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| {{#Wiki_filter:AECDXSUTIONFORPART50DOCKETMATER(TEMPORARY FORM)CONTROLNO:FILE:8FROAA1:NiagaraMohawkPowerCorpSyracuse, N;Y.13202P.D.RaymondDATEOFDOC1-22-74DATEREC'D1-23-74LTRMEMORPTOTHERTO:D.L.ZiemannORIG3signedqCCOTHERSENTAECPDRxSENTLOCALPDRXCLASSUNCLASSXXXXPROPINFOINPUTXXXXNOCSREC'D40DOCKETNO:50-220DESCRIPTION: | | {{#Wiki_filter:AEC DXS UTION FOR PART 50 DOCKET MATER (TEMPORARY FORM)CONTROL NO: FILE: 8 FROAA1: Niagara Mohawk Power Corp Syracuse, N;Y.13202 P.D.Raymond DATE OF DOC 1-22-74 DATE REC'D 1-23-74 LTR MEMO RPT OTHER TO: D.L.Ziemann ORIG 3 signedq CC OTHER SENT AEC PDR x SENT LOCAL PDR X CLASS UNCLASS XXXX PROP INFO INPUT XXXX NO C S REC'D 40 DOCKET NO: 50-220 DESCRIPTION: |
| Ltrnotarized 1-22-74,transthefollowing:
| | Ltr notarized 1-22-74, trans the following: |
| PLANTNAME:NineMilePointUnit$P1ENCLOSURES:
| | PLANT NAME: Nine Mile Point Unit$P1 ENCLOSURES: |
| ProosedChanetoTechnical Secifications:
| | Pro osed Chan e to Technical S ecifications: |
| Densification AnalysesandRelatedTechnical Specifications ChangesforType5andTypeDONOTREMOVEACKNOWLEDGED (3Orig637cysrec'd)FORACTION/INFORMATION 1-23-74GCBUTLER(L)W/CopiesCLARK(L)W/CopiesGOLLER(L) | | Densification Analyses and Related Technical Specifications Changes for Type 5 and Type DO NOT REMOVE ACKNOWLEDGED (3 Orig 6 37 cys rec'd)FOR ACTION/INFORMATION 1-23-74 GC BUTLER (L)W/Copies CLARK(L)W/Copies GOLLER(L)W/Copies KNIEL(L)W/Copies SCHWENCER(L) |
| W/CopiesKNIEL(L)W/CopiesSCHWENCER(L) | | W/Copies STOLZ(L)W/Copies VASSALLO(L) |
| W/CopiesSTOLZ(L)W/CopiesVASSALLO(L) | | 'W/Copies SCHEMEL(L) |
| 'W/CopiesSCHEMEL(L) | | W/Copi s~Z IEMANN (L)W/9Copies DICKER(E)W/Copies KNIGHTOH(E) |
| W/Copis~ZIEMANN(L)W/9CopiesDICKER(E) | | "'/Copies YOUNGBLOOD(E) |
| W/CopiesKNIGHTOH(E) | | W/Copies INTERNAL DISTRIBUTION REGAN (E)W/Copies W/Copies W/Copies W/Copies AEC PDR+GCF RSM P-506A~NTZING/STAFF CASE GIAMBUSSO BOYD MOORE (L)(BWR)DEYOUNG (L)(FllR)O'SKOVHOLT (L)P, COLLINS FILE®ION(d)) |
| "'/CopiesYOUNGBLOOD(E) | | MORRIS STEELE TECH REVIEW HENDRXE SCHROEDER MACCARY KNIGHT PAWLXCKI SHAO S TELLO HOUSTON NOVAK ROSS XPPOLITO TEDESCO LONG LAINAS BENAROYA VOLLMER DEN TON GRIMES GAMMXLL KAS THER BALLARD SPANGLER ENFIRO MULLER DXCKER BRIGHTON YOUNGBLOOD REGAN PROJECT LDR HARLESS LIC ASST HIGGS (L)GEARIN (L)GOULBOURNE (L)LEE (L)MAXGRET (L)SERVICE (L)SHEPPARD (E)SMITH (L)TEETS (L)WADE (E)WILLIAMS (E)WXLSON (L)A/T IND BRAITMAN SALTZMAN B, HURT PLANS MCDONALD~UBE w/Xnput INFO C, MILES B.KING v4.CABELL-LOCAL PDR Oswe o N.Y.-DTXE(ABERNATHY) |
| W/CopiesINTERNALDISTRIBUTION REGAN(E)W/CopiesW/CopiesW/CopiesW/CopiesAECPDR+GCFRSMP-506A~NTZING/STAFF CASEGIAMBUSSO BOYDMOORE(L)(BWR)DEYOUNG(L)(FllR)O'SKOVHOLT (L)P,COLLINSFILE®ION(d)) | |
| MORRISSTEELETECHREVIEWHENDRXESCHROEDER MACCARYKNIGHTPAWLXCKISHAOSTELLOHOUSTONNOVAKROSSXPPOLITOTEDESCOLONGLAINASBENAROYAVOLLMERDENTONGRIMESGAMMXLLKASTHERBALLARDSPANGLERENFIROMULLERDXCKERBRIGHTONYOUNGBLOOD REGANPROJECTLDRHARLESSLICASSTHIGGS(L)GEARIN(L)GOULBOURNE (L)LEE(L)MAXGRET(L)SERVICE(L)SHEPPARD(E)SMITH(L)TEETS(L)WADE(E)WILLIAMS(E)WXLSON(L)A/TINDBRAITMANSALTZMANB,HURTPLANSMCDONALD~UBEw/XnputINFOC,MILESB.KINGv4.CABELL-LOCALPDROsweoN.Y.-DTXE(ABERNATHY)
| |
| M-NSIC(BUCHANAN) 1-ASLB(YORE/SAYRE/ | | M-NSIC(BUCHANAN) 1-ASLB(YORE/SAYRE/ |
| WOODARD/"H" ST.~6-CYSACRSMQDi}MKSENTTO1-23-74EXTERNALDISTRIBUTION (I)(2XIO).NATIONAL LAB'SI-ASLBP(E/Il Bldg,gm529)1-W.PENNINGTON> | | WOODARD/"H" ST.~6-CYS ACRS MQDi}MK SENT TO 1-23-74 EXTERNAL DISTRIBUTION (I)(2XIO).NATIONAL LAB'S I-ASLBP(E/Il Bldg,gm 529)1-W.PENNINGTON> |
| RmE"201GT1-CONSULTANT'S LXC~ASST'EWARK/BLUME/AGBABIAN DXGGS,1-GERALDULRIKSON...ORNL 1-PDR-SAN/LA/NY 1-GERALDLELLOUCHE BROOKHAVEN HAT.LAB1"AGMED(Ruth Gussman)RM-B-127, GT.1<<RD..MULLER.,F-309 GT ljl~~0PhI'~
| | Rm E" 201 GT 1-CONSULTANT'S LXC~ASST'EWARK/BLUME/AGBABIAN DXGGS, 1-GERALD ULRIKSON...ORNL 1-PDR-SAN/LA/NY 1-GERALD LELLOUCHE BROOKHAVEN HAT.LAB 1"AGMED(Ruth Gussman)RM-B-127, GT.1<<RD..MULLER.,F-309 GT lj l~~0 P h I'~ |
| t,h'egUlatory DocketFileNIAGARAMOHAWKPOWERCORPORATION NIAGARA~MOHAWK300ERIEBOULEVARD, WESTSYRACUSE. | | t, h'egUlatory Docket File NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIE BOULEVARD, WEST SYRACUSE.N.Y.13202 January 22, 1974 Mr.Dennis L.Ziemann, Chief Operating Reactors Branch 82 Directorate of Li cens ing United States Atomic Energy Commission Washington, D.C.20545 |
