ML18038A334

Forwards Rev 2 to Updated FSAR for Nine Mile Point Unit 2 & Annual Safety Evaluation Summary Rept

ML18038A334
Person / Time
Site:	Nine Mile Point
Issue date:	10/31/1990
From:	WILCZEK S W NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18038A335	List: ML18038A334
References
NMP2L-1258, NUDOCS 9011090077
Download: ML18038A334 (597)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEMt<IREGULATORY XNFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9011090077 DOC.DATE:

90/10/31NOTARIZED:

YESFACIL:50-410 NineMilePointNuclearStation,Unit2,NiagaraMohaAUTH.NAMEAUTHORAFFILIATION WILCZEK,S.W.

NiagaraMohawkPowerCorp.~~j/+~pggRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)

SUBJECT:

ForwardsRev2toupdatedFSARforNineMilePointUnit2annualsafetyevaluation summaryrept.DISTRIBUTION CODE'053D COPIESRECEIVED'LTR lENCL/SIZEJTITLE:ORSubmittal:

UpdatedFSAR(50.71)andAmendments NOTES:DOCETg5041R(sXZ+l~5~DSRECIPXENT IDCODE/NAME PDl-1LAMARTIN,R.

INTERNAL:

ACRSNRR/DST8E2RGN1EXTERNAL:

XHSNSICCOPIESLTTRENCL10112210111111RECXPIENT XDCODE/NAME PD1-1PDAEOQDJ)OA/XRB GF01NRCPDRSAICLINER,RCOPIESLTTRENCL1011111111DDDNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR13ENCL10DD 0

NIAGARAMOHAWKPOWERCORPORATION/301 PLAINFIELD ROAD,SYRACUSE, N.Y.13212/TELEPHONE (315)474-1511U.S.NuclearRegulatory Commission Attention:

DocumentControlDeskWashington, D.C.20555October31,1990NMP2L1258Re:NineMilePointUnit2DocketNo.50-410NPF-6Gentlemen:

Pursuanttotherequirements of10C.F.R.550.71(e) and10C.F.R.550.59(b),

NiagaraMohawkPowerCorporation herebysubmitsRevision2totheNineMilePointNuclearStationUnit2UpdatedSafetyAnalysisReport(USAR)andtheannualSafetyEvaluation SummaryReport.Underseparatecover,wearetransmitting updatestomaterialwhichhaspreviously beengivenproprietary statusbytheNRCpursuanttotheprovisions of10C.F.R.52.790.One(1)signedoriginalandten(10)qopiesoftheUSARRevision2areenclosed.

CopiesarealsobeingsentdirectlytotheRegionalAdministrator, RegionI,and)heNRCResidentInspector atNineMilePoint.TheUSARrevisioncontainschangesmadesincethesubmittal ofRevision1inOctober1989.Includedareanumberofeditorial changes.Thesechangescorrectspellingandtypographical errors;updatereferences toUSARfigures,sections, documents ortablesofcontents; improvegrammarorclarity;ormoveinformation tomoreappropriate locations.

Thecertification requiredby10C.F.R.550.71(e)(2) isattachedtothisletter.Thetextandtablechangesassociated withUSARRevision2havebeenpreparedusinganewtextmanagement systemrecentlyimplemented byNiagaraMohawk.Consequently, theappearance oftheRevision2replacement pagesdiffersslightlyfromtheexistingUSARpages;mostnotably,thetextisnotright-margin-justified.

InNiagaraMohawk'sletterofOctober25,1989(NMP2L1210),transmitting theUpdatedSafetyAnalysisReport(USAR)Revision1,weidentified certainitemsforwhichcompliance andverification effortsassociated withtheUSARupdatewerenotyetcompleted.

Astatusoftheremaining openverification itemswasprovidedinNiagaraMohawk'slettersofNovember29,1989(NMP2L1217)andJanuary30,1990(NMP2L1224).Afinaldisposition foreachofthefourcategories ofopenitemsoriginally identified intheOctober25,1989,letterisasfollows:~C'Ig901109'0077 901031PDRADQCK05000410KPDC I

alI~OPENITEM1DescritionThemajorityofopenverification itemsinvolveinconsistencies inthelevelofdetailshownonUSARfigureswhencomparedtothesourcedesigndocuments.

Theseitemsdonotinvolvequestions ofaccuracy, butwillrequiredevelopment ofstandards andrevisionofalargenumberofdesigndrawingstosatisfyNiagaraMohawk'sinternalverification procedures.

StatusVerification activities associated withthereviewofdrawings, including generalarrangement, communication, shielding, andradiation zonedrawings, havebeencompleted.

Appropriate revisions tothedrawingsandtheassociated USARfigureshavebeenidentified andarebeingprocessed inaccordance withnormalprocedures.

OPEITEM2DescritionSeveralverification itemsrelatingtosetpoints onUSARfiguresarestillbeingcompleted.

Theseitemshaveraisedquestions aboutsetpoints contained intheUSAR.Procedures areinplace,including 10C.F.R.550.59evaluations, toensureadequatecontrolofsetpointchangesintheplant;however,setpoints onlogicsketches(LSKs)intheUSARarenotroutinely updated.Setpoints shownonLSKsareprovidedasguidevaluesandarenotas-built.

Thisisidentified ontheUSARfiguresbynotesthatstate,"Setpoints shownonlogicdrawingsareforlogicclarification onlyandmaybeonlyapproximations oftheactualprocesssetpoints.

Setpointdatasheetsmustbereferredtoforactualprocesssetpoints."

Asmallnumberofthesetpoints intheUSARtextwereoriginally verifiedusingthedesignLSKs.Thereis,therefore, thepossibility thatthesesetpoints arealsonotas-built.

Aprogramisnowbeingdeveloped toverifysetpoints inthetextagainsttheas-builtvalues.StatusAllsetpoints referenced intheUSARtexthavebeenidentified.

Eachidentified setpointhasbeenre-verified againsttheas-builtplantconfiguration byreviewing appropriate sourcedocuments (e.g.,setpointdatasheets).Anynecessary USARchangeshavebeeninitiated andarebeingprocessed inaccordance withnormalprocedures.

1I

~~DescritionSomeitemsfromthisupdate(Revision 1)arestillinthefinalverification process.StatusAllpreviously openverification itemsfromUSARRevisions 0and1havebeencompleted.

Appropriate USARchangeshavebeenincorporated inRevision2.OPENITEM4DescritionSourcedocumentation forchangesdeveloped byGEhadnotbeenavailable, preventing finalverification.

SatusAsstatedpreviously inNiagaraMohawk'sNovember29,1989,letter(NMP2L1217),allGE-developed changeshavebeenverified.

TheenclosedannualSafetyEvaluation SummaryReportcontainsbriefdescriptions ofchangestothefacilitydesign,USAR,procedures, tests,andexperiments.

NoneoftheSafetyEvaluations involvedanunreviewed safetyquestionasdefinedin10C.F.R.550.59(a)(2).

Ifyouhaveanyquestions concerning thisUSARrevision, pleasecontactJohnJ.Laffreyat(315)428-7334.

Verytrulyyours,NIAGARAMOHAWKPOWERCORPORATION S.W.Wilczek,Jr.VicePresident NuclearSupportJJL/kmsEnclosure xc:RegionalAdministrator, RegionIMr.R.A.Capra,DirectorMr.R.E.Martin,ProjectDirectorMr.W.A.Cook,SeniorResidentInspector RecordsManagement v1~l1 UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterof]]NIAGARAMOHAWKPOWERCORPORATION

](NineMilePointNuclearStation]UnitNo.2)]DocketNo.50-410CERTIFICATION S.W.Wilczek,Jr.,beingdulysworn,statesthatheisVicePresident, NuclearSupportofNiagaraMohawkPowerCorporation; thatheisauthorized onthepartofsaidCompanytosignandfilewiththeNuclearRegulatory Commission thiscertification; andthat,inaccordance with10C.F.R.$50.71(e)(2),

theinformation contained intheattachedletterandupdatedFi.nalSafetyAnalysisReportaccurately presentschangesmadesincetheprevioussubmittal necessary toreflectinformation andanalysessubmitted totheCommission orpreparedpursuanttoCommission requirement andcontainsanidentification ofchangesmadeundertheprovisions-of.-$50.59butnotpreviously submitted totheCommission.

S.W.>1czek,Jr.VicePresident NuclearSupportSubscribed andsworntobeforemethrsundayof~C,1990.NotaryPulicDlANER.NlMBALLpub"c5rno SrarsofNrrrrYoredagaCotrmyt3o.493@@Qtrardlod InOnondagaMyCommlsslon Explros Enclosure toNMP2L1258NINENILEPOINT-UNIT2SAFETYEVALUATION SUNNARYREPORTDocketNo.50-410LicenseNo.NPF-69 0

SafetyEvaluation SummaryReportPage1of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:87-063,Rev.1Mod.PN2Y86MX162 Fig.11.4-1aSolidWasteManagement System(WSS)TitleofChange:SealWatertoWasteSludgePumpsDescription ofChange:Anexistingwastesludgetransferpumpwasreplacedwithtwonewcentrifugal slurrypumps(2WSS-P50A 6B).Additional pumpsealwatersupplyandreturnlineswereconnected fromtheexistinglinesforthesecondpump;onenewmanualisolation valvewasprovidedoneachoffourlines.Thischangewaspreviously reportedinletterNMP2L1177,datedOctober26,1988.Anadditional changewasmade,basedonRevision1ofthesafetyevaluation, tominimizewiringchanges.Flowelement2WSS-FE103 wasrelocated toupstreamofvalve2WSS-V308 (fromdownstream) onthesameline.SafetyEvaluation Summary:Thesolidwastemanagement systemisnotsafety-related andisnotrequiredforsafeshutdownoftheplant.Relocation oftheflowelementdoesnotaffectitsoperation asitisstilllocatedonthecommonpumpdischarge piping.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

NOTE:Thissafetyevaluation revisionisbeingreportedatthistimeinsupportofthechangestoUSARFigure11.4-1a,whichwasrevisedinUSARRevision1.

SafetyEvaluation SummaryReportPage2of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:87-118,Rev.1Mod.PN2Y87MZ132 Figures6.2-38(Sh.5),6.2-71a,6.2-71bSystemContainment Atmosphere Monitoring System(CMS)TitleofChange:AddPSIAPressureMonitorforDrywellandSuppression ChamberPressureIndication Description ofChange:0Technical Specification 3/4.6.1.5 requiresdrywellandsuppression chamberinternalpressuretobemaintained between14.2and15.45psia.Previouspressuremonitorsonlyreadoutinpsig.Thismodification addedtwo(2)transmitters andtwo(2)controlroomindicators withpsiascales.Thisnowenablespressuremonitoring intheTechnical Specifications identified scale.Thenewmonitorsareidentified as2CMS*PT178 and2CMS-PT179.SafetyEvaluation Summary:Theaddedequipment ofthismodification onlyperformsamonitoring functionanddoesnotimpactthesafeoperation ofotheroperating equipment.

Nosafety-related functions areaffected.

Althoughitdoesnotperformasafetyfunction, 2CMS*PT178 isdesignedandinstalled assafety-related sinceitshares"acommonsensinglinewith2CMS*PT1A, whichissafety-related.2CMS-PT179 isinstalled asnonsafety-related.

Itsharesasensinglinewith2CMS-PT168.

Thissensinglineutilizesasafety-related excessflowcheckvalvetoprotecttheintegrity oftheprimarycontainment inaccordance withRegulatory Guide1.11.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

0 I4p4'(!qt.I-l~'~Safvaluation

,Sum;;yReport"Page,3of.112j7vafSafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:87-148,Rev.1Mod.PN2Y86MX184 Figures9.3-5j,11.2-1f,11.2-1hSystem:TitleofChange:LiquidRadwasteSystem(LWS)WasteandRegenerator Evaporation ReboilerCleanoutDescription ofChange:Thepipingfromthewasteevaporator reboilerbottomswas3/4"andconnected tovalvesV516,V517,V574andV575.Duringstartup,theselinesbecamepluggedduetosodiumsulfate(NA,SO,)crystallization.

Inordertocorrectthissituation, thepipingsizewasincreased to1-1/2"andthecurrentvalveswerereplacedwithpairsofvalves.Flushconnections werelocatedbetweenthem.Awarmwaterflushlineandhosewerealsoadded.Existingheattracingwasremovedandnewheattracinginstalled.

SafetyEvaluation Summary:Thismodification hasnoeffectonsafeshutdownorsafeplantoperation.

Allmodification workwasperformed inaccordance withtherequirements ofRegulatory Guide1.143.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

I ce>~>S SafetyEvaluation SummaryReportPage4of112SafetyEvaluation No.:Xmplementation DocumentNo.:87-151Mod.PN2Y87MZ187 (Partial)

USARAffectedPages:9.4-45,9.4-6,(sh.4)19(Sh.9.4-2c,32,9A.12~3139.4-46,9.4-47;Tables9.5-1(Sh.8),9.5-2Figures1.2-2,1.2-1),8.3-3(Sh.2),9.4-14(Sh.1),9.5-35g1132g12'112.3-34,12.3-46System:TitleofChange:N/ARelocation ofZ&CShopDescription ofChange:Thismodification isoneofaseriesdesignedforControlRoomenhancements.

Thismodification converted theserviceroom,elev.261'-0"oftheservicebuilding, toanI&Cshop,andproposedadditional worktotheexistingZ&CShopatelev.288'-6"inthecontrolbuilding.

Workcompleted onthenewZGCShopincludedroomfinishing (dropceiling,tilefloor,drywallandpaint),replacement ofexistingheatingandventilation equipment withnewHVACsystem,revisiontoexistingfireprotection watersprinkler systemandassociated electrical work.ProposedworkontheexistingZaCShopincludesroomfinishing andelectrical work.Thisworkisstillinprocess;therefore, thisUSARrevisiononlyreflectsworkcompleted onelev.261'-0"asofApril30,1990.SafetyEvaluation Summary:Thismodification converted theserviceroom,elev.261'-0",toanZaCshopandallowscompletion ofworkonanother.Thismodification doesnotaffectanysafety-related systemsandhas,noeffectonthesafeshutdownofthe,plant.Components addedtotheexistingI&Cshopinthecontrolbuilding(elev.288'-6")arenotseismically supported (i.e.,dropceilingandlighting).

Afailureofsuchcomponents willhavenoimpactsincenosafety-related components arelocatedinthisarea.

SafetyEvaluation SummaryReportPage5of112SafetyEvaluation No.87-151(Continued)

SafetyEvaluation Summary:(Continued)

Fireloadincreases havebeencalculated.

Thismodification doesnotaffecttheAppendixRsafeshutdownanalysis.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage6of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:87-175,Rev.2Mod.PN2Y87MX259 (Partial)

Figure10.1-6aFeedwater System(FWS)Replacement ofPaulMonroeHydraulic Actuators withLimitorque Motor-Operated Actuators, 2FWS-LV10A, 2FWS-LV10B,and2FWS-LV10C Description ofChange:Duetohighfailurerateandmaintenance frequency, theexistingPaulMonroeelectrohydraulic actuators forfeedwater controlvalves2FWS-LV10A, B,CareintheprocessofbeingreplacedwithLimitorque electrically-operated actuators.

Themodification ofeachvalveincludesthefollowing:

1)removalofexistingactuatorandinstallation ofnewactuator, controlpanelandtransformers; 2)reworkexistingconduitsandcablesandinstallnewconduitsandcablesintolocalcontrolpanel,transformers andvalveactuator; 3)revisions tothepositionindication loopwhichrequireschange-out oftransmitter cardforcurrent/voltage converter inpanelP825(Foxborocabinet);

4)minorrewiringinP825;5)theexistingcontrolcircuit,contactor, andoverloads intheaffectedMCCsaretoberemoved,astheMCCshaveonlyathermal/hydraulic magneticbreakerfortheseloads.Thefeedwater controlsystemgainchangelogicisremovedandissetatafixedvalueforallvalveoperations.

Thecavitation interlock andthefeedwater runbacklossofsignalbypassaremaintained inthecontrolcircuits.

USARRevision2reflectstheinstallation ofthemotoractuatoron2FWS-LV10B, whichwascompleted priortoApril30,1990.Thebalanceofthemodification isongoing.

SafetyEvaluation SummaryReportPage7of112SafetyEvaluation No.SafetyEvaluation Summary:87-175,Rev.2(Continued)

Thismodification isnotsafety-related.

Them'odified valvesarelocatedintheturbinebuilding, andnosafety-related equipment willbeimpacted.

Nonewtransients willoccurasaresultofthismodification.

Systemresponsewastestedbothwithandwithoutthegainchangelogicduringpowerascension andwassatisfactory inbothconfigurations.

ThisfixedgainisstandardGEBWRdesign.ThenewdesigndoesnotchangetheresponseofthevalvestoanATWSevent.Basedontheevaluations performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage8of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:88-039,Rev.2Temporary Mod.88-138Nj'ABreathing AirSystem(AAS)Temporary CappingofSafetyValve2AAS-SV126 Discharge LineDescription ofChange:Frequentliftingofsafetyvalve2AAS-SV126 wascausingbreathing airsystemcompressor 2AAS-Cltorunexcessively tomaintainacceptable systempressure.

Theoperating pressureofthecompressor wasoriginally changedto90psigtoprovidegreatermarginoverthesafetyvalvesetpoint.

Thischangewaspreviously reportedinletterNMP2L1239,datedJune11,1990.Duetoinsufficient airvolumeavailability withthecompressor operating at90psig,theoperating pressurehasbeenraisedto9Spsig,andsafetyvalve2AAS-SV126 hasbeendisabledbycappingitsdischarge line.SafetyEvaluation Summary:Disabling safetyvalve2AAS-SV126 allowssystempressurization withoutundulydeteriorating compressor 2AAS-C1.Systemprotection fromover-pressurization withsafetyvalve2AAS-SV126 cappedisprovidedbysafetyvalves2AAS-SV127 and2AAS-SV128, whichhavethesamesetpointandarelocatedjustdownstream.

There,arenovalvesbetween2AAS-SV126 and2AAS-SV127 topreventprotection oftheaffectedportionofthesystem.Thistemporary modification isexpectedtoremainineffectuntilfinalimplementation ofapermanent modification whichiscurrently scheduled forOctober1990.

0 SafetyEvaluation SummaryReportPage9of112SafetyEvaluation No.88-039,Rev.2(Continued)

SafetyEvaluation Summary:(Continued)

Thebreathing airsystem(AAS)isnotsafety-related.

Ztisdesignedtoprovideairsuitableforbreathing atbreathing airstationsforusebyunitpersonnel duringpotential oractualairbornecontamination situations.

Thetemporary modification willhavenoimpactonthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthistemporary changedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage10of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:88-046DRFL12-00766 N//AFuelExtendedLoadLineLimitAnalysis(ELLLA)forCycle1(100%RatedThermalPowerto96%RatedCoreFlow)Description ofChange:Theconfiguration ofthepowerflowmapwasmodifiedtoallowoperation at100%poweratcoreflowslessthan100%ofrated(108.5millionlb//hr).Specifically, operation downtoaminimumof96%ratedcoreflowat100%ratedpowerisallowed,aswellasoperation abovethe100%rodline(asdefinedwithinthesafetyevaluation).

SafetyEvaluation Summary:ThelimitingUSARChapter15transients (Feedwater Controller FailureandLoadRejection withBypassFailure)attheELLLA100%powerintercept point(100%RatedThermalPower,96%ofRatedCoreFlow)areboundedbythelicensebasispoint(104.3%RatedThermalPower,100%RatedCoreFlow).Forequipment out-of-servicepreviously identified, theMCPRlimitisnotaffectedbyELLLAoperation.

Theanalysesresultsalsoshowthatoperation intheELLLAregioniswithinallowable designlimitsforoverpressure protection, stability, LOCA,containment, reactorinternals andATWSevents.Operation ofNNP2withintheELLLAwindowconcurrent withsinglerecirculation loopoperation or2SRVsout-of-service isanunanalyzed condition andis,therefore, notallowed.Basedontheevaluation andanalysesperformed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage11of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:88-059,Rev.1Mod.PN2Y87MX134 9.5-6;Tables9A.3-1(Sh.4),9A.3-6(Sh.5);Figures9.5-3c,9.5-3b,9.5-3a,9A.3-7System:TitleofChange:FireProtection CO~SystemProvideCrossZoneAutoActuation toCO,Zone757SLDescription ofChange:Firezone757SL,aspreviously

designed, requiredonlyonedetectortoactivatetoinitiateCO~suppression intheturbinealternator exciterenclosure.

Thismodification providedcrosszoneactuation tofirezone757SL(changedto757XL).ThispreventsunwantedCO,actuation byrequiring twodetectors (onesmokeandonethermal)tobeactuated.

Thismodification isconsistent withothertotalfloodingCO~systems.SafetyEvaluation Summary:Thismodification preventsasinglespuriousactuation ofadetection loopfrominitiating unwantedCO~flooding.

Theinstallation ofthecrosszoneactuation complieswithNFPAStandards 12,72D,and72E.Thischangetothefiredetection systemdoesnotaffectthesafeoperation orsafeshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage12of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:88-077Mod.PN2Y87MX233 11.3-5;Figures11.3-1a,11.3-1bSystem:TitleofChange:OffgasSystem(OFG)AddSamplePumpstoOffgasH,AnalyzerDescription ofChange:Thismodification modifiestheH~analyzerportionoftheoffgassystemtocorrectidentified problemswiththeoperation oftheinstruments.

Thefollowing changesareincluded:

1)Installation ofasamplegasconditioning system,upstreamofthehydrogenanalyzers 20FG-AT16A/'B andupstreamof20FG-AT115,tocontrolmoisturecontentofthesample.2)Installation ofanaireductorinthecommondischarge lineofthesubjectH,analyzers tomaintainapositiveflowtotheanalyzers, thusassuringsamplecapability.

Threeflowswitchesandannunciation areaddedtoprovideindication whenflowandsamplecapability islost.Amanualpressurecontrolvalveandalocalpressureindicator areinstalled ontheairsupplylinetotheeductor.Acheckvalveisalsoinstalled ontheairsupplylinetopreventcrosscontamination fromtheoffgastotheinstrument airsystem.3)Relocating theH2sampledischarge lineconnection, including anewrootvalve,furtherdownstream ofthefreeze-out dryerstoalleviate problemswithfreezingoftherootconnection.

Theexistingrootvalve(V25)iscappedin-place.

SafetyEvaluation SummaryReportPage13of112SafetyEvaluation No.88-077(Continued)

SafetyEvaluation Summary:Thismodification tothenonsafety-related offgassystemenablesittoproperlymonitorhydrogenconcentration asrequired.

Thisdoesnotaffecttheoperation ofanysafetysystemsanddoesnotaffectthesafeoperation orshutdownoftheplant.Thereleaseratesoftheoffgassystemarenotaffected.

Thenewinstrument airsupplytotheH,analyzerdischarge linedoesnotimpactthecapabilities oftheinstrument airsystem,andprovisions, havebeenmadetopreventcross-contamination fromtheoffgastotheinstrument airsystem.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage14of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:88U-110EE-80SeriesDrawingsFigures9.5-5through9.5-39Communications SystemsPlantCommunications PlansDescription ofChange:ThischangerevisestheUSARcommunication planfiguresbasedonthereissuance oftheassociated sourceengineering drawings.

Thereissueddrawingsincorporate changestoresolvecommentsresulting fromtheindependent verification reviewconducted byNiagaraMohawk'sinternalNuclearCompliance andVerification group(partially satisfies thecommitment madeinItem1ofNMPCletterNMP2L1217,datedNovember29,1989).Thesechangesaffectonlythebackground detailshownonthedrawings, anddonotinvolveanyactualchangestocommunication systemsdevices.SafetyEvaluation Summary:TherevisedUSARcommunication planfiguresdepictanincreased levelofbackground detail,butdonotinvolveanyactualchangestocommunications equipment suchashandsets,

speakers, amplifiers, strobelights,jacks,ortelephones.

Sincetheeffectiveness andreliability ofthecommunications systemsisnotdiminished, thesedrawingchangesdonotinvolveanunreviewed safetyquestion.

NOTE:SafetyEvaluation 88U-110isbeingreportedagainatthistimetoaddressthereissuance ofthesourceengineering drawings.

Alladditions/relocations ofcommunications systemsequipment havebeenaddressed inSafetyEvaluation 88U-110andwerepreviously reportedinNMPCletterNMP2L1198,datedApril28,1989.

SafetyEvaluation SummaryReportPage15of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:88U-121,Rev.1LDCNsU-1295,U-1296ListedBelowSuppression PoolHydrodynamic

Analysis, HighEnergyLineBreakWhip/JetImpingement Evaluations, SpentFuelPoolStorageRacksTitleofChange:Miscellaneous Figures-UpdatingDuetoSourceVerification Description ofChange:Thismodification describes changestoFSARfiguresresulting fromsourcedocumentverification.

Wheresourcedocuments (drawings, calculations, etc.)havebeenrevisedorsuperseded, thefigureshavebeenupdatedtoreflectthechanges.Thissafetyevaluation waspreviously reportedinletterNMP2L1198datedApril28,1989.Additional corrections/updates havebeenmadeforthefollowing:

Page6A.2-9Figures3.6A-56,-57,-58,-60Figure6A.1-3Figure6A.2-6,-7Figure6A.4-39Figure9.1-3SafetyEvaluation Summary:Theidentified USARchangesareduetorevisions/superseding ofdrawingsorcalculations.

Thesechangesdonotinvolveanyactualplantchanges,donotaffectplantperformance orreliability, andhavenoimpactonstationprocedures.

Basedontheevaluation performed, itisconcluded thattheseUSARchangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage16of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:88U-323LDCNU-108112'9g12'10'2313'2.3-15; Figures12.3-1through12.3-66System:TitleofChange:N/AEditorial ChangestoUSARSection12.3Description ofChange:Variouseditorial changesaremadeinUSARSection12.3.Thesechangesaremadeforclarityandtomaintainconsistency betweenthetextandfiguresofSection12.3.SafetyEvaluation Summary:Theidentified USARchangesareeditorial innatureanddonotaltertheplantdesignbasis.Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage17of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-004EDC2E00130Figure6.2-38,Sheet10Containment Monitoring System(CMS)TitleofChange:SetpointChangetoSuppression PoolHighTemperature AlarmDescription ofChange:Thesetpointforthesuppression poolhightemperature alarmhasbeenincreased from82.5'Fto85'F.Thisprovidesadditional marginabovecurrentoperationally experienced summersuppression poolwatertemperatures, whichhavecausedconstantalarmingconditions.

SafetyEvaluation Summary:Thissetpointchangewillreducethesuppression poolwaterhightemperature alarms,receivedduringnormaloperation, withoutaffecting thesafeoperation orshutdownoftheplant.Sufficient marginisstillmaintained toallowinitiation ofRHRsuppression poolcoolingpriortoexceeding theTechnical Specifications limitof<904F;thus,theinitialsuppression pooltemperature of90'Fusedintheaccidentanalysisismaintained.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage18of112SafetyEvaluation No.:Implementation DocumentNo.:89-007Calculations MS-1722,Rev.1;MS-1126,Rev.2;MS-168S,Rev.1;MS-1424,Rev.4;PZ-002AK, Rev.1USARAffectedPages:System:TitleofChange:36A15'6A16'033Exclusion AreaPipingFSARSection3.6ARevisionDescription ofChange:Intheprocessofresolving problemswithmainsteamlineflooding(LER88-01),adiscrepancy betweentheFSARtextinSection3.6AandQuestionaResponseF210.17Awasfound.TheresponsetotheQ&Rstatedthatthedesignofpipeintheexclusion areametBranchTechnical Position(BTP)MEB3-1requirements.

MEB3-1specifies therequirements forallpipinginthe"exclusion area"betweencontainment andtheinboardoroutboardisolation valves.However,Section3.6Adescribed exceptions takentorequirements ofMEB3-1forcertainevaluations inthatitdidnotaddressnon-nuclear piping.Inresponsetothisdiscrepancy, calculations wererevisedtodemonstrate compliance withMEB3-1forClass3andnon-nuclear pipinginthe"exclusion area."ThisresultsintherevisedSection3.6Abecomingconsistent withtheQSRresponse.

SafetyEvaluation Summary:Therevisedcalculations indicatethatthepipinginquestionmeetshigherstandards thanindicated intheFSAR.Therefore, thechangestotheFSARindicatethatthedesignismeetingmorestringent requirements, therebyenhancing safety,andcontainsadditional conservatism inthedesign.Thus,thischangedoesnothaveanyaffectonthesafeoperation ofanysystemorsafeshutdownoftheplantanddoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage19of112SafetyEvaluation No.89-007(Continued)

SafetyEvaluation Summary:(Continued)

NOTE:Thissafetyevaluation isbeingreportedatthistimeinsupportofthechangestoUSARSections3.6Aand10.3,whichwereincorporated inUSARRevision0.

SafetyEvaluation SummaryReportPage20of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-009Temporary Modification N/ALiquidRadioactive WasteSystem(LWS)TitleofChange:Temporary Filtering Systemat2LWS-PI88B Description ofChange:Anacidspilloccurredinthecondenser areaoftheturbinebuilding.

Theacidreactingwithconcrete, paint,metal,etc.,introduced awastesolutionofapproximately 30%solidsandorganicmaterials, intothefloordrainsystem.Effluentfromthefloordrainsystemisprocessed bytheliquidradioactive wastesystem(LWS).Thefloordrainfiltering systemintheradwastebuildingisdesignedtoprocessawasteeffluentof2%solidsandorganicmaterials.

Collected drainageispumpedfromthefloordraincollector surgetank(2LWS-TK17),

tobeprocessed bytheLWSsystemthroughsurgepump2LWS-P17A/B.

Thistemporary modification providesforthetemporary removalofpressureindicator 2LWS-PI88B toallowtheinstallation ofa3"flexhosefromthedischarge sideofpump2LWS-P17B toaLondonNuclearFiltering System.TheLondonFiltering Systemprovidesanadditional filtering processintothissystemwhichremovesthemajorityofthesolidsandorganicmaterials priortoreturning theeffluentintothedesignedregenerant wastetank/evaporator systemandfurtherfiltering if/asrequired.

SafetyEvaluation Summary:Thistemporary modification providesanadditional filtering systemtopreventdamagetoLWSequipment following theunexpected acidspillandallowthenonsafety-related LWSsystemtoperformitsdesignfunction.

Thisdoesnotaffectthe

SafetyEvaluation SummaryReportPage21of112SafetyEvaluation No.:89-009(Continued)

SafetyEvaluation Summary:(Continued) operation ofanysafetysystemsorcomponents.

Thepressureindicator (PI88B)thatistemporarily removedisforlocalpumpdischarge pressureindication anddoesnotperformanycontrolorprotective functions fortheLWSsystemorpump2LWS-P17B.

Basedontheevaluation performed, itisconcluded thatthistemporary changedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage22of112SafetyEvaluation No.:"Implementation DocumentNo.:USARAffectedPages:89-014,Rev.1Mod.PN2Y88MX093 (Partial)

Figures9.2-1q,9.2-6a,9.2-17b,9.3-1hSystem:TitleofChange:N/AUnit2Chemistry Lab/Counting RoomDescription ofChange:Thismodification convertstheexistingcontaminated toolstorageroom(elevation 261'econtamination area,radwastebuilding, Unit2)intobothachemistry laboratory andacountingroom.Thechangesincludeinstallation ofcountingroom/chemistry labequipment insupportofroutinewaterchemistry surveillance atUnit2,andtheadditionofanairconditioning unittotheroomtomaintaindesiredenvironmental conditions.

USARRevision2reflectsportionsofthemodification completed priortoApril30,1990.SafetyEvaluation Summary:Thismodification addsanewchemistry labandcountingroomtorelievepersonnel congestion andimproveavailability andconvenience offacilities forUnit2Chemistry personnel.

Thisfacilitydoesnotperformasafetyfunction.

Postaccidentsamplingandanalysiswillnotbeperformed inthisfacility.

Theinstallation ofthislaboratory willnotaffectanysafetysystemsorcomponents andwillnotaffectthesafeoperation orshutdownoftheplant.Theinstallation ofthisfacilitycomplieswithexistingdesignandconstruction specifications andcodes.Potentially contaminated andchemicalwastewillbeprocessed throughtheexistingdrainsystemsandradioactive wasteprocessing facilities.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage23of112,SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-016,Rev.1N//AN/ADieselGenerator Ventilation System(HVP)TitleofChange:RemovePowerfrom2HVP*MOD1B and2HVP*MOD6B; 2HVP*MOD1B tobeOpenedand2HVP*MOD6B tobeClosedDescription ofChange:Thistemporary modification de-energizes motor-operated dampers2HVP*MOD1B and2HVP*MOD6B bytheremovalofpower.2HVP*MOD1B damperwillbeintheopenpositionwhile2HVP*MOD6B damperwillbeintheclosedposition, whichwillmaintaincompliance withthedieselgenerator emergency coolingcriteriabyensuringacoolingrateconsistent withtherequirements foremergency coolingwhiletheemergency dieselsareoperating.

SafetyEvaluation Summary:Theremovalofpowerfrom2HVP*MOD1B, withthepositioning ofthedamperintheopenposition, andtheremovalofpowerfrom2HVP*MOD6B withitsdamperpositioned intheclosedposition, willpreventactuation ofthesedampers.Uponanautomatic startsignaltotheemergency dieselgenerator (2EGS*EG3),

fans2HVP*FN1B a2HVP*FN1D exhaustismodulated betweentheexhaustdamper(2HVP*MOD1D) andtherecirculation damper(2HVP*MOD6D).

Themodulation ofthedampersassociated with2HVP*FN1D willmaintainacoolingrateconsistent withthethermalloadtomaintainthedieselgenerator (EG3)roomtemperature withinprescribed limitsduringoperation ofdieselgenerator 2EGS*EG3(Div.II).Therearenotripfunctions associated withthistemporary modification.

SafetyEvaluation SummaryReportPage24of112SafetyEvaluation No.:89-016Rev.1(Continued)

SafetyEvaluation Summary:(Continued)

Thistemporary modification willremovesafety-related components fromservicebutwillnotaffectthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage25of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-017Temporary Mod.89-059N/ACirculating WaterAcidTreatment SystemTitleofChange:Manual,DirectAcidInjection toCirculating WaterDescription ofChange:Duetomaintenance andrepairs,thecirculating wateracidsystemisinoperative, thusrequiring analternate methodofsupplying acidtothecirculating watersystem.Acidinjection willbeperformed atthecoolingtowerthroughtheuseofacommercial tanktruckandatemporary headerinstalled acrossthedischarge flumes.Thenormalinjection portionoftheacidsystemwillremaininoperative duringthetimethistemporary modification isinplace.However,monitoring instrumentation willbeavailable tocheckandrecordwaterpH.SafetyEvaluation Summary:Acidtreatment ofthecirculating waterisutilizedtomaintaincleanheatexchanger surfacesandtopreventbiological growthwithinthecirculating watersystemscondenser.

Thistemporary modification providesanalternate methodofperforming anonsafety-related functionthatwillnotimpactthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage26of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-019,Rev.1Temporary Mods89-061,89-062N/AMiscellaneous Equipment andFloorDrainsSystemTitleofChange:Temporary Mod.toSteamLineDrainValves2DTM-AOV128 and2DTM-AOV144 Description ofChange:Thistemporary modification removestheelectrical interlocks betweenvalves2ASS-STV112 and2DTM-AOV144, andbetweenvalves2ASS-STV143 and2DTM-AOV128, byliftingorjumpering leadsinthecontrolroom.Removaloftheseinterlocks allowsisolation ofdrainpathsthathadallowedextraction steamtoflowthroughdrainlinestothemaincondenser, resulting inalossofplantefficiency.

SafetyEvaluation Summary:Steamsupplylinedrainsremoveanycondensate build-upfromthelines.Drainlinevalves2DTM-AOV128 and2DTM-AOV144 opentoprovideadditional drainagecapacityrequiredduringlowpressureoperations andshutdownconditions.

Thenormaldrainlinepathwillstillprovidefortheremovaloflowpointcondensate fromthesteamsupplylinesduringfullpoweroperations.

Additional automatic valvecontrolstoopenthevalvesatturbinelowpressurewillbefunctional, andmanualcontrolisavailable throughcontrolswitchesinthecontrolroom.Thedrainvalvesandtheirassociated electrical interlocks arepartoftheturbinebuildingmiscellaneous drainssystem.Thisisanonsafety-related systemandisnotrequiredforsafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage27of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-020Temporary Mod.89-063N/AReactorRecirculation SystemReactorRecirculation PumpsVibration Monitoring PersonalComputerDescription ofChange:Thistemporary modification consistsoftheinstallation ofacomputerworkstation,adjacentandconnected tovibration monitoring panel2RCS-PNL100, toprovidecontinuous, remote,on-linemonitoring oftheNMP2reactorcoolantrecirculation pumps2RCS*P1Aand2RCS*P1B.

Thesystemwillreceivepowerfromalocal120Vconvenience outlet.Atemporary telephone linehook-upwillbeinstalled toprovideremoteaccesstothisinformation tositepersonnel andGeneralElectric-SanJose,eliminating theneedforfrequentaccesstorestricted areasoftheplant.SafetyEvaluation Summary:Thereactorcoolantrecirculation pumpvibration monitoring programisusedfordetecting lossofwearringboltingintegrity, performing short-andlong-term

trending, andwillserveasabasisforscheduling maintenance andrepairinatimelymanner.Thevibration monitoring systemisnotrequiredforthesafeoperation orshutdownoftheplant.Failureofequipment installed underthistemporary modification wouldnotjeopardize orchallenge plantsafetysystems.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage28of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-021,Rev.1Temporary Mod.89-066N/AServiceWaterSystemControlRoomChillerInletTemperature Control-Temporary SetpointChangeto2SWP*TSL91A(B)

Description ofChange:Servicewatertoeachcontrolbuildingchilledwatercondenser containsarecirculation loopwithapump(2SWP*P2A and2SWP*P2B).

Thesepumpsworkinconjunction withthetemperature controlvalveslocatedinthechillerreturnlinestomaintaintheservicewaterinlettemperature tothechillersabove60'F.Currently, thelogicassociated withtheservicewatersystemprovidesforastartsignalfor2SWP*P2A(B) whenservicewatertemperature decreases toanupperlimitof63'Fandalowerlimitof60'F.Thistemporary modification willallowincreasing thesetpointrangeforthecondenser waterpumps2SWP*P2A(B) toanupperrangeof754Fandlowerrangeof724F.SafetyEvaluation Summary:Thistemporary changetothesetpointfor2SWP*TSL91A(B) willaddadditional coolingcapability tohelpmaintainControlRoomenvironment.

Aslongastheservicewatertemperature enteringthechillerislessthan82'F,thereisnoimpactonstationoperation.

Inaddition, theservicewateroutlettemperature ofthechillerswillbemonitored onashiftbasiswhenservicewatertemperature isgreaterthan70'F.Iftheoutlettemperature reaches82'F,andthe2SWP*P2A(B) arestillinservice,thentheoperatorshallsecurethepumps.Operatoractionthusensuresthechillerinlettemperature doesnotexceed824F.

SafetyEvaluation SummaryReportPage29of112SafetyEvaluation No.:89-021Rev.1(Continued)

SafetyEvaluation Summary:(Continued)

Basedontheevaluation performed,'t isconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage30of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:89-022RMUNo.052578N/ASystem:TitleofChange:ControlBuildingHVACSystemTemporary ChangetoAllowOptionalOperation ofControlRoomReturnDuctHeaters2HVC*CH11A/B and2HVC*CH12A/B Description'f Change:Ductheaters2HVC*CH11A/B, CH12A/Bheatthereturnairtotheairconditioning unitswhenthetemperature intheControlRoomdecreases to40degreesFahrenheit.

Thistemporary changeeliminates theneedfortheautomatic controlling ofheaters2HVC*CH11A/B, CH12A/Bwhenclimaticconditions existsuchthatsupplemental heatingofthereturnairtotheControlRoomHVACsystemisnotrequired.

Thisisdesirable to(1)performmaintenance ontheheatersand(2)eliminate unnecessary cyclingoftheairconditioning units.SafetyEvaluation Summary:Asindicated intheFSAR,thepurposeoftheControlRoomairreturnductheatersistomaintainairreturning fromtheControlRoomabove40degreesFahrenheit.

Therefore, aslongastheControlRoomtemperature canbemaintained above40degreesFahrenheit, thereisnoimpactonstationoperation.

Basedontheevaluation performed, itisconcluded that,thistemporary modification doesnotinvolveanunreviewed safetyquestion.

45V SafetyEvaluation SummaryReportPage31of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-024,Rev.1N/A9.4-40,9.4-42TurbineBuildingVentilation System/Effluent Monitoring Operating withtheTurbineBuildingRoofVentsOpenDescription ofChange:Thischangeallowstheturbinebuildingroofventstobeopenedforintermittent periodsduringnormalplantoperation toprovideadditional coolingofthemainsteamtunnelandturbinebuilding.

Thismodification isbeingimplemented topreventinadvertent orspuriousMSIVisolation asaresultofhighoutsideairtemperature.

Duringmid-July1989,highoutsideairtemperatures causedthetemperatures inthemainsteamtunneltoreachthehighalarmsetpointonseveraloccasions.

Thetripsetpoint(Technical Specifications limit)wasreachedononeoccasion, causingahalfisolation.

Becausetheturbinebuildingismaintained atsubatmospheric pressures, asdiscussed inFSARSection9.4,byopeningtheturbinebuildingroofvents,cooleroutsideairwillbedrawninandthroughthebuilding, eventually beingexhausted throughthemainstackviathenormalturbinebuildingventilation system.Coolingtheturbinebuildingwillresultincoolingthemainsteamtunnel.SafetyEvaluation Summary:TheturbinebuildingHVACsystemhasnosafety-related function.

Failureormalfunction ofthesystemwillnotcompromise anysafety-related systemorcomponent orpreventsafereactorshutdown.

Theturbinebuildingisnotclassified asa

SafetyEvaluation SummaryReportPage32of112SafetyEvaluation No.89-024,Rev.1(Continued)

SafetyEvaluation Summary:(Continued) containment structure.

However,theturbinebuildingventilation systemisdesignedtoexhaustmoreairfromthebuildingthanisbeingsupplied, therebymaintaining asubatmospheric pressuretoinhibittheexfiltration ofcontaminants.

