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| {{#Wiki_filter:I7PRIORITY3y(ACCELERATEDRZDSPROCESSING)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9510180239DOC.DATE:95/10/11NOTARIZED:NOFACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterGAUTH.NAMEAUTHORAFFILIATIONMERCREDY,R.C.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATIONJOHNSON,A.R. | | {{#Wiki_filter:I7PRIORITY3y(ACCELERATED RZDSPROCESSING) |
| | REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9510180239 DOC.DATE: |
| | 95/10/11NOTARIZED: |
| | NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MERCREDY,R.C. |
| | Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Providespressurizedthermalshockassessmentforreactorpressurevessellimitingcircumferentialweldforreview&approval.DISTRIBUTIONCODE:A049DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:ThermalShocktoReactorVesselDOCKET05000244P0RNOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).05000244RECIPIENT1DCODE/NAMEPD1-1PDINTERNAL:AEOD/DOANRR/DEOGC/HDS3RES/DE/MEB/MESRES/DSR/RPSBRGN1ADMSTREXTERNAL:NOAC~+t'g5'3/~iCOPIESLTTRENCL111''01011111111RECIPIENTIDCODE/NAMEJOHNSOF1NRR/DSSA/SRXBRESDERES/DSIR/EIBRES/DST/PRABNRCPDRCOPIESLTTRENCL1'1111111111NNOTE,TOALL"RZDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D8(415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEEDITOTAL,NUMBEROFCOPIESREQUIRED:LTTR15ENCL13 04 ANDROCHE/TERGASANDELECTRICCORPORATION~89FASTAYENLIE,ROCHESTER,N.Y.Idio-000IAREACODE716Sd6-2700ROBERTC.MECREDYVicePresidentNvcleorOperotions,October11,1995U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:AllenR.JohnsonProjectDirectorateI-1Washington,D.C.20555
| | Providespressurized thermalshockassessment forreactorpressurevessellimitingcircumferential weldforreview&approval. |
| | DISTRIBUTION CODE:A049DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: |
| | ThermalShocktoReactorVesselDOCKET05000244P0RNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). |
| | 05000244RECIPIENT 1DCODE/NAME PD1-1PDINTERNAL: |
| | AEOD/DOANRR/DEOGC/HDS3RES/DE/MEB/MES RES/DSR/RPSB RGN1ADMSTREXTERNAL: |
| | NOAC~+t'g5'3/~iCOPIESLTTRENCL111''01011111111RECIPIENT IDCODE/NAME JOHNSOF1NRR/DSSA/SRXB RESDERES/DSIR/EIB RES/DST/PRAB NRCPDRCOPIESLTTRENCL1'1111111111NNOTE,TOALL"RZDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D8(415-2083) |
| | TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDITOTAL,NUMBEROFCOPIESREQUIRED: |
| | LTTR15ENCL13 04 ANDROCHE/TER GASANDELECTRICCORPORATION |
| | ~89FASTAYENLIE, ROCHESTER, N.Y.Idio-000I AREACODE716Sd6-2700ROBERTC.MECREDYVicePresident NvcleorOperotions, October11,1995U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-1Washington, D.C.20555 |
|
| |
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| ==Subject:== | | ==Subject:== |
| PressurizedThermalShockAssessmentforGinnaReactorVesselR.E.GinnaNuclearPowerPlantDocketNo.50-244Ref.(a):LetterfromAllenR.Johnson(NRC),toRobertC.Mecredy(RG&E),"SummaryofMeetingwithRochesterGasandElectricCorporationonMay16,1995-PressurizerThermalShockAssessmentofReactorVessels,"datedJune5,1995.
| | Pressurized ThermalShockAssessment forGinnaReactorVesselR.E.GinnaNuclearPowerPlantDocketNo.50-244Ref.(a):LetterfromAllenR.Johnson(NRC),toRobertC.Mecredy(RG&E),"SummaryofMeetingwithRochester GasandElectricCorporation onMay16,1995-Pressurizer ThermalShockAssessment ofReactorVessels," |
| | datedJune5,1995. |
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| |
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| ==DearMr.Johnson:== | | ==DearMr.Johnson:== |
| ThepurposeofthiscorrespondenceistoprovideRochesterGasandElectricCorporation's(RG&E)pressurizedthermalshock(PTS)assessmentfortheR.E.Ginnareactorpressurevessel(RPV)limitingcircumferentialweldforyourreviewandapproval.Theassessment,aspresentedintheattached,isprovidedinresponsetothereferencedletterandisbasedontheguidanceprovidedin10CFR50.61andRegulatoryGuide1.99revision2.Asprovidedforbythisguidance,theRG&EassessmentincludestheuseoftheresultsoftheRPVsurveillancecapsuleprogram.AstheattachedPTSdeterminationshows,theGinnaRPVcanbeexpectedtooperatepasttheendoflicense(EOL)of2009withoutexceedingthePTSscreeningcriterionof10CFR50.61forthelimitingcaseweld.Verytrulyyours,RobertC.MecredyREJtl,393i.70jgJ95i0180239'st5lOiiPDRADOCK05000244PPDRpyre+p8'K/prtl.
