ML15254A415

Limerick Generating Station, Unit 1 Colr for Reload 15 Cycle 16 with Appendix a

ML15254A415
Person / Time
Site:	Limerick
Issue date:	06/30/2015
From:	Holmes M Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
LG-15-092
Download: ML15254A415 (58)

Text

{{#Wiki_filter:ENCLOSURE 3UNIT 1 COLA FOR RELOAD 15 CYCLE 16WITH APPENDIX APROPRIETARY CLASS I (PUBLIC). ... ... .. ........... .. .i. : .:.:,- , ,. ...... .... .. ., ...... ..,tI .....t ; iI i1/2 i..%~.~** Exelon Nuciear-Nurcear Fuels " COLR Limoerik I, Rev. 12Core Operating Limits ReportNon-Proprietary Information Submitted in Accordanice with 10 CFR 2.390COREi OPERATING LIMITS FORLhMERICK GENERATING STATION ...,..UNIT 1 RELOAD 15 CYCLE 16i-'. -'i." , IM. Holmes... PreparerDa "e ', 2 "'" : " 3" I I _ .. ' " "Reviewed:By: i.HsuIndependent ReviewerDae: ,ae ( ,,2 /5 .A. Stefanezyk Reviewed By: ""I'T. BementEngineering Sa.fety Analysis'Manager -BWR, Designa lDa,,e: ,! 9ASratan Qualified Review By:-L. KurbeilStation Qualified Revieworoote: .f9I /&o kI ':f~m i t_" Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNan-Proprietary Information Submitted in Accordance with 10 CFR 2.390Table of ContentsCOLR Limerick i, Rev. 12 1Revision HistoryList of Tables1.0 Terms and Definitions 2.0 General 3.0 MAPLHGR Limits4.0 MCPR Limits5.0 LHGR Limits6.0 Control Rod Block Setpoints 7.0 Turbine Bypass Valve Parameters 8.0 Stability Protection Setpoints 9.0 Modes of Operation 10.0 Methodology 11!.0 References Appendix A .. ..Page34S7891316171819202021Page2of2l: i Exelon Nuclear -Nuclear Fuels COLR Limerick I, Rev. 12Core Operating Limits Report,,."** .Non-Proprietary Int'ormation Submitted in Accordance with 10 CFR 2.3g0 .. ..*" .... .'Revision History,Revision eritoRevision 12 ., .. PROOS limits. Miscellaneous ..editorial and formatting changes to ensurei: * , -- consistency with Unit -: ..Revision il ..I .: ;.,,>:'; New issue for~ycle. 16' ,::i :, ..~~~~~~.. .- ................... "'i.- ....".i..'"' ,.'.i. ............ I, 2xelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Prmpretaiy Information Submitted in Accordance with 10 CFR 22t90List of Tables "COLR Limerick !, Rev. 12 ITable 3-1..Table 3-2Table 3-3T~able 4-1Table 4-2Table 4-3Table 4.4Table 5-ITable 5-2Table 5-3Table 5-4Table 5-5Table 6-1Table 6-2Table 7- IT~able 7-2Table 8-I!Table 8-2Table 9-IMAPLHGR Versus Average Planar Exposure-GEl4 .. .MAPLHOR-Versus"AvergePlanar Exposure-GNF2. ' .. -MAPLHGR Single Loop Operation (SLO) Multiplier -All Fuel TypesOperating Limit Minimum Critical Power Ratio (OLMCPR) -GNl4Power Dependent MCPR Limits and Multipliers MCPR(P) and KP -All Fuel TypesFlow Dependent MCPR Limnits MCPR(F) -All" Fuel Types:, .!. ...: :Linear Heat Generation Rate Limits -UOz RodsLinear Heat Generation Rate Limits- (ladolinia RodsLHOR Single Loop Operation (SLO) Multiplier-All Fuel TypesPower ependnt LHR Muliplie 4HRA() lFe yePlowe Dependent LHGR Multiplier LHORFAC(P)- AIl Fuel TypesRod Block Monitor Setpolnts Reactor Coolant System Reclrculation Flow Upscale TriP :: iTurbine Bypass System-Response Time ...Minimum Required Bypass Valves To Maintain System Operability OPR" PBDFTFp-'pon. LOOPRM PBDA Trip Setpolnts Modes of Operation Page,.-810!112IIIIII12 I13 I'3 I14 I14 IIS I16 I17 I.IS I19 IPa~&4~of21~r' I Exelon Nuclear -Nuclear Fuels COLR Limerick i, Rev. 12 ICore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with.10 CFR 2.3901,0 Terms and Definitions ARTS APRM, RBM, and Technical Specification Improvement ProgramBASE A case analyzed with Turbine Bypass.System in service and Recirculation Pump-Trip in service and Feedwater Temperature Reduction allowed (FFWTR includesFWHOOS or final feedwater temperature reduction) and PLUOOS allowed at any-point during the cycle in Dual Loop mode.IDLO Dual Loop Operation DTSP Rod Block Monitor Downscale Trip SetpointEOOS Equipment out of ServiceEOR End of Rated, the cycle exposure at which reactor power is equal to rated thermal ,power with recirculation sy~stem flow equal to! a~ll control rdsfully ..,.!:. withdrawn, all feedwater heating in service and equilibrium Xenon.FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of ServiceHTSP Rod Block Monitor High Trip Setpoint]TSP Rod Block Monitor Intermnediate Trip SelpointKp Off-rated power dependent OLMCPR multiplier LHGR Linear Heat Generation RateLHGRFAC(F) ARTS LHGR thermal limit flow dependent multipliersI LHGRFAC(P) ARTS LHaR thermal limit power dependent multipliers "/LTSP Rod Block Monitor Low Trip SetpointMAPFAC(F) Off-rated flow dependent MAPLJ{GR multiplie~r MAPFAC(P) Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation RateMCPR Minimum Critical Power RatioMCPR(F) Off-rated flow dependent OLMCPR multiplier Page 5~of 21:.Main_ Steam Isolation Valve Out of ServiceOLMCPR .,. ;.~ ;,.Operating Limit Minimum Critical Power Ratio: OOS Out of ServiceOPRM Oscillation Power Range Monitor ....PBDA Period Based Detection Algorithm ..:PLUOOS Power Load Unbalance Out of Service -.;,..:. ...PROOS : :: -Pressure Regulator Out of, Service... ,.,,,:. ,.,RBM Rod Block MonitorRPTOOS ..-, Recirculation.Pump Trip Out of, ServiceRWE ~ ..... Rod.Withdrawal.Error...- ......TBVO..OS....,:: ...Traering Bynacore:Prob Out.of Service..... ......... TSV Turbine Stop ValverickI, Rev. 12 II-. C.. = Page. 6, of 2!, :i Exelon Nuclear -Nuclear Fuels COLR Limerick I, Rev. 12 I'Core Operating Limits Report .... .Non-Proprietary Information Submitted in Accordance with 10 CFR2.390 ...... ".,. "2.0 General Information

• This report provides the following cycle-specific paranmeter limits for Limerick Genera.ting Station Unit I Cycle16:* Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
• Minimum Critical Power Ratio (MCPR)" ..;... .. ....

,:* Off-rated OLMCPR adjustments (MCPR(P) or

• - Off-rated OLMCPR multipliers (Kp)" ..."-..-.:..

...

'* Off-rated LH-GR multipliers (LHGRFAC(P) or LHGRF/AC(F))"

.. -:"* Rod Block Monitor (RBM)

.,.. ..<,..::.i'.,"."

--,..:,:* M A P L H G R s i n g l e l o o p o p e r a t i o n m u l t i p l i e r , ." .: -" : .! : : .: : " " " : : ' ., .i " ; " ..- : ..., ...* LHGR single loop operation multiplier.. .',.;'..i .-".:" -: : ,:* Linear Heat Generation Rate (LHGR) .-... -,,. ..

"...,* Turbine Bypass Valve parameters

.* Reactor Coolant System RecirculationFlow Upscale Trips -.-" :..........,.:

.:..:,,......

