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A n n u a l M e e t i n g o n t h e S a f e t y a n d L i c e n s i n g o f R e s e a r c h R e a c t o r s

ENRRA Cairo, Egypt 28 August – 01 September 2016

State te O Offi ffice f for Nucle lear S Saf afety Czec ech R Repu epublic

Safety Regulations of Research Reactors

Objectives

• About SÚJB
• Overview of Nuclear Facilities
• Overview of Research Reactors
• Regulatory regulations for Research Reactors – current

status

• Siting, design, construction, operation, modifications
• New regulatory requirements and their application on

Research Reactors

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Safety Regulations of Research Reactors

SÚJB main nuclear regulatory activities

SÚJB, as regulatory body of the Czech Republic executes:

• versight of nuclear facilities according to Act No. 18/1997 Coll., (the Atomic Act) on

Peaceful Utilization of Nuclear Energy and Ionizing Radiation and on Amendments and Additions to Related Acts

• the state administration and supervision performance - inspection, assessment and

administration activities (issuance of permit for specified activities, documentation assessment and approval, etc.)

SÚJB

Chairman

Nuclear Safety Section

Inspection Department Assessment Department RAW and Spent Fuel Management Division

Radiation Protection Section

Radiation Sources Department Exposure Regulation Department Radiation Protection of Fuel Cycle Department

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Safety Regulations of Research Reactors

Overview of Nuclear Facilities

Nuclear Power Plants

• NPP Temelín:

2 x VVER-1000

• NPP Dukovany:

4 x VVER-440 Radioactive Waste Repositories

• Richard – Litoměřice (industry and research RaW)
• Hostim – Beroun (closed in 1997, in operation until 1965)
• Dukovany (RaW from NPPs operation)

Spent Fuel Storages

• 2 x SFS Dukovany
• SFS Temelín

Research Reactors

• VR-1 and LR-0 (zero power reactors)
• LVR-15 (10 MW thermal)

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Safety Regulations of Research Reactors

Overview of Research Reactors

Research Reactor LR-0 Nominal power: 1 kW thermal Nuclear fuel: VVER-1000 / VVER-440 Utilization: core physics and shielding of VVER experiments Training Reactor VR-1 Vrabec Nominal power: 1 kW thermal Nuclear fuel: type IRT-4M, enrichment 19,75 % U235 Utilization: training tasks Research Reactor LVR-15 Nominal power: 10 MW thermal Nuclear fuel: type IRT-4M, enrichment 19,75 % U235 Utilization:

material research and corrosion tests of I. circuit of NPPs radiopharmaceuticals and radioisotopes production silicone doping

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Safety Regulations of Research Reactors

Regulatory regulations for Research Reactors – current status

Acts Concerning the SÚJB Regulatory Activities:

• Act No. 18/1997 Coll., on Peaceful Utilization of Nuclear Energy and Ionizing Radiation

(the Atomic Act) and on Amendments and Additions to Related Acts.

• Act No. 255/2012 Coll., on Inspection (Inspection Code)
• Act No. 500/2004 Coll., Administrative Procedure Code

Decrees implementing the Atomic Act issued by the SÚJB

• Decree of the SÚJB No. 106/1998 Coll., on Nuclear Safety and Radiation Protection

Assurance during Commissioning and Operation of Nuclear Facilities.

• Decree of the SÚJB No. 132/2008 Coll., on Quality Assurance System in carrying
• ut activities connected with utilization of nuclear energy and radiation protection.
• Decree of the SÚJB No. 146/1997 Coll., Specifying Activities Directly Affecting

Nuclear Safety and Activities Especially Important from Radiation Protection Viewpoint, Requirements on Qualification and Professional Training of Selected Personnel

Regulatory guide BN-JB-1.15 – Safety Instructions for Assurance of Nuclear Safety,

Radiation Protection, Physical Protection and Emergency Preparedness of Research Nuclear Facilities

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Safety Regulations of Research Reactors

