Regulatory Issues and Challenges in Preparing for the Regulation of New Reactor Siting: Malaysia s Experience

Transcription

1 Regulatory Issues and Challenges in Preparing for the Regulation of New Reactor Siting: Malaysia s Experience Azlina Mohammad Jais a,b a Atomic Energy Licensing Board (AELB) Malaysia b Universiti Kebangsaan Malaysia (UKM) Halimah Hassan Department of Environmental (DOE) Malaysia Muhamad Samudi Yasir Universiti Kebangsaan Malaysia (UKM) CNRA International Workshop on New Reactor Siting, Licensing & Construction Experience ; September 2010, Prague, Czech Republic

2 OUTLINE Atomic Energy Licensing Board (AELB), Acts and Regulations Overview on the status of nuclear power development Licensing Process for NPP Regulatory Issues and Challenges Approach to facilitate Licensing Process for a Site License Siting Criteria and guidelines Selection and Evaluation for NPP Site Radiological and Environmental Impact Assessment (RIA/EIA) Social Impact Assessment (SIA) Human Resources Summary Conclusion

3 Atomic Energy Licensing Board (AELB)- A Regulatory Body for Radiation and Nuclear Activities in Malaysia Branch Branch AELB HQ Branch No Staff: 165 Licensee: > 1000 Medical and nonmedical activities, I Research Reactor (Triga Mark II), 1 mwt Branch

4 AELB - Independent RB Minister of Science, Technology & Innovation Ministry of Science, Technology & Innovation The Board (5 Members) Executive Secretary Director General AELB Department Standing Safety Committee Sub-standing Safety Committee Nuclear Installation Division Technical Support Division Policy, Code & Standard Division Licensing Division Administrative Services Division Enforcement Division

5 Atomic Energy Licensing Act, 1984 (Act 304) and its Regulations Atomic Energy Licensing Act 1984 (Act 304) Appointment of date of coming into force [P.U.(B) 44/85] Radiation Protection (Licensing) Regulations 1986 [P.U.(A) 149/86] CORRIGENDUM to Radiation Protection (Licensing) Regulations 1986 [P.U.(A) 355/86] Radiation Protection (Basic Safety Standard) Regulations 1988 [P.U.(A) 61/88] Atomic Energy Licensing (Exemption) Order 1988 [P.U.(A) 189/89] Atomic Energy Licensing (Exemption) Order 1989 [P.U.(A) 50/89] Atomic Energy Licensing (Exemption) (Smoke Detectors) Order 1989 [P.U.(A) 422/89] Radiation Protection (Transport) Regulations 1989 [P.U.(A) 456/89] Atomic Energy Licensing (Exemption) (Lightning Arrestor) Order 1990 [P.U.(A) 12/90] Atomic Energy Licensing (Exemption) (Leasing and Hire Purchase) Order 1990 [P.U.(A) 205/90] Atomic Energy Licensing (Appeal) Regulations 1990 [P.U.(A) 206/90] Radiation Protection (Transport) (Amendment) Regulations 1991 [P.U.(A) 145/91] CORRIGENDUM to Radiation Protection (Transport) Regulations 1989 [P.U.(A) 146/91] Atomic Energy Licensing (Small Amang Factory) (Exemption) Order 1994 [P.U.(A) 435/94] Atomic Energy Licensing (Exemption) (Ceramic Factory) Order 1998 [P.U.(A) 431/98] Note: This Order has been repealed by P.U.(A) 182/2002 Atomic Energy Licensing (Exemption) (Scanning Electron Microscope) Order 1998 [P.U.(A) 432/98] Atomic Energy Licensing (Exemption) (Irradiating Apparatus Below 5 Kilo Electron Volt) Order 2002 [P.U.(A) 181/2002] Atomic Energy Licensing (Exemption) (Low Activity Radioactive Material) Order 2002 [P.U.(A) 182/2002]

6 Preparation for NPP- Roles & Responsibilities of Key Players Ready to Ready make to a make knowledgeable a commitment knowledgeable to a nuclear programme decision Ready to invite bids Phase 1 Phase 2 Phase 3 Ready to commission and operate Ready the first to NPP commission Government Cabinet Decision 26th June Nuclear energy as an option) Regulatory Body Strengthening Legal framework- AELB, EC etc Policy & Public Acceptance 40 relevant national laws & regulations identified International commitment (45 Instruments identified) Operating Organization Industrial participation M1 Potential developer/operator M2 Source: IAEA M3

