ML16111B122

Issuance of the Core Operating Limits Report (COLR) for Reload 16, Cycle 17

ML16111B122
Person / Time
Site:	Limerick
Issue date:	04/20/2016
From:	Libra R Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LG-16-049
Download: ML16111B122 (21)

Text

Exelon Generation ~

T.S. 6.9.1.12 LG-16-049 April 20, 2016 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 NRC Docket Nos. 50-352

Subject:

Issuance of the Core Operating Limits Report (COLA) for Unit 1 Reload 16, Cycle 17 Enclosed is a copy of the Core Operating Limits Report (COLA) for Limerick Generating Station (LGS) Unit 1 Reload 16 Cycle 17 which incorporates the revised cycle specific parameters resulting from the new configuration implemented for LGS, Unit 1.

The COLR is being submitted to the NRC in accordance with LGS, Unit 1 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 1 Reload 16, Cycle 17 cc: D. Dorman, Administrator, Region I, USNRC (w/attachments)

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

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

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

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT1RELOAD16CYCLE17 3/11/L~

Date: ~r/16 Reviewed By:

M.R.Holmes Independent Reviewer Reviewed By: Date: 3/17/16 M. Doerzbacher Reviewed By: ~ T. R.Bement Engineering Safety Analysis

~x1~---

Approved By:

---tl- J. J. Tusar Manager - BWR Design (GNF)

Date: 03/17/2016 Station Qualified Review By: Date: 03/29/2016 L. L. Korbeil Station Qualified Reviewer Page I of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table of Contents Page Revision History 3 List of Tables 4 1.0 Tenns and Definitions 5 2.0 General lnfonnation 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 Page2 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Revision History Revision Description Revision 13 New issue for Cycle 17.

Page3 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 II Table4-3 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 - U02 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 LHGRF AC(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 Page4of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 I 00%, 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 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 thennal 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 Page5 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 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 6of20

Exelon Nuclear- Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 2.0 Gencrdl Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit I Cycle 17:

• Maximum Average Planar Linear Heat Generation Rate (MAPLl-IGR)

• Minimum Critical Power Ratio (MCPR)

• Single Loop Operation (SLO) OLMCPR adjustment

• Off-rated OLMCPR adjustments (MCPR(P) or MCPR(F))

• Off-rated OLMCPR multipliers (Kp)

• Off-rated LHGR multipliers (LHGRFAC{P) or LHGRFAC{F))

• Rod Block Monitor (RBM) setpoints

• MAPLHGR single loop operation multiplier

• LHGR single loop operation multiplier

• Linear Heat Generation Rate (LHGR)

• Turbine Bypass Valve parameters

• Reactor Coolant System Recirculation Flow Upscale Trips

• Oscillation Power Range Monitor Period Based Detection Algorithm (OPRM PBDA) Trip Setpoints This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 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% of rated core flow

• Final Feedwater Temperature Reduction (FFWTR) up to I05.0°F during cycle extension operation

• Feedwater Heater Out of Service (FWHOOS) up to 60.0°F 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 17 and the associated operating domains discussed above is available in Reference 2.

Page 7 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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) 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.

Table3-1 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 Table3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 0.80 Page 8 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description TI1e Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Table 4-1. TI1ese values are determined by the cycle-specific reload analyses in Reference 2 and are valid for all Cycle 17 operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. Limerick Unit I Cycle 17 has a mid-cycle MCPR breakpoint, as defined in Table 4-1. l11e BASE, TBSOOS, RPTOOS, and PROOS MCPR limits are applicable for any TCV delay time determined by ST-2-001-800-1.

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 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, 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.