Theopenturbinebuildingroofventsarenotconsidered asadditional radioactive releasepoints.Provisions aremadetoensurethattheopenturbinebuildingroofventsdonotprovideapotential forunmonitored effluentreleasesduringnormaloperation, andtoensurethatthereleasesofactivitytotheenvironment willnotdifferfromthoseanalyzedinFSARSection11.3.3andAppendix11A.ThedesignbasismainsteamlinebreakandoffgassystemfailureanalysesinFSARChapter15envelopetheconsequences ofadesignbasisaccidentoccurring whiletheturbinebuildingroofventsareopen.Loweringthemainsteamtunnelandturbinebuildingtemperatures willnotadversely affecttheabilityofthemainsteamtunneltemperature monitorstodetectamainsteamlinebreak.Basedontheevaluations performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

1 SafetyEvaluation SummaryReportPage33of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-025Mod.PN2Y88MZ093 N/AEssential LightingSystemTemporary MarkupofTwoEssential LightingCircuitsinPanel2LAN-PNLU01 Description ofChange:Thistemporary changedisabledtwoessential lightingcircuitsinordertofacilitate installation oftwonewessential lightingcircuitsandtoavoidworkinginahighradiation areawheninstalling thenewcircuits.

Theegress/essential lightingwasdisabledinthefollowing areas:condensate storagebuilding, radwasteswitchgear room,dirtyworkshop, sampleroom,largetoolandequipment decontamination area,andradwastecontrolroom.SafetyEvaluation Summary:Thedisabling oftheessential lightingcircuits138and540willnotaffectthesafeshutdownoftheplantsincetherearenosafety-related components locatedinthecondensate storagebuilding, theradwasteswitchgear room,thedirtyworkshop, thesampleroom,thelargetoolandequipment decontamination areaandtheradwastecontrolroom.Intheeventofalossofnormalpower(LOP)whilethesetwoessential lightingcircuitsarede-energized, thereferenced areaswouldbecompletely inthedark;however,sincetheoutagesarebriefinduration, thelikelihood ofexperiencing acoincident LOPisremote.Basedontheevaluation performed, itisconcluded thatthistemporary changedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage34of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-026Temporary Mod.88-74N//ACirculating WaterSystem(CWS)RemoveTemperature Element2CWS-TE10B Description ofChange:Thistemporary modification removesoneoffourtemperature elements(2CWS-TE10B) locatedonthetube-side discharge ofthemaincondenser, inthe72inchcirculating waterline2CWS-072-405-4.Thischangewasnecessary duetotemperature elementfailureandlackofavailability ofareplacement.

SafetyEvaluation Summary:Thecirculating watersystemisnonsafety-related andisnotrequiredforsafeoperation orshutdownoftheplant.Thethreeremaining temperature elementswillstillprovidetheirindividual computerpointsignals.Therearenoalarms,controls, orisolation functions associated withthecondenser tubesidedischarge temperature elements.

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage35of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-028,Rev.1Temporary Mod.89-71N/AContainment Monitoring System(CMS)TitleofChange:SampleTemperature forContainment Radiation MonitorDescription ofChange:Thistemporary modification installed threethermocouples torecordprocesstemperatures ononeofthecontainment atmosphere radiation monitors(2CMS*CAB10B).

Thethermocouples wereinstalled inplaceoftwosamplevalvesandonecalibration testvalve.Datacollected fromthethermocouples istobeusedtodesignmodifications toeliminate condensation ofmoistureinthemonitorprocessstream.SafetyEvaluation Summary:Thisinstallation ofthermocouples inplaceofthetwosamplevalvesandtheonecalibration testvalvewillnotaffecttheoperation oftheradiation monitor.Theradiation monitorremainsoperational forthefollowing reasons:1)Removalofthevalvesdoesnotaffectthefunctionoftheradiation monitortomonitortheprimarycontainment forairborneparticulate radioactivity andairbornegaseousradioactivity.

2)Chemistry procedure N2-CSP-7V canbetemporarily revisedsothatgrabsamplesoftheprimarycontainment atmosphere canbetakenattheradiation monitor,ifrequired.

3)Thefunctiontocalibrate thegasradiation detectorisnotchangedwhenoneofthecalibration testvalvesisremoved,sincecalibration isactuallyaccomplished byremovingthedetectorfromtheskid.

SafetyEvaluation SummaryReportPage36of112SafetyEvaluation No.89-028,Rev.1(Continued)

SafetyEvaluation Summary:(Continued) 4)Theintegrity ofthepressureboundarywillbemaintained bytheuseofseismically-qualified components.

Theprimarycontainment atmosphere radiation monitors2CMS*CAB10AJ'B provideonlyindication andalarmfunctions.

Intheeventofanaccident, thesemonitorsareisolatedfromprimarycontainment andwouldnotaffectthesafeshutdownofthereactor.Thesemonitorsarenotusedforpost-accident monitoring.

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage37of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-030Temporary Mod.89-050N/AOffgasSystem(OFG)OffgasH,SamplingDischarge LineRevisionDescription ofChange:Toenableproperoperation oftheOffgasH,Samplingsystem,thistemporary modification revisestheH~samplingcommondischarge lineconnection totheoffgasprocessstreamsincethepresentlineconnection (20FG-V290) istoorestrictive.

Stainless steeltubing(1/2")isrunfromathreadedconnection upstreamofvalve20FG-V290 toanexisting3/4"globeventvalve(20FG-V188),

whichislocatedapproximately sixfeetfurtherdownstream fromthepresentdischarge lineconnection.

Additional heattracingandinsulation arealsoprovidedtopreventfreezing.

SafetyEvaluation Summary:Thistemporary modification willmodifythenonsafety-related offgassystemtoenableittoproperlymonitorthehydrogenconcentration.

Theinstallation ofthistemporary modification willnotcompromise theintegrity oftheoffgassystemandisconsistent withthedesignintentoftheH~samplingsystem,asdescribed inUSARSections11.3.1,11.3.2andFigures11.3-1aand11.3-16(whichhavebeenmodifiedbyModification PN2YMX233 andSafetyEvaluation 88-077).Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage38of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-042Temporary Mod.89-078N/AServiceWaterSystem/Process andEffluentRadiological Monitoring andSamplingTitleofChange:ServiceWaterSamplingTapDescription ofChange:Duringrepairstoradiation monitor2SWP*CAB146A, thischangeinstalled atemporary sampletapfromservicewatereffluentline2-SWP-002-405-4.

Anabandoned conductivity element,2SWP-CE144A, wasremovedandasamplinglinerunfromitslocation.

Thelineconsisted ofapproximately 30feetofTygontubingandashutoffvalve.Theinstallation ofaservicewatersamplelineprovidedaconvenient andaccessible locationfromwhichtotakegrabsamplesrequiredbytheTechnical Specifications forcontinued operation withachannelofservicewatereffluentradiological monitoring outofservice.Accessing theusuallocationfortakinggrabsampleswasconsidered tobeahazardtopersonalsafety.SafetyEvaluation Summary:Thistemporary modification willsupporttheverification thatservicewaterradioactive levelsarewithinTechnical Specifications limits.Itwillnotimpactthesafeoperation orshutdownoftheplant.Thesamplelineinstallation isnon-safetyrelated.Effectsofabreakinthesamplelineorfailureoftheshutoffvalvehavebeenconsidered.

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage39of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-043Temporary Mod.2087N//ASolidRadioactive WasteManagement System(WSS)TitleofChange:Temporary SamplePointforEvaporator BottomsDescription ofChange:Thismodification providesatemporary samplepointinthesolidradioactive wastemanagement system(WSS)atthevalve(2WSS-V714)providedforsystemflushing.

Theblindflangedownstream of2WSS-V714 hasbeenremovedandasamplingvalveaddedinitsplace.Thetemporary samplepointoffvalve2WSS-V714 isneededbecauseitisfeltthatnon-representative samplesarebeingobtainedatthedesignedlocationduetocloggingofthesampleline.SafetyEvaluation Summary:Thistemporary modification istoanonsafety-related system.Thischangewillpermitsamplingofevaporator bottomsatalocationotherthanthedesignedshieldedlocation(2WSS-SA119).

AlthoughALARAlong-term concernsexistatthetemporary non-shieldedlocation, itisdeemedacceptable forashortdurationsince,atthisearlystageofplantoperation, theradiation levelshavenotyetrisentothelevelsexpectedastheplantages.Systemoperating procedures havebeenrevisedtorequireevaluation ofradiation levelspriortoutilizing thetemporary samplepoint.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage40of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-045Temporary Nod.89-76N/ARadwasteBuildingHVACSystem(HVW)TitleofChange:RecordAirFlowat2HVW-CAB196and2HVW-FI115 Description ofChange:Thistemporary modification recordstheairflowforcontinuous airborneradiation monitor2HVW-CAB196.

Also,aflowtransmitter hasbeeninstalled inparallelwithflowindicator 2HVW-FI115, viatheinstrument linedrainvalvesat2HVW-FI115, forthepurposeofrecording airflowintheequipment exhaustduct.Thepurposeofthistemporary modification istogatherdatatodetermine therootcauseofthenumerousflowalarmsthathavebeenexperienced forradiation monitorswhichhavegasflowcontrols.

SafetyEvaluation Summary:Thecontinuous airmonitor2HVW-CAB196 andflowindicator 2HVW-FI115arenonsafety-related.

2HVW-CAB196 isacontinuous airbornemonitorwhichmonitorstheairintheradwasteequipment exhaustsystemduct.ItisusedfortrendingonlyandhasnoTechnical Specifications basis.Theflowelementfor2HVW-FI115 islocateddownstream ofthefiltersandfansfortheequipment exhaustsystem.2HVW-FI115 isalocalindicator only.Itprovidesnocontrolnordoesitprovideanyalarms.

SafetyEvaluation SummaryReportPage41of112SafetyEvaluation No.89-045(Continued)

SafetyEvaluation Summary:(Continued)

Thetemporary recording ofairflowswillnotaffecttheoperation oftheequipment exhaustsystem.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage42of112SafetyEvaluation No.:Implementation DocumentNo.:89-048Technical Specification Table4.8.1.1.2-1 USARAffectedPages:System:Table1.8-1,page122of169DivisionI,II,andIIIDieselGenerators TitleofChange:DieselGenerator Testing,Regulatory Guide1.108Description ofChange:Thischangecorrectsaninconsistency betweenTechnical Specifications Table4.8.1.1.2-1 andUSARTable1.8-1,page122of169,regarding thedieselgenerator testschedule.

TheUSARcommitment toRegulatory Guide1.108Rev.1,regulatory positionC.2.d,isinconsistent withthereferenced Technical Specifications tableanddoesnotreflectrecentindustryconcernsoverfaststartsfordieselgenerators.

SafetyEvaluation Summary:ThischangetotheUSARmakestheUSARconsistent withtheTechnical Specifications and'eflects testingrequirements whichminimizedieselenginemechanical stressandwear.ThisUSARchangeisadministrative innatureanddoesnotaffectthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage43of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-054EDC2M00287Figures9.3-1c,9.3-1j,9.3-1k,9.5-lc,9.5-1e,9.5-if,9.5-1g,'9.5-1h FireProtection WaterSystem(FPW),ServiceAirSystem(SAS)TitleofChange:AssignNewEquipment NumbersforFireProtection AirRegulators Description ofChange:Airpressureregulator units2FPW-REG1through8werepreviously showninthefireprotection water(FPW)systemonP&IDs43C,E,F,andH.Theseregulator unitswereprovidedbytheinstalling sprinkler contractor.

Thesinglecomponent (regulator) shownontheP&IDswasactuallyseveralindividual components (isolation valves,bypassvalves,checkvalves)inadditiontotheregulator.

Theunidentified valveshavebeenassignednewequipment partnumbersinordertoprovidepositiveidentification inprocedures, valvealignments andmaintenance requests.

Thisrequiresthatthesecomponents beaddedtosystemP&IDs.Theairpressureregulators havebeenre-identified aspartoftheSASsystemandareremovedfromFPWsystemP&IDsforconsistency.

SafetyEvaluation Summary:Thischangedoesnotaddormodifyexistingplantsystemsoroperation, butmerelyaddsadditional detail'oexistingdesigndocuments.

Itdoesnotaffectthedesignoroperation oftheSASorFPWsystemanddoesnotaffectsafeshutdownoftheplant.

I SafetyEvaluation SummaryReportPage44of112SafetyEvaluation No.89-054,(Continued)

SafetyEvaluation Summary:(Continued)

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage45of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-059EDC2E10072Fig.5.1-2aNuclearBoilerInstrumentation SystemTitleofChange:NuclearBoilerInstrumentation SystemModifications Description ofChange:Thismodification revisesUSARFigure5.1-2atocorrectthealarmannunciator windownumberforreactorvesselhighpressure, andtoaddthecomponent identification numberforthesteamdomepressureindicator 2ISC-PI1108.

Thesechangescorrectinconsistencies betweentheUSARfigureandas-builtparentdocuments.

SafetyEvaluation Summary:ThechangestoUSARFigure5.1-2aareeditorial corrections/

clarifications, anddonotinvolveanyphysicalchangestotheplant.Thesechangesdonotadversely affecttheabilityofanysafety-related systemsorcomponents toperformtheirsafetyfunctions.

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage46of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-060,Rev.2N/AN/AMiscellaneous Buildings FloorDrainsSystem(DFM)Operation ofNMP2WaterTreatment BuildingSumpsasaContaminated SystemtoSupportSystemDecontamination Description ofChange:Thissafetyevaluation addresses theuseofthesumpsysteminthewatertreatment building(northannextothescreenwell building) ascontaminated.

Thisevaluation includesalldecontamination effortsrelatedtothepresentcontamination, butdoesnotincludeitslongtermroutineoperation tosatisfyoriginaldesignconsiderations.

Theextentofcontamination includessumps5,6,and7,sumppumpI7,associated linesandtrenches, andpartofthefloorofthewasteneutralizer tankcubicle.Noequipment isbeingadded,deletedormodifiedinconjunction withthisevaluation.

SafetyEvaluation Summary:Thisevaluation wasperformed inaccordance withZ.E.BulletinNo.80-10,"Contamination ofNon-Radioactive SystemandResulting Potential forUnmonitored, Uncontrolled ReleaseofRadioactivity toEnvironment."

Thewatertreatment sumpsandassociated pipingarepartofanormallynon-contaminated system.However,duetothetiminginthesumppumpstartupsequence, theconnection ofthesumppumpdischarge intothebottomofthefloordraincollector tankinletheader,andleakageofacheckvalve,contaminated waterfromthe

,

SafetyEvaluation SummaryReportPage47of112SafetyEvaluation No.89-060,Rev.2(Continued)

SafetyEvaluation Summary:(Continued) floordraincollector tankinletheaderwasabletobackflowintothewasteneutralizer tankcubiclesump.Theamountofradioactive contamination presentdoesnotreducetheabilityofthesumpstoperformtheirintendedfunction.

Althoughthesumpsystemisnotdesignedtothesamecriteriaasaradioactive system,theintegrity ofthesystemdoesassuretheshorttermcontainment ofliquidsandprecludes aninadvertent releasetoanunrestricted area.Administrative andradiation protection measureshavebeentakentosecurethecontaminated areaandrestrictitsuse.Thepumpdischarge linehasbeenisolatedandmarkedup.Theareaisproperlypostedandcontrolled asarestricted areainaccordance withplantprocedures.

Asurveyoftheaccessible portionofthepumpdischarge linehasconfirmed thatdoseratesfromthelinedonotpresentaradiological concernandthatthereisnoimpactonpersonnel orequipment intheunrestricted area.Operation ofsumppump57willbecontrolled topreventfurthercontamination ofthesystemduringanydecontamination efforts.Duringoperation ofsumppumpN7,thesystemwillbemonitored, including, asaminimum,isotopicanalysisofthesumpcontentsbeforeandaftersystemoperation, andphysicalsurveillance ofthesystempipingintheunrestricted areaduringsumpsystemoperation.

Basedontheevaluation performed, itisconcluded thatoperation ofthesumpsystem,untilsystemdecontamination effortsarecompleted, doesnotinvolveanunreviewed safetyquestion.

0 SafetyEvaluation SummaryReportPage48of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-061Procedure N2-OP-101D Table13.5-6(Sh.4)ReactorRecirculation SystemProcedure N2-0P-101D, "PowerChanges"Description ofChange:Anewoperating procedure, N2-OP-101D, "PowerChanges,"

hasbeencreated.SafetyEvaluation Summary:Thesubjectprocedure isdeveloped toconsolidate allconcernsrelatedtopowerchanges,including rapidpowerreductions.

Development andapprovalofthisprocedure satisfies unresolved itemno.89-12-02fromNRCInspection Report50-410/89-12, anddoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage49of112SafetyEvaluation No.:Implementation DocumentNo.:89-066Drawings12187-SK-032483-.25; 12177-BY-002Ag BgCgE45065-CthruE-45069CUSARAffectedPages:System:TitleofChange:Figure1.2-1VariousMinorConstruction Activities attheNineMilePointSiteDescription ofChange:Thesechangesinvolvevariousminorsiteconstruction activities suchasremovaloradditionoffences;additions, relocation, orremovalofsiteaccessandserviceroads;andregrading andseedingofsiteareasoutsidetheprotected area.SafetyEvaluation Summary:Evaluation oftheseminorconstruction activities andsitechangeshasdetermined that:1.Siteattributes thatrelatetotheprobablemaximumflood(PMF)analysisarenotadversely affected.

2.Theabilityoftherevetment ditchsystemtoprotectsafety-relatedfacilities fromthemaximumpostulated lakelevelasaresultoftheprobablemaximumwindstormisnotadversely affected.

3.Atmospheric dispersion factorsusedincalculating theradiological consequences ofaccidents arenotaffected.

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage50of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:89-068Temporary Mod.88-151N/A1TurbineBuildingHVACSystemTemporary Installation ofAirConditioning UnitsintheTurbineBuildingEastSwitchgear RoomDescription ofChange:Temporary additional coolingforpersonnel comfortisrequiredintheturbinebuildingeastswitchgear roomtosupplement theexistingcoolingsuppliedby2HVT-UC225.

Twoairconditioning unitsandacondensate pumpunitmovedfromtheradwastecontrolroomwerelocatedintheeastswitchgear room.Theexistingcondensing unitpositioned atgradeoutsideoftheradwastebuildingwasrelocated westtoanoutsideposition, atgrade,adjacenttotheswitchgear room.Theseunitsarenotconnected totheturbinebuildingHVACsystemandprovideairrecirculation withintheswitchgear roomonly.SafetyEvaluation Summary:Asindicated inUSARSection9.4.4.3,theturbinebuildingHVACsystemhasnosafety-related function.

Failureormalfunction ofthesystemorsubsystems willnotcompromise anysafety-related systemorcomponent, norwillitpreventsafereactorshutdown.

Therearenosafety-related components intheturbinebuildingeastswitchgear room.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage51of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-069,Rev.4Temporary Mod.89-092N/ACirculating WaterSystem-Units1and2TitleofChange:Circulating WaterSystemDischarge PathDescription ofChange:ArecentpHimbalance inthecirculating waterchemistry hasresultedinelevatedlevelsofcopperconcentration fromcondenser tubingcorrosion.

Thischangeallowsdischarge ofUnit2circulating waterblowdowntotheUnit1circulating watersystemwhereitwillbediluted,thenreturnedtothelakewithUnit1watereffluenthavingsufficient flowtodilutethecopperconcentrations toacceptable levels,asdetermined bytheNew~YorkStateDepartment ofEnvironmental Conservation.

Thistemporary modification providesthemeanstodrawcirculating waterdirectlyfromthecoolingtowerbasininitially andfromCWSlater,asnecessary.

Temporary discharge linesconsisting offlexiblehose,rigidpipe,andpumpshavebeenrunoverlandtotheUnit1intakecanal.Unit2circulating waterwillbedischarged totheUnit1circulating waterinfluentdownstream oftheservicewaterinfluent.

TheUnit1circulating watersystemwillbeoperatedcontinuously, providing aminimumflowtobedetermined bythecalculated needfordilutionofUnit2discharge.

Theadditionofascaleinhibitor, Betz3450,totheUnit2circulating watersystemisrequiredtocontroltheincreased scalingduetocopperconcentration andariseinpH.Theadditionofacorrosion inhibitor, BetzCopper-Trol Cu-l,willfurtherreducetheleachingofcopperintothecirculating wateratUnit2.

SafetyEvaluation SummaryReportPage52of112SafetyEvaluation No.SafetyEvaluation Summary:89-069,Rev.4(Continued)

Thecurrentlevelofcopperconcentration intheUnit2circulating waterjeopardizes systemequipment duetoincreased corrosion ratesinducedbyaccelerated corrosion ratesbeyondthosealreadyexisting.

Operation oftheUnit2circulating watersystemdoesnotjeopardize nuclearsafety,asthesystemisnotrequiredforsafeshutdownoftheplantandfailuresassociated withthesystemhavealreadybeenanalyzedintheUSAR.TheUnit2circulating watercopperconcentration controlsblowdowntoLakeOntario.Thegreatercirculating waterinfluentandeffluentflowatUnit1willprovidethemeansbywhichtosufficiently diluteUnit2circulating watersystemdischarge priortoitsreturntothelake.AsthereisadequateUnit1intakeflowtoaccommodate theUnit2discharge, andthecopperconcentration willnotaffectthereliability ofequipment, thereisnoimpactontheoperation ofUnit1.Theremainder oftheUnit2circulating watersystemwillcontinuetofunctionasdesigned.

TheUnit2CWScopperconcentration willnotaffectthereliability ortheUnit2servicewatersystemrelativetocorrosion.

Operation oftheUnit2tempering watersystemwillhavenonegativeimpactontheservicewatersystemandwillmaintaintheintakewatertemperature.

Theadditionofascaleinhibitor totheUnit2circulating waterwillhavenonegativeimpactonsystemandequipment operation orreliability, andwillhelptoextendservicelifebycontrolling thecorrosive effectsofscaling..Theadditionofacorrosion inhibitor willreducecopperleachingfromthecondenser tubesandreducethelevelofsolublecopperinthecirculating water.lntheeventofacondenser tubeleak,theadditionofthesecompounds willnothaveanegativeimpactonthechemistry ofcondensate water,feedwater, orreactorwater.Anincreaseinthelevelofchlorides intheUnit2circulating wateriswithintheabilityofthedemineralizers tomaintainthequalityoffeedwater/reactor water.

SafetyEvaluation SummaryReportPage53of112SafetyEvaluation No.SafetyEvaluation Summary:89-069,Rev.4(Continued)

(Continued)

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage54of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-070E&DCRC46950C,ECNSFC-612Figure9.1-6(Sheets3,6)SpentFuelPoolCoolingSystem(SFC)TitleofChange:SpentFuelPoolCoolingRelayChangesDescription ofChange:TheSFCcirculating pumpflowtimedelayrelayswereresetting assoonasthepumpsweretrippedonlowfloworlowdischarge pressure.

Thesealarmconditions werenot"seen"bythePMScomputerduetothealarmcontactresettimebeingmuchfasterthanthecomputerscantime.ThischangereplacedthesubjectAgastatrelayswithAgastatrelayscapableofperforming twotimedelayfunctions (fourpole,doublethrow).Theoriginaltimedelayfunctionfortrippingthepumpremainsasoriginally designed.

Thesecondtimedelayfunctionisonlyforholdingthealarmcontactsinlongenoughforthecomputertosensethecondition.

SafetyEvaluation Summary:Thesecondtimedelayfunctionofthereplacement relaysinnowayaffectstheoperation oftheSFCpumps.ThenewAgastatrelaysarethesamesizeastheoldrelaysandareinstalled intheexistingsafety-related switchgear, 2ENS*SWG101 and2ENS*SWG103.

Thenewrelaysaresafety-related andmeetthesamedesignandqualification requirements astheoldrelays.Basedontheevaluation performed,

'itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage55of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-071Temporary Mod.89-94N/ACondenser AirRemovalSystem,OffgasSystemTitleofChange:UseofHeliumLeakDetection SystemDescription ofChange:Thistemporary modification isfortheinstallation anduseofaheliumleakdetection systeminanefforttolocatepointsofairinleakage tothecondenser.

Thegeneraltestmethodistosprayheliumaroundpotential pointsofairinleakage atcomponents

~~subjecttocondenser vacuum(packings, flangedjoints,fittings, etc.)andtoobservethetestmonitorforindications ofheliumdetection.

Theheliumleakdetectorteststationwillbeinstalled at,theairremovalpump2ARC-P1Aduringstartup(steamlinepressure(200psig)andintheoffgascharcoaladsorberroomwhenthesteamjetairejectorsareoperating.

Bothlocations willutilizethesametestequipment:

heliumleakteststation(VeecoModelMS-170),3/8"coppertubingwithfittings, shutoffvalves,andavacuumpump.SafetyEvaluation Summary:Thischangehasnoeffectontheoperation orfunctionofthecondenser airremovalsystem,theoffgassystem,orthemaincondenser.

Noneofthesesystemsisrequiredforsafeshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage56of112SafetyEvaluation No.:Implementation DocumentNo.:89-072LDCNsU-782,U-1405,andU-1401USARAffectedPages:37A20g3~7A25g3~7A26g3.7A-27,3.9A-3a,3.9A-4,39A5g3'A23'A~151g3A152g3A15A1g3A~15A2g6A.3-6,6A.3-11,6A.9-3(Non-Proprietary),

and6A.3-11,6A.3-27(Proprietary)

System:TitleofChange:N/APermitUseoftheSUPERPIPE ComputerProgramforPipingAnalysisDescription ofChange:Thischangepermitsdesignengineers tousethecomputerprogramSUPERPIPE asanalternative toNUPIPE-SW forpipinganalysis.

SafetyEvaluation Summary:NUPIPE-SW andSUPERPIPE aresimilarprograms.

Bothrequirepipingtobeidealized usingdiscretemasspointswhoseconnecting membersareassignedrepresentative physicalproperties.

Bothprograms'develop stiffness matricesandsolveforresultant deflections, loads,andstresseswhensubjected toexternalloads.Theanalytical methodsusedtosolvecomplexequations arealsosimi'lar.

Allanalysismethodologies andcommitments described inUSARSections3.7,3.9,andAppendix6Athatareimplemented byroutinesinacomputerprogramremainunchanged.

Eitherprogramcanbeusedwithoutaffecting anypipinganalysisprocedure orcriteria.

Themaindifference betweentheprogramsisthatSUPERPIPE providesautomatic optionsformodelling, analyzing, andcombining loadcasesthatarenotprovidedinNUPIPE-SW.

TheSUPERPIPE programhasbeenbenchmarked inaccordance withtheNRCacceptance criteriaoutlinedinStandardReviewPlanSection 0

SafetyEvaluation SummaryReportPage57of112SafetyEvaluation No.89-072(Continued)

SafetyEvaluation Summary:(Continued) 3.9.TheSUPERPIPE vendorhasaworkingqualityassurance programandsoftwarecontrolprogramwhichhasbeenauditedbyNMPCforcompliance withtheintentof10CFR50AppendixB.Basedon-theevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion

SafetyEvaluation SummaryReportPage58of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:89-073EDC2M00308IEDC2M10080Figures5.4-16a,5.4-17(Sheet1)System:ReactorWaterCleanupSystem(WCS)TitleofChange:ChangePositionIndication for2WCS*MOV101 and2WCS*V41toShowNormalPositionDescription ofChange:Thisdrawingchangerevisesthenormalpositiondesignation onthesystemPaIDandthecorresponding USARfiguresforvalves2WCS*MOV101 (fromnormallyclosedtonormallyopen)and2WCS*V41(fromnormallyopentonormallyclosed).Thischangereflectsthemannerinwhichthereactorwatercleanupsystemisnormallyoperated.

SafetyEvaluation Summary:ThereisoneRPVbottomdrainlinethatisasupplytotheWCSsystem.This4"linehasanormallyclosedmotoroperatedvalve,2WCS*MOV101, thatisusedtocontrolthermalstratification whentheRCSpumpsareunavailable.

A2"bypasslinearound2WCS*MOV101 hasamanuallyoperatedvalve,2WCS*V41, thatisnormallyleftopentoprovideaconstantflowbacktotheWCSsystemtoremovecrudanddebrisfromthebottomheadarea.Bothvalvesarelocatedinthedrywell.Industryoperating experience indicates thatduringnormaloperation, the2"bypasslinebuildsupcrudblockageovertime.Thisblockagesignificantly reducesflowthroughthe2"bypasslinenecessitating theopeningofthe2WCS*MOV101 valvetomaintaintheflow.

SafetyEvaluation SummaryReportPage59of112SafetyEvaluation No.89-073(Continued)

SafetyEvaluation Summary:(Continued)

Tosimplifyoperations ofthesetwovalves,theWCSsystemwillbeoperatedwiththe2WCS*MOV101 valvenormallyopenandthe2WCS*V41valvenormallyclosed.Thisvalvelineupwillmaintainthedesignfunctionoftheline,whileproviding thebenefitofremoteoperating capability forvalve2WCS*MOV101 fromtheControlRoomtoisolatetheWCSsystemfromtheRPV,ifrequired.

Thischangeinnormaloperations willnotrequireanyphysicalchangestotheplant,andwillnothaveanyeffectonsysteminteraction orsafeoperation.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage60of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:89-074EDC2S100959A.2-2,9B.2-1;Figures9A.3-5,9A.3-6,9A.3-7System:TitleofChange:FireProtection FireZoneCorrections Description ofChange:Variouschangesaremadetothefireprotection arrangement drawings(EB-22series)andtheassociated USARfiguresinAppendix9A.Thesechangesareneededtocorrectly represent fireprotection equipment locations andfirezoneboundaries.

Theaffectedareasaretheauxiliary servicebuildingsouthandtheturbinebuilding(FireArea50,Zone762NZandFireArea80,Zones246NW,611NW,and761NZ).Corresponding revisions aremadetothecombustible loadingtabulations fortheaffectedfirezones,andtoProcedure N2-FDP-11, FireProtection Preplans.

Lastly,thedefinition ofafireareainUSARSections9A.2.4and9B.2isclarified toindicatethatseparation offireareasby2-hourfirebarriersisacceptable incertaincircumstances.

SafetyEvaluation Summary:ThechangestoUSARFigures9A.3.5through9A.3.7,Procedure N2-FDP-11andtheUSARfireareadefinition, Sections9A.2.4and9B.2,willensuretheplantas-builtorientation iscorrectly represented.

Thesearedocumentation changesonly,andnophysicalplantmodifications areinvolved.

Thesechangeswillnotalteranysafetyfunctiondescribed intheUSARandarenotrequiredforsafeshutdown, asFireAreas50and80donotcontainsafeshutdownequipment orcabling.Changingthedecontamination room,el.306ft.,fromZone761NZto762NZwillseparateFireAreas50and80bya2-hourratedfirewall.Thisarrangement satisfies thecircumstances underwhichseparation offireareasbya2-hourfirebarrierisacceptable perBTPCMEB9.5-1.

0 SafetyEvaluation SummaryReportPage61of112SafetyEvaluation No.89-074(Continued)

SafetyEvaluation Summary:(Continued)

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage62of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:89-077,Rev.1WR169489'and 169457N//ALiquidRadioactive WasteSystem(LWS)TitleofChange:RetubingofRegenerant Evaporator Reboiler(2LWS-E7) andRetubingofWasteEvaporator Reboiler(2LWS-E4)

Description ofChange:Thischangeinvolvestheretubingoftheregenerant evaporation reboilerandthewasteevaporator reboiler.

Thetubesofbothcomponents weredamagedbycorrosion pitting.Theregenerant evaporator reboilerhadbeentemporarily repairedbyliningthedeteriorated tubeswiththin-walled tubing.Thedamagedtubingandthesleevingusedasatemporary repairareremovedandreplacement tubing,equivalent totheoriginal, installed.

SafetyEvaluation Summary:Retubingoftheregenerant evaporator reboilerandthewasteevaporator reboilerrestoresthesecomponents totheiroriginaldesignconditions andwillhaveapositiveimpactontheeffective operation oftheliquidradwastesystem.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage63of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-001Mod.PN2Y89MX158 Figure10.1-5dCondensate System(CNM)Reworkof2CNM-RV71A/B/C PipingandReconfiguration ofVentLinesDescription ofChange:ReliefValves2CNM-RV71A/B/C werepreviously locatedabovecondensate ventvalves2CNM-V212A/B/C andtheirassociated pipinghighpoint,therebynotallowingcompleteairremoval.Themodification relocated theventlinessuchthattheytapoffthereliefvalveinletlines,riseabovetheelevation ofthevalves(2CNM-RV71A/B/C) seats,thenroutedownintotheexistingventlinestotheirassociated drain.Valves2CNM-V212A/B/C wereremovedandre-installed withinreachofthefloorelevation inthecurrentventlinepiping.Newvalves(2CNM-V370A/B/C) havebeenplacedineachofthenewhighpointventpipesections.

Thischangealsoreconfigures inletpipingto2CNM-RV71A/B slightlytoprecludefailurecausedbycyclicvibration.

SafetyEvaluation Summary:Thecondensate systemisnotsafety-related andisnotrequiredforsafeoperation orshutdownoftheplant.Thismodification ensuresproperventingofairthusprecluding theeffectsofwaterhammer,improvesaccesstotheventvalves,facilitates repairstotheventline,andenhancesvibration handlingcapability.

Basedontheevaluations performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage64of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-003Calc.A-10.1-AA-26, Rev.12.2-2,2.2-9N//ANMP2Helicopter Operations Description ofChange:NMPChelicopter servicesprovidelocaltransportation betweenthesiteandsurrounding areasincluding SyracuseHancockAirport.Thissafetyevaluation reviewstheacceptability ofthistypeofoperation inthecontextofaircrafthazardsasdiscussed inUSARSections2.2.3.1.7 and3.5.1.6.NMP2helicopter operations involveapproximately 45to60flightsperyearbetweentheSyracuseAirportandthesite.Theflightpathdoesnotencroachontheairspaceabovethesitesecurityfence.SafetyEvaluation Summary:Therearecurrently threehelicopter landingareasinthevicinityofNMP2,allwithinapproximately 0.5milesofthesite:1.Intheparkingarea,approximately 1200ftsoutheast oftheNMP2reactorbuilding.

2.Intheparkingareaadjacenttothetrainingcenter.3.Inthelawnareaadjacenttothetrainingcenter.BasedontheNRCStandardReviewPlan3.5.1.6methodology, theconservatively calculated probability ofahelicopter accidentleadingtoradiological consequences inexcessof10CFR100limitshasbeenestimated tobe1x10.Basedontheconservatisms includedincalculating thisvalue,itcanbereasonably concluded, thattheactualprobability wouldbelessthanabout10perreactoryear.Inaccordance withNRCStandardReview

SafetyEvaluation SummaryReportPage65of112SafetyEvaluation No.90-003(Continued)

SafetyEvaluation Summary:(Continued)

Plans2.2.3and3.5.1.6,thisensuresthathelicopter operations donotrepresent acrediblehazardtotheplantandneednotbeconsidered intheplantdesignbasis.Basedontheanalysesandevaluations performed, itisconcluded thatNMPChelicopter operations donotconstitute anunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage66of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-004Mod.PN2Y89MX155 Figure10.1-6cFeedwater PumpSealandLeakoffSystem(FWP)FeedPumpSealCoolingLineIsolation Description ofChange:Thismodification relocates isolation valves2FWP-V12A/B/C andaddsbreakflangesinthesealwatercoolinglinestothefeedwater pumps(2FWS-P1A/B/C).

Thepreviousarrangement didnotprovidesufficient flexibility formaintenance ofthefeedwater pumpsduringplantoperation orshutdownconditions.

SafetyEvaluation Summary:Thismodification facilitates the"performance ofmaintenance onthefeedwater pumps.Thefunctionandoriginaldesignrequirements ofthefeedwater pumpsealandleakoffsystemarenotchanged.Thesystemisnotsafety-related, andthechangeswillnothaveanyadverseeffectonthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage67of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-005QATR-1,Rev.517~21N/ARevision5toQualityAssurance TopicalReport(QATR-1)Description ofChange:Revision5totheQualityAssurance TopicalReport(QATR-1)hasbeenissued.Revision5isageneralupdateandclarification, including changesintheNuclearDivisionorganization sincetheissueofRevision4.~~SafetyEvaluation Summary:QATR-1Revision5wastransmitted totheNRCinletterNMP1L0475datedFebruary5,1990,tosatisfytherequirement of10CFR50.54 foranannualupdatetotheQAProgram.AsnotedinNMP1L0475,thechangesincludedinQATR-1Revision5donotreducetheeffectiveness oftheQAProgram.Thus,thesechangeswillnotadversely affectthesafeoperation orshutdownoftheplantanddonotinvolveanunreviewed safetyquestion.

t SafetyEvaluation SummaryReportPage68'of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:90-007Mod'.PN2Y89MX157 Figure10.1-6aTurbineBuildingEquipment DrainsSystemTitleofChange:Relocation ofFeedwater PumpDrainLineDescription ofChange:Thefeedwater pumpdrainsprovidethemeansbywhichtodrainwaterfromthepumpsandnearbypipingwhenmaintenance and/orrepairisrequired.

Previously, thewaterwasdirectedtotheturbinebuildingfloordrainsystemwithdischarge totheLWSdraincollector"subsystem.

However,thedraincollector systemdidnothavethecapacitytoadequately processthefeedwater.

Thismodification directsthepumpdrainwatertotheequipment drainsystemwithdischarge totheLWSwastecollector subsystem.

SafetyEvaluation Summary:Feedwater isnon-oily, lowconductivity watercompatible withtheequipment drainandLWSwastecollector systems,andthesesystemshavethecapacitytohandletheadditional water.Theinstallation willbemadewithmaterials andspecifications equaltothoseoftheoriginalinstallation, andtheabilitytodrainthefeedwater pumpswillnotbeimpacted.

Failuresassociated withthischangewillnotexceedfloodingconditions alreadyanalyzedintheUSAR,reference Section3.4.1.Thesechangeswillnotadversely affectthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthismodification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage69of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-009Mod.PN2Y90MZ003 Figure10.1-5dCondensate System(CNM)Feedwater PumpSuctionValve,BypassValve,2CNM-HV59A, B,CDescription ofChange:Thismodification addedamanualvalveinthebypassloopdownstream ofbypassglobevalves2CNM-HV59A, B,C.Themanualvalveprovidesameansofgradually increasing theflowofwarmerwaterandalsoprovidesapositiveisolation capability forfeedwater pumprepairs.SafetyEvaluation Summary:Thechangesimplemented bythismodification willnotalterthe.intendeddesignfunctionofthecondensate system.Themodification will,however,improveoverallperformance ofthesystem.Noneofthesafety-related structures, systems,orcomponents willbeimpactedbythismodification.

Thismodification willnotadversely impactthecapability toshutdowntheplantsafelyandtomaintaintheplantinasafeshutdowncondition.

Therefore, itisconcluded thatthismodification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage70of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-010Mod.PN2Y90MZ005 Figures9.3-12j,10.1-5dCondensate System(CNM)2CNM-HV119 Description ofChange:Thecondensate systemwasventedthroughhighpointventfeedwater pumpsuctionvalve2CNM-HV119.

Thisventdrainsintoanequi:pment drainlocatedinthevicinityofthevalve.Duetopersonnel safetyconcernsraisedduetohightemperature andsplashing ofhotfluidsintheareaatthetimeofventing,line2-CNM-750-308-4 hasbeenre-routed andtiedintoanexistingdrainline.Anisolation valvehasalsobeenaddedinline2-CNM-750-308-4 downstream ofvalve2CNM-HV119.

SafetyEvaluation Summary:Thismodification alleviates theconcernsregarding hightemperature andsplashing ofhotfluidsintheareaatthetimeofventing,allowsforthesystemtobeventeddirectlytothemaincondenser duringnormaloperation, andeliminates thereleaseofcontaminated steamtotheatmosphere.

Thechangesarenon-safety relatedanddonotadversely affecttheabilityofanysafety-related structures, systems,orcomponents toperformtheirsafetyfunction.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage71of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-012EDC2F00030N/ATurbineBuildingFloorDrainSystem(DET/DFT)

RerouteEffluentof2SST-TK1FlowPathfromtheFloorDrain(DFT)totheEquipment Drain(DET)Description ofChange:Thistemporary modification reroutestheeffluentof2SST-TK1(turbinebuildingsamplepanelrecoverytank)fromthefloor~~drainsystem(DFT)totheequipment drain(DET)system.SafetyEvaluation Summary:Thewaterfromtank2SST-TK1isnormallyofpermissible forinfluxtotheequipment drain(DET)system.Shouldconductivity waterentertheequipment drainsystemviaTKl,ahighconductivity alarmwouldbereceivedinthecontrolroom,alertingtheoperatortotakeappropriate requiredbyexistingprocedures.

qualityhigh2SST-radwasteactionasThetemporary changesarenon-safety-related anddonotadversely affecttheabilityofanysafety-related structures, systems,orcomponents toperformtheirsafetyfunctions.

Thefloodanalysisasdescribed inUSARAppendix3Cisalsonotaffected.

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage72of112SafetyEvaluation No.:Implementation DocumentNo.:90-013Temporary Mods90-003thru90-011USARAffectedPages:System:N//AEquipment andFloorDrainSystems(Various)

TitleofChange:Temporary Modification forDefeating Nine(9)Equipment and//orFloorDrainNuisanceAlarmsintheMainControlRoomPanel2CEC*PNL851 Description ofChange:Thistemporary modification istodefeatthefollowing equipment and//orfloordrainnuisancealarmsatControlRoompanel2CEC*PNL851, andallowOperations tomaintainthesesystemtroublealarmsthroughdirectresponsetothespecificradwastecontrolroomannunciator inalarmatpanel2CES-PNL513.

1.2.3.5.6.7.8.9.ReactorBuildingEquipment DrainSystemTroubleReactorBuildingFloorDrainSystemTroubleTurbineBuildingFloorDrainSystemTroubleTurbineBuildingEquipment DrainSystemTroubleMainStackFloorDrainSumpTank3SystemTroubleAuxiliary BoilerBuil'ding FloorDrainSystemTroubleRadwasteBuildingFloor/'Equipment DrainSystemTroubleCondensate StorageTankFloorDrainSystemTroubleMainStackFloorDrainTank2SystemTroubleSafetyEvaluation Summary:Currently, annunciators ontheradwastecontrolpanel2CES-PNL513supplyacommonannunciator systemtroublealarmtotheMainControlRoompanel2CEC*PNL851.

