LG-23-040, Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 17, Cycle 18

Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 17, Cycle 18

ML23151A718
Person / Time
Site:	Limerick
Issue date:	05/31/2023
From:	Gillin M Constellation Energy Generation
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LG-23-040
Download: ML23151A718 (1)

Text

Constellation T.S. 6 .9.1.12 LG-23-040 May 31, 2023 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Limerick Generating Station, Unit 2 Renewed Facility Operating License Nos. NPF-85 NRC Docket Nos. 50-353

Subject:

Issuance of the Core Operating Limits Report (COLR) for Unit 2 Reload 17, Cycle 18 Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station (LGS) Unit 2 Reload 17 Cycle 18 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 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, Michael F. Gillin Vice President - Limerick Generating Station Constellation Energy Generation, LLC

Attachment:

Core Operating Limits Report for Limerick Generating Station Unit 2 Reload 17 Cycle 18 cc: Regional Administrator, Region 1, USNRC LGS USNRC Senior Resident Inspector

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 CORE OPERATING LIMITS REPORT FOR Limerick Generating Station Unit 2 Reload 17, Cycle 18 Digitally signed by Bracke, Adam J

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Prepared By: ____________________________________________________ Date: 2023.05.05Date: 20:57:01 -04'00' Adam Bracke Fuel Cycle Management 2023.05.08 10:47:34 Reviewed By: v~~ -04'00'

____________________________________________________ Date: ____________

Victoria Riso Fuel Cycle Management - Peer Review J~f!lJJ~ Gutowski, Thomas M.

2023.05.05 21:46:43 -04'00' Reviewed By: ____________________________________________________ Date: ____________

Thomas Gutowski Reactor Engineering Digitally signed by Wolff, Christopher Wolff, Christopher DN: cn=Wolff, Christopher Date: 2023.05.08 09:33:26 -04'00' Reviewed By: ____________________________________________________ Date: ____________

Christopher Wolff Engineering Safety Analysis Digitally signed by McCoskey, Kristin Date: 2023.05.09 14:40:55 -05'00' Approved By: ____________________________________________________ Date: ____________

Kristin McCoskey Sr. Manager - BWR Fuel Cycle Management Station Qualified Doran, Declan L.

