SSG-16 (Rev. 1) Establishing the Safety Infrastructure for a Nuclear Power Programme

Phase 1: Safety infrastructure considerations before a decision to launch a nuclear power programme is taken. Average duration: 1–3 years.

Phase 2: Safety infrastructure preparatory work for the construction of a nuclear power plant after a policy decision has been taken. Average duration: 3–7 years.

Phase 3: Safety infrastructure activities to implement the first nuclear power plant. Average duration: 7–10 years.

Phase 4: Safety infrastructure during the operation phase of the nuclear power plant. Average duration: 40–60 years.

Phase 5: Safety infrastructure during the decommissioning and waste management phases of the nuclear power plant. Average duration: 20 to more than 100 years.

There should be awareness of the requirements.

Implementation of the requirements should begin.

The requirements should be fully implemented.

Governmental officials;

Legislative bodies;

Organizations that are given an explicit governmental mandate to assess the feasibility of or to coordinate the development of a nuclear power programme;¹

Regulatory bodies;

Operating organizations, including owner/operators;

External expert support entities, including technical and scientific support organizations;²

Industrial organizations, including plant vendors, manufacturers, designers and constructors;

Organizations for radioactive waste management and spent fuel management;

Organizations involved in preparedness and response for a nuclear or radiological emergency;

Organizations involved in the transport of nuclear material;

Competent authorities for matters relating to nuclear security;

Education and training organizations;

Research centres (government and private sector).

Requirement 1 of GSR Part 1 (Rev. 1) [5];

Requirements 10 and 29 of IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards [9];

Requirement 2 of IAEA Safety Standards Series No. GSR Part 5, Predisposal Management of Radioactive Waste [11];

Requirement 2 of IAEA Safety Standards Series No. GSR Part 7, Preparedness and Response for a Nuclear or Radiological Emergency [13].

Paragraph 3.8 (Principle 2) of SF-1 [1], which states that “The government is responsible for the adoption within its national legal system of such legislation, regulations, and other standards and measures as may be necessary to fulfil all its national responsibilities and international obligations effectively”.

Principle 4 of SF-1 [1], which states that “Facilities and activities that give rise to radiation risks must yield an overall benefit.”

Binding international instruments and other international instruments (see also paras 2.22–2.41 on the global nuclear safety regime);

The necessary scope and elements of the governmental, legal and regulatory framework for safety (see also paras 2.42–2.60 on the legal framework and paras 2.61–2.101 on the regulatory framework);

The need for and provision for a vigorous competence building programme and the associated human and financial resources (see also paras 2.196–2.217 on human resources development and paras 2.120–2.132 on funding and financing);

The provisions and framework for research and development (see also paras 2.218–2.232 on research for safety and regulatory purposes);

The promotion of leadership and management for safety, including the fostering of a strong culture for safety (see also paras 2.172–2.195 on leadership and management for safety);

The need for and provision for the management of spent fuel and radioactive waste, including the disposal of radioactive waste (see also paras 2.271–2.290 on the safety of radioactive waste management, spent fuel management and decommissioning);

The potential environmental, societal and economic impacts of a prospective nuclear power programme;

The need for the establishment of — or an upgrade to — the supporting infrastructure, including the infrastructure necessary to support the arrangements for emergency preparedness and response.

Requirement 1 of GSR Part 1 (Rev. 1) [5];

Requirements 10 and 29 of GSR Part 3 [9];

Requirement 2 of GSR Part 5 [11];

Requirement 2 of GSR Part 7 [13].

Requirement 1 of GSR Part 1 (Rev. 1) [5];

Requirements 10 and 29 of GSR Part 3 [9];

Requirement 2 of GSR Part 5 [11];

Requirement 2 of GSR Part 7 [13].

Requirements 1, 14 and 36 of GSR Part 1 (Rev. 1) [5];

Requirements 7 and 17 of GSR Part 7 [13].

International conventions that establish robust common principles and obligations for ensuring safety in the use of radiation, radioactive material and nuclear energy and that provide for an effective coordinated response to emergencies;

Codes of conduct that promote good practices in the relevant activities;

Internationally agreed IAEA safety standards, which support the development of harmonized national safety requirements, guides and practices;

International peer reviews of safety that provide mutual learning by participating States;

Knowledge networks and expert networks;

Multilateral and bilateral cooperation in safety matters aimed at enhancing safety by means of harmonized approaches and the increased quality and effectiveness of safety reviews and inspections.

The Convention on Nuclear Safety [18];

The Convention on Early Notification of a Nuclear Accident [19];

The Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency [20];

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management [21];

The Convention on the Physical Protection of Nuclear Material [22] and its Amendment [23];

The Code of Conduct on the Safety and Security of Radioactive Sources [24].

