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| | issue date = 09/14/1998 | | | issue date = 09/14/1998 |
| | title = 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 | | | title = 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 |
| | author name = POWERS R P | | | author name = Powers R |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | 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 = 12 | | | page count = 12 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORY11REGULATYINFORMATION DISTRIBUTIO SYSTEM(RIDS)DOCKET¹0500031505000316ACCESSION NBR:9809220081, DOC.DATE: | | {{#Wiki_filter:CATEGORY 1 1 |
| 98/09/14NOTARIZED: | | REGULAT Y INFORMATION DISTRIBUTIO SYSTEM (RIDS) |
| YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50;316PonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION POWERS,R.P.
| | ACCESSION NBR:9809220081, DOC.DATE: 98/09/14 NOTARIZED: YES DOCKET ¹ FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50;316 Ponald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION POWERS,R.P. 'Induna Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk) |
| 'IndunaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk) | |
|
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstolicensesDPR-588DPR-74,revising TSpage3/45-6.D1STRZBUT10N CODE:A'OOZDCORTESRECEZVED:LTR | | Application for amends to licenses DPR-58 8 DPR-74,revising TS page 3/4 5-6. |
| )ENCLISZEE:P1TITLE:ORSubmittal: | | A D1STRZBUT10N CODE: A'OOZD CORTES RECEZVED:LTR ) ENCL I SZEE: P TITLE: OR Submittal: General Distribution 1 |
| GeneralDistribution NOTES:AT,ERECIPIENT IDCODE/NAME PD3-3LASTANG,JINTERNAILECENTER01NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL:
| | T, NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 0 STANG,J 1 1 INTERNA ILE CENTER 01 1 1 NRR/DE/ECGB/A 1 1 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC NRC PDR 1 1 D |
| NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-3PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3NRCPDRCOPIESLTTRENCL1111111110110D'NOTETOALL"RIDS"REC1PIENTS:
| | NOTE TO ALL "RIDS" REC1PIENTS: |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRZBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 |
| LTTR13ENCL12 IC indianaMichigan~PowerCompany500CircleDriveBuchanan, Ml491071373 September 14,1998AEP:NRC:1274 10CFR50.92DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskMailStop0-Pl-17Washington, D.C.20555-0001 Gentlemen:
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| DONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATION AMENDMENT SAFETYINJECTION PUMPRUNOUTFLOWLIMITSThisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)forCookNuclearPlantunits1and2.Thisamendment willchangetherunoutlimitsforasafetyinjection pumpto675gpmunlessthepumpisspecifically testedtoahigherflowratenotexceeding 700gpm.Background information relevanttotheT/Schangeandouranalysesconcerning significant hazardsconsiderations arecontained inattachment 1tothisletter.Attachment 2containsthecurrentT/Spages,marked-up toreflecttheproposedchange.TheproposedrevisedT/Spagesarecontained inattachment 3.Thissubmittal proposesachangetoT/Spage3/45-6forbothunit1and2.Theproposedchangewillnotresultinasignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsiteorasignificant increaseinindividual orcumulative occupational radiation exposure.
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| Theproposedchangehasbeenreviewedandapprovedbytheplantnuclearsafetyreviewcommittee andthenuclearsafetyanddesignreviewcommittee.
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| Werequestthattheapprovedamendment beeffective thirtydaysfromissuance.