7 CABINET COMMITTEE ON ENERGY NUCLEAR POWER DEVELOPMENT STEERING COMMITTEE (Cabinet Decision 26th June 2009) Ministry of Energy, Green Technology and Water PROGRAM DEVELOPMENT WORKING COMMITTEE Nuclear Malaysia Agency Educational Program and Public Awareness Human Capital Development Technology Assessment PROJECT DEVELOPMENT WORKING COMMITTEE Tenaga Nasional Bhd. (TNB) Site Identification Nuclear Fuel Procurement Planning Nuclear Power Plant Conceptual Design, including Project Management and Quality Assurance REGULATORY DEVELOPMENT COORDINATION WORKING COMMITTEE Atomic Energy Licensing Board (AELB) and Energy Commission (ST) Regulation and Licensing of Electricity Generation Regulation and Licensing of Nuclear Power Plant International Legal Instruments & Governance Contribute in the development of Nuclear Power Infrastructure Development Programme (NPIDP)

8 Strengthening Regulatory Infrastructure for NPP National and International Nuclear Legislation and Regulations Assessment NPP Site License NPP construction License Study Implementation of Strategy and Action Plan (Output from assessment studies) NPP Operation License

9 Authorities Involved In Regulating The Nuclear Power Plant in Malaysia 9 Nuclear Island AELB ( & DOE, DOSH) Non-Nuclear Island EC ( & DOE, DOSH, MHLG etc.)

10 Temporary operation LICENSING PROCESS OF NUCLEAR POWER PLANT 3 STEPS LICENSE Class G Class A & B Class F Operation Licence Site Licence Construction licence Full Operation (fuel loading) Decom. Licence Radiation Protection (Licensing) Regulation, 1986

11 Site Licence Site Evaluation Report Description of the proposed installation and activities Physical characteristic of the site Population distribution Present land use Radiological, Environmental & social impact assessment Pre-operational radiological monitoring programme A description of storage facilities for radioactive materials or nuclear materials on the site Decommissioning plan Any additional information required by appropriate authority Licensing Process of NPP- Technical Information Required Construction Licence Preliminary Safety Analysis Report General layout and detail plan and design of the facility Updated EIA & RIA Postulated initiating event (A statement with respect to potential accidents and unscheduled releases of wastes and hazardous materials from the facility) Any additional information required by appropriate authority Temporary Operation Licence Any change, in the material used or in the design Radiation Protection Programme (A description of proposed measures to control radiation exposures) A detail medical surveillance programme A programme for initial and periodic training Operational radiological monitoring programme (quality and quantity of effluents to be discharge or emission from the facility) Design Basis Accident (proposed procedures to prevent accident and the proposed contingency plan in the event of an accident) Design basis Threat (plan and procedures to prevent loss, theft, or unauthorized used) Any additional information required by appropriate authority Note: Preliminary SAR Siting, Intermediate SAR Construction Final SAR - Operation Full Final Safety Analysis Report Any additional information required by appropriate authority

12 PUBLIC GOVERNM ENT GOVT. AGENCIES EXTERNAL EXPERT AELB APPLICAN T (Utility Provider) Regulatory Issues and Challenges [1] Approach to facilitate Licensing Process for a Site License Letter of Intent Prepare and submit document Additional information License notification SIA, EIA, LCP Advice applicant on license requiremen t Form inter agencies comm. to review Conform regulatory requiremen t Consult expert Decision (accept/ reject) Prepare licence One Gate Licensing Process with Multiple Regulatory Authorities Issue report to minister Report review Public participation (JPBD, DOE) Decision (issue license) 12 Public feedback