| | Thepurposeofthiscorrespondence istoprovideRochester GasandElectricCorporation's (RG&E)pressurized thermalshock(PTS)assessment fortheR.E.Ginnareactorpressurevessel(RPV)limitingcircumferential weldforyourreviewandapproval. |
| xcMr'.AllenR.Johnson(MailStop14B2)ProjectDirectorateI-1Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspector ATTACHMENTR.E.GinnaReactorVesselEOLPTSAssessmentDiscussionThepurposeofthisassessmentistoshowthattheexpectedreferencetemperaturePTS(RT~,)atEOLfortheGinnaRPVlimitingweldremainsbelowthescreeningcriteriawhenusingsurveillanceprogramdata.ThelimitingmaterialfortheGinnaRPVistheintermediatetolowershellweldhavingweldwireheatnumber61782.ThematerialusedforthesurveillancecapsuleprogramisweldwireSA-1036havingmaterialheatnumber61782whichhasbeendeterminedtobeacceptableforuseasasurveillancematerial+.ThedeterminationofthereferencetemperatureforRT~fortheRPV-PTSassessmentusesthe10CFR50.61(b)(3)plantspecificsurveillanceprogrammethodwhichincludesthesurveillancedataadjustmentsperRegulatoryGuide1.99revision2position2,where:(1)RTpgg=I+M+aRTggg(2)I=initialRT~~~(4)~RT~Y=referencetemperatureshift"> | | Theassessment, aspresented intheattached, isprovidedinresponsetothereferenced letterandisbasedontheguidanceprovidedin10CFR50.61 andRegulatory Guide1.99revision2.Asprovidedforbythisguidance, theRG&Eassessment includestheuseoftheresultsoftheRPVsurveillance capsuleprogram.AstheattachedPTSdetermination shows,theGinnaRPVcanbeexpectedtooperatepasttheendoflicense(EOL)of2009withoutexceeding thePTSscreening criterion of10CFR50.61 forthelimitingcaseweld.Verytrulyyours,RobertC.MecredyREJtl,393 i.70jgJ95i0180239 |
| 8II.MaterialValuesUsedA.RPVmaterialheat617821~I=themeanofthetestvaluesi=1nwhere:1oF(()1i=-38'F)nn=2~I=-19.5'Fando',=18.5'F2~3~4~5~fluence9EOL=3.68E19("Chemistry(')Cu=~25Ni=.54CF('):167.6oFM=2ltr~+e,~wheree,=18.5'F(II.A.1)and14oF(4)~M=46.4'FB.SurveillanceCapsulesWeldSA10361~~RTNDVRTS5.56E181.15E191.97E193.87E19140oF165oF150oF205oF2~3~MeanValueChemistry+(')+:Cu=.214Ni=.505CF>>:150'oF IXX.Ca'lculationsA.Chemistryfactorratio<4>:CFofRPV(II.A.4above)-:CFofcapsule(II.B.3above)~Ratio=167.6=1.11150.9B.BestfitCF<"1.Summingadjustedcapsule~RTNDTAdjustedVRTS140165150205X1.11X1.11X1.11X1.11155.4183.2166.5227.62~DeterminesumoffluencefactorxadjustedaRT~~wherefluencefactor(ff)=f<"~CasuleFFAdjusted~RTmProductVRTS0.8361.0391.1851.349155.4183.2166.5227.6sum=129.9.190.3197.3307.824.53~Summingsquaresofcapsulesfluencefactors(FF)forusingfluencefactorvaluesfromII.B.1:~casuleVRTS0.8361.0391.1851.349sum=0.6991.0801.4051.8205.0044SumofadjustedaRTNT-:sumofsquaresoffluence824.5(XII.B.2)-:5.004(III.B.3)=164.8F C.'RT~~forsurveillancefit9EOLEOLgRT~~(CF)frogs-oioi~owheref=3.68(I.B.4)x3.68'164.8F)(1.338)=220.5D.RTrrs~EOLRT~=I+M+aRTNg~-19~5F(II.A.1)+46.4F(II.A.5)+220.5(III.C)247.4oFIV.ResultsTheRT~valueatEOLfortheR.E.Ginnavesselis247.4F.Thisis52.64FbelowthePTSscreeningcriteriondescribedin10CFR50.61. | | 'st5lOiiPDRADOCK05000244PPDRpyre+p8'K/prtl. |