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| 980'7220081 9809'X4PDRADOCK05000815P'OR U.S~NuclearRegulatory Commission Page2AEP:NRC:1274 Inaccordance withtherequirements of10CFR50.91(b)(1),
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| copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.R.P.PowersVicePresident SWORNTOANDSUBSCRIBED BEFOREME~l~san*iINDENotaryPubliMycommission expiresl2Z01/jmcAttachments c:J.A.Abramson, w/attachments J.L.Caldwell, w/attachments MDEQ-DW&RPD,w/attachments NRCResidentInspector, w/attachments J.R.Sampson,w/attachments sLC
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| ~~ATTACHMENT 1TOAEP:NRC:1274 SUPPORTING ANALYSESFORAMENDMENT TOTHETECHNICAL SPECIFICATIONS SAFETYINJECTION PUMPRUNOUTFLOWLIMITS Attachment 1toAEP:NRC:1274 Page1BackroundAmendment numbers84(6/24/85) and64(6/18/84),
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| respectively, totheunit1andunit2.technical specifications (T/Ss)incorporated achangetotheallowable safetyinjection (SI)pumprunoutlimitsinT/S4.5.2.h.Thechangeraisedthepermissible runoutflowofasingleSIpumpfrom650gpmto700gpm.Thepumprunoutflowchangeswerenecessitated byphysicalchangestotheSIpumpminiflowrecirculation lines.Thesephysicalchangesincreased miniflowcapacityfrom30gpmtoapproximately 60gpmanditwasanticipated thattheincreased miniflowwouldmakeitdifficult toachievealloftheSIpumpdesignflowobjectives withoutexceeding the650gpmrunoutlimitexistingatthattime.Thejustification forthechangefrom650to700gpmwasbasedonvendortesting(DresserIndustries) ofasingleCookNuclearPlantreplacement safetyinjection pumpandaspareelement.Thetestingestablished safepumpoperation uptoamaximumflowof700gpm.Weconfirmed thattheavailable netpositivesuctionheadtotheSIpumps,asinstalled attheplant,wasgreaterthanthatrequiredtosafelyachieve700gpmduringthevendortesting.Therefore, webelievedthistestingwasalsoapplicable tothethree(untested) installed pumps.In1991,wereceivedcorrespondence fromWestinghouse indicating thatthegenericrunoutlimitsforPacific2"JTCHpumpswas675gpmunlesseachspecificpumpwastestedtoahigherflow.Atourrequest,DresserreviewedthepumprunoutlimitsforCookNuclearPlant.Basedontheirreview,Dresserconcluded thefollowing:
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| 1)forthespecificreplacement pumpandspareelementpreviously testedbythem,the700gpmrunoutlimitremainedapplicable (thisappliestotheunit2northpump);and2)forother(untested)
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| SIpumps,Dresser's positionwastoabidebythegeneralWestinghouse limitof675gpm(thisappliestobothunit1pumpsandtheunit2southpump).Theyindicated thatmanufacturing tolerances insandcastimpellers andmaterialchangesinthepumpcasing(ofthetestedreplacement pump)couldresultintestvariations thatlimitapplicability ofthetestingbetweenpumps.Dresseralsoindicated thatthegenericlimitof675gpmcouldbeincreased forthethreeuntestedpumps,withappropriate inplaceorvendortesting.ReviewofSIpumpflowbalancing dataindicated thatproperbalancing couldbeachievedwithoutexceeding 675gpmforthethreepumpsthathadnotbeenspecifically testedforhigherflows.Procedure 12EHP4030STP~208SIgU1&U2ECCSFLOWBALANCESAFETYINJECTlON SYSTEM",waschangedtoadministratively limitflowofthethreeuntestedpumpsto675gpm.Basedonprocedural controlsforlimitingrunoutflowofthethreeuntestedpumps,weconcluded in1992thattheintentofT/S4.5.2.hwasbeingmetandthatachangetotheT/Sswasnotnecessary.
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| However,additional recentreviewhasconcluded thatachangetotheT/Sshouldhavebeeninitiated.
