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Decree No. 2006-154 Of February 8, 2006 Authorizing The Commissioner To Atomic Energy To Proceed To The

Original Language Title: Décret n° 2006-154 du 8 février 2006 autorisant le Commissariat à l'énergie atomique à procéder au

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Keywords

ECONOMY , INDUSTRY , ENERGY , COMMISSION HAS ATOMIC ENERGY , CEA , PROCEDURE , SET THE ARRET , ARRET DEFINITIF , DEMANTELEMENT , NUCLEOLAR INSTALLATION , BASIC NUCLEAR INSTALLATION , APPOINTMENT , ENRICHED URANIUM WORKSHOP , ATUE , MOUTHS-OF THE RHONE , TECHNICAL PRESCRIPTION , WORKER PROTECTION , PERSON'S SECURITY , POLLUTION CONTROL


JORF No. 39 of 15 February 2006 Page 2318
Text #5


DECRET
Decree No. 2006-154 of 8 February 2006 authorizing the Office of the Atomic Energy Commission to carry out the operations for the final cessation and dismantling of the basic nuclear facility n ° 52 Enriched uranium workshop on the territory of the commune of Saint-Paul-lez-Durance (Bouches-du-Rhône)

NOR: INDI0506497D ELI: http://www.legifrance.gouv.fr/eli/decret/2006/2/8/INDI0506497D/jo/texte
Alias: http://www.legifrance.gouv.fr/eli/decret/2006/2/8/2006-154/jo/texte


Prime Minister,
On the report of the Minister of Economy, Finance and Industry and the Minister of Ecology and Sustainable Development,
Given the code of The environment;
Given the code of public health;
Given the Labour Code;
In the light of Law No. 61-842 of 2 August 1961 on the fight against atmospheric pollution and odours;
In view of Decree No. 63-1228 of 11 December
No 75-306 of 28 April 1975 on the protection of workers against the dangers of ionising radiation in installations Basic nuclear, in particular Articles 45-1, 45-2 and 45-3;
In view of Decree No. 77-1141 of 12 October 1977, as amended for the application of Article 2 of Law No. 76-629 of 10 July 1976 on the protection of nature;
Given the order Of 10 August 1984 on the quality of the design, construction and operation of the basic nuclear installations;
In view of the Decree of 31 December 1999 laying down general technical regulations to prevent and limit Nuisance and external risks arising from the operation of the basic nuclear installations;
In view of the declaration of the workshop facility enriched uranium to the Minister of State for Scientific Research and Atomic Questions and Space by letter from the Deputy Head of the Office of the Atomic Energy Commissioner dated January 8, 1968;
Based on the request made on March 11, 1998, by the Office of the Atomic Energy Commissioner and the file attached to this application;
In view of the opinion Issued by the Interdepartmental Committee on Basic Nuclear Facilities at its meeting on April 29, 2005;
In light of the Minister's Health Minister's assent of November 30, 2005,
Describes:

Item 1
The provisions relating to the final cessation and dismantling of the enriched uranium workshop (ATUE) located on the territory of the commune of Saint-Paul-lez-Durance in the Bouches-du-Rhône provided for in the following documents:
-the document justifying the condition chosen for the installation after its final stop and indicating the steps of its subsequent dismantling;
-the security report applicable to the Decommissioning and decommissioning operations and provisions to ensure the safety of the installation;
-the general rules for monitoring and maintenance to ensure a satisfactory level of
to Article 6 ter of the aforementioned Decree of 11 December 1963, in support of the aforementioned letter of the Office of the Atomic Energy Commissioner, shall be approved subject to the specific conditions prescribed by the present The
emergency plan of the site is not affected by these operations, it is updated independently, taking into account the decommissioning of the basic nuclear facility.

Article 2 Read more about this article ...


The Office of the Atomic Energy Commission, in its capacity as the operator of the basic nuclear facility referred to in Article 1, complies with all obligations Laid down by the Decree of 11 December 1963 and by the Decree of 31 December 1999 referred to above, to the general technical requirements referred to in Article 5, to the special technical requirements referred to in Article 5 and to the other Legislative and regulatory provisions in force, including:
-labour law enforcement;
-environmental protection;
-waste management;
-technology risk prevention;
- Radiation protection.

Item 3 Learn more about this Article ...


