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| {{#Wiki_filter:'/eREQULAT'NFORMATION DISTRIBUTION STEM(RIDS)ACCESSION NOR:870'7210518 | | {{#Wiki_filter:'/e REQULAT'NFORMATION DISTRIBUTION STEM (RIDS)ACCESSION NOR: 870'7210518 |
| 'OC.DATE:87/09/14NOTARIZED:NODOCKET0FAClL:,50-316 DonaldC.CookNuclearPowerPlantUnit2iIndianaZc05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH>M.P.Indiana5MichiganElectricCo.RECIP.NAMERECIPIENT AFFILIATION MURLEY>T.E.NRC-NoDetailedAffiliation Given | | 'OC.DATE: 87/09/14 NOTAR I ZED: NO DOCKET 0 FAClL:,50-316 Donald C.Cook Nuclear Power Plant Unit 2i Indiana Zc 05000316 AUTH.NAME AUTHOR AFFILIATION ALEX ICH>M.P.Indiana 5 Michigan Electric Co.RECIP.NAME RECIPIENT AFFILIATION MURLEY>T.E.NRC-No Detailed Affiliation Given |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Informsofutilintenttochangedesignoflowertieplateinfuelassemblies.
| | Informs of util intent to change design of lower tie plate in fuel assemblies. |
| AdvancedNuclearFuelsCorpfuelassemblies willbeinstalled duringCycle2reload.Assemblies incorporate debris-resistant tieplate.DISTRIBUTION CODE:A001DCOPIEBRECEIVED:
| | Advanced Nuclear Fuels Corp fuel assemblies will be installed during Cycle 2 reload.Assemblies incorporate debris-resistant tie plate.DISTRIBUTION CODE: A001D COPIEB RECEIVED: LTR ENCL SIZE: TITLE: OR Submittal: |
| LTRENCLSIZE:TITLE:ORSubmittal:
| | General Distribution NOTES: REC IP IENT ID CODE/NAME PD3-3 L*MIGGINGTONz D INTERNAL: ARM/DAF/LFMB NRR/DEBT/CEB NRR/DEBT/RBB B/ILRB REQ FILE 01 EXTERNAL'QM HRUSKEi S NRC PDR COPIES LTTR ENCL 1 0 1 1 1 0 1 1 1 1 1 1 1 1 1 1 HAEC IP IENT ID CODE/NAME PD3-3 PD NRR/DEST/ADB NRR/DEBT/MTB NRR/DOEA/TSB OQC/HDS1 REB/DE/EIH LPDR NBIC COPIES LTTR ENCL 5 5 1 1 1 1 0 1 1 vlggg 4I5$TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 18 II)'1 I(+~%~'~v'~I'I't~q~~)~!F~J;N N INDIANA&MICHIGAN ELECTRIC COMPANY P.O.BOX 16631 COLUMBUS, OHIO 43216 September 14, 1987 AEP'NRC:1035 Donald C.Cook Nuclear Plant Unit 2 Docket No.50-316 License No.DPR-74 UNIT 2 CYCLE 7 RELOAD: CHANGES TO LOWER TIE PLATE DESIGN U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley |
| GeneralDistribution NOTES:RECIPIENTIDCODE/NAME PD3-3L*MIGGINGTONz DINTERNAL:
| |
| ARM/DAF/LFMB NRR/DEBT/CEB NRR/DEBT/RBB B/ILRBREQFILE01EXTERNAL'QM HRUSKEiSNRCPDRCOPIESLTTRENCL1011101111111111HAECIPIENTIDCODE/NAME PD3-3PDNRR/DEST/ADB NRR/DEBT/MTB NRR/DOEA/TSB OQC/HDS1REB/DE/EIH LPDRNBICCOPIESLTTRENCL551111011vlggg4I5$TOTALNUMBEROFCOPIESREQUIRED: | |
| LTTR21ENCL18 II)'1I(+~%~'~v'~I'I't~q~~)~!F~J;NN INDIANA&MICHIGANELECTRICCOMPANYP.O.BOX16631COLUMBUS, OHIO43216September 14,1987AEP'NRC:1035 DonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74UNIT2CYCLE7RELOAD:CHANGESTOLOWERTIEPLATEDESIGNU.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.Murley
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| ==DearDr.Murley:== | | ==Dear Dr.Murley:== |
| Thepurposeofthisletteristoinformyouofourintenttomakeachangetothedesignofthelowertieplateinthefuelassemblies whichwillbefabricated byAdvancedNuclearFuelsCorporation (ANF)fortheupcomingD.C.CookUnit2Cycle7reload.D.C.CookUnit2Cycle7isscheduled tobeginoperation inJune1989.Thereloadwillconsistof80assemblies suppliedbyANF.Theassemblies willincorporate adebris-resistant lowertieplateinthefuelassemblydesigntoprovideprotection fortheassemblies intheunlikelyeventthatdebrisispresentintheprimarycoolantsystem.Thenewlowertieplateisspecifically designedtoentrapdebrisofthesizewhichwouldbeexpectedtobecomeentrapped inthefuelassemblyspacers.Unit2Cycle7willbeprecededbyanextendedoutagetoreplaceallfoursteamgenerators.
