CELEX: 51978PC0167
Language: en
Date: 1978-04-20
Title: PROPOSAL FOR A COUNCIL DECISION adopting a programme concerning the decommissioning of nuclear power plants (submitted to the Council by the Commission)

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COM (78) 167
Vol. 1978/0055
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                                                                 COM(78)167 final.
                                                                  Brussels . 20 April 1978 .
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                               PROPOSAL FOR A COUNCIL DECISION
                   adopting a programme concerning the decommissioning
                                    of nuclear power plants
                       ( submitted to the Council "by the Commission )
COM ( 78 ) 167 final
 ---pagebreak---                                    -1
CONTENTS :
   PREFACE
   PART I :  Situation and prospects regarding decommissioning of
             nuclear power plants     •
              1.  Introduction
             2.   Experience with decommissioning
             3.   Becorcmi ssioning studies
             4.   Decommissioning techniques
             5.   Estimation of the quanti«s of
                  radioactive waste from decommissioning
             6.   Guiding principles
                            *
   PART II : Proc;rar:me proposal
             1.   Underlying considerations
             2.   General features of the proposed programme
             3.   Research and development actions
             4.   Identification of guiding principles
             5.   Breakdown of proposed funding
  Annex I :  Supporting information to Part I
  Annex II : Description of proposed research and development
             actions .
                              *     *
  Proposal for a Council decision
 ---pagebreak--- PREFACE                 ■
On May 1977 "the Council approved , as part of the Community 's action
programme on the environment    the principle of an action concerning the
decomissioning of nuclear power plants . It asked the Commission to pool
and to analyse earlier studies and experience and to present , on the
basis of the results of this work , appropriate proposals to the Council .
The present document has "been drawn up with the help of a group of
national experts . Part I contains mainly an analysis of earlier studies
and experience and Part II a proposal for a funded action programme .
The scope of the analysis and the proposal has "been restricted to nuclear
power plants , excluding other nuclear installations such as research reactors
and fuel cycle facilities . However , available relevant experience with
such other installations has been taken into account . I"t may also
be noted , that the results from the proposed action are expected to be
of benefit to other installations too .
x OJ N° C  139 , 13.6.1977
 ---pagebreak---   PART I : SITUATION AMD PPOSPFCTS REGARDING DECOMMISS IONIf'G OF NUCLEAR
              PWEP PLANTS
  1 . Introduction
        Decommissioning of nuclear plants means their . safe disposition after '
 retirement from service . Its ultimate objective is the unrestricted release
 of the plant site for other uses . One must however keen in mind that only a
 relatively small part of a nuclear power station < 15 to 20 % ) will give rise
 to problems associated with the presence of radioactive matte "*.
        Every nuclear power plant will some time arrive at the end of its use­
 ful life / but the reasons for retiring a plant from service may vary . A
 prototyoe plant may be decommissioned when it has achieved its objective ,
 or when the objective has been abandoned . Commercial olants will be retired
 from service when either economic or safe operation is no longer possible .
 Such ^ situation could also he brought about by an incident if rehabilitation
                                                                                <1
 of the plant proved too costly or impossible due to radiation .
        After a plant has been retired from service , the nuclear fuel , radio­
 active materials in process and radioactive waste oroduced in normal opera­
 tion should first be removed by routine operations . As regards the further
procedure , three stages of decommissioning have been defined in the frame of
                                                                              /
 the International Atorric Energy Agency , namely      :
 St            comm_i 3 s_i cn_2 nQ
        The pl?nt is practically kent intact . The mechanical opening systems
        ( valves , nluos , etc .) of the first contamination barrier are perma-
- .     nently blocked and sealod . .The plant is under surveillance and ins­
        pections are carried out to check that it remains in good condition .
S£33£_2_!.2££!I!E25.§.2£D2n2
        The primary contamination barrier is reduced to minimum size and
            .                       i         ■'
        sealed , removing all parts which can be easily dismantled . The biolo­
        gical shield " ( e.g. concrete)    is extended so that it - completely
        surrounds the "barrier . .                  '         , ' :  .
 ---pagebreak---                                        - 4 -
      After decontamination to acceptable levels the containment building
       can be removed . The other parts of the plant ( buildings or equipment )
       can be dismantled or converted for new purposes . Surveillance around
      the barrier is necessary but can be relaxed es compared with Stage 1 .
                   *
      External inspection of the sealed part should be performed .
St_aqe _3 %cjjmrnijsj^oniing
      All remaining parts- of the plant ; the activity of which remains signi­
      ficant despite decontamination procedures, are removed . The plant is
      then released without restrictions . No surveillance or inspection
      is necessary from the point of view of radiological protection .
      Stages 1 to 3 are , though not completely corresponding , sometimes
      also referred to as /'mothbatling ", "entombment " and "( complete ) remo*?
      vsl ", respectively .
2.    Experience with deocmmi ssioning
      About 20 nuclear power plants in the Western world - all of them in
the United States and in Europe - have already been retired from service .
Five of these plants are located in the Conmunity,' namely :
      - Marcoule G 1 and Chinon    1 , in France
      - Heissdampfreaktor ( HDR ) and Kernkraftwerk Niederaichbach, in Germany
      - Dounreay Fast Reactor , in the United Kingdom.
      Decommissioning of most retired plants has not yet proceeded beyond
Stage I. Five plants have been decommissioned further , namely : HNPF , BONUS ,
ERR ( all in the USA ), CNL ( Switzerland ) and HDR ( Germany ).
      These decommi ssioning operations have complied with the regulations
for protection of the personnel- and the general public ; no particular in­
cident has been reported . They have yielded valuable experience as regards
decommissioning techniques and cost . However , this experience is not di­
rectly applicable to future decommissioning of nuclear power plants , and
of large commercial plants in particular , for the following reasons :
 ---pagebreak---        - the reactors were of one-off types, not used in commercial plants ;
       - tb'sy were relatively snail ;              ■       ' -   .
       - they had been operated for relatively short periods , and
          consequently radioactivity inventories were small ;
       Relevant experience has also been obtained from the decommissioning
 of major nuclear power plant components . Within the Community the '
 dismantling and cutting cf the thermal shields of the Trino Vercellese and
  the Chooz pressurized water reactors deserve particular mention in this respect .
      Decommi ssoning operations at research reactors and fuel cycle plants
 have also yielded experience which is of considerable value in the de­
 commissioning of nuclear power plants . Major operations performed in the
 member countries are :
      - total disnantling of the LeBouchet uranium fabrication plant
         C France )
      - total disnantling of a small prototype reprocessing plant at
         Fontenay- aux- Rcses ( Franco )
      - extensive decontamination operations at reprocessing plants at
         Mo I ( Belgium ), Dounresy ( UK ) and Trisaia ( Italy ).
      The available experience has been taken into account and carefully
 extrapolated in the studies of decommissioning of commercial plants ,     >
 which forrc the subject of Chapter 3*
 3.   Decommissioning studies
 3. 1 Light water reactors
      Light water reactors are of particular interest since they constitute
the major part of the nuclear generating capacity installed and under con­
 struction and because their proportion is forecast to increase over the
 coming decades . The decommissioning problems posed by pressurized water
 ---pagebreak---  reactors , which account for about 80 X of the Light water reactors in the
 Community and are takan as a reference here *, and by boiling water reac- ^
 tors do not differ fundamentally .
 Radioactivity
    The radioactivity inventory after 40 years of operation and one year
after shutdown is illustrated by the following data ( orders of magnitude ):
                                                              !' "
                                                    Weight        Activity
    Components ( material )                           t               Ci
 Reactor vessel internals ( stainless stetl )        1S0            '1U7
 Reactor vessel ( mild steel , cladding
                   stainless steel )                 580          5000
 Biological shield ( concrete , reinforcement
                       mild steel )                  430           700 v
              -         .                 i
                      ■)            ' •
 Systems contaminated only ( stainless steel )      6000'         3000
      The total activity inventory is lower by a factor cf ebout 1000 than
that V.    shortly after shutdown , this being due to the removal of fuel and
to the decay of short-lived nuclides. The bulk of this activity is re­
presented by a few reactor internals surrounding the core , with maximum
 specific activities of about 2 Ci / g .
      More important than these total activities are thdse of specific
 nuclides . There "are no significant amounts of the rcdiotoxic long-lived
                   ■i
 alpha emitters . Cobalt-60, because of its penetrating type of radiation,
 determines the exposure of personnel during decommissioning works and there
 fore ■ dictates the degree of shielding and remote operation required .