Review By: ____________________________________________________

2023.05.11 08:33:09 -04'00' Date: ____________

Declan Doran Reactor Engineering Page 1 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 Table of Contents Page Revision History 3 List of Tables 4 1.0 Terms and Definitions 5 2.0 General Information 7 3.0 MAPLHGR Limits 8 4.0 MCPR Limits 10 5.0 Linear Heat Generation Rate Limits 16 6.0 Control Rod Block Setpoints 21 7.0 Turbine Bypass Valve Parameters 23 8.0 Stability Protection Setpoints 24 9.0 Modes of Operation 25 10.0 Methodology 27 11.0 References 28 Page 2 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 Revision History Revision Description Rev. Number - 15 New issue for Cycle 18 Page 3 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure for GNF2 Fuel (except Bundle Number 4488) 8 Table 3-2 MAPLHGR Versus Average Planer Exposure for Bundle Number 4488 Fuel 9 Table 3-3 MAPLHGR Versus Average Planar Exposure for GNF3 Fuel 9 Table 3-4 MAPLHGR Single Loop Operation (SLO) Multiplier 9 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) for GNF2 Fuel 11 Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for GNF3 Fuel 12 Table 4-3 Power Dependent MCPR Limits and Multipliers, MCPRP and Kp 13 Table 4-4 Flow Dependent MCPR Limits MCPRF for GNF 2 Fuel 14 Table 4-5 Flow Dependent MCPR Limits MCPRF for GNF3 Fuel 14 Table 4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPRF for GNF2 Fuel 14 Table 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPRF for GNF3 Fuel 15 Table 4-8 Cycle Specific SLMCPR (MCPR99.9%) 15 Table 5-1 Linear Heat Generation Rate Limits - UO2 Rods 16 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 17 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier 17 Table 5-4 Power Dependent LHGR Multiplier LHGRFACP for GNF2 Fuel 18 Table 5-5 Power Dependent LHGR Multiplier LHGRFACP for GNF3 Fuel 19 Table 5-6 Flow Dependent LHGR Multiplier LHGRFACF for GNF2 Fuel 20 Table 5-7 Flow Dependent LHGR Multiplier LHGRFACF for GNF3 Fuel 20 Table 6-1 Rod Block Monitor Setpoints 21 Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 21 Table 6-3 RBM Operability Limits 22 Table 7-1 Turbine Bypass System Response Time 23 Table 7-2 Minimum Required Bypass Valves To Maintain System Operability 23 Table 8-1 OPRM PBDA Trip Setpoints 24 Table 9-1 Modes of Operation 25 Table 9-2 Base EOOS Option - Included Conditions 25 Table 9-3 Power Level Restrictions 26 Page 4 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 1.0 Terms and Definitions ARTS APRM and RBM 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 BSP Backup Stability Protection DLO Dual Loop Operation DTSP Rod Block Monitor Downscale Trip Setpoint ECCS Emergency Core Cooling System EOOS Equipment Out of Service EOR End of Rated. The cycle exposure at which reactor power is equal to 3515 MWth 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 HBLUA High Burnup Lead Use Assembly 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 LHGRFACF Off-rated flow dependent LHGR multipliers LHGRFACP Off-rated power dependent LHGR multipliers LOCA Loss of Coolant Accident LTSP Rod Block Monitor Low Trip Setpoint MAPFACF Off-rated flow dependent MAPLHGR multiplier MAPFACP Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR99.9% Limiting MCPR value such that 99.9 percent of the fuel in the core is not susceptible to boiling transition MCPRF Off-rated flow dependent OLMCPR MCPRP Off-rated power dependent OLMCPR MSIVOOS Main Steam Isolation Valve Out of Service Page 5 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 NFWT Normal Feedwater Temperature OLMCPR Operating Limit Minimum Critical Power Ratio OOS Out of Service OPRM Oscillation Power Range Monitor PBDA Period Based Detection Algorithm PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RBM Rod Block Monitor RPTOOS Recirculation Pump Trip Out of Service RWE Rod Withdrawal Error SLMCPR Safety Limit Minimum Critical Power Ratio 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 Turbine Control Valve Out of Service and/or Turbine Stop Valve Out of Service TSV Turbine Stop Valve Page 6 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 2.0 General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 18 x Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) x Single Loop Operation (SLO) MAPLHGR multipliers x Operating Limit Minimum Critical Power Ratio (OLMCPR) x ARTS MCPR thermal limits and multipliers x SLO MCPR limits x Cycle-specific SLMCPR (MCPR99.9%)

x Linear Heat Generation Rate (LHGR) x ARTS LHGR thermal limit multipliers x SLO LHGR multiplier x Rod Block Monitor (RBM) Allowable Values, Setpoints, and MCPR Limits x Turbine Bypass Valve Parameters x Reactor Coolant System Recirculation Flow Upscale Trips x Stability Protection Setpoints x Power Level Restrictions This report is prepared in accordance with (IAW) Technical Specification 6.9.1.9 of Reference 1.

Preparation of this report was performed IAW Constellation, Nuclear Fuels T&RM NF-AB-120-3600.

Power and flow dependent limits and multipliers 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 (Reference 2):

x Maximum Extended Load Line Limit down to 82.9% of rated core flow during full power operation.

x Increased Core Flow (ICF) up to 110% of rated core flow.

x Final Feedwater Temperature Reduction (FFWTR) up to 105qF during cycle extension operation.

x Feedwater Heater Out of Service (FWHOOS) up to 60qF feedwater temperature reduction at any time during the cycle prior to cycle extension.

x End-of-cycle (EOC) power coastdown operation to a minimum power level of 40% of rated thermal power.

There is one (1) GNF2 High Burnup Lead Use Assembly loaded in Cycle 18. The one (1) HBLUA is from fuel batch number GNF2-P10CG2B376-8G7.0/3G6.0-100T2-150-T6-4488 (Bundle Number 4488) (Reference 2). The HBLUA specific ID is provided in the High Burnup Lead Use Assembly Information Report (Reference 12).

A variation of 2.0% in core flow, or 10 psi in dome pressure, or 10 degrees Fahrenheit in feedwater temperature does not have significant impact on the transient analysis results including calculated OLMCPR and LHGRFAC (Reference 10). Equipment out of service conditions are as defined in Section 1 and Section 9. Further information on the cycle-specific analyses for Limerick Unit 2 Cycle 18 and the associated operating domains discussed above is available in Reference 2.

