Safety Analysis Report of RR. IAEA EERRI Group fellowship training course Module CTU-03
|
|
|
- Rodney Summers
- 7 years ago
- Views:
Transcription
1 Safety Analysis Report of RR IAEA EERRI Group fellowship training course Module CTU-03
2 Documentation related to research reactors Safety documentation of RR OL&C, SAR, QA, emergency plan,... Operational documentation of RR 2 IAEA National regulatory body national laws, implementing legislation, safety guides Safety Standards Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report Safety Analysis Report of RR
3 IAEA Safety Standards Safety fundamentals Thematic areas Legal and governmental infrastructure Emergency preparedness and response Management systems Assessment and verification Site evaluation Radiation protection Radioactive waste management Decommissioning Remediation of contaminated areas Transport of radioactive material Facilities and activities Nuclear power plant design Nuclear power plant operation Research reactors Fuel cycle facilities Radiation related facilities and activities Waste treatment and disposal facilities General safety (cross-cutting themes Safety of nuclear facilities Radiation protection and safety of radiation sources Safe management of radioactive waste Safe transport of radioactive material 3 Safety Analysis Report of RR
4 Requirements for safety assessment in the licensing process for a research reactor Responsibilities Acceptance criteria Information requirements during the stages of the licensing process 4 Safety Analysis Report of RR
5 Responsibilities Independent regulatory body Assurance of the safety of the facility shall be provided to the population around the site where it operates. legal and regulatory basis for assessing the safety establish safety policies, principles, guidance, criteria and regulations legal powers, statutory authority Operating organization Responsibility for the safety of the facility and for demonstrating an adequate level of safety adequate safety demonstrated through the information normally incorporated in SAR 5 Safety Analysis Report of RR
6 Acceptance criteria Legal and regulatory framework Criteria developed by operating organization (agreed by regulatory body) serves for judgement of the acceptability of the results of safety analysis in operational states and accident conditions Radiological criteria Performance criteria 6 Safety Analysis Report of RR
7 Information requirements during the stages of the licensing process Schedule for the submission of information to regulatory body (evolution of SAR) Sitting and site evaluation Design and construction Commissioning tests prior to fuel loading fuel loading tests, initial criticality tests and low power tests power ascension tests and power tests Operation (incl. utilization and modification) Periodic safety reviews Decommissioning and release from regulatory control 7 Safety Analysis Report of RR
8 Preparation of the Safety Analysis Report Purpose and scope demonstration of the safety of the design basis for the safe operation of the research reactor basis for the interaction between the operating organization and the regulatory body in the licensing process Specific requirements Development of the safety analysis iteration between design process of RR and its licensing way of prevention and mitigation of accidents responses of the reactor to range of postulated initiating event (PIE) identification of the design basis accident basis for determination OL&C deterministic vs. probabilistic techniques of safety evaluation 8 Safety Analysis Report of RR
9 Performance of the review and assessment performed by the regulatory body to determine whether the proposed facility can be sited, constructed, commissioned, operated, utilized, modified and decommissioned without undue radiological risk to site personnel, general public and environment adequacy of programmes, meeting of requirements (ability, reliability, resources, organizational structure and competent personnel) programme for review and assessment established jointly by the regulatory body and the operating organization 9 Safety Analysis Report of RR
10 Content of Safety Analysis Report 10 Safety Analysis Report of RR
11 Introduction and general description of the facility (Chap. 1) General description of the facility Historical review Comparison with other facilities Identification of owners or agents Safety features basic safety principles adopted: Nuclear safety, Radiation protection, Physical protection, Emergency preparedness Experimental programme List of drawings Material incorporated by reference Requirements for further technical information 11 Safety Analysis Report of RR
12 Safety objectives and engineering design requirements (Chap. 2) Safety objectives and general design requirements Specific design requirements Classification of structures, components and systems External events Codes and standards Technical design methods Design for internal fire protection Qualification of components Conclusions 12 Safety Analysis Report of RR
