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| | issue date = 12/20/1996 | | | issue date = 12/20/1996 |
| | title = Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency | | | title = Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency |
| | author name = FITZPATRICK E | | | author name = Fitzpatrick E |
| | author affiliation = AMERICAN ELECTRIC POWER CO., INC. | | | author affiliation = AMERICAN ELECTRIC POWER CO., INC. |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 8 | | | page count = 8 |
| | | project = |
| | | stage = Request |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORY1REGULATOROINFORMATZON DISTRIBUTION TEM(RIDE)ACCESSION NBR:9612270111 DOC.DATE: | | {{#Wiki_filter:CATEGORY 1 REGULATOROINFORMATZON DISTRIBUTION TEM (RIDE) |
| 96/12/20NOTARIZED: | | ACCESSION NBR:9612270111 DOC.DATE: 96/12/20 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 FITZPATRICK,E.E American Electric Power Co., Inc. |
| YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E AmericanElectricPowerCo.,Inc.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
| | RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstolicensesDPR-58!'PR-74,requesting revofreactorcoolantpumpflywheelinspfrequency. | | Application for amends to licenses DPR-58 !'PR-74, requesting rev of reactor coolant pump flywheel insp frequency. |
| DISTRIBUTION CODE:AOOZDCOPIESRECEIVED:LTR 1ENCLiSIZE:4I4TITLE:ORSubmittal: | | DISTRIBUTION CODE: AOOZD COPIES RECEIVED:LTR 1 ENCL i SIZE: 4I 4 TITLE: OR Submittal: General Distribution E |
| GeneralDistribution NOTES:DOCKET0500031505000316ERECIPIENT IDCODE/NAME PD3-3LAHICKMAN,J INTERNA:MLECENTE0.RDEEMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL:
| | NOTES: |
| NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-3PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS:
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 HICKMAN,J 1 1 INTERNA :M LE CENTE 0. 1 1 NRR/DE/ECGB/A 1 1 R DE EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC NRC PDR 1 1 D |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.
| | U N |
| 415-2083) | | NOTE TO ALL "RIDS" RECIPIENTS: |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| LTTR13ENCL.'12 IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071395 INQMNANICNESANPQWMDecember20,1996DocketNo:50-31550-316AEP:NRC:1245 10CFR50.90U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Gentlemen:
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL . '12 |
| DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR"74PROPOSEDLICENSEANDTECHNICAL SPECIFICATION CHANGESOFREACTORCOOLANTPUMPFLYWHEELINSPECTION FREQUENCY Thisletteranditsattachments constitute anapplication foramendment ofthetechnical specifications (T/S)forCookNuclearPlantunits1and2.Changesareproposedtoreducethefrequency andscopeofreactorcoolantpumpflywheelinspections consistent withyourstaff'sevaluation ofWCAP-14535, "TopicalReportonReactorCoolantPumpFlywheelInspection Elimination."
| |
| Adescription oftheproposedchangesandananalysisconcerning significant hazardsconsideration pursuantto10CFR50.92iscontained inattachment 1.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment
| |
| .3containstheproposed, revisedT/Spages.WebelievetheproposedT/Schangeswillnotresultinasignificant changeinthetypesofeffluents orasignificant increaseintheamountofeffluentthatmightbereleasedoffsite,orasignificant increaseinindividual orcumulative occupational radiation exposure.