Page 7 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description The MAPLHGR values for the most limiting lattice for all GNF2 fuel, except for the High Burnup Lead Use Assembly (HBLUA), Bundle Number 4488, as a function of average planar exposure are given in Table 3-1. The MAPLHGR values for the one (1) HBLUA, Bundle Number 4488, as a function of average planar exposure are given in Table 3-2. The one (1) HBLUA is the only bundle that can operate at exposures greater than 63.50 GWd/ST in Cycle 18. The MAPLHGR values for the most limiting lattice for GNF3 fuel as a function of average planar exposure are given in Table 3-3.

For single loop operation, a multiplier is used, which is shown in Table 3-4 for both GNF2 and GNF3 fuel. The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective and there is no need for MAPLHGR multipliers (MAPFACF and MAPFACP), in addition to off-rated LHGR multipliers (Reference 2). LHGRFACP and LHGRFACF are addressed in Section 5.0.

Table 3-1 MAPLHGR Versus Average Planar Exposure GNF2 Fuel (except Bundle Number 4488 fuel)

(Reference 2)

Average Planar Exposure MAPLHGR Limit (GWd/ST) (kW/ft) 0.00 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Page 8 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 Table 3-2 MAPLHGR Versus Average Planar Exposure Bundle Number 4488 GNF2 Fuel1 (Reference 2)

Average Planar Exposure MAPLHGR Limit (GWd/ST) (kW/ft) 0.00 13.78 17.52 13.78 60.78 7.50 77.11 3.00 Table 3-3 MAPLHGR Versus Average Planar Exposure GNF3 Fuel (Reference 2)

Average Planar Exposure MAPLHGR Limit (GWd/ST) (kW/ft) 0.00 14.36 21.22 13.01 40.82 10.75 57.60 8.00 63.50 6.00 Table 3-4 MAPLHGR Single Loop Operation (SLO) Multiplier All Fuel Types (Reference 2)

GNF2 SLO Multiplier 0.80 GNF3 SLO Multiplier 0.90 1

The one (1) HBLUA identified in Reference 12 is the only bundle that can exceed an exposure of 63.50 GWd/ST.

Page 9 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description The OLMCPR is provided in Table 4-1 for GNF2 fuel, including the one (1) HBLUA, and Table 4-2 for GNF3 fuel. These values are determined by the cycle-specific reload analyses in Reference 2 and are valid for all Cycle 18 domains of operation. Table 4-1 and Table 4-2 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. Limerick Unit 2 Cycle 18 MCPR limits are split into two (2) breakpoints as defined in Table 4-1 and Table 4-2. The first breakpoint is the result of exposure dependent RWE MCPR limits, and the second is the mid-cycle MCPR breakpoint.

The maximum scram insertion time verification is required per Technical Specification 3.1.3.2.

Tau, a measure of scram time performance, is determined based on the cumulative scram time test results. The calculation of Tau shall be performed in accordance with site procedures.

Linear interpolation shall be used to calculate the OLMCPR values if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A).

ARTS provides for power and flow dependent thermal limit adjustments and multipliers, which allow for more reliable administration of the MCPR thermal limit. MCPRP and MCPRF are independent of Scram Time Option. 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).

MCPRP and KP multipliers are provided in Table 4-3. The off-rated flow dependent MCPRF limits are provided in Tables 4-4, 4-5, 4-6, and 4-7. 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.

The cycle-specific SLMCPR, known as MCPR99.9% can be found in Table 4-8 for dual loop and single loop operating conditions. The values in Table 4-8 or conservative values were used to calculate the rated and off-rated MCPR limits in this section.