13 Site characteristics (Chap. 3) 1/2 General site description External effects Geology and seismology Meteorology Hydrology and oceanography Nearby industrial, transport and military facilities Radiological impact Population distribution Natural environment, land and water usage Baseline radiological levels 13 Safety Analysis Report of RR
14 Site characteristics (Chap. 3) 2/2 Atmospheric dispersion of radioactive materials Dispersion of radioactive materials through surface waters and groundwater Mitigation Conclusion 14 Safety Analysis Report of RR
15 Buildings and structures (Chap. 4) Reactor building Auxiliary structures 15 Safety Analysis Report of RR
16 Reactor (Chap. 5) Aim: demonstration that reactor is capable to fulfil its safety functions, i.e.: shutting down the reactor and maintaining it in a safe shutdown providing adequate heat removal after shutdown containing radioactive material Summary description Fuel elements Reactivity control system Nuclear design Thermal and hydraulic design Reactor materials 16 Safety Analysis Report of RR
17 Reactor coolant systems and connected systems (Chap. 6) Primary cooling system Secondary cooling system Moderator system Emergency core cooling system Decay heat removal system Primary purification system Primary coolant make-up system 17 Safety Analysis Report of RR
18 Engineered safety features (Chap. 7) summary of types, locations and functions of engineered safety features (ESF) example: emergency core cooling system design basis and various modes of operation of ESF component reliability, system interdependence, redundancy, diversity of fail-safe characteristics, Safety Analysis Report of RR
19 Instrumentation and control (Chap. 8) Reactor protection system Reactor power regulating system Alarm system Interlocks Other instrumentation systems required for safety Control room 19 Safety Analysis Report of RR
20 Electric power (Chap. 9) Normal AC power supply Emergency AC power supply Uninterruptible power supplies Cable and routing 20 Safety Analysis Report of RR
21 Auxiliary systems (Chap. 10) Fuel storage and handling Water systems Process auxiliaries Air conditioning, heating, cooling and ventilation systems Fire protection Other auxiliary systems 21 Safety Analysis Report of RR
22 Reactor utilization (Chap. 11) Experimental facilities description and safety analysis e.g. beam tubes, in-core facilities, experimental loops Experimental programme 22 Safety Analysis Report of RR
23 Operational radiological safety (Chap. 12) Radiation protection programme Radiation sources at the facility Facility design for radiological safety Waste management systems Dose assessment for normal operation Conclusion 23 Safety Analysis Report of RR
24 Conduct of operations (Chap. 13) Organizational structure Staff qualification and training Review and audit Operating instructions and procedures Maintenance, testing and inspection Physical security Records and reports 24 Safety Analysis Report of RR
25 Environmental assessment (Chap. 14) Environmental impact of the licensing action Unavoidable adverse environmental effects Alternatives to the licensing action that were considered Irreversible and irretrievable commitments of resources Analysis providing a balance of the environmental effects of the licensing action and the alternatives available for reducing or avoiding environmental effects, as well as a summary of the environmental, economic, technical and other benefits resulting from the facility 25 Safety Analysis Report of RR
26 Commissioning (Chap. 15) Commissioning programme Specific requirements e.g. utilisation of the commissioning information from similar operational facilities Commissioning of modifications 26 Safety Analysis Report of RR
27 Safety analysis (Chap. 16) to enable the operating personnel to understand the basis for safe operation of the reactor to demonstrate to the regulatory body the way in which the design of the research reactor and the related operational procedures will contribute to the prevention of accidents and mitigation of their consequences should include analyses of the response of the reactor to a range of postulated initiating events serves as a basis for the determination of the operational limits and conditions, as well as to design specifications for components and systems 27 Safety Analysis Report of RR
28 Safety analysis (Chap. 16) Introduction Reactor characteristics Selection of initiating events Loss of electric power supplies Insertion of excess reactivity (criticality accident) Loss of flow Loss of coolant Erroneous handling or failure of equipment Special internal events including failure of experiments External event Human errors Evaluation of individual event sequences Summary 28 Safety Analysis Report of RR
29 Operational limits and conditions (Chap. 17) Safety limits Safety system settings Limiting conditions for safe operation Surveillance requirements Administrative requirements 29 Safety Analysis Report of RR
30 Quality assurance (Chap. 18) QA programmes QA procedures Management status of the QA programme 30 Safety Analysis Report of RR
31 Decommissioning (Chap. 19) Design basis related to decommissioning Aspects of the facility design that facilitate decommissioning e.g. operational practices to reduce activation of material 31 Safety Analysis Report of RR
