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| {{#Wiki_filter:~,0'REGULATUR YFORMATION DISTRIBUTION SYnl(RllIS)ACCESSIO< | | {{#Wiki_filter:~, 0'REGULATUR Y FORMATION DISTRIBUTION SY nl (R llIS)ACCESSIO<NSR F AC IL: 50-315 50-316 AUTH.CIA'.>E ALEXICo,nI.H. |
| NSRFACIL:50-31550-316AUTH.CIA'.>EALEXICo,nI.H.
| | REClo ri g i!T Q as:8504260195 DOC~Donald C.Coo!t Nuc DonalE C.Coo~induc Al!l IIUR AFF[LI Indiana n erich iIEC I+l"'>'!l'FF DATE: 85/04/23 NOTARIZED: |
| REClorigi!TQas:8504260195 DOC~DonaldC.Coo!tNucDonalEC.Coo~inducAl!lIIURAFF[LIIndiananerichiIECI+l"'>'!l'FFDATE:85/04/23NOTARIZED:
| | YES l ear PoI er Plants Uni t 1<Intli ang l'ear Pos er Pl dnt0 Uni t 20 Inniana AT lOI: inan Electric Co.IL TAT IO;I t'r'acIOI e, I ldI'io!>I,~iT A'ter DOCKET US000315 05IIP v316 SUBJkCT: Application for amend to Licenses nPR"56 II PR-74RCnanoinu Teel!bPpec Tables~.3-3<3.7.].2 |
| YESlearPoIerPlantsUnit1<Intliangl'earPoserPldnt0Unit20InnianaATlOI:inanElectricCo.ILTATIO;It'r'acIOIe,IldI'io!>I,
| | ~4.7.1.2.o~oases 3/il.F 1.2 to aduress I ater oensity corrcctioi s~ben meas<Iring auxiliary feedwater pump discnarge pressure.DISTRISIITIOii CODE: ADD ID COPIES RECEIYED:LTR I Ei CL J.SIZE'+2 J TITLE: OR Submittal: |
| ~iTA'terDOCKETUS00031505IIPv316SUBJkCT:Application foramendtoLicensesnPR"56IIPR-74RCnanoinu Teel!bPpecTables~.3-3<3.7.].2 | | General Distribution NOTES!OL 0 10/25/74 OL: 12/23/72 05000315 05000316 RECIPIENT ID CODE/NAME NRR ORB1 BC 01 COPIES LT'iR ENCl.7 7 RECIPIENT ID CODE/NAt'E COPIES I TTR ENCL INTERNAL-ACRS ELO/HDS3'NRR/DL DIR NRR/DL/TSRG NRR/DSI/RAG RGN3 EXTERNAL: EGEG BRVSKE,S NRC PDR 02 6 1 1" 1 1 1 6 ADM/LFHB 0 NRR/DE/HTEB NRR/OL/ORAB |
| ~4.7.1.2.o | | =1'-NRR/DS I/MVTB 1 REG FILE 1 LPOR NSIC 04 03 05 1 u 1 1 1 0 1 1 1 1 2 2 1 1~L e~IC TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25 IND!ANA 8 MICHIGAN ELECTRIC COIMPPNy I.O.BOX 16631 COLUMBUS, OHIO 43216 April 23, 1985 AEP:NRC:0856H Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 APPLZCATION FOR AMENDMENT TO TECHNICAL SPECIFICATIONS AUXILIARY FEEDWATER PUMPS Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 |
| ~oases3/il.F1.2toaduressIateroensitycorrcctioi s~benmeas<Iring auxiliary feedwater pumpdiscnarge pressure. | |
| DISTRISIITIOii CODE:ADDIDCOPIESRECEIYED:LTR IEiCLJ.SIZE'+2JTITLE:ORSubmittal: | |
| GeneralDistribution NOTES!OL010/25/74OL:12/23/720500031505000316RECIPIENT IDCODE/NAME NRRORB1BC01COPIESLT'iRENCl.77RECIPIENT IDCODE/NAt'E COPIESITTRENCLINTERNAL-ACRSELO/HDS3'NRR/DLDIRNRR/DL/TSRG NRR/DSI/RAG RGN3EXTERNAL:
| |
| EGEGBRVSKE,SNRCPDR02611"1116ADM/LFHB0NRR/DE/HTEB NRR/OL/ORAB
| |
| =1'-NRR/DSI/MVTB1REGFILE1LPORNSIC0403051u111011112211~Le~ICTOTALNUMBEROFCOPIESREQUIRED: | |
| LTTR28ENCL25 IND!ANA8MICHIGANELECTRICCOIMPPNyI.O.BOX16631COLUMBUS, OHIO43216April23,1985AEP:NRC:0856H DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74APPLZCATION FORAMENDMENT TOTECHNICAL SPECIFICATIONS AUXILIARY FEEDWATER PUMPSMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555
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| ==DearMr.Denton:== | | ==Dear Mr.Denton:== |
| Thisletteranditsattachment constitute anapplication foramendment tothesubjectTechnical Specifications (T/S)foztheDonaldC.CookNuclearPlantUnitNos.1and2.Specifically, weproposetochangeT/STable3.3-3,T/S3.7.1.2,T/S4.7.1.2.a, andtheBases3/4.7.1.2.