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Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

GNF2 Fuel (References 2 and 8)

Cycle Exposure EOOS Combination SCRAM Time

- 3430 MWd/ST > EOR - 5217

< 3430 MWd/ST & < EOR - 5217 MWd/ST Option 2 MWd/ST B 1.31 1.29 1.29 BASE A 1.35 1.35 1.35 B 1.58 1.58 1.58 BASE SLO 3 A 1.58 1.58 1.58 B 1.31 1.31 1.32 TBSOOS A 1.37 1.37 1.38 B 1.58 1.58 1.58 TBSOOS SLO3 A 1.58 1.58 1.58 B 1.31 1.31 1.32 RPTOOS A 1.38 1.38 1.39 B 1.58 1.58 1.58 RPTOOS SLO3 A 1.58 1.58 1.58 B 1.31 1.29 1.29 PROOS A 1.35 1.35 1.35 B 1.58 1.58 1.58 PROOS SLO3 A 1.58 1.58 1.58 PROOS+TBSOOS B 1.31 1.31 1.32 PROOS+RPTOOS B 1.31 1.31 1.32 2

When Tau is not equal to 0 or 1, determine OLMCPR via linear interpolation 3

For single-loop operation, the MCPR operation limit is 0.03 greater than the analyzed two loop value. However, a minimum value of 1.58 for GNF2 fuel is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event. (Reference 2)

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Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR)

GNF3 Fuel (References 2, 8)

Cycle Exposure EOOS Combination SCRAM Time

- 3430 MWd/ST > EOR - 5217

< 3430 MWd/ST & < EOR - 5217 MWd/ST Option 4 MWd/ST B 1.31 1.29 1.29 BASE A 1.35 1.35 1.35 B 1.59 1.59 1.59 BASE SLO 5 A 1.59 1.59 1.59 B 1.31 1.31 1.32 TBSOOS A 1.37 1.37 1.38 B 1.59 1.59 1.59 TBSOOS SLO5 A 1.59 1.59 1.59 B 1.31 1.31 1.32 RPTOOS A 1.38 1.38 1.39 B 1.59 1.59 1.59 RPTOOS SLO5 A 1.59 1.59 1.59 B 1.31 1.29 1.29 PROOS A 1.35 1.35 1.35 B 1.59 1.59 1.59 PROOS SLO5 A 1.59 1.59 1.59 PROOS+TBSOOS B 1.31 1.31 1.32 PROOS+RPTOOS B 1.31 1.31 1.32 4

When Tau is not equal to 0 or 1, determine OLMCPR via linear interpolation 5

For single-loop operation, the MCPR operation limit is 0.03 greater than the analyzed two loop value. However, a minimum value of 1.59 for GNF3 fuel is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event. (Reference 2)

Page 12 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 4-3 Power Dependent MCPR Limits and Multipliers, MCPRP and Kp All Fuel Types (References 2, 8)

Core Core Thermal Power (% of rated)

Flow 25 30 > 30 45 65  > 85 100 EOOS Combination

(% of Operating Limit rated) MCPR, MCPRP Operating Limit MCPR Multiplier, Kp

< 60 2.12 1.91 Base 1.135 1.130 1.130 1.066 1.066 1.000

60 2.12 2.02

< 60 2.15 1.94 Base SLO 1.135 1.130 1.130 1.066 1.066 1.000

60 2.15 2.05

< 60 2.50 2.20 TBSOOS 1.142 1.134 1.130 1.066 1.066 1.000

60 2.51 2.44

< 60 2.53 2.23 TBSOOS SLO 1.142 1.134 1.130 1.066 1.066 1.000

60 2.54 2.47

< 60 2.12 1.91 RPTOOS 1.155 1.142 1.130 1.067 1.067 1.000

60 2.12 2.02

< 60 2.15 1.94 RPTOOS SLO 1.155 1.142 1.130 1.067 1.067 1.000

60 2.15 2.05

< 60 2.12 1.91 PROOS 1.348 1.255 1.162 1.137 1.066 1.000

60 2.12 2.02

< 60 2.15 1.94 PROOS SLO 1.348 1.255 1.162 1.137 1.066 1.000

60 2.15 2.05

< 60 2.50 2.20 PROOS+TBSOOS 1.348 1.255 1.162 1.137 1.066 1.000

60 2.51 2.44

< 60 2.12 1.91 PROOS+RPTOOS 1.348 1.255 1.162 1.137 1.067 1.000

60 2.12 2.02 Page 13 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 4-4 Flow Dependent MCPR Limits MCPRF GNF2 Fuel (Reference 2)

Flow MCPRF

(% rated) Limit 30 1.53 79 1.25 110 1.25 TABLE 4-5 Flow Dependent MCPR Limits MCPRF GNF3 Fuel (Reference 2)

