ML16202A284

Issuance of a Revision to the Core Operating Limits Report (Cola) for Reload 13, Cycle 14

ML16202A284
Person / Time
Site:	Limerick
Issue date:	07/20/2016
From:	Libra R Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-16-074 COLR Limerick 2, Rev. 10
Download: ML16202A284 (24)

Text

Exelon Generation T.S. 6.9.1.12 LG-16-074 July 20, 2016 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 NRC Docket Nos. 50-353

Subject:

Issuance of a Revision to the Core Operating Limits Report (COLA) for Unit 2 Reload 13, Cycle 14 Enclosed is a copy of the revised Core Operating Limits Report (COLA) 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. This revision of the COLA became effective on July 11, 2016.

The COLA 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 Giuseppe Rubinaccio at 610-718-3560.

Respectfully,

~~fn~~u~

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

Attachment:

Core Operating Limits Report for Limerick Generating Station Unit 2 Reload 13, Cycle 14 cc: D. Dorman, Administrator, Region I, USNRC (w/attachments)

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

A. Ennis, USN RC Project Manager for LGS (w/attachments)

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

bee: A. Libra LGS Site Vice President (w/o attachment)

D. Lewis LGS Plant Manager (w/o attachment)

M. Herr LGS Director Operations (w/o attachment)

G. Rubinaccio Mgr Reactor Engineering (w/o attachment)

A. Dickinson Mgr Regulatory Assurance (w/o attachment)

D. Helker Mgr Corp Licensing (w/o attachment)

M. Holmes Corp Fuels Engineer (w/o attachment)

S. Martin PADEP BRP (w/attachment)

Bulan Nuclear- Nuclear Fuels COLR.Umedck2,Rev.10 I Core Operating Limits Report CORBOPERATING LIMITS BBPORT FOR LIMBRICK GENERATING STATION lJNIT2 RELOAD l3, CYCLE 14 PmparedBy: /?d ~ M. Halma Dace:

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Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 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 MCPRLimits 9 5.0 LHGR Limits 12 6.0 Control Rod Block Setpoints 15 7.0 Turbine Bypass Valve Parameters 16 8.0 Stability Protection Setpoints 17 9.0 Modes of Operation 18 10.0 Methodology 19 11.0 References 19 Page 2of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. I0 I Core Operating Limits Report Revision History Revision Description Revision 10

• Incorporates revised OLMCPR limits in accordance with "Limerick Unit 2 Cycle 14 Reload Licensing Reports - Supplemental Reload Licensing Report (SRLR),

OOON9396-SRLR Revision I."

• Revises Section 9.1 text to more explicitly retlect allowed/dis-allowed conditions.

• Updates References 2, 3, and 8.

• Adds Revision History Page Revision 9 New issue for Cycle 14 Page 3of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. to I Core Operating Limits Report List of Tables Page TABLE 3-1 MAPLHGR versus Average Planar Exposure - All Fuel Types 8 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier - All Fuel Types 8 TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) - All Fuel Types 10 TABLE 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp - All Fuel Types 11 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F) - All Fuel Types II TABLE 5-1 Linear Heat Generation Rate Limits - U02 Rods 12 TABLE 5-2 Linear Heat Generation Rate Limits - Gad Rods 12 TABLE 5-3 LHGR Single Loop Operation (SLO) Multiplier-All Fuel Types 13 TABLE 5-4 Power Dependent LHGR Multiplier LHGRF AC(P)-All Fuel Types 13 TABLE 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F) - All Fuel Types 14 TABLE 6-1 Rod Block Monitor Setpoints 15 TABLE 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 15 TABLE 7-1 Turbine Bypass System Response Time 16 TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability 16 TABLE 8-1 OPRM PBDA Trip Setpoints 17 TABLE 8-2 SLO OPRM PBDA Trip Setpoints 17 TABLE 9-1 Modes of Operation 18 Page 4of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 1.0 Terms and Definitions ARTS APRM, RBM, and Technical Specification Improvement Program BASE 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.