• Oscillation Power Range Monitor Period Based Detection Algorithm (O.p RM PBDA) Trip Selpoints This report is prepared tn acordacewithTechnical Spec~ificaton 6.9.1-.9 of Referenc I, Preparation

.of. thisreport was performed in accordance with Exelon Fueis T&RM INF-AB-120-3600. The data presented in this report is valid for all lhcensed operating domians on'theoperating map, including: ': -.* Maximum Extended Load Line Limit down to 82.9%-of rated core flow'frhg.fill power operation

• Increased Core Flow (ICF) upto 1.10%of rated.core flow -.". .... ......* Final Feedwater'Teinperature Reduction (PP WTrIR)' ipt etension
• Feedwater Heater Out of Service (FWHOOS) up to 60.00F tem perature

.reduction at any time .during the cycle prior to cycle extension. .... -: -:"" -Further information on the cycle-specific analyses for Liuien~ck' - 16 and the "" ..."....": associated

"'domains discussed above is available in References 2,7T and 8. ...-I., ... ... ."'Page .7/ of 2,1-sil Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietazy Infonmation Submitted in Accordance with 10 CFR 2.390COLR Limerick I, Rev. 12 I3.0 MAPLHGR Limits3.1 Technical Specification Section 3.2.13.2 Description

• : -: +,: , : ';:The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of eachfuel type as afunction of average planar exposure is given, in Tables 3-1 and 3-2. For single loopoperation, a multiplier is used, which is' shown in Table 3-3. ,The~ power and flow dependent multipliers, for MAPLHGR hamve been removed and, replaced with. LHGRFAC(P) and ..,LHGRFAC(F);

therefore, MAPFAC(P) and~ MAPFAC(F). are equal 1to1.0 for all power and +* :: flow conditions (Reference 2). LHGRFAC(P) and LHCIRFAC(F) are addressed in Section 5.0.* Versus Average Planar Exposure -GEI4 ,; , .*.. *: ' ~(Refre nce2) ...::; ;i::,.., ._ , ". ../, *::+Average.IPlanar ++-+ ii+ W D /tb ) ..: : .' W ift)'i., +:., , 14.5I :+ ++ :' +++ +++: ++-" -+ .' "::;++:- 1' 9.1T3 '::', : ::'+: +"2.82 ( :*'++ .°,.:"" + :++:+' 57.6 1i++  ;+:" ". :?-++" :'8.00 ' -- + ... ".' + ++ ..++:+:+ '- 6 3 .50 .,. ,+ .+ ,, .,, r ..,.: ,; : :., ., 5 +.0 0 ,; ..++.. ...+ + , t.' : +.,. +,.+::,,++ .. !." +.'++... +,. : , ...., , ,.+" :" ..J" +. : ' +-+".. -...... ... .". '"+ " * ":. ..... '"+ .... ..i L .GR~er sus ve ragePla nar~xp osnie -GGN N] 2(Re .. ,,: ? ",, " :+ ++'; " ;+ ; '+' ' , '+, ; :S +: ++ : : ,: " "+ +' : '++'"er e"nc e 2 ) 0- .0'+" ++ : ++ '. ? +- , ' +++++;++ + :+ :+++']";+' + "+ ++:'+: '+kW ia+.+` .... :+:U:"ll-- -i .. .. ,+t+ + , ..... .i ...... T -"i ... .'5 ......... f " "'" +'+0.00 "" , ......... " "+ i3.'/S!3.24 13.7817.52 13.7860.78 7.5063.50 6.69Table 3-3MAPLHGR Single Loop Operatioa (SILO) Mullipller-All Fuel Types(Reference 2)i i il1 .i iult er 0.80.+ ..i i i ...i* Page 8+of 2+!jI Exelon Nuclear -Nuclear Fuels COLR Limerick I, Re,. 12Core Operating Limits Report -"Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 ....4,0 MCPR Lim~its4.1 Technical Specification ,Section 3.2.34.2 D escription "' *.. ....:.. .. .. ........ ... ... -. .*.Tables 4-I and' 4-2. are. derived 1ram References 2,.7, and-8,and are validf'o~r allICycle 16 operating I*.domains. Table 4-1 is valid fbrGEl4 fuel andTable 4-2 Is valid fbrGNF2.flieL-Tables:4-1 and 4-2-:,include tr'eatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. SLimerick Unit i.Cycle 16 has amid-cycle MCPR breakpoint, defined in Tables 4- land 4-2. The'.BASE, TBVoOS,: and...RPTOOS.MCPR limits i`.nclude the conervtve;'ssmptin of-slmultaneous--TCV and TSV :clos~ure durinig ad, turbine trip,"as discussed in .Reference

7. Lessrestrictive MCPR.limits.

for the BASE DLO. Option B condition are .provided for a 100 ms orgreater delay in the start of TCV closure' following a turbine trip. The less restrictive limits mayonly be used if it is that. the. 100oms.oro gratr delay existsfb11owing Digital EHCm odification. '.:-' .. ...... , ,.. .. ." ..- ... ..-ARTS provi-des or~pow`:e..ran.llow depnent thermalli~mit ~muti~tpliers, whichallow for a more reliable-administaton of,-.the.Mcp.R

limit. Theoflolw dependent adjustment MCPR(F) is.iufficienftlyi generic to:apply to a~ll--el.t-pes and-operai~ng domains.The power dependent adjustmetMCPR(P) is indepedent of ~lc1iloi0 p-wu iii)ip operability.

MCPR(p).and of Option.>Iii"additlon, thre ar ten sets ofpower dependent MCPR multipieri"(K.p) for wwit lf~ tiBASE,TBV.OOS,7RPT.O.OS, PROOS,DLO and SLO""conditions, and PROOS-'.TBVOOS; PROOSRPTOOS, DLI.(, only. ThePLUJOOS -conditionls-islncludfedln"the BASE MCPR(P)" and' MCPlR(F) limnits anid Kp multipliers and is hounded by the TBVOOS limits and multipliem therefore, no additional adjustments arerequired for PLUOOS in those operating conditions. The PLUOOS condition, has not beenanalyzed concurrent ~with-the ,RPT S.ciperig.'nio.Oe lon ithe PLUOOS condition concurrent with the RPTOOS oiidti rn core thernal power < 55% of rated (Reference 3).Section 7.0 contains the conditions for Turinie Bypass Valve Operability. MCPR(P) andMCPR(F) adjustments .Tables 4-3 and..4-4: The°OLMCPR~is.detenmined for agiven power and flOownditi~on" by evaluating the pi~owr .deen~enit"MCPR and the flowdependent-MC-PR and selecting the greater of the two ..... .,,,,,,...........

• " .S .~ ':: * -, -". " .--S. -.' :. .Pagofvt Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390COLR Limerick I, Rev. 12 ITable 4-IOperating Limit Minimumm Critical Power Ratio (OLMCPR)

-GE14fReferences 2.,7. "nd.*'1'*,'/'.;':.'i+:.; "";:. :. ,,:-: =: YI" :?,",* :: :. f: .:- SCRAM TIme <EOR -3234 >_ EOR -32.34EOOS Combination Option' *MWd/ST, .' B 1.39 1.41BASE B2 1"38-' 1"412_-,.-___+__-__,.,-_,_____, ...... A 1.47 1.494... " ..B 1. " !46 .1,46.J'.BASESLO4 .. ". ..' " +___...._____ A .1.50 .+. ..B... .. .. .. B -.; 1.46 ' IA4 ""I,:I A " 15, I 4 ! ':- ,' ..... .. _____;__ 1 , I.42'2': >"1".53 S....RPTOOS,-......': + A,________ .-_____ A 1.59 1. ]70 ..*RT SSO" -B -: 1.46 1! .56__". _______ ,_ A 1'.62 1°. .. ..I73 ... .... ....B .1.39: 1.4I 3* +.A ...,. 1.47 .+ .-1.55"KPROOSS' +LO4-* B l +.146, c+ .i..+i1.46 ____________' +" :+:++ A ..'" 1 l.S0O: + ' :i 1 ... .58SL', ROOS8.,+TBVOOS .. +:,.,B. ; .I ,.I4 .'-,..:+ 1 r.44. PROO RPTO S .. -B 1.. ;..142 1f > .. .+:.::. *,* f '. ;"?IIi +, ; :,..... .. ..+, .I'iWhen Tanl does rnot equal 0 or I, determinie OLMCPR via l!ineat iterdlation.; For and

.-' 9i .-,

2lLimit is only applicable if it is confirmed that a too ms or greater delay exists in the startof, TCV closure:3!Value ls, adjusted~to'obtait

