ML18113A188

Issuance of the Core Operating Limits Report (Cola) for Unit 1 Reload 17, Cycle 18

ML18113A188
Person / Time
Site:	Limerick
Issue date:	04/23/2018
From:	Libra R Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-18-057
Download: ML18113A188 (21)

Text

Exelon Generation T.S. 6.9.1.12 LG-18-057 April 23, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Limerick Generating Station, Unit 1 Renewed Facility Operating License No NPF-39 NRG Docket Nos. 50-352

Subject:

Issuance of the Core Operating Limits Report (COLA) for Unit 1 Reload 17, Cycle 18 Enclosed is a copy of the Core Operating Limits Report (COLA) for Limerick Generating Station (LGS) Unit 1 Reload 17 Cycle 18 which incorporates the revised cycle specific parameters resulting from the new configuration implemented for LGS, Unit 1.

The COLA is being submitted to the NRG in accordance with LGS, Unit 1 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 (COLA) for Unit 1 Reload 17, Cycle 18 cc: D. Dorman, Administrator, Region I, USNRC (w/attachments)

S. Rutenkroger, USNRC Sr. Resident Inspector, LGS (w/attachments)

V. Sreenivas, USN RC Project Manager for LGS (w/attachments)

R. Janati, PADEP-BRP (w/attachments)

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 1 RELOAD 17 CYCLE 18 Prepared By: Date: March 26, 2018 K. E.

K E Pfingsten/T.

Pfing J. Stathes Preparer

.BSDI



Reviewed By: 

Date:

R. C. Potter Independent Reviewer Reviewed By: Date: 03/27/2018 A. Stefanczyk Reactor Engineering Reviewed By: Date: 03/26/2018 A. M. Olson l

Engineering Safety Analysis Approved By: Date: 27MAR18 A. R A R. Johnson John hnson hn Sr. Manager - BWR Cycle Management Station Qualified Review By: Date: 04/01/18 D. Doran Station Qualified Reviewer Page 1 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 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 9 5.0 LHGR Limits 13 6.0 Control Rod Block Setpoints 16 7.0 Turbine Bypass Valve Parameters 17 8.0 Stability Protection Setpoints 18 9.0 Modes of Operation 19 10.0 Methodology 20 11.0 References 20 Page 2 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Revision History Revision Description Revision 14 New issue for Cycle 18.

Page 3 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 8 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 8 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 10 Table 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp 11 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 12 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 12 Table 5-1 Linear Heat Generation Rate Limits - UO2 Rods 13 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 13 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier 14 Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P) 14 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) 15 Table 6-1 Rod Block Monitor Setpoints 16 Table 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 16 Table 7-1 Turbine Bypass System Response Time 17 Table 7-2 Minimum Required Bypass Valves To Maintain System Operability 17 Table 8-1 OPRM PBDA Trip Setpoints 18 Table 9-1 Modes of Operation 19 Table 9-2 BASE EOOS Option - Included Conditions 19 Page 4 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 1.0 Terms and Definitions 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.

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 MCPR Minimum Critical Power Ratio MCPR(F) Off-rated flow dependent OLMCPR multiplier Page 5 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 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 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(s) 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 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 2.0 General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 1 Cycle 18:

x Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) x Minimum Critical Power Ratio (MCPR) x Single Loop Operation (SLO) OLMCPR adjustment x Off-rated OLMCPR adjustments (MCPR(P) or MCPR(F))

x Off-rated OLMCPR multipliers (Kp) x Off-rated LHGR multipliers (LHGRFAC(P) or LHGRFAC(F))

x Rod Block Monitor (RBM) setpoints x MAPLHGR single loop operation multiplier x LHGR single loop operation multiplier x Linear Heat Generation Rate (LHGR) x Turbine Bypass Valve parameters x Reactor Coolant System Recirculation Flow Upscale Trips x 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:

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 105.0qF during cycle extension operation x Feedwater Heater Out of Service (FWHOOS) up to 60.0qF feedwater temperature reduction at any time during the cycle prior to cycle extension.