Flow MCPRF

(% rated) Limit 30 1.53 86.7 1.20 110 1.20 TABLE 4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPRF GNF2 Fuel (Reference 2)

Flow MCPRF

(% rated) Limit 30 1.56 79 1.28 110 1.28 Page 14 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 4-7 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPRF GNF3 Fuel (Reference 2)

Flow MCPRF

(% rated) Limit 30 1.56 86.7 1.23 110 1.23 TABLE 4-8 Cycle Specific SLMCPR (MCPR99.9%)

All Fuel Types (Reference 2)

Loop MCPR99.9% Limit Operation BOC - 6800 6800 MWd/ST MWd/ST to EOC DLO 1.07 1.08 SLO 1.10 1.10 Page 15 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 5.0 LINEAR HEAT GENERATION RATE LIMITS 5.1 Technical Specification Section 3.2.4 5.2 Description The LHGR limits for the HBLUA, GNF2, and GNF3 fuel types are the product of the exposure dependent LHGR limit (from Table 5-1 for UO2 fuel rods and Table 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFACP, and the flow dependent LHGR Factor, LHGRFACF. For single loop operation (SLO), a multiplier is used, which is shown in Table 5-3 and applied in Tables 5-6 and 5-7. No further SLO multipliers need to be applied to the values in Tables 5-4 through 5-7.

ARTS provides for power and flow dependent thermal limit multipliers, which allow for 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, 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 selected the more limiting LHGRFACP 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 through 5-7 and are applicable to all operating domains. Linear interpolation should be used for points not listed in Appendix B of Reference 7, Appendix A of Reference 11, and Reference 12.

TABLE 5-1 Linear Heat Generation Rate Limits - UO2 Rods All Fuel Types (References 5, 7, 11, and 12)

Fuel Type LHGR GNF2 See Table B-1 of Reference 7 GNF3 See Table A-1 of Reference 11 HBLUA See Table 4-1 of Reference 12 Page 16 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods All Fuel Types (References 5, 7, 11, and 12)

Fuel Type LHGR GNF2 See Table B-2 of Reference 7 GNF3 See Table A-2 of Reference 11 HBLUA See Table 4-1 of Reference 12 TABLE 5-3 LHGR Single Loop Operation (SLO) Multiplier All Fuel Types (Reference 2)

GNF2 SLO Multiplier 6 0.80 GNF3 SLO Multiplier 7 0.90 6

Applied to Table 5-6 7

Applied to Table 5-7 Page 17 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 5-4 Power Dependent LHGR Multiplier LHGRFACP GNF2 Fuel (References 2 and 8)

Core Core Thermal Power (% of rated)

EOOS Combination Flow (% 25 30 > 30 65 85 100 of rated) LHGRFACP Multiplier

< 60 0.485 0.490 Base 0.750 0.817 0.922 1.000

 0.434 0.473

< 60 0.485 0.490 Base SLO 0.750 0.817 0.922 1.000

 0.434 0.473

< 60 0.463 0.490 TBSOOS 0.750 0.817 0.922 1.000

 0.352 0.386

< 60 0.463 0.490 TBSOOS SLO 0.750 0.817 0.922 1.000

 0.352 0.386

< 60 0.485 0.490 RPTOOS 0.750 0.817 0.922 1.000

 0.434 0.473

< 60 0.485 0.490 RPTOOS SLO 0.750 0.817 0.922 1.000

 0.434 0.473

< 60 0.485 0.490 PROOS 0.725 0.817 0.922 1.000

 0.434 0.473

< 60 0.485 0.490 PROOS SLO 0.725 0.817 0.922 1.000

 0.434 0.473

< 60 0.463 0.490 PROOS+TBSOOS 0.725 0.817 0.922 1.000

 0.352 0.386

< 60 0.485 0.490 PROOS+RPTOOS 0.725 0.817 0.922 1.000 60 0.434 0.473 Page 18 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 5-5 Power Dependent LHGR Multiplier LHGRFACP GNF3 Fuel (References 2, 8)

Core Thermal Power (% of rated)

