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| {{#Wiki_filter:RIORITY]ACCELERATED RIDSPROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9506200465 DOC.DATE: | | {{#Wiki_filter:RIORITY]ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9506200465 DOC.DATE: 95/06/15 NOTARIZED: |
| 95/06/15NOTARIZED: | | YES DOCKET g 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. |
| YESDOCKETgFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
| | Indiana Michigan Power Co.(formerly Xndiana&Michigan Ele F'ECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)R |
| IndianaMichiganPowerCo.(formerly Xndiana&MichiganEleF'ECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)R
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstolicensesDPR-58&DPR-74,revising TS4.8.1.1.2.e.7 toreducedurationofsurveillance testingforEDGsduringrefueling operations from24hto8h.DISTR1BUTION CODE:AOOIDCOPIESRECEIVED:LTR IENCLgSIZE:TITLE:ORSubmittal: | | 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.DISTR1BUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL g SIZE: TITLE: OR Submittal: |
| GeneralDistribution NOTES0INTERNALRECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J 1EECENTER1CBNRR/DSSA/SRXB OGC/HDS2COPIESLTTRENCL111111111110RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIESLTTRENCL11111111EXTERNAL:
| | General Distribution NOTES 0 INTERNAL RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J 1E E CENTER 1 CB NRR/DSSA/SRXB OGC/HDS2 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D C U N NOTE TO ALL"RIDS" RECIPIENTS: |
| NOAC11NRCPDR11DCUNNOTETOALL"RIDS"RECIPIENTS:
| | PLEASE HELP US TO REDUCE KVASTE!CONTACT THE DOCUiIENT CONTROL DESK, ROOM PI-37 (EXT.504-2083)TO ELIS!!NATE YOUR 4AML FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON"I'EED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 |
| PLEASEHELPUSTOREDUCEKVASTE!CONTACTTHEDOCUiIENT CONTROLDESK,ROOMPI-37(EXT.504-2083)TOELIS!!NATE YOUR4AMLFROMDISTRIBUTION LISTSI'ORDOCUMENTS YOUDON"I'EED!TOTALNUMBEROFCOPIESREQUIRED:
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| IndianaMicIdganPowerCompany~ŽP.O.Box16631Columbus, OH43216June15,1995AEP:NRC:0896V DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
| | Indiana MicIdgan Power Company~ŽP.O.Box 16631 Columbus, OH 43216 June 15, 1995 AEP:NRC:0896V Docket Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen: |
| DonaldC.CookNuclearPlantUnits1and2TECHNICAL SPECIFICATION CHANGESTOMODIFYSURVEILLANCE TESTINGOFTHEEMERGENCY DIESELGENERATORS DURINGREFUELING Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantUnits1and2.Specifically, weareproposing toimplement changestomodifysurveillance testingfortheemergency dieselgenerators (EDGs)duringrefueling operations.
| | Donald C.Cook Nuclear Plant Units 1 and 2 TECHNICAL SPECIFICATION CHANGES TO MODIFY SURVEILLANCE TESTING OF THE EMERGENCY DIESEL GENERATORS DURING REFUELING This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss)for Donald C.Cook Nuclear Plant Units 1 and 2.Specifically, we are proposing to implement changes to modify surveillance testing for the emergency diesel generators (EDGs)during refueling operations. |
| Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Attachment 4providesatechnical evaluation report.Inaddition, thisisacostbeneficial licensing action(CBLA)submittal andrepresents ahighpriorityitemsinceitwill,onceapproved, resultinasignificant reduction inoperating cost.Thelifetimecostsavingassociated withthisCBLAisapproximately | | Attachment 1 provides a detailed description of the proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92.Attachment 2 contains the existing T/S pages marked to reflect the proposed changes.Attachment 3 contains the proposed T/S pages.Attachment 4 provides a technical evaluation report.In addition, this is a cost beneficial licensing action (CBLA)submittal and represents a high priority item since it will, once approved, result in a significant reduction in operating cost.The lifetime cost saving associated with this CBLA is approximately |
| $600,000,asdetailedinAttachment 5.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. | | $600,000, as detailed in Attachment 5.We believe that the proposed changes will not result in (1)a significant change in the types of any effluent that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.l 9506200465 950b15 PDR ADOCK 05000315 p PDR Il'rp-<< |
| l9506200465 950b15PDRADOCK05000315pPDR Il'rp-<<
| | U.S.Nuclear Regulatory Commission Page 2 AEP:NRC:0896V These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at its next regularly scheduled meeting.In compliance with the requirements of 10 CFR 50'1(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health.This letter is submitted pursuant to 10 CFR 50.30(b)and, as such, an oath statement is attached.Sincerely, Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS~beg DAY OF~..1995 No ary Public cad Attachments T |
| U.S.NuclearRegulatory Commission Page2AEP:NRC:0896V TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee atitsnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50'1(b)(1), | | U.S.Nuclear Regulatory Commission Page 3 AEP:NRC:0896V CC: A.A.Blind G.Charnoff J.B.Martin NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett ATTACHMENT 1 TO AEP:NRC:0896V DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS Attachment 1 to AEP:NRC:0896V Page 1 A.DESCRIPTION OF CHANGES The changes proposed by this letter involve the emergency diesel generator (EDG)18 month 24 hour surveillance test.The changes are described individually as follows: Emergency Diesel Generator Surveillance Requirements T/S: 4.8.1.1.2.e.7 (Units 1 and 2)Page: 3/4 8-6 (Units 1 and 2)1)Reduce the duration of the surveillance test from 24 hours to 8 hours.2)Modify the footnote associated with the asterisk at the end of 4.8.1.1.2.e.7 to reflect the reduction of the surveillance test from 24 hours to 8 hours.B.JUSTIFICATION FOR CHANGES The proposed changes involve the 18 month 24 hour EDG surveillance which is implemented by plant procedure. |
| copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.30(b)and,assuch,anoathstatement isattached.
