ML17244A863

Forwards 30-day Response to IE Bulletin 79-17.No Leaks Found in safety-related Stainless Steel Piping Sys

ML17244A863
Person / Time
Site:	Ginna
Issue date:	08/24/1979
From:	WHITE L D ROCHESTER GAS & ELECTRIC CORP.
To:	GRIER B H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 7910030590
Download: ML17244A863 (12)

Text

ROCHESTER GASANDELECTRICCORPORATION 0z-::89EASTAVENUE,ROCHESTER, N.Y.I4649LEOND.WHITE.JR.VICEPIISSIDCHT tSI.SPECIE ASSACOCCtla546-2700August24,1979Mr.BoyceH.Grier,DirectorU.S.NuclearRegulatory Commission OfficeofInspection andEnforcement RegionI631ParkAvenueKingofPrussia,PA19406

Subject:

I8EBulletin79-17Thirty(30)DayResponseR.E.GinnaNuclearPowerPlant,Unit1DocketNo.50-244

DearMr.Grier:

Inaccordance withtherequirements ofI6EBulletin79-17,wehavepreparedathirty(30)dayresponseonthestagnantboratedwatersystemsatR.E.GinnaNuclearPowerPlant,Unit.1.Stagnantportionsofsystemsthatareaccessible duringnormalreactoroperation, wheresurfaceandvolumetric examinations havenotbeenpreviously performed, shallbeexaminedwithinthenextsixty(60)daysinaccordance withtherequirements ofItem2oftheBulletin.

Ifyouhaveanyfurtherquestions donothesitateincontacting us~Verytrulyyours,IIL.D.Whie,Jr.AEC:dmaF4 xc:DirectorDivisionofOperating ReactorsU.S.NuclearRegulatory Commission OfficeofInspection andEnforcement Washington, D.C.20555 ll R.E.GinnaNuclearPowerPlant,Unit1DocketNo.50-244Thirty(30)DayResponsetoI6EBulletin79-17PipeCracksinStagnantBoratedWaterSystemsatPWRPlantAugust24,19791.Thefollowing safetyrelatedstainless steelpipingsystemsasdelineated bytheRochester Gas&ElectricCorporation QualityAssurance Manualcontainstagnantoxygenated boratedwater.a.SafetyInjection System-ThisincludestheSafetyIn-jection(SI)PumpsuctionfromtheBoricAcidStorageTanksandtheSIPumpsdischarge fromvalves888A&Band871AGBtotheReactorCoolantSystemLoopsAGBHot,andColdLegs.b.Containment SpraySystem-ThisincludestheContainment SprayPumpsdischarge fromvalves868AGBtothespraypipinginsidecontainment attheelevation oftheCharcoalDousingSystemcheckvalves.c~ResidualHeatRemovalSystem-ThisincludestheResidualHeatRemovalPumpssuctionfromtheReactorCoolantSystemLoopAHotLegandContainment SumpBandtheRHRpumpsdischarge aftertheRHRHeatExchangers tothesuctionoftheSIPumps,fromPenetration P-111totheReactorCoolantSystemLoopBColdLegandtheSafetyInjection NozzlesontheReactorVessel.Alsofromthedischarge pipingarebranchconnections fortheResidualHeatRe-movalsampleandtotheLetdownsystem.d.Chemical6VolumeControlSystem-ThisincludestheportionofthissystemwhichprovideflowpathsforboricacidfromtheBoricAcidStorageTankstotheChargingPumpsuctionthroughvalvesV-350andV-356.e.Refueling WaterCirculating System-ThisincludespipingfromtheLetdownSystemtovalvesV-820andV-821.f.ReactorCoolantSystem-ThisincludesonlythePressurizer CodeSafetyValveloopseals.1a.Systempressuretests(hydro)andvisualexaminations inaccordance withtheASMEBGPVCode1974EditionSectionXIArticleIWA-5000havebeenperformed forallsystemsidenti-fiedabove.Thefollowing isalistingofthesesystemsandthedateofthetests.a.SafetyInjection System:*SuctionpipingDischarge piping5/13/775/6/77Page1of5

