|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:'\I,REGULATOR'r LNFORMATION 5ISTRIBUTIONSPFl'EM,(RIDS)ACCESSION NBR'408240188DOC~DATE84/08/20NOTAR'IZED | | {{#Wiki_filter:'\I, REGULATOR'r LNFORMATION 5ISTRI BUT ION SPFl'EM, (RIDS)ACCESSION NBR'408240 1 88 DOC~DATE 84/08/20 NOTAR'IZED |
| ~'OFACIL;50-315 DonaldC~CookNuclearPowerPlantrUnit1~Indiana850-316DonaldC,CookNuclearPowerPlant~Unit2<IndianaAUTH,NAME.AUTHORAFFILIATION ALEXICHgM>>P. | | ~'O FACIL;50-315 Donald C~Cook Nuclear Power Plantr Unit 1~Indiana 8 50-316 Donald C, Cook Nuclear Power Plant~Unit 2<Indiana AUTH, NAME.AUTHOR AFFILIATION ALEXICHgM>>P. |
| Indiana8MichiganElectricCo.~RECIP>>NAME RECIPIENT AFFILIATION DENTONiH~R>>OfficeofNuclearReactorRegulationi Director'
| | Indiana 8 Michigan Electric Co.~RECIP>>NAME RECIPIENT AFFILIATION DENTONiH~R>>Office of Nuclear Reactor Regulationi Director' |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| | Forwards status rept on inadequate core cooling instrumentation sysiper 831219 request.Rept addresses reactor vessel instrumentation sysgcor e exit tpermocouplesi subcool ing mal gin monitor 8 NUREG-0737gItem II~F>>2~DISTRIBUTION CODE!A002D COPIES RECEIVED:LTR ENC SIZE>>, TITLE: OR Submittal:Inadequate Core Cooling (Item II,F.2)GL 82 28.NOTES!OL>>10/25/74 OL: 12/23/72 DOCKET 05000315 05000316 05000315 05000316 RECIPIENT ID CODE/NAME NRR ORB1 BC FRIGG INGTONi D INTERNAL: ADM LFMB NRR/DHFS/HFEB15 NRR/DL/ORAB 08 NRR/DSI DIR 09 NRR.4 8 14 04 COPIES LTTR ENCL 1 1 1 1 1 0 1 1 1 1 1 1 1 1 REC IP IENT ID CODE/NAME NRR ORB1 LA NRR SHEA i J 01 NRR/DHFS/PSRB16 NRR/DL/ORB5 NRR/DSI/CPB 10 NRR/DS I/RSB 13 RGN3 07 COPIES'TTR ENCL 1 1 1 1 1 1 1 1 3 3 1 1 1 1'EXTERNAL: |
| | ACRS NRC PDR NTIS 17 02 05 10 10 1 1 1 1 LPDR NSIC 03 06 2 2 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 31 1 P tl~4 II!'I'I P!P P tA l1 P.P'S n tl I INDIANA 8 MICHIGAN ELECTRIC CONPANY P.O.BOX 1663I COLUMBUS, OHIO 432'16 August 20, 1984 AEP:NRC:0761C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-711 INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM STATUS REPORT Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 |
|
| |
|
| Forwardsstatusreptoninadequate corecoolinginstrumentation sysiper831219request.Reptaddresses reactorvesselinstrumentation sysgcoreexittpermocouplesi subcoolingmalginmonitor8NUREG-0737gItem II~F>>2~DISTRIBUTION CODE!A002DCOPIESRECEIVED:LTR ENCSIZE>>,TITLE:ORSubmittal:Inadequate CoreCooling(ItemII,F.2)GL8228.NOTES!OL>>10/25/74OL:12/23/72DOCKET05000315050003160500031505000316RECIPIENT IDCODE/NAME NRRORB1BCFRIGGINGTONiDINTERNAL:
| | ==Dear Mr.Denton:== |
| ADMLFMBNRR/DHFS/HFEB15 NRR/DL/ORAB 08NRR/DSIDIR09NRR.481404COPIESLTTRENCL11111011111111RECIPIENTIDCODE/NAME NRRORB1LANRRSHEAiJ01NRR/DHFS/PSRB16 NRR/DL/ORB5 NRR/DSI/CPB 10NRR/DSI/RSB13RGN307COPIES'TTR ENCL11111111331111'EXTERNAL:
| | This letter responds to Hr.S.A.Varga's letter'ated December 19,'983, which transmitted to Mr.John E.Dolan of the Indiana&Hichigan Electric Company (IMECo)the NRC's preliminary Safety Evaluation of the Inadequate Core Cooling Instr umentation (ICCI)system for the Donald C.Cook Nuclear Plant.More specifically, the Attachment to this letter provides a status report on the Donald C.Cook Nuclear Plant ICCI system, which consists of a Reactor Vessel Level Instrumentation System (RVLIS), Core Exit Thermocouples (CETs), and a Subcooling Margin Monitor (SMM).This status report fulfills the commitments we made in our letter AEP:NRC:0761B (dated February 3, 1984)regarding Enclosure 1 to Hr.Denton's December 19, 1983 letter.Information regarding Enclosure 2 of the December 19, 1983 letter will be transmitted following completion of the Upgrade Emergency Operating Procedures Generation Package scheduled for submittal in September, 1980.This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned. |
| ACRSNRCPDRNTIS17020510101111LPDRNSIC03062211TOTALNUMBEROFCOPIESREQUIRED:
| | Very truly yours, H.P.A exich Vice President MPA/dam cc: John E.Dolan W;G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff E.R.Swanson-NRC Resident Inspector, Bridgman 8408240188 840820 PDR ADOCK 05000315 P..PDR)O6>>I/ |
| LTTR32ENCL31 1Ptl~4II!'I'IP!PPtAl1P.P'SntlI INDIANA8MICHIGANELECTRICCONPANYP.O.BOX1663ICOLUMBUS, OHIO432'16August20,1984AEP:NRC:0761C DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-711INADEQUATE CORECOOLINGINSTRUMENTATION SYSTEMSTATUSREPORTMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555
| | ~%l~g~,,~a 4'~Je II J INA TT C NU 0 E I TUN NS RT r u o This attachment provides a status report on the Donald C.Cook Nuclear Plant Inadequate Core Cooling Instrumentation (ICCI)system, which consists of a Reactor Vessel Level Instrumentation System (RVLIS), Core Exit Thermocouples (CETs), and a Subcooling Margin Monitor (SMM).The contents of this status report address the 4 items of concern identified by the NRC in Enclosure 1 to the preliminary ICCI system Safety Evaluation, transmitted via letter dated December 19, 1983[S.A.Varga (NRC)to John E.Dolan (IMECo)].The 4 items of concern and the IMECo responses are provided below: An unresolved concern regarding post-accident environmental effects on in-containment wide range pressure transmitters and subsequent effects on RVLIS accuracy was identified. |
| | | Describe the status of the resolution of the wide range pressure transmitter application including any changes to the current installed RVLIS system and provide the schedule for completion of installation and calibration of the RVLIS system.In IMECo letter No.AEP:NRC:0761A, dated June 22, 1983;it was noted that the Westinghouse Electric Corporation (g)concern with regard to the transmitters was being discussed with g.Since that tine, the g recommendation that the wide range pressure transmitters interfacing with RVLIS be located outside containment to achieve the design RVLIS accuracy was reviewed and found to be acceptable. |
| ==DearMr.Denton:== | | Subject to final engineering and design review, it is proposed that the currently installed RVLIS be modified by relocating the existing wide range pressure transmitters from inside containment to outside containment, where they will be connected to RVLIS through level transmitter access assemblies. |