Requirements 1 and 14 of GSR Part 1 (Rev. 1) [5];

Requirement 13 of IAEA Safety Standards Series No. GSR Part 2, Leadership and Management for Safety [8];

Requirements 7 and 17 of GSR Part 7 [13];

Requirement 24 of IAEA Safety Standards Series No. SSR-2/2 (Rev. 1), Safety of Nuclear Power Plants: Commissioning and Operation [14].

Requirements 1 and 14 of GSR Part 1 (Rev. 1) [5];

Requirement 13 of GSR Part 2 [8];

Requirements 7 and 17 of GSR Part 7 [13];

Requirement 24 of SSR-2/2 (Rev. 1) [14].

Requirements 1–4 of GSR Part 1 (Rev. 1) [5];

Requirement 2 of GSR Part 3 [9];

Requirement 1 of GSR Part 5 [11];

Requirement 4 of IAEA Safety Standards Series No. GSR Part 6, Decommissioning of Facilities [12];

Requirements 2 and 20 of GSR Part 7 [13].

The safety principles for protecting people — individually and collectively — society and the environment from radiation risks, both at present and in the future (see also paras 2.233–2.247 on radiation protection);

The types of facility and activity that are included within the scope of the framework for safety (and that should be licensed in connection with nuclear power production);

The type of authorization³ that is required for the operation of facilities and the conduct of activities, in accordance with a graded approach;

The rationale for the authorization of new facilities and activities, as well as the applicable decision making process;

Provision for the involvement of interested parties and for their input to decision making (see also paras 2.102–2.119 on transparency and openness);

Provision for assigning legal responsibility for safety to the persons or organizations responsible for the facilities and activities, and for ensuring the continuity of responsibility where activities are carried out by several persons or organizations successively (see also paras 3.1–3.27 on the operating organization);

The establishment of a regulatory body (see also paras 2.61–2.101 on the regulatory framework);

Provision for the review and assessment of facilities and activities, in accordance with a graded approach (see also paras 2.248–2.270 on safety assessment);

The authority and responsibility of the regulatory body for promulgating (or preparing for the enactment of) regulations and preparing guidance for their implementation (see also paras 2.61–2.101 on the regulatory framework);

Provision for the inspection of facilities and activities, and for the enforcement of regulations, in accordance with a graded approach (see also paras 2.61–2.101 on the regulatory framework);

Provision for appeals against decisions of the regulatory body;

Provision for preparedness and response for a nuclear or radiological emergency (see also paras 2.291–2.310 on emergency preparedness and response);

Provision for the interface with nuclear security (see also paras 3.114–3.128 on interfaces with nuclear security);

Provision for the interface with the system of accounting for, and control of, nuclear material (not addressed further in this Safety Guide);

Provision for acquiring and maintaining the necessary competence nationally for ensuring safety (see also paras 2.196–2.217 on human resources development and paras 2.218–2.232 on research for safety and regulatory purposes);

Responsibilities and obligations in respect of financial provision for the management of radioactive waste and spent fuel, and for decommissioning of facilities and termination of activities (see also paras 2.271–2.290 on safety of radioactive waste management, spent fuel management and decommissioning, and paras 2.120–2.132 on funding and financing);

The criteria for release from regulatory control;

The specification of offences and the corresponding penalties;

Provision for controls on the import and export of nuclear material and radioactive material, as well as for their tracking within, and to the extent possible outside, national boundaries, such as tracking of the authorized export of radioactive sources (not further addressed in this Safety Guide).

Requirements 1–4 of GSR Part 1 (Rev. 1) [5];

Requirement 2 of GSR Part 3 [9];

Requirement 1 of GSR Part 5 [11];

Requirement 4 of GSR Part 6 [12];

Requirements 2 and 20 of GSR Part 7 [13].

Requirements 1–4 of GSR Part 1 (Rev. 1) [5];

Requirement 2 of GSR Part 3 [9];

Requirement 1 of GSR Part 5 [11];

Requirement 4 of GSR Part 6 [12];

Requirements 2 and 20 of GSR Part 7 [13].

Preparation of regulations and guides;

Authorization of facilities and activities;

Review and assessment of information relevant to safety;

Inspection of facilities and activities;

Enforcement of compliance with regulations and standards.

