Text

Cycle 21 Core Operating Limits Reports
	ML25065A046
Person / Time
Site:	LaSalle
Issue date:	03/06/2025
From:	Van Fleet J; Constellation Energy Corp, Exelon Generation Co
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	RA25-003
	Download: ML25065A046 (1)
	v • d • e

Constellation RA25-003 March 6, 2025 U.S. Nuclear Regulatory Commission Attention: NRC Region Ill Administrator 2056 Westings Avenue, Suite 400 Naperville, IL 60563-2657 LaSalle County Station, Unit 2 Renewed Facility Operating License No. NPF-18 NRC Docket No. 50-374 LaSalle County Station 2601 North 21 " Road Marseilles, IL 61341 815-415-2000 Telephone 10 CFR 50.4

Subject:

LaSalle County Station Unit 2 Cycle 21 Core Operating Limits Reports In accordance with LaSalle County Station (LSCS) Technical Specifications 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)," Item d, Constellation Energy Generation, LLC (CEG) is submitting a copy of the Unit 2, Revision 21 and Revision 22 COLR. Revision 21 of the COLR was initially issued for LSCS Unit 2 Cycle 21 (L2C21), however, an editorial correction was required, necessitating a revision to the L2C21 COLR. Revision 22 of the Unit 2 COLR is the current revision issued for L2C21.

There are no regulatory commitments contained within this letter.

Should you have any questions concerning this letter, please contact Ms. Laura Ekern, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, ff ii -:?,/,tr John Van Fleet Site Vice President LaSalle County Station

Enclosures:

LaSalle County Station Unit 2 COLR, Revision 21 LaSalle County Station Unit 2 COLR, Revision 22 cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station

LaSalle County Station Unit 2 COLR Revision 21

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report COLR LaSalle 2, Revision 21 Prepared By:

Prepared By:

Reviewed By:

Approved By:

SQR By:

Core Operating Limits Report For LaSalle Unit 2 Cycle 21 p itts JO h n Wi II i am N Digitally signed by Pitts, John William N Date: 2025.02.21 12:15:37 -06'00' John Pitts, NF CM Gutowski, Thomas M.

Thomas Gutowski, NF CM Digitally signed by Gutowski, Thomas M.

Date: 2025.02.21 14:35:05 -05'00' 2025.02.21 14:15:52 -05'00' Kelly McClure, NF CM

/ lj_

-I:

C: v')~ {--) t17l4 Chris Butler, ESA Rash, Eric J 2025-02-21 14:03-06:00 Eric Rash, RE Kristin Mccoskey, NF CM JI 2025-02-21

~

'1{_,

lvv-., 14:51-06:00 Aaron Wise, RE Page 1 of 20 Digitally signed by Butler, Christopher James Date: 2025.02.21 13:38:45 -05'00' Digitally signed by Mccoskey, Kristin Date: 2025.02.21 17:47:40 -06'00'

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report Table of Contents COLR LaSalle 2, Revision 21 Page Revision History.................................................................................................................................. 3 List of Tables....................................................................................................................................... 4

1. Terms and Definitions...................................................................................................................... 5

2. General Information......................................................................................................................... 6

3. MAPLHGR...................................................................................................................................... 7

4. MCPR............................................................................................................................................. 8 4.1. MCPR Limits........................................................................................................................... 8 4.1.1. Power-Dependent MCPR............................................................................................ 8 4.1.2. Flow-Dependent MCPR............................................................................................... 8 4.1.3. Safety Limit MCPR...................................................................................................... 8 4.2. Scram Time............................................................................................................................ 12 4.3. Recirculation Flow Control Valve Settings............................................................................. 12

5. LHGR............................................................................................................................................ 13

6. Rod Block Monitor......................................................................................................................... 15

7. Traversing In-Core Probe System (References 2, 4, and 11)....................................................... 16 7.1. Description............................................................................................................................ 16 7.2. Bases.................................................................................................................................... 16

8. Stability Protection Setpoints......................................................................................................... 17

9. Modes of Operation....................................................................................................................... 18

10. Methodology................................................................................................................................ 19

11. References.................................................................................................................................. 20 Page 2 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report Revision History Revision Description 21 Initial issuance for L2C21.