13 Act Act 304, 1984 Atomic Energy Licensing (Basic Safety Radiation Protection) Regulations 2010 Radiation Protection (Nuclear Installation Licensing) Regulations 201_ Radiation Protection (Radioactive Waste Management) Regulations 201_ Atomic Energy Licensing (Security of Radioactive Sources) Regulations 201_ Atomic Energy Licensing (Security of Nuclear Materials) Regulations 201_ Atomic Energy Licensing (Safeguards Of Nuclear Activities) Regulations 201_ Radiation Protection (Medical Dental and Veterinary Usage of Radiation) Regulations 201_ Atomic Energy Licensing (Transport Security) Regulations 201_ Radiation Protection (Licensing) Regulations 1986 Radiation Protection (Transport) Regulations 1989 Radiation Protection (Appeal) Regulations 1990 Regulatory Issues and Challenges [2]- Siting Criteria and Guidelines GS-G-1.6Regulato Issues ry Seismic Design and Qualification for NPP GS-G-3.3 Evaluation of Seismic Hazard for NPP GS-G-4.1 Format and Content of SAR for NPP NS-G-1.1 Software for Computer Based System Important to Safety in NPP NS-G-1.7 Protection Against Internal Fires and Explosion In the Design of NPP NS-G-1.11 Protection against Internal Hazard Other than Fire and Explosion Design of NPP NS-G-1.12 Design of Reactor Core for NPP NS-G-1.13 Radiation Protection Aspect of Design for NPP NS-G-2.1 Fire Safety in the Operation of NPP NS-G-1.2 NS-G-2.2 Safety Assessment and Verification To for date, NPP Operation a Limit total & Condition and Operating of Procedures For NPP NS-G-1.4 Design of Fuel Handling and Storage NS-G-2.3 System For NPP Modification to NPP over 100 IAEA NS-G-1.5 NS-G-2.4 External Event Excluding Earthquake The Operating Organization for NPP NS-G-2.7 Radiation Protection and Radioactive Waste Management in the Operation of NPP NS-G-1.8 NS-G-2.8 Design of Emergency Power System for NPP Recruitment, Qualification & Training of Personnel for NPP NS-G-1.9 Design of Reactor Coolant System and NS-G-2.9 Associated System in NPP Commissioning for NPP NS-G-1.10 documents NS-G-2.10 on Design of Reactor Containment System for NPP Periodic Safety Review for NPP NS-R-1 Safety for NPP Design National Guideline on Safety Assessment And Preparation of SAR Standard for Certification and Re-certification of RR Operator Guideline for Approval Application of Nuclear Material Transit Guideline for IAEA Safeguard Inspector Designation and Issuance of Multiple Entry Visa Guideline for Inspection Procedure For Research Reactors Guideline for Approval Application Of Transshipment of NM Standard for Certification of Inspector And Assessor Guidelines on Security of Radioactive Sources standards & guidance NPP were Guidance Documents adopted by the Guideline for Assessment of Reactor Modification Board In addition, Nuclear Siting Guidelines of Finland, Canada, RO Korea, USA & were adopted by the Board Guideline on the Site Evaluation For Nuclear Installation Guideline on Nuclear Emergency Preparedness Program Guideline on Physical Protection of Nuclear Installation NS-G-2.11 A System for the Feedback of Experience From Events in Nuclear Installation NS-G-3.1 External Human Induce Event in Site Evaluation for NPP NS-G-3.2 Dispersion of Radioactive Material in Air and Water and Consideration of Population Distribution in Site Evaluation For NPP NS-G-3.5 Flood Hazard for NPP on Coastal and River Site NS-G-3.6 Geotechnical Aspect of Site Evaluation and Foundation for NPP WS-G-2.1 Decommissioning for Research Reactor and NPP NS-R-2 Safety of NPP Operation NS-R-3 Site Evaluation for Nuclear Installation NS-G-2.5 Core Management and Fuel Handling for NPP NS-G-3.4 Meteorological Event in Site Evaluation for NPP Legend Adopted by Board In Preparation/Drafting Under Planning In Revision Published Approved by Board

