ML15254A415

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 3 UNIT 1 COLA FOR RELOAD 15 CYCLE 16 WITH APPENDIX A PROPRIETARY CLASS I (PUBLIC).... ... .. ........... .. .i. : .:.: ,- , ,. ...... .... .. ., ...... ..,t I .....t ; i I i1/2 i..%~.~** Exelon Nuciear- Nurcear Fuels " COLR Limoerik I, Rev. 12 Core Operating Limits Report Non-Proprietary Information Submitted in Accordanice with 10 CFR 2.390 COREi OPERATING LIMITS FOR LhMERICK GENERATING STATION ...,..UNIT 1 RELOAD 15 CYCLE 16 i-'. -'i." , I M. Holmes... Preparer Da "e ', 2 "'" : " 3" I I _ .. ' " " Reviewed:By: i.Hsu Independent Reviewer Dae: ,ae ( ,,2 /5 .A. Stefanezyk Reviewed By: ""I'T. Bement Engineering Sa.fety Analysis'Manager -BWR, Designa l Da,,e: ,! 9A Sratan Qualified Review By:-L. Kurbeil Station Qualified Reviewor oote: .f9I /&o k I ':f~m i t_" Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Nan-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table of Contents COLR Limerick i, Rev. 12 1 Revision History List of Tables 1.0 Terms and Definitions

3.0 MAPLHGR

Limits 4.0 MCPR Limits 5.0 LHGR Limits 6.0 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 .. ..Page 3 4 S 7 8 9 13 16 17 18 19 20 20 21 Page2of2l: i Exelon Nuclear -Nuclear Fuels COLR Limerick I, Rev. 12 Core Operating Limits Report,,."** .Non-Proprietary Int'ormation Submitted in Accordance with 10 CFR 2.3g0 .. ..*" .... .'Revision History, Revision erito Revision 12 ., .. PROOS limits. Miscellaneous ..editorial and formatting changes to ensure i: * , -- consistency with Unit -: ..Revision il ..I .: ;.,,>:'; New issue for~ycle. 16' ,::i :, ..~~~~~~.. .- ................... "'i.- ....".i..'"' ,.'.i. ............ I, 2xelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Prmpretaiy Information Submitted in Accordance with 10 CFR 22t90 List of Tables " COLR Limerick !, Rev. 12 I Table 3-1..Table 3-2 Table 3-3 T~able 4-1 Table 4-2 Table 4-3 Table 4.4 Table 5-I Table 5-2 Table 5-3 Table 5-4 Table 5-5 Table 6-1 Table 6-2 Table 7- I T~able 7-2 Table 8-I!Table 8-2 Table 9-I MAPLHGR Versus Average Planar Exposure-GEl4 .. .MAPLHOR-Versus"AvergePlanar Exposure-GNF2. ' .. -MAPLHGR Single Loop Operation (SLO) Multiplier -All Fuel Types Operating Limit Minimum Critical Power Ratio (OLMCPR) -GNl4 Power Dependent MCPR Limits and Multipliers MCPR(P) and KP -All Fuel Types Flow Dependent MCPR Limnits MCPR(F) -All" Fuel Types:, .!. ...: : Linear Heat Generation Rate Limits -UOz Rods Linear Heat Generation Rate Limits- (ladolinia Rods LHOR Single Loop Operation (SLO) Multiplier-All Fuel Types Power ependnt LHR Muliplie 4HRA() lFe ye Plowe Dependent LHGR Multiplier LHORFAC(P)- AIl Fuel Types Rod Block Monitor Setpolnts Reactor Coolant System Reclrculation Flow Upscale TriP :: i Turbine Bypass System-Response Time ...Minimum Required Bypass Valves To Maintain System Operability OPR" PBDFTFp-'pon. LOOPRM PBDA Trip Setpolnts Modes of Operation Page,.-8 10!1 12 I I I I I I 12 I 13 I'3 I 14 I 14 I IS I 16 I 17 I.IS I 19 I Pa~&4~of21~r' I Exelon Nuclear -Nuclear Fuels COLR Limerick i, Rev. 12 I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with.10 CFR 2.390 1,0 Terms and Definitions ARTS APRM, RBM, and Technical Specification Improvement Program BASE A case analyzed with Turbine Bypass.System in service and Recirculation Pump-Trip in service and Feedwater Temperature Reduction allowed (FFWTR includes FWHOOS or final feedwater temperature reduction) and PLUOOS allowed at any-point during the cycle in Dual Loop mode.I DLO Dual Loop Operation DTSP Rod Block Monitor Downscale Trip Setpoint EOOS Equipment out of Service EOR 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 Service HTSP Rod Block Monitor High Trip Setpoint]TSP Rod Block Monitor Intermnediate Trip Selpoint Kp Off-rated power dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thermal limit flow dependent multipliersI LHGRFAC(P) ARTS LHaR thermal limit power dependent multipliers "/LTSP Rod Block Monitor Low Trip Setpoint MAPFAC(F) Off-rated flow dependent MAPLJ{GR multiplie~r MAPFAC(P) Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) Off-rated flow dependent OLMCPR multiplier Page 5~of 21:.Main_ Steam Isolation Valve Out of Service OLMCPR .,. ;.~ ;,.Operating Limit Minimum Critical Power Ratio: OOS Out of Service OPRM 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 Monitor RPTOOS ..-, Recirculation.Pump Trip Out of, Service RWE ~ ..... Rod.Withdrawal.Error...- ......TBVO..OS....,:: ...Traering Bynacore:Prob Out.of Service..... .........TSV Turbine Stop Valve rickI, Rev. 12 I I-. 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 Cycle 16:* 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. this report 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 60.0 0 F 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-s il Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietazy Infonmation Submitted in Accordance with 10 CFR 2.390 COLR Limerick I, Rev. 12 I 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description

