¹ A blanket authorization is not required for a nuclear facility if the frequency of failures referred to in s. 8, para. 2 and 3, which results in a dose of more than 1 mSv for persons not exposed to radiation in the course of their profession, does not exceed 10 ^-6 In addition, in a warehouse or in a deep geological deposit, the sum of the activities of the nuclides to be stored shall not exceed 10 ¹³ LE within the meaning of Annex 3, column 9, ORaP ¹ .

² The IFSN is responsible for setting out in guidelines the method and standards of failure analysis required by para. 1. ²

A person who requires a blanket authorization must provide the following:

A.

Safety and security reports, which include:

1.

Site characteristics,

2.

The purpose of the project and its broad lines,

3.

Exposure to predictable radiation around the facility,

4.

Important personal and organizational data,

5.

In addition, for deep geological deposition, long-term security;

B.

The environmental impact report;

C.

The report on concordance with land use planning;

D.

The concept of decommissioning or closing observation phase;

E.

Proof of disposal of radioactive waste generated by the facility.

¹ Anyone requiring a building authorization must demonstrate:

A.

The principles set out in s. 7 to 12 can be respected;

B.

In addition, for the construction of a new nuclear power plant, the average frequency of damage to the heart in the event of failure within the meaning of s. 8 does not exceed 10 ^-5 Per year;

C.

And for low-risk nuclear facilities, that the requirements referred to in s. 22 are completed.

² To this end, it must provide the following parts:

A.

Documents to obtain the authority to construct referred to in Schedule 4;

B.

The environmental impact report;

C.

The report on concordance with land use planning;

D.

The quality management program for the project development and implementation phases;

E.

The concept of emergency protection;

F.

The decommissioning plan or the proposed observation phase and closure plan;

G.

The project's compliance report with the general authorization.

³ The IFSN is responsible for setting out in directives the type, content, presentation and number of parts to be provided. ¹

¹ In the quality management program referred to in s. 24, para. 2, let. D, the applicant must describe the organization and the diversion of the project, including the mechanisms of its collaboration with the agent companies and with the authorities granting the authorization and supervision.

² The quality management programme must correspond to the state of the nuclear safety and security technology.

³ The applicant must periodically review by external services that the quality management program complies with the industry standards of the moment and adapt it if necessary.

⁴ The IFSN is responsible for regulating in detail the details of the requirements to be met by the quality management program. ¹

¹ With respect to the structures and components of the facility that the authority to construct declares to be subject to the granting of a performance permit, the IFSN grants licences to: ¹

A.

The construction of the construction elements, including fasteners embedded in the concrete, the reinforcement or mounting of elements of the metal frame and the method of intervention in the large work and subsequent fixation;

B.

Manufacturing of major mechanical components;

C.

The assembly of mechanical and electrical systems, including their control-control, and the safety equipment.

² To obtain the enforcement permit, the applicant must provide the documents necessary for the assessment of the application in accordance with Annex 4.

³ The IFSN is responsible for setting out in directives the type, content, presentation and number of parts to be provided. ²

¹ The holder of the authorisation shall record all acts relating to the construction of the buildings, as well as the manufacture and assembly of the technical equipment, as well as the checks and examinations carried out, in order to Ensure traceability.

² It must keep the file in a safe place until the end of the decommissioning, until the closure or until the end of the monitoring period.

³ Changes to the facility, including decommissioning and closure, must be recorded in the file.

⁴ The holder of the authorisation must submit the dossier to the IFSN, after the decommissioning and to the department after the closure or after the period of supervision. ¹

⁵ The IFSN is responsible for regulating in directives the requirements to be met by the construction file and its conservation. ²

¹ A person who requires an authorization to operate must provide the following:

A.

The corresponding technical and organisational documents, in accordance with Annex 3;

B.

The documents required for the authorization to operate in accordance with Schedule 4;

C.

Proof of insurance coverage;

D.

The report establishing the compliance of the facility with the general authorization and with the authority to construct.

² The IFSN is responsible for setting out in directives the type, content, presentation and number of parts to be provided. ¹

¹ The authority to operate must apply for a specific enforcement permit for the following stages of commissioning:

A.

The first nuclear fuel storage;

B.

The first loading of fuel into the reactor;

C.

The first criticality;

D.

Other stages of the commissioning program;

E.

Continuous operation in the first operating cycle;

F.

