ML18038A770

From kanterella
Revision as of 03:32, 29 June 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Forwards Rev 1 to Updated SAR for Nine Mile Point Unit 2. All Errata Items Identified in Attachment 1 to Previous Updated SAR Transmittal Ltr of 890428 Resolved.Programs to Resolve Setpoint Issues Will Be Established by 891130
ML18038A770
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/25/1989
From: TERRY C D
NIAGARA MOHAWK POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18038A768 List:
References
NMP2L-1210, NUDOCS 8911020134
Download: ML18038A770 (168)
v • d • e


Text

7NIAGARAuMOHANKNIAGARAMOHAWKPOWERCORPORATION/301 PLAINFIELD ROAD,SYRACUSE, N.Y.13212/TELEPHONE (315)474-1511October25,1989NMP2L1210U.S.NuclearRegulatory Commission Attention:

DocumentControlDeskHashington, D.C.20555Re:NineMilePointUnit2DocketNo.50-410IKf=B-Gentlemen:

Pursuantto10CFR50.4(b)(6) and50.71(e),

NiagaraMohawkPowerCorporation herebysubmitsonesignedoriginalandtencopiesofRevision1totheNineMilePointUnit2UpdatedFinalSafetyAnalysisReport,hereinafter referredtoastheUpdatedSafetyAnalysisReport(USAR)forNineMilePointUnit2..CopiesarealsobeingsentdirectlytotheRegionalAdministrator, RegionIandtheNRCResidentInspector atNineMilePoint.Inaccordance with10CFR50.71(e)(4) thisupdateincludesmodifications completed priortoApril30,1989.Thecertificate requiredby10CFR50.71(e)(2) isattachedtothisletter,Allerrataitemsidentified inAttachment 1toourpreviousUSARtransmittal letterofApril28,1989,havebeenresolvedandtheappropriate changesincorporated intothisupdate.However,aswenotedinourprevioustransmittal letter,NiagaraMohawk'sinternalNuclearCompliance andVerification groupconductsanadditional independent verification ofthetechnical basisof'hanges andtheaccuracyoftheUSARchanges.Thisverification ofcertainUSARchangesforboththisupdateandtheoriginalsubmittal hasnotbeencompleted, Theremaining openverification itemsfallintooneoffourcategories:

1).Themajorityofopenverification itemsinvolveinconsistencies inthelevelofdetailshownonUSARfigureswhencomparedtothesourcedesigndocuments.

Theseitemsdonotinvolvequestions ofaccuracy, butwillrequiredevelopment ofstandards andrevisionofalargenumberofdesigndrawingstosatisfyNHPC'sinternalverification procedures.

89ii020134 89i025PDRADOCK05000410PDR1473b~$9~{

l4' 2).Severalverification itemsrelatingtosetpoints onUSARfiguresarestillbeingcompleted.

Theseitemshaveraisedquestions aboutsetpoints contained intheUSAR.Procedures areinplace,including 10CFR50.59evaluations, 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.3).Someitemsfromthisupdate(Revision 1)arestillinthefinalverification process.4).Sourcedocumentation forchangesdeveloped byGEhadnotbeenavailable, preventing finalverification.

Programstoresolvethegeneralarrangement andsetpointissueswillbeestablished nolaterthanNovember30,1989.Ascheduleforcompletion oftheprogramsandallopenverification itemsincluding anyopenitemsfrom3and4abovewi11beestablished atthattime.AsstatedinourApril28,1989submittal letter,procedures areinplacetodocumentandresolveverification comments.

USARchangesresulting fromthosecommentswillthenbeincorporated.

Attachment 1isbeingsubmitted infulfillment oftherequirements of10CFR50,71(e)(2)(ii) toidentifychangesmadeundertheprovisions of10CFR50.59butnotpreviously submitted totheCommission.

IncludedinAttachment 1areeightsafetyevaluations whichwereinadvertently leftoutofourApril28,1989submittal.

Fourofthesesafetyevaluations reflected changesmadetothedesignoftheplantpriortotheissuanceofthefull-term operating license.Theotherfourshouldhavebeenincludedaschangesforthelastsubmittal.

Alleightsafetyevaluations wereincorporated intoRevision0totheUSAR.Noneofthesafetyevaluations inAttachment 1involvedanunreviewed safetyquestionasdefinedby10CFR50.59(a)(2).

Sincerely, NIAGARAMOHAWKPOWERCORPORATION WER/sek1473bC.D.TerryVicePresident NuclearEngineering 5Licensing Attachment xc:RegionalAdministrator, RegionIMr.R.A.Capra,DirectorMr.R.E.Martin,ProjectManagerMr.W.A.Cook,ResidentInspector RecordsManagement s'

~yUNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterof]]NiagaraMohawkPowerCorporation

]](NineMilePointUnit2)]DocketNo.50-410AFFIDAVIT C.D.Terr,beingdulysworn,statesthatheisVicePresident ofNiagaraMohawkPowerCorporation; thatheisauthorized onthepartofsaidCorporation tosignandfilewiththeNuclearRegulatory Commission thedocuments attachedhereto;andthatallsuchdocuments aretrueandcorrecttothebestofhisknowledge, information andbelief.1989.Subscribed andsworntobeforeme,aNotaryPublicinandfortheStateofNewYorkandCountyof,thisW~PAdayofd'otaryPublicinandforCounty,NewYorkpgNEq,5MB~'

HdgyPubPCR th'933503 s~teg1'HGwY~~~~gyp~/m)~MyCommission expires:

t SAFETYEVALUATION REPORTSURGERYSERNo.:PG-201SERTitle:Implementation ofC02FireProtection inSwitchgear Area.System:FireProtection FSARSectionsAffected:

F9.4-3a,9.4-12b,P9.4-17,F9.4-6(All)Description:

Incorporation ofModification PN2Y86MX090.

Thismodification providesreinforcement ofwallsanddoorsandprovidesdamperstoaccommodate C02discharge andtheassociated pressureofFireProtection equipment.

ThiscoversthenormalswitchgearareaEl.261E&WandTurbineBuildingSwitchgear East.Incorporated inconjunction withmodification PN2Y86MX114.

Thischangedoesnotadversely affectthesafeshutdownanalysisanddoesnotconstitute anunreviewed safetyquestion.

(7858G).89ll020134,,

SAFETYEVALUATION REPORTSUMMARYSERNo.:PG-201SERTitle:Implementation ofC02FireProtection inSwitchgear Area.System:FireProtection FSARSectionsAffected:

F9.4-10EDescription:

Incorporation ofModification PN2Y86MX114.

Thismodification providesforreinforcement ofwalls,doorsandincorporation ofdamperstoaccommodate C02discharge andtheassociated pressureofFireProtection equipment.

Thiscoversthenormalswitchgear areaEl.237E5H,TurbineBuildingSwitchgear El.277'0"Nest,andRadwasteSwitchgear El.277'0".Incorporated inconjunction withmodification PN2Y86MX090.

Thischangedoesnotadversely affectthesafeshutdownanalysisanddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:PG-201SERTitle:Environmental SampleTapInstallation

.System:NAFSARSectionsAffected:

F9.2-lh,10.4-7dDescription:

Incorporation ofModification PN2Y86MX108.

Thismodification providesanaddedsampletaptomonitorSHPandCNS(servicewaterandcirculating water)forcontamination.

Thisisinaccordance withNRCIEBulletin¹80-10andReg.Guide4.2anddoesnotconstitute anunreviewed safetyquestion-.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:PG201CSERTitle:RemovalofHeldedTablesinControlRoomSystem:NAFSARSectionsAffected:

F1.2-15,Sh.lDescription:

Incorporation ofModification PN2Y87MX188.

Thismodification removedaweldedseismictablefromthecontrolroom.Thistablewasusedasaworktableandwastoolargeandcumbersome foruseinthecontrolroom.TablewasshowninUSARFigure1.2-15,Sh.1.Theremovalofthistablewillnotaffectcontmiroomoperation anddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUONRYSERNo.:87-039SERTitle:SealingofEmbeddedConduitinFireBarriersSystem:NAFSARSectionsAffected:

Section9A.3.5.1.2 Oescription:

Thisevaluation addresses achangeinsealingcriteriaforembeddedconduit,1"orlessindiameter.

