19. 미국 인,허가요건(NUREG-0800)_Chapter 9. Auxiliary Systems.hwp

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1 9.1.1 신핵연료저장 원자력발전소는신핵연료저장을위한저장시설을가지고있다. 저장되는신핵연료의양은발전소의고유한설계및각각의재장전요구에따라발전소마다다르다. 검토자는가능한저장조건에서저장시설이신핵연료를미임계배치상태로유지할수있는지확인한다. 검토자는핵연료집합체저장대와저장실을포함한신핵연료저장시설설계에대해다음과같은관점에서검토한다. - 저장되는신핵연료의양 - 모든저장조건에서미임계배열상태를유지하기위한저장대의설계및배치 - 미임계의정도, 이를뒷받침하는분석및관련된가정사항 - 신핵연료저장대와저장실에대한외력이나하중의영향 ( 예 : 안전정지지진, 기중기인양력 ) - 다수호기발전소에서의시설공유효과와신핵연료저장시설에인접한발전소의다른기기의고장으로인한영향 - 만약설계가이전에허용되었던설계와많이다른경우핵연료가장전된저장대의유효증배계수의적합성등을검토한다. 신핵연료저장의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.29, "Seismic Design Classification - ANSI/ANS 57.1, "Design Requirements for Light-Water Reactor Fuel Handling System - ANSI/ANS 57.3, "Design Requirements for New LWR Fuel Storage Facilities - 1 -

2 9.1.2 사용후핵연료저장 원자력발전소는사용후핵연료집합체의습식저장시설을가지고있다. 사용후핵연료저장조및저장대의안전기능은모든가능한저장조건에서핵연료집합체를안전한미임계배치상태로유지하고핵연료집합체를이송용기로장전하는안전한수단을제공하는것이다. 검토자는사용후핵연료저장대, 저장대를수용하는사용후핵연료저장조, 사용후핵연료저장조라이너플레이트및관련기기저장실등이관련요건에부합하는지확인하기위하여검토한다. 사용후핵연료저장의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.29, "Seismic Design Classification - ANSI/ANS 57.1, "Design Requirements for Light-Water Reactor Fuel Handling System - ANSI/ANS 57.3, "Design Requirements for New LWR Fuel Storage Facilities - Regulatory Guide 1.13, "Spent Fuel Storage Facilities Design Basis - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.115, "Protection Against Low-Trajectory Turbine Missiles - Regulatory Guide 1.117, "Tornado Design Classification - ANSI/ANS 57.2/ANSI N , "Design Objectives for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Stations - NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants - 2 -

3 9.1.3 사용후핵연료저장조냉각및정화계통 모든원자력발전소는사용후핵연료집합체의습식저장을위한사용후핵연료저장조를가지고있다. 저장된핵연료집합체로부터붕괴열을제거하기위한냉각방법은각발전소의설계에따라다르다. 이계통에의해수행되는안전기능은모든경우에동일하며, 이는사용후핵연료집합체가모든저장조건에서냉각되어야하고물에잠겨있어야한다는것이다. 본계통에의해서수행되는안전과관련되지않은기능에는핵연료저장조, 재장전수로, 재장전수저장탱크및다른기기저장조의수질정화수단, 재장전수로및다른저장조의충수및배수수단, 저장수의투명도를높이기위한저장조의표면부유물제거장치등이있다. 사용후핵연료저장조냉각및정화계통에대한검토분야는저장조와저장실의입구 에서출구까지, 내진범주 I 의수원및저장조보충을위한배관, 정화계통의필터와 탈염기, 그리고방사성폐기물계통으로방출하기전까지의재생공정을포함한다. 사용후핵연료저장조냉각및정화계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.13, "Fuel Storage Facility Design Basis - Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.52, "Design, Testing, and Maintenance Criteria for Engineered -Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants - Regulatory Guide 8.8, "Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable - 3 -

4 9.1.4 경하중취급계통 검토자는신연료인수및사용후핵연료를이송용기에장전하는데사용되는모든부품및기기로구성되어있는경하중취급계통이관련요건을만족하는지를검토한다. 경하중취급계통에대한검토의목적은임계사고, 사용후핵연료의손상으로발생되는방사능누출사고및허용치를초과하는종사자의피폭을예방하기위함이다. 경하중취급계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.29, "Seismic Design Classification - ANSI/ANS , "Design Requirements for LWR Fuel Handling Systems - 4 -