| | The purpose of this letter is to inform you of our intent to make a change to the design of the lower tie plate in the fuel assemblies which will be fabricated by Advanced Nuclear Fuels Corporation (ANF)for the upcoming D.C.Cook Unit 2 Cycle 7 reload.D.C.Cook Unit 2 Cycle 7 is scheduled to begin operation in June 1989.The reload will consist of 80 assemblies supplied by ANF.The assemblies will incorporate a debris-resistant lower tie plate in the fuel assembly design to provide protection for the assemblies in the unlikely event that debris is present in the primary coolant system.The new lower tie plate is specifically designed to entrap debris of the size which would be expected to become entrapped in the fuel assembly spacers.Unit 2 Cycle 7 will be preceded by an extended outage to replace all four steam generators. |
| Althoughextremecautionwillbeexercised duringthisoutagetopreventdebrisfromenteringtheprimarycoolantsystem,therevisedlowertieplatedesignisconsidered additional protection againstfueldamage.Asafetyreviewoftherevisedlowertieplatedesignhasbeenperformed byANFandisincludedasanattachment tothisletter.Thisreviewconcluded thatthereviseddesigndoesnotconstitute anunreviewed safetyquestionasdefinedin10CFR50.59.Thisconclusion wasbasedonpressuredropdataobtainedexperimentally byANF.Theseexperiments demonstrated thatthepressuredropfortherevisedlowertieplatedesignwaslessthan0.5%higherthanthepresentdesign.Thisdifference wasconsidered exceedingly smallandisboundedbytheassumptions ofthecurrentD.C.CookUnit2Cycle6safetyanalysesperformed byANF.po9~~>>88709''ePDRADQCK05000316P",."''".PDRJ
| | Although extreme caution will be exercised during this outage to prevent debris from entering the primary coolant system, the revised lower tie plate design is considered additional protection against fuel damage.A safety review of the revised lower tie plate design has been performed by ANF and is included as an attachment to this letter.This review concluded that the revised design does not constitute an unreviewed safety question as defined in 10 CFR 50.59.This conclusion was based on pressure drop data obtained experimentally by ANF.These experiments demonstrated that the pressure drop for the revised lower tie plate design was less than 0.5%higher than the present design.This difference was considered exceedingly small and is bounded by the assumptions of the current D.C.Cook Unit 2 Cycle 6 safety analyses performed by ANF.po 9~~>>8 8709''e PDR ADQCK 05000316 P",."''".PDR J |
| (,C1 Dr.T.E.Murley-2-AEP:NRC:1035 SincetheD.C.CookUnit:2Cycle7reloadwillbeverysimilartothepresentCycle6reload,thecurrentplansforCycle7aretoreviewthereloadinhouseundertheprovisions of10CFR50.59,ratherthanseekformalNRCreview.Sincethesafetyreviewoftherevisedlowertieplatedesignconcluded thattherearenounreviewed safetyquestions associated withthedesignchange,theplanstoreviewthereloadundertheprovisions of10CFR50.59areunaltered. | | (, C 1 Dr.T.E.Murley-2-AEP:NRC:1035 Since the D.C.Cook Unit: 2 Cycle 7 reload will be very similar to the present Cycle 6 reload, the current plans for Cycle 7 are to review the reload in house under the provisions of 10 CFR 50.59, rather than seek formal NRC review.Since the safety review of the revised lower tie plate design concluded that there are no unreviewed safety questions associated with the design change, the plans to review the reload under the provisions of 10 CFR 50.59 are unaltered. |
| However,becausetheCycle7fuelwilldifferindesignfromthatpreviously reviewedbytheNRC,wehavedecidedasacourtesytoinformyouofthechangeandtosolicityourcomments. | | However, because the Cycle 7 fuel will differ in design from that previously reviewed by the NRC, we have decided as a courtesy to inform you of the change and to solicit your comments.As stated above, the 10 CFR 50.59 safety evaluation performed by ANF is attached to this letter;in addition, ANF has transmitted to you, via their letter DAA:014:87, dated August 25, 1987, a copy of their report ANF-87-91,"D.C.Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report." ANF is scheduled to begin fabrication of the Cycle 7 reload fuel by October 13, 1987.Therefore, we request that you inform us of any comments you have on the new lower tie plate design by September 30, 1987, so that we do not risk disruption of the fabrication schedule.Pursuant to the requirements of 10 CFR 170.12(c), we have enclosed an application fee of$150.00.This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned. |
| Asstatedabove,the10CFR50.59safetyevaluation performed byANFisattachedtothisletter;inaddition, ANFhastransmitted toyou,viatheirletterDAA:014:87, datedAugust25,1987,acopyoftheirreportANF-87-91, "D.C.Cook2Debris-Resistant LowerTiePlatePressureDropTestReport."ANFisscheduled tobeginfabrication oftheCycle7reloadfuelbyOctober13,1987.Therefore, werequestthatyouinformusofanycommentsyouhaveonthenewlowertieplatedesignbySeptember 30,1987,sothatwedonotriskdisruption ofthefabrication schedule.
