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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstolicensesDPR-586DPR-74,revising TSTable4.8-2fromeighthtocomposite fourhbatteryemergency loadsforAB(Train-B) 6CD(Train-A) batteries 6deletingloadonlTrainBbatteries loadlist.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR | | Application for amends to licenses DPR-58 6 DPR-74,revising TS Table 4.8-2 from eight h to composite four h battery emergency loads for AB (Train-B)6 CD (Train-A)batteries 6 deleting load onlTrain B batteries load list.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR |
| !ENCLISIZE:TITLE:ORSubmittal: | | !ENCL I SIZE: TITLE: OR Submittal: |
| GeneralDistribution NOTESACCESSION NBR:9312290102 DOC.DATE:
| | General Distribution NOTES ACCESSION NBR:9312290102 DOC.DATE: 93/12/20 NOTARIZED: |
| 93/12/20NOTARIZED: | | YES FACIL:50-315 Donald C.Cook Nuclear Power Plant,, Unit 1, Indiana M 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E. |
| YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
| | Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele'ECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. |
| IndianaMichiganPowerCo.(formerly Indiana6MichiganEle'ECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
| | Document Control Branch (Document Control Desk)R RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTS B NRR/DRPN NRR/DSSA/SRXB O~C B CREG F 01 NSIC COPIES LTTR ENCL 1 1 1, 1 1 1 1 1 1 0 1 1 1.1 D D D NOTE TO ALL"RIDS" RECIPIENTS: |
| DocumentControlBranch(Document ControlDesk)RRECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:
| | D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 Indiana Michiga~~Power Compan~P.O.Box 16631 Columbus, OH 43216 5 AEP:NRC:0896R Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 TECHNICAL SPECIFICATION CHANGE REQUEST: REVISE THE TRAIN A/B BATTERIES'ROFILES AND MODIFY TRAIN N BATTERIES'ROFILES U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: T.E.Murley December 20, 1993 |
| NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2EXTERNAL: | |
| NRCPDRCOPIESLTTRENCL1122111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DORS/OTS BNRR/DRPNNRR/DSSA/SRXB O~CBCREGF01NSICCOPIESLTTRENCL111,1111110111.1DDDNOTETOALL"RIDS"RECIPIENTS:
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| DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
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| LTTR16ENCL14 IndianaMichiga~~
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| PowerCompan~P.O.Box16631Columbus, OH432165AEP:NRC:0896R DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74TECHNICAL SPECIFICATION CHANGEREQUEST:REVISETHETRAINA/BBATTERIES'ROFILES ANDMODIFYTRAINNBATTERIES'ROFILES U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyDecember20,1993
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| ==DearDr.Murley:== | | ==Dear Dr.Murley:== |
| Thisletteranditsattachments constitute anapplication foramendment.
| | This letter and its attachments constitute an application for amendment. |
| totheTechnical Specifications (T/S)fortheDonaldC.CookNuclearPlantUnits1and2inaccordance with10CFR50.90.TheproposedchangerevisesT/STable4.8-2fromeighthourtocomposite fourhourBatteryEmergency LoadsforAB(TRAIN-B) andCD(TRAIN-A) batteries.
| | to the Technical Specifications (T/S)for the Donald C.Cook Nuclear Plant Units 1 and 2 in accordance with 10 CFR 50.90.The proposed change revises T/S Table 4.8-2 from eight hour to composite four hour Battery Emergency Loads for AB (TRAIN-B)and CD (TRAIN-A)batteries. |
| Inaddition, weareproposing todeletealoadontheTrainBbatteries loadlist.Also,thisproposedchangemodifiesT/STable4.8-3fortheNTrainbatteries toaccurately reflecttheoperation loadsofthesebatteries asrecordedintheircomposite profiles.
| | In addition, we are proposing to delete a load on the Train B batteries load list.Also, this proposed change modifies T/S Table 4.8-3 for the N Train batteries to accurately reflect the operation loads of these batteries as recorded in their composite profiles.This change is consistent with LOCA/LOOP and Station Blackout for Donald C.Cook Nuclear Plant and the new Standard Technical Specifications for Westinghouse plants, published by the NRC as NUREG 1431, dated September 28, 1992.Attachment 1 provides a detailed description of the proposed change, the justification for the change, and our proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92.Attachment 2 contains the existing T/S pages marked to reflect the proposed change.Attachment 3 contains the proposed, revised T/S pages."700>3 9312290102 931220'DR ADOCK 05000315''PDR |
| Thischangeisconsistent withLOCA/LOOP andStationBlackoutforDonaldC.CookNuclearPlantandthenewStandardTechnical Specifications forWestinghouse plants,published bytheNRCasNUREG1431,datedSeptember 28,1992.Attachment 1providesadetaileddescription oftheproposedchange,thejustification forthechange,andourproposeddetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchange.Attachment 3containstheproposed, revisedT/Spages."700>39312290102 931220'DR ADOCK05000315'
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| aDr.T.E.Murley-2-AEP:NRC:0896R Webelievethattheproposedchangewillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountofanyeffluents thatmaybereleasedoffsite,and(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
| | a Dr.T.E.Murley-2-AEP:NRC:0896R We believe that the proposed change will not result in (1)a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, and (2)a significant increase in individual or cumulative occupational radiation exposure.The proposed change has been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety and Design Review Committee. |
| TheproposedchangehasbeenreviewedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommittee.
