ML13079A362

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Enclosure 3 Unit 1 COLR for Cycle 15 Rev 10 with Appendix a Proprietary Class I (Public)
ML13079A362
Person / Time
Site: Limerick Constellation icon.png
Issue date: 01/23/2013
From: Donell A
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
References
Download: ML13079A362 (58)
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Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 10 I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table of Contents Page 1.0 Terms and Definitions 4 2.0 General Information 6 3.0 MAPLHGR Limits 7 4.0 MCPR Limits 8 5.0 LHGR Limits 11 6.0 Control Rod Block Setpoints 13 7.0 Turbine Bypass Valve Parameters 14 8.0 Stability Protection Setpoints 15 9.0 Modes of Operation 15 10.0 Methodology 16 11.0 References 16 Appendix A 17 Page 2 of 57

Exelon Nuclear - Nuclear Fuels, Doc ID: COLR Limerick 1, Rev. 10 I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GE14 7 Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 7 Table 3-3 MAPLHGR SLO Reduction Factor - All Fuel Types 7 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) - GEl4 9 Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) - GNF2 9 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp - All Fuel Types 10 Table 4-4 Flow Dependent MCPR Limits MCPR(F) - All Fuel Types 10 Table 5-1 Linear Heat Generation Rate Limits - U0 2 Rods 11 Table 5-2 Linear Heat Generation Rate Limits - Gad Rods 11 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier- All Fuel Types 12 Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) - All Fuel Types 12 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) - All Fuel Types 12 Table 6-1 Rod Block Monitor Setpoints 13 Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 13 Table 7-1 Turbine Bypass System Response Time 14 Table 7-2 Minimum Required Bypass Valves To Maintain System Operability 14 Table 8-1 OPRM PBDA Trip Setpoints 15 Table 9-1 Modes of Operation 15 Page 3 of 57

Exelon Nuclear - Nuclear Fuels Doc' ID: COLR Limerick 1, Rev. 10 Core Operating Limits Report Non-Proprietary Information Submitted in Accordancewitlr10 CFR12.39 * -

1.0 Terms and Definitions ARTS APRM and RBM Technical Specification Analysis BASE A case analyzed with Turbine Bypass System in service, Recirculation Pump Trip in service, Feedwater Temperature Reduction allowed (FFWTR includes feedwater heater OOS or final feedwater temperature reduction) and PLUOOS allowed at any point in the cycle operation in Dual Loop mode.

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 system flow equal to 100%, allcontrolrods fully 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 ICF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint Kp Off-rated power dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thermal limit flow dependent multipliers LHGRFAC(P) ARTS LHGR thermal limit power dependent multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPFAC(F) Off-rated flow dependent MAPLHGR multiplier MAPFAC(P) Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) ARTS MCPR flow dependent thermal limit MCPR(P) ARTS MCPR power dependent thermal limit Page 4 of 57

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 10I0 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 MELLLA Maximum Extended Load Line Limit Analysis OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor PBDA Period Bisel Detection Algorithm PLUOOS Power Load Unbalance' Out of Service RBM Rod Block Monitor RPTIS Recirculation Pump Trip in Service RPTOOS Recirculation Pump Trip Out of Service SLO Single Loop Operation TBVIS Turbine Bypass Valves in Service TBVOOS Turbine Byjgass Valves Oat of Service Page 5 of 57

Exelon Nuclear - Nuclear Fuels Doý ID: COLR Limerick 1, Rev. 10 Core Operating Limits Report ..

Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 2.0 General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 1 Cycle 15:

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • Minimum Critical Power Ratio (MCPR)
  • Single Loop Operation (SLO) MCPR adjustlment-
  • ARTS MCPR thermal limit adjustments and multipliers (MC4PR(P) or MCPR(F))
  • ARTS LHGR thermal limit multipliers (LHGRFAC(P) or LHGRFAC(F))
  • Rod Block Monitor (RBM) setpoints
  • MAPLHGR single loop operation reduction factor,
  • LHGR single loop operation reduction factor
  • Linear Heat Generation Rate (LHGR)
  • 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 1. Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values.

The data presented in this report is valid for all licensed operating domains on the operating map, including:

  • Maximum Extended Load Line Limit down to the minimum licensed core flow during full power operation
  • Increased Core Flow (ICF) up to 110% of rated core flow
  • Final Feedwater Temperature Reduction (FFWTR) up to 105.07F during cycle extension operation

Further information on the cycle-specific analyses for Limerick Unit I Cycle 15 and the associated operating domains discussed above is available in References 2, 7 and 8.

Page 6 of 57

Exelon Nuclear - Nuclear Fuels Doc ID:,COLR Limerick 1, Rev. 10 ,1 Core Operating Limits Report .* . -,.

Non-Proprietary Information Submitted in Accor.ance with 10 CFR 2.390 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description The limiting MAPLFIGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Tabies 3-1 and 3-2. For single loop operation, a reduction factor is used, which is shown in Table 3-3. The power and flow dependent multipliers for MAPL.HGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F); therefore, MAPFAC(P) and MAPFAC(F) are equal to 1.0 for all power and flow conditions (Reference 2). LHGRFAC(P) and LHGRFAC(F) are addressed in Section 5.0.