   The capacity of the reference plant is about 1200 MWe
 ---pagebreak---  Its decay    - its half-life being five years -      is the principal reason
 for delaying dismantling . Because of their long and very lone half-lives*
                                                  «
 nick^l-63 end r. icfcel-59 will h?ve a major influence on the choice of thv.
 final storage or disposal mode of steel components .
 Even though ni ckel-59 . and ni eke 1-63 may be present in significant quanti­
 ties for long periods , their potential biological hczard must be kept 1h
 perspective , considering the low level' and penetration capability of the
 radiation .
 Deconrmssioninq alternatives
        According to the studies it would be feasible but not optiral with
 respect to both health protection and costs^ to undertake complete dis­
 mantling and removal of the plants immediately after shutdown (" Prompt
 Stage 3"). On the other hand it would not^je practical to delay Stage 3 '
 until it was reached merely by the decay or the radionuclides . The
principal reasons for proceeding to Stage 3 appear to be the denradation
 of contamination brrrisrs > the surveillance costs during lower Sta&os anc ,
 possibly , national licensing requirements . The economic value of the
 land area recovered would be comparatively insignificant , ft nuclear site
may be of high value to the utility , but it would generally be possible
to build a new plant without removing the reactor building of the old           ,
one , since this building usually occupies only a small part of the site
 area .
                                                                    I
                                                                         4
        The decision to start on Stage 2 , as against Stage 1 , will depend
                                                    » i        J
to a large extent on the national licensing requirements . Recovery of
site area and esthetic reasons will not be an incentive , since underground
* Ni eke 1-65 : half- life of 90 years
. , M ckel-59 : half-life of £0,000 years
 ---pagebreak---                                                      - 8 -
   entor.Ur. ent appears impractical and substantial overground structures or
   even the whoU containment building , as envisaged in the United States ,"*
   will remain in place during Stage 2 .
                                                                         i               •
                                                                     • ■   ι :       .1
  J>e cornrd s_s ^njn£ co^sts                                                                   -
            Decommissioning costs accrue from decommissioning works at the plant ,
   from management and disposal of the wastes produced and, until Stage 3 is
  reached ,, from surveillance and maintenance of the plant . The mode of waste
  disposal is decisive of disposal costs and may also condition preceding
  operations and their costs . As the disposal mode is unknown cs yet , cost
  estimates have been based on assumed disposal modes and therefore are to
  a certain degree hypothetical . The following costs have been estimated re­
  cently in an American ( A ) and in a European < E ) studyat<in millions of
                                  • i
  1975 US », including removal of non-nuclear buildings ):
    '                                   '• '  .. . »         "• .. »
                                                                                    Study
            Decomi ssioning alternatives                                     '   A ' I     E
                                                                                      i
        , Prompt Stage 3                                                       27       79
           ' ■ •              ' (.\) ' ^         ■'
            Delayed Stage 3 v '- after Stage 1                                 23       64
                                    - after Stage 2                            25
       ( l ) Delay after shutdown : 108 years for A , AO years for E ; no ,,
               permanent security force during Stage 1 .
         ;' i     * % » •                              ' . •                    *            i,
            These costs range from about 4 to 13 % of plant capital costs In
, 1975. The difference between ths two estimates is to a large extant due'
  to the different wasffe disposal modes assuried, which are virtually opposite
  extremes as regards their inpact on costs . Study A is based on the finan­
  cial and technical conditions In force at commercial surface burial grounds
  but assumes the radioactivity limit to be strongly increased, ffhis certainly
 unrealistic assunption affects only the Prompt Stage 3 alternative ). Stiidy E
  is based on the conditions in force at an experimental' geological disposal
  facility, which require fn paeticular that all wastes are packed in small
 units .                              *
              y      Alp/NÏSP-009SR; study E: EUR 5728 d '
 ---pagebreak---                                       - 9 -
       Moreover , these costs are not discounted . However , comparison of costs
 arising at different points in time Inevitably involves discounting and
not discounting amounts merely to using a discount rate of zero . Discount
rates may be chosen on the basis of anticipated      interest and inflation
rates, of utility practices or of macro-economic considerations . Thus no
 specific rate can be proposed here , but the preponderant influence of dis­
counting , even with rates as . low as 1 % per year , has to be stressed . This
 influence tends to reduce the-, ratio of decornmssionir.g to capital costs, the
reduction being the- greater the longer Stage 3 is delayed and permits
sinking-funds to grow .
      The current costs during Stages 1 and 2 would be lower than      assumed
in the studies if the decommissioned plant shared the site with at least
one operating plant , which will be the rcost frequent cass in the foresee­
able future . On the other hand , a permanent security force, which might be
required for o single plant in Stage 1 ,    would result in an additional
cost . Constant annual maintenance costs ., excluding major works , have been
assumed but it is recognized that this may be unrealistic , in particular
for longer periods of delay . Maintenance costs are expected to increase
at long term, as excessive degradation of the plant is to be avoided , and
this might be a reason to proceed to Stcge 3 earlier . This aspect requires
further stuc'y .
0.cci£at îonal e xp o sure
      Occipational radietion exposure is seen to be the main safety concern
in decommission ing . Not only have the individual dose limits to be complied
with , but also the total radiation dose should be kept within acceptable
limits . Besides the use of shielding , remote operation and enclosures with
controlled ventilation , careful planning of the successive decommissioning
pperations is essential . Total occipational doses estimated in the already
mentioned study A , are 630 man-rem for Prompt Stage 3 and about 450 man-rem
 ---pagebreak---                                        10 -
 for Stege 1 or 2 and Delayed Stage 3 < 108 years after shutdown ). It has to
be mentioned' that substantially higher doses have been estimated by others .
3.2 . G;;s-cooled reactors .
      Gss graphite reactors will probably form the bulk of the nuclear power
plants which will become redundant by the end of this century .
                                                                     r
      Important differences in the radioactivity inventory compared with         \
light water reactors are the lower specific activities but larger volumes ,
the preponderance of mild steel over stainless steel and the large amounts
of graphite , which , however , are present as easily manageable pieces . The
following amounts of materials have been       indicated for the pressure vessel
and the pressure vessel internals . of a typical commercial Magnox reactor
( capacity : 250 Mwe ): 2500 tpnnes of mild steel , 100 tonnes of stainless
steel and 2500 tonnes of graphite . As regards the biological shield con­
crete , only its inner layer is activated . The thickness of this layer will
be about 1.5rn two years after shutdown and will decrease with time as the
result of radioactive decay . Nevertheless this concrete would present the
major disposal problem in terms of moss. Heat exchangers would by their
size ond by the tube surface area and geometry pose a major decontamination
problem .                  -    .
      The study of the decommissioning of a representative commercial Magnox
reactor is still in progress , but a detailed technical study on the Wind-
scale Advanced Gas-cooled Reactor - ( W. A. G.R. ), has been completed and it is
likely that its conclusions will in principle be applicable also to Magnox
reactors . The W.A.G.R. study is based in one case on a progressive procedure ,
considering Sta^e 1 as an interim phase . Stage 2 as a storage situationof
unspecified duration and Stage 3 as the ideal ultimate objective * The al­
ternative case is the progression from reactor closure to Stage 3 as a con­
tinuing operation . In particular , it is concluded that a satisfactory long
 ---pagebreak---  term Stage 2     condition can be established and that there is no technical
 obstacle to proceeding directly to a Stage 3 condition . The conception of
  Stage 2 differs from that envisaged in the United States for pressurized
  water reactors in the dismantling of the containment building and the heat
 exchangers , resulting in a considerable reduction of the occupied area and
 the visual impact . For commercial steel pressure vessel Magnox reactors ,
  irrespective of output capacity , the remaining structures would be cylinders
 with a diameter of about 30 metres and a -height above ground of 18-30 metres
       A de-tailed decommissioning study has been performed on Chinon 1 , a
 70 MWe gas graphite prototype plant > which was retired from service for eco­
 nomic reasons in 1973 , after having operated for 10 years with an average
 load factor of about 50 % . From activity measurements carried out on samples
 the activity of the graphite moderator ( 1050 tonnes ) at the end of 1975
 has been estimated as 3000 Ci of cobalt-60, 1200 Ci of tritium , 300 Ci of
 carbon-14 and 0.5 Ci of plutonium-239 and - 24G . Measurements inside the fuel
 channels have shown dose rates in the order of 10 rem/ h from the graphite
 reaching a maximum of 400 rem/ h near the core support steel plate . The ac­
 tivated steel components amount to about 1500 tonnes . First measurements
indicated that the biological shield concrete is not activated .
       The Chihon 1 study compares the direct approach of Stages 1 , 2 and J.
 Stage 2 was    assumed to embrace the reactor vessel and the heat exchangers
 within a concrete enclosure; and to involve dismantling    other contaminated
 systems , storing the parts within sealed premises in the containment sphere .