| N.Y.13202January22,1974Mr.DennisL.Ziemann,ChiefOperating ReactorsBranch82Directorate ofLicensingUnitedStatesAtomicEnergyCommission Washington, D.C.20545 | |
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| ==DearMr.Ziemann:== | | ==Dear Mr.Ziemann:== |
| JAN23)974~ | | JAN23)974~ |
| 'L'InA)EIIpn~It-iiVu~~ | | 'L'In A)EIIpn~It-iiVu~~Re: Nine Mile Point Unit 1 AEC Docket No.50-220 Niagara Mohawk Power Corporation has committed in its letter of October 15, 1973 to supply analyses to determine the effects of fuel densi-ficationn and the appropriate changes to Technical Specifications for the fuel to be inserted during the Spring 1974 refueling. |
| Re:NineMilePointUnit1AECDocketNo.50-220NiagaraMohawkPowerCorporation hascommitted initsletterofOctober15,1973tosupplyanalysestodetermine theeffectsoffueldensi-ficationn andtheappropriate changestoTechnical Specifications forthefueltobeinsertedduringtheSpring1974refueling. | | The analyses have been performed using the, guidance provided in the enclosure to your December 5, 1973 letter,"Modified GE Model f'r Fuel Densification". |
| Theanalyseshavebeenperformed usingthe,guidanceprovidedintheenclosure toyourDecember5,1973letter,"Modified GEModelf'rFuelDensification".
| | These analyses and the proposed Techni:cal Specification changes are attached herewith.It is anti cipated that these changes will not limit plant power level below its full design rating of 1850 megawatts for power distributions expected during normal operation. |
| TheseanalysesandtheproposedTechni:cal Specification changesareattachedherewith.
| | The Site Operations Review Commjttee and the Safety Review and.Audit Board concur with these proposed Telchnical Specification changes.Very truly yours, Vi ce esi dent-Engineering |
| Itisanticipatedthatthesechangeswillnotlimitplantpowerlevelbelowitsfulldesignratingof1850megawatts forpowerdistributions expectedduringnormaloperation.
| | /sq Attachment Subscribed and sworn to before me this~~ay of January, 1974.VALERIE hl.KELLY Notery Pobhc in the'tete of New York Qoeliiled In Onon.Eo..No.3C n50C729~My Corernlrrlon fnplret"Merch 30r l9 r I r r'~,JANP3)ygI EENCE'Uqp lrQQ,~fyICII)CEERX r I |
| TheSiteOperations ReviewCommjttee andtheSafetyReviewand.AuditBoardconcurwiththeseproposedTelchnical Specification changes.Verytrulyyours,Viceesident-Engineering
| | ~.,,,,<<,, Regulatory Docket File Specification Changes For goaeraa~e. |
| /sqAttachment Subscribed andsworntobeforemethis~~ayofJanuary,1974.VALERIEhl.KELLYNoteryPobhcinthe'teteofNewYorkQoeliiled InOnon.Eo..No.3Cn50C729~MyCorernlrrlon fnplret"Merch30rl9rIrr'~,JANP3)ygI EENCE'Uqp lrQQ,~fyICII)CEERX rI | | n naiad Type 5 and Type 6 Fuel I.Anal ses of Fuel Densification Effects This section presents results of the effects of densification in the 8x8 reload fuel as determined from application of the models described in J Re fer'ence 1.A.Local Power Spikin A'n analysi's of potential local power.spikes due to axial gaps in a fuel pellet column for General Electric BMR's employinq an Rx8 fuel lattice design has been performed. |
| ~.,,,,<<,, | | This analysis employs the same method and basic assumotions that were reported in Reference l.Important asnects.'f thi s analys i s are noted as fo1 1 ows: l.The, equation employed to calculate maximum qap size is that noted in Reference 1: dL=~965-+0.0025)L 2 where dL=maximum axial qao length L=fuel column length Pi=mean value of measured initial p llet density (immersion |
| Regulatory DocketFileSpecification ChangesForgoaeraa~e. | | -.5X)0.0025=allowance for irradiation induced cladding growth and axial strain caused by fuel-clad mechanical interacti on.2.The magnitude of the power spike versus gap size for fuel rods of the 8x8 desiqn is shown in Figure 1 for normal operating condi ti ons and Fi gure 2 for col d zero voi d condi ti ons. |
| nnaiadType5andType6FuelI.AnalsesofFuelDensification EffectsThissectionpresentsresultsoftheeffectsofdensification inthe8x8reloadfuelasdetermined fromapplication ofthemodelsdescribed inJRefer'ence1.A.LocalPowerSpikinA'nanalysi's ofpotential localpower.spikesduetoaxialgapsinafuelpelletcolumnforGeneralElectricBMR'semployinq anRx8fuellatticedesignhasbeenperformed.