Page9of20

Exelon Nuclear- Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

(Reference 2)

Cycle Exposure SCRAM Time < EOR-2677 ;::: EOR - 2677 EOOS Combination Option 1 MWd/ST MWd/ST 3

B 1.39 1.39 BASE A 1.45 1.47 B 1.60 1.60 BASE SL0 2 A 1.60 1.60 B 1.40 1.44 TB SOOS A 1.49 1.53 B 1.60 1.60 TBSOOS SL02 A 1.60 1.60 B 1.41 1.41 RPTOOS A 1.58 1.58 B 1.60 1.60 RPTOOS SL02 A 1.62 1.62 B 1.393 1.39 PROOS A 1.45 1.47 B 1.60 1.60 PROOS SL02 A 1.60 1.60 PROOS+TBSOOS B 1.40 1.44 PROOS+RPTOOS B 1.41 1.41 1

When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation. For PROOS+TBSOOS and PROOS+RPTOOS, only Option B is allowed.

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 for GNF2 fuel 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 1.12.

Page 10 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp (Reference 2)

Core Core Thermal Power (% of Rated)

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

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

$ 60 2.52 2.52 2.42 BASE 1.340 1.131 1.067 1.000

> 60 2.78 2.78 2.57

$ 60 2.56 2.56 2.46 BASE SLO 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

$60 3.32 3.32 2.82 TBSOOSSLO 1.340 1.131 1.067 1.000

>60 3.82 3.82 3.32

$60 2.52 2.52 2.42 RPTOOS 1.340 1.131 1.067 1.000

>60 2.78 2.78 2.57

$60 2.56 2.56 2.46 RPTOOS SLO 1.340 1.131 1.067 1.000

> 60 2.82 2.82 2.61

$60 2.52 2.52 2.42 PROOS 1.367 1.236 1.160 1.000

> 60 2.78 2.78 2.57

$60 2.56 2.56 2.46 PROOS SLO 1.367 1.236 1.160 1.000

> 60 2.82 2.82 2.61

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

>60 3.78 3.78 3.28

$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 I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 U02 tUel rods and Table 5-2 for Gadolinia tUel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), and the now 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 thennal limit multipliers, which allow for a more reliable administration of the LHGR thennal 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 PLUOOS condition is included in the BASE LHGRFAC(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 thennal 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 and are applicable to all operating domains.

Linear interpolation should be used for points not listed in Appendix B of Reference 7.

Thennal limit monitoring must be perfonned with the more limiting LHG R limit resulting from the power and flow biased calculation.

Table 5-1 Linear Heat Generation Rate Limits - U02 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)

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

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2)

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

(Reference 2)

Core Core Thermal Power(% of rated)

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

(%of rated) LHGRFAC(P) Multiplier 560 0.485 0.485 0.490 BASE 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 BASE SLO 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.463 0.463 0.490 TB SOOS 0.750 0.817 0.922 1.000

> 60 0.352 0.352 0.386 560 0.463 0.463 0.490 TBSOOS SLO 0.750 0.817 0.922 1.000

>60 0.352 0.352 0.386 560 0.485 0.485 0.490 RPTOOS 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 RPTOOS SLO 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 PROOS 0.725 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 PROOSSLO 0.725 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.463 0.463 0.490 PROOS+TBSOOS 0.725 0.817 0.922 1.000

>60 0.352 0.352 0.386 560 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 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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% of rated core flow.

Table 6-l 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%

Table 6-2 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 1.34, which is less than the minimum cycle OLMCPR.

Page 16 of20

Exelon Nuclear- Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 movement' 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)

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 I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 8.0 Stability Protection Sctpoints 8.1 Technical Specification Section 2.2. I 8.2 Description llte Limerick Unit I Cycle 17 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 Confinnation Count Trip Settin~

1.12

:; 14 Page 18 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 9.0 Modes of Operation 9.1 Description

'"Tile allowable modes of operation are found in Table 9-1. The BASE application condition includes I MSIVOOS and I TCVffSVOOS provided the restrictions identified in the applicable station procedures are met. Note that I TCVffSVOOS is not allowed to be coincident with one or more TBVOOS. All EOOS options also support the allowance of I TIPOOS.