 The conclusion was that this condition would not be safer than Stage 1 and
 that it would complicate proceeding to btage 3 subsequent ly . Stage 3 was
 studied in detail , including the conceptual design of the required remotely
 operated equipment .
       On the basis of this study it was decided to convert the plant into a
 nuclear museum . This conception , which in particular allows the public
 ---pagebreak---                                       - 12 -
access to part of the containment sphere , Is planned to be achieved in 1978
or 1979. The option to proceed to Stage 3 , 3C years later - remains open .
3*3 . Decommi ssionir.g subsequent to a maior accident
      The studies considered in the foregoing sections < 3.1 , 3.2 ) are based
on plants which are . retired from service in a normal condition . Major plant
accidents, resulting in a wide spread of heavy contamination within the con­
tainment building , would pose special decommissioning problems and even
complicate routine operations , such as the discharge and the removal of the .
fuel . Whereas such accidents are taken into account in the plant design ,
their impact on decommissioning is not well known . First studies , which are
in progress , have shown the complex nature of this problem.                 '
4.    Decommissioning techniques .
4.1 . Decontamination           •
      The purpose of decontamination in decommissioning will in most cases
be to facilitate the dismantling and further treatment of components, by
reduction of the radiation level and removal of loose contamination . An­
other possible objective is " complete decontamination ", i.e. decontamina­
tion to a level below the limit for unrestricted release of material , in or
der.to reduce the volume of radioactive waste . The benefits of decontamina­
tion have to be weighed against operational risks , ari sings of consequen­
tial waste and costs . Thus different opinions exist as to what is a reason­
able decontamination effort . This question merits further study , but it
cannot be answered without a better knowledge of the technical options .
      The only proven decontamination techniques are those which are cur­
rently used in operating reactors and which mcy be classified as follows :
              %
      ~                           applied within closed systems of the plant
        and using chemical agents ;
 ---pagebreak---                                          - 13 -
       - JW2®£sion            nation ^ applied to dismantled component and
         using chemical agents , generally . combined with mechanical means
         such as brushing or ultrasonic waves ;           „
      "                          applied to systems locally through openings ,
         or to dismantled components in special dells , or even to the sur­
         faces of premises , using jets of vapour or liquid or of a mixture
         of liquid and grinding particles .
      Experience with these techniques is substantial but difficult to inter­
pret . Achieved decontamination factors vary over a wide range , depending
 on the particular conditions in a way which is not yet well understood .
                                                           \
      These proven tecnmques neve been developed for application to compo­
nents to be serviced or repaired , that is to say,      subject to the condition
of preserving component integrity . Whereas these techniques are also user
 fully employed in dc-corcmi ssioning , more aggressive methods , resulting in
more effective decontamination , would be desirable . These could be variants
    the proven techniques , i^e ., system    and immersion decontamination using
mors aggressive chemical agents- or jet decontamination using higher pres- 7
 sure or more abrasive grinding particles , etc ., but also basically new tech­
niques .                                                                ,
      System decontamination offers the advantage of preceding the opening
up and dismantling of the system , thus reducing personnel exposure . It reaches
a large surface at a time , but cannot be applied selectively to local peaks
of contamination . It is atso less effective in crevices and dead end ^ of a
system , where contamination often concentrates . Consequently , system decon­
tamination will as a general rule not result in complete decontamination .
The large    volume of certain systems, such cs the primary cob ling circuit ,
and the need for several decontamination and flushing steps give jise to
very large quantities of radioactive liquid, which may pose problems of in-,
terim storage and of treatment ." Moreover , differential attack on the various
materials of a system and the spread of contamination to initially clean
 ---pagebreak---                                                - 14, -
   regions are aspects which have to bo considered .
          Immersion decontamination can use existing equipment for small compo­
   nents , but the corrosive attack of thetanksmu3t.be considered , if nore
   aggressive chemical reagents are employed . Major components would pose
  problems of space, equipment end of volume of liquid produced .
                                                     i       /
          The folowing,n»w techniques have been proposed :
  - Decontamination by cher.ical agents applied as a surface layer , i.e. ,
      pastes and fcolten salts . Laboratory experiments have shown promising
      results, indicating hich efficiency and low volurie of consequential
      waste .                                          -
  - Electrolytical decontamination , using similar processes to the electro­
      polishing known in the non-nuclear industry .                          :
  - Decontamination by explosive methods . Preliminary experiments have de­
      monstrated that the oxide film , which incorporates the contamination
      of steel components , can be spalled off from the base rcetnl . With this
.     technique the volume of consequential waste would L>c very small .
  4.2 . Di smant lina
_D "! s mant ijn_% _cf sjte e l coripcn en t s
          The reactor vessel and the reactor vessel internals pose the most
  difficult dismantling problems , oecause of the high radiation, level , remote
  operation is required . The more active vessel internals of light water re­
  actors should preferably be cut under water , the water providing shielding
    and reducing aerosol production . Certain components have large wall-thick-
                     M
  nesses, ranging up to 500 rm ( reactor vessel flange of pressurised water
  reactors ).                                                                   '
         Mechanical;- techniques such as mill cutting and sawing can be carried
  out under water , but they « re time-consuming and require heavy . supports .
  With thermal techniques special attention has to be paid to the confinement
  of aerosols . Plasma arc cutting , which can be carried out under water ,
 ---pagebreak---                                       - 15 -
 appears attractive;. At the present time it can be enployed'to uall-tmck-
 nesses up tc about 170 mm ,, but has development potential up to 500 mm.
Another promising technique is oxy propane cutting . Electro-melt separation
 can be employed for large wal l~thicknesses but has the disadvantage of strong
                                                                   *
 aérosol production »
      Concerning the dismantling of pipework , the removal of thermal insula­
tion may pose special problems . Moreover , no' adequate technique is currently
available for cutting large-diameter large wall-thickness pipework , such as
that employed in the primary circuit of pressurized water reactors . Cutting
of pipes by explosive methods constitutes a new technique which should be
developed . Experiments carried out cn pipes of moderate size have shown that
it is possible with explosive methods to disconnect a pipe and to close its
ends in a single operation .
Dismantling of concrete structures
    1          ~~
      The concrete structure which usually poses the- main dismantling problem
is the biological shielding . Special problems due to stored energy may arise
with certain prestressed concrete pressure vessels which are employed in
some gas graphite reactors .                  '
      There are several proven techniques for dismantling concrete . In the
explosive technique charges placed in holes loosen up the whole structure
or break it up into layers . This 'method 'is relatively expensive and time-
consuming . In the thermal lance technique , : holes closely put in a line are
burnt into the concrete by a jet of oxygen , to which iron is supplied as
fuel . Dismantling by this method is relatively quick , but is accompanied
by intensive smoke formation . Additionally sawing , hydraulic or pneumatic
wedges, or high pressure water jets may be used .
      These proyen techniques will require further development and adaptation ,
to perform the more difficult tasks of future dismantling operations .
                                                       «
 ---pagebreak---                                         16 -
 Other techniques to be considered arc hydraulic cracking , oxy-arc cutting
  and successive boring and cracking by freezing *
 4.3 . Equipment for remote operations       - • .
       Remote operations such as dismantling , decontamination , conditioning
 and packing require special equipment to hold and move tools , measuring
 instruments, telecameras and the parts to be treated . Such equipment may
 be designed ad hoc for a special situation or for multiple- use . It belongs
 to a technology which is already employed in reactors and hot cells but has
 to be scaled up and further developed for decommi ssioning operations .
 4.4. Management and storage of wastes from decommi ssioning
       Conditioning , packaging ; transport and storage or disposal constitute,
 a series of op';re* ions which have to be optimized as a whole, taking as a
 basis the specific characteristics of the type of waste considered . The
 process of evolving the optimal management concepts for wastes from de­
 commissioning is still in a preliminary phase .
       The waste arising from dismantling of major activated components is
 characterized by the large initial dimensions and by' the fact that the bulk
 of radioactivity is incorporated in the base metal . One leading idea for the
 management of this waste 'would be to limit the cutting to the extent ne­
 cessary for transport , thus minimizing work under radiation and the spread
 of radioactive material . Accordingly , large transport containers should be
 developed for certain components and the storage facilities should be de­
 signed for acceptance of large units .            , 1
       For contaminated pipework a treatment reducing the storage volume ap­
 pears desirable . Press compaction , cryogenic cracking and smelting have
been proposed as techniques . The feasibility of such a treatment should be
 studied, including the question , whether the operation should be carried
 out on the site of the nuclear 'power plant or in a central facility .
 ---pagebreak---        - As regards redioactfve concrete', wsste , it would-'!*?- desirable to haW
 an inexpensive method' for the long tern • Immobilization of' the radior.utli Jes .
