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| issue date = 12/17/1993
| issue date = 12/17/1993
| title = Forwards DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation, to Replace Analysis Attached to 921111 Submittal to Justify TS Change to Increase Allowable Tolerances
| title = Forwards DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation, to Replace Analysis Attached to 921111 Submittal to Justify TS Change to Increase Allowable Tolerances
| author name = FITZPATRICK E
| author name = Fitzpatrick E
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| addressee name = MURLEY T E
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000315, 05000316
| docket = 05000315, 05000316
Line 14: Line 14:
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 7
| page count = 7
| project =
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:"'ACCELERATEDISTRIBUTIONDEMON/'RATIONSYSTEMI'!REGULATORYINFORMATIONDISTRXBUTIONSYSTEM(RIDS)DOCKET0500031505000316ACCESSXONNBR:9312230045DOC.DATE:93/12/17NOTARIZED:YESFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATIONFITZPATRXCK,E.IndianaMichiganPowerCo.(formerlyIndiana6MichiganEleRECXP.NAMERECIPIENTAFFILIATIONRMURLEY,T.E.DocumentControlBranch(DocumentControlDesk)
{{#Wiki_filter:" ' ACCELERATED                    ISTRIBUTION DEMON/'RATION SYSTEM I            '!
REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)
ACCESSXON  NBR:9312230045            DOC.DATE: 93/12/17    NOTARIZED: YES          DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana                  M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana                  M 05000316 AUTH. NAME                AUTHOR AFFILIATION FITZPATRXCK,E.         Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECXP.NAME                RECIPIENT AFFILIATION                                              R MURLEY,T.E.                 Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Forwards"DCCookUnits1&2MainSteamSafetyValveLiftSetpointToleranceRelaxation,"toreplaceanalysisattachedto921111submittaltojustifyTSchangetoincreaseallowabletolerances.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZETITLE:ORSubmittal:GeneralDistributionNOTES:SF/RECXPIENTIDCODE/NAMEPD3-1LAHICKMAN,JXNTERNAL:NRR/DE/EELBNRR/DRCH/HICBNRR/DSSA/SPLBNUDOCS-ABSTRACTOGC/HDS2EXTERNAL:NRCPDRCOPIESLTTRENCL1122111111111011RECIPIENTIDCODE/NAMEPD3-1PDNRR/DORS/OTSBNRR/DRPWNRR/DSSA/SRXBO~CLFDCB01NSICCOPIESLTTRENCL11111111101111DDDNOTETOALL"RIDS"RECIPIENTS:DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTION,LISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR16ENCL14 IndianaMichi~PowerCompai~P.O.Box16631Columbus,OH43216AEP:NRC:1169ADonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74UPDATEFORTECHNICALSPECIFICATIONSCHANGETOINCREASETHEALLOWABLETOLERANCESFORMAINSTEAMSAFETYVALVESU.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyIDecember17,1993
Forwards "DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," to replace analysis attached to 921111 submittal to justify TS change to increase allowable tolerances.
DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution ENCL      SIZE  SF/
NOTES:
RECXPIENT              COPIES            RECIPIENT          COPIES            D ID  CODE/NAME          LTTR ENCL      ID  CODE/NAME      LTTR ENCL PD3-1 LA                      1    1    PD3-1 PD              1    1            D HICKMAN,J                      2    2 XNTERNAL: NRR/DE/EELB                    1    1    NRR/DORS/OTS B        1    1 NRR/DRCH/HICB                  1    1    NRR/DRPW              1    1 NRR/DS SA/S PLB                1    1    NRR/DSSA/SRXB          1    1 NUDOCS-ABSTRACT                1    1    O~CLFDCB              1    0 OGC/HDS2                      1    0                    01      1    1 EXTERNAL: NRC PDR                        1    1    NSIC                  1    1 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION, LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR                16  ENCL    14