Thischangerelievestherequirement toprovidefirebarriersealingonsomeconduit(1"Dia.orless).Thisisbased.ontheNRCacceptance ofsimilarreliefatCleveland ElectricIlluminating (PerrySite).Itwasdetermined thatthischangedoesnotaffectthesafeshutdowncapability anddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:87-050SERTitle:AdditionofDxCoil,to2HVH-ACU2A/BandHumidification System.System:RadwasteBuildingVentilation (HVN)FSARSectionsAffected:

P9.4-37,9.4-37a,9.4-66,T9.4-4,9.4-1,F9.2-8a,9.2-8b,9.3-lie,9.4-3f,9.4-10e,9.4-21,Sh.2,9.4-11,Sh.12,9.4-11,Sh.15.Description:

Incorporation ofModifictionPN2Y86MX093.

Thismodif1cationinvolveschangestotheRadwasteControlRoomVentilation tomaintaintemperature and&umidity withinrequiredlimitsforequipment andpersonnel, Thechangesmaintaintheoriginaldesignintentoftheventilation systemanddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUNNARYSERNo.:87-059,Rev.1SERTitle:RemovalofSecondary Containment HatchesSystem:N/AFSARSectionsAffected:

F1.2-7,Sh.1,1.2-7,Sh.2,1.2-8,Sli.1,1.2-9,Sh.1,1.2-9,Sh.2,1.2-10,Sh.1,1.2-10,Sh.2,1.2-6,Sh.2.Description:

Thischangewillallowoperation oftheplantwithsecondary containment floorhatchesopenorremovedforeaseofplantoperability, maintainability andefficiency.

Thiscanbeaccomplished withoutadverseimpacttoplantdesignparameters oraccidentanalysisandtherefore doesnotconstitute anunreviewed safetyquestion.

9(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:87-060,Rev.2SERTitle:RDSScramDischarge VolumeVentandDrainValveLimitSwitches.System:ControlRodDriveSystem(RDS)FSARSectionsAffected:

F4.6-5,Sh.3,7.2-1Description:

Incorporation ofModification PN2Y87MX092.

Thismodification providesscramdischarge volumeventanddrainvalvepositionindication tothePMSComputer.

Thiswillenableverification ofvalvepositionforsurveillance testing.:

Thiswillnotaffectsystemperformance anddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:87-087SERTitle:AdditionofRRCSFeedwater RunbackInhibitSystem:Redundant Reactivity ControlSystem(RRCS)FSARSectionsAffected:

Section7.6.1.8,7.6.2.8.4, F7.6-9,Sh.6,Section7.7.1.3Description:

Incorporation ofModification PN2Y86MX110.

Thismodification willprovideaninhibitswitchfortheRedundant Reactivity Control(RRCS)featureoffeedwater runback.Thisswitchisonlytobeusedduringsurveillance testingtopreventaspurioustripatpower.Thiswillpreventthepotential severeplanttransient thatcouldoccur.Operatoraction.willmaintainplantparameters whiletheinhibitswitchisinuse.Analysishasshownthattheuseofthisswitchduringsurveillance testingwillnotincreasetheprobability orconsequences ofanaccidentandtherefore doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:87-097,Rev.2SERTitle:Secondary Containment DesignBasesSystem:N/AFSARSectionsAffected:

P6.2-57dDescription:

Thischangeprovidestheevaluation forchangesinthesecondary containment drawdownanalysis.

Thisidentifies theassumptions andrequirements formaintaining plantconditions consistent withtherevisedanalysis.

Operating conditions andtheaccidentanalysisareconsidered andtherequlrementr maintained andidentified intheUSARchanges.ThesafetyanalysisandNRCrequirements aremaintained andthesechangesdonotconstitute anunreviewed safetyquestion.

(7858G) 00 SAFETYEVALUATION REPORTSUMMARYSERNo.:87-137,Rev.1SERTitle:HasteNeutralizing TankDischarge Filter/Bypass LineAddition.System:MakeupHaterTreatment System(HTS)FSARSectionsAffected:

F9.2-5a,9.2-5eOescription:

Incorporation of'odification PN2Y87MX168.

Thismodification providesadditional filtering andpipingtomaintaineffluentdischarges withinrequiredlimits.Thisisconsistent withtheNMP2Environmental Protection PlanandStateandFederaldischarge requirements andtherefore doesnotconstitute anunreviewed safetyquestion.-

(78586)

SAFETYEVALUATION REPORTSUMMARYSERNo.:87-145;Rev.1SERTitle:Condenser DrainTank,2ARC-TKl, CheckValveSystem:AirRemovalsystem(ARC)FSARSectionsAffected:

F10.4-1,Sh.5,10.4-2a,9.3-10c,T9A.3-12, P10.4-7Description:

Incorporation ofHodification PN2Y87HX185.

Thismodification providesacheckvalveandpipingchangesinthecondenser airremovalsystemtopreventbackflowofcondensate tothedraintank(2ARC-TKl) duringsystemoperation.

Thisenhancessystemoperation anddoesnotaffectconditions ofthesafetyanal~is.Therefore thisdoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:87-155SERTitle:ReactorFeedwater PumpSealWaterModifications

.System:Feedwater System(FWP)FSARSectionsAffected:

F10.1-6cDescription:

Incorporation, ofModification PN2Y86MX098.

Thismodification incorporates aduplexstrainerandreplacement ofpressurecontrolvalves,2FWP-PCV5A/B/C withamanualplugvalve,2FWP-V35A/B/C ineachfeedwater pumpsealsupplyline.ThesechangesprovidecleanerwatertothesealsandenablesOperati'Qns tomanuallycontrolthesealwaterpressuretothe.feedwater pumps.Thesechangesdonotchangesystemoperation orthesafetyanalysis.

Therefore thisdoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATtON REPORTSUMMARYSERNo.:87-174,Rev.1SERTitle:AdditionofGEMsAnnunciators

~System:ProcessRadiation Monitoring FSARSectionsAffected:

F9.4-9,Sh.18,9.4-13,Sh.10,P9.4-44Description:

Incorporation ofModification PN2Y87MX211.

Thismodification providesadditional annunciation forGEMsmonitoring forthereactor/radwaste buildingventradiation monitoring andaddsreflashcapabilities forthemainstackeffluentandradiation monitorannunciation, Thismaintains compliance withTechnical Ypecification requiredcontrolroomannunciation fortheidentified parameters.

Thismodification doesnotaffectsystemoperation orthesafetyanalysisandtherefore doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-008,Rev.1SERTitle:-AdditionofSolenoidValvestoRCSPumpSealStagingLinesSystem:ReactorCoolantSystem(RCS)FSARSectionsAffected:

F5.4-2b,5.4-2c,9.3-lg,T3.2-1,Sh.2,3.2.1,Sh.26aDescription:

Incorporation ofModification PN2Y87HX184.

Thismodification replacedtheexistingAOVsontheRCSpumpsealstaginglinewithSOVs.ThisenablesthevalvestocloseonalossofACPowertotheRCSpumpstopreventpumpandsealdamage.ThechangetoSOVswasnecessary becausemaintaining airtotheAOVs(toclose)duringalossofpower,couldhavepotentially ledtoadegradation oftheprimarycontainment integrity andaviolation ofthebypassleakagecriteriaperTechnical Specifications.

Thismodification maintains compliance withthesafetyanalysisandtherefore doesnotconstitute anunreviewed safetyquestion.

(7858G) 0 SAFETYEVALUATION REPORTSUMMARYSERNo.:88-010SERTitle:BypassSwitchfor2HRS-PS107

.System:MainSteam(MSS)FSARSectionsAffected:

F10.1-3hDescription:

Incorporation ofModification PN2Y87MX232.

Thismodification providesabypassswitchthatpreventsthetrippingof2MSS-AOV92A/B, andisolation oftheMoistureSeparator Reheaters, duringsurveillance testingofturbinevalves.Duringsurveillance testingoftheturbinevalvesatlowpower,asmallenoughpressurecouldbesensedat2HRS-PS107 totripAOV92A/B.

Thismodification willpreventinadvertent tripsduringthiscondition anddoesnotaffectthesafetyanalysis.

Therefore thismodificaiton doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-014SERTitle:AddPressureIndicator to20FG-FT3A/B System:OffGas(OFG)FSARSectionsAffected:

F11.3-laDescription:

Incorporation ofModification PN2Y87MX246.