The operator complies with the general technical requirements listed below:


3.1. Pre-Shutdown and Decommissioning
Operations Obligations


Prior to opening a worksite for the final shutdown and dismantling operations, the operator:
- Defines the intervention perimeters, the circulations of personnel, equipment and waste and the arrangements made to prevent the possible transfer of radioactive contamination from the site area to the areas not affected by the Decommissioning and decommissioning operations;
-drafts procedures and operating procedures relating to the decommissioning and decommissioning operations as well as the safety and radiation protection analyses And related instructions.


3.2. Modifying the
shutdown and decommissioning operations


The final shutdown and dismantling operations of the enriched uranium workshop are performed under the conditions defined in the Documents referred to in Article 1.
The Director General of Nuclear Safety and Radiation Protection shall be notified by the operator of any modification resulting in an update of the installation security documents: safety report, General rules for monitoring and maintenance, internal emergency plan.
Are subject to the authorization of the Director General of Nuclear Safety and Radiation Protection the amendments, even temporary, that call into question the demonstration Security of the facility, as set out in the security report. For any other amendment, the operator may, if deemed necessary, seek the authorization of the Director General of Nuclear Safety and Radiation Protection.


3.3. Control of systems involved in safety


The proper functioning of the various systems or apparatus involved in the safety of the installation during the operations of the final stop and the dismantling of the workshop Enriched uranium is controlled in accordance with the regulations in force and according to a frequency specified in the general supervision and maintenance rules, and after any intervention on such equipment. In particular, the proper functioning of radiation detection, safety and driving devices is subject to regular monitoring and maintenance operations in order to provide reliable indications for detecting developments Important parameters for security and for ensuring the safe maintenance of facilities. The relevant documents are archived and made available to inspectors of the basic nuclear facilities.


3.4. Quality of installation


In accordance with the order of August 10, 1984, the operator shall ensure that the elements of the modified installation are obtained as appropriate by the implementation of a controlled set Planned and systematic actions, based on written and archived procedures.
The operator shall carry out a census, classification and archiving of all documents relating to the operations covered by this Decree (in particular Description and balance sheet of the operations carried out, the radiological state achieved). It ensures the continuity of this archive.


3.5. Confinement and Protection against the Risk of Release of Radioactive Substances


The installation is monitored in such a way that all applicable rules on protection against Release of radioactive substances within the facility and in its environment.
The reporting of this monitoring is addressed annually to the Director General of Nuclear Safety and Radiation
. Significant alarms for security are carried forward to premises where permanent security is maintained. In installations and locations known to the response services, detailed information is used to locate the detected event and to act effectively.


3.6. Protection of workers and the public
against exposure to ionizing radiation


Restricted areas are restricted within the facility under the conditions laid down in Article R. 231-81 of the Work.
In accordance with the current regulations on the limitation of annual doses that may be received by workers and the public, appropriate measures are taken to ensure that individual effective doses and Workers and the public remain as weak as reasonably possible. Passive dosimetry readings must be included in the annual safety record of the facility.
At the end of the final shutdown and dismantling of the facility, the operator shall forward to the Director General A radiological assessment covering the period of such operations.


3.7. Waste Management


The operator strives to reduce the volume of waste generated during the decommissioning and decommissioning operations and optimizes their management by ensuring that they are valued or treated Whenever possible, the final storage to be reserved for the final waste.
Without prejudice to the application of the public health code, the waste resulting from the abovementioned operations shall be sorted by nature and by Category of chemical or radioactive nuisance in order to facilitate their treatment, reuse or recycling, packaging and subsequent storage in licensed centres.
The operator shall make all arrangements To minimize the number of packaging containing waste that is transiently located in the facility awaiting evacuation. No storage for more than two years of this waste shall take place within the facility without the authorization of the Director General of Nuclear Safety and Radiation Protection.
The operator shall take responsibility for the waste Products during the final shutdown and decommissioning phases. It tracks waste based on written and archived documents, from production to final disposal at licensed facilities.
The inventory of waste generated is maintained as it becomes available. The progress of the decommissioning and decommissioning operations, in particular as regards the quantities produced, the radiological characteristics and the origin of the waste. Such data shall be included in the annual safety record of the facility, which shall show in particular the achievements for the past year and the forecasts for the following year.
At the end of the final stop operations and Dismantling, the operator transmits to the Director General Nuclear Safety and Radiation Protection an assessment of the waste, radioactive and non-radioactive, produced during the said operations, in which their physico-chemical nature is specified, Their volume, activity, and the associated radiological spectrum.