Thistroublealarmisageneralnon-specific indication thatrequiresoperators toaccessradwastecontrolroompanel2CES-PNL513 forthespecificproblemindication tobecorrected.

SafetyEvaluation SummaryReportPage73of112SafetyEvaluation No.90-013(Continued)

SafetyEvaluation Summary:(Continued)

Thedefeating ofcontrolroompanel2CEC*PNL851 nuisancetroublealarmswilleliminate thedistraction andtime-consuming effortsoftheMainControlRoomoperators tocorrectthesealarms.Thespecificradwastecontrolroomannunciator troublecondition willbecorrected attheradwastecontrolroomwhichismannedonacontinuous basis.Thesechangesarenon-safety-related andwillnotaffectthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage74of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:90-015,Rev.1Temporary Mod.90-012N/ARadwasteBuildingFloorandEquipment DrainSystem(DFW)TitleofChange:Temporary Replacement ofRadwasteFloorDrainSumpPumpDescription ofChange:Duetotheunavailability ofsparepumpsorparts,atemporary sumppumpisinstalled inthesumpservedbypump2DFW-P1A/B.

Thisinvolvestheremovalofa2"flangedspoolpieceandassociated sumpcoverplatefromthesumppumpdischarge piping,allowingthetemporary sumppumptobetiedin.Additionally, an~~~alternate meansofprocessing drainwaterthroughtheradwastefloordraincollector surgepumps2LWS-P17A/B isaccomplished bymeansofatemporary hoseinstalled betweenadrainvalveinthe2DFW-P1Adischarge pipeandasuctionstrainerdrainvalveofftheinletpipingtothefloordraincollector surgepumps.SafetyEvaluation Summary:Thechangeimplemented bythistemporary modification willnotchangethefunctionoftheexistingfloordrainsystemoraffectthesafeoperation orshutdownoftheplant.Theremovedspoolpiecedoesnotperformanyprotective functionfortheDFWsystem.Thistie-inwillallowfortheuseofexistingdischarge pipingcheckandisolation valvestocontroldischarge flow.Thetemporary hoseinstallation allowsalternate processing ofdrainwater,ifrequired, andisnotdetrimental tonormalsystemoperation.

Thetemporary sumppumpoperation canalsobemonitored byinstalled sumptanklevelswitches.

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage75of112SafetyEvaluation No.:Implementation Document=No.:

UFSARAffectedPages:System:90-020Temporary Mod.90-025N/AFireProtection WaterSystem(FPW)TitleofChange:Temporary Sprinkler System/Turbine BuildingEl.250'-0"Description ofChange:Atemporary sprinkler systemisinstalled toprovideadditional fireprotection totheareaatel.250'-0"underneath theturbinetrackbay.Theareaisfrequently usedasaworkareaforrepair~~~~~andmaintenance ofequipment which,onsomeoccasions, resultsinstorageofcombustibles.

Thetemporary sprinkler systemischargedfromthewatersupplytofirehosereelno.5andisattachedwithamanualvalvebetweenvalveFPW-V203andthehosereel.Theattachment issuchthatthehoseandsprinkler maybeoperatedindependently ofoneanother.Thesprinkler pipingisattachedtothebottomoftheel.261'-0"turbinetrackbaysteelandincorporates 21sprinkler headsandprovidesapproximately 900sq.ft.ofcoverage.

SafetyEvaluation Summary:Thistemporary modification islocatedinanon-safety-related areaandwillnotaffectanysafety-related equipment orsafeshutdownoftheplant.Thetemporary sprinkler systemisinstalled beneaththeturbinetrackbayusinghangerstosuspendthepipingfromthestructural steel.Theadditional loadinginducedintothestructural steelbythehangersisminimalandwillnotimpactthestructural integrity ofthetrackbayslab.Ifasprinkler piperupturewouldoccur,nosafety-related equipment wouldsustaindamagefromflooding.

0 SafetyEvaluation SummaryReportPage76of112SafetyEvaluation No.90-020(Continued)

SafetyEvaluation Summary:(Continued)

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage77of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-022FPEE-2-89-011, EDC2S10168Figure9A.3-5FireProtection Incorporation ofFireProtection Engineering Evaluations IntoFireProtection Arrangement DrawingDescription ofChange:USARFigure9A.3-5depictsanon-safeshutdown, non-BTP,balanceofplantfirebarrierwhichhasanunsealedacidtrenchrunningbeneaththebarrier.AFireProtection Engineering Evaluation

~~~~~~~~(FPEE)hasbeenwrittenanalyzing andjustifying theopening.Thischangereferences theFPEEonthefireprotection arrangement drawingandassociated USARFigure9A.3-5toprovideclarification andtraceability forthefireprotection program.SafetyEvaluation Summary:ThisrevisionhasnoadverseimpactontheFireProtection Program,doesnotadversely affecttheAppendixRSafeShutdownAnalysis, andisconsistent withtheguidanceprovidedbyStandardReviewPlanCMEB9.5.1.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage78of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:90-023N/AN/ALiquidWaste/Process andEffluentRadiological Monitoring andSamplingTitleofChange:Temporary Modification for2LWS-CAB206 anditsElectrical Interlock toValve2LWS-AOV142 Description ofChange:Thistemporary changeremovestheelectrical interlock betweenradiation monitor2LWS-CAB206 andvalve2LWS-AOV142 toallowtheoperation ofthevalveif,perTechnical Specifications, independent samplesarewithinspecification limitstodischarge liquidwasteeffluents intotheservicewatersystemdischarge bay.Radiation monitor2LWS-CAB206 iscurrently inoperative, anditsrepairrequiresitsde-energization, whichcausesvalve2LWS-V142tocycleautomatically closedpreventing theonlydischarge pathforliquidwasteeffluents intotheservicewatersystemdischarge bay.SafetyEvaluation Summary:Withradiation monitor2LWS-CAB206 inoperative, Technical Specifications requirements (L.C.O.3.3.7.9,ActionStatement "b,"andItem1,Table3.3.7.9-1) alloweffluentreleasestocontinueprovidedthat,beforeinitiating arelease,atleasttwoindependent samplesareanalyzedinaccordance withSpecification 4.11.1.1.1 (Table4.11.1-1, Item1),andatleasttwotechnically qualified membersofthefacilitystaffindependently verifythereleaseratecalculations anddischarge linevalving.TheseTechnical Specifications requirements arebeingfulfilled.

Thelossofliquidwasteeffluentmonitoring foraperiodinexcessofthirtydayswillbeaddressed intheSemiannual Radioactive EffluentReleaseReportasrequiredbySection3.3.7.9,ActionBoftheTechnical Specifications.

SafetyEvaluation SummaryReportPage79of112SafetyEvaluation No.90-023(Continued)

SafetyEvaluation Summary:(Continued)

Basedontheevaluation performed, itisconcluded thatthistemporary modification willnotimpactthesafeoperation orshutdownoftheplantanddoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage80of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:90-024EDC2E00437Figures6.2-71a,9.3-1d,9.3-1fSystem:Instrument AirSystem,Containment Atmosphere Monitoring SystemTitleofChange:PID-19D,19F,and82ATypographical ErrorsDescription ofChange:Typographical errorswerefoundandcorrected onPID-19D,19F,and82ArelatingtoERFcomputeridentification numbers~~~~~~~~~~(duplication andomissions).

Theassociated USARfiguresarerevisedaccordingly.

SafetyEvaluation Summary:Thisisadocumentation changeonlyanddoesnotinvolveanyphysicalchanges.USARfigurechanges(ERFcomputeridentification numbers)aremadetobringthefigurestoanas-builtconfiguration, andnologicfunctions areaffected.

Thesedocumentcorrections donotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage81of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:90-029EDC2M00340Figures9.4-8a,9.4-10a,9.4-12bSystem:Reactor,Turbine,andRadwasteBuildings HVACSystemsTitleofChange:RemovalofPre-filters fromtheReactor,Turbine,andRadwasteBuildings SupplyAirVentilation UnitsDescription ofChange:Thismodification providesfortheannualremovalofintakepre-~~~~~~~~filtersfromthereactorbuildingnormalventilation system,theturbinebuildingHVACsystem,andtheradwastebuildingHVACsystemforthedurationofthewintersnow'season.Theequipment identification numbersforthesepre-filters are2HVR-FLT4 throughFLT9(reactorbuilding),

2HVW-FLT1 (radwaste building),

and2HVT-FLT3 andFLT4(turbinebuilding).

Duringsevereweatherconditions, (highwindswithlake-effect snow),operation ofthesesystemshasresultedintheaccumulation ofsnowandiceonthepre-filters causingahighpressuredifferential acrossthefilters.SafetyEvaluation Summary:Operation oftheaffectedHVACsystemswithoutthepre-filters inplaceisacceptable sincedownstream filtersareinplaceandprovidetherequireddegreeoffiltration.

Theoutsideairisgenerally cleanerduringthewintermonthsbecausethegroundissnow-covered, frozen,orwet,andtheairisfreeofflyinginsects,incontrasttoconditions insummermonths.Also,theexistingsystemsprovidealowtemperature alarmintheeventthattheheatingcoilweretobecomeinefficient, andatroublealarmwillbepresentifahighdifferential pressureexistsacrossthedownstream filters.Inaddition, theoutsidesurfacesandfinsoftheheatingcoilsareinspected forcleanliness at

SafetyEvaluation SummaryReportPage82of112SafetyEvaluation No.90-029(Continued)

SafetyEvaluation Summary:(Continued) leastonceayearandcleanedifnecessary.

Thismodification affectsthenon-safety relatedportionsofthereactorbuildingventilation systemandthenon-safety relatedradwasteandturbinebuildingventilation systems.Thesechangesdonotadversely affecttheabilityofanysafety-related systemsorcomponents toperformtheirsafetyfunction.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage83of112SafetyEvaluation No.:Implementation DocumentNo.:90-035DrawingsEV-4M-1,EM-021M;GEN-930,EV4K3gEV4L3EV198AQOgEM002GgProcedures N2-MMP-931USARAffectedPages:9.1-32;Table3.2-1(Sh.16,26h);Figures1.2-10(Sh.2),9.1-25,12.3-12,12.3-45;Appendix9C,Figure5-2System:TitleofChange:Refueling Equipment ReactorInternals StoragePoolGateDescription ofChange:~~~~~Thischangeinvolvesthepurchaseandinstallation ofthereactorinternals storagepoolgatetosupportrefueling outageactivities.

Thoughthisactivitywasdeferreduntilaftercommercial operation, thegatedetailsarealreadyshownonplantdesigndrawings, andthegatestoragelocationiscurrently shownintheFSAR.Inordertofacilitate refueling outageoperations andmaintenance activities, thelaydownlocationforthereactorinternals storagepoolgate,andalsoforthereactorvesselinsulation, reactorvesselserviceplatform, andthestudtensioner andstandhavebeenrevised.Operating andmaintenance procedures havealsobeenrevisedtoaddressrestrictions ontheuseofthereactorinternals storagepoolgate.SafetyEvaluation Summary:Thereactorinternals storagepoolisdesignedtofacilitate storageofthereactordryerandseparator duringrefueling.

Thesealingmechanism associated withthegateiscomprised ofredundant inflatable seals.Thegate'ssealshavebeendesignedwithapressuregaugethatcanbereadilycheckedbyoperators atanytimeduringtheuseofthereactorinternals storagepoolgatetoconfirmsealintegrity.

Additionally, eachgatesealhasadedicated checkvalvewhichisdesignedtominimizetherateat

SafetyEvaluation SummaryReportPage84of112SafetyEvaluation No.90-035(Continued)

SafetyEvaluation Summary:(Continued) whichsealairpressuredecreases intheeventofalossofthenon-safety-related instrument airsystem.Theinternals storagepoolisrequiredtobefloodedwhileremovingtheseparator andremainsfloodedduringtheentirerefueling processuntilthesteamdryerandseparator arere-installed.

Therefore, anytimethatthereactorcavityisfloodedandthespentfuelpoolgatesareremoved,thereactorinternals storagepoolwillbeflooded.Consequently, atnotimecouldafailureofthereactorinternals storagepoolgateorsealresultinloweringwaterleveltounacceptable levelsinthespentfuelpool.Theinternals storagepoolgateisfabricated sothatafailureofthestructural aspectsofthegatewillnotoccurduringaSSE.Thisdesign/fabrication preventsportionsofthegatefromfallingintotheRPVorontotherefueling sealbetweentheRPVanddrywellwallduringaSSEwhenthegateisineithertheinstalled orstoredposition.

Thegatehasalsobeendesignedtowithstand concurrent hydrostatic andseismicloadswhenintheinstalled positionbetweenthestoragepoolandthereactorcavity.Thechangetothelaydownareasfortheinternals storagepoolgate,reactorvesselinsulation, thereactorserviceplatform, andthestudtensioner donotincreasethepossibility orconsequence ofanaccidentormalfunction sincetheentirerefuelfloorelevation issafety-related andhasbeendesignedtosupportheavyloadsregardless oflocation.

Heavyloadhandlingconsiderations, asdefinedinNUREG-0612, havebeenevaluated.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

0 SafetyEvaluation SummaryReportPage85of112SafetyEvaluation No.:Implementation DocumentNo.:90-036Temporary Mods.90-028,90-029,90-030USARAffectedPages:System:N/ATurbineBuildingEquipment Drains(DET),Condensate System(CNM)TitleofChange:DivertPumps2CNM-P2A, B,CPedestalDrainLineFlowDescription ofChange:Thecondensate boosterpumps(2CNM-P2A, B,C)areseepingoilontothepumppedestalwhicheventually flowstotheattacheddrainlinesandtheDETdrainsystem.Thistemporary changeinvolvesthediversion offlowofthecondensate boosterpumps(2CNM-P2A, B,C)pedestal'rain linesfromtheturbinebuildingequipment drainsystem(DET)toacollection apparatus.

SafetyEvaluation Summary:Theturbinebuildingequipment drainsystem(DET)isforthecollection andprocessing oflowconductivity, non-oilyradioactive, potentially radioactive, ornon-radioactive water.Thetemporary modification willpreventtheoilfromenteringtheDETsystemandallowOperations tomonitortherateofleakagefromthecondensate boosterpumps.Shouldawaterleakdeveloparoundthecondensate pumps(2CNM-P2A,B,C)thatproducesflownormallydirectedtotheequipment drainsystem(DET)throughtheaffecteddrainlines,andsaidflowweresufficient tooverflowthecollector apparatus, thefloordrainsystem(DFT)iscapableofhandlingtheaddedvolume.Thefloodanalysispreviously evaluated inSection3.4.1oftheUSARisnotaffected.

0 SafetyEvaluation SummaryReportPage86of112SafetyEvaluation No.90-036(Continued)

SafetyEvaluation Summary:(Continued)

Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage87of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:90-040Temporary Mod.90-032N/AReactorPlantSamplingSystem(SSR)TitleofChange:2SSR-IPNL145 Hydrolasing Description ofChange:Hydrolasing wasperformed onthedrainheaderforthereactorwatersamplepanel,2SSR-IPNL145, toreducecontamination andtheresulting exposures toChemistry personnel usingthesamplepanel.Seventubinglinesareservicedbytheheader.Toaccomplish thehydrolasing, theheaderwasisolatedbyclosingisolation valvesinfiveofthetubinglines(whichplacestheminaninoperable state),andbymodifying twolinesbyaddingTygontubingofsufficient length(lessthan10'-0")tobypasstheheaderandaccessequipment drain2DER-ED4404 directly.

SafetyEvaluation Summary:Althoughfivetub'inglineswhichutilizethedrainheadertoroutewatertotheequipment drain(2DER-ED4404) willbemarked-upandinoperable, thetwolineswhicharerequiredtomeetTechnical Specifications requirements inSection3/4.4.4regarding continuous monitoring ofreactorwaterconductivity (influent toRWCUfilter-demineralizers andRCSsystemloopApumpdischarge),

willremaininservice.Hydrolasing oftheheaderwillonlyrequiretheheadertobeisolatedtemporarily.

Thesamplepaneldesignstillprovidesameansforobtaining grabsamplesfromthefivesamplelineswhichareinoperable, ifneeded.Thistemporary modification isexpectedtobeinplacelessthanoneweekandwillhavenoimpactonthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthistemporary modification doesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage88of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-041EDC2F0069Figure9.2-2(Sheet19)ServiceWaterSystemUSARFigure9.2-2,DrawingErrorDescription ofChange:Thischangecorrectsanerrorthatwasfoundontheservicewatersystemlogicdiagram,USARFigure9.2-2,Sheet19.Theannunciator windowidentified as851225shouldactuallybe851255(RHRheatexchanger servicewaterdischarge radiation high).SafetyEvaluation Summary:Thisisadocumentation changeonlyanddoesnotinvolveanychangestotheactualsystemlogic.Thisdocumentcorrection reflectstheas-builtplantcondition anddoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage89of112SafetyEvaluation No.:Xmplementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-042FPQAP-l,Rev.29A.3-32FireProtection QualityAssurance ProgramRevision2toFireProtection QualityAssurance Program(FPQAP-1)

Description ofChange:Revision2totheFireProtection QualityAssurance Program(FPQAP-1) hasbeenissued.Revision2isageneralupdateandclarification, including changesintheNuclearDivisionOrganization sincetheissueofRevision1.SafetyEvaluation Summary:4FPQAP-1Revision2wastransmitted totheNRCinletterJP90-228,datedMay25,1990,tosatisfytherequirement of10CFR50.54 foranannualupdatetotheQAprogram.AsnotedintheMay25,1990letter,thechangesincludedinFPQAP-1Revision2donotreducetheeffectiveness oftheFireProtection QAprogram.Thus,thesechangeswillnotadversely affectthesafeoperation orshutdownoftheplantanddonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage90of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:90-044Temporary Modification N/AMoistureSeparators 6Reheaters TitleofChange:Temperature Monitoring ofReheate'r DrainReceiverTanks(2DSR-TK6A/6B)

LevelInstrumentation Description ofChange:Thistemporary modification involvesexternally attaching temperature sensorstothestandpipes, instrument lines,level~~~~~~~switches, andassociated reference legsofthereheaterdrainreceivertanks.Temperature datawillbecollected todetermine ifthecalibration ofthetanklevelinstrumentation containserrorsresulting fromincorrect densityvalues.Thetemperature sensorsarepoweredfromnon-safety-related sources.SafetyEvaluation Summary:Thistemporary modification addstemperature sensorstonon-safety-related piping,standpipes, andinstrument linestocollecttemperature data,andwillnotaffectthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage91of112SafetyEvaluation No.:90-050Implementation DocumentNo.:N/AUSARAffectedPages:System.TitleofChange:N/AControlBuildingChilledWaterSystem(HVK)Operation of2HVK*CHL1A withWornOilSealDescription ofChange:Controlbuildingchiller2HVK*CHL1A compressor sealhasbecomewornallowingtheoilintheuppersumptoseepdowntothelowersumpwhentheunitisnotoperating.

Thisleakagewiththechillershutdownoveralongdurationwouldmakeautomatic startsuncertain.

Thxsevaluate.on analyzestheoperation ofthechiller(2HVK*CHL1A) withthewornsealutilizing atrendingprogramtodetermine therateofdegradation.

Thiswillassurereliableoperation ofthechilleruntilrepairscanbefacilitated.

Acceptance criteriaaredeveloped whichareusedtodetermine chilleroperability.

SafetyEvaluation Summary:Toassurethatchiller2HVK*CHL1A willbecapableofanautostart,itwillbeoperatedfulltime,therebynotallowingtheoiltoseepoutofitsupperoilsump,asispossiblewhilethechillerunitisshutdown.Theweeklysurveillance procedure willchecktodetermine iftheidleleakageratefortheequipment (2HVK*CHL1A) isacceptable toassureautomatic restartforaDBAwithinterruption ofpowertothechiller.Aspecialsurveillance programwilltrendthecompressor seal'scondition usingtwomethods;onemethodtrendsbearingpressureonceeachshiftandtheothermethodtrendssealleakageonaweeklybasis.

SafetyEvaluation SummaryReportPage92of112SafetyEvaluation No.90-050(Continued)

SafetyEvaluation Summary:(Continued)

Thetrendingprogramprovidessufficient confidence thatunacceptable sealdeterioration willbedetectedinatimelymanner.Therefore, thisspecialsurveillance programallowsoperation ofNMP2withoutdeclaring chiller2HVK*CHL1A inoperable sincereasonable assurance isprovidedthatthechillerwillstartandperformitsintendedfunctionforatleastthirtydaysconsistent withtherequirements ofcontrolroomhabitability afteraLOCA.IfaLOCAeventoccurswithatotallossofoffsitepowertobothchillertrainsandasingleactivefailureoftheDivisionIIchiller(2HVK*CHL1B) torestart,adequateassurance existsthatchiller2HVK*CHL1A willperformitssafetyfunction.

Thedurationofthedowntimeassociated withtheweeklysurveillance testissufficiently longtodemonstrate thatthechillerunitwouldautomatically restartduringDBA.Basedontheevaluation performed, itisconcluded thatoperation ofthechiller(2HVK*CHL1A) isacceptable anddoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage93of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:90-066,Rev.1EAS-34-0688B, NEDC-31538P 15.0-9,15.0-12,15.1-8;Table15.0-3(Sheets1,2,3)SystemTitleofChange:VariousNMP2Increased CoreFlowAnalysis(ICFA)Description ofChange:Thepurposeofthissafetyevaluation istoallowoperations upto105%ofratedcoreflow(113.9MLB/HR)andrevisethecycle1CoreOperating LimitReport(COLR).Thissafetyevaluation appliestothecycle1COLRonly.SafetyEvaluation Summary:Theresultsofthissafetyevaluation showthattheMCPRoperating limitsforthelimitingtransients (Feedwater controller failureandloadrejection withbypassfailure)operating intheICFAregionareboundedbythelicense(100%ratedcoreflow),exceptwhenEOC-RPTisoutofservice.Acorrection ismadetotheMCPRlimitintheCoreOperating LimitReport(COLR)forEOC-RPToutofservice.Forotherequipment outofservicepreviously identified intheTechnical Specifications, theoperating MCPRlimitisnotaffectedbyincreased coreflowoperation.

Theanalysisresultsalsoshowthatoperation intheICFAregioniswithinallowable designlimitsforoverpressure protection, LOCA,containment, reactorinternals andflowinducedvibration.

Increased coreflowisallowedundertheconstraints ofNMP2Technical Specifications andCoreOperating LimitReport.Toensurethecurrentrodwithdrawal erroranalysisremainsvalid,theRMBsetpointwillbeclippedto106%.Basedontheevaluation andanalysesperformed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage94of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:90-085EDC2M10159Figures1.2-7(Sheet1),12.3-28,12.3-61System:TitleofChange:RadwasteBuildingRadwasteBuildingTruckBayRadiation ZoneDescription ofChange:USARFigures12.3-28and12.3-61arerevisedtoaddamissingradiation zonesymbol(/I)tothetruckbayarea.Figure1.2-7isrevisedtoincorporate amissingequipment identifier.

Thesearedrawingchangesonly.SafetyEvaluation Summary:Depending ontheoperations occurring, thedoseratesinthetruckbayareawillvaryfrom(1MR/HRwhentheradwastetruckbayareaisemptyto>100MR/HRwhenacaskisbeingfilledforshipment.

Thesedoserateswereassumedintheoriginalanalysisorcalculations butwereinadvertently leftoffthedrawings.

Nochangesarerequiredtoanyotherdocuments.

Basedontheevaluation performed, itisconcluded thatthesedrawingchangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage95of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:90-107NMPCLettersNMP2L0653,NMP2L06657~17aInstrumentation andControls(General)

TitleofChange:FSARSection7.1.2.3RevisionDescription ofChange:Section7.1.2.3oftheFSARisrevisedasfollows:Thecommitment toperformananalysiswithrespecttotheuseofliftedleadsorjumpersisdeleted,asthecommitment wassatisfied byNMPC'ssubmittal ofletterNMP2L0653,datedMarch6,1986.2.Supplemental information isaddedwithrespecttoprocedural requirements governing theuseofliftedleadsandjumpers.Thisinformation waspreviously submitted byNMPCinletterNMP2L0665,datedMarch21,1986.SafetyEvaluation Summary:TheNRCSafetyEvaluation Report,Supplement 3,Section7.3.2.5,concludes that,basedonNMPC'scommitments, thenecessary stepsandprecautions aretakentopermittestingofsafety-related systemswithoutdegrading systemfunctions.

TheseFSARrevisions reflecttheNRC-approved positionregarding theuseofliftedleadsandjumpersduringtestingand,therefore, donotconstitute anyunreviewed safetyquestions.

SafetyEvaluation SummaryReportPage96of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-108Procedures NTP-11,NTP-161.10-16N/AFSARTable1.10-1RevisiontoAdministration ofTrainingProgramsDescription ofChange:ThischangetotheNMPCpositionregarding NUREG-0737 ItemI.A.2.3deletesreference toNMPUnit1SROlicenseholderssinceNMPUnit2nowhasitsowninstructor qualification program.ThisrevisedFSARpositionclarifies thequalification requirement forNMPinstructors andmeetstherequirementsofNUREG-0737, andisconsistent withFSARSection13.2.1.2inthatallinstructors teachingthelicensedtrainingandretraining programsshalldemonstrate SROqualifications andparticipate inappropriate requalification programs.

SafetyEvaluation Summary:ThechangetotheNMPCpositionregarding NUREG-0737 ItemI.A.2.3enhancestheclarityofthecurrentFSARpositionwithregardtoadministration oftrainingprogramsconsistent withNRCrequirements andFSARChapter13.2commitments and,therefore, doesnotconstitute anunreviewed safetyquestion.

SafetyEvaluation SummaryReport'QPage97of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-109N/ATable1.8-1,Sht.149of169N/ANMP2FSARTable1.8-1RevisiontoLicensedPersonnel MedicalEvaluation Requirements Description ofChange:ThischangetoFSARTable1.8-1Regulatory Guide1.134,Rev.1,1976,endorsedbythisrevisionRegulatory Guide1.134,Rev.2,revisestheNMPCcommitment fromandtheassociated ANSIN546-tothecurrentrequirements ofandANSI/ANS-3.4-1983.

Additionally, reference toFSARChapter13isdeletedsinceChapter13doesnotdiscussmedicalexamination orcertification requirements forlicensedoperators.

SafetyEvaluation Summary:ThischangeupgradestheFSARcommitment formedicalevaluation oflicensedoperators andsenioroperators tothelatestNRCapprovedstandards.

Thisrevisedcommitment wascontained inNMPC'sletterNMP62510,datedFebruary21,1990.Thus,thisFSARchangeisadministrative innatureanddoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage98of112SafetyEvaluation No.:Implementation DocumentNo.:90-113Procedure N2-RTP-129, Spec.P281FUSARAffectedPages:System:Table5.2-8DrywellAtmosphere Monitoring SystemTitleofChange:Clarification ofLeakDetection DetailsDescription ofChange:setpoints:

~~1.Footnotes1and2toTable5.2-8arerevisedandcombinedintoasinglefootnotetoclarifythattheleakdetection sensitivity presented inthetableisaMinimumDetectable Concentration basedona10minuteMinimumDetectable Level(MDL)forI-131(particulate) andXe-133(gaseous) radioactivity.

Thefollowing FSARchangesaremadetoprovideclarification oftheleakdetection equipment sensitivity andadditional explanation ofthemethodfordetermining leakdetection 2.AsecondfootnoteisaddedtoTable5.2-8,clarifying themethodusedtodetectreactorcoolantpressureboundaryleakageusingairborneparticulate andgaseousradioactivity readings.

SafetyEvaluation Summary:ThechangestoFSARTable5.2-8maketheFSARdiscussion ofRCPBleakagedetection sensitivities andmethodsconsistent withtheplantas-builtcondition andworkingprocedures, andwithTechnical Specification Interpretation 539,whichaddresses thelimitations ofparticulate andgaseousradioactivity monitorstodetectRCPBleakage.

SafetyEvaluation SummaryReportPage99of112SafetyEvaluation No.90-113(Continued)

SafetyEvaluation Summary:(Continued)

Thesechangesdonotreflectadeterioration intheRCPBleakagedetection capabilities ofNMP2',nordotheyaffectanysystemoreffluentreleasesinsuchawaythattheradiological consequences ofpostulated accidents couldbeincreased.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage100of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:90-114Calc.WH(C)-001 Table2.4-15N/'ACorrectInconsistencies BetweenSourceDocumentandtheUSARDescription ofChange:USARTable2.4-15isrevisedtocorrectinconsistencies betweenthetableanditssourcedocument, calculation WH(C)-001 andDisposition No.OA.Thechangesincluderevisions toassumedbuildingdepths,flowthroughdoors,andadditionofanewdoorforconsideration inthefloodinganalysis.

Severaleditorial corrections arealsoincorporated.

SafetyEvaluation Summary:Thesechangesrevisethefloodingcalculation andtheUSARtable(whichsummarizes thefloodinganalysisresults)toproperlyreflecttheplantas-builtcondition.

Therevisedcalculations demonstrate thattheconclusions oftheprobablemaximumprecipitation (PMP)floodstudyarenotaffected; i.e.,theplantcanbesafelyshutdown.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage101of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:90-115Drawings945E400,945E493Figure9.5-41(Sheets1thru12)System:TitleofChange:High-Pressure CoreSpraySystemDivisionIIIDieselGenerator USARFigure9.5-41UpdateDescription ofChange:USARFigure9.5-41isupdatedtocorrecteditorial mistakesandaddmissinginformation toagreewiththesourcedocuments asfollows:~~~~1.Sheet8:"LowCoolingWaterExp.TankLevel"alarmisindicated asinputtocommonalarm.2.Sheet10:Missingelementsareaddedandcorrections aremadetothelogicoftheD.C.circulating oilpump.3.Sheet11:Fueloilsystemflowdiagram,legendtableandnotesarecorrected forclarification purposesandtoreflect"as-built" condition.

4.Sheet12:Thissheetisaddedformissingfueloilprimepumplogicandfueloilsystemalarms.5.6.Sheets6through11:Legendfor'!local"indication isrevisedforconsistency.

Sheets1through11:Thetotalnumberofsheetsis,corrected from11to12.

SafetyEvaluation SummaryReportPage102of112SafetyEvaluation No.SafetyEvaluation Summary:90-115(Continued)

ThischangeupdatesUSARFigure9.5-41toagreewiththesourcedocuments.

Thedesignfunctionandmethodofperformance oftheHPCSsystemanditscomponents isnotaltered,andnofieldworkisrequired.

Assuch,thischangehasnoimpactonthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage103of112SafetyEvaluation No.:Implementation DocumentNo.:90-116AppendixRSafeShutdownAnalysisUSARAffectedPages:System:TitleofChange:9B~21g9B22I9B~23g9B~4-3,9B.6-1,9B.6-2,9B.6-3,9B.8-7,9B.9-1;Tables9B.8-1,9B.8-2;Figure9B.4-2VariousUpdateofAppendixRSafeShutdownAnalysis-Appendix9BofUSARDescription ofChange:IThischangerevisesUSARAppendix9B,AppendixRSafeShutdownAnalysis, toincorporate resolutions tocommentsresulting fromtheindependent verification reviewconducted byNiagaraMohawk'sinternalNuclearCompliance andVerification group.Thechangesincludethefollowing:

2.Correction ofinconsistencies betweenSection9B.4andTable9B.8-1regarding theRCICsystem.Section9B.4correctly designates theRCICsystemaspartofsafeshutdowntrains3and4,whereasTable9B.8-1erroneously listedtheRCICsystemaspartofsafeshutdowntrains1and3.InSection9B.2,thedefinitions fortheterms"generalfirearea"and"divisional firearea"aredeleted,asthesetermsarenotusedinthesafeshutdownanalysis.

Thedefinitions offireareaandfiresubareaareclarified.

TheseUSARchangesdonotinvolveanyphysicalmodifications totheplant.SafetyEvaluation Summary:Therearenodesignorhardwarechangesasaresultoftheserevisions toUSARAppendix9B.Thesafeshutdownanalysis

SafetyEvaluation SummaryReportPage104of112SafetyEvaluation No.90-116(Continued)

SafetyEvaluation Summary:(Continued) continues toshowthatatleastonetrainofsafeshutdownsystemsisavailable tosafelyshuttheplantdownincaseoffireinanyfirearea.Therefore, safeshutdowncapability existsasrequiredbyAppendixRintheeventofafire.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage105of112SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:90-117Calc.12177-WM(B)-27, Rev.21.10-133, 2.2-6;Tables2'3g2'5(Sh1)I2272.2-8System:TitleofChange:Environmental ProgramUpdateUSARTextandTablesDescription ofChange:effectofacchabitability.

Thischangeidentifies revisions toUSARtextandtablestocorrectinconsistencies betweentheUSARandsourcedocumentation.

TheUSARrevisions relatetocalculations oftheidentalreleaseoftoxicchemicals oncontrolroomSafetyEvaluation Summary:Theidentified USARchangescorrectinconsistencies betweentheUSARandsourcedocumentation.

Thesecorrections donotinvolveanyactualplantchanges,donotaltertheplantdesignbasis,andinnowayalterthehabitability conditions inthecontrolroom.Basedontheevaluation performed, itisconcluded thattheseUSARchangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage106of112SafetyEvaluation No.:Implementation DocumentNo.:90-122FireHazardsAnalysisUSARAffectedPages:9.5-5,9.5-6,9.5-6a,9A.2-2,9A.2-3,9A.3-7,9A.3-7a,9A.3-12,9A.3-49,9A.3-56;Tables9A.3-1(Sh.3),9A.3-6(Sh.2,4)I9A~3-8(Sh.2)System:TitleofChange:FireProtection FireProtection 1990USARUpdateDescription ofChange:ThAnischangedocuments andevaluates revisions totheFireHazardsalysis.Thefollowing summarizes theUSARchangesmade:Sections9.5.1.2.8 and9A.3-Clarified toindicatethatcharcoalfilters2HVC-FLT1A, Band2HVR-FLT3 arenotprotected withsprinklers.

2.Section9.5.1.2.10

-Thecommitment toNFPA12A(halonsystems)isclarified toindicateuseofthe1980edition.3.Sections9.5.1.2.13 and9A.3.6.1.2

-Thetextisclarified toindicatethatUnit2doesnotentirelycomplywithNFPA72Dand72E.Thesedeviations arealreadyidentified inUSARTable9.5-3.4~Section9A.2-Thedefinitions fortheterms"generalfirearea"and"divisional firearea"aredeleted,asthesetermsarenotusedintheFireHazardsAnalysis.

Thedefinitions offireareaandfiresubareaareclarified.

5.Section9A.3andTables9A.3-1,9A.3-6,and9A.3-8-,Theseareupdatedtoreflectchangesinfireloadingthathaveoccurred.

6.Section9A.3-Updatedtoaccountforthedesignated storagearea(turbinebuildingtrackbay)forcombustible liquidsandClassAcombustibles.

SafetyEvaluation SummaryReportPage107of112SafetyEvaluation No.Description ofChange:90-122(Continued)

(Continued) 7.Section9A.3.7.4-Corrected toproperlystatethatthewallsoftheplantcomputerroomarepartially rated.SafetyEvaluation Summary:Therevisions described hereinaprovidedinNRCStandardReviewPositionCMEB9.5-1fortheimplProtection Program,andprovidesafetytothatalreadyprovidedchangeshaveanyadverseimpactshutdownintheeventofafireperformed, itisconcluded thatunreviewed safetyquestion.

reconsistent withtheguidancePlan9.5.1andBranchTechnical ementation andcontrolofaFireanequivalent orgreaterlevelofintheplant.Noneoftheontheplant'sabilitytosafelyBasedontheevaluation thesechangesdonotinvolvean

SafetyEvaluation SummaryReportPage108of112USARTEXTtTABLEANDFIGURECHANGES(BASEDONPREVIOUSLY REPORTEDSAFETYEVALUATIONS)

Anumberoftextandfigurerevisions weremadetotheUSARtoincludeadditional changesthatarebasedonpreviously reportedsafetyevaluations.

Thesechangesareidentified below.SafetyEvaluation No.:87-059,Revision2Previously Reported:

10/25/89USARTable3B-5Sheets1,3,4,5,Table3B-6Sheets1,3,4,5,6andFigure3B-2Sheet3,havebeenrevisedtoincludeadditional footnotes regarding plantoperation withtheremovalofsecondary containment hatches.SafetyEvaluation No.:87-155Previously Reported:

10/25/89~~~USARFigure10.1-6chasbeenupdatedtodeleteinstruments 2FWP-PDK5A/B/C, perECNFWP-604andSafetyEvaluation 87-155.SafetyEvaluation No.:88-032Previously Reported:

10/26/88USARFigure10.4-11Sheets1,2,3and9havebeenfurtherupdatedtoincludechangesperECNFWS-612andEDC2E10099,asdescribed inSafetyEvaluation 88-032.SafetyEvaluation No.:88-061Previously Reported:

06/11/90USARPage6.2-86ahasbeenupdated,perEDC2M00085,tobeconsistent withchangesmadetoFigure6.2-73a(USARRevision0),asdescribed inSafetyEvaluation 88-061.

0 SafetyEvaluation SummaryReportPage109of112SafetyEvaluation No.:88-064Revision2Previously Reported:

10/25/89USARFigure9.3-1bhasbeenrevisedtocorrectaneditorial erroronLDCNU-549,Revision3.SafetyEvaluation No.:88-085Previously Reported:

06/11/90USARFigure9.3-6Sheet1hasbeenupdatedtoreflecttherevisedsetpointfor2SSR-CSL106 perEDC2E00078,asdescribed inSafetyEvaluation 88-085.SafetyEvaluation No.:88U-014Previously Reported:

04/28/89USARFigure9.2-2Sheet19hasbeenupdatedtoreflectadditional

~~~changesperECNSWP-649,asdescribed inSafetyEvaluation 88U-014.SafetyEvaluation No.:88U-019Previously Reported:

04/28/89USARFigure9.5-40ahasbeenrevisedtoreflecttheas-builtcondition of*PI322A/B and*AOV323A/B perECNEGA-607,asdescribed inSafetyEvaluation 88U-019.SafetyEvaluat'ion No.:88U-029Previously Reported:

04-28/89USARFigure10.4-10Sheet11hasbeenrevisedtocorrectadraftingerror.Page10.4-32hasbeenupdatedtoincludetheadditionofalarmstothecondensate pumpsandcondensate boosterpumpsasdescribed inSafetyEvaluation 88U-029.

0 SafetyEvaluation SummaryReportPage110of112SafetyEvaluation No.:88U-068Previously Reported:

04/28/89USARFigures12.3-5,12.3-8,12.3-38,1.2-19Sheet2and12.3-47havebeenupdatedtoreflect'he as-builtconfiguration.

Thesechangesinvolveequipment locations andradiation zonesdescribed inSafetyEvaluation 88U-068.SafetyEvaluation No.:88U-069Previously Reported:

04/28/89USARFigures1.2-19Sheet1,12.3-13,12.3-46,1.2-19Sheet2,12.3-14and12.3-47havebeenupdatedtoreflecttheas-builtconfiguration perEDC2M10129and2M10161,asdescribed inSafetyEvaluation 88U-069.SafetyEvaluation No.:88U-071~~~~~~~~~~~Previously Reported:

04/28/89USARFigures1.2-26,1.2-27,1.2-28,12.3-22,12.3-23,12.3-55,12.3-56,and10.4-7dhavebeenupdatedtoreflecttheas-builtconfiguration perEDC2M10151,asdescribed inSafetyEvaluation 88U-071.SafetyEvaluation No.:88U-072Previously Reported:

04/28/89USARFigures12.3-24,12.3-27,12.3-57,12.3-58,and12.3-60havebeenupdatedtoreflecttheas-builtconfiguration perEDC2M10151,asdescribed inSafetyEvaluation 88U-072.

SafetyEvaluation SummaryReportPage111of112SafetyEvaluation No.:88U-120Previously Reported:

04/28/89USARFigures6A.2-13and6A.2-25havebeenupdatedtoincludepreviously approvedchanges,identified inLDCNU-447,thatwereinadvertently omittedfromtheupdate.Thisomissionwasidentified duringtheverification ofLDCNU-447.SafetyEvaluation No.:88U-129Previously Reported:

04/28/89USARFigure9.4-4(Sheet9)hasbeenupdatedperEDC2E10125,asdescribed inSafetyEvaluation 88U-129.SafetyEvaluation No.:88U-238Previously Reported:

04/28/89USARFigure9.3-11ehasbeenupdatedperEDC2M10043A, as~~~described inSafetyEvaluation 88U-238.SafetyEvaluation No.:88U-255Previously Reported:

04/28/89USARTable1.8-1Sheets65,66,and67havebeenrevisedtodeleteinformation whichwaspreviously relocated toUSARSection14.2,perLDCNU-1145,asdescribed inSafetyEvaluation 88U-255.SafetyEvaluation No.:88U-262Previously Reported:

04/28/89USARPage1.12-32hasbeenrevisedtocorrectaneditorial errorregarding thedateofaNRCletter.