The first storage of waste packages of a given type;

G.

Storage of containers of spent fuel elements or of highly radioactive waste.

² In order to obtain the enforcement permit, the applicant must provide the necessary parts for the assessment of the application in accordance with Annex 4.

³ The IFSN is responsible for setting out in directives the type, content, presentation and number of parts to be provided. ¹

¹ The organisation of the operation of the nuclear facility must be designed to assume at least responsibility for the following activities and sectors:

A.

The operation of the facility in all operational states;

B.

Maintenance, materials technology and verification, technical support;

C.

The design and monitoring of the reactor core;

D.

Radiation protection and radioactive waste;

E.

The chemistry of water and the use of chemical additives;

F.

Preparation of and implementation of contingency plans;

G.

Nuclear safety monitoring and evaluation;

H.

Security;

I.

Assurance of the quality of benefits provided by agents;

J.

Staff training and development;

K.

Strengthening a security-friendly attitude.

² The authorisation holder must apportion the staff between a number of organisational units which will not be too high, each headed by a leader. Any framework must have a designated replacement.

³ It must set up a body that will analyse the events and findings of the human factors, propose measures and monitor its implementation.

⁴ It shall designate, in order to ensure the technical operation of the nuclear facility, a position that it will have the necessary skills and resources and that it will assume responsibility for the decisions taken to ensure safety and security.

⁵ The IFSN is responsible for regulating in detail the details of the requirements to be met by the organization. ¹

In particular, the operating quality management system must meet the following requirements:

A.

Responsibilities and competencies related to the organization's processes must be clearly and concisely defined;

B.

The security and safety tasks require a management cycle; they must be systematically planned, accomplished, monitored, documented, and periodically checked by internal services and External and adapted;

C.

The system must correspond to the state of the nuclear safety and security technology.

¹ The holder of the authorization shall develop systematic maintenance programmes for safety and security equipment and carry out the planned measures, in particular:

A.

Maintenance;

B.

Recurring non-destructive reviews;

C.

Recurring operating tests.

² In the event of a deviation from the intended state, it shall perform the restoration work.

³ Maintenance must be carried out by qualified personnel who will use the appropriate processes and equipment.

⁴ The authorization holder must record the maintenance results and evaluate them on a regular basis. If necessary, it must complement the programs.

¹ The holder of the authorisation shall establish systematic assessments:

A.

The safety consequences of the installation and, in particular, the risk involved, any modification of the installation, any events that have occurred or any findings made; the assessment of the risk will, in particular, support an analysis The probabilistic security (APS) that will be recent and specific to the plant;

B.

Feedback on electrical and mechanical equipment, fuel elements, safety building, and water chemistry;

C.

Radiation protection and radioactive waste;

D.

Organization and staff;

E.

Emergency planning;

F.

The criteria set out in s. 44, para. 1.

² It must establish systematic assessments:

A.

The concept of security;

B.

Security measures.

³ The IFSN is responsible for regulating in directives the requirements to be met by systematic assessments of safety and security. ¹

¹ The holder of an authorization to operate a nuclear power plant must conduct a comprehensive security review (Periodic Security Review, RPS) every ten years.

² To this end, it must set out and evaluate:

A.

The safety plan;

B.

The operation and behaviour of the facility;

C.

Deterministic security analysis;

D.

Probabilistic security analysis;

E.

The overall assessment of the security level;

F.

Organization and staff.

³ The NSTP is responsible for regulating in detail the requirements to be met by the SDN. ¹

¹ The holder of the authorisation shall ensure, by means of the appropriate programme, the systematic monitoring of the ageing of all equipment and constructions whose function and integrity rely on safety and security.

² It must analyse the results obtained, deduce the measures to be taken and take them.

³ It must, always with the appropriate program, record the results of the monitoring of the aging of the facility and periodically update this program, depending on the status of the facility.

⁴ The IFSN is responsible for setting out in guidelines the methods of monitoring aging and how far this surveillance should go. ¹

¹ The holder of the authorisation shall monitor the development of science in his field, in particular the results of the research, and examine the extent to which it can draw lessons for the safety of the facility.

² It must follow the development of the technique, including the organization and personnel, and seek lessons learned for the safety and security of the facility. In particular, they will:

A.

Recognized technical standards in Switzerland and abroad;

B.