+n'O-R ~ liu + oi+ftl 121+'-'i 4Por sigle.loop~operatfiOte;MCPR~operatinig'hmiiis thie analyzd two~loop value.** ,However, a fuel tdtS&,i~bVGNF2! fuel is ctird to obizi ": ..OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).Ii Exelon Nuclear -Nuclear Fuels COLR LimeCore Operating Limits ReportNon-Poprietary Information Submitted In Accordance with 10 CFR2.390* "Table 4-2Operating Limit Minimum Critical Power Ratio (OLMCPR) -GNFl~Referencesq

2. 7. and 81:rick1, Rev.l12.. .... .Cycle Exposure

,.. .. +- .SCRAM Time <EOR -3234 _> EOR -3234EOOS Combination "+Option' MV/I/ST 1 .39 : 1.41 _B2 1* :!382'3 i...1.41z .____ ....._____ .._ A 1.47 1.4. I 9i BASE SLO4 1.-_ .:. .58_ . ..+, ? T '+++(O ` +. , -.:-' B !...* :,1.42 1... 444-TBVOOS .' A 1 j.+.51 !....+1.53 .'TBs VOO S-LO B ..i ,1.58..: 1....- 58:LS.+,: ... ....s -1.58 1.. ' 18 ? ;+'RPTOOSSLO B: 1.581.5A 1: .62' 1+ ;i'.73 ,B, 1. ii39_ ,1.!. ..PR O O S + -.." " .. .... .....'... ..__ _ _ _ .:._._ A +,1.: ; ... 5 .47. + 1.+..+ 55+ .. ..,; ""+ + + ,-? + B +I. .. .!.. 1.58 __ 1-,+.J 58, , -.+ PR OS:SLO t..... 4 ++ A +, , .1.58, ,1.+," I58+, +. ,+PROOS+TBVOOS B.... 1.42+ '>PROOS+P, PTOOS B 1.42,+," I,42--I: .ii .:+. i,r.-III' When Tan does not equal 0 or 1, determine OLMCPR via linear interpolation.,+ Por-PROOS+TBVOOS ......2Limit is only applicable if it is confirmed that a I00 mas or greater delay'+exists the +estarttof WTCV.-lo~surie+ ,' Value is adjusted to obtain an OPRM setpoint of 1. 12. +;,+++ :+ : 4For single-loop operation, the MCPR opem ting iuititos 0.03 gre. ter~thapiNhe al~yz~dt~wo loop However,. a mini+ mu~m val u~e~pf.l,6 o fo,++ !A~~ 0E44..e and

required, an OLMCPR limit set ,by~the .Shgle +Loop Oper.tion Recirettlation Pump Seizure Event(Reference 2). z, Page l+ I of, 21K'-I E~xelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with !0 CFR2.390COLR Limerick 1, Rev. 12 ITable 4-3Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp -All Fuel Types............

(References 2, 7, and 8) ... ..: !. LCorei ,.. -+. -"+Core Thermal Power (% of Rated) , ."... .. ,"OO Cobntin ow 0..o.]. 25:* ,"<30.*. >30,. 65s 85. 100s+ o£OO~om~naiof '(,%t ....f... Operating Linilti' -....,Operating Limit MCPR,: .... " ."rated) ....MCPR, M CPRIP M....... .l.ultiplier,..Kp ....-'!]. li BA;SESLO!ii :'27'8 ' ;,'2.78:'235+[... +:+2:;3: .58!* "i'I"140. .":Ll;;3 1 .:: :,I067. 1:, .000* .* T VOO ""::' -'+":: 60 3;"i".25 " 3:25 2.75 ~"]I: 'i I16 : 0TBV O O)S. 3.75, , "375 -"': ; 1 .340 1.131 1,.067.....

• '-3.28S .8' 27ATBVOSSL

---

i.34 1.11' .o67 1.000-?, 3.78 3.78' .3.28 .--

,: ! -.: ,.,:,...+. < 02: 75 -.25. -- --RPTO S SL ....,, -. '. .. .0_. +,+2.5375 .2.3. ,~ 1 .06 .000.Flow D60 u-2.7 2MC 7R L 2.58 -s -ul e...~~~. 2tem +.50 +.2A0. ,") }6-_____________ 4Flow.* ..I I ... . 9,,?, "++,..: +.1!.............................I..+4~4 ~*~~jf4A' ~00* , + + ,L'70-30.0 '.1.53-' ',. 3. .. .- ; .-. ,,p.79.0 _________ -, A,.. ' + L _.+ ...* .,,.. ..... ..+. .a ....... ...... ' ..¶ 4,r, 1fl.- -. :'9A..,,,,¶ +-- .A'e4.. U.h¶'2Ffl .tX44',. ....,, +;+ 4 ,, V.+ ',+ ,+ ., , + , ..S. , , , +,f.e'tt ¶ , 'zn(4. f ..+. ..A5%+ , .H .W.44.¶ V.-.+ , + .+et. + ., .. .Pago~2~I Exelon Nuclear -Nuclear Fuels COLR Limerick 1, Rev. 12 ICore Operating Limits Report..."' "Non-Proprietary Inlormation Submitted in Accordance with 10 CFR 2.390 -5.0 LHGR Limits -'..5.1 Technical Specification

5.2 Description v ., :. " : ..i ' .' " '..SThe LHGR :limit?.is the product of the expour dependent LHGR limit (fro~m Table 5-1tfor U02Sfuel rods and. Table 5-2 for Gadolinia

.fuel rods) and the- minimum otf the power dependent LHGR...Factor, LHGRFAC(P), ,and dhe flow-dependent Factor, LI-GRFAC(F). For single loopo i peration,,amniltipller, is used. ;which. is shown ,In Table 5-3 arnd applied in Table .furtherSSingle Loop Operating multipliers need -to be appilied to the jvalues in Tables 5-4 and 5-5 .....::;.ARTS provides .for poer- and flow dependent thermal limit multipliers, which itliow for a more* .:reliable, administration of the LHOR' thermal li~imits- .There are two sets ;of flow, dpendent.... multipliers for dual-loopand operatio Indditiotere are ten sets of Idependent: LHGR multiPliers for.use -wihhe .BASE,-TBVoOS, RPOS, PROOS,I..DLO and SLO-.conditions,,~and PROOS+TBVOOS and pRoOs+RFiOOS, DLO ,only.:,The .,.PLUOOS condition is included in the -BASE LHGRFAC(P) and LHGRFAC(F) multipliers land'"is bounded by the TavoOs mulltiplii.ers;th.erefore, .o additional a~djr~tmn~nts are r..quired fori;PLUOO0S in 'those ?operating

conditions.

"Thte PL UOOS .cond~ition' has not bheen .analyzed '.concurrent the" RPTOOS opeat~ing ~condit;ionl

Op rtion; ,in the PLOOS' condition S. concurrent with~ the. RPTOOS condition requires

.e of. rated (Reference '?3). 7.0 contaihs the conditionsfor :....fuel types,. Linear interpolation'should:6 Iited ii Appendix A. ...... ..--the power and' flow biased caelctioatihn.The LHGRFAgC(P) crvs reindcenderi*of pump trip operability, .. .......... " nea ... ... ,,u~ato ,,,t Liit .Ut2.ot. -.... .'T~~pe LHGR , .GElj i .-," A':S !ppendix A* .GN '2' " :..:'. ,1 Appendix AILimear Heat Geaeaii Rods--(Referencee ) ...*,ruelTyp S.I 0E1-" "~GNF-2 '-" A, I -"SeeA rpp dix A:,- .Pajel36f: Exelon Nuclear -Nuclear FuelsCare Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390COLR Limerick 1, Rev. 12ITable 5-3LHGR Single Loop Operation (SLO)) Multiplier.- All Fuel Types(Reference 2)SL Mi plier' 0.8* ._. .. .. -- , ...... ... ': : .: T able 5-4 ..... .... , .. .-..-:,;:.. ..iPower Dependent L~HGR Multiplier LH:GRFAC(P) -AUl FUel Ty.pes. i... ..... .... .. .* ...(Referen es2a d ),rPEOOS Combination, Core.Flowofratedfl-:: ' -Core ThermuaI.Power (% of rated).*0 1 2511<~30t >3o1 65 I 88 I l00I I --f -- ----I -I'--- I -- .,:-,... =j ... "- -...-BASE ~ 600.48 0.85' 0.400750 -0.922. 1.000" " ... .... " >60 0.434 0.473 .. .- BASE ,.. i.,., :, 60 0.485 0.485; 0.490 b070 , 1.0BASE SLO- __._,__ ">600, 0.434 0;434 0.473 0.5 '.87: 092 .0.. ... .. : 60 0.463 i0.463' 0490 , 't ' ..TBVOOS' ' >60:0.3520.:0352 0.3'86 ,,0.750 0.8 17, !0,922 ..TBVOOSSL0- "$00. 0.463 0.490 0.7.0.0.81..2 .000..... >60 0.352' 0.352 '0.386 -i1 -.2 -." : -<60 10.485 0.485 0.490R'.. P,'OO(XS