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| Thissubmittal providesthenecessary changeandalsoclarifies thebasisforsettingtheSIpumprunoutlimits.Thebasesclarification describes whytheinjection lineupismoreconservative thanthesumprecirculation lineup(whentheRHRpumpsareproviding asuctionpressureboost)forpotential SIpumprunout.Thisisduetosplitting oftheSI
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| Attachment 1toAEP:NRC:1274Page2trainsduringcirculation, resulting inahighersystemresistance thanwitha-singleSIpumpinjecting toallfourreactorcoolantloops.DescritionofAmendment ReuestTechnical specification 4.5.2.h(SIsystemsinglepump)isbeingchangedtorequirethemaximumpermitted runoutflowrateforaSIpumpberestricted to675gpmunlessthepumpisindividually qualified toahigherflowrateofupto700gpm.Currently, T/S4.5.2.hrecognizes arunoutflowrateof700gpmforeachoftheSIpumps.Thebasisisbeingclarified todescribewhytheinjection lineupduringflowbalancing istheminimumresistance configuration forrunoutconsiderations. | | I C indiana Michigan Power Company |
| Justification forAmendment Theproposedamendment isnecessary tocorrectatechnical discrepancy intherunoutflowlimitforsafetyinjection pumpsthat,havenotbeenspecifically testedtothelimitcurrently allowedbyT/S4.5.2.h.BasisforNoSignificant HazardsDetermination Inaccordance with10CFR50.92,thisproposedamendment doesnotinvolveasignificant hazardconsideration ifitdoesnot:1)Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. | | ~ |
| Theproposedreduction intheSIpumprunoutflowdoesnotincreasetheprobability ofoccurrence ofanypreviously evaluated accidentbecausetheSIpumpsarenotconsidered tobeaccidentinitiators.
| | 500 Circle Drive Buchanan, Ml 491071373 AEP:NRC:1274 September 14, 1998 10 CFR 50.92 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-Pl-17 Washington, D. C. 20555-0001 Gentlemen: |
| Inaddition, flowbalancing performed atCookNuclearPlanthasproventheabilitytodelivertheminimumT/Sflowof300gpmtoeachpairofcoldleginjection pointswithoutexceeding the675gpm(or700gpm)pumprunoutlimits.Therefore, theemergency corecoolingsystemperformance objectives of10CFR50.46arenotimpactedandthischangedoesnotinvolveasignificant increaseintheconsequences ofanaccidentpreviously evaluated.
| | DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION AMENDMENT SAFETY INJECTION PUMP RUNOUT FLOW LIMITS This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss) for Cook Nuclear Plant units 1 and 2. This amendment will change the runout limits for a safety injection pump to 675 gpm unless the pump is specifically tested to a higher flow rate not exceeding 700 gpm. |
| 2)Createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. | | Background information relevant to the T/S change and our analyses concerning significant hazards considerations are contained in attachment 1 to this letter. Attachment 2 contains the current T/S pages, marked-up to reflect the proposed change. The proposed revised T/S pages are contained in attachment 3. |
| Thisproposedchangeimposesagenericlimitonmaximumallowable flowforuntestedSIpumps.Nophysicalsystemchangesorchangesinoperating modesarebeingmadethatcouldintroduce newordifferent kindsofaccidents fromthosepreviously evaluated.
| | This submittal proposes a change to T/S page 3/4 5-6 for both unit 1 and 2. The proposed change will not result in a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite or a significant increase in individual or cumulative occupational radiation exposure. |
| Asdiscussed in(1)above,theSIpumpsarenotconsidered accidentinitiators, andthisstatusisnotaffectedbythechangetotheSIpumprunoutlimits.
| | The proposed change has been reviewed and approved by the plant nuclear safety review committee and the nuclear safety and design review committee. We request that the approved amendment be effective thirty days from issuance. |
| Attachment 1toAEP:NRC:1274 Page33)Involveasignificant reduction inamarginofsafety.Thischangereflectsareducedmaximumsinglepumpflowtobeobservedduringflowbalancing oftheSIsystem.FlowbalancetestingatCookNuclearPlanthasdemonstrated theabilitytomeetSIflowrequirements whilemaintaining anadequatemargintotherevisedlowerrunoutlimitsbeingproposedbythissubmittal.