Table 9-1 Modes of Operation (Reference 2)

EOOS Ootions Ooeratin2 Re2ion 1 BASE, Option A or B Yes:!

BASE SLO, Option A or B Yes~

TBSOOS, Ootion A or B Yes:!

TBSOOS SLO, Option A or B Yes:!

RPTOOS, Ootion A or B Yes 3 RPTOOS SLO, Option A or B Yes 3 TBSOOS and RPTOOS, Option A or B No TBSOOS and RPTOOS SLO, Option A or B No PROOS, Option A or B Yes:!

PROOS SLO, Option A or B Yes:!

PROOS+TBSOOS, Ootion A No PROOS+TB SOOS, Option B Yes:!

PROOS+TB SOOS SLO, Option A or B No PROOS+RPTOOS, Option A No PROOS+RPTOOS, Option B Yes 3 PROOS+RPTOOS SLO, Option A or B No 1

Operating Region refers to operation on the Power to Flow map with or without FFWTR/FWHOOS.

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 19of20

Exelon Nuclear- Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 10.0 Methodology The analytical methods used to detennine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

I. "General Electric Standard Application for Reactor Fuel," NEDE-240 I l-P-A-22, November 2015 and U.S.

Supplement NEDE-240 I 1-P-A-22-US, November 2015.

2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," NED0-32465-A, August 1996.

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

2. "Supplemental Reload Licensing Report for Limerick Unit I Reload 16 Cycle 17, Global Nuclear Fuel Document No. OOIN5161, Revision I, February 2016.

3. "Final Resolved OPL-3 Parameters for Limerick I Cycle 17, Exelon TOOi ESl500025, Rev. I, October 13,2015.

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

5. "Fuel Bundle lnfonnation Report for Limerick Unit I Reload 16 Cycle 17, Global Nuclear Fuel Document No. OOIN5162, Revision 0, February 2016.

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, Revision 5, May 2013.

Page20 of20

Exelon Generation ~

T.S. 6.9.1.12 LG-16-049 April 20, 2016 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 NRC Docket Nos. 50-352

Subject:

Issuance of the Core Operating Limits Report (COLA) for Unit 1 Reload 16, Cycle 17 Enclosed is a copy of the Core Operating Limits Report (COLA) for Limerick Generating Station (LGS) Unit 1 Reload 16 Cycle 17 which incorporates the revised cycle specific parameters resulting from the new configuration implemented for LGS, Unit 1.

The COLR is being submitted to the NRC in accordance with LGS, Unit 1 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 1 Reload 16, Cycle 17 cc: D. Dorman, Administrator, Region I, USNRC (w/attachments)

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

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

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

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT1RELOAD16CYCLE17 3/11/L~

Date: ~r/16 Reviewed By:

M.R.Holmes Independent Reviewer Reviewed By: Date: 3/17/16 M. Doerzbacher Reviewed By: ~ T. R.Bement Engineering Safety Analysis

~x1~---

Approved By:

---tl- J. J. Tusar Manager - BWR Design (GNF)

Date: 03/17/2016 Station Qualified Review By: Date: 03/29/2016 L. L. Korbeil Station Qualified Reviewer Page I of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table of Contents Page Revision History 3 List of Tables 4 1.0 Tenns and Definitions 5 2.0 General lnfonnation 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 Page2 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Revision History Revision Description Revision 13 New issue for Cycle 17.