| | Very truly yours, M.P.Al ich Vice President cm Attachment cc: John E.Dolan V.G.Smith, Jr.-Bridgman G.Bruchmann R.C.Callen G.Charnoff NRC Resident Inspector-Bridgman A.B.Davis-Region III Attachment to AEP:NRC:1035 Advanced Nuclear Fuels Safety Evaluation of Revised Lower Tie Plate Design |
| Pursuanttotherequirements of10CFR170.12(c),
| | .ADyANCED NUCLEAR FUELS CQRPORATION |
| wehaveenclosedanapplication feeof$150.00.Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned.
| | ;0!HORN RAPIDS ROAD.PO BOX 130, RICHL4PID, WA 993524130 is09i 3rs ei00 TELEx: Ie 2ere July 30, 1987 ANF-AEP/0597 FUEL ENGINEERING 4 TECHNICAL SERVICES Indiana 5 Michigan Electric Company c/o Mr.Thomas Georgantis Engineer, Nuclear Materials 3 Fuel Management American Electric Power Service Corp.One Riverside Plaza, 20th Floor Columbus, OH 43216-6631 |
| Verytrulyyours,M.P.AlichVicePresident cmAttachment cc:JohnE.DolanV.G.Smith,Jr.-BridgmanG.Bruchmann R.C.CallenG.CharnoffNRCResidentInspector
| |
| -BridgmanA.B.Davis-RegionIII Attachment toAEP:NRC:1035 AdvancedNuclearFuelsSafetyEvaluation ofRevisedLowerTiePlateDesign | |
| .ADyANCED NUCLEARFUELSCQRPORATION | |
| ;0!HORNRAPIDSROAD.POBOX130,RICHL4PID, WA993524130 is09i3rsei00TELEx:Ie2ereJuly30,1987ANF-AEP/0597 FUELENGINEERING 4TECHNICAL SERVICESIndiana5MichiganElectricCompanyc/oMr.ThomasGeorgantis | |
| : Engineer, NuclearMaterials 3FuelManagement AmericanElectricPowerServiceCorp.OneRiverside Plaza,20thFloorColumbus, OH43216-6631
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| ==Reference:== | | ==Reference:== |
|
| |
|
| ANF-87-91(P), | | ANF-87-91(P),"Debris-Resistant Lower Tie Plate Pressure Drop Test Report," Advanced Nuclear Fuels Corp., July 1987 |
| "Debris-Resistant LowerTiePlatePressureDropTestReport,"AdvancedNuclearFuelsCorp.,July1987 | |
|
| |
|
| ==DearHr.Georgantis:== | | ==Dear Hr.Georgantis:== |
|
| |
|
| AtAEP'srequest,AdvancedNuclearFuels(ANF)hasincorporated adebris-resistant lowertieplate(LTP)inthefuelassemblydesignasaprecaution againsttheunlikelyeventofdebrisbeingpresentintheprimarycoolantsystem.Thedebris-resistant LTPhasbeendesignedtoreducethepossibility ofdebrisenteringthefueledregionofthefuelassemblyfromtheprimarycoolantsystem.Specifically, itisdesignedtoentrapdebrisof*thesizewhichwouldbeexpectedtobecomeentrapped inthefuelassemblyspacers.Thisisanimprovement overthecurrentLTPdesigninthatitwillaidintheprevention offuelrodfailuresassociated withdebrisbecomingentrapped inthefuelassemblyspacersandproducing failuresduetofretting.