• : -: +,: , : ';:The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as afunction of average planar exposure is given, in Tables 3-1 and 3-2. For single loop operation, 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 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Table 3-3 MAPLHGR Single Loop Operatioa (SILO) Mullipller-All Fuel Types (Reference 2)i i il1 .i i ult er 0.80.+ ..i i i ...i* Page 8+of 2+!j I Exelon Nuclear -Nuclear Fuels COLR Limerick I, Re,. 12 Core Operating Limits Report -" Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 ....4,0 MCPR Lim~its 4.1 Technical Specification , Section 3.2.3 4.2 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. Less restrictive MCPR.limits.

for the BASE DLO. Option B condition are .provided for a 100 ms or greater delay in the start of TCV closure' following a turbine trip. The less restrictive limits may only be used if it is that. the. 100oms.oro gratr delay existsfb11owing Digital EHC m odification. '.:-' .. ...... , ,.. .. ." ..- ... ..-ARTS provi-des or~pow`:e..ran.llow depnent thermalli~mit ~muti~tpliers, which allow 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 of power 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. The PLUJOOS -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 are required for PLUOOS in those operating conditions. The PLUOOS condition, has not been analyzed 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) and MCPR(F) adjustments .Tables 4-3 and..4-4: The°OLMCPR~is.detenmined for a given power and flOownditi~on" by evaluating the pi~owr .deen~enit"MCPR and the flow dependent-MC-PR and selecting the greater of the two ..... .,,,,,,...........

• " .S .~ ':: * -, -". " .--S. -.' :. .Pagofvt Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick I, Rev. 12 I Table 4-I Operating Limit Minimumm Critical Power Ratio (OLMCPR) -GE14 fReferences 2.,7. "nd.*'1'*,'/'.;':.'i+:.; "";:. :. ,,:-: =: YI" :?,",* :: :. f: .:- SCRAM TIme <EOR -3234 >_ EOR -32.34 EOOS Combination Option' *MWd/ST , .' B 1.39 1.41 BASE B 2 1"38-' 1"412_-,.-___+__-__,.,-_,_____, ...... A 1.47 1.49 4... " ..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' +LO 4-* 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 '. ;"?I I i +, ; :,..... .. ..+, .I'iWhen Tanl does rnot equal 0 or I, determinie OLMCPR via l!ineat iterdlation.; For and

.-' 9i .-,

2 lLimit 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 4 Por 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).I i Exelon Nuclear -Nuclear Fuels COLR Lime Core Operating Limits Report Non-Poprietary Information Submitted In Accordance with 10 CFR2.390* " Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) -GNFl~Referencesq

2. 7. and 81:rick1, Rev.l12.. .... .Cycle Exposure ,.. .. +- .SCRAM Time <EOR -3234 _> EOR -3234 EOOS Combination

"+Option' MV/I/ST 1 .39 : 1.41_B 2 1* :!3 8 2'3 i...1.41z .____ ....._____ .._ A 1.47 1.4. I 9 i BASE SLO 4 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: 1.581.5 A 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.-I I I' 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 Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with !0 CFR2.390 COLR Limerick 1, Rev. 12 I Table 4-3 Power 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 : 0 TBV O O)S. 3.75, , "375 -"': ; 1 .340 1.131 1,.067.....

