On 23 August
, the
specialist publication Middle East
Monitor published an article with the intriguing headline ‘Tehran:
Britain will help upgrade Arak nuclear reactor.’ It explained that “Iran
announced on Wednesday that Britain would contribute in upgrading the Arak
nuclear reactor after the United States withdrew from the nuclear deal, adding “Experts
from Britain will replace their US counterparts during reactor redesign
process,” said Ali Akbar Salehi, head of Iran’s Atomic Energy Organization.
Under the nuclear deal, experts from both the United
States and China were redesigning the Arak heavy water reactor to reduce the
amount of plutonium produced by the reactor as a by-product, the article
explained. (https://www.middleeastmonitor.com/20180823-tehran-britain-will-help-upgrade-arak-nuclear-reactor/)
The UK has a long, nearly 60
year, history of doing nuclear deals with Iran. On 4 February 1959 the UK Parliament was informed of the outcome of the 6th
meeting of the Baghdad Pact Ministerial Council Meeting, held in Karachi
the month before. It included this revelation:
“The Council welcomed the
offer of the United Kingdom to provide equipment for a nuclear centre to be set up at Tehran. This centre will provide
facilities for training technicians in the use of nuclear energy for peaceful purposes.”
A few weeks later, on 18
February 1959, more details of the deal were provided to MPs, Under the heading
Technical assistance and joint projects, the
Government stated:
“A
Multilateral Technical Co-operation Fund was established with an initial
capital of $150,000, designed to increase technical cooperation amongst
members. It was announced that the United Kingdom would make provision each
financial year for a rate of expenditure of £850,000 for technical assistance
and joint projects. In addition Her Majesty's Government have offered to
provide equipment for a nuclear
training centre to be set up in Tehran.”
The Sixth Session of the Baghdad
Pact Council was held in Karachi from January 26th to 28th, 1959. The
delegations from countries participating in this meeting were led by: H.E. Dr.
Manouchehr Eghbal, Prime Minister, Iran; Manzur Qadir, Foreign Minister, Pakistan; H.E.
Adnan Menderes, Prime Minister, Turkey; The Right Hon. Duncan Sandys, MP, Minister
of Defence, United Kingdom; and The Hon. Loy W. Henderson, Deputy
Under-Secretary of State, United States of America.
This was a very interesting quintet of countries to establish Iran’s
nuclear programme.
Fast
forward 59 years, and on the very day the revelation of prospective new UK
involvement in the Iranian nuclear deal was published, the UK Government
released a collection of so-called
‘technical notices’ setting out prospective legislative and managerial
exigencies providing “ information
to allow businesses and citizens to understand what they would need to do in a
‘no deal’ scenario, so they can make informed plans and preparations.”
One of the first 24 notices published covered ‘Civil
nuclear regulation if there’s no Brexit deal’ ( reproduce din full below) This included
a section dealing with ‘Reporting and notification
obligations under Article 37 of the Euratom Treaty’
It explains that before 29
March 2019, when the UK is projected to leave the European Union and its
associated bodies, including the European Atomic Energy Agency (Euratom) “under Article 37 of the Euratom Treaty, the UK government
(on behalf of operators) submits information to the European Commission on
plans to dispose of radioactive waste. Operators must receive a positive
opinion from the Commission before obtaining domestic environmental permits or
proceeding with a project.”
And reveals that after
29 March 2019 - if there’s no deal - “on
exit from the EU, the requirement for the UK to notify the European Commission
of plans for the disposal of radioactive waste will no longer apply.
The Implications, it explains
are that “Operators will not need to secure the Commission’s
opinion before obtaining domestic environmental permits or proceeding with
their radioactive waste disposal plans” and goe son to add “The UK will consult
with stakeholders on any future measures to keep neighbouring states informed
of these types of activity in the UK that will apply after this date.”
This is
an additional, unexamined problem for future
relations with Ireland, which has already
expressed concern over radiological dangers posed to its citizens from
nuclear facilities on the UK ‘s west
coast at Sellafield in Cumbria and Hinkley Point in Somerset (https://www.irishtimes.com/news/environment/uk-yet-to-properly-assess-nuclear-plan-s-impact-on-ireland-1.3470471;
https://www.irishtimes.com/opinion/letters/brexit-and-nuclear-safety-treaty-1.3541656)
There is
surely a responsibility here for the national nuclear safety regulators, the Office
for Nuclear Regulation, and the Environment Agency, to step in a replace the
Euratom treaty article 37 reporting obligation on radiological releases
( as the ONR is doing with Euratom’s role in applying nuclear safeguards)
with national one, overseen by the
nuclear regulatory apparatus they
oversee.
Guidance
Civil nuclear regulation if
there’s no Brexit deal
Published
23 August 2018
Contents
- Purpose
- Nuclear safeguards
- Ownership of special fissile material
- Supply contracts for nuclear material
- Export licence arrangements
- Import licence arrangements
- Nuclear Cooperation Agreements
- Management of spent fuel and radioactive waste
- Reporting and notification obligations under Article 37
of the Euratom Treaty
- Reporting and notification obligations under Article 41
of the Euratom Treaty
- Notification of radioactive source shipments
This
publication is licensed under the terms of the Open Government Licence v3.0
except where otherwise stated. To view this licence, visit nationalarchives.gov.uk/doc/open-government-licence/version/3
or write to the Information Policy Team, The National Archives, Kew, London TW9
4DU, or email: psi@nationalarchives.gsi.gov.uk.
Where we
have identified any third party copyright information you will need to obtain
permission from the copyright holders concerned.
This
publication is available at
https://www.gov.uk/government/publications/civil-nuclear-regulation-if-theres-no-brexit-deal/civil-nuclear-regulation-if-theres-no-brexit-deal
A
scenario in which the UK leaves the EU without agreement (a ‘no deal’ scenario)
remains unlikely given the mutual interests of the UK and the EU in securing a
negotiated outcome.
Negotiations
are progressing well and both we and the EU continue to work hard to seek a
positive deal. However, it’s our duty as a responsible government to prepare
for all eventualities, including ‘no deal’, until we can be certain of the
outcome of those negotiations.
For two
years, the government has been implementing a significant programme of work to
ensure the UK will be ready from day 1 in all scenarios, including a potential
‘no deal’ outcome in March 2019.
It has
always been the case that as we get nearer to March 2019, preparations for a no
deal scenario would have to be accelerated. Such an acceleration does not
reflect an increased likelihood of a ‘no deal’ outcome. Rather it is about
ensuring our plans are in place in the unlikely scenario that they need to be
relied upon.
This
series of technical notices sets out information to allow businesses and
citizens to understand what they would need to do in a ‘no deal’ scenario, so
they can make informed plans and preparations.
This
guidance is part of that series.
Also
included is an overarching framing notice explaining the
government’s overarching approach to preparing the UK for this outcome in order
to minimise disruption and ensure a smooth and orderly exit in all scenarios.
We are
working with the devolved administrations on technical notices and we will
continue to do so as plans develop.
Purpose
This
notice explains to the civil nuclear industry and stakeholders how the sector
will be affected in the UK in the unlikely event that the UK leaves the EU and
the European Atomic Energy Community (Euratom) in March 2019 with no agreement
in place.
This
notice covers:
- nuclear
safeguards
- ownership
and movement of nuclear material, equipment and technology
- management
of spent fuel and radioactive waste
- reporting
and notifications to the European Commission.
Nuclear safeguards
Before 29 March 2019
The
European Commission currently implements nuclear safeguards in respect of
nuclear material for all EU countries, including the UK.
The UK
has already passed new legislation so that the Office for Nuclear Regulation (ONR)
can oversee domestic safeguards instead of Euratom and signed new international
agreements with the International Atomic Energy Agency (IAEA) to replace the
existing trilateral agreements between the IAEA, Euratom and the UK.
After 29 March 2019 if there’s no deal
On exit
from the EU, a new domestic nuclear safeguards regime will come into force.
Implications
The new
regime will be run by the ONR, which already has regulatory oversight of
nuclear safety and nuclear security. The new regime is not dependent on there
being a deal with the EU and Euratom.
The ONR
will publish guidance on the new inspection arrangements on its website.
Actions for businesses and other stakeholders
All
operators in the UK civil nuclear sector will need to comply with the new domestic
safeguards regime as it applies to them. This will be underpinned by
regulations and administered by the ONR. The regime will include new domestic
arrangements for nuclear material accountancy. Operators are encouraged to
submit their views on the draft Nuclear Safeguards Regulations, which
are open to public consultation until 14 September 2018.
Ownership of special fissile material
Before 29 March 2019
Under
Euratom Treaty arrangements, all special fissile material in any EU country is
legally “owned” by Euratom. Operators that hold the legal title to the material
have the unlimited right to use and consume the material as long as they comply
with obligations in the Euratom Treaty.
After 29 March 2019 if there’s no deal
On exit
from the EU, Euratom ownership of special fissile material in the UK will end.
Implications
Operators
that hold the legal title to special fissile material in the UK will have full
ownership from this date, and their associated rights will remain unaffected.
For
special fissile material on Euratom territory, Euratom rules will continue to
apply until the material is exported from Euratom territory.
Actions for businesses and other stakeholders
Operators
with special fissile material on UK or Euratom territory will not need to take
any action in relation to the ownership of special fissile material. Operators’
legal title to this material and any associated rights will be unaffected by the
UK’s withdrawal.
Supply contracts for nuclear material
Before 29 March 2019
Under
current arrangements operators in the EU, including the UK, are required to
obtain approval from the Euratom Supply Agency and, depending on the nature of
the contract, the European Commission, before they conclude a supply contract
for nuclear material.
After 29 March 2019 if there’s no deal
On exit
from the EU, Euratom Supply Agency approval will no longer be required for
contracts agreed by UK-established operators, except where these involve an
EU27-established operator. For EU27-established operators, Euratom Supply
Agency procedures will continue to apply as currently.
Implications
The EU
has set out its view that some existing contracts will need to be re-approved.
Further details of the actions to be taken are set out below.
Actions for businesses and other stakeholders
The steps
that UK and EU27 operators may wish to consider taking will depend on when
their contract was, or is due to be, concluded.
On exit
from the EU, some existing supply contracts will need to be re-approved as a
result of the UK’s withdrawal. This will apply only to supply contracts that:
- involve both
a UK-established operator and an EU27-established operator
- have been
co-signed by the Euratom Supply Agency prior to the UK’s withdrawal
- have a
supply period which extends beyond the date of the UK’s withdrawal.
For
existing supply contracts of this type, UK and EU27 operators affected should
engage with the Euratom Supply Agency on the process for re-approval and agree
with their counterparts on any steps that will need to be taken to manage the
period during which this process takes place. We will continue to work with the
UK operators concerned to ensure that appropriate contingency supply arrangements
are in place.
For
UK-established operators, Euratom Supply Agency approval will only be required
after the day of withdrawal if the contract involves an EU27-established
operator. Operators will need to comply with standard Euratom Supply Agency
processes.