| | ~4 3.The core power histogram employed v>>as for a 13.4 kl</ft C maximum design linear heat generation rate:.see Figure 3.The results from this analysis are shown in Fiaure 4 with initial fuel density as a parameter. |
| Thisanalysisemploysthesamemethodandbasicassumotions thatwerereportedinReference l.Important asnects.'fthisanalysisarenotedasfo11ows:l.The,equationemployedtocalculate maximumqapsizeisthatnotedinReference 1:dL=~965-+0.0025)L2wheredL=maximumaxialqaolengthL=fuelcolumnlengthPi=meanvalueofmeasuredinitialplletdensity(immersion
| | The line shown for an initial fuel density of 95%T.D.is considered to be most representative considering curr nt General Electric data on manufactured fuel pellet densities. |
| -.5X)0.0025=allowance forirradiation inducedcladdinggrowthandaxialstraincausedbyfuel-clad mechanical interacti on.2.Themagnitude ofthepowerspikeversusgapsizeforfuelrodsofthe8x8desiqnisshowninFigure1fornormaloperating conditionsandFigure2forcoldzerovoidconditions. | | The power snike penalty shown in Figure 4 for several mean pellet densities as a function of axial position, is the required margin which must be maintained durinq normal ooeration between the actual peak operating condition and the oeak design LHGR;i.e., 13.4 kM/ft, Maintaining this margin will assure, with better than 95%confidence, that no more than one rod will exceed the desi qn neak LHGR due to the random occurrence of power spikes-resulting from axial fuel column gans.Consistent with General Electric's position on densification previously discussed in Reference 2 and its supplements, the results of this analysis are considered to he a very conservative representation of the power oeakinq penalty requi red to accommodate 4 potential axial fuel column gaps during normal operating conditions in General Electric BHR's.Since the results of the power spikinq analysis for normal oneration will be utilized to limit bundle power to assure that the random occurrence of power spikes will not result in exceeding the design peak LHGR, it is not believed necessary to separately consider power snikes in the analysis of transients or accidents which have as an initial condition some form of normal oneration. |
| ~4 3.Thecorepowerhistogram employedv>>asfora13.4kl</ftCmaximumdesignlinearheatgeneration rate:.seeFigure3.TheresultsfromthisanalysisareshowninFiaure4withinitialfueldensityasaparameter. | | The control rod drop acci dent is unique in the respect that it begins at the cold condi tion, and is not affected by normal operating power level.Further, the existence of fuel column gaps can result in oower spiking in the cold condition during a control rod drop which should thus be considered in the evaluation of this accident.For this purpose, a separate power spikinq analysis has been performed using the same assumptions as indicated above, but employina a power spi ke versus gap si ze calculated to occur in the cold condi tion with zero voWs (Fi gure 2).This analysis was performed for a conservative maximum gap si ze calculated employing a pellet average immersion density of 94.5ÃT.D., and a position near the top of the core in order to maximize the oower sniking effect.This analysis yielded a 99K probabil'ity th'at any qiven fuel rod would have a power spike of 45K.B.Cladding Creep Collapse Using the same conservative bases presented in References 1 and 2, the critical pressure ratio;i.e., ratio of collapse pressure to actual coolant pressure, was calculated. |
| Thelineshownforaninitialfueldensityof95%T.D.isconsidered tobemostrepresentative considering currntGeneralElectricdataonmanufactured fuelpelletdensities.
| | Figure 5 presents the clad mid-wall temperature versus time for the 8x8 reload fuel..No credit is taken for internal qas pressure due to released fissi on gas or volati les.The internal pressure due to helium backfill at 1 atmosphere during fabrication is considered. |
| ThepowersnikepenaltyshowninFigure4forseveralmeanpelletdensities asafunctionofaxialposition, istherequiredmarginwhichmustbemaintained durinqnormalooeration betweentheactualpeakoperating condition andtheoeakdesignLHGR;i.e.,13.4kM/ft,Maintaining thismarginwillassure,withbetterthan95%confidence, thatnomorethanonerodwillexceedthedesiqnneakLHGRduetotherandomoccurrence ofpowerspikes-resulting fromaxialfuelcolumngans.Consistent withGeneralElectric's positionondensification previously discussed inReference 2anditssupplements, theresultsofthisanalysisareconsidered toheaveryconservative representation ofthepoweroeakinqpenaltyrequiredtoaccommodate 4potential axialfuelcolumngapsduringnormaloperating conditions inGeneralElectricBHR's.Sincetheresultsofthepowerspikinqanalysisfornormaloneration willbeutilizedtolimitbundlepowertoassurethattherandomoccurrence ofpowerspikeswillnotresultinexceeding thedesignpeakLHGR,itisnotbelievednecessary toseparately considerpowersnikesintheanalysisoftransients oraccidents whichhaveasaninitialcondition someformofnormaloneration.
| | The fuel characteristics for creep collapse'calculations are as follows: Clad O.D., in.Clad Thickness, in.0.493 0.034+0:003 Peak LHGR, kw/ft 13.4 Fast Flux vl Nev.n/cm2-sec 4.37 x 1013 Figure 6 gives the calculated critical pressure ratio.As evidenced by the curve, the calculated critical oressure ratio is always o1.0.C.Increased Linear Heat Generation Rate The following expression was employed to calculate the decrease in fuel column length due to densification in calculation of a penalty in linear heat generation rate:~0.965-5L=2 L 0~I Where hL=decrease in fuel column.length L=fuel column length p;=mean value of measured initial pellet density (immersion |
| Thecontrolroddropaccidentisuniqueintherespectthatitbeginsatthecoldcondition,andisnotaffectedbynormaloperating powerlevel.Further,theexistence offuelcolumngapscanresultinoowerspikinginthecoldcondition duringacontrolroddropwhichshouldthusbeconsidered intheevaluation ofthisaccident.
| | -.5/}The length reduction due to densification as calculated by the above equation requires knowledge of the mean immersion density (p;}obtained from the gC data.A correction of 0-.5A T.D.is applied to convert the immersion densi ty to a geometric density.The mean pellet immersion density for Nine Mile Point 1 8xS reload fuel is 95.29/.T.D.This results in: A L=0.965-0.9529-0.005=0.01709=0.009 L 2 2 or AL=0.9X L Due=-to thermal expansion, an SxS pellet normally exnands in goinq from the cold to hot condition, an amount equal to 1.25 for a pellet at 13.4 kW/ft.This increase in length from the cold to hot condition is not taken credit for in either design calculations or in the process of core nerformance analysis during reactor operations. |
| Forthispurpose,aseparatepowerspikinqanalysishasbeenperformed usingthesameassumptions asindicated above,butemployina apowerspikeversusgapsizecalculated tooccurinthecoldconditionwithzerovoWs(Figure2).Thisanalysiswasperformed foraconservative maximumgapsizecalculated employing apelletaverageimmersion densityof94.5ÃT.D.,andapositionnearthetopofthecoreinordertomaximizetheoowersnikingeffect.Thisanalysisyieldeda99Kprobabil'ity th'atanyqivenfuelrodwouldhaveapowerspikeof45K.B.CladdingCreepCollapseUsingthesameconservative basespresented inReferences 1and2,thecriticalpressureratio;i.e.,ratioofcollapsepressuretoactualcoolantpressure, wascalculated.
