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| {{#Wiki_filter:REGULATOR NFORMATION DISTRIBUTION TEM(RIDS)ACCESSION NBR:8310060006 DOC~DATE:83/10/03NOTARI'ZED: | | {{#Wiki_filter:REGULATOR NFORMATION DISTRIBUTION TEM (RIDS)ACCESSION NBR: 8310060006 DOC~DATE: 83/10/03 NOTARI'ZED: |
| NODOCKETFACIL:50~315 DonaldO,CookNuclearPowerPlantiUnit1iIndiana805000315AUTH,NAMEAUTHORAFFILIATION ALEXICHgM
| | NO DOCKET FACIL:50~315 Donald O, Cook Nuclear Power Planti Unit 1i Indiana 8 05000315 AUTH, NAME AUTHOR AFFILIATION ALEXICHgM~P, Indiana 8 Michigan Electric Co.RECIP.'NAME RECIPIENT AFFILIATION DENTONiH.R. |
| ~P,Indiana8MichiganElectricCo.RECIP.'NAME RECIPIENT AFFILIATION DENTONiH.R. | | .Office of Nuclear Reactor Regulationr Director VARGAiS,A, NRC No Detailed Affiliation Given |
| .OfficeofNuclearReactorRegulationr DirectorVARGAiS,A, NRCNoDetailedAffiliation Given | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Application toamendLicense.DPR-58irevising Tech'Spec4.52.ftoincreasetotalflowlimittofourbranchlinesfrom070gpmto500gpmonboroninJection sys(singlecentrifugal chargingpump).DISTRIBUTION CODE:A001SCOPIESRECEIYED:LTR ENCL,j.SIZE:,TITLE:RayMilleriInc:RelatedCorrespondence (SSINS-5340) | | Application to amend License.DPR-58irevising Tech'Spec 4.52.f to increase total flow limit to four branch lines from 070 gpm to 500 gpm on boron inJection sys (single centrifugal charging pump).DISTRIBUTION CODE: A001S COPIES RECEIYED:LTR ENCL,j.SIZE:, TITLE: Ray Milleri Inc: Related Correspondence (SSINS-5340) |
| NOTES:RECIPIENT IDCODE/NAME NRRORB1BC01INTERNAL: | | NOTES: RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL: ELD/HDS3 NRR/DL D IR TB REG FILE 04 EXTERNAL: ACRS 09 NRC PDR 02 NTIS COPIES LTTR ENCL 7 7 1 0 1 1 1 1 1 1 6 6 1 1 1 1 RECIPIENT ID CODE/NAME NRR/DE/MTEB NRR/DL/ORAB NRR/DS I/RAB RGN3 LPDR NSIC 03 05 COPIES LT'TR ENCL 1 1 1''0 1 1 1 1 1 1 1 I TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 23 |
| ELD/HDS3NRR/DLDIRTBREGFILE04EXTERNAL: | | >>>>), f'<<r<<l.'>00)>a f<<<<i,"C)r 4, f gII)>gy s~,i ll~<<s f]~>>)<<,I II>I II" lI l'I'<<'I*II'l II)I fia'I t<<4'I'3~))9))<<)iver fife)"l~<<f<<~",J'I~~~\,<<~>>fW f I<<gf<<sf,)')t<<<f~f ll f r rf 0 f I'II)'1)I>e''>>g I)"lgkl ,)>>$" i',<<>>>>I<lg~g>>>>, Il f I 1!w<<>>I f<<'OI l>>l<<'>>II<'t 1>>il~ll)g"))i l g g Q<<, ii')J)i II'il)>>k I>>0 f<<>>>)~<<f Ilp i II>>II i i>><<lit II i II"<<l, II l't X INDIANA 8 M ICHIGAN ELECTRIC COMPANY P.O.BOX 16631 COLUMBUS, OHIO 43216 October 3, 1983 AEP:NRC:0849 Donald C.Cook Nuclear Plant Unit No.1 Docket No.50-315 License No.DRP-58 PROPOSED CHANGE TO TECHNXCAL SPECIFICATION 4.5'.f Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Attention: |
| ACRS09NRCPDR02NTISCOPIESLTTRENCL7710111111661111RECIPIENT IDCODE/NAME NRR/DE/MTEB NRR/DL/ORAB NRR/DSI/RABRGN3LPDRNSIC0305COPIESLT'TRENCL111''01111111ITOTALNUMBEROFCOPIESREQUIRED:
| | Mr.Steven A.Varga |
| LTTR25ENCL23
| |