For
EU27-established operators, Euratom Supply Agency procedures will continue to
apply as currently.
Further information
Further
details on the Euratom Supply Agency’s standard procedures can be found on the Euratom
Supply Agency’s website.
Export licence arrangements
Before 29 March 2019
The
controls that apply to the export and transfer of dual-use goods and technology
are implemented by the EU Dual-Use Regulation (428/2009). At present, an
export licence is required to move certain sensitive nuclear materials,
facilities and equipment between the UK and other EU countries.
After 29 March 2019 if there’s no deal
On exit
from the EU, there will be a continued requirement for operators to obtain
export licences for certain sensitive nuclear materials, facilities and
equipment.
Implications
Further
details of the export licence arrangements that will apply are set out in the Exporting Controlled Goods technical notice.
Actions for businesses and other stakeholders
Operators
can find further detail on export licensing and information on the steps they
will need to take in the Exporting Controlled Goods technical notice.
Further information
Further information
on how to apply for export licences is available from the Export Control Joint Unit.
Import licence arrangements
Before 29 March 2019
The
current import licensing regime set out in the Notice to Importers 2867 means that the import of
relevant nuclear materials from EU countries does not require operators to
obtain an import licence.
After 29 March 2019 if there’s no deal
The
Notice to Importers 2867 will be updated in time for Exit Day to set out the
arrangements that will apply following the UK’s withdrawal from the EU.
Implications
Under the
updated arrangements, importers may need to obtain an import licence for
imports of relevant nuclear materials from the EU. The UK will engage with
importers on any new arrangements that will apply from this date and provide
further guidance on these.
Actions for businesses and other stakeholders
Importers
should check the updated Notice to Importers for details of the import licence
arrangements that will apply after the date of the UK’s exit from the EU.
Further guidance will also be published on the website below.
Further information
Further
information can be found on the import control arrangements GOV.UK
page.
Nuclear Cooperation Agreements
Before 29 March 2019
Euratom
is currently party to a number of Nuclear Cooperation Agreements (NCAs) with
third countries which provide the framework for the UK’s civil nuclear trade
with these countries.
After 29 March 2019 if there’s ‘no deal’
Discussions
to agree bilateral NCA arrangements with priority countries are on track to be
completed before the UK leaves the EU, and the UK has already signed new
bilateral NCAs with a number of third countries. This will ensure that civil
nuclear trade can continue unimpeded.
Implications
Civil
nuclear trade and cooperation will continue under the UK’s bilateral
agreements.
Actions for businesses and other stakeholders
Operators
do not need to take any action in relation to NCAs.
Further information
Further
information is available from the Nuclear Cooperation Agreement Factsheet.
Management of spent fuel and radioactive waste
Before 29 March 2019
The
current Euratom arrangements provide the framework for the movement of spent
fuel and radioactive waste between countries. This includes authorisations for
shipments under the Supervision and Control of Shipments of Radioactive Waste and Spent Fuel Directive 2006
(Directive 2006/117/Euratom – “the 2006 Directive”).
Under
these arrangements, a number of EU countries have contracts in place for the
reprocessing of spent fuel and the treatment and processing of radioactive
waste in the UK. The UK government’s policy is not to accept overseas origin
radioactive waste for disposal in the UK except in specific circumstances which
are set out in the relevant UK government policy documents.
After 29 March 2019 if there’s no deal
The UK’s
current arrangements for the reprocessing of spent fuel and treatment of
radioactive waste will continue after the UK’s withdrawal from Euratom.
On exit
from the EU, the process for authorising new shipments of spent fuel and
radioactive waste from the UK to EU27 will change to reflect the fact that the
UK will no longer be within the EU. The UK will engage with operators on any
new arrangements that will apply for the authorisation of new shipments of
spent fuel and radioactive waste from the EU27 to the UK, and will provide
further guidance on these.
Beyond
this, arrangements for new shipments of spent fuel and radioactive waste from
EU27 countries to the UK for the purposes of management will not be affected.
Under EU rules, there will be some small changes applicable to shipments of
radioactive waste for the purposes of disposal, but the UK government’s policy
on accepting such shipments will remain unaffected.
Implications
The
management of EU27 spent fuel and radioactive waste in the UK will continue in
line with existing contractual arrangements.
For new
shipments of spent fuel and radioactive waste between the UK and EU27, all
operators will need to comply with the arrangements that apply to third
countries when shipping spent fuel and radioactive waste from the UK to EU27
countries. Further guidance will be provided on the arrangements that will
apply for authorisations of spent fuel and radioactive waste from the EU27 to
the UK.
The
government will continue working with the Scottish government, Welsh government
and Northern Ireland Civil Service to ensure that these arrangements work for
the whole of the UK.
The
current arrangements that determine which state has ultimate responsibility for
the safe and responsible disposal of any spent fuel and radioactive waste
generated will not be affected by the UK’s exit for either the UK or EU27
countries.
Actions for businesses and other stakeholders
The management
of spent fuel and radioactive waste in the UK and EU27 will continue as now. UK
and EU27 operators will not need to take any action.
Please
note that if the existing contract is considered to be a supply contract under
Euratom Supply Agency arrangements, operators should check the section of this
technical notice on ‘Supply Contracts for Nuclear Material’.
For new
shipments, all operators wishing to ship radioactive waste or spent fuel from
the UK to an EU27 country will need to comply with the arrangements for third
countries as set out in the 2006 directive. This means that shipments from the
UK to EU27 countries will require authorisation from competent authorities in
both the originating and destination states, and that EU27 competent authorities
will no longer be subject to the current two-month deadline to grant
authorisations.
Operators
wishing to secure new authorisations to ship radioactive waste or spent fuel
from EU27 countries to the UK should check the website below for further
guidance of the arrangements that will apply after this date.
EU27
operators will be able to continue to enter into management contracts for spent
fuel and radioactive waste in the UK.
Under the
Community Framework for the Responsible and Safe Management
of Spent Fuel and Radioactive Waste Directive (Directive 2011/70/EURATOM),
EU27 operators will need to comply with the arrangements that apply to third
countries prior to any shipment of radioactive waste for the purposes of
disposal in the UK. This will not affect new shipments of spent fuel and
radioactive waste in the UK for the purposes of processing, treatment or
reprocessing.
Further information
Further
guidance on authorisations for shipments of radioactive waste and spent fuel
will be published on the radioactive waste and spent fuel GOV.UK page.
Reporting and notification obligations under Article 37
of the Euratom Treaty
Before 29 March 2019
Under
Article 37 of the Euratom Treaty, the UK government (on behalf of operators)
submits information to the European Commission on plans to dispose of
radioactive waste. Operators must receive a positive opinion from the
Commission before obtaining domestic environmental permits or proceeding with a
project.
After 29 March 2019 if there’s no deal
On exit
from the EU, the requirement for the UK to notify the European Commission of
plans for the disposal of radioactive waste will no longer apply.
Implications
Operators
will not need to secure the Commission’s opinion before obtaining domestic
environmental permits or proceeding with their radioactive waste disposal
plans.
The UK
will consult with stakeholders on any future measures to keep neighbouring
states informed of these types of activity in the UK that will apply after this
date.
Actions for businesses and other stakeholders
UK
operators should continue to follow the requirement to notify the Commission of
plans to dispose of radioactive waste until the date of the UK’s exit from the
EU. This includes continuing to work with the Department for Business, Energy
and Industrial Strategy to complete and return submissions and secure
Commission opinions.
Further information
Further
details of the application of the current requirements are set out in Commission Recommendation 2010/635/Euratom.
Reporting and notification obligations under Article 41
of the Euratom Treaty
Before 29 March 2019
Under
Article 41 of the Euratom Treaty operators with plans for certain nuclear
investments must report the details of these to the Commission. The type of
nuclear investments that require notification are defined in Council Regulation (Euratom) 2587/1999, and the
required content of the reports is set out in Commission Regulation (EC) 1209/2000.
After 29 March 2019 if there’s no deal
On exit
from the EU, the requirement for nuclear operators to inform the Commission of
investment projects in the UK civil nuclear sector will no longer apply. The EU
Regulations defining the content of Article 41 submissions (Council Regulation
2587/1999 and Commission Regulation 1209/2000) as they apply in the UK will be
repealed.
Implications
UK and EU
operators will no longer need to inform the Commission of planned investments
in the UK civil nuclear sector after the date of the UK’s exit from the EU.
Actions for businesses and other stakeholders
UK and EU
operators should continue to follow the requirement to inform the Commission of
planned investments in the UK civil nuclear sector until the date of the UK’s
exit from the EU. This includes continuing to complete and return submissions
and discuss the submissions with the Commission. After the date of the UK’s exit
from the EU, operators will no longer need to comply with this requirement.
Further information
Further
details of the current requirements are set out in Council Regulation (Euratom) 2587/1999 and Commission Regulation (EC) 1209/2000.
Notification of radioactive source shipments
Before 29 March 2019
Before
any shipment of radioactive sources between EU countries, radioactive source
holders must obtain a prior written declaration from the receiver of the
source, noting that they have complied with national requirements for the safe
storage, use and disposal of the source being received. These requirements are
set out in Council Regulation 1493/93/Euratom.
After 29 March 2019 if there’s no deal
UK
radioactive source holders who plan to send material to other EU states will
continue to comply with Regulation 1493/93 by obtaining prior written
declarations until the date of withdrawal. The UK will engage with operators on
any new arrangements that will apply after this date, and provide further guidance
on these.
Implications
The UK
will provide further guidance on the arrangements that will apply after the
date of the UK’s exit from the EU. Any changes to these notification procedures
will not prevent the shipment of radioactive sources into the UK after exit.
Actions for businesses and other stakeholders
Operators
should continue to comply with the notification requirements for radioactive
source shipments until the date of the UK’s exit from the EU. Operators should
check the website below for further guidance of the arrangements that will
apply after this date.
Further information
Further
guidance will be published on the radioactive waste and spent fuel GOV.UK page.
This
notice is meant for guidance only. You should consider whether you need
separate professional advice before making specific preparations.
It is
part of the government’s ongoing programme of planning for all possible
outcomes. We expect to negotiate a successful deal with the EU.