| | This letter and its attachment constitute an application for amendment to the subject Technical Specifications (T/S)foz the Donald C.Cook Nuclear Plant Unit Nos.1 and 2.Specifically, we propose to change T/S Table 3.3-3, T/S 3.7.1.2, T/S 4.7.1.2.a, and the Bases 3/4.7.1.2. |
| Proposedrevised...T/S pagesarecontained intheAttachment tothisletter.Thisletterconstitutes ourresponsetotheconcernsofGenericLetter83-37,Section3,"LongTermAuxiliary Feedwater SystemEvaluation."
| | Proposed revised...T/S pages are contained in the Attachment to this letter.This letter constitutes our response to the concerns of Generic Letter 83-37, Section 3,"Long Term Auxiliary Feedwater System Evaluation." Zn addition, the specified action in Mr.Steven A.Varga letter dated April 11, 1985 is addressed in this proposal.Specifically, we are proposing that the Techni-cal Specification and the Bases be changed to address water density cor-rections when measuring auxiliary feedwater pump discharge pressure.The change to Table 3.3-3 for both Units 1 and 2 would delete the zequirement that the Motor Driven Auxiliary Feedwater Pumps (MDAFP)be automatically started in MODE 3 due to a loss of main feedwater pump signal.Currently, during normal plant startup, the main feedwater pumps are not running when entering MODE 3.Thus, the"loss of main feedwater pumps" instrumentation trip logic now automatically starts the MDAFP even though delivery of auxiliary feedwater to the steam generators is not required.When water is required, it is usually added slowly at the direction of the operator.This change will make the automatic initiating signals required in MODE 3 consistent with those identified. |
| Znaddition, thespecified actioninMr.StevenA.VargaletterdatedApril11,1985isaddressed inthisproposal.
| | in the Westinghouse Standard Technical Specifications (STS), NUREG-0452, Revision 4 (i.e., steam genera-tor water level-low-low, 4 kv bus loss of voltage, and safety injection). |
| Specifically, weareproposing thattheTechni-calSpecification andtheBasesbechangedtoaddresswaterdensitycor-rectionswhenmeasuring auxiliary feedwater pumpdischarge pressure. | | The removal of the loss of main feedwater initiating signal may result in some increase to the probability or consequence of a previously analyzed accident, or may reduce in some way a safety margin, but the results of this change are clearly within all acceptable criteria with respect to the system specified in the STS.For this reason, we believe that this change does not involve a significant hazards consideration as defined in 10 CFR 50.92.EMITS'.8S04P3 PDR ADQCN 050003i S PDR j~"Mr.Harold R.Dent AEP.NRC.0856H A section is added to the Bases for T/S 3/4.7.1.2 that desc ibes the dual function of the AFW System and its interrelation w'th the automatic initialing signals.This change is consistent with the changes to Table 3.3-3 and T/S 3.7.1.2.In addition, the word"of" was inserted in the phrase"will be limited to a small fraction of 10 CFR Part 100" to the Unit 1 Bases 3/4.7.1.4. |
| ThechangetoTable3.3-3forbothUnits1and2woulddeletethezequirement thattheMotorDrivenAuxiliary Feedwater Pumps(MDAFP)beautomatically startedinMODE3duetoalossofmainfeedwater pumpsignal.Currently, duringnormalplantstartup,themainfeedwater pumpsarenotrunningwhenenteringMODE3.Thus,the"lossofmainfeedwater pumps"instrumentation triplogicnowautomatically startstheMDAFPeventhoughdeliveryofauxiliary feedwater tothesteamgenerators isnotrequired.