• '-3.28S .8' 27 ATBVOSSL ----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 I Core 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 U0 2 Sfuel 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 loop o i peration,,amniltipller, is used. ;which. is shown ,In Table 5-3 arnd applied in Table .further SSingle 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 for i;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 .Ut 2.o t. -.... .'T~~pe LHGR , .GElj i .-," A':S !ppendix A* .GN '2' " :..:'. ,1 Appendix AI Limear Heat Geaeaii Rods--(Referencee ) ...*, ruelTyp S.I 0E1-" "~GNF-2 '-" A, I -"SeeA rpp dix A:,- .Pajel36f: Exelon Nuclear -Nuclear Fuels Care Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 COLR Limerick 1, Rev. 12 I Table 5-3 LHGR 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 ),rP EOOS Combination, Core.Flowof ratedfl-:: ' -Core ThermuaI.Power (% of rated).*0 1 2511<~30t >3o1 65 I 88 I l00 I 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 , 1.0 BASE 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 0.490 R'.. 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 0.473 PROOS+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 !00 PROOS+___T_______ >:60 0.434 0.434 0.4730.5 087 092 1.0.. ...... ...................... .. ., ..................... ...., ' ................

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

'. Exelon Nuclear -Nuclear Fuels COLR Limerick l, Rev. +12 Core Operating Limits Report Non-Proprietary Information Sub mitted in Accordance with 10 CFR 2.390 Table 5-5 Flow 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: 1.000 single L~oop 0.506 0 .706 0..... 00O 0 .800"-. .' ... A*.*,." ' , " *L ' ' ' ! ' ' "" : ' ." .. .' "..... + " ii "+: :"" , ii; : ' :, "'of'" 2: 1.. .:.ii , :' Exelon Nuclear Fuels Core Operating Limits Report Nan-Proprietary Information Submitted in Accordance with 10 CFR 2.390 6.0 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 constant data are shown in Table 6-I. The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2. These selpoints are set high enough to allow ful utilization of the enhanced ICF domain up to 110% of rated core ../ .Table 6-1....... ................ Rod Block M onitor Setpoinls' ...a.Power Level I Analytical I' Aliowuble I Nominal TrIp limit [ Value. Selpolat LTSP i23.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) are based 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 I Core 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 these S,.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 movement 1 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 2.390 8.0 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 two loop operation OPRM Setpointls specified in Table 8-1 must be implemented prior to restarting the idle 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 Fuels Core Operating Limits Report Non-Prprietary Information Submitted in Accordance with 10 CFR 2.390 COLR 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 the applicable 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 ' :.. ./,., .. .. ': Yes 2:.. : .-BASE SLO. Option A or B .... 2:! ',TBV..OOS, Option A or B .... ..... .... 2 ...TB VOOS SLO, option A or B. :"-.,- ........ , Yes 2' ..RPTOOS, Option A or B. --. Yes 3 " .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 ..... .Yes 2PROOS+TBVOOS, Option A ...No*PROOS+TBVOOS, Option ' .... Yes 2.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. 2 The 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 *I Core Operating Limits Report Non-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 and approved by the NRC, specifically those described in the following documents: I.: "General Electric Standard :Application for Reactor Fuel 1" NEDE-2401 l-P-A-21, May 2015 and U.S. I Supplement May 2015. -.. .... ..... .... ...2. "Reactor Stability Detect and Suppress Solutions .Licensing:.. Basis Methodology for Reload Applications," 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, License No. 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", I GE Hitachi Nuclear Energy Docwuent No. 002N4397, Rev. 0, February 24, 2015.I , ~~~~~~~~~~~. ..... ....... .! .' .-.:., .,.,. .... .. .Page-20 of2l I Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A (36 pages)COLR Limerick I, Rev. 12 I".:. :.:' :,. ' :? : : : :. ":

• ;.:i',' ......i..: .... * ,-.;.

il :'

..... ;. ....