Thismodification providesapressureindicator totheoffgassystemtoenableOperations personnel toperformdensitycompensation ofindicated systemflowtodetermine actualsystemflow.Thiswillenchancesystemperformance anddoesnotaffectthesafetyanalysis.

Therefore, thiswillnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-022SERTitle:SetpointChangefor2DFR*LS145 from2.25"to2.75"'ystem:ReactorBuildingDrains(DFR)FSARSectionsAffected:

F9.3-13,Sh.5,9.3-9eDescription:

Thissetpointchangewillincreasethealarmcondition sensedby2DFR*LS145 intheRCICpumproom.ThislevelswitchmonitorswaterlevelintheRCICpumproom,Thesetpointchangemoreaccurately identifies analarmcondition andwillnotimpacttheexistingfloodanalysisforthearea.Thiswilltherefore notconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-027,Rev.1SERTitle:ChangeofQAClassification ofConduit-System:N/AFSARSectionsAffected:

T3.2-1,Sh.26c,3.2-1,Sh.16,3.2-1,Sh.15aDescription:

ThischangerevisestheQualityAssurance requirements identified inTable3.2-1forconduitanditsassociated appurtenances (exceptwhenpartofanenvironmental seal).Thischangestherequirements from"I"-to"NA"whilemaintaining pertinent provisions oftheoperational qualityassurance program.Thischangedoesnotaffectthesafetyrelatedfunctionofanysystemorcomponent andtherefore doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-029SERTitle:InstallIsolation ValvesforHVKMakeupCheckValvesSystem:ControlBuildingChilledHaterSystem(HVK)FSARSectionsAffected:

F9.4-laDescription:

Incorporation ofModification PN2Y87HX252.

Thismodification providesisolation valvestofacilitate maintenance onvalves2HVK*V12and*V95.Theadditionoftheseisolation valveswillenablemaintenance tobeperformed withouttheneedtoisolatethesubsystem expansion tankandrenderthesubsystem ii95perable perTechnical Specifications.

Thismaintains therequirements ofthesafetyanalysisandtherefore doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-034,Rev.1SERTitle:RemovalofRestricting Orifice2ICS*R0158 System:ReactorCoreIsolation Cooling(ICS)FSARSectionsAffected:

F5.4-9,Sh.1,5.4-9,Sh.2Description:

Thischangeaddresses theremovalofRestricting Orifice2ICS*R0158.

Duringsystemtesting,itwasidentified thatrestricting orifice*R0158didnotperformitsintendedfunctionduetotheexistingpipingdesign.Theorificewastherefore removedtoenhancesystemoperation andmaintainrequiredparameters.

Thischangeidentifies theorificeremovalintheaffectedSARfigure.Thereisnochangetoactualsystemperformance andtherefore doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUNDRYSERNo.:88-035,Rev.lSERTitle:RedesignofCondenser SamplingLinesSystem:TurbinePlantSampling(SST)FSARSectionsAffected:

F9.3-5e,9.3-5fDescription:

Incorporation ofModification PN2Y87MX209.

Thismodification replacessamplepumps,changessamplepipingandprovidesbackflush capabilities tothecondenser samplingsystem.Thesechangescorrectexcessive failuresanddifficulties inthesamplingsystem.Thisdoesnotaffectthedesignfunctionofthesystemorthesafetyanalysis.

Therefore, thisdoesnotconstitute anunrevlewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-037SERTitle:RerouteSecondPointFNHeaterLevelTransmitter Piping.System:Feedwater Heaters(HOL)FSARSectionsAffected:

F10.1-7a,10.1-7b,10.1-7cDescription:

Incorporation ofModification PN2Y88MX055.

Thismodification reconfigures thelevelinstrumentation forthesecondpointfeedwater heaters.Thisreconfiguration isdesignedtoreducetheeffectoffeedwater transients ontheextraction steamsystemandreducespurioustrips.Thischangewillno~ffectthesafetyanalysisandwillnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSURGERYSERNo.:88-038SERTitle:AdditionofEHCNarrowRangePressureIndicator

,System:MainSteam(MSS)/Electro-Hydraulic ControlSystem(TMB)FSARSectionsAffected:

F10.1-3gDescription:

Incorporation ofModification PN2Y88MX012.

Thismodification installed anarrowrangepressuretransmitter andindicator at2MSS-PT143, toprovidemainsteam,pressure.

Thisindicator willenableoperations tomoreaccurately determine

.steampressuretosettheEHCpressureregulator.

Thiswillenchancesystemoperation andwillnotaffectthesafetyanalysis.

Therefore thisdoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATIONREPORTSUMMARYSERNo.:88-047,Rev.2SERTitle:GTSSystemSingleFailureMods.System:Standby,GasTreatment (GTS)FSARSectionsAffected:

F6.5-1,Sh.2,6.5-1,Sh,5,6.5-1,Sh.8,9.4-81,T8.3-1,Sh.3,8.3-2,Sh.3,8.3-4,Sh.6,8.3-4,.Sh.18Description:

Incorporation ofModification PN2Y88MX101.

Thismodification modifiedvalves2GTS*MOV28A/B internally toprovidefailopencapability onlossofpower.Theairinletvalves2GTS*MOV4A/B arecrossconnected.

ThesechangesinsureMatthedelayheatremovalcapability ofthestandbygastreatment systemwi11beprotected againstthelossofasingletrain.Valves*MOV28A/B willalsobechangedtothenormallyopenpositiontoprotectagainstasinglefailure.Thismodification maintains therequirement ofthesafetyanalysisandtherefore willnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVAlUATION REPORTSUMMARYSERNo.:88-049SERTitle:ModifyAirflowstoRWCUPumpRoomsSystem:ReactorBuildingVentilation (HVR)FSARSectionsAffected:

F9.4-8c,9.4-8d,9.4-8fDescription:

Toinsureproperventilation isprovidedtotheReactorWaterCleanup(WCS)Rooms,duringtherecirculation modeoftheReactorBuildingVentilation System,holeswillbecutinthecurtainsplacedovertheWCSRoomdoors.Thecurtains.

wereprovidedtomaintaindesignconditions forahighenergylinebreWandi.nsureproperventilation duringnormaloperating conditions.

TheairflowtoandfromtheWCSRoomhasbeenad)ustedtoinsureproperventilation isprovidedinallmodes.Thischangehelpsmaintaintherequirements ofthesafetyanalysisandtherefore willnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-055SERTitle:ReactorBuildingUnitCoolerThermostat SetpointChange.System:ReactorBuilding.

Ventilation (HVR)FSARSectionsAffected:

F9.4-9,Sh.8,9.4-9,Sh.20Description:

AsrequiredbytheSecondary Containment DrawdownAnalysis, aminimumQTmustbemaintained betweenservicewaterandreactorbuildingtemperature.

Thiscouldrequireheatingofthereactorbuildingwhiletheunitcoolerswereinoperation.

ThischangerevisedtheunitcoolersetpointsoasnottoconflictwithheatingoftheReactorBuildingasrequired.

Thesetpointisarangebetween85to97FtoallowOperations personnel flexibility Inad)usting theunitcoolersetpointtomaintaintherequiredb,Twhenservicewatertemperature changes.Thischangemaintains therequirement ofthesafetyanalysisandwi11notconstitute anunreviewed safetyquestion.

(7858G) 0 SAFETYEVALUATION REPORTSUMMARYSERNo.:88-057SERTitle:Relocate'Nitrogen BottleRack,TBEl;261'ystem:

HotHaterHeating(HVH)FSARSectionsAffected:

F9.4-22@,1.2-19;Sh.2Description:

Incorporation ofModification PN2Y88MX109.

Thismodification relocated afrequently accessednitrogenbottlerackoutofapotential radiation/contamination areatoanunrestricted area:Thiswastoreducecollective exposures andradwastevolume.Thesenitrogenbottlesareusedinthehotwaterh~tingsystemforpressurization andtominimizeoxidation inthepiping.Thischangedoesnotaffectthesafetyanalysisanddoesnotconstitute anunreviewed safetyquestion.

~g(7858G)

SAFETYEVALUATION REPORTSUIOIARYSERNo.:88-058SERTitle:Circulating HaterGateValveMid-Position Indication

~System:Circulating HaterSystem(CHS)FSARSectionsAffected:

F10.4-7d,10.4-8,Sh.8,10.4-8,Sh.9Description:

Incorporation ofModification PN2Y88MX070.