| | This editorial change makes the Unit 1 Bases identical to the respective Unit 2 Bases.The Action statement of T/S 3.7.1.2 for Units 1 and 2 are proposed to be made identical to that specified in the Westinghouse STS.This change will address the ACTION to'e taken if more than one auxiliary feedwater pump is inoperable. |
| Whenwaterisrequired, itisusuallyaddedslowlyatthedirection oftheoperator.
| | This change was recommended in Generic Letter 83-37.This change constitutes an additional restriction not presently included in the T/S.Therefore, we believe this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.The term"independent" is proposed to be added to Unit 2 T/S 3.7.1.2.This change would make this Unit 2 T/S identical to the Unit 1 T/S and the Westinghouse STS.This change would be purely administrative and therefore does not involve a significant hazards consideration as defined by 10 CFR 50.92.Changes are proposed to T/S 4.7.1.2.a.l and T/S 4.7.1.2.a.2 to make the Units 1 and 2 T/S identical and to clarify that the acceptance discharge pressures are based on a fluid temperature of 60 F.Commensurately, we are 0 proposing that the Bases Section B 3/4.7.1.2 be changed to include the following clarification for discharge pressure."The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 F.Water density corrections are permitted to allow comparison of test results which vary depending on ambient conditions." The addition of this phrase clarifies that a correction for water density is permitted when testing the auxiliary feedwater pumps.Allowance for this density correc-tion permits accurate comparison of test results which vary depending on ambient conditions. |
| Thischangewillmaketheautomatic initiating signalsrequiredinMODE3consistent withthoseidentified.
| | These changes may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but the results of the changes are clearly within all acceptable criteria with respect to the safety analysis.There-fore, we believe these changes do not involve a significant hazards consideration as defined by 10 CFR 50.92.T/S 4.7.1.2.a.3 in both Units 1 and 2 is changed to agree with the Westinghouse STS.This change will remove several surveillances including some that were redundant to those covered in T/S 4.7.1.2.a.4. |
| intheWestinghouse StandardTechnical Specifications (STS),NUREG-0452, Revision4(i.e.,steamgenera-torwaterlevel-low-low,4kvbuslossofvoltage,andsafetyinjection).
| | This change may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the STS.Therefore, we believe this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.T/S 4.7.1.2.a.4 for both Units 1 and 2 is to be replaced by the following: |
| Theremovalofthelossofmainfeedwater initiating signalmayresultinsomeincreasetotheprobability orconsequence ofapreviously analyzedaccident, ormayreduceinsomewayasafetymargin,buttheresultsofthischangeareclearlywithinallacceptable criteriawithrespecttothesystemspecified intheSTS.Forthisreason,webelievethatthischangedoesnotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.EMITS'.8S04P3PDRADQCN050003iSPDR j~"Mr.HaroldR.DentAEP.NRC.0856H AsectionisaddedtotheBasesforT/S3/4.7.1.2 thatdescibesthedualfunctionoftheAFWSystemanditsinterrelation w'ththeautomatic initialing signals.Thischangeisconsistent withthechangestoTable3.3-3andT/S3.7.1.2.Inaddition, theword"of"wasinsertedinthephrase"willbelimitedtoasmallfractionof10CFRPart100"totheUnit1Bases3/4.7.1.4.
| | Verifying that when above 10%RATED THERMAL POWER each automatic valve in the flow path is in the fully open position and that each auxiliary feedwater pump is in automatic control (capable of automatic actuation). |
| Thiseditorial changemakestheUnit1Basesidentical totherespective Unit2Bases.TheActionstatement ofT/S3.7.1.2forUnits1and2areproposedtobemadeidentical tothatspecified intheWestinghouse STS.ThischangewilladdresstheACTIONto'etakenifmorethanoneauxiliary feedwater pumpisinoperable.