| >>>>),f'<<r<<l.'>00)>af<<<<i,"C)r4,fgII)>gys~,ill~<<sf]~>>)<<,III>III"lIl'I'<<'I*II'lII)Ifia'It<<4'I'3~))9))<<)iverfife)"l~<<f<<~",J'I~~~\,<<~>>fWfI<<gf<<sf,)')t<<<f~fllfrrf0fI'II)'1)I>e''>>gI)"lgkl,)>>$"i',<<>>>>I<lg~g>>>>,IlfI1!w<<>>If<<'OIl>>l<<'>>II<'t1>>il~ll)g"))ilggQ<<,ii')J)iII'il)>>kI>>0f<<>>>)~<<fIlpiII>>IIii>><<litIIiII"<<l,IIl'tX INDIANA8MICHIGANELECTRICCOMPANYP.O.BOX16631COLUMBUS, OHIO43216October3,1983AEP:NRC:0849 DonaldC.CookNuclearPlantUnitNo.1DocketNo.50-315LicenseNo.DRP-58PROPOSEDCHANGETOTECHNXCAL SPECIFICATION 4.5'.fMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555Attention: | |
| Mr.StevenA.Varga | |
|
| |
|
| ==DearMr.Denton:== | | ==Dear Mr.Denton:== |
| ThisletterrequestsachangetotheDonaldC.CookNuclearPlantUnitNo.1Technical Specification (T/S)Surveillance Requirement 4.5.2.f.toincreasethetotalflowlimittothefourbranchlinesfrom470gpmto500gpmontheBoronInjection Syst:em(singlecentrifugal chargingpump).T/S4.5.2.fcurrently requiresperformance of"...aflowbalance,testduringshutdownfollowing completion ofmodifications totheEmergency CoreCoolingSystem(ECCS)subsystem thatalterthesubsystem flowcharacteristics."
| | This letter requests a change to the Donald C.Cook Nuclear Plant Unit No.1 Technical Specification (T/S)Surveillance Requirement 4.5.2.f.to increase the total flow limit to the four branch lines from 470 gpm to 500 gpm on the Boron Injection Syst: em (single centrifugal charging pump).T/S 4.5.2.f currently requires performance of"...a flow balance , test during shutdown following completion of modifications to the Emergency Core Cooling System (ECCS)subsystem that alter the subsystem flow characteristics." The footnote (*)to this T/S currently requires The actual flow in each (Boron Xnjection) |
| Thefootnote(*)tothisT/Scurrently requiresTheactualflowineach(BoronXnjection)
| | BX line may deviate from the nominal so long as~..the total flow to the four branch lines does not exceed 470 gpm." The T/S Bases (B3/4.5.2) states, in part,"Surveillance requirements for...flow balance testing provide assurance that, proper ECCS flows will be maintained in the event of a LOCAL Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1)prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2)provide the proper split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3)provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses." ,'j)Q3fpOb000b 8~~DOS'~<~.,",.-PDR ADPCg 08000315 |
| BXlinemaydeviatefromthenominalsolongas~..thetotalflowtothefourbranchlinesdoesnotexceed470gpm."TheT/SBases(B3/4.5.2) states,inpart,"Surveillance requirements for...flowbalancetestingprovideassurance that,properECCSflowswillbemaintained intheeventofaLOCALMaintenance ofproperflowresistance andpressuredropinthepipingsystemtoeachinjection pointisnecessary to:(1)preventtotalpumpflowfromexceeding runoutconditions whenthesystemisinitsminimumresistance configuration, (2)providethepropersplitbetweeninjection pointsinaccordance withtheassumptions usedintheECCS-LOCA
| | ~~P~~h I I">,)f 1 1',I~~>IF')P I[,rl l~I a.~~:~~~1 I I I~=~P I=>II>>'r f>E),t I'~I rr)f I,)I>~")E, f.>I)',)I>r'..~IE)f~,r,'))I~Erl r>F~~~'>1')I>X'f)I~>I>)~'~'>>f, E'P*',',, h)rltrth')fg J'Fh)').'">'.>>'lf)f r~~ft.," ti>"').'1')'frt I'ft-'>Et.p..'f'1 f'.I'.'')If)1 I'>E lft>1)f f>~h'I'I''rr>I E)Et>I'>)>")'<E (f)'.)X 1)'t'I""I!)))f'>, tj)g".f))rtf>'lf>hrj>j jj>,"I'>>>h)r f,'I r f>II)lt~Fr,>" It'f I)t>P 1)I)I',~t t'X'h>>x (', f>, I fhf'I'>g.~,~~";))'t.">>,.'.i)'.f"','f>'))t>t)h>r',>~>)r>1~'.,"',>.f>>>I f, Itf',,'l>>").I'>C f.)it fr,>))"E>f Mr.Harold R.ton AEP:NRC:0849 On October 1, 1983, while performing the above surveillance requirements for flow balance testing on the centrifugal charging pumps, we found that one of the two pumps (i.e., the East pump)exceeded the maximum flow requirement. |