COMMISSION RECOMMENDATION
of 11 October 2010
on the application of Article 37 of the Euratom Treaty
(2010/635/Euratom)
THE EUROPEAN COMMISSION,
Having regard to the Treaty establishing the European
Atomic Energy Community, and in particular Article 37 thereof in conjunction
with Article 106a referring to Article 292 of the Treaty on the Functioning of
the European Union,
Having consulted the group of persons appointed in
accordance with Article 31 of the Euratom Treaty by the Scientific and
Technical Committee,
Whereas:
|
(1)
|
Article 37 requires that each Member State is to provide
the Commission with such general data relating to any plan for the disposal
of radioactive waste in whatever form as will make it possible to determine
whether the implementation of such plan is liable to result in the
radioactive contamination of the water, soil or airspace of another Member
State. The Commission is to deliver its opinion within six months, after
consulting the group of experts referred to in Article 31.
|
|
(2)
|
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(3)
|
The Court of Justice of the European Union, in its
judgment of 22 September 1988 in Case 187/87 (5), ruled that
Article 37 of the Euratom Treaty must be interpreted as meaning that the
European Commission shall be provided with general data before the discharge
authorisation of radioactive effluents is granted by the Member State
concerned, in order to make it possible for the Commission to issue its
opinion before such discharges are authorised so that the Commission’s
opinion can be taken into account.
|
|
(4)
|
Article 37 has as its objective to forestall any
possibility of radioactive contamination of another Member State. The
Commission, having consulted the abovementioned group of experts has deemed
the disposal of radioactive waste associated with certain operations not to
be liable to result in the radioactive contamination of another Member State.
|
|
(5)
|
In exceptional cases due to information received, the
Commission may call for general data to be submitted for a plan for the
disposal of radioactive waste, otherwise deemed not to be liable to result in
the radioactive contamination of another Member State on the basis of the
present Recommendation; the Commission’s opinion may then pertain to an
authorisation which has been granted at an earlier stage.
|
|
(6)
|
To appraise disposal plans in a consistent manner, it is
necessary to specify which types of operation may result in the disposal of
radioactive waste within the meaning of Article 37 of the Treaty, and to
specify for the different types of operation which information is to be
supplied as the general data.
|
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(7)
|
Mixed-oxide fuel fabrication plants process large amounts
of plutonium oxide, a submission of general data for the dismantling of such
plants should be required as is already the case for the dismantling of
nuclear reactors and reprocessing plants.
|
|
(8)
|
Trivial operations having no or negligible radiological
impact in other Member States should not be submitted to the Commission.
|
|
(9)
|
Member States may communicate an integrated submission
for a complex site where major changes are scheduled to be carried out over a
long period of time, involving several steps and including the operation of
new facilities, and the completeness of the information contained in the
initial general data should allow the Commission to fulfil its obligations
pursuant to Article 37 of the Euratom Treaty and deliver a sound opinion.
|
|
(10)
|
In view of the number of existing nuclear plants on which
no opinion has already been issued within the meaning of Article 37 of the
Treaty and which may be subject to modifications or dismantling operations,
it is necessary to specify which information is to be supplied as the general
data to allow the Commission to fulfil its obligation without prejudice to
the principle of equity between installations subject to modifications and those
which are not.
|
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(11)
|
In cases where the exposure of the population in the
vicinity of the site of interest is very low, this information may be
sufficient for the assessment of the impact on other Member States.
|
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(12)
|
To appraise in a consistent manner the radiological
impact on other Member States of accidental situations, information requested
in the general data on unplanned releases from nuclear reactors and
reprocessing plants should be extended beyond the reference accidents to
accidents taken into consideration for the establishment of the site related
national emergency plan.
|
|
(13)
|
To clarify and limit the information required by the
Commission pertaining to the predisposal management of radioactive waste and
to modifications of a plan on which no opinion has already been issued by the
Commission, two new annexes have been included.
|
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(14)
|
All Member States have now declared that they will desist
from sea dumping and no Member State intends to carry out sub-seabed burial
of radioactive waste,
|
HAS ADOPTED THIS RECOMMENDATION:
|
1.
|
The ‘disposal of radioactive waste’ within the meaning of
Article 37 of the Treaty should cover any planned or accidental release of
radioactive substances associated with the operations listed below, in
gaseous, liquid or solid form in or to the environment:
|
|
2.
|
‘General data’ within the meaning of Article 37 of the
Treaty should be understood to mean:
|
|
3.
|
Operations falling within the scope of point 1(12) should
be deemed not to be liable to result in the radioactive contamination of
another Member State, significant from the point of view of health, unless in
any specific case the Commission calls for general data to be provided.
|
|
4.
|
For operations falling within the scope of point 1(9),
the submission of general data should be governed by the following
conditions:
|
|
5.
|
If a Member State envisages modifying (10) a plan for
the disposal of radioactive waste, the submission of general data should be
governed by the following conditions:
|
|
6.
|
The general data should be submitted to the Commission:
|
|
7.
|
Where Member States communicate an integrated submission
of general data for a complex site where major changes are scheduled to be
carried out over long periods of time, involving several steps and including,
inter alia, the operation of new facilities, the initial submission should
contain a complete and detailed overview of the planned operations, to be
updated by subsequent submissions in case of any modifications to the
existing plan. As regards the accident scenarios in the initial submission,
the general data should include at least information on estimated amounts and
physico-chemical forms of radionuclides present in each of the facilities on
the site as well as quantities assumed to be released in the event of the
accident considered for each of those facilities. The general data may
provide background on past and current operations on the site, bearing in
mind that the Commission’s opinions will relate only to future operations.
|
|
8.
|
Since submission of a plan for the disposal of
radioactive waste is the responsibility of the relevant Member State, that
State should accept responsibility for all information submitted to the
Commission in respect of such a plan.
|
|
9.
|
Following receipt of an opinion, the Member State
concerned should inform the Commission of the actions it envisages in
response to any recommendation given in the Commission opinion on a disposal
plan.
|
|
10.
|
Following receipt of an opinion, the Member State
concerned should communicate to the Commission the discharge authorisation as
well as any later amendments for comparison with the information in the
general data on which the Commission opinion was based.
|
This
Recommendation is addressed to the Member States.
It replaces Recommendation 1999/829/Euratom.
Done at Brussels, 11 October 2010.
For the Commission
Günther
OETTINGER
Member of the Commission
(5) [1988] ECR 5013.
(6) Provided that the operation is not
incorporated in a plan submitted under another heading.
(7) The term ‘predisposal management’
includes storage of radioactive waste.
(8) Decommissioning comprises all
technical and administrative procedures, activities and measures taken after
the final shut-down of a facility and up to the release of the site for
unrestricted or other licensed use. Within these activities ‘dismantling’
comprises disassembling, cutting and demolition of contaminated or activated
components, systems and structures including their packaging and transfer
off-site.
(9) Oxides of uranium and plutonium.
(10) Modifications of a plan might also
include preparatory work in view of the operations referred to in point 1(9).
ANNEX I
General
data applicable to the operations referred to in point 1(1) to (7)
Introduction
|
—
|
general presentation of the plan,
|
|
—
|
present stage of licensing procedure, envisaged commissioning
steps.
|
1. THE
SITE AND ITS SURROUNDINGS
1.1. Geographical,
topographical and geological features of the site and the region with
|
—
|
a map of the region showing the location and geographical
coordinates (degrees, minutes) of the site,
|
|
—
|
the relevant features of the region, including geological
features,
|
|
—
|
the location of the installation in relation to such
other installations, the discharges from which need to be considered in
conjunction with those from the installation in question,
|
|
—
|
the location of the site with regard to other Member
States giving the distances from frontiers and relevant conurbations,
together with their populations.
|
1.2. Seismology
|
—
|
the degree of seismic activity in the region; probable
maximum seismic activity and designed seismic resistance of the installation.
|
1.3. Hydrology
For an installation situated near to a waterbody providing
a potential contamination pathway to another Member State, a brief description
of appropriate hydrological features, extending to the other Member State(s),
for example:
|
—
|
brief description of the path(s), tributaries, estuary,
water abstraction, floodplains, etc.,
|
|
—
|
average, maximum and minimum water flows and their
frequency of occurrence,
|
|
—
|
underground water table, levels and flows,
|
|
—
|
brief description of the littoral areas,
|
|
—
|
direction and force of currents, tides, circulation
patterns, both local and regional,
|
|
—
|
flood risk and protection of the installation.
|
1.4. Meteorology
Local climatology with frequency distributions of:
|
—
|
wind directions and speeds,
|
|
—
|
precipitation intensity and duration,
|
|
—
|
for each wind sector, atmospheric dispersion conditions,
duration of temperature inversions,
|
|
—
|
extreme weather phenomena (for example, tornadoes, severe
storms, heavy rainfall, droughts).
|
1.5. Natural
resources and foodstuffs
Brief description of:
|
—
|
water utilisation in the region and as appropriate in
neighbouring Member States,
|
|
—
|
principal food resources in the region and as appropriate
in other Member States: crops, stock breeding, fishing and, for discharges
into sea, data on fishing in territorial and extraterritorial waters,
|
|
—
|
foodstuff distribution system and particularly the export
to other Member States from the regions concerned, in so far as they are related
to the risk of exposure from discharges through the significant exposure
pathways.
|
1.6. Other
activities in the vicinity of the site
|
—
|
where appropriate, other nuclear facilities and any
hazardous industrial or military activities, surface and aerial traffic,
pipelines, storages and any other factors which may have an influence on the
safety of the installation,
|
|
—
|
protection measures.
|
2. THE
INSTALLATION
2.1. Main
features of the installation
|
—
|
brief description of the installation,
|
|
—
|
type, purpose and main features of the processes,
|
|
—
|
site layout plan,
|
|
—
|
safety provisions.
|
2.2. Ventilation
systems and the treatment of gaseous and airborne wastes
Description of ventilation, decay, filtration and discharge
systems, in normal conditions and in the case of an accident, including flow
diagrams
2.3. Liquid
waste treatment
Description of liquid waste treatment facilities, storage
capacities and discharge systems, including flow diagrams
2.4. Solid
waste treatment
Description of solid waste treatment facilities and storage
capacities
2.5. Containment
Description of systems and provisions to confine
radioactive substances
2.6. Decommissioning
and dismantling
|
—
|
envisaged period of operation of the installation,
|
|
—
|
consideration given to decommissioning and dismantling,
|
|
—
|
outline of regulatory and administrative provisions for
decommissioning and dismantling.
|
3. RELEASE
FROM THE INSTALLATION OF AIRBORNE RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
3.1. Authorisation
procedure in force
|
—
|
outline of the procedure in force,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities, including the assumed radionuclide composition.
|
3.2. Technical
aspects
|
—
|
annual discharges foreseen,
|
|
—
|
origins of the radioactive effluents, their composition
and physico-chemical forms,
|
|
—
|
management of these effluents, methods and paths of
release.
|
3.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of the monitoring equipment,
|
|
—
|
for operations listed under (1) and (2), key
radionuclides and associated detection limits should at least fulfil the
specifications laid down in Commission Recommendation 2004/2/Euratom (1),
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
3.4. Evaluation
of transfer to man
Except for operations listed under (1) and (2), if the
assessed maximum exposure levels from releases in normal conditions to adults,
children and infants in the vicinity of the plant are below 10 μSv per annum
and there are no exceptional pathways of exposure, e.g. involving the export of
foodstuffs, no data on effective doses in other affected (2) Member States are required if doses to the
reference groups in the vicinity of the plant are provided.
