ML18082A057

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Issuance of a Revision to the Core Operating Limits Report (Cola) for Unit 2 Reload 14, Cycle 15
ML18082A057
Person / Time
Site: Limerick Constellation icon.png
Issue date: 03/23/2018
From: Libra R W
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-18-041
Download: ML18082A057 (25)
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Exelon Generation , LG-18-041 March 23, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Limerick Generating Station, Unit 2 Renewed Facility Operating License No NPF-85 NRG Docket Nos. 50-353 T.S. 6.9.1.12

Subject:

Issuance of a Revision to the Core Operating Limits Report (COLA) for Unit 2 Reload 14, Cycle 15 Enclosed is a copy of a revision to the Core Operating Limits Report (COLR) for Limerick Generating Station (LGS) Unit 2 Reload 14, Cycle 15. The COLR is being submitted to the NRG in accordance with LGS, Unit 2 Technical Specification 6.9.1.12.

If you have any questions or require additional information, please contact Shawn Pinney at 610-718-3560.

Respectfully, \ Richard W. Libra Site Vice President-Limerick Generating Station Exelon Generation Company, LLC

Attachment:

Core Operating Limits Report for Limerick Generating Station Unit 2 Reload 14, Cycle 15 cc: D. Dorman, Administrator, Region I, USNRC S. Rutenkroger, USNRC Sr. Resident Inspector, LGS V. Sreenivas, USNRC Project Manager for LGS R. Janati, PADEP-BRP (w/attachments) (w/attachments) (w/attachments) (w/attachments) 02MAR18 3/09/18 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 2 of 24 Table of Contents Page Revision History 3 List of Tables 4 1.0Terms and Definitions 6 2.0General Information 8 3.0MAPLHGR Limits 9 4.0MCPR Limits 10 5.0LHGR Limits 17 6.0Control Rod Block Setpoints 20 7.0Turbine Bypass Valve Parameters 21 8.0Stability Protection Setpoints 22 9.0Modes of Operation 23 10.0Methodology2411.0References24 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 3 of 24 Revision History RevisionDescription Revision 12 Revision 11 Incorporates MCPR penalties due to lost part identified in Issue Reports 4061623/4063206.

See also Issue Report 4063380. New issue for Cycle 15 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 4 of 24 List of Tables Page TABLE 3-1 MAPLHGR versus Average Planar Exposure 9 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 9 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) Central Orifice Bundle Locations 11 TABLE 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) Peripheral and Bottom Entry Orifice Bundle Locations 12 TABLE 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp Central Orifice Bundle Locations 13TABLE 4-4 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp Peripheral and Bottom Entry Orifice Bundle Locations 14 TABLE 4-5 Flow Dependent MCPR Limits MCPR(F) Central Orifice Bundle Locations 15 TABLE 4-6 Flow Dependent MCPR Limits MCPR(F) Peripheral and Bottom Entry Orifice Bundle Locations 15 TABLE 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) Central Orifice Bundle Locations 16 TABLE 4-8 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) Peripheral and Bottom Entry Orifice Bundle Locations 16 TABLE 5-1 Linear Heat Generation Rate Limits - UO 2 Rods 17TABLE 5-2 Linear Heat Generation Rate Limits - Gad Rods 17TABLE 5-3 LHGR Single Loop Operation (SLO) Multiplier 18TABLE 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) 18TABLE 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) 19TABLE 6-1 Rod Block Monitor Setpoints 20TABLE 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 20TABLE 7-1 Turbine Bypass System Response Time 21 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 5 of 24 List of Tables (continued) Page TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability 21TABLE 8-1 OPRM PBDA Trip Setpoints 22 TABLE 9-1 Modes of Operation 23 TABLE 9-2 "BASE" EOOS Option - Included Conditions 23 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 6 of 24 1.0Terms and DefinitionsAPRM Average Power Range Monitor ARTS APRM, RBM, and Technical Specification Improvement Program BASE This condition is defined by a group of individual operating conditions that are applicable to all Modes of Operation discussed in Section 9. The "BASE" condition includes the EOOS conditions provided in Table 9-2 as well as operation with FWHOOS/FFWTR. Central Orifice Bundle locations associated with the PANACEA dataset IBORF=1. Bundle Locations 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%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon. FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heater(s) 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 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 7 of 24 MCPR Minimum Critical Power Ratio MCPR(F) Off-rated flow dependent OLMCPR multiplier MCPR(P) Off-rated power dependent OLMCPR multiplier MELLLA Maximum Extended Load Line Limit Analysis MSIVOOS Main Steam Isolation Valve Out of Service OLMCPR Operating Limit Minimum Critical Power Ratio OOS Out of Service OPRM Oscillation Power Range Monitor PBDA Period Based Detection Algorithm Peripheral and Bottom Bundle locations associated with the PANACEA dataset IBORF=2. Entry Orifice Bundle Locations 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 SRVOOS Safety Relief Valve Out of Service TBSOOS Turbine Bypass System Out of Service TBVOOS Turbine Bypass Valve(s) Out of Service TCV Turbine Control Valve TCV/TSVOOS 1 Turbine Control Valve Out of Service and/or 1 Turbine Stop Valve Out of Service TSV Turbine Stop Valve Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 8 of 24 2.0General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 15: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 Linear Heat Generation Rate (LHGR) Turbine Bypass Valve parameters Reactor Coolant System Recirculation Flow Upscale Trips 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. 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 110% of rated core flow Final Feedwater Temperature Reduction (FFWTR) up to 105F during cycle extension operation Feedwater Heater Out of Service (FWHOOS) up to 60F feedwater temperature reduction at any time during the cycle prior to cycle extension. Further information on the cycle specific analyses for Limerick 2 Cycle 15 and the associated operating domains discussed above is available in Reference 2.