| | I'r.Harold R.Dento w3 AEP:NRC:0856H This change allows the valves to be partially or fully closed when the plant is operating below 10%RATED THERMAL POWER.This reflects our belief that the fully open position is not always the coxrect position for the valves.At various times, particularly during startup and also during accident conditions, it is appropriate to run the auxiliar: feedwa er pumps and regulate the flow bv adjusting the valves.It should be noted that wha ever position the valves are in, an initiating signal to the auxiliary feedwater pumps will move the valves to the fully open position.This change may result in some increase to.the probab'lity or consequences o a previouslv analyzed accident or may reduce in some way a safety margin, but the results of the change are clearly within all acceptable criteria with respect to the safety analysis.Therefore, we believe this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.We believe that the proposed changes will not result in (1)a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, and (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC)and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC)at their next regularly scheduled meeting.Pursuant to 10 CFR 50.91(b)(1), copies of this letter and its attachment have been transmitted to Mr.R.C.Callen of the Michigan Public Service Commission and Mr.G.Bruchmann of the Michigan Department of Public Health.Pursuant to 10 CFR 170.12(c), we have enclosed an application fee of$150.00 for the proposed amendments. |
| Thischangewasrecommended inGenericLetter83-37.Thischangeconstitutes anadditional restriction notpresently includedintheT/S.Therefore, webelievethischangedoesnotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92.Theterm"independent" isproposedtobeaddedtoUnit2T/S3.7.1.2.ThischangewouldmakethisUnit2T/Sidentical totheUnit1T/SandtheWestinghouse STS.Thischangewouldbepurelyadministrative andtherefore doesnotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92.ChangesareproposedtoT/S4.7.1.2.a.l andT/S4.7.1.2.a.2 tomaketheUnits1and2T/Sidentical andtoclarifythattheacceptance discharge pressures arebasedonafluidtemperature of60F.Commensurately, weare0proposing thattheBasesSectionB3/4.7.1.2 bechangedtoincludethefollowing clarification fordischarge pressure.
| | This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned. |
| "Theacceptance discharge pressures fortheauxiliary feedwater pumpsarebasedonafluidtemperature of60F.Waterdensitycorrections arepermitted toallowcomparison oftestresultswhichvarydepending onambientconditions." | | Very truly yours, M.P.Al xict;((]ci~vice President d)2>I'ttachments cc: John E.Dolan W.G.Smith, Jr.-Bridgman R.C.Callen G.Bruchmann G.Charnoff NRC Resident Inspector-Bridgman}} |
| Theadditionofthisphraseclarifies thatacorrection forwaterdensityispermitted whentestingtheauxiliary feedwater pumps.Allowance forthisdensitycorrec-tionpermitsaccuratecomparison oftestresultswhichvarydepending onambientconditions.
| |
| Thesechangesmayresultinsomeincreasetotheprobability orconsequences ofapreviously analyzedaccidentormayreduceinsomewayasafetymargin,buttheresultsofthechangesareclearlywithinallacceptable criteriawithrespecttothesafetyanalysis.
| |
| There-fore,webelievethesechangesdonotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92.T/S4.7.1.2.a.3 inbothUnits1and2ischangedtoagreewiththeWestinghouse STS.Thischangewillremoveseveralsurveillances including somethatwereredundant tothosecoveredinT/S4.7.1.2.a.4. | |
| Thischangemayresultinsomeincreasetotheprobability orconsequences ofapreviously-analyzed accidentormayreduceinsomewayasafetymargin,buttheresultsofthechangeareclearlywithinallacceptable criteriawithrespecttothesystemorcomponent specified intheSTS.Therefore, webelievethischangedoesnotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92.T/S4.7.1.2.a.4 forbothUnits1and2istobereplacedbythefollowing:
| |
| Verifying thatwhenabove10%RATEDTHERMALPOWEReachautomatic valveintheflowpathisinthefullyopenpositionandthateachauxiliary feedwater pumpisinautomatic control(capableofautomatic actuation). | |
| I'r.HaroldR.Dentow3AEP:NRC:0856H Thischangeallowsthevalvestobepartially orfullyclosedwhentheplantisoperating below10%RATEDTHERMALPOWER.Thisreflectsourbeliefthatthefullyopenpositionisnotalwaysthecoxrectpositionforthevalves.Atvarioustimes,particularly duringstartupandalsoduringaccidentconditions, itisappropriate toruntheauxiliar: | |
| feedwaerpumpsandregulatetheflowbvadjusting thevalves.Itshouldbenotedthatwhaeverpositionthevalvesarein,aninitiating signaltotheauxiliary feedwater pumpswillmovethevalvestothefullyopenposition.
| |
| Thischangemayresultinsomeincreaseto.theprobab'lity orconsequences oapreviouslv analyzedaccidentormayreduceinsomewayasafetymargin,buttheresultsofthechangeareclearlywithinallacceptable criteriawithrespecttothesafetyanalysis.