Table 3-1 MAPLHGR Versus Average Planar Exposure - GE14 (References 2 and 7)

Average Planar Exposure . MAPLHGR Limit

(%GWD/ST) (kW/ft) 0.0 12.82 19.13 12.82 57.61 8.00 63.50. 5.00 Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 (References 2 and 7)

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 SLO Reduction Factor - All Fuel Types (References 2 and 7)

SLO Reduction Factor 0.80 Page 7 of 57

Exelon Nuclear - Nuclear Fuels Doc - COLR Limerick 1, Rev. 10 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Tables 4-1 and 4-2 are derived from References 2, 7 and 8 and are valid for all Cycle 15 operating domains. Table 4-1 is valid for GE14 fuel and Table 4-2 is valid for GNF2 fuel. Because it was identified that the Loss of Stator Cooling (LOSC) transient event may be limiting for GNF2 fuel, Table 4-2 has been revised, as necessary, to include the result's of the LOSC analyses performed (References 7 and 8). Tables 4-1 and 4-2 include treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. Limerick Unit 1 Cycle 15 was analyzed with no mid-cycle MCPR breakpoint.

ARTS provides for power and flow dependent thermal limit adjustments and multipliers, which allow for a more reliable administration of the MCPR thermal limit. The flow dependent adjustment MCPR(F) is sufficiently generics to apply to all fuel types and operating domains.

The power dependent adjustment MCPR(P) is independent of recirculation pump trip operability.

MCPR(P) and MCPR(F) are independent. of Scram, Time Option. In addition, there are six sets of power dependent MCFR multipliers (Kp) for use with the BASE; TBVOOS, RPTOOS, DLO and SLO conditions. The PLUOOS condition is included in the BASE MCPR(P) and MCPR(F) limits and Kp multipliers and is bounded by the: TBVOOS limits and multipliers; therefore, no additional adjustments are required for PLUOOS in those oper'ating conditions. The PLUOOS condition has not been analyzed concurrent with'the RPTOOS* operating condition. Operation in the PLUOOS condition concurrent with the RPTOOS conditioii'frluires 'core thermal power < 55% of rated (Reference 3). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. MCPR(P) and MCPR(F) adjustments for all fuel types-are provided in Table 4-3 and 4-4, respectively. The OLMCPR is determined for a given. power and. flow ,condition by evaluating the power dependent MCPR and the flow dependent MCPR. and selecting the greater of the two.

Page 8 of 57 I

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 10 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Table 4-1 Operating Limit Minimum Critical Power Ratio*(OLMCPR) - GE14 (References 2, 7 and 8)

SCRAM Time All Cycle EOOS Combination Option' Exposures B 1.37 BASE B 1.37 0A 1.45 BASE SLO2 AAB 1.46 1.48 B 1.43 TBVOOS A 1.52 2 B 1.46

,TBVOOS SLO A 1.55 B 1.42 RPTOOS

_ _ _ A 1.59 2 B 1.46 RPTOOS SL0

. . . _ .._.._A

.. 1.62 Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) - GNF2 (References 2, 7 and 8)

. SCRAM 'rime All Cycle EOOS Combination Option' Exposures BASE '.A B 144 1.46 2 B 1.58 BASE SL0 A 1.58 B *1.44 TBVOOS

_________A B 144 1.52 2 B 1.58 TBVOOS SLO A 1.58 RPTOOS B 1.44 A 1.59 2 B 1.58 RPTOOS SLO A 1.62 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

2 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed two loop value.

However, a minimum value of 1.46 for GEl4 fuel and 1.58 for GNF2 fuel is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).

Page 9 of 57

Exelon Nuclear - Nuclear Fuels Doc ID"

. COLR

.. -. .. ,. Limerick

- .. .. 1,, Rev.

. 10 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 i&k'2.390 Table"4-3 Power Dependent MCPR Limits and Multipliers'MCPR(P) and 1(p - All Fuel Types (Rdfereiices 2iand 7)

Core Core Thermal Power (% of Rated)

EOOS Flow: -0 < 30'. .[..'j0 .- 65'. 85 100 Combination (% of Operating-Litmit MCPR, Operating Limit MCPR rated) . MCPR(P).... . . Mu_.iplier, Kp BASE *60 2.50 - 2.50 2.40 1.340, 1.131 1.067 1.000

-> 60 2.75 -_2.75. .2.55 ...

BASESLO <60

> 60-' 2.53 2.7 8 __ ..2.53

.2.7.8 .2.43 2.58 1340 1.131 1.067 1.000 TBVOOS 560 3.25 3.25 2.75 1.340 [.131 1.067 1.000

> 60 3.75 3.75 3.25 TBVOOS < 60 3.28 3.28 2.78 SLO > 60 3.78 3.78 3.28

< 60 2.50 2.50 ... 2.40...

RPTOOS >60

> 60 2.75 2.75 2.75 2.75 2.5 2.55 1.340. ' 1.131 1.067 1.000 RPTOOS *60 ' 2.53 2.53 2.43 SLO > 60 2.78 2.78 i2.58 1.340

___________ 1.131 1.067 1.000 Tab!e 4-4: -::

Flow Dependent MCPR Limits MCPR(F) - All Fuel Types (References 2 and 7)

Flow MCPR(F).,

_(/o rated) Limit

-. .0 0 . 1.70..