SafetyEvaluation SummaryReportPage112of112SafetyEvaluation No.:88U-276Previously Reported:

04/28/89USARTable7.1-3Sheet4hasbeenrevisedtoreflectRevision3ofRegulatory Guide1.97tobeconsistent withLDCNU-361Revision1,andSafetyEvaluation 88U-276.SafetyEvaluation No.:88U-282Previously Reported:

04/28/89USARFigure6.2-70Sheet21hasbeenupdatedtobeconsistent withPaIDs13A-10,13D-9andSafetyEvaluation 88U-282.USARFigure6.2-70Sheet30hasbeenupdatedtobeconsistent withPGIDs19D-10,19F-7andSafetyEvaluation 88U-282.SafetyEvaluation No.:89-056Previously Reported:

10/25/89~~~~~~~~USARTables9A.3-2Sheet2,9A.3-9Sheet2,9A.3-1Sheet2,and9A.3-6Sheet5havebeenrevisedtoreflectcalculation FPW-28Revision8,asdescribed inSafetyEvaluation 89-056.Thesechangesresolveverification commentsregarding LDCNsU-883,U-1117andU-1200,whichwereincorporated intoUSARRevision1.ENDOFSAFETYEVALUATION SUMMARYREPORT

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~F=FiureNumberPageT=TableAmendment

~F=FiureNumberUSARRevision1EP2-19October1989

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-DouglasE.IslerAffidavit

-JohnJ.MarkhamAffidavit

-JohnH.Peck(2pg)Figure1Figure2Figure3Figure4App2NAmendment Number16161616161616161616161616RORORO-ROROROROROROROROROROROROROROROROROROROROROROROROROROROROUSARRevision1EP2"20October1989

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(T451.15-2)

(T451.15-3)

(T4S1.1S-4)

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureF5.2"1F5.2-2F5.2-3F5.2-4S111S112F5~2-5F5.2-5aF5'-6F5.2-7F5.2-8F5.2-95.3-15~325.3-35.3-45.3"55.3-65~375.3-7a5.3"7b5.3-85.3"95.3-105.3-115.3-125.3-135.3-145.3-155.3-165.3-175.3-185.3-195.3-205.3-215~322T5.3"1Sjl1Sjl2T5~32F5.3-1F5'-2F5.3-3F5.3-4Amendment Number23230700002423241124RO2724240llRlRlll0ll240RO24Rl2427000002400-PageT=Table~F=FiureF5.3-55.4-15.4-25.4-35.4-45.4-4a5.4-4b5.4-55.4-5a5.4-5b5.4-65.4-75.4-85.4-95.4-9a5.4-9b5.4-105.4-115.4-125.4-135.4-145.4-155.4-165.4-175.4-17a5.4-17b5.4-185.4-195.4-205.4-215.4-21a5.4-21b5.4-225.4-235.4-23a5.4-23b5.4-245.4-255.4-265.4-275.4-285.4-28a5.4-28b5.4-29Amendment Number24RO242423232324242424242428282828RO28RO2828RORORORO000524724RORORO9242427524524PageT=Table~F=Fiure5.4"305.4-315'-325.4-335.4-345.4-34a5.4"34b5.4"34c5.4-34d5.4-355.4"365.4-375.4-37a5.4-37b5.4-385.4-38a5.4"38b5.4-395.4-405.4-415.4-425.4-42a5.4-42b5.4-435.4-43a5.4-43b5.4-445.4-455.4-45a5.4-45b5.4-465.4-475.4"485.4-495.4-505.4-50a5.4-50b5.4-515.4-5la5.4-5lb5.4-525.4-535.4-54T5.4-1S111Amendment Number24242424132828880RORORO13262313RO5275RO5Rl1050RO55RORORO24RORORORl1313002824USARRevisionEP5-2October1989 i

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER6PageT=Table~F=Fiuee6-i6-ii6-iii6-iv6-v6-vi6-vii6-viii6-ix6-x6-xa6-xb6-xi6-xii6-xiii6-xiv6-xiva6-xivb6"xv6-xvi6-xvii6-xviii6"xix6-xixa6-xixb6-xx6-xxi6-xxii6-xxiia6-xxiib6"xxiii6.1-16.1-26.1-36.1-46.1-4a6.1-4b6.1-56.1"6T6.1-1~S}11S}12T6.1-2Sh1Amendment NumberRORO242424RORO2424RORO11RO242424241715272427RORO272424242424242727RO33328282728ROPageT=Table~F-FiueeSh2T6.1-36.2-16.2-26.2-2a6.2-2b6.2-36.2-46.2-56.2-66.2-6a6.2-6b6.2-76.2-86.2-96.2-106.2-116.2-126.2-136.2-146.2-156.2-15a6.2-15b6.2-166.2-176.2-186.2-196.2-206.2-216.2-226.2-236.2-246.2-24a6.2-24b6.2-24c6.2-24d6.2-256.2-25a6.2-25b6'-266.2-276.2-286.2-296'-30Amendment NumberRO2807RO70023RO23RO0RO230RO000RORORORO0RO0000RO2018RORO17RORORORO5500PageT=Table~F=Fiuee6'-30a6.2-30b6.2-316.2-326.2-336.2-33a6.2-33b6.2-346.2-356.2-35a6.2-35b6.2-366.2-376.2-37a6.2-37b6.2"386.2-396'-406.2-416.2-426.2-436.2-43a6.2-43b6.2-446.2"456.2-466.2-46a6.2-46b6.2-476.2-47a6.2-47b6.2"486.2-496.2-506'-516.2-51a6.2-5lb6.2-526.2-536.2-53a6'-53b6.2-546.2-54a6.2-54b6.2-55Amendment Numberll1100RORORO112355RO23RORORO00018RORlRO15RORORORO235515RORO27251327Rl88RORO2721USARRevision1EP6-1October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=Fiure6.2-5Sa6.2-55b6.2-55c6.2-55d6.2-566.2"576.2-57a6.2-57b6.2-57c6.2-S7d6.2-57e6.2-57K6.2-586.2-596.2-59a6.2-59b6.2-606.2-60a6.2-60b6.2-616.2-61a6'-61b6.2-626.2-62a6.2-62b6.2"636.2-63a6.2"63b6.2-646'-656.2-65a6.2-65b6.2-666.2"676.2-67a6.2"67b6.2"686.2"68a6.2-68b6.2"696.2-69a6.2-69b6,2-706.2-716.2-71aAmendment Number27RlRORO18RORORORORlRO260RORORO2828526RORO7237RORORO18171717026212126255ll5.5RO55PageT=Table~F-Fiure6.2-71b6.2-726.2-72a6.2-72b6.2-736.2-746.2"756.2-75a6.2"75b6.2-766.2-76a6.2-76b6.2-776.2-77a6.2-77b6.2-786.2-796.2-79a6.2-79b6.2-806.2-80a6.2-80b6.2-816.2-826.2-836.2-83a6.2-83b6.2"846.2-84a6.2-84b6.2-856.2-85a6.2-85b6.2-866.2-86a6'-86b6.2-876.2-87a6.2-87b6.2-886.2-88a6.2-88b6.2-89T6.2-1T6'-2Amendment Number5RlRORO2827RO2751528527RO158151515RO1515RO15Rl272327232327171727191726Rl17RlRlRO150PageT=Table~F=FiureSh1S112T6.2-3S111Sh2Sh3T6.2-4T6.2-4aT6.2-5T6'-6S111S112T6.2-7T6.2-8T6.2-9T6.2-10T6.2-11T6.2-12T6.2-13T6.2-14T6.2-15S111S112T6.2-16T6.2-17T6.2-18T6.2-19T6.2-20T6.2-20aT6'-21T6.2-22T6'-23T6'-24T6.2-25T6.2-26T6'-27T6.2-27AT6.2-28T6'-29T6.2-30T6.2-31T6.2-32T6.2-33T6.2-34T6.2-35Amendment NumberRORORO0RO0RORO00RO0000026000000210000000ROllRORORORORORO11USARRevision1EP6-2October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureT6.2-36T6.2-37T6.2-38S}11.S}12T6.2-39S}11Sjl2S}13S}14Sjl5S}16T6.2-40T6.2-41T6.2-42T6.2-43T6.2-43AT6'-43BT6.2-44T6.2-44AT6.2-44BT6.2-45T6.2"45AT6.2-45BT6'-46T6.2-47T6.2-48T6.2"49T6.2-50T6.2-51T6.2-52T6.2"53T6.2-54T6'-55T6.2-55aS}l1S}12S}13T6.2"55bS}11Sjl2Sjl3T6'-55cS}11S}12Amendment Numberll27ll111111llllllll11ll11RO111111ll1128111128280RORORORl21RORORORORORORlROPageT=Table~F-FiureS}13T6.2-55dSh1S}12Sjl3T6.2-56S}11Sjl2Sh2aSh3S}L4S}15S}16Sh7S}18S}19S}110Sh11Sh12Sh13S}114Sh15S}L16S}117Sh17aS}118Sh19Sh19aS}l20Sh20aS}121Sh22Sh22aS}123Sh23aSh24S}124aSh24bT6.2-57T6.2-58T6.2"59Sjl1Sh2T6.2-59ASh1Amendment NumberRORORORORORl2828282128RORO27272826282728282828RO1717RORO26272628RO282726280RORO18PageT=Table~F=FiureSh26.2-59B6.2"59C6.2-59D6.2-606.2-616.2-626.2-63S}11S}126.2-646.2"65S}11S}126.2-16.2-26.2-36.2-46.2-56.2-66.2-76.2-86.2-96'-106.2-116.2-126.2-136.2"146.2-156.2-166.2-176.2-186.2-196.2-206.2-216'-226.2-236.2-246'-256.2-266.2-276.2-286.2-28A6.2-28B6.2-28CAmendment Number181815RO2727252424RORORORO000000002700000000018180180000ROROROROUSARRevision1'EP6-3October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureF6.2-29F6.2"29AF6.2-29BF6.2-29CF6.2-29DF6.2-29EF6'-29FF6.2-29GF6.2-29HF6.2-29IF6.2"29JF6.2-30F6.2-30AF6'-31F6.2-31AF6.2-31BF6.2-32F6.2-33Sjl1Sh2Sh3sh4S}15S}16S}17Sh8F6.2-33AF6.2-33BF6.2-34F6.2-35F6.2"36F6.2-37F6.2"38S}11S}12S}13Sh4S}l5S}16S}17Sh8S}19Sh10S}111S}112Amendment Number0llll11llll1111ll11ll11ll11RORO112323232323232323RORO0000ROROROROROROROROROROROROPageT=Table~F-FiureF6.2-39F6.2-39AF6.2-40F6.2-41F6.2-42F6.2-43F6.2"44F6.2"45F6.2-46F6'-46AF6.2-47F6.2-48F6.2-49F6.2-50F6.2-51F6.2-52F6.2-53S}11Sjl2S}13S}14S}15Sjl6F6.2-54F6.2-55F6.2-56S}11S}l2S113S}14Sh5S}16S}17S}18S}19Sjl10F6.2-57F6.2-58F6.2-59Sh1S}12S}13Sjl4S}15F6.2"60Amendment Number"0927272827RORORORO00027RO1111llll1111112311ll232323232323232323llllllllllll1123PageT=Table~F=FiureF6.2-61F6'-62Sjl1Sh2S}13Sh4Sjl5F6.2-62AF6.2-63F6.2-64S}11S}12S}13S}14Sh5F6.2-64AF6.2-65F6'-66S}l1S}l2S}13Sh4S}15Sh6F6'-66AF6'-67F6.2-68F6.2-68AF6.2-69F6'-69AF6.2-70Sh1Sh2Sh3S}14S}15Sh6S}17S}18Sjl9Sjl10S}111S}112S}113S}114Amendment Number111111llllllll11llll11ll111111llllll11llllll11271127RlRORORORO.ROROROROROROROROROUSARRevision1EP6-4October1989

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureSjl6F7.4-27.5-17.5-1a7.5"lb7.5-27.5-37.5-47.5-57.5-67~57T7.5-1S}11S}12Sjl3S}14S}15S}16Sjl7Sh8S}19~S}110Sh11Sh12S}113S}114T7.5"2Sh1Sh2S}13Sh4Sh5Sh6S}17S}18Sh9S}110S}111S}112Sjl13S}114S}115S}116S}117Sjl18S}119Amendment Number'ORORORORO270RO2723RORlRORORORORlROROROROROROROROROROROROROROROROROROROROROROROROROROROPageT=Table~F=FiureS}l20Sh21S}1227.6-17.6-27.6-2a7.6.2b7.6-37.6-3a7.6-3b7.6-47.6-4a7.6-4b7.6-57.6-67.6"6a7.6-6b7.6"77.6"87.6-8a7.6-8b7.6-8c7.6-8d7.6"97.6-9a7.6-9b7.6-107.6-10a7,.6-10b7.6"117.6-127.6"137.6-147.6-157.6-167.6-177.6-187.6"197.6-207.6-217.6-227.6-22a7.6"22b7.6-237.6-23a7.6"23bAmendment NumberRORORO18RlRO10RO1010Rl101026Rl18102724RlRORO'ORO1010RlRl18RlRlRl100027270270RlRORO131010PageT=Table~F=Fiure7.6-247.6-257.6-267.6-26a7.6-26b7.6-26c7.6-26d7.6-26e7.6-26K7.6-26g7.6-26h7.6-27T7.6-1T7'-2T7.6-3S}11S}12T7.6"4T7.6-5T7.6-6F7.6-1Sh1Sh2F7.6-2F7.6-3S}l1Sh2F7.6-4,F7'-5F7.6-6S}11S}12S}13S}14Sh5Sjl6Sjl7F7.6-7F7'-8F7.6-9S}l1S}l2S}l3S}l4S}15Sjl6Sh7Amendment Number1010181824181818RlRl180Rl10RORl102727RORO02323002323232323232327272323232323Rl23USARRevision1EP7"3October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureS}18S119Sh107.7-17.7-1a7.7"1b7~727~737'"47~757.7-67~777.7-87.7-97.7-107.7-117.7-127.7-137.7"147.7-157.7-167'-177.7-187.7-197.7"207.7-217.7-21a7.7-2lb7'-227'22a7'-22b7~7237'-247.7-24a7.7-24b7'-257.7-267~7277.7-27a7.7-27b7'-287.7-297.7-307.7-317'-327~733Amendment Number2323RO261010010'0270027Rl0002700Rl00RORORO1818182710RORlRl1410RO232323023RORO140PageT=Table~F=Fiure7.7-347.7-357.7-367~7377.7-387.7-397.7-39a7.7-39b7.7-407.7-417.7-42T7.7-1T7~72T7.7-3S}11,Sjl2F7.7-1S}11S}12S}13sh4S}15Sjl6S}17F7'-2S}11Sh2Sjl3Sjl4S}l5sh6S}17S}18S}19Sjl10S}111Sh12S}113S}114S}l15S}l16Sjl17S}118Sjl19Sjl20S}121S}122Amendment Number0999102626261010101010100RO2323RO23RORO23232323232323232323232323232323232323232323PageT=Table~F=FiureS}123Sh24S}125Sh,26Sjl27S}128Sjl29S}l30S}131Sh32S}133Sh34S}135F7.7-3F7.7-4F7.7-5F7.7-6S111S}12S}l3S}14S}15S}16Sh7F7.7-7F7.7-8F7.7-9F7'-10App7A7A.1-17A.1-27A.1-37A.1-47A.1-57A.1-67A.1-77A.1-87A.1-97A.1-107A.1-117A.1-127A.1-137A.1-147A.1-157A.1-16T7A.1-1Amendment Number232323RO23232323232323232301002323RORO23RORORORO0ROROROROROROROROROROROROROROROROROROROUSARRevision1EP7-4October1989 0

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER8PageT=Table~F=Fiure8-i8-ii8-iii8-iiia8-iiib8-iv8-v8-va8"vb8-vi8.1-18.1-28.1-38.1-3a8.1-3b8.1"48.1-58.1-68.1-78.1-8F8'-18.2"18.2-1a8.2-lb8.2-28.2"2a8.2-2b8.2-38.2-48.2-58.2-5a8.2"5b8.2-68.2-6a8,2-6b8.2-78.2-7a8.2-7b8.2-88.2-98.2"108.2-118.2-128.2"138.2-14Amendment NumberRORORO24240RORO26RO72727272700RO002714RO7RORORO021261414231471313130423RO2321ROPageT=Table~F=Fiure8.2-158.2-15a8.2"15b8.2-168.2-16a8.2"16b8.2-178.2-188.2-198.2-208.2-218'-228.2-238.2-23a8.2-23b8.2-248.2-24a8.2-24b8.2-24c8.2-24d8.2-258.2-26T8'-1Sh1Sh2Sh3sh4F8.2-1aF8.2-1bF8.2-lcF8.2-2F8.2-3F8.2-4F8.2-4a'F8.2-5F8.2-5aF8.2-6F8.2-6aF8.2-6bF8.2-6cF8.2-7F8.2-8F8.2-98.3-18.3-28.3-3Amendment Number2626262626267RORO23RORl23771523RO2828RORORORO1628RORORO267026262626262626RORO26PageT=Table~F=Fiure8.3-48.3-4a8.3-4b8.3-58.3-68.3-78.3-7a8.3-7b8.3-88.3-8a8.3-8b8.3-98.3-9a8.3-9b8.3-108.3-118.3-1la8.3-11b8.3-128.3-12a8.3-12b8.3-138.3-148.3-158.3-168.3"178.3-188.3-18a8.3-18b8.3-18c8.3-18d8.3-198.3-19a8.3-19b8.3-208.3-20a8.3-20b8.3-218.3-228.3-238.3-248.3-24a8.3-24b8.3-258.3-25a8.3-25b8.3-26Amendment Number23246RO23RO77Rl77Rl231323RO197RO23232720RO19RORORO28RO7RORORO25RO23RORO26RO2727RORO20ROUSARRevisionEP8-1October1989

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MilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER9PageT=Table~F=Fiure9-i9-ii9-iii9-iv9-iva9-ivb9-v9"vi9-vii9-viia9-viib9-viii9-ix9-x9-xi9-xii9-xiii9-xiiia9"xiiib9-xiv9"xv9-xvi9"xvii9-xviii9-xix9-xx9-xxi9"xxii9.1-19.1-29.1-2a9.1-2b9.1-39.1-3a9.1-3b9.1-49.1-59.1"69.1-6a9'-6b9.1-79.1-7a9.1-7b9.1-8Amendment Number5RO24121212RO242424230RORORORO24262624RlRORORORO24RORl052055225052020202855ROPageT=Table~F=Fiure9.1-8a9.1-8b9.1-99.1-9a9.1-9b9.1-109.1-10a9.1-10b9.1-119.1-11a9.1-11b9.1-129.1-139.1-149.1-14a9.1-14b9.1-159.1-15a9.1-15b9.1-169.1-179.1-189'-199.1-209.1-219.1-229.1-239'-249'-259.1-269.1-279.1-289.1-299.1-29a9'-29b9.1-309.1-319.1-329.1-339.1-349.1-359.1-369.1-379.1-389.1-39Amendment Number2320141414RO14142323232619261952828500242109021002100RORO28027210000000PageT=Table~F=Fiure9.1-409.1-419.1-429.1-42a9.1-42b9.1-439.1-449.1-459.1-46T9.1-1T9.1-2T9.1-3T9.1-4S}11S}12T9.1-5T9.1-6F9'-1F9'-1AF9.1-2F9.1-3F9'-3AF9'-4F9'-5aF9'-5bF9.1-5cF9.1-5dF9.1-6S}11S}12S}13S}14S}15Sh6S}17Sh8F9.1-7F9.1-8F9.1-9F9.1-10F9.1-11F9.1-12F9.1-13F9.1-14F9'-15Amendment Number,02727992320202000000519054RO523RORORORORORORORORORORORO2700000000USARRevision1EP9-1October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureF9.1-16F9.1-17F9.1-18F9.1-19aF9.1-20aF9'-21F9.1-22F9'-23F9.1-24F9.1-25F9.1-26a9.2-19.2-29.2-2a9.2-2b9.2-39.2-49.2-4a9.2-4b9.2"59.2-5a9.2"5b9.2"69.2-79.2-7a9.2-7b9.2-89.2-99.2-109.2-10a9.2-10b9.2-119.2-1la9.2<<lib9.2-129.2-139.2-149.2-159'-169.2-179.2-189.2-18a9.2-18b9.2-19Amendment Number000RORO0000RORO0RO552525255ll25524Rl252325282722222723232727RO027RORORO2525PageT=Table~F=Fiure9.2-209.2-219.2"229.2-22a9.2-22b9.2-239.2-23a9.2-23b9.2-249.2-259.2-25a9.2-25b9.2-269.2-26a9.2-26b9.2-279.2-289.2-28a9.2"28b9.2-299.2-309.2-319.2-329.2"339.2-349'-359.2-369.2-379.2-389.2-399.2-39a9.2-39b9.2-409.2"419.2-429.2-439.2-449'-459.2"469.2-46a9.2-46b9.2-479.2-489.2-48a9.2"48bAmendment Number25RORORORO23232323232318232318RO25252500000000002626260Rl22RORO23524524RO2020PageT=Table~F=Fiure9.2-499.2-509.2-51T9.2"lAS}11S}12Sh3S}14Sh5Sh6T9'-1BS}11Sh2S}13S}14S}15T9.2-2S}11S}12S}13Sh4S}15S}16S}17S}18S}19T9.2-3Sh1S}12T9.2-4S}11S}12S}13T9.2-5T9.2"6T9.2-7T9'-8T9.2-9F9.2-la9.2-1b9.2-1c9.2-1d9.2-le9.2-1j9.2-lgAmendment NumberRO230Rl282828RlRlRl282828RlRl282828Rl282828RlRO2323232300000ROROROROROROROUSARRevisionEP9"2October1989

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=Fiuee9A.3"44a9A.3"44b9A.3-459A.3-45a9A.3-45b9A.3"469A.3-479A.3-489A.3-48a9A.3-48b9A.3-499A.3-49a9A.3-49b9A.3"509A.3-50a9A.3-50b9A.3-50c9A.3-50d9A.3-50e9A.3-50K9A.3-519A.3-5la9A.3-51b9A.3-529A.3-52a9A.3-52b9A.3-52c9A.3-52d9A.3-539A.3"53a9A.3-53b9A.3-53c9A.3-53d9A.3"549A.3"559A.3-55a9A.3-55b9A.3-569A.3-579A.3-57a9A.3"57b9A.3-589A.3-599A.3"60T9A.3-1Amendment NumberRO13999RORO28RO28RO2813282828RO28RO28RO1010RlRORORORO28RORORO282623RO18RORO1713ROROROPageT=Table~F=FiueeSh1Sjl2S}l3Sjl4T9A.3-2S}L1S}L2Sh3T9A.3-3T9A.3-4Sh1Sjl2S}13Sjl4Sjl5S}16T9A.3-5T9A.3-6S}11S}12Sjl3S}l4Sjl5T9A.3-7S}11S}l2T9A.3-8Sjl1S}L2T9A.3-9Sjl1S}12Sh3T9A.3-10S}11S}12T9A.3-11T9A.3-12T9A.3-13,T9A.3-14T9A.3-15S}11Sjl2Sjl3S}14Amendment NumberRORlRlRORORlRORlRORlRlRlRlRlRlRORlRlRlRORORORORlRlRlRlRlRORORlRO626-122626PageT=Table~F=FiueeS}L5Sjl6T9A.3-16T9A.3-17S}L1S}12Sjl3T9A.3-18Sh1Sjl2Sjl3Sjl4Sjl5Sjl6S}L7T9A.3-19T9A.3-20Sjl1Sh2T9A.3-21F9A.3-1F9A.3-2F9A.3-3F9A.3-4F9A.3-5F9A.3-6F9A.3"7F9A.3"8F9A.3-9F9A.3-10F9A.3-11F9A.3-12F9A.3-13F9A.3-14Sjl1Sjl2F9A.3-15S}i1Sjl2F9A.3-16Sjl1Sjl2F9A.3-17Sjl1S}12Amendment Number2626RO28282828RO2828282828Rl2828RORlRORlRlRlRlRlRO232323RORORO28282828282828USARRevisionEP9-11October1989

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER1010-i10-ii10-iii10"iv10-v10-va10-vb10"vi2424240RORO24RO10.1-110.1-210.1-3T10'"1F10.1"1F10.1-2F10.1-3aF10.1-3bF10.1-3cF10.1"3d10021021ROROROROF10.1-3e.ROF10.1"3EF10.1-3gF10.1-34F10.1"3jF10.1-31@F10.1-4aF10.1"4bF10.1-4cF10.1-4dF10.1-5aF10.1-5bF10.1-5cF10.1-5dF10.1-5eF10.1"6aF10.1-6bF10.1-6cF10.1-6dF10.1-6eF10.1-7aF10.1-7bRORlRlRORlRORORORORlRlRORlRORORORORORORlRlF10.1-7cRlF10.1-7dF10.1-7eF10.1-7KF10.1-7gF10.1-711F10.1-7jROROROROROROPageT=TableAmendment ~F=FiureNumberPageT=Table~F=FiureF10.1-7kF10.1-71F10.1-7mF10.1-7nF10.1-7pF10.1-7qF10.1-7rF10.1-7sF10.1-7tF10'-7uF10.1-7wF10.1-8aF10.1-8bF10.1-8cF10.1-8dF10.1-8eF10.1-8KF10.1-8gF10.1-9aF10.1-9bF10.1-9cF10.1"9dF10.1-9eF101-9EF10.1-9gF10.1-9410.2-110'-210.2-310.2-3a10.2-3b10.2-410.2-510.2-5a10.2"5b10.2-610.2-710.2-810.2-910.2-1010.2-1110'-12F10.2-1F10.2-2F10.2-3Sh1Sh2Amendment NumberRORORORORORORORORORORORORORORORORORORORORORORORORORO21013287RORORORO0023000000Rl'PageT=Table~F=FiureSh310.3"110.3-la10.3-1b10.3-210.3-310.3-3a10.3-3b10.3-410.3"510.4-110.4-210.4-310.4-3a10.4-3b10.4"410.4-4a10.4-4b10.4-510.4-610.4-710.4-7a10.4-7b10.4-810.4-910.4-1010.4-1110'-1210.4"1310.4-1410.4-1510.4-1610.4-1710.4-17a10.4-17b10.4"1810'-1910.4-19a10.4-19b10'-2010.4-2110'-2210.4-2310.4-23a10.4-23b10.4-24Amendment Number55527RORO50230RO2166286600Rl2121RO27212100RORO0RORORO182828180002655RlUSARRevision1EP10-1October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=TableAmendment ~F=FiureNumberPageT=Table~F=FiureAmendment NumberPageT=Table~F=FiureAmendment Number10.4-2510.4-25a10.4-25b10.4-2610.4-26a10.4"26b10.4"2710.4-2810.4-28a10.4"28b10.4"2910.4"3010.4-3110.4-3210.4-3310.4-33a10.4-33b10.4-3410.4-34a10.4-34b10.4-3510.4-3610.4-3710.4-3810.4-39T10.4"1T10'-2F10.4>>1S}11Sh2S}13S}14Sh5F10.4-2aF10.4-3S}11Sh2S}13S}14Sh5F10.4-4F10.4-5F10.4-6F10.4-7aF10.4-7bF10.4"7cF10.4-7dF10.4-7e10552155RO24147RO00RO252520RO2020000240RO27RORORORORlRlRORORORORO000RORORORlROF10.4-7ZF10.4-7gF10.4-7}1F10.4-8Sh1Sh2Sh3Sh4Sh5Sh6Sh7Sh8S}19Sh10F10.4-9S}11Sh2Sh3sh4Sh5Sh6S}17Sh8Sh9Sh10F10.4-10Sh1Sh2Sh3Sh4S}15Sh6S}17Sh8Sh9Sh10S}111S}112S}113S}114Sh15Sh16Sh17Sh18Sh19Sh20S}121S}122RORORORORORORORORORORlRlROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROS}123F10.4-11S}11Sh2Sh3Sh4S}15Sh6Sh7S}i8Sh9F10'-12Sh1Sh2S}13S}14Sh5Sh6Sh7F10.4-13S}11S}12Sh3Sh4S}15Sh6S}17Sh8ROROROROROROROROROROROROROROROROROROROROROROROROROUSARRevision1EP10-2October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER11PageT=Table~F=Fiure11-i11-ii11-iia11-iibll-iii11-iv11-v11-vi11.1-111.1-211.1-311.1-411.1-5llew1-611.1-711.1"811.1-911.1"1011.1-1111.1"1211.1"1311.1"1411.1-15T11.1-1S}11Sh2S}13T11'-2'11.1-3T11.1-4T11'-5T11.1-6T11.1-7T11.1-8F11.1-1F11.1-2F11.1-311.2-111.2-211.2-311.2-3a11.2-3b11.2"411.2"4a11.2-4bAmendment Number24242323RO08RO00000000000000RO000231919Rl00000023RO232323RO55PageT=Table~F=Fiure11.2-511.2-5a11.2-5b11.2-611.2-6a11.2-6b11.2-711.2-811.2-911.2-1011.2-1111.2-1211.2-1311.2-1411.2-14a11.2-14b11.2-1511.2"1611.2"1711.2-18T11.2-1S}11S}12S}13S}14S}15T11.2-2T11'-3T11'-4T11.2-5S}11Sh2T11.2-6S}11Sh2F11.2-laF11.2-lbF11.2-lcF11.2-1dF11.2-1eF11.2-lfF11.2-1gF11.2-1hF11.2-1jF11.2-1kF11'-1LF11.2-1mAmendment Number5RO5RO55RORORORO23RORORORO23230RORORORORO2525RORO027272727RORORORORORORORORlROROROPageT=Table~F=Fiure11.3-111.3-1a11.3-1b11.3-211.3-2a11.3-2b11.3-311.3-411.3-511.3-5a'11.3-5b11.3"611.3-711.3-7a11.3-7b11.3".811.3-9T11'-1S}11S}12T11.3"2Sh1S}12T11.3-3S}11S}12F11.3-1aF11.3"lbF11.3-lcF11.3-211.4-111.4-1a11.4-1b11.4-211.4-2a11.4-2b11.4-311.4-3a11.4-3b11.4-411.4-4a11.4-4b11.4-511.4-6T11.4"1Amendment Number333RO2352323RORO5249991212120RORO1212RlRlRO0333'ORO8RORlRORORl23RlRORlUSARRevision1EP11-1October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureT11.4-2T11.4-3Sh1Sh2Sh3Sh4Sh5T11.4-4Sh1Sh2T11.4-5T11.4-6T11.4"7F11.4-laF11.4-lbF11.4-1cF11.4-1dF11.4-1eF11.4-1fF11.4"lgF11.4-1h11.5-111.5-211.5-2a11.5-2b11.5-311.5-3a11.5-3b11.5-411.5-511.5-5a11.5"5b11.5-611.5-711.5"811.5-911.5-1011.5-10a11.5-10b11.5"1111.5-lla11.5-11b11.5-1211.5-12a11.5"12b11'-13Amendment NumberRO282602626RORO888RlRORORORORORORO2323RO232323232323232323232323282323Rl2523237728PageT=Table~F=Fiure11.5-14T11.5-1S}11Sh2Sh2aT11'-2Sh1Sh2Sh3Sh4F11.5-1F11.5-2F11.5-3aF11.5-3bF11.5-3cF11.5-4F11.5-5F11'-6F11.5-7F11.5-8Sh1Sh2App11AllA-i11A-ii11A.l-lllA.1-2T11A.1-1T11A.l"2AT11A.1-3TllA.1-4TllA.1-5TllA.1-6T11A.1-7T11A.1-8TllA.1-9T11A.1-10T11A.1-11T11A.1-12TllA.1-13TllA.1-14TllA.1-15T11A.1-16T11A.1-17T11A.1-18TllA.1-19Amendment Number23RORORO00RO0RORORORORO230RORO0000RORORORORO00RO000002525250ROROROPageT=Table~FFiurellA.2-1llA.2-2T11A.2-1T11A.2-2Amendment NumberRO0ROROUSARRevision1EP11-2October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER12PageT=Table~F=Fiure12-i12-ii12-iii12"iv12-iva12-ivb12-v12-vi12-vii12-viia12-viib12-viii12-ix12-x12-xi12-xii12,1-112.1-212.1-312.1-412.1-512.1-612.1-712.1-812.1-912.1-9a12.1-9b12.1-1012.1-1112.1-1212.1-1312.1-13a12.1-13b12.1-1412.1-14a12.1-14b12.1-1512.2-112.2-1a12.2-1b12.2-212.2-312.2-412.2-512.2-6Amendment NumberRO24RO24241224Rl2424,240RORORORO0RO00RORO9Rl26990007777770ll1111011llRO0PageT=Table~F=Fiure12'-712.2-812.2-8a12.2-8b12.2-912.2-1012.2-1112.2-1212.2-1312.2-1412.2-1512.2-16T12.2-1T12.2-2T12.2-3T12.2-4S}11S}12S}13T12'-5S}11S}12T12~2-6S}11S}l2Sh3T12.2-7S}11S}12T12.2"8S}11S}l2T12.2-9T12'-10S}11S}12S}13T12.2-11T12.2-12S}11S}12S}13T12.2-13S}11S}12S}13T12.2-14Amendment Number0999RO2507799llRORORORORORlRlRO0RORl00RlRlRlRl0RlRlRlRlRlRO7PageT=Table~F=FiureT12.2-15aT12.2-15bT12.2"1612.3"112.3"212.3-312.3-412.3"512.3-612.3-712.3-7a12.3-7b12.3-812.3"912.3-1012.3"ll12.3-11al 12.3-1lbl 12.3-11a12.3-11b12.3-11c12.3-11d12.3-lie12.3-llf12.3-1212.3-1312.3-1412.3-1512.3-15a12.3-15b12.3-1612.3-1712.3-1812.3-1912.3-2012.3-2112.3-2212.3-2312.3-23a12'-23b12.3-2412.3-2512.3-2612.3-2712.3-2812.3-29Amendment NumberROROll000RO'0RORORO07RORO20201313RORORO13RO005550010Rl010101010RO100010ROUSARRevisionEP12-1October1989

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NineMilePoint'Unit 2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=Fiure12.5-1412.5-14a12.5-14b12.5-1512.5-1612.5-1712.5-1812.5-1912.5-20T12'-1T12.5"2T12.5-3T12.5-4Amendment Number55528RORORO2626RlRO51PageT=TableAmendment ~F=FiureNumberPageT=TableAmendment ~F=FiureNumberUSARRevision1EP12-3October1989 3 NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER13PageT=Table~F=Fiure13"i13-ii13-iii13-iv13-iva13-ivb13-v13-vi13-vii13-viii13.1-113.1-213.1-2a13.1-2b13.1-313.1-3a13.1-3b13.1-413.1-4a13.1"4b13.1-513.1-5a13.1-5b13.1-6T13.1-1T13.1-2T13.1"3Sh1ShlaSh2Sh2aS}12bSh2cSh3Sh3aSh4Sh5Sh6S}17T13.1"4Sh1S}L2S}13Sh4Amendment NumberRORORORORO9RORORORO28RlRO9RO99RORO1RO9928RO28RORORORORORORORO282302828282816PageT=Table~F=FiureSh5T13.1"5F13.1-1F13.1-1aF13.1-2F13.1-3F13.1-3aF13.1"4F13.1-4aF13.1-5F13'-5aF13.1-5bF'3.1"6F13'-7F13.1"8F13'"9F13.1-1013.2-113.2-213.2-313.2-413.2-513.2-613'-713.2-813.2-913.2-1013.2-1113.2-1213.2-1313.2-1413.2-1513.2-1613.2-1713.2-1813.2-1913.2-2013.2-2113.2-2213.2-2313.2-2413.2-2513.2-2613.2-27Amendment Number2828RlRlRlRORORORORO139RORORORORORORORORORORORORORORORORORORORORORORORORORORORlROROROROPageT=Table~F=Fiure13.2-2813.2-2913.2-3013.2-3113.2-3213.2-3313.2"3413.2"3513.2-3613.2-3713.2-3813.2-3913.2-40T13.2-1F13.2-113.3"113.3-213.4-113.4"213.4-2a13.4-2b13.4-313.4-4T13.4"1T13.4-2Sh1S}12S}L3T13.4-3Sh1Sh2Sh3F13.4-113.5-113.5-213.5-313.5-3a13.5-3b13.5"413.5-4a13.5"4b13.5-5Amendment NumberRORORORORORORORORORORORORORO28RORORORORORORORORORORORORORORORORORORORO6RO66ROUSARRevisionEP13-1October1989

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER15PageT=Table~F=Fiure15-i15-ii15-iii15-iv15-v15-vi15-vii15-viii15-ix15-x15-xi15-xii15-xiii15-xiv15-xv15-xvi15-xvii15-xviii15-xix15-xx15-xxi15-xxii15-xxiia15-xxiib1S-xxiii15-xxiv15-xxv15-xxvi15-xxvii15.0-115.0-215.0-315.0-415.0-515.0-615.0"715.0-7a15.0-7b15.0-815.0-915.0"1015.0-1115.0-lla15.0-11b15.0-11cAmendment NumberRO0000RO24240RO62412RO018RORO24024RO18180022240000000666Rl00772828PageT=Table~F=Fiure15.0"lid15.0-12T15'-1S111Sjl2S113T15.0-2T15.0-3Sh1Sh2S113T15.0-4T15.0-5S}11Sjl2F15.0-1F15.0-2F15.0-315.1-115'-215.1-2a15'-2b15.1-315'-415.1-515'-615.1-715.1-815.1-915.1-1015.1-1115.1-1215.1-1315.1-1415.1-1515.1-1615.1-17T15'-1T15.1-2T15'-3T15.1-4T15'-5T15.1-6F15.1-1F15.1-2Amendment NumberRORORlRlRl002200RORO000022660272200270022270000022RO22260000PageT=Table~F=FiureF15.1-3F15'"415.2-115.2-215.2-315.2-415.2-515;2-615.2-715.2-815.2-8a15'-8b15.2-915.2-1015.2-1115.2-1215.2-1315.2-1415.2-1515.2-1615.2-1715.2-1815.2-1915.2-2015.2-2115.2-21a15.2-21b15.2-2215.2-2315.2-2415'-2515.2-25a15.2-25b15.2-2615'-2715.2-2815.2-2915.2-3015.2-3115'-3215.2-32a15.2-32b15.2-3315.2"34'15'-1Amendment Number000622220RlRlRl022028RORO22230000RORORO220010101000222200222222000USARRevisionEP15-1October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=FiureT15.2-2T15.2-3T15.2-4T15.2-5T15.2-6T15.2-7Sh1S}l2T15.2-8T15.2-9T15.2-10S}11S}12T15.2-11T15.2-12T15.2-13F15.2-1F15.2-2F15.2-3F15.2-4F15.2-5F15.2-6F15.2-7F15.2-8F15'-9F15.2-10F15.2-11NotesS}11S}12F15.2-12F15.2-13F15.2-14F15.2"15F15.2-16F15.2-1715.3-115.3-215.3-315.3-415.3-515.3-615.3-715.3-815.3"9Amendment Number000280000220022272200222200001022222222000000000220022270PageT=Table~F=Fiure15.3-1015.3-1115.3-1215.3-1315.3-14T15'-1T15'-2T15.3-3T15.3-4T15.3-5F15.3-1F15.3-2F15.3-3F15.3-4F15.3-515.4-115.4-215.4-315.4-415.4-4a15.4-4b15.4-515.4-615'-715.4-815.4-915.4-1015.4-1115.4-1215.4-1315'-1415'-1515.4-15a15.4-15b15.4-1615.4-1715.4-1815.4-18a15.4-18b15.4-1915.4-2015.4-21T15.4-1T15.4-2T15'-3Amendment Number2200002210102210000000222828RO280022000022220226272212RORO12120280022PageT=Table~F=FiureT15.4-4T15.4-5T15.4-6T15.4-7T15.4-8T15.4-9T15.4-10S}11S}l2T15.4-11T15.4-12T15.4-13T15.4-14T15.4-15T15.4-16F15.4-1F15.4-2F15.4-3F15.4-4F15.4-5F15.4-6F15.4-7F15.4-815.5-115.5-215.5-3T15.5-1F15.5"115.6-115.6-215.6-315.6"415.6-515.6-615.6"715.6-815.6-8a15.6-8b15.6-915.6-1015.6-1115.6-1215.6-12a15.6-12a.l Amendment Number220002722121212121212121222220000.001212RO120012RO1212250ROROROROUSARRevision1EP15"2October1989 ' NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=Fiuee15.6-12a.2 15'-12b15.6"12c15.6-12d15.6-1315.6-13a15.6-13b15.6-1415.6-14a15.6-14b15.6-1515.6-1615.6-1715.6-18T15.6-1S}11Sh2T15.6-2T15.6-3T15.6-4T15.6-5T15.6"6Sb1Sh2T15.6-7T15.6"8T15.6-9T15.6"10T15.6-11T15,6"12T15.6-13Sh1S}12Sjl3S114S45Sh6Sb7Sh8Sb9S1110S1111S1112Sh13T15.6-14T15.6-15aAmendment Number25RORO18Rl1313231010025018RORl012Rl28RORO12RORO121212RORORORORORORORORlRORORORORO23PageT=Table~F=FiueeT15.6-15bT15.6-16aT15.6-16bT15.6-17T15.6-18T15.6-19T15.6-20T15.6-2115.7-115.7-215.7-315.7-415.7-515.7-615.7-715.7-815.7-915.7-1015.7-1115.7-1215.7-1315.7-13a15.7-13b15.7-1415.7-1515.7-1615.7-1715.7-18T15.7-1T15.7-2T15.7-3T15.7-4T15.7-5T15.7-6T15.7-7Sh1Sh2T15.7-8S111Sb2T15.7-9S}11Sb2T15.7-10T15.7-11Amendment NumberRO23RO131313132202523190RO000000RORORO121812RORl251300Rl0230RORORlROPageT=Table~F=FiueeT15.7-12T15.7-13T15.7-14T15.7-15T15.7-16Sb1S112T15.7-1715.8-115.8-215.8-315.8-4App15A15A-i15A"ii15A-iii15A-iv15A-v15A-vi15A-vii15A-viii15A-115A-215A-315A-415A-515A-615A-715A-815A-915A-1015A"1115A-1215A-1315A-1415A-1515A-1615A-1715A-1815A-1915A-2015A-2115A-2215A-23Amendment NumberRO121212RlRlRl18181818USARRevisionEP15-3October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=Fiure15A"2415A-2515A-2615A"2715A-2815A-2915A-3015A"3115A-3215A-3315A-3415A"3515A-3615A-3715A-3815A-3915A"4015A"4115A"4215A-4315A-4415A-4515A-4615A-4715A"4815A-4915A-5015A-5115A-5215A-5315A-5415A-5515A-5615A"5715A-5815A-59T15A"1T15A-2S111S}12T15A-3T15A-4T15A-5T15A"6T15A-7T15A-8Amendment NumberPageT=Table~F=FiureT15A-9T15A-10T15A-11F15A-1F15A-2F15A-3F15A-4F15A-5F15A-6F15A-7F15A-8F15A-9F15A-10F15A-llF15A-12F15A-13F15A-14F15A-15F15A-16F15A-17F15A-18F15A-19F15A-20F15A-21F15A-22F15A-23F15A-24F15A-25F15A-26F15A-27F15A-28F15A-29F15A-30F15A-31F15A-32F15A-33F15A-34F15A-35F15A-36F15A-37F15A-38F15A-39F15A-40F15A-41F15A-42F15A-43Amendment Number000000000000000028000002800000000000000000000000PageT=Table~F=FiureF15A-44F15A-45F15A-46F15A-47F15A-48F15A-49F15A-50F15A-51F15A-52F15A-53App15B15.B-i15.B-ii15.B-iii15'-iv15.B.1-115.B.1-215.B.2-115.B.2-215.B.2-315.B.2-415'.2-515.B.2-615'.3-115'.3-215.B.3-315.B.3-415.BE3-515.BE3-615.B.3-715.B.3-815.B.3-915.B.3-10 15.B.3-11 15.B.3-12 15.B.3-13 15.B.3-14 15.B.3-15 15.B.3-16 15'.3-1715.B.3-18 15.B.3-19 15'E3-2015.B.3-21 15.B.3-22 Amendment Number2626262626Rl2626262626262626262626262626262626262626262626262626262626USARRevisionEP15-4October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~F=Fiure15.B.4-115.8.4-215.B.4-315.B.5-115.BE5-215.B.5-315.BE5-415.B.6-115.B.6-215.B.6-315.B.6-415.B.6-515.B.7-115.B.7-215.B.8-115.B.8-2App15C15C-i15C-.ii15C-iii15C"115C-215C"315C-415C-515C-615C-715C-815C-915C-1015C-1115C-1215C-1315C-1415C-1515C-1615C-1715C-1815C"1915C-20App15DApp15E15E-iAmendment Number262626262626262626262626262626262626262626262626262626262626262626262626262626262626ROPageT=Table~F=Fiure15E-ii15E-iii15E.1-115E.1-215E.2-115E.2-215E.3-115E.3-215E.3-315E.3-415E.3-515E.3-615E.3-715E.3-815E.3-915E.3-1015E.3-1115E.3-1215E.3-1315E.3-1415E.3-1515E.3-1615E.3-1715E.3"1815E.4-115E.4-215E.4-315E.4"415E.4-5>15E.4-615E.5-1App15FApp15GApp15H15H-115H-2158-3158-415H-515H-615H-715H-815H-9Amendment NumberRO2626RORORORO26RORlRORl26RO26RORO262626282626262626RORO2626ROROROROROROROROROROROROROPageT=Table~F=Fiure15H-1015H-ll15H-1215H-1315H-14Amendment NumberROROROROROUSARRevision1EP15-5October1989