3.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the plant and for other affected Member States:
|
—
|
atmospheric dispersion of the effluents,
|
|
—
|
ground deposition and re-suspension,
|
|
—
|
food chains, inhalation, external exposure etc.,
|
|
—
|
living habits (diet, exposure time etc.),
|
|
—
|
other parameter values used in the calculations.
|
3.4.2. Evaluation of concentration and
exposure levels associated with the envisaged discharge limits cited in 3.1
above:
|
—
|
annual average concentrations of activity in the
atmosphere near the ground and surface contamination levels, for the most
exposed areas in the vicinity of the plant and in other affected Member
States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States, corresponding annual exposure levels:
effective dose to adults, children and infants, taking account of all
significant exposure pathways.
|
3.5. Radioactive
discharges to atmosphere from other installations
Procedures for coordination with radioactive discharges
from other installations referred to in 1.1, third indent
4. RELEASE
FROM THE INSTALLATION OF LIQUID RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
4.1. Authorisation
procedure in force
|
—
|
outline of the general procedure involved,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities, including the assumed radionuclide composition.
|
4.2. Technical
aspects
|
—
|
annual discharges foreseen,
|
|
—
|
origins of the radioactive effluents, their composition
and physico-chemical forms,
|
|
—
|
management of the effluents, methods and paths of
release.
|
4.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of monitoring equipment,
|
|
—
|
for operations listed under (1) and (2), key
radionuclides and associated detection limits should at least fulfil the
specifications laid down in Recommendation 2004/2/Euratom,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
4.4. Evaluation
of transfer to man
Except for operations listed under (1) and (2), if the
assessed maximum exposure levels from releases in normal conditions to adults,
children and infants in the vicinity of the plant are below 10 μSv per annum
and there are no exceptional pathways of exposure, e.g. involving the export of
foodstuffs, no data on effective doses in other affected Member States are
required if doses to reference groups in the vicinity of the plant are
provided.
4.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the plant and for other affected Member States:
|
—
|
aquatic dispersion of the effluents,
|
|
—
|
their transfer by sedimentation and ion exchange,
|
|
—
|
food chains, inhalation of sea spray, external exposure
etc.,
|
|
—
|
living habits (diet, exposure time etc.),
|
|
—
|
other parameter values used in the calculations.
|
4.4.2. Evaluation of concentration and
exposure levels associated with the discharge limits cited in 4.1 above:
|
—
|
annual average concentrations of activity in surface
waters, at the points where such concentrations are highest, in the vicinity
of the plant and in other affected Member States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States: effective dose to adults, children and
infants, taking account of all significant exposure pathways.
|
4.5. Radioactive
discharges into the same receiving waters from other installations
Procedures for coordination with discharges from other
installations referred to in 1.1, third indent
5. DISPOSAL
OF SOLID RADIOACTIVE WASTE FROM THE INSTALLATION
5.1. Solid
radioactive waste
|
—
|
categories of solid radioactive waste and estimated
amounts,
|
|
—
|
processing and packaging,
|
|
—
|
storage arrangements on site.
|
5.2. Radiological
risks to the environment
|
—
|
assessment of risks to the environment,
|
|
—
|
precautions taken.
|
5.3. Off-site
arrangements for the transfer of waste
5.4. Release
of materials from the requirements of the basic safety standards
|
—
|
national strategy, criteria and procedures for the
release of contaminated and activated materials,
|
|
—
|
clearance levels established by competent authorities for
disposal, recycling and reuse,
|
|
—
|
envisaged types and amounts of released materials.
|
6. UNPLANNED
RELEASES OF RADIOACTIVE EFFLUENTS
6.1. Review
of accidents of internal and external origin which could result in unplanned
releases of radioactive substances
List of the accidents studied in the safety report
6.2. Reference
accident(s) taken into consideration by the competent national authorities for
evaluating possible radiological consequences in the case of unplanned releases
In addition, for operations (1) and (2) accidents taken
into consideration by the competent authorities for the establishment of the
site related national emergency plan.
Outline of the accident(s) considered and reasons for its
(their) choice
6.3. Evaluation
of the radiological consequences of the reference accident(s) and for
operations (1) and (2), the accident(s) taken into consideration by the
competent authorities for the establishment of the site related national
emergency plan
6.3.1. Accidents
entailing releases to atmosphere
Except for operations listed under (1) and (2), if the
assessed maximum exposure levels from the reference accident to adults,
children and infants in the vicinity of the plant are below 1 mSv and there are
no exceptional pathways of exposure, e.g. involving the export of foodstuffs,
no data on exposure levels in other affected Member States are required if
exposure levels in the vicinity of the plant are provided.
|
—
|
assumptions used to calculate the releases to atmosphere,
|
|
—
|
release paths; time patterns of the releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameter values used to calculate for the
releases their atmospheric dispersion, ground deposition, re-suspension and
transfer via food chains and to evaluate the maximum exposure levels via the
significant exposure pathways in the vicinity of the plant and for other
affected Member States,
|
|
—
|
maximum time-integrated concentrations of radioactivity
in the atmosphere near the ground and maximum surface contamination levels
(in dry and wet weather) for the most exposed areas in the vicinity of the
plant and for relevant areas in other affected Member States,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
6.3.2. Accidents
entailing releases into an aquatic environment
Except for operations listed under (1) and (2), if the
assessed maximum exposure levels from the reference accident to adults,
children and infants close to the plant are below 1 mSv and there are no
exceptional pathways of exposure, e.g. involving the export of foodstuffs, no
data on exposure levels in other affected Member States are required if
exposure levels in the vicinity of the plant are provided.
|
—
|
assumptions used to calculate the liquid release,
|
|
—
|
release paths, time pattern of releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameters used to calculate for the releases
their aquatic dispersion, their transfer by sedimentation and ion exchange,
their transfer via food chains and to evaluate the maximum exposure levels
via the significant exposure pathways,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
7. EMERGENCY
PLANS, AGREEMENTS WITH OTHER MEMBER STATES
In relation to possible radiological emergencies which may
affect other Member States in order to facilitate the organisation of
radiological protection in these States:
Brief description of:
|
—
|
intervention levels established for different types of
countermeasures,
|
|
—
|
emergency planning arrangements, including the emergency
planning zones adopted for the installation,
|
|
—
|
arrangements in place for the early exchange of
information with other Member States, bilateral or multilateral agreements on
transfrontier information, coordination of emergency plans and their
implementation and mutual assistance,
|
|
—
|
emergency plan testing arrangements with particular
reference to the involvement of other Member States.
|
8. ENVIRONMENTAL
MONITORING
|
—
|
external radiation monitoring,
|
|
—
|
monitoring of radioactive substances in air, water, soil
and the food chains, whether undertaken by the operator or by competent
authorities.
|
With reference to 3.1 and 4.1 above, monitoring programs as
approved by the competent national authorities, organisation, sample forms and
frequency, type of monitoring instruments used in normal and accident
circumstances; where appropriate, any collaboration arrangements in this
respect with neighbouring Member States.
(1) Commission Recommendation of 18
December 2003 on standardised information on radioactive airborne and liquid
discharges into the environment from nuclear power reactors and reprocessing
plants in normal operation (OJ L 2, 6.1.2004, p. 36).
(2) Affected Member States are to be
selected by taking into account distance from the installation, wind direction
for gaseous effluent releases and the route of water courses for liquid
effluent releases.
ANNEX II
General
data applicable to the operation referred to in point 1(8)
The
predisposal management of radioactive waste arising from the operations
referred to in point 1(1) to (7) and (9)
Introduction
|
—
|
general presentation of the plan,
|
|
—
|
present stage of licensing procedure, and
|
|
—
|
envisaged commissioning steps.
|
1. THE
SITE AND ITS SURROUNDINGS
1.1. Geographical,
topographical and geological features of the site and the region with
|
—
|
a map of the region showing the location and geographical
coordinates (degrees, minutes) of the site,
|
|
—
|
the relevant features of the region, including geological
features,
|
|
—
|
the location of the installation in relation to such
other installations, the discharges from which need to be considered in
conjunction with those from the installation in question,
|
|
—
|
the location of the site with regard to other Member
States giving the distances from frontiers and relevant conurbations,
together with their populations.
|
1.2. Seismology
|
—
|
the degree of seismic activity in the region; probable
maximum seismic activity and designed seismic resistance of the installation.
|
1.3. Hydrology
For an installation situated near to a waterbody providing
a potential contamination pathway to another Member State, a brief description
of appropriate hydrological features, extending to the other Member State(s),
for example:
|
—
|
brief description of the path(s), tributaries, estuary,
water abstraction, floodplains, etc.,
|
|
—
|
average, maximum and minimum water flows and their
frequency of occurrence,
|
|
—
|
underground water table, levels and flows,
|
|
—
|
brief description of the littoral areas,
|
|
—
|
direction and force of currents, tides, circulation
patterns, both local and regional,
|
|
—
|
flood risk and protection of the installation.
|
1.4. Meteorology
Local climatology with frequency distributions of:
|
—
|
wind directions and speeds,
|
|
—
|
precipitation intensity and duration,
|
|
—
|
for each wind sector, atmospheric dispersion conditions,
duration of temperature inversions,
|
|
—
|
extreme weather phenomena (for example, tornadoes, severe
storms, heavy rainfall, droughts).
|
1.5. Natural
resources and foodstuffs
Brief description of:
|
—
|
water utilisation in the region and as appropriate in
neighbouring Member States,
|
|
—
|
principal food resources in the region and as appropriate
in other Member States: crops, stock breeding, fishing and, for discharges
into sea, data on fishing in territorial and extraterritorial waters,
|
|
—
|
foodstuff distribution system and particularly the export
to other Member States from the regions concerned, in so far as they are
related to the risk of exposure from discharges through the significant
exposure pathways.
|
1.6. Other
activities in the vicinity of the site
|
—
|
where appropriate, other nuclear facilities and any
hazardous industrial or military activities, surface and aerial traffic,
pipelines, storages and any other factors which may have an influence on the
safety of the installation,
|
|
—
|
protection measures.
|
2. THE
INSTALLATION
2.1. Main
features of the installation
|
—
|
brief description of the installation,
|
|
—
|
type, purpose and main features of the processes,
|
|
—
|
description of radioactive waste to be received for
storage and processing, facilities and storage capacities, categories and
types of radioactive waste (for example, low or intermediate level, metal,
combustible waste) to be stored and processed, including volumes and
radionuclide content,
|
|
—
|
site layout plan,
|
|
—
|
safety provisions.
|
2.2. Ventilation
systems and the treatment of gaseous and airborne wastes
Description of ventilation, decay, filtration and discharge
systems, in normal conditions and in the case of an accident, including flow
diagrams
2.3. Liquid
waste treatment
Description of secondary liquid waste treatment facilities,
storage capacities and discharge systems, including flow diagrams
2.4. Solid
waste treatment
Description of secondary solid waste treatment facilities
and storage capacities
2.5. Containment
Description of systems and provisions to confine
radioactive substances
2.6. Decommissioning
and dismantling
|
—
|
envisaged period of operation of the installation,
|
|
—
|
consideration given to decommissioning and dismantling,
|
|
—
|
outline of regulatory and administrative provisions for
decommissioning and dismantling.
|
3. RELEASE
FROM THE INSTALLATION OF AIRBORNE RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
3.1. Authorisation
procedure in force
|
—
|
outline of the procedure in force,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities, including the assumed radionuclide composition.
|
3.2. Technical
aspects
|
—
|
annual discharges expected,
|
|
—
|
origins of the radioactive effluents, their composition
and physico-chemical forms,
|
|
—
|
management of these effluents, methods and paths of
release.
|
3.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of the monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
3.4. Evaluation
of transfer to man
If the assessed maximum exposure levels from releases in
normal conditions to adults, children and infants in the vicinity of the plant
are below 10 μSv per annum and there are no exceptional pathways of exposure,
e.g. involving the export of foodstuffs, no data on effective doses in other
affected (1) Member States are required if doses to the
reference groups in the vicinity of the plant are provided.