32 Emergency planning and preparedness (Chap. 20) Emergency plan Emergency procedures 32 Safety Analysis Report of RR
33 References Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, IAEA Safety Series, Safety Guides, SS 35-G1,1994 Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report, IAEA Safety Standards, Safety Guide, DS-396, Aug (draft version) Safety of Research Reactors, Safety Requirements, IAEA Safety Standards Series NS-R-4, 2005 Safety Analysis for Research Reactors, IAEA Safety Reports Series No. 55, Safety Analysis Report of RR
34 IAEA publications on Safety analysis for RR 34 Safety Analysis Report of RR
35 IAEA publications on Safety analysis for RR 35 Safety Analysis Report of RR
RC-17. Alejandro V. Nader National Regulatory Authority Montevideo - Uruguay
RC-17 Radiation Protection in Waste Management and Disposal Implementing the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Alejandro V. Nader
SAFETY DESIGN OF A NUCLEAR POWER PLANT
GUIDE YVL B.1 / 15 November 2013 SAFETY DESIGN OF A NUCLEAR POWER PLANT 1 Introduction 5 2 Scope 5 3 Management of design 5 3.1 Organisations responsible for design 5 3.2 Design processes 6 3.3 Configuration
PROBABILISTIC RISK ASSESSMENT AND RISK MANAGEMENT OF A NUCLEAR POWER PLANT
PROBABILISTIC RISK ASSESSMENT AND RISK MANAGEMENT OF A NUCLEAR POWER PLANT 1 Introduction 3 2 Scope of application 3 3 Development and use of the PRA 4 3.1 General requirements 4 3.2 PRA during the design
Human Resource Management in Nuclear Safety
Human Resource Management in Nuclear Safety Christer Viktorsson Nuclear Installations Safety Role of the (IAEA) Established in 1957 143 Member States 2,200 staff Three Pillars: Safeguards Nuclear Technology
IAEA Safety Standards for Regulatory Activities
Safety Standards for Regulatory Activities April 2010 Gustavo Caruso Regulatory Activities Section Division of Nuclear Installation Safety International Atomic Energy Agency Content Safety Standards and
Belgian Stress tests specifications Applicable to all nuclear plants, excluding power reactors 22 June 2011
Belgian Stress tests specifications Applicable to all nuclear plants, excluding power reactors 22 June 2011 Introduction Considering the accident at the Fukushima nuclear power plant in Japan, the European
Government Degree on the Safety of Nuclear Power Plants 717/2013
Translation from Finnish. Legally binding only in Finnish and Swedish. Ministry of Employment and the Economy, Finland Government Degree on the Safety of Nuclear Power Plants 717/2013 Chapter 1 Scope and
Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT
Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT 24 th September 2014 Table of Content WENRA Safety Reference Levels
7.1 General 5 7.2 Events resulting in pressure increase 5
GUIDE YVL 2.4 / 24 Ma r ch 2006 Primary and secondary circuit pressure control at a nuclear power plant 1 Ge n e r a l 3 2 General design requirements 3 3 Pressure regulation 4 4 Overpressure protection
NUCLEARINSTALLATIONSAFETYTRAININGSUPPORTGROUP DISCLAIMER
NUCLEARINSTALLATIONSAFETYTRAININGSUPPORTGROUP DISCLAIMER Theinformationcontainedinthisdocumentcannotbechangedormodifiedinanywayand shouldserveonlythepurposeofpromotingexchangeofexperience,knowledgedissemination
ANTEP 2015 Needs from China (NNSA)
ANTEP 2015 Needs from China (NNSA) 1 Content of training/education that Decommissioning plan and technologies 2 Background of above need 1. Design life of Qinshan NPP is 30 years, and it has been put into
How To Decommission A Nuclear Plant
International Atomic Energy Agency Decommissioning of Nuclear Facilities Management of Decommissioning Projects Lawrence E. Boing Manila, Philippines, October 2006 1 Lesson Objectives Understand the management
APPENDIX B SUPPLEMENTAL INSPECTION PROGRAM A. OBJECTIVES AND PHILOSOPHY OF THE SUPPLEMENTAL INSPECTION PROGRAM
APPENDIX B SUPPLEMENTAL INSPECTION PROGRAM A. OBJECTIVES AND PHILOSOPHY OF THE SUPPLEMENTAL INSPECTION PROGRAM The supplemental inspection program is designed to support the NRC s goals of maintaining
Operating Performance: Accident Management: Severe Accident Management Programs for Nuclear Reactors REGDOC-2.3.2
Operating Performance: Accident Management: Severe Accident Management Programs for Nuclear Reactors REGDOC-2.3.2 September 2013 Accident Management: Severe Accident Regulatory Document REGDOC-2.3.2 Canadian
QUALITY ASSURANCE CRITERIA APPLICABLE TO THE DESIGN PROCESS SUBJECT: PRESENTATION TO THE NUCLEAR WASTE TECHNICAL REVIEW BOARD
U.S. DEPARTMENT OF ENERGY OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT PRESENTATION TO THE NUCLEAR WASTE TECHNICAL REVIEW BOARD SUBJECT: PRESENTER: PRESENTER'S TITLE AND ORGANIZATION: QUALITY ASSURANCE
Belgian Stress tests specifications Applicable to power reactors 17 May 2011
Belgian Stress tests specifications Applicable to power reactors 17 May 2011 Introduction Considering the accident at the Fukushima nuclear power plant in Japan, the European Council of March 24 th and
Nuclear power plant systems, structures and components and their safety classification. 1 General 3. 2 Safety classes 3. 3 Classification criteria 3