.' .60" 04,34. 0.434. 0.473 0.5 .1 0.92 RPTOOS SLO -

6 0.48'5 10.485 0.490i .5 .1 .2 .0.. '... ., * ->60 0.434 0.434. 0.473 -_ .. ....* :pROoS, ..., '<60, 0.485 0.485 0.490 -......______ > 60 0.434 0.434 0.473 i'0.750

.0.922 1.000)PROOS SLO "<60, 0.485 0.485, 0.490 0.750 0.8 17 0.922 1.000_________> 60 0,434 0.434 0.473PROOS+TBVOOS' j;'60, 0.463. 0;463 0.490 0.7i50 0.922 1.000______________>60 0,352 0~32 0.386 ---PRO+PTO- <60 0.485 10.485 0.4900,0 081 0.2 !00PROOS+___T_______ >:60 0.434 0.434 0.4730.5 087 092 1.0.. ...... ...................... .. ., ..................... ...., ' ................

• ,, -,,. .:.' Applied through Table 5-5PugeJ4.of~2I,;~

'. Exelon Nuclear -Nuclear Fuels COLR Limerick l, Rev. +12Core Operating Limits ReportNon-Proprietary Information Sub mitted in Accordance with 10 CFR 2.390Table 5-5Flow Dependent LHGR Multiplier LHGRFAC(F) -All Fuel Types(Reference 2)' -~~Core Flow (% Or rated) .....EOOS Combination 0 30 44.1 70 *80 110.:.U....LHGRFAC(F) Multiplier ..":Dual Loop' .506 : '0.706' " 0.973 j 1.4000: 1.000single L~oop 0.506 0 .706 0..... 00O 0 .800"-. .' ... A*.*,." ' , " *L ' ' ' ! ' ' "" : ' ." .. .' "..... + " ii "+: :"" , ii; : ' :, "'of'" 2: 1.. .:.ii , :' Exelon Nuclear FuelsCore Operating Limits ReportNan-Proprietary Information Submitted in Accordance with 10 CFR 2.3906.0 Control Rod Block Setpoints 6.1 Technical Specification

• ,". ...Sectio)ns 3.1.4.3 and ...*.. ...,6.2" DescriptiOn

, ,!COLR Limerick !, Rev. 12...-... The ARTS Rod Block Monitor provides-- for power dependent RBM trips. Technical Specification 3 :.::3.36. states: control irod block instrumentation channels be. OPERABLE with their trip,.. .setpoints consistent with the values shown in the Trip Setpoint column of Technical SpecificationLTable 3.3.6-2.. The trip .setPointslallowablelyalues and applicable R BM signal. filter time constantdata are shown in Table 6-I. The Reactor Coolant System Recirculation Flow Upscale Trip isshown in Table 6-2. These selpoints are set high enough to allow ful utilization of the enhancedICF domain up to 110% of rated core ../ .Table 6-1....... ................ Rod Block M onitor Setpoinls' ...a.Power Level I Analytical I' Aliowuble I Nominal TrIplimit [ Value. SelpolatLTSPi23.o0%121.5%1 ______________ ..-.. 9* j :"ITSP' ... ... ... ;" .'-71

i6.5%A

HTSP 113.2% .!. !1i.7% !1! .0%.,Tsp, No L 2.0% .__,, ___.,0 __

(Z~at Rc. ai~ou, Fltow U, cle Trip..:... { : (ReI~encee4) -:-- 'Analyticl Limit N/A.Allowable Value I 15.6%...Nominal Trip Setpoint ...113.4%t These setpoints (with Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds) arebased on a cycle-specific rated RWE MCPR limit of 1.37, which is less than the minimum cycle OLMCPR. of2 I ,,, Exelon Nuclear -Nuclear Fuels COLR Limerick I, Rev. 12 ICore Operating Limits Report_Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 '""7.0 Turbine Bypass Valve Parameters 7.1 Teclmical Specification"".,':" "Sections 3.7.8 and 4.7.S.c. ,. -....7.2 De~scription , ' ' ." :,,'.,.,The operability requirements for the ste~znbypass system are found in: Tables"7-I !and. 7-2. if theseS,.requirements cannot be~met .the MCPR,.MCPR(P) and LHGRFAC(P) limits for inoperable Steam-.r .Bypass System,. known as Turbine ByPass ,Valves Out: Of .Service (TB VOOS), be used. I.,..-",Additional information onthe operability of the turbine bypass-system can be found ,in Ref rence 6.Turbine Bypass System Relisponse Time;- " :.(Reference 3)'Maximum delay time be.t0.re .start o~f valv .' *: ...... 0.1 I e .....following initial turbine inlet valve movement 'Maximum time slier initial lturbine inlet valve movement1 for ' ., -,bypass valve position to reah 80% of thel: ;.-;,-o.7.-.

--::0.31

-sec;: .Saboved e~lay lini.) ". "" I -< ,... First movement of ay TS, g~r any TCV gj;generton ofrthe tubine bypas valve.flow signal (whichever occu s frs) ,. , , , .+ , -. ,, 1 ... * , .. ,,+, Minimum _ Requiredlt.,ypass..Valves To Operabihity-+. Reo1~wr jo. oyIein ~ i ce I.. .P.,,'L2S% 7 , .... .....Rmemriower+.i. .." + : Pagd I7o?21<~I Exelon Nuclear -Nuclear Fuels COLR Limerick i, Rev. 12. [Core Operating Limits Report ,Non-Proprietary Information Submitted in Accordance with 10 CFR 2.3908.0 Stability Protection Setpoints ., .8.1 Technical Specification +,, .Section 2.2.1+ i 8.2 + Description

• ......-,,

, :+.: .The Limerick Un~it. I Cycle :16 OPRM PBDA Trip Setpolnts for the OPRM System are found in.:., Table 8-1. These values are based on +the +cycle s pec+ific analysis documented in. Reference

2. The:,.:,setpoints provided in.Tabl.e 8-1 are bounding for all modes of operation shown in Table 9-1. The provided in :Table 8-2 are acceptable for use in Single Loop Operaton.

The standard twoloop operation OPRM Setpointls specified in Table 8-1 must be implemented prior to restarting theidle pump whedn exitinig:teSLO condition.- , .. ..i/..++; ........ .... .. ........... .... T ab le 8-1 ..+ ,.... ...: .+:,: .=- ... ..i ...... ..... .. .:): :- -*OPIM PBDA +Trip S lit eln s ......: " -+..;: + ....PBD Tr~ip Amplitude" I +++...... ++-Co :~idng+.=., ax 1+:++ ::i+* --+ ..+ .... ...* .... -'F++' 14 , -" ..++ ". ... ..*-=1 : -++ 4 "+ ' 1 +': + ,* +*. ",U ,++ ..k............................ ,..+ .B T i ~ ...:..I, Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Prprietary Information Submitted in Accordance with 10 CFR 2.390COLR Limerick I, Rev'. 12 ]'9.0 Modes of Operation 9.lI Description The allowable modes of operation are found in Table 9-1. Operation with I MSIVOOS, or I.TCV/TSV 00S is supported in all modes of operation, provided the restri'ctions identified in theapplicable station procedures are met. All BOOS options also support the allowance of I TIPOOS. I-:,.:-:i: Table,9-1 / :-/ i / !r,. :.. ."Modes of Operation : :": "? :..::~,.(Refe rence lnd ) ..I':..',BoosOpons0 ...O : peratn! e Ine'!BASE, Option Aor B ' :.. ./,., .. .. ': Yes2:.. : .-BASE SLO. Option A or B .... 2:! ',TBV..OOS, Option A or B .... ..... .... 2 ...TB VOOS SLO, option A or B. :"-.,- ........ , Yes2' ..RPTOOS, Option A or B. --. Yes3 " .RPTOOS SLO.Optioh, or B ____.........____...............____..... _........ TBVOOS andl RPTOOSSL OOption A or B -..... =......... 'No -' ............... TBPR e PTOSSL, Option,. r ................... A o B.... .....- No..... Y e,:.-........... PROOS S.LO, Option A or B ..... .Yes2PROOS+TBVOOS, Option A ...No*PROOS+TBVOOS, Option ' .... Yes2.PROOS+TBVOOS SLO, Olption or B..', -.No ""PROOS+RPTOOS, Option,,A PROOS+RPTOOS,.Option B. ..- -........... .... .: .... ...... ,Yes-............:.. -.I, ,~~.:.. ...z, , ~...;ys:,,4 -4..n .-. ., .:. ' Operating Region refers to operation on the Power to Flow map with or without FFWTR/FWHOOS. 2The PLUOOS condition is supported in this mode of operation with no power reduction required. Th PLUOOS condition requires core thermal power level < 55% of rated (Reference 3). Exelon Nuclear -Nuclear Fuels COLR Limerick 1, Rev. 12 *ICore Operating Limits ReportNon-Proprietery Information Submitted in Accordance with 10 CFR 2.390...., 10.0 Methodology .The analytical methods used to determine the core operating limits shall be those previously reviewed andapproved by the NRC, specifically those described in the following documents: I.: "General Electric Standard