Page 3 of20 COLR LaSalle 2, Revision 21

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report List of Tables COLR LaSalle 2, Revision 21 Table 2-1 Cycle Exposure Range Definitions............................................................................................................. 6 Table 3-1 MAPLHGR versus Average Planar Exposure............................................................................................ ?

Table 3-2 MAPLHGR SLO Multiplier.......................................................................................................................... 7 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)........................................................................ 9 Table 4-2 Power-Dependent MCPR Multipliers (KP)............................................................................................... 10 Table 4-3 SLO and DLO Flow-Dependent MCPR Limits (MCPRF)......................................................................... 10 Table 4-4 Cycle Specific SLMCPR (MCPRss.s-A.)..................................................................................................... 11 Table 4-5 Scram Times Required for Option A and Option B Application at Notch Position 39............................. 12 Table 5-1 LHGR Limits............................................................................................................................................ 13 Table 5-2 Power-Dependent LHGR Multipliers (LHGRFACP), DLO and SLO........................................................ 14 Table 5-3 Flow-Dependent LHGR Multipliers (LHGRFACF)................................................................................... 14 Table 6-1 Rod Block Monitor Setpoints................................................................................................................... 15 Table 8-1 OPRM PBDA Trip Setpoints.................................................................................................................... 17 Table 9-1 Allowed Modes of Operation and EOOS Combinations......................................................................... 18 Table 9-2 Power Level Restrictions......................................................................................................................... 18 Page 4 of20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report COLR LaSalle 2, Revision 21

1. Terms and Definitions ARO ARTS BOC CRD DLO EOC EOOS EOR FFWTR FWHOOS GE GNF ICF KP LHGR LHGRFACF LHGRFACP LOCA LPRM L2C21 MAPLHGR MCPR MCPRss.s%

MCPRF MCPRP MELLLA MOC MSIVOOS MSR MSROOS NRC OLMCPR OOS OPRM PBDA PLUOOS PROOS RPTOOS RWE SLMCPR SLO SRVOOS TBV TBVOOS TCV TCVSC TIP TSV 30M All rods out Average power range monitor, rod block monitor and technical specification improvement program Beginning of cycle Control rod drive Dual loop operation End of cycle Equipment out of service End of rated - Cycle exposure corresponding to all rods out, 100% power/100% flow, and normal feedwater temperature Final feedwater temperature reduction Feedwater heater out of service General Electric Global Nuclear Fuels - Americas Increased core flow Power-dependent MCPR multiplier Linear heat generation rate Flow-dependent LHGR multiplier Power-dependent LHGR multiplier Loss of coolant accident Local power range monitor LaSalle Unit 2 Cycle 21 Maximum average planar linear heat generation rate Minimum critical power ratio Limiting MCPR value such that 99.9% of the fuel in the core is not susceptible to boiling transition Flow-dependent MCPR Power-dependent MCPR Maximum extended load line limit analysis Middle of cycle point for licensing purposes Main steam isolation valve out of service Moisture separator reheater Moisture separator reheater out of service Nuclear Regulatory Commission Operating limit minimum critical power ratio Out of service Oscillation power range monitor Period based detection algorithm Power load unbalance out of service Pressure regulator out of service Recirculation pump trip out of service Rod withdrawal error Safety limit minimum critical power ratio Single loop operation Safety/relief valve out of service Turbine bypass valve Turbine bypass yalve out of service Turbine control valve Turbine control valve slow closure Traversing in-core probe Turbine stop valve 30 Monicore Page 5 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

2. General Information The data provided in this report is valid for (Reference 7):

COLR LaSalle 2, Revision 21 Maximum Extended Load Line Limit (MELLLA) down to 82.8% of rated core flow during full power operation (rated core flow is 108.5 Mlb/hr) (Reference 6).