14 IAEA Standards and Guidelines Adopted by AELB GS-R-1 Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety INSAG-5 The Safety of Nuclear Power INSAG-12 Basic Safety Principles for Nuclear Power Plants INSAG-22 Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles INSAG-21 Strengthening the Global Nuclear Safety Regime - IAEA Handbook on Nuclear Law GS-G-1.1 Organization and Staffing of the Regulatory Body for Nuclear Facilities Infrastructure for Research and Development in Nuclear Safety GS-G-1.2 Review and Assessment of Nuclear Facilities by the Regulatory Body GS-G-1.3 Regulatory Inspection of Nuclear Facilities and Intakes of Radionuclides Enforcement by the Regulatory Body RS-G-1.3 DS416 Assessment of Occupational Exposure due to Licensing Process for Nuclear Installations External Sources of Radiation GS-G-1.5 RS-G-1.4 Regulatory Control of Radiation Sources Building Competence in Radiation Protection and WS-G-2.3 the Safe Use of Radiation Sources Regulatory Control of Radioactive Discharges to the Environment Application of the Concepts of Exclusion, INSAG-17 Exemption and Clearance RS-G-1.8 Independence in regulatory decision making Environmental and Sources Monitoring for INSAG-20 Purposes of Radiation Protection Stakeholder Involvement in Nuclear Issues DS427 GSR Part 5 Radiological Environmental Impact Analysis for the Predisposal Management of Radioactive verification of Radiological Protection WS-R-5 INSAG-9 Decommissioning of Facilities Using Radioactive Material DS429 External Expert Support on Safety issues GS-G-3.2 The Management System for Technical Services in Radiation Safety DS349 The Management System for Nuclear Installations INSAG-18 Managing Change in the Nuclear Industry: the Effects on Safety GS-G-3.3 The Management System for the Processing, Handling and Storage of Radioactive Waste GS-G-3.4 The Management System for the Disposal of Radioactive Waste TS-G-1.4 Management System for the Safe Transport of Radioactive Material INSAG-13 Management of Operational Safety in Nuclear Power Plants INSAG-15 Key Practical Issues in Strengthening Safety Culture RS-G-1.4 Building Competence in Radiation Protection and the Safe Use of Radiation Sources INSAG-16 Maintaining Knowledge, Training and RS-G-1.1 Occupational Radiation Protection RS-G-1.2 Assessment of Occupational Exposure due to RS-G-1.7 Potential Exposure in Nuclear Safety DS365 Risk-Informed Decision Making GS-G-1.2 Review and Assessment of Nuclear Facilities by the Regulatory Body DS 395 Deterministic Safety Analyses and their Application for Nuclear Power Plants 111-G-1.1 Classification of Radioactive Waste DS390 Classification of Radioactive Waste WS-G-2.5 Predisposal Management of Low and Intermediate Level Radioactive Waste WS-G-2.6 Predisposal Management of High Level Radioactive Waste WS-G-6.1 Storage of Radioactive Waste DS284 Safety Assessment for Radioactive Waste Predisposal Facilities and Activities WS-R-5 Decommissioning of Facilities Using Radioactive Material DS354 Disposal of Radioactive Waste (to become new SSR5) GS-G-3.3 The Management System for the Processing, Handling and Storage of Radioactive Waste NS-R-5 Safety of Nuclear Fuel Cycle Facilities DS371 Storage of Spent Fuel GS-G-2.1 Arrangements for Preparedness for a Nuclear or Radiological Emergency SS109 Intervention Criteria in a Nuclear or Radiation Emergency DS44 Criteria for Use in Planning Response to Nuclear and Radiological Emergencies TS-G-1.2 Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material NS-G-2.12 Ageing Management for Nuclear Power Plants NS-G-2.14 Conduct of Operations at Nuclear Power Plants DS385 Severe Accident Management Programme for Nuclear Power Plants DS388 Chemistry Programme for Water Cooled Nuclear Power Plants INSAG-23 Improving the International System for Operating Experience Feedback 50-SG-S9 Site survey for Nuclear Power Plants (under update and revision process) DS405 Volcanic hazards for nuclear installations DS367 Safety Classification of Structures, Systems and Components in Nuclear Power Plants DS393 Development and Application of Level 2 PSA for Nuclear Power Plants DS394 Development and Application of Level 1 PSA for Nuclear Reactors DS395 Deterministic Safety Analyses and their Application for Nuclear Power Plants SS79 Design of Radioactive Waste Management Systems at Nuclear Power Plants GSR Part 4 Safety Assessment for Facilities and Activities INSAG-6 Probabilistic Safety Assessment INSAG-10 Defence in Depth in Nuclear Safety TS-G-1.1 (Rev.1) Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material TS-G-1.2 Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material TS-G-1.3 Radiation Protection Programmes for Transport Radioactive Material TS-G-1.4 Management System for the Safe Transport of Radioactive Material TS-G-1.5 Compliance Assurance for the Safe Transport of Radioactive Material INSAG-24 Safety and Security Interface in Nuclear Installations Additional 56 IAEA Std. & 16 draft Std. adopted in 2010