| | The cold pellet length is assumed for these condi ti ons.Therefore, the decrease in pellet length due to densification is more than offset by pellet axial thermal expansion. |
| Figure5presentsthecladmid-walltemperature versustimeforthe8x8reloadfuel..Nocreditistakenforinternalqaspressureduetoreleasedfissiongasorvolatiles.Theinternalpressureduetoheliumbackfillat1atmosphere duringfabrication isconsidered.
| | D.Decreased Pellet-Cl ad Thermal Conducti vi t Figure 7 provides plots of Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)versus exposure, for Nine Mile Point Sx8 reload fuel.Them (omega}curve is suitable for incorporation into the plant technical specifications. |
| Thefuelcharacteristics forcreepcollapse'calculations areasfollows:CladO.D.,in.CladThickness, in.0.4930.034+0:003PeakLHGR,kw/ft13.4FastFluxvlNev.n/cm2-sec 4.37x1013Figure6givesthecalculated criticalpressureratio.Asevidenced bythecurve,thecalculated criticaloressureratioisalwayso1.0.C.Increased LinearHeatGeneration RateThefollowing expression wasemployedtocalculate thedecreaseinfuelcolumnlengthduetodensification incalculation ofapenaltyinlinearheatgeneration rate:~0.965-5L=2L 0~I WherehL=decreaseinfuelcolumn.lengthL=fuelcolumnlengthp;=meanvalueofmeasuredinitialpelletdensity(immersion
| | The LOCA analyses were performed using the approved Interim Acceotance Criteria Model with gap conductance values as calculated per the new GEGAP III model with AEC modifications.(1 |
| -.5/}Thelengthreduction duetodensification ascalculated bytheaboveequationrequiresknowledge ofthemeanimmersion density(p;}obtainedfromthegCdata.Acorrection of0-.5AT.D.isappliedtoconverttheimmersion densitytoageometric density.Themeanpelletimmersion densityforNineMilePoint18xSreloadfuelis95.29/.T.D.Thisresultsin:AL=0.965-0.9529-0.005=0.01709=0.009L22orAL=0.9XLDue=-tothermalexpansion, anSxSpelletnormallyexnandsingoinqfromthecoldtohotcondition, anamountequalto1.25forapelletat13.4kW/ft.Thisincreaseinlengthfromthecoldtohotcondition isnottakencreditforineitherdesigncalculations orintheprocessofcorenerformance analysisduringreactoroperations. | |
| Thecoldpelletlengthisassumedfortheseconditions.Therefore, thedecreaseinpelletlengthduetodensification ismorethanoffsetbypelletaxialthermalexpansion.
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| D.Decreased Pellet-Cl adThermalConductivitFigure7providesplotsofMaximumAveragePlanarLinearHeatGeneration Rate(MAPLHGR) versusexposure, forNineMilePointSx8reloadfuel.Them(omega}curveissuitableforincorporation intotheplanttechnical specifications. | |
| TheLOCAanalyseswereperformed usingtheapprovedInterimAcceotance CriteriaModelwithgapconductance valuesascalculated perthenewGEGAPIIImodelwithAECmodifications.(1
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| REFERENCES l.Hinds,J.A.,(GeneralElectric) lettertoY.A.Hoore(USAEC),"PlantEvaluations withGEGAPIII,"December12,1973.2."GenericDesignInformation forGeneralElectricReloadFuel",NEDO-20103; September 1973.3.NEDtl-10735, Supplement 6,"FuelDensification EffectsonGeneralElectricBoilingMaterReactorFuel,"August1973. | | REFERENCES l.Hinds, J.A., (General Electric)letter to Y.A.Hoore (USAEC),"Plant Evaluations with GEGAP III," December 12, 1973.2."Generic Design Information for General Electric Reload Fuel", NEDO-20103; September 1973.3.NEDtl-10735, Supplement 6,"Fuel Densification Effects on General Electric Boiling Mater Reactor Fuel," August 1973. |
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| ,7.0~FIGURE18x8POWERSPIKEVERSUSGAPSIZE-NORMALOPERATION 6.05.0hPp4.0(I)3.02.01.00RODRELATIONSHIP (gO2OeO2O3O5O~05gonadjacentPellet-npod59~opg~o~ongo<~9@9dyponRod8apinRogreccdg5onRod81EffectofagapinRoEffecofa9dg4onRodNEffectofa9ap01.02,03.0GAPSIZE(CM)4.05.06.0 | | , 7.0~FIGURE 1 8x8 POWER SPIKE VERSUS GAP SIZE-NORMAL OPERATION 6.0 5.0 hP p 4.0 (I)3.0 2.0 1.0 0 ROD RELATIONSHIP (g O2 Oe O2 O3 O5 O~05 g on adjacent P ellet-n pod 59~op g~o~on go<~9@9 d yp on Rod 8 ap in Ro grec c d g5 on Rod 81 Effect of a gap in Ro Ef fec of a 9 d g4 on Rod N Effect of a 9ap 0 1.0 2,0 3.0 GAP SIZE (CM)4.0 5.0 6.0 |
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| FIGURE28x8POWERSPIKEVERSUSGAPSIZE-COLDZEROVOIDCONDITION RODRELATIONSHIPS OlO2O4020305o~O4O~0~~0o~d>onRod1inRooggaP~"<~g.ectoRod4onRod1EffectofqapinREffectofgapvariRod5onRod]GAPSIZE(Cg)
| | FIGURE 2 8x8 POWER SPIKE VERSUS GAP SIZE-COLD ZERO VOID CONDITION ROD RELATIONSHIPS Ol O2 O4 02 03 05 o~O4 O~0~~0 o~d>on Rod 1 in Ro og gaP~"<~g.ect o Rod 4 on Rod 1 Effect of qap in R Effect of gap vari Rod 5 on Rod]GAP SIZE (Cg) |
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| FIGURE34.01.21.0.8.6A'.0C).2012LHGR(KH/FT=X)13140