- 30.0 .... 1.53 79.0. . 1.25 110.0 1.25 Page 10 of 57 I

Exelon Nuclear - Nuclear Fuels. Doc ID: COLR.Limerick.1, Rev.. 19 Core Operating Limits Report Non-Proprietary Information Submitted inAccordance with. 10 CFR 2.390 5.0 LHGR Limits 5.1 Technical Specification 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 Table 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), and the flow dependent LHGR Factor, LHGRFAC(F). For single loop operation, a reduction factor is used, which is shown in Table 5-3 and applied in Table 5-5. 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 thermal limits. There are two sets of flow dependent LHGR -multipliers for dual-loop and single-loop operation. In addition, there are six sets of power dependent LHGR multipliers for use with the BASE, TBVOOS, RPTOOS, DLO and SLO conditions. The PLUOOS condition is included in the BASE LHGRFAC(P) and LHGRFAC(F) multipliers and is bounded by the TBVOOS iirultipliers; therefore, no additional adjustments are required for PLUOOS in those operating conditions. The PLUOOS condition has not been analyzed concurrent with the RPTOOS operating condition. Operation in the PLUOOS condition concurrent with the RPTOOS condition requires core thermal power

< 55% of rated (Reference 3). Tables 5-4 and 5-5 for LHGRFAC(P) and LHGRFAC(F),

respectively, are applicable to both GEl4 and GNF2 fuel types. Section 7.0 contains the conditions for Turbine Bypass .Valve Operability. Linear interpolation should be used for points not listed in Appendix A. .i..

Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power and flow biased calculation. The LHGRFAC(P) curves are independent of recirculation pump trip operability.

Table 5-1 Linear Heat Generation Rate Limits - U0 2 Rods

".(Reference5)

Fuel Type LHGR GEl4 See Appendix A GNF2 See Appendix A Table 5-2 Linear Heat Generation Rate Limits - Gad Rods (Reference 5)

Fuel Type I LHGR GE14 See Appendix A GNF2 See A pendix A Page 11 of 57

.Exelon Nuclear- Nuclear Fuels' Doz ID
COLR Limerick 1, Rev. 10 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10CFR.2.390 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier - All Fuel Types (References 2 and 7)

SLO Multiplier' T 0.80 1 Table 5-4 Power Dependent LHGR MultiplierLHGRFAC(P) - All Fuel Types (References 2 and 7).

Core Core Thermal Power (% of rated)

E OO S Flo w - - - -I Combination (% of 0 2 <30 3 65 185 100 rated) LHGRFAC(P) Multiplier BASE > 60 0.43 4 0.484 0.407 0.750 -.0.8.17 0.922 1.000 BASE SLO _ 60 0.485 0.485 ..0.490 0.750 .0.817 0.922 1.000

> 60 0.434 0.434 0.473 _

< 60 0.463 0.463 0.490' TBVOOS 0.750 0.817 0.922 1.000

> 60 0.352 0.352, 0.386

< 60 0.463 0..463 .,O.49.0 TBVOOS SLO >60

>6.0 0352 0.352 0352

.0.352.. 0386 0.386. 0.750, 0.817' 0.922 1.000 RPTOOS < 60 0.485 0.485 0.490- "0.750 0.817 0.922 1.000

> 60 0.434 0.434 0.473.

<! 60 0.485 0.485 0.490 RPTOOS SLO *60

> 60 0.485 0.434 0.485 0.434 0.490 0.473 ___0.750' 0.8 17 0.922 1.000 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) - All Fuel Types (References 2 and 7) I Core Flow (% of rated)

EOOS Combination 0 30 44.082 70 80 110 LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 j , 0.973 1.000 1.000 Single Loop 0.506 0.706 0.800 1 0. tOO 8

Applied through Table 5-5 Page 12 of 57

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 10 .

Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 6.0 Control Rod Block Setpoints 6.1 Technical Specification Sections 3.1.4.3 and 3.3.6 6.2 Description The ARTS Rod Block Monitor provides for power dependent RBM trips. Technical Specification 3.3.6 states controi rod block instrumentation channels shall be OPERABLE with their trip setpoints consistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shown in Table 6-1. The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110% of rated core flow.

Table 6-1 Rod Block Monitor Setpoints' (References 2 and 4)

Power Level Analytical Allowable Nominal Trip MCPR Limit Value Setpoint Limit LTSP 123.0% 121.5% 121.5%

ITSP 118.0% 116.5% 116.5% < 1.70(2)

HTSP 113.2% 111.7% 111.0% < 1.40 DTSP No Limritation. 2.0% 5.0%

Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 4)

Analytical Limit N/A Allowable Value 115.6%

Nominal Trip Setpoint 113.4%

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.

2 This is the MCPR limit (given THERMAL POWER is > 28.4% and < 90%) below which the RBM is required to be OPERABLE (see Reference 2 and TS Table 3.3.6-2).

3 This is the MCPR limit (given THERMAL POWER is > 90%) below which the RBM is required to be OPERABLE (see Reference 2 and TS Table 3.3.6-2).

Page 13 of 57

Exelon Nuclear - Nuclear Fuels DocID: COLR Limerick 1, Rev. 10 I Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 7.0 Turbine Bypass Valve Parameters 7.1 Technical Specification Sections 3.7.8 and 4.7.8.c 7.2 Description The operability requirements for the steam bypass system are found in Tables 7-1 and 7-2. If these requirements cannot be met, the MCPR, MCPR(P) and LHGRFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.

Additional information on the operability of the turbine bypass system can be found in Reference 6.