• Requirements are set for all types of nuclear installation with nuclear reactor generally,

graded approach is applied

• A licence issued by the Office is required for

a) siting of a nuclear installation or radioactive waste repository, b) construction of a nuclear installation, c) particular stages of nuclear installation commissioning, d) operation of a nuclear installation, e) restart of a nuclear reactor to criticality following a fuel reload, f) reconstruction or other changes affecting nuclear safety, radiation protection, physical protection and emergency preparedness of a nuclear installation, g) particular stages of decommissioning of a nuclear installation, h) discharge of radionuclides into the environment, i) ionising radiation sources management, j) radioactive waste management, k) import or export of nuclear items or transit of nuclear materials and selected items, l) professional training of selected personnel, m) performance of personal dosimetry

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Conditions for nuclear energy and ionising radiation utilisation

Safety Regulations of Research Reactors

Documentation for the issue of a licence for siting of a nuclear installation or radioactive waste repository

I. Initial Safety Report which shall include 1. Description and evidence of suitability of the selected site from the aspect of siting criteria for nuclear installations or radioactive waste repositories as established in a legal implementing regulation; 2. Description and preliminary assessment of design conception from the aspect of requirements laid down in an implementing regulation for nuclear safety, radiation protection and emergency preparedness; 3. Preliminary assessment of impact of operation of proposed installation on personnel, the public and the environment; 4. Proposal of conception for safe termination of operation; 5. Assessment of quality assurance in process of selection of site, method of quality assurance for preparatory stage of construction and quality assurance principles for linking stages.

• II. Analysis of needs and possibilities of physical protection.

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Safety Regulations of Research Reactors

Documentation for the issue of a licence for construction of a nuclear installation

I. Preliminary Safety Report which shall include 1. Evidence that the proposed design meets all requirements for nuclear safety, radiation protection and emergency preparedness, 2. Safety analyses and analyses of the potential unauthorised handling of nuclear materials and ionising radiation sources, and an assessment of their consequences for personnel, public and environment, 3. Information on predicted lifetime of nuclear installation, 4. Assessment of nuclear waste generation and management of it during commissioning and operation of the installation or workplace being licensed, 5. Conception of safe termination of operation and decommissioning of the installation or workplace being licensed, including disposal of nuclear waste; 6. Conception for spent nuclear fuel management; 7. Assessment of quality assurance during preparation for construction, 8. List of classified equipment. * II. Proposed method of providing physical protection * *The documentation specified under I.8 and II shall be subject to approval by the Office.

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Safety Regulations of Research Reactors

Documentation for the issue of a licence for nuclear installation operation

1. Supplements to the Pre-operational Safety Report and further supplements to documentation required for the issue of a licence for the first nuclear fuel loading into the reactor, 2. Evaluation of results of previous commissioning stages, 3. Evidence of implementation of previous decisions and conditions of the Office, 4. Evidence that installation and personnel are prepared for operation, 5. Operation time schedule, 6. Limits and conditions for safe operation.*

*The documentation specified under point 6. shall be subject to approval by the Office.

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Safety Regulations of Research Reactors

Documentation for the issue of a licence for reconstruction or other changes impacting on nuclear safety, radiation protection, physical protection or emergency preparedness of nuclear installation

1. Description and justification of prepared reconstruction or other changes, 2. Up-date of documentation approved for commissioning and operation of nuclear installation, 3. Anticipated time schedule for reconstruction or changes, 4. Evidence that the consequences of reconstruction or other changes will not adversely influence nuclear safety, radiation protection, physical protection or emergency preparedness. *Documentation specified under point 2 shall be subject to approval by the Office.

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Safety Regulations of Research Reactors

Role of the Office as Regulatory Body in the processes

• f licencing (1/2)

1. In administrative proceedings, the Office shall conduct independently of the proceedings of any other administrative body. The applicant shall be the

• nly participant in the proceedings.

2. The Office shall take a decision on the issue of a licence having verified that the applicant has fulfilled all the conditions within a) four months, in the case of a licence for siting of a nuclear installation, b)

• ne year, in the case of a licence for construction of a nuclear installation,

c) six months, in the case of a licence for the first fuel load into a reactor, d) 10 days in the case of commissioning stages , e) 24 hours, in the case of restart of a nuclear reactor to criticality following a fuel reload, f) 90 days, in the case of other licences for particular practices.