Application for Reactor Fuel1" NEDE-2401 l-P-A-21, May 2015 and U.S. ISupplement May 2015. -.. .... ..... .... ...2. "Reactor Stability Detect and Suppress Solutions

.Licensing:.. Basis Methodology for ReloadApplications," NEDO-32465.A, August 1996.1 1.0 R eferences ... ........ .... .. .... ..... ..... ......... ... .... ..... .. ... ..... .I.. "Technical Specificat.ionsoand Bases. tbr Limerick Generating Station.Unit I!", Docket No- 50-352, LicenseNo. NPF-39, Exelon Document.

• . *.; .......' ..2.1 "Supplemental Reloadl LIc:ensing fbr Limerick 1 Reloadl 15 Cycle i16", Global Nuclear Fuel -Document Revision l,iFebrm 2014 .... ;-.';..:,

.... ,',3.' "FInal Resolved OPL-3 Parameters for Limerick Unit I CyCle 1",EeoT lE5301Rv., Octobr23,2013

4. "G3E NUMAC PRNM Setpolnt Study",F.Exelon Dndgn Analys-s LE-O 107, Rev. 2, Februar 23,12012.

5. Fuelj~ Bundle Information Report for L.imerick I Reload-15Cycle 16.";Global Nuclear/Fuel Document No.0 00N5028-FBIR-P, Revision 1, February 2014. -......:,- "- ,. .."6. "Tech Eval. Stop Valve Load-Limit Documentation",

Exelon D;cuent 'IR 917231 Assignment 7,November11,-2009. ...... ......- -" .: , :'. ": ':7. "Limerick Unit i Cycle 16 Contingency FWCF Analysis", GE Hitachi Nuclear Energy Document No.000N5273-R0, March 10, 2014.8. "Limerick Generating Station (LGS) Units I and 2 TRACG Cycle-Independent PROOS Analysis Report", IGE Hitachi Nuclear Energy Docwuent No. 002N4397, Rev. 0, February 24, 2015.I, ~~~~~~~~~~~. ..... ....... .! .' .-.:., .,.,. .... .. .Page-20 of2lI Exelon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Information Submitted in Accordance with 10 CFR 2.390Appendix A(36 pages)COLR Limerick I, Rev. 12 I".:. :.:' :,. ' :? : : : :. ":

• ;.:i',' ......i..: .... * ,-.;.

il :'

..... ;. ....

....-. !. Page21of21~ i Exclan Nuclear -Nuc~lear FuelsCorc Operating Limits ReportNwn-l'ropriclmry lnlbrmntion Submitted in Accordance with 10 CFR 2.390COIR Limerick I Rev. 12 Appendix AGlobal Nuclear FuelJ Vomn.l Of & tahGlobal Nuclear Fuel000N5028-FBIR-NP Revision IFebruary 2014" .... ", Non-Proprietaiy Information -Class l (Public)Fuel Bundle I[aformation ReportforReload 15 Cycle 16Copyright 2014 Global Nuclear Fuel -Americas, LLCAll Rights Reserved 1!.'thn Nuclear -Nuclear Furls,,Core Opemlins Limits RerortNon-Proprietary Information Submilttd in Accordance with 10 CFRI 2.390 COIR Urnanckc I Rev. 12 Appendix ALimerick Unit I Non-Proprietary Information 000N5028-FBIR.-NP,. .Re~load 15 Class i (Public) Revision !Important Notice Regarding Contents of This ReportPlease Read Carefully This report was. prepared by GlObal Nuclear Fuel -'Americas, LLC (GNF-A) solely for use by-EXelon Corporation in support of the operating license for Limerick ,Unit 1 (the "Nuclear Plant").The information contained in this report (the "Information") is believed by tobe an accurate andtrue representation of the 'facts known by, Obtained by or provided to GNF-A ait the time this report-was: prepared.. The only, undertakings of GNF-A .respecting the Information are contained in the contract betweenRecipient and GNF-A for nuclear fuel and related services for the Nluclear Plant (the "Fuel Cont~tct") andnothing contained in this document shall be construed as amending or modify'ing the F~uel Contract. The:use of the Information for any purpose other than that for which it wasintended uinder the Fuel contract, is not authorized by ONF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any-representation or warranty (either expressed or implied) as to the completeness,

accuracy, or useftulness ofthe information or that such unauthorized use may, not infringe privately owned rights, nor (b) assumesany responsibility for .liability or damage of any kind which may result from such use of suchinformation.

Information NoticeThis is a non-proprietary version of the document 000N5028-FBIR-P, Revision 1, which has theproprietary information removed. Portions of the document that have been removed are indicated by, anopen and closed bracket as shown here [[ 3).Page 2 E'wlon NUCILar -Nutclear IFuelsCore Operating Limits ReportNon-Proprietumy lnlbrmation Submitted in Accordance with I0 CFR 2.390Limerick Ulnit I .... Non-Proprietary Information Relnud ' I COLR Llmerick I Rev. 12 Apperndix A000N5028-FBI R-NPRevision I: 1 l.Introduction and SummaryThis report, which supplements the Supplemental Reload Licensing Report, contains thermal-mechanical linear heat generation rate (LHGR) limits for the GNF-A fuel designs to be loaded into Limerick I forCycle 16. These LHGR limits are obtained from thermal-mechanical considerations only. ApprovedGN F-A calculation models documented in Reference I were u~sed in performing this, analysis. LHGR l imits asa function' of exposure each bundle of the cor'e design are given in, Appendix A. The "LHGR values provided in A.pp~endix A p'rovide upper and, lower exposure dependent LHGR boundaries which envelope the actual gadolinia dependent I-fOR.limits. LHGRs reportedh~ave been rounded to:two places past the decimal.Appendix B contains a desc.ription of the fuel bundles. Table" B-I contains a Summaryof bundle-specific information, and. the figures provide the enric'hm ent distrbution and gadoliniumi distribution for the fuelbundles included, in this appendix. "These bundles have been approved f'or use unKder the fuele licensing acceptance criteria of Reference ...I., -. ..".. .:. , ... "'. ..,*' i ':.L .... ." ". , ..':... " " : ,' ...) ' ,Page 3 Exdon Nuclear -Nuclear FuelsCore Operating Limits ReportNon-Proprietary Inlbnnahicn Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Re'load IS Class I COLR Umenck 1 Rev. 12 Appendix A000N502S-FBIR-NP Revision 1............... 1 ...... ( ...........