| | FIGURE 3 4.0 1.2 1.0.8.6 A'.0 C).2 0 12 LHGR (KH/FT=X)13 14 0 |
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| FIGURE48x8POMERSPIKEPENALTYYSAXIALPOSITION-NORMALOPERATION 1.02.03.096,095.04.04.03.094.02.095.096.056-7DISTANCEFROMBOTTOMOFCORE(FEET)81012
| | FIGURE 4 8x8 POMER SPIKE PENALTY YS AXIAL POSITION-NORMAL OPERATION 1.0 2.0 3.0 96,0 95.0 4.0 4.0 3.0 94.0 2.0 95.0 96.0 5 6-7 DISTANCE FROM BOTTOM OF CORE (FEET)8 10 12 |
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| 690FIGURE5CLADDINGAVERAGETEMPERATURE ATAFUELCOLUMNAXIALGAP6806706606500640UJ63062086'j0a-6005905805705605500IRRADIATION TIME,YEARS
| | 690 FIGURE 5 CLADDING AVERAGE TEMPERATURE AT A FUEL COLUMN AXIAL GAP 680 670 660 650 0 640 UJ 630 620 8 6'j0 a-600 590 580 570 560 550 0 IRRADIATION TIME, YEARS |
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| 4.0FIGURE6CLADCRITICALCOLLAPSEPRESSURERATIOVERSUSTIME8x8RELOADFUEL3.01.023IRRADIATION TIME,YEARS 0 | | 4.0 FIGURE 6 CLAD CRITICAL COLLAPSE PRESSURE RATIO VERSUS TIME 8x8 RELOAD FUEL 3.0 1.0 2 3 IRRADIATION TIME, YEARS 0 |
| I716FIGURE7MAPLHGRVERSUSEXPOS'MAXIMUMALLOWABLE TOSTAYBELOWCURRENTTECHNICAL SPECIFICATION LIMITFORLHGR0MAXIMUMALLOWABLE WITHGEGAPIIIANDAEClODIFICATIONS 15~1413~12OC1005,00010,00015,00020,000AVERAGEPLANAREXPOSURE(mWd/t)25,00030,000
| | I7 16 FIGURE 7 MAPLHGR VERSUS EXPOS'MAXIMUM ALLOWABLE TO STAY BELOW CURRENT TECHNICAL SPECIFICATION LIMIT FOR LHGR 0 MAXIMUM ALLOWABLE WITH GEGAP III AND AEC lODI FICATIONS 15~14 13~12 OC 10 0 5,000 10,000 15,000 20,000 AVERAGE PLANAR EXPOSURE (mWd/t)25,000 30,000 |
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| II.ProposedChanestoTechnicalSpecificationsChangepages37a,37b,37c,etc.asfollows:~ChaneAAddtheattachedFigure3.1.7etotheTechnical Specification. | | II.Proposed Chan es to Techni cal Speci fi cations Change pages 37a, 37b, 37c, etc.as follows:~Chan e A Add the attached Figure 3.1.7e to the Technical Specification. |
| UndertheLimitingCondition forOperation 3.1.7,addFigure3.1.7etothelistoffiguresattheendofthelastsentenceinparagraph a.~ChaneBRep'lacethenotes;totheequationinLimitingConditions forOoeration 3.1.7bwiththefollowing:
| | Under the Limiting Condition for Operation 3.1.7, add Figure 3.1.7e to the list of figures at the end of the last sentence in paragraph a.~Chan e B Rep'lace the notes;to the equation in Limiting Conditions for Ooeration 3.1.7b wi th the following: |
| "LHGRd=DesignLHGR=17.5kw/ftfor7x7fuelor13.4kw/ftfor8x8fuelQp/p)~AX=Maximumpowerspikingpenalty'0.040for7x7fuelor0.027forBx8fuel.LT=TotalCorelenath=12ft.L=Axialpositionabovebottonofcore"~ChaneCAddFigure3.1.7etothelistoffiquresinthethirdoaraaranh oftheBases3.1.7a.ReasonsforChanesA,BRCTheresultsofanalysesperformed for8x8reloadfuelhasindicatedthatlimitsonflAPLHGRandpowersoikingoenalties duetodensification arerequired. | | " LHGRd=Design LHGR=17.5 kw/ft for 7x7 fuel or 13.4 kw/ft for 8x8 fuel Qp/p)~AX=Maximum power spiking penalty'0.040 for 7x7 fuel or 0.027 for Bx8 fuel.LT=Total Core lenath=12 ft.L=Axial posi tion above botton of core"~Chan e C Add Figure 3.1.7e to the list of fiqures in the third oaraaranh of the Bases 3.1.7a.Reasons for Chan es A, B R C The results of analyses performed for 8x8 reload fuel has indi cated that limits on flAPLHGR and power soiking oenalties due to densification are required.These limits as they apply to Type 5 and Type 6 fuel are presented for incorporation into Nine Nile Point Unit 1 Technical Specifications. |
| TheselimitsastheyapplytoType5andType6fuelarepresented forincorporation intoNineNilePointUnit1Technical Specifications.
| | Similar limits for previously loaded 7x7 fuel are already nart of-the'echni cal Speci fi cati ons. |
| Similarlimitsforpreviously loaded7x7fuelarealreadynartof-the'echnicalSpecifications.
| | J IE 17 NINE hflLE POINT-PilIT 1 16~4~14~13~12 OC 10 0 5,000 10,000 15,000 20,000 AVERAGE PLANAR EXPOSURE (ml<d/t)25,000 30,000 FIGURE'.1.7.e ftAXIf GAUM ALLOWABLE AVERAGE PLANAR LHGR APPLICABLE TO FUEL TYPE 5 and 6 0 0 A'l}} |
| JIE 17NINEhflLEPOINT-PilIT 116~4~14~13~12OC1005,00010,00015,00020,000AVERAGEPLANAREXPOSURE(ml<d/t)25,00030,000FIGURE'.1.7.eftAXIfGAUMALLOWABLE AVERAGEPLANARLHGRAPPLICABLE TOFUELTYPE5and6 00A'l}}
| |
|
|---|
Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
IR 05000410/20243012023-12-14014 December 2023
Initial Operator Licensing Examination Report 05000410/2024301
2024-09-04
[Table view]
Category:Technical Specification
MONTHYEARNMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML22298A0112022-10-25025 October 2022
License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To.