| | The proposed changes are designed to reduce operating costs, increase outage scheduling flexibility, reduce shutdown risk, and increase diesel life.Reducing the surveillance time from 24 to 8 hours would significantly improve outage performance without reducing EDG reliability. |
| Sincerely, VicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS~begDAYOF~..1995NoaryPubliccadAttachments T | | Based on examination of Cook Nuclear Plant test data.from'1974 to 1994, it is clear that extensive run times beyond.the..''point where the EDG'i's sta'rted, loa'ded to:3500KW, and achieves an e'quilibrium |
| U.S.NuclearRegulatory Commission Page3AEP:NRC:0896V CC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector | | .condition provide'ittle insight regarding EDG.reliability. |
| -BridgmanJ.R.Padgett ATTACHMENT 1TOAEP:NRC:0896V DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:0896V Page1A.DESCRIPTION OFCHANGESThechangesproposedbythisletterinvolvetheemergency dieselgenerator (EDG)18month24hoursurveillance test.Thechangesaredescribed individually asfollows:Emergency DieselGenerator Surveillance Requirements T/S:4.8.1.1.2.e.7 (Units1and2)Page:3/48-6(Units1and2)1)Reducethedurationofthesurveillance testfrom24hoursto8hours.2)Modifythefootnoteassociated withtheasteriskattheendof4.8.1.1.2.e.7 toreflectthereduction ofthesurveillance testfrom24hoursto8hours.B.JUSTIFICATION FORCHANGESTheproposedchangesinvolvethe18month24hourEDGsurveillance whichisimplemented byplantprocedure. | | The engine steady-state characteristics are achieved in approximately'2 ho'urs and the dominant failure modes of the EDG are expected to occur.wi'thin this period.Xn addition, r'eview of the'4.hour,te'st |
| Theproposedchangesaredesignedtoreduceoperating costs,increaseoutagescheduling flexibility, reduceshutdownrisk,andincreasediesellife.Reducingthesurveillance timefrom24to8hourswouldsignificantly improveoutageperformance withoutreducingEDGreliability.