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Safety Regulations of Research Reactors

Role of the Office as Regulatory Body in the processes

• f licencing (2/2)

Requisites of Licence In decision on the issue of a licence, the Office a) shall specify identification of the applicant and the assigned registration number; b) shall define the subject and scope of the practice being licensed; c) shall set conditions for performance and termination of the practice being licensed, as required from the aspect of nuclear safety, radiation protection and physical protection and conditions for emergency preparedness; d) shall specify the period for which the licence is issued (the Office can issue a licence for an indefinite period of time as well - in case of construction, modifications, discharge of radionuclides, ionising radiation sources management, etc.)  An integral part of the licence Statement shall be an approval of documentation specified in each of the licencing stages (siting, construction,

• peration, ...).

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Safety Regulations of Research Reactors

New regulatory requirements and their application on Research Reactors

Act no. 18/1997 Coll., on Peaceful Utilization of Nuclear Energy and Ionizing Radiation (the Atomic Act) and on Alterations and Amendments of Some Legislation

– Adopted by the czech Parliament in 1996, came into effect in 1997 – Amended by 24 subsequent acts – 50 articles and 1 annex (18 parts)

New Atomic Act

– in the legislative process – approved by Chamber of Deputies – Implementing legislation – various stages of the legislative process – 238 articles and 2 annexes

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Safety Regulations of Research Reactors

New regulatory requirements and their application on Research Reactors

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Safety Regulations of Research Reactors

Atomic Act

Scope Definitions and source classification Specific security provisions SONS Fees General provisions Technical safety Specific radiation protection provisions Licensing Obligations of a licensee (general & specific) Type approval (sources and packaging) Radioactive waste management Civil liability for nuclear damage State supervision, remedial measures and penalties

New Atomic Act

– Chapter I - Introductory provisions – Chapter II

• Use of nuclear energy (Art. 43 – 59)
• Radiation protection
• Complete decommissioning
• Management of radioactive waste and

spent nuclear fuel

• Fees
• Type-approval of certain products and

transport

• Radiation situation monitoring
• Radiological emergency management
• Security
• Non-proliferation of nuclear weapons

– Chapter III – Penalties – Chapter IV – State supervision – Chapter V – Final, transitional provisions

New regulatory requirements and their application on Research Reactors

For the first time definition of Research Reactor in Czech legislative is about to be established! „Research nuclear installation means a nuclear installation with a nuclear reactor, which is used as a source of ionising radiation for the purposes of research, education, production of radionuclides, neutron radiography, testing of materials, or the provision of health services, whose output does not exceed 50 MWt and whose main purpose is not electricity or heat production.“

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Safety Regulations of Research Reactors

New regulatory requirements and their application on Research Reactors

Graded Approach „When ensuring nuclear safety, radiation protection, technical safety, radiation situation monitoring, radiological emergency management and security while using nuclear energy or performing activities in exposure situations, a graded approach, depending on the magnitude of potential exposure and its possible consequences (hereinafter “graded approach”), shall be applied.“ The graded approach shall be commensurate to a) the type of the nuclear installation or category of the workplace with sources of ionising radiation, b) the type of nuclear material and radioactive waste present in the nuclear installation and c) the activities carried out.

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Safety Regulations of Research Reactors

New regulatory requirements and their application on Research Reactors

Categorisation in the area of the use of nuclear energy safety functions

– 3 categories – in accordance with the graded approach

selected equipment

– 3 safety classes – for the purposes of applying the graded approach to ensuring its quality – depending on the safety functions to the performance of which its contributes

• perational occurrences

– significant or less significant – depending on their impact on nuclear safety – for the purposes of utilising the feedback system for activities related to the use of nuclear energy

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Safety Regulations of Research Reactors

New regulatory requirements and their application on Research Reactors

Principles of the safe use of nuclear energy Nuclear safety, radiation protection, radiation situation monitoring, radiological emergency management, and security of nuclear installations shall be ensured throughout the life cycle of a nuclear installation by means of defence-in-depth A nuclear installation with a nuclear reactor shall