Further information on the cycle-specific analyses for Limerick Unit 1 Cycle 18 and the associated operating domains discussed above is available in Reference 2.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description The limiting MAPLHGR value for the most limiting lattice for 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 MAPLHGR Limit (GWD/ST) (kW/ft) 0.00 13.78 13.24 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 0.80 Page 8 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Table 4-1. These values are determined by the cycle-specific reload analyses in Reference 2 and are valid for all Cycle 18 operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. Limerick Unit 1 Cycle 18 has a mid-cycle MCPR breakpoint, as defined in Table 4-1.

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 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 selecting the more limiting OLMPCR 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 4-2, 4-3, and 4-4. 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.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

(References 2 and 8)

Cycle Exposure SCRAM Time < EOR - 3968 EOR - 3968 EOOS Combination Option1 MWd/ST MWd/ST 3

B 1.37 1.38 4 3,4 BASE B 1.37 1.374 A 1.41 1.46 B 1.60 1.60 BASE SLO2 A 1.60 1.60 B 1.373 1.41 TBSOOS A 1.45 1.50 B 1.60 1.60 TBSOOS SLO2 A 1.60 1.60 3

B 1.37 1.40 RPTOOS A 1.53 1.57 B 1.60 1.60 RPTOOS SLO2 A 1.60 1.61 3

B 1.37 1.38 PROOS A 1.41 1.46 B 1.60 1.60 PROOS SLO2 A 1.60 1.60 PROOS+TBSOOS B 1.373 1.41 PROOS+RPTOOS B 1.373 1.40 1

When Tau (as defined per Technical Specification 3.2.3) does not equal 0 or 1, determine OLMCPR via linear interpolation.

2 For single-loop operation, the MCPR operating limit is 0.04 greater than the analyzed two loop value.

However, a minimum value of 1.60 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).

3 Value is adjusted to obtain an OPRM amplitude setpoint of 1.11.

4 Limit is only applicable if it is confirmed that a 45ms or greater delay exists between the time of the first TSV movement and the time of the first TCV movement following a turbine trip.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Table 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp (References 2 and 8)

Core Core Thermal Power (% of Rated)

Flow 0 25 < 30 t 30 65 85 100 EOOS Combination

(% of Operating Limit Operating Limit MCPR rated) MCPR, MCPR(P) Multiplier, Kp d 60 2.52 2.52 2.42 BASE 1.340 1.131 1.067 1.000

> 60 2.78 2.78 2.57 d 60 2.56 2.56 2.46 BASE SLO 1.340 1.131 1.067 1.000

> 60 2.82 2.82 2.61 d 60 3.28 3.28 2.78 TBSOOS 1.340 1.131 1.067 1.000

> 60 3.78 3.78 3.28 d 60 3.32 3.32 2.82 TBSOOS SLO 1.340 1.131 1.067 1.000

> 60 3.82 3.82 3.32 d 60 2.52 2.52 2.42 RPTOOS 1.340 1.131 1.067 1.000

> 60 2.78 2.78 2.57 d 60 2.56 2.56 2.46 RPTOOS SLO 1.340 1.131 1.067 1.000

> 60 2.82 2.82 2.61 d 60 2.52 2.52 2.42 PROOS 1.367 1.236 1.160 1.000

> 60 2.78 2.78 2.57 d 60 2.56 2.56 2.46 PROOS SLO 1.367 1.236 1.160 1.000

> 60 2.82 2.82 2.61 d 60 3.28 3.28 2.78 PROOS+TBSOOS 1.367 1.236 1.160 1.000

> 60 3.78 3.78 3.28 d 60 2.52 2.52 2.42 PROOS+RPTOOS 1.367 1.236 1.160 1.000

> 60 2.78 2.78 2.57 Page 11 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Table 4-3 Flow Dependent MCPR Limits MCPR(F)

(Reference 2)

Flow MCPR(F)

(% rated) Limit 0.0 1.70 30.0 1.53 79.0 1.25 110.0 1.25 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)

(Reference 2)

Flow MCPR(F)

(% rated) Limit 0.0 1.74 30.0 1.57 79.0 1.29 110.0 1.29 Page 12 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 5.0 LHGR Limits 5.1 Technical Specification Section 3.2.4 5.2 Description The LHGR limit for the GNF2 fuel type is 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, 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 Operation 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, 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 - UO2 Rods (References 5 and 7)

Fuel Type LHGR GNF2 See Table B-1 of Reference 7 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (References 5 and 7)

