ML11119A034

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Core Operating Limits Report, Reload 11, Cycle 12, Revision 7
ML11119A034
Person / Time
Site: Limerick Constellation icon.png
Issue date: 04/08/2011
From: Henry P, Stratton C
Exelon Nuclear, Global Nuclear Fuel
To:
Office of Nuclear Reactor Regulation
References
COLR Limerick 2, Rev. 7 0000-0118-5622-FBIR-NP, Rev 0
Download: ML11119A034 (64)
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{{#Wiki_filter:ENCLOSURE 1 NON-PROPRIETARY INFORMATION UNIT 2 COLR for Cycle 12 Rev. 7 Exekln Nuclear -Nuclear Fuels Core Operating Limits Report Non.Proprietai Informaton Submitted in Accordance wim 10 CFR 2.390 Doc 10, COLR Limerick 2. Rev. 7 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 RELOAD 11, CYCLE 12 (This is a complete re-write; no annotations are used.)Prepared By: t te: Ai4r K.. M.Hyncs Reviewed By: Reviewed By: Reviewed By: Approved By: Station Qualifiec Reviewed By:~M. Hynes Independent Reviewer L. Korbeil R tor Engineering A. Olson Date: Date: Date: _ _ _ _Date:4V ZL.Date: i J. J. Tusar~Ingr -BWR Design (GNF)Robert Potter Station Qualified Reviewer Page I of 63 Exelon Nuclear -Nuclear Fuels'Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Doc ID: COLR Limerick 2, Rev. 7 Table of Contents Page 1.0 Terms And Definitions 4 2.0 General Information 5 3.0 MAPLHGR Limits 6 4.0 MCPR Limits 7 5.0 Linear Heat Generation Rate Limits 11 6.0 Control Rod Block Setpoints 14 7.0 Turbine Bypass Valve Parameters 15 8.0 Stability Protection Setpoints 16 9.0 Modes of Operation 16 10.0 Methodology 17 11.0 References 17 Appendix A 18 Page 2 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390, oc ID:.COLR Limerick 2. Rev. 7-CIE List of Tables -, ..Page TABLE 3-1 MAPLHGR Versus Average Planar Exposure -GE14 6 TABLE 3-2 MAPLHGR Versus Average Planar Exposure -GNF2 6 TABLE 3-3 MAPLHGR Single Loop, Operation (SLO) Reduction Factor- -Gp.14 and GNF2 6 TABLE 4-1 Operating Limit Minimum Critical. Power Ratio (OLMCPR) -GEl4 8 TABLE 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) -GNF2 9 TABLE 4-3 Power Dependent....CPR LM..itAdjustmepts. and Multipliers MCPR(P) and Kp 10.TABLE 4-4 Flqw Depqndprqt.MCPR Limits MCP.R(F), .10 TABLE 5-1 Linear Heat Generation Rate, Limit- Lfor..UQ 2 J,9,ds ....11 TABLE 5-2 Linear Heat Generation Rate Limn'gipfor Gad: Rds. , 12, TABLE 5-3 LHGR Single Loop Operation.,(SL.)Reductiog.F.ato0:- GE14: and GNF2 12 TABLE 5-4 Power Dependent LHGR Multiplier LHGRFAC(P). 13 TABLE 5-5 Flow Dependent LHGR Multiplier LHGCR_AC(F) ý .13 TABLE 6-1 Rod Block Monitor Setpoints .14 TABLE 6-2 Reactor Coolant System Recirculation Flow Upscale Trip ..14 TABLE 7-1 Turbine Bypass System Response Time .15 TABLE 7-2 Minimum Required Bypass Valves ToMaintainSystem Operability 15 TABLE 8-1 OPRM PBDA Trip Setpoints, 16: TABLE 9-1 Modes of Operation 16 Page 3 of 63 Exelon Nuclear -Nuclear Fuels'Core Operating Limits Report Non-Proprietary ,lnformatilon Submitted in AccordcincWith' 1'CF'2.39O

1.0 Terms

And Definitions Doc ID: COLR Limerick , 2, Rev. 7 ARTS BASE DTSP EOOS EOR FFWTR FWHOOS HTSP ICF ITSP LHGR LHGRFAC(F) LHGRFAC(P) LTSP MAPFAC(F)MAPFAC(P)MAPLHGR MCPR MCPR(F)MCPR(P)MELLLA OLMCPR APRM, RBM, and Technical Specification Improvement Program 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) at any point during the cycle in.Dual-Lopýffiode and also :ahalyzed. iin.Single-Ltoop mde. ,-'RodBlock Mdni'tor D6ivdýcale-Trip Setpoirit

.,., Equipment Out of Se;vce. '
-.,"End of Rated, the cycle exposure atAhicE ie&dt6& p06eris equal to rated therml power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwatee hetidm t

Xenon.Final Feedwater TemijýeltUrý R Redtibi"Y

  • i.
  • t.-,,-, -i.Feedwater Heaters-O1t.-of .ii -. '-.'; ". ..- o"., , > -: .-.. :.* L.Rod Bl&k Mdnitd&High!

Frip'~tpint) -' .-'" t., Increased Core Flw .... ..Rod Block Monitor hintermediate Trip: Sepoint ' " Linear Heat Generation Rate .-'-ARTS LHGR thermal limit flow dependent multipliers, ARTS LHGR thermal limit power dependent multipliers -Rod Block Monitor Low Trip Setpoint ARTS MAPLHGR thermal limit flow dependent multipliers ARTS MAPLHGR thermal limit power dependent multipliers Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio ARTS MCPR flow dependent thermal limit ARTS MCPR power dependent thermal limit Maximum Extended Load Line Limit Analysis Operating Limit Minimum Critical Power Ratio Page 4 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in rick Rev. 7 Accordance with.10.CFR 2.390 Doc k : o ri OPRM PBDA Oscillation Power Range Monitor Period Based Detection Alg 9 n" thmf RPTIS Recirculation Pump Trip in Service , RPTOOS Recirculation Pump Trip Out of Service e -SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single. Loop Operation* C'. ..,. 'a L a .TBViOS Turbitie Valves in.- Seice .. , .TBVOOS Turbine Bypass Valves Out of Service 2.0 General Information This report provides the following cycle-specific para-ileter limits for Limerick Geperating Station Unit 2 Cycle 1 2 :.. ...,. ...' " ". ...* Maximum Average Planar-Linear Heat.Generation Rate (MAPLHGR).

  • Minimum Critical PowerAtio (MCPR), " -'Single Loop Oppraioi nSLO) MCP-. adjustment-
  • ARTS MCPR ther..al-.imait adjustments-ad m ultipliers_(MC.

PR(P) or. MCPR(F))* ARTS LHGR thermal limit.multipliers (LHGRFAC(P) ot. LHGRFAC(F))..... ti* Rod Block Monitor (RBM) setpoints* MAPLHGR single loop operation reduction factor ..* LHGR single loop operation reduction factor* Linear Heat Generation Rate (LHGR)* Turbine Bypass Valve parameters .,. -,F Reactor Coolant System Recirculation low Upscale Trips -o,.Oscillation Power Range Monitor .Period..Based Detection Algorithm (OPRM PBDA) Trip Setpoints This report is prepared in accordance with Technical Specification;6.9.1.9 of Reference E Preparation of this report was performed in accordance ý,ith ExelonNuclear,-Nuclear Fuels T&RM NF-AB-120-3600. The data presented in this report is valid forall licensed operating domains on the operating map, including:

  • Maximum Extended Load Line Limit down to 82.9% of rated core flow during full power operation" Increased Core Flow (ICF) up to 110% of rated core flow* Final -Feedwater Tempe~rature Reduction (FFWTR) up to'105°Fduring cycle extension operation" Feedwater Heater Out of Service' (FWHOOS) up to 60'F feedwater temperature reduction at any time during the cycle prior to cycle extension.
  • The Limerick 2 Cycle .12 reload licensing .anralyses were performed at 3515 MWt. The Limerick COLR, "COLR Limerick 2, Rev 7," is applicable for operation at both 3458 MWt and 3515 MWt (Reference 2).Further information on the cycle specific analyses for Limerick 2 Cycle 12 and the associated operating domains discussed above is available in Reference 2.Page 5 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Inkormation Submitted in Accordanbý with 10 CFR 2.390 Doc ID COLR Limerick 2, Rev. 7 3.0 MAPLHMGRLiniits