Ensuring that on-site emergency arrangements, including emergency plans and procedures, are in place and provide for an effective response and that they are integrated with the emergency arrangements of other response organizations and other plans, as appropriate (see paras 4.11–4.15 of GSR Part 7 [13]);

Establishing appropriate means for providing information to interested parties in a transparent manner (see Requirement 36 of GSR Part 1 (Rev. 1) [5]);

Promoting a culture for safety (see Requirement 12 of GSR Part 2 [8]);

Promoting the necessary coordination with other national bodies and with international bodies.

Requirements 1, 3, 4, 7 and 11 of GSR Part 1 (Rev. 1) [5];

Requirements 2 and 3 of GSR Part 3 [9];

Requirement 1 of GSR Part 5 [11].

Requirements 1, 3, 4, 7, 11, 15–19, 21–26, 30 and 32 of GSR Part 1 (Rev. 1) [5];

Requirement 3 of GSR Part 2 [8];

Requirements 2 and 3 of GSR Part 3 [9];

Requirements 1 and 3 of GSR Part 5 [11];

Requirement 5 of GSR Part 6 [12];

Requirement 2 of GSR Part 7 [13].

A prescriptive regulatory approach places a great deal of importance on the adequacy of the regulations for safety and requires detailed development. The regulations establish clear requirements and expectations for the regulatory body, as well as for the operating organization, and thus can be used to promote systematic interaction between the regulatory body and other parties. The regulations could establish detailed technical requirements or identify specific issues that the operating organization and its suppliers should address and present for assessment by the regulatory body. For the latter approach, specific technical requirements can then be taken from relevant international industrial standards (including nuclear specific standards) or the industrial standards of other States, as agreed by the regulatory body at an early stage of the licensing process for nuclear power plants. The development and updating of detailed regulations place a high demand on the regulatory body’s resources.

A performance based regulatory approach allows the operating organization more flexibility in determining how to meet the established safety goals and necessitates fewer and less detailed regulations. However, this approach requires the establishment of specific safety goals and targets. Verifying that appropriate measures to ensure safety have been identified by the operating organization might be difficult unless the regulatory body’s staff, the staff of its external support organization and the staff of the operating organization all have a high level of professional competence and are able to interact to determine whether established safety objectives are met.

Requirements 1, 3, 4, 7, 11, 16–18 and 21–33 of GSR Part 1 (Rev. 1) [5];

Requirement 3 of GSR Part 2 [8];

Requirements 2 and 3 of GSR Part 3 [9];

Requirements 1 and 3 of GSR Part 5 [11];

Requirement 5 of GSR Part 6 [12];

Requirement 2 of GSR Part 7 [13].

Routine inspections (including unannounced inspections) conducted by resident or non-resident inspectors;

Topical inspections conducted by inspectors with relevant expertise, in accordance with a scheduled programme;

Reactive inspections conducted after abnormal events.

Requirements 1 and 36 of GSR Part 1 (Rev. 1) [5];

Requirements 5 and 12 of GSR Part 2 [8];

Requirement 1 of GSR Part 5 [11].

Requirements 1, 21, 34 and 36 of GSR Part 1 (Rev. 1) [5];

Requirements 5 and 14 of GSR Part 2 [8];

Requirement 3 of GSR Part 3 [9];

Requirements 1 and 3 of GSR Part 5 [11];

Requirements 10 and 13 of GSR Part 7 [13];

Requirement 2 of SSR-2/2 (Rev. 1) [14].

The responsibility of the regulatory body for the establishment and enforcement of regulations and requirements on nuclear safety;

The authority of the regulatory body to give binding orders for ensuring safety;

The independence of the regulatory body from undue influences in decision making;

The technical competence of the regulatory body and the available human resources;

The independence of the regulatory body.

Requirements 1, 21, 34 and 36 of GSR Part 1 (Rev. 1) [5];

Requirements 5 and 14 of GSR Part 2 [8];

Requirement 3 of GSR Part 3 [9];

Requirements 1 and 3 of GSR Part 5 [11];

Requirements 10 and 13 of GSR Part 7 [13];

Requirement 2 of SSR-2/2 (Rev. 1) [14].

Requirements 1, 3, 10 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 9 of GSR Part 2 [8];

Requirement 1 of GSR Part 5 [11];

Requirement 9 of GSR Part 6 [12];

Requirement 2 of GSR Part 7 [13];

Requirements 1, 3 and 4 of SSR-2/2 (Rev. 1) [14].

Requirements 1, 3, 10 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 9 of GSR Part 2 [8];

Requirement 1 of GSR Part 5 [11];

Requirement 9 of GSR Part 6 [12];

Requirement 2 of GSR Part 7 [13];

Requirements 1, 3 and 4 of SSR-2/2 (Rev. 1) [14].