3.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the plant and for other affected Member States:
|
—
|
atmospheric dispersion of the effluents,
|
|
—
|
ground deposition and re-suspension,
|
|
—
|
food chains, inhalation, external exposure etc.,
|
|
—
|
living habits (diet, exposure time etc.),
|
|
—
|
other parameter values used in the calculations.
|
3.4.2. Evaluation of the concentration and
exposure levels associated with the envisaged discharge limits cited in 3.1
above:
|
—
|
annual average concentrations of activity in the
atmosphere near the ground and surface contamination levels, for the most
exposed areas in the vicinity of the installation and in other affected
Member States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States, corresponding annual exposure levels:
effective dose to adults, children and infants, taking account of all
significant exposure pathways.
|
3.5. Radioactive
discharges to atmosphere from other installations
Procedures for coordination with radioactive discharges
from other installations referred to in 1.1, third indent
4. RELEASE
FROM THE INSTALLATION OF LIQUID RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
4.1. Authorisation
procedure in force
|
—
|
outline of the general procedure involved,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities, including the assumed radionuclide composition.
|
4.2. Technical
aspects
|
—
|
annual discharges expected,
|
|
—
|
origins of the radioactive effluents, their composition
and physico-chemical forms,
|
|
—
|
management of the effluents, methods and paths of
release.
|
4.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
4.4. Evaluation
of transfer to man
If the assessed maximum exposure levels from releases in
normal conditions to adults, children and infants in the vicinity of the plant
are below 10 μSv per annum and there are no exceptional pathways of exposure,
e.g. involving the export of foodstuffs, no data on effective doses in other
affected Member States are required if doses to reference groups in the
vicinity of the plant are provided.
4.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the plant and for other affected Member States:
|
—
|
aquatic dispersion of the effluents,
|
|
—
|
their transfer by sedimentation and ion exchange,
|
|
—
|
food chains, inhalation of sea spray, external exposure
etc.,
|
|
—
|
living habits (diet, exposure time etc.),
|
|
—
|
other parameter values used in the calculations.
|
4.4.2. Evaluation of concentration and
exposure levels associated with the discharge limits cited in 4.1 above:
|
—
|
annual average concentrations of activity in surface
waters, at the points where such concentrations are highest, in the vicinity
of the plant and in other affected Member States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States: effective dose to adults, children and
infants, taking account of all significant exposure pathways.
|
4.5. Radioactive
discharges into the same receiving waters from other installations
Procedures for coordination with discharges from other
installations referred to in 1.1, third indent
5. DISPOSAL
OF SOLID RADIOACTIVE WASTE FROM THE INSTALLATION
5.1. Solid
radioactive waste
|
—
|
categories of solid radioactive waste and estimated
amounts,
|
|
—
|
processing and packaging,
|
|
—
|
storage arrangements on site.
|
5.2. Radiological
risks to the environment
|
—
|
assessment of risks to the environment,
|
|
—
|
precautions taken.
|
5.3. Off-site
arrangements for the transfer of waste
5.4. Release
of materials from the requirements of the basic safety standards
|
—
|
national strategy, criteria and procedures for the
release of contaminated and activated materials,
|
|
—
|
clearance levels established by competent authorities for
disposal, recycling and reuse,
|
|
—
|
envisaged types and amounts of released materials.
|
6. UNPLANNED
RELEASES OF RADIOACTIVE EFFLUENTS
6.1. Review
of accidents of internal and external origin which could result in unplanned
releases of radioactive substances
List of the accidents studied in the safety report
6.2. Reference
accident(s) taken into consideration by the competent national authorities for
evaluating possible radiological consequences in the case of unplanned releases
Outline of the accident(s) considered and reasons for its
(their) choice
6.3. Evaluation
of the radiological consequences of the reference accident(s)
6.3.1. Accidents
entailing releases to atmosphere
If the assessed maximum exposure levels from the reference
accident to adults, children and infants in the vicinity of the plant are below
1 mSv and there are no exceptional pathways of exposure, e.g. involving the
export of foodstuffs, no data on exposure levels in other affected Member
States are required if exposure levels in the vicinity of the plant are
provided.
|
—
|
assumptions used to calculate the releases to atmosphere,
|
|
—
|
release paths; time patterns of the releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameter values used to calculate for the
releases their atmospheric dispersion, ground deposition, re-suspension and
transfer via food chains and to evaluate the maximum exposure levels via the
significant exposure pathways in the vicinity of the plant and for other
affected Member States,
|
|
—
|
maximum time-integrated concentrations of radioactivity
in the atmosphere near the ground and maximum surface contamination levels
(in dry and wet weather) for the most exposed areas in the vicinity of the
plant and for relevant areas in other affected Member States,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
6.3.2. Accidents
entailing releases into an aquatic environment
If the assessed maximum exposure levels from the reference
accident to adults, children and infants close to the plant are below 1 mSv and
there are no exceptional pathways of exposure, e.g. involving the export of
foodstuffs, no data on exposure levels in other affected Member States are
required if exposure levels in the vicinity of the plant are provided.
|
—
|
assumptions used to calculate the liquid release,
|
|
—
|
release paths, time pattern of releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameters used to calculate for the releases
their aquatic dispersion, their transfer by sedimentation and ion exchange,
their transfer via food chains and to evaluate the maximum exposure levels
via the significant exposure pathways,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
7. EMERGENCY
PLANS, AGREEMENTS WITH OTHER MEMBER STATES
In relation to possible radiological emergencies which may
affect other Member States in order to facilitate the organisation of
radiological protection in these States:
Brief description of:
|
—
|
intervention levels established for different types of
countermeasures,
|
|
—
|
emergency planning arrangements, including the emergency
planning zones adopted for the installation,
|
|
—
|
arrangements in place for the early exchange of
information with other Member States, bilateral or multilateral agreements on
transfrontier information, coordination of emergency plans and their
implementation and mutual assistance,
|
|
—
|
emergency plan testing arrangements with particular
reference to the involvement of other Member States.
|
8. ENVIRONMENTAL
MONITORING
|
—
|
external radiation monitoring,
|
|
—
|
monitoring of radioactive substances in air, water, soil
and the food chains, whether undertaken by the operator or by competent
authorities.
|
With reference to 3.1 and 4.1 above, monitoring programs as
approved by the competent national authorities, organisation, sample forms and
frequency, type of monitoring instruments used in normal and accident
circumstances; where appropriate, any collaboration arrangements in this
respect with neighbouring Member States.
(1) Affected Member States are to be
selected by taking into account distance from the installation, wind direction
for gaseous effluent releases and the route of water courses for liquid
effluent releases.
ANNEX III
General
data applicable to the operations referred to in point 1(9)
The
dismantling of nuclear reactors, mixed-oxide fuel fabrication plants and
reprocessing plants (except research reactors whose maximum power does not
exceed 50 MW continuous thermal load)
Introduction
|
—
|
general presentation of the plan,
|
|
—
|
description of the different decommissioning and
dismantling phases envisaged,
|
|
—
|
decommissioning and dismantling licensing procedures.
|
1. THE
SITE AND ITS SURROUNDINGS
1.1. Geographical,
topographical and geological features of the site and region with
|
—
|
a map of the region showing the location and geographical
coordinates (degrees, minutes) of the site,
|
|
—
|
the relevant features of the region, including geological
features,
|
|
—
|
the location of the installation in relation to such
installations, the discharges from which need to be considered in conjunction
with those from the installation in question,
|
|
—
|
the location of the site with regard to other Member
States giving the distances from frontiers and relevant conurbations,
together with their populations.
|
1.2. Hydrology
For an installation situated near to a waterbody providing
a potential contamination pathway to another Member State, a brief description
of appropriate hydrological features, extending to the other Member State(s),
for example:
|
—
|
brief description of the path(s), tributaries, estuary,
water abstraction, floodplains, etc.,
|
|
—
|
average, maximum and minimum water flows and their
frequency of occurrence,
|
|
—
|
underground water table, levels and flows,
|
|
—
|
brief description of the littoral areas,
|
|
—
|
direction and force of currents, tides, circulation
patterns, both local and regional,
|
|
—
|
flood risk and protection of the installation.
|
1.3. Meteorology
Local climatology with frequency distributions of:
|
—
|
wind directions and speeds,
|
|
—
|
precipitation intensity and duration,
|
|
—
|
for each wind sector, atmospheric dispersion conditions,
duration of temperature inversions,
|
|
—
|
extreme weather phenomena (for example, tornadoes, severe
storms, heavy rainfall, droughts).
|
1.4. Natural
resources and foodstuffs
Brief description of:
|
—
|
water utilisation in the region and as appropriate in
neighbouring Member States,
|
|
—
|
principal food resources in the region and as appropriate
in other Member States: crops, stock breeding, fishing and, for discharges
into sea, data on fishing in territorial and extraterritorial waters,
|
|
—
|
foodstuff distribution system and particularly the export
to other Member States from the regions concerned, in so far as they are
related to the risk of exposure from discharges through the significant exposure
pathways.
|
2. THE
INSTALLATION
2.1. Brief
description and history of the installation to be dismantled
2.2. Ventilation
systems and the treatment of gaseous and airborne wastes
Description of ventilation, decay, filtration and discharge
systems during dismantling, in normal conditions and in the case of an
accident, including flow diagrams
2.3. Liquid
waste treatment
Description of liquid waste treatment facilities during
dismantling, storage capacities and discharge systems, including flow diagrams
2.4. Solid
waste treatment
Description of solid waste treatment facilities and storage
capacities at the site during dismantling
2.5. Containment
Description of systems and provisions to confine
radioactive substances
3. RELEASE
FROM THE INSTALLATION OF AIRBORNE RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
3.1. Authorisation
procedure in force
|
—
|
outline of the procedure in force,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities for the dismantling operations, including the assumed
radionuclide composition,
|
|
—
|
for comparison: discharge limits and associated
requirements in force for the time before the envisaged dismantling
operations, including the radionuclide composition.
|
3.2. Technical
aspects
|
—
|
annual discharges expected during dismantling,
|
|
—
|
origins of the radioactive effluents, their composition
and physico-chemical forms,
|
|
—
|
management of these effluents, methods and paths of
release.
|
3.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of the monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
3.4. Evaluation
of transfer to man
If the assessed maximum exposure levels from releases in
normal conditions to adults, children and infants in the vicinity of the plant
are below 10 μSv per annum and there are no exceptional pathways of exposure,
e.g. involving the export of foodstuffs, no data on effective doses in other
affected (1) Member States are required if doses to the
reference groups in the vicinity of the plant are provided.