GUIDE 26 June 2000 YVL 2.1 Nuclear power plant systems, structures and components and their safety classification 1 General 3 2 Safety classes 3 3 Classification criteria 3 4 Assigning systems to safety
How To License A Nuclear Plant
Contents Introduction... 1 Two-Step Licensing Process (10 CFR Part 50)... 2 Construction Permit... 2 Operating License... 4 Additional Licensing Processes (10 CFR Part 52)... 4 Early Site Permits... 6
Training in Emergency Preparedness and Response
Working to Protect People, Society and the Environment Training in Emergency Preparedness and Response Nuclear Safety and Security Programme Nuclear Safety and Security Programme Training in Emergency
NEI 06-13A [Revision 0] Template for an Industry Training Program Description
![NEI 06-13A [Revision 0] Template for an Industry Training Program Description](/thumbs/30/14663734.jpg "NEI 06-13A [Revision 0] Template for an Industry Training Program Description")
NEI 06-13A [Revision 0] Template for an Industry Training Program Description NEI 06-13A [Revision 0] Nuclear Energy Institute Template for an Industry Training Program Description ACKNOWLEDGEMENTS This
Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]
![Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]](/thumbs/22/1436302.jpg "Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]")
Nuclear Safety Council Instruction number IS-22, of July 1st 2009, on safety requirements for the management of ageing and long-term operation of nuclear power plants Published in the Official State Gazette
Safety assessment of the Loviisa nuclear power plant
/ OCTOBER 2007 B Safety assessment of the Loviisa nuclear power plant Statement regarding the licence application by Fortum Power and Heat Oy concerning the operation of the Loviisa nuclear power plant
IAEA INTERNATIONAL FACT FINDING EXPERT MISSION OF THE NUCLEAR ACCIDENT FOLLOWING THE GREAT EAST JAPAN EARTHQUAKE AND TSUNAMI
IAEA INTERNATIONAL FACT FINDING EXPERT MISSION OF THE NUCLEAR ACCIDENT FOLLOWING THE GREAT EAST JAPAN EARTHQUAKE AND TSUNAMI Tokyo, Fukushima Dai-ichi NPP, Fukushima Dai-ni NPP and Tokai NPP, Japan 24
Safety Analysis for Nuclear Power Plants
Regulatory Document Safety Analysis for Nuclear Power Plants February 2008 CNSC REGULATORY DOCUMENTS The Canadian Nuclear Safety Commission (CNSC) develops regulatory documents under the authority of paragraphs
Improving reactor safety systems using component redundancy allocation technique
NUKLEONIKA 2005;50(3):105 112 ORIGINAL PAPER Improving reactor safety systems using component redundancy allocation technique Aziz Shafik Habib, Hoda Abd-el Monem Ashry, Amgad Mohamed Shokr, Azza Ibrahim
Nuclear Power Plant Electrical Power Supply System Requirements
1 Nuclear Power Plant Electrical Power Supply System Requirements Željko Jurković, Krško NPP, zeljko.jurkovic@nek.si Abstract Various regulations and standards require from electrical power system of the
U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION
U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION NUREG-0800 (Formerly NUREG-75/087) 9.2.2 REACTOR AUXILIARY COOLING WATER SYSTEMS REVIEW RESPONSIBILITIES Primary
Office for Nuclear Regulation
ONR GUIDE CONTAINMENT: CHEMICAL PLANTS Document Type: Nuclear Safety Technical Assessment Guide Unique Document ID and Revision No: NS-TAST-GD-021 Revision 2 Date Issued: March 2013 Review Date: March
Human Factors in Design and Construction Regulatory Perspective
Further needs in the Area of management systems Safety culture, leadership and preoperational stages of nuclear projects Human Factors in Design and Construction Regulatory Perspective Technical Meeting,
GENERAL REGULATIONS ON ENSURING SAFETY OF NUCLEAR POWER PLANTS OPB-88/97, NP-001-97 (PNAE G- 01 011-97) Cover page. Contents
GENERAL REGULATIONS ON ENSURING SAFETY OF NUCLEAR POWER PLANTS OPB-88/97, NP-001-97 (PNAE G- 01 011-97) Cover page Contents Federal Nuclear and Radiation Safety Authority of Russia (Gosatomnadzor of Russia)
IAEA Action Plan on Nuclear Safety 1
IAEA Action Plan on Nuclear Safety 1 In June 2011 a Ministerial Conference on Nuclear Safety was convened to direct, under the leading role of the IAEA, the process of learning and acting upon lessons
Elements of the Russian Emergency Preparedness Program
Elements of the Russian Emergency Preparedness Program Randolph L. Sullivan, NRC National Radiological EP Conference St. Louis, Missouri March 2006 2 3 4 5 6 Volgodonsk NPP 1000 MWe VVER, a PWR Large Staff
Cyber Security Design Methodology for Nuclear Power Control & Protection Systems. By Majed Al Breiki Senior Instrumentation & Control Manager (ENEC)
Cyber Security Design Methodology for Nuclear Power Control & Protection Systems By Majed Al Breiki Senior Instrumentation & Control Manager (ENEC) 1. INTRODUCTION In today s world, cyber security is one
IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS
IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS Eduardo Kibrit 1, Afonso Rodrigues de Aquino 2 and Désirée Moraes Zouain 3 1 Centro Tecnológico da Marinha em São
Long-Term Recovery from Nuclear Accidents
Long-Term Recovery from Nuclear Accidents THE SCIENCE AND RESPONSE TO A NUCLEAR REACTOR ACCIDENT Post Emergency Transition to Recovery The National Academy of Sciences Washington, DC May 13, 2014 S.Y.