.' '3.1 Technical Specification Section 3.2.1 3.2 Description The limiting MAPLHGR value for the most limiting lattice (exclu.ding natural uranium) of each fuel type as a function of average planar exposure is given in Tables 3-1 and 3-2 (Reference 2)., For single loop operation, a reduction facior is tisid wvhi'ch is show niri Table 3-3 (Reference 2).MAPFAC(P) and MAPFAC(F) are 1.0 for all power and flow conditions. The power and flow dependent multipliers for 'b'eenifemoved ird replaced with LHGRFAC(P) and LHGRFAC(F). LHGRFAC(P) and LHGRFAC(F) are addressed in Section 5.0..................... ... *T L 7J ..TABLE 3t-MAPLHGR6 Versus Average'Planar Exposure -6E14 (Reference 2)Average Planar Exposure ,.i",i' ;MAPLHGRLimit, .. .... * ..(GWD/ST) .*(kWft)-'0.0. I,12.82: ,~ ,. 12.82 .: ...' i;..19.13 -. ... 12.82 .57.61 : ... -,:.. ,8.00 ' .; ' .'63.50 ., 5.00 TABLE 3-2 MAPLHGR Versus Average Planar Exposure -GNF2 S..(Reference 2)' " Average Planar Exposure MAPLHGR Limit (GWD/ST) ..(kW/ft)0.0 " ' 13.78 17.52 .13.78 60.78 7.50 63.50 6.69 TABLE 3-3 MAPLHGR Single Loop Operation (SLO) Reduction Factor -. GE14 and GNF2 (Reference2). SLO Reduction Factor 0.80.1 1" Page 6 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Roc, IDc cbLR Limerick 2. Rev. 7 4.0 MCPR Limits 4.1 Technical Specification .Section 3.2.3-.4.2 Description." Tables 4-land 4-2 .re derived from Reference 2 and are valid for all operating domains. Table 4-1 is valid for GE14 fuel and Table 4-2 is valid for GNF2 fuel. Tables 4-1 and.4-2 include treatment of, these MCPR limmisfor SLO. Botinding MICPR values are-also provided for RPTOOS or TBVOOS: These hwo o-ptionqs repiesent tfie Equipment out of Service conditions. ARTS provides for power and-flow-cipendent thermal limit adjustments and multipliers, which allow fOr a morc reliable' adm..I,-i3atizn. of .-he--MCPR thermal limit, *The flow dependent adjustment MCPR(F). is sufficiently-generic to apply to all fuel types and operating domains (Referen..

2) .. .Jn ad~di~ti, there are, .s' set~s .of power depenide;nt .MCPR multipliers (Kp) for use withb. -ie TBVIS. and'lRTIS,.
TBVOOS, .RPTOOS, Dual Loop Operation and SLO conditions (Reference 2).- Section, 7.0 contains the cohditions for Turbine Bypass Valve Operability.

ARTS MCPM-thermal limit adjustments are provided in Tables 4-3 and 4-4. The OLMCPR .is determined 'for a given power and flbw.:.cdndiotio by evaluating the power dependent MC 'R and the fl6iw dependeAi MCIkR aii" selifing-the: grieater of the two. The MCPR(P) values are independent of recirculation pump trip operability. Tables 4-3 and 4-4 are applicable to both GEl4 and GNF2 fuel types.Page 7 of 63 Exelon Nuclear -Nuclear Fuels ,Core Operating Limits Report Non-Proprietary Information Submitted in Accordaih1c

with iO-&FR'ý.396
  • , C _. 0 ; "" ". e ,'k .- .7 Doc ID! Limeri'ck 2, Rev,. 7 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) -,GE14 (Reference 2)SCRAM Cycle Exposure Time < EOR -5475 > EOR- 5475 EOOS Combination Option' MWd/ST MWd/ST.'B .. " " .43 ..143 2 .BASE A ' 1.43(g);, 1,_-t!43-B: 1.46 1.'46 BASE SLO(') A.. .....1.46 "1.46 B .143(2) 1.44 TBVOOS A 1.4.... ' .147 T .B ... ..1..46 4 ..1.547-R .TVO ,, A. .0, J.4 ,... .1.65 RPTOOS -144 ." 1.658.. .'lB, .." , ...1.51:. RPTOOSSLO (3)' .. .' vA,, " .i. 1 47'. ,, "I -£t. 68"!4.I-,.":"T," When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

2 Value is adjusted to obtain an OPRM amplitude setpoint of 1.12.3 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed two loop value. However, a minimum value of 1.43 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).'Page 8 of'63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance withi 10 CFR 2.3p0 P~ D' .CQLR L-im, qdgksý,-Rev. 7-' .~-: ., -, , ...:.: , ; ,.-,TA B L E '!-2 .. .* ; -.-Operating Limit Minimum Critical Power Ratio (OLMCPR) -GNF2 (Reference 2)SCRAM' Cycle Exposnr. .Time < EOR-5475 >EOR -5475, E00S Combination Option 1 MWd/ST MWd/ST_13B 1.43(2) 1,____46_BASE A1 " .43(2)1 -:, .1:8..~ 1.54.... .. ... .. '_ .. ..B .. * ." 1.54 k -. 1.54 BASE SLO ) ; A:.- ... 1.54- .. .1.54.. .-B .-1.4312) .1.49-."TBV S ...A-' 1.43(2) 1.54-TB- 1.54 ...1.54 TBVOOSSLO(3) ' A -1.54 ..--1.57 ..." .4 2);" ' 1":51 RPTGOS A .:I.45- 1.61 lS - jj .A , ! 514"7 , -1.64 .. .I, 1 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation. 2 Value is adjusted to obtain an OPRM amplitude setpoint of 1.12.For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed two loop value with a minimum value of 1.54 to obtain OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure (Reference 2).Page 9 of 63 Exelon Nuclear -Nuclear Fuels.Core Operating Limits Report Non-Proprietary Information Submitted in Accordance: with i 0'CFR 2.390'Do6 ID:COLN'Lihierick 2,'Rev. 7 TABLE 4-3 Power Dependent MCPR Limit Adjustmelnts and Multipliers MCPR(P) and Kp., (Reference 2)i -Pore'. Core Thermal Power (% of Rated)EOOS71--. flow 0, 25 I <30 >30 45 60 85 100 Combinatioi, I.(%.of "".rated, ..-MCPR(P) .._Operating-ldimit MCPR Multiplier, Kp60 2.71 1 271 2.49 , Base <6 2.7 2.71 2.4......L481 ..... .L280 .. L.150 1.099 1.000> 60 .3.45 .3.45 098 .___< 60 2.74 2.74_ -s--- 52 ..9 Base SLO -- .,2.52 22I481- iO..1150. 1.099 1.000 5'"60 ' 3.48"_ 3.7_8-_'__. 0_.< 60 3:13 '3:613 -- :-2.68 --TBVOQS 60 462 1:-218- 1.481 i.280 1.150 1.099 1.000 TBVOQS.. > 60 4-.462 17 4.62- ....`3-.84"" ............. ....TBVOOSSLO <60 3.16.-:16 2.- 1'.481 '"1.280 "1.150' 1.099 1.000.. >60 4.65 .:..4 6 5 . .... ........ .. 60 -2.7.1-'- '74 --1 -.. ..2-49 -'-RPTOOS .< 2.71- -- ..2.9-.1.481 1.280, 1.150 1.099 1.000>.>60- -3.45.__ __ __ __RPOSSL 60-1 -2,7 2,7 _26ý_-___ ý274-- 2 4 -. 152.-. ' 481 '. .1h.28 [.,' 1.j50. 1.099 1.000 RPTOOS S..>-60., -3.48 3"48 -.. -.TABLE 4-4 Flow Dependent MCPR Limits MCPR(F)(Reference 2)Flow MCPR(F)(% rated) Limit 30.0 1.53 79.0 1.25 110.0 1.25 Page 1.0 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Doc ID-:COLR Limerick 2, Rev. 7 5.0 Linear Heat Generation Rate Limits 5.1 Technical Specfficatin .'. ..n-i. ..¢ 'Section 3.2.4 5.2 Description The LHGR limit is the product of the exposure dependent LHGR limit (from Table 5-1 for U02 fuel rods and Tablý 502 fir'.G.doniiaiiihfuelr6ds)aaid-the miniffium-of: ihe power dependent LHGR Factor, LHGRFAC(P), and the flow dependent LHGR Factor, LHGRFAC(F). For single loop operation, faktor is iied, Wndicig sfiown'in Tible"5-3and'applied in Table 5-5 (Reference 2). No further Single Loop Operating reduction factors need to be applied to the values in Tables 5-4 and 5-5.ARTS provides for power and flow dependent thermal limit multipliers, which allow for a more reliable administration of the LHGR. thermna limits. There are two sets of flow dependent LGHR multipliers for dual-loop ard-single-loop oDeration (Reference 2). In addition, there are sxetsof power dependt Lrnii~k imullipiierg for use With the 'I ViS and RPriS, TBVOOS, RPtOOS, Dual Loop Operation and&SL'O'c'6riditions (Reference 2). Tables 5-4 and 5-5 LHGRFAC(P) and LHGRFAC(F) are applicable to both GE14 and GNF2 fuel types. Section 7.0 contains.the .ypass.Va!ve Operability-, The LHGR multipliers are shown in Tables 5-4 and 5-5. Linear interpolation should be used for points not listed in Appendix A.Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power and flow biased calculation. The LHGRFAC(P) values are independent of recirculation pump trip operability. TABLE 5-1 Linear Heat Generation Rate Limits for U0 2 Rods (Reference 9)Fuel Type LHGR GE 14 See Appendix A GNF2 See Appendix A Page 11 of 63 Exelon Nuclear -Nuclear Fuels ,Core Operating Limits Report Non-PIropri, tary Irfornjation Submitted in Accordance with 10 CFR 2.390 Doc ID: COLR Limerick 2, Rev. 7' , '" $ j ': TABLE 5-2 Linear Heat Generation Rate Limits for Gad Rods-.(Reference 9)Fuel Type LHGR GE14 See Appendix A GNF24FI, '-.Seep'pendii xA..777",. , o .7 * .:,,-. j: -. , : ..-: ':. 'LHGR Single Loop Op eratin (SLOe R,!c4iqon Tnactor dEl4 and GNF2 SLO Reduction Factor I: I 0.86 I;,;' Applied through Table 5-5 Page 12 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with, 10 .CFR 2.390 DoqI D-.CCLR UJmedc',.* 2, Rev. 7 TABLE 5-4 ', Power Dependent LHGR Multiplier LHGRFAC(P)(Reference