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Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 II Table4-3 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 - U02 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 LHGRF AC(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 Page4of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 I 00%, 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 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 thennal 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 Page5 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 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 6of20

Exelon Nuclear- Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 2.0 Gencrdl Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit I Cycle 17:

• Maximum Average Planar Linear Heat Generation Rate (MAPLl-IGR)

• Minimum Critical Power Ratio (MCPR)

• Single Loop Operation (SLO) OLMCPR adjustment

• Off-rated OLMCPR adjustments (MCPR(P) or MCPR(F))

• Off-rated OLMCPR multipliers (Kp)

• Off-rated LHGR multipliers (LHGRFAC{P) or LHGRFAC{F))

• Rod Block Monitor (RBM) setpoints

• MAPLHGR single loop operation multiplier

• LHGR single loop operation multiplier

• Linear Heat Generation Rate (LHGR)

• Turbine Bypass Valve parameters

• Reactor Coolant System Recirculation Flow Upscale Trips

• Oscillation Power Range Monitor Period Based Detection Algorithm (OPRM PBDA) Trip Setpoints This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 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% of rated core flow

• Final Feedwater Temperature Reduction (FFWTR) up to I05.0°F during cycle extension operation

• Feedwater Heater Out of Service (FWHOOS) up to 60.0°F 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 17 and the associated operating domains discussed above is available in Reference 2.

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Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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) 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.

Table3-1 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 Table3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)

SLO Multiplier 0.80 Page 8 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description TI1e Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Table 4-1. TI1ese values are determined by the cycle-specific reload analyses in Reference 2 and are valid for all Cycle 17 operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Modes of Operation. Limerick Unit I Cycle 17 has a mid-cycle MCPR breakpoint, as defined in Table 4-1. l11e BASE, TBSOOS, RPTOOS, and PROOS MCPR limits are applicable for any TCV delay time determined by ST-2-001-800-1.

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 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, 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 I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

(Reference 2)

Cycle Exposure SCRAM Time < EOR-2677 ;::: EOR - 2677 EOOS Combination Option 1 MWd/ST MWd/ST 3

B 1.39 1.39 BASE A 1.45 1.47 B 1.60 1.60 BASE SL0 2 A 1.60 1.60 B 1.40 1.44 TB SOOS A 1.49 1.53 B 1.60 1.60 TBSOOS SL02 A 1.60 1.60 B 1.41 1.41 RPTOOS A 1.58 1.58 B 1.60 1.60 RPTOOS SL02 A 1.62 1.62 B 1.393 1.39 PROOS A 1.45 1.47 B 1.60 1.60 PROOS SL02 A 1.60 1.60 PROOS+TBSOOS B 1.40 1.44 PROOS+RPTOOS B 1.41 1.41 1

When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation. For PROOS+TBSOOS and PROOS+RPTOOS, only Option B is allowed.

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 for GNF2 fuel 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 1.12.

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Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table 4-2 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp (Reference 2)

Core Core Thermal Power (% of Rated)

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

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

$ 60 2.52 2.52 2.42 BASE 1.340 1.131 1.067 1.000

> 60 2.78 2.78 2.57

$ 60 2.56 2.56 2.46 BASE SLO 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

$60 3.32 3.32 2.82 TBSOOSSLO 1.340 1.131 1.067 1.000

>60 3.82 3.82 3.32

$60 2.52 2.52 2.42 RPTOOS 1.340 1.131 1.067 1.000

>60 2.78 2.78 2.57

$60 2.56 2.56 2.46 RPTOOS SLO 1.340 1.131 1.067 1.000

> 60 2.82 2.82 2.61

$60 2.52 2.52 2.42 PROOS 1.367 1.236 1.160 1.000

> 60 2.78 2.78 2.57

$60 2.56 2.56 2.46 PROOS SLO 1.367 1.236 1.160 1.000

> 60 2.82 2.82 2.61

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

>60 3.78 3.78 3.28

$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 I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 U02 tUel rods and Table 5-2 for Gadolinia tUel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), and the now 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 thennal limit multipliers, which allow for a more reliable administration of the LHGR thennal 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 PLUOOS condition is included in the BASE LHGRFAC(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 thennal 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 and are applicable to all operating domains.

Linear interpolation should be used for points not listed in Appendix B of Reference 7.