3.8. Fire Protection


Provisions are made to limit the risks and consequences of fires of internal origin at the facility, to allow their detection, to prevent their spread and to ensure their Extinction.
During the final shutdown and dismantling phases, escape routes must be fully defined and cleared. They must have been brought to the attention of all the agents present on the installation. Security exercises are regularly held, at least annually, and the reports of such exercises are made available to the inspectors of the basic nuclear installations.


3.9. Protection from Environmental Assault


Provision is made for adequate containment of radioactive substances, taking into account all plausible circumstances that may result from the Normal or accidental operation of adjacent facilities or transportation in the vicinity of the facility, including dynamic effects and projectiles capable of reaching the facility.
The operator is informed of All environmental modification projects in relation to the description of the file attached to the application for authorisation referred to above, having or may have consequences for compliance with the provisions of this Decree or on the safety of The facility, and submits a file to the Director General of Nuclear Safety and Radiation Protection specifying the consequences of the proposed amendment, having regard to foreseeable normal or accidental circumstances.


3.10. Staff training and information


Without prejudice to the provisions of Articles R. 231-89 and R. 231-90 of the Labour Code, the personnel assigned to the final decommissioning and decommissioning operations shall Possess professional skills and specific training in nuclear safety and radiation protection requirements.


3.11. Transport of radioactive substances


Transport packages of radioactive substances are subject to regulatory controls upon receipt and prior to shipment outside the facility.

Item 4 Read more about this Article ...


The final decommissioning and decommissioning operations shall be completed no later than five years from the date of publication of this Decree. Within six months of the end of such operations, the operator shall submit to the Director General Nuclear Safety and Radiation Protection a report presenting, on the one hand, the return of experience of those operations (in particular the facts Events, the collective and individual doses associated with the various decommissioning phases, the balance sheet on the waste produced), on the other hand, the elements showing the realization of the final state sought for the installation After dismantling. This file is transmitted to the prefecture of Bouches-du-Rhône and to the town hall of Saint-Paul-lez-Durance, where it is available.
After the end of the dismantling operations, the installation can be removed from the list of nuclear installations of the Basis by decision of the Ministers responsible for Industry and the Environment. This decision must be preceded by prior approval by these ministers:
a) The balance sheets referred to in Articles 3.6 and 3.7 and the detailed account referred to in the first paragraph of this Article;
(b) A document confirming the Future location of the facility and specifying and justifying, on the basis of its radiological state after remediation, the monitoring and management arrangements envisaged by the operator in order to avoid unjustified doses in the framework Potential reuse of the installation after decommissioning.

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Industry and environment ministers shall notify specific technical requirements applicable to the operation of the facility, to which the operator must comply
Subject to the authorisation of the ministers responsible for industry and the environment for the amendments, even temporary, which lead to the failure to comply with the technical requirements they have notified.

Article 6 Learn more about this Article ...


Without prejudice to the application of the regulations in force, the operator shall immediately declare to the Ministers responsible for the environment, industry and health any accident or incident, whether nuclear or non-nuclear, having Have or may have a significant impact on the safety of the facility.

Article 7 Read more about this Article ...


Advertising of the impact statement provided for in the decree of 12 October 1977 shall be provided before the work is carried out and as soon as this Decree is published. The impact study can be consulted at the Directorate-General for Nuclear Safety and Radiation Protection, Regional Directorate for Industry, Research and Environment of Provence-Alpes-Côte d' Azur, in the prefecture of Bouches-du-Rhône and the town hall of Saint-Paul-lez-Durance.

Article 8 Learn more about this Article ...


The Minister of Economy, Finance and Industry, the Minister of Ecology and Sustainable Development, and the Minister Delegate to Industry are responsible for the implementation of the This Decree shall be published in the Official Gazette of the French Republic.


Done at Paris, February 8, 2006.


Dominique de Villepin


By the Prime Minister:


The Minister of Economy,

Finance and Industry,

Thierry Breton

Minister of Ecology

and Sustainable Development,

Nelly Olin

Industry Minister,

François Loos


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