3.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the plant and for other affected Member States:
|
—
|
atmospheric dispersion of the effluents,
|
|
—
|
ground deposition and re-suspension,
|
|
—
|
food chains, inhalation, external exposure etc.,
|
|
—
|
living habits (diet, exposure time etc.),
|
|
—
|
other parameter values used in the calculations.
|
3.4.2. Evaluation of the concentration and
exposure levels associated with the envisaged discharge limits for the
dismantling operations cited in 3.1 above:
|
—
|
annual average concentrations of activity in the
atmosphere near the ground and surface contamination levels, for the most
exposed areas in the vicinity of the plant and in other affected Member
States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States, corresponding annual exposure levels:
effective dose to adults, children and infants, taking account of all significant
exposure pathways.
|
4. RELEASE
FROM THE INSTALLATION OF LIQUID RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
4.1. Authorisation
procedure in force
|
—
|
outline of the general procedure involved,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities for the dismantling operations, including the assumed
radionuclide composition,
|
|
—
|
for comparison: discharge limits and associated
requirements in force before the envisaged dismantling operations, including
the radionuclide composition.
|
4.2. Technical
aspects
|
—
|
annual discharges expected during dismantling,
|
|
—
|
origins of the radioactive effluents, their composition
and physico-chemical forms,
|
|
—
|
management of the effluents, methods and paths of
release.
|
4.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
4.4. Evaluation
of transfer to man
If the assessed maximum exposure levels from releases in
normal conditions to adults, children and infants in the vicinity of the plant
are below 10 μSv per annum and there are no exceptional pathways of exposure,
e.g. involving the export of foodstuffs, no data on effective doses in other
affected Member States are required if doses to reference groups in the
vicinity of the plant are provided.
4.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the plant and for other affected Member States:
|
—
|
aquatic dispersion of the effluents,
|
|
—
|
their transfer by sedimentation and ion exchange,
|
|
—
|
food chains, inhalation of sea spray, external exposure,
etc.,
|
|
—
|
living habits (diet, exposure time etc.),
|
|
—
|
other parameter values used in the calculations.
|
4.4.2. Evaluation of the concentration and
exposure levels associated with the envisaged discharge limits for the
dismantling operations cited in 4.1 above:
|
—
|
annual average concentrations of activity in surface
waters, at the points where such concentrations are highest, in the vicinity
of the plant and in other affected Member States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States, corresponding annual exposure levels:
effective dose to adults, children and infants, taking account of all
significant exposure pathways.
|
5. DISPOSAL
OF SOLID RADIOACTIVE WASTE FROM THE INSTALLATION
5.1. Solid
radioactive wastes
|
—
|
categories of solid radioactive wastes and estimated
amounts,
|
|
—
|
processing and packaging,
|
|
—
|
storage arrangements on site.
|
5.2. Radiological
risks to the environment
|
—
|
assessment of risks to the environment,
|
|
—
|
precautions taken.
|
5.3. Off-site
arrangements for the transfer of waste
5.4. Release
of materials from the requirements of the basic safety standards
|
—
|
national strategy, criteria and procedures for the
release of contaminated and activated materials,
|
|
—
|
clearance levels established by competent authorities for
disposal, recycling or reuse,
|
|
—
|
envisaged types and amounts of released materials.
|
6. UNPLANNED
RELEASES OF RADIOACTIVE EFFLUENTS
6.1. Review
of accidents of internal and external origin which could result in unplanned releases
of radioactive substances
List of the accidents studied in the safety report
6.2. Reference
accident(s) taken into consideration by the competent national authorities for
evaluating possible radiological consequences in the case of unplanned releases
Outline of the accident(s) considered and reasons for its
(their) choice
6.3. Evaluation
of the radiological consequences of the reference accident(s)
6.3.1. Accidents
entailing releases to atmosphere
If the assessed maximum exposure levels from the reference
accident to adults, children and infants in the vicinity of the plant are below
1 mSv and there are no exceptional pathways of exposure, e.g. involving the
export of foodstuffs, no data on exposure levels in other affected Member
States are required if exposure levels in the vicinity of the plant are
provided.
|
—
|
assumptions used to calculate the releases to atmosphere,
|
|
—
|
release paths; time patterns of the releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameter values used to calculate for the
releases their atmospheric dispersion, ground deposition, re-suspension and
transfer via food chains and to evaluate the maximum exposure levels via the
significant exposure pathways in the vicinity of the plant and for other
affected Member States,
|
|
—
|
maximum time-integrated concentrations of radioactivity
in the atmosphere near the ground and maximum surface contamination levels
(in dry and wet weather) for the most exposed areas in the vicinity of the
plant and for relevant areas in other affected Member States,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants in the vicinity of the plant and in relevant
areas of other affected Member States taking account of all significant
exposure pathways.
|
6.3.2. Accidents
entailing releases into an aquatic environment
If the assessed maximum exposure levels from the reference
accident to adults, children and infants close to the plant are below 1 mSv and
there are no exceptional pathways of exposure, e.g. involving the export of
foodstuffs, no data on exposure levels in other affected Member States are
required if exposure levels in the vicinity of the plant are provided.
|
—
|
assumptions used to calculate the liquid release,
|
|
—
|
release paths, time pattern of releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameters used to calculate for the releases
their aquatic dispersion, their transfer by sedimentation and ion exchange,
their transfer via food chains and to evaluate the maximum exposure levels
via the significant exposure pathways,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
7. EMERGENCY
PLANS, AGREEMENTS WITH OTHER MEMBER STATES
In relation to possible radiological emergencies which may
affect other Member States in order to facilitate the organisation of
radiological protection in these States:
Brief description of:
|
—
|
intervention levels established for different types of
countermeasures,
|
|
—
|
emergency planning arrangements, including the emergency
planning zones adopted for the installation,
|
|
—
|
arrangements in place for the early exchange of
information with other Member States, bilateral or multilateral agreements on
transfrontier information, coordination of emergency plans and their
implementation and mutual assistance,
|
|
—
|
emergency plan testing arrangements with particular
reference to the involvement of other Member States.
|
In the case of reactors no data are required if all nuclear
fuel has been transferred off-site to a licensed facility or to an on-site
storage facility, on which an opinion has already been given under the terms of
Article 37.
8. ENVIRONMENTAL
MONITORING
|
—
|
external radiation monitoring,
|
|
—
|
monitoring of radioactive substances in air, water, soil
and the food chains, whether undertaken by the operator or by competent
authorities.
|
With reference to 3.1 and 4.1 above, monitoring programs as
approved by the competent national authorities, organisation, sample forms and
frequency, type of monitoring instruments used in normal and accident
circumstances; where appropriate, any collaboration arrangements in this
respect with neighbouring Member States.
(1) Affected Member States are to be
selected by taking into account distance from the installation, wind direction
for gaseous effluent releases and the route of water courses for liquid
effluent releases.
ANNEX IV
General
data applicable to the operations referred to in point 1(10)
The
emplacement of radioactive waste above or under the ground without intention of
retrieval
Introduction
|
—
|
general presentation of the waste emplacement plan,
|
|
—
|
general presentation of the repository, type and class of
waste,
|
|
—
|
present stage of project and licensing procedure,
envisaged commissioning and licensing steps,
|
|
—
|
timescale, envisaged starting date, operational period
and closure date.
|
1. THE
SITE AND ITS SURROUNDINGS
1.1. Geographical,
topographical and geological features of the site and the region with
|
—
|
a map of the region showing the location and geographical
coordinates (degrees, minutes) of the site,
|
|
—
|
the relevant features of the region, including geological
features,
|
|
—
|
the location of the repository in relation to such other
installations, the discharges from which need to be considered in conjunction
with those from the installation in question,
|
|
—
|
the location of the site with regard to other Member
States giving the distances from frontiers and closest conurbations, together
with their populations,
|
|
—
|
anticipated changes in geography and topography over the
time period considered for the assessment of post-closure impact.
|
1.2. Geology
and seismology
|
—
|
geological setting,
|
|
—
|
active tectonic processes, historical earthquakes, the
degree of seismic activity in the region; probable maximum seismic activity,
|
|
—
|
structural and geotechnical soil characteristics, soil liquefaction
(as appropriate),
|
|
—
|
surface processes (landslides and erosion) (1),
|
|
—
|
anticipated changes in geology over the time period
considered for the assessment of post-closure impact.
|
1.3. Hydrology
and hydrogeology
A brief description of hydrological features providing a
potential contamination pathway to another Member State:
|
—
|
regional and local water tables and their seasonal
variations,
|
|
—
|
ground water flow direction and velocity, water discharge
and extraction points,
|
|
—
|
existing and projected major water users, location of the
repository with respect to potential potable water aquifers,
|
|
—
|
brief description of the surface water bodies (rivers,
lakes, estuary, water abstraction, floodplains, etc.) and littoral areas (as
appropriate),
|
|
—
|
average, maximum and minimum water flows and their
frequency of occurrence (as appropriate),
|
|
—
|
chemical composition of ground water,
|
|
—
|
flood risk and protection of the installation (as
appropriate),
|
|
—
|
anticipated changes in hydrology, hydrogeology over the
time period considered for the assessment of post-closure impact.
|
1.4. Meteorology
and climate
A brief description of climate and meteorological features:
|
—
|
wind directions and speeds,
|
|
—
|
precipitation intensity (rain and snow) and duration,
|
|
—
|
temperature (average, minimal and maximal),
|
|
—
|
atmospheric dispersion conditions,
|
|
—
|
extreme weather phenomena (for example, tornadoes, severe
storms, heavy rainfalls, droughts) (1),
|
|
—
|
anticipated changes of climate (for example, glacial
effects, potential impact of global warming), and, for coastal sites, sea
level changes and coastal erosion over the time period considered for the
assessment of post-closure impact.
|
1.5. Natural
resources and foodstuffs
A brief description of:
|
—
|
water utilisation in the region and as appropriate in
neighbouring Member States,
|
|
—
|
principal food resources in the region and as appropriate
in other Member States: crops, stock breeding, fishing and, for discharges
into sea, data on fishing in territorial and extraterritorial waters,
|
|
—
|
foodstuff distribution system and particularly the export
to other Member States from the regions concerned, in so far as they are
related to the risk of exposure from discharges through the significant
exposure pathways,
|
|
—
|
assumptions made on future population patterns, habits
and food sources.