2) ",..Core Core Thermal Power (% of rated)EOOS Combination Flow EOOS(% o 0 25 <30 >301 0Q -rated) LHGRFAC(P)

Multiplier

  • 1 <ý60 0.485 0.485 0.4906 E:.. ., a e,.,, -, t 0,64....0 Base>601 0.434 -0.434 0.473"60 '0.485 0.485 0.490:BitseSLO

--- ----- 0.634 1-.000>"60 .'6.434"' 0434 0.473.-.. O S -,, .<60 0.463 0.463 0.490 '0.634 1.000-. .... .-64".0..... >,60 0.352 0.352. .0.386 TBVOOS-Sw.O <60 10..463, _04631 0.490 0.634 1.000>60 0.352 0.352 0.3867 RPTOOS <60 0.485 0.485 0.490 0.634 1.000>60 0.434 0.434 0.473 S<56:'0 15; "0.485 0.490 RPTOOS SLO 7 V -.4 0.634 1.000-.: ,;6 ,0;.,43K.

434 :.,0.473,': ,_ 2 .,~ 1~4)LE5-.57 Flo Deenet IGM-Multiplier LHGiUFACF)

-,-.(Refere'nce'2) -i L-Core Flow-(% of rated)..EOOS Combination 0 44.07 -. 70 .. 80- .110-...... -LHiGRFAC(F) Multiplier. Dual Loop 0.506 0.973 1.000 1.000 Single Loop 0.506 0.800 0.800 0.800 0.800 I, Page 13 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in 10.CFR22.390i

6.0 Control

Rod Block Setpoints 6.1 Technical Specification ": .;* ,.! " ' " .,- : -..Doc ID:-CLR Limerick 2.Rev. 7.- s c7--f .4and336 5.3.6...............

6.2 Desi1nht1on

.. ..,.Teclhik-al-Speifica-ti0Tr=Y3 3:&t~es channels shall be OPERABLE with their tfip setloirts'-cosisteht-rith the values~sh6wn in the Trip Setpoint column of Technical Specification TAble _3:3.6 _The- ARTS Rod-Block Monitorý provides for power-dependent RBM tnps.--4he v-oirlt/altýable 'alues and'applicable RBM signal filter time constant-data are -shown-in-Tible-6-1.---4.' Reactor Coolant-System Recirculation Flow Upscale Trip is a cycle-specific value-and as-sudh- foum Table 6-2 of this COLR1 Table 6-2 lists the Nominal Trip- Setpboit-and Alowable-i:Vluo.--Thes-setpoints-are set -high 'enough to allow full utilization of the e hnýed ICF 4ýin p .ift. H.1%of re f1ov{; These values are for use with Technical Specificiti6n3.-.6. _ .: '" ' " o '" -..... .... .."' .... ...,; ' ' "' ._ .Rod BlockM6nitor Setomints (References 2 and 8)Nomi.a..T.... .oint Allowable Value LTSP " 121.5%-.~- --- W~5016-..HTSP '- ..-% -- 111.7%-DTS? q ,. 7 0 ... .2.0%...... ... .. ........ ..T A BLE 6-2 -... ..Reactor Coolant System Recirculation Flow Upscale Trip (Reference 8)Nominal Trip Setpoint 113.4%Allowable Value 115.6%i: 1 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 1.32, which is less than the minimum cycle OLMCPR (see COLR References 2 and 8).Page 14of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390.", .... -, ..* 1 ' ." , .' .', Doc ID: COLR.Limerick2, Rev. 7 7CP1V.1S 013j C-ixve~.7.0 Turbine Bypass Valve Parameters

7.1 Technical

Specification Section 3.7.8 and 4.7.8.C 7.2 Description The operability requirements for the steam bypass system for use in Technical Specifications 3.7.8 and 4.7.8&C ki- foiund in Tables 7-1 and 7-2. If these requirements carot; 6e met, the MCPR, MCPR(P) 'aid 'LHGRFAC(P)'Iimitý for'i .p rable -steam Byjiass Systein, known as Turbine Bypass Vaive Otit"Of rnu~t ~beused. Additional informaion on the operability of the turbine bypass systerd can b'e'fouaid ii` Reference 1L.'TABLE 7-1 Turbine Bypass -Sytem Response Time (Refeienice 54)Maximum oir 6t b...0. V al eiig 6P6 following generation of the torbmne.bypas-valye flow signal J / -0.11 sec Maximum time after generation of a turbine bypass valve flow signal for bypass valve position to reach 80% of full flow 0.31 sec (includes the above delay time)TABLE 7-2.Minimumn Required Bypass Valves To Maintain System Operability (Reference 5)No. df ValvesA n girvic-e.7" II Page 15 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report NonFrPoprietary.lifofmation Submitted in Accordance with 10 CFR 2.390 Doc ID: COLR Limerick 2, Rev. 7 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1.2.F 8.2 Description ,The Limerick,2 Cycle 12 OPRM Period Based Detection .Algoi'thr, (PBDAj) Trip Setpoints for the OPRM System for use in Tec"iahCl Speification 2.2i,. are, foundin. .able.8-1. These values ,. .., ased on h.c pcific analyis documented in Reference.2, Tle setpoints provided in Table 8-1 are bounding for all modes. of qper ý,iohoiWyn*n Table 9-J, OPkR ArQM]K ' (Reference 2)PBDA Trip Amplitude 6a' 8dC d , ., im ul. .*PBDA Tr

  • II [6. nfiri-tkon Codnt Ttip Setting.--1..1 1.12 S ] <14 9.0- Modes of Operation..........................

.....-TABILE 9-1.Modes of Operation 2)1*~**4 4 4.. EOOS Options- ... .... .Operating Region'Base, OptioiiVA'ri B Y- '-' Yes Base SLO, Option A or B Yes A orB ... .... ... .Yes..TBVOOS SLO, Option A or B Yes RPTOOS, Option A or B Yes RPTOOS SLO, Option A or B Yes Operating Region refers to operation on the Power to Flow map with or without FFWTR.Page 16 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 IorP'9QL~R limerickZ Rev: 7 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 document: 1. "General Electric Standard Application for Reactor Fuel", Global Nuclear Fuel Document, NEDE-2401 I-P-A-17, September 2010 and U.S. Supplement NEDE-2401 1-P-A-17-US, Revision 17, September 2010.2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", GENE Document, NEDO-32465-A, Re. C, , .igust 1996.11.0 References

1. "Technical Specifications and Bases for Limerick Generating Station Unit 2", Docket No. 50-353, License No. NPF-85, Exelon Document.2. "Supplemental Reload Licensing Report for Limerick Unit 2 Reload I I Cycle 12", Global Nuclear Fuel Document No. 0000-01 18-5622-SRLR, Revision 0, February 2011.3. NOT USED 4. NOT USED 5. "Final Resolved OPL-3 Parameters for Limerick Unit 2 Cycle 12", TODI: ES 1000015 Rev. 0, December 2010, Exelon Document.6. NOT USED 7. NOT USED 8. "GE NUMAC PRNM Setpoint Study", LE-0107, Rev. IA, April 2011, Exelon Document.9. "Fuel Bundle Information Report for Limerick Unit 2 Reload 11 Cycle 12", Global Nuclear Fuel Document No. 0000-011 8-5622-FBIR-P, Revision 0, February 2011.10. NOT USED 11. "Tech Eval Stop Valve Load Limit Documentation", Exelon Document IR 917231 Assignment 7, November 11, 2009.Page 17 of 63 Exelon Nuclear -Nuclear Fuels'Core Operating Limits Report Non-Proprietary Information ,ubmitted in Accordance with 10 CFR*2.39O Doc' ID: COLR Limerick 2, Rev. 7£ I '-.£ 1 * , y f ": , .I-: Appendix A ...' -, J Page 18 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Doc ID: COLR. Limerick 2, Rev. 7 Accordance with 10 CFR 2.390 ppendix.-.