2. References

1. General Electric Standard Application for Reactor Fuel, NEDE-240l1I-P-A-20, December 201!3; andthe U.S. Supplement, NEDE-2401 I-P-A-20-US, December 2013.v ....... ' .. .. .... .-.L. ..... .: ...... ...!.. -4.:.0 *

...... .: " ., ..... ... .. * , .. .... ' .-.... .. ... .. ..... ..J:' i3/4..-4

• Nuclear.-

Nuclear FuelsCore Operating Limits ReportNnn-Proprictary Inloinution Submiiled rn Accordance with 10 CFK 2,390Limerick Unit I Non-Proprietary Information Relnnd 15 fllsqs I COLR Uimerick I Rev. 12 Appendix A000N5028-FBIR.-NP Revision IAppendix AUO2IGd Thermal-Mechanical LHGR Limits-, ..,' ' .' " , * .Bundle Type: GEl4-PI OCNAB394-15GZ- 120T- 150-T6-3271 (GE 14C)Bundle Number: 3271Peak Pellet Exposure! Uoa LHGR GW~dIMT (GWdIST ... kW/f ;[[ ... ...._ _ _ _ _ _ _ _ _ _ _ _IPek-Peflet Expsuei~",,. ..... M~ost Limating. Gadolina ..._______ -._._. __ ... H GR, Lli itt: .' ;.GwdiMTr (GWd/ST) i kwln ft11Bounding Ia <bund*le desig~n5 Excinn Niiclenr. Nuclcor FuelsCore Operuting Limits ReportNon-Proprietary Inlanmation Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload ! 5 I (Public'1 COLR LUmenck I Rev. 12 Appendix A000N5028-FBIR-NP Revi~inn II f .........

• UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GE I 4-Pi O CNAB4O 1- 1,3 GZ- 1 20T-i 50-T6-3273 (GE i 4C).'. .Bundle Number: 3273Peak Pellet Ezposure UOa LHGR Utmit ,Peak Pellet Exposure

...Limiting Gadofluia _ _ ............... .... .: ..... .H G R *Lim it1z.. ..GWd/MT (GWdl/ST,): kW/ft-[ i -..... ...... ..""*____________________ 11J?2" Bounding na:H :'* 6 Exelon Nuclear-Nuclear FuelsCore Operating Lignits ReportNon.ProprietniyInrormation Subrnittcd in Accordance will, l0 CFR 2.390Limerick Unit I Non-Proprietary Information Reloand I15 Classq I (PuhilciCOLR Limerick I Rev. 12 Appendix A000N5028-FBIR-NP Revision !............... Z ...... r ........... UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GE 14-P I 0CNAB402-1I3GZ-1 20T- 1 50-T6-3274 (GEl 4C) ..Bundle Number: 3274 -"Peak Pellet' Exposure

.,, , U02,LHGR Limit,-,,

GWd/MT (GWd/ST) " , kW/R :::.,t .Peak ,Most Limiting GadolinieaLHGR Limit 3G:wdIM (GWd/ST) i '%kW/:.,If.t

.riSBounding.

.

LI-IG.R-limit:, fori all this,. bundle .design.[[ ]1I. =Page 7 Exelon Nuclear-Nuclear IFuelsCore Operating Limits ReportNsin-I'Prieopdry Informationl Submitted an Accordanece with 10 CFR 2.390Limerick Unit 1 Non-Proprietary [nformation Reload I5 Class I (Public)COLR Umedick 1 Rev. 12 Appendix A000N5028-FBIR-NP Revkinin IUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GEI14-P IOCNAB398-12GZ- I20T-1I50-T6-3275 (GElI4C) '.. -' -. -..Bundle Number: 3275.' ,.:.,-,, -,,Peak Pellet' Exposure" U02 LUGR Limit...., GWd/MT (GWdIST) ! "kWlf/ :,.':-R[1[Peik 'Pellet E xposure,

.Most

, ,-....o." ...... LHGR i~mit4::GWdIMT(GWdlST][)_ .., , : ,::

'....rr ,...._________________

I]SBounding LKGR-iinzit:, Jr.-t.Mllgadolinium this v!bund~le [[ I]. i -",., .:!:Page 8 FE'clon Nulcle'ar-Nucicur FuelsCase Op-'ul~nW Limits ReportNonnPropricimy Inl'onntion Submiued in Accordance with tO CFR 2,190Limerick Unit.!" Non-Proprietary Information Reload 1S Claq.q ! COIR Umedck I Rev. 12 Appendix A000NS02S-FBIR-NP Revision 1UO2IGd.Thermal-Mechanical LHGR Limits ",Bundle Type; GE 14-P 10CNAB394-15GZ-120T- 150-T6-3272 (GEI14C)

,, .7' .Bundle Number: 3272 **Peak Peliet U02 LHGR Lmit ....G;Wd/MT (GWd/Sr) kW/ft ,; .[[ .., ,_ _ __ _ I ]. 1 *Peak P*t Exposure4 Most Limiting Gadolinla LHGR Limit'GWdIMT (GWdIST~

k~V~ft ....[r-Y________________________ n~.Bouig ..89n LHR, oa adlnuicncnminocuun i thu ,udl.esgPage 9 Exeton Nuclear -Nucetar FuelsCore Operating Limnils ReportNon-I'roprietiuy Informiation Submiued in Accordance with [0 CFR 2.3903Limerick Unit I Non-Proprietary Information Relnnd I 5 I COLR Llmertel 1 Rev. 12 Appendix A000N5O28-FBIR-NP .. ... .....Revision iUO21Gd Thermal-Mechanical LHGR Limits 'Bundle Type: GNF2-P I0CG2B393-1I0G7.012G6.0-1 20T2-,I150-T6,404 '(GNF2) K :(';'Bundle Number: 4048 !,.'!Peak Pellet Exposure/" .UO2 GWd/MTF (GWd/S)..... " kW/ft ':!i(...: i [........... ..... .... .. .~ .. .....! ...! .................. ............ ...LIH G R Lim it .. ........ ,. .... i ;i-,,.[ ..........................................,)6 LHGR~ limi for"

• ocnrun~eun-n h, bundle 4..... g n:: (-Page '10 E~xelon Nucleer -Nucleur FuelsCore Operating Limits ReportNon.Proprietary Inarmanninn Submitied in Accordance with 10 CFR 2.390Limerick Unit I1 N.. , on-Proprietary information Reload 15 Class ! (Public)COLR Umernck t Rev. 12 .Appendix A000N502g-FBIR-NP Revision IUO2IGd Thermal-Mechanical LHGR LimitsBundle Type: GNF2:PIOCG2B404-I206.0-100T2-150-T6-404.4,.

, ... ..(GNF2),,, .,: .i, :. ,Bundle Number: 4044 ....,.....,, ....-Peak Pellet.Exposure., .U02, LHGR Limit.,,GWdlMT (GWd/ST)" -" :kW/~ft.!.::,ii.: _______________ 1]Bou( in ]d1. .,G:lt~ n.~p~rig ttisbn~ desiPage !II Exelon Nuclear -Nuclear FuelsCorn Opcruling Limits ReportNnn-t'roprictnry lnlormation Submaited in Accordance with 10 CFR 2,390Limerick Unit 1 Non-Proprietary Information Reload 15 Class ! fPubliclCOLR Umerlck 1 Rev. 12 Appendix A000N5028-FBIR.-NP Revision !UO2IGd Thermal-Mechanical LHGR Limits .Budle Type GN2P IOCG2B404-12G6.- 120T2-I0T634 (GNP2)Bundle Number: 3643 ! - Peak Pellet UJOZ LHlGR LimitGWOIMT.(GWdI.S.T- -kW/ft,:: Ii___________________ Peak Pe~et Exposure."