15 National Standards and Guidelines Adopted by AELB USNRC : Reactor Site Criteria (10 Code of Federal Regulation, Part 100), Standards For Protection Against Radiation (10 Code of Federal Regulation, Part 20), Domestic Licensing Of Production And Utilization Facilities (10 Code of Federal Regulation, Part 50) Physical Protection Of Plants And Materials (10 Code of Federal Regulation, Part 73) Site Investigations For Foundations Of Nuclear Power Plants (Regulatory Guide 1.132), 2003 Laboratory Investigations Of Soils And Rocks For Engineering Analysis And Design Of Nuclear Power Plants (Regulatory Guide 1.138), 2003 Identification And Characterization Of Seismic Sources And Determination Of Safe Shutdown Earthquake Ground Motion (Regulatory Guide 1.165), 1997 Procedures And Criteria For Assessing Seismic Soil Liquefaction At Nuclear Power Plant Sites (Regulatory Guide 1.198), 2003 A Performance-Based Approach To Define Te Site-Specific Earthquake Ground Motion (Regulatory Guide 1.208), 2007 Preparation Of Environmental Reports For Nuclear Power Stations (Regulatory Guide 4.2), 1976 General Site Suitability Criteria For Nuclear Power Stations (Regulatory Guide 4.7), 1998 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plant (NUREG 654). November 1980 Standard Format and Content of Safety Analysis Report for Nuclear Power Plants: LWR Edition (Regulatory Guide 1.70, Revision 3). November 1978 Assumption Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors (Regulatory Guide 1.3, Revision 2). June 1974 Assumption Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors (Regulatory Guide 1.4, Revision 2). June 1974 Assumption Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Regulatory Guide 1.4, Revision 2). June 1974 Meteorological Monitoring Programs for Nuclear Power Plants (Regulatory Guide 1.23, Revision 1). March 2007 Assumption Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel handling and Storage Facility for Boiling and Pressurized Water Reactors (Regulatory Guide 1.25, Revision 0). March 1972 Ultimate Heat Sink for Nuclear Power Plants (Regulatory Guide 1.27, Revision 2). January 1976 Seismic Design Classification (Regulatory Guide 1.29, Revision 4). March 2007 Design Basis Flood for Nuclear Power Plants (Regulatory Guide 1.59, Revision 2). August 1977 Evaluating the Habitability of a Nuclear Power Plants Control Room during a Postulated Hazardous Chemical Releases (Regulatory Guide 1.78, Revision 1). December 2001 Atmospheric Dispersion Models for Potential Accident Consequences Assessment at Nuclear Power Plants (Regulatory Guide 1.145, Revision 1). February 1983 Canada: Site Evaluation for New Nuclear Power Plants. Canadian Nuclear Safety Commission. Regulatory Documents (RD) No. 346, 2008 EPRI,USA Siting Guide: Site Selection and Evaluation Criteria for an Early Site Permit Application. Electric Power Research Institute, Inc. (EPRI) 2002 Finland: Safety Criteria For Siting A Nuclear Power Plant. Radiation and Nuclear Safety Authority (STUK). Guide YVL No. 1.10, July 2000 Adopted by Board in 2010 for reference purposes

16 Regulatory Issues and Challenges [3] Site Selection and Evaluation Criteria Site Selection Site Evaluation Public Participation Current Land Use and Socioeconomics Environment Protection Health & Safety Criteria Population Density & Distribution Uses of Land & Water in the Region Atmospheric, Surface & Groundwater Dispersion External Natural & Human Induced Event

17 Regulatory Issues and challenges [4] Radiological and Environmental Impact Assessment (RIA & EIA) RIA- Requirements under Atomic Energy Licensing Act, 1984 EIA- Requirements under Environmental Quality Act 1974 Construction of a nuclear fueled power station is a prescribed activity under the EIA Order Undergo a Detailed EIA procedure, including public display and public comments on the EIA Report

18 Regulatory Issues and challenges [5] Social Impact Assessment (SIA) required during application for Planning Approval by the Local Authority submitted together with the Proposed Project Development

19 CONCLUSION A clear political decision on NPP is important-regulatory body need more trained human resources, adequate financial, independent, effective and competent. Development of regulatory procedures and guidelines for the site evaluation, licensing process and inspection programme is important to perform effective regulatory reviews and inspection in an efficient and timely manner at the beginning stage of NPP development- possible areas of cooperation and partnership among the Regulatory Authority of newcomers & advance NPP countries need to be identified and strengthened.

20 Thank You