| | " data'rom 1974'to 1994 does'not.;indicate~he, discovery.of any abnoraral conditions that would'have'je'opardized'the' |
| Basedonexamination ofCookNuclearPlanttestdata.from'1974 to1994,itisclearthatextensive runtimesbeyond.the..''pointwheretheEDG'i'ssta'rted, loa'dedto:3500KW, andachievesane'quilibrium
| | 'iesel from completing its mission during an actual emergency demand.Therefore, as described in Attachment 4, reduction of the test duration from a 24 to an 8 hour period will maintain an equivalent level of confidence in EDG reliability and may actually improve overall EDG reliability. |
| .condition provide'ittleinsightregarding EDG.reliability. | | Attachment 1 to AEP:NRC:0896V Page 2 C.10 CFR 50 2 CRITERIA Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration if the change does not: involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety.Criterion 1 The safety function of the EDGs is to supply ac electrical power to plant safety systems whenever the preferred ac power supply is unavailable. |
| Theenginesteady-state characteristics areachievedinapproximately'2 ho'ursandthedominantfailuremodesoftheEDGareexpectedtooccur.wi'thinthisperiod.Xnaddition, r'eviewofthe'4.hour,te'st "data'rom1974'to1994does'not.;indicate~he,discovery
| | Through surveillance requirements, the ability of the EDGs to meet their load and timing requirements is tested and the quality of the fuel and the availability of the fuel supply are monitored. |
| .ofanyabnoraral conditions thatwould'have'je'opardized'the' | | Reduction of the 24 hour run to 8 hours will not reduce the surveillance factors under consideration and will sufficiently exercise the EDG and its support systems to identify potential conditions that could lead to performance degradation (See Attachment 4).Based on these considerations, it is concluded that the proposed changes do not involve a significant increase'n the probability or consequences of an accident previously evaluated. |
| 'ieselfromcompleting itsmissionduringanactualemergency demand.Therefore, asdescribed inAttachment 4,reduction ofthetestdurationfroma24toan8hourperiodwillmaintainanequivalent levelofconfidence inEDGreliability andmayactuallyimproveoverallEDGreliability. | | 0 Criterion 2 The proposed changes do not involve physical changes to the plant or changes.in'lant operating.configuration. |
| Attachment 1toAEP:NRC:0896V Page2C.10CFR502CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificant hazardsconsideration ifthechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, orinvolveasignificant reduction inamarginofsafety.Criterion 1ThesafetyfunctionoftheEDGsistosupplyacelectrical powertoplantsafetysystemswheneverthepreferred acpowersupplyisunavailable. | | The changes only involve the reduction of'18 moth 24:hour EDG.survei3.lanpe test dur'ation, Thus,',it. |
| Throughsurveillance requirements, theabilityoftheEDGstomeettheirloadandtimingrequirements istestedandthequalityofthefuelandtheavailability ofthefuelsupplyaremonitored.
| | is'"~'.concluded that the.proposed changes.do not'create'he possibility of".a new or different kind of accident from any accident previously evaluated. |
| Reduction ofthe24hourrunto8hourswillnotreducethesurveillance factorsunderconsideration andwillsufficiently exercisetheEDGanditssupportsystemstoidentifypotential conditions thatcouldleadtoperformance degradation (SeeAttachment 4).Basedontheseconsiderations, itisconcluded thattheproposedchangesdonotinvolveasignificant increase'n theprobability orconsequences ofanaccidentpreviously evaluated. | | Criterion 3 Although the duration of the 18 month 24 hour EDG surveillance test would be reduce'd, the EDG components will continue to be sufficiently exercised such that the ability to detect incipient and degraded conditions will be maintained (See Attachment 4, Figure 2).The proposed changes have been determined to be compatible with our plant operating experience and commensurate with past surveillance test results.Based on these considerations, it is concluded that the proposed changes do not involve a significant reduction in a margin of safety.}} |
| 0Criterion 2Theproposedchangesdonotinvolvephysicalchangestotheplantorchanges.in'lantoperating
| |
| .configuration. | |
| Thechangesonlyinvolvethereduction of'18moth24:hourEDG.survei3.lanpe testdur'ation, Thus,',it.
| |
| is'"~'.concluded thatthe.proposedchanges.donot'create'he possibility of".anewordifferent kindofaccidentfromanyaccidentpreviously evaluated. | |
| Criterion 3Althoughthedurationofthe18month24hourEDGsurveillance testwouldbereduce'd, theEDGcomponents willcontinuetobesufficiently exercised suchthattheabilitytodetectincipient anddegradedconditions willbemaintained (SeeAttachment 4,Figure2).Theproposedchangeshavebeendetermined tobecompatible withourplantoperating experience andcommensurate withpastsurveillance testresults.Basedontheseconsiderations, itisconcluded thattheproposedchangesdonotinvolveasignificant reduction inamarginofsafety.}} | |
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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
RIORITY]ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9506200465 DOC.DATE: 95/06/15 NOTARIZED:
YES DOCKET g 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.
Indiana Michigan Power Co.(formerly Xndiana&Michigan Ele F'ECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)R
SUBJECT:
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.DISTR1BUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL g SIZE: TITLE: OR Submittal:
General Distribution NOTES 0 INTERNAL RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J 1E E CENTER 1 CB NRR/DSSA/SRXB OGC/HDS2 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D C U N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE KVASTE!CONTACT THE DOCUiIENT CONTROL DESK, ROOM PI-37 (EXT.504-2083)TO ELIS!!NATE YOUR 4AML FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON"I'EED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11
Indiana MicIdgan Power Company~ŽP.O.Box 16631 Columbus, OH 43216 June 15, 1995 AEP:NRC:0896V Docket Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:
Donald C.Cook Nuclear Plant Units 1 and 2 TECHNICAL SPECIFICATION CHANGES TO MODIFY SURVEILLANCE TESTING OF THE EMERGENCY DIESEL GENERATORS DURING REFUELING This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss)for Donald C.Cook Nuclear Plant Units 1 and 2.Specifically, we are proposing to implement changes to modify surveillance testing for the emergency diesel generators (EDGs)during refueling operations.