b.Containment SpraySystem:Suctionpiping(including NaOH)Discharge pipingc.ResidualHeatRemoval:*SuctionpipingDischarge piping(including samplepiping)Tie-intotheLetdownSystemd.Chemical6VolumeControlSystem:Immediate boratepathsV-350andV-356e.Refueling WaterCirculating System:Suction(letdowntoV-820)Discharge (V-821toletdown)5/13/775/16/773/5/793/5/795/7/773/18'/765/7/775/7/77f.ReactorCoolantSystem:Pressurizer SafetyValveLoopSeals4/29/78*NOTE-ThoseportionsofthesesystemswhichtieintotheReactorCoolantSystem(RCS)wereisolatedfromtheRCSduringtheirhydrotest.

Theremaining pipingtotheRCSwashydrotested duringtheRCShydrotest on4/29/78.Inaccordance withtheInservice Inspection ProgramfoundinRochester GasandElectric's QualityAssurance Manual,AppendixB,whichmeetstherequirements of10CFR50.55a(g),

surfaceandvolumetric examinations havebeenperformed ontheSafetyIn-jectionSystem,ResidualHeatRemovalSystemandthePressurizer SafetyValveloopseals.Surfaceandvolumetric examinations arenotperformed ontheContainment SpraySystem,ChemicalandVolumeControlSystems,theRefueling WaterCirculating SystemandportionsoftheSafetyInjection Systemforthefollowing reasons:a.Containment SpraySystems-Thisportionofthesystemareexemptedcomponents asallowedbytheASMEBGPVCode1974EditionSectionXIArticlesIWC-1220.

b.Chemical6VolumeControlSystem-Theportionsofthissystemareexemptedcomponents asallowedbytheASMEB&PVCode1974EditionSectionXIArticlesIWC-1220andarenotwithinthescopeofArticleIWD-2600.

c.Refueling WaterCirculating System-TheportionsofthissystemarenotwithinthescopeoftheASMEBGPVCode1974EditionSectionXIArticleIWD-2600.

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d.SafetyInjection System-Theportionsincludethe3"and4"discharge pipingwhichareexemptedcomponents bytheASMEBGPVCode1974EditionSectionXIArticleIWC-1220.

Thefollowing isasummaryofinservice inspection, visual,surfaceandvolumetric examinations performed ontheSafetyInjection System,ResidualHeatRemovalSystemandthePressurizer SafetyValveLoopSealswithinthe10yearperiodfrom1970to1979.Theseexami-nationshavebeencategorized bylowpressure/high pressure(suction/discharge) andbypipesize..a.SafetyInjection LowPressure:

8II10"HighPressure:

2IIVisual20welds'1weld13weldsSurfaceandVolumetric 65RT's,85weldsUT's9welds1weldb.ResidualHeatRemoval:LowPressure:

6II8li10"HighPressure:

41I6Tl8II10"Visual01weld14welds04welds1weld3weldsSurfaceandVolumetric 2welds3welds28welds2welds15welds11welds12weldsc~SafetyLine4IIPressurizer SafetyValveLoopSeals:SurfaceandVisualVolumetric 3welds.5weldsTheseinservice examinations wereconducted inaccordance withtheASMEBoilerandPressureVesselCodeJuly1,1974,EditionsofSectionsVandXIthroughtheSummer1975Addenda.Thiswouldincludetheprocedure qualification requirements andacceptance criteria.