....-. !. Page21of21~ i Exclan Nuclear -Nuc~lear Fuels Corc Operating Limits Report Nwn-l'ropriclmry lnlbrmntion Submitted in Accordance with 10 CFR 2.390 COIR Limerick I Rev. 12 Appendix A Global Nuclear FuelJ Vomn.l Of & tah Global Nuclear Fuel 000N5028-FBIR-NP Revision I February 2014" .... ", Non-Proprietaiy Information -Class l (Public)Fuel Bundle I[aformation Report for Reload 15 Cycle 16 Copyright 2014 Global Nuclear Fuel -Americas, LLC All Rights Reserved 1!.'thn Nuclear -Nuclear Furls,, Core Opemlins Limits Rerort Non-Proprietary Information Submilttd in Accordance with 10 CFRI 2.390 COIR Urnanckc I Rev. 12 Appendix A Limerick Unit I Non-Proprietary Information 000N5028-FBIR.-NP,..Re~load 15 Class i (Public) Revision !Important Notice Regarding Contents of This Report Please 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 and true 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 between Recipient and GNF-A for nuclear fuel and related services for the Nluclear Plant (the "Fuel Cont~tct") and nothing 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 of the information or that such unauthorized use may, not infringe privately owned rights, nor (b) assumes any responsibility for .liability or damage of any kind which may result from such use of such information. Information Notice This is a non-proprietary version of the document 000N5028-FBIR-P, Revision 1, which has the proprietary information removed. Portions of the document that have been removed are indicated by, an open and closed bracket as shown here [[ 3).Page 2 E'wlon NUCILar -Nutclear IFuels Core Operating Limits Report Non-Proprietumy lnlbrmation Submitted in Accordance with I0 CFR 2.390 Limerick Ulnit I .... Non-Proprietary Information Relnud ' I COLR Llmerick I Rev. 12 Apperndix A 000N5028-FBI R-NP Revision I: 1 l.Introduction and Summary This 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 for Cycle 16. These LHGR limits are obtained from thermal-mechanical considerations only. Approved GN 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 fuel bundles 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 Fuels Core Operating Limits Report Non-Proprietary Inlbnnahicn Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information Re'load IS Class I COLR Umenck 1 Rev. 12 Appendix A 000N502S-FBIR-NP Revision 1............... 1 ...... ( ...........

2. References

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

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

• Nuclear.-

Nuclear Fuels Core Operating Limits Report Nnn-Proprictary Inloinution Submiiled rn Accordance with 10 CFK 2,390 Limerick Unit I Non-Proprietary Information Relnnd 15 fllsqs I COLR Uimerick I Rev. 12 Appendix A 000N5028-FBIR.-NP Revision I Appendix A UO 2 IGd Thermal-Mechanical LHGR Limits-, ..,' ' .' " , * .Bundle Type: GEl4-PI OCNAB394-15GZ- 120T- 150-T6-3271 (GE 14C)Bundle Number: 3271 Peak 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 ft 11 Bounding Ia <bund*le desig~n5 Excinn Niiclenr. Nuclcor Fuels Core Operuting Limits Report Non-Proprietary Inlanmation Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information Reload ! 5 I (Public'1 COLR LUmenck I Rev. 12 Appendix A 000N5028-FBIR-NP Revi~inn I I f .........

• UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GE I 4-Pi O CNAB4O 1- 1,3 GZ- 1 20T-i 50-T6-3273 (GE i 4C).'. .Bundle Number: 3273 Peak Pellet Ezposure UOa LHGR Utmit , Peak Pellet Exposure ...Limiting Gadofluia_ _ ...............

.... .: ..... .H G R *Lim it 1 z.. ..GWd/MT (GWdl/ST,): kW/ft-[ i -..... ...... ..""*____________________ 11 J?2" Bounding na:H :'* 6 Exelon Nuclear- Nuclear Fuels Core Operating Lignits Report Non.ProprietniyInrormation Subrnittcd in Accordance will, l0 CFR 2.390 Limerick Unit I Non-Proprietary Information Reloand I15 Classq I (Puhilci COLR Limerick I Rev. 12 Appendix A 000N5028-FBIR-NP Revision !............... Z ...... r ........... UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P I 0CNAB402-1I3GZ-1 20T- 1 50-T6-3274 (GEl 4C) ..Bundle Number: 3274 -" Peak Pellet' Exposure :.,, , U0 2 ,LHGR Limit,-,, GWd/MT (GWd/ST) " , kW/R :::.,t .Peak ,Most Limiting GadolinieaLHGR Limit 3 G:wdIM (GWd/ST) i '%kW/:.,If.t

.ri SBounding.

.