| | 980'7220081 9809'X4 PDR P |
| BecausetheminimumrequiredSIflowdelivered tothecorehasnotbeenreducedbythischange,thechangedoesnotinvolveareduction inamarginofsafety.Basedonthepreceding, theevaluation concluded thattheproposedchangetotheSIpumprunoutlimitsdoesnotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.
| | ADOCK |
| ATTACHMENT 2TOAEP:NRC:1274 CURRENTPAGESMARKED-UP TOSHOWPROPOSEDCHANGESTOTHEDONALDCDCOOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATION SAFETYINJECTION PUMPRUNOUTFLOWLIMITS UNITNO.1}} | | 'OR05000815 |
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| | U. S ~ Nuclear Regulatory Commission AEP:NRC:1274 Page 2 In accordance 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. |
| | R. P. Powers Vice President SWORN TO AND SUBSCRIBED BEFORE ME |
| | ~l ~san*i INDE Notary Publi My commission expires l 2Z 01 |
| | /jmc Attachments c: J. A. Abramson, w/attachments J. L. Caldwell, w/attachments MDEQ - DW & RPD, w/attachments NRC Resident Inspector, w/attachments J. R. Sampson, w/attachments |
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| | sL C |
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| | ~ ~ |
| | ATTACHMENT 1 TO AEP:NRC:1274 SUPPORTING ANALYSES FOR AMENDMENT TO THE TECHNICAL SPECIFICATIONS SAFETY INJECTION PUMP RUNOUT FLOW LIMITS to AEP:NRC:1274 Page 1 Back round Amendment numbers 84 (6/24/85) and 64 (6/18/84), respectively, to the unit 1 and unit 2.technical specifications (T/Ss) incorporated a change to the allowable safety injection (SI) pump runout limits in T/S 4.5.2.h. The change raised the permissible runout flow of a single SI pump from 650 gpm to 700 gpm. The pump runout flow changes were necessitated by physical changes to the SI pump miniflow recirculation lines. These physical changes increased miniflow capacity from 30 gpm to approximately 60 gpm and it it was difficult to anticipated that the increased miniflow would make achieve all of the SI pump design flow objectives without exceeding the 650 gpm runout limit existing at that time. The justification for the change from 650 to 700 gpm was based on vendor testing (Dresser Industries) of a single Cook Nuclear Plant replacement safety injection pump and a spare element. The testing established safe pump operation up to a maximum flow of 700 gpm. We confirmed that the available net positive suction head to the SI pumps, as installed at the plant, was greater than that required to safely achieve 700 gpm during the vendor testing. Therefore, we believed this testing was also applicable to the three (untested) installed pumps. |
| | In 1991, we received correspondence from Westinghouse indicating that the generic runout limits for Pacific 2" JTCH pumps was 675 gpm unless each specific pump was tested to a higher flow. At our request, Dresser reviewed the pump runout limits for Cook Nuclear Plant. Based on their review, Dresser concluded the following: 1) for the specific replacement pump and spare element previously tested by them, the 700 gpm runout limit remained applicable (this applies to the unit 2 north pump); and 2) for other (untested) SI pumps, Dresser's position was to abide by the general Westinghouse limit of 675 gpm (this applies to both unit 1 pumps and the unit 2 south pump). They indicated that manufacturing tolerances in sand cast impellers and material changes in the pump casing (of the tested replacement pump) could result in test variations that limit applicability of the testing between pumps. Dresser also indicated that the generic limit of 675 gpm could be increased for the three untested pumps, with appropriate in place or vendor testing. Review of SI pump flow balancing data indicated that proper balancing could be achieved without exceeding 675 gpm for the three pumps that had not been specifically tested for higher flows. Procedure 12 EHP 4030 STP 208SIg |
| | ~ U1 & U2 ECCS FLOW BALANCE SAFETY INJECTlON SYSTEM", was changed to administratively limit flow of the three untested pumps to 675 gpm. |
| | Based on procedural controls for limiting runout flow of the three untested pumps, we concluded in 1992 that the intent of T/S 4.5.2.h was being met and that a change to the T/Ss was not necessary. |