Thismodification providesmidpositionindication forthecirculating watergatevalvestofacilitate operation ofthevalvesinthezoningmodeofthecoolingtower.Theadditional valvepositionindication isprovidedontherevisedSARfigures.ThisQiangeenhancessystemoperation andwillnotaffectthesafetyanalysis.

Therefore thismodification willnotconstitute anunreviewed safetyquestion.

(7858G) 0 SAFETYEVALUATION REPORTSUMMARYSERNo.:8&-064,Rev.2SERTitle:ChicagoFluidPowerActuatorUpgrade,System:VariousFSARSectionsAffected:

F9.3-lbDescription:

Incorporation ofModification PNZY&&MX064.

Thismodification incorporates changestoairsupplyequipment to'hicago FluidPowerActuators intheAuxiliary Steam,Turb)neAuxiliary, andMoistureSeparator ReheaterSystems.Thisisduetohighlevelofrepairandmaintenance requiredontheseactuators-.

Thesecomponents donotperformanysafetyfunctions andtherewillnotbeanimpacttothesafetyanalysis.

Therefore thismodification doesnotconstitute anunreviewed safetyquestion.

(785&G)

.~

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-068SERTitle:ReactorBuildingHVACFanInterlocks

.System:ReactorBuildingVentilation (HVR)FSARSectionsAffected:

F9.4-9,Sh.1,9.4-9,Sh.2,9.4-9,Sh.3Description:

Incorporation ofModification PN2Y88MX043.

Thismodification addsinterlocks betweentheoperating ReactorBuildingVentilation Fans,bothsupplyandexhaust,andtheirassociated discharge dampers.Thesewillcausethedamperstogofullyclosedifitsassociated fanshouldfailtostart.Thiswillpreventarecirculation flowpathandpossibleimproperairflowthroughtheReactorBuilding, resulting inexhaustfantripsandGTSinitiation, ifthefansfailtostart.Thiswillenhancesystemoperation andnotaffectthesafetyanalysis.

Therefore thiswillnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATlON REPORTSUMMARYSERNo.:88-069,Rev.1SERTitle:ReactorBuildingHVACLowFlowOverrideSwitch,System:ReactorBuildingVentilation (HVR)FSAR.SectionsAffected:

F9.4-9,Sh.5,9.4-9(New)Description:

Incorporation ofModification PN2YSSMX053.

Thismodification provides-alowflowoverrideswitchfortheReactorBuildingHVAC.Thisreplacesanexistingpushbuttonfor"thesamepurpose.Theswitchwillbeusedduringfanmanipulations untilnormalflowhasbeenestablished andpreventinadvertent isolations oftheHVRsystemduetolowflowconditions.

Thismodification doesnotaffectthesafetyanalysisanddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUNNARYSERNo.:88-070SERTitle:C02TankRoomPlatformSystem:N/AFSARSectionsAffected:

F1.2-8,Sh.1,12.3-8,12.3-41Description:

Incorporation ofHodification PN2Y86MXlll.

Thismodification providesanaccessplatformfromtheHotwaterequipment areatotheC02TankRoom.Thisistoenhancepersonalsafetyandreplacetheuseofaladdertogainaccess.Thiswillnotaffectthesafetyanalysisanddoesnotconstitute anunreviewed safetyquestion.

(7858G) 0 SERNo.:8&-071SAFETYEVALUATION REPORTSUNMARYSERTitle:ReactorRecirculation PumpSealReplacement System:ReactorRecirculation System(RCS)FSARSectionsAffected:

T5.2-5,Sh.4Description:

Incorporation ofHodification PN2Y&7HX157.

Thismodification providesareplacement mechanical shaftsealassemblyfortheReactorRecirculation pumps.Thisisduetothehighfailurerateoftheexistingtypeofsealassemblyandunavailability ofreplacement parts.Additional changestothe.sealstagingflowwillalsobemade.Thereplacement sealmeetsorexceedstherequirements oftheoriginalsealandtherefore doesnotconstitute anunreviewed safetyquestion.

OO(785&G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-073SERTitle:ReactorBuildingHVACSurveillance TestSwitches,System:ReactorBuildingVentilation (HVR)FSARSectionsAffected:

P9.4-32,F9.4-9,sh.5,9.4-9,Sh.10Description:

Incorporation ofModification PN2Y88HX042.

Thismodification providesabypasstestswitchforthehighradiation isolation ontheReactorBuildingVentilation System.Thisistoreplace)umpersusedduringsurveillance testingandwillenhance'personal safetyandreduceunintentional isolations that~have occurredduringtesting.Thismodification doesnotaffectthesafetyanalysisanddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUNDRYSERNo.:88-078,Rev.1SERTitle:AddCondenser NeckSpraySystem.System:Condensate SystemFSARSectionsAffected:

F10.1-5a,10.1-5b,10.1-3kDescription:

Incorporation ofModification PN2Y88MX037.

Thismodification providesacoolingsystemtothecondenser neckareatobeusedwhensteamisdumpeddirectlytothemaincondenser.

Thiswi11helpinreducinghigherthannormalexhausthoodtemperatures andpreventturbinetripsfromthiscondition.

Waterwillbeutilizedfromthecondensate systemforcoolingwhensteamfromthebypassvalvesisdumpedtothemaincondenser.

Thismodification doesnotaffectanysafetyfunctions orimpactthesafetyanalysis.

Therefore, thisdoesnotconstitute anunreviewed safetyquestion.

'I(7858G)

SAFETYEVALUATIONREPORTSENARYSERNo.:88-080SERTitle:PositionIndication forRCICValvesSystem:ReactorCoreIsolation Cooling(ICS)FSARSectionsAffected:

F5.4-9b,5.4-9dDescription:

Incorporation ofModification PN2Y88HX102.

Thismodification providespositionindication fortheRCICpumptestbypassvalvetocondensate storagetankandtheRCICpumpturbinegoverning valve.Thispositionindication wi11berecordedontheGETARSsystemforuseduringsurveillance testing.Thisg.llnotaffectsystemperformance oranysafetyfunctions.

Therefore, thismodification doesnotconstitute anunreviewed safetyquestion.

E,~.(7858G)

SAFETYEVALUATiON REPORTSUMMARYSERNo.:88-081SERTitle:DieselFuelOilSpillPrevention System.System:DieselBuildingDrainSystem(DFD)FSARSectionsAffected:

F9.3-12bDescription:

Incorporation ofModification PN2Y88MX050.

Thismodification providesafueloilspillcontainment areaatthedieselfueloilfilllocationoutsidetheDieselGenerator Building.

ThisincludesaconcretepadtocontainaspillandpipingtoremovewaterfromthepadareaanddirectittotheDieselBUildingDrainSystem.Thismodification

.isinresponsetoanEnvironmental Protection Agency(EPA)inspection.

Thismodification complieswithEPArequirements anddoesnotaffectthesafetyanalysis.

Therefore, thischangedoesnotconstitute anunreviewed safetyquestion.

(7858G) 0 SAFETYEVALUATION REPORTSUMMARYSERNo.:88-086,Rev.2,88-065,Rev.1SERTitle:NineMilePointNuclearDivisionOrganization asofMarch1989System:NAFSARSectionsAffected:

P13.5-1,13.5-2,13.5-3,13.5-3a,13.5-4,13.5-5,13.5-6,13.5-7,T13.5-1,Sh.1,13.5-1a(Deletion) 13.5-3,Sh.1,13.5-3,Sh.2,T13.5-4,13.5-6,Sh.2,13.5-6,sh.3,13.5-6,Sh.4,P1.10-19*,

1.10-19a*,

1.10-33*,

1.10-33a*,

13.4-1*,13.4-2*,13.4-2a',

13.4-2b*,

13.4-3*,F13.4-1*,P1.10-16*,

1.10-9*,9A.3-la,9A.3-2,9A.3-3,Section13.1(exceptTable13.1-4)*,

T13.4-1*,13.4-2,Sh.1*,13.'4-2,'Sh.

2*,13.4-3,Sh.1*,13.4-3,Sh.2*,T13.4-35,Sh.3*Description:

Thisevaluation addresses changesintheNineMilePointNuclearDivisionorganization asofMarch1989.Thisincludesorganizational changesmadeinSeptember, 1988.Thesechangeshavenoimpactonthesafetyanalysisandwillnotconstitute anunreviewed safetyquestion.