| | In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr.J.R.Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health.This letter is submitted pursuant to 10 CFR 50.30(b)and, as such, an oath statement is attached.Sincerely, Vice President eh Attachments cc: A.A.Blind-Bridgman G.Charnoff J.B.Martin-Region III NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett COUNTY OF FRANKLIN E.E.Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing Technical Specification Change Request: Revise the Train A/B Batteries'rofiles and Modify Train N Batteries'rofiles and knows the contents thereof;and that said contents are true to the best of his knowledge and belief.Subscribed and sworn to before me this~yA day of 19~>N TARY PU IC RITA 0.HILL NOTARY POBI.IC, STATE OF OHIO Attachment 1 to AEP:NRC:0896R 10CFR50.92 Determination for Proposed Changes to the Donald C.Cook Nuclear Plant Units 1 and 2 Technical Specifications Attachment 1 to AEP:NRC:0896R Page 1 1.0 SECTIONS TO BE CHANGED Unit 1: Table 4.8-2 Table 4.8-3 Unit 2: Table 4.8-2 Table 4.8-3 2.0 EXTENT OF CHANGES.We are proposing to revise the CD batteries'Train A)and the AB batteries'Train B)eight hour profiles to four hour profiles and we are proposing to modify the Train N batteries'xisting four hour profiles.Additionally, we are proposing to delete a load on the Train B batteries'oad list.3.0 CHANGES RE UESTED Identical changes are being sought for both the Unit 1 and Unit 2 Technical Specifications. |
| Incompliance withtherequirements of10CFR50.91(b)(1),
| | Revise the Batter Emer enc Loads tables Table 4.8-2 on page 3/4 8-15 lists the eight hour Battery Emergency Loads for the AB and CD batteries and Table 4.8-3 on page 3/4 8-19 lists the four hour Battery Emergency Loads for the N battery.We are proposing to revise these tables (as illustrated in Attachments 2 and 3)since, as addressed in Paragraph 2.0, we have proposed revision of the Train A/B batteries'ight hour profiles and modification of the Train N battery's four hour profile.Additionally, we are proposing to delete the FMO and TDTV valve"Operating Sequence" list from Table 4.8-3 since it is no longer used to place actual loads on the Train N battery during surveillance testing.Instead, simulated loads are placed on the battery as allowed by a previous T/S change (AEP:NRC:0896J). |
| copiesofthisletteranditsattachments havebeentransmitted toMr.J.R.PadgettoftheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.30(b)and,assuch,anoathstatement isattached.
| | Delete a load from the AB Batter Loads list Table 4.8-2 on page 3/4 8-15 lists as a load the"Computer Static Inverter". |
| Sincerely, VicePresident ehAttachments cc:A.A.Blind-BridgmanG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector | | We are proposing to delete this load from the table since this load was physically removed from the Train B battery as a function of a design change.4.0 DISCUSSION The 250 VDC System provides a reliable source of continuous power for supply and control of plant safety systems.Included in the Attachment 1 to AEP:NRC:0896R Page 2 safety systems are the reactor trip syst: em, engineered safety features, and auxiliary support features.A number of different DC plant loads are served from each of the main and transfer distribution cabinets.The plant loads include control circuits (switchgear 6 annunciators), static inverters, valve control centers, emergency lighting, and motor control centers, in general, plus vital bus inverters, fire protection control, and main turbine lube oil pumps, in particular. |
| -BridgmanJ.R.Padgett COUNTYOFFRANKLINE.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnical Specification ChangeRequest:RevisetheTrainA/BBatteries'rofiles andModifyTrainNBatteries'rofiles andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed andsworntobeforemethis~yAdayof19~>NTARYPUICRITA0.HILLNOTARYPOBI.IC,STATEOFOHIO Attachment 1toAEP:NRC:0896R 10CFR50.92 Determination forProposedChangestotheDonaldC.CookNuclearPlantUnits1and2Technical Specifications Attachment 1toAEP:NRC:0896R Page11.0SECTIONSTOBECHANGEDUnit1:Table4.8-2Table4.8-3Unit2:Table4.8-2Table4.8-32.0EXTENTOFCHANGES.Weareproposing torevisetheCDbatteries'Train A)andtheABbatteries'Train B)eighthourprofilestofourhourprofilesandweareproposing tomodifytheTrainNbatteries'xisting fourhourprofiles. | | The N Train loads include the turbine driven aux feedwater (TDAFW)control bus, the AMSAC inverter, and a valve control center.This submittal addresses the test durations for the emergency loads on the Class 1E batteries and the deletion of a load on the Train B batteries. |
| Additionally, weareproposing todeletealoadontheTrainBbatteries'oad list.3.0CHANGESREUESTEDIdentical changesarebeingsoughtforboththeUnit1andUnit2Technical Specifications. | | Reason for Pro osed Technical S ecification Chan e Re uest There are two reasons we are proposing a change to the Technical Specifications. |
| RevisetheBatterEmerencLoadstablesTable4.8-2onpage3/48-15liststheeighthourBatteryEmergency LoadsfortheABandCDbatteries andTable4.8-3onpage3/48-19liststhefourhourBatteryEmergency LoadsfortheNbattery.Weareproposing torevisethesetables(asillustrated inAttachments 2and3)since,asaddressed inParagraph 2.0,wehaveproposedrevisionoftheTrainA/Bbatteries'ight hourprofilesandmodification oftheTrainNbattery's fourhourprofile.Additionally, weareproposing todeletetheFMOandTDTVvalve"Operating Sequence" listfromTable4.8-3sinceitisnolongerusedtoplaceactualloadsontheTrainNbatteryduringsurveillance testing.Instead,simulated loadsareplacedonthebatteryasallowedbyapreviousT/Schange(AEP:NRC:0896J).