IAEA-TECDOC-1458. Effective corrective actions to enhance operational safety of nuclear installations
IAEA-TECDOC-1458 Effective corrective actions to enhance operational safety of nuclear installations July 2005 IAEA SAFETY RELATED PUBLICATIONS IAEA SAFETY STANDARDS Under the terms of Article III of its
INTERNATIONAL ATOMIC ENERGY AGENCY WAGRAMERSTRASSE 5, P.O. BOX 100, A-1400 VIENNA, AUSTRIA FACSIMILE: (+43 1) 26007, TELEPHONE: (+43 1) 2600
INTERNATIONAL ATOMIC ENERGY AGENCY WAGRAMERSTRASSE 5, P.O. BOX 100, A-1400 VIENNA, AUSTRIA FACSIMILE: (+43 1) 26007, TELEPHONE: (+43 1) 2600 - CRAFT - The International Project on COMPLIMENTARY SAFETY
System/activ. ity of interest Comment Priority. Referenc. Id Category Text. Waste management Establish waste classification 5 Romuald Duperrier Waste
1 Waste management Establish waste classification 5 Romuald Duperrier Waste IAEA GSG- 1 or SSI FS 1996-2? page 34 2 Evaluate environmental impact (including workers) of the decommissioning 5 Romuald Duperrier
Draft IAEA Action Plan on Nuclear Safety
Atoms for Peace Board of Governors General Conference GOV/2011/59-GC(55)/14 Date: 5 September 2011 For official use only Item 3(b) of the Board's provisional agenda (GOV/2011/46) Item 14(b) of the Conference's
Nuclear Safety Council Instruction number IS-19, of October 22 nd 2008, on the requirements of the nuclear facilities management system
Nuclear Safety Council Instruction number IS-19, of October 22 nd 2008, on the requirements of the nuclear facilities management system Published in the Official State Gazette (BOE) number 270 of November
Report. November 2013
Report A comparison of U.S. and Japanese regulatory requirements in effect at the time of the Fukushima accident November 2013 Page 1 EXECUTIVE SUMMARY In the Staff Requirements Memo (SRM) to SECY-12-0110
Introductions: Dr. Stephen P. Schultz
Introductions: Dr. Stephen P. Schultz Vienna, Austria 1 3 September 2015 Work Experience Current Member Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 12/2011 Chair, Fukushima
Public SUMMARY OF EU STRESS TEST FOR LOVIISA NUCLEAR POWER PLANT
1 (8) SUMMARY OF EU STRESS TEST FOR LOVIISA NUCLEAR POWER PLANT 1 LOVIISA NUCLEAR POWER PLANT Loviisa town is located approximately 90 km eastwards from Helsinki at the coast of Gulf of Finland. Loviisa
Office for Nuclear Regulation
ONR GUIDE LC17 Management Systems Document Type: ONR Nuclear Safety Technical Inspection Guide Unique Document ID and Revision No: NS-INSP-GD-017 Revision 2 Date Issued: November 2012 Review Date: November
MANAGEMENT SYSTEM FOR A NUCLEAR FACILITY
GUIDE YVL A.3 / 2 June 2014 MANAGEMENT SYSTEM FOR A NUCLEAR FACILITY 1 Introduction 5 2 Scope of application 6 3 Management system 6 3.1 Planning, implementation, maintenance, and improvement of the management
Office for Nuclear Regulation
ONR GUIDE Essential Services Document Type: Nuclear Safety Technical Assessment Guide Unique Document ID and Revision No: Date Issued: May 2013 Review Date: May 2016 Approved by: D Senior Director Regulatory
2.0 Land Quality Programme
2.0 Land Quality Programme The Sellafield site has a legacy of ground contamination from its historical use as a Royal Ordnance factory and its subsequent development as a nuclear facility. The ground
IAEA Recommendations on a Decommissioning Plan (DP)
IAEA Recommendations on a Decommissioning Plan (DP) Ernst Warnecke, IAEA-NSRW Patrick O Sullivan, IAEA-NEFW Research Reactor Decommissioning Demonstration Project (R²D²P) Review of a Decommissioning Plan
WASTE Application Form - Dublin Waste to Energy SECTION J ACCIDENT PREVENTION & EMERGENCY RESPONSE
SECTION J ACCIDENT PREVENTION & EMERGENCY RESPONSE Describe the existing or proposed measures, including emergency procedures, to minimise the impact on the environment of an accidental emission or spillage.
Nuclear Energy: Nuclear Energy
Introduction Nuclear : Nuclear As we discussed in the last activity, energy is released when isotopes decay. This energy can either be in the form of electromagnetic radiation or the kinetic energy of
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001. June 1, 2005
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001 June 1, 2005 NRC INFORMATION NOTICE 2005-14: FIRE PROTECTION FINDINGS ON LOSS OF SEAL COOLING
3 rd Review Meeting Convention on Nuclear Safety First Anniversary Report Status of Actions on Canada April 2006
3 rd Review Meeting Convention on Nuclear Safety First Anniversary Report Status of Actions on Canada April 2006 1. Introduction At the 3 rd review meeting of the Convention on Nuclear Safety, held in
Regulatory Requirements and Licensing of OPG s DGR Project
Regulatory Requirements and Licensing of OPG s DGR Project OPG s Deep Geologic Repository Project for Low and Intermediate Level Radioactive Waste Presentation to Joint Review Panel July 18, 2012 nuclearsafety.gc.ca
TRANSIENT AND ACCIDENT ANALYSES FOR JUSTIFICATION OF TECHNICAL SOLUTIONS AT NUCLEAR POWER PLANTS
TRANSIENT AND ACCIDENT ANALYSES FOR JUSTIFICATION OF TECHNICAL SOLUTIONS AT NUCLEAR POWER PLANTS 1 GENERAL 3 2 EVENTS TO BE ANALYSED 3 2.1 General requirements 3 2.2 Analyses of plant behaviour 4 2.3 Analyses
Guide to nuclear decommissioning
Guide to nuclear decommissioning Contents: What is decommissioning? Stages of decommissioning Site restoration Waste management The UK decommissioning industry The international picture What is decommissioning?