         Controlled burning has been proposed for the graphite arising in the
decommissioning of gas graphite reactors and advanced gas cooled reactors .
 In order to decide whether this method is appropriate / it is. necessary to
 consider not only its local radiological impact , but also the long-tern
 consequences , through the contribution to the worldwide background radia-.
 ticn /of " releasing to the atmosphere 'considerable amounts of the long-lived
 radionuclide carbon-14.                                                               ^ ,
        Consequential wastes nced.no special consideration here , since they
 can be managed appropriately by the methods which are currently employed
 for wastes arising at operating nuclear power' plants .                         v
        The following methods have been envisaged by certain countries for fi­
   nal storage or disposal of different types' of waste arising from decommissioning
  surface storage , storage in a former mine , disposal in drilled deep holes and sea
  dumping .
   5 . - Estimation of the quantities of radioscti vo wastes from ,
         deconni ssioning
   5.1 . General considerations '
         The following information is required to estimate the arisings of :
  radioactive wastes from the decommissioning of nuclear power plants :
         a ) schedule of retirement of the plants from service ;
         b ) inventory of the radioactive components , systems and structures
             of the plants and estimate of associated radionuclides ;
         c ) schedule of de commissioning works and, in particular of
             dismant ling ;
         d ) extent to which the original volume and radioactivity of t lie
                                                                                     »
             materials concerned are changed by decontamination , conditioning ,
             overpacking , etc ., and production of consequential wastes .
 ---pagebreak---                                        - ia -
        • The result of a first tentative approach to item a ) is given in
  point 5.2 . kotow .
           As regards item b ), because of the variety of existing nuclear power
  stations , most of them are to be considered individually . Some information
. is already available , but a great deal of work is still needed before a com­
  plete survey of radioactivity inventories can be established .
           For the evaluation of items, c ) and d ?, reference strategies have to
  be evolved ; this is to be considered as a long-term task .
  5.2 .    Retirement of nuclear power plants from service         ,
         . It 7 s premature to make firm estimates on the schedule of retirement
  of nuclear power plants from service , since the operational life is uncer­
  tain within a wide range . The following table illustrates a possible pattern
     1                                       5           ,                               1
  It takes into account the . plants which are currently in operation or under
  construction in the Community and is based . on an assutned operational - life of
  30 years , except for certain prototype plants, for which specific shorter.,
  periods have been adopted .
                             1 1
                                                Reactors retired over       period :
           Reactor type
                                               1981-1990   1V91-2C00         2001-2010
                                                                       _j
                                                         I
                                                         I
  Gas graphite and advanced .
 gas-cooled reactors                               11 r       20     '          14
  Light water reactors ,               .   I     , 3 .         ■'7 •
  Other types     1                                 2.           2         "     4
                                                                                     - -   »
                                                                                »        ]
                                          1                              i
           Total                          {       '16 j                  i
 ---pagebreak---                                       - 19 -
 6.      Guiding princinles
        Guiding principles concerning decommissioning con be formulated only
 in s very general way as regards the immediate future and can only be deve­
 loped in greater detail as a long-term process , Moreover , consideration at
Community level must take into account the different conditions prevailing
 in the Member States , such as reactor types employed , territorial conditions
and urgency of decommissioning .
        Community efforts in this field should not duplicate or hamper the
measures undertaken on a world scale by the International Atomic Energy
Agency , but it should be recognized , that the Community could bring its point
of view to bear with greater weight in this wider framework if it had clear
conceptions substantiated by appropriate studies .                      '
                                              /
6. 1 .  Guiding principles in the design anr' operation of nuclear power
        plants with a view to sinpli fying dace rami ssioning
        Studies have indicated , that as regards decommissioning modern nuclear
                           !              \       •                       , •
power plants pose no fundamental difficulties which would require basic
changes in design . . Improvements with a view to facilitating decommissioning
have been proposed and appear possible , concerning features such as the ar­
rangement , design an^ materials 'of plant ccr.ipon&nts .
        Features which are increasingly introduced into modern nuclear power
plants, in order to facilitate maintenance and repair during the operation
period , will ultimately also facilitate decommissioning .
6.2 .   Guiding principles in the decommissioning of nuclear power plants
        Decommissioning operations are subject to general nuclear regulations ,
but no specific detailed guidelines for decommissioning exist in the iiember
States as yet . For instance , permissible radiation limits for the- personnel
and the oeneral public are laid down in the general regulations , but there
 ---pagebreak---                                       20 -
are no criteria for the unrestricted release of equipment and sites . Such
matters have boon settled in past decommissioning operations on a case-by-
case basis . In -this context mention shoulc be mcde of the present efforts
by the International Atomic Energy Agency .
 ---pagebreak---                            PART II : PROGRAMME PROPOSAL
 1 . Underlying considerations •
     iiajor advances in concepts and techniques will be required to
decommission the nuclear power plants in the best way, with respect to
both health protection and economy . The solutions adopted may influence
the development of nuclear power through their economic impact and through
the reception they meet with among the public .
     As the number of plants to be decommissioned will increase at only a
slow pace during the coming decades and , moreover , dismantling and removal
of the plants , if necessary, may be postpones for considerable periods
after their withdrawal from service , it might be conctuded that no sub- •
stantial effort to solve the problems of decommissioning is called for at
the present time . This conclusion would , however , be a dangerous mistake ,
for the following reasons : .
- Features which facilitate decommissioning should be developed and
    increasingly introduced in the design of new plants .
- The task of identifying , developing and . irp lamenting the optimum solutions
    will take a long time . The technical developments will be conditioned by
    the legal and administrative framework , and in particular by the criteria
    for release or for acceptance at central depositories of the- wastes .
    The industry therefore need3 guidance on these questions at an early stege .
    On the other hand , better knowledge of the possible technical options is
    needed in order to evolve the legal and admini strative framework . ■
- Uetter knowledge of decommissioning costs will enable utilities to
    accumulate provisions for decommissioning in accordance with national
    requirements .
- Decommissioning operations may be urgently required in particular
    situations , for instance after an incident .
 ---pagebreak---                                          - 22 -
- It is becoming * increasingly important , in order to secure public
    acceptance of new plants , to have elaborated and weLl-founded concepts
   for the " back ends" of nuclear energy generation , even if definitive
   solutions are not yet really needed . One could go so far as to consider
   dismantling and removing a olant earlier than would otherwise be appro­
   priate , in order to demonstrate the feasibility of a decommissioning
   concept .
       The Commission therefore holds the view that in addition to the    research acti­
   vities of the Joint Research Centre an indirect action joining forces at Community
   level , in the form of exchanging information and sharing work , could save money
and time . Moreover , a Community approach could favourable influence accep­
tance by the public of the solutions adopted by the Member States , whatever
their differences to suit the orrticular features of the nuclear power
plants and other national conditions . Work already going on in a member
country could be pursued under the common programme , if the country
 agrees ?ncj -jf the work is of interest to the Community . The public service
nature of this work and the secondary importance of competing commercial
interests at stake will facilitate a Community approach .
2 . General features of the proposed programme
       The programme , which is proposed to cover a period of five years be­
ginning 1 July 1978 , must be regarded as the first stage of a longer-term
effort . It consists of a series of studies and experimental projects aimed
at evolving the most appropriate solutions , with respect to both health
protection and economy, for the decommissioning of nuclear power plants .
       These studies and projects will be financed largely by the Commission
and coordinated by it with the help of an Advisory Committee on Programme
Management comprising representatives of the Member States and Commission
officials.' This committee will have to meet as soon as this programme is
                            «                                  ·
approved . The work will bo carried out by qualified public or private
agencies in the Member States .      V                       - •           v
 ---pagebreak---                                      - ?3 -
       In order to avoid duplication , the programme takes into account the :
relevant activities of the international organisations . On the other hand ,
the scope of the programme has been strictly delimited to prelude ovorlan-
pinn with the Community programme on radioactive waste management and
storage . In particular , it takes into account activities dealing with
the decontamination of reactor components being carried out at JPC
                                                                               ««•
within the frame of their multiannual programme 1977-1980 and will be
closely coordinated with these activities .
                                                                            \
      The programme may be submitted for review at the end of two years , to
reorientate or amplify.it , whore necessary , in the light of the results
obtained .     -
3 . research and development actions
      The proposed actions , which arc described in annex II , concern 'the
following subjects :                                        '           ,
Action      1 : Long tern integrity of buildings and systems .
Action * '° 2 : Decontamination for decommissioning purposes .
Action H° 3 : Dismantling techniques .
Action N° 4 : Treatment of specific waste materials : steel , concrete and
                 graohite .