  • Rev.0Changes(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:88-087SERTitle:RelocateOffGasFreezeOutDryerLevelControlSystem:OffGasSystem(OFG)FSARSectionsAffected:

F11.3-1bDescription:

Incorporation ofModification PN2Y88MX077.

Thismodification removedtheexistinglevelcontrolinstrumentation fortheOffGasFreezeOutOryersandinstalled anewdrainreceiving tankanddischarge pumpwithassociated instrumentation andcontrols.

Thiscorrectslevelcontrolproblemswithcollected moistureandpreventssysteminefficiencies createdbytheoldinstruments.

Thisdoesnotaffectanysafetyfunctionorthesafetyanalysis.

Therefore, thismodification doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATiON REPORTSUNMARYSERNo.:89-003SERTitle:CorrectandClarifyClassification ofFireBarriers.System:FireProtection FSARSectionsAffected:

F9A.3-3,9A.3-4,9A.3-5,9A,3-6Description:

Theevaluation correctsdiscrepancies identified betweentheFSARfiguresidentifying firebarriersandactualplantconditions.

Nochangestotheplantwererequired.

Thisdoesnotaffectthesafeshutdownanalysisanddoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATlON REPORTSUGARYSERNo.:89-006(Unit1SE¹)SERTitle:VicePresident QAReporting toExecutive VP-Nuclear Operations

.System:N/AFSARSectionsAffected:

P13.1-2,F13.1-1,13.1-1a,13.1-2Description:

Thisevaluation addresses thechangeinreporting levelfortheVicePresident-Quality Assurance.

Thischangedoesnotaffectanysafetyfunctions orthesafetyanalysis.

Thisdoesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:89-008,Rev.5SERTitle:ServiceWaterSystemDivisional Separation Logic.System:ServiceWaterSystem(SWP)FSARSectionsAffected:

F9.2-2,Sh.6,9.2-2,Sh.10,9.2-2,Sh.25,9.2-1h,P9.2-7,9B.8-3,9B.8-5,T9B.8-3,Sh.13Oescription:Incorporation ofHodificationPN2Y89MX030.

Thismodification provideschangestothecontrolcircuitsofservicewatervalvestosatisfysinglefailurecriteriaonafullloopandpartialloop.Thesechangeshelpmaintainservicewateroperability duringaccidentandtransient conditions.

Thishelpstomaintaintherequiredconditions forsafeshutdownandwillnotaffectthesafetyanalysis.

Therefore, thismodification doesnotconstitute anunreviewed safetyquestion.

(7858G)

SAFETYEVALUATIONREPORTSUMMARYSERNo.:89-012SERTitte:HighLevelAnnunciator Alarmfor2LHS-TK30

-System:LiquidRadioactive HasteSystem(LHS)FSARSectionsAffected:

F11.2-1]Description:

Thisevaluation addresses softwarechangesthatweremadetotheLHS(LiquidRadioactive Haste)computertoalarmacommonannunciator on,ahighlevelintank2LHS-TK30.

ThischangedoesnotchangethefunctionoftheLHSsystemoraffectanysafetyfunctions.

Therefore, thischangedoesnotconstitute anutireviewed safetyquestion.

(7858G)

SAFETYEVALUATION REPORTSUNMARYSERNo.:89-018SERTitle:Isolation Valves2RCS*SOV104/105 tobeintheNormallyOpenPositionSystem:ReactorRecirculation System(RCS)FSARSectionsAffected:

F5.4-2bDescription:

Thisevaluation identifies thecorrection toUSARFigure5.4-2btocorrectly reflectthenormalpositionof2RCS*SOV104/105.

Thesevalvesarenormallyopentoenablecontinuous monitoring ofrectorcoolantchemistry.

Thenormalpositionofthesevalveswasinadvertently changedinUSAR,Rev.0toindicateanormallyclosedposition.

Thischangecorrectsthatindication.

Nophysicalchangestotheplantormethodsofoperation resultedfromthischange.Therefore, thiscorrection doesnotconstitute anunreviewed safetyquestion.

(7858G)

Attachment 6SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:89"031,Revision1Incorporation ofNUREG"0313, Technical ReportonMaterialSelection andProcessing Guidelines forBWRCoolantPressureBoundaryPiping,Revision2CriteriaintotheLicensing BasisSYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

NASections5.2.3.4.1; 1.13Thischangeincorporates thecriteriaofRevision2toNUREG-0313, Technical ReportonMaterialSelection andProcessing Guildelines forBWRCoolantPressureBoundaryPiping,intothelicensing basis,USARSec-tion5.2.3.4.1.

Inaddition, afieldweldhasbeennotedasanexception totheNUREG-0313 criteriaandwillreceiveaugmented examination.

ThischangeresultedinplantTechnical Specification andInser-viceInspection (ISI)programchanges.TheTechnical Specification changewasapprovedbytheNRCbylet-terdatedJune14,1989.Thischangeestablishes requirements consistent withNUREG-0313, Revision2,toenhancemitigatic.:

ofintergranular stresscorrosion crackingandtherefore doesnotconstitute unreviewed safetyquestions.

4436-176720183-HC4

Attachment 5SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:89"032Incorporation ofMainSteamIsolation Valve(MSIV)ClosureAssistDescription andAssociated LeakTestingIntotheLicensing BasisSYSTEM:NAUSARSECTIONSAFFECTED:

DESCRIPTION:

Section5.4.5.2a~~">ThisUSARchangerevisestheUSARtoincludeanMSIVspringclosureassistdescription andacommitment toperformassociated leaktightness testing.ThischangeisaresultofGeneralElectric(GE)ReportNo.PED-01-0189 andassociated GESIL477.Thischangedoesnotchangethecurrentplantdesignandhasnoimpactonanalytical resultsorprocedures exceptforISI/ISTprogramprocedures foradditional testing,whichsupportsnuclearsafety.Therefore, thischangedoesnotconstitute anunreviewed safetyquestion.

4476-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:USAR,SECTIONS AFFECTED:

DESCRIPTION:

89-033USARClarifications andEditorial Corrections NA1.Section9.4.6.52.FailureModesandEffectsAnalysis'(FMEA)Sec-tion4.4,Table4-1,AppendixA,andAppendixBThechangestotheUSARsectionandtheUSARFailureModesandEffectsAnalysisarearesultofidentify-ingclarifications, typographic errors,andeditorial discrepancies oromissions discovered duringreviewoftheUSARRevision0,April1989submission.

Thereviewconcluded thatthechangesdonotconstitute anyunreviewed safetyquestions.

5029-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:89-034Miscellaneous Editorial ChangestotheUSARNAUSARSECTIONSAFFECTED:

Figures9.4-5,Sheet8;6.2-70,Sheet21;9.2-4,Sheet6;9.4-11,Sheet5y8'lip8'3ySheet2yFigure9.3-7,Sheet4;Table2.3-4A;Chapter14,ListofTables;98.8.2.2DESCRIPTION:

Theseeditorial changesrevisetheUSARsectionslisted.Thesechangesrevisevarioussystemlogicdiagrams, theplantmasterone"linediagram,andvar-iousUSARpageswhichwereinadvertently deleted.Thesechangesareeditorial innatureandhavenoim-pactonplantsafetyand,therefore, donotconsti-tuteanunreviewed safetyquestion.

5036-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:~~89-035SYSTEMUSARSECTIONSAFFECTED:

NAPage3B-ll;Table3B-7;Figure.3B-1,Sheet2;andFigure3B-2,Sheet2DESCRIPTION:

Editorial typographical and/orclarification changeshavebeenmadetotheaboveUSARpages,table,andfigures.Thesechangesweremadetocorrectthe'ex-istingUSARsothatitisconsistent withthedesigncalculations.

Thismodification doesnotinvolvetheplantdesignbasis,procedures, oranalysesanddoesnotconstitute anunreviewed safetyquestion.

