IAEA标准引导链接-201410.pdf

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1、2014-10-20 1 LONG TERM STRUCTURE OF THE IAEA SAFETY STANDARDS AND CURRENT STATUS October 2014 Electronic version available at:http:/www-ns.iaea.org/committees/files/CSS/205/status.pdf New:You may download the whole collection of safety standards in one portable file There are six files,each for one

2、official language,at http:/www-ns.iaea.org/standards/default.asp?s=11&l=90 Table of content 1.RECENT PUBLICATIONS 2 2.USEFUL HYPERLINKS 2 3.OVERALL STATUS OF THE SAFETY STANDARDS SERIES 2 4.APPLICATION TO FACILITIES AND ACTIVITIES 2 5.HIERARCHY 3 6.STRUCTURE 4 7.STATUS OF DEVELOPMENT 4 8.THE CURRENT

3、 IAEA SAFETY STANDARDS 5 9.SAFETY FUNDAMENTALS 10 10.GENERAL SAFETY REQUIREMENTS 10 11.SPECIFIC SAFETY REQUIREMENTS 14 12.GENERAL SAFETY GUIDES 16 13.SPECIFIC SAFETY GUIDES 23 14.PROJECTS 43 15.NUCLEAR SECURITY DRAFT IMPLEMENTING GUIDES WITH INTERFACE WITH SAFETY 44 2014-10-20 2 1.Recent Publication

4、s Safety standards published in 2009:NS-G-2.12,GSR Part 4,GSR Part 5,TS-R-1 2009 edition,NS-G-2.13,TS-G-1.5,NS-G-2.15,GS-G-3.5,GSG-1,SSG-1,SSG-2 Safety standards published in 2010:SSG-3,SSG-4,SSG-5,SSG-6,SSG-7,SSG-8,SSG-9,GSR Part 1,SSG-10,SSG-12 Safety standards published in 2011:SSG-13,SSG-11,GSG-

5、2,SSR-5,SSR-2/2,SSG-19,SSG-14 GSR Part 3 Interim Edition,SSG-18 Safety standards published in 2012:SSG-15,SSG-16,SSG-17,SSR-2/1,SSG-20,SSG-21,SSG-22,SSG-23,SSG-24,SSR-6 Safety standards published in 2013:GSG-3,GSG-4,SSG-25 Safety standards published in 2014:TS-G-1.6(Rev.1),SSG-26,SSG-27,SSG-28,SSG-2

6、9,NS-R-5(Rev.1),SSG-30,SSG-31,GSR Part 6,GSR Part 3,GSG-5 2.Useful Hyperlinks General information on the IAEA Safety Standards is available at:http:/www-ns.iaea.org/standards/default.asp The 2007 Edition of the IAEA Safety Glossary is available in Arabic,Chinese,English,French,Russian and Spanish at

7、:http:/www-ns.iaea.org/standards/safety-glossary.asp 3.Overall status of the safety standards series-129 are established of which 124 are published-42 drafts are in the development process(30 to revise 41 published Safety Standards)-10 draft DPPs are approved by the Coordination Committee of which 9

8、 to revise 9 published Safety Standards Currently,91%of the standards are established.40%of the established standards are under revision.The expected total number is 131.4.Application to facilities and activities For each document in the long term structure of safety standards,a table is provided th

9、at indicates to which types of facilities and activities the standard applies.The green boxes indicate the application:-green NPPs means applicable to nuclear power plants,-green RRs means applicable to research reactors,-green FCFs means applicable to fuel cycle facilities and facilities of the pre

10、disposal management of radioactive waste,-green WDF means applicable to waste disposal facilities,-green MM means applicable to mining/milling activities,-green RS means applicable to use of radiation sources,and-green TR means applicable to the transport of radioactive material NPPs RRs FCFs WDFs M

11、M RS TR 2014-10-20 3 5.Hierarchy The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment from harmful effects of ionizing radiation.They are issued in the IAEA Safety Standards Series,which has three categories