|
1.6. Other
activities in the vicinity of the site
|
—
|
where appropriate, other nuclear facilities and any
hazardous industrial or military activities, surface and aerial traffic,
pipelines, storages and any other factors which may have an influence on the
safety of the installation,
|
|
—
|
protection measures (as appropriate),
|
|
—
|
anticipated evolution of activities over the time period
considered for the assessment of long-term impact.
|
2. THE
REPOSITORY
2.1. Conceptual
approach and design
|
—
|
disposal concept,
|
|
—
|
depth and location in relation to geological strata (as
appropriate) (2),
|
|
—
|
design criteria for natural phenomena,
|
|
—
|
waste emplacement methods, backfill and sealing strategy
and methods,
|
|
—
|
safety approach: role of the geological and engineered
barriers,
|
|
—
|
closure of repository,
|
|
—
|
approach to retrievability of waste (if applicable),
|
|
—
|
auxiliary waste treatment, conditioning and buffer
storage facilities to be constructed at the site of the repository.
|
2.2. Wastes
to be disposed of in the repository
|
—
|
types of waste,
|
|
—
|
waste form, applied conditioning methods and
characteristics of waste packages (as appropriate),
|
|
—
|
waste inventory; amounts and radionuclide activities,
|
|
—
|
potential heat generation, potential gas generation,
potential criticality (as appropriate),
|
|
—
|
waste acceptance requirements/criteria, waste package
verification procedure and techniques to ensure compliance with established
waste acceptance criteria.
|
2.3. Ventilation
systems and the treatment of gaseous and airborne wastes
Description of ventilation, filtration and discharge
systems, in normal conditions and in the case of an accident (as
appropriate)
2.4. Drainage
system and the treatment of liquid effluents
Description of potentially contaminated water collection,
drainage and discharge systems, in normal conditions and in the case of an
accident (as appropriate)
2.5. Management
of secondary solid and liquid waste in normal conditions and in the case of an
accident
|
—
|
categories of secondary liquid and solid radioactive
waste and estimated amounts,
|
|
—
|
storage and transportation of waste,
|
|
—
|
treatment of waste.
|
3. RELEASE
FROM THE INSTALLATION OF AIRBORNE RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
During normal operation of waste disposal facilities only
very minor releases of radioactive substances, if any, are expected and
significant exposure of members of the public is not anticipated. Therefore
this section is not applicable if there is no authorisation for radioactive
discharges granted. However, if radionuclide discharge limits are prescribed
and discharge monitoring is in place, the general data must be submitted
according requirements specified in Section 3 of Annex II.
4. RELEASE
FROM THE INSTALLATION OF LIQUID RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
During normal operation of waste disposal facilities only
very minor releases of radioactive substances, if any, are expected and
significant exposure of members of the public is not anticipated. Therefore
this section is not applicable if there is no authorisation for radioactive
discharges granted. However, if radionuclide discharge limits are prescribed
and discharge monitoring is in place, the general data must be submitted
according requirements specified in Section 4 of Annex II.
5. DISPOSAL
OF SOLID RADIOACTIVE WASTE FROM THE INSTALLATION
This section is normally not applicable.
6. UNPLANNED
RELEASES OF RADIOACTIVE EFFLUENTS
6.1. Review
of accidents of internal and external origin which could result in unplanned
releases of radioactive substances. Accidents studied in the safety assessment
report and evaluated radiological consequences in the case of unplanned
releases.
6.2. Evaluation
of the radiological consequences of releases to atmosphere
If the assessed maximum exposure levels from the reference
accident to adults, children and infants in the vicinity of the plant are below
1 mSv and there are no exceptional pathways of exposure, e.g. involving the
export of foodstuffs, no data on exposure levels in other affected (3) Member States are required if exposure
levels in the vicinity of the plant are provided.
|
—
|
assumptions used to calculate the releases to atmosphere,
|
|
—
|
release paths; time patterns of the releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameter values used to calculate for the
releases their atmospheric dispersion, ground deposition, re-suspension and
transfer via food chains and to evaluate the maximum exposure levels via the
significant exposure pathways in the vicinity of the plant and for other
affected Member States,
|
|
—
|
maximum time-integrated concentrations of radioactivity
in the atmosphere near the ground and maximum surface contamination levels
(in dry and wet weather) for the most exposed areas in the vicinity of the
plant and for relevant areas in other affected Member States,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
6.3. Evaluation
of the radiological consequences of releases into an aquatic environment
If the assessed maximum exposure levels from the reference
accident to adults, children and infants close to the plant are below 1 mSv and
there are no exceptional pathways of exposure, e.g. involving the export of
foodstuffs, no data on exposure levels in other affected Member States are
required if exposure levels in the vicinity of the plant are provided.
|
—
|
assumptions used to calculate the liquid release,
|
|
—
|
release paths, time pattern of releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameters used to calculate for the releases
their aquatic dispersion, their transfer by sedimentation and ion exchange,
their transfer via food chains and to evaluate the maximum exposure levels
via the significant exposure pathways,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
7. EMERGENCY
PLANS; AGREEMENTS WITH OTHER MEMBER STATES
In relation to possible radiological emergencies which may
affect other Member States in order to facilitate the organisation of
radiological protection in these States:
Brief description of:
|
—
|
intervention levels established for different types of
countermeasures,
|
|
—
|
emergency planning arrangements, including the emergency
planning zones adopted for the installation,
|
|
—
|
arrangements in place for the early exchange of
information with other Member States, bilateral or multilateral agreements on
transfrontier information, coordination of emergency plans and their
implementation and mutual assistance,
|
|
—
|
emergency plan testing arrangements with particular
reference to the involvement of other Member States.
|
8. POST-CLOSURE
PERIOD
The different post-closure phases (e.g. active and passive
institutional control phases) should be taken into account where appropriate.
8.1. Regulatory
and administrative provisions
|
—
|
plans for the repository closure,
|
|
—
|
time periods considered (periods of active and passive
institutional control),
|
|
—
|
description of measures foreseen for active institutional
control period,
|
|
—
|
description of measures foreseen for passive
institutional control period,
|
|
—
|
record-keeping,
|
|
—
|
dismantling programme for auxiliary installations,
|
|
—
|
periodical safety reviews before closure.
|
8.2. Radiological
impact during post-closure period
If the assessed maximum exposure levels from releases
resulting from normal evolution and from early degradation of barriers to
adults, children and infants in the vicinity of the installation are below 1
mSv per annum and there are no exceptional pathways of exposure, e.g. involving
the export of foodstuffs, no data on effective doses in other affected Member
States are required if doses to reference groups in the vicinity of the plant
are provided.
|
—
|
redundancy and performance of barriers (if relevant),
|
|
—
|
time periods considered,
|
|
—
|
analysed features, events and processes, description of
scenarios assumed (brief descriptions of the normal evolution scenario, most
relevant degraded evolution scenarios and human intrusion scenarios),
|
|
—
|
methods and techniques used for assessment of
radiological impact,
|
|
—
|
parameters and assumptions,
|
|
—
|
main exposure pathways in vicinity of repository and
other affected Member States resulting from normal evolution and for early
degradation of barriers,
|
|
—
|
activity and timing of radionuclide release,
|
|
—
|
corresponding maximum exposure levels: effective doses
and/or estimated risks to adults, children and infants living in the vicinity
of the plant and in relevant areas of other affected Member States taking
account of all significant exposure pathways,
|
|
—
|
evaluation of the uncertainties.
|
9. ENVIRONMENTAL
MONITORING
|
—
|
operational monitoring of external radiation and
radioactive substances in air, water, soil and the food chains, whether
undertaken by the operator or by competent authorities (sample forms and
frequency, type of monitoring instruments used in normal and accident
circumstances),
|
|
—
|
guidelines for post-closure monitoring of radioactive
substances in air, water, soil and the food chains, whether undertaken by the
operator or by competent authorities (1),
|
|
—
|
any collaboration arrangements with neighbouring Member
States in respect of environmental monitoring.
|
Notes:
(1) Relevant for new surface
repositories only.
(2) Relevant for geological repositories
only.
(3) Affected Member States are to be
selected by taking into account distance from the installation, wind direction
for gaseous effluent releases and the route of water courses for liquid
effluent releases.
ANNEX V
General
data applicable to modifications of a plan on which an opinion has already been
given
STANDARD
FORM
|
1.
|
Name and location of the facility concerned:
|
|
2.
|
Date of the Commission’s Opinion:
|
|
3.
|
Brief description of the planned modifications:
|
|
4.
|
Authorised discharge limits in the existing plan, and
other relevant conditions:
|
|
4.1.
|
Gaseous effluents:
|
|
4.2.
|
Liquid effluents:
|
|
4.3.
|
Solid waste:
|
|
5.
|
New discharge limits envisaged by the authorities,
including modifications in the assumed radionuclide composition, and other
relevant conditions:
|
|
5.1.
|
Gaseous effluents:
|
|
5.2.
|
Liquid effluents:
|
|
5.3.
|
Solid waste:
|
|
6.
|
Consequences of the new discharge limits and associated
requirements (gaseous and/or liquid effluents) in relation to the evaluation
of the exposure of the population in other Member States:
|
|
7.
|
Consequences of the modifications in relation to the
disposal of solid waste:
|
|
8.
|
Consequences of the modifications in relation to the
reference accident(s) taken into account in the previous opinion:
|
|
9.
|
In the case of new reference accident(s): description and
evaluation of the radiological consequences:
|
|
10.
|
Implications of the modifications in relation to the
current emergency plans and the current environmental monitoring:
|
ANNEX VI
General
data applicable to modifications of a plan on which no opinion has been given
yet
Introduction
|
—
|
general presentation of the plan,
|
|
—
|
present stage of licensing procedure.
|
1. THE
SITE AND ITS SURROUNDINGS
1.1. Geographical,
topographical and geological features of the site and the region with
|
—
|
a map of the region showing the location and geographical
coordinates (degrees, minutes) of the site,
|
|
—
|
the relevant features of the region, including geological
features,
|
|
—
|
the location of the installation in relation to such
other installations, the discharges from which need to be considered in
conjunction with those from the installation in question,
|
|
—
|
the location of the site with regard to other Member
States giving the distances from frontiers and closest conurbations, together
with their populations.
|
1.2. Hydrology
Data mentioned in this section 1.2 are required only if the
modification of the discharges from the plant of liquid radioactive effluents
in normal conditions envisages less restrictive authorised limits or associated
requirements than in the existing plan or if the potential consequences of the
reference accident(s) entailing releases into an aquatic environment are
increased.