5035-176720183"HC4

Attachment 8SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

89-038Revisions toUSARTable9.4-1NAUSARTable9.4-1,pages1,2,and3ThisSERdocuments changestoUSARTable9.4-1.Thefoot-notedescribing thedesignbasisformaximumindoortem-peratures forsafety-related equipment wasexpandedtoinclude"andthesummeroutdoor'design maximumtemperature of100'Fdrybulband73'Fwetbulb."Added"cablechasesandcorridors" underthecontrolbuildingel261ftasaseparateareaonpage1ofthetabletoreflectthein-creasefrom104'Fto110'Finsidedesignmaximumtempera-turefortheseareas.Theincreaseinindoortemperature isaresultofusingthehigheroutdoorairtemperature asadesignbasis.Thesechangesprovidegreaterflexibility forplantopera-tionbyrevisingacceptable temperature ranges.Thein-creaseintheplantoutsideairdesigntemperature from.93'Fto100'Fprovidesreasonable assurance thattheout-doorambienttemperature willnotresultinaplantshut-downinthefuture.Thischangewillnotincreasetheprobability ofequipment malfunction orfailure,sincethesafety-related equipment locatedinthecontrolbuildingel261ftcablechasesandcorridors arequalified fortheambientconditions whichwererevisedfrom104'Fto110'F.Thesechangeshavenoimpactonplantsafetyandtherefore donotconstitute anunreviewed safetyquestion.

5053-176720183"HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM'SAR SECTIONSAFFECTED:

DESCRIPTION:

89-039Miscellaneous ChangestotheUSARNAFigures9.2-7(Sheet9)and11.4-1aInordertoeliminate anuisancealarmcausedbyhighambienttemperatures, thewatertreatment systemcausticstoragetankhightemperature switchsetpointwasincreased from80'Fto90'F,(Figure9.2-7,Sheet9).Atthisnewsetting,thehightemperature switchwillcontinuetoperformitsdesignfunctionwhichistoprovideindication ofoverheating bythetank'splateheatingcoil.Tworadioactive solidwastesystemcheckvalvesym-bolswererevisedfrom"socketweld"to"flanged" endconnections astheresultofachangeinvalvetype(pistonchecktoswingcheck).Thechangewasmadetominimizethepotential forvalvefailureduetoparticles presentinthesystemfluidandtofacili-tatevalveremovalformaintenance.

Thedesignfunc-tionofthesevalvesremainsunchanged.

Thesechangesarewithinthedesignbasisoftheplantanddonotaffectanysafetyfunctions oranal-ysis,andtherefore donotconstitute anunreviewed safetyquestion.

5063-176720183-HC4 00 Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:89-040UpdatetoUSARFailureModesandEffectsAnalysis(FMEA)Volumes1and2toApril1989As-BuiltDesignLevelSYSTEM:USARSECTIONSAFFECTED:

VariousSafety-Related SystemsFailureModesandEffectsAnalysis(FMEA)Volumes1and2DESCRIPTION:

ChangesweremadeasfollowstotheUSARfortheFMEAwhichhasbeenupdatedtotheas-builtdesignlevel,effective April30,1989.Sections4and5ofFMEA,Volume1,havebeenchangedtoreflecttheupdatedFMEA.Thischangeincludeseditorial corrections, clarifications, an'pdatedlistofreference documents, andadescription offindingswithresolutions.

Appendixes AandBinFMEA,Volumes1and2,havehadsectionsreplacedbynewprintouts reflecting theupdatetot;heApril30,1989,as-builtdesignlevel.TheFMEAdemonstrates NMP2BOP,BOP/NSSSinterface, electrical powersupplyanddistribution systemscom-pliancewiththesingle-failure criterion asrequiredbyIEEE279-1971andIEEE308-1978.

Therefore, thesechangestotheUSARdonotconsti-tuteanunreviewed safetyquestion.

5108-176720183"HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:89.-049Editorial ChangestoUSARSection11.4Regarding LowSpecificActivity(LSA)MaterialSYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

Solid'WasteManagement SystemSection11.4.Theseeditorial changestotheUSAR,textandTable11.4-1aremadetocorrecteditorial discrep-anciesthatwereidentified inthereviewoftheUSARRevision0update.Theseareeditorial changesnotaffecting plantdesignorprocedures and,therefore, donotconstitute anunreviewed safetyquestion.

5120-176720183'"HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNo.:89"050SERTITLE:RevisiontoHPCSDieselGenerator CoolingSystemLogicSYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

HPCSDieselGenerator CoolingFigure9.5-41,Sheet8ofllUSARFigure9.5-41,Sheet8ofll,hasbeenrevisedtochangethesetpointforthedieselgenerator cool-ingwaterlowpressure, thetimedelaysforthisalarmandthelogicwhichdepictsthealarmfunction.

Thesechangeshavenoadverseimpactonplantsafetyandreflecttheas-builtdesignoftheplant.There-fore,theydonotconstitute anunreviewed safetyquestion.

5124-176720183-HC4

SAFETYEVALUATION REPORTSUNMARYSERNo.:89-055,Rev.1SERTitle:Resolution ofGeneralItemsandTypographical ErrorsforUpdatedSAR,Revision1System:N/AFSARSectionsAffected:

P12.5-1,P12.5-4,P7.1-7a,6.2-55b,8.3-8,8.3-9,T12.5-1,P6.2-88a,15.6-13,T15.7-5,15.7-16,Sh.1,15.7-17,Sh.1,F10.1-5d,5.4-13d,6.2-70,Sh,34,T15.0-1,Sh.1,15.0-1,Sh.2,15.0-1,Sh.3,P2.4-22,F9.3-1c,9.3-1g,T6A.9-1,9.4-1,Sh.3,15.6-13,Sh.9,P9A,3-42a, T9A.3-5,9A.3-10,Sh.1,98.8-2,Sh.38b,P2.5-171,3.9A-14,6.2-43a,6.2-53,T6.2-54,P9.5-27,T3.9A-12,Sh.17,T6.2-55C,Sh.1Description:

Thisevaluation addresses omissions, unintentional additions, typographical errors,printingerrorsandresolution ofcommentsthatresultedfromRevision0oftheUpdatedSafetyAnalysisReport(USAR).Thesechanges,donotaffectthedesignbasisorthesafeoperation orshutdownoftheplant.Therefore,

'thisdoesnotconstitute anunreviewed safetyquestion...

(7858G)

SAFETYEVALUATION REPORTSUMMARYSERHo.:89-056SERTitle:USARFireProtection Update.System:F,ireProtection FSARSectionsAffected:

P9A-iii,9A.3-4,9.5-7,9A.3-7a,9A.3-8,9A.3-10,9A.3-17,9A.3-42,T9A.3-4,Sh.2,9A.3-4,Sh.4,9A.3-4,Sh.5,9A.3-4,Sh.3,9A.3-1,Sh.2,9A.3-1,Sh.3,9A.3-2,Sh.2,9A.3-3,Sh.1,9A.3-4,Sh.6,9A.3-6,Sh.2,9A.3-6,Sh.3,9A.3-6,Sh.4,9A.3-8,Sh.2,9A.3-9,Sh.9A.3-9,Sh.2,9A.3-9,Sh.3,9A.3-10,Sh.1,9A.3-19,F9A.3-1Description:

TIO"sevaluation documents therevisions necessary totheUSARtoreflectthesourcedocuments usedinestablishing,and maintaining thefireprotection systemsasrequired.

Therevisions totheUSARdfdnotrequirephysicalchangestotheplantanddonotadversely affectthesafeshutdownorfireprotection analysis<Appendix R).Therefore, thesechangesdonot.constitute anunreviewed safetyquestion.

<7858G)

SAFETYEVALUATION REPORTSUMMARYSERNo.:89-058SERTitle:USARFireProtection UpdateSystem:FireProtection FSARSectionsAffected:

P9A.3-16,9A.3-17,9A.3-40,9A.3-41,9A.3-4la, 9A.3-4lb, 9A.3-52Description:

Thisevaluation documents revisions necessary totheUSARtoreflectthesourcedocuments usedinestablishing andmaintaining thefireprotection systemsasrequired.

Therevisions totheUSARdidnotrequirephysicalchangestotheplantanddonotadversely affectthesafeshutdownorfireprotectionmnalysis (Appendix R).Therefore, thesechangesdonotconstitute anunreviewed safetyquestion.

(7858G)

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:USARSECTIONSAFFECTED:

88U-300,Revision1Editorial ChangestotheUSARNASection10.4.6.2.2 andFigures6.2-70,Sheet1,and9.4-1CDESCRIPTION:

ThesechangesaremadetotheUSARsectionandfig-urestoestablish consistency withpreviously issuedUSARchanges.(LDCNs)thatareaddressed bySafetyEvaluation (SE)Nos.87-007,88U"129,and88U-282.Sincethesechangesarebeingmadeforconsistency withpreviously issuedLDCNsthatareaddressed bySEs,theyareeditorial anddonotaffecttheplantdesignorprocedures.