| | The first deals with changing the design duty cycles of'the Train A/B batteries from eight hour profiles to four hour profiles and modifing the existing four hour profiles of the N Train batteries. |
| DeletealoadfromtheABBatterLoadslistTable4.8-2onpage3/48-15listsasaloadthe"Computer StaticInverter".
| | The second deals with removing the"Computer Static Inverter" load from the AB Battery Loads portion of Table 4.8-2.The following discussion provides more details regarding the proposed changes.The existing Battery Emergency Loads tables in the Technical Specifications represent eight hour duty cycles for the A/B Train batteries and four hour duty cycles for the N Train batteries. |
| Weareproposing todeletethisloadfromthetablesincethisloadwasphysically removedfromtheTrainBbatteryasafunctionofadesignchange.4.0DISCUSSION The250VDCSystemprovidesareliablesourceofcontinuous powerforsupplyandcontrolofplantsafetysystems.Includedinthe Attachment 1toAEP:NRC:0896R Page2safetysystemsarethereactortripsyst:em,engineered safetyfeatures, andauxiliary supportfeatures.
| | As discussed below, however, the nuclear related DC loads are only tested to three hours even though the overall profile is eight hours.Vhereas this proposal intends only to modify the four hour duty cycle for the N Train batteries, it intends to change the duty cycles for the A/B Train batteries from their current eight hour duty cycles to"composite" four hour duty cycles.The details of this change follow.A." The existing Train A/B eight hour duty cycles contain two distinct requirements: |
| Anumberofdifferent DCplantloadsareservedfromeachofthemainandtransferdistribution cabinets.
| | 1)The nuclear related DC loads are required to be supplied by the batteries for three hours.This is based on a LOCA/LOOP event, a failure of the associated battery charger and a reasonable time to restore the battery charger or spare charger to service.This.three hour requirement is included in Chapter 8 of the UFSAR. |
| Theplantloadsincludecontrolcircuits(switchgear 6annunciators),
| | Attachment 1 to AEP:NRC:0896R Page 3 2)The turbine shutdown loads are required for eight hours to properly cool down the main and feed pump turbines'il lubricated components. |
| staticinverters, valvecontrolcenters,emergency
| | This is based on operational experience and is not discussed in the UFSAR.B.Since the three hour duty cycles have their basis in the UFSAR and Donald C.Cook Nuclear Plant has committed to four hour station blackout (SBO)duty cycles, these two duty cycles form the basis for the proposed four hour composite load profiles.The eight hour loads listed in the existing T/S Battery Emergency Loads tables are no longer valid since a four hour coping duration has been established for Cook Nuclear Plant upon a Loss of All AC (SBO)event.This means, at worst, that DC.loads are required only to cope for four hours on the batteries with no AC powered battery charger.As a function of the Station Blackout Rule, four hour load profiles were developed for the A/B Train batteries. |
| : lighting, andmotorcontrolcenters,ingeneral,plusvitalbusinverters, fireprotection control,andmainturbinelubeoilpumps,inparticular.
| | These profiles include load shedding of certain loads one hour into the event as allowed by NUMARC 87-00 and the NRC.Since SBO has become a condition for operating the Cook Nuclear Plant and since the UFSAR continues to be a condition for operating the plant, the proposed profiles of record for the Class 1E batteries are composites of both the three hour UFSAR load profiles and the four hour SBO profiles.The composite profiles envelope both of their constituent profiles and as such represent conservative sizing/application of the Class lE batteries. |
| TheNTrainloadsincludetheturbinedrivenauxfeedwater (TDAFW)controlbus,theAMSACinverter, andavalvecontrolcenter.Thissubmittal addresses thetestdurations fortheemergency loadsontheClass1Ebatteries andthedeletionofaloadontheTrainBbatteries.