ICF to 105% of rated core flow.

Coastdown to 40% rated power (rated core thermal power is 3546 MWth) (Reference 6 and 7).

o Operation at a power level above that which can be achieved with ARO, ICF, FFWTR, and steady-state equilibrium Xenon concentrations is not supported.

Maximum reduction of 100°F of the feedwater temperature for FWHOOS/FFWTR.

Throughout this report, power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values unless otherwise specified.

Table 2-1 defines the three exposure ranges used in the COLR. The term (EOR21 - 4951 MWd/ST) means the Cycle 21 EOR exposure minus 4951 MWd/ST of exposure. The value of the EOR exposure is based on actual plant operation and is thus determined from projections to this condition made near, but before, the time when the EOR21 - 4951 MWd/ST exposure will be reached. For cycle exposure dependent limits at the exact MOC exposure, the more limiting of the BOC to MOC and the MOC to EOC limits should be used. This can be achieved by applying the MOC to EOC limits to the MOC point as all cycle exposure dependent limits in the MOC to EOC limit sets are the same as, or more limiting than, those in the BOC to MOC limit sets.

Nomenclature BOC to MOC MOC to EOC BOC to EOC Table 2-1 Cycle Exposure Range Definitions (Reference 7)

Cycle Exposure Range BOC21 to (EOR21 - 4951 MWd/ST)

(EOR21 -4951 MWd/ST) to EOC21 BOC21 to EOC21 Page 6 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

3. MAPLHGR Technical Specification Sections 3.2.1 and 3.4.1 COLR LaSalle 2, Revision 21 MAPLHGR values as a function of average planar exposure are given in Tables 3-1. During SLO, these limits are multiplied by the SLO multiplier listed in Table 3-2. Tables 3-1 and 3-2 provide coverage for all equipment out-of-service conditions.

Table 3-1 MAPLHGR versus Average Planar Exposure (Reference 7)

Avg. Planar MAPLHGR Exposure (kW/FT)

(GWd/ST) 0.00 14.36 21.22 13.01 40.82 10.75 57.60 8.00 63.50 6.00 Table 3-2 MAPLHGR SLO Multiplier (Reference 7)

SLO Fuel Type MAPLHGR Multiplier GNF3 0.90 Page 7 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report COLR LaSalle 2, Revision 21

4. MCPR Technical Specification Sections 3.2.2. 3.3.4.1. 3.4.1. and 3.7.7 4.1. MCPR Limits The rated OLMCPRs given in Table 4-2 are the maximum values obtained from analysis of the pressurization events, non-pressurization events, and the Option Ill stability evaluation. MCPR values are determined by the cycle-specific fuel reload analyses in Reference 7. Table 4-2 is used in conjunction with the ARTS-based power (Kp) and flow (MCPRF) dependencies presented in Tables 4-3, 4-4, and 4-5 below. The OLMCPR is determined for a given power and flow condition by evaluating the power dependent OLMCPR, comparing to the flow dependent OLMCPR and selecting the greater of the two.

4.1.1. Power-Dependent MCPR The power-dependent MCPR multiplier, KP, is determined from Table 4-3, and is dependent only on the power level and the Application Group (EOOS). The product of the rated OLMCPR and the proper KP provides the power-dependent OLMCPR (MCPRP).

4.1.2. Flow-Dependent MCPR Tables 4-4 through 4-5 give the MCPRF limit as a function of the core flow, based on the applicable plant conditions. The MCPRF limit determined from these tables is the flow-dependent OLMCPR and applies to all application conditions 4.1.3. Safety Limit MCPR The cycle-specific SLMCPR, known as MCPR99.9%, can be found in Table 4-6 for dual loop and single loop operating conditions. The values in Table 4-6 were used to calculate the rated and off-rated MCPR limits.