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| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee~
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| .Incompliance withtherequirements of10CFR50.91(b)(1),
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| copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment.
| |
| ofPublicHealth.Sincerely, SWORNTOANDSUBSCRIBED BEFOREMEITHIS~ODAYOF~~Mt1996E.E.Fitpatrick96OO3VicePresident Attachments NotaryPublicMyCommission Expires:JANWATSONNOTARYPUBUC,BERRIENCOUNTY,MIIMYCOMMISSION EXPIRESFEB101999'Pbi2270iii 9hi220PDRADQCK050003l5PPDR J1';C.1Wtq'ae4~Ia,<<W*<<i~u~""C U.S.NuclearRegulatory Commission Page2AEP:NRC:1245cc:A.A.BlindA.B.BeachMDEQ"DWEcRPDNRCResidentInspector J.R.Padgett ATTACHMENT 1TOAEP:NRC:124S 10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:1245 Page11.0SECTIONTOBECHANGED1.Unit1technical specification (T/S)4.4.10.12.Unit2T/S4.4.10.12.0EXTENTOFCHANGES1.Weareproposing tochangeunit1T/S4.4.10.1torequirereactorcoolantpump(RCP)flywheelinspections onceevery10yearsinthemannerdescribed below.Weareproposing tochangeunit2T/S4.4.10.1torequireRCPflywheelinspections onceevery10yearsinthemannerdescribed below.3.0CHANGESREUESTEDWeareproposing tomakethefollowing changetotheunit1andunit2T/Ss.Currently T/Ssection4.4.10.1requiresthateachreactorcoolantpumpflywheelbeinspected pertherecommendations ofregulatory positionC.4.bofRegulatory Guide(RG)1.14,Revision1,August1975.Theregulatory positionofRG1.14concerning ISIcallsforanin-placeultrasonic volumetric examination oftheareasofhigherstressconcentration attheboreandkeywayatapproximately 3-yearintervals andasurfaceexamination ofallexposedsurfacesandcompleteultrasonic volumetric examination atapproximately 10-yearintervals.
| |
| TheproposedT/Srequiresthateitheraqualified in-placeUTexamination overthevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination (MTand/orPT)ofexposedsurfacesdefinedbythevolumeofthedisassembled flywheels beconducted onceevery10years.4.0DISCUSSION Technical Secification 4.4.10.1BasesT/S4.4.10.1ensuresthatthestructural integrity ofthereactorcoolantpumpflywheels willbemaintained atanacceptable levelthroughout thelifeoftheplant.Justification forProosedTechnical Secification ChanesTheproposedT/Samendment requesttoreducethefrequency andscopeofsurveillance oftheRCPflywheels isjustified forseveralreasons.Thischangeisconsistent withMr.Sheron's(Director DivisionofEngineering, OfficeofNuclearReactorRegulation) letterentitled"Acceptance forReferencing ofTopicalReportWCAP-14535,'TopicalReportonReactorCoolantPumpFlywheelInspection Elimination' andrelatedattachments.
| |
| Pertherequirement ofthisletter,wehaveconfirmed thattheRCPflywheels inplaceatCookNuclearPlantarecomposedofSA533Bmaterial.
| |
| ThoughWestinghouse ElectricCorporation reportWCAP-14535, entitled"TopicalReportonReactorCoolantPumpFlywheelInspection Elimination",
| |
| seekselimination offlywheelinspections, weonly Attachment 1toAEP:NRC:1245 Page2seektoreducethefrequency oftheseinspections toonceevery10years.WCAP-14535-concludes thefollowing.
| |
| 1.Flywheels arecarefully designedandmanufactured fromexcellent qualitysteel,whichhasahighfracturetoughness.
| |
| 2.Flywheeloverspeed isthecriticalloading,butleakbeforebreakhaslimitedthemaximumspeedtolessthan1500rpm.6.7.Flywheelinspections havebeenperformed for2Cyears,withnoindications ofserviceinducedflaws.Flywheelintegrity evaluations showveryhighflawtolerance fortheflywheels.
| |
| Crackextension overa60yearservicelifeisnegligible.
| |
| Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlife willnotsignificantly changetheprobability offailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreservice inspection oratworstearlyinplantlife,andcrackgrowthoverplantlifeisnegligible.
| |
| AsstatedintheSERassociated withWCAP-14535, assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Inspections resultinmanremexposureandthepotential forflywheeldamageduringdisassembly andreassembly.
| |
| Basedontheaboveconclusions, inspections ofRCPflywheels witha10-yearfrequency andmodifiedscopearejustified.
