and technological development programme for the European Atomic
Energy Community in the field of the decommissioning of nuclear installa¬
tions , as defined in the Annex , is hereby adopted for a period of five
years from 1 January 1989 .
(1)   OJ N° C. ..
(2)   OJ N° C. ..
(3)   OJ N° C. ..
(4 )  OJ N° L 36 , 8.2.1984 , p. 23 .
(5)   OJ N° L 302 , 24.10.1987 , p. 1 .
                                           - 30 -
 ---pagebreak---                                      Artide 2
The amount deemed necessary for the execution of the programme is 31.5
million ECU including expenditure on a staff of five .
                                      Article 3
The Commission shall be responsible for the execution of the programme . Tt
shall be assisted by the Management and Coordination Advisory Committee
CGC6 "Nuclear fission energy - Fuel cycle /processing and storage of waste",
set up by Council Decision 84 / 338 / Euratom , ECSC , EEC ( 1 ).
The contracts entered into by the Commission shall regulate the rights and
obligations of each party , in particular the methods of disseminating ,
protecting and exploiting the research results .
                                     Article 4
In the third year of the programme , the Commission shall undertake a review
of the programme and it shall report to the Council and to the European
Parliament on the results thereof , together , if necessary , with a proposal
for modification or prolongation .
An evaluation of the results achieved will be conducted by the Commission ,
which shall report thereon to the Council and the European Parliament .
The   above-mentioned   reports   shall be established having regard to   the
objectives and criteria set out in the Annex to this Decision and in
conformity with the provisions of Article 2(2 ) of the framework programme .
                                     Article 5
The Commission is authorised to negotiate , in accordance with Article 101
( 2 ) of the EAEC Treaty , agreements or contracts with a third State , an
international organisation or a national of a third State , with a view to
associating them wholly or partly with this programme .
                                     Article 6
This Decision is addressed to the Member States .
Done at
                                             For the Council
                                             The President
(1)    OJ N° L 177 , 4.7.1984 , p. 25 .
                                          - 31
 ---pagebreak---                                      ANNEX
                  ( to the proposal for a Council Decision)
              RESEARCH AND TECHNOLOGICAL DEVELOPMENT PROGRAMME
         IN THE FIELD OF THE DECOMMISSIONING OF NUCLEAR INSTALLATIONS
The aim of the programme is the joint development of a system of management
of nuclear installations finally shut down and of the radioactive wastes
produced in their dismantling which , at its various stages , will provide
mankind and the environment with the best protection possible . The pro ¬
gramme will involve demonstration of relevant technologies .
The programme seeks to promote :
A. Research and development projects concerning the following areas :
Area N°  1: Long-term integrity of buildings and systems ;
Area N°  2: Decontamination for decommissioning purposes ;
Area N°  3: Dismantling techniques ;
Area N°  4: Treatment of specific waste materials : steel ,     concrc
                                                                concrète  and
            graphite ;
Area N° 5 : Qualification and adaptation of remote-controlled semi-autono-
                                                                 semi-autono ¬
            mous manipulator systems ;
Area N° 6 : Estimation of the quantities of radioactive wastes arising from
            the decommissioning of nuclear installations in the Community ;
B. Identification of guiding principles relating to :
   the design and operation of nuclear installations with a view to simpli¬
   fying their subsequent decommissioning ;
-  the decommissioning operations with a        view to making occupational
   radiation exposures as low as reasonably achievable ;
-  the technical elements of a Community policy in this field .
C. Testing of new techniques in practice , within the framework of large -
   scale decommissioning operations undertaken in Member States . The tests
   will be focused mainly on a few selected pilot dismantling projects , but
   include complementary tests performed in other nuclear installations .
   The secondment of research staff from other member countries ,      to the
   pilot dismantling projects , will be promoted .
The implementation of the programme shall be done mainly through cost -
shared research and development contracts , but also through concerted
actions , studies and coordination activities .
Besides this , secondment of scientific staff from other Member countries to
the pilot projects , as well as training and mobility grants , shall be
promoted .
The Community’s participation in shared-cost action research contracts will
not exceed 50% of the total costs .
                                       - 32
 ---pagebreak--- The programme is to be evaluated by independent experts in accordance with
the Community plan of action relating to the evaluation of Community
research and development activities ( 1 ). The following criteria are to be
considered in the evaluation :
-     the extent to which research proposals were selected against relevant
      criteria ;
-     the extent to which substantial development of knowledge , techniques and
      equipment has resulted from the work supported ;
-     the potential relevance of the results with regard to industrial decom¬
      missioning operations ;
-     the potential relevance of the results with regard to safety and protec¬
      tion aspects of decommissioning and in particular to occupational
      radiation exposure of decommissioning workers ;
-     the extent to which information exchange and co-operation across the
      borders of Member States have been promoted .
 ( 1 ) COM ( 86 ) 660 final .