Table 7-1 Turbine Bypass System Response Time (Reference 3)

Maximum delay time before start of bypass valve opening 0.11 sec following generation of the turbine bypass valve flow signal 0.1se 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 Minimum Required Bypass Valves To Maintain System Operability (Riference 3)

Reactor Power No. of Valves in Service P > 25% 7 Page 14 of 57

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 10 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR12.390 ,

8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1 8.2 Description The Limerick Unit 1 Cycle 15 OPRM PBDA Trip Setpoints for the OPRM System are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 2. The setpoints provided in Table 8-1 are bounding for all modes of operation shown in Table 9-1.

Table 8-1 OPRM PBDA Trip Setpoints (Reference 2) 9.0 Modes of Operation Table 9-1 Modes of Operation (Reference 2)

EOOS Options Operating Region' BASE, Option A or B Yes 2 BASE SLO, Option A or B Yes 2 TBVOOS, Option A or B Yes 2 TBVOOS SLO, Option A or B Yes 2 RPTOOS, Option A or B Yes 3 RPTOOS SLO, Option A or B Yes 3 TBVOOS and RPTOOS, Option A or B No TBVOOS and RPTOOS SLO, Option A or B No 1 Operating Region refers to operation on the Power to Flow map with or without FFWTR.

2 The PLUOOS condition is supported in this mode of operation with no power reduction required.

3 The PLUOOS condition requires core thermal power level < 55% of rated (Reference 3).

Page 15 of 57

Exelon' Nuclear- Nuclear Fuels Doc 'ID: COLR Limerick 1, Rev. 10 Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 10.0 Methodology The analytical methods used to determine the core operating limits shall bethose previously reviewed and approved by the NRC, specifically those described in the following documents:

1. "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-18, April 2011 and U.S.

Supplement NEDE-240 11-P-A-I 8-US, April 2011.

2. "Reactor Stability Detect and Suppress Solutions Licefising Basis Methodology for Reload Applications," NEDO-32465-A, Rev. 0, August 1996.

11.0 References

1. "Technical Specifications and Bases for Limerick Generating Station Unit 1", Docket No. 50-352, License No. NPF-39.
2. "Supplemental Reload Licensing Report for Limerick 1 Reload 14 Cycle 15", Global Nuclear Fuel Document No. 0000-013 1-9339-SRLR, Revision 1, January 2012".
3. "Final Resolved OPL-3 Parameters for Limerick Unit I-Cycle - 15", Exelon TODI ES 1100022 Rev. 0, September 9, 2011.
4. "GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0 107, Rev. 2, February 23, 2012.
5. "Fuel Bundle Information Report for Limerick I Peload 14 tCycle 15", Global Nuclear Fuel Document No.

0000-0131-9339-FBIR-NP, Revision 0, January 2012.

6. "Tech Eval Stop Valve Load Limit Documentation", Sxelon Document IR 917231 Assignment 7, November 11, 2009.
7. "Evaluation of Loss of Stator Water Cooling at Limerick- Generating Station", General Electric-Hitachi Document No. 0000-0150-6369 Rev. 1, July22, 2012.
8. "Evaluation of Loss of Stator Water Cooling for Limerick Generating StationUnit I Cycle 13, Unit 1 Cycle 14, and Unit 2 Cycle 11", General Electric-Hitachi Document No. 0000-0151-7357 Rev. 0, September 5, 2012.

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Exelon Nuclear - Nuclear Fuels Doc ID: COLR'Limerick 1, Rev. 10 l Core Operating Limits Report Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Page 17 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Propdetary Information Submitted in Accordance with 10 CFR 2.390 Appendix A F Global Nuclear Fuel Global Nuclear Fuel AJoint Venau ol GEToshib., &Himchi 0000-0131-9339-FBIR-NP Revision 0 Class I January 2012 Non-ProprietaryInformation - Class I (Public)

Fuel Bundle Information Report for Limerick 1 Reload 14 Cycle 15 Copyright2012 Global NuclearFuel - Americas, LLC All Rights Reserved COLR Page 18 of 57

Exelon Nuclear - Nuclear Fuels . :1 ;. 1 .

Core Operating Limits Report Doc ID: COLRLin'Lerck 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with .10 CFR 2.390 Appendix A.

Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR-NP.

Reload 14 Class I (Public) Revision 0 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 ("Recipient") in support of the operating license for Limerick Unit 1 (the "Nuclear Plant").

The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at 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 Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-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 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 the document 0000-0131-9339-FBIR-P, Revision 0, 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 ((

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Exelon Nuclear - Nuclear Fuels W.

Core Operating:imitý Repoi't Doc ID: C-OLR Limerick"1, Rev. 10 No6i-Proprietary Information Submitted in Accordance with 10 CFR 2.390 ApperidixA'

'Linierick Unit 1 Non-Propriefary Information 0000-0131-9339-FBIR-NP Reload 14 . .Class F(Public) .. Revision 0

1. 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 15. These LHGR limits are obtained from thermal-mechanical considerations only. Approved GNF-A calculation models documented in Reference 1 were used in performing this analysis.

LHGR limits as a function of exposure for each bundle of the core design are given. in Appendix A. . The LHGR values. provided in Appendix A provide upper and lower exposure 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 bundles. .Table B- 1 contains a summary of bundle-specific information, and the figures provide the enrichment distribution and gadoliniuum, distribution for the rfuel bundles included in this appendix. These bundles have been approved for use under the fuel licensing acceptance criteria of Reference 1. * .