Core Flow EOOS Combination

(% of rated) 25 30 > 30 45 I 65 85 100 LHGRFACP Multiplier

< 60 0.510 0.510 Base 1.000 1.000 1.000 1.000 1.000

60 0.510 0.510

< 60 0.510 0.510 Base SLO 1.000 1.000 1.000 1.000 1.000

60 0.510 0.510

< 60 0.470 0.510 TBSOOS 1.000 1.000 1.000 1.000 1.000

60 0.420 0.420

< 60 0.470 0.510 TBSOOS SLO 1.000 1.000 1.000 1.000 1.000

60 0.420 0.420

< 60 0.510 0.510 RPTOOS 1.000 1.000 1.000 1.000 1.000

60 0.510 0.510

< 60 0.510 0.510 RPTOOS SLO 1.000 1.000 1.000 1.000 1.000

60 0.510 0.510

< 60 0.510 0.510 PROOS 0.620 0.740 0.950 1.000 1.000

60 0.510 0.510

< 60 0.510 0.510 PROOS SLO 0.620 0.740 0.950 1.000 1.000

60 0.510 0.510

< 60 0.470 0.510 PROOS+TBSOOS 0.620 0.740 0.950 1.000 1.000

60 0.420 0.420

< 60 0.510 0.510 PROOS+RPTOOS 0.620 0.740 0.950 1.000 1.000 60 0.510 0.510 Page 19 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 5-6 Flow Dependent LHGR Multiplier LHGRFACF GNF2 Fuel (Reference 2)

Core Flow (% of rated EOOS Combination 30 44.1 70 80 110 I I I I LHGRFACF Multiplier I I I Dual Loop 0.706 0.973 1.000 1.000 Single Loop 0.706 0.800 0.800 I I I I I I I TABLE 5-7 Flow Dependent LHGR Multiplier LHGRFACF GNF3 Fuel (Reference 2)

Core Flow (% of rated)

EOOS Combination 30 65.5 80.3 110 LHGRFACF Multiplier Dual Loop 0.660 1.000 1.000 Single Loop 0.660 0.900 0.900 Page 20 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 6.0 CONTROL ROD BLOCK SETPOINTS 6.1 Technical Specification Section 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 3.3.6-2. The trip setpoints/allowable values and applicable RBM signal filter time constant data shown in Table 6-

1. The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2, in percent of rated drive flow. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110% of rated core flow.

The ARTS RWE analysis validated the MCPR values in Table 6-3 for use in Cycle 18. The RBM operability requirements have been evaluated and shown to be sufficient to ensure that SLMCPR and the cladding strain criteria will not be exceeded in the event of an RWE.

TABLE 6-1 Rod Block Monitor Setpoints 8 (References 2 and 4)

Analytical Allowable Nominal Trip Power Level Limit Value Setpoint LTSP 125.8% 124.3% 123.0%

ITSP 121.0% 119.5% 117.0%

HTSP 116.0% 114.5% 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%

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

Page 21 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 6-3 RBM Operability Limits9 (Reference 2)

Power (% rated) RBM Operability Limit

3RZHU MCPR < 1.72 I

3RZHU90 MCPR < 1.41 I 9

These are the MCPR limits below which the RBM is required to be operable (Reference 2).

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Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 7.0 TURBINE BYPASS VALVE PARAMETERS 7.1 Technical Specification Section 3.7.8 and 4.7.8.c 7.2 Description The operability requirements for the steam bypass system for use in Technical Specifications 3.7.8 and 4.7.8.C are found in Tables 7-1 and 7-2. If these requirements cannot be met, the MCPR, MCPRP and LHGRFACP 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 0.11 sec opening following initial turbine inlet valve movement 10 Maximum time after initial turbine inlet valve movement10 for bypass valve position to reach 80% of rated bypass 0.31 sec valve flow (includes the above delay time) I I TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (References 1 and 3)

Reactor Power No. of Valves in Service 3 8 I I

10 First Movement of any TSV or any TCV (whichever occurs first)

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Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 8.0 STABILITY PROTECTION SETPOINTS 8.1 Technical Specification Section 2.2.1 8.2 Description The Limerick Unit 2 Cycle 18 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.

Backup Stability Protection regions calculated for Limerick Unit 2 Cycle 18 are documented in the Supplemental Reload Licensing Report (Reference 2).