Requirements 1, 3, 10 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 9 of GSR Part 2 [8];

Requirement 1 of GSR Part 5 [11];

Requirement 9 of GSR Part 6 [12];

Requirement 2 of GSR Part 7 [13];

Requirements 1, 3 and 4 of SSR-2/2 (Rev. 1) [14].

Advisory bodies;

Dedicated external support organizations;

Research centres;

Academic institutions;

Regulatiry bodies of other States;

International and regional organizations;

Consultants with experience in specific technical or scientific topics.

Plant vendors;

Suppliers of equipment and services;

External maintenance organizations;

Organizations conducting material testing and inspections;

Dedicated external support organizations;

Research centres;

Academic institutions;

Consultants with experience in specific technical or scientific topics.

Requirements 4, 11, 13 and 20 of GSR Part 1 (Rev. 1) [5];

Requirements 3 and 11 of GSR Part 2 [8];

Requirement 2 of GSR Part 3 [9];

Requirement 3 of SSR-2/2 (Rev. 1) [14].

Individual monitoring and environmental monitoring;

In-service testing and inspection;

Maintenance of special technical equipment;

Metrological activities.

Requirements 4, 11, 13, 17 and 20 of GSR Part 1 (Rev. 1) [5];

Requirements 3 and 11 of GSR Part 2 [8];

Requirements 2 and 3 of GSR Part 3 [9];

Requirements 3 and 31 of SSR-2/2 (Rev. 1) [14].

Requirements 4, 11, 13, 17 and 20 of GSR Part 1 (Rev. 1) [5];

Requirements 3, 10 and 11 of GSR Part 2 [8];

Requirements 2, 3 and 20 of GSR Part 3 [9];

Requirements 3 and 31 of SSR-2/2 (Rev. 1) [14].

Training of operating staff;

Preparation of documentation, including that required for licensing;

Commissioning of the plant;

Maintenance and in-service inspection;

Technical assistance during operation;

Preparation of normal operating procedures and emergency operating procedures.

Requirements 1 and 19 of GSR Part 1 (Rev. 1) [5];

Requirements of GSR Part 2 [8] as a whole;

Requirement 5 of GSR Part 3 [9];

Requirement 2 of IAEA Safety Standards Series No. SSR-1, Site Evaluation for Nuclear Installations [15].

Requirements 1, 19 and 35 of GSR Part 1 (Rev. 1) [5];

Requirements of GSR Part 2 [8] as a whole;

Requirement 5 of GSR Part 3 [9];

Requirement 7 of GSR Part 5 [11];

Requirement 2 of SSR-1 [15];

Requirement 2 of SSR-2/2 (Rev. 1) [14];

Paragraph 306 of IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material, 2018 Edition [17].

Requirements 1, 19 and 35 of GSR Part 1 (Rev. 1) [5];

Requirements of GSR Part 2 [8] as a whole;

Requirement 5 of GSR Part 3 [9];

Requirement 7 of GSR Part 5 [11];

Requirement 26 of GSR Part 7 [13];

Requirement 2 of SSR-1 [15];

Requirement 2 of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design [16];

Requirements 2, 8, 9 and 15 of SSR-2/2 (Rev. 1) [14];

Paragraph 306 of SSR-6 (Rev. 1) [17].

Requirements 1, 11 and 18 of GSR Part 1 (Rev. 1) [5];

Requirement 9 of GSR Part 2 [8];

Requirement 2 of GSR Part 3 [9];

Requirements 21 and 25 of GSR Part 7 [13];

Requirement 4 of SSR-2/2 (Rev. 1) [14].

Requirements 1, 11 and 18 of GSR Part 1 (Rev. 1) [5];

Requirement 9 of GSR Part 2 [8];

Requirements 2–4 and 26 of GSR Part 3 [9];

Requirements 21 and 25 of GSR Part 7 [13];

Requirements 4 and 7 of SSR-2/2 (Rev. 1) [14];

Paragraphs 311–315 of SSR-6 (Rev. 1) [17].

Requirements 1, 11 and 18 of GSR Part 1 (Rev. 1) [5];

Requirement 9 of GSR Part 2 [8];

Requirements 2–4 and 26 of GSR Part 3 [9];

Requirements 21 and 25 of GSR Part 7 [13];

Requirements 4 and 7 of SSR-2/2 (Rev. 1) [14];

Paragraphs 311–315 of SSR-6 (Rev. 1) [17].

Requirements 1 and 11 of GSR Part 1 (Rev. 1) [5].

Requirements 1 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 3 of GSR Part 5 [11].

Requirements 1 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 3 of GSR Part 5 [11].