5 9.1.5 중하중취급계통 검토자는발전소에서핵연료집합체한다발과관련취급장비를합한중량보다무거운중하중의이동에사용되는모든부품및기기로구성되어있는중하중취급계통이관련요건을만족하는지를확인한다. 중하중취급계통의검토에서중요한점은부적절한운전또는기기의오작동중하나또는두가지의중복시에임계하중의취급은방사능누출, 임계사고, 원자로용기내또는사용후핵연료저장조내에서의연료냉각또는원자로의안전정지불능을초래할수있다. 중하중취급계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 100, "Reactor Site Criteria - Regulatory Guide 1.13, "Spent Fuel Storage Facility Design Basis - Regulatory Guide 1.29, "Seismic Design Classification - NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants - NUREG-0554, "Single-Failure-Proof Cranes for Nuclear Power Plants - ANSI N , "Radioactive Materials - Special Lifting Devices for Shipping Containers Weighing Pounds(4500kg) or More - ASME B , "Overhead and Gantry Cranes - Top Running Bridge, Single or Multiple Girder, Top Running Trolley Hoist - ASME B , "Slings - ASME NOG1-2004, "Rules for Construction of Overhead and Gantry Cranes - 5 -

6 9.2.1 용수계통 용수계통은안전관련설비에대한필수냉각을제공하며정상운전중사용되는비안전관련보조기기에대한냉각도제공한다. 이절에서는용수펌프흡입측에서부터냉각수배출측까지의동계통이관련요건에적합한지를검토한다. 최종열제거원은발전소정지에요구되는설비의장기간냉각을위한용수계통의입구수원을제공하며, 용수계통에연계되는계통들과같이가상사고를예방하거나사고결과를완화시키는데필요한특정기기에도열제거원으로제공된다. 용수계통의펌프능력이가상사고후연장된운전기간동안제공될수있는지를보장하기위하여최종열제거원의고수위와저수위에서용수계통펌프의성능특성을비교한다. 용수계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50, Appendix A, GDC 2, Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, GDC 4, Environmental and Dynamic Effects Design Bases - 10 CFR 50, Appendix A, GDC 5, Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, GDC 44, Cooling Water - 10 CFR 50, Appendix A, GDC 45, Inspection of Cooling Water System - 10 CFR 50, Appendix A, GDC 46, Testing of Cooling Water Systems - Regulatory Guide 1.29, Seismic Design Classification - NRC Letter to All Holders of Operating Licenses or Construction Permits for Nuclear Power Plants, Service Water System Problems Affecting Safety-Related Equipment(Generic Letter No ), July 18, NRC Letter to All Holders of Operating Licenses or Construction Permits for Nuclear Power Plants, Service Water System Problems Affecting Safety-Related Equipment(Generic Letter No , Supplement 1), April 4, NRC Letter to Specified Licensees and Applicants of Pressurized-Water Reactor Nuclear Power Plants, Request for Information Related to the Resolution of Generic Issue 130, Essential Service Water System Failures at Multi-Unit Sites, (Generic Letter No ), July 18,

7 - NRC Letter to All holders of operating licenses for nuclear power reactors, except for those licenses that have been amended to possession-only status, Assurance of Equipment Operability And Containment Integrity During Design-Basis Accident Conditions (Generic Letter No ), September 30, NRC Letter to All holders of operating licenses for nuclear power reactors, except for those licenses that have been amended to possession-only status, Assurance of Equipment Operability And Containment Integrity During Design-Basis Accident Conditions (Generic Letter No , Supplement 1), November 13, NUREG-0718, Proposed Licensing Requirements for Pending CP s and Manufacturing License - NUREG-0927, Revision 1, Evaluation of Water Hammer Occurrences in Nuclear Power Plants, March NUREG-1461, Regulatory Analysis for the Resolution of Generic Issue 153: Loss of Essential Service Water in LWRs, August

8 9.2.2 원자로보조냉각수계통 원자로보조냉각수계통은정상운전, 예상운전과도및사고시안전정지를위하여요구되며사고결과의완화또는사고발생의방지를위하여필요하다. 본계통은원자로계통기기, 원자로정지설비, 환기설비, 비상노심냉각계통등의기기에대한폐회로보조냉각계통을포함한다. 본계통에대한검토는계통기기, 밸브및배관과타계통과의연결부또는연계부를포함한다. 비상노심냉각계통설비, 환기설비및원자로정지설비와같은안전관련기기에대한보조냉각수계통에주안점을두고검토한다. 원자로보조냉각수계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - IEEE Std IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations - NUREG-0927, Revision 1 Evaluation of Water Hammer Occurrences in Nuclear Power Plants - Regulatory Guide 1.29 Seismic Design Classification - Regulatory Guide Criteria for Power, Instrumentation, and Control Portions of Safety System - Regulatory Guide Station Blackout - Branch Technical Position SPLB 3-1 Protection Against Postulated Piping Failures in Fluid Systems Outside Containment (attached to SRP Section 3.6.1) - 10 CFR 50.34(f), Contents of Applications, Technical Information, Additional TMI-Related Requirements - 10 CFR 50, Appendix A, General Design Criterion 2 Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, General Design Criterion 4 Environmental and Dynamic Effects Design Bases - 10 CFR 50, Appendix A, General Design Criterion 5 Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, General Design Criterion 44 Cooling Water - 10 CFR 50, Appendix A, General Design Criterion 45 Inspection of Cooling Water System - 8 -