... Glcbal Nuclear Fuel.- Americas .AFFIDAVIT I, Russell M. Fawcett, state as follows: .(1) I am Manager;, Core,, Fuel, and Advanced. Design, Global Nuclear Fuel -Americas, LLC.("GNF-A"),. and have been delegated the function of reviewing the information-described in paragraph (2), which ,is sought to be withheld,:.and have been -authorized to apply for its wi~thholding.

.. ,.(2) The. information sought to be withheld is contained in 0000-0,1 18-5622-FBIR-P, "Fuel Bundle Information Report for Limerick .Unit 2. Reload. 11 Cycle 12," Revision 0, dated February 2011. GNF7A, proprietary information in 0000-0118-5622-FBIR-P, is identified by a dotted underline inside double, sqt~arebl'ackets.

[[.Th.is sentence is an_.e..aj] A"" marking at the beginning of a table, figure, or paragraph closed with a "" marking at the end of the table, figure or paragraph is used to indicate that the entire content between the double brackets is proprietary... In-,each case, the superscript notation {31 refers -to* Paragraph (3) of this Affidavit, which prpvides the basis for the proprietary deiermination. k i , t .... .. f.r .. ... ... .... ., 1 * ,..(3) In making *this application. for withholding of,proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material forwhich exemption..fro disclosure is here 3ought also qualify under the narrowerdefinition of "trade secret'; within the meanings assigned to.those terms for purposes ofFOIA Exemption, 4 in,, respectively, Critical Mass Energy.,Proiect.. Nuclear Regulatory Commission, 975F2d87,1 (DC.Cir. 1992), ,and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983). -I. .......* ...;" (4) Some examples of categories of information. which fit,.into the :definition of proprietary information are: a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention-,of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;

b. Information which, if used by a competitor, .would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar.product;
c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;0000-0118-5622-FBIR-P

.Affidavit Page I of 3ý COLR Page 19 of 63 Exelon Nuclear- Nuclear Fuels Core Operating Limits Report :" ".';" -" Non-Proprietary'Information Submitted in Doc ID!'COLR, Limerick 2, Rev. 7 Accordance with 10OCFR'2!390 Appe'ndix' 'A d. Information which discloses patentable isubject ý natter for which it may be desirable to obtain patent protection. The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.(5) To address I0:-CFR 2.390 (b) (4), the infobnidtion soig&t t&,be being submitted-toNRC in confidencei Thý informationtN ofW so cuStoiiiaiilý hre'ld in'coifidende'by GNF-* .; .It .;ý' ihh l has ;t ,.-b s f m A, arand is in' fact so- held. The- itfOrmatlion fs6ught to be'witih1d has', to thebestof my knowledge and belief, consistently been held in confidence by GNF-A, no:public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals 'to NRC, ma de; -or must be made, puirsuant to regulatory provisions or proprietary agreemn`6ts which pi'ovidef flb* maintenance of the information in confidence. Its 'initial-desýignation as 'prpnet'ýary infoimation, and the subsequent steps taken to r'event 'iis'iuinaithotied'di~llos"e',"are a§ set forth in paragraphs (6) and (7) following. ...."'(6) initial appioval pi'6pi'ietai 'a document if mhdebtyhe manager of the°nginating component,- the'* prson 'Mo6 lihkely to 'be' acqtiaiiited With the value and sensitivity of the information in relation to industry knowledge, or subject to the terms tinder'which it wa's licensed f6-GNOFLA) ' O' such "documents" withi .GNF-A is limited'on a "need toknow,,'bais." ': .,, * ., .(7) The procedure for approwl 'of exterfial ieleiee- 6o such a document typically requites review by the staff manager, I projec.t :manager, jrincipal scientist or other equivalent authority, by'the manage .of the Cognizant 'miarkdting' funi6bn. '(or his 'delegate), and 'by the:- Legal--' Operation, fi.. techinichl 'content, competitive effect-'and determination of the accurhcy of.. the propnetary deslgnatin. Dis'closuires 6utside GNF-Adiare limited to:.-regula'tory! bodies, customers, and potential customers, -and theii agents,- suppliers, and- licensees, 'and 'others with a legitimate need for the information, and then only in accordance with appropriate regulatory'prov'isions'or proprietary Agreerients. (8) The information identified in paragraph (2) is classified as proprietary because it contains'deta'ils of GNF-A's fuel design and licensing methodology.

The development of this methodology, along with the testing, 'development and approval x.vas achieved at a significant cost to GNF-A or its licensor.The development of the fuel design and licensing methodology along with'the" interpretation and application of the analytical results is derived 'from an extensive experience database that constitutes a major GNF-A asset.0000-0118-5622-FBIR-P Affidavit Page 2 bf 3 COLR Page 20 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report .Non-Proprietary Information Submitted in Doc ID: COLR Limerick 2, Revi 7 Accordance-with 10 CFR2.390 ,-:1:,Appendix A,-C i,) 01 dw -on,..'.(9) ubilc,..discosure;.:of the iaformation sought .to.. be. withheld is likely.-to-ca-u-se.

substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and techndcgy .base, and its commercial value extends beyond the original development cost.The' value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.The precise value of the expertis e. io-devise an.'evaluation process and apply the correct analytical methodology is difficult to quantify' but it clearly is substantial. GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same. or similar conclusions. The value of this informatio.0, ta GNIF-A. wpyuld.e. lot.. if, the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A 4of itie opportunity to exercise its competitive advantage to seek an adequate return on its lirge investment in developing and obtaining these very valuable analytical tools.I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.Executed at Wilmington, North Carolina this 1 4 th day of March 2011.Russell M. Fawcett Manager, Core, Fuel, and Advanced Design Global Nuclear Fuel -Americas, LLC 0000-0118-5622-FBIR-P Affidavit Page 3 of 3 COLR Page 21 of 63 Exelon Nuclear -Nuclear Fuels<Core Operating Limits Report Non-Proprietary Information:i ubmitted in Accordance with 10 CFR 2.390 1 ., .",,I.I,: V , ..., Doc ID'.COLR Limerick 2, Rev. 7 Appendix A Global Nuclear Fuel.A JpintVenture of GE, Toshiba, & Hitachi 0000-0118-5622-FBIR-NP

  • . ' ., -...Revision 0 , r' *.. ...- February 2011 Non-Proprietary Information S'.CaI( lc)';~ ~ ~ ~~~~. ......................
  • .- .........