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 9 of 24 3.0MAPLHGR Limits 3.1Technical Specification Section 3.2.1 3.2Description The limiting MAPLHGR value for the most limiting lattice of GNF2 fuel 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 (Reference 2)

Average Planar Exposure (GWD/ST) MAPLHGR Limit (kW/ft) 0.0 13.7817.52 13.7860.78 7.5063.50 6.69 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2) SLO Multiplier 0.80 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 10 of 24 4.0MCPR Limits 4.1Technical Specification Section 3.2.3 4.2Description The Operating Limit MCPR (OLMCPR) for GNF2 fuel, by bundle location relative to orifice type, is provided in Tables 4-1 and 4-2. These values are determined by the cycle-specific reload analyses in References 2 and 9 and are valid for all Cycle 15 operating domains. 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 2 Cycle 15 has a mid-cycle breakpoint, as defined in Tables 4-1 and 4-2. 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 operating domains. 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, and PROOS equipment out of service combinations, in both DLO and SLO, as well as PROOS+TBSOOS and PROOS+RPTOOS equipment out of service combinations for DLO only. The PROOS+TBSOOS and PROOS+RPTOOS combinations were developed by selecting the more limiting OLMCPR from the PROOS condition and the other EOOS condition (TBSOOS or RPTOOS) (Reference 8). Section 7.0 contains the conditions for Turbine Bypass Valve Operability.MCPR(P) and MCPR(F) adjustments are provided in Tables 4-3, 4-4, 4-5, 4-6, 4-7, and 4-8 (Reference 9). The table titles indicate the bundle locations to which the presented values apply. 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.

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 11 of 24 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) Central Orifice Bundle Locations (Reference 9)EOOS Combination SCRAM Time Option (1)Cycle Exposure

< EOR - 3847 MWd/ST EOR - 3847 MWd/STBASE B1.40 1.40 A1.44 1.49 BASE SLO B1.62 1.62 A1.62 1.62 TBSOOS B1.401.45 A1.48 1.54 TBSOOS SLO B1.62 1.62 A1.62 1.62 RPTOOS B1.401.44 A1.56 1.61 RPTOOS SLO B1.62 1.62 A1.62 1.65 PROOS B1.40 1.41 A1.44 1.49 PROOS SLO B1.62 1.62 A1.62 1.62 PROOS+TBSOOS B 1.401.45 PROOS+RPTOOSB 1.40 1.44 1 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 12 of 24 TABLE 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) Peripheral and Bottom Entry Orifice Bundle Locations (Reference 9) EOOS Combination SCRAM Time Option (1)Cycle Exposure