12、(see Fig.1):Safety Fundamentals The Safety Fundamentals SF-1 presents the fundamental safety objective and principles of protection and safety and provides the basis for the safety requirements.Safety Requirements An integrated and consistent set of Safety Requirements establish the requirements tha

13、t must be met to ensure the protection of people and the environment,both now and in the future.The requirements are governed by the objective and principles of the Safety Fundamentals.If the requirements are not met,measures must be taken to reach or restore the required level of safety.The format

14、and style of the requirements facilitate their use for the establishment,in a harmonized manner,of a national regulatory framework.The General Safety Requirements and the Specific Safety Requirements1 include overarching requirements and associated requirements,both expressed as“shall”statements.Man

15、y requirements are not addressed to a specific party,the implication being that the appropriate parties are responsible for fulfilling them.Safety Guides Safety Guides provide recommendations and guidance on how to comply with the safety requirements,indicating an international consensus that it is

16、necessary to take the measures recommended(or equivalent alternative measures).The Safety Guides present international good practices,and increasingly they reflect best practices,to help users striving to achieve high levels of safety.The recommendations provided in Safety Guides are expressed as sh

17、ould statements.Fig.1:Safety Standards Categories 1 This does not currently apply to TS-R-1(SSR 6)2014-10-20 4 6.Structure The long-term set of Safety Standards includes a unified Safety Fundamentals(SF1),a General Safety Requirements(GSR)in seven parts applicable to all facilities and activities wi

18、th a graded approach,complemented by a set of six facilities and activities Specific Safety Requirements(SSRs).The Safety Requirements are implemented through a set of general and specific safety guides.The following list provides you with the long term set of Safety Standards as well as the status

19、of the current corresponding set of published safety standards and drafts in preparation for the transition to the long term structure.7.Status of development Throughout this report the first column provides the list of established IAEA Safety Standards(Safety Fundamentals and Safety Requirements ar

20、e established when approved by the BoG and Safety Guides are established by the DG when approved by the Publication Committee).The second column gives the working identification number(DS)of standards being developed or revised and links to the corresponding dpp.Bold titles indicate standards issued

21、,or to be issued,under the authority of the Board of Governors,others are issued under the authority of the Director General.Thre third column provides the development status.The last column provides the list of Committees;the first Committee listed has the lead in the preparation and review of that

22、 particular standard.STEP 1:Preparing a DPP STEP 2:Internal review of the DPP STEP 3:Review of the DPP by the SSC(s)STEP 4:Review of the DPP by the CSS STEP 5:Preparing the draft safety standard STEP 6:First internal review of the draft safety standard STEP 7:First review of the draft safety standar

23、d by the SSC(s)STEP 8:Soliciting comments by Member States STEP 9:Addressing comments by Member States STEP 10:Second internal review of the draft safety standard STEP 11:Second review of the draft safety standard by the SSC(s)STEP 12:Review of the draft safety standard by the CSS STEP 13:Establishi

24、ng as an IAEA safety standard(by the Publications Committee and/or Board of Governors(for SF and SR only)STEP 14:Publication of the safety standard Safety FundamentalsFundamental Safety PrinciplesGeneral Safety RequirementsSpecific Safety RequirementsPart 1.Governmental,Legal and Regulatory Framewor

25、k for Safety1.Site Evaluation for Nuclear Installations3.Safety of Research Reactors4.Safety of Nuclear Fuel Cycle Facilities5.Safety of Radioactive Waste Disposal Facilities6.Safe Transport of Radioactive Material2.Safety of Nuclear Power Plants2.1.Design and Construction2.2.Commissioning and Opera

26、tionCollection of Safety GuidesPart 2.Leadership and Management for SafetyPart 3.Radiation Protection and the Safety of Radiation SourcesPart 4.Safety Assessment for Facilities and ActivitiesPart 5.Predisposal Managementof Radioactive WastePart 6.Decommissioning and Termination of ActivitiesPart 7.E

27、mergency Preparedness and ResponseSafety FundamentalsFundamental Safety PrinciplesGeneral Safety RequirementsSpecific Safety RequirementsPart 1.Governmental,Legal and Regulatory Framework for Safety1.Site Evaluation for Nuclear Installations3.Safety of Research Reactors4.Safety of Nuclear Fuel Cycle