ML22292A1312022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Technical Specification Bases, Rev. 69
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022
Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022
License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.
NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021
Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021
License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020
Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability
NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019
Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019
Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability
RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019
Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls
NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018
Technical Specification Bases, Rev. 57
NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018
Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017
License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note
NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017
License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
ML16309A4002016-10-24024 October 2016
Revision 47 to Technical Specification Bases, List of Effective Pages
ML16309A4022016-10-24024 October 2016
Revision 47 to Technical Specification Bases, Section B2.0, Safety Limits (Sls)
ML16309A4032016-10-24024 October 2016
Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability
ML16309A4052016-10-24024 October 2016
Revision 47 to Technical Specification Bases, Section B3.2, Power Distribution Limits
ML16309A4012016-10-24024 October 2016
Revision 47 to Technical Specification Bases, Table of Contents
ML16309A4132016-10-24024 October 2016
Revision 47 to Technical Specification Bases, Section B3.9, Refueling Operations
ML16309A4082016-10-24024 October 2016
Revision 47 to Technical Specification Bases, Section B3.5, Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) System
ML16209A2182016-07-26026 July 2016
Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance2016-03-18018 March 2016
License Amendment Request - Reactivity Anomalies Surveillance
NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request2015-09-24024 September 2015
Supplemental Information Regarding TSTF-425 License Amendment Request
NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015
Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
ML15089A2312015-03-26026 March 2015
Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
NMP1L3010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-03-26026 March 2015
Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015
License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014
License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change
ML14191A2552014-07-10010 July 2014
Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
ML12156A3632012-06-0101 June 2012
Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit
ML11306A2982011-10-27027 October 2011
Submittal of Revision 22 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b)
ML11214A2142011-07-25025 July 2011
License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information
ML1109602832011-03-30030 March 2011
License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ...
ML0935000902009-12-0909 December 2009
License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating
ML0931602572009-10-26026 October 2009
Submittal of Revision 21 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b)
ML0907802502009-03-0909 March 2009
Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency
ML0906403012009-03-0303 March 2009
License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
ML0827502992008-09-29029 September 2008
Technical Specifications
ML0802501622008-01-24024 January 2008
Response to NRC Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup
ML0726401032007-09-19019 September 2007
License Amendment Request for Adoption of TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities.
ML0721906052007-07-30030 July 2007
Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process
ML0721205922007-07-23023 July 2007
Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement
ML0721205872007-07-23023 July 2007
License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b
ML0720504232007-07-12012 July 2007
Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
2024-07-31
[Table view]
Category:Amendment
MONTHYEARML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML22298A0112022-10-25025 October 2022
License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To.
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022
Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021
Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020
Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability
NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019
Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019
Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls
NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018
Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017
License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note
NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017
License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015
Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015
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License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change
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License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ...
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Tech Spec Pages for Amendment 115 and 188 Reporting Requirements for Annual Radiological Environmental Operating Report
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Unit I, License Amendment Request Pursuant to 10 CFR 50.90: Addition of 24 Hours for Restoration of Primary Containment Oxygen Concentration
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Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications (Appendix a) to Clarify Cloride and Oxygen Levels
ML17037C1771975-12-19019 December 1975
Letter Enclosing a Corrected Attachment to License Amendment No. 11 Change No. 27 to the Technical Specifications Provisional Operating License No. DPR-16
ML17037C1831975-11-0303 November 1975
Letter Regarding Application for Amendment to Technical Specifications and an Inadvertent Error Not Made on the Persons Listed in the Certificate of Service
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Letter Regarding a Stress Assisted Corrosion Problem and an Enclosed Safety Evaluation by the Office of NRR - Supporting Amendment to License No. DPR-63 and Changes to the Technical Specifications Inoperable Control Rod ..
2024-04-12
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AEC DXS UTION FOR PART 50 DOCKET MATER (TEMPORARY FORM)CONTROL NO: FILE: 8 FROAA1: Niagara Mohawk Power Corp Syracuse, N;Y.13202 P.D.Raymond DATE OF DOC 1-22-74 DATE REC'D 1-23-74 LTR MEMO RPT OTHER TO: D.L.Ziemann ORIG 3 signedq CC OTHER SENT AEC PDR x SENT LOCAL PDR X CLASS UNCLASS XXXX PROP INFO INPUT XXXX NO C S REC'D 40 DOCKET NO: 50-220 DESCRIPTION:
Ltr notarized 1-22-74, trans the following:
PLANT NAME: Nine Mile Point Unit$P1 ENCLOSURES:
Pro osed Chan e to Technical S ecifications:
Densification Analyses and Related Technical Specifications Changes for Type 5 and Type DO NOT REMOVE ACKNOWLEDGED (3 Orig 6 37 cys rec'd)FOR ACTION/INFORMATION 1-23-74 GC BUTLER (L)W/Copies CLARK(L)W/Copies GOLLER(L)W/Copies KNIEL(L)W/Copies SCHWENCER(L)
W/Copies STOLZ(L)W/Copies VASSALLO(L)
'W/Copies SCHEMEL(L)
W/Copi s~Z IEMANN (L)W/9Copies DICKER(E)W/Copies KNIGHTOH(E)
"'/Copies YOUNGBLOOD(E)
W/Copies INTERNAL DISTRIBUTION REGAN (E)W/Copies W/Copies W/Copies W/Copies AEC PDR+GCF RSM P-506A~NTZING/STAFF CASE GIAMBUSSO BOYD MOORE (L)(BWR)DEYOUNG (L)(FllR)O'SKOVHOLT (L)P, COLLINS FILE®ION(d))
MORRIS STEELE TECH REVIEW HENDRXE SCHROEDER MACCARY KNIGHT PAWLXCKI SHAO S TELLO HOUSTON NOVAK ROSS XPPOLITO TEDESCO LONG LAINAS BENAROYA VOLLMER DEN TON GRIMES GAMMXLL KAS THER BALLARD SPANGLER ENFIRO MULLER DXCKER BRIGHTON YOUNGBLOOD REGAN PROJECT LDR HARLESS LIC ASST HIGGS (L)GEARIN (L)GOULBOURNE (L)LEE (L)MAXGRET (L)SERVICE (L)SHEPPARD (E)SMITH (L)TEETS (L)WADE (E)WILLIAMS (E)WXLSON (L)A/T IND BRAITMAN SALTZMAN B, HURT PLANS MCDONALD~UBE w/Xnput INFO C, MILES B.KING v4.CABELL-LOCAL PDR Oswe o N.Y.-DTXE(ABERNATHY)
M-NSIC(BUCHANAN) 1-ASLB(YORE/SAYRE/
WOODARD/"H" ST.~6-CYS ACRS MQDi}MK SENT TO 1-23-74 EXTERNAL DISTRIBUTION (I)(2XIO).NATIONAL LAB'S I-ASLBP(E/Il Bldg,gm 529)1-W.PENNINGTON>
Rm E" 201 GT 1-CONSULTANT'S LXC~ASST'EWARK/BLUME/AGBABIAN DXGGS, 1-GERALD ULRIKSON...ORNL 1-PDR-SAN/LA/NY 1-GERALD LELLOUCHE BROOKHAVEN HAT.LAB 1"AGMED(Ruth Gussman)RM-B-127, GT.1<<RD..MULLER.,F-309 GT lj l~~0 P h I'~
t, h'egUlatory Docket File NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIE BOULEVARD, WEST SYRACUSE.N.Y.13202 January 22, 1974 Mr.Dennis L.Ziemann, Chief Operating Reactors Branch 82 Directorate of Li cens ing United States Atomic Energy Commission Washington, D.C.20545
Dear Mr.Ziemann:
JAN23)974~
'L'In A)EIIpn~It-iiVu~~Re: Nine Mile Point Unit 1 AEC Docket No.50-220 Niagara Mohawk Power Corporation has committed in its letter of October 15, 1973 to supply analyses to determine the effects of fuel densi-ficationn and the appropriate changes to Technical Specifications for the fuel to be inserted during the Spring 1974 refueling.