Requirement 7 of GSR Part 1 (Rev. 1) [5];

Requirements 2 and 43 of GSR Part 3 [9];

Requirements 25–27 of SSR-1 [15].

GSG-8, Radiation Protection of the Public and the Environment [34];

GSG-9, Regulatory Control of Radioactive Discharges to the Environment [35];

GSG-10, Prospective Radiological Environmental Impact Assessment for Facilities and Activities [36].

Requirement 7 of GSR Part 1 (Rev. 1) [5];

Requirements 1–4, 6–16, 18–32 and Schedule III of GSR Part 3 [9];

Requirements 25–27 of SSR-1 [15];

Requirements 78 and 79 of SSR-2/1 (Rev. 1) [16];

Paragraphs 301–303 of SSR-6 (Rev. 1) [17].

Requirement 7 of GSR Part 1 (Rev. 1) [5];

Requirements 1–4, 6–16, 19–32 and Schedule III of GSR Part 3 [9];

Requirements 25–27 of SSR-1 [15];

Requirements 5, 78 and 79 of SSR-2/1 (Rev. 1) [16];

Requirement 21 of SSR-2/2 (Rev. 1) [14];

Paragraphs 301–303 of SSR-6 (Rev. 1) [17].

Requirements 5, 6 and 8 of GSR Part 4 (Rev. 1) [10].

Requirements 24–26 of GSR Part 1 (Rev. 1) [5];

Requirement 13 of GSR Part 3 [9];

Requirements 1–6, 8 and 14–16 of GSR Part 4 (Rev. 1) [10].

Requirements 24–26 of GSR Part 1 (Rev. 1) [5];

Requirement 13 of GSR Part 3 [9];

Requirements 1–24 of GSR Part 4 (Rev. 1) [10];

Requirements 5 and 10 of SSR-2/1 (Rev. 1) [16];

Requirement 12 of SSR-2/2 (Rev. 1) [14].

Requirements 7 and 10 of GSR Part 1 (Rev. 1) [5];

Requirement 2 of GSR Part 3 [9];

Requirements 1 and 2 of GSR Part 5 [11];

Requirements 1, 4, 5 and 9 of GSR Part 6 [12].

Requirements 7 and 10 of GSR Part 1 (Rev. 1) [5];

Requirements 2 and 31 of GSR Part 3 [9];

Requirements 1–12 and 17 of GSR Part 5 [11];

Requirements 1, 4–6, 8 and 9 of GSR Part 6 [12];

Requirement 15 of GSR Part 7 [13];

Requirements 35, 36 and 38 of SSR-2/1 (Rev. 1) [16];

Requirement 21 of SSR-2/2 (Rev. 1) [14].

Requirements 7 and 10 of GSR Part 1 (Rev. 1) [5];

Requirements 2 and 31 of GSR Part 3 [9];

Requirements 1–20 of GSR Part 5 [11];

Requirements 1, 4–6 and 8–10 of GSR Part 6 [12];

Requirement 15 of GSR Part 7 [13];

Requirements 35, 36 and 38 of SSR-2/1 (Rev. 1) [16];

Requirements 21 and 33 of SSR-2/2 (Rev. 1) [14].

Requirements 7 and 8 of GSR Part 1 (Rev. 1) [5];

Requirement 43 of GSR Part 3 [9];

Requirements 1 and 2 of GSR Part 7 [13].

Requirements 7 and 8 of GSR Part 1 (Rev. 1) [5];

Requirements 43 and 44 of GSR Part 3 [9];

Requirements 1, 2, 4, 5 and 20–23 of GSR Part 7 [13];

Requirements 18 and 19 of SSR-2/2 (Rev. 1) [14];

Paragraphs 304 and 305 of SSR-6 (Rev. 1) [17].

Basic legislation and regulations for emergency preparedness and response;

Hazard assessment;

Emergency plans, including concepts of operations and procedures;

Procedures for emergency classification;

Procedures for protecting emergency workers and helpers in an emergency;

Procedures for providing public warnings, information and instructions;

Procedures for the implementation of urgent and early protective actions and other response actions;

Procedures for requesting and effectively using assistance resources from other identified organizations capable of augmenting the planned response;

Procedures for medical response;

Procedures for dealing with non-radiological consequences;

Procedures for managing radioactive waste following the emergency;

Guidelines for terminating the emergency and for analysis of the emergency and the emergency response;

Procedures for effective communication;

Procedures for effective radiation monitoring;

Development of drill, training and exercise programmes.