| | For the A/B Train batteries, it is desired to revise the"Minimum Time" column of the Battery Emergency Loads tables (as illustrated in Attachments 2 and 3)to reflect the time durations included in the composite profiles.The composite profiles of the batteries (as discussed previously) envelope the worst case conditions for the station batteries and are maintained as formal calculations in the Power Systems and Human Factors (NEEP)section of the Nuclear Engineering Department (NE).For the N Train batteries, it is desired to revise the"Minimum Time" column and to remove the valve operating sequence list of Table 4..8-3 as shown in Attachments 2 and 3.It should be noted that these modifications do not change the T/S four hour duty cycle of the N Train batteries. |
| ReasonforProosedTechnical Secification ChaneReuestTherearetworeasonsweareproposing achangetotheTechnical Specifications.
| | Rather, the modifications are intended to more accurately reflect the operation of the N Train battery loads.as recorded in the composite profiles for these batteries. |
| Thefirstdealswithchangingthedesigndutycyclesof'theTrainA/Bbatteries fromeighthourprofilestofourhourprofilesandmodifingtheexistingfourhourprofilesoftheNTrainbatteries.
| | Removal of the valve operating sequence portion of Attachment 1 to AEP:NRC:0896R Page 4 the table will have no impact on the testing of the valves to the composite profiles..This list is being removed because it is no longer used.It had been used to place actual loads on the N Train batteries but since the approval of T/S change AEP:NRC;0896J, only simulated loads have been placed on the batteries during surveillance testing.These batteries will continue to be tested to their design basis duty cycles (composite profiles)using simulated loading.Like the Train A/B composite profiles, the Train N composite profiles envelope the worst case conditions for these batteries and are maintained as formal calculations in the NEEP section of NE.It is desired to remove the"Computer Static Inverter" load from Table 4.8-2 (as shown in Attachments 2 and 3)since this load was physically removed from the AB Batteries as a function of design change RFC-12-2996,"Upgrade Plant Process Computer System".The power supply for this system is now the Technical Support Center Uninterruptible Power Supply system.Justification for Pro osed Technical S ecification Chan es The composite load profiles for the Train A/B batteries are a result of the combination of the three hour LOCA/LOOP and four hour SBO battery load profiles.The three hour LOCA/LOOP load profiles are a function of the UFSAR for the Cook Nuclear Plant whereas the four hour SBO load profiles were performed for the NUMARC 87-00 Station Blackout Rule.These load profiles were compared to determine the most demanding loading of the station batteries. |
| Theseconddealswithremovingthe"Computer StaticInverter" loadfromtheABBatteryLoadsportionofTable4.8-2.Thefollowing discussion providesmoredetailsregarding theproposedchanges.TheexistingBatteryEmergency LoadstablesintheTechnical Specifications represent eighthourdutycyclesfortheA/BTrainbatteries andfourhourdutycyclesfortheNTrainbatteries.
| | Since the LOCA/LOOP set of load profiles generally detailed a higher first-minute load and the SBO set yielded a longer loading period, the composite load profiles were developed to envelope the worst case profiles for each battery.These composite load profiles are intended for use as the models for performance of the 18-month surveillance testing of the batteries. |
| Asdiscussed below,however,thenuclearrelatedDCloadsareonlytestedtothreehourseventhoughtheoverallprofileiseighthours.VhereasthisproposalintendsonlytomodifythefourhourdutycyclefortheNTrainbatteries, itintendstochangethedutycyclesfortheA/BTrainbatteries fromtheircurrenteighthourdutycyclesto"composite" fourhourdutycycles.Thedetailsofthischangefollow.A."TheexistingTrainA/Beighthourdutycyclescontaintwodistinctrequirements:
| | Additionally, since Cook Nuclear Plant has been designated as a four hour plane for an SBO event, retaining the eight hour battery duty cycles is no longer justifiable. |
| 1)ThenuclearrelatedDCloadsarerequiredtobesuppliedbythebatteries forthreehours.ThisisbasedonaLOCA/LOOP event,afailureoftheassociated batterychargerandareasonable timetorestorethebatterychargerorsparechargertoservice.This.threehourrequirement isincludedinChapter8oftheUFSAR. | | The composite load profiles for the N Train batteries, which remain unchanged at four hours in duration, are more conservative and more accurately reflect the postulated loads on these batteries than what is listed in the Technical Specifications. |
| Attachment 1toAEP:NRC:0896R Page32)Theturbineshutdownloadsarerequiredforeighthourstoproperlycooldownthemainandfeedpumpturbines'il lubricated components. | | The composite load profiles are intended for use as the models for performance of the 18-month surveillance testing of the batteries. |
| Thisisbasedonoperational experience andisnotdiscussed intheUFSAR.B.SincethethreehourdutycycleshavetheirbasisintheUFSARandDonaldC.CookNuclearPlanthascommitted tofourhourstationblackout(SBO)dutycycles,thesetwodutycyclesformthebasisfortheproposedfourhourcomposite loadprofiles.
| | The valve operating sequence list of Table 4.8-3 is being removed because it is no longer used to place actual loads on.the N Train batteries during surveillance testing.Instead, Attachment 1 to AEP:NRC:0896R Page 5 the N Train batteries will continue to be tested (using the composites profiles as the basis)using simulated loads.The justification for removing the Computer Static Inverter Load from the AB Battery Loads list is self-explanatory. |
| TheeighthourloadslistedintheexistingT/SBatteryEmergency Loadstablesarenolongervalidsinceafourhourcopingdurationhasbeenestablished forCookNuclearPlantuponaLossofAllAC(SBO)event.Thismeans,atworst,thatDC.loadsarerequiredonlytocopeforfourhoursonthebatteries withnoACpoweredbatterycharger.AsafunctionoftheStationBlackoutRule,fourhourloadprofilesweredeveloped fortheA/BTrainbatteries.