| | However, additional recent review has concluded that a change to the T/S should have been initiated. This submittal provides the necessary change and also clarifies the basis for setting the SI pump runout limits. The bases clarification describes why the injection lineup is more conservative than the sump recirculation lineup (when the RHR pumps are providing a suction pressure boost) for potential SI pump runout. This is due to splitting of the SI |
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| | to AEP:NRC: 1274 Page 2 trains during circulation, resulting in a higher system resistance than with a- single SI pump injecting to all four reactor coolant loops. |
| | Descri tion of Amendment Re uest Technical specification 4.5.2.h (SI system single pump) is being changed to require the maximum permitted runout flow rate for a SI pump be restricted to 675 gpm unless the pump is individually qualified to a higher flow rate of up to 700 gpm. Currently, T/S 4.5.2.h recognizes a runout flow rate of 700 gpm for each of the SI pumps. The basis is being clarified to describe why the injection lineup during flow balancing is the minimum resistance configuration for runout considerations. |
| | Justification for Amendment The proposed amendment is necessary to correct a technical discrepancy in the runout flow limit for safety injection pumps that, have not been specifically tested to the limit currently allowed by T/S 4.5.2.h. |
| | Basis for No Significant Hazards Determination In accordance with 10 CFR 50.92, this proposed does not involve a significant hazard consideration if itamendment does not: |
| | : 1) Involve a significant increase in the probability or consequences of an accident previously evaluated. |
| | The proposed reduction in the SI pump runout flow does not increase the probability of occurrence of any previously evaluated accident because the SI pumps are not considered to be accident initiators. In addition, flow balancing performed at Cook Nuclear Plant has proven the ability to deliver the minimum T/S flow o f 300 gpm to each pair o f cold leg injection points without exceeding the 675 gpm (or 700 gpm) pump runout limits. Therefore, the emergency core cooling system performance objectives of 10 CFR 50.46 are not impacted and this change does not involve a significant increase in the consequences of an accident previously evaluated. |
| | : 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | This proposed change imposes a generic limit on maximum allowable flow for untested SI pumps. No physical system changes or changes in operating modes are being made that could introduce new or different kinds of accidents from those previously evaluated. As discussed in (1) above, the SI pumps are not considered accident initiators, and this status is not affected by the change to the SI pump runout limits. |
| | to AEP:NRC:1274 Page 3 |
| | : 3) Involve a significant reduction in a margin of safety. |
| | This change reflects a reduced maximum single pump flow to be observed during flow balancing of the SI system. Flow balance testing at Cook Nuclear Plant has demonstrated the ability to meet SI flow requirements while maintaining an adequate margin to the revised lower runout limits being proposed by this submittal. Because the minimum required SI flow delivered to the core has not been reduced by this change, the change does not involve a reduction in a margin of safety. |
| | Based on the preceding, the evaluation concluded that the proposed change to the SI pump runout limits does not involve a significant hazards consideration as defined in 10 CFR 50.92. |
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| | ATTACHMENT 2 TO AEP:NRC:1274 CURRENT PAGES MARKED-UP TO SHOW PROPOSED CHANGES TO THE DONALD CD COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION SAFETY INJECTION PUMP RUNOUT FLOW LIMITS |
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| | UNIT NO. 1}} |
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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 1
REGULAT Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9809220081, DOC.DATE: 98/09/14 NOTARIZED: YES DOCKET ¹ FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50;316 Ponald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION POWERS,R.P. 'Induna Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Application for amends to licenses DPR-58 8 DPR-74,revising TS page 3/4 5-6.