Requirements 7 and 8 of GSR Part 1 (Rev. 1) [5];

Requirements 43–46 and Schedule IV of GSR Part 3 [9];

Requirements 1–26 and appendices I and II of GSR Part 7 [13];

Requirement 18 of SSR-2/2 (Rev. 1) [14];

Paragraphs 304 and 305 of SSR-6 (Rev. 1) [17].

Specifying the safety requirements for the plant design in accordance with national laws and regulations and appropriate international standards, and verifying that these requirements are met;

Ensuring the quality of structures, systems and components of the plant;

Ensuring that a knowledgeable workforce is acquired and maintained, including the plant operators and other plant staff;

Ensuring the safe operation of the plant by implementing an adequate organizational structure, and allocating responsibilities and delegating authority within the organization to achieve proper management and to address interface issues, including interfaces between safety and security, and between maintenance and operations;Specifying the safety requirements for the plant design in accordance with national laws and regulations and appropriate international standards, and verifying that these requirements are met.

Establishing safety policies and implementing management programmes for safe operation and verifying their effectiveness;

Establishing and implementing a policy for personnel qualification, as well as programmes for the continuing training of staff;

Establishing and implementing an appropriate policy on an individual’s suitability for duty, and addressing the adequacy of the physical and mental fitness of all employees, contractors and visitors, as applicable;

Establishing liaison with the regulatory body and other public authorities for the purposes of considering, understanding and ensuring compliance with regulatory requirements;

Establishing liaison with organizations for design, construction, commissioning and manufacturing, and other organizations involved in the nuclear power programme, to ensure the proper understanding and transfer of information and experience;

Providing resources, services and facilities to plant management and adequately supervising safety related work performed by contractors;

Providing adequate information for the purposes of liaison and public relations;

Ensuring the collection, evaluation, implementation and dissemination of operating experience;

Ensuring that the decision making process gives adequate consideration to the selection of priorities and the organization of activities.

To control the radiation exposure of people and the release of radioactive material to the environment;

To restrict the likelihood of events that might lead to a loss of control over a nuclear reactor core, nuclear chain reaction, radioactive source or any other source of radiation;

To mitigate the consequences of such events if they were to occur.”

Requirements 5, 6 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 4 of GSR Part 3 [9];

Requirements 1 and 4 of SSR-2/2 (Rev. 1) [14].

The capabilities and resources of existing electrical power producing companies to enter into the nuclear field;

The safety implications of various contract options for nuclear power plants, such as turnkey, super turnkey, split package or multicontract approaches;⁶

The possibilities of joint ventures with operating organizations in other States to strengthen safety capabilities, and the legal implications of such ventures;

The possibilities of ownership by other States, and the legal implications of such ownership;

The design authority function (see Action 177 and paras 3.60–3.83);

The preliminary environmental impact assessment (both radiological and non-radiological).

Policy making functions, such as making investment decisions, setting management objectives, establishing a policy for nuclear safety and for quality, developing human resources, allocating resources, approving the contents of management programmes, and setting policies on fitness for duty;

Operating functions, which include executive decision making and actions for the operation of the plant, both in operational states and in accidents;

Support functions, which include obtaining from both on‑site and off‑site organizations the technical and administrative services and facilities necessary to perform the operating functions;

Safety functions and quality management functions, which include review of the design and oversight of the construction, manufacturing and supporting functions, as well as the internal quality management processes of the operating organization.

Requirements 5, 6 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 4 of GSR Part 3 [9];

Requirements 1–5 of SSR-2/2 (Rev. 1) [14].

To implement the project management on its own;

To train and maintain its staff to ensure safe plant operation;

To specify the site characteristics, including the external events and the features of the local infrastructure that should be taken into account in plant design;

To gain an understanding of how to meet all safety requirements and to incorporate the safety requirements properly into the call for bids;

To specify the evaluation process for bids, giving due importance to safety criteria;

To assess, with the help of external support organizations, as necessary, the safety features of the plants being offered by vendors, and to explain the conclusions of safety assessment to the regulatory body;

To verify the capabilities of the potential vendor organizations, including the vendor’s management system, in-house competences, practices and contractual arrangements in using subcontractors for major tasks and equipment supplies, and their experience in managing large construction projects;

To verify the preparedness of potential vendors to implement the project, including maturity of the detailed design;

To develop the operating organization’s own effective and efficient management system, including quality control, for construction and manufacturing, on the basis of good knowledge of national and international standards and requirements;

To consider approaches to spent fuel management and radioactive waste management.

Requirements 5, 6 and 11 of GSR Part 1 (Rev. 1) [5];

Requirement 3 of GSR Part 2 [8];

Requirement 4 of GSR Part 3 [9];

Requirement 2 of GSR Part 7 [13];

Requirement 1 of SSR-2/1 (Rev. 1) [16];

Requirements 1–32 of SSR-2/2 (Rev. 1) [14];

Requirements 58, 63 and 68 of SSR-4 [42].

