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{{#Wiki_filter:REGULATUiNFORHATIONDISTRIBUTION'TEH(RIDS)ACCESSIONNUR:8105190381OVC~DATE:81/05/14NOTARIZED:NOFACIL:50-387SusquehannaSteamElectricStation,Unit1>Pennsylva50-368SusquehannaSteamElectricStation~Unit2,PennsylvaAUTH~NAivifAUTHORAfFiLIATIONCORTISi"l.WoPennsylvaniaPowerK,LightCo.RECIP.NAiwfRECIPItiV1AFFILIATIONYOUNGBLOODiB.J~LicensingBranch1SUBJECT;Forwardssummaryofconformancew/iOCFR20I50L100'onformancew/luCrRSOAppAisaiscussedinSection3.1ofFSAR~DISTRIBUTIUNCODE:8001SCOPIESRECEIVED:LTRENCLSIZE::D8TITLE:PSALM/f.SARAiiDTSandRelatedCorrespondenceOOCKET0008iVOTES:SendIKE3copiesfSeR8allamends'cy.'BAR-LRGPN(CRIB)05000387SendISE3copiesFSAR4allamends.1cy'.BwR-LRGPs(L.RIB)05000388ACTIOiV;<ECIPIEN'1Ii)C00f/iVAt1fA/~L(CENSNGRUSHBROO<.~.Ci)p'ESLTTRENCL100RfC[PIEivTIDCODE/NAi'lELICRRa2BCSTARK,R,04CDPIESLTTRENCL101INTERNAL:ACCIDEvALBR2>CH'ANEVGBRCO/EPERFBRf;,~IERGPREP22GEUSCIE>VCES14wY>/GEOBR1514E-ObLICQUALiR,<ECHE,<GBRioNiRCPOR02OPLlCBRPROC/TSTRE,Y20"SBR22GOlSr<UCTENGBR2>11101311111111AuXSYSBR07CONTSYSBR09EFFTRSYSUR12EQUIPQUALuR13Hu<FACTENGuRI~CSYS.BRlbLICGUIOBRvIATLENGoR17,QPAOELOPOWERSYSBH19QABR21REACSYSl3R23SITAj~iALbR2411111131111111101011111111-XTERNAL:ACRSNSlC27Oylvlb11LPOR03gAY23,1981515ITOTALNUWBEROFCOPIFSgE.~U<Rt.D:,LTTR'bEivCL'54 iI PpalTWONORTHNINTHSTREET,ALLENTOWN,PA.18101PHONE:(215)821-5151NORMANW.CURTISVicePresident-Engineering&Constructen821.5381May14,1981Mr.B.J.Youngblood,ChiefLicensingBranchNo.1U.S.NuclearRegulatoryCommissionWashington,D.C.20555SUSQUEHANNASTEAMELECTRICSTATION10CFRCOMPLIANCEER100450FILE841PLA-777DOCKETNOS,50-387AND50-388
{{#Wiki_filter:REGULATUiNFORHATION DISTRIBUTION
'TEH(RIDS)ACCESSION NUR:8105190381 OVC~DATE:81/05/14NOTARIZED:
NOFACIL:50-387 Susquehanna SteamElectricStation,Unit1>Pennsylva 50-368Susquehanna SteamElectricStation~Unit2,Pennsylva AUTH~NAivifAUTHORAfFiLIATION CORTISi"l.WoPennsylvania PowerK,LightCo.RECIP.NAiwfRECIPItiV 1AFFILIATION YOUNGBLOODiB.J
~Licensing Branch1SUBJECT;Forwardssummaryofconformance w/iOCFR20I50 L100'onformance w/luCrRSO AppAisaiscussed inSection3.1ofFSAR~DISTRIBUTIUN CODE:8001SCOPIESRECEIVED:LTR ENCLSIZE::D8TITLE:PSALM/f.SAR AiiDTSandRelatedCorrespondence OOCKET0008iVOTES:Send IKE3copiesfSeR8allamends'cy.'BAR-LRG PN(CRIB)05000387SendISE3copiesFSAR4allamends.1cy'.BwR-LRG Ps(L.RIB) 05000388ACTIOiV;<ECIPIEN'1Ii)C00f/iVAt1fA/~L(CENSNGRUSHBROO<.~.
Ci)p'ESLTTRENCL100RfC[PIEivTIDCODE/NAi'lE LICRRa2BCSTARK,R,04CDPIESLTTRENCL101INTERNAL:
ACCIDEvALBR2>CH'ANEVGBRCO/EPERFBRf;,~IERGPREP22GEUSCIE>VCES 14wY>/GEOBR1514E-ObLICQUALiR,<ECHE,<GBRioNiRCPOR02OPLlCBRPROC/TSTRE,Y20"SBR22GOlSr<UCTENGBR2>11101311111111AuXSYSBR07CONTSYSBR09EFFTRSYSUR12EQUIPQUALuR13Hu<FACTENGuRI~CSYS.BRlbLICGUIOBRvIATLENGoR17,QPAOELOPOWERSYSBH19QABR21REACSYSl3R23SITAj~iALbR2411111131111111101011111111-XTERNAL:
ACRSNSlC27Oylvlb11LPOR03gAY23,1981515ITOTALNUWBEROFCOPIFSgE.~U<Rt.D:,
LTTR'bEivCL'54 iI PpalTWONORTHNINTHSTREET,ALLENTOWN, PA.18101PHONE:(215)821-5151NORMANW.CURTISVicePresident-Engineering
&Constructen 821.5381May14,1981Mr.B.J.Youngblood, ChiefLicensing BranchNo.1U.S.NuclearRegulatory Commission Washington, D.C.20555SUSQUEHANNA STEAMELECTRICSTATION10CFRCOMPLIANCE ER100450FILE841PLA-777DOCKETNOS,50-387AND50-388


==DearMr.Youngblood:==
==DearMr.Youngblood:==
InresponsetotheCommission'srequest,enclosedyouwillfindanitemizedreviewofthecomplianceofPennsylvaniaPowerandLightCompanyandtheSusquehannaSteamElectricStation,onits1and2to10CFR,Parts20,50and100.Pleasenotethatconformanceto10CFR50AppendixA,GeneralDesignCriteriaforNuclearPowerPlants,isdiscussedinSection3.1oftheFinalSafetyAnalysisReport(FSAR).Ifyouhaveanyquestionsontheencloseddocumentoranyofthereferencedmaterial,pleasecontactme.Verytrulyyours,N.3.CurtisVicePresident-EngineeringandConstruction-NuclearRRS/mkspoolAttachment(I(~~.>gzg~a3PENNSYLVANIAPOWER&LIGHTCOMPANY 4lI~4'I SUSQUEHANNASTEAMELECTRICSTATION,UNITS1AND2ASummaryofConformancetoNuclearRegulatoryCommissionRegulationsof10CZRParts20,50and100PennsylvaniaPower6LightCompanyMay1981