Action N° 5 : Large transport containers for radioactive waste orocluced
                 in the dismantling of nuclear power olants .
Action N° 6 : Estimation of the quantities of radioactive wastes arising
                 from decommissioning of nuclear power plants in the Community .
Action *!0 7 : Influence of nuclear powef plant design features on
                 decommissioning .
      These proposals have been formulated on the basis of the analysis of
earlier studies and experience , which is contained in Part I of this
document .
                                                                      ι
 ---pagebreak---                                          - 24
        Tn addition to these proposals it is envisaged that the Community
participates in a Large-scale operation , carried out in the context of
decommissioning of a nuclear power plant or of a major component of such a
nlant and involving the demonstration of new techniques or the extension
of proven techniques to a wirier range of conditions , such as size and
radiation level of components . As no SDecific action can be proposed at
present , the subject is mentioned here only for the record , but a proposal
should , if possible , be submitted for the revision of the programme .
Th?> Community 's financial contribution would depend on the general
interest jof the information - expected to be obtained from the proposed
action .
    Ir' - nt1'fi cation of guiding principles    .
    This activity relates to :
- Cuidinq principles in the design , and operation of nuclear power plants
  with a view to simplifying their subsequent decommissioning .
- Guiding principles in the decommissioning of nuclear power plants .
          Guiding principles need to be progressively evolved in order
 to plan the research and development actions efficiently ; conversely ,
 the results of the actions may influence the shaping of the guiding
 principles . In view of this interdependence the programme includes
 provision for the progressive evolvement of guiding principles .
          The intention is that rough material for guiding principles
 prepared in the Member States should be assembled and analysed , and
 an assessment then made of the scope for approximation and joint
 development .        At a later stage of the programme it will be endeavoured
 to frame proposals for c«amon guiding principles .
          The Commission should also have a limited "budget for this action so
that it could have the necessary analyses performed under study contracts .
 ---pagebreak---  5 . Breakdown of proposed funding
     Costs over five years in millions cf Furonean units cf account ( EUA ) :
    Item                                                          Costs
    Contribution to research and development actions :
                                                                        /
              Action      1                       •                0.3
              Action N° ?                                \         1-.4
              Action i*:0 3                                        1.1
              Action * !° 4                                        0.6 •
              Action / ;° 5                                        0.2
              Action f'° 6                    .                    0.4
              Action N° 7                                       .  0.6
            • Subtotal rctions 1 to 7                              4.6
    Identification rf guidino princinlaes                          0.2
    Staff *                                                        1.51
    Meetings .                                                     0.27
    Total                                                          6.38
* This programme will require a staff of 5 ( 2A + 2B + 1C )
 ---pagebreak---                                     ANNEX  I
                       SUPPORTING INFORMATION TO PART I
to 2 .      Experience with decommissioning
            The nuclear power plants which have already been retired from
 service are listed in Table 1 . Further information on nuclear power plants
which have been decommissioned beyond, Stage 1 is given in Table - 2 .
to 3.1 .   Light water reactors     .
            Table 3 gives information concerning radionuclides of significance
as regards activation of steels . Table 4 gives sipplementary information
concerning the cost data . ' v                     ,
to 5.2 .    Retirement of nuclear power plants from service
           The nuclear power plants taken into account in the summary table
under point 5.2 . of Part I are listed in Table 5 .
to 6.1 .   Guiding principles in the design and operation of nuclear power
           plants 'with a view to simplifying decommissioning
           The following design features have been recommended in the frame
of the International Atomic Energy Agency ( document IAEA-179 ):
Arrangement of compenents ana structures
       ,   Components and structures should be so arranged tnats
- The site can utlimately be developed to its maximum potential despite the
   eventual existence of decommissioned structures ;
                        ,
- There is sufficient space around them to permit access with transporting
   equipment , shielding or tools ;
- Suitable cells or cabins can be erected around them to restrict the dis-
   perison of radioactive material during their dismantling and , if neces-
   scry , to permit operations at s lower pressure than in the surrounding
   atmosphere ;
- They tan be removed in one piece through adjoining roon/ s or the roof ,-
   using -ilsnt or external lifting devicsr if "oc' "    .
 ---pagebreak---                                             - 2 -
   Construction of £o_np ^ en.is_ "Jici_st r_uc t ur es
               Components and structures should be so designed that :
 - The contaminated or activated components can be cut off ;
    Example } Detachable concrete layers on the biological shield ;
 ■* Their activation level is reduced ;
    Example : Distance between the steel reinforcement of the concrete and
                      ι
    the neutron flux zone ;
 - The components and structures can be broken down into parts which arc
    relatively light , small and suitably shaped fcr transportation ;
 - Suitable passages and openings are provided for removing them from the
    containment or reactor building ;
- As many components as possible are replaceable ;
- ilateriels are selected to reduce the formation of nuclides with a long
    half-life .                                         .
J)e£ont£mi na1 i o_n provasi on_s
               To simplify the decontamination of components , pipe systems and
rooms , the following provisions should be made ;
- The spreading of active corrosion products or deposits during operation
    or deccmmi ssioning should be limited by for example , the incorporation of
    drain points , devices for flushing the pipinj systems and traps in pipe
    systems ;
- Facilities for the decontamination of components and rooms , including
    means of introducing and draining decontamination solution .
Adjnijii^t£_a^iji/e_mea_SLire_s
               A reliable documentation system should be established and used
to record all changes in the design and materials of the plant during its
operation .
 ---pagebreak---             Table 1 .       Nuclear oower plants retired from service
                                      Plant
                                                         *      Capacity       Opérât ing
   . Country                                        Type           MWa   !       period
■ -          –
                          J
     France                  tiarcoule G1           GGR             4        1956 r 19 66
         II
                             Chinon 1               GGR            70        1963 * 1973
     Germany                 HDR Grosswelzheiin     BWH            25     , 1970 - 1972
         II
                             KKN Niüderaichbach     iiWR          100        1974 - 1974
     United
                             DFR Dounreay         . FSR            15        1963 - 1977
   - Kingdoni                                              ' I
                1     I
     Switzerland             CNL Lucens,            HWR             8        196ö - 1969
     USA                     Vallecitos ¿fVEíjR     BWK             5        1957 - 1963 '
                             Elk River Reactor      BWR            22        1964 - 1968
      II
                             Hallam HNPF            SGR            75        1962 - 1964 .
                             30NUS                  BUR            16.5      1962 - 1968     '
       M
                             Vallecitos VBWR        OWR            10        1957 - 1963
                        I
                        i    Santa Susana           SGR             7.5      1958 - 1966
                             Piqua OMR              OMR            11.4      1963 - 1966
                             Carolinas CVTR         PWR            17     ' 1963 - 1967
                             Enrico Férmi           FÜR            61        1966 - 1971
                             Pathfinder             BW *      !    62        1962 - 1967
                             Saxton-.               PWR       !     4.2      1962 - 1972
                             Pesch üottom           MIR       ;    40      . 1966 - 1974   .
         BWR = boiling water reactor
         GGR s gas graphite reactor
         FBR s fast breeder reactor
         HTR « high temperature reactor
         HWR = heavy water reactor
         OMR = organic moderated reactor
         PWR * pressurized water reactor
         SGR = sodium graphite reactor
 ---pagebreak---                          • able 2 .   Plants which have been decommissioned beyond Stage 1
                          KNPF ( Hoi lam Nuclear   tiONUS ( Boiling Nu­ CNL ( Centrale        ERR ( Elk River
  Plant
                         Tower facility )          clear Superheater "nucléaire Lucens ) ,          Reactor )!