... ... .--..-( ' 'I ~.~. .'. las[ ,,,b i)i ,!,= .I' -.i',j Fue1 Bundle; lnfdrnatlion Repoxt t: t:Limerick' Unit 2 , ., Reload 11 Cycle 12*'t, Copyright 2011 Global Nuclear Fuel -Americas, LLC All Rights Reserved COLR Page 22 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Doc ID: COLR Limerick 2, Rev. 7 Accordance with 10 CFR'2.390 ex A , Limerick Unit 2 .Non-Proprietary Information 00bf-o Reload 11 Class i (Public) It Revision-0 Important Notice Regarding Contents of This Report" :,:. , -i" .t: '" t 'Please Read Carefully This report was prepared.by ,GlobaliNuclear. Fuel t- Americas, LLC..(GNF-A) solely, for use by Exelon Corporation ("Recipient") in support of the operating license for Limerick Unit 2 (the "Nuclear Plant").The ihforination'containcd-in this -iepiort"(the "Iff0itioh")' believcd byGNF-A t6 ben accurate ard Strie' representation of;hlie facts: known by,'bbtained by or-:provided ,td GNF-A at-the tittle this report was pepa.ed.The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A fori nuclear, fuel arid related set-Vices; forlthe NuclearPlant(the:¶!.Ftfel ContractO)'and nothing 'contained in: hisi docum-.ntfshallbecb sttMuedas:anmendiag or modifying theFdel Contract.,, The use. of the. Information for any pýurpose. othernthan, thatv for' whichit was ýintended under rtheFuel Contract, is not authorized by GNF-A. In the event of any such unauthorized tise,,.GNF-A neither (a) mahes .any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness 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 0000-0118-5622-FBIR-P, which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside open and closed bracket as shown here [[Page 2 COLR Page 23 of 63 Exelon Nuclear -Nuclear Fuels.-'Core Operating Limits Report ,. ..Non-Pfopnietary Inforation Submitted in Doc ID.:-COLR Lirmerick 2 .Rev. 7.ej, _ Appendix A nini 0i Non-Pi'borietarl information 0000-0118-56522-FBIi-NP.leld-" ........ ---Cfass 1-(0'bfic) .ReOi-ion 0 1. Introduction and Summary 10 f,: .; 1, .I, , ..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 Unit 2 for Cycle 12. These LHGR limits are obtained from thermal-mechanical considerations only. Approved GNF-A dalculation inodels d6cumented in Reference lFwere .usediniperfotmifig this analysis. ".LHGR limits as a function of exposure for. each, bundle , 9 f the core.design, are~given..in Appendix A. The LHGR values provided* inAppeondixA provide uppeT aqpd..tower eposure .dependent,.LHGR boundaries which envelope the actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded to two places past the decimal.::Appendix -B contains .a description of. the fuel blmdles., Taible _-1 J ootin3 ,a stnnary of bundle-specific ,:information., and the. figures provide the.enrichment,1distributtion.,and~gadolinium distribjution, for the fuel bundles included-id this.appendix-T.hesek bundles hav~erbejn..approýed~for use; under the fuel licensing jacceptance criteria.of Refetence 1 ... .. ." "-.3:..., .,',. ..".' .*r',; ,, ;. .'/ t : :- i8 , ,. r ...!:. , .. '... .. ... ..V.*n. ' .,. , .' : .. , Page 3 COLR Page 24 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non'Proprietary Infornation Submitted in Accordance with 10 CFR,2.390. Limerick Unit 2 Reload11: .,' c ID: COLR Lirnerick 2, Rev. 7 Afpendix' A.'0000-Oi 2-15iD,.lR-NP .....e~.tsion 0 Non-Proprietary Information ý -Clas I (Public_)2. References "" , *'-* ... ...";" .' .. i .,, 1. General Electric Standard Application for Reactor Fuel, NEDE-2401 1-P-A- 17, September 2010; and the U.S. Supplement, NEDE-2401 1-P-A- 17-US, September 2010.;' .; : .- ., , .....: ..... ..,.. ., ,...-.., ., ..., .t .-. ..,.~, ...., .., -Page 4 COLR Page 25 of 63 Exelon Nuclear -Nuclear Fuels.Core Operating Limits Report Non-Proprietaýy Information Submitted in Accordance with 10 I Limei-.- .[ .1 0-00CO Reload:IT1 ..Doc ID: COLR. Limerick 2,:Rev. 7 Appendix(A f,- -.., 0000-01 1 8-5622-EBIR-NP Revision 0 Non-Proprietary Information -Class I(,Pubic)Appendix A UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 1OCG2B386-2G8.0/13G7.0-120T2-150-T6-3644 (GNF2)Bundle Number: 3644 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'GWd/MT (GWd/ST) kW/ft[[I_____________________ _________________________________ ]]' Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [[Page 5 COLR Page 26 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10- CFR 2.390 Limerick Unit 2.SReload:l I Non-Proprietary Information -Clas' I (Public)Do' ID: COLR Limerick 2, Rev. 7 r .,' C.I;,ri P d !x A0..... l.~~~ 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB389-14GZ-120T- 150-T6-3157 (GE 14C)Bundle Number: 3157[.. Peak. Pellet-Exposure- .-.. U0 2-LHGR.Limit GWdIMT'1I'(W TG" 'W a / " kW/f'........ 0. .00) ............ -.2 -.. ~.......6,0o.(14.sl) .-..-+...... ' -.11.4G..... ......63.50157.61-) ._.. '.8.00 ..I ... 70& 0 (63.50) ......i ' '... ".5,00".:. .. ., Peak Pellet Exposure.,. Most Limiting Gadolinia.... ' ' 3" LHGR'Limit GWd/MT- (GjWd/ST) .kW/ft d.00 (0.00),.... .-12 Z.00.13.42(2.17) 12.00..60.17(54.59) '7_6....... ...7 ....-.. 66.57 (60,39) ......4.48 2 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 7.0% Gd).Page 6 COLR Page 27 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information.Submitted in Unit 2 Reload 11 Doc 11D: dOLR Linierick,2, Rev. 7 Appendix A 0000-Oi 18-5622-FBIR-NP Revision 0 Non-Proprietary Information -Class I (Public)UO 2 1Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-PI OCNAB389-15 GZ- 120T- 150-T6-3158 (GE 14C)Bundle Number: 3158 Peak Pellet Exposure re ,OLIGR Linit..GWd/MT (GWd/ST) .k-W/ft 0..oo (o.o0 o ..... --3 16.00"1(t4:51 1-340....63.50-(57.6r).....-- .. .. .... -: 8:00;- ...170.00 (6350) Peak Pellet Exposure Most Limiting Gadolinia,'LHGR LfmitV-...GWd/iMT (GWdiST) kWlft--... .00)... 12.00 ...12.0o-6 0 : 7 "( 5 4 _5 9 ) .. 7 .1 6 .'66.57"(60.39) .. 4.48 .3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 7.0% Gd).Page 7 COLR Page 28 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Inforfnation Submitted in Accordance with 10 CFR 2.390 Limerick Unit 2 Reload'1 I.,"Doc :D: COLR Limerick 2, Rev. 7 O .... -ýrjn-0000-011 8-02,2I2EBIR-NP Revision -0 Non-Proprie*tary Information -Class I (-Public),.UO/2 Gd ThermalkMechanical LHGR.irMits Bundle Type: GEI 4-P 1OCNAB391-lI:3GZ-- 120T- 150-T6-31"59 (GE44C)Bundle Number: 3159 Peak P.iletexpboure i U0 2.LHR"Limit GWd/MT'(GWd/ST) -kW/ft .: 0100 (i0.00) '1340'16.00(14.51) -.13.0'63:50,(57.61) 800- -70.00 (63.50) 5!00" Peak Pellet Exposure Most;Linditing Gadolinia LHGR Limit 4 GWd/MT (GWd/ST) .kW/ft 0.00.( 0.00) L. 'M1.76 13.31 (12.08) 14176.59.76 (54.21) ' -. 7.02 66.12 (59.98) 4.39 4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 8 COLR Page 29 of 63 Exelon Nuclear -Nuclear Fuels iCore Operating Limits Report Nor-Proprietary Information-Submitted in Accordance with 10 CFR,:23,k* Lime jL-2 10- 0000 1 Doc ID" COLR Limerick 2,'Rev: 7 Appendx A 0000-01 18-5622-FBIR-NP 0 Non-Proprietary, Inforination ' -Class I (-Public]Reload I i Revisi6n 0 U0 2/GdThermaI-Mechjn!caI LHGR Limits Bundle Type: GE 14-P liOCNAB391-13G8.0-: 120T- 1,50-T6-3160 (GE 14C)'Bundle Number: 3160 P ., ". .' ,,. .PeakPellet. Exposure J 'U,O 2 LHGR-Limit GWd/MT'(GWd/ST) J k.Wif .0.00(' 0.00) 13 40 16.00:(14.51) 13 63.50 (57.61) i '- 8:,00..'.70.00 (63.50) J `.,5.00!i-Pea% Pellet. 'T,4, ostre Most Limiting Gadolinia , .LHGR Limit'GWd/MT (GWd/ST) lkW/ft" 0.00'( 0.00) 113.76 1331 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) :. 4.39 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 9.COLR Page 30 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR2.390 Limerick.Unit 2'Reload 1 I Non-Proprietary Information -Class I'(Public) Doc ID: COLR Limerick 2, Rev"'7.Appendix A. .*. C:.3 960-1011-"8 -556ý22-IR-NP Y tI 6 -sion 0 UO 2 IGd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 10CNAB390-12GZ-120T-150-T6-3161 (GE 14C)Bundle Number: 3161-Peak-Pellet Exposure.- -U0 2 LHGR Limit GWd/MT (,GWdIST, )-! -- W/ft -6 A0.00 (-.00) : -8100-16.'0(1.i. 13-3 .40.--- 63.150 (57.61-). ..I -8.00.... .. .0__ 0 ... ...... _-_.. .. ..... ... 5 0 0 ..... .Peak Pellet Expostre. Most Limiting Gadolinia"LHGR Limit 6 GWd/MT (GWd/ST) .kW/ft 0-.00-(0.00) -....... 7.....6 13.31 (12.08) 1 ..1.76 59.76 (54.21) .7:02-66:1-2 (59.98) .. 4,39 6 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in thig bundle design ( 8.0% Gd).Page 10 COLR Page 31 of 63 Exelon Nuclear -Nuclear Fuels.'Core Operating Limits Report Non-Proprietary Informatiorn Submitted in Accode,,w' A0,QFR2,3"* r..f-' .- , 14,-90o Limerick-Unit 2 Non-Propridtary, Information Rel6adT1........... -ClIassI (Pib-lic), ,, -":. .-... M..3 Doc ID:.,COLR Limerick 2,-Rev. 7 Appendix A 0000-0118-5622-FBIR-NP0 UJO 2/Gd T hermaI-Me(hanical LHGR Limits Bundle Type: GE14-PIOCNAB409-16GZ-120T-150-T6-2956 (GE14C)Bundle Number: 2956-Peak Pellet Exposure U0. --U 2 LHGR Limit- .....GWd/MT (GWd/ST)------- .-.kW/ft 0.00-(0.00)- ..410....- ..16.00, 4.{'451) -.. .. ... ......- ...---40. .. .. ..-... ... 63:-50-(57.6 -) .. .- .... ... ....8:00......... _____,__._"_____,___,___......--- _70.,0"-(63.50-)...... 5.00 .* Peal Pet.Fxposure Most Limiting Gadolinia. ..... -- -LHGR Limit'GWd/MT-(GWd/ST) -A- --- kW/ft.0.00-(0.00)- ............. 1.76 .13.-31 (1-2.08 .76 .1 E-....-59.76 (54.2) ..7.02-.-66.12 (-59.98)- ..... ...4.39.It r 7 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 11 COLR Page 32 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary. In-'ormation Submitted in Accordance with 10 CFR 2.390 Limerick:Unit 2, Reload 1.1 Doc ID: COLR Limerick. 2, Rev. 7 lendix. ,- , 0 0000-0 11 8-5,212ABIR-NP.Re~vision. 0 Non-Proprietary Information -Class I (Public)..U10 2/Gd Thermal-rMechanica, LHGRI.tmits Bundle Type: GE14.-P!10CNAB410-16GZ-120T-150-,T6-2950 (GE14C)Q.Bundle Number: 2950: ., -I -..I '..[ *PkPeUet. Exposure " U(2 LHGR Limit GWd/MT'(GWd/ST) " kW/ft,-0.00_(:0.00) 13.40: 16.QQ00(.14.51) .. .13.40 6350 (57.61) 8.;, .00 70.0-0.(63.50) .5i00'Peak Pe.let. Exposure Most JLimiting'Gadolinia LHGR Limit 8 GWd/MT'(GWd/ST) kW/ft: 0.00.(0.00) ' .,176 13.31'(12.08) 11.76-59.76 (54.21) .7.02-66.12.(59.98) -4.39 8 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8:0% Gd).Page 12 COLR Page 33 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Inforniation Submitted in Accordance with 10 CFR2q3SO0'Limefidk,1lhit-21 10-0000"Reload lTl , , ,- .-'! " .,"F : Doc ID: COLIR Limerick 2:.Rev: 7 A p p e n i dx A A .-.... ...-0000-0118-5622-FBI.R-NP ..I..... Revision 0 Non"Proprietaiy Information" lass i (Public)t-UO 2/Gd -Thermal-Mechanical tHGR Limits Bundle Type: GE 14-P 1 OCNAB409" 12GZ- 120'r- 150-T6-2951 (GE 14C), Bundle Number: 2951 PeaklPeliet'Exposure vU-0'"UQ LHGRLimnit GWd/MT'(GWd/ST) ' .1lWift 0.00ý(.O.00) .41340, 16.00'(14.5