.Mo.st Limiting.Gadolinla:

__________________2 LH /Lift =sBounding gahdlinia

ailadolhnim concentrations

'ocur khis` bun~dle ;design.: [[E.l; )Page 12 Exclon Nuclear -Nuclear FuelsCare Oporuting Limits ReportNun-Prrpritlory Intbrmution Submittcd in Accordance with I0 CFR 2-390Limerick Unit I Non-Proprietary Information Relnnd 15 ., Class I COLR Umedlck 1 Rev. 12 Appendix A000N5028-FBI R-NPRevision i....... ....... ........ I ...... iUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P ! 0CG2B3 87-I SGZ- 1 20T2-I150-T6-4045 (GNF'2).' ' .Bundle Number: 4045Peak Pellet Exposure- .U02 LHIGR Limit, -.:GWd/MT (GWd/ST) ... :kW/a ,ft :,P~eak 'Oeile Exposure: i ;Most fimiting G;adoilnia LHRLimtG: d IM ..... ... ........ ...... ... .... k W/.. ... .... ..... _] .... ..SBounding ,gadolinia .LHIGRJilirit~sforc;IIl ,gadoliniuitn;cpncenuratoons~ioCctirng .in, ,this, bundle -::: 13 Exeloa Nuclear -Nuclear FuelsCulre Opetoting Limits ReportHNn-l'roprielwry Information Subnutlcd in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Relnnd15~ ! (Puhlin' .COLR Llmerick 1 Rev. 12 Appendix A000N5028-FBIR-NP .. .......Revi~qinn IUO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P IOcG2B38S-130Z-(GN F2)y' :: .::: Bundle Number: 4046 " "'": -.::,/!Peak Pellet Expeau ,;re ':Mqt imitlin~g 10 Boun-din gadohina L.AUIR ltim~it forrI al ~i~goniuiW*on m6 ,-this ,,design:', [[ 1]. 4: -.Page 14 Exelon Nuclgnr-Nucelsr FuelsCare Opezuling Limits tReportNwo-.roprietnry Informution Submifletl in Accordunce with 10 CFR 2,398Limerick Unit].I Non-Proprietary Information Reload 15 Claqss I (Public1COILR Limerlrck 1 Rev. 12 Appendix A000N5028-FBIR-NP Revision IUO2IGd Thermal-Mechanical LHGR LimitsBundle Type: (ONF2-P 10CG2B392-1 5GZ-1I20T2-11504T6-4047 (GNF2) -: ,,.,.IIBundle Number: 4047.: l ,.+ll, l:. .Peak Pellet Exposure U.01 U .LHGR Limit:,.. GWdIMT (G~dIST) ..... k} ..;iW/ft:i::::: Peak L Gadoilnia, S[[._._.__ ._ _ ....._ _... ..,__,, _ __ I,]..., ; 15 Exelan Nuclear-Nuclear FuelsCore Operating Limits ReportNon.Praprieiuwy Ilbnulaimnn Submitted an Accodancec wiih 10 CPR 2.390Limerick Unit i Non-Proprietary Information Reload 15 * .. Class 1 COIN Limatick I Rev. 12 Aeppendlx A000N5028-FBIR-NP S Revision IUO21Gd Thermal-Mechanical LHGR Limits .-:Bundle Type: GNF2-PIOCG2B386-i 4GZ-1 20T2-1 50-T6-4272 .: :?:: iBundle Number:. 4272 , :,.' ,' ,,:,:Peak Pellet Exposurei U02 LHGR Umtnit.. Peak; Pellet

,.l'Most mIimtlIng.Gadidoluia GWd/MTI(GWd/ST) I.________________________

a2fondn i l .,' g flmb.r*ncntamn~ccrmg, i: ~this, ;bundlte [[ l]~. ~Page 16

• Flxwlon Nuclear -Nuclear FuelsCOre Operating Limits ReportNon-Fropricwzy Inoramation Submitted on Accardamce with 10 CPR 2,390Limerick Unit I Non-Proprietary Information Reload 15 Class ! (PubliclCOLR LUmedick I Rev. 12 Appendix A000N5028-FBIR-NP Revision IUO2IGd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-P IOC.G2B387-1I3G7.0-I20T2-1I50-T6-4274, (ON F2) .: ::-::!',Bundle Number:.

4274 ::' .. ., .,: ".Peak Pellet Exposure -i .. UOz LHGR Limit _ iGWd/MT (GWd/ST) '.,: kW/ft: , ;::..;... [[______________J 14H(Gh.imivj, fobr.zaIl. ga~doliniuim this :bundle -desig~n: [[ 11..Page i7 Eixwlon Nulear -Nucleu FuelsCore Opamling Limits R-'portNon-I'roprielory Inlornmoion Submitted in Aceordwiee with 10 CFR 2..390Limerick Unit I Non-Proprietary Information Reload IS I (PuhliaI COLR Limerick 1 Rev. 12 Appendix A000N5028-FBIR.-NP [UO21Gd Thermal-Mechanical LHGR LimitsBundle Type: GNF2-Pi0CG2B400-13GT.0-120T2-1 50-T6-4275 (GNF2) :-: i"..Bundle Number. 4275 .: -.:.,..-:,, ,,,..,:Peak Pellet Exp~osurei: -..: U01.LHGR GWd/MT.(GWd/ST) ...... t, .. ..[:! [[ -..peak r.e LimitIng Gadolldala ,,____________.__, ! LHGR Limit 1 "GWd/MT (GWd/ST) ...._ __ _ __ _ _ __ _ __ _1Boudin gaolisaLHG~ 'init~for".I:,adliR~niur:n this b'undle designW "Di ]]. .Page 18 IL,'elon Nuclear-Nuclear FuelsCore Opeiating Limils ReputNnn-rmprietury Inronnution Suhmitted in MAccrdance wilhl0 CFR 2.390 COI..R Uimerick 1 Rev. 12 Appendix ALimerick Unit 1. .. Non-Proprietary Information O00N5028-FBIR-NP Reload 15, Class I (Public) Revision i*UO21Gd.Thermal-Mechanical LHGR LimitsBundle Type: GN F2-P I 0CG2B3S7-12G7.0-1l20T2-I50-T6-4273 (GNF2).:'

.:.i!: ' 'iBundle Number: 4273., : :..::,:,:

,..! iPekPellet Exposre! U"O2 LHGR Limit..:.. ................................ , .!, ... " : .-: .',i ':':. .'re~lt Pelet

• Mos ,.lhl:_i.0,i ci::::;":::/::::

.:..... ..... ..... .... .3 ...... -. ... .......:... ..... i .... ....... ;H G ,l im t s .. .!:",,,.:.:!

: .: ..-IGOM (Wm~ i~n: :I.:;.? '~Bondng gaolni L~i .........ad..iu..~n~nrjt~n ocma 'in th's budl des"ign",

: ' ' -Page ' 19

• • Eiclan Nulclr -Nuclear FuelsCore Opemt~ine:

Limits ReportNon-lPrprictary Inrornation Submniatcd in Accordance with 10 CFR 2.3'iOLimerick Unit I Non-Proprietary Information Reload 15 ...laic:e I COLR Limerick 1 Rev. 12 Appendix A000N5028-FBTR-NP. Rpevq;.nn I........ ~Appendix B, -..* Fuel Bundle Information i .* ; ~~~~~~Table B]-1 I : ,* ";": :: +..__ _..... ........ .. ........ i ... ..Bundle specific Infor~m ationi .... .__....____.,.____

• ': , ,' ' I Max+ .I..xposure:.