| ThisletterrespondstoHr.S.A.Varga'sletter'ated December19,'983,whichtransmitted toMr.JohnE.DolanoftheIndiana&HichiganElectricCompany(IMECo)theNRC'spreliminary SafetyEvaluation oftheInadequate CoreCoolingInstrumentation (ICCI)systemfortheDonaldC.CookNuclearPlant.Morespecifically, theAttachment tothisletterprovidesastatusreportontheDonaldC.CookNuclearPlantICCIsystem,whichconsistsofaReactorVesselLevelInstrumentation System(RVLIS),CoreExitThermocouples (CETs),andaSubcooling MarginMonitor(SMM).Thisstatusreportfulfillsthecommitments wemadeinourletterAEP:NRC:0761B (datedFebruary3,1984)regarding Enclosure 1toHr.Denton'sDecember19,1983letter.Information regarding Enclosure 2oftheDecember19,1983letterwillbetransmitted following completion oftheUpgradeEmergency Operating Procedures Generation Packagescheduled forsubmittal inSeptember, 1980.Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.
| | This installation, together with the required calibration, is scheduled to be completed by the end of the next refueling outages for both units.These outages are currently expected to begin in March 1985 for Unit No.1 and in November 1985 for Unit No.2.The RVLIS installation is complete in both Units with the exception of the aforementioned relocation of the wide range pressure transmitters scheduled to be completed by the end of 1985.The systems are functional. |
| Verytrulyyours,H.P.AexichVicePresident MPA/damcc:JohnE.DolanW;G.Smith,Jr.-BridgmanR.C.CallenG.CharnoffE.R.Swanson-NRCResidentInspector, Bridgman8408240188 840820PDRADOCK05000315P..PDR)O6>>I/
| | Remaining calibration tasks reported in the past have been completed. |
| ~%l~g~,,~a4'~JeIIJ INATTCNU0EITUNNSRTruoThisattachment providesastatusreportontheDonaldC.CookNuclearPlantInadequate CoreCoolingInstrumentation (ICCI)system,whichconsistsofaReactorVesselLevelInstrumentation System(RVLIS),CoreExitThermocouples (CETs),andaSubcooling MarginMonitor(SMM).Thecontentsofthisstatusreportaddressthe4itemsofconcernidentified bytheNRCinEnclosure 1tothepreliminary ICCIsystemSafetyEvaluation, transmitted vialetterdatedDecember19,1983[S.A.Varga(NRC)toJohnE.Dolan(IMECo)]. | | Should the systems be required in an emergency, the level indicators and recorders are available. |
| The4itemsofconcernandtheIMECoresponses areprovidedbelow:Anunresolved concernregarding post-accident environmental effectsonin-containment widerangepressuretransmitters andsubsequent effectsonRVLISaccuracywasidentified.
| | However, operators are not now permitted to use these systems. |
| Describethestatusoftheresolution ofthewiderangepressuretransmitter application including anychangestothecurrentinstalled RVLISsystemandprovidethescheduleforcompletion ofinstallation andcalibration oftheRVLISsystem.InIMEColetterNo.AEP:NRC:0761A, datedJune22,1983;itwasnotedthattheWestinghouse ElectricCorporation (g)concernwithregardtothetransmitters wasbeingdiscussed withg.Sincethattine,thegrecommendation thatthewiderangepressuretransmitters interfacing withRVLISbelocatedoutsidecontainment toachievethedesignRVLISaccuracywasreviewedandfoundtobeacceptable.
| | 4 tm2 Provide an evaluation of the final CET system with respect to conformance with Item II.F.2 Attachment 1 and Appendix B of NUREG-0737 requirements since the data provided is insufficiently spread over numerous referenced documents and a definitive determination of conformance is not possible.e o e t e The CET system in Unit No.1 is undergoing upgrade work which is expected to be complete during the 1985 refueling outage with the following exception: |
| Subjecttofinalengineering anddesignreview,itisproposedthatthecurrently installed RVLISbemodifiedbyrelocating theexistingwiderangepressuretransmitters frominsidecontainment tooutsidecontainment, wheretheywillbeconnected toRVLISthroughleveltransmitter accessassemblies.
| | The relocation of two (2)thermocouples to monitor the upper head region will not be done during the 1985 refueling outage because of technical problems that still remain to be resolved.This work is anticipated to be completed during the next refueling outage after the 1985 refueling outage.Presently, thirty-two (32)new environmentally and seismically qualified connectors and thirty-two (32)temporary transition cables have been installed. |
| Thisinstallation, togetherwiththerequiredcalibration, isscheduled tobecompleted bytheendofthenextrefueling outagesforbothunits.Theseoutagesarecurrently expectedtobegininMarch1985forUnitNo.1andinNovember1985forUnitNo.2.TheRVLISinstallation iscompleteinbothUnitswiththeexception oftheaforementioned relocation ofthewiderangepressuretransmitters scheduled tobecompleted bytheendof1985.Thesystemsarefunctional.
| | ~Additionally, a recovery method for the inoperable CETs is being tested and appears to be successful at this time.We believe that the design of the upgraded CET system meets, with the exception of cable separation criteria and core map display capabilities (explained later), all the requirements of NUREG-0737 Item II.F.2, Attachment 1.The following describes the upgraded CET system to be installed in Unit No.1~Upon successful recovery'of the inoperable thermocouples, sixty-thr ee (63)of the, sixty-five (65)thermocouples will be divided into two (2)electrically independent channels.Each channel will be energized from a Class IE power source, and physically separated, except at the Reactor Vessel Head area, using the appropriate guidance of Regulatory Guide 1.75, up to and including the isolation devices.These thermocouples will be divided as evenly as possible to provide adequate coverage of each core quadrant.Two (2)thermocouples, one (1)from each channel, are planned to be relocated to monitor temperatures in the upper head region to assist in monitoring local vessel temperature conditions during natural circulation modes of operation. |
| Remaining calibration tasksreportedinthepasthavebeencompleted. | | It should be noted that these two thermocouples are not required to meet the requirements of NUREG-0737. |
| Shouldthesystemsberequiredinanemergency, thelevelindicators andrecorders areavailable.