The analyses have been performed using the, guidance provided in the enclosure to your December 5, 1973 letter,"Modified GE Model f'r Fuel Densification".
These analyses and the proposed Techni:cal Specification changes are attached herewith.It is anti cipated that these changes will not limit plant power level below its full design rating of 1850 megawatts for power distributions expected during normal operation.
The Site Operations Review Commjttee and the Safety Review and.Audit Board concur with these proposed Telchnical Specification changes.Very truly yours, Vi ce esi dent-Engineering
/sq Attachment Subscribed and sworn to before me this~~ay of January, 1974.VALERIE hl.KELLY Notery Pobhc in the'tete of New York Qoeliiled In Onon.Eo..No.3C n50C729~My Corernlrrlon fnplret"Merch 30r l9 r I r r'~,JANP3)ygI EENCE'Uqp lrQQ,~fyICII)CEERX r I
~.,,,,<<,, Regulatory Docket File Specification Changes For goaeraa~e.
n naiad Type 5 and Type 6 Fuel I.Anal ses of Fuel Densification Effects This section presents results of the effects of densification in the 8x8 reload fuel as determined from application of the models described in J Re fer'ence 1.A.Local Power Spikin A'n analysi's of potential local power.spikes due to axial gaps in a fuel pellet column for General Electric BMR's employinq an Rx8 fuel lattice design has been performed.
This analysis employs the same method and basic assumotions that were reported in Reference l.Important asnects.'f thi s analys i s are noted as fo1 1 ows: l.The, equation employed to calculate maximum qap size is that noted in Reference 1: dL=~965-+0.0025)L 2 where dL=maximum axial qao length L=fuel column length Pi=mean value of measured initial p llet density (immersion
-.5X)0.0025=allowance for irradiation induced cladding growth and axial strain caused by fuel-clad mechanical interacti on.2.The magnitude of the power spike versus gap size for fuel rods of the 8x8 desiqn is shown in Figure 1 for normal operating condi ti ons and Fi gure 2 for col d zero voi d condi ti ons.
~4 3.The core power histogram employed v>>as for a 13.4 kl</ft C maximum design linear heat generation rate:.see Figure 3.The results from this analysis are shown in Fiaure 4 with initial fuel density as a parameter.
The line shown for an initial fuel density of 95%T.D.is considered to be most representative considering curr nt General Electric data on manufactured fuel pellet densities.
The power snike penalty shown in Figure 4 for several mean pellet densities as a function of axial position, is the required margin which must be maintained durinq normal ooeration between the actual peak operating condition and the oeak design LHGR;i.e., 13.4 kM/ft, Maintaining this margin will assure, with better than 95%confidence, that no more than one rod will exceed the desi qn neak LHGR due to the random occurrence of power spikes-resulting from axial fuel column gans.Consistent with General Electric's position on densification previously discussed in Reference 2 and its supplements, the results of this analysis are considered to he a very conservative representation of the power oeakinq penalty requi red to accommodate 4 potential axial fuel column gaps during normal operating conditions in General Electric BHR's.Since the results of the power spikinq analysis for normal oneration will be utilized to limit bundle power to assure that the random occurrence of power spikes will not result in exceeding the design peak LHGR, it is not believed necessary to separately consider power snikes in the analysis of transients or accidents which have as an initial condition some form of normal oneration.
The control rod drop acci dent is unique in the respect that it begins at the cold condi tion, and is not affected by normal operating power level.Further, the existence of fuel column gaps can result in oower spiking in the cold condition during a control rod drop which should thus be considered in the evaluation of this accident.For this purpose, a separate power spikinq analysis has been performed using the same assumptions as indicated above, but employina a power spi ke versus gap si ze calculated to occur in the cold condi tion with zero voWs (Fi gure 2).This analysis was performed for a conservative maximum gap si ze calculated employing a pellet average immersion density of 94.5ÃT.D., and a position near the top of the core in order to maximize the oower sniking effect.This analysis yielded a 99K probabil'ity th'at any qiven fuel rod would have a power spike of 45K.B.Cladding Creep Collapse Using the same conservative bases presented in References 1 and 2, the critical pressure ratio;i.e., ratio of collapse pressure to actual coolant pressure, was calculated.
Figure 5 presents the clad mid-wall temperature versus time for the 8x8 reload fuel..No credit is taken for internal qas pressure due to released fissi on gas or volati les.The internal pressure due to helium backfill at 1 atmosphere during fabrication is considered.