INTRODUCTIONThisdocumenthasbeenpreparedasasummaryoftheconformanceofSusquehannaSteamElectricStation(SSES)designandoperationtotheNRCregulationsof10CFRParts20,50and100.Thosesectionsofregulationswhichspecificallyimposecompliancerequirementsonlicenseesareaddressed.
InresponsetotheCommission's request,enclosedyouwillfindanitemizedreviewofthecompliance ofPennsylvania PowerandLightCompanyandtheSusquehanna SteamElectricStation,onits1and2to10CFR,Parts20,50and100.Pleasenotethatconformance to10CFR50AppendixA,GeneralDesignCriteriaforNuclearPowerPlants,isdiscussed inSection3.1oftheFinalSafetyAnalysisReport(FSAR).Ifyouhaveanyquestions ontheencloseddocumentoranyofthereferenced
II ENCLOSUREComLIANCEOFSUSqUEHANNASTEmELECTRICSTATIONUNITS1AND2WITHTHENRCREGULATIONSOF10CFRPARTS2050AND100Regulation(10CFR)20.1(c)~ComliaaceConformancetotheALARAprinciplestatedinthisregulationisensuredbytheimplementationofPPSLpoliciesandappropriateTechnicalSpecificationsandhealthphysicsprocedures.Chapterslland12oftheFSARdescribethespecificequipmentanddesignfeaturesutilizedinthiseffort.20.3ThedefinitionscontainedinthisregulationareadheredtoinallappropriateTechnicalSpecificationsandprocedures,andinapplicablesectionsoftheFSAR.20.4TheUnitsofRadiationDosespecifiedinthisregulationareacceptableandconformedtoinallapplicableSSESprocedures.20.5TheUnitsofRadioactivityspecifiedinthisregulationareacceptedandconformedtoinallapplicableSSESprocedures.20.101Theradiationdoselimitsspecifiedinthisregulationarecompliedwiththroughtheimplementationofandadherencetoadministrativepoliciesandcontrolsandappropriatehealthphysicsproceduresdevelopedforthispurpose.Conformanceisdocumentedbytheuseofappropriatepersonnelmonitoringdevicesandthemaintenanceofallrequiredrecords.(SeeFSARChapter12.)20.102Whenrequiredbythisregulation,theaccumula'teddoseforanyindividualpermittedtoexceedtheexposurelimitsspecifiedin20.101(a)isdeterminedbytheuseofFormNRC-4.Appropriatehealthphysicsproceduresandadministrativepoliciescontrolthisprocess.(SeeFSARChapter12.)20.103(a)Compliancewiththisregulationisensuredthroughtheimplementationofappropriatehealthphysicsproceduresrelatingtoairsamplingforradioactivematerials,andbioassayofindividualsforinternalcontamination.Administrativepoliciesandcontrolswillprovideadequatemarginsofsafetyfortheprotectionofindividualsagainsttheintakeof 0Id/
: material, pleasecontactme.Verytrulyyours,N.3.CurtisVicePresident-Engineering andConstruction-Nuclear RRS/mkspoolAttachment (I(~~.>gzg~a 3PENNSYLVANIA POWER&LIGHTCOMPANY 4lI~4'I SUSQUEHANNA STEAMELECTRICSTATION,UNITS1AND2ASummaryofConformance toNuclearRegulatory Commission Regulations of10CZRParts20,50and100Pennsylvania Power6LightCompanyMay1981
radioactivematerials.ThesystemsandequipmentdescribedinChapterslland12oftheFSARprovidethecapabilitytominimizethesehazards.20.103(b)(1)Thereactorbuildingventilationsystemisdesignedtoprovideameanstoreducetheconcentrationofparticulateandgaseouscontaminationtoassuresafecontinuousaccess(40hours/week)duringnormalreactorshutdown(FSAR,Sections12.3.3.1and12.5.3.2.3.1).Portableventilationsystems,hoods,andtestsareusedaspracticabletocontainandreduceairborneparticulateandgaseouscontaminationduringtheperformanceofvariousjobs.20.103(b)(2)EvaluationofairborneactivityinrestrictedareasisdiscussedintheevaluationofcompliancetoSection20.103-Paragraph(a)(l).IssuanceandSelectionofResiratoEuimentRadiationprotectionpersonnelatSSESwillselectappropriaterespiratoryequipmentsothatcontaminantconcentrationinhaledbythewearerdoesnotexceedtheappropriateregulatorylimitsspecifiedinAppendixB,TableI,Columnl.Shouldanindividualreceivegreaterthan40MPChoursin7consecutivedays,anevaluationwillbemadetoidentifythecauseandactionswillbetakentopreventrecurrence.Recordswillbemaintainedforeachoccurrence.20.103(c)RadiationprotectionpersonnelatSSESwillselectappropriaterespiratoryequipmentsothatcontaminantconcentrationinhaledbythewearerdoesnotexceedtheappropriateregulatorylimits.TheprotectionfactorsusedatSSEScomplywiththeprotectionfactorspermittedunderRegulatoryGuide8.15.20.103(e)a(f)SSESisincompliancewith10CFR20.103-Paragraph(c)andthereforeisexemptfromtherequirementsofParagraph(e).20'04ConformancewiththisregulationisassuredbyappropriatePPGLpoliciesregardingemploymentofindividualsundertheageof18andtheSSESAdministrativeProceduresrestrictingtheseindividuals'ccesstorestrictedareas.
20..105(a)Chapters11and12oftheFSARprovidetheinformationandrelatedradiationdoseassessmentsspecifiedbythisregulation.20.105(b)TheradiationdoseratelimitsspecifiedinthisregulationwillbecompliedwiththroughtheimplementationofSSESprocedures,TechnicalSpecifications,andadministrativepolicieswhichcontroltheuseandtransferofradioactivematerials.Appropriatesurveysandmonitoringdeviceswilldocumentthiscompliance.20.106(a)ConformancewiththelimitsspecifiedinthisregulationwillbeassuredthroughtheimplementationofSSESproceduresandapplicableTechnicalSpecificationswhichprovideadequatesamplingandanalyses,andmonitoringofradioactivematerialsineffluentsbeforeandduringtheirrelease.Thelevelofradioactivityinstationeffluentswillbeminimizedtotheextentpracticablebytheuseofappropriateequipmentdesignedforthispurpose,asdescribedinChapter11of=theFSAR.20.106(b)20.106(c)PPRLhasnotanddoesnotcurrentlyintendtoincludeinanylicenseoramendmentapplicationsproposedlimitshigherthanthosespecifiedin20.106(a),asprovidedintheseregulations.20.106(d)Appropriateallowancesfordilutionanddispersionofradioactiveeffluentswillbemadeinconformancewiththisregulation,andaredescribedindetailinChapterlloftheFSAR,andinSections3/4.11and3/4.12oftheTechnicalSpecifications.20.108Necessarybioassayequipmentandprocedures,includingWholeBodyCounting,willbeutilizedtodetermineexposureofindividualstoconcentrationsofradioactivematerials.Appropriatehealthphysicsproceduresandadministrativepoliciesimplementthisrequirement.(SeeFSARChapter12.)20.201Thesurveysrequiredbythisregulationwillbeperformedatadequatefrequenciesandcontainsuchdetailastobeconsistentwiththeradiationhazardbeingevaluated.Whennecessary,theRadiationWorkPermitsystemestablishedatthestationprovidesfordetailedphysicalsurveysofequipment,structuresandworksitestodetermineappropriate levelsofradiationprotection.TheSSESAdminis-trativeProceduresandapplicablehealthphysicsprocedureswillrequirethesesurveysandprovide~fortheirdocumentationinsuchmannerastoensurecompliancewiththeregulationsof10CFRPart20.(SeeFSARChapter12.)20.202(a)TheSSESAdministrativeProceduresandapplicablehealthphysicsprocedureswillsetforthpoliciesandpracticeswhichensurethatallindividualsaresuppliedwith,andrequiredtouse,appropriatepersonnelmonitoringequipment.TheRadiationWorkPermitsystemwillbeestablishedtoprovideadditionalcontrolofpersonnelworkinginradiationareasandtoensurethatthelevelofprotectionaffordedtotheseindividualsisconsistentwiththe'adiologicalhazardsintheworkplace.(SeeFSARChapter12.)20.202(b)20.203(a)TheterminologysetforthinthisregulationwillbeacceptedandconformedtoinallapplicableSSEShealthphysicsprocedures,TechnicalSpecifications,andthoseSSESAdministrativeProceduresinwhichitsuseismade.Allmaterialsusedforlabeling,posting,orotherwisedesignatingradiationhazardsorradioactivematerials,andusingtheradiationsymbol,conformtotheconventionaldesignprescribedinthisregulationperSSESprocedures.20.203(b)ThisregulationwillbeconformedtothroughtheimplementationofappropriatehealthphysicsproceduresandportionsoftheSSESAdministrativeProceduresrelatingtopostingofradiationareas,asdefinedin10CFRPart,20.202(b)(2).20.203(c)Therequirementsofthisregulationfor"HighRadiationAreas"willbeconformedtobytheimplementationoftheSSESTechnicalSpecificationsandappropriateplanthealthphysicsprocedures,aswellastheSSESAdministrativeProcedures.ThecontrolsandotherprotectivemeasuressetforthintheregulationaremaintainedunderthesurveillanceoftheSSESHealthPhysicsgroup.ItshouldbenotedthatTechnicalSpecification6.12.1willprovidealternateaccesscontrolmethodstobeapplied"inlieuofthe'controldevice'r'alarmsignal'equiredbyParagraph20.203(c)(2)of10CFR20,"whichwillpreventunauthorizedentryintoahighradiationarea.
20.203(d)EachAirborneRadioactivityArea,asdefinedinthisregulation,willberequiredtobepostedbyprovisionsoftheSSESAdministrativeProceduresandappropriatehealthphysicsprocedures.Theseproceduresalsoprovideforthesurveillancerequirementsnecessarytodetermineairborneradioactivitylevels.20.203(e)Theareaandroompostingrequirementssetforthinthisregulationpertainingtoradioactivematerialswillbecompliedwiththroughtheimplementationofappropriatehealthphysicsprocedures,andSSESAdministrativeProcedures.20.203(f)Thecontainerlabelingrequirementssetforthinthisregulationwillbecompliedwiththroughtheimplementationofappropriatehealthphysicsprocedures,andportionsoftheSSESAdministrativeProcedures.20.204ThepostingrequirementexceptionsdescribedinthisregulationareusedwhereappropriateandnecessaryatSSES.AdequatecontrolsareprovidedwithintheSSEShealthphysicsprocedurestoensuresafeandproperapplicationoftheseexceptions.20.205Alloftherequirementsofthisregulationpertainingtoproceduresforpickingup,receiving,andopeningpackagesofradioactivematerialswillbeimplementedbytheSSESAdministrativeProceduresandappropriatehealthphysicsprocedures.Theseproceduresalsoprovideforthenecessarydocumentationtoensureanauditablerecordofcompliance.(SeeFSARChapter12.)20.206TherequirementsoflOCFR19.12referredtobythisregulationaresatisfiedbytheradiationworkertrainingconductedatSSES.Appropriatehealthphysicsproceduressetforthrequirementsforallradiationworkerstoreceivethisinstructiononaperiodicbasis.(SeeFSARChapter12.)20.207LicensedmaterialsarenotstoredoutsideoftherestrictedareasatSSES.20.301ThegeneralrequirementsforwastedisposalsetforthinthisregulationarecompliedwiththroughSSEShealthphysicsprocedures,theTechnicalSpecifications,andtheprovisionsofthestationlicense.Chapter11oftheFSARdescribestheSolidVasteDisposalSysteminstalledatSSES.
20.302Nosuchapplicationforproposeddisposalprocedures,asdescribedinthisregulation,hasbeenmadeoriscurrentlycontemplatedatPPSL.20'03Noplansforwastedisposalbyreleaseintosanitaryseweragesystems,asprovidedforinthisregulation,arecontemplatedbySSES,noristhispracticecurrentlyutilized.20.305SpecificAuthorization,asdescribedinthisregulation,isnotcurrentlybeingsoughtbyPPSLfortreatmentordisposalofwastesbyincineration.20.401AlloftherequirementsofthisregulationwillbecompliedwiththroughtheimplementationofappropriateTechnicalSpecificationsandhealthphysicsprocedurespertainingtorecordsofsurveys,radiationmonitoringandwastedisposal.Theretentionperiodsspecifiedforsuchrecordsarealsoprovidedforinthesespecificationsandprocedures.(SeeFSARChapter12.)20.402SSEShasestablishedanappropriateinventoryandcontrolprogramtoensurestrictaccountabilityforalllicensedradioactivematerials.Reportsoftheftorlossoflicensedmaterialwillberequiredbyreferencetotheregulationsof10CFRintheTechnicalSpecifications.20.403Notificationsofincidents,asdescribedinthisregulationwillbeassuredbytherequirementsoftheTechnicalSpecifications,theSSESAdministrativeProceduresandappropriateplantprocedures,whichalsoprovideforthenecessaryassessmentstodeterminetheoccurrenceofsuchincidents.20.405Reportsofoverexposurestoradiationandtheoccurrenceofexcessivelevelsandconcentrations,asrequiredbythisregulation,willbeprovidedforbyreferenceintheTechnicalSpecificationsandinappropriatehealthphysicsprocedures.20.407ThepersonnelmonitoringreportrequiredbythisregulationwillbeexpresslyprovidedforbytheTechnicalSpecifications.Appropriatehealthphysicsproceduresestablishthedatabasefromwhichthisreportisgenerated.(SeeFSARChapter12.)
20.408Thereportofradiationexposurerequiredbythisregulationuponterminationofanindividual'semploymentorworkassignmentisgeneratedthroughtheprovisionsofthehealthphysicsprocedure.20.409Thenotificationandreportingrequirementsofthisregulation,andthosereferredtobyit,aresatisfiedbytheprovisionsofthehealthphysicsprocedure.50.30Thisregulationsetsdownproceduralrequirementsforthefilingoflicenseapplications.PPMhascompliedwiththeproceduralrequirementsineffectatthetimewhenfilingitslicenseapplicationandtheamendmentstoit.50.33Thisregulationrequiresthelicenseapplicationtocontaincertaingeneralinformation,suchasanidentificationoftheapplicant,informationabouttheapplicant'sfinancialqualifications,andalistofregulatoryagencieswithjurisdictionovertheapplicant'sratesandservices.ThisinformationwasprovidedintheSSESoperatinglicenseapplication.50.34a(c)Thedescriptionsrequiredpursuantto50.34a(a)arepresentedinChapter11oftheFSAR.TheOperatingLicenseStageEnvironmentalReportprovidestheexpectedreleaseinformationrequired.50.34(b)TheSSESFinalSafetyAnalysisReport(FSAR)wasinitiallysubmittedonApril10,1978andwasdocketed(Nos.50-387/388)onJuly31,1978pursuanttoSection50.34of10CFR50.ThisdocumentanditsnumerousamendmentshavebeenundergoingreviewbytheNRCanditsstaff.50.34(c)ThephysicalsecurityplanforSSESwassubmittedtotheNuclearRegulatoryCommission(NRC)inApril1978withthemostrecentamendmentsubmittedApril8,1981.ThisplanispresentlyundergoingNRCreview.50.34(d)TheSafeguardsContingencyplanforSSESwassubmittedtotheNRConJuly11,1980'hisplanwasmostrecentlyamendedonApril8,1981andispresentlyundergoingNRCreview.
50.36(a)6(b)TheSSESapplicationsforoperatinglicensesincorporatethetechnicalspecificationsrequirementsof10CFR50.36-Paragraphs(a)and(b).DraftsofthesetechnicalspecificationsareundergoingNRCreview.50.36(c)Alloftheabovelistedcategoriesarecontainedinthecurrentdrafttechnicalspecifications.Thetechnicalspecificationswillbea"living"document.Amendments,therefore,willbenecessarytomaintainthedocumentcurrentwithNRCrequirements,aswellaswithplantmodificationsforimprovedoperations.50.36aTheSSESFSAR,Section12.1,includesconsiderationswhichrequirecompliancewith10CFR50.34a(releasesaslowasisreasonableachievable),andtheSSESTechnicalSpecifications,Sec.3/4.11ensurethatconcentrationsofradioactiveeffluentsreleasedtounrestrictedareasarewithinthelimitsspecifiedin10CFR20.106.Thereportingrequirementsof10CFR50.36a(a)(2)arecompliedwiththroughappropriateSSESprocedures.50.37Thisregulationrequirestheapplican'ttoagreetolimitaccesstoRestrictedData.Applicantcomplianceisinherenttotheoperatinglicenseapplication"whethersostatedthereinornot."50.38ThisregulationprohibitstheNRCfromissuingalicensetoforeign-controlledentities.PPGL'sstatementthatitisnotowned,controlled,ordominatedbyanalien,foreigncorporation,orforeigngovernmentisintheoperatingli'censeapplicationfortheSusquehannaSteamElectricStation.50.40Thisregulationprovidesconsiderationsto"guide"theCommissioningrantinglicensesasfollows:50.40(a)ThedesignandoperationofthefacilityistoprovidereasonableassurancethattheapplicantwillcomplywithNRCregulations,includingthosein10CFRPart20,andthatthehealthandsafetyofthepublicwillnotbeendangered.ThebasisforPPM'sassurancethattheregulationswillbemetandthepublicprotectediscontainedinthisenclosureandinthelicenseapplicationandtherelatedcorrespondenceovertheyears.Moreover,thelengthyprocessbywhichtheplantisdesigned,constructed,andreviewed,includingreviewsby