| | At AEP's request, Advanced Nuclear Fuels (ANF)has incorporated a debris-resistant lower tie plate (LTP)in the fuel assembly design as a precaution against the unlikely event of debris being present in the primary coolant system.The debris-resistant LTP has been designed to reduce the possibility of debris entering the fueled region of the fuel assembly from the primary coolant system.Specifically, it is designed to entrap debris of*the size which would be expected to become entrapped in the fuel assembly spacers.This is an improvement over the current LTP design in that it will aid in the prevention of fuel rod failures associated with debris becoming entrapped in the fuel assembly spacers and producing failures due to fretting.Further, entrapping debris in the LTP instead of in a spacer will provide more time for the flow to recover due to cross flow affects before reaching the HONBR region, A review of the pressure drop information provided in Reference (1)indicates that the unchamfered debris-resistant LTP proposed for D.C.Cook Unit 2 has essentially the same pressure drop as the current LTP.That is, less than a 0.5%difference was observed in the test data obtained between the current LTP and the prcposed unchamfered debris-resistant LTP.Since this difference is exceedingly small, it will produce only a very minor inlet flow perturbation. |
| Further,entrapping debrisintheLTPinsteadofinaspacerwillprovidemoretimefortheflowtorecoverduetocrossflowaffectsbeforereachingtheHONBRregion,Areviewofthepressuredropinformation providedinReference (1)indicates thattheunchamfered debris-resistant LTPproposedforD.C.CookUnit2hasessentially thesamepressuredropasthecurrentLTP.Thatis,lessthana0.5%difference wasobservedinthetestdataobtainedbetweenthecurrentLTPandtheprcposedunchamfered debris-resistant LTP.Sincethisdifference isexceedingly small,itwillproduceonlyaveryminorinletflowperturbation. | | This minor inlet flow perturbation would be expected to disappear due to cross flow effects prior to reaching the axial location at which HONBR would occur.Further, the current HONBR analysis performed for 0, C.Cook Unit 2 assumed a 5%inlet flow maldistribution for the hot channel which is significantly larger than the inlet flow maldistribution which would be expected from the LTP change.Based on this, it is concluded that the Cycle 6 safety analysis will cover the plant conditions expected to occur as a result of the LTP change.Thus, Advanced Nuclear Fuels (ANF)has concluded that the results presented in the Cycle 6 Disposition of Events and safety analysis reports are not affected by the change in LTP and that these reports will remain applicable to future T.Georgantis (AEP)July 30, 1987 ANF-AEP/0597 cycles with the unchamfered debris-resistant LTP.Consequently, ANF concludes that the substitution of the unchamfered debris-resistant LTP for the current D.C, Cook Unit 2 LTP: (I)Does not involve a significant increase in the probability of occurrence or the consequences of an accident previously evaluated in the safety analysis reports (2)Does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report.(3)Does not involve a significant reduction in the margin of safety as defined in the bases for the technical specifications. |
| Thisminorinletflowperturbation wouldbeexpectedtodisappear duetocrossfloweffectspriortoreachingtheaxiallocationatwhichHONBRwouldoccur.Further,thecurrentHONBRanalysisperformed for0,C.CookUnit2assumeda5%inletflowmaldistribution forthehotchannelwhichissignificantly largerthantheinletflowmaldistribution whichwouldbeexpectedfromtheLTPchange.Basedonthis,itisconcluded thattheCycle6safetyanalysiswillcovertheplantconditions expectedtooccurasaresultoftheLTPchange.Thus,AdvancedNuclearFuels(ANF)hasconcluded thattheresultspresented intheCycle6Disposition ofEventsandsafetyanalysisreportsarenotaffectedbythechangeinLTPandthatthesereportswillremainapplicable tofuture T.Georgantis (AEP)July30,1987ANF-AEP/0597 cycleswiththeunchamfered debris-resistant LTP.Consequently, ANFconcludes thatthesubstitution oftheunchamfered debris-resistant LTPforthecurrentD.C,CookUnit2LTP:(I)Doesnotinvolveasignificant increaseintheprobability ofoccurrence ortheconsequences ofanaccidentpreviously evaluated inthesafetyanalysisreports(2)Doesnotcreatethepossibility foranaccidentormalfunction ofadifferent typethananyevaluated previously inthesafetyanalysisreport.(3)Doesnotinvolveasignificant reduction inthemarginofsafetyasdefinedinthebasesforthetechnical specifications.