| |
| Therefore, webelievethischangedoesnotinvolveasignificant hazardsconsideration asdefinedby10CFR50.92.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,and(2)asignificant increaseinindividual orcumulative occupational radiation exposure. | |
| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee (PNSRC)andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee (NSDRC)attheirnextregularly scheduled meeting.Pursuantto10CFR50.91(b)(1),
| |
| copiesofthisletteranditsattachment havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.G.Bruchmann oftheMichiganDepartment ofPublicHealth.Pursuantto10CFR170.12(c),
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| wehaveenclosedanapplication feeof$150.00fortheproposedamendments.
| |
| Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned.
| |
| Verytrulyyours,M.P.Alxict;((]ci~vicePresident d)2>I'ttachments cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.Bruchmann G.CharnoffNRCResidentInspector
| |
| -Bridgman}} | |
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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
~, 0'REGULATUR Y FORMATION DISTRIBUTION SY nl (R llIS)ACCESSIO<NSR F AC IL: 50-315 50-316 AUTH.CIA'.>E ALEXICo,nI.H.
REClo ri g i!T Q as:8504260195 DOC~Donald C.Coo!t Nuc DonalE C.Coo~induc Al!l IIUR AFF[LI Indiana n erich iIEC I+l"'>'!l'FF DATE: 85/04/23 NOTARIZED:
YES l ear PoI er Plants Uni t 1<Intli ang l'ear Pos er Pl dnt0 Uni t 20 Inniana AT lOI: inan Electric Co.IL TAT IO;I t'r'acIOI e, I ldI'io!>I,~iT A'ter DOCKET US000315 05IIP v316 SUBJkCT: Application for amend to Licenses nPR"56 II PR-74RCnanoinu Teel!bPpec Tables~.3-3<3.7.].2
~4.7.1.2.o~oases 3/il.F 1.2 to aduress I ater oensity corrcctioi s~ben meas<Iring auxiliary feedwater pump discnarge pressure.DISTRISIITIOii CODE: ADD ID COPIES RECEIYED:LTR I Ei CL J.SIZE'+2 J TITLE: OR Submittal:
General Distribution NOTES!OL 0 10/25/74 OL: 12/23/72 05000315 05000316 RECIPIENT ID CODE/NAME NRR ORB1 BC 01 COPIES LT'iR ENCl.7 7 RECIPIENT ID CODE/NAt'E COPIES I TTR ENCL INTERNAL-ACRS ELO/HDS3'NRR/DL DIR NRR/DL/TSRG NRR/DSI/RAG RGN3 EXTERNAL: EGEG BRVSKE,S NRC PDR 02 6 1 1" 1 1 1 6 ADM/LFHB 0 NRR/DE/HTEB NRR/OL/ORAB
=1'-NRR/DS I/MVTB 1 REG FILE 1 LPOR NSIC 04 03 05 1 u 1 1 1 0 1 1 1 1 2 2 1 1~L e~IC TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25 IND!ANA 8 MICHIGAN ELECTRIC COIMPPNy I.O.BOX 16631 COLUMBUS, OHIO 43216 April 23, 1985 AEP:NRC:0856H Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 APPLZCATION FOR AMENDMENT TO TECHNICAL SPECIFICATIONS AUXILIARY FEEDWATER PUMPS Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
Dear Mr.Denton:
This letter and its attachment constitute an application for amendment to the subject Technical Specifications (T/S)foz the Donald C.Cook Nuclear Plant Unit Nos.1 and 2.Specifically, we propose to change T/S Table 3.3-3, T/S 3.7.1.2, T/S 4.7.1.2.a, and the Bases 3/4.7.1.2.
Proposed revised...T/S pages are contained in the Attachment to this letter.This letter constitutes our response to the concerns of Generic Letter 83-37, Section 3,"Long Term Auxiliary Feedwater System Evaluation." Zn addition, the specified action in Mr.Steven A.Varga letter dated April 11, 1985 is addressed in this proposal.Specifically, we are proposing that the Techni-cal Specification and the Bases be changed to address water density cor-rections when measuring auxiliary feedwater pump discharge pressure.The change to Table 3.3-3 for both Units 1 and 2 would delete the zequirement that the Motor Driven Auxiliary Feedwater Pumps (MDAFP)be automatically started in MODE 3 due to a loss of main feedwater pump signal.Currently, during normal plant startup, the main feedwater pumps are not running when entering MODE 3.Thus, the"loss of main feedwater pumps" instrumentation trip logic now automatically starts the MDAFP even though delivery of auxiliary feedwater to the steam generators is not required.When water is required, it is usually added slowly at the direction of the operator.This change will make the automatic initiating signals required in MODE 3 consistent with those identified.
in the Westinghouse Standard Technical Specifications (STS), NUREG-0452, Revision 4 (i.e., steam genera-tor water level-low-low, 4 kv bus loss of voltage, and safety injection).