| | 5.0 10 CFR 50.92 CRITERIA Per 10 CFR 50.92, a proposed amendment does not involve a s'ignificant hazards consideration if the change does not: (1)involve a significant increase in the probability or consequences of an accident previously evaluated. |
| TheseprofilesincludeloadsheddingofcertainloadsonehourintotheeventasallowedbyNUMARC87-00andtheNRC.SinceSBOhasbecomeacondition foroperating theCookNuclearPlantandsincetheUFSARcontinues tobeacondition foroperating theplant,theproposedprofilesofrecordfortheClass1Ebatteries arecomposites ofboththethreehourUFSARloadprofilesandthefourhourSBOprofiles.
| | (2)create the possibility of a new or different kind of accident from any previously analyzed.(3)involve a significant reduction in a margin of safety.Criterion 1 The change is proposed to comply with the LOCA/LOOP and SBO requirement for Cook Nuclear Plant for battery testing.The composite test as addressed above meets these requirements for four hour test profiles.This change is consistent with the UFSAR three hour LOCA/LOOP and NUMARC 87-00 Station Blackout Rule four hour.Based on these considerations, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. |
| Thecomposite profilesenvelopebothoftheirconstituent profilesandassuchrepresent conservative sizing/application oftheClasslEbatteries.
| | Criterion 2 The change only addresses the battery profile test which meets both LOCA/LOOP and SBO for Cook Nuclear Plant.No specific physical or operational changes to the plant will occur due to this change.Thus, the change will not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| FortheA/BTrainbatteries, itisdesiredtorevisethe"MinimumTime"columnoftheBatteryEmergency Loadstables(asillustrated inAttachments 2and3)toreflectthetimedurations includedinthecomposite profiles.
| | Criterion 3 The proposed change revises the battery profile test table from an eight hour to a four hour composite test which complies with both LOCA/LOOP and SBO as defined for Cook Nuclear Plant.Therefore, the proposed change does not involve a significant reduction in a margin of safety.}} |
| Thecomposite profilesofthebatteries (asdiscussed previously) envelopetheworstcaseconditions forthestationbatteries andaremaintained asformalcalculations inthePowerSystemsandHumanFactors(NEEP)sectionoftheNuclearEngineering Department (NE).FortheNTrainbatteries, itisdesiredtorevisethe"MinimumTime"columnandtoremovethevalveoperating sequencelistofTable4..8-3asshowninAttachments 2and3.Itshouldbenotedthatthesemodifications donotchangetheT/SfourhourdutycycleoftheNTrainbatteries.
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| Rather,themodifications areintendedtomoreaccurately reflecttheoperation oftheNTrainbatteryloads.asrecordedinthecomposite profilesforthesebatteries. | |
| Removalofthevalveoperating sequenceportionof Attachment 1toAEP:NRC:0896R Page4thetablewillhavenoimpactonthetestingofthevalvestothecomposite profiles.
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| .Thislistisbeingremovedbecauseitisnolongerused.IthadbeenusedtoplaceactualloadsontheNTrainbatteries butsincetheapprovalofT/SchangeAEP:NRC;0896J, onlysimulated loadshavebeenplacedonthebatteries duringsurveillance testing.Thesebatteries willcontinuetobetestedtotheirdesignbasisdutycycles(composite profiles) usingsimulated loading.LiketheTrainA/Bcomposite | |
| : profiles, theTrainNcomposite profilesenvelopetheworstcaseconditions forthesebatteries andaremaintained asformalcalculations intheNEEPsectionofNE.Itisdesiredtoremovethe"Computer StaticInverter" loadfromTable4.8-2(asshowninAttachments 2and3)sincethisloadwasphysically removedfromtheABBatteries asafunctionofdesignchangeRFC-12-2996, "UpgradePlantProcessComputerSystem".ThepowersupplyforthissystemisnowtheTechnical SupportCenterUninterruptible PowerSupplysystem.Justification forProosedTechnical Secification ChanesThecomposite loadprofilesfortheTrainA/Bbatteries arearesultofthecombination ofthethreehourLOCA/LOOP andfourhourSBObatteryloadprofiles.
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| ThethreehourLOCA/LOOP loadprofilesareafunctionoftheUFSARfortheCookNuclearPlantwhereasthefourhourSBOloadprofileswereperformed fortheNUMARC87-00StationBlackoutRule.Theseloadprofileswerecomparedtodetermine themostdemanding loadingofthestationbatteries.
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| SincetheLOCA/LOOP setofloadprofilesgenerally detailedahigherfirst-minute loadandtheSBOsetyieldedalongerloadingperiod,thecomposite loadprofilesweredeveloped toenvelopetheworstcaseprofilesforeachbattery.Thesecomposite loadprofilesareintendedforuseasthemodelsforperformance ofthe18-monthsurveillance testingofthebatteries.