The normative systems of nuclear energy adopted by the supplier country of the nuclear facility and by other countries;

C.

Recommendations from international organizations;

D.

The state of the art in comparable nuclear installations and in other significant technical installations.

³ It must follow the experience of comparable installations and evaluate the consequences for the installation.

¹ The holder of the authorization shall submit to the NSN reports evaluating the condition and operation of the facility in accordance with Annex 5. ¹

² The IFSN is responsible for regulating in directives the type, content, presentation and number of reports to be submitted. ²

¹ The holder of an authorisation to operate must notify the IFSN, before carrying out them, in particular the following activities:

A.

Programmed shutdown of the reactor;

B.

Restarting the reactor after a failure due to failure;

C.

Work involving a probable collective dose greater than 50 mSv;

D.

Radioactive releases to the programmed but unusual environment;

E.

The renewal of activated carbon in aeration emergency filters;

F.

Planning and carrying out emergency drills;

G.

Tests performed on systems or components that rely on safety.

² It is expected to announce the following activities to IFSN:

A.

Any modification of the facility that does not require authorization or licence to execute;

B.

Any change in the content of the files referred to in s. 27 and 41.

³ It is expected to announce the following events and findings to the NSN:

A.

Events that compromise or may compromise safety;

B.

Other public interest events;

C.

Findings that could compromise security but did not provoke an event.

⁴ Reports required by Schedule 6 on any events or findings must be reported to the IFSN.

⁵ The IFSN is responsible for regulating in directives the procedure to be followed by the holder in order to carry out the notifications referred to in paras. 1 and 2, and to classify the events and findings referred to in para. 3.

¹ The holder of an authorisation to operate must notify the IFSN before carrying out in particular the following activities:

A.

Any modification of the buildings or the facility or any new construction for which an enforcement permit is being requested from the IFSN;

B.

Any exercise involving military, cantonal or communal bodies;

C.

Any extraordinary security activities.

² It shall immediately announce the following events and findings to the IFSN:

A.

Acts of violence against staff;

B.

Acts of sabotage and sabotage attempts;

C.

Threats of bombing;

D.

Threats of blackmail and takeovers;

E.

Malfunctions, damage and failures of equipment and security systems that extend beyond 24 hours;

F.

Other events in or around the nuclear facility that are attributable to or indicative of unlawful acts;

G.

Other events and findings that affect or may affect the security of the security.

³ It must provide a report to the IFSN within 30 days of any events or findings. This report must be classified.

¹ Generally considered as amendments are not significantly different from an authorization but require a performance permit within the meaning of s. 65, para. 3, LENu, in particular:

A.

Modifications to buildings that are classified as important to the safety or security, to the components of the nuclear facility, to the systems and equipment that are classified as such, as well as the modifications to the facilities that Rely on safety or security, if the project maintains or improves their current security or safety functions;

B.

The following modifications to the reactor core:

1.

The modification of the loading of the heart with combustible elements in the context of the renewal of these elements,

2.

Modification and repair work of the fuel elements and control rods,

3.

An increase in the allowable burn rate,

4.

Modification of the justification methods,

5.

Modification of certain safety criteria,

6.

The increase in the proportion of combustible elements to mixed uranium-plutonium in the reactor core up to a maximum of 50 %;

C.

Modification of the content of the following documents:

1.

The regulation of the plant resp. Operating regulations,

2.

The regulation for emergencies,

3.

The Radiation Protection Regulations,

4

The tech spec

5.

Requirements and directives in the field of security.

² To obtain a licence to carry out the amendments referred to in s. 1, let. A and b, the applicant shall submit the documents necessary for the assessment of the request in accordance with Annex 4.

³ To obtain a licence to carry out the amendments referred to in s. 1, let. C, the applicant must present the documents necessary for the assessment of the application and justify the requested amendment.

⁴ If the applicant requests an amendment to the technical specifications, the applicant must also set out the method and technical criteria to which he has referred in order to assess the effect that this amendment will have on the safety of the installation.

⁵ The IFSN is responsible for setting out in directives the type, content, presentation and number of parts to be provided. ¹

¹ The holder of the authorisation shall maintain, for the duration of the operation of the nuclear facility and up to the end of the decommissioning or closure, the relevant technical and organisational documents, In accordance with Annex 3, and shall continuously adapt them to the state of the installation.