| | Environmentally and seismically qualified connectors and mineral insulated cabling will be installed from 0he CET nozzles up to a location past the missile shield wall, where a transition to qualified organic cabling will take place via qualified splices.From this point the qualified organic thermocouple cabling will be run through penetrations and will terminate at new signal processing equipment. |
| However,operators arenotnowpermitted tousethesesystems. | | Signal processing equipment will consist of two (2)racks of hardware capable of converting the low level thermocouple signals into high level{4-20 or]0-50 ma)signals.The two (2)racks will be Class IE and qualified'to the appropriate environmental and seismic requirements of IEEE Std 323-1974.Isolation between IE and non-IE signals will be provided.Cold junction compensation will be done automatically by the equipment. |
| 4tm2Provideanevaluation ofthefinalCETsystemwithrespecttoconformance withItemII.F.2Attachment 1andAppendixBofNUREG-0737 requirements sincethedataprovidedisinsufficiently spreadovernumerousreferenced documents andadefinitive determination ofconformance isnotpossible.
| | The two (2)r acks w1ll be physically separated using the guidance of Regulatory Guide 1.75 including the IE signals and non-IE signals.Thirty-three (33)signals will be processed on one (1)rack and thirty-two (32)on the other.(This may vary slightly when final determinations of CET configuration is made.)These racks will each be powered by a IE power source.The outputs of these racks will be transmitted to the normal plant process and Technical Support Center computers, two (2)back-up displays, and the SHM's incore thermocouple inputs (two (2)per quadrant for a total of eight (8)).Isolation between IE and non-IE equipment is provided in the electronics of the various pieces of equipment. |
| eoeteTheCETsysteminUnitNo.1isundergoing upgradeworkwhichisexpectedtobecompleteduringthe1985refueling outagewiththefollowing exception:
| | The primary display will be the plant process computer which has direct readout an(hard copy capabilities for all thermocouples. |
| Therelocation oftwo(2)thermocouples tomonitortheupperheadregionwillnotbedoneduringthe1985refueling outagebecauseoftechnical problemsthatstillremaintoberesolved.
| | The range will be 200 F to 2300 F.Trending capabilities also exist which can'show the time history of CET temperatures on demand.Alarm capabilities |
| Thisworkisanticipated tobecompleted duringthenextrefueling outageafterthe1985refueling outage.Presently, thirty-two (32)newenvironmentally andseismically qualified connectors andthirty-two (32)temporary transition cableshavebeeninstalled.
| | 'presently exist and will be made to be consistent with Emergency Operating Procedures. |
| ~Additionally, arecoverymethodfortheinoperable CETsisbeingtestedandappearstobesuccessful atthistime.WebelievethatthedesignoftheupgradedCETsystemmeets,withtheexception ofcableseparation criteriaandcoremapdisplaycapabilities (explained later),alltherequirements ofNUREG-0737 ItemII.F.2,Attachment 1.Thefollowing describes theupgradedCETsystemtobeinstalled inUnitNo.1~Uponsuccessful recovery'oftheinoperable thermocouples, sixty-thr ee(63)ofthe,sixty-five (65)thermocouples willbedividedintotwo(2)electrically independent channels. | | The operator d1splay devices are presently under review, as is the entire control room for human factors.Results of this review, when complete,. |
| Eachchannelwillbeenergized fromaClassIEpowersource,andphysically separated, exceptattheReactorVesselHeadarea,usingtheappropriate guidanceofRegulatory Guide1.75,uptoandincluding theisolation devices.Thesethermocouples willbedividedasevenlyaspossibletoprovideadequatecoverageofeachcorequadrant.
| | will be taken into account.A spatially oriented core map, available on demand, showing the temperature at each CET location will be available from the Technical Support Center CRT located in the control room.The Technical Support Center computer 1s not designated as the primary operator display.Therefore, this method of providing a core map is in variance with NUREG-0737. |
| Two(2)thermocouples, one(1)fromeachchannel,areplannedtoberelocated tomonitortemperatures intheupperheadregiontoassistinmonitoring localvesseltemperature conditions duringnaturalcirculation modesofoperation. | | However, it is our opinion that the Technical Support Center computer man-machine interface, together with operator tra1ning in use of the upgraded Emergency Operating Procedures, provides adequate compensatory methods for th1s,deviation. |
| Itshouldbenotedthatthesetwothermocouples arenotrequiredtomeettherequirements ofNUREG-0737.
| | It is therefore concluded that this deviation from NUREG-0737 is not significant and should be an acceptable method of providing a core map.A Class IE back-up display will be provided for each channel with the capability for the selective reading of a minimum of sixteen{16)operable thermocouples (four (4)per quadrant). |
| Environmentally andseismically qualified connectors andmineralinsulated cablingwillbeinstalled from0heCETnozzlesuptoalocationpastthemissileshieldwall,whereatransition toqualified organiccablingwilltakeplaceviaqualified splices.Fromthispointthequalified organicthermocouple cablingwillberunthroughpenetrations andwillterminate atnewsignalprocessing equipment. | | The present design specifies manual switching between each thermocouple. |
| Signalprocessing equipment willconsistoftwo(2)racksofhardwarecapableofconverting thelowlevelthermocouple signalsintohighlevel{4-20or]0-50ma)signals.Thetwo(2)rackswillbeClassIEandqualified'to theappropriate environmental andseismicrequirements ofIEEEStd323-1974.
| | It is expected that the switching can be completed between all CETs within a time interval of six (6$minutes.The displayed temperature range will be 200 F to 2300 F.Approximately fifty-seven (57)of the sixty-five (65)CETs are oper able in Unit No.2.Provided the Unit No.1 upgrade is successful, the anticipated schedule for Unit No.2 is as follows: Completion of Unit No.1 upgrading in 1985, except for the thermocouples in the upper head area.One (1)year operational study.Complete detail design November 1987.Complete installation during first refueling outage which occurs after December 1987.A definite schedule and a detailed description for review of compliance with NUREG-0737 cannot be available until the Unit No.2 detailed design is complete.Should the Unit No.1 upgrade be successful it is likely that the Unit No.2 upgrade will be designed in a similar, if not identical, manner as Unit No.1, providing that the hardware is still available for purchase.Provide justification for the schedule for completion of the ICCI system and for the adequacy of the CET system during the interim period until upgrading can be completed. |
| Isolation betweenIEandnon-IEsignalswillbeprovided. | | es onse to te The ICCI system completion schedule is contingent upon the successful upgrade of the CET system.The RVLIS is installed and calibrated and after some modifications can be made oper able prior to the completion of the CET system in either Unit.The SHM is installed and operational and operators have been trained in its use.Since the SMM's primary inputs are wide range Reactor Coolant System temperatures, the remaining work on upgrading the CETs does not impact the SMM normal operation. |
| Coldjunctioncompensation willbedoneautomatically bytheequipment.