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 I00%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service HTSP Rod Block Monitor High Trip Setpoint JCF Increased Core Flow JTSP 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 thennaJ 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 MCPR(P) Off-rated power dependent OLMCPR multiplier Page 5of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 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 TB SOOS Turbine Bypass System Out of Service TCV Turbine Control Valve TIPOOS Traversing In core Probe Out of Service TSV Turbine Stop Valve Page 6of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. I0 I Core Operating Limits Report 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 LHGRF AC(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 I. 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% ofrated core flow during full power operation

• Increased Core Flow (ICF) up to 110% ofrated core flow

• Final Feedwater Temperature Reduction (FFWTR) up to I05°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.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 Core Operating Limits Report 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.

TABLE3-1 MAPLHGR versus Average Planar Exposure-All Fuel Types (Reference 2)

Average Planar Exposure MAPLHGR Limit (GWD/ST) (kW/ft) 0.0 13.78 17.52 13.78 60.78 7.50 63.50 6.69 TABLE3-2 MAPLHGR Single Loop Operation (SLO) Multiplier- All Fuel Types (Refere nee 2)

SLO Multiplier 0.80 Page 8of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 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.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report TABLE4-1 Operating Limit Minimum Critical Power Ratio (OLM CPR) - All Fuel Types (References 2 and 8)

SCRAM Cycle Exposure Time < EOR-2542 ~EOR-2542 EOOS Combination Option< 1> MWd/ST MWd/ST B I .36< 2 > 1.36 BASE A 1.43 1.44 B 1.58 1.58 BASE SL0< 3 >

A 1.58 1.58 B 1.38 1.39 TB SOOS A 1.47 1.48 B 1.58 1.58 TBSOOS SL0< 3 >

A 1.58 1.58 B 1.38 1.39 RPTOOS A 1.55 1.56 B 1.58 1.58 RPTOOS SL0<3 >

A 1.58 1.59 B 1.36(2) 1.36 PROOS A 1.43 1.47 B 1.58 1.58 PROOS SL0< 3 >

A 1.58 1.58 PROOS+TBSOOS B 1.38 1.39 PROOS+RPTOOS B 1.38 1.39 1

When Tau does not equal 0 or I, 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.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report TABLE4-2 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 rated)

MCPR(P) Operating Limit MCPR Multiplier, Kp S 60 2.50 2.50 2.40 Base 1.340 1.131 1.067 1.000

> 60 2.75 2.75 2.55 S 60 2.53 2.53 2.43 Base SLO 1.340 1.131 1.067 1.000

> 60 2.78 2.78 2.58 S 60 3.25 3.25 2.75 TB SOOS 1.340 1.131 1.067 1.000

> 60 3.75 3.75 3.25 S60 3.28 3.28 2.78 TBSOOSSLO 1.340 1.131 1.067 1.000

>60 3.78 3.78 3.28 S60 2.50 2.50 2.40 RPTOOS 1.340 1.131 1.067 1.000

> 60 2.75 2.75 2.55 S60 2.53 2.53 2.43 RPTOOSSLO 1.340 1.131 1.067 1.000

> 60 2.78 2.78 2.58 S60 2.50 2.50 2.40 PROOS 1.367 1.236 1.160 1.000

> 60 2.75 2.75 2.55 PROOS SLO

s 60 2.53 2.53 2.43 1.367 1.236 1.160 1.000

>60 2.78 2.78 2.58 PROOS+TB SOOS

s 60 3.25 3.25 2.75 1.367 1.236 1.160 1.000

>60 3.75 3.75 3.25 PROOS+RPTOOS

s 60 2.50 2.50 2.40 1.367 1.236 1.160 1.000

>60 2.75 2.75 2.55 TABLE4-3 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 11 of 19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 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 LHGRF AC(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 ofrecirculation pump trip operability.

TABLES-1 Linear Heat Generation Rate Limits - U02 Rods (References 5 and 7)

Fuel Type LHGR I GNF2 See Table B-1 of Reference 7 ~

TABLES-2 Linear Heat Generation Rate Limits - Gad Rods (References 5 and 7)

Fuel Type LHGR GNF2 See Table B-2 of Reference 7 Page 12of19

Exelon Nuclear- Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report TABLES-3 LHGR Single Loop Operation (SLO) Multiplier-All Fuel Types (Reference 2)

SLO Multiplier 1 0.80 TABLES-4 Power Dependent LHGR Multiplier LHGRFAC(P)-All Fuel Types (References 2 and 8)

Core Core Thermal Power (% of rated)

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

(%of rated) LHGRFAC(P) Multiplier

60 0.485 0.485 0.490 BASE 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473