Fuel Type LHGR GNF2 See Table B-2 of Reference 7 Page 13 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier1 0.80 Table 5-4 Power Dependent LHGR Multiplier LHGRFAC(P)

(References 2 and 8)

Core Core Thermal Power (% of rated)

Flow EOOS Combination 0 25 < 30 t 30 65 85 100

(% of rated) LHGRFAC(P) Multiplier d 60 0.485 0.485 0.490 BASE 0.750 0.817 0.922 1.000

> 60 0.434 0.434 0.473 d 60 0.485 0.485 0.490 BASE SLO 0.750 0.817 0.922 1.000

> 60 0.434 0.434 0.473 d 60 0.463 0.463 0.490 TBSOOS 0.750 0.817 0.922 1.000

> 60 0.352 0.352 0.386 d 60 0.463 0.463 0.490 TBSOOS SLO 0.750 0.817 0.922 1.000

> 60 0.352 0.352 0.386 d 60 0.485 0.485 0.490 RPTOOS 0.750 0.817 0.922 1.000

> 60 0.434 0.434 0.473 d 60 0.485 0.485 0.490 RPTOOS SLO 0.750 0.817 0.922 1.000

> 60 0.434 0.434 0.473 d 60 0.485 0.485 0.490 PROOS 0.725 0.817 0.922 1.000

> 60 0.434 0.434 0.473 d 60 0.485 0.485 0.490 PROOS SLO 0.725 0.817 0.922 1.000

> 60 0.434 0.434 0.473 d 60 0.463 0.463 0.490 PROOS+TBSOOS 0.725 0.817 0.922 1.000

> 60 0.352 0.352 0.386 d 60 0.485 0.485 0.490 PROOS+RPTOOS 0.725 0.817 0.922 1.000

> 60 0.434 0.434 0.473 1

Applied through Table 5-5 Page 14 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 Table 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F)

(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 Page 15 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 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, 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.

Table 6-1 Rod Block Monitor Setpoints1 (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%

1 These setpoints (with Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit of 1.34 (Reference 2).

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Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 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 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 sec following initial turbine inlet valve movement1 Maximum time after initial turbine inlet valve movement1 for bypass valve position to reach 80% of rated bypass valve flow 0.31 sec (includes the above delay time) 1 First 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 Page 17 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1 8.2 Description The Limerick Unit 1 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.

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

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trip Setting d 1.11 d 14 Page 18 of 20

Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 9.0 Modes of Operation 9.1 Description The following conditions are supported by the Limerick Unit 1 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 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)

Supported Scram Speed Supported Recirculation EOOS Options1 Option Loops BASE2,3 Option A or B DLO or SLO TBSOOS4 Option A or B DLO or SLO RPTOOS5 Option A or B DLO or SLO PROOS Option A or B DLO or SLO PROOS+TBSOOS4 Option B DLO PROOS+RPTOOS5 Option B DLO TABLE 9-2 BASE EOOS Option - Included Conditions (Reference 2)

Condition PLUOOS 1 MSIVOOS6 1 TCV/TSVOOS4 2 TBVOOS 2 SRVOOS 1

All EOOS Options include the BASE EOOS Option. Any restrictions beyond the BASE conditions 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, alone or coincident with another EOOS condition, is valid only at 90% rated thermal power, except when coincident with TBSOOS, which is valid only at 85% 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.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 1, Rev. 14 Core Operating Limits Report for Limerick 1 Cycle 18 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 documents:

1. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-26, January 2018 and U.S.

Supplement NEDE-24011-P-A-26-US, January 2018.

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

11.0 References

1. Technical Specifications and Bases for Limerick Generating Station Unit 1, Docket No. 50-352, License No. NPF-39, Exelon Document.

2. Supplemental Reload Licensing Report for Limerick Unit 1 Reload 17 Cycle 18, Global Nuclear Fuel Document No. 004N1986, Rev. 0, February 2018.

3. Final Resolved OPL-3 Parameters for Limerick Unit 1 Cycle 18, Exelon TODI ES1700022, Rev. 0, October 17, 2017.

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

5. Fuel Bundle Information Report for Limerick Unit 1 Reload 17 Cycle 18, Global Nuclear Fuel Document No. 004N1987, Rev. 0, February 2018.

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-P-A (GESTAR II), Global Nuclear Fuel Document No. NEDC-33270P, Rev. 9, December 2017.

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.

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