| | Therefore, ANF concludes that the substitution of the unchamfered debris-resistant LTP for the current LTP does not involve an unreviewed safety issue as defined in 10 CFR 50.59.No additional analyses are required in support of this finding.If you have any questions or comments regarding the above, please feel free to contact us.cc: J.M.Cleveland D H.Malin~V.VanderBurg Sincerely,.r.-..g'-wŽ'ary N.Ward, Manager Reload Licensing}} |
| Therefore, ANFconcludes thatthesubstitution oftheunchamfered debris-resistant LTPforthecurrentLTPdoesnotinvolveanunreviewed safetyissueasdefinedin10CFR50.59.Noadditional analysesarerequiredinsupportofthisfinding.Ifyouhaveanyquestions orcommentsregarding theabove,pleasefeelfreetocontactus.cc:J.M.Cleveland DH.Malin~V.VanderBurg Sincerely, | |
| .r.-..g'-wŽ'aryN.Ward,ManagerReloadLicensing}} | |
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FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
ML17325B4641999-03-17017 March 1999
Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17328A4481990-09-21021 September 1990
Requests Withdrawal of Mode 6 Proposed Tech Spec Change Since Issue Currently Being Addressed by New STSs
ML17328A4331990-08-27027 August 1990
Informs of Preliminary Assessment of 900713 Electrical Contact Accident at Facility.Investigation Concludes That No Safety Rules Violated
ML17328A4001990-08-24024 August 1990
Responds to 900725 Ltr Re Commitments Made in Response to Generic Ltr 88-14 on Instrument Air Supply Problems Affecting safety-related Equipment.Simulator Training to Be Provided as Stated
ML17334B3781990-08-24024 August 1990
Forwards Info to Certify Plant Simulator Facility.Results of Evaluation of Dual Unit Simulation Facilities Demonstrate That Plant Simulator Performance Compares Favorably W/Units
ML17328A4231990-08-21021 August 1990
Forwards Under Separate Cover,Semiannual Radioactive Effluent Release Rept for Jan-June 1990
ML17328A3901990-08-17017 August 1990
Responds to NRC 900720 Ltr Re Violations Noted in Onsite Audit of Spds.Corrective Actions:Apparent Disparity in Selection of Reactor Trip & Sys Capacity or Anticipatory Values Rectified
ML17328A3891990-08-15015 August 1990
Forwards Performance Data Sheets for Plant fitness-for-duty Program for Period Jan-June 1990,per 10CFR26.Encl Includes Statistics on Various Categories of Testing,Substances Tested for & cut-off Levels Used
ML17328A3571990-08-0202 August 1990
Responds to Open Items in Safety Evaluation of Util Response to Unresolved Issues on post-fire Safe Shutdown Methodology. Open Items 1 & 21 Will Be Closed by Implementing Plant Procedures Providing Equivalent Degree of Protection
ML17328A3431990-07-23023 July 1990
Requests Withdrawal of 890830 Proposed Tech Spec Changes Re Sections 3.0 & 4.0.Util Will Resubmit Generic Ltr 87-09 Recommended Improvement Items on Case by Case Basis
ML17328A3421990-07-23023 July 1990
Provides Results of Offsite Dose Calculation for Reactor Coolant Pump Locked Rotor Event for Facility Cycle 8.Util Identified Previously Issued SERs Addressing Short Term Containment Analysis & LOCA Containment Integrity
ML20055G7551990-07-18018 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-315/90-10 & 50-316/90-10.Corrective Actions:Required Review Performed & Updated Procedure 12 Mhp 5021.019.001 Revised & Issued
ML17328A3191990-07-12012 July 1990
Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Electrical Testing Techniques Improved & Surveillance Procedures for Feedwater Pumps Will Be Rewritten
ML17328A3181990-07-0909 July 1990
Responds to Generic Ltr 90-03,Suppl 1, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' Licensee Will Contact safety-related Vendors on Annual Basis
ML17328A3111990-07-0303 July 1990
Provides Certification of Funding Plan for Decommissioning of Plant,Per 10CFR50.33 & 50.75
ML17328A2961990-06-25025 June 1990
Forwards Response to Generic Ltr 90-04 Re Closeout of Generic Safety Issues.Util Supports Concern & Desire to Close long-standing Generic Safety Issues
ML17328A2921990-06-22022 June 1990
Forwards WCAP-12483, Analysis of Capsule U from American Electric Power Co DC Cook Unit 1 Reactor Vessel Radiation Surveillance Program.
ML20044A3521990-06-22022 June 1990
Submits Info Re Sensitivity Study Performed on Number of Fuel Axial Intervals,Per Topical Rept, American Electric Power Reactor Core Thermal-Hydraulic Analysis Using Cobra III-C/MIT-2 Computer Code.
