ML15156A386

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Issuance of the Core Operating Limits Report (COLR) for Reload 13, Cycle 14
ML15156A386
Person / Time
Site: Limerick Constellation icon.png
Issue date: 05/15/2015
From: Dougherty T J
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-15-067
Download: ML15156A386 (19)
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Text

AmExelon Generation, T.S. 6.9.1.12 LG-1 5-067 May 15, 2015 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 j2~*~4- ~Limerick Generating Station, Unit 2 Renewed Facility Operating License No NPF-85 NRC Docket Nos. 50-353

Subject:

Issuance of the Core Operating Limits Report (COLR) for Reload 13, Cycle 14 Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station (LGS) Unit 2 Reload 13 Cycle 14 which incorporates the revised cycle specific parameters resulting from the new configuration implemented for LGS, Unit 2.The COLR is being submitted to the NRC in accordance LGS, Unit 2 Technical Specification 6.9.1.12.If you have any questions or require additional information, please contact Giuseppe Rubinaccio at 610-718-3560.

Sincerely,-/-.3--- //Thomas J. Dougherty

-Site Vice President-Limerick Generating Station Exelon Generation Company, LLC

Attachment:

Core Operating Limits Report for Limerick Generating Station Reload 13, Cycle 14 cc: D. Dorman, Administrator, Region I, USNRC S. Rutenkroger, USNRC Sr. Resident Inspector, LGS R. Ennis, USNRC Project Manager for LGS R. R. Janati, PADEP-BRP (w/attachments)(w/attachments)(w/attachments)(w/attachments)

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Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 RELOAD 13, CYCLE 14 (This is a complete re-write; no annotations are used.)Prepared By- ." ( g-s .olmýesv.parv.Reviewed By: ___F. Trikur Independent Review .Reviewed By:Arthur Stefancyzk per TelecorJ-

! 'Reviewed By
Approved By: A. Stefanczyk iacto.gineenng-

/T. -ement E g'meering Safety Analysis J. Tusar Manager -BWR Design (GNF)Date: 5, Date: ~Date: 511/2015 Dat. : /Date: Z/Z/'/ -Date: L).()415_Station Qualified Reviewed By: )L. Korbeil Station Qualified Reviewer Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 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 I I 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 17 10.0 Methodology 18 11.0 References 18 Page 2 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 List of Tables TABLE 3-I TABLE 3-2 TABLE 4-I TABLE 4-2 TABLE 4-3 TABLE 5-I TABLE 5-2 TABLE 5-3 TABLE 5-4 TABLE 5-5 TABLE 6-I TABLE 6-2 TABLE 7-1 TABLE 7-2.TABLE 8-i TABLE 8-2 TABLE 9-I Page MAPLHGR versus Average Planar Exposure -All Fuel Types 7 MAPLHGR Single Loop Operation (SLO) Multiplier-All Fuel Types 7 Operating Limit Minimum Critical Power Ratio (OLMCPR) -All Fuel Types 9 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp -All Fuel Types 10 Flow Dependent MCPR Limits MCPR(F) -All Fuel Types 10 Linear Heat Generation Rate Limits -U0 2 Rods 11 Linear Heat Generation Rate Limits -Gad Rods I I LHGR Single Loop Operation (SLO) Multiplier

-All Fuel Types 12 Power Dependent LHGR Multiplier LHGRFAC(P)