| | The scheduling for Unit No.2 is based on the ongoing Unit No.1 CET upgrade program.The design and procurement of materials for the Unit No.2 CETs cannot proceed until the results of the Unit No.1 upgrade program are known.The adequacy of the present Unit No.2 CET system can be shown by the fact that after seven (7)years, fifty-seven (57)of the thermocouples are still operational. |
| Thetwo(2)racksw1llbephysically separated usingtheguidanceofRegulatory Guide1.75including theIEsignalsandnon-IEsignals.Thirty-three (33)signalswillbeprocessed onone(1)rackandthirty-two (32)ontheother.(Thismayvaryslightlywhenfinaldeterminations ofCETconfiguration ismade.)TheserackswilleachbepoweredbyaIEpowersource.Theoutputsoftheserackswillbetransmitted tothenormalplantprocessandTechnical SupportCentercomputers, two(2)back-updisplays, andtheSHM'sincorethermocouple inputs(two(2)perquadrantforatotalofeight(8)).Isolation betweenIEandnon-IEequipment isprovidedintheelectronics ofthevariouspiecesofequipment.
| | These could be used to provide the operators with adequate secondary information under accident conditions. |
| Theprimarydisplaywillbetheplantprocesscomputerwhichhasdirectreadoutan(hardcopycapabilities forallthermocouples.
| | ~~I~~During the interim period until CET upgrading can be completed, the SMM can be used to detect Inadequate Core Cooling conditions. |
| Therangewillbe200Fto2300F.Trendingcapabilities alsoexistwhichcan'showthetimehistoryofCETtemperatures ondemand.Alarmcapabilities
| | Wide range pressure and temperature (i.e., Resistance Temperature Detectors) |
| 'presently existandwillbemadetobeconsistent withEmergency Operating Procedures. | | Class IE signals are used as inputs, and the operators have been trained in the SMM's use and emergency procedures are in place.We believe that the RVLIS can now be used in an emergency, although it has not been declared operational. |
| Theoperatord1splaydevicesarepresently underreview,asistheentirecontrolroomforhumanfactors.Resultsofthisreview,whencomplete,.
| | Additionally, the survivability of incore thermocouples was demonstrated during the THI-2 accident.From the results of that accident, it is believed that a sufficient portion of the present CET system should survive a postulated incident and could provide the operators with adequate information to establish qualitative trending indications. |
| willbetakenintoaccount.Aspatially orientedcoremap,available ondemand,showingthetemperature ateachCETlocationwillbeavailable fromtheTechnical SupportCenterCRTlocatedinthecontrolroom.TheTechnical SupportCentercomputer1snotdesignated astheprimaryoperatordisplay.Therefore, thismethodofproviding acoremapisinvariancewithNUREG-0737.
| | The Subcooling Margin Monitor receives input signals from a mix of Class 1E and non-Class 1E instrumentation sources.Furthermore it is not clear that the subcooling margin computer and display are seismically and environmentally qualified. |
| However,itisouropinionthattheTechnical SupportCentercomputerman-machine interface, togetherwithoperatortra1ninginuseoftheupgradedEmergency Operating Procedures, providesadequatecompensatory methodsforth1s,deviation. | | Clarify that in all instances Class 1E equipment is protected by qualified isolation devices to preclude the possibility of adverse interaction between Class 1E and non-Class 1E devices or signals.t te Inputs to the saturation meter consist of Class IE signals (i.e., Reactor Coolant System wide range pressure detectors) and non-Class IE signals (i.e., CETs).Each of these input signals is isolated by a qualified Signal Converter Transformer. |
| Itistherefore concluded thatthisdeviation fromNUREG-0737 isnotsignificant andshouldbeanacceptable methodofproviding acoremap.AClassIEback-updisplaywillbeprovidedforeachchannelwiththecapability fortheselective readingofaminimumofsixteen{16)operablethermocouples (four(4)perquadrant).
| | All cabling and connections for these isolation devices to the saturation meter are confined to the control room, eliminating the need for environmental qualification. |
| Thepresentdesignspecifies manualswitching betweeneachthermocouple.
| | The saturation margin meter and display were installed to meet the requirements of NUREG-0578. |
| Itisexpectedthattheswitching canbecompleted betweenallCETswithinatimeintervalofsix(6$minutes.Thedisplayed temperature rangewillbe200Fto2300F.Approximately fifty-seven (57)ofthesixty-five (65)CETsareoperableinUnitNo.2.ProvidedtheUnitNo.1upgradeissuccessful, theanticipated scheduleforUnitNo.2isasfollows:Completion ofUnitNo.1upgrading in1985,exceptforthethermocouples intheupperheadarea.One(1)yearoperational study.CompletedetaildesignNovember1987.Completeinstallation duringfirstrefueling outagewhichoccursafterDecember1987.Adefinitescheduleandadetaileddescription forreviewofcompliance withNUREG-0737 cannotbeavailable untiltheUnitNo.2detaileddesigniscomplete.
| | These devices were designed, purchased, and installed during the period of October 1979 to October 1980 in a good faith effort to meet the then existing requirements. |
| ShouldtheUnitNo.1upgradebesuccessful itislikelythattheUnitNo.2upgradewillbedesignedinasimilar,ifnotidentical, mannerasUnitNo.1,providing thatthehardwareisstillavailable forpurchase.
| | Therefore, they were not required to be and as such have not been seismically and environmentally qualified. |
| Providejustification forthescheduleforcompletion oftheICCIsystemandfortheadequacyoftheCETsystemduringtheinterimperioduntilupgrading canbecompleted.
| | II 4 4}} |
| esonsetoteTheICCIsystemcompletion scheduleiscontingent uponthesuccessful upgradeoftheCETsystem.TheRVLISisinstalled andcalibrated andaftersomemodifications canbemadeoperablepriortothecompletion oftheCETsystemineitherUnit.TheSHMisinstalled andoperational andoperators havebeentrainedinitsuse.SincetheSMM'sprimaryinputsarewiderangeReactorCoolantSystemtemperatures, theremaining workonupgrading theCETsdoesnotimpacttheSMMnormaloperation.