Bundle .I Number +l(wt% 1-235) of ,,02 or k,.-t; at0 Bu dl ....I -; .I..... ... I+ ?'" + (GW d/ST)GEI4"PI0CNAB394"-15GZ-3273. .......... .................. 120T-!150-T6-3273 (G E 14C) ....._73......................................................._ GEI4-P!0CNAB402-1 3GZ: 3274.............. .....+ .. ................ .. ...120T-l 50-T6-3274 (GEl 4C) ______120T-150-T6-3275 (GEl4C),: 'i-:.-,GE 14-PI 0CNAB394-l15GZ- .. .......................- .... .......................... 120T-l50-TB-3272 (GEI/4C) 327....... -:_;.:+:.......... .. ']"+ +GNP2-PIO0CG2B393-4048I 0G7.0/2G6.0-120T"2-1!50-T6-444048 (G N F2) -...... ........... ... .... ..._... .. ..... ... ........ .......GNF2-PI 0CG2B404-12G6.0- .... i +,........... 100T2-150-T6-4044 (GNF2) .............................. GNF2-PIO CG2B4O4-12G6.0-3643 iI120T2-1I50-T6-3643 (GNF2) ____ ____GNF2-P10C02B387-IS GZ- 44! 20T2-1 50-T6-4045 (ONF2)______ GNF2-PI 0CG2B388-13GZ-44120T2-150-T6-4046 (GNF2) 44GNF2-P10C02B392-1 5GZ-120T2-1I50-T6-4047 (GNF2) 44GN2PI 0C032B3S0-140Z-... 120T2-I 50-T6-4272 (GNF2) 47GNF2-P10CG2B387-1!3G7.0-1 20T2-1 50-T6-4274 (GNF2)4274-I a & I -& IP p .,p" Maximum lattice k, rot the most reactive uncontrolled state plus a [[ 3] adder for uncertaintdes(:" Page 20. Exelon Nuclear-Nucleur FuelsCnra Operating Li-"mits RepurtNon-Proprietrny Infocmiuton Submnitted~in Accordance with 10 CFR 3,390Limerick Unit :1 Non-Proprietary Information nI._, I q I(Pu~hlicl COLR Umarick 1 Rev. 12 Appendlx A'000N5028-FB[R-NP. Revision ITable 1B-IBundle Specific Information __________ Fuel Bundle Enrichment [Weight Weight Max ExposureBundle Number (wt% U-235) ofUO) o (kg Ia20oc aGWd/MTaX! (kg) (kg_,, (GWdiST)GNF2-PIO CG2B400- !30G7.0-4275120T2- 150-T6-4275 (GNF2) "-4 75_ ... .._ __ ,__ __ _'._,__"..... .. ..... .......... ........ ..GNF2-P10CG2B387-12GT,..-.... 4273 " -........... ..... ]]t20T2-150-:T6-4273 (GNF2). ____ ______....________ ("..: ,.:;..:. " , ! "" i ".............. "i : iii i:!!i: iii ii iiii:i!!' i ii!:. '... .. , i ! .; ," ' :..,:, ::.! .:... , , " i :.!". .. '-";-; I.,,,, ., ,,, -,... .. .. ... .. ......-.,. , ..Page 21i.... , E:xelon Nucde-r-Nuclear FuelsCore Operuting Limils ReportNon-Proprietary Inrormation Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload I5 Class [ (Public)COLR umenc1k I Rev. 12 Appendix A000N5028-FBIR-NP Revision lIiFigure B-1 Enrichment and Gadolinium Distribution for EDBNo. 3:271'.:Fuel Bundle GE14-P1OCNAB394-15GZ_-.20T,-15O-T6-3271 (GE14C)Page 22 FExclon Nuclear. Nuclear FuelsCore Operating Limits ReportNan-Proprietary Iniannotion Submitted in Accordance wvith t0 CFR 2.390Limerick Unit I: Non-Proprjetaty Information Reload 15.:. ,.Class 1 (Public)COLR Limterck I Rev. 12 Appendix A000N5028-FBIR-NP , Revision 1.:.......... li ...... 11].... igureEI,,grlctiuitengand Oadohiniu, Distributtou (or EDB No.3273.:- r~S~Page 23 Exelnn Nueclr -Nueclr FuelsCore Opcmting Limits ReportNon-rropcictnr Inf'ormaton Submitted an Accordance wvilh 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class ! (Public)C0LR Limerick I Rev. 12 Appendix A000N5028-FBIR-NP Revision !-- -FF I II] Bh3 Enrichment aud~adoliniuni Di'stribuionfoqr' E.D.B No.;3L274 S.-Fuel Bundle :G Page 24 E~xelun Nuclear -Nuclear F~uelsCore Opcmting Limits Report.Non-Propriew Inframinion Subminted in Aceordance wvith 10 CFR 2.390Limerick Unit I Non-Proprietary Inrormation Relnnri ! S Cl:nn I (Pumhli&'t COLR Unmerici I Rev. 12 Appendix A000N5028-FBIR-NP R....Pev~ision i, -..]] EDB No. 3275k:MFUiiu I5o-r63z7(G E14c)Page 25 Exelan Nuclear-Nucleaur FuelsCore Operating Limits ReportNan-lropric.tmy Inrormation Submitted in Accordance with 10) CFR 2 39t2Limerick Unit I Non-Proprietary Information Re load 15 Classi I COLR Limenck 1 Rev. 12 Appendix A000N5028-FBIR-NP Revision I[[l11: Figure,'lB$i En'richntunt~and GadoliniiumDistribution (for EDE 3272, Fuel--Bundle 4CPage 26 E.'celan Nuclear -Nuclear FUelsCare Operating Limits ItcpaflNon.Priprietm-y Inrrmiutinn Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 ;* Class ! (Public)* COLR ILlmedck 1 Rev. 12 ,appendix A' 000N5028-FBIR-NP Revision I[[1]8.6r EflricbmentanudGadoi~nium 1DB No.40488(GNF2)Page 27 Exchmn Nuclear. Nueclar FuelsCorn Opemoling Limits ReportNun-Proprictocy Inrormntion Submiuted an Accordonce with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload IS Class I (Public)COLR Unmdck I Rev. 12 Appendix A000N5028-FBIR-NP R II B I I]]Figure..-.. ..Enih en i. d1nii.~srbtiao ED N- 44., ,i.Fuel Bundle GN p2-P1OCG2B4O4-12G (G;NF2).Page 28 E..c-lon Nuclear -Nuclear F~uelsCore Oplraling Limits ReportNon.Proprietary Inlormation SubmiUt-d in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Information Reload 15 Class ! ('Public3 COLR Limerck 1 Rev. 12 Appendlx A000N5028-FBIR-NP Revision I...... E .... wI[[1]SFigure fl- Enrichment and Gadolinium Distribution for EDB No. 3643...... 0ie *u'l GN 2PI(GB'4 2*t20'-I0T.34 (NPage 29 FExclon Nucku'-'Nuclc& luulsCorc OpenilinK Limits Nnn-l'ropiic.tazy Inr'onnntion Submitted in Accordance with 10 CFR 2.390Limerick Unit I Non-Proprietary Iniformationt Reload !S 5 l1.n. I (Puihlirn COIR Umeulct I Rev. 12 Appendix A000"N5028-FBIR-NP Revision II !.......... .................. [[:Figue B- Enichmut No.404Page 30 Exelan Nuclear -Nuclear IuclsCore Operating Lhints ReportNon-Proprielaiy lnlbnnniion Submitted an Accordance with tO dIR 2.3g0Limerick Unit I Non-Proprietary Information Reload !15 *Clas I COLR Umarclck 1 Rev. 12 Appendix A000N5028-FBIR-NP Revision 1,- ...... ..... ... ..... ,e"t" " I ...... r ........... [r_]]!O0 and GadoliniumDPbtributign forEDB No..4046 (GNF2)Page 31! FExciwn Nuclnr -Nwlcur I:.dsCorn Umils tRepaNu ln-I'roprwiwly Inlormutiwi Submittecd In Accatdunco with ID Ci*R 2.390Limerick Unit I Non-Proprietary Information Reload 15 .. ..Class I COLR LimerIck 1 Rev. 12 AppendIx A000N5028-FBIR-NP -Revision I..11'i" rlu.e Bi4 Ew~r "."Fuel :Page 32 E.'wlon Nutclur -Nuclemr FuelsCore Opernting Limits RcportNan-I'reprlctniy lnotmlatian Sulrnuued in AccOrdnnce with 50 CFR 2.390Limerick Unit I Non-Proprietary [n formation Reload. 15 Class I COLR Limerick I Rev. 12 AppendIx A000N5028-PBIR-NP -- ~Revision I[[.11 2 ,Eoriehme~nt~and Gadolinium Distribution for EIDB No..4272".;,'!',, Page 33 F-xelon Nuctear -Nuclear FuelsCore Oporalin8 Limits ReportNan-Pmropelm'y Inlomiation Submittedi in Accordance with 10 CFR 2,390Limerick Unit I Non-Proprietary Information Reload 15 'Class l (Public'} COLR Limerick.1 Rev. 12 Apperndix A000N5028-FBI R-NPRevision I1]Figue Enrlehmenit

hd'Gadolniuin

-Fuel BundleN TZ4G82Page 34 Exelun Nuclear-Nuclear Fuels,Core Operating Limits ReportNon41'rprietswy tntbrmatian Submitted in Accordance with 10 CFR 2.390Limerick Unit I :Non-Proprietary Information Reload 15,S Class I COLR Llmaenk 1 Raw, 12 Appendix A000NS028-FBIR-NP Revision 1I[1]* :":.F igure:B44EizriebiihwntIaud Gadolinium Distribution (0or-EDB No. :4275 1tCQ2JWIO-13G7, O12@T2;i5O-T6.'427S (GNF2)Page 35 FE etnn Nuclear-Nuclear FuelsCore Operatin8 Limits ReportNennt'rprietmy Infonmuzion Submitted in Accordauec with t0 CFR 2.390Limerick Unit ! Non-Proprietary Information Reload !5 ! COLR Limerick 1 Rev. 12 Appendix A000N5028-FBIR-NP Revision I[I:!i-.Figure Bl$5 Enrichment and Gado1ini ritDlstribu'tibrn~ofoEDB No. '273* (GNF]2)Page 36}}