-All Fuel Types 12 Flow Dependent LHGR Multiplier LHGRFAC(F)-All Fuel Types 13 Rod Block Monitor Setpoints 14 Reactor Coolant System Recirculation Flow Upscale Trip 14 Turbine Bypass System Response Time 15 Minimum Required Bypass Valves To Maintain System Operability 15 OPRM PBDA Trip Setpoints 16 SLO OPRM PBDA Trip Setpoints 16 Modes of Operation 17 Page 3 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 1.0 ARTS BASE DLO DTSP EOOS EOR FFWTI FWHO HTSP ICF ITSP Kp LHGR LHGRJ LHGRJ LTSP MAPF/MAPFt MAPLI MCPR MCPR MCPRI Terms and Definitions 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) and PLUOOS allowed at any point during the cycle in Dual Loop mode.Dual Loop Operation Rod Block Monitor Downscale Trip Setpoint Equipment Out of Service End of Rated, the cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.t Final Feedwater Temperature Reduction OS Feedwater Heaters Out of Service Rod Block Monitor High Trip Setpoint Increased Core Flow Rod Block Monitor Intermediate Trip Setpoint Off-rated power dependent OLMCPR multiplier Linear Heat Generation Rate FAC(F) ARTS LHGR thermal limit flow dependent multipliers FAC(P) ARTS LHGR thermal limit power dependent multipliers Rod Block Monitor Low Trip Setpoint AC(F) Off-rated flow dependent MAPLHGR multiplier AC(P) Off-rated power dependent MAPLHGR multiplier HGR Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio (F) Off-rated flow dependent OLMCPR multiplier (P) Off-rated power dependent OLMCPR multiplier Page 4 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 MELLLA Maximum Extended Load Line Limit Analysis MSIVOOS Main Steam Isolation Valve Out of Service OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor OOS Out of Service PBDA Period Based Detection Algorithm PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RBM Rod Block Monitor RPTOOS Recirculation Pump Trip Out of Service RWE Rod Withdrawal Error SLO Single Loop Operation TBSOOS Turbine Bypass System Out of Service TCV Turbine Control Valve TIPOOS Traversing In core Probe Out of Service TSV Turbine Stop Valve Page 5 of 1.8 Exelon Nuclear- Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 2.0 General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 14: " Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)" Minimum Critical Power Ratio (MCPR)* Single Loop Operation (SLO) OLMCPR adjustment

  • Off-rated OLMCPR adjustments (MCPR(P) or MCPR(F))" Off-rated OLMCPR multipliers (Kp)* Off-rated LHGR multipliers (LHGRFAC(P) or LHGRFAC(F))
  • Rod Block Monitor (RBM) setpoints" MAPLHGR single loop operation multiplier" LHGR single loop operation multiplier
1. Preparation of this report was performed in accordance with Exelon Nuclear, Nuclear Fuels T&RM NF-AB-120-3600.

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 82.9% of rated core flow during full power operation* Increased Core Flow (ICF) up to I 10% of rated core flow* Final Feedwater Temperature Reduction (FFWTR) up to 105°F during 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.

Further information on the cycle specific analyses for Limerick 2 Cycle 14 and the associated operating domains discussed above is available in Reference 2.Page 6 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Table 3-1. For single loop operation, a multiplier is used, which is shown in Table 3-2. The power and flow dependent multipliers for MAPLHGR 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 -All Fuel Types (Reference 2)Average Planar Exposure MAPLHGR Limit (GWDIST) (kW/ft)0.0 13.78 17.52 13.78 60.78 7.50 63.50 6.69 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier

-All Fuel Types (Reference 2)SLO Multiplier 0.80 Page 7 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Table 4-1 is derived from Reference 2 and is valid for all fuel types and all operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation.

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 generic 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 ten sets of power dependent MCPR multipliers (Kp) for use with BASE, TBSOOS, RPTOOS, PROOS, DLO and SLO conditions, and PROOS+TBSOOS, PROOS+RPTOOS, DLO only. The PLUOOS condition is included in the BASE MCPR(P) and MCPR(F) limits and Kp multipliers and is bounded by the TBSOOS limits and multipliers; 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). Section 7.0 contains the conditions for Turbine Bypass Valve Operability.

MCPR(P) and MCPR(F) adjustments are provided in Tables 4-2 and 4-3. 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 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) -All Fuel Types (References 2 and 8)SCRAM Cycle Ex posure Time < EOR -2542 _ EOR -2542 EOOS Combination MWd/ST MWd/ST B 1.36(2) 1.36 A 1.41 1.44 BASE SLO(3 B 1.58 1.58 A 1.58 1.58 B 1.37 1.39 A 1.46 1.48 TBSOOS SLO(3 B 1.58 1.58 A 1.58 1.58 B 1.37 1.39 A 1.54 1.56 RPTOOS SLO3) B 1.58 1.58 A 1.58 1.59 B 1.36,2) 1.36 A 1.41 1.47 PROOS SLO(3) B 1.58 1.58 A 1.58 1.58 PROOS+TBSOOS B 1.37 1.39 PROOS+RPTOOS B 1.37 1.39 1 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

For PROOS+TBSOOS and PROOS+RPTOOS, only Option B is allowed.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 1.58 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event.Page 9 of 18 Exelon Nuclear- Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 TABLE 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp -All Fuel Types (References 2 and 8)Core Core Thermal Power (% of rated)EOOS Flow 0 25 < 30 >30 65 85 100 Combination