ML17328A2821990-06-15015 June 1990
Submits Ltr Re Proposed Control Room Habitability Tech Spec Changes & Supporting Analyses,Per 900521 Discussion.Revised Calculations of Control Room Thyroid Doses Will Be Submitted within 60 Days of Receipt of Proposed Generic Ltr
ML17328A2741990-06-12012 June 1990
Submits Followup,Per 900205 & 0308 Ltrs & Provides Update Re Inoperable Fire Barrier.Fire Seal Repaired & Restored to Operability on 900419
ML17328A2551990-06-0505 June 1990
Forwards Addl Info Re Util 900126 Revised Response to NRC Bulletin 88-002,per NRC 900509 Request
ML17328A7361990-06-0101 June 1990
Forwards Addl Info Re 890825 & 1212 Applications for Amends to Licenses DPR-58 & DPR-74,per Request.Amends Make Changes to Administrative Controls
ML17328A7331990-05-29029 May 1990
Forwards Nonproprietary WCAP-12577 & Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument... Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Per 900419 Commitment
ML17328A7321990-05-24024 May 1990
Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 Series B or D or Model 1154 Transmitters Installed at Facility.Transmitters Purchased as commercial-grade Units
ML17328A6991990-05-0909 May 1990
Provides Suppl to 900103 Response,Certifying That Fitness for Duty Program Implemented at Plant.Change Also Clarifies When More Stringent cut-off Levels Adopted at Plant Program Apply
ML17328A7001990-05-0909 May 1990
Responds to NRC 900406 Ltr Re Inadequacies of Spds,Per Audit on 900221-22.Corrective Actions:Software Mod Will Prevent User from Accessing Displays Other than Iconic Displays from SPDS Dedicated Terminal
ML17328A7071990-05-0707 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept Mar 1990 for Donald C Cook Nuclear Plant Unit 1
ML17328A7031990-05-0707 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for DC Cook Nuclear Plant Unit 2
ML17328A6951990-04-30030 April 1990
Certifies That Training Programs for Initial Licensing & Requalification Training of Operators & Senior Operators at Plant Accredited by Inpo,Per Generic Ltr 87-07
ML17328A6861990-04-30030 April 1990
Forwards Annual Environ Operating Rept,Jan-Dec 1989, & DC Cook Nuclear Plant Units 1 & 2 Operational Radiological Environ Monitoring Program 1989 Rept Jan-Dec 1989.
ML17328A6801990-04-23023 April 1990
Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Study Planned to Evaluate Alternative Actions to Be Taken for Protecting RHR Pumps
ML17328A6771990-04-23023 April 1990
Forwards DC Cook Nuclear Plant 1990 Annual Emergency Preparedness Exercise. Exercise Scope & Objectives & Detailed Scenario Documentation Encl
ML17334B3641990-04-11011 April 1990
Responds to NRC 900301 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Reliability Centered Maint Program Initiated
ML17328A6601990-04-11011 April 1990
Forwards Updated QA Program Description for Cook Nuclear Plant, Incorporating Editorial,Organizational & Position Title Changes
ML17328A6551990-04-0909 April 1990
Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-316/90-08.Corrective Actions:Procedure for Steam Generator Stop Valve Operability Test Revised to Require That MSIV Be Declared Inoperable After Failing Stroke Test
ML17334B3601990-04-0606 April 1990
Forwards Revised Figures for Loss of Load Event Previously Submitted in Attachment 4,App B of Vantage 5 Reload Transition Safety Rept Supplied by Westinghouse in Jan 1990. Update Is Editorial in Nature
ML17334B3621990-04-0606 April 1990
Forwards 1989 Annual Rept & Projected Cash Flow
ML17328A6341990-03-30030 March 1990
Forwards Application for Renewal of Plant NPDES Permit,For Info,Per Section 3.2 of App B to Plant Tech Specs.W/O Encl
ML17328A6331990-03-30030 March 1990
Responds to NUMARC 900104 Request for Addl Info Re Station Blackout Submittals.Target Reliability for Emergency Diesel Generator of 0.0975 Established for 4 H ac-independent Coping Category Will Be Maintained
ML17328A6321990-03-30030 March 1990
Forwards Response to Generic Ltr 90-01, NRC Regulatory Impact Survey. Util Ack Recommendation by NUMARC
ML17328A6221990-03-27027 March 1990
Responds to 900226 Ltr Transmitting Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000. Corrective Actions:Flow Retention Circuitry Setpoints Set to Compensate for Missized Process Flow Orifice
ML17328A6191990-03-27027 March 1990
Forwards Payment in Amount of $75,000 for Civil Penalty Imposed Through Notice of Violation Issued in Insp Rept 50-316/89-02 on 891016-20,24-26 & 1204.Response to Violation & Corrective Actions Provided in Separate Submittal
ML17328A6161990-03-20020 March 1990
Responds to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs (USI A-47).Both Units Have Steam Overfill Protection Sys That Would Automatically Prevent Water Carryover Into Steam Lines If Control Sys Failed
ML17328A6121990-03-13013 March 1990
Forwards Monthly Performance Monitoring Rept,Jan 1990.