< EOR - 3847 MWd/ST EOR - 3847 MWd/STBASE B 2.38 2.38 A2.45 2.53 BASE SLO B2.76 2.76 A2.76 2.76 TBSOOS B2.38 2.47 A2.52 2.62 TBSOOS SLO B2.76 2.76 A2.76 2.76 RPTOOS B2.38 2.45 A2.66 2.74 RPTOOS SLO B2.762.76 A2.76 2.81 PROOS B2.38 2.40 A2.45 2.53 PROOS SLO B2.76 2.76 A2.76 2.76 PROOS+TBSOOS B 2.38 2.47 PROOS+RPTOOSB 2.38 2.45 1 When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 13 of 24 TABLE 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp Central Orifice Bundle Locations (Reference 9) EOOS Combination Core Flow

(% of rated)Core Thermal Power (% of rated)0 25 < 30 30 65 85 100 MCPR(P)Operating Limit MCPR Multiplier, KpBase 60 2.55 2.552.45 1.340 1.131 1.067 1.000 > 60 2.82 2.822.60Base SLO 60 2.59 2.592.49 1.340 1.131 1.067 1.000 > 60 2.86 2.862.64TBSOOS 60 3.32 3.322.82 1.340 1.131 1.067 1.000 > 60 3.83 3.833.32TBSOOS SLO 60 3.36 3.362.86 1.340 1.131 1.067 1.000 > 60 3.87 3.873.36RPTOOS 60 2.55 2.552.45 1.340 1.131 1.067 1.000 > 60 2.82 2.822.60RPTOOS SLO 60 2.59 2.592.49 1.340 1.131 1.067 1.000 > 60 2.86 2.862.64PROOS 60 2.55 2.552.45 1.367 1.236 1.160 1.000 > 60 2.82 2.822.60 PROOS SLO 60 2.59 2.592.49 1.367 1.236 1.160 1.000 > 60 2.86 2.862.64PROOS+TBSOOS 60 3.32 3.322.82 1.367 1.236 1.160 1.000 > 60 3.83 3.833.32PROOS+RPTOOS 60 2.55 2.552.45 1.367 1.236 1.160 1.000 > 60 2.82 2.822.60 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 14 of 24 TABLE 4-4 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp Peripheral and Bottom Entry Orifice Bundle Locations (Reference 9) EOOS Combination Core Flow (% of rated)Core Thermal Power (% of rated)0 25 < 30 30 65 85 100 MCPR(P)Operating Limit MCPR Multiplier, KpBase 60 4.34 4.344.17 1.340 1.131 1.067 1.000 > 60 4.79 4.794.43Base SLO 60 4.41 4.414.24 1.340 1.131 1.067 1.000 > 60 4.86 4.864.50TBSOOS 60 5.66 5.664.79 1.340 1.131 1.067 1.000 > 60 6.52 6.525.66TBSOOS SLO 60 5.72 5.724.86 1.340 1.131 1.067 1.000 > 60 6.59 6.595.72RPTOOS 60 4.34 4.344.17 1.340 1.131 1.067 1.000 > 60 4.79 4.794.43RPTOOS SLO 60 4.41 4.414.24 1.340 1.131 1.067 1.000 > 60 4.86 4.864.50PROOS 60 4.34 4.344.17 1.367 1.236 1.160 1.000 > 60 4.79 4.794.43 PROOS SLO 60 4.41 4.414.24 1.367 1.236 1.160 1.000 > 60 4.86 4.864.50PROOS+TBSOOS 60 5.66 5.664.79 1.367 1.236 1.160 1.000 > 60 6.52 6.525.66PROOS+RPTOOS 60 4.34 4.344.17 1.367 1.236 1.160 1.000 > 60 4.79 4.794.43 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 15 of 24 TABLE 4-5 Flow Dependent MCPR Limits MCPR(F)Central Orifice Bundle Locations (Reference 9)

Flow(% rated)