(% of Combinatin rated% MCPR(P) Operating Limit MCPR Multiplier, Kp< 60 2.50 2.50 2.40 Base >60 2.5 2.5 2.55 1.340 1.131 1.067 1.000> 60 2.75 2.75 2.55 Base SLO >560 2.53 2.53 2.43 1.340 1.131 1.067 1.000> 60 2.78 2.78 2.58L< 60 3.25 3.25 2.75 TBSOOS >60 3.75 3.75 3.25 1.340 1.131 1.067 1.000> 60 3.75 3.75 3.25 TBSOOS SLO <560 3.28 3.28 2.78 1.340 1.131 1.067 1.000> 60 3.78 3.78 3.28 RPTOOS -60 2.50 2.50 2.40 1.340 1.131 1.067 1.000> 60 2.75 2.75 2.55 R<OS L 60 2.53 2.53 2.43 RPTOOS SLO 5 60 2.78 2.78 2.58 1.340 1.131 1.067 1.000> 60 2.78 2.78 2.58 PROOS <560 2.50 2.50 2.40 1.367 1.236 1.160 1.000> 60 2.75 2.75 2.55 PROOS SLO >560 2.53 2.53 2.43 1.367 1.236 1.160 1.000> 60 2.78 2.78 2.58 PROOS+TBSOOS

>560 3.25 3.25 2.75 1 .367 1.236 1.160 1.000> 60 3.75 3.75 3.25 PROOS+RPTOOS

> 60 2.50 2.50 2.40 1.367 1.236 1.160 1.000__________

> >60 2.75 2.75 2.55 _________TABLE 4-3 Flow Dependent MCPR Limits MCPR(F) -All Fuel Types (Reference 2)Flow MCPR(F)(% rated) Limit 0.0 1.70 30.0 1.53 79.0 1.25 110.0 1.25 Page 10 of 18 Exelon Nuclear-Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 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 U0 2 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 multiplier is used, which is shown in Table 5-3 and applied in Table 5-5. No further Single Loop Operating multipliers 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 ten sets of power dependent LHGR multipliers for use with the BASE, TBSOOS, RPTOOS, PROOS, DLO and SLO conditions, and PROOS+TBSOOS and PROOS+RPTOOS, DLO only. The PLUOOS condition is included in the BASE LHGRFAC(P) and LHGRFAC(F) multipliers and is bounded by the TBSOOS multipliers; 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). Section 7.0 contains the conditions for Turbine Bypass Valve Operability.

The ARTS LHGR multipliers are shown in Tables 5-4 and 5-5. Linear interpolation should be used for points not listed in Reference 7.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 (References 5 and 7)I Fuel Type I LHGR I GNF2 See Table B-I of Reference 7 TABLE 5-2 Linear Heat Generation Rate Limits -Gad Rods (References 5 and 7)Fuel Type LHGR GNF2 See Table B-2 of Reference 7 Page 11 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 TABLE 5-3 LHGR Single Loop Operation (SLO) Multiplier

-All Fuel Types (Reference 2)SLO Multiplier' 0.80 TABLE 5-4 Power Dependent LHGR Multiplier LHGRFAC(P)

-All Fuel Types (References 2 and 8)Core Core Thermal Power (% of rated)Flow _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _EOOS Combination

(%of 0 25 <130 1 301 65 85 100 rated) LHGRFAC(P)

Multiplier

=BASE 60 0.485 0.485 0.490 .750 0.817 0.922 1.000_ _ _ _ > 60 0.434 0.434 0.473 BASE SLO > 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473 TBSOOS 60 043 043 .90.0750 0.817 0.922 i.000<5 6 0.463 0.463 0.490____________

> 60 0.352 0.352 0386 0.750_ 0.817_ 1 0.22 .00 TBSOOS SLO 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000> 60 0.352 0.352 0.386 60 0.485 0.485 0.490 RPTOOS 0.434 0.434 0.473 0.750 0.817 0.922 1.000 S 60 0.434 0.434 0.4973* 60 0.485 0.485 0.497 RPTOOS SLO 60 0.45 0.45 0.40 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473 PROOS :L 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000> 60 0.434 0.434 0.473 60 0.434 0.434 0.473 PROOS+TBSOOS

< 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000> 60 0.352 0.352 0.386 0.750 0.817 0.2 _.0 PROOS+RPTOOS s60 0.485 0.485 0.490 0.750 0.817 0.922 1.000 I O O > 60 0.434 0.434 0.473 = -1 Applied through Table 5-5 Page 12 of 18 Exelon Nuclear- Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 TABLE 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F)

-All Fuel Types (Reference 2)Core Flow (% of rated)EOOS Combination 0 30 44.1 70 80 110 LHGRFAC(F)