| : analyses, and(3)provideanacceptable leveloftotalECCSflowtoallinjection pointsequaltoorabovethatassumedintheECCS-LOCA analyses."
| | During the test, the system was set up to provide the proper flow split between injection points, and both pumps had an acceptable level of total flow to satisfy the minimum flow requirements. |
| ,'j)Q3fpOb000b 8~~DOS'~<~.,",.-PDR ADPCg08000315 | | Further adjustment of the throttle valves in the piping configuration to allow the East pump to meet the maximum flow requirement will infringe upon the minimum flow requirement for the West pump~In order to alleviate this situation, it would therefore require physical rework and retesting of the East pump to lower its performance to the extent that maximum flow came within T/S.Such rework and retesting is estimated to delay the Unit 1 startup by two weeks or longer.Therefore, on the basis of the need for power and the plant being subjected to an unnecessarily long shutdown, we request a technical specification change to allow us to operate in our"as tested condition". |
| ~~P~~hII">,)f11',I~~>IF')PI[,rll~Ia.~~:~~~1III~=~PI=>II>>'rf>E),tI'~Irr)fI,)I>~")E,f.>I)',)I>r'..~IE)f~,r,'))I~Erlr>F~~~'>1')I>X'f)I~>I>)~'~'>>f,E'P*',',,h)rltrth')fgJ'Fh)').'">'. | | The actual technical specification change request is included as Attachment, 1 to this letter.The bjsis for that change is discussed in Attachment, 2.Based on our review, we have concluded that this change would not result in an increase to the probability or consequences of a previously-analysed accident, does not, reduce a safety margin, and is clearly within all acceptable criteria with respect to the component. |
| >>'lf)fr~~ft.,"ti>"').'1')'frtI'ft-'>Et.p..'f'1f'.I'.'')If)1I'>Elft>1)ff>~h'I'I''rr>IE)Et>I'>)>")'<E(f)'.)X1)'t'I""I!)))f'>,tj)g".f))rtf>'lf>hrj>jjj>,"I'>>>h)rf,'Irf>II)lt~Fr,>"It'fI)t>P1)I)I',~tt'X'h>>x(',f>,Ifhf'I'>g. | | Since our conclusions are consistent with that published under the examples cited on page 14870 of Vol.48, No.67 of the Federal Register, it is therefore our belief that our proposed change will not constitute Significant Hazards Considerations as defined in 10 CFR 50.92.This proposed change to Technical Specification has been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at its next meeting.As required by 10 CFR 50.91(b)(1), a copy of this application for a license amendment is being transmitted to the appropriate official of the State of Michigan.AEPSC interprets 10 CFR 170.22 as requiring that a Class III Amendment Fee be paid for the change.A check in the amount of$4000 will be transmitted to you in a future letter. |