Therefore, theydonotconsti-tuteanunreviewed safetyquestion.

4479-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.SERTITLE:SYSTEM:88U-301TurbineTripTransient AnalysisNAUSARSECTIONSAFFECTED:

Section15.2.3.2.1 DESCRIPTION:

ThischangerevisesUSARSection1S.2.3.2.1 toincludetheresultsoftheTurbineTripTransient Analysisconsidering theunavailability offeed"watersystemflowtothereactorvesselimmediately following thetrip.TheeventresultsshowtheexistingUSARanalysisisbounding.

There-fore,thischangedoesnotconstitute anunreviewed safetyquestion.

4449-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO~:SERTITLE:SYSTEM:88U-302,Revision1Editorial ChangestotheUSARNAUSARSECTIONSAFFECTED:

Sections6.2.3.4,7.3.2.1.3, 7.4.2.2.4, 7.6.2.4.4, and14.2.7;Tables1.6-1,Sheet7,and1.8"1,Sheets64and161;page11.4-3aThefollowing editorial changesweremadetotheUSARSectionandtablesnoted:1.USARsectioncross<<references wereadded.2.Additional reference documents wereadded.3.Clarifications wereaddedtodistinguish testpersonnel qualifications duringplantdesign,construction, testing,andoperation phases.4.Revisedreference documents andmadeeditorial changes.Thesewereeditorial changesnotaffecting plantdesignorprocedures andtherefore donotconstitute anunreviewed safetyquestion.

5119-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTCHANGEDESCRIPTION SERNO.!SERTITLE:SYSTEM:FSARSECTIONSAFFECTED:

DESCRIPTION:

88U-304,Revision1USARTextClarifications NAFigure7.3-10,Sheet1of2;Page1.10-61;Page15E.3-4;Page15E.3-6;Table7.3"17,15of16;Table7.3-17,16of16;Page7.7-9;Page9.5-8;Page4A-1;Page3.9B-13;Page8.2-22Editorial andtypographical changesveremadetotheabovepages,tables,andfigures.Thesetypesof,changesareconsidered necessary toaccurately represent theactualdesignoftheplant.Thereisnoimpacttoplantdesignbasis,physicalarrangement, orprocedures andthusthesechangesdonotrepresent anunreviewed safetyquestion.

5006-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO,:SERTITLE:88U-'05UpdateofRadiation Source,TermandDoseRateTablesinUSARChapters12and15SYSTEM:USARSECTIONSAFFECTED:

Radiation SourcesTables12.2-4,Sheet3;12.2-6,Sheet1;12.2-7,Sheet2;12.2.-9;12.2-10,Sheets1,2,3;12.2-12,Sheets1,2,3;12.2-13,Sheets1and2;12.3-4,Sheets1'and2;15.7-10DESCRIPTION:

ChangesweremadeasfollowstotheUSARforradia-tionsources.TheRWCUsourcetermwasrevisedtoaccurately reflectthoseusedinradiological anal-ysesandthesupporting radiation protection sourcecalculation',

thetitleofTable12.2-6ischangedtoaccurately reflectthecontentofthetable;spentfuelpoolcoolingandcleanupsystemsourceactivi-tieswererevisedtoincludeisotopespreviously neglected; TheN-16activities inequipment intheturbinebuildingarerevisedtobe'onsistent with-thesupporting radiological analysesandcalculation; thecondensate systemsourceterm,liquidradwastesystemcomponents activities, andsolidradwastesystemcomponents activities areallrevisedtopro-videconsistency withthesupporting radiological calculations; thepost-LOCA gammadoseratesinTable12.3-4arerevisedtomakethemconsistent withradiological calculations; andtheairborneactivityinthereactorbuildingduetoafuelhandlingaccidentisrevisedtocorrectatypographical errorintheI-135isotopicactivity.

Thismodification doesnotinvolvetheplantdesignbasis,procedures, oranalysesresults,anddoesnotconstitute anunreviewed safetyquestion.

4475-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SER,TITLE:

SYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

88U-306ResidualHeatRemovalSystemModifications ResidualHeatRemoval(RHR)Figure5.4-14,Sheet3Thischangerevisesthedesignpressureandtemperature ofcertainpor-tionsoftheresidualheatremovalsystem(RHS).Thesechangesarecon-sistentwithplantsystemdesigndocuments andreflectmaximumanticipa-tedoperating conditions.

Therevisedconditions arewithinthedesigncapabilities of-theRHSpipingandcomponents anddonotimpactthephysicaldesignoftheRHSsystem.Therefore, thischangedoesnotconstitute anunreviewed safetyquestion.

4491-116720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO~:SERTITLE:SYSTEM:88U"308Editorial ChangestotheUSARStandbyDieselGenerator FuelOilStorageandTransferSystem(EGF);Equipment Qualification USARSECTIONSAFFECTED:

Figures9.5-40b,9.5-41,Sheet2of11~,andpages3.11-4and3.11-7DESCRIPTION:

Thisevaluation addresses theeditorial andclarifica-tionsfortheUSARupdate.ThesechangesupdatetheUSAR,anddonotchange/modify anystructure, system,component, testorexperiment.

Thereviewconcluded thatthechangesdonotconstitute anyunreviewed safetyquestions.

  • ChangedinRevision0.5020-.176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO~.'ERTITLE:88U-309USARTable8.3-4UpdateSYSTEM'SAR SECTIONSAFFECTED:

Safety-Related Electrical LoadsTable8.3-4,Sheets1and30DESCRIPTION:

Thismodification describes

'achangetoUSARTable8.3-4toagreewiththeplantas-builtconditions fortheClass1Esafety-related loads.Thechangein-volvedrevisionofthelockedrotorcurrentofunitcoolers2HVC*UC108A andBfrom84.0to64.3amperes.5019-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:88U-310USARTABLE7'-3UPDATESYSTEM:LEAKDETECTION SYSTEMUSARSECTIONSAFFECTED:

TABLE7.6-3,Sheet2DESCRIPTION:

Thismodification describes achangetoUSARTable7.6-3,page2of2,toagreewiththeplantas"builtconditions fortherangeoftemperature switchesE31"N622A andB.Thechangeinvolvedrevisionoftheinstrument "rangefrom"0-350'F" to"50-350'F."

Also,footnote(1)waseditorially revisedtoreadfrom"Chapter16"to"the.Technical Specifications."

5032-176720183-HC4

SAFETYEVALUATION REPORTSUMMARYAttachment 4SERNO.:TITLE:SYSTEM:88U-311Editorial ChangestotheUSARServiceWaterSystemFSARSECTIONS.AFFECTED:

Tables9.2-1A,Sheets1,5,and6;9.2-1B,Sheets1and5;and9.2-2,Sheets1,5,and9'ESCRIPTION:

ThesechangestotheUSARtablesarearesultofaneditorial omissiondiscovered duringthereviewofSER88U-014,Revision0,ServiceWaterSystemModifi-cations.Thechangetotheservicewaterflowre-quirements madeintheaffectedtablesisconsistent withthechangedescribed onSER88U-014toprovidecontinuous flowtofourofthesafety-related unitcoolersservingtheresidualheatremovalandlowpressurecorespraypumprooms.Therefore, these-changesupdatetheUSARtablestoincorporate apreviously approvedplantmodification.

Thereviewconcluded thatthechangesdonotconstitute anyunreviewed safetyquestions, 5018-176720183-HC4

Attachment 5SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:88U-312Instrument LineBreakandSpentFuelCaskDropAccident:

AnalysisSYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

NASection15.7.5,Tables15.6-1,Sheet2,and15.6-4USARTable15.6-4isrevisedtoincorporate changesinInstrument LineBreak,EAB,LPZ,andControlRoomdosesduetoarevisionofthesourcecalculation.

Atypo-graphical:

errorinTable15.6-1iscorrected.

Sec-tion15.7.5isrevisedtocorrecttheamountofI-131releasedtotheenvironments Thismodification doesnotinvolvetheplantdesignbasisorprocedures.

Itdoesnotadversely affectplantaccidentanalyses, andtherefore, doesnotconstitute anunreviewed safetyquestion.