Thennal limit monitoring must be perfonned with the more limiting LHG R limit resulting from the power and flow biased calculation.

Table 5-1 Linear Heat Generation Rate Limits - U02 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)

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

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2)

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

(Reference 2)

Core Core Thermal Power(% of rated)

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

(%of rated) LHGRFAC(P) Multiplier 560 0.485 0.485 0.490 BASE 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 BASE SLO 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.463 0.463 0.490 TB SOOS 0.750 0.817 0.922 1.000

> 60 0.352 0.352 0.386 560 0.463 0.463 0.490 TBSOOS SLO 0.750 0.817 0.922 1.000

>60 0.352 0.352 0.386 560 0.485 0.485 0.490 RPTOOS 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 RPTOOS SLO 0.750 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 PROOS 0.725 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.485 0.485 0.490 PROOSSLO 0.725 0.817 0.922 1.000

>60 0.434 0.434 0.473 560 0.463 0.463 0.490 PROOS+TBSOOS 0.725 0.817 0.922 1.000

>60 0.352 0.352 0.386 560 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 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 of20

Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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% of rated core flow.

Table 6-l 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%

Table 6-2 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 1.34, which is less than the minimum cycle OLMCPR.

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Exelon Nuclear- Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 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 movement' 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)

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 I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 8.0 Stability Protection Sctpoints 8.1 Technical Specification Section 2.2. I 8.2 Description llte Limerick Unit I Cycle 17 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 Confinnation Count Trip Settin~

1.12

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Exelon Nuclear - Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 9.0 Modes of Operation 9.1 Description

'"Tile allowable modes of operation are found in Table 9-1. The BASE application condition includes I MSIVOOS and I TCVffSVOOS provided the restrictions identified in the applicable station procedures are met. Note that I TCVffSVOOS is not allowed to be coincident with one or more TBVOOS. All EOOS options also support the allowance of I TIPOOS.

Table 9-1 Modes of Operation (Reference 2)

EOOS Ootions Ooeratin2 Re2ion 1 BASE, Option A or B Yes:!

BASE SLO, Option A or B Yes~

TBSOOS, Ootion A or B Yes:!

TBSOOS SLO, Option A or B Yes:!

RPTOOS, Ootion A or B Yes 3 RPTOOS SLO, Option A or B Yes 3 TBSOOS and RPTOOS, Option A or B No TBSOOS and RPTOOS SLO, Option A or B No PROOS, Option A or B Yes:!

PROOS SLO, Option A or B Yes:!

PROOS+TBSOOS, Ootion A No PROOS+TB SOOS, Option B Yes:!

PROOS+TB SOOS SLO, Option A or B No PROOS+RPTOOS, Option A No PROOS+RPTOOS, Option B Yes 3 PROOS+RPTOOS SLO, Option A or B No 1

Operating Region refers to operation on the Power to Flow map with or without FFWTR/FWHOOS.

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).

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Exelon Nuclear- Nuclear Fuels COLR Limerick I, Rev. 13 Core Operating Limits Report for Limerick I Cycle 17 10.0 Methodology The analytical methods used to detennine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

I. "General Electric Standard Application for Reactor Fuel," NEDE-240 I l-P-A-22, November 2015 and U.S.

Supplement NEDE-240 I 1-P-A-22-US, November 2015.

2. "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," NED0-32465-A, August 1996.

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

2. "Supplemental Reload Licensing Report for Limerick Unit I Reload 16 Cycle 17, Global Nuclear Fuel Document No. OOIN5161, Revision I, February 2016.

3. "Final Resolved OPL-3 Parameters for Limerick I Cycle 17, Exelon TOOi ESl500025, Rev. I, October 13,2015.

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

5. "Fuel Bundle lnfonnation Report for Limerick Unit I Reload 16 Cycle 17, Global Nuclear Fuel Document No. OOIN5162, Revision 0, February 2016.

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, Revision 5, May 2013.

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