==DearDr.Murley:==
Indiana Michi~
ThisletterissubmittedtoreplaceananalysisthatwasattachedtoourNovember11,1992submittaltojustifyatechnicalspecificationchangetoincreasetheallowancetolerancesforthemainsteamsafetyvalvesforDonaldC.CookNuclearPlantUnits1and2to+3%.TheanalysisissuedasAttachment4intheoriginalsubmittalassumesnominalratherthanminimumauxiliaryfeedwaterflowsforUnit1.Thisisanon-conservativeassumptionwhenconsideringasmallbreakLOCA,aswasdiscussedwithyourstaffonNovember12,1993.WestinghouseReportSECL-91-429,Revision2,"DonaldC.CookUnits1and2,MainSteamSafetyValveLiftSetpointToleranceRelaxation,"isfoundinAttachment1ofthisletter.Unit2auxiliaryfeedwaterflowassumptionswerecorrectintheoriginalsubmittal.Attachment1hasbeenupdatedwiththecorrectauxiliaryfeedwaterflowsforUnit1andtheresultsdonotchangetheconclusionsreachedintheoriginalsubmittalletter.PleasereplaceAttachment4oftheNovemberll,1992letterwithAttachment1ofthisletter.9312230045931217PDRADOCK05000315.P,'DR Dr.T.E.Murley2-AEPNRC:1169AThisletterissubmittedpursuantto10CFR50.54(f)and,assuchanoathstatementisattached.Sincerely,VicePresidentcadAttachmentcc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspectorJ.R.Padgett Dr.T.E.Murley3AEP:NRC:1169Abc:S.J.BrewerD.H.MalinM.L.Horvath-Bridgman-w/oattachmentJ.B.KingseedD.F.PowellJ.B.Shinnock-w/oattachmentW.G.Smith,Jr.J.B.Hickman,NRC-Washington,D.C.AEP'NRC'1169ADC-N-6015.1-w/oattachment STATEOFOHIO)COUNTYOFFRANKLIN)E.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingUPDATEFORTECHNICALSPECIFICATIONSCHANGETOINCREASETHEALLOWABLETOLERANCESFORMAINSTEAMSAFETYVALVESandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.Subscribedandsworntobeforemethis~~~dayof19~8NOTARPUBLICRITAD.HILLHOTARVPUCI.IC.STATOFOHIOf8COI,IMISSIOXDIPIRiS ATTACHMENT1toAEP:NRC:1169AWESTINGHOUSEREPORTSECL-91-429,Revision2,"DONALDC.COOKUNITS1AND2MAINSTEAMSAFETYVALVELIFTSETPOINTTOLERANCERELAXATION" hyI!1}}
Power Compai~
P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1169A Donald C. Cook Nuclear Plant Units      1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO            INCREASE  THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T.      E. Murley I
December      17, 1993
 
==Dear Dr. Murley:==
 
This letter is submitted to replace an analysis that was attached to our November 11, 1992 submittal to justify a technical specification change to increase the allowance tolerances for the main steam safety valves for Donald C. Cook Nuclear Plant Units 1 and 2 to + 3%.           The analysis issued as Attachment 4 in the original submittal assumes nominal rather than minimum auxiliary feedwater flows for Unit 1. This is a non-conservative assumption when considering a small break LOCA, as was discussed with your staff on November 12, 1993. Westinghouse Report SECL-91-429, Revision 2, "Donald C. Cook Units 1 and 2, Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," is found in Attachment 1 of this letter. Unit 2 auxiliary feedwater flow assumptions were correct in the original submittal. Attachment 1 has been updated with the correct auxiliary feedwater flows for Unit 1 and the results do not change the conclusions reached in the original submittal letter.           Please  replace Attachment 4 of the November      ll, 1992 letter with Attachment 1 of this letter.
9312230045  931217 PDR  ADOCK 05000315
.P   ,           'DR
 
Dr. T. E. Murley                  2-               AEP NRC:1169A This letter is submitted pursuant to 10 CFR 50.54(f) and, as such an oath statement is attached.
Sincerely, Vice President cad Attachment cc:   A. A. Blind G. Charnoff J. B. Martin - Region  III NFEM Section  Chief NRC Resident  Inspector J. R. Padgett
 
Dr. T. E. Murley                3              AEP:NRC:1169A bc: S. J. Brewer D. H. Malin M. L. Horvath - Bridgman - w/o attachment J. B. Kingseed D. F. Powell J. B. Shinnock - w/o attachment W. G. Smith, Jr.
J. B. Hickman, NRC - Washington, D. C.
AEP'NRC'1169A DC-N-6015.1 - w/o attachment
 