9 - 10 CFR 50, Appendix A, General Design Criterion 46 Testing of Cooling Water System - 9 -

10 9.2.4 식수및위생수계통 건설허가단계의검토에는신청자의안전성분석보고서에기술된식수및위생수계 통에대하여검토하고, 운영허가단계의검토에는건설허가단계에서허용된설계 내용과일치하는지검토한다. 식수및위생수계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50, Appendix A, General Design Criteria 60, "Control of Release of Radioactive Materials to the Environment

11 9.2.5 최종열제거원 최종열제거원은정상적인원자로정지또는냉각재상실사고를포함한사고에의한원자로정지이후에원자로의잔열과필수냉각계통의열부하제거를위한냉각수원이다. 최종열제거원의설계는관련요건을만족하여야한다. 계통성능분야담당부서는최종열제거원을구성하는수원을검토한다. 여기에는원자로의정상, 사고혹은정지조건에대하여냉각수공급원 ( 즉, 대양, 호수, 자연또는인공적인저수조, 강또는냉각탑 ) 의형태와크기, 적절한온도로요구되는냉각수를공급하기위한열제거능력이포함된다. 이검토에서는최종열제거원이설계코드요건에만족되는지를확인한다. 최종열제거원의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50, "Early Site Permit: Standard Design Certifications: And Combined Licenses For Nuclear Power Plant - 10 CFR 50, Appendix A, General Design Criterion 2, "Design Bases for Protection against Natural Phenomena - 10 CFR 50, Appendix A, General Design Criterion 5, "Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, General Design Criterion 44, "Cooling Water - 10 CFR 50, Appendix A, General Design Criterion 45, "Inspection of Cooling Water System - 10 CFR 50, Appendix A, General Design Criterion 46, "Testing of Cooling Water System - 10 CFR 52, "Licenses, Certifications, and approvals for Nuclear Power Plants - Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Power Plants - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.72, "Spray Pond Piping made from Fiberglass-Reinforced Thermosetting Resin - Generic Letter 89-13, "Service Water System Problems Affecting Safety-Related Equipment - ANS 5.1, "Decay Heat Power for Light Water Reactors, October

12 9.2.6 응축수저장시설 응축수저장시설은주복수기집수정 (Condenser Hot Well), 저방사능액체폐기물재처리응축수, 보충수처리계통들에의해발생된물의저장조로사용된다. 또한응축수저장시설은여러보조계통의보충수원또는물공급을위해사용된다. 응축수저장시설은검토대상발전소의특성에따라안전관련여부가결정된다. 응축수저장시설이관련요건에부합되는지를확인하기위하여응축수저장탱크에서기타계통과의연결부또는경계부까지검토한다. 응축수저장시설의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.29, Seismic Design Classification - Regulatory Guide 1.59, Design Basis Floods for Nuclear Power Plants - Regulatory Guide 1.76, Design Basis Tornado for Nuclear Power Plants - Regulatory Guide 1.102, Flood Protection for Nuclear Power Plants - Regulatory Guide 1.117, Tornado Design Classification - Regulatory Guide 1.143, Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed In Light-Water-Cooled Nuclear Power Plants - Regulatory Guide 1.155, Station Blackout - 10 CFR Loss of all Alternating Current Power - 10 CFR 50 Appendix A, General Design Criterion 2, Design Bases for Protection against Natural Phenomena - 10 CFR 50 Appendix A, General Design Criterion 5, Sharing of Structures, Systems, and Components - 10 CFR 50 Appendix A, General Design Criterion 44, Cooling Water - 10 CFR 50 Appendix A, General Design Criterion 45, Inspection of Cooling Water System - 10 CFR 50 Appendix A, General Design Criterion 46, Testing of Cooling Water System - 10 CFR 50 Appendix A, General Design Criterion 60, Control of Release of Radioactive Materials to the Environment - 10 CFR 100 Reactor Site Criteria