| |
| Thescheduling forUnitNo.2isbasedontheongoingUnitNo.1CETupgradeprogram.Thedesignandprocurement ofmaterials fortheUnitNo.2CETscannotproceeduntiltheresultsoftheUnitNo.1upgradeprogramareknown.TheadequacyofthepresentUnitNo.2CETsystemcanbeshownbythefactthatafterseven(7)years,fifty-seven (57)ofthethermocouples arestilloperational.
| |
| Thesecouldbeusedtoprovidetheoperators withadequatesecondary information underaccidentconditions.
| |
| ~~I~~DuringtheinterimperioduntilCETupgrading canbecompleted, theSMMcanbeusedtodetectInadequate CoreCoolingconditions. | |
| Widerangepressureandtemperature (i.e.,Resistance Temperature Detectors)
| |
| ClassIEsignalsareusedasinputs,andtheoperators havebeentrainedintheSMM'suseandemergency procedures areinplace.WebelievethattheRVLIScannowbeusedinanemergency, althoughithasnotbeendeclaredoperational.
| |
| Additionally, thesurvivability ofincorethermocouples wasdemonstrated duringtheTHI-2accident. | |
| Fromtheresultsofthataccident, itisbelievedthatasufficient portionofthepresentCETsystemshouldsurviveapostulated incidentandcouldprovidetheoperators withadequateinformation toestablish qualitative trendingindications.
| |
| TheSubcooling MarginMonitorreceivesinputsignalsfromamixofClass1Eandnon-Class 1Einstrumentation sources.Furthermore itisnotclearthatthesubcooling margincomputeranddisplayareseismically andenvironmentally qualified.
| |
| Clarifythatinallinstances Class1Eequipment isprotected byqualified isolation devicestoprecludethepossibility ofadverseinteraction betweenClass1Eandnon-Class 1Edevicesorsignals.tteInputstothesaturation meterconsistofClassIEsignals(i.e.,ReactorCoolantSystemwiderangepressuredetectors) andnon-Class IEsignals(i.e.,CETs).Eachoftheseinputsignalsisisolatedbyaqualified SignalConverter Transformer.
| |
| Allcablingandconnections fortheseisolation devicestothesaturation meterareconfinedtothecontrolroom,eliminating theneedforenvironmental qualification.
| |
| Thesaturation marginmeteranddisplaywereinstalled tomeettherequirements ofNUREG-0578.
| |
| Thesedevicesweredesigned, purchased, andinstalled duringtheperiodofOctober1979toOctober1980inagoodfaithefforttomeetthethenexistingrequirements.
| |
| Therefore, theywerenotrequiredtobeandassuchhavenotbeenseismically andenvironmentally qualified. | |
| II44}}
| |
Similar Documents at Cook |
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999
Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21
IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
ML20217D9241999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
ML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML20196K5961999-06-30030 June 1999
Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML20207A9201999-05-21021 May 1999
Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML20205P0591999-04-14014 April 1999
Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
ML17325B4641999-03-17017 March 1999
Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17328A4481990-09-21021 September 1990
Requests Withdrawal of Mode 6 Proposed Tech Spec Change Since Issue Currently Being Addressed by New STSs
ML17328A4331990-08-27027 August 1990
Informs of Preliminary Assessment of 900713 Electrical Contact Accident at Facility.Investigation Concludes That No Safety Rules Violated
ML17328A4001990-08-24024 August 1990
Responds to 900725 Ltr Re Commitments Made in Response to Generic Ltr 88-14 on Instrument Air Supply Problems Affecting safety-related Equipment.Simulator Training to Be Provided as Stated
ML17334B3781990-08-24024 August 1990
Forwards Info to Certify Plant Simulator Facility.Results of Evaluation of Dual Unit Simulation Facilities Demonstrate That Plant Simulator Performance Compares Favorably W/Units
ML17328A4231990-08-21021 August 1990
Forwards Under Separate Cover,Semiannual Radioactive Effluent Release Rept for Jan-June 1990
ML17328A3901990-08-17017 August 1990
Responds to NRC 900720 Ltr Re Violations Noted in Onsite Audit of Spds.Corrective Actions:Apparent Disparity in Selection of Reactor Trip & Sys Capacity or Anticipatory Values Rectified
ML17328A3891990-08-15015 August 1990
Forwards Performance Data Sheets for Plant fitness-for-duty Program for Period Jan-June 1990,per 10CFR26.Encl Includes Statistics on Various Categories of Testing,Substances Tested for & cut-off Levels Used
ML17328A3571990-08-0202 August 1990
Responds to Open Items in Safety Evaluation of Util Response to Unresolved Issues on post-fire Safe Shutdown Methodology. Open Items 1 & 21 Will Be Closed by Implementing Plant Procedures Providing Equivalent Degree of Protection
ML17328A3431990-07-23023 July 1990
Requests Withdrawal of 890830 Proposed Tech Spec Changes Re Sections 3.0 & 4.0.Util Will Resubmit Generic Ltr 87-09 Recommended Improvement Items on Case by Case Basis
ML17328A3421990-07-23023 July 1990
Provides Results of Offsite Dose Calculation for Reactor Coolant Pump Locked Rotor Event for Facility Cycle 8.Util Identified Previously Issued SERs Addressing Short Term Containment Analysis & LOCA Containment Integrity
ML20055G7551990-07-18018 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-315/90-10 & 50-316/90-10.Corrective Actions:Required Review Performed & Updated Procedure 12 Mhp 5021.019.001 Revised & Issued
ML17328A3191990-07-12012 July 1990
Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Electrical Testing Techniques Improved & Surveillance Procedures for Feedwater Pumps Will Be Rewritten
ML17328A3181990-07-0909 July 1990
Responds to Generic Ltr 90-03,Suppl 1, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' Licensee Will Contact safety-related Vendors on Annual Basis
ML17328A3111990-07-0303 July 1990
Provides Certification of Funding Plan for Decommissioning of Plant,Per 10CFR50.33 & 50.75
ML17328A2961990-06-25025 June 1990
Forwards Response to Generic Ltr 90-04 Re Closeout of Generic Safety Issues.Util Supports Concern & Desire to Close long-standing Generic Safety Issues
ML17328A2921990-06-22022 June 1990
Forwards WCAP-12483, Analysis of Capsule U from American Electric Power Co DC Cook Unit 1 Reactor Vessel Radiation Surveillance Program.