| ~,~~";))'t.">>,.'.i)'.f"','f>'))t>t)h>r',>~>)r>1~'.,"',>.f>>>If,Itf',,'l>>").I'>Cf.)itfr,>))"E>f Mr.HaroldR.tonAEP:NRC:0849 OnOctober1,1983,whileperforming theabovesurveillance requirements forflowbalancetestingonthecentrifugal chargingpumps,wefoundthatoneofthetwopumps(i.e.,theEastpump)exceededthemaximumflowrequirement. | | I")J,.P')I''Dr-F~)A 0 D A',~)'t'.)lt jVDII PX4;Di'I h Ir,l I, F)Fr AD~'A I r)A 4')1 I I 1~gp FV~Q g)-1", r D A D 1=.)I''.)'D'I A)4 11~~tg 1"''YF 4~I D F V.A D 4~F F.S X)'l I-F)I*e F'I I)-D, 4~hrtt''l I A I')k I r)ej hlV I I"',"',fjl(!e.I Il D~-I-W D f D DXJ'P~ll I I IV)'",Ff I Mr.Harold R.ton AEP:NRC:0849 Due to this letter being written on short notice, our Corporate procedures have not been followed during its preparation. |
| Duringthetest,thesystemwassetuptoprovidetheproperflowsplitbetweeninjection points,andbothpumpshadanacceptable leveloftotalflowtosatisfytheminimumflowrequirements.
| | We will review the letter according to our Corporate procedures and will inform you if any modification is required.Very truly yours M..Al ich Vice President MPA/pb cc: John E.Dolan W.G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff E.R.Swanson, NRC Resident Inspector-Bridgman J 8}} |
| Furtheradjustment ofthethrottlevalvesinthepipingconfiguration toallowtheEastpumptomeetthemaximumflowrequirement willinfringeupontheminimumflowrequirement fortheWestpump~Inordertoalleviate thissituation, itwouldtherefore requirephysicalreworkandretesting oftheEastpumptoloweritsperformance totheextentthatmaximumflowcamewithinT/S.Suchreworkandretesting isestimated todelaytheUnit1startupbytwoweeksorlonger.Therefore, onthebasisoftheneedforpowerandtheplantbeingsubjected toanunnecessarily longshutdown, werequestatechnical specification changetoallowustooperateinour"astestedcondition".
| |
| Theactualtechnical specification changerequestisincludedasAttachment, 1tothisletter.Thebjsisforthatchangeisdiscussed inAttachment, 2.Basedonourreview,wehaveconcluded thatthischangewouldnotresultinanincreasetotheprobability orconsequences ofapreviously-analysed
| |
| : accident, doesnot,reduceasafetymargin,andisclearlywithinallacceptable criteriawithrespecttothecomponent.
| |
| Sinceourconclusions areconsistent withthatpublished undertheexamplescitedonpage14870ofVol.48,No.67oftheFederalRegister, itistherefore ourbeliefthatourproposedchangewillnotconstitute Significant HazardsConsiderations asdefinedin10CFR50.92.ThisproposedchangetoTechnical Specification hasbeenreviewedandapprovedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee atitsnextmeeting.Asrequiredby10CFR50.91(b)(1),
| |
| acopyofthisapplication foralicenseamendment isbeingtransmitted totheappropriate officialoftheStateofMichigan.
| |
| AEPSCinterprets 10CFR170.22asrequiring thataClassIIIAmendment Feebepaidforthechange.Acheckintheamountof$4000willbetransmitted toyouinafutureletter.
| |
| I")J,.P')I''Dr-F~)A0DA',~)'t'.)ltjVDIIPX4;Di'IhIr,lI,F)FrAD~'AIr)A4')1II1~gpFV~Qg)-1",rDAD1=.)I''.)'D'IA)411~~tg1"''YF4~IDFV.AD4~FF.SX)'lI-F)I*eF'II)-D,4~hrtt''lIAI')kIr)ejhlVII"',"',fjl(!e.IIlD~-I-WDfDDXJ'P~llIIIV)'",FfI Mr.HaroldR.tonAEP:NRC:0849 Duetothisletterbeingwrittenonshortnotice,ourCorporate procedures havenotbeenfollowedduringitspreparation. | |
| Wewillreviewtheletteraccording toourCorporate procedures andwillinformyouifanymodification isrequired.