Page 8 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report COLR LaSalle 2, Revision 21 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

(Reference 7)

Application Group DLO/SLO Exposure Range Option A Option B BOC-MOC 1.34 1.33 DLO Base Case MOC-EOC 1.38 1.33 SLO BOC-EOC 1.57 1.57 Base Case + TCVSC BOC-MOC 1.38 1.33 DLO

+ RPTOOS + PROOS +

MOC-EOC 1.40 1.34 MSROOS SLO BOC-EOC 1.57 1.57 BOC-MOC 1.37 1.33 Base Case + TCVSC +

DLO TBVOOS (all 5 valves)

MOC-EOC 1.39 1.33 SLO BOC-EOC 1.57 1.57 Base Case + TCVSC +

BOC-MOC 1.42 1.41 TBVOOS (all 5 valves)

DLO

+ RPTOOS + PROOS +

MOC-EOC 1.43 1.41 MSROOS SLO BOC-EOC 1.57 1.57 BOC-MOC 1.36 1.33 DLO Base Case + MSROOS MOC-EOC 1.39 1.33 SLO BOC-EOC 1.57 1.57 Page 9 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report COLR LaSalle 2, Revision 21 Table 4-2 Power-Dependent MCPR Multipliers (KP)

(Reference 7)

Core Thermal Power (% rated)

Application Group 25 45 60 S 85

>85 KP Operating Limit MCPR Multiplier Base Case 1.150 1.150 1.150 1.056 1.056 Base Case + TCVSC +

RPTOOS + PROOS +

1.242 1.207 1.178 1.111 1.064 MSROOS Base Case + TCVSC +

1.150 1.150 1.150 1.058 1.058 TBVOOS (all 5 valves)

Base Case + TCVSC +

TBVOOS (all 5 valves) 1.242 1.207 1.178 1.111 1.070

+ RPTOOS + PROOS

+ MSROOS Base Case + MSROOS 1.242 1.207 1.178 1.111 1.070 Table 4-3 SLO and DLO Flow-Dependent MCPR Limits (MCPRF)

(Reference 7)

Flow MCPRF

(% Rated)

DLO SLO 30.0 1.58 1.61 86.3 1.20*

1.23*

105.0 1.20*

1.23*

100 1.000 1.000 1.000 1.000 1.000

This value is lower than the initial MCPR analyzed in the LOCA analysis. However, because PANACEA calculates the offrated MCPR by taking the maximum of the MCPRp, MCPRf, and OLMCPR, the offrated MCPR is inherently higher than analyzed in the LOCA analysis and the LOCA analysis remains applicable at all conditions.

Page 10 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report Table 4-4 Cycle Specific SLMCPR (MCPRs9.9%)

(Reference 7)

Flow MCPR09.9%

DLO 1.09 SLO 1.11 Page 11 of 20 COLR LaSalle 2, Revision 21

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report 4.2. Scram Time COLR LaSalle 2, Revision 21 Option A and Option B MCPR analyses and results are dependent upon core average control rod blade scram speed insertion times.

The Option A scram time is the Improved Technical Specification scram speed based insertion time. To utilize the MCPR limits for the Option A scram speed insertion times, the core average scram speed insertion time for 20% insertion must be less than or equal to 0.900 seconds (Reference 9) (0.875 seconds at notch position 39, Reference 10).

To utilize the MCPR limits for the Option B scram speed insertion times, the core average scram speed time for insertion to notch 39 must be less than or equal to, 8 (Reference 13, see equation 1 ).

(___!!J_) a or r 8 = 0.603 + 1.65 Lf=l Ni

( ~:

1

.) 0.0106 L,1=1 N, (1)

Whereµ (0.603 for LaSalle) is the mean of means plus two standard deviations scram insertion time to notch position 39 dropout and a (0.0106 for LaSalle) is the standard deviation of the distribution for average scram insertion time to notch position 39 dropout used in the Option B scram speed statistical analysis, and where n is the number of surveillance tests performed in the cycle, Ni is the number of active control rods measured in surveillance test i, and N1 is the total number of active rods measured.

Alternatively, to use Option B, omitting the right-hand side of the, 8 equation would be conservative, and is acceptable. See Table 4-1 for a summary of scram time requirements related to the use of Option A and Option B MCPR limits.