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Exelon Nuclear - Nuclear Fuels Core Operating Limits Report- _ Doc ID: COL.R Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR,2.390 AppendixA Limerick Unit I Non-Proprietary Information 0000-0131 -9339-FBIR-NP Reload 14 Class .1(Public) Revision 0 e.vision 0

2. References
1. General Electric StandardApplicationfor Reactor Fuel, NEDE-2401 I-P-A- 18, April 2011; and the U.S. Supplement, NEDE-24011-P-A-18-US, April 2011.

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Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: 'COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appehdix A Limerick Unit 1 Non-Proprietarý Information 0000-0 131-9339-FBIR-NP Reload 14 Class-I (Public} -.. PRevision 0 Appendix A UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE14-PIOCNAB415-15GZ-120T-150-T6-3035 (GE14C)

Bundle Number: 3035 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft 0.00(0.00) 11.76 13.31 (12.08) 11.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39

'Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 5 COLR Page 22 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID' C0OLk Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A" Limerick Unit I Non-Proprietary Information 0000-0131-93339-FBIR-NP Reload 14 Class I (Public) Revision 0 U0 2/Gd-Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB415-15GZ- 120T-.150-T6-3038 (GE 14C)

Bundle Number: 3038 Peak Pellet Exposure 'U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00.(0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST). . kW/ft 0.00 (0.00) 11.76 13.3,1 (12.08) . 11.76 59.76 (54.21) 7.02 66.12 (59.98) .4.39 2 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 6 COLR Page 23 of 57

Exelon Nuclear - Nuclear- Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-ProprietarY Information Submitted in Accordance with 10 CFR 2.390

  • Apoendix A

,Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR-NP Reload 14 Class.I (Public) . Revision 0 UO2 Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB415-15GZ- 120T- 150-T6-3041 (GE 14C)

Bundle Number: 3041 Peaik Pellet Exposure U0 2 .LHGR Limit GWd/MT (GWd/ST) . kW/ft 0.00 (0.00) .. 13.40.:

16.00 (14.51) 13.40 63.50 (57.61)... 8.00 .

70.00-.(63.50) . 5.00 Peak 'Pellet Exposure Most Limiting Gadolinia 3

LHGR Limit GWd/MT (GWd/ST).. kW/ft 0.00(0.00) 11.76

.13.31 (.12.08) .4 176 59.76 (54.21) .. . - 7.02 66.12 (59.98) . 4.39 3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 7 COLR Page 24 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix.A - '.

Limerick Unit 1 Non-Proprietary Inf6rmation 0000-0131-9339-FBIR-.NP Revision Reload 14 Class I (PUblic) 0 UO.2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB394-15GZ- 120T- 150-T6-3271 (GE 14C)

Bundle Number: 3271 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT,(GWd/ST) kW/ft 0.00 (g.00) 13140 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure. -Most Limiting Gadolinia LHGR Limit 4, GWd/MT(GWd/ST) . . kW/ft 0.00 (0.00) .. 12.00 13.42 (12.17) . . . . . 12.00 60.17 (54.59) 7.16 66.57 (60.39) 4.48 4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (7.0% Gd).

Page 8 COLR Page 25 of 57

Exelon Nuclear- Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Ipformation, Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit I Non-Proprietary Information 0000-0131-933 9-FBIR-NP Reload [4 . . . .Class I (Public) -Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB401-13GZ- 120T- 150-T6-3273 (GE 14C)

Bundle Number: 3273 Peak Pellet Exposure U0 2 LHGR Limit.

GWd/MT (GWd/ST) kw/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63,50) .. 5.00 Peak Pellet Exposure Most Limiting Gaidolinia 5

LHGR Limit

  • GWd/MT (GWd/ST) -. kW/ft .

....0.00(0.00) .11.76 13.3.1 (.12.08) ............ 11.76,

.. 59.76 (54.21) . 7.02 66.12-(59.98). 4.39 5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 9 COLR Page 26 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report.. Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-013179339-FBIR-NP.

Reload 14 Class I (Puhlic) Revision 0 U0 2!Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB402-13 GZ- 120T- 150-T6-3274 (GE 14C)

Bundle Number: 3274 Peak Pellet. Exposure UO, LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limitn GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 0 11.76 13.31 (121.08) 1.1.76 59.76 (54.21) 7.02 66.12 (59.98) 4.39 6 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 10 COLR Page 27 of 57

Exelon Nuclear -..Nuclear Fuels Core Operating Limits Report. Doc ID: COLR Limerick 1, Rev. 10 Non-Propnetary.Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-ProPrietary Information 0000-0131-9339-FBIR-NP Reload 14 Class I (Public) - . Revision .0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB416-15GZ' 120T- 150-T6-3040 (GE 14C)

Bundle Number: 3040 Peak Pellet. Exposure U0 2 LHGR Limit:

GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.5.1) 63.50(57.61) 70.00 (63.50) 1 .

13.40 8.00 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST).. kW/ft 0.00 (0.00) . 1,176.

13.31.(12.08) ... . 11.76 59.76 (54.21).. -7.02 .

66.12.(59.98) . 4. 39 7Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 11 COLR Page 28 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Linerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary jnformation 0000-0131-9339-FBIR-NP.