FIRE RISK ASSESSMENT IN GERMANY - PROCEDURE, DATA, RESULTS -
International Conference Nuclear Energy in Central Europe 2000 Golf Hotel, Bled, Slovenia, September 11-14, 2000 FIRE RISK ASSESSMENT IN GERMANY - PROCEDURE, DATA, RESULTS - H.P. Berg Bundesamt für Strahlenschutz
Code of Conduct on the Safety and Security of Radioactive Sources
FOREWORD In recent years there has been a growing awareness of the potential for accidents involving radiation sources, some such accidents having had serious, even fatal, consequences. More recently still,
THE DECOMMISSIONING OF THE UK NUCLEAR INDUSTRY S FACILITIES
THE DECOMMISSIONING OF THE UK NUCLEAR INDUSTRY S FACILITIES Introduction 1. This statement of the UK Government and devolved administrations policy on the decommissioning of nuclear facilities updates
Proposed Terms of Reference for EIA studies
1 Proposed Terms of Reference for EIA studies Base line data collection will be collected for the Post-Monsoon season 2016 (September to November 2016) in study area and 10 kms radius from project site.
Licence condition handbook
Licence condition handbook January 2016 Office for Nuclear Regulation page 1 of 24 The standard licence conditions attached to nuclear site licences Introduction This booklet has been produced as an aide-memoire
HOISTING AND TRANSFER EQUIPMENT OF A NUCLEAR FACILITY
HOISTING AND TRANSFER EQUIPMENT OF A NUCLEAR FACILITY 1 Introduction 5 2 Scope of application 6 3 Equipment requirement specifications for hoisting device units 7 4 Manufacturer 7 4.1 General 7 4.2 Obligations
Licensing Process for New Nuclear Power Plants in Canada. INFO-0756 (Revision 1)
Licensing Process for New Nuclear Power Plants in Canada INFO-0756 (Revision 1) May 2008 Licensing Process for New Nuclear Power Plants in Canada Minister of Public Works and Government Services Canada
Nuclear Safety Council Instruction number IS- 23 on in-service inspection at nuclear power plants
Nuclear Safety Council Instruction number IS- 23 on in-service inspection at nuclear power plants Published in the Official State Gazette (BOE) No 283 of November 24 th 2009 Nuclear Safety Council Instruction
IAEA Safety Standards. Operational Limits and Conditions and Operating Procedures for Research Reactors
IAEA Safety Standards for protecting people and the environment Operational Limits and Conditions and Operating Procedures for Research Reactors Safety Guide No. NS-G-4.4 OPERATIONAL LIMITS AND CONDITIONS
Report. Radioactive Waste Disposal Facilities Safety Reference Levels
Report Radioactive Waste Disposal Facilities Safety Reference Levels - 22 December 2014 Radioactive Waste Disposal Facilities Safety Reference Levels Table of Content - Executive Summary 4 WENRA Policy
Nuclear Safety. Policy 2013-2016
Nuclear Safety Policy 2013-2016 Nuclear Safety Policy 2013-2016 T he organisational principles and actions defined in the Nuclear Safety Charter and applied within the group have achieved significant improvements
ESRS guidelines for software safety reviews
IAEA Services Series No. 6 ESRS guidelines for software safety reviews Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in
HEALTH & SAFETY EXECUTIVE NUCLEAR DIRECTORATE ASSESSMENT REPORT. New Reactor Build. EDF/AREVA EPR Step 2 PSA Assessment
HEALTH & SAFETY EXECUTIVE NUCLEAR DIRECTORATE ASSESSMENT REPORT New Reactor Build EDF/AREVA EPR Step 2 PSA Assessment HM Nuclear Installations Inspectorate Redgrave Court Merton Road Bootle Merseyside
Risk management for external beam radiotherapy Recommendations (draft)
Patient safety in external beam radiotherapy - Guidelines on risk assessment and analysis of adverse events and near misses. Risk management for external beam radiotherapy Recommendations (draft) Jean-Luc
Security and Safeguards Considerations in Radioactive Waste Management. Canadian Nuclear Safety Commission
Security and Safeguards Considerations in Radioactive Waste Management Raoul Awad Director General, Directorate of Security and Safeguards Canadian Nuclear Safety Commission Radioactive Waste Management
This occurrence is considered to be of no significance with respect to the health and safety of the public.