PPGL'sstaff,theNRCstaff,theACRS,andNRClicensingboards,providesagreatdealofassurancethatthepublichealthandsafetywillnotbeendangered.Inparticular,theAtomicSafetyandLicensingBoard,afteranextensivereview,concludedthatPPGLhadthecommitmentandtechnicalqualificationsnecessarytooperateSusquehannaSteamElectri'cStationsafetyandincompliancewithallapplicableradiologicalhealthandsafetyrequirements.Anotherconsiderationisthattheapplicantbetechnicallyandfinanciallyqualified.BothPPGL'stechnicalqualificationsanditsfinancialqualificationswerereviewedinhearingsbeforetheAtomicSafetyandLicensingBoard.Anotherconsiderationisthattheissuanceofthelicenseisnottobeinimicaltothecommondefenseandsecurityortothehealthandsafetyofthepublic.Theindividualshowingsofcompliancewithparticularregulationscontainedinthisenclosure,aswellasthecontentsoftheentireFSARandrelatedcorrespondenceovertheyears,plusthelengthyprocessofdesign',construction,andreviewbyPAL,itsNSSSvendor,andthegovernment,providePPMwithconsiderableassurancethatthelicensewillnotbeinimicaltothehealthandsafetyofthepublic.Asforthecommondefenseandthesecurity,thereisconsiderableassurancethatthelicensewillnotbeinimicalinthatPP&LhasanapprovedsecurityplanforSusquehannaSteamElectricStation,thatPPGLisnotcontrolledbyagentsofforeigncountries,'andthatPPGLhasagreedtolimitaccesstoRestrictedData.Thefinal50.40"consideration"isthattheapplicablerequirementsofPart51havebeensatisfied.Part51concernscompliancewiththeNationalEnvironmentalPolicyActof1969.PPGIhassubmittedaFinalEnvironmentalReportandtheNRCstaffisreviewingthereportandwillpublishafinalEnvironmentalImpactStatementpursuantto10CFR51.EnvironmentalTechnicalSpecificationsarepending.ThisregulationappliestoClass104licensees,suchasthosefordevicesusedinmedicaltherapy.SusquehannaSteamElectricStationhasnotappliedforaClass104license,andso50.41isnotapplicable.10 Section50.42providesadditional"considerations"to"guide"theCommissioninissuingClass103licenses.Thetwoconsiderationsare:(a)thattheproposedactivitieswillserveausefulpurposeproportionatetothequantitiesofspecialnuclearmaterialorsourcematerialtobeutilizedand(b)thatdueaccountwillbetakenoftheantitrustadviceprovidedbytheAttorneyGeneralundersubsection105coftheAtomicEnergyAct.The"usefulpurpose"tobeservedistheproductionofelectricpower.Theneedforthepowerwasdeterminedbythelicensingboardattheconstructionpermitstage.Althoughconditionsaffectingtheneedforpowerareconstantlychanging,PPGLperiodicallymakesloadprojections,andinPPGL'sjudgementtheneedforSusquehannaSteamElectricStationisstillsubstantial.Asfortheamountofspecialnuclearmaterialorsourcematerialused,thereisnoreasontobelievethattheirproportioninrelationtothepowerproducedissubstantiallygreaterthanthatofothercommercialpowerreactorsinthiscountry.TheNRCispresentlyundertakingtheantitrustreviewfor~SSESand'asnotyetinformedtheapplicantofitsconclusions.CompliancewithParagraphs(a)through(e)isdiscussedindetailinFSARSection6.2.5.Paragraph(f)isnotapplicable,sincetheconstructionpermitforSSESwaspublishedafterNovember5,1970.Paragraph(g)isnotapplicable,sincethenoticeofhearingontheapplicationfortheconstructionpermitforSSESwaspublishedafterDecember22,1968.Asdiscussedabove,thecombustiblegascontrolsystemsforSSESmeettherequirementsof10CFR50.44.Compliancewith10CFR50.46isdocumentedintheFSAR,Section6.3.3.ThisanalysisshowsthatSSESmeets10CFR50.46criteriaandtheECCSequipmentwillperformitsfunctioninanacceptablemanner.Compliancewith10CFR50.48isdocumentedthroughthePPMCompanyFireProtectionReviewReportforSSES.,ThisreportisinRevision1andwassubmittedtotheNRCforreview'inMarch,1981.11 50.5150.53Thisregulationspecifiesthemaximumdurationoflicenses.CompliancewillbeaffectedsimplybytheCommission'swritingthelicensesoastocomply.I'hisregulationprovidesthatlicensesarenottobeissuedforactivitiesthatarenotunderorwithinthejurisdictionoftheUnitedStates.TheoperationofSusquehannaSteamElectricStationwillbewithintheUnitedStatesandsubjecttothejurisdictionoftheUnitedStates,asisevidentfromthedescriptionofthefacilityintheoperatinglicenseapplic'ation.50.54Thisregulationspecifiescertainconditionsthatareincorporatedineverylicenseissued.Complianceiseffectedsimplybyincludingtheseconditionsinthelicensewhenitisissued.Indeed,muchof50.54merelyprovidesthatotherprovisionsofthelawapply,whichwouldbethecaseevenwithout50.54.50.55a(a)(1)VariouschaptersoftheFSARdiscussdesign,fabrication,erection,construction,testing,andinspectionofsafety-relatedequipment.Forexample,Chapter14providesinformationontestingofsafety-relatedsystems.Chapter17providesinformationconcerningthe(}ualityAssuranceProgramthatwasutilized.Asafurtherexampleofaspecificsystem,Chapter5,Section5.2,"IntegrityoftheReactorCoolantPressureBoundary,"discussesthedesignofthereactorcoolantsystem.50.55a(a)(2)ThisparagraphisageneralparagraphleadingintoParagraphs(c)through(i)oftheregulation.50.55a(b)(l)50.55a(b)(2)TheseparagraphsprovideguidanceconcerningtheapprovedEditionandAddendaofSectionIIIandXIoftheASMEBSPVCode.50.55a(c)DesignandfabricationofthereactorvesselwascarriedoutinaccordancewithASMESectionIII(1968)ClassAincludingAddendathroughSummer1970.InformationcanbefoundinChapters3and5oftheFSAR.50.55a(d)ReactorcoolantsystempipingmeetstherequirementsofASMESectionIII(1971)Class1.InformationcanbefoundinChapters3and5oftheFSAR.12 50.55a(e)PumpswhicharepartofthereactorcoolantpressureboundarymeettherequirementsofASMESectionIII(1971).InformationcanbefoundinChapters3and5oftheFSAR.50.55a(f)ThevalveswhicharepartofthereactorcoolantpressureboundaryweredesignedandfabricatedinaccordancewiththerequirementsofASMESection,III,1971edition.(SeeFSARChapters3and5.)50.55a(g)InserviceInspection(ISI)requirementsaredelineatedinthispartandarespecifiedintheTechnicalSpecifications,Paragraph4.0.5.AspermittedbythispartandtheTechnicalSpecifications,certainexemptionshavebeenrequestedfortheinserviceinspectionofvarioussystemsandtheinservicetestingofvariouspumpsandvalves.ThesereliefrequestsweresubmittedtotheNRCasasupplementtotheSSESInserviceInspectionProgramforpumpsandvalvesinaletterdatedMarch20,1981.50.55a(h)50.55a(i)AsdiscussedinFSARChapter7,theprotectionsystemsmeetIEEE279-1971.FracturetoughnessrequirementsaresetforthinAppendicesGandHof10CFR50.TechnicalSpecificationsrequiretheuseofreactorvesselmaterialirradiationsurveillancespecimensandupdatingofthe"heatup"and"cooldown"curvesgivenintheTechnicalSpecifications'urtherinformationonthissubjectisgiveninChapter5oftheFSAR.50.56ThisregulationprovidesthattheCommissionwill,intheabsenceofgoodcauseshowntothecontrary,issueanoperatinglicenseuponcompletionoftheconstructionofafacilityincompliancewiththetermsandconditionsoftheconstructionpermit.Thisimposesnoindependentobligationsontheapplicant.50.58ThisregulationprovidesforthereviewandreportoftheAdvisoryCommitteeonReactorSafeguards.TheACRSisreviewingtheoperatinglicenseapplicationforSSESinaccordancewithitsusualpractice.13 50.59TheSusquehannaReviewCommitteeshallreview:aThesafetyevaluationfor1)changestoprocedures,equipment,orsystems,and2)testsorexperimentscompletedundertheprovisionof10CFR50.59toverifythatsuchactionsdidnotconstituteanunreviewedsafetyquestion;b.Proposedchangestoprocedures,equipmentorsystemswhichinvolveanunreviewedsafetyquestionasdefinedinlOCFR50.59;andc.Proposedtestsorexperimentswhichinvolveanunreviewedsafetyquestionasdefinedin10CFR50.59.TheSRCshallreporttoandadvisetheSeniorVicePresident-Nuclearoftheiractivities.Safetyevaluationsofchangesmadetotheequipmentorreviewoftestsandexperimentstocomplywith10CFR50.59shallbekeptinamannerconvenientforreviewandshallberetainedforatleastfiveyears.SSESwillcomplywiththereportingrequirementssetforthin10CFR50.59.50.70TheCommissionhasassignedresidentinspectorstotheSSES.PPScLhasprovidedofficespaceinaccordancewiththerequirementsofthissection.PP&LpermitsaccesstothestationtoNRCinspectorsinaccordancewith10CFR50.70(b)(3).50.71RecordsareandwillbemaintainedinaccordancewiththerequirementsofParagraphs(a)through(e)ofthisregulationandthelicense.Paragraph(e)requiresthattheFSARbeupdated(within24monthsoftheissuanceoftheoperatinglicenseandannuallythereafter).SuchupdateswillbemadeinaccordancewiththisSection.50.72NotificationofsignificanteventstotheNRCwillbemadeinaccordancewiththisregulation.AppendixAThedetailsofSSEScompliancewithGeneralDesignCriteriaisdiscussedindetailintheFSAR,Section3.1.AppendixBChapter17oftheFSARdescribesindetailtheprovisionsofthequalityassuranceprogramwhich14 hasbeenimplementedtomeetallapplicablerequirementsofAppendixB.AppendixECompliancewith10CFR50,AppendixE,isdocumentedthroughthePPGLCompanyEmergencyPlanforSSES.ThisplanincorporatestherequirementsofNUREG0654exceptforsomechangeswithrespecttoTableB-1.ThesechangesarepresentlybeingreviewedbytheNRCstaff.TheplanhasbeenunderrevisionandwassubmittedtotheNRConApril28,1981.AppendicesG,HCompliancewithAppendicesGandHcannotbeevaluatedatthistime.InordertoanswerNRCquestionsintheseareas,PPM.hasrequestedanevaluationbyGeneralElectric.PPSLexpectstoreceivethenecessaryinformationbyMay21,1981.Itistheintentoftheevaluationtoshowcompliancewiththeseregulations.AppendixIThisAppendixprovidesnumericalguidesfordesignobjectivesandlimitingconditionsforoperationtomeetthecriteria"aslowasisreasonablyachievable"forradioactivematerialinlight-water-coolednuclearpowerreactoreffluents,PPGLhasfiledwiththeCommissionthenecessaryinformationtopermitanevaluationoftheSSESwithrespecttotherequirementsofSctionII.A,II.B,andII.CofAppendixI.TheSSESapplicationforconstructionpermitwasdocketedafterJanuary2,1971andpriortoJune4,1976.Nocost-benefitanalysisisrequired.AllcalculateddosesarewithintheAppendixIof10CFR50guidelines.AppendixJReactorpressureboundaryleakagetestingforwatercooledpowerreactorsisdelineatedinthisAppendix.TheserequirementsaregiveninTechnicalSpecification3/4.6.1.AdditionalinformationconcerningcompliancecanbefoundinFSARChapters3and6.AppendixKCompliancewith10CFR50AppendixKisspecificallyrequiredby10CFR50~46'SCScomplianceisdocumentedinSection6.3.3oftheSSESFSAR.NEDO-20566providesacompletedescriptionofthemethodsusedtoperformthecalculations.100.10Thefactorslistedrelatedtoboththeunitdesignandthesitehavebeenprovidedintheapplication.Sitespecifics,includingseismology,meteorology,geology,andhydrology,,arepresentedinChapter215 oftheFSAR.Theexclusionarea,lowpopulationzone,andpopulationcenterdistanceareprovidedanddescribed.TheFSARalsodescribesthecharacteristicsofreactordesignandoperation.100.11Theexclusionarea,lowpopulationzoneandpopulationcenterdistancearedescribedintheFSAR,Chapter2.Allrequirementsofthissectionwithregardtotheseareasanddistancesaremet.TheFSARaccidentanalyses,particularlythoseinChapters6and15,demonstratethatoffsitedosesresultingfrompostulatedaccidentswouldnotexceedthecriteriainthissectionoftheregulation.AppendixAStructuresandequipmentimportanttoplantsafetyareprotectedfromordesignedtowithstandallappropriatenaturalphenomenaattheplantsite.Designisbasedonthemostseverephenomenaprobablewithspecialconsiderationfortheuncertaintyinprediction.Detaileddiscussionsofthephenomenathemselves,andhowtheyareappliedtothestructuresandequipment,arefoundinthefollowingFSARsections:Meteorology,Section2.3;Hydrology,Section2.4;Geology,Seismology,andGeotechnicalEngineering,Section2.5;ClassificationofStructures,Components,andSystems,Section3.2;WindandTornadoLoadings,Section3.3;Wateri,evel(Flood)Design,Section3.4;MissileProtection,Section3.5;SeismicDesign,Section3.7;DesignofCategoryIStructures,Section3.8;MechanicalSystemsandComponents,Section3.9;SeismicQualificationsofCategoryIinstrumentationandElectricalEquipment,Section3.10;andEnvironmentalDesignofMechanicalandElectricalEquipment,Section3.11.,8C/cak}}
INTRODUCTION Thisdocumenthasbeenpreparedasasummaryoftheconformance ofSusquehanna SteamElectricStation(SSES)designandoperation totheNRCregulations of10CFRParts20,50and100.Thosesectionsofregulations whichspecifically imposecompliance requirements onlicensees areaddressed.
II ENCLOSURE ComLIANCE OFSUSqUEHANNA STEmELECTRICSTATIONUNITS1AND2WITHTHENRCREGULATIONS OF10CFRPARTS2050AND100Regulation (10CFR)20.1(c)~ComliaaceConformance totheALARAprinciple statedinthisregulation isensuredbytheimplementation ofPPSLpoliciesandappropriate Technical Specifications andhealthphysicsprocedures.
Chapterslland12oftheFSARdescribethespecificequipment anddesignfeaturesutilizedinthiseffort.20.3Thedefinitions contained inthisregulation areadheredtoinallappropriate Technical Specifications andprocedures, andinapplicable sectionsoftheFSAR.20.4TheUnitsofRadiation Dosespecified inthisregulation areacceptable andconformed toinallapplicable SSESprocedures.
20.5TheUnitsofRadioactivity specified inthisregulation areacceptedandconformed toinallapplicable SSESprocedures.
20.101Theradiation doselimitsspecified inthisregulation arecompliedwiththroughtheimplementation ofandadherence toadministrative policiesandcontrolsandappropriate healthphysicsprocedures developed forthispurpose.Conformance isdocumented bytheuseofappropriate personnel monitoring devicesandthemaintenance ofallrequiredrecords.(SeeFSARChapter12.)20.102Whenrequiredbythisregulation, theaccumula'ted doseforanyindividual permitted toexceedtheexposurelimitsspecified in20.101(a) isdetermined bytheuseofFormNRC-4.Appropriate healthphysicsprocedures andadministrative policiescontrolthisprocess.(SeeFSARChapter12.)20.103(a)