Reload. 14 Class 1 (Public'i Revision 0 Reload 14 Class I (Pubficý Revision 0 UOIGd ThermaI-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB398-12GZ- 120T-150-T6-3275 (GE 14C)

Bundle Number: 3275 Peak Pellet Exposure U0, LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pel!et Exposure Most Limiting Gadolinia LHGR Limit 8 GWd/MT (GWdIST) kW/ft 0.00 (.0.00) 11.76 13.3.1 (12.08) 11.76 59.76 (54.21) 1.02 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 29 of 57

Exelon Nuclear .- Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 -Appendix A

'Limerick Unit I Non-Proprietary Informationi 0000-0 131-9339-FBIR-NP Reload -14 . Class 14.PtblicY. . .. .. Revision 0 UO2 Gd Thermal'Mechanical LHGRtLimits Bundle Type: GE 14-P 1OCNAB394-15GZ- 120T 150-T6-3272 (GE 14C)

Bundle Number: 3272 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) . kW/ft 0.00 (0.00) .. - 13.40' .-

16.00 (14.51) .. 13.40'

.63.50 (57.61),. 8.00 70.00 (63.50). 5.00 Peak Pellet Exposure Most Limiting Gadolinia LH.GR Limit 9 GWd/MT (GWd/ST) .. kW/ft 0.oo...(0.00) .1176: .

13.31 (12.08) _ _ _11_76 59.76 (54.21). 7.02.

.66.12 (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 30 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A '

Limerick Unit 1. Non-Proprietary Information 0000-0131 -93,39"FBIR-NP.

Reload 14 Revision Class I (Public) 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB415-15GZ-120T- 150-T6-3042 (GE 14C)

Bundle Number: 3042 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) 'kW/ft 0.00 (0.00) .13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit'o GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 11.76 13.3 1(12.08) 11.76 59.76 (54.21)... 7.02

" 66.12 (59.98) ..... .4.39

'0Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (8.0% Gd).

Page 14 COLR Page 31 of 57

Exelon Nuclear -.Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0131 -9339-FBIR-NP Reload 14 - Class I (Public) . Revision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P 1OCNAB415-15GZ- 120T- 150-T6-3039 (GE 14C)

Bundle Number: 3039 Peak Pellet Exposure UO 2 LHdR Limit-GWd/MT (GWd/ST) kW/ft' .

0.00 (0.00) 13.40 16.00 (.1.4.5 1) 13.40.

63.50 (57.61) 8.00 .

70.00 (63.50) " 5.00 -

Peak Pellet Exposure" Most Limiting Gadoiinia

.... LHGR-Limit "

GWd/MT (GWd/ST) " AW/ft.

..0.00(0.00) .... 1176 13.31(12.08) ...... -1.76.

.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 15 COLR Page 32 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLk Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0131-9339°:FBIR-NP Reload 14 Class~ I (Puiblic/ *Revision 0

eload 14 Class I (Publi c)

U0 2/Gd Thermal-Mechanica! L.HGR Limits Bundle Type: GNF2-P 10CG2B393-I0G7.0/2G6.0-120T2-150-T6-4048 (GNF2)

Bundle Number: 4048 Peak Pellet Exposure U0 2 LHGR Limit" GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure- Most Limiting Gadolinia LHGR Limit12 GWd/MT.(GWd/ST) kW/ft 12 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design

(( 1].

Page 16 COLR Page 33 of 57

Exelon Nuclear, Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 10 Core Operating Limits Report Appendix*A Non-Proprietary. Information Submitted in Accordance with 10 CFR 2.390 Limerick Unit 1 Non-PropritarInformation 0000-0131-'9339-FBIR-NP

  • Reloaid 14-.. ... .. lass I (Publiel ... -..... . .... Revision 0 eload 14- Cldssl(PubliO UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI0CG2B404-12G6.0-100T2-150-T6-4044 (GNF2)

Bundle Number: 4044 Peak Pellet.Exposure U0 2 LHGR Limii GWd/MT' (GWd/ST) kW/ft Peak Pellet Exposure Most Limitinfig Gadolinia LUGR Limit .13

_. GWdIMT (GWd/ST) . . kW/ft 13 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 17 COLR Page 34 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report- Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A .

Limerick-Unit 1. Non-Proprietary Information 0000-0131-93J9-FBIR-NP Reload 14 Class I (Public) Rev'ision 0 U0 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P 10CG2B404-12G6.0-120T2-1.50-T6-3643 (GNF2)

Bundle Number: 3643 Peak Pellet Exposure 1102 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit14 GWd/MT (GWd/ST) kW/ft

_ _ _ . .. . _ .. 11**.

14 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design

(( 1].