LI-IG.R-limit:, fori all this,. bundle .design.[[ ]1I. =Page 7 Exelon Nuclear- Nuclear IFuels Core Operating Limits Report Nsin-I'Prieopdry Informationl Submitted an Accordanece with 10 CFR 2.390 Limerick Unit 1 Non-Proprietary [nformation Reload I5 Class I (Public)COLR Umedick 1 Rev. 12 Appendix A 000N5028-FBIR-NP Revkinin I UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GEI14-P IOCNAB398-12GZ- I20T-1I50-T6-3275 (GElI4C) '.. -' -. -..Bundle Number: 3275.' ,.:.,-,, -,, Peak Pellet' Exposure" U0 2 LUGR Limit...., GWd/MT (GWdIST) ! "kWlf/ :,.':-R[1[Peik 'Pellet E xposure, : .Most , ,-....o." ...... LHGR i~mit 4::GWdIMT(GWdlST][)_ .., , : ,::

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

I]SBounding LKGR-iinzit:, Jr.-t.Mllgadolinium this v!bund~le [[ I]. i -" ,., .:!:Page 8 FE'clon Nulcle'ar-Nucicur Fuels Case Op-'ul~nW Limits Report NonnPropricimy Inl'onntion Submiued in Accordance with tO CFR 2,190 Limerick Unit.!" Non-Proprietary Information Reload 1S Claq.q ! COIR Umedck I Rev. 12 Appendix A 000NS02S-FBIR-NP Revision 1 UO 2 IGd.Thermal-Mechanical LHGR Limits ", Bundle Type; GE 14-P 10CNAB394-15GZ-120T- 150-T6-3272 (GEI14C) :: ,, .7' .Bundle Number: 3272 **Peak Peliet U0 2 LHGR Lmit ....G;Wd/MT (GWd/Sr) kW/ft ,; .[[ .., ,_ _ __ _ I ]. 1 *Peak P*t Exposure 4 Most Limiting Gadolinla LHGR Limit'GWdIMT (GWdIST~ k~V~ft ....[r-Y________________________ n~.Bouig ..89n LHR, oa adlnuicncnminocuun i thu ,udl.esg Page 9 Exeton Nuclear -Nucetar Fuels Core Operating Limnils Report Non-I'roprietiuy Informiation Submiued in Accordance with [0 CFR 2.3903 Limerick Unit I Non-Proprietary Information Relnnd I 5 I COLR Llmertel 1 Rev. 12 Appendix A 000N5O28-FBIR-NP .. ... .....Revision i UO 2 1Gd 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/" .UO 2 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 Fuels Core Operating Limits Report Non.Proprietary Inarmanninn Submitied in Accordance with 10 CFR 2.390 Limerick Unit I1 N.. , on-Proprietary information Reload 15 Class ! (Public)COLR Umernck t Rev. 12 .Appendix A 000N502g-FBIR-NP Revision I UO 2 IGd Thermal-Mechanical LHGR Limits Bundle Type: GNF2:PIOCG2B404-I206.0-100T2-150-T6-404.4,. , ... ..(GNF2),,, .,: .i, :. , Bundle Number: 4044 ....,.....,, ....-Peak Pellet.Exposure., .U0 2 , LHGR Limit.,, GWdlMT (GWd/ST)" -" :kW/~ft.!.::,ii.:

_______________ 1]Bou( in ]d1. .,G:lt~ n.~p~rig ttisbn~ desi Page !II Exelon Nuclear -Nuclear Fuels Corn Opcruling Limits Report Nnn-t'roprictnry lnlormation Submaited in Accordance with 10 CFR 2,390 Limerick Unit 1 Non-Proprietary Information Reload 15 Class ! fPublicl COLR Umerlck 1 Rev. 12 Appendix A 000N5028-FBIR.-NP Revision !UO 2 IGd Thermal-Mechanical LHGR Limits .Budle Type GN2P IOCG2B404-12G6.- 120T2-I0T634 (GNP2)Bundle Number: 3643 ! - Peak Pellet UJOZ LHlGR Limit GWOIMT.(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 Fuels Care Oporuting Limits Report Nun-Prrpritlory Intbrmution Submittcd in Accordance with I0 CFR 2-390 Limerick Unit I Non-Proprietary Information Relnnd 15 ., Class I COLR Umedlck 1 Rev. 12 Appendix A 000N5028-FBI R-NP Revision i....... ....... ........ I ...... i UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P ! 0CG2B3 87-I SGZ- 1 20T2-I150-T6-4045 (GNF'2).' ' . Bundle Number: 4045 Peak Pellet Exposure- .U0 2 LHIGR Limit, -.: GWd/MT (GWd/ST) ... :kW/a ,ft :, P~eak 'Oeile Exposure: i ;Most fimiting G;adoilnia LHRLimt G: d IM ..... ... ........ ...... ... .... k W/.. ... .... ..... _] .... ..SBounding ,gadolinia .LHIGRJilirit~sforc;IIl ,gadoliniuitn;cpncenuratoons~ioCctirng .in, ,this, bundle -::: 13 Exeloa Nuclear -Nuclear Fuels Culre Opetoting Limits Report HNn-l'roprielwry Information Subnutlcd in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information Relnnd15~ ! (Puhlin' .COLR Llmerick 1 Rev. 12 Appendix A 000N5028-FBIR-NP .. .......Revi~qinn I UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle 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 Fuels Care Opezuling Limits tReport Nwo-.roprietnry Informution Submifletl in Accordunce with 10 CFR 2,398 Limerick Unit].I Non-Proprietary Information Reload 15 Claqss I (Public1 COILR Limerlrck 1 Rev. 12 Appendix A 000N5028-FBIR-NP Revision I UO 2 IGd Thermal-Mechanical LHGR Limits Bundle Type: (ONF2-P 10CG2B392-1 5GZ-1I20T2-11504T6-4047 (GNF2) -: ,,.,.II Bundle Number: 4047.: l ,.+ll, l:. .Peak Pellet Exposure U.0 1 U .LHGR Limit:,..GWdIMT (G~dIST) ..... k} ..;iW/ft:i::::: Peak L Gadoilnia, S[[._._.__ ._ _ ....._ _... ..,__,, _ __ I,]..., ; 15 Exelan Nuclear- Nuclear Fuels Core Operating Limits Report Non.Praprieiuwy Ilbnulaimnn Submitted an Accodancec wiih 10 CPR 2.390 Limerick Unit i Non-Proprietary Information Reload 15 * .. Class 1 COIN Limatick I Rev. 12 Aeppendlx A 000N5028-FBIR-NP S Revision I UO 2 1Gd Thermal-Mechanical LHGR Limits .-: Bundle Type: GNF2-PIOCG2B386-i 4GZ-1 20T2-1 50-T6-4272 .: :?:: i Bundle Number:. 4272 , :,.' ,' ,,:,: Peak Pellet Exposurei U0 2 LHGR Umtnit.. Peak; Pellet

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

a 2fondn i l .,' g flmb.r*ncntamn~ccrmg, i: ~this, ;bundlte [[ l]~. ~Page 16

• Flxwlon Nuclear -Nuclear Fuels COre Operating Limits Report Non-Fropricwzy Inoramation Submitted on Accardamce with 10 CPR 2,390 Limerick Unit I Non-Proprietary Information Reload 15 Class ! (Publicl COLR LUmedick I Rev. 12 Appendix A 000N5028-FBIR-NP Revision I UO 2 IGd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P IOC.G2B387-1I3G7.0-I20T2-1I50-T6-4274, (ON F2) .: ::-::!', Bundle Number:. 4274 ::' .. ., .,: ".Peak Pellet Exposure -i .. UOz LHGR Limit _ i GWd/MT (GWd/ST) '.,: kW/ft: , ;::..;...[[______________J 14H(Gh.imivj, fobr.zaIl.

ga~doliniuim this :bundle -desig~n:[[ 11..Page i7 Eixwlon Nulear -Nucleu Fuels Core Opamling Limits R-'port Non-I'roprielory Inlornmoion Submitted in Aceordwiee with 10 CFR 2..390 Limerick Unit I Non-Proprietary Information Reload IS I (PuhliaI COLR Limerick 1 Rev. 12 Appendix A 000N5028-FBIR.-NP [UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-Pi0CG2B400-13GT.0-120T2-1 50-T6-4275 (GNF2) :-: i"..Bundle Number. 4275 .: -.:.,..-:,, ,,,..,: Peak Pellet Exp~osurei: -..: U0 1.LHGR GWd/MT.(GWd/ST) ...... t, .. ..[:! [[ -..peak r.e LimitIng Gadolldala ,,____________.__, ! LHGR Limit 1 " GWd/MT (GWd/ST) ...._ __ _ __ _ _ __ _ __ _1 Boudin gaolisaLHG~ 'init~for".I:,adliR~niur:n this b'undle designW " Di ]]. .Page 18 IL,'elon Nuclear- Nuclear Fuels Core Opeiating Limils Reput Nnn-rmprietury Inronnution Suhmitted in MAccrdance wilhl0 CFR 2.390 COI..R Uimerick 1 Rev. 12 Appendix A Limerick Unit 1. .. Non-Proprietary Information O00N5028-FBIR-NP Reload 15, Class I (Public) Revision i*UO 2 1Gd.Thermal-Mechanical LHGR Limits Bundle Type: GN F2-P I 0CG2B3S7-12G7.0-1l20T2-I50-T6-4273 (GNF2).:'