13 9.3.1 압축공기계통 압축공기계통중계기용공기계통은안전성에중요한기능을수행하는계통및기기운전에요구되는압축공기를제공하는안전기능을갖고있으며, 압축공기가사용되는계통이나기기들은다양한종류의부하와이에상응하는압축공기를필요로하므로압축공기가공급되는계통및기기들간의상호영향에의해서안전성에영향을미치는사고 고장이발생할가능성이존재한다. 따라서압축공기계통을검토하는목적은압축공기계통으로부터공급을받는계기용공기계통이적정한공기품질을확보할수있으며, 정상운전이나과도, 고장또는비상조건등에서압축공기공급계통의부주의한작동, 배관의파단, 직류전원의상실, 기기의오작동과같은가상사건으로공기압력이완전또는급격하게상실되거나, 이로인한분배계통의일부나전체에걸쳐부분적또는점진적공기압력의상실, 그리고기기오작동이나고장으로인한압력상승시에도적절히대응할수있어서동계통의운전성이확보되고, 계통설계시고려된고유안전기능이유지될수있는지를검토한다. 압축공기계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50.63, "Loss of All Alternating Current Power - 10 CFR 50, Appendix A, General Design Criterion 1, "Quality Standards and Records - 10 CFR 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, General Design Criterion 5, "Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.155, "Station Blackout - NUREG-1275, Volume 2, "Operating Experience Feedback Report - Air Systems Problems - NRC Letter to All Holders of Operating Licenses or Construction Permits for Nuclear Power Reactors, "Instrument Air Supply System Problems Affecting Safety-Related equipment (Generic Letter No ), August 8, ANSI/ISA-S , Reaffirmed 1981, "Quality Standard for Instrument Air

14 9.3.2 공정및사고후시료채취계통 건설허가단계에서는공정시료채취계통및사고후시료채취계통의설계목적과설계기준을검토하며, 운영허가단계에서는건설허가단계에서승인된설계를준수하는지검토하고이러한분야에대한신청자운영기술지침서가적절한지를평가한다. 검토내용에는시료채취되는공정류 (stream) 와시료채취를통하여결정되는인자 ( 예를들면, 총베타-감마농도, 붕산농도 ) 의확인이포함된다. 운영허가단계에서는공정시료채취계통및사고후시료채취계통에대한계통설명을검토한다. 검토에는 (1) 배관및계기도면, (2) 대표시료채취방안, (3) 시료채취점및시료채취지역의위치, (4) 시료채취관의정화를위한설비가포함된다. 건설허가단계에서는배관및설비의내진설계, 품질등급분류및선정된등급분류기준의근거를검토한다. 운영허가단계에서는설계및예상되는온도와압력그리고, 계통기기의제작재료를검토한다. 건설허가단계에서는계통격리설비를검토하며, 원자로냉각재상실을제한함으로써방사능방출을제한하기위한수단을검토한다. 공정및사고후시료채취계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR (b), "Radiation Protection Programs - 10 CFR 50.34(f), "Additional TMI-related requirements - 10 CFR 50, App. A, General Design Criterion 1, "Quality Standards and Records - 10 CFR 50, App. A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, General Design Criterion 13, "Instrumentation and Control - 10 CFR 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary - 10 CFR 50, Appendix A, General Design Criterion 26, "Reactivity Control System Redundancy and Capability - 10 CFR 50, Appendix A, General Design Criterion 41, "Containment Atmosphere Cleanup - 10 CFR 50, Appendix A, General Design Criterion 60, "Control of Releases of Radioactive Materials to the Environment - 10 CFR 50, Appendix A, General Design Criterion 63, "Monitoring Fuel and

15 Waste Storage - 10 CFR 50, Appendix A, General Design Criterion 64, "Monitoring Radioactivity Releases - NUREG-0737, "Clarification of TMI Action Plan Requirements - Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants - Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.56, "Maintenance of Water Purity in Boiling Water Reactors - Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environments Conditions during and following an Accident - Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable - ANSI N (R93), "Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, American National Standards Institute(1969)(reaffirmed 1993)

16 9.3.3 기기및바닥배수계통 기기및바닥배수계통은폐기유체, 밸브및펌프의밀봉누설, 탱크의배수가공정또는처분을위한적절한위치로보내지도록설계된다. 계통성능분야담당부서는격납건물외부로의액체유출물의수집및처분을포함한기기및바닥배수계통을검토한다. 여기에는기기또는바닥배수로부터집수조까지의배관및펌프가포함되며유출물을배수탱크로보낸다음방사성폐기물계통으로보내는데필요한기기도포함된다. 기기및바닥배수계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50, Appendix A, General Design Criterion 2, "Design Bases for Protection against Natural Phenomena - 10 CFR 50, Appendix A, General Design Criterion 4, "Environmental and Dynamic Effects Design Bases - 10 CFR 50, Appendix A, General Design Criterion 60, "Control of Releases of Radioactive Materials to the Environment - Regulatory Guide 1.29, "Seismic Design Classification