Serial No. MNS-15-072 September 10, 2015,. DUKESteven Vice D. President Capps, ENERGYMcGuire Nuclear Station Duke Energy MGOIVP 1 12700 Hagers Ferry Road Huntersville, NC 28078 0: 980.875.4805 f: 980.875.4809
Standardised Decommissioning Cost Estimating of WWER-440 Nuclear Power Plants (SCE)
COMMISSION OF THE EUROPEAN COMMUNITIES (5th Framework Programme) Standardised Decommissioning Cost Estimating of WWER-440 Nuclear Power Plants (SCE) Topical Information Meeting on Decommissioning of Nuclear
Nuclear Emergency Response Program
Nuclear Emergency Response Program NUCLEAR POWER PLANTS In California, there are two operating nuclear power plant sites: Diablo Canyon in San Luis Obispo County has two active units and San Onofre Nuclear
Shell s Health, Safety and Environment (HSE) management system (see Figure 11-1) provides the framework for managing all aspects of the development.
Section 11.1 APPLICATION FOR APPROVAL OF THE DEVELOPMENT PLAN FOR NIGLINTGAK FIELD PROJECT DESCRIPTION INTRODUCTION 11.1.1 HSE MANAGEMENT SYSTEM Shell s Health, Safety and Environment (HSE) management
INES The International Nuclear and Radiological Event Scale
INES The International Nuclear and Radiological Event Scale User s Manual 2008 Edition Co sponsored by the IAEA and OECD/NEA INES THE INTERNATIONAL NUCLEAR AND RADIOLOGICAL EVENT SCALE USER S MANUAL 2008
MDEP Generic Common Position No DICWG 02
MDEP Generic Common Position No DICWG 02 Related to: Digital Instrumentation and Controls Working Group activities COMMON POSITION ON SOFTWARE TOOLS FOR THE DEVELOPMENT OF SOFTWARE FOR SAFETY SYSTEMS 1
OVERVIEW OF THE OPERATING REACTORS BUSINESS LINE. July 7, 2016 Michael Johnson Deputy Executive Director for Reactor and Preparedness Programs
OVERVIEW OF THE OPERATING REACTORS BUSINESS LINE July 7, 2016 Michael Johnson Deputy Executive Director for Reactor and Preparedness Programs Program Overview Bill Dean Director Office of Nuclear Reactor
RADIOACTIVE WASTE MANAGEMENT AND DECOMMISSIONING IN FINLAND
RADIOACTIVE WASTE MANAGEMENT AND DECOMMISSIONING IN FINLAND 1. NATIONAL FRAMEWORK FOR MANAGEMENT AND REGULATION OF RADIOACTIVE WASTE AND DECOMMISSIONING 1.1 National framework 1.1.1 Overview of national
Quality Management System-A Revision 7 (NRC-approved Version)
Westinghouse Non-Proprietary Class 3 2013 Westinghouse Electric Company LLC. All Rights Reserved. Quality Management System-A (NRC-approved Version) Westinghouse Electric Company Quality Management System
Bonn Call-for-Action Joint Position Statement by the IAEA and WHO
Bonn Call-for-Action Joint Position Statement by the IAEA and WHO The International Atomic Energy Agency (IAEA) held the International Conference on Radiation Protection in Medicine: Setting the Scene
IAEA-TECDOC-1254. Training the staff of the regulatory body for nuclear facilities: A competency framework
IAEA-TECDOC-1254 Training the staff of the regulatory body for nuclear facilities: A competency framework November 2001 The originating Section of this publication in the IAEA was: Safety Co-ordination
RADIOACTIVE WASTE MANAGEMENT PROGRAMMES IN OECD/NEA MEMBER COUNTRIES AUSTRALIA NATIONAL NUCLEAR ENERGY CONTEXT
RADIOACTIVE WASTE MANAGEMENT PROGRAMMES IN OECD/NEA MEMBER COUNTRIES AUSTRALIA NATIONAL NUCLEAR ENERGY CONTEXT Australia is one of the only developed countries that does not use electricity, either indigenous
IAEA Research Reactor Operations & Maintenance Support 2014 TRTR Meeting August 3rd-7th, 2014 Benson Hotel Portland Oregon
IAEA Research Reactor Operations & Maintenance Support 2014 TRTR Meeting August 3rd-7th, 2014 Benson Hotel Portland Oregon By Charles R Morris Personal Nuclear History Contents 1. Introduction 2. Digital
FOOD SAFETY MANAGEMENT SYSTEMS (FSMS): REQUIREMENTS FOR ANY ORGANISATION IN THE FOOD CHAIN (ISO 22000:2005)
FOOD SAFETY MANAGEMENT SYSTEMS (FSMS): REQUIREMENTS FOR ANY ORGANISATION IN THE FOOD CHAIN (ISO 22000:2005) Dr.R.MANAVALAN, M.Pharm., Ph.D. Professor and Research Director, Department of Pharmaceutics,
AP1000 European 18. Human Factors Engineering Design Control Document
18.2 Human Factors Engineering Program Management The purpose of this section is to describe the goals of the AP1000 human factors engineering program, the technical program to accomplish these goals,
Environmental Guidelines for Preparation of an Environmental Management Plan
2013 Environmental Guidelines for Preparation of an Environmental Management Plan Environmental Management Division Environmental Protection Agency 3/13/2013 ENVIRONMENTAL GUIDELINES FOR PREPARATION OF
Nuclear Regulation for SMR in India Current Perspectives
Licensing and Safety Issues for Small and Mediumsized Reactors (SMRs) 29 July 2 August 2013 IAEA Headquarters, Vienna, Austria Nuclear Regulation for SMR in India Current Perspectives Dr. A. Ramakrishna,
Hazard Classification of the Remote Handled Low Level Waste Disposal Facility
1 Hazard Classification of the Remote Handled Low Level Waste Disposal Facility Abstract Boyd D. Christensen Battelle Energy Alliance, Idaho National Laboratory P.O. Box 1625 Idaho Falls, Idaho 83415 208
Nuclear Design Practices and the Case of Loviisa 3
Nuclear Design Practices and the Case of Loviisa 3 Harri Tuomisto Fortum Power, Finland Third Nuclear Power School, 20-22 October 2010, Gdańsk, Poland 22 October 2010 Harri Tuomisto 1 Objectives The objective
Chemical Decontamination and Fluid Handling Services
Chemical Decontamination and Fluid Handling Services Westinghouse is a global industry expert in decontamination and fluid handling processes, with proven abilities in decontamination and remediation work.