– allow for immediate and safe shut-down of the nuclear reactor and for maintaining it in a subcritical state – prevent the uncontrolled development of a fission chain reaction – make it physically impossible for a critical or supercritical state to develop outside the inner part of a nuclear reactor – ensure dissipation of the heat produced by nuclear fuel and technological systems – ensure shielding and prevent the release of a radioactive substance and propagation of ionising radiation into the environment

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Safety Regulations of Research Reactors

New regulatory requirements and their application on Research Reactors

Licence – use of nuclear energy Performing all the activities related to the use of nuclear energy requires licence (exception – urgent action to mitigate or avert) Licence

– the siting of a nuclear installation, – the construction of a nuclear installation, – the first physical start-up of a nuclear installation with a nuc. reactor, – the first power-generation start-up of a nuclear installation with NR, – the commissioning of a nuclear installation without a nuc. reactor, – the operation of a nuclear installation, – the individual phases of decommissioning of a nuclear installation, and – the carrying out of modifications affecting nuclear safety, technical safety and physical protection of a nuclear installation.

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Safety Regulations of Research Reactors

Requirements for nuclear installation design and the design process

Nuclear installation design

– in a manner ensuring their nuclear safety, radiation protection, radiation situation monitoring, radiological emergency management, and security throughout their life cycle – design basis – proven methods, procedures and technology – requirements for technical procedures and organizational measures for construction, commissioning and decommissioning

Modification of a nuclear installation

– prior to implementation – subject to the design process – documented

Documentation of the nuclear installation

– correspond to the actual state of the nuclear installation

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Safety Regulations of Research Reactors

Requirements for nuclear installation design and the design process

Nuclear installation design

– compliance with

• safety objectives
• principles of the safe use of nuclear energy
• defence-in-depth
• prevention, resilience and protection against the hazards resulting from the

characteristics of the area where the nuclear installation is sited and from external influences & internal influences

• requirements for the technical means of radiation protection assurance
• requirements for radiological emergency management
• requirements for security

– safety functions in accordance with their categorisation – selected equipment

• requirements in terms of the safety functions
• classify into safety classes

– …

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Safety Regulations of Research Reactors

Siting of a nuclear installation

Assessment of the characteristics of an area where a nuclear installation is to be sited

– characteristics that can affect nuclear safety, radiation protection, technical safety, radiation situation monitoring, radiological emergency management and security – impact of the nuclear installation on individuals, the general public, the society and the environment

Siting not allowed in an area

– characteristics negatively affecting above mentioned – unsolvable for present level of science and technology

Baseline survey of the location where the nuclear installation is to be sited (radiation situation & radionuclide content)

– prior to siting a nuclear installation – values retained for the needs of the complete decommissioning

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Safety Regulations of Research Reactors

Obligations – construction of a nuclear installation

Existing level of safety of another nuclear installation located in the area where the nuclear installation under constructions is sited must not degrade Testing in accordance with the trials and testing programme Readiness of the nuclear installation and its personnel for the first physical start-up

– non-active testing – compliance with the pass criteria – completeness and readiness of all systems necessary for the first physical start-up

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Safety Regulations of Research Reactors

Obligations – operation of a nuclear installation

General obligations

– stable and safe operation – continuously ensure, verify and document – decommissioning (inform about planed cessation, reserves, take away spent fuel, ensure decommissioning immediaetly) – long-term shut-down of the research nuclear installation

Obligations prior to bringing a nuclear reactor to criticality

– good working order of structure, components and systems – analyse and eliminate the causes that led to the shut-down and take corrective action (shut-down for unplanned causes) – ensure and verify the readiness of the nuclear installation and its personnel

Obligations after replacement of the nuclear fuel

– pass criteria for works and tests relating to fuel replacement – perform all the checks required for physical & power-generation start-up – provide evidence of the readiness of the nuclear installation

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Safety Regulations of Research Reactors

Thank you for your attention

Contact details Michal Hodáň email: michal.hodan@sujb.cz tel.: +420 221 624 232 State Office for Nuclear Safety Senovážné nám. 9, Praha 1 Czech Republic

Safety Regulations of Research Reactors