Page 18 COLR Page 35 of 57

Exelon Nuclear - Niuclear Fuels Core Operating Limits Report Doc ID. COLR Limerick. 1, Rev. 10 Non-Proprietary.Information Submitted in Accordance with 10 CFR 2.30 Appendix A

  • Limerick Unnit I Non-Proprietary Information° 0000-0131-9339-FBIR-NP Reload 14 Class-I(Pub!ic) -- Revision 0 U0 2/Gd Thermal-Mechanicar LHGR 'Limits Bundle Type: GNF2-PIOCG2B387-15GZ-120T2-150-T6-4045 (GNF2)

Bundle Number: 4045 Peak Pellet*Exposure U0 2 LHGR Limit GWd/MT (GWd/ST). kW/ft Peak Pellet Exposure Mit, Limiting Gadolinia LHGR Limit s GWd/MT (GWd/ST) kW/.ft 15 Bounding gadolinia LHGR lirnit for all gadolinium concentrations occurring in this bundle design Page 19 COLR Page 36 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick.1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR-NP Reload 14 r ClaSs I (Public) Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P I 0CG2B388-13GZ- 120T2-150-T6-4046 (GNF2)

Bundle Number: 4046

[ -Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet-Exposure Most Limiting Gadolinia 6

LHGR Limit '

GWd/MT (GWd/ST) kW/ft Erj 16 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 20 COLR Page 37 of 57

Exelon Nuclear-. Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-,Proprietary. Information Submitted in Accordance with. 10 CFR..2.390 Appendix A Limerick Unit I Non-Proprietary Information 0000-0131-9339-FBIR-NP Reload I4 Class I (Public.. Revision 0 U0 2IGd Thermal-Mechahical LHGR Limits Bundle Type: GNF2-P 10CG2B392-15GZ- 120T2-150-T6-4047 (GNF2)

Bundle Number: 4047

.Peak-Pellet Exposure- U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft .

(( . . .. . . .. . .

Peak Pellet, Exposure Most Limiting Gadolinia LHGR-Limit 17 GWd/MT (GWd/ST) kW/ft 17 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design Page 21 COLR Page 38 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report, Doc ID: tOI"R Li erick 1, Rev: 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR-NP .

Reload 14 Class.! (Public) Revision 0 Appendix B Fuel Bundle Information Table B-1 Bundle Specific Information Max Exposure Fuel Bundle Enrichment Weight of UO2 Weight of U !k at at Max k,,

20C 0 GdM Bundle Number (wt% U-235) 20 C GWd/MT (kg) (kg) 18 (GWd/ST)

GE14-PLOCNAB415-15GZ-120T-150-T6-3035 (GE4C) 3035 GE14-PIOCNAB415- 15GZ- 33 120T-150-T6-3038 (GEI4C)

GE14-P1OCNAB415-15GZ-120T-150-T6-3041 (GE4C) 30 GE14-PIOCNAB394- 15GZ- 37 120T-150-T6-3271 (GE14C)

GE 14-P 1OCNAB4O1-13GZ-120T-150-T6-3273 (GE14C)

GE14-P10CNAB402-13GZ-120T-150-T6-3274 (GE14C) 327 GEI4-PI OCNAB4 16-1 5GZ- 34 120T-150-T6-3040 (GE14C)

GE 14-PIOCNAB398-12GZ-120T-150-T6-3275 (GE14C) 327 GEI4-P1OCNAB394-I5GZ- 3272 120T- 150-T6-3272 (GE 14C)

GE14-P1OCNAB415-15GZ-120T-150-T6-3042 (GE14C)

GE14-PLOCNAB415-15GZ-120T-150-T6-3039 (GE14C)

GNF2-P10CG2B393-10G7.0/2G6.0-120T250-T(1 4048 4048 (GNF2) 14_)

GNF2-P 10CG2B4104-1 2G6.0- 4044 100T2- 150-T6-4044 (GNF2) 18 Maximum lattice k. for the most reactive uncontrolled state plus a ((

)) adder for uncertainties.

Page 22 COLR Page 39 of 57

Exelon Nuclear - Nuclear.Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 * 'Appendix A Limerick Unit I NOn-Proprietary Information 0000-0131 -9339-FBIR-NP Reload 14 Class .1(Public)- - - Revision 0 GNF2-P 10CG2B404-12G6.0-120T2-150-T6-3643 (GNF2)

GNF2-P10CG2B387-15GZ- 404 120T2-150-T6-4045 (GNF2)

GNF2-P10CG2B388-13GZ-120T2-150-T6-4046 (GNF2)

GNF2-P10CG2B392-15GZ- 4047 120T2-150-T6-4047 (GNF2) ___

Page 23 COLR Page 40 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Lir.,erick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit I Non-Proprietary Information 0000-0131-9339-FBIR-NP ,.

Reload 14 Class I (Public) Revision 0 Figure B-1 Enrichment and Gadolinium Distribution for EDB No. 3035 Fuel Bundle GE14-P1OCNAB415-15GZ-120T-150-T6-3035 (GE14C)

Page 24 COLR Page 41 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Rieport Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix: A Lirherick Unit 1' Non-Proprietary Inforiation 0000-0131-9339-FBIR-NP Reload 14 Class I-(Public)--- . ... . .. Revision 0 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 3038 Fuel Bundle GE14-P1OCNAB415-15GZ-120T-150-T6-3038 (GE14C)

Page 25 COLR Page 42 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick1 ReRv. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR-NP Reload 14 Class I (Public) Revision 0

[1 Figure B-3 -Enrichment and Gadolinium Distribution for EDB No. 3041 Fuel Bundle GE14-P1OCNAB415-15GZ-120T-150-T6-3041 (GE14C)

Page 26 COLR Page 43 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Liniits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary information Submitted in Accordance with 10 CFR 2.390 :Appendix A

'Limerick Ufiit 1 Non-Proprietary Informatiofi ' 0000-013 1-9339-FBIR-NP Reload 14 .. Class I (Public)i: Revision 0 Figure B-4 Enrichment and GadoliniumDistribution for EDB No. 3271 Fuel Bundle GE14-P1OCNAB394-15GZ-120T-150-T6-3271 (GE14C)