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 LICENSE RENEWAL Hamilton County, Tennessee
Document Type: EIS-Administrative Record Index Field: Environmental Document Transmitted Public/Agencies Project Name: Sequoyah Nuclear Plant License Renewal Project Number: 2009-61 FINAL SUPPLEMENTAL
SCK CEN Stress Test. SCK CEN Boeretang 200 BE-2400 Mol. Methodology Report. F. Vermeersch & B. Martens. December 15, 2011
SCK CEN Stress Test Methodology Report F. Vermeersch & B. Martens December 15, 2011 SCK CEN Boeretang 200 BE-2400 Mol Table of Contents 1 Objective... 3 2 Stress test for the nuclear facilities of SCK
NRC s Program for Remediating Polluted Sites J.T. Greeves, D.A. Orlando, J.T. Buckley, G.N. Gnugnoli, R.L. Johnson US Nuclear Regulatory Commission
NRC s Program for Remediating Polluted Sites J.T. Greeves, D.A. Orlando, J.T. Buckley, G.N. Gnugnoli, R.L. Johnson US Nuclear Regulatory Commission Background The U.S. Nuclear Regulatory Commission (NRC)
STATE OF NEVADA Department of Administration Division of Human Resource Management CLASS SPECIFICATION
STATE OF NEVADA Department of Administration Division of Human Resource Management CLASS SPECIFICATION TITLE GRADE EEO-4 CODE RADIATION CONTROL SUPERVISOR 38 B 10.538 SERIES CONCEPT Radiation Control Specialists
INSERT COMPANY LOGO/HEADER
LICENCE REFERENCE No. Insert licence reference number RISK ASSESSMENT METHODOLOGY STAGE & STEP Insert methodology stage and step, e.g. Stage 3 Step 1 REPORT VERSION Insert report version no., e.g. Draft,
Republic of Turkey. Date of acceptance: 9 November 2007 PART 1. Goal, scope, definitions and abbreviations. Goal and scope.
Republic of Turkey Unofficial Translation 1 of the Turkish Law No. 5710 2 Concerning the Construction and Operation of Nuclear Power Plants and the Sale of Energy Generated from Those Plants Date of acceptance:
Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP)
Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP) A. Yamamoto a, A. Huerta a, K. Gott b, T. Koshy c a Nuclear Safety Division, OECD Nuclear Energy
NEI 06-13A [Revision 2] Template for an Industry Training Program Description
![NEI 06-13A [Revision 2] Template for an Industry Training Program Description](/thumbs/37/17741646.jpg "NEI 06-13A [Revision 2] Template for an Industry Training Program Description")
NEI 06-13A [Revision 2] Template for an Industry Training Program Description NEI 06-13A [Revision 2] Nuclear Energy Institute Template for an Industry Training Program Description ACKNOWLEDGEMENTS This
EMERGENCY PREPAREDNESS FREQUENTLY ASKED QUESTION (EPFAQ) NEI 99 01 REVISIONS 4 THROUGH 6; NUMARC/NESP 007
EPFAQ Number: 2015 001 DATE ACCEPTED 20 Apr 15 ORIGINATOR DAVID YOUNG ORGANIZATION Nuclear Energy Institute (NEI) PHONE # 202 739 8016 RELEVANT GUIDANCE: NEI 99 01 REVISIONS 4 THROUGH 6; NUMARC/NESP 007
Exhibit SHN-029. Commission Mandatory Hearing SHINE Construction Permit Application Environmental Overview December 15, 2015
Exhibit SHN-029 Commission Mandatory Hearing SHINE Construction Permit Application Environmental Overview December 15, 2015 Development of the Environmental Report Began work October 2011 SHINE production