Safety analysis reports (see paras 2.248–2.270 on safety assessment).

Probabilistic safety analyses (which might be included in the safety analysis report).

Operational limits and conditions (which might be included in the safety analysis report). The operation of the nuclear power plant should be controlled in accordance with a set of operational limits and conditions, derived from the safety analysis, which identify the boundaries of safe operation. The application of these operational limits and conditions is intended to prevent conditions arising that could lead to accidents and to mitigate the consequences of any such accidents, if they do occur. Operational limits and conditions are developed as part of ensuring that the plant is operated in accordance with the design assumptions and design intent as well as with its licence conditions.

Staffing (see paras 2.196–2.217 on human resources development);

Qualification and training (see paras 2.196–2.217 on human resources development);

Commissioning (see paras 3.84–3.95);

Plant operations (in conjunction with the operational limits and conditions);

Maintenance;

In-service inspection;

Surveillance;

Fuel management;

Chemistry;

Safety analysis and review;

Radiation protection (see paras 2.233–2.247);

Industrial safety;

Waste management (see paras 2.271–2.290 on safety of radioactive waste management, spent fuel management and decommissioning);

Environmental monitoring (see paras 2.233–2.247 on radiation protection and paras 3.28–3.59 on site survey and site evaluation);

Emergency preparedness (see paras 2.291–2.310 on emergency preparedness and response);

Fire safety;

Quality assurance (see paras 2.172–2.195 on leadership and management for safety and paras 2.133–2.171 on external support organizations and contractors);

Human factors;

Feedback on operating experience;

Plant modifications (see paras 3.60–3.83 on design safety);

Document control and records (see paras 2.172–2.195 on leadership and management for safety);

Management of ageing;

Decommissioning (see paras 2.271–2.290 on safety of radioactive waste management, spent fuel management and decommissioning).

Requirement 31 of GSR Part 3 [9];

Requirements 1–27 of SSR-1 [15].

Requirement 31 of GSR Part 3 [9];

Requirements 1–27 of SSR-1 [15].

Comparison and ranking studies of the candidate sites, focusing on a number of sites as identified, selected and preliminarily ranked in Phase 1;

A detailed evaluation and assessment, focusing on the selected site and making use of specific data, information and studies, as well as assessments conducted on a large scale of investigation, both temporal (e.g. prehistoric, historical and instrumental time periods) and spatial (e.g. regional, near‑regional, site vicinity and site areas).

Requirement 31 of GSR Part 3 [9];

Requirements of SSR-1 [15] as a whole.

The concept of multiple barriers and defence in depth for the prevention and mitigation of accidents and the independence of safety provisions for different levels of defence in depth;

The concept of deterministic analysis for design safety, failure criteria, redundancy, diversity and physical separation;

The concept of postulated initiating events and minimization of the plant’s sensitivity to such events;

The concepts of design basis accidents and design extension conditions;

The practical elimination of event sequences that could lead to an early or large radioactive release;

Design with sufficient margins or protection of items important to safety against internal and external hazards, with consideration of the potential for specific hazards to impact several units at the site simultaneously;

High reliability of heat transfer to an ultimate heat sink including during conditions generated by natural hazards more severe than those derived from the site evaluation;

Design features to enable the safe use of non-permanent equipment for cooling and power supply;

The systematic consideration of human factors, including the human–machine interface;

Verification of a balanced design by means of probabilistic analyses;

Safety classification of structures, systems and components and the correlation of safety classes with requirements on quality and reliability;

The use of proven codes and standards for the design of structures, systems and components;

Active versus passive safety functions;

Safety aspects of structures, systems and components important to safety, such as the reactor core, the reactor cooling system, the containment, the emergency power system and the instrumentation and control systems.

Optimization of radiation protection (for occupational and public exposure);

Minimization of the generation of radioactive waste;

The feasibility of decommissioning.

Requirements of SSR-2/1 (Rev. 1) [16] as a whole.

Requirements 5, 15, 16 and 29 of GSR Part 3 [9];

Requirements of SSR-2/1 (Rev. 1) [16] as a whole;

Requirements 15 and 16 of SSR-4 [42].

Requirements 5, 15, 16 and 29 of GSR Part 3 [9];

Requirements of SSR-2/1 (Rev. 1) [16] as a whole;

Requirements 10 and 11 of SSR-2/2 (Rev. 1) [14];

Requirements 15 and 16 of SSR-4 [42].