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| Additionally, sinceCookNuclearPlanthasbeendesignated asafourhourplaneforanSBOevent,retaining theeighthourbatterydutycyclesisnolongerjustifiable. | |
| Thecomposite loadprofilesfortheNTrainbatteries, whichremainunchanged atfourhoursinduration, aremoreconservative andmoreaccurately reflectthepostulated loadsonthesebatteries thanwhatislistedintheTechnical Specifications.
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| Thecomposite loadprofilesareintendedforuseasthemodelsforperformance ofthe18-monthsurveillance testingofthebatteries.
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| Thevalveoperating sequencelistofTable4.8-3isbeingremovedbecauseitisnolongerusedtoplaceactualloadson.theNTrainbatteries duringsurveillance testing.Instead, Attachment 1toAEP:NRC:0896R Page5theNTrainbatteries willcontinuetobetested(usingthecomposites profilesasthebasis)usingsimulated loads.Thejustification forremovingtheComputerStaticInverterLoadfromtheABBatteryLoadslistisself-explanatory.
| |
| 5.010CFR50.92CRITERIAPer10CFR50.92,aproposedamendment doesnotinvolveas'ignificant hazardsconsideration ifthechangedoesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. | |
| (2)createthepossibility ofanewordifferent kindofaccidentfromanypreviously analyzed. | |
| (3)involveasignificant reduction inamarginofsafety.Criterion 1ThechangeisproposedtocomplywiththeLOCA/LOOP andSBOrequirement forCookNuclearPlantforbatterytesting.Thecomposite testasaddressed abovemeetstheserequirements forfourhourtestprofiles. | |
| Thischangeisconsistent withtheUFSARthreehourLOCA/LOOP andNUMARC87-00StationBlackoutRulefourhour.Basedontheseconsiderations, theproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
| |
| Criterion 2Thechangeonlyaddresses thebatteryprofiletestwhichmeetsbothLOCA/LOOP andSBOforCookNuclearPlant.Nospecificphysicaloroperational changestotheplantwilloccurduetothischange.Thus,thechangewillnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. | |
| Criterion 3Theproposedchangerevisesthebatteryprofiletesttablefromaneighthourtoafourhourcomposite testwhichcomplieswithbothLOCA/LOOP andSBOasdefinedforCookNuclearPlant.Therefore, theproposedchangedoesnotinvolveasignificant reduction inamarginofsafety.}} | |
Similar Documents at Cook |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
ACCELERATED 7S'BUBUTION DEMON MWTION SYSTEM 4 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DOCKET 05000315 05000316
SUBJECT:
Application for amends to licenses DPR-58 6 DPR-74,revising TS Table 4.8-2 from eight h to composite four h battery emergency loads for AB (Train-B)6 CD (Train-A)batteries 6 deleting load onlTrain B batteries load list.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR
!ENCL I SIZE: TITLE: OR Submittal:
General Distribution NOTES ACCESSION NBR:9312290102 DOC.DATE: 93/12/20 NOTARIZED:
YES FACIL:50-315 Donald C.Cook Nuclear Power Plant,, Unit 1, Indiana M 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele'ECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)R RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTS B NRR/DRPN NRR/DSSA/SRXB O~C B CREG F 01 NSIC COPIES LTTR ENCL 1 1 1, 1 1 1 1 1 1 0 1 1 1.1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 Indiana Michiga~~Power Compan~P.O.Box 16631 Columbus, OH 43216 5 AEP:NRC:0896R Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 TECHNICAL SPECIFICATION CHANGE REQUEST: REVISE THE TRAIN A/B BATTERIES'ROFILES AND MODIFY TRAIN N BATTERIES'ROFILES U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: T.E.Murley December 20, 1993
Dear Dr.Murley:
This letter and its attachments constitute an application for amendment.
to the Technical Specifications (T/S)for the Donald C.Cook Nuclear Plant Units 1 and 2 in accordance with 10 CFR 50.90.The proposed change revises T/S Table 4.8-2 from eight hour to composite four hour Battery Emergency Loads for AB (TRAIN-B)and CD (TRAIN-A)batteries.
In addition, we are proposing to delete a load on the Train B batteries load list.Also, this proposed change modifies T/S Table 4.8-3 for the N Train batteries to accurately reflect the operation loads of these batteries as recorded in their composite profiles.This change is consistent with LOCA/LOOP and Station Blackout for Donald C.Cook Nuclear Plant and the new Standard Technical Specifications for Westinghouse plants, published by the NRC as NUREG 1431, dated September 28, 1992.Attachment 1 provides a detailed description of the proposed change, the justification for the change, and our proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92.Attachment 2 contains the existing T/S pages marked to reflect the proposed change.Attachment 3 contains the proposed, revised T/S pages."700>3 9312290102 931220'DR ADOCK 05000315PDR
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a Dr.T.E.Murley-2-AEP:NRC:0896R We believe that the proposed change will not result in (1)a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, and (2)a significant increase in individual or cumulative occupational radiation exposure.The proposed change has been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety and Design Review Committee.