² It shall ensure the traceability of the operation by means of the operating surveys referred to in Annex 3 and the proof of the operating tests and maintenance work.

³ It must keep the records in a safe place until the end of the decommissioning, until the closure or until the end of the monitoring period.

⁴ Once the decommissioning is complete, the documentation must be returned to IFSN; after the closure or after the monitoring period has been completed, it must be returned to the department. ¹

⁵ The IFSN is responsible for setting out in directives the details of the requirements for documents and their preservation. ²

¹ The holder of an authorisation to operate shall verify and update every ten years the decommissioning plan for the nuclear facility or, for a deposit in deep geological layers, the project of the observation phase and the plan of Closing.

² An update is also required:

A.

Significant changes have been made to the facility;

B.

If significant changes have been made to the decommissioning or observation phase and closure requirements;

C.

If a significant evolution of the technique requires it.

¹ The holder of an authorisation to operate a nuclear power plant shall stop the installation when one of the stopping criteria laid down in the technical specification or in the regulation of the plant is fulfilled.

² It is only permitted to refit it at a reactor power of more than 5 % after taking the necessary measures.

¹ The holder of an authorization to operate shall stop the nuclear reactor and reequipment when one or more of the following technical criteria are met:

A.

Events or findings indicate that the cooling of the reactor core after a failure under s. 8 is no longer insured;

B.

Events or findings indicate that the integrity of the primary circuit is no longer assured;

C.

Events or findings indicate that the integrity of containment is no longer assured.

² The department sets in an ordinance the method and standards for verification of these criteria.

Any person who is responsible for the decommissioning of a nuclear facility shall provide the following documents concerning the decommissioning project:

A.

The comparative presentation of possible variants, with the phases and timing of the decommissioning work and the foreseeable end state, indicating the reasons for the chosen solution;

B.

The presentation of the successive stages of the work and the means necessary for this purpose, in particular the seizure of the radiological state of the installation, dismantling, cutting and decontamination of equipment, decontamination and demolition Buildings;

C.

The process to separate radioactive waste from those that are not and the evacuation of the former;

D.

Measures to ensure radiation protection for staff and to prevent the release of radioactive substances into the environment;

E.

Security measures;

F.

Failure considerations, including identification of possible malfunctions during decommissioning, assessment of the frequency and radiological consequences of such failures, and countermeasures and Potential emergency protection measures to be taken;

G.

The proof of staff commitment in sufficient numbers and with the professional qualifications required to carry out and supervise the decommissioning work, as well as the proof of the appropriate organisation, with a clear Assignment of skills;

H.

The quality management program;

I.

The environmental impact report;

J.

A complete list of costs attributable to decommissioning, including those for the disposal of radioactive and non-radioactive waste, as well as proof of the existence of the financial means.

The fixed decision in particular:

A.

The extent of the decommissioning work;

B.

Each phase of the operation, including the duration of a possible safety containment of the nuclear facility;

C.

The limits of the release of radioactive substances into the environment;

D.

Monitoring of the immissions of radioactive substances and direct radiation;

E.

The organization of the decommissioning.

The decision referred to in s. 46 rules the requirement to obtain a performance permit for each of the following activities:

A.

The process used for the measurement of material release;

B.

Packaging of radioactive waste;

C.

Demolition of recognized non-active buildings after decontamination;

D.

Non-nuclear reuse of parts of the facility prior to decommissioning;

E.

The lifting of security measures;

F.

In addition, during the decommissioning of a nuclear power plant, the disassembly of the reactor pressure vessel and the parts of the reactor surrounding it.

Anyone who is responsible for decommissioning a nuclear facility shall submit an annual progress report and a final report to the IFSN.

Art. 38 and 39 shall apply mutatis mutandis to the notification in the case of decommissioning.

A nuclear facility must be designed, constructed and operated in such a way that its operation and decommissioning produce as little radioactive waste as possible, in terms of volume and radioactivity. To this end, in particular:

A.

Select for the construction of materials for which activation product formation is low;

B.

Limit the assets used in the controlled area as far as possible during the operation of the facility;

C.

Decontaminate to the extent possible, where appropriate, materials and assets contaminated with radioactive substances.

For the purpose of disposal, radioactive waste must be classified in the following categories:

A.

High-activity waste:

1.

Used fuel elements that are not reused,

2.

Vitrified fission product solutions from the reprocessing of spent fuel elements;

B.