ML17325B3901990-03-0606 March 1990
Forwards Annual Rept to NRC Per 10CFR50.54(W)(2) Re Nuclear Property Insurance
ML17325B3921990-03-0606 March 1990
Modifies Application for Amend to License DPR-74 Re Cycle 8, Per 900228 Telcon
ML17325B3781990-02-28028 February 1990
Forwards Response to NRC Info Notice 89-056 Re Questionable Certification of Matl Supplied to Dod by Nuclear Suppliers. Matl Capable of Performing Design Function & Acceptable for Continued Use
ML17328A5971990-02-27027 February 1990
Withdraws 890203 Application for Amend to License DPR-74, Modifying Tech Spec Table 3.2-1 Re DNB Parameters to Express RCS Flow Rate on Volumetric Rather than Mass Basis
ML17334B3511990-02-22022 February 1990
Submits Annual Rept of Changes to or Errors in Acceptable LOCA Evaluation Models or Application of Models for Plants. Wflash Analyses Will Be Superceded by Notrump Analyses for Unit 2,Cycle 8 Reload
ML17328A5881990-02-21021 February 1990
Responds to NRC 890914 Request for Addl Info Re Safe Shutdown Methodology.App R Fire Barriers Being Maintained & Surveilled Under 3/4.7.10 for Units 1 & 2
ML17328A5861990-02-16016 February 1990
Provides Revised Comments in Response to NRR Comments During 891213 Telcon Re Allowable Stresses for Piping & Piping Supports
1990-09-21
[Table view] |
Text
'/e REQULAT'NFORMATION DISTRIBUTION STEM (RIDS)ACCESSION NOR: 870'7210518
'OC.DATE: 87/09/14 NOTAR I ZED: NO DOCKET 0 FAClL:,50-316 Donald C.Cook Nuclear Power Plant Unit 2i Indiana Zc 05000316 AUTH.NAME AUTHOR AFFILIATION ALEX ICH>M.P.Indiana 5 Michigan Electric Co.RECIP.NAME RECIPIENT AFFILIATION MURLEY>T.E.NRC-No Detailed Affiliation Given
SUBJECT:
Informs of util intent to change design of lower tie plate in fuel assemblies.
Advanced Nuclear Fuels Corp fuel assemblies will be installed during Cycle 2 reload.Assemblies incorporate debris-resistant tie plate.DISTRIBUTION CODE: A001D COPIEB RECEIVED: LTR ENCL SIZE: TITLE: OR Submittal:
General Distribution NOTES: REC IP IENT ID CODE/NAME PD3-3 L*MIGGINGTONz D INTERNAL: ARM/DAF/LFMB NRR/DEBT/CEB NRR/DEBT/RBB B/ILRB REQ FILE 01 EXTERNAL'QM HRUSKEi S NRC PDR COPIES LTTR ENCL 1 0 1 1 1 0 1 1 1 1 1 1 1 1 1 1 HAEC IP IENT ID CODE/NAME PD3-3 PD NRR/DEST/ADB NRR/DEBT/MTB NRR/DOEA/TSB OQC/HDS1 REB/DE/EIH LPDR NBIC COPIES LTTR ENCL 5 5 1 1 1 1 0 1 1 vlggg 4I5$TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 18 II)'1 I(+~%~'~v'~I'I't~q~~)~!F~J;N N INDIANA&MICHIGAN ELECTRIC COMPANY P.O.BOX 16631 COLUMBUS, OHIO 43216 September 14, 1987 AEP'NRC:1035 Donald C.Cook Nuclear Plant Unit 2 Docket No.50-316 License No.DPR-74 UNIT 2 CYCLE 7 RELOAD: CHANGES TO LOWER TIE PLATE DESIGN U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley
Dear Dr.Murley:
The purpose of this letter is to inform you of our intent to make a change to the design of the lower tie plate in the fuel assemblies which will be fabricated by Advanced Nuclear Fuels Corporation (ANF)for the upcoming D.C.Cook Unit 2 Cycle 7 reload.D.C.Cook Unit 2 Cycle 7 is scheduled to begin operation in June 1989.The reload will consist of 80 assemblies supplied by ANF.The assemblies will incorporate a debris-resistant lower tie plate in the fuel assembly design to provide protection for the assemblies in the unlikely event that debris is present in the primary coolant system.The new lower tie plate is specifically designed to entrap debris of the size which would be expected to become entrapped in the fuel assembly spacers.Unit 2 Cycle 7 will be preceded by an extended outage to replace all four steam generators.
Although extreme caution will be exercised during this outage to prevent debris from entering the primary coolant system, the revised lower tie plate design is considered additional protection against fuel damage.A safety review of the revised lower tie plate design has been performed by ANF and is included as an attachment to this letter.This review concluded that the revised design does not constitute an unreviewed safety question as defined in 10 CFR 50.59.This conclusion was based on pressure drop data obtained experimentally by ANF.These experiments demonstrated that the pressure drop for the revised lower tie plate design was less than 0.5%higher than the present design.This difference was considered exceedingly small and is bounded by the assumptions of the current D.C.Cook Unit 2 Cycle 6 safety analyses performed by ANF.po 9~~>>8 8709e PDR ADQCK 05000316 P",."".PDR J
(, C 1 Dr.T.E.Murley-2-AEP:NRC:1035 Since the D.C.Cook Unit: 2 Cycle 7 reload will be very similar to the present Cycle 6 reload, the current plans for Cycle 7 are to review the reload in house under the provisions of 10 CFR 50.59, rather than seek formal NRC review.Since the safety review of the revised lower tie plate design concluded that there are no unreviewed safety questions associated with the design change, the plans to review the reload under the provisions of 10 CFR 50.59 are unaltered.