17 9.3.4 화학및체적제어계통 가압경수로형원전의화학및체적제어계통 (CVCS) 과붕산회수계통 (BRS) 은 (1) 원자로냉각재계통에요구되는냉각재의양과수질을유지하는기능, (2) 원자로냉각재펌프의밀봉수와가압기보조살수용보충수를공급하는기능, (3) 원자로냉각재의중성자흡수재인붕소의농도를조절하는기능, (4) 일차수질화학제어기능및냉각재의방사능준위를감소시키는기능을수행한다. 또한본계통은정상운전시탈염수보충을위해냉각재를재순환시키며, 가상사고시비상노심냉각계통에고압안전주입수를제공할수도있다. 동계통은일반설계기준 1, 2, 5, 14, 29, 33, 35, 60 및 61의요건을만족하는지검토한다. 추가적으로화학및체적제어계통은교류전원완전상실 (SBO) 에대처하기위해필요한원자로냉각재재고량의제어및원자로냉각재펌프에밀봉수를주입한다. 이러한기능을수행하기위한화학및체적제어계통성능이 10 CFR (a)(2) 와일치하는가를검토한다. 화학및체적제어계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50, 50.34(f), "Additional TMI-Related Requirements - 10 CFR 50, 50.63, "Loss of All Alternating Current Power - 10 CFR 50, Appendix A, General Design Criterion 1, "Quality Standards and Records - 10 CFR 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, General Design Criterion 5, "Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary - 10 CFR 50, Appendix A, General Design Criterion 29, "Protection Against Anticipated Operational Occurrences - 10 CFR 50, Appendix A, General Design Criterion 33, "Reactor Coolant Makeup - 10 CFR 50, Appendix A, General Design Criterion 35, "Emergency Core Cooling - 10 CFR 50, Appendix A, General Design Criterion 60, "Control of Release of

18 Radioactive Material to the Environment - 10 CFR 50, Appendix A, General Design Criterion 61, "Fuel Storage and handling and Radioactivity Control - Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.155, "Station Blackout - NUREG-0737, "Clarification of TMI Action Plan Requirements - "PWR Primary Water Chemistry Guidelines, Electric Power Research Institute

19 9.4.1 제어실지역환기계통 제어실지역환기계통은정상운전, 예상운전과도및설계기준사고동안제어실종사자의안전과편의를위해제어된환경을제공하며, 제어실기기들의운전성을보장한다. 제어실지역환기계통의일부분은소내정전사고 (SBO) 로부터견딜수있어야하고복구하도록설계되어야한다. 동계통에대해서는공기흡입측에서부터기체정화및처리계통혹은발전소배기계통으로연결된방출지점까지의설계가기술기준의요건에적합한지를검토한다. 검토범위에는공기흡입구, 덕트, 공기조화설비, 여과기, 송풍기, 격리댐퍼그리고배기팬등이포함되며또한주제어실, 배전및축전지실, 출입통제구역, 제어건물 (control building) 공기조화기기실및전산실도포함된다. 제어실지역환기계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 20, "Standards For Protection Against Radiation - 10 CFR 50.63, "Loss of All Alternating Current Power - 10 CFR 50, Appendix A, GDC 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, GDC 4, "Environmental and Dynamic Effects Design Bases - 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, GDC 19, "Control Room - 10 CFR 50, Appendix A, GDC 60, "Control of Releases of Radioactive Materials to the Environment - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.52, "Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants - Regulatory Guide 1.78, "Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release - Regulatory Guide 1.95, "Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release

20 - Regulatory Guide 1.140, "Design, Testing and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light Water Cooled Nuclear Power Plants - Regulatory Guide 1.155, "Station Blackout - ASME Code AG-1, "Code for Nuclear Air and Gas Treatment, 1991(including the AG-1a-92 Addenda thereto)

21 9.4.2 사용후핵연료저장조지역환기계통 사용후핵연료저장조지역환기계통은정상운전, 예상운전과도기간및핵연료취급사고이후종사자의출입을허용하고, 방사성공기를제어하고사용후핵연료저장조지역에서환기상태를유지한다. 동계통은공기입구측에서부터기체정화및처리계통혹은발전소배기계통으로연결된방출지점까지의설계가기술기준의요건에적합한지를검토한다. 검토범위에는공기흡입구, 덕트, 공기조화설비, 여과기, 송풍기, 격리댐퍼그리고배기팬등이포함되며사용후핵연료냉각펌프실및사용후핵연료저장조와연계된모든지역도포함된다. 사용후핵연료저장조지역환기계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 20, "Standards For Protection Against Radiation - 10 CFR 50, Appendix A, GDC 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, GDC 60, "Control of Releases of Radioactive Materials to the Environment - 10 CFR 50, Appendix A, GDC 61, "Fuel Storage and Handling and Radioactivity Control - Regulatory Guide 1.13, "Fuel Storage Facility Design Basis - Regulatory Guide 1.25, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactor - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.52, "Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants - Regulatory Guide 1.140, "Design, Testing and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Absorption Units of Light Water Cooled Nuclear Power Plants - ANSI/ANS , "Safety Criteria for Nuclear Power Plant HVAC Systems