In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr.J.R.Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health.This letter is submitted pursuant to 10 CFR 50.30(b)and, as such, an oath statement is attached.Sincerely, Vice President eh Attachments cc: A.A.Blind-Bridgman G.Charnoff J.B.Martin-Region III NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett COUNTY OF FRANKLIN E.E.Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing Technical Specification Change Request: Revise the Train A/B Batteries'rofiles and Modify Train N Batteries'rofiles and knows the contents thereof;and that said contents are true to the best of his knowledge and belief.Subscribed and sworn to before me this~yA day of 19~>N TARY PU IC RITA 0.HILL NOTARY POBI.IC, STATE OF OHIO Attachment 1 to AEP:NRC:0896R 10CFR50.92 Determination for Proposed Changes to the Donald C.Cook Nuclear Plant Units 1 and 2 Technical Specifications Attachment 1 to AEP:NRC:0896R Page 1 1.0 SECTIONS TO BE CHANGED Unit 1: Table 4.8-2 Table 4.8-3 Unit 2: Table 4.8-2 Table 4.8-3 2.0 EXTENT OF CHANGES.We are proposing to revise the CD batteries'Train A)and the AB batteries'Train B)eight hour profiles to four hour profiles and we are proposing to modify the Train N batteries'xisting four hour profiles.Additionally, we are proposing to delete a load on the Train B batteries'oad list.3.0 CHANGES RE UESTED Identical changes are being sought for both the Unit 1 and Unit 2 Technical Specifications.
Revise the Batter Emer enc Loads tables Table 4.8-2 on page 3/4 8-15 lists the eight hour Battery Emergency Loads for the AB and CD batteries and Table 4.8-3 on page 3/4 8-19 lists the four hour Battery Emergency Loads for the N battery.We are proposing to revise these tables (as illustrated in Attachments 2 and 3)since, as addressed in Paragraph 2.0, we have proposed revision of the Train A/B batteries'ight hour profiles and modification of the Train N battery's four hour profile.Additionally, we are proposing to delete the FMO and TDTV valve"Operating Sequence" list from Table 4.8-3 since it is no longer used to place actual loads on the Train N battery during surveillance testing.Instead, simulated loads are placed on the battery as allowed by a previous T/S change (AEP:NRC:0896J).
Delete a load from the AB Batter Loads list Table 4.8-2 on page 3/4 8-15 lists as a load the"Computer Static Inverter".
We are proposing to delete this load from the table since this load was physically removed from the Train B battery as a function of a design change.4.0 DISCUSSION The 250 VDC System provides a reliable source of continuous power for supply and control of plant safety systems.Included in the Attachment 1 to AEP:NRC:0896R Page 2 safety systems are the reactor trip syst: em, engineered safety features, and auxiliary support features.A number of different DC plant loads are served from each of the main and transfer distribution cabinets.The plant loads include control circuits (switchgear 6 annunciators), static inverters, valve control centers, emergency lighting, and motor control centers, in general, plus vital bus inverters, fire protection control, and main turbine lube oil pumps, in particular.
The N Train loads include the turbine driven aux feedwater (TDAFW)control bus, the AMSAC inverter, and a valve control center.This submittal addresses the test durations for the emergency loads on the Class 1E batteries and the deletion of a load on the Train B batteries.
Reason for Pro osed Technical S ecification Chan e Re uest There are two reasons we are proposing a change to the Technical Specifications.
The first deals with changing the design duty cycles of'the Train A/B batteries from eight hour profiles to four hour profiles and modifing the existing four hour profiles of the N Train batteries.
The second deals with removing the"Computer Static Inverter" load from the AB Battery Loads portion of Table 4.8-2.The following discussion provides more details regarding the proposed changes.The existing Battery Emergency Loads tables in the Technical Specifications represent eight hour duty cycles for the A/B Train batteries and four hour duty cycles for the N Train batteries.
As discussed below, however, the nuclear related DC loads are only tested to three hours even though the overall profile is eight hours.Vhereas this proposal intends only to modify the four hour duty cycle for the N Train batteries, it intends to change the duty cycles for the A/B Train batteries from their current eight hour duty cycles to"composite" four hour duty cycles.The details of this change follow.A." The existing Train A/B eight hour duty cycles contain two distinct requirements:
1)The nuclear related DC loads are required to be supplied by the batteries for three hours.This is based on a LOCA/LOOP event, a failure of the associated battery charger and a reasonable time to restore the battery charger or spare charger to service.This.three hour requirement is included in Chapter 8 of the UFSAR.
Attachment 1 to AEP:NRC:0896R Page 3 2)The turbine shutdown loads are required for eight hours to properly cool down the main and feed pump turbines'il lubricated components.
This is based on operational experience and is not discussed in the UFSAR.B.Since the three hour duty cycles have their basis in the UFSAR and Donald C.Cook Nuclear Plant has committed to four hour station blackout (SBO)duty cycles, these two duty cycles form the basis for the proposed four hour composite load profiles.The eight hour loads listed in the existing T/S Battery Emergency Loads tables are no longer valid since a four hour coping duration has been established for Cook Nuclear Plant upon a Loss of All AC (SBO)event.This means, at worst, that DC.loads are required only to cope for four hours on the batteries with no AC powered battery charger.As a function of the Station Blackout Rule, four hour load profiles were developed for the A/B Train batteries.