| |
| VerytrulyyoursM..AlichVicePresident MPA/pbcc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.CharnoffE.R.Swanson,NRCResidentInspector
| |
| -Bridgman J8}} | |
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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
REGULATOR NFORMATION DISTRIBUTION TEM (RIDS)ACCESSION NBR: 8310060006 DOC~DATE: 83/10/03 NOTARI'ZED:
NO DOCKET FACIL:50~315 Donald O, Cook Nuclear Power Planti Unit 1i Indiana 8 05000315 AUTH, NAME AUTHOR AFFILIATION ALEXICHgM~P, Indiana 8 Michigan Electric Co.RECIP.'NAME RECIPIENT AFFILIATION DENTONiH.R.
.Office of Nuclear Reactor Regulationr Director VARGAiS,A, NRC No Detailed Affiliation Given
SUBJECT:
Application to amend License.DPR-58irevising Tech'Spec 4.52.f to increase total flow limit to four branch lines from 070 gpm to 500 gpm on boron inJection sys (single centrifugal charging pump).DISTRIBUTION CODE: A001S COPIES RECEIYED:LTR ENCL,j.SIZE:, TITLE: Ray Milleri Inc: Related Correspondence (SSINS-5340)
NOTES: RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL: ELD/HDS3 NRR/DL D IR TB REG FILE 04 EXTERNAL: ACRS 09 NRC PDR 02 NTIS COPIES LTTR ENCL 7 7 1 0 1 1 1 1 1 1 6 6 1 1 1 1 RECIPIENT ID CODE/NAME NRR/DE/MTEB NRR/DL/ORAB NRR/DS I/RAB RGN3 LPDR NSIC 03 05 COPIES LT'TR ENCL 1 1 10 1 1 1 1 1 1 1 I TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 23
>>>>), f'<<r<<l.'>00)>a f<<<<i,"C)r 4, f gII)>gy s~,i ll~<>)<<,I II>I II" lI l'I'<<'I*II'l II)I fia'I t<<4'I'3~))9))<<)iver fife)"l~<<f<<~",J'I~~~\,<<~>>fW f I<<gf<<sf,)')t<<<f~f ll f r rf 0 f I'II)'1)I>e>>g I)"lgkl ,)>>$" i',<<>>>>I<lg~g>>>>, Il f I 1!w<<>>I f<<'OI l>>l<<'>>II<'t 1>>il~ll)g"))i l g g Q<<, ii')J)i II'il)>>k I>>0 f<<>>>)~<<f Ilp i II>>II i i>><<lit II i II"<<l, II l't X INDIANA 8 M ICHIGAN ELECTRIC COMPANY P.O.BOX 16631 COLUMBUS, OHIO 43216 October 3, 1983 AEP:NRC:0849 Donald C.Cook Nuclear Plant Unit No.1 Docket No.50-315 License No.DRP-58 PROPOSED CHANGE TO TECHNXCAL SPECIFICATION 4.5'.f Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Attention:
Mr.Steven A.Varga
Dear Mr.Denton:
This letter requests a change to the Donald C.Cook Nuclear Plant Unit No.1 Technical Specification (T/S)Surveillance Requirement 4.5.2.f.to increase the total flow limit to the four branch lines from 470 gpm to 500 gpm on the Boron Injection Syst: em (single centrifugal charging pump).T/S 4.5.2.f currently requires performance of"...a flow balance , test during shutdown following completion of modifications to the Emergency Core Cooling System (ECCS)subsystem that alter the subsystem flow characteristics." The footnote (*)to this T/S currently requires The actual flow in each (Boron Xnjection)
BX line may deviate from the nominal so long as~..the total flow to the four branch lines does not exceed 470 gpm." The T/S Bases (B3/4.5.2) states, in part,"Surveillance requirements for...flow balance testing provide assurance that, proper ECCS flows will be maintained in the event of a LOCAL Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1)prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2)provide the proper split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3)provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses." ,'j)Q3fpOb000b 8~~DOS'~<~.,",.-PDR ADPCg 08000315