Compliance withthisregulation isensuredthroughtheimplementation ofappropriate healthphysicsprocedures relatingtoairsamplingforradioactive materials, andbioassayofindividuals forinternalcontamination.
Administrative policiesandcontrolswillprovideadequatemarginsofsafetyfortheprotection ofindividuals againsttheintakeof 0Id/
radioactive materials.
Thesystemsandequipment described inChapterslland12oftheFSARprovidethecapability tominimizethesehazards.20.103(b)(1)Thereactorbuildingventilation systemisdesignedtoprovideameanstoreducetheconcentration ofparticulate andgaseouscontamination toassuresafecontinuous access(40hours/week) duringnormalreactorshutdown(FSAR,Sections12.3.3.1and12.5.3.2.3.1).
Portableventilation systems,hoods,andtestsareusedaspracticable tocontainandreduceairborneparticulate andgaseouscontamination duringtheperformance ofvariousjobs.20.103(b)(2)Evaluation ofairborneactivityinrestricted areasisdiscussed intheevaluation ofcompliance toSection20.103-Paragraph (a)(l).IssuanceandSelection ofResiratoEuimentRadiation protection personnel atSSESwillselectappropriate respiratory equipment sothatcontaminant concentration inhaledbythewearerdoesnotexceedtheappropriate regulatory limitsspecified inAppendixB,TableI,Columnl.Shouldanindividual receivegreaterthan40MPChoursin7consecutive days,anevaluation willbemadetoidentifythecauseandactionswillbetakentopreventrecurrence.
Recordswillbemaintained foreachoccurrence.
20.103(c)
Radiation protection personnel atSSESwillselectappropriate respiratory equipment sothatcontaminant concentration inhaledbythewearerdoesnotexceedtheappropriate regulatory limits.Theprotection factorsusedatSSEScomplywiththeprotection factorspermitted underRegulatory Guide8.15.20.103(e)a(f)SSESisincompliance with10CFR20.103
-Paragraph (c)andtherefore isexemptfromtherequirements ofParagraph (e).20'04Conformance withthisregulation isassuredbyappropriate PPGLpoliciesregarding employment ofindividuals undertheageof18andtheSSESAdministrative Procedures restricting theseindividuals'ccess torestricted areas.
20..105(a)
Chapters11and12oftheFSARprovidetheinformation andrelatedradiation doseassessments specified bythisregulation.
20.105(b)
Theradiation doseratelimitsspecified inthisregulation willbecompliedwiththroughtheimplementation ofSSESprocedures, Technical Specifications, andadministrative policieswhichcontroltheuseandtransferofradioactive materials.
Appropriate surveysandmonitoring deviceswilldocumentthiscompliance.
20.106(a)
Conformance withthelimitsspecified inthisregulation willbeassuredthroughtheimplementation ofSSESprocedures andapplicable Technical Specifications whichprovideadequatesamplingandanalyses, andmonitoring ofradioactive materials ineffluents beforeandduringtheirrelease.Thelevelofradioactivity instationeffluents willbeminimized totheextentpracticable bytheuseofappropriate equipment designedforthispurpose,asdescribed inChapter11of=theFSAR.20.106(b) 20.106(c)
PPRLhasnotanddoesnotcurrently intendtoincludeinanylicenseoramendment applications proposedlimitshigherthanthosespecified in20.106(a),
asprovidedintheseregulations.
20.106(d)
Appropriate allowances fordilutionanddispersion ofradioactive effluents willbemadeinconformance withthisregulation, andaredescribed indetailinChapterlloftheFSAR,andinSections3/4.11and3/4.12oftheTechnical Specifications.
20.108Necessary bioassayequipment andprocedures, including WholeBodyCounting, willbeutilizedtodetermine exposureofindividuals toconcentrations ofradioactive materials.
Appropriate healthphysicsprocedures andadministrative policiesimplement thisrequirement.
(SeeFSARChapter12.)20.201Thesurveysrequiredbythisregulation willbeperformed atadequatefrequencies andcontainsuchdetailastobeconsistent withtheradiation hazardbeingevaluated.
Whennecessary, theRadiation WorkPermitsystemestablished atthestationprovidesfordetailedphysicalsurveysofequipment, structures andworksitestodetermine appropriate levelsofradiation protection.
TheSSESAdminis-trativeProcedures andapplicable healthphysicsprocedures willrequirethesesurveysandprovide~fortheirdocumentation insuchmannerastoensurecompliance withtheregulations of10CFRPart20.(SeeFSARChapter12.)20.202(a)
TheSSESAdministrative Procedures andapplicable healthphysicsprocedures willsetforthpoliciesandpractices whichensurethatallindividuals aresuppliedwith,andrequiredtouse,appropriate personnel monitoring equipment.
TheRadiation WorkPermitsystemwillbeestablished toprovideadditional controlofpersonnel workinginradiation areasandtoensurethatthelevelofprotection affordedtotheseindividuals isconsistent withthe'adiological hazardsintheworkplace.(SeeFSARChapter12.)20.202(b) 20.203(a)
Theterminology setforthinthisregulation willbeacceptedandconformed toinallapplicable SSEShealthphysicsprocedures, Technical Specifications, andthoseSSESAdministrative Procedures inwhichitsuseismade.Allmaterials usedforlabeling, posting,orotherwise designating radiation hazardsorradioactive materials, andusingtheradiation symbol,conformtotheconventional designprescribed inthisregulation perSSESprocedures.
20.203(b)Thisregulation willbeconformed tothroughtheimplementation ofappropriate healthphysicsprocedures andportionsoftheSSESAdministrative Procedures relatingtopostingofradiation areas,asdefinedin10CFRPart,20.202(b)(2).
20.203(c)
Therequirements ofthisregulation for"HighRadiation Areas"willbeconformed tobytheimplementation oftheSSESTechnical Specifications andappropriate planthealthphysicsprocedures, aswellastheSSESAdministrative Procedures.
Thecontrolsandotherprotective measuressetforthintheregulation aremaintained underthesurveillance oftheSSESHealthPhysicsgroup.ItshouldbenotedthatTechnical Specification 6.12.1willprovidealternate accesscontrolmethodstobeapplied"inlieuofthe'controldevice'r'alarmsignal'equired byParagraph 20.203(c)(2) of10CFR20,"
whichwillpreventunauthorized entryintoahighradiation area.
20.203(d)
EachAirborneRadioactivity Area,asdefinedinthisregulation, willberequiredtobepostedbyprovisions oftheSSESAdministrative Procedures andappropriate healthphysicsprocedures.
Theseprocedures alsoprovideforthesurveillance requirements necessary todetermine airborneradioactivity levels.20.203(e)
Theareaandroompostingrequirements setforthinthisregulation pertaining toradioactive materials willbecompliedwiththroughtheimplementation ofappropriate healthphysicsprocedures, andSSESAdministrative Procedures.
20.203(f)
Thecontainer labelingrequirements setforthinthisregulation willbecompliedwiththroughtheimplementation ofappropriate healthphysicsprocedures, andportionsoftheSSESAdministrative Procedures.
20.204Thepostingrequirement exceptions described inthisregulation areusedwhereappropriate andnecessary atSSES.AdequatecontrolsareprovidedwithintheSSEShealthphysicsprocedures toensuresafeandproperapplication oftheseexceptions.
20.205Alloftherequirements ofthisregulation pertaining toprocedures forpickingup,receiving, andopeningpackagesofradioactive materials willbeimplemented bytheSSESAdministrative Procedures andappropriate healthphysicsprocedures.
Theseprocedures alsoprovideforthenecessary documentation toensureanauditable recordofcompliance.
(SeeFSARChapter12.)20.206Therequirements oflOCFR19.12 referredtobythisregulation aresatisfied bytheradiation workertrainingconducted atSSES.Appropriate healthphysicsprocedures setforthrequirements forallradiation workerstoreceivethisinstruction onaperiodicbasis.(SeeFSARChapter12.)20.207Licensedmaterials arenotstoredoutsideoftherestricted areasatSSES.20.301Thegeneralrequirements forwastedisposalsetforthinthisregulation arecompliedwiththroughSSEShealthphysicsprocedures, theTechnical Specifications, andtheprovisions ofthestationlicense.Chapter11oftheFSARdescribes theSolidVasteDisposalSysteminstalled atSSES.
20.302Nosuchapplication forproposeddisposalprocedures, asdescribed inthisregulation, hasbeenmadeoriscurrently contemplated atPPSL.20'03Noplansforwastedisposalbyreleaseintosanitaryseweragesystems,asprovidedforinthisregulation, arecontemplated bySSES,noristhispracticecurrently utilized.
20.305SpecificAuthorization, asdescribed inthisregulation, isnotcurrently beingsoughtbyPPSLfortreatment ordisposalofwastesbyincineration.
20.401Alloftherequirements ofthisregulation willbecompliedwiththroughtheimplementation ofappropriate Technical Specifications andhealthphysicsprocedures pertaining torecordsofsurveys,radiation monitoring andwastedisposal.
Theretention periodsspecified forsuchrecordsarealsoprovidedforinthesespecifications andprocedures.
(SeeFSARChapter12.)20.402SSEShasestablished anappropriate inventory andcontrolprogramtoensurestrictaccountability foralllicensedradioactive materials.
Reportsoftheftorlossoflicensedmaterialwillberequiredbyreference totheregulations of10CFRintheTechnical Specifications.
20.403Notifications ofincidents, asdescribed inthisregulation willbeassuredbytherequirements oftheTechnical Specifications, theSSESAdministrative Procedures andappropriate plantprocedures, whichalsoprovideforthenecessary assessments todetermine theoccurrence ofsuchincidents.
20.405Reportsofoverexposures toradiation andtheoccurrence ofexcessive levelsandconcentrations, asrequiredbythisregulation, willbeprovidedforbyreference intheTechnical Specifications andinappropriate healthphysicsprocedures.
20.407Thepersonnel monitoring reportrequiredbythisregulation willbeexpressly providedforbytheTechnical Specifications.
Appropriate healthphysicsprocedures establish thedatabasefromwhichthisreportisgenerated.
(SeeFSARChapter12.)
20.408Thereportofradiation exposurerequiredbythisregulation upontermination ofanindividual's employment orworkassignment isgenerated throughtheprovisions ofthehealthphysicsprocedure.
20.409Thenotification andreporting requirements ofthisregulation, andthosereferredtobyit,aresatisfied bytheprovisions ofthehealthphysicsprocedure.
50.30Thisregulation setsdownprocedural requirements forthefilingoflicenseapplications.
PPMhascompliedwiththeprocedural requirements ineffectatthetimewhenfilingitslicenseapplication andtheamendments toit.50.33Thisregulation requiresthelicenseapplication tocontaincertaingeneralinformation, suchasanidentification oftheapplicant, information abouttheapplicant's financial qualifications, andalistofregulatory agencieswithjurisdiction overtheapplicant's ratesandservices.
Thisinformation wasprovidedintheSSESoperating licenseapplication.
50.34a(c)
Thedescriptions requiredpursuantto50.34a(a)arepresented inChapter11oftheFSAR.TheOperating LicenseStageEnvironmental Reportprovidestheexpectedreleaseinformation required.
50.34(b)TheSSESFinalSafetyAnalysisReport(FSAR)wasinitially submitted onApril10,1978andwasdocketed(Nos.50-387/388) onJuly31,1978pursuanttoSection50.34of10CFR50.Thisdocumentanditsnumerousamendments havebeenundergoing reviewbytheNRCanditsstaff.50.34(c)ThephysicalsecurityplanforSSESwassubmitted totheNuclearRegulatory Commission (NRC)inApril1978withthemostrecentamendment submitted April8,1981.Thisplanispresently undergoing NRCreview.50.34(d)TheSafeguards Contingency planforSSESwassubmitted totheNRConJuly11,1980'hisplanwasmostrecentlyamendedonApril8,1981andispresently undergoing NRCreview.
50.36(a)6(b)TheSSESapplications foroperating licensesincorporate thetechnical specifications requirements of10CFR50.36
-Paragraphs (a)and(b).Draftsofthesetechnical specifications areundergoing NRCreview.50.36(c)Alloftheabovelistedcategories arecontained inthecurrentdrafttechnical specifications.
Thetechnical specifications willbea"living"document.
Amendments, therefore, willbenecessary tomaintainthedocumentcurrentwithNRCrequirements, aswellaswithplantmodifications forimprovedoperations.
50.36aTheSSESFSAR,Section12.1,includesconsiderations whichrequirecompliance with10CFR50.34a (releases aslowasisreasonable achievable),
andtheSSESTechnical Specifications, Sec.3/4.11ensurethatconcentrations ofradioactive effluents releasedtounrestricted areasarewithinthelimitsspecified in10CFR20.106.
Thereporting requirements of10CFR50.36a(a)(2) arecompliedwiththroughappropriate SSESprocedures.
50.37Thisregulation requirestheapplican't toagreetolimitaccesstoRestricted Data.Applicant compliance isinherenttotheoperating licenseapplication "whethersostatedthereinornot."50.38Thisregulation prohibits theNRCfromissuingalicensetoforeign-controlled entities.
PPGL'sstatement thatitisnotowned,controlled, ordominated byanalien,foreigncorporation, orforeigngovernment isintheoperating li'censeapplication fortheSusquehanna SteamElectricStation.50.40Thisregulation providesconsiderations to"guide"theCommission ingrantinglicensesasfollows:50.40(a)Thedesignandoperation ofthefacilityistoprovidereasonable assurance thattheapplicant willcomplywithNRCregulations, including thosein10CFRPart20,andthatthehealthandsafetyofthepublicwillnotbeendangered.
ThebasisforPPM'sassurance thattheregulations willbemetandthepublicprotected iscontained inthisenclosure andinthelicenseapplication andtherelatedcorrespondence overtheyears.Moreover, thelengthyprocessbywhichtheplantisdesigned, constructed, andreviewed, including reviewsby
 