The removal of the loss of main feedwater initiating signal may result in some increase to the probability or consequence of a previously analyzed accident, or may reduce in some way a safety margin, but the results of this change are clearly within all acceptable criteria with respect to the system specified in the STS.For this reason, we believe that this change does not involve a significant hazards consideration as defined in 10 CFR 50.92.EMITS'.8S04P3 PDR ADQCN 050003i S PDR j~"Mr.Harold R.Dent AEP.NRC.0856H A section is added to the Bases for T/S 3/4.7.1.2 that desc ibes the dual function of the AFW System and its interrelation w'th the automatic initialing signals.This change is consistent with the changes to Table 3.3-3 and T/S 3.7.1.2.In addition, the word"of" was inserted in the phrase"will be limited to a small fraction of 10 CFR Part 100" to the Unit 1 Bases 3/4.7.1.4.
This editorial change makes the Unit 1 Bases identical to the respective Unit 2 Bases.The Action statement of T/S 3.7.1.2 for Units 1 and 2 are proposed to be made identical to that specified in the Westinghouse STS.This change will address the ACTION to'e taken if more than one auxiliary feedwater pump is inoperable.
This change was recommended in Generic Letter 83-37.This change constitutes an additional restriction not presently included in the T/S.Therefore, we believe this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.The term"independent" is proposed to be added to Unit 2 T/S 3.7.1.2.This change would make this Unit 2 T/S identical to the Unit 1 T/S and the Westinghouse STS.This change would be purely administrative and therefore does not involve a significant hazards consideration as defined by 10 CFR 50.92.Changes are proposed to T/S 4.7.1.2.a.l and T/S 4.7.1.2.a.2 to make the Units 1 and 2 T/S identical and to clarify that the acceptance discharge pressures are based on a fluid temperature of 60 F.Commensurately, we are 0 proposing that the Bases Section B 3/4.7.1.2 be changed to include the following clarification for discharge pressure."The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 F.Water density corrections are permitted to allow comparison of test results which vary depending on ambient conditions." The addition of this phrase clarifies that a correction for water density is permitted when testing the auxiliary feedwater pumps.Allowance for this density correc-tion permits accurate comparison of test results which vary depending on ambient conditions.
These changes may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but the results of the changes are clearly within all acceptable criteria with respect to the safety analysis.There-fore, we believe these changes do not involve a significant hazards consideration as defined by 10 CFR 50.92.T/S 4.7.1.2.a.3 in both Units 1 and 2 is changed to agree with the Westinghouse STS.This change will remove several surveillances including some that were redundant to those covered in T/S 4.7.1.2.a.4.
This change may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the STS.Therefore, we believe this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.T/S 4.7.1.2.a.4 for both Units 1 and 2 is to be replaced by the following:
Verifying that when above 10%RATED THERMAL POWER each automatic valve in the flow path is in the fully open position and that each auxiliary feedwater pump is in automatic control (capable of automatic actuation).
I'r.Harold R.Dento w3 AEP:NRC:0856H This change allows the valves to be partially or fully closed when the plant is operating below 10%RATED THERMAL POWER.This reflects our belief that the fully open position is not always the coxrect position for the valves.At various times, particularly during startup and also during accident conditions, it is appropriate to run the auxiliar: feedwa er pumps and regulate the flow bv adjusting the valves.It should be noted that wha ever position the valves are in, an initiating signal to the auxiliary feedwater pumps will move the valves to the fully open position.This change may result in some increase to.the probab'lity or consequences o a previouslv analyzed accident or may reduce in some way a safety margin, but the results of the change are clearly within all acceptable criteria with respect to the safety analysis.Therefore, we believe this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.We believe that the proposed changes will not result in (1)a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, and (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC)and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC)at their next regularly scheduled meeting.Pursuant to 10 CFR 50.91(b)(1), copies of this letter and its attachment have been transmitted to Mr.R.C.Callen of the Michigan Public Service Commission and Mr.G.Bruchmann of the Michigan Department of Public Health.Pursuant to 10 CFR 170.12(c), we have enclosed an application fee of$150.00 for the proposed amendments.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.P.Al xict;((]ci~vice President d)2>I'ttachments cc: John E.Dolan W.G.Smith, Jr.-Bridgman R.C.Callen G.Bruchmann G.Charnoff NRC Resident Inspector-Bridgman