However,onOctober8,1976aleakwasdetectedinasectionof8"Schedule10stainless steelpipeasreportedinLER76-24onOctober11,1976.Thisleakresultedinultrasonic examination beingperformed on75weldsintheaffectedsystem.Theprocedures andtechniques usedwerequalified andverifiedoncrackedpipingwhich'had beenremovedfromserviceandutilizedasatestmock-up.Severalotherweldsinrelatedsystemswerealsoexaminedwithnofurtherproblemsfound.Corrective actiononthecracksfoundbothfromleakageandultra-sonicexaminations werelistedinLER76-24onOctober11,1976andsupplemented reportsonOctober22,1979,December21,1976,February10,1977andJune8,1977.Page3of5

~~1b.Certainportionsofthosesystemidentified aboveareinter-mittently stagnantandarerecirculated onamonthlybasisorhaveflowoccuringonaquarterly basiswithwaterfromtheRefueling WaterStorageTank.Thesesystemsareasfollows:a.SafetyXnjection System-ThisincludesthesuctionfromtheRefueling WaterStorageTankthroughtheSlPumpstotheRefueling WaterStorageTank,whichisrecirculated onamonthlybasis.b.Containment SpraySystem-Thisincludesthesuctionfrom'heRefueling WaterStorageTankthroughtheCSPumpstotheRefueling WaterStorageTank,whichisrecirculated onamonthlybasis.c.ResidualHeatRemovalSystem-ThisincludesthesuctionfromtheRefueling WaterStorageTankthroughtheRHRPumpsandRHRHeatExchangers totheRefueling WaterStorageTank,whichisrecirculated onamonthlybasis.d.Chemical8VolumeControlSystem-ThisincludesthepipingfromtheRefueling WaterStorageTankthroughvalveAOV-112BtothesuctionogtheChargingPumps.whichreceivesflowduringthequarterly testingofAOV-112B.

Chemistry controlsfortheRefueling WaterStorageTankandtheBoricAcidStorageTanksfollows:a.Refueling WaterStorageTank(RWST):Thechemistry oftheRWSTiscontrolled byuseofthespentfuelpitdemineralizer.

Priortoandaftereachrefueling theRWSTisnormallyrecirculated tobringtheCl6Fwithinspecification.

TheWestinghouse specifi-cationswere0.5ppmC1and0.15ppmF.Thenewlimitsare0.15ppmforbothClSF.WehavenormallybeenwithinlimitsforFbutoccasionally the0.5ppmlimitforchloridehasbeenexceeded.

OxygenintheRWSTisnotsampledandtherearenoconcentration requirements.

TheRWSTisopentoatmosphere andtherefore willabsorboxygen,soaconcentration specification ismeaningless.

Boronismaintained between2000-3000ppmandsampledmonthly.b.BoricAcidStorageTanks:Chloride,

Flouride, OxygenandpHarenotnormallysampledforonthestoragetanks.Theonlycontrolfortheseimpurities isbydemineralization ofallprocessed boricacid(mixedbedandcationD.Z.'s).Boronconcentration ischeckedthreetimesperweek.Modifications previously completed toincreaserecirculation ofthesetankshas.beenforwarded totheNRCunderLER76-24.Reference item1dofthisbulletinresponse.'age 4of5

~A 1c.Preservice nondestructive examinations performed ontheweldjointsofthesepipingsystemswasvolumetric utilizing radiographic examinations.

Theseexaminations wereper-formedbytheM.W.KelloggCo.duringspoolpieceshopfabrication andbyPittsburgh TestingLaboratories duringfieldinstallation.

Allradiography wasperformed inaccordance withtheAmericanNationalStandardCodeforPressurePipingANSIB-31.1.1d.Rochester GasandElectricCorporation reportedtotheUSNRConOctober8,1976byLicenseeEventReport76-24,information regarding cracksintheSafetyInjection PipingbetweentheBoricAcidStorageTanksandandtheSafetyInjection Pump.Supplemental reportswereforwarded totheNRCon11/11/76, 11/22/76, 2/10/77and6/8/77regarding LER76-24.Alsoon12/21/76, RGGEprovidedtheNRCwithresponsetoI&ECircular76-06.Allcorrective actionsperformed asaresultofLER76-24andIGECircular76-06areincludedinthesecorre-spondences.

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