PPGL'sstaff,theNRCstaff,theACRS,andNRClicensing boards,providesagreatdealofassurance thatthepublichealthandsafetywillnotbeendangered.
Inparticular, theAtomicSafetyandLicensing Board,afteranextensive review,concluded thatPPGLhadthecommitment andtechnical qualifications necessary tooperateSusquehanna SteamElectri'c Stationsafetyandincompliance withallapplicable radiological healthandsafetyrequirements.
Anotherconsideration isthattheapplicant betechnically andfinancially qualified.
BothPPGL'stechnical qualifications anditsfinancial qualifications werereviewedinhearingsbeforetheAtomicSafetyandLicensing Board.Anotherconsideration isthattheissuanceofthelicenseisnottobeinimicaltothecommondefenseandsecurityortothehealthandsafetyofthepublic.Theindividual showingsofcompliance withparticular regulations contained inthisenclosure, aswellasthecontentsoftheentireFSARandrelatedcorrespondence overtheyears,plusthelengthyprocessofdesign',construction, andreviewbyPAL,itsNSSSvendor,andthegovernment, providePPMwithconsiderable assurance thatthelicensewillnotbeinimicaltothehealthandsafetyofthepublic.Asforthecommondefenseandthesecurity, thereisconsiderable assurance thatthelicensewillnotbeinimicalinthatPP&LhasanapprovedsecurityplanforSusquehanna SteamElectricStation,thatPPGLisnotcontrolled byagentsofforeigncountries,
'andthatPPGLhasagreedtolimitaccesstoRestricted Data.Thefinal50.40"consideration" isthattheapplicable requirements ofPart51havebeensatisfied.
Part51concernscompliance withtheNationalEnvironmental PolicyActof1969.PPGIhassubmitted aFinalEnvironmental ReportandtheNRCstaffisreviewing thereportandwillpublishafinalEnvironmental ImpactStatement pursuantto10CFR51.Environmental Technical Specifications arepending.Thisregulation appliestoClass104licensees, suchasthosefordevicesusedinmedicaltherapy.Susquehanna SteamElectricStationhasnotappliedforaClass104license,andso50.41isnotapplicable.
10 Section50.42providesadditional "considerations" to"guide"theCommission inissuingClass103licenses.
Thetwoconsiderations are:(a)thattheproposedactivities willserveausefulpurposeproportionate tothequantities ofspecialnuclearmaterialorsourcematerialtobeutilizedand(b)thatdueaccountwillbetakenoftheantitrust adviceprovidedbytheAttorneyGeneralundersubsection 105coftheAtomicEnergyAct.The"usefulpurpose"tobeservedistheproduction ofelectricpower.Theneedforthepowerwasdetermined bythelicensing boardattheconstruction permitstage.Althoughconditions affecting theneedforpowerareconstantly
: changing, PPGLperiodically makesloadprojections, andinPPGL'sjudgement theneedforSusquehanna SteamElectricStationisstillsubstantial.
Asfortheamountofspecialnuclearmaterialorsourcematerialused,thereisnoreasontobelievethattheirproportion inrelationtothepowerproducedissubstantially greaterthanthatofothercommercial powerreactorsinthiscountry.TheNRCispresently undertaking theantitrust reviewfor~SSESand'asnotyetinformedtheapplicant ofitsconclusions.
Compliance withParagraphs (a)through(e)isdiscussed indetailinFSARSection6.2.5.Paragraph (f)isnotapplicable, sincetheconstruction permitforSSESwaspublished afterNovember5,1970.Paragraph (g)isnotapplicable, sincethenoticeofhearingontheapplication fortheconstruction permitforSSESwaspublished afterDecember22,1968.Asdiscussed above,thecombustible gascontrolsystemsforSSESmeettherequirements of10CFR50.44.
Compliance with10CFR50.46 isdocumented intheFSAR,Section6.3.3.ThisanalysisshowsthatSSESmeets10CFR50.46 criteriaandtheECCSequipment willperformitsfunctioninanacceptable manner.Compliance with10CFR50.48isdocumented throughthePPMCompanyFireProtection ReviewReportforSSES.,ThisreportisinRevision1andwassubmitted totheNRCforreview'inMarch,1981.11 50.5150.53Thisregulation specifies themaximumdurationoflicenses.
Compliance willbeaffectedsimplybytheCommission's writingthelicensesoastocomply.I'hisregulation providesthatlicensesarenottobeissuedforactivities thatarenotunderorwithinthejurisdiction oftheUnitedStates.Theoperation ofSusquehanna SteamElectricStationwillbewithintheUnitedStatesandsubjecttothejurisdiction oftheUnitedStates,asisevidentfromthedescription ofthefacilityintheoperating licenseapplic'ation.
50.54Thisregulation specifies certainconditions thatareincorporated ineverylicenseissued.Compliance iseffectedsimplybyincluding theseconditions inthelicensewhenitisissued.Indeed,muchof50.54merelyprovidesthatotherprovisions ofthelawapply,whichwouldbethecaseevenwithout50.54.50.55a(a)(1)
VariouschaptersoftheFSARdiscussdesign,fabrication,
: erection, construction, testing,andinspection ofsafety-related equipment.
Forexample,Chapter14providesinformation ontestingofsafety-related systems.Chapter17providesinformation concerning the(}ualityAssurance Programthatwasutilized.
Asafurtherexampleofaspecificsystem,Chapter5,Section5.2,"Integrity oftheReactorCoolantPressureBoundary,"
discusses thedesignofthereactorcoolantsystem.50.55a(a)
(2)Thisparagraph isageneralparagraph leadingintoParagraphs (c)through(i)oftheregulation.
50.55a(b)(l) 50.55a(b)(2)
Theseparagraphs provideguidanceconcerning theapprovedEditionandAddendaofSectionIIIandXIoftheASMEBSPVCode.50.55a(c)
Designandfabrication ofthereactorvesselwascarriedoutinaccordance withASMESectionIII(1968)ClassAincluding AddendathroughSummer1970.Information canbefoundinChapters3and5oftheFSAR.50.55a(d)Reactorcoolantsystempipingmeetstherequirements ofASMESectionIII(1971)Class1.Information canbefoundinChapters3and5oftheFSAR.12 50.55a(e)
Pumpswhicharepartofthereactorcoolantpressureboundarymeettherequirements ofASMESectionIII(1971).Information canbefoundinChapters3and5oftheFSAR.50.55a(f)
Thevalveswhicharepartofthereactorcoolantpressureboundaryweredesignedandfabricated inaccordance withtherequirements ofASMESection,III,1971edition.(SeeFSARChapters3and5.)50.55a(g)
Inservice Inspection (ISI)requirements aredelineated inthispartandarespecified intheTechnical Specifications, Paragraph 4.0.5.Aspermitted bythispartandtheTechnical Specifications, certainexemptions havebeenrequested fortheinservice inspection ofvarioussystemsandtheinservice testingofvariouspumpsandvalves.Thesereliefrequestsweresubmitted totheNRCasasupplement totheSSESInservice Inspection ProgramforpumpsandvalvesinaletterdatedMarch20,1981.50.55a(h) 50.55a(i)
Asdiscussed inFSARChapter7,theprotection systemsmeetIEEE279-1971.
Fracturetoughness requirements aresetforthinAppendices GandHof10CFR50.Technical Specifications requiretheuseofreactorvesselmaterialirradiation surveillance specimens andupdatingofthe"heatup"and"cooldown" curvesgivenintheTechnical Specifications'urther information onthissubjectisgiveninChapter5oftheFSAR.50.56Thisregulation providesthattheCommission will,intheabsenceofgoodcauseshowntothecontrary, issueanoperating licenseuponcompletion oftheconstruction ofafacilityincompliance withthetermsandconditions oftheconstruction permit.Thisimposesnoindependent obligations ontheapplicant.
50.58Thisregulation providesforthereviewandreportoftheAdvisoryCommittee onReactorSafeguards.
TheACRSisreviewing theoperating licenseapplication forSSESinaccordance withitsusualpractice.
13 50.59TheSusquehanna ReviewCommittee shallreview:aThesafetyevaluation for1)changestoprocedures, equipment, orsystems,and2)testsorexperiments completed undertheprovision of10CFR50.59 toverifythatsuchactionsdidnotconstitute anunreviewed safetyquestion; b.Proposedchangestoprocedures, equipment orsystemswhichinvolveanunreviewed safetyquestionasdefinedinlOCFR50.59; andc.Proposedtestsorexperiments whichinvolveanunreviewed safetyquestionasdefinedin10CFR50.59.
TheSRCshallreporttoandadvisetheSeniorVicePresident
-Nuclearoftheiractivities.
Safetyevaluations ofchangesmadetotheequipment orreviewoftestsandexperiments tocomplywith10CFR50.59 shallbekeptinamannerconvenient forreviewandshallberetainedforatleastfiveyears.SSESwillcomplywiththereporting requirements setforthin10CFR50.59.
50.70TheCommission hasassignedresidentinspectors totheSSES.PPScLhasprovidedofficespaceinaccordance withtherequirements ofthissection.PP&LpermitsaccesstothestationtoNRCinspectors inaccordance with10CFR50.70(b)(3).
50.71Recordsareandwillbemaintained inaccordance withtherequirements ofParagraphs (a)through(e)ofthisregulation andthelicense.Paragraph (e)requiresthattheFSARbeupdated(within24monthsoftheissuanceoftheoperating licenseandannuallythereafter).
Suchupdateswillbemadeinaccordance withthisSection.50.72Notification ofsignificant eventstotheNRCwillbemadeinaccordance withthisregulation.
AppendixAThedetailsofSSEScompliance withGeneralDesignCriteriaisdiscussed indetailintheFSAR,Section3.1.AppendixBChapter17oftheFSARdescribes indetailtheprovisions ofthequalityassurance programwhich14 hasbeenimplemented tomeetallapplicable requirements ofAppendixB.AppendixECompliance with10CFR50,AppendixE,isdocumented throughthePPGLCompanyEmergency PlanforSSES.Thisplanincorporates therequirements ofNUREG0654exceptforsomechangeswithrespecttoTableB-1.Thesechangesarepresently beingreviewedbytheNRCstaff.Theplanhasbeenunderrevisionandwassubmitted totheNRConApril28,1981.Appendices G,HCompliance withAppendices GandHcannotbeevaluated atthistime.InordertoanswerNRCquestions intheseareas,PPM.hasrequested anevaluation byGeneralElectric.
PPSLexpectstoreceivethenecessary information byMay21,1981.Itistheintentoftheevaluation toshowcompliance withtheseregulations.
AppendixIThisAppendixprovidesnumerical guidesfordesignobjectives andlimitingconditions foroperation tomeetthecriteria"aslowasisreasonably achievable" forradioactive materialinlight-water-cooled nuclearpowerreactoreffluents, PPGLhasfiledwiththeCommission thenecessary information topermitanevaluation oftheSSESwithrespecttotherequirements ofSctionII.A,II.B,andII.CofAppendixI.TheSSESapplication forconstruction permitwasdocketedafterJanuary2,1971andpriortoJune4,1976.Nocost-benefit analysisisrequired.
Allcalculated dosesarewithintheAppendixIof10CFR50guidelines.
AppendixJReactorpressureboundaryleakagetestingforwatercooledpowerreactorsisdelineated inthisAppendix.
Theserequirements aregiveninTechnical Specification 3/4.6.1.Additional information concerning compliance canbefoundinFSARChapters3and6.AppendixKCompliance with10CFR50AppendixKisspecifically requiredby10CFR50~46'SCScompliance isdocumented inSection6.3.3oftheSSESFSAR.NEDO-20566 providesacompletedescription ofthemethodsusedtoperformthecalculations.
100.10Thefactorslistedrelatedtoboththeunitdesignandthesitehavebeenprovidedintheapplication.
Sitespecifics, including seismology, meteorology, geology,andhydrology,,
arepresented inChapter215 oftheFSAR.Theexclusion area,lowpopulation zone,andpopulation centerdistanceareprovidedanddescribed.
TheFSARalsodescribes thecharacteristics ofreactordesignandoperation.
100.11Theexclusion area,lowpopulation zoneandpopulation centerdistancearedescribed intheFSAR,Chapter2.Allrequirements ofthissectionwithregardtotheseareasanddistances aremet.TheFSARaccidentanalyses, particularly thoseinChapters6and15,demonstrate thatoffsitedosesresulting frompostulated accidents wouldnotexceedthecriteriainthissectionoftheregulation.
AppendixAStructures andequipment important toplantsafetyareprotected fromordesignedtowithstand allappropriate naturalphenomena attheplantsite.Designisbasedonthemostseverephenomena probablewithspecialconsideration fortheuncertainty inprediction.
Detaileddiscussions ofthephenomena themselves, andhowtheyareappliedtothestructures andequipment, arefoundinthefollowing FSARsections:
Meteorology, Section2.3;Hydrology, Section2.4;Geology,Seismology, andGeotechnical Engineering, Section2.5;Classification ofStructures, Components, andSystems,Section3.2;WindandTornadoLoadings, Section3.3;Wateri,evel(Flood)Design,Section3.4;MissileProtection, Section3.5;SeismicDesign,Section3.7;DesignofCategoryIStructures, Section3.8;Mechanical SystemsandComponents, Section3.9;SeismicQualifications ofCategoryIinstrumentation andElectrical Equipment, Section3.10;andEnvironmental DesignofMechanical andElectrical Equipment, Section3.11.,8C/cak}}