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

,..! i PekPellet Exposre! U"O 2 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 Fuels Core Opemt~ine:

Limits Report Non-lPrprictary Inrornation Submniatcd in Accordance with 10 CFR 2.3'iO Limerick Unit I Non-Proprietary Information Reload 15 ...laic:e I COLR Limerick 1 Rev. 12 Appendix A 000N5028-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 ,,0 2 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-PIO0CG2B393-4048 I 0G7.0/2G6.0-120T"2-1!50-T6-44 4048 (G N F2) -...... ........... ... .... ..._... .. ..... ... ........ .......GNF2-PI 0CG2B404-12G6.0- .... i +,........... 100T2-150-T6-4044 (GNF2) .............................. GNF2-PIO CG2B4O4-12G6.0-3643 i I120T2-1I50-T6-3643 (GNF2) ____ ____GNF2-P10C02B387-IS GZ- 44! 20T2-1 50-T6-4045 (ONF2)______ GNF2-PI 0CG2B388-13GZ-44 120T2-150-T6-4046 (GNF2) 44 GNF2-P10C02B392-1 5GZ-120T2-1I50-T6-4047 (GNF2) 44 GN2PI 0C032B3S0-140Z-... 120T2-I 50-T6-4272 (GNF2) 47 GNF2-P10CG2B387-1!3G7.0-1 20T2-1 50-T6-4274 (GNF2)4274-I a & I -& I P p .,p" Maximum lattice k, rot the most reactive uncontrolled state plus a [[ 3] adder for uncertaintdes(:" Page 20. Exelon Nuclear- Nucleur Fuels Cnra Operating Li-"mits Repurt Non-Proprietrny Infocmiuton Submnitted~in Accordance with 10 CFR 3,390 Limerick Unit :1 Non-Proprietary Information nI._, I q I(Pu~hlicl COLR Umarick 1 Rev. 12 Appendlx A'000N5028-FB[R-NP. Revision I Table 1B-I Bundle Specific Information __________ Fuel Bundle Enrichment [Weight Weight Max Exposure Bundle Number (wt% U-235) ofUO) o (kg Ia20oc aGWd/MTaX!(kg) (kg_,, (GWdiST)GNF2-PIO CG2B400- !30G7.0- 4275 120T2- 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 Fuels Core Operuting Limils Report Non-Proprietary Inrormation Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information Reload I5 Class [ (Public)COLR umenc1k I Rev. 12 Appendix A 000N5028-FBIR-NP Revision l Ii Figure 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 Fuels Core Operating Limits Report Nan-Proprietary Iniannotion Submitted in Accordance wvith t0 CFR 2.390 Limerick Unit I: Non-Proprjetaty Information Reload 15.:. ,.Class 1 (Public)COLR Limterck I Rev. 12 Appendix A 000N5028-FBIR-NP , Revision 1.:.......... li ...... 1 1].... igureEI,,grlctiuitengand Oadohiniu, Distributtou (or EDB No.3273.:- r~S~Page 23 Exelnn Nueclr -Nueclr Fuels Core Opcmting Limits Report Non-rropcictnr Inf'ormaton Submitted an Accordance wvilh 10 CFR 2.390 Limerick Unit I Non-Proprietary Information Reload 15 Class ! (Public)C0LR Limerick I Rev. 12 Appendix A 000N5028-FBIR-NP Revision !-- -FF I I I] Bh3 Enrichment aud~adoliniuni Di'stribuionfoqr' E.D.B No.;3L274 S.-Fuel Bundle :G Page 24 E~xelun Nuclear -Nuclear F~uels Core Opcmting Limits Report.Non-Propriew Inframinion Subminted in Aceordance wvith 10 CFR 2.390 Limerick Unit I Non-Proprietary Inrormation Relnnri ! S Cl:nn I (Pumhli&'t COLR Unmerici I Rev. 12 Appendix A 000N5028-FBIR-NP R....Pev~ision i, -..]] EDB No. 3275 k:MFUiiu I5o-r63z7(G E14c)Page 25 Exelan Nuclear- Nucleaur Fuels Core Operating Limits Report Nan-lropric.tmy Inrormation Submitted in Accordance with 10) CFR 2 39t2 Limerick Unit I Non-Proprietary Information Re load 15 Classi I COLR Limenck 1 Rev. 12 Appendix A 000N5028-FBIR-NP Revision I[[l 11: Figure,'lB$i En'richntunt~and