NineMilePointUnit2FSAR~LISTOFEFFECTIVE PAGESCHAPTER16IPagePageT=TableAmendment T=TableAmendment ~F=FiureNumber'F=FiureNumberPageT=TableAmendment ~F=FiureNumber16"1ROUSARRevision0EP16-1April1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER17PageT=Table~F=Fiure17-i17"ii17-iii17-iv17-v17.0"117.0-217.0-3T17.0-117.1-117.1-1a17.1-1b17.1-217.1-2a17.1-2b17.1-317.1-417.1-4a17.1-4b17.1-517.1-5a17.1-5b17.1-617.1-717'-817.1-917.1-1017'-10817.1-10b17.1-1117.1-1217.1-1317.1-13a17.1-13b17.1-1417.1-1517.1-15a17.1-15b17.1-1617.1-16a17.1-16b17.1-1717.1-17aAmendment Number'3915RO2470157RO262028RO92828282828RO528RO280281313RO092852899555555PageT=Table~F=Fiure17.1-17b17.1-1817.1-1917.1-2017.1-2117.1-2217.1-22a17'-22b17.1-2317.1-23a17.1-23b17.1-2417.1-24817.1-24b17.1-2517.1-2617.1-2717.1-27a17.1-27b17.1-2817.1-2917.1-3017.1-30817.1-30b17.1-3117.1-3217.1-32a17.1-32b17.1"3317.1-33a17.1-33b17.1-3417.1-34617.1-34b17.1-3517.1-35a17.1-35b17.1-3617.1-36817.1-36b17.1"3717.1-3817.1-38a17.1-38b17.1-39Amendment Number5000028289RO5555105999005519999555'9Rl9281515928501528285PageT=Table~F=Fiure17.1-39a17.1-39b17.1-4017.1-40a17.1-40b17.1-4117.1-4217.1-4317.1-43817.1-43b17.1-4417.1-44a17.1-44b17.1-4517.1-4617.1-4717.1-4817.1-4917.1-5017.1-50a17.1-50b17.1-5117.1-5217.1-53T17.1-1S111Sh2S113Sh4Sh5F17.1-1F17.1-217.2-1Amendment Number959225905555559028285111013180000028ROROUSARRevisionEP17-1October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER18PageT=Table~F=Fiure18.1-118.1-1a18.1-1b18.1-218.1-2a18.1-2bT18.2-1Sh1Sh2Sh3Sh4T18.2-2T18.2-3T18.2-4T18.2-5S}11Sh2Sh3Sh4Sh5Sh6Sh7Sh8T18.2-6S}11S}12F18.2-1F18.2-2F18.2-3F18.2-4F18.2-5F18.2-6F18.2-7F18.2-8F18.2-9F18.2-10F18.2-11F18.2-12F18.2-13F18.2-14F18.2-15Amendment NumberROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROROPageT=Table~F=Fiure18.2-1618.2-1718.2-1818.2-1918.2-2018.2-2118.2"2218.2-2318.2-2418.2-2518.2-2618.2-2718.2-2818.2-2918.2"3018.2"3118.2-3218.2-3318.2-3418.2-3518.2-3618.2-3718.2"3818.2-3918.2-4018,2-4118.2-42Amendment NumberROROROROROROROROROROROROROROROROROROROROROROROROROROROPageT=TableAmendment ~F=FiureNumberUSARRevision18-1April1989

NineMilePointUnit2DARLISTOFEFFECTIVE PAGESDESIGNASSESSMENT REPORTAPPENDIX6APageT=Table~F=Fiuee6A-i6A-ii6A-iii6A-iiia6A-iiib6A-iv6A-v6A-vi6A-vii6A-viia6A-viib6A-viii6A-viiia6A-viiib6A-ix6A-ixa6A-ixb6A-x6A-xi6A-xii6A-xiii6A-xiv6A-xv6A"xvi6A-xvii6A-xviii6A-xviiia 6A-xviiib 6A-xix6A-xx6A-xxi6A-xxii6A-xxiia6A-xxiib6A-xxiii6A-xxiv6A-xxv6A-xxvi6A-xxvii6A-xxviii 6A.l-l6A.1-26A.1-2a6A.1-2b6A.1-3Amendment Number24024242424247242492799212417RO24RO27242524RO2422222424RORO242402424242424269999PageT=Table~F=Fiuee6A.1-46A.1-5T6A.1-1S}L1S}12Sh3F6A.l-lF6A.1-2F6A.1-36A.2-16A.2-26A.2-36A.2-46A.2-56A.2-66A.2-76A.2-86A.2-8a6A.2-8b6A.2-96A.2-106A.2-116A.2-126A.2-136A.2-14T6A.2-1Sh1S}12T6A.2-1aSh1Sh2T6A.2-1bSh1S}L2T6A.2-2S}L1S}12Sh3T6A.2-3S}11S}12S}13F6A.2-1F6Ae2-2F6A.2-3'mendment Number023000170RO00000027555RO023230272727232323023000PageT=Table~F=FiueeF6A.2-4F6A.2"5F6A.2-6F6A.2-7F6A.2-8F6A.2-9F6A.2-10F6A.2-11F6A.2-12F6A.2-13F6A.2-14F6A.2-15F6A.2-16F6A.2-17F6A.2-18F6A.2-19F6A.2-20F6A.2-21F6A.2-22F6A.2-23F6A.2-24F6A.2-25F6A.2-26F6A.2-276A.3-16A.3-26A.3-36A.3-46A.3-56A.3-66A.3-76A.3-86A.3-96A.3-9a6A.3-9b6A.3-9c6A.3-9d6A.3-9e6A.3-9Z6A.3-9g6A.3-9h6A.3-9i6A.3-9j6A.3-9k6A.3-91Amendment Number0RORORORORORORORORORORORORORORORORORORORORO0230000260260'22222222222222222222222222USARRevision1DAR-1October1989

NineMilePointUnit2DARLISTOFEFFECTIVE PAGESPageT=Table~F=Fiure6A.3-106A.3-116A.3"12T6A.3-1T6A.3-2T6A.3-3T6A.3"4T6A.3"5T6A.3-6T6A.3-7T6A.3-8T6A.3"9T6A.3"10T6A.3-11T6A.3-12T6A.3"13T6A.3-14T6A.3-15F6A.3-1F6A.3-2F6A.3-3F6A.3-4F6A.3-5F6A.3"6F6A.3-7F6A.3"8F6A.3-9F6A.3-10F6A.3-11F6A.3-12F6A.3-13F6A.3"14F6A.3-15F6A.3-16F6A.3-17F6A.3-18F6A.3-19F6A.3"20F6A.3-21F6A.3"22F6A.3-23F6A.3"24F6A.3"25F6A.3-26F6A.3"27F6A.3-28Amendment Number000000000000000000RORO00RORORO0000RORORORORO0RORORORORO000000PageT=Table~F=FiureF6A.3-29F6A.3-30F6A.3-,31F6A.3-32F6A.3-33F6A.3-34F6A.3-35F6A.3-36F6A.3-37F6A.3-38F6A.3-39F6Ae3-40F6A.3-41F6A.3-42F6A.3-43F6A.3-446A.4-16A.4-26A.4-2a6A.4-2b6A.4-36A.4-46A.4-4a6A.4-4b6A.4-56A.4-5a6A.4-5b6A.4-66A.4-76A.4-86A.4-8a6A.4-8b6A.4-96A.4-106A.4-116A.4-126A.4-12a6A.4-12b6A.4-136A.4-146A.4-156A.4-166A.4-16a6A.4-16b6A.4-17Amendment Number00RO0RORORORO0RO000RO23230RORORO0232121232321RO0232321000232360232626660PageT=Table~F=Fiure6A.4-186A,4-196A.4-19a6A.4-19b6A.4-206A.4-216A.4-226A.4-236A,.4-246A.4-24a6A.4-24b6A.4-256A.4-25a6A.4-25b6A.4-266A.4-276A.4-286A.4"296A.4-306A.4"316A.4-326A.4-336A.4-346A.4-356A.4-366A.4-376A.4-37a6A.4-37b6A.4-386A.4-396A.4-406A.4-41T6A.4-1sh1Sh2T6A.4-2T6A.4-3T6A.4-3aT6A.4-4T6A.4-5T6Ae4-6T6A.4-7S}11Sh2T6A.4-8T6A.4-9Amendment Number0621212302827232319222222232323232626026000232121RORO021RORO0RO21280002300USARRevision1DAR-2October1989

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NineMilePointVnit2DARLISTOFEFFECTIVE PAGESPageT=Table~F=PiureF6A.5-40F6A.5-41F6A.5-42F6A.5-436A.6-16A.6-26A.6-36A.6"4T6A.6-1T6A.6-2Sb1Sh2F6A.6-1F6A.6-2F6A.6-3F6A.6-4Sh1S}12F6A.6-5F6A.6-6F6A.6-76A.7-16A.7-26A.7-36A.7-46A.7-56A.7-5a6A.7-5b6A.7-66A.7-7T6A.7-1T6A.7-2F6A.7-16A.8"16A.8-26A.9-16A.9-26A.9-36A.9-46A.9-4a6A.9-4b6A.9-5Amendment Number2323232300260232323RO000700237723230230000RORORO27PageT=Table~P=Fiure6A.9"66A9-76A.9-86A.9-96A.9-9a6A.9"9b6A.9-106A.9-116A.9-11al 6A.9-llbl 6A.9-lla6A.9-11b6A.9-11c6A.9-11d6A.9-11e6A.9-1lf6A.9-12T6A.9"1T6A.9-2T6A.9-2aT6A.9-2bT6A.9-3T6A.9-4T6A.9-5T6Ae9-6T6A.9-7F6A.9-1F6A.9-2F6A.9-36A.10-16A.10-26A.10-36A.10"46A.10-56A.10-66A..10-76A.10-86A.10-96A.10-9a6A.10-9b6A.10-10T6A.10-1T6A.10-2S111Sjl2Amendment NumberRORO202020202020202099999923RlRORORORORORORORO232323RlRO212221212121RO2424ROROROROPageT=Table~FPiureT6A.10-3T6Ae10-4T6A.10-5T6A.10"6T6A.10-7T6A.10-8T6A.10-9F6A.10-1F6A.10-2F6A.10"3F6A.10-4F6A.10-5F6A.10-6F6A.10-7F6A.10-8F6A.10-9F6A.10-10F6A.10-11F6A.10-12F6A.10-13F6A.10-14F6A.10-15F6A.10-16F6A.10-17F6A.10-18F6A.10-19F6A.10-20Amendment Number21212121Rl212121RORORORORORORORORORlRlRl22222222222222USARRevision1DAR-4October1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESAPPENDIXRREVIEWSAFESHUTDOWNANALYSISAPPENDIX98PageT=Table~F=Fiure98-i98-ia98-ib98-ii98-iii98-iv98.1-198.2-198'-298.2-398.3-198'-198.4-298.4-398.4-498.4-598.4-698.4-798.4-8F98.4-1F98.4-298.5"198.5-298.5-398.5-498'-5T98.5-198.6-198.6-298.6-398.6-4T98.6-1Sh1Sh2Sh3Sh4Sh5Sh6T98.6-2Amendment Number242423RO24423RO442342244224442222RO442123RO221125112828RORORORO11Page"T=Table~F=FiureT98'-3Sh1Sh2Sh3Sh4Sh5sh6Sh7Sh7aS}18Sh9F98.6-1F98'-2F98.6-3F98.6-4F98.6-5F98'-698.7-198.8-198.8-298.8-398.8-498.8-598.8-5a98.8-5b98.8-698.8-7T98'-1Sh1ShlaSh2S}13sh4Sh5Sh5aSh6S}17Sh8Sh9Sh10Sh11Sh12Sh13Amendment Number23llRO11RO1123RO28114llllllllll23RO23Rl23RlRlRO25RORO2811RO28282811282828RO11RO11PageT=Table~F=FiureSh14Sh15Sh16Sh17Sh18Sh19Sh20Sh21Sh22Sh23Sh24Sh25Sh26Sh27Sh28Sh29Sh30Sh30aSh31Sh32Sh33Sh34S}135Sh36Sh37Sh38Sh39Sh40Sh41Sh42Sh43Sh44Sh45Sh46Sh47Sh48Sh49Sh50Sh51Sh52Sh53Sh54Sh55Sh56Sh57Amendment NumberllRO1111RO11282828282828ROROROROROROllRORO2828232323232323232323232323232323llRORO23RO1919USARRevisionSSA-1October.1989

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESPageT=Table~P=PiureS}158Sh59Sh60Sh60aSh61Sh62Sh63Sh64Sh65Sh66Sh66aSh67Sh68Sh69Sh70Sh71Sh72Sh73Sh73aSh74Sh75Sh75aT9B.8-2Sh1Sh2Sh3Sh4Sh5Sh6Sh7Sh8S}19Sh10Sh11Sh12S}113Sh14Sh15Sh16Sh17Sh18Sh19Sh20Sh21Sh22Amendment NumberROllRORORORORORORORORORORORORORORORORORORORO281128ll2828281111ll11ll282828282828ROROROROPageT=Table~F=FiureSh23Sh24Sh25Sh26Sh27Sh28Sh29Sh29aSh29bSh29cSh29dSh29eSh29'h30Sh31Sh32Sh33Sh33aSh34Sh34aSh35Sh36Sh37Sh38Sh38aSh38bT9B.8-3Sh1Sh2Sh3Sh4Sh5Sh5aS}16Sh7Sh8Sh9Sh10S}111Sh12Sh13Sh149B.9-1Amendment NumberRORO2828282323232323232323llllRO2323RORO11'328RO23Rl23RORORORORORORORORORO23RORlROROPageT=Table~F=Fiure9B.10-19B.ll-l9B.12-19B.12-29B.12-39B.12-49B.12-59B.12-69B.12-79B.12-89B.12-99B.12-109B.12-11Amendment NumberRO21ROROROROROROROROROROROUSARRevisionSSA-2October1989 f0I>' NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolume5.3ReactorVessel5.4Component andSubsystem DesignAppendixes 5A,5B131313CHAPTER6ENGINEERED SAFETYFEATURES136.16.26,36.46.56.6Appendixes 6Athrough6CEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 13141515151515CHAPTER7INSTRUMENTATION ANDCONTROLSYSTEMS157.17.27'7.47.57.67~7Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControls.Engineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMS16161616i1717179.19.29.39'9.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17181920,2121,2223USARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSION SYSTEM2310.110.210.310.4Summary,Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion System23'232411.111.211.311.411.5SourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystemsAppendix11ACHAPTER12RADIATION PROTECTION CHAPTER11RADIOACTIVE WASTEMANAGEMENT 2424252525252512.112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B262626,26262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARCHAPTER1LISTOFFIGURESFigureNumber1.1-11.2-11.2-21.2-31.2-41.2-5TitleHEATBALANCEATRATEDPOWERPLOTPLANSTATIONARRANGEMENT DELETEDDELETEDDELETED261.2-6Sjl.1l.2-6S}1.21.2-71.2-7SI1.21.2-8S11.11.2-8Sjl.2GENERALARRANGEMENT, REACTORBUILDINGPLANEK175'-0"AND188.'-6"GENERALARRANGEMENT, REACTORBUILDINGPLANEK196'-0"GENERALARRANGEMENT, REACTORBUILDINGPLANEL215'-0~~GENERALARRANGEMENT, REACTORBUILDINGPLANEK240'-0"GENERALARRANGEMENT, REACTORBUILDINGPLAN-EL261'-0"ANDMISCELLANEOUS GENERALARRANGEMENT, REACTORBUILDINGPLANEL215'-0"ANDMISCELLANEOUS 1.2-9S11.1GENERALARRANGEMENT, REACTORBUIKDINGPLANEL289'-0"1.2-9Sh.21.2-10Sh.1GENERALARRANGEMENT, REACTORBUILDINGPLANEL306'-0"GENERALARRANGEMENT, REACTORBUILDINGPLANEL328'-10"1.2-10Sh.2GENERALARRANGEMENT, REACTORBUILDINGPEANEL353'-10"Amendment 261-viiMay1986 NineMilePointUnit2FSARCHAPTER1LISTOFFIGURES(Cont)FigureNumberTitle1.2-111.2-121.2-131.2-141.2-151.2-161.2-171.2-18GENERALARRANGEMENT, REACTORBUILDINGSECTIONS(SHEETS1THROUGH4)GENERALARRANGEMENT, REACTORBUILDINGSECTION2-21GENERALARRANGEMENT, RADWASTEBUILDINGPLANEL261'0",270'9I'ND309'0"(SHEETS1THROUGH3)GENERALARRANGEMENT, RADWASTEBUILDINGSECTIONSGENERALARRANGEMENT, CONTROLROOMPLANEL360'-0"I288'-6"I261'-0"(SHEETS1THROUGH3)GENERALARRANGEMENT, CONTROLBUILDINGGENERALARRANGEMENT, EMERNGECY DIESEIGENERATOR BUILDINGPLAN(SHEETS1THROUGH6)GENERALARRANGEMENT, EMERGENCY DIESELGENERATOR BUILDINGSECTIONS1.2-191.2-201.2-22'"I1.2-231.2-24GENERALARRANGEMENT, TURBINEBUILDINGPLANEL250'-0"(SHEETS1AND2)GENERALARRANGEMENT, TURBINEBUILDINGPLANEL277'-6"(SHEETS1AND2)GENERALARRANGEMENT, TURBINEBUILDINGPLANEL306'-6"(SHEETS1AND2)GENERALARRANGEMENT, TURBINEBUILDINGSECTION1-1(SHEETS1AND2)GENERALARRANGEMENT, TURBINEBUILDINGPLANSECTION2-2AND4-4.(SHEETS 1AND2)GENERALARRANGEMENT, TURBINEBUiLDINGPLANSECTION3-3Amendment 241ViiiFebruary1986 .NineMilePointUnit2FSARCHAPTER1LISTOFFIGURES(Cont)FigureNumberTitle1.2-25GENERALARRANGEMENT, TURBINEBUILDINGPLANSECTION5-51.2-261.2-271.2-281.2-291.2-301~2-311.2-321~2331.2-341.2-351.2>>361~2371.2-38GENERALARRANGEMENT, SCREENWELL BUILDINGWATERTREATMENT ANDSERVICEWATERPUMPSPLAN(SHEETS1AND2)GENERALARRANGEMENT, SCREENWELL BUILDINGWATERTREATMENT ANDSERVICEWATERPUMPSPLANSECTION(SHEETS1AND2)GENERALARRANGEMENT, SCREENWELL BUILDINGWATERTREATMENT AND,SERVICE WATERPUMPSPLANSECTIONGENERALARRANGEMENT ANDDETAILS,INTAKEANDDISCHARGE TUNNELS(SHEETS1THROUGH3)GENERALARRANGEMENT ANDDETAILS,INTAKESTRUCTURE GENERALARRANGEMENT ANDDETAILS,MAINSTACKGENERALARRANGEMENT, NORMALSWITCHGEAR BUILDINGPLANS(SHEETS1THROUGH3)GENERALARRANGEMENT, NORMALSWITCHGEAR BUILDINGGENERALARRANGEMENT, AUXILIARY BOILERHOUSEGENERALARRANGEMENT, STANDBYGASTREATMENT BUILDINGEL261'-0"GENERALARRANGEMENT, STANDBYGASTREATMENT BUILDINGANDRAILROADACCESSIOCKSECTIONGENERALARRANGEMENT, CONDENSATE STORAGETANKBUILDING(SHEETS1AND2)COOLINGTOWERFILLLEVELPLANANDSECTIONAmendment 241-ixFebruary1986 NineMilePointUnit.2FSARCHAPTER1LISTOFFIGURES(Cont)FigureNumber1.2-391.2-401.7-11.7-21.7-31.7-41.8-1~TitleCOOLINGTOWERSECTIONBELOWTHEFILLLEVELGENERALARRANGEMENTi HYDROGENSTORAGEAREAPIPINGANDINSTRUMENTATION DIAGRAM(SWEC)(SHEETS1THROUGH5)PIPINGANDINSTRUMENT SYMBOLS(GE)LOGICDIAGRAMSSYMBOLS(SWEC)(SHEETS1AND2)ELECTRICAL'NE-LINE DIAGRAMSSYMBOLS(SWEC)ENGINEERED SAFETY-FEATURE FILTERDRAINARRANGEMENT 1.10-11.10-21.10,-31.10-4DELETEDDELETEDDELETEDDELETEDUSARRevision01-xApril1989 NineMilePointUnit2FSARTABLE1.8-1(Cont)ReulatorGuide1.23Revision0Februar1972OnsiteMeteorological ProgramFSARSection2.3.3PositionNiagaraMohawkPowerCorporation complieswithRegulatory Guide1.23(SafetyGuide23)(February, 1972).However,thewindspeedsensorinuseatthe200-ftleveluntilJuly1982didnotmeettherequirements oftheguide.Thenewsensorinstalled afterJuly1982hasthestartingspeedandac-curacyspecified bytheRegulatory Guide.Thesevereweatherconditions encountered atNineMilePointleadtothechoiceoftheveryruggedwindspeedsensorin-stalledinNovember1972.Ithadastartingspeedofabout2.6mphandwouldcontinuetooperatewithspeedsof1to1.5mph.Thewindspeedaccuracyis+1.0mphabove10mphasopposedto,theRegulatory Guide1.23Criterion I0.5mphforall)windspeeds.Moresensitive windspeedsensorsavailable atthattimewerepronetoicingandphysicaldamagefromhighwindspeeds.24of169

NineNilePointUnit2FSARTABLE1.8-1(Cont)RelatorGuide1.58Revision1Setember1980Cont3.5.2LevelIIOneyearofsatisfactory performance asLevelIor5yearsrelatedexperience inthecorresponding inspection, examination, ortestcategoryorclass,or2.Highschoolgraduation/GED equivalent plus3yearsofrelatedexperience inequivalent inspection, examination, ortestingactivities, or3.Completion ofcollege-level workleadingtoanas-sociatedegreeinarelateddiscipline plus1yearrelatedexperience inequivalent inspection, examination, ortestingactivities, or4.-Four-year collegegraduateplus6monthsofrelatedexperience inequivalent inspection, examination, ortestingactivities. 3.5.3LevelIIISixyearsofsatisfactory performance asaLevelIIor15yearsofrelatedexperience inthecor-responding inspection, examination, ortestcategoryorclass,or2.Highschoolgraduate/GED equivalent plus10yearsofrelatedexperience inequivalent inspection, examination, ortestingactivities; orhighschoolgraduation plus8yearsexperience inequivalent inspection, examination, ortestingactivities, withatleast2yearsasLevelII,andwithat'least2yearsassociated withnuclearfacilities orifnot,atleastsufficient trainingtobeac-quaintedwiththerelevantqualityassurance aspectsofanuclearfacility, or3.Completion ofcollegelevelworkleadingtoanas-sociatedegreeand7yearsofrelatedexperience inequivalent inspection, examination, ortestingactivities, withatleast2yearsofthisex-perienceassociated withnuclearfacilities, orifnot,atleastsufficient trainingtobeacquainted 65of169 0-NineMilePointUnit2FSARTABLE1.8-1(Cont)ReulatorGuide1.58Revision1Setember1980Contwiththerelevantqualityassurance aspectsofanuclearfacility, orFour-year collegegraduateplus5yearsofrelatedexperience inequivalent inspection, examination, ortestingactivities, withatleast2yearsofthisexperience associated withnuclearfacilities -orifnot,atleastsufficient, trainingtobeacquainted withtherelevantqualityassurance aspectsofanuclearfacility. 5.Graduatedegreeplus3yearsofrelatedexperience inequivalent inspection, examination, ortestingactivities, withatleast2yearsofexperience as-sociatedwithnuclearfacilities or,ifnot,atleastsufficient trainingtobeacquainted withtherelevantqualityassurance aspectsofanuclearfacility. NMPCTheNMPCqualityassurance programforUnit2iscurrently incompliance withRegulatory Positions C.5,6,7,8,and10ofRegulatory Guide1.58,Revision1.NSSSGeneralElectricstartupoperations personnel qualifications meettherequirements ofthisguideasdescribed below:1.Personnel areselectedandtrainedaccording tothecriteriaofANSIN18.1-1971 (NRC.Regulatory Guide1.8),withtheexception ofNRCLicensing. 2.TheOperations Managermeetstheequivalent ofANSIN18.1,Paragraph 4.2.2,Operations Manager.TheOperations Managerisnormallypresentforpreoperational testing,andwilltherefore bequalified atthetimethatpreoperational testingisbegun.3.TheOperations Superintendent meetstheequivalent ofANSIN18.1,Paragraph 4.3.1,Supervisors Requiring NRCLicenses. TheOperating Superinten-66of169

NineMilePointUnit2FSARTABLE1.8-1(Cont)RelatorGuide1.58Revision1Setember1980Contdentwillnormallybepresentforpreoperational testingandtherefore willbequalified atthetimepreoperational testingisbegun.TheShiftSuperintendents meetthequalification ofANSIN18.1,Paragraph 4'.1,Supervisors Requiring NRCLicenses. 5.TheLeadStartupTestDesignandAnalysisEngineermeetsthequalifications ofANSI.N18.1,Paragraph 4.4.1,ReactorEngineering andPhysics.Hewillbequalified atthetimeofinitialcoreloadingorappointment, totheposition. Hisonsiteresponsibilities beginjustpriortofuelloading.6.TheStartupTestDesignandAnalysisEngineers meetthequalifications ofANSIN18.1,Paragraph 3.3,ReactorTechnical supportpersonnel. Theironsiteresponsibilities beginjustpriortofuelloading.7.TheStartupControlandInstrumentation Engineermeetsthequalifications ofANSIN18.1,Paragraph 4.4.2,Instrumentation andControl.Hewillbequalified atthetimepreoperational test-ingisbegun.8.TheStartupChemistmeetsthequalifications ofANSIN18.1,Paragraph 4.4.3,.Radiochemistry, utilizing cumulative experience fromseveralreac-torstartupprograms. Hewillbequalified atthetimeoftheinitialcoreloading.67of169

NineMilePointUnit2FSARTABLE1.8-1(Cont)RelatorGuide1.108Revision1Auust1977PeriodicTestingofDieselGenerator UnitsUsedasOnsiteElectricPowerSystemsat,NuclearPowerPlantsFSARSections8.3.1.2,14.2PositionTheUnit2projectcomplieswith'theRegulatoxy Position(Paragraph C)ofthisguide.TheIEEE387-1977(Section3.7)definitions ofContinuous RatingandShort-Time Ratingareappliedtothedieselgenerator continuous ratingand2-hourratingreferredtoinSectionC.2.a.3oftheRegulatory Guide.Section3/4.8oftheTechnical Specifications detailstheperiodictestingrequirements ofthedieselgenerator units.26Amendment 26122of169May1986

NineMilePointUnit2CESARTABLE1.8-1(Cont)RelatorGuide1.134Revision1March1979MedicalEvaluation ofNuclearPowerPlantPersonnel Requiring Operating LicensesFSARSectionChapter13PositionTheUnit2projectcomplieswiththeRegulatory Position(Paragraph C)ofthisguide.Themedicalrequirements forpersonnel requiring operatorlicenses, asdetailedinANSIN546-1976 andendorsedbythisguidewillbeimplemented bySiteAdministrative Procedures. 149of169

NineMilePointUnit,2FSARThestaffrealizesthatthenecessary knowledge andexperience canbegainedinavarietyofways.Consequently, creditforequivalent experience shouldbegiventoapplicants forSROlicenses. Applicants forSROlicensesatafacilitymayobtaintheir1yroperating experience inalicensedcapacity(Operator orSeniorOperator) atanothernuclearpowerplant.Inaddition, actualoperating experience inapositionthatisequivalent toaLicensedOperatororSeniorOperatoratmilitarypropulsion reactorswillbeacceptable onaone-for-one basis.Individual applicants mustdocumentthisexperience intheirindividual applications insufficient detailsothatthestaffcanmakeafindingregarding equivalency. Applicants forSROlicenseswhopossessadegreeinengineering orapplicable sciencesaredeemedtomeettheaboverequirement, providedtheymeettherequirements setforthinSectionsA.l.aandA.2inenclosure 1intheletterfromH.R.Dentonandallpowerreactorapplicants andlicensees, datedMarch28,1980,andhaveparticipated inatrainingprogramequivalent tothatofacoldSeniorOperatorApplicant. TheNRChasnotimposedthe1-yrcoldapplicants forSROlicenses. workonafacilitynotyetinprogramsaredesignedtosupplyexperience notavailable tothem.experience requirement onColdapplicants aretooperation; theirtrainingtheequivalent oftheNineMilePointUnit2PositionTheUpgrading ofOperatorTrainingandSeniorOperatorTrainingforUnit2isbeingperformed asdescribed -inSection13.2oftheFSAR.Thisisalsoinaccordance withtheSiteAdministrative Procedures. 1.10-15 NineMilePointUnit2FSARI.A.2.3ADMINISTRATION OFTRAININGPROGRAMSFSARCrossReference Section13.2.1NUREG-0737 PositionPendingaccreditation oftraininginstitutions, licensees andapplicants foroperating licenseswillassurethattrainingcenterandfacilityinstructors whoteach-systems, integrated responses, transient, andsimulator coursesdemonstrate SROqualifications andareenrolledinappropriate requalification programs. Theabovepositionisashort-term position. Inthefuture,accreditation oftraininginstitutions willincludereviewof,theprocedure forcertification ofinstructors. Thecertification ofinstructors mayormaynotincludesuccessful completion ofaSeniorOperatorexamination. Thepurposeoftheexamination istoprovidetheNRCwithreasonable assurance duringtheinterimperiodthatinstructors aretechnically competent. Therequirement isdirectedtopermanent membersofthetrainingstaffwhoteachthe.subjects enumerated above,including membersofotherorganizations whoroutinely conducttrainingatthefacility. Thereisnointention torequireguestlecturers whoareexpertsinparticular subjects(reactortheory,instrumentation, thermodynamics, healthphysics,chemistry, etc)tosuccessfully completeaSeniorOperatorexamination. Nordoweintendtorequireasystemexpert,suchastheSupervisor-Instrument andControlMaintenance teachingtherodcontrol"drive systemtositforaSeniorOperatorexamin-ation.Theuseofguestlecturers shouldbelimited.NineMilePointUnit2PositionTrainingcenterandfacilityinstructors whoteachsystems,integrated responses, transient, andsimulator coursespresently holdSROlicensesonUnit1and,assuch,areenrolledinoperatorrequalification

programs, asoutlinedinsiteadministrative procedures.

Thequalification ofthetraininginstructors meetstherequirements ofthistask,asdescribed inSection13.2oftheFSAR.USARRevision01.10-16April1989 NineMilePointUnit2'FSARII.K.3.22 RCICSUCTIONSOURCEFSARCrossReference Sections5.4.6,7.4NUREG-0737 PositionThereactorcoreisolation cooling(RCIC)systemtakessuc-tionfromthecondensate storagetankwithmanualswitchover tothesuppression poolwhenthecondensate storagetanklevelislow.Thisswitchover shouldbemadeautomatically. Untiltheautomatic switchover isimplemented, licensees shouldverifythatclearandcogentprocedures existforthemanualswitchover oftheRCICsystemsuctionfromthecon-densatestoragetanktothesuppression pool.NineMilePointUnit2PositionTheUnit2projecthasimplemented theNRCpositiontoautomatically transferRCICsuctionsource.Condensate storagetanklowwaterinventory automatically initiates transferofthesuctionoftheRCICpumptothesuppression pool.Themodification oftheRCICsystemallowsautomatic switchover ofpumpsuctionfromthecondensate storagetanktothesuppression poolifthecondensate storagetankfallstoapresetlowlevel.Lowlevelinthetankismonitored bytworedundant leveltransmitters. Ifeithertransmitter senseslowlevel,pumpsuctionisautomatically transferred tothesuppression pool.Thesearedifferent transmitters/trip unitsfromthosethatactivateswitchover fortheHPCSsystem.Thecondensate storagetanksuctionvalvewillbesignaledtocloseuponopeningofthesuppression poolsuctionvalve.TheP&ID,Figure5.4-9,andelementary diagramhavebeenrevisedtoreflectarelocation ofthetransmitter tothepumpsuctionline.USARRevision01.10-93April1989 NineMilePointUnit2FSARII.K.3.24 RCICANDHPCISUPPORTPOWER'SAR CrossReference Section9.4NUREG-0737 PositionLong-term operation ofthereactorcoreisolation cooling(RCIC)andhighpressurecoolantinjection (HPCI)systemsmayrequirespacecoolingtomaintainthepumproomtem-peratures withinallowable limits.Licensees shouldverifytheacceptability oftheconsequences ofacompletelossofacpower.TheRCICandHPCIsystemsshouldbedesignedtowithstand acompletelossofoffsiteacpowertotheirsup-port,systems,including coolers,foratleast2hr.NineMilePointUnit2PositionTheUnit2ECCSdesignemploysacubiclearrangement toen-surephysical, electrical, andenvironmental separation ofeachportionoftheECCS.TheRCICsystemisalsolocatedwithinaseparatecubicle.TheHPCS,pump roomiscooledbyeitheroftwofullyredundant CategoryIunitspacecoolers.Theremaining ECCSpumproomsandtheRCICpumproomareeachcooledbyoneCategoryIunitspacecoolerwithanad-ditionalcoolerprovidedasaspare.Thesecoolersarepartofthereactorbuildingheating,ventilation, andaircon-ditioning (HVAC)systemwhichutilizecoolingwaterfromtheservicewater(SWP)system.Thesafety-related portionsoftheSWPsystemarepoweredfromthestandbydieselgenerators .following alossofoffsitepower;therefore areliablesupplyofcoolingwaterisprovided.,

Likewise, thecontrolsystemsinvolvedintheoperation oftheunitcoolersalsoreceivetheirpowerfromthedieselgenerators following alossofoffsitepower.Thisdesignassuresthat.thepumproomtemperatures aremaintained withinnormallimitsforanindefinite periodfollowing acompletelossofoffsitepower.1.10-94 NineMilePointUnit2FSAR'ABLEIII.D.3.4-1 RESULTSOFTOXICCHEMICALANALYSISFORTHECONTROLROOMHABITABILITY STUDYChemicalLocationJ.A.FitzPatrick PlantAlcanRoute104NineMilePointUnit1NineMil'ePointUnit2OswegoWireIncorporated USARRevision0ChemicalN~HqSOCO~PropaneHalonCl~PropaneNqHclCO~HclN~CO~NqCOqHqSOHclHalonHqSOCO~Halon1301N~Isopropyl AlcoholNqPropaneH~SOMaximumControlRoomConcentration (m'1.26.6x106.21.291.730.0381.10.090.0032.5x100.0090.540.022.214.71.3x0.0090.576.6x10446.83.8832.12.2x1041.2x102.1x101.0x101.10-133ToxicLimit(m'74-0.00254.843.10.04543.12740.0554.80.05027454.827454.80.0020.054320.00254.84322741.227443.10.002Allowable TimePeriod(min1521515215151521515215152151521515151515152April1989 h

NineMilePointUnit2FSARInadditiontotheloadcombination requirement forthecon-tainmentdesign,thereisa.fatigueanalysisrequirement forthelinerofaconcretecontainment. Forsteelcontainment, theconsideration offatigueisspecified inASMEBoilerandPressureVesselCodeSectionIII,Division1,Subsection NE.However,thelinerontheconcretefoundation mat.ofthesteelcontainment shouldbetreatedasthelinerofacon-cretecontainment. Sincethestaff'spositionrequiresthepoollinertobedesignedinaccordance withtheASMEBEcPVCodeSectionIII,Division1,Subsection NE,itissuggested thatagenericmethodtoconsiderfatigueofboththesteelcontainment andthesteellinerintheconcretecontainment shouldbeadopted.PositionTheabsolutesummethodofcombining dynamicloadsisusedforthedesignofstructures. Thedetailsofloadcom-binations usedindesigning thestructures arecoveredinFSARSection3.8.TheUnit2primarycontainment linerisevaluated forfatiguetotherequirements ofASMEBoilerandPressureVes-selCodeSectionIII,Division1,Subsection NE.LICENSING ISSUE:43-FLUID/STRUCTURE INTERACTION IssueThedynamicforcingfunctions forvariousloadshavebeenestablished throughtestingonmodelsthataregenerally morestiffthantheactualstructures towhichtheloadswillbeapplied.Bydirectlyapplyingsuchforcingfunc-tionstoactualstructures intheanalysis, theinteractive effectbetweenthefluidmassandthestructure isneglected. Undercertainconditions, thiseffectmaybesignificant. Itisproposedthatagenericapproachtostudysucheffectsshouldbeestablished. PositionThisissueisnotdirectlyapplicable totheUnit2MarkIIcontainment. SincetheUnit2containment isstiffinthesuppression pool,regionandthedynamicforcingfunctions areconservatively defined,anyinteractive effectbetweenthefluidmassandthestructure isinherently included. Amendment 31.12-31June1983 NineMilePointUnit2FSARLICENSING ISSUE44-LONG-TERM POST-LOCA OPERABILITY OFDEEP-DRAFT ECCSPUMPSIssueIEBulletin79-15,datedJuly1979,identified problemswithdeep-draft ECCSpumpsthatcouldthreatentheirlong-term post-LOCA operability. Structure flexibility; shaft/column misalignment; vibrational frequencies nearrotationspeeds;inletflowinducedvortices; anddimensional deficiencies such*asthosediscovered withcertainLaSalleECCSpumps,couldcauseexcessive vibration andbearingwear.TheNRCstaffhasaskedapplicants todefineprogramsandprovidedatathatcomparetheexpectedservicelifewiththeac-cumulated operating timeandconfirmthelong-term operability. PositionTherearefivesafety-related deepdraftpumpsutilizedintheUnit2design.Thesearethreeresidualheatremovalpumps,onelowpressurecorespraypump,andonehighpres-surecorespraypump.TheinherentdesignfeaturesoftheByronJacksonECCSpumpsinUnit2precludeexcessive vibration andbearingwear.Eachpumpissuppliedwithacasingorsuctionbarrelandisnotinstalled inawetsump.Theydonothavelong,limbercolumns;thelongestpumpisonly24ft,comparedtothe30-to160-ftpumpsdescribed inIEBulletin79-15.Alsothepumpassemblyrigidityisenhancedbyseismicringsbetweentheassemblyandthebarrel.Thepumpsuseadouble-suction firststagetoprovidestability overawiderangeofflows.Columnfrequencies arewellremovedfrompumpspeed.Largerdiameterbarrelsprovidelowflowvelocities aroundpumpinlets,andringseismicrestraints 'ctasflowstraighteners tosuppressvortexformation. Thepumpshavehigh-precision, keyed,sleeve-type couplings. AnNRCletterdatedDecember8,1983,requested additional information onmethodsusedtoqualifylong-term operability ofdeepdraftpumps.Thefollowing isadescription ofthemethodused.Long-term operability hasbeenconsidered intheemergency corecoolingsystem(ECCS)pump-design.TheECCSpumps'ffectiveness isevaluated byacceptance, qualification, andin-planttesting.Long-term operability isassuredbypreventive maintenance, functional testingandsurveil-lance,"andvibration monitoring. Scheduled preventive maintenance consistsofresistance readingsofmotorwindings; lubrication ofcriticalrotatingcomponents; generalcleaningandinspection ofrotatingelectrical equipment; andinspection,

overhaul, alignment, andadjust-USARRevision01.12-32April1989 Ni.'neMilePo'intUnit2FSARmentofimpellerlift.Functional-testing measurements ofeachpump'sinletpressure, differential

pressure, flowrate,andvibration asprescribed bySectionXIoftheASMEB&PVCodeandapplicable addenda,asrequiredby10CFR50.55a, providedataforengineering analysistoidentifyper-formance.changesortrends.Inaddition, vibrati'on databases,established duringthe,preoperational/startup testing,arecomparedwithfunctional-testing vibration datatomonitorjournalbearingwearandshaftwhip.Functional testingandsurveillance requirements arespeci-fiedinUnit2Technical Specifications, surveillance procedures, andinservice inspection (ISI)programs.