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| ==5.0 NOSIGNIFICANT==
| | Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071395 INQMNA NICNESAN PQWM December 20, 1996 AEP:NRC:1245 10 CFR 50.90 Docket No: 50-315 50-316 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: |
| HAZARDSCONSIDERATION Wehaveevaluated theproposedT/Schangesandhavedetermined they'onotrepresent asignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c).Operation ofCookNuclearPlantinaccordance withtheproposedamendment willnot:1.Involveasinificantincreaseintherobabilit orconseenceofanaccidentreviouslevaluated Thischangewillreducetnefrequency andscopeofthesurveillance testingonthereactorcoolantpumpflywheels.
| | Donald C. Cook Nuclear Plant Units 1 and 2 LICENSE NOS. DPR-58 AND DPR"74 PROPOSED LICENSE AND TECHNICAL SPECIFICATION CHANGES OF REACTOR COOLANT PUMP FLYWHEEL INSPECTION FREQUENCY This letter and its attachments constitute an application for amendment of the technical specifications (T/S) for Cook Nuclear Plant units 1 and 2. Changes are proposed to reduce the frequency and scope of reactor coolant pump flywheel inspections consistent with your staff's evaluation of WCAP-14535, "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination." |
| Operating powerplantshavebeeninspecting theirflywheels forover20yearswithnoflawsidentified whichaffectflywheelintegrity. | | A description of the proposed changes and an analysis concerning significant hazards consideration pursuant to 10 CFR 50.92 is contained in attachment 1. Attachment 2 contains the existing T/S pages marked to reflect the proposed changes. Attachment .3 contains the proposed, revised T/S pages. |
| Pastexaminations performed tosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextension overa60yearservicelifeisnegligible.
| | We believe the proposed T/S changes will not result in a significant change in the types of effluents or a significant increase Committee in the amount of effluent that might be released offsite, or a significant increase in individual or cumulative occupational radiation exposure. |
| Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlifewillnotsignificantly change'he probability offailure.Mostflawswhichcouldleadto Attachment 1toAEP:NRC:1245 Page3failurewouldbedetectedduringpreservice inspection or,atworst,earlyinplantlife,andcrackgrowthoverplantlifeisnegligible. | | These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the Michigan Department. of Public Health. |
| AsstatedintheSERassociated withWCAP-14535, assuminganinitialcrackof10%ofthedistancefromthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgrowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Therefore, thechangeintestfrequency willnotendangerpublichealthorsafety.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated accident.
| | Sincerely, SWORN TO AND SUBSCRIBED BEFORE ME I |
| Createtheossibilit ofanewordifferent kindofaccidentfromanaccidentreviouslevaluated.
| | THIS ~O DAY OF ~~Mt 1996 E. E. Fit patrick Vice President Notary Public My Commission Expires: |
| Thechangeswillnotintroduce anynewmodesofplantoperation, norwillanyphysicalchangestotheplantberequired.
| | Attachments JAN WATSON 96 O O3 NOTARY PUBUC, BERRIEN COUNTY, MI I MY COMMISSION EXPIRES FEB 10 1999 |
| Thus,thechangeswillnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated. | | 'Pbi2270iii 9hi220 PDR ADQCK 050003l5 P PDR |
| 3.Involveasinificantreduction inamarinofaafetThischangewillreducethefrequency andscopeofthesurveillance testingonthereactorcoolantpumpflywheels. | | |
| Operating powerplantshavebeeninspecting theirflywheels forover20yearswithnoflawsidentified whichaffectflywheelintegrity. | | 1' J |
| Pastexaminations performed tosatisfyT/S4.4.10.1havenotrevealedanycrackingofflywheelplatesatCookNuclearPlant.Crackextension overa60yearservicelifeisnegligible.