GadoliniiumDistribution (for EDE 3272 , Fuel--Bundle 4C Page 26 E.'celan Nuclear -Nuclear FUels Care Operating Limits Itcpafl Non.Priprietm-y Inrrmiutinn Submitted in Accordance with 10 CFR 2.390 Limerick 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 Fuels Corn Opemoling Limits Report Nun-Proprictocy Inrormntion Submiuted an Accordonce with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information Reload IS Class I (Public)COLR Unmdck I Rev. 12 Appendix A 000N5028-FBIR-NP R I I 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~uels Core Oplraling Limits Report Non.Proprietary Inlormation SubmiUt-d in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Information Reload 15 Class ! ('Public3 COLR Limerck 1 Rev. 12 Appendlx A 000N5028-FBIR-NP Revision I...... E .... w I[[1]SFigure fl- Enrichment and Gadolinium Distribution for EDB No. 3643...... 0ie *u'l GN 2PI(GB'4 2*t20'-I0T.34 (N Page 29 FExclon Nucku'-'Nuclc& luuls Corc OpenilinK Limits Nnn-l'ropiic.tazy Inr'onnntion Submitted in Accordance with 10 CFR 2.390 Limerick Unit I Non-Proprietary Iniformationt Reload !S 5 l1.n. I (Puihlirn COIR Umeulct I Rev. 12 Appendix A 000"N5028-FBIR-NP Revision I I !.......... .................. [[: Figue B- Enichmut No.404 Page 30 Exelan Nuclear -Nuclear Iucls Core Operating Lhints Report Non-Proprielaiy lnlbnnniion Submitted an Accordance with tO dIR 2.3g0 Limerick Unit I Non-Proprietary Information Reload !15 *Clas I COLR Umarclck 1 Rev. 12 Appendix A 000N5028-FBIR-NP Revision 1 ,- ...... ..... ... ..... ,e"t" " I ...... r ........... [r_]]!O0 and GadoliniumDPbtributign forEDB No..4046(GNF2)Page 31! FExciwn Nuclnr -Nwlcur I:.ds Corn Umils tRepa Nu ln-I'roprwiwly Inlormutiwi Submittecd In Accatdunco with ID Ci*R 2.390 Limerick Unit I Non-Proprietary Information Reload 15 .. ..Class I COLR LimerIck 1 Rev. 12 AppendIx A 000N5028-FBIR-NP -Revision I..11'i" rlu.e Bi4 Ew~r "."Fuel :Page 32 E.'wlon Nutclur -Nuclemr Fuels Core Opernting Limits Rcport Nan-I'reprlctniy lnotmlatian Sulrnuued in AccOrdnnce with 50 CFR 2.390 Limerick Unit I Non-Proprietary [n formation Reload. 15 Class I COLR Limerick I Rev. 12 AppendIx A 000N5028-PBIR-NP -- ~Revision I[[.112 ,Eoriehme~nt~and Gadolinium Distribution for EIDB No..4272".;,'!',, Page 33 F-xelon Nuctear -Nuclear Fuels Core Oporalin8 Limits Report Nan-Pmropelm'y Inlomiation Submittedi in Accordance with 10 CFR 2,390 Limerick Unit I Non-Proprietary Information Reload 15 'Class l (Public'}COLR Limerick.1 Rev. 12 Apperndix A 000N5028-FBI R-NP Revision I 1]Figue Enrlehmenit

hd'Gadolniuin -Fuel BundleN TZ4G82 Page 34 Exelun Nuclear- Nuclear Fuels, Core Operating Limits Report Non41'rprietswy tntbrmatian Submitted in Accordance with 10 CFR 2.390 Limerick Unit I :Non-Proprietary Information Reload 15,S Class I COLR Llmaenk 1 Raw, 12 Appendix A 000NS028-FBIR-NP Revision 1 I[1]* :":.F igure:B44EizriebiihwntIaud Gadolinium Distribution (0or-EDB No. :4275 1tCQ2JWIO-13G7, O12@T2;i5O-T6.'427S (GNF2)Page 35 FE etnn Nuclear- Nuclear Fuels Core Operatin8 Limits Report Nennt'rprietmy Infonmuzion Submitted in Accordauec with t0 CFR 2.390 Limerick Unit ! Non-Proprietary Information Reload !5 ! COLR Limerick 1 Rev. 12 Appendix A 000N5028-FBIR-NP Revision I[I:!i-.Figure Bl$5 Enrichment and Gado1ini ritDlstribu'tibrn~ofoEDB No. '273* (GNF]2)Page 36}}