For an installation situated near to a waterbody providing
a potential contamination pathway to another Member State, a brief description
of appropriate hydrological features, extending to the other Member State(s),
for example:
|
—
|
brief description of the path(s), tributaries, estuary,
water abstraction, floodplains, etc.,
|
|
—
|
average, maximum and minimum water flows and their
frequency of occurrence,
|
|
—
|
brief description of the littoral areas,
|
|
—
|
direction and force of currents, tides, circulation
patterns, both local and regional.
|
1.3. Meteorology
Data mentioned in this section 1.3 are required only if the
modification of the discharges from the plant of gaseous radioactive effluents
in normal conditions envisages less restrictive authorised limits or associated
requirements than in the existing plan or if the potential consequences of the
reference accident(s) entailing releases to atmosphere are increased.
Local climatology with frequency distributions of:
|
—
|
wind directions and speeds,
|
|
—
|
precipitation intensity and duration,
|
|
—
|
for each wind sector, atmospheric dispersion conditions,
duration of temperature inversions,
|
|
—
|
extreme weather phenomena (for example, tornadoes, severe
storms, heavy rainfall, droughts).
|
1.4. Natural
resources and foodstuffs
Brief description of:
|
—
|
water utilisation in the region and as appropriate in
neighbouring Member States,
|
|
—
|
principal food resources in the region and as appropriate
in other Member States: crops, stock breeding, fishing, hunting and, for
discharges into sea, data on fishing in territorial and extraterritorial
waters,
|
|
—
|
foodstuff distribution system and particularly the export
to other Member States from the regions concerned, in so far as they are
related to the risk of exposure from discharges through the significant
exposure pathways.
|
2. THE
INSTALLATION
|
—
|
brief description of the installation,
|
|
—
|
type, purpose and main features of the processes,
|
|
—
|
site layout plan,
|
|
—
|
safety provisions,
|
|
—
|
waste treatment,
|
|
—
|
relevant details of the modification.
|
3. RELEASE
FROM THE INSTALLATION OF AIRBORNE RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
Data mentioned in this section 3 are required only if the
modification of the discharges from the plant of gaseous radioactive effluents
in normal conditions envisages less restrictive authorised limits or associated
requirements than in the existing plan.
3.1. Authorisation
procedure in force
|
—
|
outline of the procedure in force,
|
|
—
|
current authorisation limits,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities, including the assumed radionuclide composition.
|
3.2. Technical
aspects
|
—
|
annual discharges expected,
|
|
—
|
composition and physico-chemical forms of the radioactive
effluents,
|
|
—
|
management of these effluents, methods and paths of
release.
|
3.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of the monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
3.4. Evaluation
of transfer to man
If the assessed maximum exposure levels from releases in
normal conditions to adults, children and infants in the vicinity of the plant
are below 10 μSv per annum and there are no exceptional pathways of exposure,
e.g. involving the export of foodstuffs, no data on effective doses in other
affected Member States are required if doses to the reference groups in the
vicinity of the plant are provided.
3.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the installation and for other affected (1) Member States:
|
—
|
atmospheric dispersion of the effluents,
|
|
—
|
ground deposition and re-suspension,
|
|
—
|
food chains, inhalation, external exposure, etc.,
|
|
—
|
living habits (diet, exposure time, etc.),
|
|
—
|
other parameter values used in the calculations.
|
3.4.2. Evaluation of the concentration and
exposure levels associated with the envisaged discharge limits cited in 3.1
above:
|
—
|
annual average concentrations of activity in the
atmosphere near the ground and surface contamination levels, for the most
exposed areas in the vicinity of the plant and in other affected Member
States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States, corresponding annual exposure levels:
effective dose to adults, children and infants, taking account of all
significant exposure pathways.
|
3.5. Radioactive
discharges to atmosphere from other installations
Procedures for coordination with radioactive discharges
from other installations referred to in 1.1, third indent
4. RELEASE
FROM THE INSTALLATION OF LIQUID RADIOACTIVE EFFLUENTS IN NORMAL CONDITIONS
Data mentioned in this section 4 are required only if the
modification of the discharges from the plant of liquid radioactive effluents
in normal conditions envisages less restrictive authorised limits or associated
requirements than in the existing plan.
4.1. Authorisation
procedure in force
|
—
|
outline of the general procedure involved,
|
|
—
|
current authorisation limits,
|
|
—
|
discharge limits and associated requirements envisaged by
the authorities, including the assumed radionuclide composition.
|
4.2. Technical
aspects
|
—
|
annual discharges expected,
|
|
—
|
composition and physico-chemical forms of the radioactive
effluents,
|
|
—
|
management of the effluents, methods and paths of
release.
|
4.3. Monitoring
of discharges
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
4.4. Evaluation
of transfer to man
If the assessed maximum exposure levels from releases in
normal conditions to adults, children and infants in the vicinity of the plant
are below 10 μSv per annum and there are no exceptional pathways of
exposure, e.g. involving the export of foodstuffs, no data on effective doses
in other affected Member States are required if doses to reference groups in
the vicinity of the plant are provided.
4.4.1. Models, including where appropriate
generic models, and parameter values used to calculate the consequences of the
releases in the vicinity of the plant and for other affected Member States:
|
—
|
aquatic dispersion of the effluents,
|
|
—
|
their transfer by sedimentation and ion exchange,
|
|
—
|
food chains, inhalation of sea spray, external exposure,
etc.,
|
|
—
|
living habits (diet, exposure time, etc.),
|
|
—
|
other parameter values used in the calculations.
|
4.4.2. Evaluation of concentration and
exposure levels associated with the discharge limits cited in 4.1 above:
|
—
|
annual average concentrations of activity in surface
waters, at the points where such concentrations are highest, in the vicinity
of the plant and in other affected Member States,
|
|
—
|
for the reference group(s) in the vicinity of the plant
and in other affected Member States: effective dose to adults, children and
infants, taking account of all significant exposure pathways.
|
4.5. Radioactive
discharges into the same receiving waters from other installations
Procedures for coordination with discharges from other
installations referred to in 1.1, third indent
5. DISPOSAL
OF SOLID RADIOACTIVE WASTE FROM THE INSTALLATION
Data mentioned in this section 5 are required only if the
modification of the disposal from the plant of solid radioactive waste in
normal conditions envisages less restrictive authorised limits or associated
requirements than in the existing plan.
5.1. Solid
radioactive waste
|
—
|
categories of solid radioactive waste and estimated
amounts,
|
|
—
|
processing and packaging,
|
|
—
|
storage arrangements on site.
|
5.2. Radiological
risks to the environment
|
—
|
assessment of risks to the environment,
|
|
—
|
precautions taken.
|
5.3. Off-site
arrangements for the transfer of waste
5.4. Release
of materials from the requirements of the basic safety standards
|
—
|
national strategy, criteria and procedures for the
release of contaminated or activated materials,
|
|
—
|
clearance levels established by competent authorities for
disposal, recycling and reuse,
|
|
—
|
envisaged types and amounts of released materials.
|
6. UNPLANNED
RELEASES OF RADIOACTIVE EFFLUENTS
Data mentioned in this section 6 are required only if the
potential consequences of the reference accident(s) are increased.
6.1. Review
of accidents of internal and external origin which could result in unplanned
releases of radioactive substances
List of the accidents studied in the safety report
6.2. Reference
accident(s) taken into consideration by the competent national authorities for
evaluating possible radiological consequences in the case of unplanned releases
Outline of the accident(s) considered and reasons for its
(their) choice
Impact of the modification on the reference accident(s)
6.3. Evaluation
of the radiological consequences of the reference accident(s)
6.3.1. Accidents
entailing releases to atmosphere
Data mentioned in this section 6.3.1 are required only if
the potential consequences of the reference accident(s) entailing releases to
atmosphere are increased.
If the assessed maximum exposure levels from the reference
accident to adults children and infants in the vicinity of the plant are below
1 mSv and there are no exceptional pathways of exposure, e.g. involving
the export of foodstuffs, no data on exposure levels in other affected Member
States are required if exposure levels in the vicinity of the plant are
provided.
|
—
|
assumptions used to calculate the releases to atmosphere,
|
|
—
|
release paths; time patterns of the releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameter values used to calculate for the
releases their atmospheric dispersion, ground deposition, re-suspension and
transfer via food chains and to evaluate the maximum exposure levels via the
significant exposure pathways in the vicinity of the plant and for other
affected Member States,
|
|
—
|
maximum time-integrated concentrations of radioactivity
in the atmosphere near the ground and maximum surface contamination levels
(in dry and wet weather) for the most exposed areas in the vicinity of the
plant and for relevant areas in other affected Member States,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
If not already submitted under heading 3.3:
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of the monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
6.3.2. Accidents
entailing releases into an aquatic environment
Data mentioned in this section 6.3.2 are required only if
the potential consequences of the reference accident(s) entailing releases into
an aquatic environment are increased.
If the assessed maximum exposure levels from the reference
accident to adults children and infants close to the plant are below 1 mSv and
there are no exceptional pathways of exposure, e.g. involving the export of
foodstuffs, no data on exposure levels in other affected Member States are
required if exposure levels in the vicinity of the plant are provided.
|
—
|
assumptions used to calculate the liquid release,
|
|
—
|
release paths, time pattern of releases,
|
|
—
|
amounts and physico-chemical forms of those radionuclides
released which are significant from the point of view of health,
|
|
—
|
models and parameters used to calculate for the releases
their aquatic dispersion, their transfer by sedimentation and ion exchange,
their transfer via food chains and to evaluate the maximum exposure levels
via the significant exposure pathways,
|
|
—
|
expected levels of radioactive contamination of
foodstuffs which might be exported to other affected Member States,
|
|
—
|
corresponding maximum exposure levels: effective dose to
adults, children and infants living in the vicinity of the plant and in
relevant areas of other affected Member States taking account of all
significant exposure pathways.
|
If not already submitted under heading 4.3:
|
—
|
sampling, measurement and analysis of discharges, whether
undertaken by the operator or by competent authorities,
|
|
—
|
principal features of the monitoring equipment,
|
|
—
|
alarm levels, intervention actions (manual and
automatic).
|
7. EMERGENCY
PLANS; AGREEMENTS WITH OTHER MEMBER STATES
In relation to possible radiological emergencies which may
affect other Member States in order to facilitate the organisation of
radiological protection in these States
Brief description of:
|
—
|
intervention levels established for different types of
countermeasures,
|
|
—
|
emergency planning arrangements, including the emergency
planning zones adopted for the installation,
|
|
—
|
arrangements in place for the early exchange of
information with other Member States, bilateral or multilateral agreements on
transfrontier information, coordination of emergency plans and their
implementation and mutual assistance,
|
|
—
|
emergency plan testing arrangements with particular
reference to the involvement of other Member States.
|
8. ENVIRONMENTAL
MONITORING
Relevant information in relation with the modification
(1) Affected Member States are to be
selected by taking into account distance from the installation, wind direction
for gaseous effluent releases and the route of water courses for liquid
effluent releases.
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