60 0.485 0.485 0.490 BASE SLO 0.750 0.817 0.922 1.000

> 60 0.434 0.434 0.473

60 0.463 0.463 0.490 TB SOOS 0.750 0.817 0.922 1.000

> 60 0.352 0.352 0.386

60 0.463 0.463 0.490 TBSOOS SLO 0.750 0.817 0.922 1.000

>60 0.352 0.352 0.386

60 0.485 0.485 0.490 RPTOOS 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473

60 0.485 0.485 0.490 RPTOOS SLO 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473

60 0.485 0.485 0.490 PROOS 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473

60 0.485 0.485 0.490 PROOSSLO 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473

60 0.463 0.463 0.490 PROOS+IBSOOS 0.750 0.817 0.922 1.000

> 60 0.352 0.352 0.386

60 0.485 0.485 0.490 PROOS+RPTOOS 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 1

Applied through Table 5-5 Page 13of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. to I Core Operating Limits Report TABLES-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 Page 14of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 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 I JO%

of rated core flow.

TABLE 6-1 Rod Block Monitor Setpoints 1 (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%

TABLE6-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 4)

Analytical Limit NIA 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 1.32, which is less than the minimum cycle OLM CPR.

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Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 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 LHGRF AC(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.

TABLE7-1 Turbine Bypass System Response Time (Reference 3)

Maximum delay time before start of bypass valve opening O.llsec following initial turbine inlet valve movemene 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) 1 First movement of any TSV or any TCV or generation of the turbine bypass valve flow signal (whichever occurs first)

TABLE7-2 Minimum Required Bypass Valves To Maintain System Operability (References 1 and 3)

Reactor Power No. of Valves in Service P2:25% 7 Page 16of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 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. l11ese 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)

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trip Setting

1.12

:; 14 TABLE8-2 SLO OPRM PBDA Trip Setpoints (Reference 2)

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Trip Setting

1.15

:; 16 Page 17of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. 10 I Core Operating Limits Report 9.0 Modes of Operation 9.1 Description The allowable modes of operation are found in Table 9-1. The BASE application condition includes I MSIVOOS and 1 TCVtrSVOOS provided the restrictions identified in the applicable station procedures are met. Note that 1 TCV trSVOOS is not allowed to be coincident with one or more TBVOOS. All EOOS options also support the allowance of 1 TIPOOS.

TABLE 9-1 Modes of Operation (References 2 and 8) 1 EOOS Options Operatin2 Re2ion BASE, Option A or B Yes2 BASE SLO, Option A or B Yes2 TBSOOS, Option A or B Yes-TBSOOS SLO, Option A or B Yes-RPTOOS, Option A or B YesJ RPTOOS SLO, Option A or B Yes3 TBSOOS and RPTOOS, Option A or B No TBSOOS and RPTOOS SLO, Option A or B No PROOS. Ootion A or B Yes-PROOS SLO, Option A or B Yes-PROOS+TBSOOS, Option A No PROOS+TBSOOS, Option B Yes2 PROOS+TBSOOS SLO, Option A or B No PROOS+RPTOOS, Option A No PROOS+RPTOOS, Option B YesJ PROOS+RPTOOS SLO, Option A or B No 1

Operating Region refers to operation on the Power to Flow map " ith or without FFWTRIFWHOOS.

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 18of19

Exelon Nuclear - Nuclear Fuels COLR Limerick 2, Rev. I0 I Core Operating Limits Report 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:

I . "General Electric Standard Application for Reactor Fuel", Global Nuclear Fuel Document, NEDE-240 I l-P-A-21, May 2015 and the U.S. Supplement NEDE-24011-P-A-2 I-US, May 2015.

2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", GENE Document, NED0-32465-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 2 Reload 13 Cycle 14", Global Nuclear Fuel Document No. OOON9396-SRLR, Rev. I, September 2015.

3. "Final Resolved OPL-3 Parameters for Limerick 2 Cycle 14", Exelon TOOi ESl400022 Rev. I, August 31,2015.

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. OOON9397-FBIR, Rev. 0, February 2015.

6. "Tech Eva) 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 Fuel Document No. NEDC-33270P, Rev. 5, May 2013.

8. "Limerick Generating Station (LGS) Units 1 and 2 TRACG Cycle-Independent PROOS Analysis Report", GE Hitachi Nuclear Energy Document No. 002N4397, Rev. I, January 15, 2016.

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