The fuel characteristics for creep collapse'calculations are as follows: Clad O.D., in.Clad Thickness, in.0.493 0.034+0:003 Peak LHGR, kw/ft 13.4 Fast Flux vl Nev.n/cm2-sec 4.37 x 1013 Figure 6 gives the calculated critical pressure ratio.As evidenced by the curve, the calculated critical oressure ratio is always o1.0.C.Increased Linear Heat Generation Rate The following expression was employed to calculate the decrease in fuel column length due to densification in calculation of a penalty in linear heat generation rate:~0.965-5L=2 L 0~I Where hL=decrease in fuel column.length L=fuel column length p;=mean value of measured initial pellet density (immersion
-.5/}The length reduction due to densification as calculated by the above equation requires knowledge of the mean immersion density (p;}obtained from the gC data.A correction of 0-.5A T.D.is applied to convert the immersion densi ty to a geometric density.The mean pellet immersion density for Nine Mile Point 1 8xS reload fuel is 95.29/.T.D.This results in: A L=0.965-0.9529-0.005=0.01709=0.009 L 2 2 or AL=0.9X L Due=-to thermal expansion, an SxS pellet normally exnands in goinq from the cold to hot condition, an amount equal to 1.25 for a pellet at 13.4 kW/ft.This increase in length from the cold to hot condition is not taken credit for in either design calculations or in the process of core nerformance analysis during reactor operations.
The cold pellet length is assumed for these condi ti ons.Therefore, the decrease in pellet length due to densification is more than offset by pellet axial thermal expansion.
D.Decreased Pellet-Cl ad Thermal Conducti vi t Figure 7 provides plots of Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)versus exposure, for Nine Mile Point Sx8 reload fuel.Them (omega}curve is suitable for incorporation into the plant technical specifications.
The LOCA analyses were performed using the approved Interim Acceotance Criteria Model with gap conductance values as calculated per the new GEGAP III model with AEC modifications.(1
}
REFERENCES l.Hinds, J.A., (General Electric)letter to Y.A.Hoore (USAEC),"Plant Evaluations with GEGAP III," December 12, 1973.2."Generic Design Information for General Electric Reload Fuel", NEDO-20103; September 1973.3.NEDtl-10735, Supplement 6,"Fuel Densification Effects on General Electric Boiling Mater Reactor Fuel," August 1973.
, 7.0~FIGURE 1 8x8 POWER SPIKE VERSUS GAP SIZE-NORMAL OPERATION 6.0 5.0 hP p 4.0 (I)3.0 2.0 1.0 0 ROD RELATIONSHIP (g O2 Oe O2 O3 O5 O~05 g on adjacent P ellet-n pod 59~op g~o~on go<~9@9 d yp on Rod 8 ap in Ro grec c d g5 on Rod 81 Effect of a gap in Ro Ef fec of a 9 d g4 on Rod N Effect of a 9ap 0 1.0 2,0 3.0 GAP SIZE (CM)4.0 5.0 6.0
FIGURE 2 8x8 POWER SPIKE VERSUS GAP SIZE-COLD ZERO VOID CONDITION ROD RELATIONSHIPS Ol O2 O4 02 03 05 o~O4 O~0~~0 o~d>on Rod 1 in Ro og gaP~"<~g.ect o Rod 4 on Rod 1 Effect of qap in R Effect of gap vari Rod 5 on Rod]GAP SIZE (Cg)
FIGURE 3 4.0 1.2 1.0.8.6 A'.0 C).2 0 12 LHGR (KH/FT=X)13 14 0
FIGURE 4 8x8 POMER SPIKE PENALTY YS AXIAL POSITION-NORMAL OPERATION 1.0 2.0 3.0 96,0 95.0 4.0 4.0 3.0 94.0 2.0 95.0 96.0 5 6-7 DISTANCE FROM BOTTOM OF CORE (FEET)8 10 12
690 FIGURE 5 CLADDING AVERAGE TEMPERATURE AT A FUEL COLUMN AXIAL GAP 680 670 660 650 0 640 UJ 630 620 8 6'j0 a-600 590 580 570 560 550 0 IRRADIATION TIME, YEARS
4.0 FIGURE 6 CLAD CRITICAL COLLAPSE PRESSURE RATIO VERSUS TIME 8x8 RELOAD FUEL 3.0 1.0 2 3 IRRADIATION TIME, YEARS 0
I7 16 FIGURE 7 MAPLHGR VERSUS EXPOS'MAXIMUM ALLOWABLE TO STAY BELOW CURRENT TECHNICAL SPECIFICATION LIMIT FOR LHGR 0 MAXIMUM ALLOWABLE WITH GEGAP III AND AEC lODI FICATIONS 15~14 13~12 OC 10 0 5,000 10,000 15,000 20,000 AVERAGE PLANAR EXPOSURE (mWd/t)25,000 30,000
II.Proposed Chan es to Techni cal Speci fi cations Change pages 37a, 37b, 37c, etc.as follows:~Chan e A Add the attached Figure 3.1.7e to the Technical Specification.
Under the Limiting Condition for Operation 3.1.7, add Figure 3.1.7e to the list of figures at the end of the last sentence in paragraph a.~Chan e B Rep'lace the notes;to the equation in Limiting Conditions for Ooeration 3.1.7b wi th the following:
" LHGRd=Design LHGR=17.5 kw/ft for 7x7 fuel or 13.4 kw/ft for 8x8 fuel Qp/p)~AX=Maximum power spiking penalty'0.040 for 7x7 fuel or 0.027 for Bx8 fuel.LT=Total Core lenath=12 ft.L=Axial posi tion above botton of core"~Chan e C Add Figure 3.1.7e to the list of fiqures in the third oaraaranh of the Bases 3.1.7a.Reasons for Chan es A, B R C The results of analyses performed for 8x8 reload fuel has indi cated that limits on flAPLHGR and power soiking oenalties due to densification are required.These limits as they apply to Type 5 and Type 6 fuel are presented for incorporation into Nine Nile Point Unit 1 Technical Specifications.
Similar limits for previously loaded 7x7 fuel are already nart of-the'echni cal Speci fi cati ons.
J IE 17 NINE hflLE POINT-PilIT 1 16~4~14~13~12 OC 10 0 5,000 10,000 15,000 20,000 AVERAGE PLANAR EXPOSURE (ml<d/t)25,000 30,000 FIGURE'.1.7.e ftAXIf GAUM ALLOWABLE AVERAGE PLANAR LHGR APPLICABLE TO FUEL TYPE 5 and 6 0 0 A'l