| | xcMr'.AllenR.Johnson(MailStop14B2)ProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector ATTACHMENT R.E.GinnaReactorVesselEOLPTSAssessment Discussion Thepurposeofthisassessment istoshowthattheexpectedreference temperature PTS(RT~,)atEOLfortheGinnaRPVlimitingweldremainsbelowthescreening criteriawhenusingsurveillance programdata.ThelimitingmaterialfortheGinnaRPVistheintermediate tolowershellweldhavingweldwireheatnumber61782.Thematerialusedforthesurveillance capsuleprogramisweldwireSA-1036havingmaterialheatnumber61782whichhasbeendetermined tobeacceptable foruseasasurveillance material+. |
| | Thedetermination ofthereference temperature forRT~fortheRPV-PTSassessment usesthe10CFR50.61(b)(3) plantspecificsurveillance programmethodwhichincludesthesurveillance dataadjustments perRegulatory Guide1.99revision2position2,where:(1)RTpgg=I+M+aRTggg(2)I=initialRT~~~(4)~RT~Y=reference temperature shift"> |
| | 8II.MaterialValuesUsedA.RPVmaterialheat617821~I=themeanofthetestvaluesi=1nwhere:1oF(()1i=-38'F)nn=2~I=-19.5'Fando',=18.5'F2~3~4~5~fluence9EOL=3.68E19(" |
| | Chemistry(') |
| | Cu=~25Ni=.54CF('):167.6oFM=2ltr~+e,~wheree,=18.5'F(II.A.1)and14oF(4)~M=46.4'FB.Surveillance CapsulesWeldSA10361~~RTNDVRTS5.56E181.15E191.97E193.87E19140oF165oF150oF205oF2~3~MeanValueChemistry+(')+: |
| | Cu=.214Ni=.505CF>>:150'oF IXX.Ca'lculations A.Chemistry factorratio<4>: |
| | CFofRPV(II.A.4above)-:CFofcapsule(II.B.3above)~Ratio=167.6=1.11150.9B.BestfitCF<"1.Summingadjustedcapsule~RTNDTAdjustedVRTS140165150205X1.11X1.11X1.11X1.11155.4183.2166.5227.62~Determine sumoffluencefactorxadjustedaRT~~wherefluencefactor(ff)=f<"~CasuleFFAdjusted~RTmProductVRTS0.8361.0391.1851.349155.4183.2166.5227.6sum=129.9.190.3197.3307.824.53~Summingsquaresofcapsulesfluencefactors(FF)forusingfluencefactorvaluesfromII.B.1:~casuleVRTS0.8361.0391.1851.349sum=0.6991.0801.4051.8205.0044SumofadjustedaRTNT-:sumofsquaresoffluence824.5(XII.B.2) |
| | -:5.004(III.B.3) |
| | =164.8F C.'RT~~forsurveillance fit9EOLEOLgRT~~(CF)frogs-oioi~o wheref=3.68(I.B.4)x3.68'164.8F)(1.338)=220.5D.RTrrs~EOLRT~=I+M+aRTNg~-19~5F(II.A.1)+46.4F(II.A.5)+220.5(III.C)247.4oFIV.ResultsTheRT~valueatEOLfortheR.E.Ginnavesselis247.4F.Thisis52.64FbelowthePTSscreening criterion described in10CFR50.61. |
|
| |
|
| ==REFERENCES:== | | ==REFERENCES:== |
| (1)BAW1803Revision1,"CorrelationsforPredictingtheEffectsofNeutronRadiationonLinde80Submerged-ArcWelds."(2)WCAP-13902,"AnalysisofCapsuleSfromtheRochesterGasandElectricCorporationR.e.GinnaReactorVesselRadiationSurveillanceProgram,"datedDecember1993.(3)CodeofFederalRegulations,10CFR50.61,"FractureToughnessRequirementsforProtectionAgainstPressurizedThermalShockEvents."(4)RegulatoryGuide1.99,revision2,"RadiationEmbrittlementofReactorVesselMaterials."(5)BAW1920P,"AnalysisofCapsuleDB1-LG1,"October1986.(6)LettertoRogerW.KoberfromMortonB.Fairtile,"SafetyEvaluationbytheOfficeofNuclearReactorRegulationRelatedtoAmendmentNo.15toFacilityOperatingLicenseNo.DPR-18RochesterGasandElectricCorporationR.E.GinnaNuclearPowerPlantDocketNo.50-244,"datedJune12(1986.(7)BAW-1500,"Chemistryof177-FAB&WOwner'sGroupReactorVesselBeltlineWelds,"September1978.(8)10CFR50.61,"Fracturetoughnessrequirementsforprotectionagainstpressurizedthermalshockevents."(9)BAW-2121P,"ChemicalCompositionofB&WFabricatedReactorVesselBeltlineWelds,"April1991.}} | | |