28、 Facilities5.Safety of Radioactive Waste Disposal Facilities6.Safe Transport of Radioactive Material2.Safety of Nuclear Power Plants2.1.Design and Construction2.2.Commissioning and OperationCollection of Safety GuidesPart 2.Leadership and Management for SafetyPart 3.Radiation Protection and the Safe

29、ty of Radiation SourcesPart 4.Safety Assessment for Facilities and ActivitiesPart 5.Predisposal Managementof Radioactive WastePart 6.Decommissioning and Termination of ActivitiesPart 7.Emergency Preparedness and Response2014-10-20 5 8.The Current IAEA Safety Standards Standards highlighted in Yellow

30、 appear several times in the list as they are applicable to different types of facilities and/or activities Safety Fundamentals SF-1 Fundamental Safety Principles(2006)Co-sponsorship:Euratom,FAO,ILO,IMO,OECD/NEA,PAHO,UNEP,WHO General Safety Standards(applicable to all facilities and activities)GSR P

31、art 1 Governmental,Legal and Regulatory Framework for Safety(2010)GS-R-3 The Management System for Facilities and Activities(2006)GSR Part 3 Radiation Protection and Safety of Radiation Sources:International Basic Safety Standards(2014)GSR Part 4 Safety Assessment for Facilities and Activities(2009)

32、GSR Part 5 Predisposal Management of Radioactive Waste(2009)GSR Part 6 Decommissioning of Facilities(2014)GS-R-2 Preparedness and Response for a Nuclear or Radiological Emergency(2002)Co-sponsorship:FAO,OCHA,OECD/NEA,ILO,PAHO,WHO GSG-4 Use of External Experts by the Regulatory Body(2013)GS-G-2.1 Arr

33、angements for Preparedness for a Nuclear or Radiological Emergency(2007)Co-sponsorship:FAO,OCHA,ILO,PAHO,WHO GSG-2 Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency(2011)GS-G-3.1 Application of the Management System for Facilities and Activities(2006)GS-G-3.2 The

34、Management System for Technical Services in Radiation Safety(2008)GS-G-3.3 The Management System for the Processing,Handling and Storage of Radioactive Waste(2008)GSG-1 Classification of Radioactive Waste(2009)GSG-3 The Safety Case and Safety Assessment for the Predisposal Management of Radioactive

35、Waste(2013)RS-G-1.1 Occupational Radiation Protection(1999)Co-sponsorship:ILO RS-G-1.2 Assessment of Occupational Exposure Due to Intakes of Radionuclides(1999)Co-sponsorship:ILO RS-G-1.3 Assessment of Occupational Exposure Due to External Sources of Radiation(1999)Co-sponsorship:ILO RS-G-1.4 Buildi

36、ng Competence in Radiation Protection and the Safe Use of Radiation Sources(2001)Co-sponsorship:ILO,PAHO,WHO RS-G-1.7 Application of the Concepts of Exclusion,Exemption and Clearance(2004)RS-G-1.8 Environmental and Source Monitoring for Purposes of Radiation Protection(2005)RS-G-1.9 Categorization o

37、f Radioactive Sources(2005)WS-G-2.3 Regulatory Control of Radioactive Discharges to the Environment(2000)(under revision)WS-G-2.5 Predisposal Management of Low and Intermediate Level Radioactive Waste(2003)(under revision)WS-G-2.6 Predisposal Management of High Level Radioactive Waste(2003)(under re

38、vision)WS-G-3.1 Remediation Process for Areas Affected by Past Activities and Accidents(2007)WS-G-5.1 Release of Sites from Regulatory Control on Termination of Practices(2006)WS-G-5.2 Safety Assessment for the decommissioning of Facilities Using Radioactive Material(2008)WS-G-6.1 Storage of Radioac

39、tive Waste(2006)GSG-5 Justification of Practices,Including Non-Medical Human Imaging(2014)2014-10-20 6 Specific Safety Standards(applicable to specified facilities and activities)Nuclear Power Plants SSR-2/1 Safety of Nuclear Power Plants:Design(2012)SSR-2/2 Safety of Nuclear Power Plants:Commission