ML20044A3521990-06-22022 June 1990
Submits Info Re Sensitivity Study Performed on Number of Fuel Axial Intervals,Per Topical Rept, American Electric Power Reactor Core Thermal-Hydraulic Analysis Using Cobra III-C/MIT-2 Computer Code.
ML17328A2821990-06-15015 June 1990
Submits Ltr Re Proposed Control Room Habitability Tech Spec Changes & Supporting Analyses,Per 900521 Discussion.Revised Calculations of Control Room Thyroid Doses Will Be Submitted within 60 Days of Receipt of Proposed Generic Ltr
ML17328A2741990-06-12012 June 1990
Submits Followup,Per 900205 & 0308 Ltrs & Provides Update Re Inoperable Fire Barrier.Fire Seal Repaired & Restored to Operability on 900419
ML17328A2551990-06-0505 June 1990
Forwards Addl Info Re Util 900126 Revised Response to NRC Bulletin 88-002,per NRC 900509 Request
ML17328A7361990-06-0101 June 1990
Forwards Addl Info Re 890825 & 1212 Applications for Amends to Licenses DPR-58 & DPR-74,per Request.Amends Make Changes to Administrative Controls
ML17328A7331990-05-29029 May 1990
Forwards Nonproprietary WCAP-12577 & Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument... Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Per 900419 Commitment
ML17328A7321990-05-24024 May 1990
Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 Series B or D or Model 1154 Transmitters Installed at Facility.Transmitters Purchased as commercial-grade Units
ML17328A6991990-05-0909 May 1990
Provides Suppl to 900103 Response,Certifying That Fitness for Duty Program Implemented at Plant.Change Also Clarifies When More Stringent cut-off Levels Adopted at Plant Program Apply
ML17328A7001990-05-0909 May 1990
Responds to NRC 900406 Ltr Re Inadequacies of Spds,Per Audit on 900221-22.Corrective Actions:Software Mod Will Prevent User from Accessing Displays Other than Iconic Displays from SPDS Dedicated Terminal
ML17328A7071990-05-0707 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept Mar 1990 for Donald C Cook Nuclear Plant Unit 1
ML17328A7031990-05-0707 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for DC Cook Nuclear Plant Unit 2
ML17328A6951990-04-30030 April 1990
Certifies That Training Programs for Initial Licensing & Requalification Training of Operators & Senior Operators at Plant Accredited by Inpo,Per Generic Ltr 87-07
ML17328A6861990-04-30030 April 1990
Forwards Annual Environ Operating Rept,Jan-Dec 1989, & DC Cook Nuclear Plant Units 1 & 2 Operational Radiological Environ Monitoring Program 1989 Rept Jan-Dec 1989.
ML17328A6801990-04-23023 April 1990
Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Study Planned to Evaluate Alternative Actions to Be Taken for Protecting RHR Pumps
ML17328A6771990-04-23023 April 1990
Forwards DC Cook Nuclear Plant 1990 Annual Emergency Preparedness Exercise. Exercise Scope & Objectives & Detailed Scenario Documentation Encl
ML17334B3641990-04-11011 April 1990
Responds to NRC 900301 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Reliability Centered Maint Program Initiated
ML17328A6601990-04-11011 April 1990
Forwards Updated QA Program Description for Cook Nuclear Plant, Incorporating Editorial,Organizational & Position Title Changes
ML17328A6551990-04-0909 April 1990
Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-316/90-08.Corrective Actions:Procedure for Steam Generator Stop Valve Operability Test Revised to Require That MSIV Be Declared Inoperable After Failing Stroke Test
ML17334B3601990-04-0606 April 1990
Forwards Revised Figures for Loss of Load Event Previously Submitted in Attachment 4,App B of Vantage 5 Reload Transition Safety Rept Supplied by Westinghouse in Jan 1990. Update Is Editorial in Nature
ML17334B3621990-04-0606 April 1990
Forwards 1989 Annual Rept & Projected Cash Flow
ML17328A6341990-03-30030 March 1990
Forwards Application for Renewal of Plant NPDES Permit,For Info,Per Section 3.2 of App B to Plant Tech Specs.W/O Encl
ML17328A6331990-03-30030 March 1990
Responds to NUMARC 900104 Request for Addl Info Re Station Blackout Submittals.Target Reliability for Emergency Diesel Generator of 0.0975 Established for 4 H ac-independent Coping Category Will Be Maintained
ML17328A6321990-03-30030 March 1990
Forwards Response to Generic Ltr 90-01, NRC Regulatory Impact Survey. Util Ack Recommendation by NUMARC
ML17328A6221990-03-27027 March 1990
Responds to 900226 Ltr Transmitting Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000. Corrective Actions:Flow Retention Circuitry Setpoints Set to Compensate for Missized Process Flow Orifice
ML17328A6191990-03-27027 March 1990
Forwards Payment in Amount of $75,000 for Civil Penalty Imposed Through Notice of Violation Issued in Insp Rept 50-316/89-02 on 891016-20,24-26 & 1204.Response to Violation & Corrective Actions Provided in Separate Submittal
ML17328A6161990-03-20020 March 1990
Responds to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs (USI A-47).Both Units Have Steam Overfill Protection Sys That Would Automatically Prevent Water Carryover Into Steam Lines If Control Sys Failed
ML17328A6121990-03-13013 March 1990
Forwards Monthly Performance Monitoring Rept,Jan 1990.
ML17325B3901990-03-0606 March 1990
Forwards Annual Rept to NRC Per 10CFR50.54(W)(2) Re Nuclear Property Insurance
ML17325B3921990-03-0606 March 1990
Modifies Application for Amend to License DPR-74 Re Cycle 8, Per 900228 Telcon
ML17325B3781990-02-28028 February 1990
Forwards Response to NRC Info Notice 89-056 Re Questionable Certification of Matl Supplied to Dod by Nuclear Suppliers. Matl Capable of Performing Design Function & Acceptable for Continued Use
ML17328A5971990-02-27027 February 1990
Withdraws 890203 Application for Amend to License DPR-74, Modifying Tech Spec Table 3.2-1 Re DNB Parameters to Express RCS Flow Rate on Volumetric Rather than Mass Basis
ML17334B3511990-02-22022 February 1990
Submits Annual Rept of Changes to or Errors in Acceptable LOCA Evaluation Models or Application of Models for Plants. Wflash Analyses Will Be Superceded by Notrump Analyses for Unit 2,Cycle 8 Reload
ML17328A5881990-02-21021 February 1990
Responds to NRC 890914 Request for Addl Info Re Safe Shutdown Methodology.App R Fire Barriers Being Maintained & Surveilled Under 3/4.7.10 for Units 1 & 2
ML17328A5861990-02-16016 February 1990
Provides Revised Comments in Response to NRR Comments During 891213 Telcon Re Allowable Stresses for Piping & Piping Supports
1990-09-21
[Table view] |
Text
'\I, REGULATOR'r LNFORMATION 5ISTRI BUT ION SPFl'EM, (RIDS)ACCESSION NBR'408240 1 88 DOC~DATE 84/08/20 NOTAR'IZED
~'O FACIL;50-315 Donald C~Cook Nuclear Power Plantr Unit 1~Indiana 8 50-316 Donald C, Cook Nuclear Power Plant~Unit 2<Indiana AUTH, NAME.AUTHOR AFFILIATION ALEXICHgM>>P.