Requirement 25 of SSR-2/2 (Rev. 1) [14].

Overall cold and hot system performance tests;

Fuel loading;

First criticality and zero power tests;

Power tests on different levels;

Trial operation;

Commercial operation.

Confirm that the plant as built is consistent with the provisions of the safety analysis report, and record baseline data — to be used later as reference data — on the performance of structures, systems and components;

Ensure that the plant meets the requirements of the regulatory body;

Demonstrate the validity of the operating instructions and procedures, and provide an opportunity for the operating personnel to learn operating skills and acquire experience in the plant’s response to control commands;

Supply the information and data necessary to verify the adequate implementation of the integrated management system.

Requirement 7 of GSR Part 1 (Rev. 1) [5];

Requirement 2 of GSR Part 3 [9];

Provisions of SSR-6 (Rev. 1) [17] as a whole.

Design assessment: In many cases, this function will be limited in terms of scope and resources (or might not exist at all) until a nuclear power programme is established.

Witnessing of testing: The level of testing in relation to the transport of radioactive material in a nuclear power programme is significantly different from that required for the majority of shipments of radioactive material. The testing might involve skills that are not available in the regulatory body if there is no nuclear power programme.

Witnessing of manufacture: It is possible that the regulatory body for the transport of radioactive material need not witness any manufacturing until a nuclear power programme is established. Although it is the responsibility of the packaging owner to witness manufacturing, the regulatory body should periodically witness the manufacture of packaging as a part of compliance assurance.

Examination of maintenance and servicing arrangements: The complexity of packages, types of material, hostile environments and length of operating lifetime of components all introduce issues that are specific to the transport of radioactive material in a nuclear power programme. In some cases, packages used in a State will be serviced and maintained in another State until a nuclear power programme decision is made.

Monitoring of transport operations: Since the number of shipments remains reasonably constant, the monitoring of transport operations is unlikely to be of concern, either in terms of competence or in terms of resources.

Enforcement actions and investigation of incidents: Most States will have adequate capabilities in this area.

Interdepartmental liaison and cooperation: The key issue with regard to interdepartmental liaison and cooperation is that any new regulatory body that is proposed should fit into the existing regulatory framework without any overlaps or gaps.

Issuing of approvals: The issuing of approvals might be a new process for the regulatory body. The approval system may be modelled on other industries within the State (e.g. aircraft certification) or on other systems identified through networking and interactions with other States.

Regulatory review and maintenance of an effective legal framework: The area of regulatory review and maintenance of an effective legal framework might increase resource requirements, but the necessary skills should be available in one of the existing regulatory bodies. Some new legislation might be necessary.

Staff training and distribution of information: Staff training and the distribution of information on how the regulatory body works are likely to be among the first requirements in Phase 3. An advantage of globally harmonized regulations for the transport of radioactive material is that information and training can be imported from other States and adapted as necessary.

Emergency planning and exercises: Since the quantity of radioactive material being transported will increase considerably, there should be effective planning for an emergency response. Prior to a nuclear power programme, in most cases the radioactive material being transported is most likely to pose a secondary risk in a serious transport accident. However, with the development of a nuclear power programme, there could be cases in which the radioactive material could give rise to the primary risk in an accident. This could have wide ranging implications, depending on the national infrastructure and arrangements for emergency preparedness and response.

Audits of management systems: Most States will have adequate capability in the area of audits of management systems.

Requirement 7 of GSR Part 1 (Rev. 1) [5];

Requirement 2 of GSR Part 3 [9];

Requirement 2 of GSR Part 7 [13];

Provisions of SSR-6 (Rev. 1) [17] as a whole.

Requirement 7 of GSR Part 1 (Rev. 1) [5];

Requirement 2 of GSR Part 3 [9];

Requirement 2 of GSR Part 7 [13];

Provisions of SSR-6 (Rev. 1) [17] as a whole.

Requirement 12 of GSR Part 1 (Rev. 1) [5];

Requirement 6 of GSR Part 2 [8].

Requirement 12 of GSR Part 1 (Rev. 1) [5];

Requirement 6 of GSR Part 2 [8];

Requirement 5 of GSR Part 5 [11];

Requirements 2 and 23 of GSR Part 7 [13];

Requirement 8 of SSR-2/1 (Rev. 1) [16];

Requirement 17 of SSR-2/2 (Rev. 1) [14].

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Requirement 5 of GSR Part 5 [11];

Requirements 2 and 23 of GSR Part 7 [13];

Requirement 8 of SSR-2/1 (Rev. 1) [16];

Requirement 17 of SSR-2/2 (Rev. 1) [14].

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