1) 1 63.50(57.61)

.8.0 0" 70.00-(63.50) 5.00...Pekk PelletExpo'sufe Most-Limitiiig Gadolinia"_........ _ ,LHGR Limit 9 GWd/MT(GWd/ST) kW/ft 0.00 (0.00) .-11.76 13,31 :(12.08) .11.76 59"76(54.21) .. 7.02 66.1-2 (59.98) 4.39 9 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd):,'Page 13 COLR Page 34 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordancewith 10 CFR.2.390 Limerick Unit 2 Reload1 V Non-Proprietary Information

-Clas'sI,(-Public)

".Doc ID:.COLR L-.erick 2, Rev.'7* -' rw.Appenstix A ",

1. 11 14.9Ri"9ion 0 UO 2 1Gd Thermal-Mechanical LHGR.Limits Bundle Type: GNF2-P10CG2B396-6G7.0/6G6.0-120T2-150-T6-3648 (GNF2)Bundl.. Numb... 3648..........

Bundle Number: 3648 I.. Peak.Pellet Exposure -. .UO 2 LHGR Limit Peak Pellet Exposure.. .Mo~t Limiting. Gadolinia I LPGR'ýLimicL1 GWd/MT (GWdST). kW/ft ..... ..... [ ,* I. :. ....'0 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [[fl.Page 14 COLR Page 35 of 63 Exelon Nuclear -Nuclear Fuels."Core Operatir Limits Report Non-Propr, .y InformationSubmitted in Accord' 1 'tL;Q { .. ..Limeick Unit 2 Non-Proprietary Information-Class I (Public)Doc I'Di k COL Rev. 7 AppendixA 1: I .. .1'" ..0000-01 1 8-5622-FIBIR-NP Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB410-15GZ-120T- 150-T6-2952 (GE 14C)Bundle Number: 2952 t-Peak Pellet Euposuire IA HGR !-iW--GWdiMT (GWd/STy .---kW/ft...... 0.00 (-o.00) .. .... ..-13.40.r6.00-(14.-5) I Y ----, 13.40. .63:50(57.61) -...8 .00 .--... 70.00(63.50).. .5:00.Peak.Pelle.t; Exposure Most Limiting Gadolinia............... LHGRLiinit. GWd/MT-(GWd/ST) .kW/ft..... 0.00(0.00) .-11.76....... .331(i2.8) ..11.76.59.76-(54.21y.. 7.02 66.I2(59.98) .-- --- 4.39 -.'1 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 15 COLR Page 36 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Noan-Proprietary Informaition Submitted in Accordance with 10 CFR"2.390 Limerick Unit 2 Reload 11-Doc'ID: COLR Limerick:2, Rev. 7 AppenadxA .., , -.,.'0000-011 9t-#,J: .,B3IR-NP.. ....R ision 0 Non-Proprietary Information SClass I (Public)UO 2 IGd-i.hermbI-Mechanical LHGR Limits Bundle Type: GE 14-P I OCNAB4O8-14GZ- 120T- 150-T6-295'3 (GV 14C)!, Bundle Number: 2953 Pik'PlibtEx6sure "U02 LHGR Limit* GWdI-/Mi" 'kW/ft....... .................0 00(,0.00)

:'13!40 1600(4.51)1140 63-.0 576.) ............ ...70..0_0 (6.3.t50.)_

... .i... ...;;5:0.0. _ .....PeAk PiletEipo dsure, Most Limiting Gadolinia" -LHGR Limit 12 GWd/MT.(GWd/ST). kW/ft..0.00..(.0.00) .11.76'.13.31(208) .14.76 59.76 (54.21)... ........... 702.6612.(59.9.8).. 4.39 .12 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 16 coLR Page 37 of 63 Exelon Nuclear -Nuclear Fuels ,Core Operating Limits Report Non;Propriet ary Information Submitted in Accordance with 10 g2.Lime?'* ... r I0-0000 Reload -!,1 Doc ID COLR Limerick 2Rev.7 Appendix:A 0000-01 18-5622-FBlIR-NP Revision 0..Non-Pr-oprietary., Information -,.Class I (Public),U 2/Gd ,Therma1-M/lechanical LHGR.iritits Bundle Type: GE14.-P lOCNAB41-.13GZ-120T-1!.0-T6-2955 (GE14C)Bundle Number: 2955 Peak Pelle~t, Exposure ..U'0 2 GWd/iMT(GWd/ST) ...ft , 0.00,(0.00) j 3.40i, 16._002(ý14.51) -1 :. 3,40(-63.50,(57.61) 800 .... Peak Pellt. Exposqre Most Limiting Gadolinia , .LHGR Limit 1 3 GWdIMT (GWd/ST) .-kW/ft 0.00 (:0.00) 11.76: 13,.31(12.08) .11.76.. __ ___ __ ___5 7 7.2 J -5976 (54.21) -------------. 0--: 66,12;(59.98) -4.39 Bounding gadotin.a LHGR limit for all gadolinium concentrations occurring in this bundle design ( 8.0% Gd).Page 17 COLR Page 38 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with :10 CFR 2.39Q Limerick Unit 2 Reload: 1 I-1 1 -: t .-.1 I .Doc ID: COLR Limerick 2, Rev.q Appendix A.0C.1C IN " ,5.2-.R-NP S keViSion 0 Non-Proprietary Information