                                                   Reactor )
  Country                           USA      %                USA            Switzerland    j        USA
  Reactor type           graphite moderated        boil in .3 water      heavy water mode­    boiling water
                          sodium cooled            nuclear super­        rated , gas cooled   ( fossil super­
                                                   heating                                      heating )
  Caprcity ( fî'Jc )                 75                       16.5                8                    22
  Opercting period             1962-1964                  1962-1968          1966-1969            1964 " 1966
  Activity *         ^              3s105                                                           9000
  inventory ( Ci)'                                           50.000              5U0
  Ccr.c it ion
  reached                 Underground en­          Entombment in         Low active parts     Stage 3 completed
                          tombment ; top           biological shield ;  (total '1.5 Ci )      in 1974
                          planted and acces­       plant converted to    entombed ; other
                          sible without            museum                parts packed and
                          restriction                                    stored on site ;
                                                                         recctor caverns
                                                                         accessible withoui
                       i
                                                                         restriction
  Deccnmissioning
  cost                    4.2 millions US t        not available         not available        5.7 millions 'J3 £
1
  HNPF : at time of entombment closure ; others : at start of decommissioning
 ---pagebreak---                  Table 3 . Radionuclides of significance as regards activation of steels used
                           in light water reactors
                                                                  Cobalt-60      iJickel-ô3       Nickel - 59
  Radionuclide                               i  Iron-55
  Half-life, years                                   2.4            5.2               92           80,000
                                                                ■
  Radiation                                    garc^a , X-ray gamma , beta .      . beta         gamma , X-ray
                                                  Iron              Cobalt                  Nickel
  Mother element
  Content ,( % ) of mother element in :
I     - stainless steel ( 1 )                       70               traces                     10
                                                    97               traces                 0 . 5-0.8
      - carbon steel ( 2 )                 J
       (1)   Conponentj:: Reactor vessel internals , reactor vessel caldding
       (2)   Component :   Reactor vessel
 ---pagebreak---                                                      - 6 -
    Table 4 : Cost estimates for decommissioning of light water reactors
                 ( 1200 HWe plants ; operating time : 40 years )
                 Costs in millions of 1975 US8               (1)
  f
  I Study
          "                 '
                                          r                E                       F           Â;          i
     Référencé                                       EUR 5728                     I ' AIF / NESP-U09SR
     Reactor                                   '   PWR               BWR          | • PWR        ;|  BWR
 | Discounting                             | (2 ) |j no          (2 ) | no         1     n°      1L_rl
     Prompt Stage 5                         όδ . 4
                                                       78.Ç j    33.4    95.4           26.9     !   31.2
{ Delayed Stace 3 - after Stage 1
j - Stace 1                              !I 4.5         4.6       4.5     4.6            2.3     I    2.4
     - Interim costs ( 3 ) - case I          0.3        0.7       0.3     0.7            9.5          9.2
                               - case II ( 4 )          ( 4)      ( 4)'   ( 4)       ■  18.0         17.4
     - Stage 3 ( 5 )                        12.2       59.0      13.1    63.3 |I        11.0         11.7
I - Totnl                      - case I     17.0       64.3      17.9 i 68 . 6 IΓ 22 . δ ,           23.3
j                              - case I]j    ( 4)       (4)
                                                                  ( 4) | <^> j 51.3 |                31 * 5 |
I Delayed Starve 2 - nftcr Stag                                                            rn
     - Stage 2 '                         I                                               7.4          7.6     I
     - Interim costs ( 3 )                                 ( 4)           '
                                                                                       ' 6.3    j     6.0     i
     - Stage 3 ( 5 )                                                                    io.îs        12.2
i - Total                                                                              24.5 |        25.8 |
I                                                                                                           . I
     ( 1 ) Data from study E converted with the rato'1 DM = 0.4 US2
     ( 2 ) Discounted to shutdown date at an annual rate of 3.7 % ( This rate
            results from assumed annual rates of 12 )'<. for interest and of 8 %
            for inflrtion )                                                                >
     ( 3) Based on following 'annual costs of mainter'iance and surveillance :
             Study                                                              E .                A
             After Stage 1 - case I : no security force                     0.C19             C.0S8    .
                              - cr.se II : with security force               ( 4)             0.167
             After Stage 2                                                    ( 4)            0.058'
     ( 4 ) Alternative not considered
     ( 5 ) Delayed Stage 3 40 years ( study t )„ 1QS years ( study A , PWR )
            and 104 years ( study A , tJ'iR ) after shutdown ( The delay periods
            assumed in study A were estimated to permit manual - as opposed
            to remotely operated - dismantling ).
 ---pagebreak---                                                           - 7 -
                 Table 5 :   Nuclear power plants built or under construction
                              in the Europenn Community                              •                           .
 I        Plant                 ! Countn Type               I Caoccity              Start of
                                                                                                   I Year or                I
                                                                        I nJO       operation
                                                                                                    I assumed period
                                                                                                          of closure
 1 Marcou le 61        '                        I GGR                                  1956        I            1968
     H DR Gross'wclzhçim              »            fcHvR                   25          1970                     1972
     Chinon 1                         F            GGR         .           70           19A5                    1973
    KKN Niederaichbech               0             HUR                   100           1974                     1974
  I DFR Dounreny               [I UK             I FUR      L           _15       I    1963          l          1977        |
  I BR-3 hol                                     I PUR             ■       10          1966                              n
  I MZFR Karlsruhe                   D             HWR                     51          1966
     ( Otto Hahn                     0             PUR           .
                                                                                       1966
     El-4 Monts ci'Arré               F            HU'R                    70          1967                  1931-1990
     VAK Kahl                        »             BWR                     15          1961
    •JAGR Windscale                UK              AGR                     32          1963
    M ar cou le G2                    F            GGR                     40          1959
 I  Marcoule G3                      F      .      GGR                     40          1960
 l Calderhall                      JK              GGR                 4 X 50       1956-1959
 I   Chapolcrosj               |I UK ' I GGR                I          4 X 50 ||1 95 9- 'i960
 j Berkeley                        UK           I GGR                  2 X 13b         1961        n
 I  Bradwell                       UK              GGR                 2 X 150         1961
I   Latina                           1             GGR                  210            1964
I   Hunterston A                   UK              GGR                 2 X 150         1964
I Garigliano                         I  ■          DUR                  160            1964                                J
 I  Trino Vercellese                 I             PiVR                 257            1965
I   Chinon 2                        .F             GGR                  200            1965                  1991-2000
I Hinkley Point A                  •JK             GGR                 2 X 250         1965
I Trawnsfynydd                     UK              GGR                 2 X 250         1965
I Dungeness A                      UK              GGR                 2 X 275         1965
I Chinon 3                           F             GGR                  480            1966
I   Sizewell A                     UK     -        GGR                 2 X 290         1966
I KR3 Gundremmingen                  £>            PWR                  237            1966                              M
I. SENA Choo2                        F             PWR                  305            1967
]   AVR Jûlich                       0             HTR                     13          1967
I   Oldbury A                      UK           | GGR                  2 X 300 1967-1968
l   KUL L ingen                      0          S fcJWR                 182    '       196S             ■
]   KW0 Obrigheim
                                                                                                                       '
                                                   PWR                  328            1968
I   GKN Dodewaard                  NL           ! ÛWR                .    52           1968                -
I   SGHWR Uinfrith                 UK           i  HWR                    92.'         1968
    St Laurent 1                     F         I GGR                    480      |I    1969       |                  ;
j St Laurent 2                       F        1 ÏSGR I                  515            1971      I        ...      •
I Wylfei                        ;. UK              GGR                 2 X 590         1971        !
I   Ki\!K Karlsruhe .    . ...       0             SZR                     19          1972
    KUW Wurgossen                    t>            B'.v'R               640            1972
    KKS Stade                        D             PWR                  630            1972
    Bugey 1                          F             GGR                  540            1972  ' '       -    2001-2010
    Borssele                       NL              PWR                  450            1973
    Phénix
                                     F j FBR |                          233
                                                                                       1973      j                        !
 ---pagebreak---              Table 5 :  continued
                                                                                        Year or
           Plant
                              Country Type            Capacity
                                                        f'IWe
                                                                    Start of j
                                                                    operation
                                                                                        assumed period
                                                                                        of closure
                                                                                 l
 I Biblis A                        P       I PUR [       1146         1974      I
    Doel 1                         Β          PUR          390  1     1974
   Tihange 1                       Β          pwr          870        1975
 I PFR Dounreay              I UK             FBR ;I       230  ;     1975
                                                                                              ... - -
    Doel 2                         «3         PWR          390        1975            ■   •
   Biblis 0                    .   D          PWR       1240          1976    '
   GKN Neckarwestheim         ■    &          PWR          775        1976
   KK3 Brunsbùttel ,               D       luWR            770'       1976
   Hinley Pofnt S                 UK      ; AGR       2 X 625       1976-1977
   Hunterston B                   uk     : AGR        2 X 625       1976-1977
   Fessenhoim 1,2                   f    i PUR        2 X 890         1977
   KKI Isar                        D     ' BWR             870        1977               2UC1-2010
   KKP-1 Philippsburg              D          BWR          864        1977       !          .
   KKU Unterweser                  »     I PWR          1230          1977      I
   Bugcy 2 , 3                     F          PUR     2 X 925     .   1978      ]
   Caorso                          I          PUR          840        1978       I
   Bugey 4 , 5                     F   •    " PWR     2 X 905       1978-1979    IΚ
   Tricastin 1,2,3,4               F          PWR     4 X 925       1979-1960
   Gravelin.es 1,2,3,4             F          PWR     4 X 925       1979-1.981
    KKf Graf enrheinfeld           0          PWR       1229          1979
   tfulhein-K'årlich               0          PWR       1154          1979
   Duirjensss 0                   UK          AGR     2 X 600         1979
   Hartlepool >                   UK          AGR   I 2 X 625         1979
   Heysham                        UK '        AGR   l 2 X 625         1979
   Dsmpierre 1,2,3,4               F          PUR     4 X 925       1979-1981        .