5010-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:FSARSECTIONSAFFECTED:

DESCRIPTION:

88U-313USARMiscellaneous ChangesNAPage1.10-80;Table11.1-5;Table6A.10-7;Figures6A.10-11, 6A.10-12, and6A.10-13; Figure6.5-1,Sheet8;Page12.1-8,andTable6.2"56,Sheet2Editorial and/orclarification changeshavebeenmadetotheaboveaffectedUSARpages,tables,andfig-ures,including changestoequipment designatio'ns, radiological sourceterms,andsuppression pool'thermalanalysis.

Thechangesdonotrevisetheplantdesign,procedures, orresultsofanalysesandtherefore donotconstitute anunreviewed safetyquestion.

5045-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

88U-314RevisiontoReactorVesselSkirtAmbientTemperature NATable14.2-301, Sheet2ThischangerevisesUSARTable14.2-301toupdatethereactorvesselskirtambienttemperature tobeinagreement withtheGeneralElectricdesignbasis.Thischangedoesnotimpactanydesignbasisanalysesandisconsistent withtheNSSSproviders designcri-teria.Therefore, thischangedoesnotconstitute anunreviewed safetyquestion.

5014-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM!USARSECTIONSAFFECTED:

88U-316Editorial ChangestotheUSARNASections8.3.2.1.2, 9.5.6.2.2.3, and9.5.6.5;Table3.9A-12,Sheet4;andFigures6.2-72K,Sheet1and6.2-83DESCRIPTION:

Theseeditorial changestotheUSARtext,table,andfiguresareper-formedtocorrectcertaineditorial discrepancies thatwereidentified asaresultofreviewing theUSARRevision0update.Theseareeditorial changesnotaffecting plantdesignorprocedures andtherefore donotconstitute anunreviewed safetyquestion.

5012-176720183"HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNo.:88U"317SERTITLE:RevisiontoReactorBuildingClosedLoopCoolingWaterLogicDiagramSYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

ReactorBuildingClosedLoopCoolingWaterFigure9.2-4,Sheets1of12,3of12,and11*of12ThesechangesrevisetheUSARfigureslistedtore-visethereactorbuildingclosedloopcoolingwaterlowsuctionpressuresetpointtoprovideimprovedoperational flexibility, addanotethatthereactorrecirculation pumpscooleroutletvalveshavebeenrenderednonfunctional toreflectachangeincoolingphilosophy atthecoolers'n

addition, theinstru-mentaircompressor, waterexpansion tanklevelset-pointhasbeenrevised.Thesechangesdonotaffect.anysafetyanalysisorsafetyfunctions, andthere-foredonotconstitute anunreviewed safetyquestion.
  • ChangedinRevision05044-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

88U-318Editorial RevisiontoUSARFigure9.4-17Miscellaneous Buildings HVACSystems(HVY)Figure9.4-17,Sheet3ThechangestoUSARFigure9.4"17,Sheet3aretheresultofaninadvertent omissionrelatingtochangespreviously addressed onSER88U-118.Note2onUSARFigure9.4-17(Sheet3)wasrevisedtoremovethedemineralized waterstoragetankbuildingandaddthechillerbuildingtoagreewiththelogicshownandtherelatedtextdescription inUSARSec-tion9.4.7.5(page9.4-56)whichwaspreviously revisedbyLDCNsU-515andU-808andaddressed inSER88U-118.Thesechangesareeditorial innatureandhaveno"impactonplantsafetyandtherefore donotconstitute anunreviewed safetyquestion.

5041-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:88U-319USARTextClarification SYSTEM:VariousUSARSECTIONSAFFECTED:

DESCRIPTION:

Figure9.4-2b;Figure9.4-17,Sheets1of13and2of13;Table1.9-1,page7of11Editorial and/orclarification changeshavebeenmadetotheaboveaffectedUSARsections.

ThesechangesweremadetoenhancetheexistingUSARsothatitisconsistent withdesigndrawingsandprocurement spe-cifications.

Also,acompliance statement, whichwasinadvertently omitted,hasbeenaddedtoTable1.9toaddressNRCStandardReviewPlan9.1.2,SpentFuelStorage.Thischangedoesnotinvolveanyhardware,

analysis, orprocedure modification anddoesnotconstitute anunreviewed safetyquestion.

5051-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:88U"321USARFigure8.3-7,Editorial UpdateReactorProtection SystemUSARSECTIONSAFFECTED:

DESCRIPTION:

Figure8.3-7datedApril1989Changeshavebeenmadetotheabove-affected USARsectionsregarding thecircuitbreakertripratingsforthereactorprotection system.ThesechangesmaketheRPSovercurrent protection consistent withtheas-builtloadsandweremadetocorrecttheexistingUSARsothatitisconsistent withdesigndrawingsandprocurement specifications.

Thischangedoesnotinvolveanyhardwareorprocedure modifica-tionanddoesnotconstitute anunreviewed safetyquestion.

5065"176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNo.:SERTITLE:SYSTEM:88U-322Miscellaneous PIDChangesControlRodDriveSystemUSARSECTIONSAFFECTED:

Figures4.6-5a,9.4-3d,9.3-5e,9.3-5jDESCRIPTION:

Thischangedeletesapressureswitch,2RDS-PS105, whichhasnotbeeninstalled andwasneverintendedforuseatNMP2.Inaddition, editorial changestocontinuation flagshavebeenmade.Thesechangeshavenoadverseimpactonplantsafetyandtherefore donotconstitute anunreviewed safetyquestion.

5081-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

88U-324Editorial ChangetoUSARFigure9.3-12dMiscellaneous Drains(DFM)Figure9.3-12dThischangetoUSARFigure9.3-12distheresultofaninadvertent omission'n theengineering changedocumentinitiated torevisethisfigure'ssourcedocument.

Thischangetothescreenwell buildingmiscellaneous drainsystemsumppumpperformance isinagreement withthechangedescribed inSafetyEvaluation 87-121,whichevaluated thereplacement ofthesepumpstoaccommodate thewaterflowintotheassociated sumps.Therefore, thischangetoupdateUSARFigure9.3-12dincorporates apreviously ap-provedplantmodification.

Thereviewconcluded thatthechangedoesnotconstitut'e anyunreviewed safetyquestions.

5104"176720183-HC4

Attachment 4SERNO.:SERTITLE:SAFETYEVALUATION REPORTSUMMARY88U-325Miscellaneous ChangestoUSARFiguresSYSTEM'A'SARFIGURESAFFECTEDDESCRIPTION:

6.2-70(Sheets15,27,29,37,and41)9.2"7(Sheet9of12),and9.3"10c.Thissafetyevaluation addresses changesto.USARFigures'or theprimarycontainment isolation valvearrangements, turbinebuildingdrains,andthedemineralized makeupwatersystemlogicdiagram.Thechangesdescribed aretheresultofidentifying clar-ifications andeditorial revisions.

Thereviewconcluded thatthechangesdonotconstitute anyunreviewed safetyquestions.

5121-176720183-HC4

Attachment 4SAFETYEVALUATION REPORTSUMMARYSERNO.:SERTITLE:SYSTEM:88U-326USARTable7.5-1UpdateServiceWaterSystemUSARSECTIONSAFFECTED:

Table7;5-1,Sheets1and6DESCRIPTION:

ChangestoUSARTable7.5-1havebeenmadetoupdatetheUSARinordertobeconsistent withdesigndrawingsandspecifications andNMP2licensing commitments.

Thischangedoesnotinvolveanyhardwareorprocedure modifi-cationanddoesnotconstitute anunreviewed safetyquestion.

5125"176720183-HC4 0

(18~11~lid:albKW(.'HJC44RSM814Attachment 4SAFETYEVhWATION REPORTSUMMARYSERNo.SERTZTLB:SYSTEM:USARSECTIONSAFFECTED:

DESCRIPTION:

88U-328Editorial ChangestoVSARSection6.2,5,5HydrogenControlSystemUSARSection6.2.5.5Thischangedeletesastatement describing theoperation ofthecontrolsvitohforthehydrogenrecombkner coolingeaterstrainerblovdomvalves.Thischangeiseditorial innaturaandhasnoadverseimPactonylantsafetyandtherefore does.notconstitute anunrevised safetyquestion.

II

Retrieved from "https://kanterella.com/w/index.php?title=ML18038A770&oldid=731334"