STATE OF OHIO)
COUNTY OF FRANKLIN)
E. E. Fitzpatrick, being duly sworn, deposes and says that he  is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES and knows the contents thereof; and  that said contents are true to the best of his                knowledge and  belief.
Subscribed and sworn to before    me this    ~~~
day of                                  19  ~8 NOTAR        PUBLIC RITA D. HILL HOTARV PUCI.IC. STAT OF OHIO f8 COI,IMISSIOX DIPIRiS
 
ATTACHMENT 1  to AEP:NRC:1169A WESTINGHOUSE REPORT  SECL-91-429, Revision 2, "DONALD C. COOK UNITS 1 AND 2 MAIN STEAM SAFETY VALVE LIFT SETPOINT TOLERANCE RELAXATION"
 
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1}}

Latest revision as of 13:56, 22 October 2019

Forwards DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation, to Replace Analysis Attached to 921111 Submittal to Justify TS Change to Increase Allowable Tolerances
ML17331B131
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 12/17/1993
From: Fitzpatrick E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17331B132 List:
References
AEP:NRC:1169A, NUDOCS 9312230045
Download: ML17331B131 (7)
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Text

" ' ACCELERATED ISTRIBUTION DEMON/'RATION SYSTEM I '!

REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)

ACCESSXON NBR:9312230045 DOC.DATE: 93/12/17 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRXCK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECXP.NAME RECIPIENT AFFILIATION R MURLEY,T.E. Document Control Branch (Document Control Desk)

SUBJECT:

Forwards "DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," to replace analysis attached to 921111 submittal to justify TS change to increase allowable tolerances.

DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution ENCL SIZE SF/

NOTES:

RECXPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 2 2 XNTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTS B 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DS SA/S PLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 O~CLFDCB 1 0 OGC/HDS2 1 0 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION, LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14

Indiana Michi~

Power Compai~

P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1169A Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley I

December 17, 1993

Dear Dr. Murley:

This letter is submitted to replace an analysis that was attached to our November 11, 1992 submittal to justify a technical specification change to increase the allowance tolerances for the main steam safety valves for Donald C. Cook Nuclear Plant Units 1 and 2 to + 3%. The analysis issued as Attachment 4 in the original submittal assumes nominal rather than minimum auxiliary feedwater flows for Unit 1. This is a non-conservative assumption when considering a small break LOCA, as was discussed with your staff on November 12, 1993. Westinghouse Report SECL-91-429, Revision 2, "Donald C. Cook Units 1 and 2, Main Steam Safety Valve Lift Setpoint Tolerance Relaxation," is found in Attachment 1 of this letter. Unit 2 auxiliary feedwater flow assumptions were correct in the original submittal. Attachment 1 has been updated with the correct auxiliary feedwater flows for Unit 1 and the results do not change the conclusions reached in the original submittal letter. Please replace Attachment 4 of the November ll, 1992 letter with Attachment 1 of this letter.

9312230045 931217 PDR ADOCK 05000315

.P , 'DR

Dr. T. E. Murley 2- AEP NRC:1169A This letter is submitted pursuant to 10 CFR 50.54(f) and, as such an oath statement is attached.

Sincerely, Vice President cad Attachment cc: A. A. Blind G. Charnoff J. B. Martin - Region III NFEM Section Chief NRC Resident Inspector J. R. Padgett

Dr. T. E. Murley 3 AEP:NRC:1169A bc: S. J. Brewer D. H. Malin M. L. Horvath - Bridgman - w/o attachment J. B. Kingseed D. F. Powell J. B. Shinnock - w/o attachment W. G. Smith, Jr.

J. B. Hickman, NRC - Washington, D. C.

AEP'NRC'1169A DC-N-6015.1 - w/o attachment

STATE OF OHIO)

COUNTY OF FRANKLIN)

E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing UPDATE FOR TECHNICAL SPECIFICATIONS CHANGE TO INCREASE THE ALLOWABLE TOLERANCES FOR MAIN STEAM SAFETY VALVES and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.

Subscribed and sworn to before me this ~~~

day of 19 ~8 NOTAR PUBLIC RITA D. HILL HOTARV PUCI.IC. STAT OF OHIO f8 COI,IMISSIOX DIPIRiS

ATTACHMENT 1 to AEP:NRC:1169A WESTINGHOUSE REPORT SECL-91-429, Revision 2, "DONALD C. COOK UNITS 1 AND 2 MAIN STEAM SAFETY VALVE LIFT SETPOINT TOLERANCE RELAXATION"

hy I!

1

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