Revision as of 04:47, 29 June 2018

Forwards Summary of Conformance w/10CFR20,50 & 100. Conformance w/10CFR50 App a Is Discussed in Section 3.1 of FSAR
ML18026A352
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 05/14/1981
From: CURTIS N W
PENNSYLVANIA POWER & LIGHT CO.
To: YOUNGBLOOD B J
Office of Nuclear Reactor Regulation
References
PLA-777, NUDOCS 8105190381
Download: ML18026A352 (26)
v • d • e


Text

REGULATUiNFORHATION DISTRIBUTION

'TEH(RIDS)ACCESSION NUR:8105190381 OVC~DATE:81/05/14NOTARIZED:

NOFACIL:50-387 Susquehanna SteamElectricStation,Unit1>Pennsylva 50-368Susquehanna SteamElectricStation~Unit2,Pennsylva AUTH~NAivifAUTHORAfFiLIATION CORTISi"l.WoPennsylvania PowerK,LightCo.RECIP.NAiwfRECIPItiV 1AFFILIATION YOUNGBLOODiB.J

~Licensing Branch1SUBJECT;Forwardssummaryofconformance w/iOCFR20I50 L100'onformance w/luCrRSO AppAisaiscussed inSection3.1ofFSAR~DISTRIBUTIUN CODE:8001SCOPIESRECEIVED:LTR ENCLSIZE::D8TITLE:PSALM/f.SAR AiiDTSandRelatedCorrespondence OOCKET0008iVOTES:Send IKE3copiesfSeR8allamends'cy.'BAR-LRG PN(CRIB)05000387SendISE3copiesFSAR4allamends.1cy'.BwR-LRG Ps(L.RIB) 05000388ACTIOiV;<ECIPIEN'1Ii)C00f/iVAt1fA/~L(CENSNGRUSHBROO<.~.

Ci)p'ESLTTRENCL100RfC[PIEivTIDCODE/NAi'lE LICRRa2BCSTARK,R,04CDPIESLTTRENCL101INTERNAL:

ACCIDEvALBR2>CH'ANEVGBRCO/EPERFBRf;,~IERGPREP22GEUSCIE>VCES 14wY>/GEOBR1514E-ObLICQUALiR,<ECHE,<GBRioNiRCPOR02OPLlCBRPROC/TSTRE,Y20"SBR22GOlSr<UCTENGBR2>11101311111111AuXSYSBR07CONTSYSBR09EFFTRSYSUR12EQUIPQUALuR13Hu<FACTENGuRI~CSYS.BRlbLICGUIOBRvIATLENGoR17,QPAOELOPOWERSYSBH19QABR21REACSYSl3R23SITAj~iALbR2411111131111111101011111111-XTERNAL:

ACRSNSlC27Oylvlb11LPOR03gAY23,1981515ITOTALNUWBEROFCOPIFSgE.~U<Rt.D:,

LTTR'bEivCL'54 iI PpalTWONORTHNINTHSTREET,ALLENTOWN, PA.18101PHONE:(215)821-5151NORMANW.CURTISVicePresident-Engineering

&Constructen 821.5381May14,1981Mr.B.J.Youngblood, ChiefLicensing BranchNo.1U.S.NuclearRegulatory Commission Washington, D.C.20555SUSQUEHANNA STEAMELECTRICSTATION10CFRCOMPLIANCE ER100450FILE841PLA-777DOCKETNOS,50-387AND50-388

DearMr.Youngblood:

InresponsetotheCommission's request,enclosedyouwillfindanitemizedreviewofthecompliance ofPennsylvania PowerandLightCompanyandtheSusquehanna SteamElectricStation,onits1and2to10CFR,Parts20,50and100.Pleasenotethatconformance to10CFR50AppendixA,GeneralDesignCriteriaforNuclearPowerPlants,isdiscussed inSection3.1oftheFinalSafetyAnalysisReport(FSAR).Ifyouhaveanyquestions ontheencloseddocumentoranyofthereferenced

material, pleasecontactme.Verytrulyyours,N.3.CurtisVicePresident-Engineering andConstruction-Nuclear RRS/mkspoolAttachment (I(~~.>gzg~a 3PENNSYLVANIA POWER&LIGHTCOMPANY 4lI~4'I SUSQUEHANNA STEAMELECTRICSTATION,UNITS1AND2ASummaryofConformance toNuclearRegulatory Commission Regulations of10CZRParts20,50and100Pennsylvania Power6LightCompanyMay1981

INTRODUCTION Thisdocumenthasbeenpreparedasasummaryoftheconformance ofSusquehanna SteamElectricStation(SSES)designandoperation totheNRCregulations of10CFRParts20,50and100.Thosesectionsofregulations whichspecifically imposecompliance requirements onlicensees areaddressed.

II ENCLOSURE ComLIANCE OFSUSqUEHANNA STEmELECTRICSTATIONUNITS1AND2WITHTHENRCREGULATIONS OF10CFRPARTS2050AND100Regulation (10CFR)20.1(c)~ComliaaceConformance totheALARAprinciple statedinthisregulation isensuredbytheimplementation ofPPSLpoliciesandappropriate Technical Specifications andhealthphysicsprocedures.

Chapterslland12oftheFSARdescribethespecificequipment anddesignfeaturesutilizedinthiseffort.20.3Thedefinitions contained inthisregulation areadheredtoinallappropriate Technical Specifications andprocedures, andinapplicable sectionsoftheFSAR.20.4TheUnitsofRadiation Dosespecified inthisregulation areacceptable andconformed toinallapplicable SSESprocedures.

20.5TheUnitsofRadioactivity specified inthisregulation areacceptedandconformed toinallapplicable SSESprocedures.

20.101Theradiation doselimitsspecified inthisregulation arecompliedwiththroughtheimplementation ofandadherence toadministrative policiesandcontrolsandappropriate healthphysicsprocedures developed forthispurpose.Conformance isdocumented bytheuseofappropriate personnel monitoring devicesandthemaintenance ofallrequiredrecords.(SeeFSARChapter12.)20.102Whenrequiredbythisregulation, theaccumula'ted doseforanyindividual permitted toexceedtheexposurelimitsspecified in20.101(a) isdetermined bytheuseofFormNRC-4.Appropriate healthphysicsprocedures andadministrative policiescontrolthisprocess.(SeeFSARChapter12.)20.103(a)

Compliance withthisregulation isensuredthroughtheimplementation ofappropriate healthphysicsprocedures relatingtoairsamplingforradioactive materials, andbioassayofindividuals forinternalcontamination.

Administrative policiesandcontrolswillprovideadequatemarginsofsafetyfortheprotection ofindividuals againsttheintakeof 0Id/

radioactive materials.

Thesystemsandequipment described inChapterslland12oftheFSARprovidethecapability tominimizethesehazards.20.103(b)(1)Thereactorbuildingventilation systemisdesignedtoprovideameanstoreducetheconcentration ofparticulate andgaseouscontamination toassuresafecontinuous access(40hours/week) duringnormalreactorshutdown(FSAR,Sections12.3.3.1and12.5.3.2.3.1).

Portableventilation systems,hoods,andtestsareusedaspracticable tocontainandreduceairborneparticulate andgaseouscontamination duringtheperformance ofvariousjobs.20.103(b)(2)Evaluation ofairborneactivityinrestricted areasisdiscussed intheevaluation ofcompliance toSection20.103-Paragraph (a)(l).IssuanceandSelection ofResiratoEuimentRadiation protection personnel atSSESwillselectappropriate respiratory equipment sothatcontaminant concentration inhaledbythewearerdoesnotexceedtheappropriate regulatory limitsspecified inAppendixB,TableI,Columnl.Shouldanindividual receivegreaterthan40MPChoursin7consecutive days,anevaluation willbemadetoidentifythecauseandactionswillbetakentopreventrecurrence.

Recordswillbemaintained foreachoccurrence.

20.103(c)

Radiation protection personnel atSSESwillselectappropriate respiratory equipment sothatcontaminant concentration inhaledbythewearerdoesnotexceedtheappropriate regulatory limits.Theprotection factorsusedatSSEScomplywiththeprotection factorspermitted underRegulatory Guide8.15.20.103(e)a(f)SSESisincompliance with10CFR20.103

-Paragraph (c)andtherefore isexemptfromtherequirements ofParagraph (e).20'04Conformance withthisregulation isassuredbyappropriate PPGLpoliciesregarding employment ofindividuals undertheageof18andtheSSESAdministrative Procedures restricting theseindividuals'ccess torestricted areas.