   Doel 3                          Β          PUR          900        1980
   Ti hange 2                      Β          PWR          900        1980 .
   KKK Krummel                     D         B'JR       1260          19b0
J THTR-300 -Uentroo        J[_!>           LHTRj           300  I     1980      I
                                                                                   I
   St Laurent ü 1,2                F          PWR     2 X 925         1981         j
   Le Blayais 1,2                  F          PUR     2 X 925         1981         i .
   KWG Grohnde                     0          PUR       1294          1981         l
   KRü B,C Grundremmingen          D         3UR      2 X 1250      1981-1982            after 2010
   Chinon B 1,2                    F          PWR     2 X 925       1981-1982      i
   KBR Brokdorf                    D          PvJR      1294          1982
   KUS Wyhl                        D          PUR       1283          1982
   SNF.-300 Kalkar ,               D          FBR          282        1982
   Cirene                          1          Hi.'S         32        1982
   Paluit 1,2                      F          PUR     2 X 1300        1982
   Superphénix                     F          FUR       1200 -        1983
   KKP-2 Philippsburg              0          PUR       1230          1982
   ENEL 6,8 foontalto            • I         BWR      2 X 980       1983-1984
                                                                                                      i
   Note :  The assumed periods of closure result from the assumption indicated
           in under point 5.2 of Part I. There are generally no planned dates
           of closure as yet .
 ---pagebreak---                                       ANNEX      II
                     DESCRIPTION OF PROPOSED RESEARCH
                          A ! !D ' OEVELOPi'it.UT ACTIONS
Long term mtogrity of builomgs and systems
 -      It has been proposed thnt the dismantling of nuclear power plants be
delayed for periods ranging from several decodes to about a hundred years,
mainly in ordsr to reduce personnel radiation exposure . Significant degra- . - .
detion of the plant , and in particular of the contamination barriers , during
this time would pose problems of safety, maintenance costs and, ultimately ,
dismantling * This aspect , which has not been assessed in most existing de­
commissioning studies , is among others important for the purpose of esti­
mating what would be a reasonable period of . delaying dismantling .
 *     The objective of this action would be to improve the knowledge on de­
gradation and to propose appropriate preventive measures .
Prooramme-'                                  ;      >
- Estimation of the progress of degradation and of the required maintenance
   effort to be expected cs a function of time for containment buildings ,
   based on a review of available oxperionce with similar buildings .
- study of the internal corrosion of closed contaminated systems due to
   residual amounts of humidity and aggressive agents ; development of methods
   for removing residues of corrosive agents .
- study of other measures aimed at maintaining plants in a safe condition .
Community contribution ; 0.3 million EUA .
 ---pagebreak--- Action * '° ?
 Decontaminntion for de commi ss ioni ne; curposes
  I                                                           '
      The object of this action , comnlementary to these carried out at JRC
within the frame of their nrultianpual programme is to develop and to assess
decontamination methods which are specifically suitable for decommissioning
purposes . These methods nay apply to closed systems / to dismantled compo­
nents , especially those of Isroe dimensions , or to the surfaces cf premises
The? methods may be more aggressive than those currently employed at ope­
rating reactors . Development should aim in narticular at obtaining the
following characteristics : high decontamination efficiency ; simple and
safe application ; unnroblematic nature and low volume of consequential
waste . Methods which can be applied within the premises of nuclear power .
nlants and with e minimum cf additional eauipment are of snecirl interest .
      Among the methods which seem to deserve development , the following
ones may be mentioned : decontamination by pastes and by molten salts ;
electrolytical decontamination ; decontamination by explosive methods .
     Moreover , a synoptic study should be performed in order to assess the
reasonable decontamination effort in decommissioning , taking as a basis
typical reference components . This study should in particular identify the
components for which " comnlctc decontamination", permitting the unrestric­
ted release of the? treated item , would be practicable .
      The soecial decommissioning problems posed by nuclear power plants
which hsve ha :! a major apcident will also be analyzed . The study should .
be based on a loss of coolant accident which leads to severe contamination
of the plant . The study should propose procedures by which the plant can
be brought to a condition , in which it can be safely handled by normal
decommissioning orocedures . If necessary , reasonable modifications of the
plant design should be ororoscd .
Commumty contribution : 1.4 million FUA
 ---pagebreak---  Action N° 3
 Dismantlinn te* clini ques
        Various ( hsnantling techniques have already been utilized in decom­
 missioning , but would require further development to perform the ir.or~' dif­
 ficult t nsKS required in the future . " T.n addition , promising now techniques:
 have been proposed .                        ,
        Because of 'the. variety of techniques , which Cc-n te envisoQfcd .* it !
proposed that a comparative screening study , consioering' several typi^l di
mantling tasks , be carried out in order to assess the possible applications
 and the relative merits of the different techniques * On this btsis , the rr.os
promising techniques should be selected and developed further .
        The following techniques have, hou4ver, already been identified for
further development :
- explosive methods , for dismantling both .sieel piping and concrete struc­
   tures;'
•- thermal techniques for cutting thick wallsd steel- components *
Community contribution :    l.i million EUA „
 ---pagebreak---  Act-^n N' 0      4
 Troc.tncr;t of specific Wdst . materials : steely concrete end graphite
           Largs amounts cf radioactive waste consisting of steel will arise at
every nuclear power plant which is dismantled . Cryogenic cracking end .
 smelting have been proposed as -promising new techniques for the conditioning
^f such waste .
           Cryogenic cracking is aimed principally at reducing the storage volume
 rr.d ^ oert particularly expropriate for elements such as piping .
           Sneltini would nav<? several purposes , i.e. :
- maximum reduction of the storage volume ;
- maximum reduction of the surface which , csuld become accessible to
    corrosion after . disposal ; .
- decontamination by slag removal ;
- incorporation of residual contamination into the base material ;
- pocsibly separation of long-lived radioelements .
           The object of the action , where these techniques are concerned , is
to carry out feaj-ib'1 lity studies , including :
- basic studies on specific aspects , such as the effectiveness of deconta­
    mination by smelting and the possibility of separating long-lived radio­
    ed monts ;                                               1
- conceptual studies with a view to arriving at tho principal process
    parameters 2nd conditions of application and to assessing the industrial
    interest of the techniques in question *
           The problems posed by triiieted steel waste will also be studied .
           As regards concrete w^ste , a conditioning method should be developed ,
by which the radioactivity is durably immobilized .
           Large aivouias of graphite will arise from the decommissioning of gas
5 rep'-, -it *, rei.ctii's and advanced gas-cooled reactors . The object cf this ac­
tion is tJ develop a method for the disposition of this waste , taking into
account the global and long term radiological irrpact of carbon-14 in the
atmc rphr;;"e r in case the graphite would bo burnt .
Community contribution : C.6 million HUA
 ---pagebreak---                                         - 5 -
                                . . ■ I                              .
   Action 11° 5
                                  '                    ■                1
   Large transport containers for radioactive i.'^ste produced in the
   dismantling of nuclear power plants
                            ♦                                             *
                     /        ,
          Studies have shown that it is desirable to transport the radioactive
" waste resulting from dismantling of certain major reactor components in
   larger units than those currently used for other types of radioactive \is ste ,
   in order to - reduce the required amount of cutting and , consequently , the
   personnel radiation exposure and the decommissioning costs . The size and
 ' weight of the shipping units should at least be such as to take full advan-'
   tags of the normrl transport facilities ! ,
   Programme
   - System study aimed at defining th.e types of large transport and/ or dis­
     posal containers needed , depending on the characteristics of the waste ,
      such cs radiation level , previous conditioning , etc .
                                                    /                           '
   - Conceptual study of large containers, including shielding design and
      safety analysis ; definition of the test programme required for licensing
     purposes .
                                          ! '     '        I
   Community contribution : .0.2 million EUA
 ---pagebreak---                                             6
 Action         6
 Estimation of the quantities of radioaef've wastes arising from
 decommissioning of _nuclear power plants in the Community                    1
         This r.ctitn involves the definition of reference* strategies for de- , '
 com/hi ssi on i .13 end is therefore to be considered as a . long-term task . Con­
 sequent ly , the objective in this five-year programme can only be to arrive
 at a first tentative . approach to the problem .