| | 1W t q' |
| Structural reliability studieshaveshownthateliminating inspections after10yearsofplantlifewillnotsignificantly changetheprobability offailure.Mostflawswhichcouldleadtofailurewouldbedetectedduringpreservice irepection oratw'orstearlyinplantlife,andcrackgr.~thoverplantlifeisnegligible. | | a e 4 |
| AsstatedintheSERassociated withWCAP-,14535,assuminganinitialcrackof10%ofthedistancef'romthekeywaytotheflywheelouterradiusandamaximumfatiguecrackgiowth,ASMEmarginswouldbemaintained duringthe10-yearinspection period.Forthesereasons,itisourbelieftheproposedchangesdonotinvolveasignificant reduction inamarginofsafety.6.0PENDINGTSPROPOSALS IMPACTING THISSUBMITTAL TherearenootherT/Sproposals underreviewthatimpactthissubmittal~
| | ~ |
| .}} | | ; I C. |
| | a |
| | ,<<W* |
| | C <<i ~ u~"" |
| | |
| | U. S. Nuclear Regulatory Commission AEP: NRC: 1245 Page 2 cc: A. A. Blind A. B. Beach MDEQ " DW Ec RPD NRC Resident Inspector J. R. Padgett |
| | |
| | ATTACHMENT 1 TO AEP:NRC:124S 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS to AEP:NRC:1245 Page 1 1.0 SECTION TO BE CHANGED |
| | : 1. Unit 1 technical specification (T/S) 4.4.10.1 |
| | : 2. Unit 2 T/S 4.4. 10. 1 2.0 EXTENT OF CHANGES |
| | : 1. We are proposing to change unit 1 T/S 4.4.10.1 to require reactor coolant pump (RCP) flywheel inspections once every 10 years in the manner described below. |
| | We are proposing to change unit 2 T/S 4.4.10.1 to require RCP flywheel inspections once every 10 years in the manner described below. |
| | 3.0 CHANGES RE UESTED We are proposing to make the following change to the unit 1 and unit 2 T/Ss. |
| | Currently T/S section 4.4.10.1 requires that each reactor coolant pump flywheel be inspected per the recommendations of regulatory position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975. |
| | The regulatory position of RG 1. 14 concerning ISI calls for an in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals and a surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals. The proposed T/S requires that either a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces defined by the volume of the disassembled flywheels be conducted once every 10 years. |
| | 4.0 DISCUSSION Technical S ecification 4.4.10.1 Bases T/S 4.4.10.1 ensures that the structural integrity of the reactor coolant pump flywheels will be maintained at an acceptable level throughout the life of the plant. |
| | Justification for Pro osed Technical S ecification Chan es The proposed T/S amendment request to reduce the frequency and scope of surveillance of the RCP flywheels is justified for several reasons. This change is consistent with Mr. Sheron's (Director Division of Engineering, Office of Nuclear Reactor Regulation) letter entitled "Acceptance for Referencing of Topical Report WCAP-14535, 'Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination' and related attachments. Per the requirement of this letter, we have confirmed that the RCP flywheels in place at Cook Nuclear Plant are composed of SA 533 B material. Though Westinghouse Electric Corporation report WCAP-14535, entitled "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination", seeks elimination of flywheel inspections, we only |
| | |
| | Attachment 1 to AEP:NRC:1245 Page 2 seek to reduce the frequency of these inspections to once every 10 years. WCAP-14535- concludes the following. |
| | : 1. Flywheels are carefully designed and manufactured from excellent quality steel, which has a high fracture toughness. |
| | : 2. Flywheel overspeed is the critical loading, but leak before break has limited the maximum speed to less than 1500 rpm. |
| | Flywheel inspections have been performed for 2C years, with no indications of service induced flaws. |
| | Flywheel integrity evaluations show very high flaw tolerance for the flywheels. |
| | Crack extension over a 60 year service life is negligible. |
| | : 6. Structural reliability studies have shown that eliminating inspections after 10 years of plantlife will not significantly change the probability of failure. Most flaws which could lead to failure would be detected during preservice inspection or at worst early in plant life, and crack growth over plant life is negligible. As stated in the SER associated with WCAP-14535, assuming an initial crack of 10% of the distance from the keyway to the flywheel outer radius and a maximum fatigue crack growth, ASME margins would be maintained during the 10-year inspection period. |