| | (1)BAW1803Revision1,"Correlations forPredicting theEffectsofNeutronRadiation onLinde80Submerged |
| | -ArcWelds."(2)WCAP-13902, "Analysis ofCapsuleSfromtheRochester GasandElectricCorporation R.e.GinnaReactorVesselRadiation Surveillance Program," |
| | datedDecember1993.(3)CodeofFederalRegulations, 10CFR50.61, "Fracture Toughness Requirements forProtection AgainstPressurized ThermalShockEvents."(4)Regulatory Guide1.99,revision2,"Radiation Embrittlement ofReactorVesselMaterials." |
| | (5)BAW1920P,"Analysis ofCapsuleDB1-LG1," |
| | October1986.(6)LettertoRogerW.KoberfromMortonB.Fairtile, "SafetyEvaluation bytheOfficeofNuclearReactorRegulation RelatedtoAmendment No.15toFacilityOperating LicenseNo.DPR-18Rochester GasandElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244,"datedJune12(1986.(7)BAW-1500, "Chemistry of177-FAB&WOwner'sGroupReactorVesselBeltlineWelds,"September 1978.(8)10CFR50.61, "Fracture toughness requirements forprotection againstpressurized thermalshockevents."(9)BAW-2121P, "Chemical Composition ofB&WFabricated ReactorVesselBeltlineWelds,"April1991.}} |
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Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
[Table view] |
Text
I7PRIORITY3y(ACCELERATED RZDSPROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9510180239 DOC.DATE:
95/10/11NOTARIZED:
NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MERCREDY,R.C.
Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Providespressurized thermalshockassessment forreactorpressurevessellimitingcircumferential weldforreview&approval.
DISTRIBUTION CODE:A049DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
ThermalShocktoReactorVesselDOCKET05000244P0RNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
05000244RECIPIENT 1DCODE/NAME PD1-1PDINTERNAL:
AEOD/DOANRR/DEOGC/HDS3RES/DE/MEB/MES RES/DSR/RPSB RGN1ADMSTREXTERNAL:
NOAC~+t'g5'3/~iCOPIESLTTRENCL11101011111111RECIPIENT IDCODE/NAME JOHNSOF1NRR/DSSA/SRXB RESDERES/DSIR/EIB RES/DST/PRAB NRCPDRCOPIESLTTRENCL1'1111111111NNOTE,TOALL"RZDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D8(415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDITOTAL,NUMBEROFCOPIESREQUIRED:
LTTR15ENCL13 04 ANDROCHE/TER GASANDELECTRICCORPORATION
~89FASTAYENLIE, ROCHESTER, N.Y.Idio-000I AREACODE716Sd6-2700ROBERTC.MECREDYVicePresident NvcleorOperotions, October11,1995U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-1Washington, D.C.20555
Subject:
Pressurized ThermalShockAssessment forGinnaReactorVesselR.E.GinnaNuclearPowerPlantDocketNo.50-244Ref.(a):LetterfromAllenR.Johnson(NRC),toRobertC.Mecredy(RG&E),"SummaryofMeetingwithRochester GasandElectricCorporation onMay16,1995-Pressurizer ThermalShockAssessment ofReactorVessels,"
datedJune5,1995.
DearMr.Johnson:
Thepurposeofthiscorrespondence istoprovideRochester GasandElectricCorporation's (RG&E)pressurized thermalshock(PTS)assessment fortheR.E.Ginnareactorpressurevessel(RPV)limitingcircumferential weldforyourreviewandapproval.
