ML17131A180

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Issuance of the Core Operating Limits Report (COLR) for Reload 14, Cycle 15
ML17131A180
Person / Time
Site: Limerick Constellation icon.png
Issue date: 05/11/2017
From: Libra R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-17-065
Download: ML17131A180 (21)
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Text

Exelon Generation .

T.S. 6.9.1.12 LG-17-065 May 11, 2017 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 the Core Operating Limits Report (COLR) for Unit 2 Reload 14, Cycle 15 Enclosed is a copy of the Core Operating Limits Report (COLA) for Limerick Generating Station (LGS) Unit 2 Reload 14, Cycle 15 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 Giuseppe Rubinaccio 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 (w/attachments)

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

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

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

Exelon Nuclear- Nuclear Fuels COLRLimerick2 Rev. 11 Care Operating Limits Report for Limerick 2 Cycle 1S CORE OPERATING LIMil'S REPORT

!OR LIMERICK GENERA.TING SfATION UNn' l RELOAD 14, CYCLE 15 (This is a complebs re-write; no annotalions are used.)

PftJpared Uy: Date: ~ (!>/11 Reviewed By: Y/¥17 Reviewed By: Dam: 41312017 D.Doran Reviewed By:

S\ ~....Reac;,i:gineering

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Approved By: l.lale:

A.l n Sr. Manager- BWR Cycle Management StalionQuallflcd Reviewed By:

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Dale:

~ R.Kopenec Station Qualified Reviewer Page lof20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 1S Table of Contents Page Revision History 3 List of Tables 4 1.0 Tenns and Definitions 5 2.0 General Infonnation 7 3.0 MAPLHGR Limits 8 4.0 MCPRLimits 9 s.o LHGRLimits 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 Pagc2 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 Revision History Revision Description Revision 11 New issue for Cycle 15 Page3 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 List of Tables Page TABLE3-I MAPLHGR versus Average Planar Exposure 8 TABLE3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 8 TABLE4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) IO TABLE4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp 11 TABLE4-3 Flow Dependent MCPR Limits MCPR(F) 12 TABLE4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 12 TABLE 5-1 Linear Heat Generation Rate Limits - U02 Rods 13 TABLE5-2 Linear Heat Generation Rate Limits - Gad Rods 13 TABLES-3 LHGR Single Loop Operation (SLO) Multiplier 14 TABLBS-4 Power Dependent LHGR Multiplier LHGRFAC(P) 14 TABLES-5 Flow Dependent LHGR Multiplier LHGRF AC(F) 15 TABLE6-l Rod Block Monitor Setpoints 16 TABLE6-2 Reactor Coolant System Recirculation Flow Upscale Trip 16 TABLE7-1 Turbine Bypass System Response Time 17 TABLE7-2 Minimum Required Bypass Valves To Maintain System Operability 17 TABLES-I OPRM PBDA Trip Setpoints 18 TABLE9-1 Modes of Operation 19 TABLE9-2 "BASE" EOOS Option - Included Conditions 19 Page4of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 1.0 Terms and Definitions APRM Average Power Range Monitor ARTS APRM, RSM, and Technical Specification Improvement Program BASE This condition is defmed 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 thennal 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 lCF Increased Core Flow ITSP Rod Block Monitor Intermediate Trip Setpoint Kp Off-rated power dependent OLMCPR multj.plier LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thermal limit flow dependent multipliers LHGRFAC(P) ARTS LHGR thennal 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 S of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 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 Out of Service msoos Turbine Bypass System Out of Service TBVOOS Turbine Bypass Valve(s) Out of Service TCV Turbine Control Valve TCV!I'SVOOS l Turbine Control Valve Out of Service and/or 1 Turbine Stop Valve Out of Service TSV Turbine Stop Valve Page6of20

Exelon Nuclear- Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 2.0 General 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 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)
  • 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% 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 105°F during cycle extension operation

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

Page 7 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description 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.

TABLEJ-1 MAPLHGR versus Average Planar Exposure (Rerereoce 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 TABLEJ-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 0.80 Page 8 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 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 15 operating domains. Table 4-1 includes 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 Table 4-1.