 Programme
                                       \
- Survey of data concerning radioactivity inventories after shutdown of
    nuclear power plants in the member countries ; this survey should be comple-
, . mented    progressively , taking into account new studies which become
    available .                                                                  ■  ~
- Assessment of different schemes for decommissioning of plants and
    conditioning' of wastes produced .
- Estimate of the an' sings of radioactive wastes to be expected from
    decommi ssioning of the nuclear power plants , starting from some selected
    decommissioning schemes , in order to arrive at Icnrer-term at a forecast
   of the wastes arising in the member countries .
Community contribution : 0.4 million £UA
 ---pagebreak---  Action N O 7
 Influence of nuclear power plant desigrr features on decommissioning
       The object of this action would be to identify and develop reasonable
improvements in plant design with a view to decommissioning . In order to
perform this tr.sk effectively , while safeguarding the industrial information
the participation of plant constructors would be sought .
Programmo
- In a first phase , exchange of information and views on tho extent to which
  features facilitating decommissioning are already taken into account and
  on the possibilities of further improvements ; identification of some spe­
  cific potential improvements - which ere suitable for study under this ac­
  tion .
- Assessment of these specific improvements from the point of view of their
  technical feasibility / with due regard to safety and reliability of ope­
  ration / and of their economic and environmental impact .
- Experimental studies on specific selected subjects ( e.g ,/ detachable
  surface layers ).                                            'a .
Commuait / contribution : 0.6 million EUA .
 ---pagebreak---         PROPOSAL FCR A COUf.'CIL DECISIOf ADOPTING A P !\ OGRAr-ÌME CO? CERiòING
        THE DECOHMSSIOr'IrtG OF NUCLLMR POWLR PLANTS
The Council of the European Communities
 HAVING regard to the Treaty establishing the European Atomic Energy
 Community , end in particular Article 7 thereof ;
HAVING regard to the proposal presented by the Commission after consulting
the Scientific and Technical Committee ;
HAVING regard to the Opinion of the European Parliament ;
HAVING regard to the Opinion of the Economic and Social Committee ;
WHEREAS the programme of action of the European Communities on the
environment approved by the Council of the European Communities and the
representatives of the Governments of the fiercer St3tes meeting in the
                                            it
Council in the Declaration of 17 Hay 1977 , underlines the need for
Community measures on the decommissioning of nuclear power plants and
whereas it lays down the content of and procedures for implementing such
measures ;                        .
WHEREAS certain parts of nuclear power plants inevitably become radio­
active during operation , and whereas it is therefore essential to find
effective solutions which are capable of ensuring the safety and protection
of both man and his environment against the potential hazards involved in
the decommissioning of these plants ;
* OJ No C 139 , 13.6.1977 , P. 34-35
 ---pagebreak--- HAS ADOPTED THIS DECISION
                                  Article 1
A nrorranme on the research rclatinn to the decommissioning of nuclear
power plant shall be adopted in the form set out in the Annex for a
five-year neriod from 1 July 1978 . The Annex forms an integral part of
this Decision .
                                  Article 2
The expenditure commitments necessary for the implementation of this
programme are estimated at 6.38 millions Furopean units of account ( EUA )
with a staff of five .                           '
                                               ι
                                  Article 3
The orogramme set out in the Annex may be submitted for amendment at the
end of the second year - in accordance with the appropriate procedures .
 ---pagebreak--- ANNEX
PPOGRAfWE
Tho aim of the oroqrammc is the joint development of a system nf
management , of redundant nuclear power plants and of the radioactive
wastes produced in their dismantling which , at its various stages , will
orovide man and his environment , with the best protection possible ;
the. programme seeks to promote :
A. °csearch and development actions concerning tho following subjects :
Action f'° 1 : l^ng term integrity of buildings and systems .
Action ' 3 2 : Do contamination for decommissioning purposes .
Action fv° 3 : Dismantlinr* techniques .
Action M° 4 : Treatment of specific waste materials : steel , concrete
                and graphite .
Action N°( 5 : Large transport containers for radioactive . waste produced
                in the dismantling of nuclear power plants .
Action N° 6 : Fstimrticn of tho quantities of radioactive wastes rrising
                from decommissioning of nuclear power plants in the
                Community . .
                                                           Ί
Action N° 7 : Influence of nuclear power plant design features on
                decommissioning .
B. Identification of guiding principles , namely :
- certain guiding principles in the design and operation of nuclear
  power nlant with a view to simplifying their subsequent decommissioning
- cuiding principles in tho decommissioning of nuclear power plant which
  could for*i the initial elements of a Community policy in this field .
 ---pagebreak---                                 FINANCIAL SHEET
1.    Relevant budget heading code : 3359
2.    Title of budget heading :                            v
      Decommissioning of nuclear installations
3 . . Legal basis
      Article 7 of the Treaty establishing the EAEC
                                           ι
4.    Description , objective and justification of the action
                     ι
 ---pagebreak---                                        -2-
4.1 . Description
      This is a EURATOM research programme ( indirect action ) on the decommis­
      sioning of nuclear installations . The programme relates to the following
      topics :
      - development of specialized techniques ;
      - forecasting of radioactive waste generation ;
      - study of certain power plant characteristics from a decommissioning .
        standpoint ;
      - definition of guiding principles .
      The programme primarily concerns electricity producers and public
      and private bodies competent in the field of nuclear research .
4.2 . Objective
               /
      The objective of the action is to promote the development of methods
      and techniques for decommissioning nuclear installations in such a
      way as to ensure protection for man and his environment .
4.3 . Justification
      The proposed programme is the outcome of the action programme on the
      environment approved by the Council on 17 May 1977 ; it has been drawn
      up with the aid of a group of national experts . Action at Community
      1-evel will make for economy work through the exchange of information
      and the apportionment of tasks .
 ---pagebreak---                                                         -3-
            5 . Financial incidence of the action ( in EUA )
            5.0 . Incidence on expenditure                    •
            5.0.0 . Total cost during the envisaged period
                        - from the budget of the Communities :                6,3.80,000 EUA
                        - from national adminlist rat ions :
                        - from other sectors at national level :
            5.0.1 Multiannual timetable                         Total cost : 6,380,000 EUA
                                           Appropriations for commitment
                 <         1978           1979          1980           1981            1982  j      1983
                                                                                   ■
                                                                                          '
                                                      '
                  i                                                                           i
Staff
expenditure                           262;000       277,000          294,000         311,000      164,000
Admini strati v e
expenditure,            24,000    .    49,000         52,000          55,000          59,000    . 30,000
Contra et s            476,000      2,000,000 ,   1,327,000        1,000,000
                                                                 I
Total             i 500,000         2,311,000     1,656,000        1,349,000         370,000      194,000
                                                  Appropriations for payment
                          1978          . 1979          1980           1981            1982         1983  ■
Staff                                                    i. 1
expenditure                           262,000       277,000         294,000          311,000      164,000
Administr . ' !I 24,000                49,000         52,000         55,500 ,         59,000     . 30,000
expenditure         !
Contracts           Ii 476,000. ,
                                    1,000,000     1,000,000      1,000,000      1,000,000         327,000
                     !
Total                ! 500,000      1,311,000     1,329,000      1,349,000    |tl , 370,000
                                                                              !
                                                                                                  521,000
 ---pagebreak---  5.0t 2 Method of calculation
        a ) Staff expenditure
            The appropriations for this programme were evaluated on the basis
            of the following staff :
                           2 officials of grade A
                           2 officials of grade B.
                         ' 1 officiai of grade C
                                        \                        .
            The calculations take account of the data as established for the
            setting-up of the draft budget for the year 1979 . No net increase
            of salaries is assumed .! Only a variation of the weightings has
            been considered in order to take account of the trend in the general
            level of prices in the Community .
        b ) Administrative and technical expenditure
            They cover expenditures on missions and on the organization of
            meetings as well as the utilization of scientific and technical
            support if appears necessary for the good development of the pro­
            gramme .
        c ) Contract expenditure
            Depending on the nature of the subject and the qualifications of
            the contractors , no standard method of calculation can be laid
            down .
            Anyhow , the Advisory Committee on Programme Management will be
            consulted on the awarding of appropriations .
        d ) Multiannual previsions                                       *
            The rates held for the calculations of the previsions are resp . :
            1979 = 1.07 ; 1980 = 1.13 ; 1981 = 1.20;1982 = 1.27 ; 1983 = 1.34 . .
'5.1    Implications on the funds                                          '
 6.     Control regime foreseen
        Scientific control : ACPM and the responsible staff of the DG XII
       Administrative controls :
       Budgetary execution : Financial Control
        Regularity of expenditure : Division Contracts of DG XII .
 ---pagebreak---                                  - 5 -
7 . Action financing
    7.0
    7 ..1
    7.2
    7.3 Appropn ations to be entered under future budgets .