TABLE 8-1 OPRM PBDA Trip Setpoints (Reference 2)

PBDA Trip Amplitude Corresponding Maximum Confirmation Setpoint (Sp) Count Setpoint (Np) 1.15 16 Page 24 of 28

Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 9.0 MODES OF OPERATION 9.1 Description The following conditions are supported by the Limerick Unit 2 Cycle 18 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 all modes of operation with thermal limit sets in this COLR. Table 9-2 provides all EOOS included in the BASE case. Table 9-3 provides power level restrictions that support specific operation conditions. One or more TCVFASVOOS resulting in TCVSC event is bounded by the PLUOOS condition (Reference 9).

In the event of one or more TCVFASVOOS, apply limitations associated with PLUOOS described in Tables 9-1, 9-2, and 9-3.

TABLE 9-1 Modes of Operation (References 2 and 8)

EOOS Options 11 Supported Scram Speed Option Supported Recirculation Loops BASE 12,13,14 Option A or B DLO or SLO TBSOOS 15 Option A or B DLO or SLO RPTOOS15 Option A or B DLO or SLO PROOS15 Option A or B DLO or SLO PROOS+TBSOOS15 Option B DLO PROOS+RPTOOS15 Option B DLO TABLE 9-2 BASE EOOS Option - Included Conditions (Reference 2)

Condition PLUOOS15 1 MSIVOOS15 1 TCV/TSVOOS15 1 TBVOOS15 2 SRVOOS 11 All EOOS Options include the BASE EOOS Option. Any restrictions beyond the BASE conditions restrictions are noted on the applicable EOOS option.

12 The BASE condition includes the conditions listed in Table 9-2 13 The BASE condition includes operation with or without FWHOOS/FFWTR 14 Deleted 15 See Table 9-3 for power restrictions that may apply to this condition.

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Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 TABLE 9-3 Power Level Restrictions (Reference 2)

Condition Power Level Restriction (% rated) 1TCVOOS and/or 1 TSVOOS 

1 TCVOOS and/or 1 TSVOOS + PROOS 

1 TCVOOS and/or 1 TSVOOS + 1 TBVOOS 

1 TCVOOS and/or 1 TSVOOS + TBSOOS 

PLUOOS + RPTOOS 

1 MSIVOOS 

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Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15 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, NEDE-24011-P-A-31, November 2020; and U.S. Supplement NEDE-24011-P-A-31-US, November 2020.

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Constellation - Nuclear Fuels Core Operating Limits Report for Limerick 2 Cycle 18 COLR Limerick 2 Rev. 15

11.0 REFERENCES

1. Technical Specifications and Bases for Limerick Generating Station Unit 2, Constellation Document, Docket No. 50-353, License No. NPF-85

2. Supplemental Reload Licensing Report for Limerick Unit 2 Reload 17 Cycle 18, Global Nuclear Fuel Document No. 006N9211, Rev. 0, March 2023

3. Limerick Unit 2 Cycle 18 OPL-3, Constellation TODI NF220744, Rev. 0, November 2022

4. GE NUMAC PRNM Setpoint Study, Constellation Design Analysis LE-0107, Rev 2, February 23, 2012

5. Fuel Bundle Information Report for Limerick Unit 2 Reload 17 Cycle 18, Global Nuclear Fuel Document No. 006N9212, Rev. 1, April 2023

6. Tech Eval Stop Valve Load Limit Documentation, Constellation Document IR 917231 Assignment 7, November 11, 2009

7. GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), Global Nuclear Fuel Document No. NEDC-33270P, Rev 11, August 2020

8. Limerick Generating Station GNF3 PROOS and EOOS Combination Limits Report, Global Nuclear Fuel Document No. 006N6029, Rev. 0, April 2021

9. Operating Limits Evaluation for TCV FASV OOS Condition and TCVSC Event, Constellation Technical Evaluation No. 636198, Rev. 0, March 2022

10. Sensitivity Evaluation of Variation in Key Reactor Heat Balance Parameters for Exelon BWRs with GNF Fuel - Transient Analysis, GE Hitachi Document No. 0000-0166-3223-R0, Rev. 0, August 22, 2014

11. GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II), Global Nuclear Fuel Document No.

NEDC-33879P, Rev. 4, August 2020

12. High Burnup Lead Use Assembly (HBLUA) Information Report for Limerick 2, Global Nuclear Fuel Document Number 006N3997P, Rev. 1, February 2021 Page 28 of 28