22 Located Outside Primary Containment - ANSI/ASME AG , "Code on Nuclear Air and Gas Treatment - ASTM D , "Standard Test Methods for Radiological Testing of Nuclear Grade Gas Phase Absorbers

23 9.4.3 보조및방사성폐기물건물환기계통 보조및방사성폐기물건물환기계통은정상운전, 예상운전과도및예상되는사고후에보조및방사성폐기물건물에환기를유지하고종사자들의출입을허용하며공기중방사성물질의농도를제어한다. 보조및방사성폐기물건물환기계통은공기입구측에서부터기체정화및처리계통혹은발전소배기계통으로연결된방출지점까지의설계가관련요건에적합한지를검토한다. 검토분야는공기흡입구, 덕트, 공기조화설비, 여과기, 송풍기, 격리댐퍼그리고배기팬등이포함되며또한방사성폐기물건물및출입통제비방사지역과이들과연계된보조건물에있는안전관련지역도포함된다. 보조및방사성폐기물건물환기계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 20, "Standards For Protection Against Radiation - 10 CFR 50, Appendix A, GDC 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, GDC 60, "Control of Releases of Radioactive Materials to the Environment - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.140, "Design, Testing and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants - Regulatory Guide 1.52, "Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmospheric Cleanup System Air Filtration and Absorption Units of Light Water Cooled Nuclear Power Plants - ANSI/ANS , "Safety Criteria for Nuclear Power Plant HVAC Systems Located Outside Primary Containment - ANSI/ASME AG , "Code on Nuclear Air and Gas Treatment - ASTM D , "Standard Test Methods for Radiological Testing of Nuclear-Grade Gas-Phase Absorbers

24 9.4.4 터빈건물환기계통 터빈건물환기계통은정상운전, 예상운전과도및방사성물질의배출을초래하는사고후에터빈건물에환기를유지하고종사자들의출입을허용하며공기중방사성물질의농도를제어한다. 동계통에대해서는공기흡입구에서방출지점까지의설계가관련요구조건을만족하는지확인하기위하여검토한다. 검토항목으로공기흡입구, 덕트, 공기조화설비, 송풍기, 격리댐퍼, 여과기그리고배기팬등이포함된다. 터빈건물환기계통의검토는터빈건물그리고그건물에연계된안전관련기기가위치한지역도포함된다. 터빈건물환기계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 20, "Standards For Protection Against Radiation - 10 CFR 50, Appendix A, GDC 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, System, and Components - 10 CFR 50, Appendix A, GDC 60, "Control of Releases of Radioactive Materials to the Environment - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.140, "Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Absorption Units of Light Water Cooled Nuclear Power Plants - Regulatory Guide 1.52, "Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmospheric Cleanup System Air Filtration and Absorption Units of Light Water Cooled Nuclear Power Plants - ANSI/ANS , "Safety Criteria for Nuclear Power Plant HVAC Systems Located Outside Primary Containment - ANSI/ASME AG , "Code on Nuclear Air and Gas Treatment - ASTM D , "Standard Test Methods for Radiological Testing of Nuclear- Grade Gas-Phase Absorbers

25 9.4.5 공학적안전설비지역환기계통 공학적안전설비지역환기계통은설계기준사고나예상되는과도상태시공학적안전설비기기를위해적절하게제어된환경을제공한다. 공기흡입측에서부터대기로의방출지점까지관련요건을만족하는지검토한다. 검토항목에는공기흡입구, 덕트, 공기조화설비, 유량조절장치, 격리댐퍼, 배기구및배기팬등을포함한다. 동계통의검토는안전관련기기가있는지역내에제어된환경을유지시키기위한모든환기계통들을포함한다. 즉, 용수펌프건물, 디젤발전기가위치한지역, 비상노심냉각계통펌프실, 기기냉각수펌프실, 보조급수펌프가위치한지역, 사고를완화시키거나미연에방지하는데필요하거나원자로안전정지를위해필요한기기들이있는지역들을포함한다. 공학적안전설비지역환기계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 20, "Standards For Protection Against Radiation - 10 CFR 50.63, "Loss of All Alternating Current Power - 10 CFR 50, Appendix A, GDC 2, "Design Bases for Protection Against Natural Phenomena - 10 CFR 50, Appendix A, GDC 4, "Environmental and Missile Design Bases - 10 CFR 50, Appendix A, GDC 5, "Sharing of Structures, Systems, and Components - 10 CFR 50, Appendix A, GDC 17, "Electric Power Systems - 10 CFR 50, Appendix A, GDC 60, "Control of Releases of Radioactive Materials to the Environment - Regulatory Guide 1.29, "Seismic Design Classification - Regulatory Guide 1.52, "Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants - Regulatory Guide 1.140, "Design, Testing and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Absorption Units of Light Water Cooled Nuclear Power Plants - Regulatory Guide 1.155, "Station Blackout - NUREG-CR/0660, "Enhancement of Onsite Emergency Diesel Generator Reliability