A D1STRZBUT10N CODE: A'OOZD CORTES RECEZVED:LTR ) ENCL I SZEE: P TITLE: OR Submittal: General Distribution 1
T, NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 0 STANG,J 1 1 INTERNA ILE CENTER 01 1 1 NRR/DE/ECGB/A 1 1 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC NRC PDR 1 1 D
NOTE TO ALL "RIDS" REC1PIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12
I C indiana Michigan Power Company
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500 Circle Drive Buchanan, Ml 491071373 AEP:NRC:1274 September 14, 1998 10 CFR 50.92 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-Pl-17 Washington, D. C. 20555-0001 Gentlemen:
DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION AMENDMENT SAFETY INJECTION PUMP RUNOUT FLOW LIMITS This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss) for Cook Nuclear Plant units 1 and 2. This amendment will change the runout limits for a safety injection pump to 675 gpm unless the pump is specifically tested to a higher flow rate not exceeding 700 gpm.
Background information relevant to the T/S change and our analyses concerning significant hazards considerations are contained in attachment 1 to this letter. Attachment 2 contains the current T/S pages, marked-up to reflect the proposed change. The proposed revised T/S pages are contained in attachment 3.
This submittal proposes a change to T/S page 3/4 5-6 for both unit 1 and 2. The proposed change will not result in a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite or a significant increase in individual or cumulative occupational radiation exposure.
The proposed change has been reviewed and approved by the plant nuclear safety review committee and the nuclear safety and design review committee. We request that the approved amendment be effective thirty days from issuance.
980'7220081 9809'X4 PDR P
ADOCK
'OR05000815
U. S ~ Nuclear Regulatory Commission AEP:NRC:1274 Page 2 In accordance 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.
R. P. Powers Vice President SWORN TO AND SUBSCRIBED BEFORE ME
~l ~san*i INDE Notary Publi My commission expires l 2Z 01
/jmc Attachments c: J. A. Abramson, w/attachments J. L. Caldwell, w/attachments MDEQ - DW & RPD, w/attachments NRC Resident Inspector, w/attachments J. R. Sampson, w/attachments
sL C
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ATTACHMENT 1 TO AEP:NRC:1274 SUPPORTING ANALYSES FOR AMENDMENT TO THE TECHNICAL SPECIFICATIONS SAFETY INJECTION PUMP RUNOUT FLOW LIMITS to AEP:NRC:1274 Page 1 Back round Amendment numbers 84 (6/24/85) and 64 (6/18/84), respectively, to the unit 1 and unit 2.technical specifications (T/Ss) incorporated a change to the allowable safety injection (SI) pump runout limits in T/S 4.5.2.h. The change raised the permissible runout flow of a single SI pump from 650 gpm to 700 gpm. The pump runout flow changes were necessitated by physical changes to the SI pump miniflow recirculation lines. These physical changes increased miniflow capacity from 30 gpm to approximately 60 gpm and it it was difficult to anticipated that the increased miniflow would make achieve all of the SI pump design flow objectives without exceeding the 650 gpm runout limit existing at that time. The justification for the change from 650 to 700 gpm was based on vendor testing (Dresser Industries) of a single Cook Nuclear Plant replacement safety injection pump and a spare element. The testing established safe pump operation up to a maximum flow of 700 gpm. We confirmed that the available net positive suction head to the SI pumps, as installed at the plant, was greater than that required to safely achieve 700 gpm during the vendor testing. Therefore, we believed this testing was also applicable to the three (untested) installed pumps.