These profiles include load shedding of certain loads one hour into the event as allowed by NUMARC 87-00 and the NRC.Since SBO has become a condition for operating the Cook Nuclear Plant and since the UFSAR continues to be a condition for operating the plant, the proposed profiles of record for the Class 1E batteries are composites of both the three hour UFSAR load profiles and the four hour SBO profiles.The composite profiles envelope both of their constituent profiles and as such represent conservative sizing/application of the Class lE batteries.
For the A/B Train batteries, it is desired to revise the"Minimum Time" column of the Battery Emergency Loads tables (as illustrated in Attachments 2 and 3)to reflect the time durations included in the composite profiles.The composite profiles of the batteries (as discussed previously) envelope the worst case conditions for the station batteries and are maintained as formal calculations in the Power Systems and Human Factors (NEEP)section of the Nuclear Engineering Department (NE).For the N Train batteries, it is desired to revise the"Minimum Time" column and to remove the valve operating sequence list of Table 4..8-3 as shown in Attachments 2 and 3.It should be noted that these modifications do not change the T/S four hour duty cycle of the N Train batteries.
Rather, the modifications are intended to more accurately reflect the operation of the N Train battery loads.as recorded in the composite profiles for these batteries.
Removal of the valve operating sequence portion of Attachment 1 to AEP:NRC:0896R Page 4 the table will have no impact on the testing of the valves to the composite profiles..This list is being removed because it is no longer used.It had been used to place actual loads on the N Train batteries but since the approval of T/S change AEP:NRC;0896J, only simulated loads have been placed on the batteries during surveillance testing.These batteries will continue to be tested to their design basis duty cycles (composite profiles)using simulated loading.Like the Train A/B composite profiles, the Train N composite profiles envelope the worst case conditions for these batteries and are maintained as formal calculations in the NEEP section of NE.It is desired to remove the"Computer Static Inverter" load from Table 4.8-2 (as shown in Attachments 2 and 3)since this load was physically removed from the AB Batteries as a function of design change RFC-12-2996,"Upgrade Plant Process Computer System".The power supply for this system is now the Technical Support Center Uninterruptible Power Supply system.Justification for Pro osed Technical S ecification Chan es The composite load profiles for the Train A/B batteries are a result of the combination of the three hour LOCA/LOOP and four hour SBO battery load profiles.The three hour LOCA/LOOP load profiles are a function of the UFSAR for the Cook Nuclear Plant whereas the four hour SBO load profiles were performed for the NUMARC 87-00 Station Blackout Rule.These load profiles were compared to determine the most demanding loading of the station batteries.
Since the LOCA/LOOP set of load profiles generally detailed a higher first-minute load and the SBO set yielded a longer loading period, the composite load profiles were developed to envelope the worst case profiles for each battery.These composite load profiles are intended for use as the models for performance of the 18-month surveillance testing of the batteries.
Additionally, since Cook Nuclear Plant has been designated as a four hour plane for an SBO event, retaining the eight hour battery duty cycles is no longer justifiable.
The composite load profiles for the N Train batteries, which remain unchanged at four hours in duration, are more conservative and more accurately reflect the postulated loads on these batteries than what is listed in the Technical Specifications.
The composite load profiles are intended for use as the models for performance of the 18-month surveillance testing of the batteries.
The valve operating sequence list of Table 4.8-3 is being removed because it is no longer used to place actual loads on.the N Train batteries during surveillance testing.Instead, Attachment 1 to AEP:NRC:0896R Page 5 the N Train batteries will continue to be tested (using the composites profiles as the basis)using simulated loads.The justification for removing the Computer Static Inverter Load from the AB Battery Loads list is self-explanatory.
5.0 10 CFR 50.92 CRITERIA Per 10 CFR 50.92, a proposed amendment does not involve a s'ignificant hazards consideration if the change does not: (1)involve a significant increase in the probability or consequences of an accident previously evaluated.
(2)create the possibility of a new or different kind of accident from any previously analyzed.(3)involve a significant reduction in a margin of safety.Criterion 1 The change is proposed to comply with the LOCA/LOOP and SBO requirement for Cook Nuclear Plant for battery testing.The composite test as addressed above meets these requirements for four hour test profiles.This change is consistent with the UFSAR three hour LOCA/LOOP and NUMARC 87-00 Station Blackout Rule four hour.Based on these considerations, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Criterion 2 The change only addresses the battery profile test which meets both LOCA/LOOP and SBO for Cook Nuclear Plant.No specific physical or operational changes to the plant will occur due to this change.Thus, the change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
Criterion 3 The proposed change revises the battery profile test table from an eight hour to a four hour composite test which complies with both LOCA/LOOP and SBO as defined for Cook Nuclear Plant.Therefore, the proposed change does not involve a significant reduction in a margin of safety.