Page 27 COLR Page 44 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit I Non-Proprietary Information. 0000-0131-9339-FBIR'NP Reload 14 Class I (Public) Revision 0 evision 0

((

Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3273 Fuel Bundle GE14-P1OCNAB401-13GZ-120T-150-T6-3273 (GE14C)

Page 28 COLR Page 45 of 57

Exelon Nuclear w,Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit I Non-Pr-oprietary. Information 0000-0131-9339-FBIR-NP Reload 14 Class I (Public)-'- - .- Revision 0 U[

Figure B-6 Enrichment and Gadolinium. Distribution for EDB No. 3274 Fuel Bundle GE14-P1OCNAB402-13GZ-120T-150-T6-3274 (GE14C)

Page 29 COLR Page 46 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit1 ,. . Non-Proprietary Information 0000-0131 -9339-FBI-NP Reload 14 Class I (Public) Revision 0

((

Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3040 Fuel Bundle GEl4-P1OCNAB416-15GZ-120T-150-T6-3040 (GE14C)

Page 30 COLR Page 47 of 57

Exelon Nuclear.- Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary.Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick R o 14Unit 1 Non-Proprietary Ihf6rmaiion I ... 0000-0131-9339-F'BIR-NP Reload "Class I (Pubfic) - Revision 0 Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3275 Fuel Bundle GE14-P1OCNAB398-12GZ-120T-150-T6-3275 (GE14C)

Page 31 COLR Page 48 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Intormation Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR-NP Reload 14 Class I (Public) Revision 0 a

1[

Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 3272 Fuel Bundle GE14-P1OCNAB394-15GZ-120T-150-T6-3272 (GE14C)

Page 32 COLR Page 49 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Do c ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit I Non-Proprietary Information 0000-0131 -933 9-FBIR-NP Reload 14 Class I (Public)..--. - .... Revision 0 0

Figure B-10 Enrichment and Gadolinium Distribution for EDB No. 3042 Fuel Bundle GE14-P1OCNAB415-15GZ-12OT-150-T6-3042 (GE14C)

Page 33 COLR Page 50 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLRlLimerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 AppendixA - : 1- i .

Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIRZNP .

Reload 14 Class I (Public) Revision 0

((

Figure B-11 Enrichment and Gadolinium Distribution for EDB No. 3039 Fuel Bundle GE14-P1OCNAB415-15GZ-120T-150-T6-3039 (GE14C)

Page 34 COLR Page 51 of 57

Exelon Nuclear-- Nuclear Fuels Core Operating Limits Report Doc ID: COMR Limerick 1, Rev. 10 Non-.Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0 131-9339-FBIR-NT Reload 14 ClaSs I (Public)-. Revision 0 Figure B-12 Enrichment and Gadolinium Distribution for EDB No. 4048 Fuel Bundle GNF2-P1OCG2B393-10G7.0/2G6.0-120T2-150-T6-4048 (GNF2)

Page 35 COLR Page 52 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A.......

Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR7-NP "

Reload 14 Class I (Public) Revision 0 1]

Figure B-13 Enrichment and Gadolinium Distribution for EDB No. 4044 Fuel Bundle GNF2-P1OCG2B404-12G6.0-100T2-150-T6-4044 (GNF2)

Page 36 COLR Page 53 of 57

Exelon Nuclear -:Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limernck 1, Rev. 10 Non-Proprietary !nformation Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit I Non-Proprietaryi'nformation 0000-0131-9339-FBIR-NP Reload 14 'Class I (Public) Revision 0 Figure B-14 Enrichment and Gadolinium Distribution forEDB No. 3643 Fuel Bundle GNF2-P10CG2B404-12G6.0-120T2-150-T6-3643 (GNF2)

Page 37 COLR Page 54 of 57

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A.

Limerick Unit 1 .I Non-Proprietary Information 0000-0131-9339-FBIR'NP -

Reload 14 Class I (Public) Revision 0 ,

Figure B-15 Enrichment and-Gadolinium Distribution for EDB No. 4045 Fuel Bundle GNF2-P10CG2B387-15GZ-120T2-150-T6-4045 (GNF2)

Page 38 COLR Page 55 of 57

Exelon Nuclear - Nuclear Fuels Core Operatinm'Limits Report Doc ID: COLR Limerick 1,Rev. 10 Non-Proprietary. Information Submitted in Accordance with 10 CFR 2:390 Appendix A

" LimerickUnit 1 Non-Proprieia1'y Iniformation 0000-0131-9339-FBIR-NP Reload 14 Class I (Puhlic)- - Revision 0 Figure B-16 Enrichment. and Gadolinium Distribution for EDB No. 4046 Fuel Bundle GNF2-PIOCG2B388-13GZ-12.0T2-150.-T6-4046 (GNF2)

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Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Doc ID: COLR Limerick 1, Rev. 10 Non-Proprietary Information Submitted in Accordance with 10 CFR 2.390 Appendix A Limerick Unit 1 Non-Proprietary Information 0000-0131-9339-FBIR'NP *-

Reload 14 Class I (Public) Revision00

  • A Figure B-17 Enrichment and Gadolinium Distribution for EDB No. 4047 Fuel Bundle GNF2-P10CG2B392-15GZ-120T2-150-T6-4047 (GNF2)

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