MCPR(F)Limit 0.0 1.72 30.0 1.55 79.0 1.27 110.0 1.27 TABLE 4-6 Flow Dependent MCPR Limits MCPR(F)Peripheral and Bottom Entry Orifice Bundle Locations (Reference 9)

Flow(% rated)

MCPR(F)Limit 0.0 2.93 30.0 2.64 79.0 2.16 110.0 2.16 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 16 of 24 TABLE 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)Central Orifice Bundle Locations (Reference 9)

Flow(% rated)

MCPR(F)Limit 0.0 1.76 30.0 1.59 79.01.31110.0 1.31 TABLE 4-8 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)Peripheral and Bottom Entry Orifice Bundle Locations (Reference 9)

Flow(% rated)

MCPR(F)Limit 0.0 3.00 30.0 2.71 79.0 2.22 110.02.22 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 17 of 24 5.0LHGR Limits 5.1Technical Specification Section 3.2.4 5.2Description The LHGR limit for the GNF2 fuel type is the product of the exposure dependent LHGR limit (from Table 5-1 for UO 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 BASE, TBSOOS, RPTOOS, and PROOS equipment out of service combinations, in both DLO and SLO, as well as PROOS+TBSOOS and PROOS+RPTOOS equipment out of service combinations for DLO only. The PROOS+TBSOOS and PROOS+RPTOOS combinations were developed by selecting the more limiting LHGRFAC(P) from the PROOS condition and the other EOOS condition (TBSOOS or RPTOOS) (Reference 8). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. The ARTS LHGR multipliers are shown in Tables 5-4 and 5-5 and are applicable to all operating domains. Linear interpolation should be used for points not listed in Appendix B of Reference 7.Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power and flow biased calculation.

TABLE 5-1 Linear Heat Generation Rate Limits - UO 2 Rods (References 5 and 7) Fuel Type LHGR GNF2 See Table B-1 ofReference 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 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 18 of 24 TABLE 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2) SLO Multiplier 1 0.80 TABLE 5-4 Power Dependent LHGR Multiplier LHGRFAC(P)(References 2 and 8) EOOS Combination Core Flow (% of rated)Core Thermal Power (% of rated) 0 25 < 30 30 65 85 100 LHGRFAC(P) MultiplierBASE 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000 > 60 0.4340.4340.473 BASE SLO 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000 > 60 0.4340.4340.473TBSOOS 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000 > 60 0.3520.3520.386TBSOOS SLO 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000 > 60 0.3520.3520.386RPTOOS 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000 > 60 0.4340.4340.473RPTOOS SLO 60 0.485 0.485 0.490 0.750 0.817 0.922 1.000 > 60 0.4340.4340.473 PROOS 60 0.485 0.485 0.490 0.725 0.817 0.922 1.000 > 60 0.4340.4340.473PROOS SLO 60 0.485 0.485 0.490 0.725 0.817 0.922 1.000 > 60 0.4340.4340.473PROOS+TBSOOS 60 0.463 0.463 0.490 0.725 0.817 0.922 1.000 > 60 0.3520.3520.386PROOS+RPTOOS 60 0.485 0.485 0.490 0.725 0.817 0.922 1.000 > 60 0.4340.4340.473 1 Applied through Table 5-5 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 19 of 24 TABLE 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F)(Reference 2) EOOS Combination Core Flow (% of rated)0 30 44.1 70 80 110 LHGRFAC(F) MultiplierDual Loop0.506 0.706 0.973 1.000 1.000 Single Loop0.506 0.706 0.800 0.800 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 20 of 24 6.0Control Rod Block Setpoints 6.1Technical Specification Sections 3.1.4.3 and 3.3.6 6.2Description 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 Setpoints 1 (References 2 and 4)Power Level Analytical LimitAllowable ValueNominal Trip SetpointLTSP 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 6-2Reactor Coolant System Recirculation Flow Upscale Trip (Reference 4) Analytical LimitN/AAllowable Value115.6%Nominal Trip Setpoint113.4%

1These setpoints are based on a Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds.