~~P~~h I I">,)f 1 1',I~~>IF')P I[,rl l~I a.~~:~~~1 I I I~=~P I=>II>>'r f>E),t I'~I rr)f I,)I>~")E, f.>I)',)I>r'..~IE)f~,r,'))I~Erl r>F~~~'>1')I>X'f)I~>I>)~'~'>>f, E'P*',',, h)rltrth')fg J'Fh)').'">'.>>'lf)f r~~ft.," ti>"').'1')'frt I'ft-'>Et.p..'f'1 f'.I'.)If)1 I'>E lft>1)f f>~h'I'Irr>I E)Et>I'>)>")'<E (f)'.)X 1)'t'I""I!)))f'>, tj)g".f))rtf>'lf>hrj>j jj>,"I'>>>h)r f,'I r f>II)lt~Fr,>" It'f I)t>P 1)I)I',~t t'X'h>>x (', f>, I fhf'I'>g.~,~~";))'t.">>,.'.i)'.f"','f>'))t>t)h>r',>~>)r>1~'.,"',>.f>>>I f, Itf',,'l>>").I'>C f.)it fr,>))"E>f Mr.Harold R.ton AEP:NRC:0849 On October 1, 1983, while performing the above surveillance requirements for flow balance testing on the centrifugal charging pumps, we found that one of the two pumps (i.e., the East pump)exceeded the maximum flow requirement.
During the test, the system was set up to provide the proper flow split between injection points, and both pumps had an acceptable level of total flow to satisfy the minimum flow requirements.
Further adjustment of the throttle valves in the piping configuration to allow the East pump to meet the maximum flow requirement will infringe upon the minimum flow requirement for the West pump~In order to alleviate this situation, it would therefore require physical rework and retesting of the East pump to lower its performance to the extent that maximum flow came within T/S.Such rework and retesting is estimated to delay the Unit 1 startup by two weeks or longer.Therefore, on the basis of the need for power and the plant being subjected to an unnecessarily long shutdown, we request a technical specification change to allow us to operate in our"as tested condition".
The actual technical specification change request is included as Attachment, 1 to this letter.The bjsis for that change is discussed in Attachment, 2.Based on our review, we have concluded that this change would not result in an increase to the probability or consequences of a previously-analysed accident, does not, reduce a safety margin, and is clearly within all acceptable criteria with respect to the component.
Since our conclusions are consistent with that published under the examples cited on page 14870 of Vol.48, No.67 of the Federal Register, it is therefore our belief that our proposed change will not constitute Significant Hazards Considerations as defined in 10 CFR 50.92.This proposed change to Technical Specification has been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at its next meeting.As required by 10 CFR 50.91(b)(1), a copy of this application for a license amendment is being transmitted to the appropriate official of the State of Michigan.AEPSC interprets 10 CFR 170.22 as requiring that a Class III Amendment Fee be paid for the change.A check in the amount of$4000 will be transmitted to you in a future letter.
I")J,.P')IDr-F~)A 0 D A',~)'t'.)lt jVDII PX4;Di'I h Ir,l I, F)Fr AD~'A I r)A 4')1 I I 1~gp FV~Q g)-1", r D A D 1=.)I.)'D'I A)4 11~~tg 1"YF 4~I D F V.A D 4~F F.S X)'l I-F)I*e F'I I)-D, 4~hrttl I A I')k I r)ej hlV I I"',"',fjl(!e.I Il D~-I-W D f D DXJ'P~ll I I IV)'",Ff I Mr.Harold R.ton AEP:NRC:0849 Due to this letter being written on short notice, our Corporate procedures have not been followed during its preparation.
We will review the letter according to our Corporate procedures and will inform you if any modification is required.Very truly yours M..Al ich Vice President MPA/pb cc: John E.Dolan W.G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff E.R.Swanson, NRC Resident Inspector-Bridgman J 8