Preventive maintenance andsurveillance testingaresche-duledatperiodicintervals astheISIprogramtestresultsindicate. AspartoftheUnit2plantISIprograms, vibration measurements willbetakeninaccordance withSectionXIoftheASMEBoilerandPressureVesselCodeandapplicable Addendaasrequiredby10CFR50.55a. Thedatawillbeevaluated onascheduled basistopredictpotential bearingandjournalfailuresandestablish replacement schedules. Datawillbeavailable onsiteforinspection. Vibration shouldbelimitedto0.3in/secvelocitypeak-to-peakoverallmeasuredfrequencies, asmeasuredbyanIRD360orequivalent equipment, whenthemotorandpumpareoperatedasaunitoverthenormaldesignrangeofpressureandflow.Thislimitisbasedonnormaloperation. Highermomentary increases maybeacceptable duringstartingoratshutoff.Thislimitisnotbasedonwhattheequipment canwithstand. Theequipment damagethreshold ishigher:closeto0.020inch,momentary andnotsustained. Anysustained vibration over0.3in/secmaycauseextensive bearingwear.Thesedeepdraftpumps,duetotheirrelativeshortness, demonstrate feweroftheproblemsassociated withlongerpumps.Thehydraulic designhasbeendeveloped overthelast40yearsofexperience inmanyapplications. TheECCSpumpscontaindesignfeaturestoprecludefailureoftheimpellers, impellerstaking,shafts,bearings, wearrings,couplings, andstuffingboxes.Thedesignincludes,safetyfactors(loadingcriteria) basedontheexpectedpressures, temperatures, andloadingsdefinedinthedesignspeci'fication. Lateralrestraints areincludedinthepumptocontroldeflections. Tolerances assuringalignment oftheshaftandpumpingelementsareverifiedbydesigncalculations. Motorshaftdeflections withintolerance arepredicted inastaticseismicanalysisandareverifiedbyaqualification testofasimilarmotor.Adynamicanalysisofthepumpandmotorisperformed todetermine USAR-Revision01.12-32aApril1989 NineMilePointUnit"2FSAR.resonances andpredictloadingsthroughout thepumpandmotor.Testsareperformed oneachpumpdelivered. Thetestsincludeheadversusflow,NPSH,andvibration monitoring. Theassembled pumpsarecheckedforproperassemblyandlowfrictionbyhandturning(rotating) theshaft.Eachpumpisrunforatotalof100hrduringtesting.Aqualifica-tiontestofasimilarpumpmotorwasperformed. Thisdataprovidesqualification oftheUnit2pumpsmotorsbyasimilarity analysis. USARRevision01.12-32bApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolume5.3ReactorVessel5.4Component andSubsystem DesignAppendixes 5A,5B131313CHAPTER6ENGINEERED SAFETYFEATURES136.16.26.36.46.56.6Appendixes 6Athrough6CEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 13141515151515CHAPTER7INSTRUMENTATION ANDCONTROLSYSTEMS157.17'7'7.47.57.67~7Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafety'ontrol SystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8AELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystem1616.16'16,17ICHAPTER9AUXILIARY SYSTEMS179.19.29.39.49.5Appendixes FuelStorageandHandlingWater'SystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17,181920,2121,2223USARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont:)SectionCHAPTER1010.110.210.310.4CHAPTER11TitleSTEAMANDPOWERCONVERSION SYSTEMSummary.Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemRADIOACTIVE WASTEMANAGEMENT Volume2323232411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems242425252525-CHAPTER12RADIATION PROTECTION 2512.112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)iv26 NineMilePointUnit2FSARCHAPTER2LISTOFTABLES'ableNumberTitle2~11MINIMUMDISTANCEBYSECTORBETWEENRESTRICTED AREABOUNDARYANDROUTINERELEASEPOINTS2.1-22~132.1-42.1-52.1-62~172.1-82.1-92.1-102.1-112.1-122~1132.1-142.1-152.1-162'-172.1-181980POPULATION ANDPOPULATION DENSITIES FORTOWNSANDCITIESWITHIN16KM(10MI)OFUNIT21970-1980 POPULATION GROWTHFORTOWNSANDCITIESWITHIN16KM(10MI)OFUNIT2DELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDDELETEDPOPULATION CENTERSWITHOVER25,000PEOPLEIN1980Amendment 72-izDecember1983 NineMilePointUnit2FSARCHAPTER2LISTOF,TABLES(Cont)TableNumberTitle2.1-192.1-202.1-212.1-222.2-12.2-22~232.2-4DELETEDDELETEDDELETEDDELETEDDAILYTRAFFIC,VOLUMEOF.COUNTYHIGHWAYSINTHEVICINITYOFUNIT21978FREIGHTTRAFFICFORLAKEONTARIOAROUNDOSWEGOHARBORINDUSTRIAL FIRMSWITHIN8KM(5MI)OFUNIT2ARMYCORPSOFENGINEERS HAZARDOUS MATERIALCOMMODITY DESIGNATION FORRATERBORNE COMMERCE2.2-52.2-62~272.2-82.2-92.3-12.3-2HAZARDOUS MATERIALS STORED/USED BYINDUSTRIES WITHIN8KM(5MI)1978LAKEONTARIOCARGOTRANSPORT FOROSWEGOHARBORSOURCESOFTOXICCHEMICALS WITHIN8KM(5MI)OFUNIT2SITEPREDICTED VAPORCONCENTRATIONS INTHEUNIT2CONTROLROOMINPUTDATAFORVAPORRUNDESIGNBASISTORNADOPARAMETERS VERTICALPROFILEOFTHE100-YEARRECURRENCE INTERVALFASTESTMILEOFWINDAmendment, 242-xFebruary1985 NineMilePointUnit2FSAR2.2NEARBYINDUSTRIAL, TRANSPORTATION, ANDMIIITARYFACILITIES 2.2.1Locations andRoutesOnlyonemanufacturing orindustrial plant,AlcanAluminumCorporation's AlcanSheetandPlateDivision, islocatedwithin8km(5mi)ofUnit2.Therearealsotwoelectrical powergeneration facilities, theJ.A.FitzPatrick NuclearPowerPlantoperatedbyNYPAandNineMilePointUnit1operatedbyNiagaraMohawkPowerCorporation, locatedwithin8km(5mi)ofUnit2.Figure2.1-2showsthelocationofthesetwofacilities relativetoUnit2.Theprincipal productsoftheAlcanAluminumCorporation plantarealuminumsheetandplate.Therearenochemicalplants,refineries, militarybases,orunderground gasstoragefacilities within8kmoftheplant.Inaddition, nopipelineorfuelstoragefacilities liewithinthe8-kmradiusexceptthosestoragefacilities associated withtheAlcanplant,theFitzPatrick plant,andNineMilePointUnits1and2.Finally,therearenohazardous wastestorageordisposalsitespermitted bythestateinthe8-kmradiusfromtheplant.Majortransportation facilities areshownonFigure2.2-1.Theprincipal roadwaywithin8kmofUnit2isU.S.Route104whichpasses6.2km(3.9mi)southoftheplantandconnectsthecityofOswegoandMexicoVillage.DailytrafficvolumeforU.S.Route104was5,841vehiclesin1979.Highwayaccesstothesiteisviatwocountyroutes,RoutelAtothesouthwest andRoute29totheeast.Aprivateeast-west roadcrossesthesiteandconnectsthesetwocountyroutes.Otherlocalroadsinthe,vicinitygenerally hadaveragedailytrafficcountsoffewer.than2,000vehiclesin1978-1979, themostcurrentsurveydates. Table2.2-1presentsdailytrafficvolumecountsforcountyhighwayswithin8kmoftheplant.Onerailroadcompany,Consolidated RailCorporation (Conrail), transports freightinthevicinity, oftheplant.TheraillinesandspursservingUnit2,aswellastheJ.A.FitzPatrick plantandNineMilePointUnit1,areshownonFigure2.1-2.TheclosestraillinetoUnit2istheOswego-Mexico branchofConraillocatedapproximately 2.5km(1.5mi)fromtheNineMilePointsite.Thisbranchlinehasdailyserviceondemandandaveragesonetraindaily,5daysaweek.Arailspurwasconstructed toserveUnit2duringconstruction andoperation oftheplant.PossibleAmendment 192.2-1May1985 NineMilePointUnit2FSARrsourcesoftrafficorhazardous materials utilizing groundtransportation routeswithin8kmoftheplantareiden-tifiedanddetailedinSection2.2.3.TheOswegoRiverpasseswithinllto12km(6.6to7.2mi)ofUnit2atitsnearestpointandservesasamajorrouteforwaterborne commerceonLakeOntario.Freighttrafficstatistics aremaintained bytheU.S.ArmyCorpsofEngineers. TotalsfortheriversectionfromNewYorkStateBargeCanal'LockNo.8totheportoftheCityofOswegoaretheonlystatistics applicable forthenearestreachofrivertothestation.Table2.2-2detailsthe1978freighttrafficforthisreachofriver.ThePortofOswego,theeasternmost portonLakeOntario,islocatedapproximately llkm(6.6mi)southwest ofUnit2andprovidesalinkwithallportsontheGreatLakesandSt.LawrenceRiver.Shipsinnormalcommercial lanesboundtoandfromthePortofOswegopassnocloserthan11.3km(7mi)totheintakestructures ofUnit2.Regularcommercial airserviceisprovidedattheClarenceE.HancockAirport,located49.8km(31mi)southeast ofUnit2nearSyracuse, NY.Thenearestflightcorridorassociated withthisairportis22.2km(13.8mi)fromtheNineMilePointStation.LightplanetrafficishandledattheOswegoCountyAirportinthetownofVolney,approximately 19.3km(12mi)southoftheNineMilePointsite.LakesideAirstrip, aprivatefacilitywhichoperatesprimarily asamaintenance

facility, withverylittleairtraffic,islocatedalongRoute176approximately 10km(6.2mi)southoftheNineMilePointsite.Itisnotanticipated thattherewillbeanysignificant in-creaseinthenumberofindustrial, transportation, andmilitaryfacilities locatedwithinan8-kmradiusofUnit2overtheplantlifetime.

Therearealsonosignificant changesexpectedinthenatureofexistingfacilities ortheextentoftheiractivities withinthedesignated areaovertheprojected lifetimeofUnit2.2.2.2Description 2.2.2.1Description ofFacilities Majorindustrial facilities within8kmofUnit2arelistedinTable2.2-3.AlcanRolledProducts, locatedap-proximately 4.5km(2.7mi)southwest ofNineMilePointStation,isthelargestemployerwithapproximately 1,000workersmanufacturing aluminumsheetandplating.Nohazar-dousmaterials aremanufactured withinthe8-kmradius.Hazardous materials storedorusedarediscussed inSection2.2.2.2.TheNewYorkStateDepartment ofUSARRevision0202-2April1989 NineMilePointUnit2FSAR.Environmental Conservation recordsthetype,amount,androuteofhazardous materials carriedinthestate.Oneraillinepassesthroughthe8-kmradius.ConrailhasabranchlineservingAlcanAluminum, NineMilePointUnits1and2,andtheJames'.FitzPatrick NuclearPowerPlant.Themainlineislocatedapproximately 3.5km(2.1mi)atitsnearestpointfromUnit2.Waterborne commercestatistics preparedbytheU.S.ArmyCorpsofEngineers onlypartially identifyspecifichazardous materials onLakeOntario.Commerceisrecordedbygeneralcommodity <'~.Alistingofhazardous materials identified,and theircommodity designations isprovidedinTable2.2-4.Hazardous materials transported byairhavenotbeenidentified becauseofthedistanceofairwaysandfacilities fromUnit2.2.2.2.2Description ofProductsandMaterials Toidentifyhazardous materials regularly storedorusedwithin8kmofUnit2,surveyswereconducted ofindustrial firms,pipelinecompanies, anddistributors thatmightbeexpectedtohandletoxicchemicals orexplosives. Appendix2Adescribes themethodusedtocollectdataregarding hazardous materials usedbyvariousindustries near.the-site.Hazardous materials considered areincludedinTable2.2-4.Toxicchemicals andexplosives storedorusedbyindustries ordistributors inthevicinityofthestationaresummarized inTable2.2-5.Nopipelines orlocaldistribution andstoragelocations arefoundwithin8kmofUnit2.Waterborne .commercefor1978LakeOntariotrafficisdescribed inTables2.2-2and2.2-6.Approximately 1.2milliontonsofcargoweretransported onLakeOntario.Sincemorespecificcommodity categories arenotusedindatacollection, therearenomeansofidentifying types,frequency, andamountsofhazardous materialshipments pastthesite.Thenearestpassageofcommercial vesselstoUnit2occurswhennavigating toandfromtheCityofOswegoharbor,locatedapproximately 10km(6.2mi)fromNineMile.PointSt'ation. ThePortofOswegoAuthority indicates thatnoneofthehazardous materials listedinTable2.2-5havebeenUSARRevision02~23April1989 NineMilePoint'nit 2FSARtransported onLakeOntario,eitheroriginating atordestinedtothePortofOswego.Allindustries reportedreceiving hazardous materialshipments viaU.STHighway104andCountyRoute1bytruck.2.2.2.3Projections ofIndustrial GrowthTherearenoplansformajorexpansion intransportation, storage,orindustrial facilities inthevicinityofUnit2.2.2.3Evaluation ofPotential Accidents Theconsideration ofa'arietyofpotential accidents, andtheireffectsontheplantorplantoperation, isincluded.inthissection.Typesofaccidents considered includeexplosions, flammable vaporclouds,toxicchemicals, fires,collisions withintakestructures, andliquidspills.2.2~3~1Determination ofDesignBasisEvents2.2.3'.1Explosions Basedonacomprehensive surveyofindustries withina10-km(6.2-mi)radiusofUnit2,thenearest.highwayonwhichexplosive materials canbetransported isRoute104,,whichisadistanceofabout6.2km(3.9mi)fromsafety-related structures. Thisseparation distancefarex-ceedsthesafedistancefortrucktraffic(approximately S48.6m,1,800.ft) givenonFigure1ofRegulatory Guide1.91.Indiscussions withConrail,it,wasdetermined thatnoex-plosiveorflammable materials aretransported to,theOswegoterminaloftheraillinebetweenOswegoandMexico,NY.Inanyevent,thedistancefromthisraillinetoUnit2ismuchgreater,thanthesafedistanceforrailtrafficgiveninRegulatory Guide1.91.Sincethenearestcommercial shippinglanesonLakeOntarioaremorethan10km(6'mi)fromUnit2(according totheU.S.CoastGuard),potential explosions onashiporbargearenotconsidered adesignbasisevent'.Thisdistanceiswellbeyondtheradiusofthepeakincidentpressureof1psiasgiveninRegulatory Guide1.91.Therefore, accord-ingtoguidancecontained inRegulatory Guide1.91,ex-'losions onnearbytransportation routesarenotconsidered designbasiseventsduetotheseparation distances ofpotential sourcesofexplosions fromUnit2.Amendment 262.2-4May1986 NineMilePointUnit2FSARThisresultsinaneffective releaserateof6,802g/sec(1.17xl0'g/172 sec),therebyyieldingacenterline puffconcentration of0.04whichislessthanthecriticalvalueof0.07.Therefore, thedelayedignitionofthepufforplumereleasefromthepropanetankattheFitzPatrick stationwillnotcausea1-psioverpressure toreachtheUnit2containment building. 2.2.3.1.3 ToxicChemicals Potential SourcesofToxicChemicals According toRegulatory Guide1.78,bothonsiteandoffsitepotential toxicgashazardsmustbeconsidered. Anytoxicsubstance storedonsiteinaquantitygreaterthan45kg(100lb)mustbeevaluated. Offsitesourcestobeevaluated includestationary, facilities andfrequenttransportation oftoxicsubstances (truck,rail,andbarge)within8km(5mi)ofthesite.Frequentshipments aredefinedasexceeding 10/yrfortruckshipments, 30/yrforrailshipments, and50/yrforbargeshipments. FortheNineMilePointsite,sourcesofpotential toxicchemicalhazardsincludechemicals storedonsite,aswellasfourstationary andtwotransportation sourceswithin8kmofthesite.Table2.2-7liststhechemicals associated witheachsourcealongwiththeirquantities anddistances fromtheUnit2controlroomairintake.Thethreestationary sourcesincludetheJamesA.FitzPatrick plant,theALCANRolledProductsDivision, OswegoWireInc.,andUnitl.Onetransportation sourceofpossiblehazardous materials istrucktrafficalongRoute104,whichpasseswithin6.2"km(3.9mi)ofthesite.Thesecondtranspor-tationsourceistherailroadlinebetweenOswegoandMexico,NY.Discussions withConrailindicatethatonanaverage,onlyonehazardous chemicalshipmentduringan18-monthperiodpassesthroughtheOswegoterminal. Trafficonaspurtothesiteisnotfrequentenough(<30/yr)towarrantcon-sideration.' Onlythosechemicals thathavethepotential toformatoxicvaporcloudorplumeafterreleaseto=theenvironment needtobeevaluated. Thiscriterion ismetbyallchemicals listedinTable2.2-7.8USARRevision02.2-5bApril1989 NineMilePointUnit2FSARControlRoomHabitabilit Determination Theeffectofanaccidental releaseofeachofthechemicals described intheprevioussectiononcontrolroomhabitability isevaluated bycalculating vaporconcentrations insidethecontrolroomasafunctionoftimefollowing theaccident. Thiscalculation isperformed usingtheconservative methodology outlinedinNUREG-0570 andutilizing theassumptions described inRegulatory Guide1.78.Inapostulated

accident, theentirecontentofthelargestsinglestoragecontainer isreleased, resulting inatoxicvaporcloudand/orplumethatisconservatively assumedtobetransported bythewinddirectlytowardthecontrolroomintake.Theformation ofthetoxiccloudand/orplumeisdependent onthecharacteristics ofthechemicalandtheenvironment.

Theentireamountofachemicalstoredasagasistreatedasapufforcloudthathasafinitevolumedetermined fromthequantityanddensityof'thestoredchemical. Asubstance storedasa.liquidwithaboilingpointbelowtheambienttemperature formsaninstantaneous puffduetoflashing(rapidgasformation) ofsomefractionofthestoredquantity. Theremaining liquidformsapuddlethatquicklyspreadsintoathinlayerontheground,subsequently vaporizing andformingaground-level vaporplume.Ahighboilingpointliquid(aboveambienttemperature) formsapuddlethatevaporates byforcedconvection withnoflashinginvolved. Thecalculations aredonebyacomputerprogram(VAPOR)basedonNUREG-0570 methodology thatrequiresthefollowing inputinformation: chemicalphysicalproperties, controlroomparameters, meteorology, distancefromthespilltothecontrolroomintake,quantityofchemicalreleased, andtoxicitylimits.Thefollowing Unit2control-roomparameters areused:ventilation rateof0.551cum/sec(1,167cuft/min),andnetfreevolumeof5,935cum(209,600cuft).Themostconservative meteorological condition isassumedforthecalculation, consisting ofPasquillClassGstability, awindspeedof0.5m/sec(1.6ft/sec),andanambienttemperature of32.8'C(91F).Thecriteriafordetermining chemicaltoxicityandsettinglimitsforhabitability determinations aretakenfromregulatory guidancedocuments. According toRegulatory Guide1.78,thetoxicitylimitofachemicalisthemaximumconcentration thatcanbetolerated byanaveragehumanfor2minwithoutphysicalincapacitation (severecoughing, eyeburn,severeskinirritation). StandardReviewPlanSectionUSARRevision02.2-6April1989 NineMilePointUnit2FSAR(1,000ft)toreachtheintakestructures andwouldbesub-jecttodilutionduringtransport. Anyliquidspillsoriginating duringcommoncommercial shiptransport wouldhavetotravelappromimately 10km(6.2mi)toreachthein-I~6takelocation. Duetothecombinedeffectsofthesubmerged intakestructures'esign andthedistancebetweenintakestructure locationandoriginofthepotential liquidspill,theriskofentrainment ofanysignificant quantities ofoil,orcorrosive, cryogenic, orcoagulable liquidsbytheintakestructures isnegligible. 2.2.3.1.7 AirplaneCrashesThenearestaircorridorisapproximately 22.5km(14mi)east,ofthesite(Section3.5'.6).Thereareonlytwoair-fieldsbetweenthe8-km(5-mi)and24-km(15-mi)radiiofthesite;theLakesideAirparkandOswegoCountyAirportareabout12km(7.5mi)and19km(12mi)southofthesite,respectively. Theaircraftapproaches totheseairportsarenotneartheplantsite.Thegeneralaviationmovements attheseairportstotalapproximately 1,460/yrand19,900/yr, respectively. Theannualmovements arebelowthecriticalnumberatwhichaprobability analysisforaircraftac-cidentswouldberequiredaccording toRegulatory Guide1.70.Therefore, theprobability ofaircraftcrashingintothesiteisconsidered toberemote,andairplanecrashesneednotbeconsidered designbasisevents.2.2.3.2EffectsofDesignBasisEventsPotential designbasiseventsareidentified inSection2.2.3.1.Theeffectsoftheseeventsonthesafety-relatedcomponents oftheplantareinsignificant. Thepotential fortoxicchemicalaccidents affecting maincon-trolroompersonnel hasbeenevaluated. Thisshowsnopotential impact,onmaincontrolroomhabitability. Self-contained breathing apparatus, however,willbeprovidedformaincontrolroomoperators'mendment 262.2-9May1986 NineMilePointUnit2FSAR2.2.4References Transmittal fromMr.MartinWeiss,OswegoCountyPlanningBoard,November7,1979.Updatedandverified, April4,1981.2.Waterborne CommerceoftheUnitedStates,Part3,1978.Department oftheArmy,CorpsofEngineers, Virginia. 3.Telephone conversation betweenP.A.Hughes(SWEC)andJ.Robinson(U.S.CoastGuard,9thDistrict). June23,1981'ransmittal fromB.Gorman,PowerAuthority oftheStateofNewYork,December7,1979,toP.Johnson,Stone6WebsterEngineering Corporation. 5.Patty,F.A.(ed.).Industrial HygieneandToxicology, Vol.IandII.Interscience Publishers, NewYork,NY,1958,1963,and1978.6.Sax,N.E.Dangerous Properties ofIndustrial Materials, 3rdEdition,VanNostrandReinhold, NewYork,NY,1968.7.CriteriaforaRecommended Standard: Occupational ExposuretoCarbonDioxide,Publication No.NIOSH76-194,August1976.8.Tilton,B.E.andBruce,R.M.ReviewofCriteriaforVapor-Phase Hydrocarbons, Environment CriteriaandAssessment Office,USEPA,EPA-600/8-80-045, p6-150.9.FireProtection

Handbook, 13thEdition,NationalFireProtection Association, 1969,Boston,MA,p15.14-45.

10.Transmittal fromR.J.Mangold,AlcanAluminumCorporation, July8,1981,toP.D.Patel,StoneEcWebsterEngineering Corporation. Transmittal fromT.J.Perkins,NiagaraMohawkPowerCorporation, August3,1981,toK.A.Baraniak, Stone&WebsterEngineering Corporation. 12.Burgess,D.S.andZabetakes, M.-G.Detonation ofaFlammable CloudFollowing aPropanePipelineBreak.U.S.BureauofMinesReportofInvestigations (RI7752), 1973.Amendment 32.2-10June1983 NineMilePointUnit2FSARTABLE2.2-3INDUSTRIAL FIRMSWITHIN8KM(5MI)OFUNIT2FirmAlcanAluminumCorporation Distance/ Direction fromSite(km4.5/SWAluminumsheetandplate1,000JamesA.FitzPatrick <1/ENuclearPowerPlantElectrical 515generation NineMile'Point Unit1AdjacenttoUnit2Electrical 450generation SOURCE:References 4,10,llUSARRevision01of1April1989

NineMilePointUni.t2FSARTABLE2.2-5HAZARDOUS MATERIALS STORED/USED BYINDUSTRIES WITHIN8KM(5MI)MaterialCarbondioxideIndustrial UserAlcanFitzPatrick StorageonPremises(Max.atO~eTLeMOd*~A*aSla65tonsTruck6tons26,000lbTruck6,900galMaximumQuantity~Shed10tons6,900galShient~FeueeWeeklyInfrequently, asneededsystemAverageQuantity~Shi~edyr250tonsSmallquantitres usedtorechargeChlorineNMPUnit1Alcan20,000lb30tonsTruckTruck5,000lb1(1ton)cylinder6,300gal12tonsMonthlyBiweekly56,000gal350cylinders HeliumAlcan1,917ftTruck213ft9cylinders (213fteach)Asneeded94cylinders (20i022ft)Hydrochloric acidHydrogenNitrogenPropaneSodiumhydroxide AlcanFitzPatrick NMPUnit1OswegoWireAlcanFitzPatrick NMPUnit1OswegoWireFitzPatrick AlcanFitzPatrick AlcanNMPUnit1OswegoWire500galTruck28,800ftTruck12,000ftTruck6,450ftTruck970,000ftTruck10,000galTruck15,300galTruck160,000ftTruck55gal128g000ft24,000ft515ft670,000'ft6,900gal6,300gal385gal128,000ft24,000ft5,375ft670,000ft6,900gal6,300gal145,000ft160,000ft80i000lb5,000gal3,000gal165gal385galTruckTruckTruckTruckTruck7,000lb3g000lb55gal55gal55gal22,500lb7,000lb3,000lb1,000gal55gal55gal1,000galTruck22,500lbWeeklyBiweeklyBimonthly 10WeeksHonthlyMonthlyMonthlyWeeklyMonthlyBiweeklyMonthlyMonthlyAsneededMonthly16,000gal221,000ft72,000ft27,305ft8,999,200 ft129,000gal56,000gal8,000,000 ft3,000gal200,000gal246,000lb10,000gal100gal660galUSARRevision01of2April1989

NineMilePointUnit2FSARTABLE2.2-7SOURCESOFTOXICCHEMICALS WITHIN8KM(5MI)OFUNIT2SITEChemicalLocationChemicalAmountDistancetoIntakes(mJamesA.Fitz-PatrickplantAlcanN2H2SOCO2PropaneHalonClqPropaneN2HCLCOR0.3050.3461.180.2210.2600.1810.3630.2600.2260.533x10sx10sx10'10'10'10'10sx10sx107x10s6206206206206204,9904,9904,9904,9904i990Route104HC1N2CO20.542x1070.183x10'.272x10~5,4705,4705,470NineMilePointUnit1N2CO2H2SOHCLHalon0.4430.9070.1140.4540.227x10sx10'10'10'10e290265290290290NineMilePointOswegoWireIncorporated H22Halon1301N2Isopropyl AlcoholN2PropaneH2SOHCL0.118x10'.113x10'.671x10s0.330x10e0.525x10e0.947x10e0.750x10e0.182x10"33451507,0807,0807,0807,0807,080USARRevision01of1April1989

NineMilePointUnit2FSARTABLE2.2-8PREDICTED VAPORCONCENTRATION INTHEUNIT2CONTROLROOMChemicalLocationJamesA.FitzPatrick plantAlcanRoute104NineMilePointUnit1NineMilePointUnit2OswegoWireIncorporated ChemicalN~HqSOCOqPropaneHalonClqPropaneN~HCLCO~HclN~CO~NqCOqH~SOHalonHclHqSOCO~Halon1301N~Isopropyl AlcoholNqPropaneHqSOMaximumControlRoomConcentration (m~11.26.6x10-~6.21.291.730.0381.10.090.0032.5x10-'.0090.540.022.214.71.3x10-~0.570.0096.6x1046.83.8832.12.2x10-41.2x10-~2.1x101.0x10-'oxicLimit2740.00254.843.14320.04543.12740.0554.80.05027454.827454.80.0024320.050.00254.84322741.227443.10.002Allowable TimePeriod(min152151515215151521515215152151521515151515152USARRevision01of1April1989 ' NineMilePointUnit2FSARSurveillance, including inkingandroutinepreventive maintenance, isperformed atleasttwiceweekly.Chartsarechangedat2-weekintervals. Calibrations occuratleastevery6monthswithcomponent checks'ndadjustments performed whenrequired. 'Allmetersandotherequipment usedincalibrations are,inturn,-calibrated atscheduled intervals. Inspection andmaintenance ofallequipment isaccomplished inaccordance withprocedures intheinstrument manufacturer's manuals.Inspection iscarriedoutbyqualified technicians capableofperforming themaintenance, ifrequired. Theresultsoftheinspections andmaintenance'erformed arekeptinalog.F2.3.3.1.6 DataAcquisition andReduction FromJanuary1974toOctober1980,analogstripchartswerechangedevery2weeksandprocessed. Aftereachchartwasscannedforinstrument malfunctions, hourlyvalueswereread.Thedatawereroutinely keypunched onamonthlybasis.Afterkeypunchverification, acomputerlistingandqualitycontrolsummarywasgenerated ofhourlyreadings. The'atawereagaincheckedforinconsistencies byaninstrument specialist andaqualified meteorologist. Afterincorporating anycalibrations fromsitepersonnel, afinallistingwasgenerated. Thedatawerethentransferred tomagnetictapeandacopywasmade.2.3.3.1.7 DataAnalysisProcedures Alldataweresubjecttoqualitycontrolcheckspriortofinalization intomonthlylistings. Attheendofeachquarter,routinesummaries ofwinddirection, speed,andstability werecomputed. Monthlyandannualdataanalyseswereperformed aswarranted forspecialprojectsinadditiontotheroutinesubmittal ofthedataforNineMilePointUnit1totheNRC.2.3.3.2Operational Measurements Program2.3.3.F1Description Thepreoperational onsitemeteorological measurements programhasbeenupgradedandexpandedtomeettheintentandrecommendations ofRegulatory Guide1.23andNUREG-06S4 fortheoperational measurements program'. Thepreoperational, steel,openlattice61-m(200-ft)meteorological towerservesastheprimaryinstallation. Newmeteorological sensors.wereinstalled atthefacilityAmendment 32'31June1983 NineMilePointUnit2FSARstartinginJuly1982andtheentirereplacement wascompleted byFebruary1983.Supplemental inlandmeasurements areobtainedfrominstrumentation attheOswegoCountyAirportnearFulton.Back-upinstrumentation islocatedeastof'heJ.A.FitzPatrick Plant.Amapshowingthedetailedrelationship ofUnit2totheprimarymeteorological towerandthebackuptowerisshownonFigure2;3-40.Figure2.3-40Ashowsthelocationoftheinlandtower,theprimarytower,andthebackuptowerwithrespecttoUnit2onalargerscalemap.Theprimarytowerisinstrumented .withwinddirection andspeedsensorsatthreelevels:9m(30ft),30m(100ft),and61m(200ft).Sigmathetaisderivedforeachofthethreewindlevels.Inaddition, ambienttemperature ismeasuredat8m(27ft)andtemperature differences aredetermined betweenthe61-m(200-ft)and8-m(27-ft)levels.Dewpointtemperature isobtainedatthe8-m(27-ft)level.Nearthebaseofthetower,precipitation andbarometric pressurearealsomeasured. Theinland10-m(33-ft)meteorological towerislocatedwithgoodexposureinalldirections andissituatedawayfromallrunwaysandbuildings attheOswegoCountyAirport.Theinstrumentation provideswindspeedanddirection fromwhichsigmathetavaluesarecalculated. Theback-upwinddirection andspeedinstrumentation islocatedeastoftheJ.A.FitzPatrick Plant,ona.27-m(90-ft)utilitypole.Onecoincident annualcycleofwinddatafromthebackupinstrumentation andtheprimarytowerwillnotbeavailable untilmid-1984. Atthattime,acomparison ofthetwodatasetswillbemadetodetermine therepresentativeness ofthebackupwindmeasurements. Theresults.ofthiscomparison willbeprovidedbytheendof1989.2.3.3.2.2 Meteorological Instrumentation Theoperational meteorological measurements programisdesignedtomeettheNRCrecommendations atthetimeofinstallation inmid-summer 1982andisinaccordance withRegulatory Guide1.23.Manufacturers'odel numbersandspecifications forthesensorsareshowninTable2.3-4-A.Component errors,aswellassensorandsystemaccuracies, arelistedinTable2.3-5A.WindInstruments Allmonitoring locations employtheTeledyneGeotechthree-cup anemometer andvane.USARRevision02'-32April1989 NineMilePointUnit2FSAR67.Dewey,K.E.Lake-Effect Snowstorms andtheRecordBreaking1976-1977 SnowfalltotheLeeofLakesErieandOntario,Weatherwise, Vol.30,No.6,1976.68.U.S.Department ofCommerceLocalClimatological Data-MonthlySummary-Syracuse, New=York.NOAA,Environmental, DataandInformation Service,NationalClimaticCenter,Asheville, NC,1977-October1983.69.Sykes,R.,Pack,A.B.andLoveridge, E.TheClimateandSnowClimatology ofOswego,NewYork.LakeOntarioEnvironmental Laboratory, Contribution No.2,Vol.1,June1971,p.59.70.Hershfield, D.M.RainfallFrequency AtlasoftheUnitedStatesforDurations From30Minutesto24HoursandReturnPeriodsFrom1to100Years.Technical PaperNo.40,WeatherBureau,U.S.Department ofCommerce, Washington, D.C.,1961.Amendment 192.3-62aMay1985 NineMilePointUnit2FSARTHISPAGEINTENTIONALLY BLANKAmendment 192.3-62bMay1985 NineMilePointUnit2PSARTABLE2.4-15SUMMARYOFRESULTSANALYSISOFBUILDINGFLOODINGDUETOPMPBASEDONHYDROMET51AND52~BiidiDieselgenerator ControlbuildingAuxiliary baysouthElectrical tunnel-southareaStoplogsC261-29C261-24C261-31SA262-3ET262-4Length~ft15TotalFlow~ftA404.2551.1257.2110.2110.263.663.6Bldg.Depth~inDistribution ofPlowFluxEvenlyoverfloor;providedcaulkingmaterialtomakestoplogswatertight. C261-29andC261-31flowswillcombineandspreadthroughEl.261corridors andintosomerooms.C261-24willflowdownstairwell andspreadthroughcorridors onlowerfloors.Nofixisrequired. Plowwillbeconfinedtoauxiliary baystairwell area.Nofixisrequired. Plowwillbespreadevenlythrougheachtunnel.Electrical tunnel-northareaET261-1102.6Auxiliary baynorthRBrailroadtrackbayStandbygastreatment Servicewaterpumproom(north)fromauxiliary boilerroomET261-2NA262-1RR-261-1SG261-2SG261-1SG261-6AB261-317102.663.6NA273.6273.6102.6NANA2.5Plowwillbeconfinedtoauxiliary baystairwell area.Nofixisrequired. Doorsareequippedwithinflatable airseals;waterleakagewillbenegligible. Nosafety-relatedequipment isinthisarea.Plowisspreadevenlythroughout thebuilding(seeNote5).Plowintoauxiliary boilerbuildingisdis-tributedintothepumphouse ifAB261-3isopen.USARRevision01of2April1989

NineMilePointUnit2FSARTABLE2.4-15(Cont)B~B'd'ervice waterpumproom(south)fromscreenwell areaDoorSW261-14Length~ftTotalFlow~ftA94.2Bldg.Depth~inDistribution ofFlowFluxEvenlythroughout building. NOTES:l.Usehydrographs fromCalculation No.12177-WH(B)-062 forwatersurfaceelevations. 2.Doorsillelevation isinthedooridentification number,e.g.,SH261-14, where"261"isthedoorsillelevation. 3.Calculation methodforinflowthroughdoorwaysfromPHFsubmerged orificedischarge equation: 9=CA~gh()-"Flow(cfs)C=Discharge coefficient =0.6A=Crosssectional areaofflow=lengthofdoor(L)xcrackwidthofdooropening(1/16induetoflow"necking" )g"-Gravityh=Headwater surfaceelevation onexteriorofdoor4.Nocredithasbeentakenintheanalysisforsump~aterretainage orsumppumpoperation. 5.Sinceequipment structural padheightis6in,resultant buildingwaterdepthslessthanthisareacceptable. USARRevision02of2April1989

NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER7Title6Athrough6CINSTRUMENTATION ANDCONTROLSYSTEMSReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components Volume1313131313141515151515157.17'7'7,47.57.67'Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8AELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystem16161616,1717'CHAPTER9AUXILIARY SYSTEMS179.19.29.39.49.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9Ag9C17181920,2121,22IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER1010.110.210.310.4STEAMANDPOWERCONVERSION SYSTEMSummary.Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion System23232324CHAPTER11RADIOACTIVE WASTEMANAGEMENT 11'11.211.311.411'SourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystemsAppendixllACHAPTER12RADIATION PROTECTION 2424252525252512.112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER76Athrough6CINSTRUMENTATION ANDCONTROLSYSTEMSTitleReactorVesselComponent andSubsystem Design5Ag5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components Volume1313131313141515151515157'7'7'7'7.57.67'Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMS16161616,17I179.19.29.39.49.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17181920,2121,2223IUSARRevisionApril1989 NineNilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSION SYSTEM2310.110.210.310.4Summary,Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion System232324CHAPTER11RADIOACTIVE WASTEMANAGEMENT 11.111.211.311.411.5AppendixllACHAPTER12RADIATION PROTECTION SourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems2424252525252512.112.212.312~412.5CHAPTER1313.113.213.313.413.513.6Appendixes EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)-Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgramCONDUCTOFOPERATIONS Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B25252526262626262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER7TitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components through6CINSTRUMENTATION ANDCONTROLSYSTEMSVolume1313131313141515151515157.17'7'7'7.57.67'Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMS16161616,1717I179.19.29.39'9.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17181920,2121,22IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER1010.110.210.310.4CHAPTER11TitleSTEAMANDPOWERCONVERSION SYSTEMSummary.Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemRADIOACTIVE WASTEMANAGEMENT Volume2323232411.111.211.311.411'AppendixllASourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems242425252525CHAPTER12RADIATION PROTECTION 2512.112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B262626.26'62626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER7TitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 6Athrough6CINSTRUMENTATION ANDCONTROLSYSTEMSVolume"1313131313141515151515157'7'7'7'7.57.67~7Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety15.15151616161616CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5Appendixes ELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C1616'16'16,17171717.181920,2121,22IUSARRevision0I~IApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER1010.110.210.310.4CHAPTER11STEAMANDPOWERCONVERSION SYSTEMSummary.Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemRADIOACTIVE WASTEMANAGEMENT 2323232411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystemsII242425252525CHAPTER12RADIATION PROTECTION 2512~112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613~113.213,.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B26262626'62626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit.2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER7TitleReactorVesselComponent andSubsystem Design5Ag5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components ~through6CINSTRUMENTATION ANDCONTROLSYSTEMSVolume1313131313141515151515157.17'7'7.47.57'7~7Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.39.49.5Appendixes ELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9Ag9C1616,16'16,1717I1717.181920,2121,22IUSARRevisionApril1989 .NineMilePointUnit2FSARTABLEOFCONTENTS'(Cont), SectionCHAPTER1010.110.210.310'TitleSTEAMANDPOWERCONVERSION SYSTEMISummary,Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemVolume23232324CHAPTER11RADIOACTIVE WASTEMANAGEMENT 11.111.211.311.411.5AppendixllASourceTerms1LiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems242425252525CHAPTER12RADIATION PROTECTION 2512.112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26iv FigureNumberNineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont)Title3.6A-403.6A-413.6A-423.6A-433.6A-443.6A-453.6A-463.6A-473.6A-483.6A-493.6A-503.6A-513.6A-523.6A-533.6A-54HIGHENERGYPIPEBREAKSREACTORWATERCLEANUPOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSREACTORWATERCLEANUPOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSSTANDBYLIQUIDCONTROLINSIDECONTAINMENT HIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENT HIGHENERGYPIPEBREAKSCONTROLRODDRIVESYSTEMOUTSIDECONTAINMENT DELETEDDELETEDHIGHENERGYPIPECOMPOSITE PLANEL175'-0"AND215'-0"HIGHENERGYPIPECOMPOSITE PLANEL240'-0"HIGHENERGYPIPECOMPOSITE PLANEL261'-0"27Amendment 273-xliJuly1986 NineMilePointUnit2FSARCHAPTER3LISTOFFIGURES(Cont)FigureNumber3.6A-553.6A-563.6A-573.6A-58TitleHIGHENERGYPIPECOMPOSITE PLANEL289'-0"HIGHENERGYPIPECOMPOSITE PLANEL306'-6"HIGHENERGYPIPECOMPOSITE PLANEL328'-10"HIGHENERGYPIPECOMPOSITE SECTION1-13.6A-593.6A-603.6B-13.6B-23.6B-3HIGHENERGYPIPECOMPOSITE SECTION2-2HIGHENERGYPIPECOMPOSITE SECTIONS3-3AND4-4TYPICALRESTRAINT FORCEDEFLECTION CURVETYPICALPIPEWHIPRESTRAINT'ONFIGURATION BREAKLOCATIONS ANDRESTRAINTS

ANALYZED, PDAVERIFICATION PROGRAM3.7A-l3.7A-23.7A-33.7A-4HORIZONTAL SSEDESIGNRESPONSESPECTRANORMALIZED TO0.15GVERTICALSSEDESIGNRESPONSESPECTRANORMALIZED TO0.15GHORIZONTAL SSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTAL SSESYNTHETIC TIMEHISTORY(EAST-WEST EARTH-QUAKE)BASEDON2.0PERCENTDAMP1NGRATIOHORIZONTAL SSEDESIGNRESPONSESPECTRUMANDRESPONSESPECTRUMDERIVEDFROMHORIZONTAL SSESYNTHETIC TIMEHISTORY(EAST-WEST EARTHQUAKE)