Indiana 8 Michigan Electric Co.~RECIP>>NAME RECIPIENT AFFILIATION DENTONiH~R>>Office of Nuclear Reactor Regulationi Director'
SUBJECT:
Forwards status rept on inadequate core cooling instrumentation sysiper 831219 request.Rept addresses reactor vessel instrumentation sysgcor e exit tpermocouplesi subcool ing mal gin monitor 8 NUREG-0737gItem II~F>>2~DISTRIBUTION CODE!A002D COPIES RECEIVED:LTR ENC SIZE>>, TITLE: OR Submittal:Inadequate Core Cooling (Item II,F.2)GL 82 28.NOTES!OL>>10/25/74 OL: 12/23/72 DOCKET 05000315 05000316 05000315 05000316 RECIPIENT ID CODE/NAME NRR ORB1 BC FRIGG INGTONi D INTERNAL: ADM LFMB NRR/DHFS/HFEB15 NRR/DL/ORAB 08 NRR/DSI DIR 09 NRR.4 8 14 04 COPIES LTTR ENCL 1 1 1 1 1 0 1 1 1 1 1 1 1 1 REC IP IENT ID CODE/NAME NRR ORB1 LA NRR SHEA i J 01 NRR/DHFS/PSRB16 NRR/DL/ORB5 NRR/DSI/CPB 10 NRR/DS I/RSB 13 RGN3 07 COPIES'TTR ENCL 1 1 1 1 1 1 1 1 3 3 1 1 1 1'EXTERNAL:
ACRS NRC PDR NTIS 17 02 05 10 10 1 1 1 1 LPDR NSIC 03 06 2 2 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 31 1 P tl~4 II!'I'I P!P P tA l1 P.P'S n tl I INDIANA 8 MICHIGAN ELECTRIC CONPANY P.O.BOX 1663I COLUMBUS, OHIO 432'16 August 20, 1984 AEP:NRC:0761C Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-711 INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM STATUS REPORT Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
Dear Mr.Denton:
This letter responds to Hr.S.A.Varga's letter'ated December 19,'983, which transmitted to Mr.John E.Dolan of the Indiana&Hichigan Electric Company (IMECo)the NRC's preliminary Safety Evaluation of the Inadequate Core Cooling Instr umentation (ICCI)system for the Donald C.Cook Nuclear Plant.More specifically, the Attachment to this letter provides a status report on the Donald C.Cook Nuclear Plant ICCI system, which consists of a Reactor Vessel Level Instrumentation System (RVLIS), Core Exit Thermocouples (CETs), and a Subcooling Margin Monitor (SMM).This status report fulfills the commitments we made in our letter AEP:NRC:0761B (dated February 3, 1984)regarding Enclosure 1 to Hr.Denton's December 19, 1983 letter.Information regarding Enclosure 2 of the December 19, 1983 letter will be transmitted following completion of the Upgrade Emergency Operating Procedures Generation Package scheduled for submittal in September, 1980.This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, H.P.A exich Vice President MPA/dam cc: John E.Dolan W;G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff E.R.Swanson-NRC Resident Inspector, Bridgman 8408240188 840820 PDR ADOCK 05000315 P..PDR)O6>>I/
~%l~g~,,~a 4'~Je II J INA TT C NU 0 E I TUN NS RT r u o This attachment provides a status report on the Donald C.Cook Nuclear Plant Inadequate Core Cooling Instrumentation (ICCI)system, which consists of a Reactor Vessel Level Instrumentation System (RVLIS), Core Exit Thermocouples (CETs), and a Subcooling Margin Monitor (SMM).The contents of this status report address the 4 items of concern identified by the NRC in Enclosure 1 to the preliminary ICCI system Safety Evaluation, transmitted via letter dated December 19, 1983[S.A.Varga (NRC)to John E.Dolan (IMECo)].The 4 items of concern and the IMECo responses are provided below: An unresolved concern regarding post-accident environmental effects on in-containment wide range pressure transmitters and subsequent effects on RVLIS accuracy was identified.
Describe the status of the resolution of the wide range pressure transmitter application including any changes to the current installed RVLIS system and provide the schedule for completion of installation and calibration of the RVLIS system.In IMECo letter No.AEP:NRC:0761A, dated June 22, 1983;it was noted that the Westinghouse Electric Corporation (g)concern with regard to the transmitters was being discussed with g.Since that tine, the g recommendation that the wide range pressure transmitters interfacing with RVLIS be located outside containment to achieve the design RVLIS accuracy was reviewed and found to be acceptable.
Subject to final engineering and design review, it is proposed that the currently installed RVLIS be modified by relocating the existing wide range pressure transmitters from inside containment to outside containment, where they will be connected to RVLIS through level transmitter access assemblies.
This installation, together with the required calibration, is scheduled to be completed by the end of the next refueling outages for both units.These outages are currently expected to begin in March 1985 for Unit No.1 and in November 1985 for Unit No.2.The RVLIS installation is complete in both Units with the exception of the aforementioned relocation of the wide range pressure transmitters scheduled to be completed by the end of 1985.The systems are functional.
Remaining calibration tasks reported in the past have been completed.
Should the systems be required in an emergency, the level indicators and recorders are available.
However, operators are not now permitted to use these systems.
4 tm2 Provide an evaluation of the final CET system with respect to conformance with Item II.F.2 Attachment 1 and Appendix B of NUREG-0737 requirements since the data provided is insufficiently spread over numerous referenced documents and a definitive determination of conformance is not possible.e o e t e The CET system in Unit No.1 is undergoing upgrade work which is expected to be complete during the 1985 refueling outage with the following exception:
The relocation of two (2)thermocouples to monitor the upper head region will not be done during the 1985 refueling outage because of technical problems that still remain to be resolved.This work is anticipated to be completed during the next refueling outage after the 1985 refueling outage.Presently, thirty-two (32)new environmentally and seismically qualified connectors and thirty-two (32)temporary transition cables have been installed.