Theassessment, aspresented intheattached, isprovidedinresponsetothereferenced letterandisbasedontheguidanceprovidedin10CFR50.61 andRegulatory Guide1.99revision2.Asprovidedforbythisguidance, theRG&Eassessment includestheuseoftheresultsoftheRPVsurveillance capsuleprogram.AstheattachedPTSdetermination shows,theGinnaRPVcanbeexpectedtooperatepasttheendoflicense(EOL)of2009withoutexceeding thePTSscreening criterion of10CFR50.61 forthelimitingcaseweld.Verytrulyyours,RobertC.MecredyREJtl,393 i.70jgJ95i0180239
'st5lOiiPDRADOCK05000244PPDRpyre+p8'K/prtl.
xcMr'.AllenR.Johnson(MailStop14B2)ProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector ATTACHMENT R.E.GinnaReactorVesselEOLPTSAssessment Discussion Thepurposeofthisassessment istoshowthattheexpectedreference temperature PTS(RT~,)atEOLfortheGinnaRPVlimitingweldremainsbelowthescreening criteriawhenusingsurveillance programdata.ThelimitingmaterialfortheGinnaRPVistheintermediate tolowershellweldhavingweldwireheatnumber61782.Thematerialusedforthesurveillance capsuleprogramisweldwireSA-1036havingmaterialheatnumber61782whichhasbeendetermined tobeacceptable foruseasasurveillance material+.
Thedetermination ofthereference temperature forRT~fortheRPV-PTSassessment usesthe10CFR50.61(b)(3) plantspecificsurveillance programmethodwhichincludesthesurveillance dataadjustments perRegulatory Guide1.99revision2position2,where:(1)RTpgg=I+M+aRTggg(2)I=initialRT~~~(4)~RT~Y=reference temperature shift">
8II.MaterialValuesUsedA.RPVmaterialheat617821~I=themeanofthetestvaluesi=1nwhere:1oF(()1i=-38'F)nn=2~I=-19.5'Fando',=18.5'F2~3~4~5~fluence9EOL=3.68E19("
Chemistry(')
Cu=~25Ni=.54CF('):167.6oFM=2ltr~+e,~wheree,=18.5'F(II.A.1)and14oF(4)~M=46.4'FB.Surveillance CapsulesWeldSA10361~~RTNDVRTS5.56E181.15E191.97E193.87E19140oF165oF150oF205oF2~3~MeanValueChemistry+(')+:
Cu=.214Ni=.505CF>>:150'oF IXX.Ca'lculations A.Chemistry factorratio<4>:
CFofRPV(II.A.4above)-:CFofcapsule(II.B.3above)~Ratio=167.6=1.11150.9B.BestfitCF<"1.Summingadjustedcapsule~RTNDTAdjustedVRTS140165150205X1.11X1.11X1.11X1.11155.4183.2166.5227.62~Determine sumoffluencefactorxadjustedaRT~~wherefluencefactor(ff)=f<"~CasuleFFAdjusted~RTmProductVRTS0.8361.0391.1851.349155.4183.2166.5227.6sum=129.9.190.3197.3307.824.53~Summingsquaresofcapsulesfluencefactors(FF)forusingfluencefactorvaluesfromII.B.1:~casuleVRTS0.8361.0391.1851.349sum=0.6991.0801.4051.8205.0044SumofadjustedaRTNT-:sumofsquaresoffluence824.5(XII.B.2)
-:5.004(III.B.3)
=164.8F C.'RT~~forsurveillance fit9EOLEOLgRT~~(CF)frogs-oioi~o wheref=3.68(I.B.4)x3.68'164.8F)(1.338)=220.5D.RTrrs~EOLRT~=I+M+aRTNg~-19~5F(II.A.1)+46.4F(II.A.5)+220.5(III.C)247.4oFIV.ResultsTheRT~valueatEOLfortheR.E.Ginnavesselis247.4F.Thisis52.64FbelowthePTSscreening criterion described in10CFR50.61.
REFERENCES:
(1)BAW1803Revision1,"Correlations forPredicting theEffectsofNeutronRadiation onLinde80Submerged
-ArcWelds."(2)WCAP-13902, "Analysis ofCapsuleSfromtheRochester GasandElectricCorporation R.e.GinnaReactorVesselRadiation Surveillance Program,"
datedDecember1993.(3)CodeofFederalRegulations, 10CFR50.61, "Fracture Toughness Requirements forProtection AgainstPressurized ThermalShockEvents."(4)Regulatory Guide1.99,revision2,"Radiation Embrittlement ofReactorVesselMaterials."
(5)BAW1920P,"Analysis ofCapsuleDB1-LG1,"
October1986.(6)LettertoRogerW.KoberfromMortonB.Fairtile, "SafetyEvaluation bytheOfficeofNuclearReactorRegulation RelatedtoAmendment No.15toFacilityOperating LicenseNo.DPR-18Rochester GasandElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244,"datedJune12(1986.(7)BAW-1500, "Chemistry of177-FAB&WOwner'sGroupReactorVesselBeltlineWelds,"September 1978.(8)10CFR50.61, "Fracture toughness requirements forprotection againstpressurized thermalshockevents."(9)BAW-2121P, "Chemical Composition ofB&WFabricated ReactorVesselBeltlineWelds,"April1991.