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 21 of 24 7.0Turbine Bypass Valve Parameters 7.1Technical Specification Section 3.7.8 and 4.7.8.c 7.2Description 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 following initial turbine inlet valve movement 1 0.11 sec Maximum time after initial turbine inlet valve movement 1 for bypass valve position to reach 80% of full flow (includes the above delay time) 0.31 sec 1First movement of any TSV or any TCV (whichever occurs first)

TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (References 1 and 3) Reactor Power No. of Valves in Service P 25% 7 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 22 of 24 8.0Stability Protection Setpoints 8.1Technical Specification Section 2.2.1 8.2Description The Limerick Unit 2 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) PBDA Trip Amplitude Corresponding Maximum Confirmation Count Trip Setting 1.11 14 Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 23 of 24 9.0Modes of Operation 9.1Description The following conditions are supported by the Limerick Unit 2 Cycle 15 licensing analysis; operation in a condition (or conditions) is controlled by station procedures. If a combination of options is not listed, it is not supported. Table 9-1 provides allowed modes of operation with thermal limit sets in this COLR. Table 9-2 provides allowed modes of operation that do not contain explicit thermal limit sets in this COLR.TABLE 9-1 Modes of Operation (References 2 and 8) EOOS Options 1 Supported Scram Speed Option Supported Recirculation Loops BASE2,3 Option A or B DLO or SLO TBSOOS 4 Option A or BDLO or SLO RPTOOS 5Option A or BDLO or SLO PROOS Option A or BDLO or SLO PROOS+TBSOOS 4Option BDLO PROOS+RPTOOS 5Option BDLO TABLE 9-2 "BASE" EOOS Option - Included Conditions (Reference 2)

Condition PLUOOS 1 MSIVOOS 6 1 TCV/TSVOOS4,7 2 TBVOOS 2 SRVOOS 1 All EOOS Options include the "BASE" EOOS Option. Any restrictions beyond the "BASE" condition's restrictions are noted on the applicable EOOS option.

2 The "BASE" condition includes the conditions listed in Table 9-2.

3 The "BASE" condition includes operation with or without FWHOOS/FFWTR.

4 1 TCV/TSVOOS is valid coincident with the TBSOOS condition, but only at power levels 64% rated thermal power. 5 PLUOOS is valid coincident with the RPTOOS condition, but only at power levels < 55% rated thermal power.

6 1 MSIVOOS is valid only at power levels 75% rated thermal power.

7 1 TCV/TSVOOS is valid only at power levels 70% rated thermal power.

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 12 Core Operating Limits Report for Limerick 2 Cycle 15 Page 24 of 24 10.0Methodology 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-24011-P-A-23, September 2016 and the U.S. Supplement NEDE-24011-P-A-23-US, September 2016.2."Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications",GENE Document, NEDO-32465-A, August 1996.11.0References 1."Technical Specifications and Bases for Limerick Generating Station Unit 2", Exelon Document, DocketNo. 50-353, License No. NPF-85.2."Supplemental Reload Licensing Report for Limerick Unit 2 Reload 14 Cycle 15", Global Nuclear FuelDocument No. 002N6932, Rev. 0, March 2017.3."Final Resolved OPL-3 Parameters for Limerick 2 Cycle 15", Exelon TODI ES1600020 Rev. 0, November 8, 2016.4."GE NUMAC PRNM Setpoint Study", Exelon Design Analysis LE-0107, Rev. 2, February 23, 2012.5."Fuel Bundle Information Report for Limerick Unit 2 Reload 14 Cycle 15", Global Nuclear FuelDocument No. 002N6933, Rev. 0, March 2017.6."Tech Eval Stop Valve Load Limit Documentation", Exelon Document IR 917231 Assignment 7,November 11, 2009.7."GNF2 Advantage Generic Compliance with NEDE-24011-PA (GESTAR II)", Global Nuclear FuelDocument No. NEDC-33270P, Rev. 7, October 2016.8."Limerick Generating Station (LGS) Units 1 and 2 TRACG Cycle-Independent PROOS Analysis Report",GE Hitachi Document No. 002N4397 R1, Rev. 1, January 2016.9."OLMCPR Penalties Supporting Lost Part for Limerick Unit 2 Cycle 15", Global Nuclear Fuel DocumentNo. 004N6492, Rev. 0, February 2018.

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