BASEDON1PERCENTDAMPINGRATIOAmendment 213-xlilSeptember 1985 NineMilePointUnit2PSARTABLE3.2-1(Cont)125-VDCPowerSstemsScopeof~Su~1LocationElectrical Classifi-cationSeismicC~atoGroupClassifi-cationQuality(31,32,Assurance 33,Reirement34TornadoProtection Notes125-Vdcemergency batteries andracks125-Vdcemergency batterychargers125-Vdcemergency switchgear 125-Vdcemergency centers125-Vdcemergency distribution panelsEmergency cablesCabletrayandfabricated supportswithsafetyfunctions DCcontainment penetrations Conduitandnonemergency cabletrayMiscellaneous ComnentsReactorbuildingpolarcraneCivilStructures Primarycontainment Reactorbuilding, including fuelstoragefacilities andauxiliary baysRadwastebuildingControlbuildingDieselgenerator buildingTurbinebuilding, including heaterbay,exceptasnotedMainsteamtunnelPortionofturbinebuildingPipetunnelportionoftheturbinebuildingbetweencolumnlinesAKandAMbelowel261ftPipetunnelportionoftheturbinebuildingbetweencolumnlines10and12belowel248ftTurbinebuildingel250ftslaboverthepipetunnelsbetweencolumnlines10and12NAM,C,RBMiCiRBMiCgRBRBMgCgRB1E1E1ENA1ENANon-1ENANANANANANANAIZ(22)NRTT(34)(29)(28g44)(28,29i36)(20)USARRevision116of26October1989 1I Nine'ilePointUnit2FSARTABLE3.2-1(Cont)Penetration Z-328-32RCS-750-151-2 Extension ofPrimarContainment, ReactorBuildinEuiment(DER)Penetration Z-452DER-002-034-2 (47)Theequipment anditsclassification alsoapplytotheairstartsystemassociated withtheDivisionIII(HPCS)dieselgenerator. (48)TheGEcompressor motorisSeismicCategoryI.Thecom-pressormotorstarterisSeismicCategoryNA,butitisseismically mountedandevaluated toensurethatiffailureoccursitwillnotcausedegradation ofsafety-relatedequipment. USARRevision026hof26April1989

NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35'Appendixes CHAPTER6TitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESVolume131313136.16.26.36.46.56.6Appendixes 6Athrough6CEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 13141515151515CHAPTER77.17'7'7'7.57.67~7Appendixes CHAPTER88.18.28.3Appendix8AINSTRUMENTATION ANDCONTROLSYSTEMSIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety7A,7BELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystem1515151516161616161616.16'16,1717'CHAPTER9AUXILIARY SYSTEMS179.19.29.39'9.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9Ag9C17.181920,2121,2223IUSARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER10TitleSTEAMANDPOWERCONVERSION SYSTEMVolume2310.110.210.310.4CHAPTERllSummary,Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemRADIOACTIVE WASTEMANAGEMENT 23232411.111.211.311.411'AppendixllASourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems242425252525CHAPTER12RADIATION PROTECTION 2512.112.212.312.412.5CHAPTER1313.113.213.313.4-13.513.6Appendixes EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgramCONDUCTOFOPERATIONS Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B25,2525262626262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER77.17'7'7.47'7'7~7.Appendixes CHAPTER8TitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 6A.through6CINSTRUMENTATION ANDCONTROLSYSTEMSIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdown.Safety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety7Ag7BELECTRICPOWERVolume13131313131415151515151515151516'16161616168.18.28.3Appendix8ACHAPTER9Introduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMS16,1616,1717I179.19.29.39.49.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17,181920,2121,22IUSARRevision0April1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER1010.110.210.310'CHAPTERllTitleSTEAMANDPOWERCONVERSION SYSTEMSummary.Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemRADIOACTIVE WASTEMANAGEMENT Volume2323232411.111.211.311.411.5AppendixllASourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems242425252525CHAPTER12RADIATION PROTECTION 2512.112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113~213.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B2626262626'626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSAR3.7.3.1.3A OtherDynamicLoadsLoadingcombinations andstresslimits,including loadsduetohydrodynamic effects,aredescribed inSection3.9.3.1A. Afurtherdiscussion ofhydrodynamic phenomena isincludedintheDesignAssessment ReportforHydrodynamic Loads(Appendix 6A).3.7.3.2ADetermination ofNumberofEquivalent StressCyclesThefollowing criteriaareappliedtoallCategoryIsubsystems: l.AtotaloffiveOBEandoneSSEareconsidered. 2.Forsubsystems, exceptpiping,20cycles(fullsignreversals) perseismicevent,i.e.,atotalof120cycles,areconsidered. 3.Forallpipingsystems,10maximumstresscyclesperOBE(i.e.,atotalof50cycles)arepostulated. 4.Wheretimehistoryanalysisisperformed, aminimumdurationof10secisassumed.3.7.3.3AProcedure UsedforModelingTheprocedure described inthefollowing sectionsisspecifically writtenforpipingsystems.Othersubsystems areseismically qualified asdescribed inSection3.7.3.1.1A. 3.7.3.3.1ASummaryPortionsofpipingsystemsthatareboundedbyanchorsorequipment arestatically anddynamically independent fromtheremainder ofthepiping.Generally, apipingsystemconsistsofseveralsuchsubsystems. Theanalytical modelanditsgeometric boundaries aredescribed indetailinthefollowing sections. 3.7.3.3.2A Geometric Boundaries ofAnalytical ModelsForthepurposeofanalysis, pipingsystemsaresubdivided intosmallerunits(referred toasproblems) thatareboundedbystructural anchors(6-deg-of-freedom constraints) orbyothervirtually rigidpointssuchasequipment, penetrations, andpipingofmuchlargerdiameter. Amendment 233.7A-19December1985 NineMilePointUnit2FSARAbranchlinewithamomentofinertiaof1/10orlessoftherunpipemaybeignoredinthemodel.However,ifthebranchlineneedstobeanalyzed, itsmodelincludestheef-fectoftherunpipe.WhereCategoryIpipingisconnected tononseismic piping,theadjoining portionofthenon-seismicpipinguptothefirstanchorisincludedintheanalytical modeloftheCategoryIpiping,andallsupportsuptoandincluding thisanchor,aredesignedseismically (Section3.7.3.13A). 3.7.3.3.3A ModelThebasicmethodofanalysisusedisNUPIPE,afiniteelementcomputerprogram(Appendix 3A)~Inaccordance withthismethod,thecontinuous pipingismathematically idealized asanassemblyofelasticstructural memberscon-nectingdiscretenodalpoints.Nodalpointsareplacedinsuchamannerastoisolateparticular typesofpipingelementssuchasstraightrunsofpipe,elbows,valves,etc,forwhichforce-.deformation characteristics canbecategorized. Nodalpointsarealsoplacedatalldiscon-tinuities suchaspipingsupports, concentrated weights,branchlines,andchangesincrosssection.Systemloadssuchasweights,equivalent thermalforces,fluidtransient dynamicforces,andinertiaforcesareappliedatthenodalpoints.Stiffness characteristics oftheinterconnecting membersarerelatedtotheeffective shearareaandmomentofinertiaofthepipe.Thestiffness ofpipingelbowsandcertainbranchconnectors ismodifiedtoaccountfor.localdeformation effectsbytheflexibility factorsspecified inASMESectionIII,1974,Subarticles NB-3600(SafetyClass1pipinganalysis) andNC-3600(SafetyClass2and3pipinganalysis). Theincreased stiffness ofvalvebodiesistakenintoconsideration. 3.7.3.3.4A Selection ofMassPointsThelumpedmassesarelocatedtoadequately represent thedynamicproperties ofthepipingsystem.Masspointsaregenerally selectedinaccordance withthefollowing guidelines: At.-eachnodewhereaconcentrated weightisplaced(valves,flanges,orotherin-line"pipingcomponents). 2~Ateachintersection wherethreeormorepipingelementsareconnected (branchconnections, tees,andy-fittings). Amendment, 33.7A-20June1983 NineMilePointUnit2FSARResonseSectrumMethodWhenapipingsystemisanalyzedbymeansoftheresponsespectrummethod,thecomputercodeNUPIPEisusedtocal-culatethemodalresponseateachnodepointinthepipingsystemduetotheARSexcitation appliedtothesystem.Generation orselection oftheappropriate setofARSforasubsystem supported atdifferent elevations, andcon-sideration oftheeffectofseismicdifferential displacements betweenrestraints arediscussed inSection3.7.3.9A. ThedampingvaluesforpipingdependonpipesizeandaregiveninTable3.7A-1.Theequations ofmotionandtheirsolutionareaspreviously described forstructures (Section3.7.2).TimeHistorMethodTheapplicable basemotiontimehistoryisthestructural responseatarepresentative masspointofthestructure tothegroundmotiontimehistory.Theequations ofmotionandtheirsolutionarethesameasinSection3.7.2.5A, butthescalaracceleration termintheexcitation functionisnowtheamplitude oftheacceleration ofthebaseofthesub-system(pointsofattachment), notoftheground.Theef-fectofparameter variations onthefloorresponsespectraaretakenintoaccount(Section3.7.2.9A). DnamicAnalsisFormulation Thebasicequations ofmotionandtheirsolutions arethesameasforstructures (Section3.7.2).Absoluteac-celerations atpointsonthepipingsystemaresometimes neededforqualification ofcritical, safety-related equipment. Withtheresponsespectrummethod,themaximumabsoluteacceleration atamasspointinmodeiisobtainedfromNewton'slawbydividingtheeffective inertiaforcebythemassatthemasspoint:ta1=tMl'lQl(3.7A-6)Where:[M]=Diagonalmassmatrixofthesystem[Qf=Effective inertiaforcesinmodeiWiththetimehistorymethod,theabsoluteaccelerations areobtainedbyaddingthebaseacceleration totherelativeac-celerations ofthemasspoints.I"Amendment, 263.7A-25May1986 NineMilePointUnit2FSARSeismicDifferential Dislacements DescritionofInutTheseismicdifferential displacements arealsocalledseismicanchormovements. ThiseffectisanalyzedinaseparatestaticloadcaseforOBEanchormovements. Theanchormovements areobtainedfromtheseismicdifferential displacements ofthestructural nodes.Thedisplacements areobtainedinthefollowing form,onesetforeachmasspoint,N,ofthebuildingmodel:EarthuakeDirection MassNodeX(East-~WestVerticalZ(North-~SouthDgXDpXD3XDgYDpD3DzzDgzD3zNWhere:NXNNzDN(DN,DN)=SRSSofdisplacements inX(Y,Z)dir-xyzectionduetoearthquake excitation inX,Y,andZdirections atNodeNThesearethemovements ofpointsonthewallsrelativetothefoundation ofthebuilding. Relativedisplacements betweenmasspointsareusedtodetermine themovements ofsupportpoints.Supportdisplacements areimposedonthesysteminaconservative manner.Combination ofAnchorMovementLoadsTheindividual X,Y,andZanchormovementcomponents ofOBEareanalyzedasthreeseparatestaticanchormovementloadcasesintheNUPIPEcomputerprogram.TheseloadcasesarethencombinedbytheSRSSmethodinNUPIPE,andtheresultant loadcaseisusedinthecodestressevaluation. CombinedSeismicResonseThesystemresponsetotheresponsespectrumexcitation (i.e.,displacements, internalforcesandmoments,stresses, andsupportreactions) isobtainedbyfirstcombining the3.7A-26 NineMilePointUnit2FSARmodalcontributions foreachearthquake component. Incon-formancewithRegulatory Guide1.92,theeffectofcloselyspacedmodesistakenintoaccountbytheprocedure described inSection3.7.2.7A. Thecontributions ofeachofthethreecomponents arethencombinedbytheSRSSmethods;Whentheresponsespectrummethodisused,responsetothedifferential supportmotionisconsidered. .InSafetyClass1pipinganalysis, thismotioniscombinedwiththeinertialresponse; theresultis-thencombinedwithotherloadcases.Intheanalysisofotherpipingclasses,theseismicanchormovementiscombinedwithsecondary loads.Seismicloadcasesarecombinedwithotherloadcases(thermal, weight,pressure, otheroccasional loads)inac-cordancewithASMESectionIII,1974.Theloadcombinations aregiveninSection3.9.3.1A. FatiueConsiderations ForASMESafetyClass1piping,ifEquation(10)ofSubpara-graphNB-3653.1 isnotsatisfied, afatigueanalysisisper-formedinaccordance withSubparagraph NB-3653.2 orSubarti-cleNB-3200.ThisanalysisusesthetotalnumberofstresscyclesofallOBEs.Thenumberofearthquake cyclesisdiscussed inSection3.7.3.2A. ComuterProramsUsedforSeismicAnalsisAllanalysesareperformed withNUPIPE.Thisprogramhan-dlesresponsespectrumandsupportmotiontimehistoryanalyses. PSPECTRAisusedforpeakspreading, aswellasforenvelopegeneration, toobtaintheARSrequiredasNUPIPEinputtoallspectralanalyses. Theseprogramsusedinpipinganalysisaredescribed inAppendix3A.DevelomentofRelativeDislacements andTheirAlicationtoPiinAnalsisTherelativedisplacement betweenapointonthereactorbuildingandapointontheprimarycontainment isobtainedasfollows:1.Thedisplacement timehistoryateachpointiscalculated usingasinputthethree-directional synthetic timehistoryofgroundmotion.2.Thedisplacement timehistoryofthefirstpointissubstracted fromthatofthesecondtogetatimehistoryofrelativedisplacement. Someexamplesofdisplacements areincludedonFigure3.7A-35.USARRevision03.7A-27April1989 NineMilePointUnit2FSARTheeffectofrelativedisplacement betweenthesupportsisconsidered inthepipinganalysis. Onesupportisselectedasareference point.Dynamicdisplacements atthisreference pointaretakeneitheraszeroorasdisplacements relativetoagivenstructural node.Atthe'first(adjacent) supportfromthereference point,relativedisplacements betweenthissupportandthereference pointaretakenandaddedtothedynamicdisplacement ofthereference point(thedirection ofdisplacements isdetermined andappliedtothesupportsinrelationtoitsfunction). Theresultant displacements becomethedynamicdisplacements ofthefirstsupport.Thefirstsupportthenbecomesthenewreference point.Thisprocessisrepeateduntildynamicdisplacements atallsupportsareobtained. 3.7.3.9AMultiplySupported Equipment Components withDistinctInputsWhenasubsystem isattachedtodifferent partsofastructure, suchasseparateelevations ononewallorseveralwalls,theresponsespectraofallstructural nodesforwhichresponsespectraexistandwhichlienearesttothesupportelevation atthesubsystem, bothbelowandabovethesupportelevation, areenveloped, andthisenvelopespectrumisappliedtothesubsystem. Incaseswhereasub-systemrunsbetweentwodifferent buildings, asingleARSenveloping thespectraassociated withallsupportpointsisused.USARRevision03'A-27aApril1989 NineMilePointUni't2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.3-6.46.56.6Appendixes CHAPTER77.17'7'7'7.57.67'Appendixes CHAPTER88.18.28.3Appendix8ACHAPTER99.19.29.3,9.49.5Appendixes TitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency 'CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 6A.through6CINSTRUMENTATION ANDCONTROLSYSTEMSIntroduction ReactorProtection (Trip)-'System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety7A,7BELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMSFuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9CVolume131313131314,.15151515151515151516161616161616'.16'16,1717I1717:181920,2121,2223USARRevision0April1989 NineMilePointUnit2FSARTABLE'OFCONTENTS(Cont)SectionCHAPTER1010.110.210.310'TitleSTEAMANDPOWERCONVERSION SYSTEMSummary.Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemVolume2323232411.111.211.311.411.5SourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystemsAppendixllACHAPTER12RADIATION PROTECTION CHAPTERllRADIOACTIVE WASTEMANAGEMENT 242424252525252512.112.212.312.412.5CHAPTER1313.113.213.313.413.513.6Appendixes EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgramCONDUCTOFOPERATIONS Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures. Industrial Security13A,13B252525262626.26262626'*262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)iv26 NineMilePointUnit2FSARAnalytical modelingandseismicanalysisaredescribed inSection3.7.3.8A. Staticanalysisandotherdynamicanalysesthatcontribute theremaining stressesinthecodestresscriteriaaredescribed inthefollowing sections. Pipingengineering anddesignspecifications forUnit2allowtheuseofvarioustypesofbranchconnections, including pipe-to-pipe. Unlessaspecificbranchconnection isindica-tedinthespecification oronthepipingdrawings, anunre-inforcedpipe-to-pipe connection isusedinthepipestressanalysis. Nofurtheractionisrequirediftheallowable stressesaremet.Iftheallowable stressesarenotmet,thenthepipingstresscalculation identifies thereinforce-mentof,thebranchconnection thatisrequired. Forcaseswherethebranchlineisdecoupled fromtherunpiping,theproperstressintensification factorisusedintheanalysisofboththebranchlineandthemainrunpiping.Ifreinforcement formechanical loadsisrequired, itissoidentified inthepipingstresscalculation anddrawings. Reinforcement requirements formechanical loads,identified bythepipestresscalculations, areincorporated onthepipingdrawings. Pressurereinforcement calculations requiredbyASMEIII,paragraph NB-3643,andANSIB31.1,paragraph 104.3,areperformed bythepipingfabricator, andadditional reinforcement, ifrequired, isidentified andaddedtothefabricated pipe.3.9.1.5.1A StaticAnalysisThestaticequationofequilibrium fortheidealized systemmaybewritteninmatrixform,asfollows:KU=P-Q(3.9A-1)Where:K=Stiffness matrixforassembled systemU=Nodaldisplacement vectorExternalforces,weights,etcEquivalent thermalforcesCross-section area0E=Young'sModulus~<=Thermalexpansion coefficient T=Averagewalltemperature less70'Finstallation temperature USARRevision03.9A-3April1989 NineMilePointUnit2FSAR=Coordinate alongpipeaxisL=LengthofpipeTheunknownnodaldisplacements areobtainedfromtheNUPIPEcomputerprogrambysolvingthisequationusingtheGaussianmethod.Thenodaldisplacements arethenappliedtotheindividual members,andmemberstiffnesses areusedtofindinternalforces.Thenodaldisplacements atsupportlocations canbeusedalongwiththesupportstiffness todetermine supportreactions. DeadLoadsWeiht,PressureandLiveLoadsInNUPIPE,theeffectofpressureiscalculated simultaneously withthedeadweight case.Theanalysisfordeadweight assumesallflexiblerestraints, suchasspringhangers,toberigid.Ifapipehasdifferent contents(medium)andtherefore different weightsinvariousflowUSARRevision03.9A-3aApril1989 NineMilePointUnit2FSARTHISPAGEINTENTIONALLY BLANKUSARRevision03.9A-3bApril1989 NineMilePointUnit2FSARmodes,thisistakenintoconsideration. Otherdetailsarediscussed inSection3.7.3.8.3A. Liveloadsareconsidered iftheyareexpectedtoconstitute asignificant component ofthetotalmechanical load.Thefillingofmainsteamlineswithwaterduringvesselfloodingandalternate shutdowneventsisindicated onthemainsteamthermaltransients andconsidered inpipestressanalysisinaccordance withNB-3600.Springhangersaredesignedtocarrythefullwater-filled pipingloadduringhydrotest. Additional deadweight stressasaresultoffillingthepipingwithwaterisconsidered intheNB-3600analysisofthesystem.Themainsteamsafetyreliefvalve(S/RV)discharge pipinghasbeendesignedandqualified forthesteamhammerloadduetosteamblow'down. TheresultsoftheBWROwners'roup SafetyReliefValveTestProgram,inwhichUnit2hasbeenaparticipant, showthatthemeasuredspringandsupportresponsewassignificantly lessforwaterthansteam.Thetestreport,asdocumented inNEDE-24988-P, statedthat"themaximumpiperesponseduetoliquiddischarge wasgenerally lessthan30%ofthatduetosteamdischarge." Thetestprogramwasestablished tomeasuretheS/RVdischarge line(S/RVDL)responseforalternate shutdowncoolingconditions andtocomparetheseloadswithsteamloads.Additional deadweight stressresulting fromwater-filled mainsteamsafetyreliefisconsidered intheND-3600analysisofthemainsteamreliefvalvelines.InitialDislacements AnchorMovements NUPIPEpermitscalculation ofthethermalinitialsupportdisplacements combinedwiththethermalresponseduetotheaveragepipewalltemperature change.Earthquake anchormovements areconsidered (Section3.7.3.8.3A). InASMESafetyClass1analysistheloadsduetoOBEanchormovements arecombinedwiththeOBEinertialoadsviaabsolutesummation. InASMESafetyClass2and3analysisthecodepermitstheirexclusion fromoccasional loadsiftheyareincludedwiththethermalexpansion loads.ThermalLoadsApipingsystemmayexperience variousoperating modes.Alloperating modesaremodeledasfollows:Portionsofpipingwithflowingmediumhavethetemperature ofthemedium,whileinactivebrancheshaveambienttemperature. Nonuniform temperature distributions alongthepipenearbranchconnections ofactiveandinactivelegsareconsidered. USARRevision03.9A-4April1989 NineMilePointUnit2FSARInSafetyClass1analysis, stressesduedistribution acrossthethickness ofthegeometric andmaterialdiscontinuities transients mustbeconsidered. TheseareASMESectionIII,Subarticle NB-3600,by:totemperature pipewallandduringthermalrepresented inE~hT,andE(~T-cx12'b(aabb((3.9A-2)Basedongeometry, fluidtype,transients, environmental data:insulation, thermal~hT,~AT,andE~Ta-~T12ababb(3.9A-3)areobtainedfromtheHTLOADprogram(Appendix 3A),orhandcalculations. USARRevision03.9A-4aApril1989 NineMilePointUnit2FSARTHISPAGEINTENTIONALLY BLANKUSARRevision03.9A-4bApril1989 NineMilePointUnit2FSAR3.9.1.5.2A Occasional DynamicLoadsExcluding SeismicandHydrodynamic InertiaLoadsOccasional loadsarealsomatrixequationofmotion:analyzedwithNUPIPE.IntheMU+CU+KU=F(t)(3.9A-4)Where:M=MassmatrixC=DampingmatrixK=Stiffness matrixU=Displacement vectortheforcingfunctionF(t)isappliedasasetofforcetimehistories, oneforeachmassdegree-of-freedom thatexperiences adynamicload.FluidTransients Fluidtransients areconsidered inthefollowing systems:1.Mainsteamandmainsteambypasssystems.2.Mainsteamsafety/relief valve(SRV)discharge system.3.Moistureseparator/reheater safetyreliefsystem.4.Feedwater system.5.Emergency corecoolingsystem(ECCS),including ECCSpressurereliefvalvedischarge piping.6.Servicewatersyst:em.7.Residualheatremovalsystem.8.Reactorcoreisolation coolingsystem.9.Reactorwatercleanupsystem.10.Standbyliquidcontrolsystem.11.Controlroddrivesystem.Amendment 233.9A-SDecember1985 NineMilePointUnit2FSARThecomputerprograms(Appendix 3A)usedtocalculate theseforcetimehistories duetowaterhammer,steamhammer,andpipewithairtrappedinwaterlines,areWATHAM,STEHAM,andWATAIR,respectively. JetIminementTheeffectsofdirectjetimpingement onpipingareevaluated afterallotherpipinganalysesarecompleted andtargetsfromallpostulated breakshavebeenidentified. Amendment 193'A-5aMay1985 NineMilePointUnit2FSAR3.9.3,.3A DesignandInstallation DetailsforMountingofPressure-Relief DevicesPressure-relieving devicesforASMESafetyClass1and2systemcomponents are:1.Mainsteamsafety/relief valves(SRV).2.SRVsforprotecting residualheatremoval(RHR)systemheatexchangers. Thedesignandinstallation ofmainsteamSRVsisdescribed inSection3.9.3.3B. 4Thedesignandinstallation ofSRVsforprotecting theRHRsystemheatexchangers (Section5.4.7.2.3) isinaccordance withASMESectionIII,ArticleNC-7000,andRegulatory Guide1.67.PipingtoandfromSRVsisdesignedinaccordance withASMESectionIII,Paragraph NC-3677.TheSTEHAMcomputerprogram(Appendix 3A)isusedtocalculate fluidtransient forcesineachpipingsegment(straight pipepiecebetweentwoelbows,anelbowandatee,oranelbowandaterminalend)downstream oftheSRVs.'conservatively lowvalueofvalveopeningtimeisusedinthiscalculation. Waterslugsinpipesegmentsendinginthesuppression poolaretakenintoaccount.Dynamicstressesinthepipingarecomputedbytimehistoryintegration ortheequivalent staticmethodsusingtheNUPIPEcomputerprogram(Appendix 3A).Thesestressesarecombinedwiththoseduetoothermechanical loads,inaccordance withloadcombinations described inSection3.9.3.1A. BothSRVsprotecting aheatexchanger areassumedtodischarge concurrently. Theseloadsmeetdesignallowables providedbythevendor.3.9.3.4AComponent SupportsExpansion anchorbolts,usedinsupporting themechanical components fromconcretestructures, aredrilled-in wedge-typeuniformholeanchors.Drilled-in bearing-type flaredholeanchorsarealsousedinsupporting themechanical components fromconcretestructures. Drilled-in wedge-type, uniformholeexpansion anchorsaredesignedforaminimumsafetyfactoroffour,asdetermined bytheultimateloadtestsperformed bythemanufacturer. Thesettingtorqueisdetermined fromin-situtests.USARRevision03.9A-23April1989 NineMilePointUnit2FSARDrilled-in bearing-type, flaredholeanchorsaredesignedforaminimumsafetyfactorofthree,asdetermined byfieldtesting.Theloadsaretransferred intoconcretebydirectbearingagainstconcrete. Theboltmaterialiscapableofreachingfullductility priortofailure.Duetothesereasons,theanchorsaffordgreaterreliability, andalowersafetyfactori'sjustified. Thedesign,procurement, andinstallation ofbuildingsteelcomplywithrequirements oftheAISCspecification forthedesign,fabrication, anderectionofstructural steelforbuildings, asdescribed inSections3.8.4.2and3.8.4.6.3. Theexamination andinspection ofbuildingsteelcomplywiththerequirements ofNRCRegulatory Guide1.94,asdescribed inTable1.8-1.3.9.3.4.1A PipeSupportsThepipesupportdesigns,usingbaseplatesandconcrete. expansion anchorbolts,areperformed usingtheflexibility criteriaofNRCIEBulletin79-02beforetheyarereleasedforfabrication. Verification ofas-builtconditions inaccordance withNRCIEBulletin79-14is.described inSection3.7.3.8.1A. Thebasesfordesignandconstruction ofASMEandnon-ASMEpipingsupportsaregiveninTable3.9A-16.USARRevision03.9A-23aApril1989 NineMilePointUnit2FSARTABLE3.9A-14LOADCONDITIONS FORPIPESUPPORTSLoadCondition NumberPlantCondition NormalLoadsPrimarysustained DLD~Bct1tSoAllowable StressASMEIZZ(1974,including Summer1974Addenda), Subsection NF;andSubsection NA,AppXVIliArticleXVZI-2000 UpsetUpsetPrimarysustained andoccasional associated withupsetAllprimaryandsecondary DL+SRSS(OBEIgOCCU) DL+THER+SRSS (OBEIgOCCU) Emergency FaultedPrimarysustained andoccasional associated withemergency Primarysustained andoccasional associated withfaultedDL+SRSS(OBEIiOCCE) DL+SRSS(SSEIgOCCF) ASMEIII(1974,including Summer1974Addenda), Subsection NA,App.XVZI,-ArticleXVII-2110 ASMEIIZ(1974,including Summer1974Addenda)> App.FiParagraph F-1370KEY:DLOBEIOBETOCC(UiEiF) SSETHER*USARRevision0=Deadload=Operating basisearthquake inertialoadofpiping=Operating basisearthquake total,i.e.,theabsolutesumoftheamplitudes ofOBEinertialoadandloadduetoOBEanchormovements =Primaryoccasional mechanical operating loadsassociated withupset,emergency, andfaultedoperating conditions, respectively, butexcluding earthquake loads.Occasional loadsmaybevibratory ornonvibratory forloadcombination purposes. Theyarecombinedwitheachotherandwithotherloadtypesinthesamewayasintheassociated pipinganalysis. (Seenotestoloadcombinations forpiping,Table3.9A-2).Themaximumandtheminimumresponsefromeachtimehistoryisusedwiththeassociated signinthecombination. =Safeshutdownearthquake inertialoadofpiping=Thermalload;asecondary loadTHER1=Selecting thethreemomentsfromthatthermalloadwhosethreemomentsrepresent themaximumsquarerootofthesumofthesquaresofthemoments.Theforcesselectedarethe-most(+)ofeachforcecomponent alongwithitspropersign(eachforcecomponent chosenmaycomefromadifferent thermalload).THER2=SameasforTHER1,exceptthatthemost(-)ofeachforcecomponent withsignsischosen.THER3=Forcesandmomentsarethoseforthenormaloperating condition.

• Forfeedwater piping,includesapplicable thermalstratification load.1of1April1989

NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER77.17'7'7'7.57.67~7Appendixes CHAPTER8TitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 6A.through6CINSTRUMENTATION ANDCONTROLSYSTEMSIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety7A,7BELECTRICPOWERVolume1313131313141515151515151515151616161616168.18.28.3Appendix8AIntroduction OffsitePowerSystemOnsitePowerSystem16,16'16,1717ICHAPTER9,AUXILIARY SYSTEMS179.19.29.39.49.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17,181920g2121,2223IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER10TitleSTEAMANDPOWERCONVERSION SYSTEMVolume2310.110.210.310.4CHAPTER11Summary.Description TurbineGenerator MainSteamSupplySyst:emOtherFeaturesofSteamandPowerConversion SystemRADIOACTIVE WASTEMANAGEMENT 23232411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems242425252525CHAPTER12RADIATION PROTECTION 2512.112.212.312.412.5EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213.313.413.513.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARAPPENDIX3ACOMPUTERPROGRAMSFORDYNAMICANDSTATICANALYSISOFCATEGORYISTRUCTURES, EQUIPMENT, ANDCOMPONENTS TABLEOFCONTENTSSectionINTRODUCTION TitlePacae3A-13A~13A.l.l3A.1.23A.1.3SHELI1GeneralDescription ProgramVerification References 3A.1-13A.1-13A.l-l3A.1-33A.23A.2.13A.2.23A.2.33A.33A.3.13A.3.23A.2.,3ASAASGeneralDescription ProgramVerification References TAC2DGeneralDescription ProgramVerification Ref'erences 3A.2-13A.2-13A.2-13A.2-43A.3-13A.3-13A.3-13A.3-53A.43A.4.'13A.4.23A.4.33A.53A.5.13A.5.23A.5.33A.63A.6.13A.6.23A.6.33A.73A.7.13A.7.23A.83A.8.13A.8.23A.8.3Amendment 27MAT6GeneralDescription ProgramVerification References STRUDLIIandSTRUDL-SW GeneralDescription ProgramVerification References Time'istory (TIMHIS6) ProgramGeneralDescription ProgramVerification References DELETEDDELETEDDELETEDDINASAWGeneralDescription ProgramVerification References 3A-i3A.4-13A.4-13A.4-13A~4-23A.5-13A.5-13A.5-13A.5-23A.6-13A.6-13A.6-13A.6-23A.7-13A.7-13A.7-1.3A.8-13A.8-13A.8-13A.8-3July198627 NineNilePointUnit2FSARSection3A.93AF9.13A.9.23A.9.33A.103A.10.13A.10.23A.10.33A.113A.11.13A.11.23A.123A.12.1,3A.12.23A.12.33A.133A~13.13A.13.23A.13.3APPENDIX3ATABLEOFCONTENTS(Cont)TitleLIMITAIIGeneralDescription ProgramVerification References LIMITAIIIGeneralDescription ProgramVerification References STARDYNEGeneralDescription ProgramVerification SSLAMGeneralDescription ProgramVerification References SSLOADGeneralDescription ProgramVerification References Pacae3A.9-13A.9-13A.9-43A.9-53A.10-13A.10-13A.10-23A.10-33A.ll-l3A.ll-l3A.ll-l3A.12-13A.12-13A.12-13A.12-23A.13-13A.13-13A~13-13A:13-23A.143A.14.13A.14.23A.14.33A.14.4MISSILEGeneralDescription HighTrajectory Verification LowTrajectory Verification References 3A.3A.3A.3A.3A~14-114-114-114-214-33A.153A.15.13A.15.23A.15~33A.163A.16.13A;16.2,3A.16'3A.173A.17.13A.17.23A.17.3Amendment 19NUPIPEGeneralDescription ProgramVerification References DELETEDDELETEDDELETEDDELETEDHTLOADGeneralDescription ProgramVerification References 3A-ii3A.15-13A.15-13A.15-13A.15-23A.16-13A.16-13A.16-1.3A.16-23A.17-13A.17-13A.17-23A.17-3May1985 N.'n~NilePointUnit2FSAP.APPENDIX. 3ATABLEOFCONTENTS(Cont)Section3A.183A.18.13A.18.23A.18.33A.19"3A.19.13A.19.23A.203A.20F13A.20.23A.20.3.3A.213A.21.13A21.23A.21.3JA.d23~.22.13.i.22.23A.22.3TitleGHOSH-WILSON GeneralDescription ProgramVerification References PSPECTRAGeneralDescription ProgramVerification STEHAMGeneralDescription ProgramVerification References WATHAMGeneralDescription ProgramVerification References PITRUSTGeneralDescription ProgramVerification References ~Pae3A.'~.8-13h1;3-)3A.18-13A.18-?3A.19-13A.19-13A.19-13A.20"13A.20"13A.20-13A.20.-23A.21-13A.21-13A.21-i3A.21-z3A.22-13A.22-13A.22-13A.22-23A.233A.23.13A~23.23A.23.33A.243A.24.13A.24.23A.24.:93A.253A.25.13A.25.23A.263A.26.13A.26.23A.26.3PILUGGeneralDescription ProgramVerification References WATAIRGeneralDescription ProgramVerification References ANSYSGeneralDescription ProgramVerification CWI(Containment WallLoading)GeneralDescription Pr'ogramVerification References 3A.23-13A.23-13A.23-13A.23-23A.24-13A.24-13A.24-13A.24-23A.25-13A.25-13A.25-23A.26-13A.26-13A.26-13n,262 NineMilePointUnit2FSARAPPENDIX3A'ABLEOFCONTENTS(Cont)23.Section3A.273A.27.13A.27.23A.27.33A.283A.28.13A.28.23A.28.33A.28.43A.293A.303A.30.13A.30.23A.30.33A.313A.31.13A.31.23A.31.33A~323A.32.13A.32.23A.333A.33.13A.33.23A.33.3TitleLUGSTRGeneralDescription ProgramVerification References ComputerProgramsforStructural Responses toHydrodynamic Loading(TRANFUNANDINVTRAN)Introduction TRANFUNINVTRANReferences NASTRANBIJLAARD: VesselPenetration AnalysisGeneralDescription ProgramVerification References SLOSH:Simplified TankSloshingAnalysisGeneralDescription ProgramVerification References SNUFFE:Supplement toNUPIPEforFatigueEvaluation GeneralDescription ProgramVerification PITRIFEGeneralDescription ProgramVerification References Pacae3A.27-13A.27-13A.27-13A.27-23A.28-13A.28"13A.28-13A.28-13A.28-33A.29-13A.30-13A.30-13A.30-13A.30-23A~31-13A.31-13A.31-13A.31-23A.32-13A.32-13A.32-13A.33-13A.33-13A.33-13A.33-2Amendment 233A-ivDecember1985 NineMilePointUnit2FSAR3A.15NUPIPE3A.15.1GeneralDescription NUPIPEwasdeveloped bytheNuclearServicesCorporation andisfullydocumented.'he SWECversionofNUPIPEdiffersslightlyfromthepublicdomainprogramNUPIPEinthepost-processing oftheanalytical results.NUPIPEperformsalinearelasticanalysisofthree-dimensional pipingsystemssubjected tothermal,static,anddynamicloads.Itutilizesthefiniteelementmethodofanalysiswithspecialfeaturesincorporated toaccommodate specificrequirements inpipinganalysis. Inaddition, itchecksanalytical conformance toASMESectionIIIandANSIB31.1.Thisprogramacceptsthecompletegeometric andphysicaldescription ofthepipingsystem,providesacompleteerrorandcoordinate checkfortheinputs,andcomputesinternalforcesandmoments,supportandequipment reactions, anddisplacements andstressvaluesforavarietyofloadingcases.3A.15.2ProgramVerification NUPIPEhasbeenverifiedwithADLPIPEor thermal,weight,andresponsespectrumseismicanalyses. Theresultsfrombothprogramsarepresented inTables3A.15-1through3A.15-7.Themodelusedforthiscomparison ispresented onFigure3A.15-1.Thecomparison isalsomadewithASMEBenchmark solutionforforcetimehistorydynamicresponse'. Themodelusedforthiscomparison isshownonFigure3A.15-2.Theresultsforcomparisons arepresented intheformofplotsonFigure3A.15-2.Thenaturalfrequencies aregiveninTable3A.15-8.TheSafetyClass1pipingstresscomputation conformswiththehandcalculations. ThemodelusedisshownonFigure3A.15-3.Theresultsaretabulated inTables3A.15-9and3A.15-10. 3A.15-1 NineMilePointUnit2FSAR3A.'15.3References 1.ArthurD.Iittle,Inc.ADLPIPE:Static,Dynamic,ThermalPipeStressAnalysis. 2.AmericanSocietyofMechanical Engineers. PressureVesselandPiping;1972ComputerProgramsVerification. ProblemNo.5.3A.15-2 NineMilePointUnit2FSARAPPENDIX3BTABLEOFCONTENTSSection3B.l3B.23B.33B.3.13B.3.23B.3.33B.3.43B.3.53B.3.63B~3'3B.4TitleDESIGNBASESDESIGNFEATURESDESIGNEVALUATION Elevation 175ft0in.215ft0in.Elevation 215ft0in.240ft0in.Elevation 240ft0in.261ft0in.Elevation 261ft0in.289ft0in.Elevation 289ft0in.306ft6.in.Elevation 306ft6in.328ft10in.Elevation 328ft10inREFERENCES toElevation toElevation toElevation toElevation toElevation toElevation andAbovePacae3B-13B-33B-53B-53B-6.3B-73B-83B-9.3B-103B-103B-llUSARRevision03B-iApril1989 NineMilePoint'nit 2FSARAPPENDIX3BLISTOFTABLESTableNumberTitle3B-13B-23B-33B-43B-53B-63B-7HIGHENERGYLINEBREAKSANALYZEDINTHEREACTORBUIIDINGHIGHENERGYLINEBREAKSANALYZEDINTHEMAINSTEAMTUNNELSUBCOMPARTMENT NODALDESCRIPTION -HIGHENERGYLINEBREAK"ANALYSIS INREACTORBUILDINGSUBCOMPARTMENT,NODAL DESCRIPTION -MAINSTEAMTUNNELHIGHENERGYLINEBREAK'ANALYSIS SUBCOMPARTMENT VENTPATHDESCRIPTION REACTOR,BUILDINGHIGHENERGYLINEBREAKANALYSIS(4-NODEMODEL)SUBCOMPARTMENT VENTPATHDESCRIPTION REACTORBUILDINGHIGHENERGYLINEBREAKANALYSIS(33-NODEMODEL)VENTPATHDESCRIPTION -MAINSTEAMTUNNEIHIGHENERGYLINEBREAKANALYSIS-TWO-PHASE BREAKINMST-33B-83B-93B-103B-113B-12VENTPATHDESCRIPTION -MAINSTEAMTUNNELHIGHENERGYLINEBREAKANALYSIS-TWO-PHASE BREAKINMST>>5MASSANDENERGYRELEASEFOR4-INRCICDERINVOLUME175-1-BREAKNO.19MASS,ANDENERGYRELEASEFOR4-INRCICDERINVOLUME175-2-BREAKNO.20MASSANDENERGYRELEASEFOR8-INRWCUDERINVOLUMES215-1AND215-5BREAKNO.16AND17MASSANDENERGYRELEASEFOR4-INRWCUDERINVOLUME215-9-BREAKNO.15 NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHEHT VENTPATHDESCRIPTION: HIGH-ENERGY LIKEBREAKANALYSISINTHEREACTORBUILDING(45NODEHOOEL)VentPathNumberFromVolunaNurberToVoluneNumberHeadLossCoefficients InertiaVentFactorAreaL/A(1)Turning(ft2)(1/ft)Contraction Expansion Obstruction LossFrictionSharpEdgeLossTotal1175-'I175-2(a)2175-1175-9(a)3175-2175-3(a)4175-2175-3(b)5175-2215-1175-2175-1175-9175-1175-3175-2175-3175-2215-1175-225.8825.8810.0010.0010.0010.0010.0010.001.0471.0470.3270.3270.2580.2580.3660.3660.3660.3662.6482.6480.49320.47150.45170.46460.45170'646O.C7730.49820.88910.97290.86350.81610.86350.81610.993D0.91130.2000.2000.33680.34450.15680.15460~15680.15460.02600.02600.03470.03470.03470.03470.09200.09200.6310.6311.4111.4111.7451.8151.50714701F5071.4701.7621.7026'175-3175-4175-4175-321.0021.000.2150.2150'240.2240.8981.1221.5841.8087175.4175-5175-5175-4242.86242.860.0150.0150.2000.2000.9941.1941.8472.0478175-4175-6175-6175-4265.09265.090~0140.0140.2000.2000.9921.1921.8402.0409175-4175-7'175-7175-4241.26241.260.0140.0140.2DO0.2000.9941.1941.8482.04810175-4175-811175-4175-9175-8175-4175-9175-4240.31240.31140.18140.180.0150.0150.0200.0200.2000.2000.2000.2000.99C1.1941.8482.0480.8141.0141.6981.89812175-4215-8215-8175-462.4262.420.0390.0390.49640.49620.98490.98560.2000.2001.15481~15490'0660.00662.8432.843USARRevision01of5April1989

NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHEHT VEHTPATHDESCRIPTION: HIGH-ENERGY LINEBREAKANALYSISIHTHEREACTORBUILDIHG(45NOOENOOEL)VentPathNumberFromVoluneNunberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)Contraction Expansion HeadLossCoefficients Sharp(1)TurningEdgeObstruction LossFrictionLossTotal25215-6215-8215-8215-621.00N/A0.321N/A0.36980.96553.424(c)0.90100.00985.670(c)2627215-8215-9215-8215-10215-9215-8215-10215-8H/A14.33N/A14.33N/A0.313N/A0.313(c)3.424(c)3.4242.0872.185(c)5.511(c)5.60928215-8240-5240-5215-852.0352.030.0450.0450.49690.49700.98780.98760.2000.2001.14191.14180.00720.00722.8342.83429215-9215-10215-10215-915.7515.750.4140.4140.43790.43790.76690.76690.05870.05870.03660.03661.3001.30030240.1240-2240-2240-1101.05101.050.0640.0640.8350.8350.5570.55731240-1261-1261-1240-128.3828.380.3360.3360.2000.2000.6520.8520.3790.57932240-3240-4240-4240-337.8337.830.1100.1100.2000.2000.5040.7041.0931.29333240-3240-5240-5240-316.38N/A0.234N/A3.424(c)1.6885.112(c)34240-3240-3261-3261-339.6839.680.1430.1430.2000.2000.8671.6171.0671.8173536240-5240-7240-5240-8240-7240-5240-8240-52.2992.2992.2992.2990.0910.0910.0930.0930.49930.49620.49930.49580.98470.99710.98340.99711.26721.27111.26631.27070.00330.00330.00330.00332.7552.7682.7522.767USARRevision03of5April1989 0 NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHEHT VENTPATHDESCRIPTION: HIGH-EHERGY LINEBREAKANALYSISIHTHEREACTORBUILDING(45NOOEHOOEL)VentPathNumberFromVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)HeadLossCoefficients Sharp(1)TurningEdgeContraction Expansion Obstruction LossFrictionLossTotal373839240-5261-4240.6306-4261-1261-2261-4240-5306-4240.6261-2261-167.4567.4521.1521.1533.2633.260.0290.0291.6741.6740.1690.1699600.49670.98680.98400.1880.1880.2000.2001.16151.16060.7680.1810.00640.00642.8392.8361.1461.9140.6630.8440.9381.1381.2461.44640261-1261-4261-4261-115.93H/A0.213N/A3.424(c)1.7655~189(c)414243261-2289-1261-3261-5261-4289-3289-'I261-2261-5261-3289-3261-426.3026.3049.9549.95503.31503.310.2930.2930.2270.2270.0100.0100.48020.47960.91990.92240.2000.2000.2000.2001'6071.06140.00230.00230.7750.9750.8971.0970.2200.4200.1980.3982.4632.466261-5289-2289-2261-565.7565.750.1740.1740.2000.2000'820.4820.2350.435454647289.1306-1289-2306-4289-3306-5289-3306-5306-1289-1306-4289-2306-5289-3306-5289-340.8240.8236.8636.862079.02079.02590.02590.00.1740.1740.1690.1690.0100.0100.0100.0100.31660.46760.41560.39100.39480.36430.87460.40100.61160.69070.53070.62350.2000.2000.4000.4000.75110.61820.93170.96050.84590.88580.01080.01080.00150~00150.00130.00131.1680.5201.3680.7202.3531.8981.9602.0441.7731.875USARRevision04of5April1989

NineNilePointUnit2FSARTABLE38-5SUBCOHPARTHENT VENTPATHDESCRIPTION: HIGH-ENERGY LINEBREAKANALYSISINTHEREACTORBUILDING(45NODEMODEL)VentPathNumberFromVolcanoHumberToVoluneNunberInertiaVentFactorAreaL/A(ft2)(1/ft)Contraction Expansion HeadLossCoefficients Sharp(1)TurningEdgeObstruction LossFrictionLossTotal49306.1306-2245.990.014306.2306-1245.990.0142.3112.3112.3902.39050306-1328-28.9560.4010.49690.9731328-2306-18.9560.4010.49320.98750~16450.16510.02720.02721.662'I.67351306-2306-3136.800.035306.3"306-2136.800.0351.6451.6451.9591.95952306.3306-492.480.445306-43D6.392.480.4450.3240.3240.3900.39053306-5328-1508.580.0100.47330.7057328-1306-5508.580.0100.42000.89621.05041.11510.00230.002322322.4345C328-1353-1502.880.0100.42090.9554353-1328-1502.M0.010O.C8870.70871.15221.06930.00230.00232.5312.269(1):Theobstruction Lossincludeslossesfromagrill,grating,wiremeshdoor,and/orventcurtains. Theselossesaredescribed inSection38.2:DesignFeatures. (a):Thisventpathisablowoutpanel.Thevaluesinthistableareforafterthepanelhasfullyopened(ifitisnotassumedtofoilclosedunderthesingle-fai lurecriteria). Theblowoutpanelisfullyopen0.3secondsaftera0.5psidforceisappliedacrossit.Thepanelopensinthedirection showninthetoplistingfortheventpath.(b):ThisJunctionisusedonlyforBreakNumbers6and9.Thisisexplained inTable38-1:High-Energy LineBreaksAnalyzedintheReactorBuildingandSection38.3.2:Elevation 215'0<<toElevation 240'0<<.(c):ThisJ~tionhasventcurtains. Thecurtainallo~sflowinonLyonedirection. Ventcurtainsarediscussed inSection3B.2:DesignFeatures, Section3B.3.2:Elevation 215~0<<toElevation 240'0",Section3B.3.3:Elevation 240'0<<toElevation 261'0",andSection38.3.4:Elevation 261'0<<toElevation 289'0<<.NOTE:thehonogeneous equfLIbrfunmodel(HEN)forchokedflowisusedforallbreeksandnodalizations. Appendix6B:THREEDSubncompartment Analytical Nodalgivesadescription oftheHEHusedintheSWECcomputercodeTHREED.USARRevision05of5April1989 0 NineHitePointUnit2FSARTABLE3B-6SUBCOHPARTNENT VENTPATHDESCRIPTIOH: HIGH-ENERGY LINEBREAKANALYSISIHTHEREACTORBUILDIHG(46HODENODEL)VentPathNumberFromVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)Contraction Expansion HeadLossCoefficients Sharp(1)TurningEdgeObstruction LossFrictionLossTotal175-1175.2(a)2175-1175-9(a)3175-2175-3175.2175-1175-9'175-1175-3175-225.8825.8810.0010.0010.0010.000.3270.3270.2580.2580.3660.3660.49320.47150.45170.46460.88910.97290.86350.81610.33680.34450.15680.15460.02600.02600.03470.03470.6310.6311.4111.4111.7451.8151.5071.470175-2215-1215-1175-21.0471.0472.6482.6480.47730.49820.99300.91130.2000.2000.09200.09201.7621.702175-3175-4'175-4175-5175-4175-3175-5175-421.0021.00242.86242.860.2150.2150.0150.0150.2240.2240.2000.2000.8981.1221.5841.8080.9941.1941.8472.047175-4175-6175-6175-4265.09265.090.0140~0140.2000.2000.9921.1921.8402.0401012175-4175-7175-4175-8175-4175.,9175-4215-8175-10215-3175.7175.4175-8175-4175-9175-4215.8175-4215-3175-10241.26241.26240.31240.31140.18140.1862.4262.4281.3081.300.0140.0140.0150.0150.0200.0200.0390.0390.1210.1210.49640.49620.98490.98560.2000.2000'000.2000.2000.2000.2000.2000.2000.2001.15481.15490.00660.00660.9941.1941.8482.0480.9941.1941.8482.0480.8141.0141.6981.8982.8432.8431.3371.5370.7630.963USARRevision01of6April1989

NineNilePointUnit2FSARTABLE38-6SUBCOHPARTNENT VENTPATHDESCRIPTION: HIGH-ENERGY LINEBREAKAHALYSISINTHEREACTORBUILOIHG(46NODEMODEL)VentPathNurherFromVoiuneNunberToVoiuneNumberVentArea(ft2)InertiaFactorL/A(1/ft)HeadLossCoefficients Sharp(1)TurningEdgeContraction Expansion Obstruction LossFrictionLossTotal252627215-8215-9215-8215-10215;8215-8215-9215-8215-10215-8240-5240-5N/A14.33H/A14.3352.0352.03N/A0.313N/A0.3130.0450.0450.49690.49700.98780.9876(b)3.424(b)3.4240.2000.2001.14191.14180.00720.00722.0872.185(b)5.511(b)5.6092.8342.83428215-9215-10215-10215-915.7515.750.4140.4140.43790.43790.76690.76690.05870.05870.03660.03661.3001.30029240-1240-2240-2101.05240-1101.050.0640.0640.8350.8350.5570.5573031240-1261-1240-3240-4261-1240-1240-4240-328.3828.3837.8337.830.3360.3360.1100.1100.2000.2000.2000.2000.6520.8520.3790.5790.5040.7041'931'9332240-3240-5240-5240.316.38H/A0.234H/A3.424(b)1.6885.112(b)33240-3240-3261-3261-339.6839.680.1430.1430'000.2000.8671.6171.0671.81734240.5240-7240-7240-52.2992.2990.0910.0910.49930.49620.98470.99711.26721.27110.00330.00332.7552.76835240.5240-8240.8240-52.2992.2990.0930.0930.49930.49580.98340.99711.26631.27070.00330.00332.7522.76736240-5261-4261-4240-567.4567.450.0290.0290.49600.49670.98680.98400.1880.1881.16151.16060.00640.00642.8392.836USARRevision03of6April1989

NineNilePointUnit2FSARTABLE38-6SUBCONPARTHENT VENTPATHDESCRIPTION: HIGH-ENERGY LINEBREAKANALYSISINTHEREACTORBUILDING(46NODEHODEL)HeadLossCoefficients VentPathNumberFramVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1)Turning(1/ft)Contraction Expansion Obstruction LossSharpEdgeFrictionLossTotal37240.6306.4306-4240-621.1521.151.6741.6740.7680.1811.1461.9140.6630.84438261.1261-2261-2261-133.2633.260.1690.1690.2000.2000.9381.1381.2461.44639261-1261-4261-4261-115.93N/A0.213N/A3.424(b)1.7655.189(b)40261-2289.1289-1261-226.30.26.300.2930.2930.2000.2000.7750.9750.8971.09741261-3261-5261-4289.3261-5261-3289-3261-449.9549.95503.31503.310.2270.2270.0100.0100.48020.47960.91990.92240.2000.2001.06071.06140.00230.00230.2200.4200.1980.3982.4632.46643261-4289-3289-3261-4197.42197.420.0100.0100.49220.49200.96820.96921.20781.20800.00400.00402.6722.67344261-5289-2289-2261-565.7565.750.1740.1740.2000.2000.2820.4820.2350.43545289-1306-1306-1289-140.8240.820.1740.1740.2000.2001.1680.5201.3680.72046289.2306.4306-4289-236.8636.860.1690.1690.31660.46760.87460.40100.4000.4000.75110.61820.01080.01082.3531.89847289.3306.5306-5289-32079.02079.00.0100.0100.41560.39100.61160.69070.93170.96050.00150.00151.9602.04448289-3306-5306-5289-32590.02590.00.0100.0100.39480.36430.53070.62350.84590.88580.00130.00131.7731.875USARRevision04of6April1989 4 HineNilePointUnit2FSARTABLE38-6SUBCONPARTHENT VENTPATHDESCRIPTIOH: HIGH-ENERGY LINEBREAKANALYSISIHTHEREACTORBUILDING(46NODEHOOEL)VentPathNumberFromVoluneNumberToVoluneNumberVentArea(ft2)InertiaFactorL/A(1/ft)HeadLossCoefficients Sharp(1)Turn>ngEdgeContraction Expansion Obstruction LossFrictionLossTotal49289-3306-5306.5289.3202'6202.160.0100.0100.49180.48940.95810.96741.20221.20500.00390.00392.6562.6665051306-1306.2306-1328-2306-2306.1328-2306-1245.99245.997.1927.1920.0140.0140.4930.4930.49690.49320.97310.9S750.2000.2000.16450.16510.02720.02722.3112.3112.3902.3901.8621.8735253306-2306.3306-3306-4306-3306-2306-4306-3136.80136.8092.4892.480.0350.0350.4450.4451.6451.6451.9591.9590.3240.3240.3900.390306-5328-1328-1306-5508.58508.580.0100.0100.47330.42000.70570.89621.05041.11510.00230.002322322.43455328-'I353-1353-1328-1502.88502.880.0100.0100.42090.48870.95540.70871.15221.06930.00230.00232.5312.26956SC328190306-1306-1SC3281900.1700.17020.6520.650.50000.50001.00001.00000.26180.26181.7621.76257SC328190306-1306-1SC3281900.0490.04971.5171.510.50000.50001.00001.00000.58620.58622.0862.0865eSC32e190306-1306-1SC32819059SC328190328-2328-2SC32819060SC328190328-2328-2SC3281900.8630.8630.7180.7180.7180.7184.0984.0984.9154.9154.9154.9150.50000.50000.50000.50000.50000.50001.00001.00001.0000F00001F00001.00000.14580.14580.14580~14580~14580.14581.6461.6461.6461.6461.6461.646USARRevision05of6April1989

NineNilePointUnit2FSARTABLE38-6SUBCOHPARTHEHT VEHTPATHDESCRIPTION: HIGH-ENERGY LINEBREAKANALYSISIHTHEREACTORBUILDING(46NODEHODEL)VentPathNumberFromVoiuneNunberToVoluneHwherVentArea(ft2)InertiaFactorL/A(1/ft)Contraction HeadLossCoefficients Sharp(1)TurningEdgeExpansion Obstruction LossFrictionLossTotal61SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001.00001.00000.35370.35371.8541.85462SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001F00001.00000.35370.35371.8541.85463SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001.00001.00000.35370.35371.8541.85464SC328190328-2328-2SC3281900.1810.18119.39019.3900.50000.50001.00001.00000.35370.35371.8541.854Thisnodalization modelisusedforthe6"RNCUbreaksinVoiunes328-2andSC328190~ThefiredeeperJunctionbetweenVolwes175-2and215-1isassumedtobeopenfortheentiretransient. (1):Theobstruction lossincludeslossesfromagrill,grating,wiremeshdoor,and/orventcurtains. Theselossesaredescribed inSection38.2:DesignFeatures. (a):Thisventpathisablowoutpanel.Thevaluesinthistableareforafterthepanelhasfullyopened.Theblowoutpanelisfullyopen0.3secondsaftera0.5psidforceisappliedacrossit.Thepanelopensinthedirection showninthetoplistingfortheventpath.(b):ThisJunctionhasventcurtains. Thecurtainallowsflowinonlyonedirection. Ventcurtainsarediscussed inSection3B.2:DesignFeatures, Section38.3.2:Elevation 215'OatoElevation 240'0",Section38.3.3:Elevation 240'0"toElevation 261'0",andSection38.3.4:Elevation 261'OwtoElevation 289'0".NOTE:Thehomogeneous equiIibriunmodel(HEH)forchokedflowisusedforallbreaksandnodalizations. Appendix68:THREEDSubmcompartment Analytical Nodalgivesadescription oftheHEHusedintheSPECcomputercodeTHREEO.USARRevision06of6April1989

TO261-4FROM215-8TO261-3240-5GENERALAREA240-3TIPGUBlGLETO261-1240-7PENETRATION AREA240-8PENETRATION AREA240-1PIPECHASE240-2PENETRATION AREA240"4PIPECHASEFROM215-1FROM215-2NOTES:sVENTCURTAINJUNCTION~COONWITNLOUVERsDIRECTION OfVENTFLOWVOLUIIE2404ISSHOWNONSHEET4OFFIOURESSIFIGURE3B-2NODALI2ATION DIAGRAM-REACTORBUILDINGHIGH-ENERGY LINEBREAKANALYSIS(4SNODEMODEL)SHEET3OF6NIAGARAMOHAWKPOWERCORPORATION NINEMILEPOINT-UNIT2UPDATEDSAFETYANALYSISREPORTUSARREVISION0APRIL1989 4 NineMilePointUnit2FSARTHISPAGEINTENTIONALLY BLANKAmendment 183C-11bMarch1985 NineMilePointUnit2FSARreactororthatcouldincreasetheoffsiteradiation beyondthelimitsof10CFR100. 3C.2.9.2RPVSteamVentLine28)Thelocations ofpostulated pipebreaksareshownonFigure3.6A-15.Themainsteam2-inventlinebranchesoffthemainsteamline(2MSS-026-43-1) at.el314ft10in.Itthenloopsitswayuptoel342ft8ll/16inanddropsvertically intotheRPVhead.2828ITheMSSpiping,ifallowedtowhip,couldimpact,targetssuchasdrywellhead,vesseldome,insulation supportstructure, mainsteamline2MSS-026-43-1, andrupturerestraint 2RHS*PRR014. Sincethepipingisa2-indiameterline,theimpacting forcesofthepipingsystemarerelatively smallandwillnotcausedetrimental resultstothetargetsmentioned above.Thepipewhipduetoabreakinthislinewillnotcauseanylossofstructural integrity tothetargetsmentioned above.Conclusions Usingveryconservative assumptions andcriteria, nopostulated failureoftheMSSventlinecancausedamagethatcouldimpairtheabilitytosafelyshutdownthereactororthatcouldincreasetheoffsiteradiation effectsbeyondthelimitsof10CFR100. 3C.2.10MainSteamSafetyReliefValvePiping(SVV)asfsa/ThelocationofpipebreaksareshownonFigures3.6A-16and3.6A-17'hemainsteamsafetyreliefvalvepipingforeachofthe18SRVsconsistsofan8-inconnection offthemainsteamlinetotheSRVanda10-indischarge linefromtheSRVtothesuppression pool.Thehigh-energy portionofthesystemisthe1-ftlengthfortheconnection frommainsteampipetothenormallyclosedSRV.Twobreaksarepostulated foreachSRV;theyareterminalpoint,circumferential breaksforthe8-inconnection. Targetsfrompipewhiparethe12-inRHSlines.ImpactanalysisshowsfailureofSVVpipingcannotcauseadditional damagethatcouldimpairtheAmendment 28I'C-12May1987 NineMilePointUnit2FSARTABLE'OFCONTENTS(Cont).Section5.35.4Appendixes CHAPTER6TitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESVolume131313136.16.26.36.46.56.6Appendixes 6A.through6CEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components 13141515151515CHAPTER77.17'7~37'7.57.67'Appendixes CHAPTER8INSTRUMENTATION ANDCONTROLSYSTEMSIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety7Ai7BELECTRICPOWER151515151616161616168.18.28.3Appendix8AIntroduction OffsitePowerSystemOnsitePowerSystem=-16,16'16,1717I~CHAPTER9AUXILIARY SYSTEMS179.19.29.39.49.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17.181920,2121,2223USARRevision0April1989 NineNilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionCHAPTER10TitleSTEAMANDPOWERCONVERSION SYSTEMVolume2310.110.210.310.4CHAPTERSummaryDescription TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion SystemRADIOACTIVE WASTEMANAGEMENT 23232411.111.211.3~11.411.5SourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystemsAppendix11ACHAPTER12RADIATION PROTECTION 24242525252525,12.1-12.212.312.4.12.5EnsuringThat,Occupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgram2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213'13.413.5.13.6Appendixes Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B26262626262626CHAPTER14INITIALTESTPROGRAM2614.1Specific"Information,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26 NineMilePointUnit2FSARCHAPTER5LISTOFFIGURESFigureNumber5.l-la5.l-lb5.1-2a,b,c5.2-15.2-25.2-35.2-45.2-55.2-5a5.2-65.2-75.2-85.2-95.3-15.3-25.3-35.3-4TitleRATEDOPERATING CONDITIONS OFTHEBOILINGWATERREACTORCOOLANTVOLUMESOFTHEBOILINGWATERREACTORNUCLEARBOILERSYSTEMSAFETYRELIEFVALVECAPACITYSIZINGTRANSIENT "MSIVCLOSUREWITHHIGHFLUXTRIP"SAFETYRELIEFVALVESCHEMATIC ELEVATION SAFETYRELIEFVALVEANDSTEAMLINESCHEMATIC NUCLEARBOILERSYSTEMPAIDSCHEMATIC OFSAFETYRELIEFVALVEWITHAUXILIARY ACTUATING DEVICEABNORMALAMBIENTCONDITIONS FORACTUATORQUALIFICATION TESTTYPICALBWRFLOWDIAGRAMCONDUCTIVITY'Hg CHLORIDECONCENTRATION OFAQUEOUSSOLUTIONS AT77F(25C)CALCULATED LEAKRATEVSCRACKLENGTHASAFUNCTIONOFAPPLIEDHOOPSTRESSAXIALTHROUGHWALL CRACKLENGTHDATACORRELATION BRACKETFORHOLDINGSURVEILLANCE CAPSULEMINIMUMTEMPERATURES REQUIREDVERSUSREACTORPRESSUREPREDICTED ADJUSTMENT OFREFERENCE TEMPERATURE "A"ASAFUNCTIONOFFLUENCEANDCOPPERCONTENTREACTORVESSELUSARRevision05-ixApril1989 NineMilePoint'Unit2FSARCHAPTER5LISTOFFIGURES(Cont)FigureNumber5.3-5TitleNOMINALREACTORVESSELWATERLEVELTRIPANDALARMELEVATION SETTINGS5.4-1RECIRCULATION SYSTEMELEVATION ANDISOMETRIC 5.4-2athroughREACTORRECIRCULATION SYSTEMP&ID5.4.265.4-35.4-45.4-55.4-65.4-75.4-8RECIRCULATION PUMPHEAD,NPSH,FLOWANDEFFICIENCY CURVESOPERATING PRINCIPLE OFJETPUMPCOREFLOODINGCAPABILITY OFRECIRCULATION SYSTEMMAINSTEAMLINE FLOWRESTRICTOR MAINSTEAMISOLATION VALVECUTAWAYVIEWDELETED5.4-9athroughRCICSYSTEM5.4-915.4-105.4-10a5.4-10b5.4-115.4-12REACTORCOREISOLATION COOLANTSYSTEMPROCESSDIAGRAMRCICTURBINECHARACTERISTIC CURVESSTEAMFLOWVS.POWERRCICTURBINECHARACTERISTIC CURVESSTEAMFLOWVS.PRESSUREVESSELCOOLANTTEMPERATURE VERSUSTIME(TWOHEATEXCHANGERS AVAILABLE) VESSELCOOLANTTEMPERATURE VERSUSTIME(ONEHEATEXCHANGER AVAILABLE) 5.4-13athroughRHRSYSTEM5.4-13gUSARRevision05-xApril1989 NineMilePointUnit2FSARCHAPTER5LISTOFFIGURES(Cont)FigureNumber5.4-145.4-15TitleRESIDUALHEATREMOVALSYSTEMPROCESSDIAGRAMANDDATARHRPUMPCHARACTERISTIC CURVES5.4-16athroughREACTORWATERCLEANUPANDFILTER5.4-16fDEMINERALIZER SYSTEMPAID5.4-175.4-18REACTORWATERCLEANUPSYSTEMDELETEDUSARRevision05-xaApril1989 ,NineMilePoi.ntUnit2FSARTHISPAGEINTENTIONALlY BLANKAmendment 75-xbDecember1983 NineMilePointUnit2FSAR(SeeSection3.9.6Afortheprogramforpumpsandvalves.)Subsequent inservice inspections willbeperformed inaccordance withtherequirements of10CFR50.55a(g) asdescribed intheInservice Inspection Program.5.2.5ReactorCoolantPressureBoundaryandECCSLeakageDetection System5.2.5.1LeakageDetection MethodsThenuclearboilerleakdetection system(LDS)consistsoftemperature,

pressure, level,flow,airbornegaseousandparticulate fissionproductsensors,andprocessradiation sensorswithassociated instrumentation usedtoindicateandalarmleakagefromtheRCPB.TheLDSincertaincasesisusedtoinitiatesignalsusedforautomatic closureofisolation valvestoshutoffleakageexternaltothecontainment.

Thesystemisassessedtobeinconformance withRegulatory Guide1.45.Thoseportionsofthesystemwhichaffectautomatic isolation ofleakagearedesignedtoIEEE279-1971(refertoTable3.2-1).Abnormalleakagefromthefollowing systemswithinthecontainment andwithintheselectedareasoftheplantoutsidetheprimarycontainment isdetected, indicated, alarmed,andincertaincases,isolated. 1.Mainsteamlines.2.RWCUsystem.3.RHRsystem.45.RCICsystem.Feedwater system.6.HPCS.7.Coolantsystemswithinthecontainment. 8.LPCS.9.RPV.10.Miscellaneous systems.Leakdetection methodsusedtoobtainconformance withRegulatory Guide1.45forplantareasinsidetheprimarycontainment differfromthoseforareaslocatedoutsidetheAmendment 265.2-29May1986 NineMilePointUnit2FSARprimarycontainment. Theseareasareconsidered separately inthefollowing sections. 5.2.5.1.1 Detection ofLeakageWithinthePrimaryContainment Theprimarydetection methodsforsmallunidentified leakswithintheprimarycontainment includecontinuous monitoring ofdrywellfloordraintankfillrateandairbornegaseousandparticulate radioactivity increases. (Thesensitivities oftheseprimarydetection methodsforunidentified leakagewithintheprimarycontainment arelistedinTable5.2-8.)Thesevariables arecontinuously indicated and/orrecordedinthecontrolroom.Iftheunidentified leakageincreases toatotalof5gpm,thedetecting instrumentation channel(s) willtripandactivateanalarminthemaincontrolroom.Thisdoesnotresultinacontainment isolation signal.Thesecondary detection methods(i.e.,themonitoring ofpressureandtemperature oftheprimarycontainment atmosphere) areusedtodetectgrossunidentified leakage.Highprimarycontainment pressurewillalarmandtriptheisolation logicwhichresultsinclosureofthecontainment isolation valves.Thedetection ofsmallidentified leakagewithintheprimarycontainment isaccomplished bycontinuous drywellequipment draintankfillratemonitoring. Analarmwillbeactivated !inthemaincontrolroomwhentheleakratereaches25gpmaveragedovera24-hrperiod.Thedetermination ofthesourceofidentified leakagewithintheprimarycontainment isaccomplished bymonitoring thedrainlinestothedrywellequipment draintankfromvariouspotential leakagesources.Theseincludereactorrecirculation pumpsealdrainflowandreactorvesselheadsealdrainlinepressure. Additionally, temperature ismonitored intheSRVdischarge linestothesuppression pooltodetectleakagethrougheachoftheSRVs.Allofthesemonitors, exceptthereactorrecirculation pumpsealdrainflowmonitor,continuously indicateand/orrecordinthecontrolroom.Allofthesemonitorstripandactivateanalarminthecontrolroomondetection ofleakagefrommonitored components. Excessive leakageinsidetheprimarycontainment (e.g.,processlinebreakorLOCAwithinprimarycontainment) isdetectedbyhighprimarycontainment

pressure, lowreactorwaterlevelorhighsteamlineflow(forbreaksdownstream USARRevision05.2-30April1989 NineMilePointUnit2FSARoftheflowelements).

Theinstrumentation channelsforthesevariables tripwhenthemonitored variableexceedsapredetermined limittoactivateanalarmandtriptheisolation logicwhichclosesappropriate isolation valves(Table5.2-9).Thealarmsandindication andisolation tripfunctions initiated bytheLDSsaresummarized inTables5.2-9and.5.2-10.5.2.5.1.2 Detection ofLeakageExternaltothePrimaryContainment (WithinReactorBuilding) Thedetection ofleakagewithinthereactorbuilding(outsidetheprimarycontainment) isaccomplished bydetection ofincreases inreactorbuildingfloordrainsumpandreactorbuildingequipment draintankfilluptimeandpumpout,time(Section5.2.5.2.2). Thereactorbuildingfloordrainsumpmonitorswilldetectunidentified leakageincreases andactivateanalarminthemaincontrolroom.Thereactorbuildingequipment draintankmonitorswilldetectidentified leakageincreases andactivateanalarminthemaincontrolroomwhenleakageincreases abovenormalbackground levels.SeeSection5.2.5.2.2 foradiscussion ofthefuelpoollinerleakagedetection method.5'.2.5.1.3 Detection ofLeakageExternaltothePrimaryContainment Areasoutsidetheprimarycontainment thataremonitored forprimarycoolantleakageare:equipment areasintheauxiliary bays,themainsteamtunnel,andtheturbinebuildi'ng. Theprocesspipingforeachsystemtobemonitored forleakageislocatedincompartments orroomsseparatefromothersystemswherefeasiblesothatleakagemaybedetectedbyareatemperature indications. Theseareasaremonitored bydualelementthermocouples forsensinghighambienttemperature inalltheseareasandhighdifferential temperature betweentheinletand"outletventilation ductsinthemainsteamtunnel.Thetemperature elementsarelocatedorshieldedsothattheyaresensitive toairtemperature onlyandnottoradiatedheatfromhotpipingorequipment. Increases inambientand/ordifferential temperature indicateleakageofreactorcoolantUSARRevision05.2-31April1989 NineMilePointUnit2FSAR23intothearea.Themonitorslocatedinthemainsteamtunnelandturbinebuildinghavesensitivities suitablefordetection ofincreases inambientairtemperature whichareequivalent toreactorcoolantleakageintothemonitored areasof2Sgpmorless.Thetemperature tripsetpointsareafunctionofroomsizeandthetypeofventilation provided. Thesemonitorsprovidealarm,indication, andrecording inthemaincontrolroom,and'riptheisolation logictocloseselectedisolation valves(e.g.,themainsteamtunnelmonitorsclosetheMSIVandmainsteamlinedrainisolation valvesandothervalves[Table5.2-9]).23Theturbinebuildingtemperature monitorsalarmandindicateinthemaincontrolroomandtriptheisolation logictoclosethemainsteamisolation andmainsteamlinedrainisolation valveswhenleakageexceeds2Sgpm.Thesesensorsmonitorambienttemperature intheenclosedspacebetweenthesteamtunneloutletandtheinlettothehighpressureturbine.2323Excess-leakageexternaltothecontainment (e.g.,processlinebreakoutsidecontainment.) isdetectedby.lowreactorwaterlevel,highprocesslineflow,highambienttemperature inthepipingorequipment areas,highdifferential flow,andlowmaincondenser vacuum.Thesemonitorsprovidealarmandindication inthemaincontrolroomandtriptheisolation logictocauseclosureofappropriate systemisolation valvesonindication ofexcessleakage(Table5.2-9).Setpointsforthehighambienttemperature monitorsinthepipingandequipment areasofthereactorbuildingandauxiliary baysarebasedonlimitingthemaximumenvironmental conditions oftheseareastowithintheenvironmental qualification capabilities oftheapplicable equipment. 5.2.5.1.4 Intersystem LeakageMonitoring LeakagefromtheHPCS,LPCS,RCIC,andRHRsystemsoutsidecontainment isdetectedbyacombination ofmethods,including highareatemperature, higharearadiation, highsumplevel,andreactorpressurevesselcondition (seeSection5.2.5.1~3).Radiation monitorsareusedtodetectreactorcoolantleakageintocoolingwatersystemssupplying theRHRheatexchangers andtheRWCUnonregenerative heatexchanger. Thesemonitoring channelsarepartoftheprocessradiation monitoring system.Processradiation monitoring channelsmonitorforleakageintoeachcommoncoolingwaterheaderdownstream oftheRHRheatexchangers andtheRWCUAmendment 235.2-32December1985 NineNilePointUnit2FSARTABLE5.2-1(Cont)CodeCaseNumber/RevisionApplicable RaJ'-""TitleTherequiredexposuretimesforlowhydrogenelectrodes wereadheredtoexceptfortheexposuretimeswereincreased slightlyforsomesitewelding.Forelectrode E70XX,theexposuretimewasincreased form4to5hr,andforelectrode E80XX,from2to4hr.'nthesecases,allcoveredelectrodes continued tobeissuedinheatedportablerodovens.Theincreased exposuretimesarebasedonindustryusagedataandtestdatatomeettheintentofRegulatory Guide1.85andCodeCase1644-9requirements. Amendment 243bof8February1986

NineMilePointUnit2FSARTABLE5'-8LEAKDETECTION METHODS,ACCURACY, ANDSENSITIVITY LeakDetection MethodDrywellfloordraintanklevelDrywellequipment draintanklevel4Airborneparticulates Gaseousradioactivity ~Accurac1gpm1gpmSensitivit 1gpm/hr1gpm/hr6.6-12uCi/cc.9-07uCi/cc'~'OTE: 6.6-12=6.6x10Theairborneparticulate radiation levelcorresponding toa1"gpm/hrleakrateis1.1-07uCi/cc.'~'Thegaseousradioactivity levelcorresponding toa1gpm/hrleakrateis6.3-07uCi/cc.Amendment 191of1May1985

~~ltNineMilePointUnit2FSARrrequirements. The'material forstuds,nuts,andwashersisSA-540GradeB23orB24atthe130,000psi-specified minimumyieldstrengths level.Hardness. testsareperformed onallmainclosureboltingtodemonstrate 'thatheattreatment hasbeenproperlyperformed. Aminimumof45ft-lbCharpyV-notch(C)energyand25milsV,lateralexpansion isrequiredat70~F.Themaximumreportedultimatetensilestrengthisbelowthe170,000-psi maximumspecified. inRegulatory Guide1.65.Also,theCharpyimpacttest,requirements of10CFR50AppendixGaresatisfied, sincethelowestreportedQenergyis46ft-lbat+10OF,comparedtotherequirement of45ft-lbat70F,andthelowestreportedC>expansion was26mils,comparedtothe25milsrequired. Studs,nuts,andwashersareultrasonically examinedinaccordance withASMESectionIII,Paragraph NB-2585,andthefollowing additional require-ments:1.Examination wasperformed afterheattreatment andpriortomachining threads.2.3.Straightbeamexamination wasperformed on100percentofeachstud.Reference standardfortheradialscanisa1/2-indiameterflat-bottom holehavingadepthequalto10percentofthematerialthickness. FortheendscanthestandardofParagraph NB-2585isused.Nutsandwasherswereexaminedbyanglebeamfromtheoutsidecircumference inaccordance withASMESA-388inboththeaxialandcircumferential directions. The.surfaceexaminations requiredbyParagraph NB-2583areappliedafterheattreatment andthreading. Therearenometalplatingsappliedtoclosurestuds,nuts,orwashers.A-manganese-phosphate coatingisappliedtothreadedareasofstudsandnutsandbearingareasofnutsandwasherstoassistinretaining lubricant onthesesurfaces. Subsequent tofabrication, thestudsarelubricated withagraphite/alcohol ornickelpowderbaselubricant. Regulatory Guide1.65definesacceptable materials andtestingprocedures withregardtoreactorvesselclosurestudboltingforlight-water-cooled reactors. Amendment 115.3-9June1984 NineMilePointUnit:2FSARTheRPVclosurestudsareSA-540GradeB23or24(AISI-4340) andhaveamaximumultimatetensilestrengthof170ksi.Additionally, =,theboltingmaterial.wasspecified tohaveCharpyV-notchimpactproperties of45ft-lbminimumwith25milslateralexpansion. Nondestructive examination beforeandafterthreading isspecified tobeinaccordance ,,with=ASMESectionIII,Subsubarticle NB-2580whichcomplieswithReglatory Guide1.65(C.2).Inaccordance withRegulatory Guide1.65(C.2.b),theboltingmaterials wereultrasonically examinedafterfinalheattreatment andpriortothreading. Asrequiredforcompliance, theexamination 'asdoneinaccordance withSA-388.,Theprocedures approvedforuseinpracticewerejudgedtoensurecomparable materialqualityand,moreover, wereconsidered adequateonthebasisofcompliance withtheapplicable" requirements ofASMESectionIII,Paragraph NB-2583. Additionally, 'straight beamexamination wasperformed on100percentofcylindrical

surfaces, andfrombothendsofeachstudusinga3/4-inmaximumdiametertransducer.

Inadditiontothecode-required notch,thereference standardfortheradialscancontained a1/2-indiameterflat-bottom holewithadepthequalto10percentofthethickness'he endscanstandardcontained a1/4-indiameterflat-bottom hole1/2-indeep.Anglebeam,ultrasonic examination wasperformed ontheoutercylindrical surfaceinbothaflatandcircumferential .direction. Surfaceexaminations wereperformed onthestudsandnutsafterfinalheattreatment andthreading, asspecified byRegulatory Guide1.65,inaccordance withParagraph NB-2583oftheapplicable ASMEcode.Radialscan-calibration isbasedona1/2-in(12.7-mm)diameterflatbottomholeofadepthequalto10percentofthematerialthickness. Anglebeamexamination isperformed ontheoutercylindrical surfaceofnutsandwashersinaccordance withASMESA-388inbothaxialandcircumferential directions. Noindication greaterthan,theindication fromtheapplicable calibration featurewasacceptable. Adistance-amplitude correction curveinaccordance withParagraph NB-2858isusedforthelongitudinal waveexamination. Inrelationship toRegulatory Guide1.65(C.3),studboltingsurfacesareallowedtobeexposedtohigh-purity fillwater;nutsandwashersaredrystoredduringrefueling. 5.3-10 NineMilePointUnit2FSARthistime,theturbinebypasssystemdivertsthesteam.tothemaincondenser, andthefeedwater systemsuppliesthemakeupwaterrequiredtomaintainreactorvesselinventory. Intheeventthereactorvesselisisolatedandthefeedwater supplyunavailable, reliefvalvesareprovidedtoautomatically (orremotemanually) maintainvesselpressurewithindesirable limits.Thewaterlevelinthereactorvesseldropsduetocontinued steamgeneration bydecayheat.Uponreachingapredetermined lowlevel,theRCICsystemisinitiated automatically. Theturbine-driven pumpsuppliesdemineralized makeupwaterfromthecondensate storagetanktothereactorvessel.Analternate sourceofwaterisavailable fromthesuppression pool.TheRCICsystemallowsautomatic switchover ofpumpsuctionfromthecondensate storagetanktothesuppression poolifthecondensate storagetankfallstoapresetlowlevel.Lowlevelinthetankismonitored bytworedundant level.transmitters. Ifeithertransmitter senseslowlevel,pumpsuctionisautomatically transferred tothesuppression pool.Theturbineisdrivenwithaportionofthedecayheatsteamfromthereactorvesselandexhauststothesuppression pool.Suppression poolwaterisnotmaintained demineralized andisusedonlyintheeventallsourcesofdemineralized waterhavebeenexhausted. Ifthemainfeedwater systemisnotoperable, areactorscramisautomatically initiated whenreactorwaterlevelfallstoLevel3.TheoperatorcanthenremotelymanuallyinitiatetheRCICsystemfromthemaincontrolroom,orthesystemisautomatically initiated asfollows.Reactorwaterlevelcontinues todecreaseduetoboil-offuntilLevel2isreached.Atthispoint,thehigh-pressure corespray(HPCS)and:thereactorcoreisolation cooling(RCIC)systemsareautomatically initiated tosupplymakeupwatertotheRPV.Thesesystems'ontinue automatic injection untilthereactorwaterlevelreachesLevel8,atwhichtimetheHPCSinjection valveisclosedandtheRCICsteamsupplyvalveisclosed.Inthenonaccident case,the-RCICsystemisnormallytheonlymakeup.systemusedtofurnishsubsequent makeupwatertotheRPV.TheoperatorremotelymanuallyshutsdowntheHPCSsystem,fromthemaincontrolroom.WhenlevelreachesLevel2againduetolossofinventory throughthemainsteamreliefvalvesortothemaincondenser, theRCICsystemautomatically restartsasdescribed inSectionII.K.3.13. Thissystemthenmaintains thecoolantmakeupsupply.RPVpressureisregulated bytheautomatic orremotemanualoperation ofthemainsteamreliefvalveswhichdischarge tothesuppression pool.USARRevision05.4-17April1989 NineMilePointUnit2FSARToremovedecayheatduringaplannedisolation event,assumingthatthemaincondenser isnotavailable, thesteamcondensing modeoftheRHRsystemcanbemanuallyinitiated. ResidualsteamisroutedthroughtheRHRheatexchangers whereitiscondensed andcooled,thenreturnedtotheRPVthroughaninterconnection withtheRCICpump.Thus,closedloopcoolingisprovidedbythismode.Ifthesteamcondensing modeisunavailable foranyreason,thesafetyreliefvalvescanbeusedtodumptheresidualsteamtothesuppression pool.Thesuppression poolwillthenbecooledbyremotemanualalignment oftheRHRsysteminthesuppression poolcoolingmodewhichroutesthepoolwaterthroughtheRHRheatexchangers, coolsit,andreturnsittothesuppression poolinaclosedcycle.MakeupwatertotheRPVisstillsuppliedbytheRCICsystem.FortheaccidentcasewiththeRPVathighpressure, theHPCSsystemcanalsobeusedtoautomatically providetherequiredmakeupflow.Nomanualoperations arerequired. IftheHPCSsystemispostulated tofailattheseconditions andtheRCICcapacityisinsufficient, theautomatic depressurization system(ADS)willautomatically initiatedepressurization oftheRPVtopermitthecondensate pumpsorthelowpressureECCS(LPCIandLPCS)toprovidemakeupcoolant.WhenevertheRCICsystemisinitiated, theLSTGturbineistrippedtopreventwaterinduction intotheturbine,andthecontrolroomisalarmedthattheRCICinjection valveisopen.Therefore, althoughmanualactionscanbetakentomitigatetheconsequences ofalossoffeedwater, therearenoshorttermmanualactionswhichmustbetaken.Sufficient systemsexisttoautomatically mitigatetheseconsequences. DuringRCICoperation, thesuppression poolactsastheheatsinkforsteamgenerated byreactordecayheat.Thisresultsinariseinpoolwatertemperature. Heatexchangers intheresidualheatremoval(RHR)systemareusedtomaintainthepoolwatertemperature withinacceptable limitsbycoolingthewaterdirectlyorbycondensing generated steam.Thecondensate discharge fromtheRHRheatexchangers maybeusedasRCICpumpsuctionsupplyoritmaybedirectedtothesuppression pool;'TheRCICsystemisequippedwithadischarge linefillpumpthat,operatestomaintainthepumpdischarge lineinafilledcondition. Keepingthedischarge linefilledreducesthelagtimebetweenpumpstartupandattainment offullflowtotheRPV.Additionally, itsoperation eliminates thepossibility ofRCICpumpsdischarging intoadrypipeandminimizes waterhammereffects.Thefillpumpisclassified asCategoryIandSafetyClass2.ThepumpmotorisUSARRevision05.4-17aApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER76Athrough6CINSTRUMENTATION ANDCONTROLSYSTEMSTitleReactorVesselComponent andSubsystem Design5A,5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment SystemsEmergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components Volume1313131313141515151515157.17.27'7'7.57.67~7Appendixes 7A,7BIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety1515151616161616CHAPTER88.18.28.3Appendix8ACHAPTER9ELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMS16161616,1717I179.19.29.39.49.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9A,9C17181920~2121,2223USARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSION SYSTEM2310.110.210.310.4Summary.Description TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion System232324CHAPTER11RADIOACTIVE WASTEMANAGEMENT ll.111.211.311.411.5SourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystemsAppendixllACHAPTER12RADIATION PROTECTION 2424252525252512.112.212.312.412~5CHAPTER1313.113.213.313.413.513.6Appendixes EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment HealthPhysicsProgramCONDUCTOFOPERATIONS Organizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security13A,13B252525262626262626.26262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation,To BeIncludedinPreliminary SafetyAnalysisReport(PSAR)26}}