| | : 7. Inspections result in man rem exposure and the potential for flywheel damage during disassembly and reassembly. |
| | Based on the above conclusions, inspections of RCP flywheels with a 10-year frequency and modified scope are justified. |
| | : 5. 0 NO SIGNIFICANT HAZARDS CONSIDERATION |
| | 'ocriteria We have evaluated the proposed T/S not represent a established in 10 CFR changes and have determined they significant hazards 50.92(c) . |
| | consideration based on the Operation of Cook Nuclear Plant in accordance with the proposed amendment will not: |
| | : 1. Involve a si nificant increase in the robabilit or conse ence of an accident reviousl evaluated This change will reduce tne frequency and scope of the surveillance testing on the reactor coolant pump flywheels. Operating power plants have been inspecting their flywheels for over 20 years with no flaws identified which affect flywheel integrity. Past examinations performed to satisfy T/S 4.4.10.1 have not revealed any cracking of flywheel plates at Cook Nuclear Plant. Crack extension over a 60 year service life is negligible. Structural reliability studies have shown that eliminating inspections after 10 years of plant life will not significantly change'he probability of failure. Most flaws which could lead to to AEP:NRC:1245 Page 3 failure would be detected during preservice inspection or, at worst, early in plant life, and crack growth over plant life is negligible. As stated in the SER associated with WCAP-14535, assuming an initial crack of 10% of the distance from the keyway to the flywheel outer radius and a maximum fatigue crack growth, ASME margins would be maintained during the 10-year inspection period. Therefore, the change in test frequency will not endanger public health or safety. |
| | For these reasons, it is our belief the proposed changes do not involve a significant increase in the probability or consequences of a previously evaluated accident. |
| | Create the ossibilit of a new or different kind of accident from an accident reviousl evaluated. |
| | The changes will not introduce any new modes of plant operation, nor will any physical changes to the plant be required. Thus, the changes will not create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated. |
| | : 3. Involve a si nificant reduction in a mar in of aafet This change will reduce the frequency and scope of the surveillance testing on the reactor coolant pump flywheels. Operating power plants have been inspecting their flywheels for over 20 years with no flaws identified which affect flywheel integrity. Past examinations performed to satisfy T/S 4.4.10.1 have not revealed any cracking of flywheel plates at Cook Nuclear Plant. Crack extension over a 60 year service life is negligible. Structural reliability studies have shown that eliminating inspections after 10 years of plant life will not significantly change the probability of failure. Most flaws which could lead to failure would be detected during preservice irepection or at w'orst early in plant life, and crack gr .~th over plant life is negligible. As stated in the SER associated with WCAP-, 14535, assuming an initial crack of 10% of the distance f'rom the keyway to the flywheel outer radius and a maximum fatigue crack giowth, ASME margins would be maintained during the 10-year submittal inspection period. For these reasons, it is our belief the proposed changes do not involve a significant reduction in a margin of safety. |
| | 6.0 PENDING T S PROPOSALS IMPACTING THIS SUBMITTAL There are no other T/S proposals under review that impact this |
| | .}} |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
CATEGORY 1 REGULATOROINFORMATZON DISTRIBUTION TEM (RIDE)
ACCESSION NBR:9612270111 DOC.DATE: 96/12/20 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 FITZPATRICK,E.E American Electric Power Co., Inc.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to licenses DPR-58 !'PR-74, requesting rev of reactor coolant pump flywheel insp frequency.