26 9.5.1 화재방호계획 원자력발전소화재방호계획 (Fire Protection Program : FPP) 의목적은심층방어개념을통하여원자로안전및방사성물질누출과관련된화재방호목표가만족됨을보장하는것이다. 심층방어개념은 (1) 화재의발생을방지 (2) 화재를신속하게감지하여즉각적인제어및진화 (3) 화재진압활동에의해즉각적으로진화되지않은화재가발전소의안전정지기능을방해하지않도록하기위하여안전에중요한구조물, 계통및기기들을보호하는것이다. 관련규정에서는화재및폭발의가능성과그로인한영향이최소화될수있도록안전에중요한구조물 계통및기기들을관련설계요건에적합하도록설계하고배치하도록요구하고있다. 화재방호계획의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50, "Domestic Licensing of Production and Utilization Facilities , "Specific exemptions , "Contents of applications; technical information , "Fire protection , "Application for amendment of license or construction permit , "Notice for public comment; State consultation , "Issuance of amendment - 10 CFR 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants , "Scope , "Contents of application - technical specifications - 10 CFR 50, Appendix R, "Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, Branch Technical Position (BTP) SPLB "Guidelines for Fire Protection for Nuclear Power Plants (Formerly BTP CMEB 9.5-1) - Branch Technical Position (BTP) APCSB 9.5-1, Appendix A, "Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, ANS X, "Standard on Methodology for Fire PRA, American Nuclear Society (draft) - Regulatory Guide 1.139, "Guidance for Residual Heat Removal (for Comment)

27 - Regulatory Guide 1.174, Revision 1, "An Approach for Using Probabilistic Risk Assessment In Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis - Regulatory Guide 1.188, Revision 1, "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses - Regulatory Guide 1.189, Revision 1, "Fire Protection for Nuclear Power Plants - Regulatory Guide 1.191, "Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown - Regulatory Guide 1.206, "Combined License Applications for Nuclear Power Plants (LWR Edition) - NUREG-0933, "A Prioritization of Generic Safety Issues - NUREG-1800, Revision 1, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants - NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report - NUREG-1824/EPRI , "Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications (Draft for Comment) - NUREG/CR-6850 (EPRI TR ), "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities - SECY , "Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements - SECY , "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs - SECY , "Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems in Passive Plant Designs - Staff Requirements - SECY Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs, July 21, Staff Requirements - SECY Evolutionary Light-Water Reactor (ALWR) Certification Issues and Their Relationship to Current Regulatory Requirements, June 26, Information Notice , "Recent Fires at Commercial Nuclear Power Plants in the United States - NEI 95-10, Revision 6, "Industry Guide for Implementing the Requirements of

28 10 CFR Part 54 - The License Renewal Rule - NFPA 804, "Standard for Fire Protection for Advanced Light Water Reactor Electric Generating Plants - NFPA 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants

29 9.5.2 통신계통 통신계통에대한검토는정상운전, 과도상태, 화재및사고, 비정상적인환경및보안관련사건동안에발전소소내그리고발전소와외부간에사용되는통신계통으로한정한다. 검토시고려할점은정상운전및소외전원상실을포함한과도상태, 화재, 및사고상태중에발전소내, 외부에서의효과적인통신능력및관련설계에대해검토한다. 통신계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다 CFR 50 Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities - 10 CFR 50.34, "Contents of applications; technical information - 10 CFR 50.47, "Emergency plans - NUREG-0700, "Guidelines for Control Room Design Reviews, September EPRI NP-5652, "Guideline for the Utilization of Commercial-Grade Items in Nuclear Safety-Related Applications - EPRI TR , "Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications - Regulatory Guide 1.180, "Guidelines for Evaluating EMI and RFI in Safety- Related Instrumentation and Control Systems

30 9.5.3 조명계통 건설허가및운영허가단계에서정상및비상조명계통혹은검토와관련된참조정보를포함한보조조명계통에대하여아래와같은사항들을검토한다. 1. 발전소의모든운전상태에서적절한조명을제공하는정상조명계통의능력 2. 화재, 과도및사고상태를포함한모든운전기간에적절한조명을제공하는비상조명계통의능력 3. 비상조명계통에대한모든교류전력상실 ( 즉, 발전소정전사고동안 ) 의영향 4. 정상및비상조명계통의고장분석 조명계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - NUREG-0700, "Human-System Interface Design Review Guidelines, Rev. 2, May, Standard Review Plan Section 8.2, "Offsite Power System - Illuminating Engineering Society of North America Lighting Handbook