20..105(a)

Chapters11and12oftheFSARprovidetheinformation andrelatedradiation doseassessments specified bythisregulation.

20.105(b)

Theradiation doseratelimitsspecified inthisregulation willbecompliedwiththroughtheimplementation ofSSESprocedures, Technical Specifications, andadministrative policieswhichcontroltheuseandtransferofradioactive materials.

Appropriate surveysandmonitoring deviceswilldocumentthiscompliance.

20.106(a)

Conformance withthelimitsspecified inthisregulation willbeassuredthroughtheimplementation ofSSESprocedures andapplicable Technical Specifications whichprovideadequatesamplingandanalyses, andmonitoring ofradioactive materials ineffluents beforeandduringtheirrelease.Thelevelofradioactivity instationeffluents willbeminimized totheextentpracticable bytheuseofappropriate equipment designedforthispurpose,asdescribed inChapter11of=theFSAR.20.106(b) 20.106(c)

PPRLhasnotanddoesnotcurrently intendtoincludeinanylicenseoramendment applications proposedlimitshigherthanthosespecified in20.106(a),

asprovidedintheseregulations.

20.106(d)

Appropriate allowances fordilutionanddispersion ofradioactive effluents willbemadeinconformance withthisregulation, andaredescribed indetailinChapterlloftheFSAR,andinSections3/4.11and3/4.12oftheTechnical Specifications.

20.108Necessary bioassayequipment andprocedures, including WholeBodyCounting, willbeutilizedtodetermine exposureofindividuals toconcentrations ofradioactive materials.

Appropriate healthphysicsprocedures andadministrative policiesimplement thisrequirement.

(SeeFSARChapter12.)20.201Thesurveysrequiredbythisregulation willbeperformed atadequatefrequencies andcontainsuchdetailastobeconsistent withtheradiation hazardbeingevaluated.

Whennecessary, theRadiation WorkPermitsystemestablished atthestationprovidesfordetailedphysicalsurveysofequipment, structures andworksitestodetermine appropriate levelsofradiation protection.

TheSSESAdminis-trativeProcedures andapplicable healthphysicsprocedures willrequirethesesurveysandprovide~fortheirdocumentation insuchmannerastoensurecompliance withtheregulations of10CFRPart20.(SeeFSARChapter12.)20.202(a)

TheSSESAdministrative Procedures andapplicable healthphysicsprocedures willsetforthpoliciesandpractices whichensurethatallindividuals aresuppliedwith,andrequiredtouse,appropriate personnel monitoring equipment.

TheRadiation WorkPermitsystemwillbeestablished toprovideadditional controlofpersonnel workinginradiation areasandtoensurethatthelevelofprotection affordedtotheseindividuals isconsistent withthe'adiological hazardsintheworkplace.(SeeFSARChapter12.)20.202(b) 20.203(a)

Theterminology setforthinthisregulation willbeacceptedandconformed toinallapplicable SSEShealthphysicsprocedures, Technical Specifications, andthoseSSESAdministrative Procedures inwhichitsuseismade.Allmaterials usedforlabeling, posting,orotherwise designating radiation hazardsorradioactive materials, andusingtheradiation symbol,conformtotheconventional designprescribed inthisregulation perSSESprocedures.

20.203(b)Thisregulation willbeconformed tothroughtheimplementation ofappropriate healthphysicsprocedures andportionsoftheSSESAdministrative Procedures relatingtopostingofradiation areas,asdefinedin10CFRPart,20.202(b)(2).

20.203(c)

Therequirements ofthisregulation for"HighRadiation Areas"willbeconformed tobytheimplementation oftheSSESTechnical Specifications andappropriate planthealthphysicsprocedures, aswellastheSSESAdministrative Procedures.

Thecontrolsandotherprotective measuressetforthintheregulation aremaintained underthesurveillance oftheSSESHealthPhysicsgroup.ItshouldbenotedthatTechnical Specification 6.12.1willprovidealternate accesscontrolmethodstobeapplied"inlieuofthe'controldevice'r'alarmsignal'equired byParagraph 20.203(c)(2) of10CFR20,"

whichwillpreventunauthorized entryintoahighradiation area.

20.203(d)

EachAirborneRadioactivity Area,asdefinedinthisregulation, willberequiredtobepostedbyprovisions oftheSSESAdministrative Procedures andappropriate healthphysicsprocedures.

Theseprocedures alsoprovideforthesurveillance requirements necessary todetermine airborneradioactivity levels.20.203(e)

Theareaandroompostingrequirements setforthinthisregulation pertaining toradioactive materials willbecompliedwiththroughtheimplementation ofappropriate healthphysicsprocedures, andSSESAdministrative Procedures.

20.203(f)

Thecontainer labelingrequirements setforthinthisregulation willbecompliedwiththroughtheimplementation ofappropriate healthphysicsprocedures, andportionsoftheSSESAdministrative Procedures.

20.204Thepostingrequirement exceptions described inthisregulation areusedwhereappropriate andnecessary atSSES.AdequatecontrolsareprovidedwithintheSSEShealthphysicsprocedures toensuresafeandproperapplication oftheseexceptions.

20.205Alloftherequirements ofthisregulation pertaining toprocedures forpickingup,receiving, andopeningpackagesofradioactive materials willbeimplemented bytheSSESAdministrative Procedures andappropriate healthphysicsprocedures.

Theseprocedures alsoprovideforthenecessary documentation toensureanauditable recordofcompliance.

(SeeFSARChapter12.)20.206Therequirements oflOCFR19.12 referredtobythisregulation aresatisfied bytheradiation workertrainingconducted atSSES.Appropriate healthphysicsprocedures setforthrequirements forallradiation workerstoreceivethisinstruction onaperiodicbasis.(SeeFSARChapter12.)20.207Licensedmaterials arenotstoredoutsideoftherestricted areasatSSES.20.301Thegeneralrequirements forwastedisposalsetforthinthisregulation arecompliedwiththroughSSEShealthphysicsprocedures, theTechnical Specifications, andtheprovisions ofthestationlicense.Chapter11oftheFSARdescribes theSolidVasteDisposalSysteminstalled atSSES.

20.302Nosuchapplication forproposeddisposalprocedures, asdescribed inthisregulation, hasbeenmadeoriscurrently contemplated atPPSL.20'03Noplansforwastedisposalbyreleaseintosanitaryseweragesystems,asprovidedforinthisregulation, arecontemplated bySSES,noristhispracticecurrently utilized.

20.305SpecificAuthorization, asdescribed inthisregulation, isnotcurrently beingsoughtbyPPSLfortreatment ordisposalofwastesbyincineration.

20.401Alloftherequirements ofthisregulation willbecompliedwiththroughtheimplementation ofappropriate Technical Specifications andhealthphysicsprocedures pertaining torecordsofsurveys,radiation monitoring andwastedisposal.

Theretention periodsspecified forsuchrecordsarealsoprovidedforinthesespecifications andprocedures.

(SeeFSARChapter12.)20.402SSEShasestablished anappropriate inventory andcontrolprogramtoensurestrictaccountability foralllicensedradioactive materials.

Reportsoftheftorlossoflicensedmaterialwillberequiredbyreference totheregulations of10CFRintheTechnical Specifications.

20.403Notifications ofincidents, asdescribed inthisregulation willbeassuredbytherequirements oftheTechnical Specifications, theSSESAdministrative Procedures andappropriate plantprocedures, whichalsoprovideforthenecessary assessments todetermine theoccurrence ofsuchincidents.

20.405Reportsofoverexposures toradiation andtheoccurrence ofexcessive levelsandconcentrations, asrequiredbythisregulation, willbeprovidedforbyreference intheTechnical Specifications andinappropriate healthphysicsprocedures.

20.407Thepersonnel monitoring reportrequiredbythisregulation willbeexpressly providedforbytheTechnical Specifications.

Appropriate healthphysicsprocedures establish thedatabasefromwhichthisreportisgenerated.

(SeeFSARChapter12.)

20.408Thereportofradiation exposurerequiredbythisregulation upontermination ofanindividual's employment orworkassignment isgenerated throughtheprovisions ofthehealthphysicsprocedure.

20.409Thenotification andreporting requirements ofthisregulation, andthosereferredtobyit,aresatisfied bytheprovisions ofthehealthphysicsprocedure.

50.30Thisregulation setsdownprocedural requirements forthefilingoflicenseapplications.

PPMhascompliedwiththeprocedural requirements ineffectatthetimewhenfilingitslicenseapplication andtheamendments toit.50.33Thisregulation requiresthelicenseapplication tocontaincertaingeneralinformation, suchasanidentification oftheapplicant, information abouttheapplicant's financial qualifications, andalistofregulatory agencieswithjurisdiction overtheapplicant's ratesandservices.

Thisinformation wasprovidedintheSSESoperating licenseapplication.

50.34a(c)

Thedescriptions requiredpursuantto50.34a(a)arepresented inChapter11oftheFSAR.TheOperating LicenseStageEnvironmental Reportprovidestheexpectedreleaseinformation required.

50.34(b)TheSSESFinalSafetyAnalysisReport(FSAR)wasinitially submitted onApril10,1978andwasdocketed(Nos.50-387/388) onJuly31,1978pursuanttoSection50.34of10CFR50.Thisdocumentanditsnumerousamendments havebeenundergoing reviewbytheNRCanditsstaff.50.34(c)ThephysicalsecurityplanforSSESwassubmitted totheNuclearRegulatory Commission (NRC)inApril1978withthemostrecentamendment submitted April8,1981.Thisplanispresently undergoing NRCreview.50.34(d)TheSafeguards Contingency planforSSESwassubmitted totheNRConJuly11,1980'hisplanwasmostrecentlyamendedonApril8,1981andispresently undergoing NRCreview.

50.36(a)6(b)TheSSESapplications foroperating licensesincorporate thetechnical specifications requirements of10CFR50.36

-Paragraphs (a)and(b).Draftsofthesetechnical specifications areundergoing NRCreview.50.36(c)Alloftheabovelistedcategories arecontained inthecurrentdrafttechnical specifications.

Thetechnical specifications willbea"living"document.

Amendments, therefore, willbenecessary tomaintainthedocumentcurrentwithNRCrequirements, aswellaswithplantmodifications forimprovedoperations.

50.36aTheSSESFSAR,Section12.1,includesconsiderations whichrequirecompliance with10CFR50.34a (releases aslowasisreasonable achievable),

andtheSSESTechnical Specifications, Sec.3/4.11ensurethatconcentrations ofradioactive effluents releasedtounrestricted areasarewithinthelimitsspecified in10CFR20.106.

Thereporting requirements of10CFR50.36a(a)(2) arecompliedwiththroughappropriate SSESprocedures.

50.37Thisregulation requirestheapplican't toagreetolimitaccesstoRestricted Data.Applicant compliance isinherenttotheoperating licenseapplication "whethersostatedthereinornot."50.38Thisregulation prohibits theNRCfromissuingalicensetoforeign-controlled entities.

PPGL'sstatement thatitisnotowned,controlled, ordominated byanalien,foreigncorporation, orforeigngovernment isintheoperating li'censeapplication fortheSusquehanna SteamElectricStation.50.40Thisregulation providesconsiderations to"guide"theCommission ingrantinglicensesasfollows:50.40(a)Thedesignandoperation ofthefacilityistoprovidereasonable assurance thattheapplicant willcomplywithNRCregulations, including thosein10CFRPart20,andthatthehealthandsafetyofthepublicwillnotbeendangered.

ThebasisforPPM'sassurance thattheregulations willbemetandthepublicprotected iscontained inthisenclosure andinthelicenseapplication andtherelatedcorrespondence overtheyears.Moreover, thelengthyprocessbywhichtheplantisdesigned, constructed, andreviewed, including reviewsby

PPGL'sstaff,theNRCstaff,theACRS,andNRClicensing boards,providesagreatdealofassurance thatthepublichealthandsafetywillnotbeendangered.

Inparticular, theAtomicSafetyandLicensing Board,afteranextensive review,concluded thatPPGLhadthecommitment andtechnical qualifications necessary tooperateSusquehanna SteamElectri'c Stationsafetyandincompliance withallapplicable radiological healthandsafetyrequirements.

Anotherconsideration isthattheapplicant betechnically andfinancially qualified.