DISTRIBUTION CODE: AOOZD COPIES RECEIVED:LTR 1 ENCL i SIZE: 4I 4 TITLE: OR Submittal: General Distribution E
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 HICKMAN,J 1 1 INTERNA :M LE CENTE 0. 1 1 NRR/DE/ECGB/A 1 1 R DE EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC NRC PDR 1 1 D
U N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL . '12
Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071395 INQMNA NICNESAN PQWM December 20, 1996 AEP:NRC:1245 10 CFR 50.90 Docket No: 50-315 50-316 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and 2 LICENSE NOS. DPR-58 AND DPR"74 PROPOSED LICENSE AND TECHNICAL SPECIFICATION CHANGES OF REACTOR COOLANT PUMP FLYWHEEL INSPECTION FREQUENCY This letter and its attachments constitute an application for amendment of the technical specifications (T/S) for Cook Nuclear Plant units 1 and 2. Changes are proposed to reduce the frequency and scope of reactor coolant pump flywheel inspections consistent with your staff's evaluation of WCAP-14535, "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination."
A description of the proposed changes and an analysis concerning significant hazards consideration pursuant to 10 CFR 50.92 is contained in attachment 1. Attachment 2 contains the existing T/S pages marked to reflect the proposed changes. Attachment .3 contains the proposed, revised T/S pages.
We believe the proposed T/S changes will not result in a significant change in the types of effluents or a significant increase Committee in the amount of effluent that might be released offsite, or a significant increase in individual or cumulative occupational radiation exposure.
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the Michigan Department. of Public Health.
Sincerely, SWORN TO AND SUBSCRIBED BEFORE ME I
THIS ~O DAY OF ~~Mt 1996 E. E. Fit patrick Vice President Notary Public My Commission Expires:
Attachments JAN WATSON 96 O O3 NOTARY PUBUC, BERRIEN COUNTY, MI I MY COMMISSION EXPIRES FEB 10 1999
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U. S. Nuclear Regulatory Commission AEP: NRC: 1245 Page 2 cc: A. A. Blind A. B. Beach MDEQ " DW Ec RPD NRC Resident Inspector J. R. Padgett
ATTACHMENT 1 TO AEP:NRC:124S 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS to AEP:NRC:1245 Page 1 1.0 SECTION TO BE CHANGED
- 1. Unit 1 technical specification (T/S) 4.4.10.1
- 2. Unit 2 T/S 4.4. 10. 1 2.0 EXTENT OF CHANGES
- 1. We are proposing to change unit 1 T/S 4.4.10.1 to require reactor coolant pump (RCP) flywheel inspections once every 10 years in the manner described below.
We are proposing to change unit 2 T/S 4.4.10.1 to require RCP flywheel inspections once every 10 years in the manner described below.
3.0 CHANGES RE UESTED We are proposing to make the following change to the unit 1 and unit 2 T/Ss.
Currently T/S section 4.4.10.1 requires that each reactor coolant pump flywheel be inspected per the recommendations of regulatory position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975.
The regulatory position of RG 1. 14 concerning ISI calls for an in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals and a surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals. The proposed T/S requires that either a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces defined by the volume of the disassembled flywheels be conducted once every 10 years.
4.0 DISCUSSION Technical S ecification 4.4.10.1 Bases T/S 4.4.10.1 ensures that the structural integrity of the reactor coolant pump flywheels will be maintained at an acceptable level throughout the life of the plant.
Justification for Pro osed Technical S ecification Chan es The proposed T/S amendment request to reduce the frequency and scope of surveillance of the RCP flywheels is justified for several reasons. This change is consistent with Mr. Sheron's (Director Division of Engineering, Office of Nuclear Reactor Regulation) letter entitled "Acceptance for Referencing of Topical Report WCAP-14535, 'Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination' and related attachments. Per the requirement of this letter, we have confirmed that the RCP flywheels in place at Cook Nuclear Plant are composed of SA 533 B material. Though Westinghouse Electric Corporation report WCAP-14535, entitled "Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination", seeks elimination of flywheel inspections, we only
Attachment 1 to AEP:NRC:1245 Page 2 seek to reduce the frequency of these inspections to once every 10 years. WCAP-14535- concludes the following.