40、ing and Operation(2011)NS-R-3 Site Evaluation for Nuclear Installations(2003)under revision SSG-16 Establishing the Safety Infrastructure for a Nuclear Power Programme(2012)GS-G-1.1 Organization and Staffing of the Regulatory Body for Nuclear Facilities(2002)GS-G-1.2 Review and Assessment of Nuclear

41、 Facilities by the Regulatory Body(2002)GS-G-1.3 Regulatory Inspection of Nuclear Facilities and Enforcement by the Regulatory Body(2002)GS-G-1.4 Documentation for Use in Regulating Nuclear Facilities(2002)GS-G-3.5 The Management System for Nuclear Installations(2009)SSG-12 Licensing Process for Nuc

42、lear Installations(2010)GS-G-4.1 Format and Content of the Safety Analysis report for Nuclear Power Plants(2004)SSG-30 Safety Classification of Structures,Systems and Components in Nuclear Power Plants(2014)NS-G-1.1 Software for Computer Based Systems Important to Safety in Nuclear Power Plants(2000

43、)(under revision)NS-G-1.3 Instrumentation and Control Systems Important to Safety in Nuclear Power Plants(2002)(under revision)NS-G-1.4 Design of Fuel Handling and Storage Systems for Nuclear Power Plants(2003)NS-G-1.5 External Events Excluding Earthquakes in the Design of Nuclear Power Plants(2003)

44、NS-G-1.6 Seismic Design and Qualification for Nuclear Power Plants(2003)NS-G-1.7 Protection against Internal Fires and Explosions in the Design of Nuclear Power Plants(2004)NS-G-1.8 Design of Emergency Power Systems for Nuclear Power Plants(2004)(under revision)NS-G-1.9 Design of the Reactor Coolant

45、 System and Associated Systems in Nuclear Power Plants(2004)NS-G-1.10 Design of Reactor Containment Systems for Nuclear Power Plants(2004)NS-G-1.11 Protection against Internal Hazards other than Fires and Explosions in the Design of Nuclear Power Plants(2004)NS-G-1.12 Design of the Reactor Core for

46、Nuclear Power Plants(2005)NS-G-1.13 Radiation Protection Aspects of Design for Nuclear Power Plants(2005)NS-G-2.1 Fire Safety in the Operation of Nuclear Power Plants(2000)NS-G-2.2 Operational limits and Conditions and Operating Procedures for Nuclear Power Plants(2000)NS-G-2.3 Modifications to Nucl

47、ear Power Plants(2001)NS-G-2.4 The Operating Organization for Nuclear Power Plants(2001)NS-G-2.5 Core Management and Fuel Handling for Nuclear Power Plants(2002)NS-G-2.6 Maintenance,Surveillance and In-Service Inspection in Nuclear Power Plants(2002)NS-G-2.7 Radiation Protection and Radioactive Wast

48、e Management in the Operation of Nuclear Power Plants(2002)NS-G-2.8 Recruitment,Qualification and Training of Personnel for Nuclear Power Plants(2002)SSG-28 Commissioning for Nuclear Power Plants(2014)SSG-25 Periodic Safety Review for Nuclear Power Plants(2013)NS-G-2.11 A System for the Feedback of

49、Experience from Events in Nuclear Installations(2006)NS-G-2.12 Ageing Management for Nuclear Power Plants(2009)NS-G-2.13 Evaluation of Seismic Safety for Existing Nuclear Installations(2009)NS-G-2.14 Conduct of Operations at Nuclear Power Plants(2008)NS-G-2.15 Severe Accident Management Programmes f

50、or Nuclear Power Plants(2009)SSG-13 Chemistry Programme for Water Cooled Nuclear Power Plants(2011)NS-G-3.1 External Human Induced Events in Site Evaluation for Nuclear Power Plants(2002)NS-G-3.2 Dispersion of Radioactive Material in Air and Water and Consideration of Population Distribution in Site