ARTS provides for power and flow dependent thennal limit adjustments and multipliers, which allow for a more reliable administration of the MCPR thennal 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 4-2, 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.

Pagc9of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 1S TABLE4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

(References 2 and 8)

SCRAM Cvde Exoosure Time <EOR-3847 ~ EOR-3847 EOOS Combination Ootion<1> MWd/ST MWd/ST B 1.38(Z) 1.39 BASE Bl 1.38(2),(3) l .38(l)

A 1.42 l.47 B 1.60 1.60 BASESL04 A 1.60 l.60 B 1.38<2> 1.43 TB SOOS A 1.46 1.52 B 1.60 1.60 TBSOOS SL04 A 1.60 1.60 B 1.3s<2> 1.42 RPTOOS A 1.54 1.59 B 1.60 1.60 RPTOOSSL04 A 1.60 1.63 B l.38(Z) 1.39 PROOS A 1.42 l.47 B 1.60 1.60 PROOSSL04 A 1.60 1.60 PROOS+TBSOOS B 1.38 1.43 PROOS+RPTOOS B l.38 1.42 1

When Tau docs not equal 0 or I, dctcnnine OLMCPR via linear interpolation.

2 Value is adjusted to obtain an OPR.i\1 amplitude setpoint of 1.11.

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

4 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.

Page 10 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 TABLE4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp (References 2 and 8}

Core Core Thermal Power (% of rated}

EOOS Flow 0 2S <JO ~30 6S 8S 100 Combination (%or rated)

MCPR(P) Operating Limit MCPR Multiplier, Kp

S 60 2.52 2.52 2.42 Base 1.340 1.131 l.067 1.000

>60 2.78 2.78 2.57 Base SLO s 60 2.56 2.56 2.46 1.340 1.131 1.067 1.000

>60 2.82 2.82 2.61

<60 3.28 3.28 2.78 TB SOOS 1.340 1.131 1.067 1.000

> 60 3.78 3.78 3.28 TBSOOSSLO s 60 3.32 3.32 2.82 1.340 1.131 l.067 1.000

>60 3.82 3.82 3.32

S 60 2.52 2.52 2.42 RPTOOS 1.340 1.131 1.067 1.000

>60 2.78 2.78 2.57

S60 2.56 2.56 2.46 RPTOOS SLO 1.340 1.131 1.067 1.000

>60 2.82 2.82 2.61

S 60 2.52 2.52 2.42 PROOS 1.367 1.236 1.160 1.000

>60 2.78 2.78 2.57 S60 2.56 2.56 2.46 PROOSSLO 1.367 1.236 1.160 1.000

>60 2.82 2.82 2.61

S 60 3.28 3.28 2.78 PROOS+TBSOOS 1.367 1.236 1.160 1.000

>60 3.78 3.78 3.28

S 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 of20

Exelon Nuclear- Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 1S TABLE4-3 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 TABLE4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F)

(Reference 2)

Flow MCPR(F)

(%rated) Limit 0.0 l.74 30.0 1.57 79.0 1.29 110.0 l.29 Page 12 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 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 U02 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.

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

Fuel T e LHGR GNF2 See Table B-1 of Reference 1 TABLES-2 Linear Heat Generation Rate Limits - Gad Rods (References S and 7)

Fuel Type LHGR GNF2 See Table B-2 of Reference 7 Page 13 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 1S TABLE5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 1 0.80 TABLE5-4 Power Dependent LHGR Multiplier LHGRFAC(P)

(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

5 60 0.485 0.485 0.490 BASE 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 S60 0.485 0.485 0.490 BASESLO 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 TBSOOSSLO s 60 0.463 0.463 0.490 0.750 0.817 0.922 1.000

>60 0.352 0.352 0.386

~60 0.485 0.485 0.490 RPTOOS 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 S60 0.485 0.485 0.490 RPTOOSSLO 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 S60 0.485 0.485 0.490 PROOS 0.725 0.817 0.922 1.000

>60 0.434 0.434 0.473

~60 0.485 0.485 0.490 PROOSSLO 0.725 0.817 0.922 1.000

>60 0.434 0.434 0.473 S60 0.463 0.463 0.490 PROOS+TBSOOS 0.725 0.817 0.922 1.000

>60 0.352 0.352 0.386 S60 0.485 0.485 0.490 PROOS+RPTOOS 0.725 0.817 0.922 l.000

>60 0.434 0.434 0.473 1

Applied through Table 5-5 .