Multiplier Dual Loop 0.506 0.706 0.973 1.000 1.000 Single Loop 0.506 0.706 0.800 0.800 S. ._ , .; ~ ,:.080 Page 13 of 18 Exelon Nuclear- Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9.6.0 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

control 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 Setpointsi (References 2 and 4)Power Level Analytical Allowable Nominal Trip Limit Value Setpoint LTSP 123.0% 121.5% 121.5%ITSP 118.0% 116.5% 116.5%HTSP 113.2% 111.7% 111.0%DTSP No Limitation 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.Page 14 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR.Liierick.2 Rev. 9 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 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 System Out Of Service (TBSOOS), 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 s following initial turbine inlet valve movement'Maximum time after initial turbine inlet valve movement' for bypass valve position to reach 80% of full flow (includes the 0.31 sec above delay time) II First movement of any TSV or any TCV or generation of the turbine bypass valve flow signal (whichever occurs first)TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (References I and 3)Reactor Power No. of Valves in Service P > 25% 7 Page 15 of 18 Exelon Nuclear- Nuclear Fuels S. .Core Operating Iinits Report COLR Limerick 2 Rev. 9 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1 8.2 Description The Limerick 2 Cycle 14 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. The setpoints provided in Table 8-2 are acceptable for use in Single Loop Operation.

The standard two loop operation OPRM Setpoints specified in Table 8-1 must be implemented prior to restarting the idle pump when exiting the SLO condition.

TABLE 8-1 OPRM PBDA Trip Setpoints (Reference 2)TABLE 8-2 SLO OPRM PBDA Trip Setpoints (Reference 2)Page 16 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 9.0 Modes of Operation 9.1 Description The allowable modes of operation are found in Table 9-1. Operation with I MSIVOOS, or I TCVITSV OOS is supported in all modes of operation, provided the restrictions identified in the applicable station procedures are met. All EOOS options also support the allowance of I TIPOOS.TABLE 9-1 Modes of Operation (References 2 and 8)EOOS Options Operating Region'BASE, Option A or B Yes 2 BASE SLO, Option A or B Yes 2 TBSOOS, Option A or B Yes 2 TBSOOS SLO, Option A or B Yes 2 RPTOOS, Option A or B Yes 3 RPTOOS SLO, Option A or B Yes 3 TBSOOS and RPTOOS, Option A or B No TBSOOS and RPTOOS SLO, Option A or B No PROOS, Option A or B Yes'PROOS SLO, Option A or B Yese PROOS+TBSOOS, Option A No PROOS+TBSOOS, Option B Yes 2 PROOS+TBSOOS SLO, Option A or B No PROOS+RPTOOS, Option A No PROOS+RPTOOS, Option B Yes 3 PROOS+RPTOOS SLO, Option A or B No'Operating Region refers to operation on the Power to Flow map with or without FFWTR/FWHOOS.

2 The PLUOOS condition is supported in this mode of operation with no power reduction required.3 The PLUOOS condition requires core thermal power level < 55% of rated (Reference 3).Page 17 of 18 Exelon Nuclear -Nuclear Fuels Core Operating Limits Report COLR Limerick 2 Rev. 9 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-2 1, May 2015 and the U.S. Supplement NEDE-2401 I-P-A-21-US, May 2015.2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", GENE Document, NEDO-32465-A, August 1996.11.0 References I. "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 13 Cycle 14", Global Nuclear Fuel Document No. 000N9396-SRLR, Rev. 0, February 2015.3. "Final Resolved OPL-3 Parameters for Limerick Unit 2 Cycle 14", Exelon TODI ES1400022 Rev. 0, October 30,2014.4. "GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0107, Rev. 2, February 23, 2012.5. "Fuel Bundle Information Report for Limerick 2 Reload 13 Cycle 14", Global Nuclear Fuel Document No. 000N9397-FBIR, Rev. 0, February 2015.6. "Tech Eval Stop Valve Load Limit Documentation", Exelon Document IR 917231 Assignment 7, November 11, 2009.7. "GNF2 Advantage Generic Compliance with NEDE-2401 1-PA (GESTAR IlI)", Global Nuclear Fuel Document No. NEDC-33270P, Rev. 5, May 2013.8. "Limerick Generating Station (LGS) Units I and 2 TRACG Cycle-Independent PROOS Analysis Report", GE Hitachi Nuclear Energy Document No. 002N4397, Rev. 0, February 24, 2015.Page 18 of 18

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