Alphatoxic waste: waste with a content of alpha emitters exceeding the value of 20 000 becquerel/g of conditioned waste;

C.

Low or medium-sized waste: all other radioactive waste.

¹ Waste disposal authorities should provide guidance in their management program on:

A.

The source, type and quantity of radioactive waste;

B.

Necessary deep geological deposits and how they are designed;

C.

The allocation of waste to these deposits;

D.

The plan for making these deposits;

E.

The duration of centralized or decentralized warehouse storage and the capacity that these warehouses must have;

F.

The financial plan for the disposal of waste until the decommissioning of nuclear facilities, specifying:

1.

The work to be done,

2.

The amount of costs;

3.

The method of funding;

G.

The concept of information.

² Waste disposal officials must adapt their waste management programs every five years.

³ The IFSN and the Office are competent to verify the waste management programme and monitor its application. ¹

¹ Any person who intends to remove material considered to be inactive in the controlled area of a nuclear facility shall perform a measurement of their release by means of a certified quality method and shall record the operation.

² If the release relates to materials of a weight greater than 1000 kg or greater than 1 m ³ , the IFSN must be informed at least ten days before the transport of these materials outside the nuclear facility; the relevant documents must be submitted to it at the same time. ¹

³ The IFSN is responsible for regulating in directives the detailed requirements to be met by the measurement of material release and the manner in which it is to be informed. ²

¹ Radioactive waste must be packed as quickly as possible. The collection of unpackaged waste in preparation for periodic packaging campaigns is permitted.

² Packages of packaged waste must be suitable for transport, storage and final storage.

³ Each package of waste must be marked and accompanied by documentation that describes its manufacture, composition and properties. The documentation must be kept and forwarded to the company that will complete the subsequent phases of the evacuation.

⁴ A request for approval of a package or type of package must be submitted to the IFSN prior to the manufacture of a package of packaged waste. ¹

⁵ Upon request, all the documents required for the assessment shall be attached and, in particular, shall provide guidance on:

A.

The packaging process;

B.

The waste package and its components;

C.

Quality assurance;

D.

The established record.

⁶ The IFSN is responsible for regulating in detail the requirements for packaging and application files. ²

The Office is competent to grant:

A.

Authorisations for the handling of radioactive waste;

B.

The approval of the Convention for the resumption of radioactive waste referred to in Art. 34, para. 3, let. D et al. 4, LENu.

¹ The request for authorization to transport, import, export or transport radioactive waste must be made jointly by the consignor, the consignee, the carrier and the organiser of the transport.

² The documents to be attached must provide all the information necessary for the assessment of the application, in particular:

A.

The composition and properties of radioactive waste;

B.

The names of the evacuation officer, the sender and the consignee;

C.

The source and destination of the waste;

D.

Transport, including proof of compliance with the requirements for the transport of dangerous goods.

Art. 16, 18, 20 and 21 shall apply mutatis mutandis to the handling of radioactive waste.

A person who requires authorization to conduct geological investigations must provide the following documents:

A.

The investigation programme;

B.

A geological report;

C.

A report on the possible consequences of investigations on geology and the environment;

D.

Maps and set plans;

E.

Indication of the desired duration of the authorisation.

The investigation programme shall provide guidance on:

A.

The objectives of the investigations;

B.

The anticipated scope of the investigations;

C.

The date of commencement of the investigation and its probable duration.

The geological report shall provide in particular the following particulars:

A.

A geological description of the area concerned;

B.

An overview of the geological surveys already undertaken in the region to which the applicant has access and a summary of the results obtained;

C.

A description of the geological and hydrogeological factors determining the choice of the region concerned.

¹ An authorization is not required for the following geological investigations:

A.

Seismic and other geophysical surveys such as gravimetric, geoelectrical and electromagnetic measurements;

B.

Surface geological surveys and existing underground structures, including rock sampling;

C.

The collection of groundwater and source water samples, source measurements, shallow piezometric surveys, and marking tests;

D.

Measuring natural gas.

² The authorisations required by the cantonal law or the federal law to carry out these activities are reserved.

A person who requires blanket authorization for a deep geological deposit must present, in addition to the documents referred to in s. 23, a report containing the following indications:

A.

A comparison of possible solutions in terms of security of deposit;

B.

An assessment of the defining characteristics of the site selection;

C.