~Additionally, a recovery method for the inoperable CETs is being tested and appears to be successful at this time.We believe that the design of the upgraded CET system meets, with the exception of cable separation criteria and core map display capabilities (explained later), all the requirements of NUREG-0737 Item II.F.2, Attachment 1.The following describes the upgraded CET system to be installed in Unit No.1~Upon successful recovery'of the inoperable thermocouples, sixty-thr ee (63)of the, sixty-five (65)thermocouples will be divided into two (2)electrically independent channels.Each channel will be energized from a Class IE power source, and physically separated, except at the Reactor Vessel Head area, using the appropriate guidance of Regulatory Guide 1.75, up to and including the isolation devices.These thermocouples will be divided as evenly as possible to provide adequate coverage of each core quadrant.Two (2)thermocouples, one (1)from each channel, are planned to be relocated to monitor temperatures in the upper head region to assist in monitoring local vessel temperature conditions during natural circulation modes of operation.
It should be noted that these two thermocouples are not required to meet the requirements of NUREG-0737.
Environmentally and seismically qualified connectors and mineral insulated cabling will be installed from 0he CET nozzles up to a location past the missile shield wall, where a transition to qualified organic cabling will take place via qualified splices.From this point the qualified organic thermocouple cabling will be run through penetrations and will terminate at new signal processing equipment.
Signal processing equipment will consist of two (2)racks of hardware capable of converting the low level thermocouple signals into high level{4-20 or]0-50 ma)signals.The two (2)racks will be Class IE and qualified'to the appropriate environmental and seismic requirements of IEEE Std 323-1974.Isolation between IE and non-IE signals will be provided.Cold junction compensation will be done automatically by the equipment.
The two (2)r acks w1ll be physically separated using the guidance of Regulatory Guide 1.75 including the IE signals and non-IE signals.Thirty-three (33)signals will be processed on one (1)rack and thirty-two (32)on the other.(This may vary slightly when final determinations of CET configuration is made.)These racks will each be powered by a IE power source.The outputs of these racks will be transmitted to the normal plant process and Technical Support Center computers, two (2)back-up displays, and the SHM's incore thermocouple inputs (two (2)per quadrant for a total of eight (8)).Isolation between IE and non-IE equipment is provided in the electronics of the various pieces of equipment.
The primary display will be the plant process computer which has direct readout an(hard copy capabilities for all thermocouples.
The range will be 200 F to 2300 F.Trending capabilities also exist which can'show the time history of CET temperatures on demand.Alarm capabilities
'presently exist and will be made to be consistent with Emergency Operating Procedures.
The operator d1splay devices are presently under review, as is the entire control room for human factors.Results of this review, when complete,.
will be taken into account.A spatially oriented core map, available on demand, showing the temperature at each CET location will be available from the Technical Support Center CRT located in the control room.The Technical Support Center computer 1s not designated as the primary operator display.Therefore, this method of providing a core map is in variance with NUREG-0737.
However, it is our opinion that the Technical Support Center computer man-machine interface, together with operator tra1ning in use of the upgraded Emergency Operating Procedures, provides adequate compensatory methods for th1s,deviation.
It is therefore concluded that this deviation from NUREG-0737 is not significant and should be an acceptable method of providing a core map.A Class IE back-up display will be provided for each channel with the capability for the selective reading of a minimum of sixteen{16)operable thermocouples (four (4)per quadrant).
The present design specifies manual switching between each thermocouple.
It is expected that the switching can be completed between all CETs within a time interval of six (6$minutes.The displayed temperature range will be 200 F to 2300 F.Approximately fifty-seven (57)of the sixty-five (65)CETs are oper able in Unit No.2.Provided the Unit No.1 upgrade is successful, the anticipated schedule for Unit No.2 is as follows: Completion of Unit No.1 upgrading in 1985, except for the thermocouples in the upper head area.One (1)year operational study.Complete detail design November 1987.Complete installation during first refueling outage which occurs after December 1987.A definite schedule and a detailed description for review of compliance with NUREG-0737 cannot be available until the Unit No.2 detailed design is complete.Should the Unit No.1 upgrade be successful it is likely that the Unit No.2 upgrade will be designed in a similar, if not identical, manner as Unit No.1, providing that the hardware is still available for purchase.Provide justification for the schedule for completion of the ICCI system and for the adequacy of the CET system during the interim period until upgrading can be completed.
es onse to te The ICCI system completion schedule is contingent upon the successful upgrade of the CET system.The RVLIS is installed and calibrated and after some modifications can be made oper able prior to the completion of the CET system in either Unit.The SHM is installed and operational and operators have been trained in its use.Since the SMM's primary inputs are wide range Reactor Coolant System temperatures, the remaining work on upgrading the CETs does not impact the SMM normal operation.
The scheduling for Unit No.2 is based on the ongoing Unit No.1 CET upgrade program.The design and procurement of materials for the Unit No.2 CETs cannot proceed until the results of the Unit No.1 upgrade program are known.The adequacy of the present Unit No.2 CET system can be shown by the fact that after seven (7)years, fifty-seven (57)of the thermocouples are still operational.
These could be used to provide the operators with adequate secondary information under accident conditions.
~~I~~During the interim period until CET upgrading can be completed, the SMM can be used to detect Inadequate Core Cooling conditions.
Wide range pressure and temperature (i.e., Resistance Temperature Detectors)
Class IE signals are used as inputs, and the operators have been trained in the SMM's use and emergency procedures are in place.We believe that the RVLIS can now be used in an emergency, although it has not been declared operational.
Additionally, the survivability of incore thermocouples was demonstrated during the THI-2 accident.From the results of that accident, it is believed that a sufficient portion of the present CET system should survive a postulated incident and could provide the operators with adequate information to establish qualitative trending indications.
The Subcooling Margin Monitor receives input signals from a mix of Class 1E and non-Class 1E instrumentation sources.Furthermore it is not clear that the subcooling margin computer and display are seismically and environmentally qualified.
Clarify that in all instances Class 1E equipment is protected by qualified isolation devices to preclude the possibility of adverse interaction between Class 1E and non-Class 1E devices or signals.t te Inputs to the saturation meter consist of Class IE signals (i.e., Reactor Coolant System wide range pressure detectors) and non-Class IE signals (i.e., CETs).Each of these input signals is isolated by a qualified Signal Converter Transformer.
All cabling and connections for these isolation devices to the saturation meter are confined to the control room, eliminating the need for environmental qualification.
The saturation margin meter and display were installed to meet the requirements of NUREG-0578.
These devices were designed, purchased, and installed during the period of October 1979 to October 1980 in a good faith effort to meet the then existing requirements.
Therefore, they were not required to be and as such have not been seismically and environmentally qualified.
II 4 4