  • Class I'(Public), UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10CG2B404-12G6.0-120T2-150-T6-3643 (GNF2)Bundle Number: 3643 Peak, Pellet Fx.pnsur.e. -UOz LHGR Limit

____kW/ft-Peak Pellet Exposure .. Most-Limiting Gadolinia-Limit 1 4 GWd/IIT (GWd/ST) ..kW/ft.. .............. ... .. .. ]. ..14 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [[Page 18 COLR Page 39 of 63 Exelon Nuclear -Nuclear Fuels"Core Operating Iimits Report Non-Proprietary Information'Submitted in AccorQie~ywitýýi Q&Fiýl12UJ*)0 Limerick Unit 2 Reload 11 Doc 1D6 C OLR limer'ickl2, Rev. 7 Appendix A Non-Proprietary Information 0000-01 18-5622-FBIR-NP -Class I (Public) Revision 0 Reload I I UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 1OCG2B389-14GZ-120T2-150-T6-3645 (GNF2)Bundle Number: 3645 Peak Pellet .I LHGR Liii-..GWdiMT (GWd/ST) --------- kW/ft-Peak.Pellet Eaposure Most Limiting Gadolinia LHGR Limit 15 GWd/MT (GWd/ST) kW/ft 7 15 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [[Page 19 COLR Page 40 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR'2.390 Limerick.Unit 2 Reload i..I Doc ID: COLR Limerick 2, Rev. 7 qp1endix Revision 0*Non-Proorietary Information Reload Ll evision. 0 Y.WO/Gf -ThermaIMea hanica! LHGR Limits Bundle Type: GNF2-P1 0CG2B3917.15GZ-l-2OT2-150-T6-3646 (GNF2)Bundle Number: 3646?I... 1elle, Exposure UO 2 LHGR Limit.CWd/ai-T: GWd/ST) .kW/ft---.... ......Peak Pellet Exposure 'Most Limiting Gadolinia'16 LHGR Limit GWd/MT (GWd/ST) kW'ft 16 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [[Page 20 COLR Page 41 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Pýopiietary Info!ration SUibmitted in"t 0"Oz C ..I'RieljiaktyA1 ... 00 R-elýad Doc Rev. 7 Appendix A 0000-01 1 8-5622-FBIR-NP .Revision 0 Non-Pf6pri~iairy Informat .ion UO 2 1Gd Therhial-Mechanical LHGR Limits Bundle Type: GN'F2-'P 1 0G2B392'- 4GZ- 10T2-i 50-T6-3647' (GNF2)Bundle Number: 3647 Peak Pe!let Expos ure... ;.UGd:LHGR LiIDJ .Gwl/MTL(GWd/ST)-. .. kWTft..... ... .. ....... .. .... .. .......... __......... .... ............................-- ..--- ... ..... .. ..... ....Peak Pellet Exptosure Most Limitin;g Gadolinia........... LHIGR.Limit 17 SGWd/MT. (,GWdl/S.T). ....;.. :'kW/ft, liii i.. ....... ........]]....17 Bounding gadolinia LHGR limit for all gadolinium corckentrations occurring in this bundle design [[]I].Page 21 COLR Page 42 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordancre with 10 CFR 2.390 Limerick Unit 2 Reload 11!Dod ID: COLR Limerick 2, Rev. 7 Revision 0 Non-Proprietary Information .... -Class i (Puiblic)Reload I I UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10CG2B391-14GZ-120T2-150-T6-3725 (GNF2)Bundle Number: 3725 ........... ........,~~~~~~. .."... 1'Peak Pellet Expore. ., , UQ 2 ,LHGR Limit (GWd/ST); I :

  • kW/ft.. ......_______................

__ 1 9.....1.. ..... '.. ..... i. i.......... ... ..Peak Peftei _Expo'_su'_ _re_'_-Most Limiting Gadolinia LHGR Limit'8 GWd/MT (GWd/ST). kW/ft,.[[ ', ...18 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design [[Page 22 COLR Page 43 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report .Non-Piropdetary'lnfo(naýt9f Submitted in Accor0 e ýj I" .L -. 1U.-k, 2 Doc ID: C0LC'Lim6"rick 2, 1ev, 7 Appendix*A 0000-0118-5622-FBIR-NP ... Revision 0 Non-Proprietary Iniformation ...... .*- : -4 .Appendix B, Fuel Bundle Information Table B-1 Bundle Specific Information ..n.. ...... ... .ee ht MExposure Fuel , ,iBndle E.Weight' M at Max M"... .. ... .. --.. ......I f- UOp..f-U0 -U -- .! at Bundle .. Number (wto 0 1 20-.C) 19 GWd/MT..........t... ... .... ..g) ... 20 C 9 (G W d/ST)GNF2-P10CG12B386- ................. ................ .2G8.0/13G7.0-120,T2-1507T6=- .......3644-..... 3644 (GNF2)GE14-P10CNAB389-14GZ-31:.. ............ _ E _. 3................... ..... .. ___........ .... ....... ...120T-150-T6-3157 (GE14C)GE 14-P 1OCNAB389-15GZ-3158 120T-150-T6-3156 (GEl4C) ........GEl4-P1OCNAB4O9-6Z..... ...,. 3!59 , " 120T-150-T6-3156 (GE14C). -295 GEI4-P10CNAB4391Ol3G8.Z-" 120T-150-T6-3160 (GE14C) 2950 GE 14-P1OCNAB390-12GZ-120T-150-T6-3161 (GE1-4C) 216 GE14-P10CNA2B349-6GZ-2956 120T-150-T6-2956 (GE14C) ... .. ..36 GE 14-P 1 OCNAB410-16GZ-2950 120T-150-T6-2950 (GE14C)GE14-PI OCNAB409-12GZ-2951 120T-150-T6-2951 (GE14C)GNF2-PIOCG2B3396-6G7.0/6G6.0-120T2-150-T6-3648 3648 (GNF2)GE 14-P I10CNAB410-15GZ-2952 120T-150-T6-2952 (GE14C)GE 14-P10 CNAB408-14GZ-2953 120T-150-T6-2953 (GE14C)19 Maximum lattice k.o for the most reactive uncontrolled state plus a [[]] adder for uncertainties. Page 23 COLR Page 44 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary lformption Submitted in Accordarcý with 10 CFR"2'.390 Limerick-Unit 2'Reload L1 Doc-ID: COLR Limerick 2, Rev. 7 Revision 0 Non-Proprietary. Information -Class I (Public)GE14-P 10CNAB410-13GZ-25 120T-150-T6-2955 (GE14C)GNF2-P 10CG2B404-12G6.0-3643 120T2-150-T6-3643 (GNF2)GNF2-P 10CG2B389-14GZ-120T2-150-T6-3645 (GNF2)GNF2-P 10CG2B391-15GZ-34 120T2-150-T6-3646 (GNF2)GNF2-P10CG2B392-14GZ-120T2-150-T6-3647 (GNF2)GNF2-P10CG2B39 1- 14GZ- 3725 120T2-150-T6-3725 (GNF2)Page 24 COLR Page 45 of 63 Exelon Nuclear -Nuclear Fuels.Core Operating Limit Report Non-Proprietar6 lnforrnaltion Submitted in A ,. fttq Accorai -l:ith10CH 2..Re16ad:V.I I- o ,)Doc ID: COLR Lirnck 2, Rev. 7 A ppendix A " ' : I " 0000-0118-56X2-:FBIR-'NP ... .. .. .. ..... Revision 0 Nod-Proprietary Information ....-. i (PUblic)l[E'I Figure B-i Enrichment and Gadolinium Distribution for EDB No. 3644 Fuel Bundle GNF2-P10CG2B386-2G8.O/13G7.O-1 20T2-1 5O-T6-3644 (GNFZ)Page 25 COLR Page 46 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Prop'etary Infopmation Submitted in Accordah'ce-With 10 CFR 2.390 Limerick Unit 2 Nork-Proprietary Information Reloa'd 1,I- -Class'I (Pub licj Do ID: CUOLR Limerick'2, Rev. 7 Revision 0 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3157 Fuel Buodle GE14-P10CNAB389-14GZ-12OT-150-T6r3157 (GE14C)Page 26 COLR.Page 47 of 63 Exelon Nuclear -Nuclear Fuels Core Operagrng Limits Repq.rt Non-Pr prietary lnfornrai6ni Submitted in Accord e J 0,9 Doc ID: COLR Linjerck 2, Rev. 7 Appendix A 0000-0118-5622-FBIR-NP .. eviinio" 0 Norn-'Prbpnieaiy information ... Cla~q-1 as 4iýbfie Figure B-3 Enrichment 'iad Gadolinihm Distribution for EDB No. 3158 Fuel Bundle Gd14-P1OCNAB389-15GZ-120T-150-T6-3158 (GE14C)Page 27 COLR Page 48 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accdrdance6Withl 10 CFR'2.390 Limerick Unit Reload 1.1-'Non-PrQprietary Information -Class I (Public)Doc ID: COLR Limerick 2, Rev. 7 Revision 0 Figure B4 Enrichment and Gadoliniumi Distribution for EDB No. 3159 Fuel. Bundle GE14-P1OCNAB391-13GZ-120T-150-T6-3159 (GE14C)Page 28 COLR Page 49 of 63 Exelon Nuclear -Nuclear Fuels Core Opeirating Limits Report.Non-PNi0lribtary Informiatiori.nSubmitted in Accordenne I0 C -R .2 9)Limieihý if- Non-P rp'ietArylinfprmation Readt-- ...... ... -Class -(Public)Doc IDp.COLR Limerick 2, Rev. 7 Appendix A 0000-0118-5622-.FBIR-NP --.. Reiision 0 Figure B-5 Enrichment and Gadolinium Distribution for EDB"No. 3160 Fuel BRundle GE14-P1OCNAB391-13G8.0-120T-150-T6-3160 (GE14C)COLR Page 50 of 63 Page 29 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR2.390 Limerick Unit 2 Reload 1.1 DoC ID: COLR Limerick 2, Rev.'. 7 R. ev;isio ,b n 0 Non-Proprietary Information -Class I (Public)Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 3161 Fuel Bundle GE14-P1OCNAB390-12GZ-120T-150-T6-3161 (GE14C)Page 30.COLR Page 51 of 63 Exelon Nuclear -Nuclear Fuels'Core Operating Limits. Report_Non-Prop letary'lnfofmtation Suibmitted in Accordrje