In 1991, we received correspondence from Westinghouse indicating that the generic runout limits for Pacific 2" JTCH pumps was 675 gpm unless each specific pump was tested to a higher flow. At our request, Dresser reviewed the pump runout limits for Cook Nuclear Plant. Based on their review, Dresser concluded the following: 1) for the specific replacement pump and spare element previously tested by them, the 700 gpm runout limit remained applicable (this applies to the unit 2 north pump); and 2) for other (untested) SI pumps, Dresser's position was to abide by the general Westinghouse limit of 675 gpm (this applies to both unit 1 pumps and the unit 2 south pump). They indicated that manufacturing tolerances in sand cast impellers and material changes in the pump casing (of the tested replacement pump) could result in test variations that limit applicability of the testing between pumps. Dresser also indicated that the generic limit of 675 gpm could be increased for the three untested pumps, with appropriate in place or vendor testing. Review of SI pump flow balancing data indicated that proper balancing could be achieved without exceeding 675 gpm for the three pumps that had not been specifically tested for higher flows. Procedure 12 EHP 4030 STP 208SIg
~ U1 & U2 ECCS FLOW BALANCE SAFETY INJECTlON SYSTEM", was changed to administratively limit flow of the three untested pumps to 675 gpm.
Based on procedural controls for limiting runout flow of the three untested pumps, we concluded in 1992 that the intent of T/S 4.5.2.h was being met and that a change to the T/Ss was not necessary.
However, additional recent review has concluded that a change to the T/S should have been initiated. This submittal provides the necessary change and also clarifies the basis for setting the SI pump runout limits. The bases clarification describes why the injection lineup is more conservative than the sump recirculation lineup (when the RHR pumps are providing a suction pressure boost) for potential SI pump runout. This is due to splitting of the SI
to AEP:NRC: 1274 Page 2 trains during circulation, resulting in a higher system resistance than with a- single SI pump injecting to all four reactor coolant loops.
Descri tion of Amendment Re uest Technical specification 4.5.2.h (SI system single pump) is being changed to require the maximum permitted runout flow rate for a SI pump be restricted to 675 gpm unless the pump is individually qualified to a higher flow rate of up to 700 gpm. Currently, T/S 4.5.2.h recognizes a runout flow rate of 700 gpm for each of the SI pumps. The basis is being clarified to describe why the injection lineup during flow balancing is the minimum resistance configuration for runout considerations.
Justification for Amendment The proposed amendment is necessary to correct a technical discrepancy in the runout flow limit for safety injection pumps that, have not been specifically tested to the limit currently allowed by T/S 4.5.2.h.
Basis for No Significant Hazards Determination In accordance with 10 CFR 50.92, this proposed does not involve a significant hazard consideration if itamendment does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed reduction in the SI pump runout flow does not increase the probability of occurrence of any previously evaluated accident because the SI pumps are not considered to be accident initiators. In addition, flow balancing performed at Cook Nuclear Plant has proven the ability to deliver the minimum T/S flow o f 300 gpm to each pair o f cold leg injection points without exceeding the 675 gpm (or 700 gpm) pump runout limits. Therefore, the emergency core cooling system performance objectives of 10 CFR 50.46 are not impacted and this change does not involve a significant increase in the consequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
This proposed change imposes a generic limit on maximum allowable flow for untested SI pumps. No physical system changes or changes in operating modes are being made that could introduce new or different kinds of accidents from those previously evaluated. As discussed in (1) above, the SI pumps are not considered accident initiators, and this status is not affected by the change to the SI pump runout limits.
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- 3) Involve a significant reduction in a margin of safety.
This change reflects a reduced maximum single pump flow to be observed during flow balancing of the SI system. Flow balance testing at Cook Nuclear Plant has demonstrated the ability to meet SI flow requirements while maintaining an adequate margin to the revised lower runout limits being proposed by this submittal. Because the minimum required SI flow delivered to the core has not been reduced by this change, the change does not involve a reduction in a margin of safety.
Based on the preceding, the evaluation concluded that the proposed change to the SI pump runout limits does not involve a significant hazards consideration as defined in 10 CFR 50.92.
ATTACHMENT 2 TO AEP:NRC:1274 CURRENT PAGES MARKED-UP TO SHOW PROPOSED CHANGES TO THE DONALD CD COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION SAFETY INJECTION PUMP RUNOUT FLOW LIMITS
UNIT NO. 1