Attachment 1 provides a detailed description of the proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92.Attachment 2 contains the existing T/S pages marked to reflect the proposed changes.Attachment 3 contains the proposed T/S pages.Attachment 4 provides a technical evaluation report.In addition, this is a cost beneficial licensing action (CBLA)submittal and represents a high priority item since it will, once approved, result in a significant reduction in operating cost.The lifetime cost saving associated with this CBLA is approximately
$600,000, as detailed in Attachment 5.We believe that the proposed changes will not result in (1)a significant change in the types of any effluent that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.l 9506200465 950b15 PDR ADOCK 05000315 p PDR Il'rp-<<
U.S.Nuclear Regulatory Commission Page 2 AEP:NRC:0896V These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at its next regularly scheduled meeting.In compliance with the requirements of 10 CFR 50'1(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health.This letter is submitted pursuant to 10 CFR 50.30(b)and, as such, an oath statement is attached.Sincerely, Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS~beg DAY OF~..1995 No ary Public cad Attachments T
U.S.Nuclear Regulatory Commission Page 3 AEP:NRC:0896V CC: A.A.Blind G.Charnoff J.B.Martin NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett ATTACHMENT 1 TO AEP:NRC:0896V DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS Attachment 1 to AEP:NRC:0896V Page 1 A.DESCRIPTION OF CHANGES The changes proposed by this letter involve the emergency diesel generator (EDG)18 month 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance test.The changes are described individually as follows: Emergency Diesel Generator Surveillance Requirements T/S: 4.8.1.1.2.e.7 (Units 1 and 2)Page: 3/4 8-6 (Units 1 and 2)1)Reduce the duration of the surveillance test from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.2)Modify the footnote associated with the asterisk at the end of 4.8.1.1.2.e.7 to reflect the reduction of the surveillance test from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.B.JUSTIFICATION FOR CHANGES The proposed changes involve the 18 month 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> EDG surveillance which is implemented by plant procedure.
The proposed changes are designed to reduce operating costs, increase outage scheduling flexibility, reduce shutdown risk, and increase diesel life.Reducing the surveillance time from 24 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> would significantly improve outage performance without reducing EDG reliability.
Based on examination of Cook Nuclear Plant test data.from'1974 to 1994, it is clear that extensive run times beyond.the..point where the EDG'i's sta'rted, loa'ded to:3500KW, and achieves an e'quilibrium
.condition provide'ittle insight regarding EDG.reliability.
The engine steady-state characteristics are achieved in approximately'2 ho'urs and the dominant failure modes of the EDG are expected to occur.wi'thin this period.Xn addition, r'eview of the'4.hour,te'st
" data'rom 1974'to 1994 does'not.;indicate~he, discovery.of any abnoraral conditions that would'have'je'opardized'the'
'iesel from completing its mission during an actual emergency demand.Therefore, as described in Attachment 4, reduction of the test duration from a 24 to an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period will maintain an equivalent level of confidence in EDG reliability and may actually improve overall EDG reliability.
Attachment 1 to AEP:NRC:0896V Page 2 C.10 CFR 50 2 CRITERIA Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration if the change does not: involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety.Criterion 1 The safety function of the EDGs is to supply ac electrical power to plant safety systems whenever the preferred ac power supply is unavailable.
Through surveillance requirements, the ability of the EDGs to meet their load and timing requirements is tested and the quality of the fuel and the availability of the fuel supply are monitored.
Reduction of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> will not reduce the surveillance factors under consideration and will sufficiently exercise the EDG and its support systems to identify potential conditions that could lead to performance degradation (See Attachment 4).Based on these considerations, it is concluded that the proposed changes do not involve a significant increase'n the probability or consequences of an accident previously evaluated.
0 Criterion 2 The proposed changes do not involve physical changes to the plant or changes.in'lant operating.configuration.
The changes only involve the reduction of'18 moth 24:hour EDG.survei3.lanpe test dur'ation, Thus,',it.
is'"~'.concluded that the.proposed changes.do not'create'he possibility of".a new or different kind of accident from any accident previously evaluated.
Criterion 3 Although the duration of the 18 month 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> EDG surveillance test would be reduce'd, the EDG components will continue to be sufficiently exercised such that the ability to detect incipient and degraded conditions will be maintained (See Attachment 4, Figure 2).The proposed changes have been determined to be compatible with our plant operating experience and commensurate with past surveillance test results.Based on these considerations, it is concluded that the proposed changes do not involve a significant reduction in a margin of safety.