The amount of costs.

The criteria under s. 14, para. 1, paragraph f, c. 1, LENu and which shall be included in the general authorisation shall relate to:

A.

The extent of suitable host rock areas;

B.

The hydrogeological conditions of the site;

C.

The duration of stagnation of groundwater.

A deep geological layer deposit consists of the main deposit where the radioactive waste, a pilot deposit and experimental areas will be stored.

¹ The characteristics of the host rock that matter for safety need to be investigated further, at the site, in the experimental areas, to confirm the security credential.

² Techniques that rely on safety and reliability must be tested prior to the introduction of deep geological deposition. This concerns in particular:

A.

The introduction of the duplicating material;

B.

The extraction of this material for the eventual recovery of waste packages;

C.

The waste package recovery technique.

³ The sealing of the caves and galleries must be tested and its reliability demonstrated during the period of operation of the deposit into deep geological layers.

¹ The pilot deposition is used to monitor the behaviour of waste, material and host rock until the end of the observation phase. The monitoring carried out there shall provide data of such a nature as to confirm the security rationale for the closure.

² The results of the monitoring must be applicable to what is happening in the main repository. They are used to make the decision to close the deposit.

³ During the design phase of the pilot deposit, the following principles must be respected:

A.

The geological and hydrogeological conditions must be comparable with those prevailing in the main deposit;

B.

The pilot deposition must be separated from the main deposit in the space and the hydraulic plan;

C.

The method of construction of the pilot deposit, the storage of the waste and the duplicating must be the same as those of the main deposit;

D.

The pilot deposit must contain a small but representative amount of waste.

¹ The owner of a deep geological deposit must fill the caves and galleries of the deposit after storing the waste packages.

² They must be bridged to ensure long-term safety and to allow for the recovery of waste without major efforts.

¹ The owner of a deep geological deposit must describe, in the project updated for the observation phase, the measures planned to monitor the deposit after the end of the storage of waste. In so doing, it must propose the duration of the observation phase.

² The department orders the monitoring and sets the duration. It may extend it if necessary.

¹ At the time of closure, the owner of a deep geological deposit must fill all remaining open parts of the deposit and seal the elements that matter for long-term safety and security.

² In the closing project, it should describe in particular:

A.

The sealing and sealing of access to storage facilities;

B.

The work to be done to bring the pilot depot to a secure, long-term condition;

C.

The sealing and sealing of access to the deposit in depth;

D.

Ensuring long-term security.

³ In closing the deposit, it must ensure in particular:

A.

There will be no unacceptable leakage of radionuclides through access to the depot;

B.

The separation of the aquifers will, in the long term, return to its configuration prior to the construction of the deposit;

C.

The deposit in deep geological layers is marked by a durable marking.

¹ The area of protection for deep geological deposition shall be established on the basis of the long-term safety report and submitted with the request for the general authorization of the project. It should include:

A.

All elements of the deposit in depth, including access;

B.

Rock masses ensuring the hydraulic containment of the deposit;

C.

Rock masses that contribute significantly to the retention of radionuclides that may be released through deposition over time;

² Following the granting of the general authorisation by the Federal Council, the Office shall invite the Office of the Land Registry to affix to the parcels concerned the reference "Area of provisional protection, deposited in deep geological layers". Once the authorization to operate is issued, it will place the words "Area of Final Protection, Deeper Geological Layers" on the parcels concerned.

³ The department decides on the lifting, of the provisional or permanent protection zone. The Office then invites the Office of the Land Registry to delete the statement.

⁴ The department grants authority to carry out projects in the area of protection. The prerequisite is that the long-term safety of the deposit is not compromised.

¹ The owner of a deep geological deposit must establish a file where the deposit information will be recorded in a sustainable manner.

² The file must show:

A.

The situation and extent of underground construction;

B.

Inventory of stored radioactive waste, broken down by type and quantity in each storage room;

C.

The design of technical safety barriers, including the sealing of access;

D.

The key elements of the final analysis of long-term security and its results.

³ After the deposit is closed or at the end of the monitoring period, the deposit owner must submit the file to the department.

¹ Geological data collected during investigations or during the construction of a deep geological deposit must be transmitted to the Geological Information Service of Confederation.

² The Geological Information Service of Confederation and the one that is held under para. 1, to provide the geological data by contract on access to and use of the data.