Page 14of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 TABLE 5-5 Flow Dependent LHGR Multiplier LHGRFAC(F}

(Reference 2)

Core Flow (% of rated)

EOOS Combination 0 30 44.l 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 of20

Exelon Nuclear- Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 1S 6.0 Control Rod Block Setpoints 6.1 Technical Specification Sections 3.1.4.3 and 3.3.6 6.2 Description The ARTS Rod Block Monitor provides for power-dependent RBM trips. Technical Specification 3.3.6 states control rod block instrumentation channels shall be OPERABLE with their trip setpoints consistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-

2. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shown in Table 6-1. The Reactor Coolant System Recirculation Flow Upscale Trip is shown in Table 6-2.

These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110%

ofrated core flow.

TABLE6-1 Rod Block Monitor Setpoints1 (References 2 and 4)

Power Level Analytical Allowable Nominal Trip Limit Value Setpoint LTSP 123.0% 121.5% 121.5%

!TSP 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 sctpoints (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 1.36.

Page 16 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 7.0 Turbine Bypass Valve Parameters 7.1 Technical Specification Section3.7.8 and4.7.8.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.

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

Maximum delay time before start of bypass valve opening 0.11 sec following initial turbine inlet valve movernent 1 Maximum time after initial turbine inlet valve movement 1 for bypass valve position to reach 80% of full flow (includes the 0.31 sec above delay time)

First movement of any TSVor 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 P2:25% 7 Page 17 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle l S 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1 8.2 Description The Limerick Unit 2 Cycle 15 OPRM PBDA Trip Setpoints for the OPRM System arc found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 2. The setpoints provided in Table 8-l are bounding for all modes of operation shown in Table 9-1.

TABLE8-1 OPRM PBDA Trip Setpoints (Reference 2)

Corresponding Maximum PBDA Trip Amplitude Confirmation Count Triu Settin2 s Lil ~ 14 Page 18of20

Exelon Nuclear- Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 15 9.0 Modes of Operation 9.1 Description The following conditions are supported by the Limerick Unit 2 Cycle 1S 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 thennal 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 Options 1 Option Loops BASE2.J Option A or B DLOorSLO TBSOOS 4 Option A or B DLOorSLO RPTOOS 3 Option A or B DLOorSLO PROOS Option Aor B DLOorSLO PROOS+TBSOOS" Option B DLO PROOS+RPTOOS~ Option B DLO TABLE9-2 "BASE" EOOS Option - Included Conditions (Reference 2)

Condition PLUOOS 1 MSIVOOSc.

I TCV/TSVOOS4 ' 1 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 TCVffSVOOS is valid coincident with the TBSOOS condition, but only at power levels $ 64% rated thermal rower.

PLUOOS is valid coincident with the RPTOOS condition, but only at power levels < 55% rated thermal power.

6 l MSIVOOS is valid only at power levels ::; 75% rated thermal power.

7 l TCVffSVOOS is valid only at power levels$ 70% rated thermal power.

Page 19 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick 2 Rev. 11 Core Operating Limits Report for Limerick 2 Cycle 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", Global Nuclear Fuel Docwnent, 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, NED0-32465-A, August 1996.

11.0 References

l. "Technical Specifications and Bases for Limerick Generating Station Unit 2", Exelon Docwnent, Docket No. 50-353, License No. NPF-85.
2. "Supplemental Reload Licensing Report for Limerick Unit 2 Reload 14 Cycle 15", Global Nuclear Fuel Document 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 Fuel Document No. 002N6933, Rev. 0, March 2017.
6. "Tech Eval Stop Valve Load Limit Docwnentation", 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. 7, October 2016.
8. "Limerick Generating Station (LGS) Units I and 2 TRACG Cycle-Independent PROOS Analysis Report", GE Hitachi Document No. 002N4397 Rl, Rev. I, January 2016.

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