- 1. Flywheels are carefully designed and manufactured from excellent quality steel, which has a high fracture toughness.
- 2. Flywheel overspeed is the critical loading, but leak before break has limited the maximum speed to less than 1500 rpm.
Flywheel inspections have been performed for 2C years, with no indications of service induced flaws.
Flywheel integrity evaluations show very high flaw tolerance for the flywheels.
Crack extension over a 60 year service life is negligible.
- 6. Structural reliability studies have shown that eliminating inspections after 10 years of plantlife will not significantly change the probability of failure. Most flaws which could lead to failure would be detected during preservice inspection or at worst early in plant life, and crack growth over plant life is negligible. As stated in the SER associated with WCAP-14535, assuming an initial crack of 10% of the distance from the keyway to the flywheel outer radius and a maximum fatigue crack growth, ASME margins would be maintained during the 10-year inspection period.
- 7. Inspections result in man rem exposure and the potential for flywheel damage during disassembly and reassembly.
Based on the above conclusions, inspections of RCP flywheels with a 10-year frequency and modified scope are justified.
- 5. 0 NO SIGNIFICANT HAZARDS CONSIDERATION
'ocriteria We have evaluated the proposed T/S not represent a established in 10 CFR changes and have determined they significant hazards 50.92(c) .
consideration based on the Operation of Cook Nuclear Plant in accordance with the proposed amendment will not:
- 1. Involve a si nificant increase in the robabilit or conse ence of an accident reviousl evaluated This change will reduce tne frequency and scope of the surveillance testing on the reactor coolant pump flywheels. Operating power plants have been inspecting their flywheels for over 20 years with no flaws identified which affect flywheel integrity. Past examinations performed to satisfy T/S 4.4.10.1 have not revealed any cracking of flywheel plates at Cook Nuclear Plant. Crack extension over a 60 year service life is negligible. Structural reliability studies have shown that eliminating inspections after 10 years of plant life will not significantly change'he probability of failure. Most flaws which could lead to to AEP:NRC:1245 Page 3 failure would be detected during preservice inspection or, at worst, early in plant life, and crack growth over plant life is negligible. As stated in the SER associated with WCAP-14535, assuming an initial crack of 10% of the distance from the keyway to the flywheel outer radius and a maximum fatigue crack growth, ASME margins would be maintained during the 10-year inspection period. Therefore, the change in test frequency will not endanger public health or safety.
For these reasons, it is our belief the proposed changes do not involve a significant increase in the probability or consequences of a previously evaluated accident.
Create the ossibilit of a new or different kind of accident from an accident reviousl evaluated.
The changes will not introduce any new modes of plant operation, nor will any physical changes to the plant be required. Thus, the changes will not create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated.
- 3. Involve a si nificant reduction in a mar in of aafet This change will reduce the frequency and scope of the surveillance testing on the reactor coolant pump flywheels. Operating power plants have been inspecting their flywheels for over 20 years with no flaws identified which affect flywheel integrity. Past examinations performed to satisfy T/S 4.4.10.1 have not revealed any cracking of flywheel plates at Cook Nuclear Plant. Crack extension over a 60 year service life is negligible. Structural reliability studies have shown that eliminating inspections after 10 years of plant life will not significantly change the probability of failure. Most flaws which could lead to failure would be detected during preservice irepection or at w'orst early in plant life, and crack gr .~th over plant life is negligible. As stated in the SER associated with WCAP-, 14535, assuming an initial crack of 10% of the distance f'rom the keyway to the flywheel outer radius and a maximum fatigue crack giowth, ASME margins would be maintained during the 10-year submittal inspection period. For these reasons, it is our belief the proposed changes do not involve a significant reduction in a margin of safety.
6.0 PENDING T S PROPOSALS IMPACTING THIS SUBMITTAL There are no other T/S proposals under review that impact this
.