31 9.5.4 비상디젤엔진연료유계통 원자력발전소는안전관련기기에전원을공급하기위해충분한용량의소내비상전원을다중성개념으로보유하고있어야한다. 거의모든경우에소내비상전원은디젤엔진구동발전기세트를포함한다. 비상디젤엔진연료유계통에대한검토는엔진경계연결부분까지의모든배관, 연료저장탱크, 연료이송펌프, 일일탱크및연료저장탱크건물이관련요건에대한만족여부를확인하는것이다. 그리고검토에는소내에저장되는연료의품질과용량, 소외로부터의추가적인연료의이용성및공급등이포함된다. 비상디젤엔진연료유계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - KEPIC, MI, 원자력발전소가동중검사 - Regulatory Guide 1.115, "Protection Against Low-Trajectory Turbine Missiles - Regulatory Guide 1.117, "Tornado Design Classification - Regulatory Guide 1.137, Diesel Generator Fuel Oil Systems - Regulatory Guide 1.29, Seismic Design Classification - NUREG/CR-0660, "Enhancement of Onsite Emergency Diesel Generator Reliability, University of Dayton Research Institute, UDR-TR-79-07, February ANSI/ANS , "Fuel Oil Systems for Safety-Related Emergency Diesel Generators - Diesel Engine Manufacturers Association (DEMA) Standard

32 9.5.5 비상디젤엔진냉각수계통 비상디젤엔진냉각수계통은발전소비상디젤엔진에냉각수를공급하며, 관련규정을만족하는지여부를확인하기위해검토된다. 검토대상으로는비상디젤엔진의적절한운전에필수적인부품으로부터열을받아들이는부분과디젤엔진격실 (compartment) 내에위치하는계통부분그리고열을열제거원으로전달하는계통의추가적인부분을포함한다. 본계통의구성은모든밸브, 열교환기, 펌프그리고엔진연결부분까지의배관을포함한다. 비상디젤엔진냉각수계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.115, "Protection Against Low Trajectory Turbine Missiles - Regulatory Guide 1.117, "Tornado Design Classification - Regulatory Guide 1.29, Seismic Design Classification - NUREG/CR-0660, "Enhancement of Onsite Emergency Diesel Generator Reliability University of Dayton Research Institute, UDR-TR-79-07, February Diesel Engine Manufacturers Association (DEMA) Standard

33 9.5.6 비상디젤엔진기동계통 비상디젤엔진기동계통에대한검토에는관련요건을만족하도록소외전원상실에따른비상디젤엔진의신뢰할수있는기동을보증하는데필요한계통을포함한다. 본검토에는공기압축기, 공기건조기, 공기저장조, 디젤엔진축회전 (cranking) 장치, 밸브, 엔진연결부분까지배관, 여과기그리고관련된부수적인계측과제어계통을포함한다. 비상디젤엔진기동계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.115, "Protection Against Low-Trajectory Turbine Missiles - Regulatory Guide 1.117, "Tornado Design Classification - NUREG/CR-0660, "Enhancement of Onsite Emergency Diesel Generator Reliability University of Dayton Research Institute, UDR-TR-79-07, February Diesel Engine Manufacturers Association (DEMA) Standard

34 9.5.7 비상디젤엔진윤활계통 비상디젤엔진윤활계통은비상디젤엔진의기기에필수적인윤활을수행한다. 관련규정의요건에따르는것을보증하기위해비상디젤엔진윤활계통과관련된보조계통을검토한다. 검토에는엔진경계부까지계통운전에필수적인배관, 펌프, 기기및관련보조장치를포함한다. 비상디젤엔진윤활계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - Regulatory Guide 1.115, "Protection Against Low-Trajectory Turbine Missiles - Regulatory Guide 1.117, "Tornado Design Classification - NUREG/CR-0660, "Enhancement of Onsite Emergency Diesel Generator Reliability University of Dayton Research Institute, UDR-TR-79-07, February ANSI/ANS , Lubricating Oil System for Safety-Related Diesel Generators - Diesel Engine Manufacturers Association (DEMA) Standard

35 9.5.8 비상디젤엔진흡기및배기계통 비상디젤엔진흡기및배기계통은디젤엔진에신뢰할수있는품질의연소공기를공급하고디젤엔진으로부터대기로연소생성물을배출한다. 검토자는외부흡입구에서부터디젤엔진에연결된연소공기공급배관에이르는계통과디젤엔진의배기연결부위로부터건물외부에로의배기지점까지의계통을검토하여이들이관련규정을만족하는지를확인한다. 비상디젤엔진흡기및배기계통의검토와관련하여적용할수있는규제요건및허용기준은다음과같다. - NUREG/CR-0660, "Enhancement of Onsite Emergency Diesel Generator Reliability University of Dayton Research Institute, UDR-TR-79-07, February Regulatory Guide 1.115, "Protection Against Low-Trajectory Turbine Missiles - Regulatory Guide 1.117, "Tornado Design Classification - Diesel Engine Manufacturers Association (DEMA) Standard