  1. ,th .1i0 , r -...... .... .... ....-..Doc l: OibLR Lim erick 2, Rev. 7 Appendix A 0000-0118-5622-FBIR-NP

--ReVision 0 Non-Proprietay "Information .... ....'-P -ic ..eiiia[1 Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 2956 Fuel Bundle GE14-P1OCNAB409-16GZ-120T-150-T6-2956 (GE14C)Page 31 COLR Page 52 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit 21 Reload 14 Non-Proprietary Information Class I (Public); ,Doc ID: COLR Limerick ,2 Rev. 7 0000-011-$,,-NP Revision-0 1]Figure B-8 Enrichment and, Gadolinipm Distribution for EDB No. 2950 Fuel Bundle GE14-P1OCNAB410-16GZ-120T-150-T6-2950 (GE14C)Page 32 COLR eage 53 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Prdprietary Information Submitted in Accordance with 10 CF 2[3ý 9 Relm ' 1.. 1 .. ."0.Non-Proprietary'Information -:Cassg I (Pjubfic)Doc ID' COLR. Limerick 2, Rev. 7 Appendix'A 0000-0118-5622-FBIR-NP ....- Revision 0 Figure B-9 Enrichment and Gadolinium Disfilbution for EDB No. 2951 Fuel Bundle GE14-P1OCNAB40912GZ-120T-150-T6-2951 (GE14C)Page 33 COLR Page' 54 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick, Unit 2 " Reload i I Non-Proprietary Information -Class I (Public)Doc ID: COLR Limerick 2, Rev. 7 0000-01 1l1,$A2AgR-NP Revision 0 Figure B-10 Enrichment and Gadolinium Distribution for. EDB No. 3648 Fuel Bundle GNF2-P10CG2B396-6G7.O/6G6.0-120T2-150-T6-3648 (GNF2)Page 34 COLR Page 55 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report , Non-Proprietaýy Information Submitted in Accordance with 10'CFR 2:390 Reloadl' ---l. .........Doc ID COLR Limerick 2, Rev. 7 AppendixA 0000-0118-5'622-FBIR-NP .. .... .. -Revision 0 InforrMation --lass TI-(Public) .1[Figure B-11 Enrichment and Gadolinium Distribution for EDB No. 2952 Fuei Bundle GE14-PIOCNAB410-i5GZ-f 20T-150-T6-2952 (GE14C)Page 35 bOLR Page 56'of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick, Unit 2 Reload 11 Non-Proprietary Information -Class I (Public)Dob ID: bOLR Limerick 2, Rev: 7'...... ...edt. A K1evhi~in 0 1]figure B-12, Enrichment and Gadolinium Distribution for EDB No. 2953 Fuel Bundle GE14-P1OCNAB408-14GZ-120T-150-T6-2953 (GE14C)Page 36 COLR Page 57 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Informati9n Submitted in Accord,ýnce~vith 410,CFI 2.399, Non-Proprietary Information Reloac 1 .------- -----------. -lass -Doc I D: :OLR'lLimerick 2, Rev. 7 Appendix A 0000-0118-5622-F.BiR-NP .. ... Revikion 0[['Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 2955 Fuel Bundle (GE14C)Page 37 COLR Page 58 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance'with 10 CFR'2.390 LimerickUnit 2 Reload 11 'Non-Proprietary Information

-Class I (Public)D'c ID COLR Limerick 2, Rev. 7',11,.,,s e 0 R~evision, 0... ... .. i I Figure B-14 Enrichment and Gadolinium Distribution for EDB No. 3643 Fuel Bundle GNF2-PIQCG2B404-12G6.0-12QTZ-150-T6-3643 (GNF2)Page 38 CO.LR Page 59 of 63 Exelon Nuclear -Nuclear Fuels\ Core Operating Limits Report_Non-Proprietary Information.

Submitted in Acco~5 rd with l0 1218'R 0 0 Lioad f 2 ... ...Reload-f1...... Doc D6-6LR Limenjck 2, Rev. 7.A.., e. Appendix , I .z , .A Non-Pr'p'fie'tary Information 0000-0118-5622-FBIR-NP -fClas I- (Public) .. .... .......... .. -Revision 0 Figure B-15 Enrichment ýid Gadolinium Distribution for EDB No. 3645 Fuel Bundle GNF2-Pl}CG2B389-14GZ-12OT2-l50-T6-3645 (GNF2)Page 39'COLR Page 60 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR2.390 Limerick.Unit 2.Reloadl 11,. .Non-Proprietary Information -. Class I (Pub~licY' Doc ID: COLR Limerick 2, Rev. 7'R~evision 0 eload 11 ' -.Clas's I (Nblfc)[[Figure B-16 Enrichment and Gadolinium Distribution for EDB No. 3646 Fuel Bundle GNF2-P1OCG2B391-15GZ-120T2-150-T6-3646 (GNF2)Page 40 COLR Page 61 of 63 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Inf .mation.Submitted in Ac( Cei'~.A( .4 e,w~th 0,F ,.".' .LimhericK:,unit-R e oad=f1--- -..... ..... .... .Doc ID',COL) Limerick2, Rev. 7 Appendix A 0000-01 18-5622-F.BIR-NP ....Revision 0 Non-Propi'etaiyInformation w... ..( l s ' s l u l ..Re a 'las'11Public) Figure B-17 Enrichment and Gadolinium Di"ribu"tion for E46B No. 3647 Fuel Bundle GNF2-P10CG2B392-14GZ-120 IT2-150-T6-3647 (GNF2)COLR Page 62 of 63 Page 41 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit 2 Reload 11 Doc ID: COLR Limerick 2, Rev. 7 Appendix A 0000-0118-5622-FBIR-NP Revision 0 Non-Proprietary Information -Class I (Public)[[Figure B-18 Enrichment and Gadolinium Distribution for EDB No. 3725 Fuel Bundle GNF2-P1OCG2B391-14GZ-120T2-150-T6-3725 (GNF2)Page 42 COLR Page 63 of 63}}

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