However, because the Cycle 7 fuel will differ in design from that previously reviewed by the NRC, we have decided as a courtesy to inform you of the change and to solicit your comments.As stated above, the 10 CFR 50.59 safety evaluation performed by ANF is attached to this letter;in addition, ANF has transmitted to you, via their letter DAA:014:87, dated August 25, 1987, a copy of their report ANF-87-91,"D.C.Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Report." ANF is scheduled to begin fabrication of the Cycle 7 reload fuel by October 13, 1987.Therefore, we request that you inform us of any comments you have on the new lower tie plate design by September 30, 1987, so that we do not risk disruption of the fabrication schedule.Pursuant to the requirements of 10 CFR 170.12(c), we have enclosed an application fee of$150.00.This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.P.Al ich Vice President cm Attachment cc: John E.Dolan V.G.Smith, Jr.-Bridgman G.Bruchmann R.C.Callen G.Charnoff NRC Resident Inspector-Bridgman A.B.Davis-Region III Attachment to AEP:NRC:1035 Advanced Nuclear Fuels Safety Evaluation of Revised Lower Tie Plate Design
.ADyANCED NUCLEAR FUELS CQRPORATION
- 0!HORN RAPIDS ROAD.PO BOX 130, RICHL4PID, WA 993524130 is09i 3rs ei00 TELEx
- Ie 2ere July 30, 1987 ANF-AEP/0597 FUEL ENGINEERING 4 TECHNICAL SERVICES Indiana 5 Michigan Electric Company c/o Mr.Thomas Georgantis Engineer, Nuclear Materials 3 Fuel Management American Electric Power Service Corp.One Riverside Plaza, 20th Floor Columbus, OH 43216-6631
Reference:
ANF-87-91(P),"Debris-Resistant Lower Tie Plate Pressure Drop Test Report," Advanced Nuclear Fuels Corp., July 1987
Dear Hr.Georgantis:
At AEP's request, Advanced Nuclear Fuels (ANF)has incorporated a debris-resistant lower tie plate (LTP)in the fuel assembly design as a precaution against the unlikely event of debris being present in the primary coolant system.The debris-resistant LTP has been designed to reduce the possibility of debris entering the fueled region of the fuel assembly from the primary coolant system.Specifically, it is designed to entrap debris of*the size which would be expected to become entrapped in the fuel assembly spacers.This is an improvement over the current LTP design in that it will aid in the prevention of fuel rod failures associated with debris becoming entrapped in the fuel assembly spacers and producing failures due to fretting.Further, entrapping debris in the LTP instead of in a spacer will provide more time for the flow to recover due to cross flow affects before reaching the HONBR region, A review of the pressure drop information provided in Reference (1)indicates that the unchamfered debris-resistant LTP proposed for D.C.Cook Unit 2 has essentially the same pressure drop as the current LTP.That is, less than a 0.5%difference was observed in the test data obtained between the current LTP and the prcposed unchamfered debris-resistant LTP.Since this difference is exceedingly small, it will produce only a very minor inlet flow perturbation.
This minor inlet flow perturbation would be expected to disappear due to cross flow effects prior to reaching the axial location at which HONBR would occur.Further, the current HONBR analysis performed for 0, C.Cook Unit 2 assumed a 5%inlet flow maldistribution for the hot channel which is significantly larger than the inlet flow maldistribution which would be expected from the LTP change.Based on this, it is concluded that the Cycle 6 safety analysis will cover the plant conditions expected to occur as a result of the LTP change.Thus, Advanced Nuclear Fuels (ANF)has concluded that the results presented in the Cycle 6 Disposition of Events and safety analysis reports are not affected by the change in LTP and that these reports will remain applicable to future T.Georgantis (AEP)July 30, 1987 ANF-AEP/0597 cycles with the unchamfered debris-resistant LTP.Consequently, ANF concludes that the substitution of the unchamfered debris-resistant LTP for the current D.C, Cook Unit 2 LTP: (I)Does not involve a significant increase in the probability of occurrence or the consequences of an accident previously evaluated in the safety analysis reports (2)Does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report.(3)Does not involve a significant reduction in the margin of safety as defined in the bases for the technical specifications.
Therefore, ANF concludes that the substitution of the unchamfered debris-resistant LTP for the current LTP does not involve an unreviewed safety issue as defined in 10 CFR 50.59.No additional analyses are required in support of this finding.If you have any questions or comments regarding the above, please feel free to contact us.cc: J.M.Cleveland D H.Malin~V.VanderBurg Sincerely,.r.-..g'-wŽ'ary N.Ward, Manager Reload Licensing