BothPPGL'stechnical qualifications anditsfinancial qualifications werereviewedinhearingsbeforetheAtomicSafetyandLicensing Board.Anotherconsideration isthattheissuanceofthelicenseisnottobeinimicaltothecommondefenseandsecurityortothehealthandsafetyofthepublic.Theindividual showingsofcompliance withparticular regulations contained inthisenclosure, aswellasthecontentsoftheentireFSARandrelatedcorrespondence overtheyears,plusthelengthyprocessofdesign',construction, andreviewbyPAL,itsNSSSvendor,andthegovernment, providePPMwithconsiderable assurance thatthelicensewillnotbeinimicaltothehealthandsafetyofthepublic.Asforthecommondefenseandthesecurity, thereisconsiderable assurance thatthelicensewillnotbeinimicalinthatPP&LhasanapprovedsecurityplanforSusquehanna SteamElectricStation,thatPPGLisnotcontrolled byagentsofforeigncountries,

'andthatPPGLhasagreedtolimitaccesstoRestricted Data.Thefinal50.40"consideration" isthattheapplicable requirements ofPart51havebeensatisfied.

Part51concernscompliance withtheNationalEnvironmental PolicyActof1969.PPGIhassubmitted aFinalEnvironmental ReportandtheNRCstaffisreviewing thereportandwillpublishafinalEnvironmental ImpactStatement pursuantto10CFR51.Environmental Technical Specifications arepending.Thisregulation appliestoClass104licensees, suchasthosefordevicesusedinmedicaltherapy.Susquehanna SteamElectricStationhasnotappliedforaClass104license,andso50.41isnotapplicable.

10 Section50.42providesadditional "considerations" to"guide"theCommission inissuingClass103licenses.

Thetwoconsiderations are:(a)thattheproposedactivities willserveausefulpurposeproportionate tothequantities ofspecialnuclearmaterialorsourcematerialtobeutilizedand(b)thatdueaccountwillbetakenoftheantitrust adviceprovidedbytheAttorneyGeneralundersubsection 105coftheAtomicEnergyAct.The"usefulpurpose"tobeservedistheproduction ofelectricpower.Theneedforthepowerwasdetermined bythelicensing boardattheconstruction permitstage.Althoughconditions affecting theneedforpowerareconstantly

changing, PPGLperiodically makesloadprojections, andinPPGL'sjudgement theneedforSusquehanna SteamElectricStationisstillsubstantial.

Asfortheamountofspecialnuclearmaterialorsourcematerialused,thereisnoreasontobelievethattheirproportion inrelationtothepowerproducedissubstantially greaterthanthatofothercommercial powerreactorsinthiscountry.TheNRCispresently undertaking theantitrust reviewfor~SSESand'asnotyetinformedtheapplicant ofitsconclusions.

Compliance withParagraphs (a)through(e)isdiscussed indetailinFSARSection6.2.5.Paragraph (f)isnotapplicable, sincetheconstruction permitforSSESwaspublished afterNovember5,1970.Paragraph (g)isnotapplicable, sincethenoticeofhearingontheapplication fortheconstruction permitforSSESwaspublished afterDecember22,1968.Asdiscussed above,thecombustible gascontrolsystemsforSSESmeettherequirements of10CFR50.44.

Compliance with10CFR50.46 isdocumented intheFSAR,Section6.3.3.ThisanalysisshowsthatSSESmeets10CFR50.46 criteriaandtheECCSequipment willperformitsfunctioninanacceptable manner.Compliance with10CFR50.48isdocumented throughthePPMCompanyFireProtection ReviewReportforSSES.,ThisreportisinRevision1andwassubmitted totheNRCforreview'inMarch,1981.11 50.5150.53Thisregulation specifies themaximumdurationoflicenses.

Compliance willbeaffectedsimplybytheCommission's writingthelicensesoastocomply.I'hisregulation providesthatlicensesarenottobeissuedforactivities thatarenotunderorwithinthejurisdiction oftheUnitedStates.Theoperation ofSusquehanna SteamElectricStationwillbewithintheUnitedStatesandsubjecttothejurisdiction oftheUnitedStates,asisevidentfromthedescription ofthefacilityintheoperating licenseapplic'ation.

50.54Thisregulation specifies certainconditions thatareincorporated ineverylicenseissued.Compliance iseffectedsimplybyincluding theseconditions inthelicensewhenitisissued.Indeed,muchof50.54merelyprovidesthatotherprovisions ofthelawapply,whichwouldbethecaseevenwithout50.54.50.55a(a)(1)

VariouschaptersoftheFSARdiscussdesign,fabrication,

erection, construction, testing,andinspection ofsafety-related equipment.

Forexample,Chapter14providesinformation ontestingofsafety-related systems.Chapter17providesinformation concerning the(}ualityAssurance Programthatwasutilized.

Asafurtherexampleofaspecificsystem,Chapter5,Section5.2,"Integrity oftheReactorCoolantPressureBoundary,"

discusses thedesignofthereactorcoolantsystem.50.55a(a)

(2)Thisparagraph isageneralparagraph leadingintoParagraphs (c)through(i)oftheregulation.

50.55a(b)(l) 50.55a(b)(2)

Theseparagraphs provideguidanceconcerning theapprovedEditionandAddendaofSectionIIIandXIoftheASMEBSPVCode.50.55a(c)

Designandfabrication ofthereactorvesselwascarriedoutinaccordance withASMESectionIII(1968)ClassAincluding AddendathroughSummer1970.Information canbefoundinChapters3and5oftheFSAR.50.55a(d)Reactorcoolantsystempipingmeetstherequirements ofASMESectionIII(1971)Class1.Information canbefoundinChapters3and5oftheFSAR.12 50.55a(e)

Pumpswhicharepartofthereactorcoolantpressureboundarymeettherequirements ofASMESectionIII(1971).Information canbefoundinChapters3and5oftheFSAR.50.55a(f)

Thevalveswhicharepartofthereactorcoolantpressureboundaryweredesignedandfabricated inaccordance withtherequirements ofASMESection,III,1971edition.(SeeFSARChapters3and5.)50.55a(g)

Inservice Inspection (ISI)requirements aredelineated inthispartandarespecified intheTechnical Specifications, Paragraph 4.0.5.Aspermitted bythispartandtheTechnical Specifications, certainexemptions havebeenrequested fortheinservice inspection ofvarioussystemsandtheinservice testingofvariouspumpsandvalves.Thesereliefrequestsweresubmitted totheNRCasasupplement totheSSESInservice Inspection ProgramforpumpsandvalvesinaletterdatedMarch20,1981.50.55a(h) 50.55a(i)

Asdiscussed inFSARChapter7,theprotection systemsmeetIEEE279-1971.

Fracturetoughness requirements aresetforthinAppendices GandHof10CFR50.Technical Specifications requiretheuseofreactorvesselmaterialirradiation surveillance specimens andupdatingofthe"heatup"and"cooldown" curvesgivenintheTechnical Specifications'urther information onthissubjectisgiveninChapter5oftheFSAR.50.56Thisregulation providesthattheCommission will,intheabsenceofgoodcauseshowntothecontrary, issueanoperating licenseuponcompletion oftheconstruction ofafacilityincompliance withthetermsandconditions oftheconstruction permit.Thisimposesnoindependent obligations ontheapplicant.

50.58Thisregulation providesforthereviewandreportoftheAdvisoryCommittee onReactorSafeguards.

TheACRSisreviewing theoperating licenseapplication forSSESinaccordance withitsusualpractice.

13 50.59TheSusquehanna ReviewCommittee shallreview:aThesafetyevaluation for1)changestoprocedures, equipment, orsystems,and2)testsorexperiments completed undertheprovision of10CFR50.59 toverifythatsuchactionsdidnotconstitute anunreviewed safetyquestion; b.Proposedchangestoprocedures, equipment orsystemswhichinvolveanunreviewed safetyquestionasdefinedinlOCFR50.59; andc.Proposedtestsorexperiments whichinvolveanunreviewed safetyquestionasdefinedin10CFR50.59.

TheSRCshallreporttoandadvisetheSeniorVicePresident

-Nuclearoftheiractivities.

Safetyevaluations ofchangesmadetotheequipment orreviewoftestsandexperiments tocomplywith10CFR50.59 shallbekeptinamannerconvenient forreviewandshallberetainedforatleastfiveyears.SSESwillcomplywiththereporting requirements setforthin10CFR50.59.

50.70TheCommission hasassignedresidentinspectors totheSSES.PPScLhasprovidedofficespaceinaccordance withtherequirements ofthissection.PP&LpermitsaccesstothestationtoNRCinspectors inaccordance with10CFR50.70(b)(3).

50.71Recordsareandwillbemaintained inaccordance withtherequirements ofParagraphs (a)through(e)ofthisregulation andthelicense.Paragraph (e)requiresthattheFSARbeupdated(within24monthsoftheissuanceoftheoperating licenseandannuallythereafter).

Suchupdateswillbemadeinaccordance withthisSection.50.72Notification ofsignificant eventstotheNRCwillbemadeinaccordance withthisregulation.

AppendixAThedetailsofSSEScompliance withGeneralDesignCriteriaisdiscussed indetailintheFSAR,Section3.1.AppendixBChapter17oftheFSARdescribes indetailtheprovisions ofthequalityassurance programwhich14 hasbeenimplemented tomeetallapplicable requirements ofAppendixB.AppendixECompliance with10CFR50,AppendixE,isdocumented throughthePPGLCompanyEmergency PlanforSSES.Thisplanincorporates therequirements ofNUREG0654exceptforsomechangeswithrespecttoTableB-1.Thesechangesarepresently beingreviewedbytheNRCstaff.Theplanhasbeenunderrevisionandwassubmitted totheNRConApril28,1981.Appendices G,HCompliance withAppendices GandHcannotbeevaluated atthistime.InordertoanswerNRCquestions intheseareas,PPM.hasrequested anevaluation byGeneralElectric.

PPSLexpectstoreceivethenecessary information byMay21,1981.Itistheintentoftheevaluation toshowcompliance withtheseregulations.

AppendixIThisAppendixprovidesnumerical guidesfordesignobjectives andlimitingconditions foroperation tomeetthecriteria"aslowasisreasonably achievable" forradioactive materialinlight-water-cooled nuclearpowerreactoreffluents, PPGLhasfiledwiththeCommission thenecessary information topermitanevaluation oftheSSESwithrespecttotherequirements ofSctionII.A,II.B,andII.CofAppendixI.TheSSESapplication forconstruction permitwasdocketedafterJanuary2,1971andpriortoJune4,1976.Nocost-benefit analysisisrequired.

Allcalculated dosesarewithintheAppendixIof10CFR50guidelines.

AppendixJReactorpressureboundaryleakagetestingforwatercooledpowerreactorsisdelineated inthisAppendix.

Theserequirements aregiveninTechnical Specification 3/4.6.1.Additional information concerning compliance canbefoundinFSARChapters3and6.AppendixKCompliance with10CFR50AppendixKisspecifically requiredby10CFR50~46'SCScompliance isdocumented inSection6.3.3oftheSSESFSAR.NEDO-20566 providesacompletedescription ofthemethodsusedtoperformthecalculations.

100.10Thefactorslistedrelatedtoboththeunitdesignandthesitehavebeenprovidedintheapplication.

Sitespecifics, including seismology, meteorology, geology,andhydrology,,

arepresented inChapter215 oftheFSAR.Theexclusion area,lowpopulation zone,andpopulation centerdistanceareprovidedanddescribed.

TheFSARalsodescribes thecharacteristics ofreactordesignandoperation.

100.11Theexclusion area,lowpopulation zoneandpopulation centerdistancearedescribed intheFSAR,Chapter2.Allrequirements ofthissectionwithregardtotheseareasanddistances aremet.TheFSARaccidentanalyses, particularly thoseinChapters6and15,demonstrate thatoffsitedosesresulting frompostulated accidents wouldnotexceedthecriteriainthissectionoftheregulation.

AppendixAStructures andequipment important toplantsafetyareprotected fromordesignedtowithstand allappropriate naturalphenomena attheplantsite.Designisbasedonthemostseverephenomena probablewithspecialconsideration fortheuncertainty inprediction.

Detaileddiscussions ofthephenomena themselves, andhowtheyareappliedtothestructures andequipment, arefoundinthefollowing FSARsections:

Meteorology, Section2.3;Hydrology, Section2.4;Geology,Seismology, andGeotechnical Engineering, Section2.5;Classification ofStructures, Components, andSystems,Section3.2;WindandTornadoLoadings, Section3.3;Wateri,evel(Flood)Design,Section3.4;MissileProtection, Section3.5;SeismicDesign,Section3.7;DesignofCategoryIStructures, Section3.8;Mechanical SystemsandComponents, Section3.9;SeismicQualifications ofCategoryIinstrumentation andElectrical Equipment, Section3.10;andEnvironmental DesignofMechanical andElectrical Equipment, Section3.11.,8C/cak

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