IAEA Safety Standards for Research Reactors

Transcription

1 Safety Standards for Research Reactors David Sears Research Reactor Safety Section Division of Nuclear Installation Safety ANSN Workshop on Periodic Safety Review of RRs 2-6 December 2013, BAPETEN Training Centre, Indonesia. International Atomic Energy Agency

2 Contents Safety Standards: Categories Existing and long-term structure of the Safety Standards Safety Standards for Research Reactors Supporting Documents Concluding remarks

3 Existing Structure of the Safety Standards Two categories 1. Thematic: Areas of a cross-cutting nature 2. Facility-specific: Nuclear power plants (NPPs), research reactors (RRs), fuel cycle facilities, etc. The structure consists of a small number of thematic safety standards and a larger number of facility-specific safety standards.

4 Long-term Structure of the Safety Standards The structure ensures a logical relationship between the Safety Standard Fundamental Safety Principles (SF-1), and the Safety Requirements and Safety Guides.

5 Safety Standards for Research Reactors The Safety Standards for RRs reflect international consensus on what constitutes a high level of safety, and: Serve as the basis for safety review services and assistance; Cover all areas important to the safety of RRs; Provide guidance for effective implementation of the Code of Conduct on the Safety of Research Reactors ; Should be used by all organizations involved in RRs, including the operating organization, regulatory body, users, designers and vendors; Use regulatory language to facilitate their incorporation into national safety regulations and guides

6 Safety Standards for Research Reactors SF-1 Fundamental Safety Principles NS-R-4 Safety of Research Reactors NS-G-4.1 Commissioning of RRs NS-G-4.2 Maintenance, Periodic Testing and Inspections of RRs NS-G-4.3 Core Management and Fuel Handling for RRs NS-G-4.4 Operational Limits and Conditions and Operating Procedures for RRs NS-G-4.5 The Operating Organization and the Recruitment, Training and Qualification of Personnel for RRs NS-G-4.6 Radiation Protection and Radioactive Waste Management in the Design and Operation of RRs

7 Safety Standards for Research Reactors SSG-10 Ageing Management for RRs SSG-20 Safety Assessment for RRs and Preparation of the Safety Analysis Report SSG-22 Use of a Graded Approach in the Application of the Safety Requirements for RRs SSG-24 Safety in the Utilization And Modification of RRs WS-G-2.1 Decommissioning of NPPs and RRs DS 436 Instrumentation and Control and Software Important to Safety for RRs

8 NS-R-4: Safety of Research Reactors Design Regulatory Supervision Operation Decommissioning Management and Verification of Safety Site Evaluation RRs with power levels in excess of several tens of megawatts, fast reactors, and RRs using an experimental device, such as a high-pressure and temperature loop or a cold neutron source, may require application of safety standards for NPPs or additional safety measures.

9 NS-G-4.1: Commissioning of RRs Provides guidance on preparation and implementation of a commissioning programme Can also be used for: Re-commissioning of a RR after an extended period of shutdown; Commissioning of a new experimental device; Commissioning of a modification with major safety significance

10 NS-G-4.2: Maintenance, Periodic Testing and Inspection of RRs Provides guidance on preparation and implementation of maintenance, periodic testing and inspection programmes Covers topics related to: Preventive and corrective maintenance of safety systems and components (SSCs); Testing intended to ensure that operations are within the established operating limits and conditions (OLCs); Inspections initiated by the operating organization of SSCs to determine whether they are acceptable for continued safe operation

11 NS-G-4.3: Core Management and Fuel Handling for RRs Provides guidance on core management and fuel handling activities that should be performed to optimize reactor core operation and reactor utilization in a manner that ensures the safety of the fuel and the reactor Covers topics related to: Core design; Core operation; Monitoring core safety parameters; Refuelling; Receipt, storage, handling and transport of fresh and irradiated fuel

12 NS-G-4.4: Operational Limits and Conditions and Operating Procedures for RRs Provides guidance on all important aspects of developing, formulating and presenting the OLCs, including: Safety limits; Safety system settings; Limiting conditions for safe operation; Surveillance requirements; Administrative requirements Provides guidance on development, content and implementation of operation procedures that should ensure that reactor operations in all modes and operations of experiments are consistent with the OLCs

13 NS-G-4.5: The Operating Organization and the Recruitment, Training and Qualification of Personnel for RRs Provides guidance on the following topics: The nature of the operating organization and how to establish the operating organization; The recruitment process and required qualifications for reactor personnel ; The initial training and re-training programmes for reactor personnel; The authorization process for individuals whose duties have immediate effects on safety

14 NS-G-4.6: Radiation Protection and Radioactive Waste Management in Design and Operation of RRs Identifies and provides guidance on important components that should be considered in the design stage to facilitate radiation protection and waste management Provides good practices to be followed in operational radiation protection and radioactive waste management programmes and their optimization

15 SSG-10: Ageing Management for RRs Provides guidance on the following topics: Ageing management in different stages of the lifetime of a RR; Elements for a systematic programme on ageing management for SSCs important to safety; Managing obsolescence; Interfaces of ageing management with other technical areas such as maintenance, periodic safety reviews, equipment qualification, design basis reconstitution, configuration management, continued safe operation and post-service surveillance

16 SSG-20: Safety Assessment of RRs and Preparation of the Safety Analysis Report Provides guidance on the preparation, review and assessment of the safety analysis report (SAR) Provides guidance on the initial licensing process for new RRs, and also on re-licensing and periodic safety reviews of existing RRs

17 SSG-22: Use of a Graded Approach in the Application of the Safety Requirements for RRs Provides guidance for grading the application of the safety requirements to account for the differences in RR designs, operation and utilization programmes Covers using a graded approach throughout the various stages of the lifetime of a RR without compromising safety Can be used by use by regulatory bodies, operating organizations and other organizations involved in the design, construction and operation of research reactors

18 SSG-24: Safety in the Utilization and Modification of RRs Provides guidance on the safety categorization of modifications and utilization activities and the associated safety assessments, reviews and approval channels Applies to existing and new research reactors and new experiments and utilization activities

19 DS 436: Instrumentation and Control and Software Important to Safety for RRs The document is intended to provide guidance on the safety during the design, operation and maintenance of the instrumentation and controls (I&C) and software important to safety for new RRs The document will also cover safety aspects to be considered in different stages of projects for replacement or modernization of I&C systems of existing RRs During the end of 2012, the draft document received clearance from the Nuclear Safety Standards Committee and Nuclear Security Guidance Committee to deliver the draft to Member States for comment Member States provided comments by 31 May, 2013, on the draft guide and the is currently responding to the comments

20 Some other Safety Guides that can be used for RRs GS-G-3.1 Application of the Management System for Facilities and Activities NS-G-1.4 Design of Fuel Handling and Storage Systems in Nuclear Power Plants NS-G-1.7 Protection Against Internal Fires and Explosions in the Design of Nuclear Power Plants NS-G-2.1 Fire Safety in the Operation of Nuclear Power Plants SSG-15 Storage of Spent Nuclear Fuel DS407 Criticality Safety for Facilities and Activities Handling Fissionable Material

21 Supporting Documents Complement the Safety Standards and include Safety Reports and TECDOCs Provide technical information, practical examples and detailed methods that can be used to implement the Safety Standards Do not establish requirements or recommendations

22 Safety Standards and Supporting Publications for RRs Available Online Safety Standards homepage: Safety Standards for RRs: Safety Report Series: TECDOCs:

23 Concluding Remarks Application of the Safety Standards will help Member States to achieve the highest level of safety for RRs The programme on the safety of RRs gives priority to the development and promotion of proper use of the Safety Standards through: Providing assistance to Member States in application of the Safety Standards; Conducting of safety review missions based on the Safety Standards; Implementing workshop and other training activities based on the Safety Standards

24 Thank you for your kind attention! This activity is conducted by the, with funding by the European Union, among others. The views expressed in this presentation do not necessarily reflect the views of the European Union. International Atomic Energy Agency