If the core average scram insertion time does not meet the Option B criteria, but is within the Option A criteria, the appropriate steady state MCPR value may be determined from a linear interpolation between the Option A and B limits with standard mathematical rounding to two decimal places.

Table 4-5 Scram Times Required for Option A and Option 8 Application at Notch Position 39 (References 10 and 13)

Notch Position*

Scram Time Required for Option A Scram Time Required for Option 8 Application (sec)

Application (sec)**

5: 0.603 OR 39 5: 0.875 (L

nNl

.) 0.0106

$ 0.603 + 1.65

\\

1=1N,

The InsertIon time to a notch posItIon Is calculated using the CRD reed switch drop-out time per Reference 10 and interpolation with scram time values per Reference 9.

- Reference 13 uses the term Option B'. However, since Option B' is a plant-specific Option B scram speed, demonstrating compliance remains the same as the generic Option B scram speed, and LaSalle will continue to use the term Option B.

4.3. Recirculation Flow Control Valve Settings Cycle 21 was analyzed with a maximum core flow runout of 105%; therefore, the recirculation pump flow control valves must be set to maintain core flow less than 105% (113.925 Mlbm/hr) for all runout events (Reference 7).

Page 12 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

5. LHGR Technical Specification Sections 3.2.3 and 3.4.1 COLR LaSalle 2, Revision 21 The LHGR limit is the product of the exposure dependent LHGR limits from Table 5-1 and the minimum of the power dependent LHGR Factor, LHGRFACP, or the flow dependent LHGR Factor, LHGRFACF. as applicable.

Interpolation of the Table 5-1 limits should be performed as directed in Reference 8. The LHGRFACP multiplier is determined from Table 5-2. The LHGRFACF multiplier is determined from Table 5-3. The SLO multipliers in Table 5-3 have been limited to a maximum value of 0.90, the SLO LHGR multiplier for GNF3 fuel (Reference 7).

Table 5-1 LHGR Limits (References 5 and 8)

Peak Pellet Ex osure U02 LHGR Limit See Table A-1 of Reference 8 Peak Pellet Exposure I Gadolinia LHGR Limit See Table A-2 of Reference 8 Page 13 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report COLR LaSalle 2, Revision 21 Table 5-2 Power-Dependent LHGR Multipliers (LHGRFACp), DLO and SLO (Reference 7)

Core thermal Power(% rated)

Application Group 25 45 60 85 100 LHGRFACp Multiplier Base Case 1.000 1.000 1.000 1.000 1.000 Base Case + TCVSC +

RPTOOS + PROOS +

0.720 0.850 0.940 1.000 1.000 MSROOS Base Case + TCVSC +

0.955 0.955 1.000 1.000 1.000 TBVOOS (all 5 valves)

Base Case + TCVSC +

TBVOOS (all 5 valves) 0.720 0.850 0.940 1.000 1.000

+ RPTOOS + PROOS

+MSROOS Base Case+

0.720 0.850 0.940 1.000 1.000 MSROOS Table 5-3 Flow-Dependent LHGR Multipliers (LHGRFACF)

(Reference 7)

Flow LHGRFACF

(% Rated)

DLO SLO 30.0 0.584 0.584 64.18 0.900 0.900 75.0 1.000 0.900 105.0 1.000 0.900 Page 14 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

6. Rod Block Monitor Technical Specification Sections 3.3.2.1 and 3.4.1 COLR LaSalle 2, Revision 21 The Rod Block Monitor Upscale Instrumentation allowable values are determined from the relationships shown below (Reference 3):

Table 6-1 Rod Block Monitor Setpoints Rod Block Monitor Upscale Trip Function Allowable Value Two Recirculation Loop 0.66 Wd + 54.0%

Operation Single Recirculation Loop 0.66 Wd + 48. 7%

Operation Wd - percent of rated recirculation drive flow.

The setpoint may be lower/higher and will still comply with the rod withdrawal error (RWE) analysis because RWE is analyzed unblocked (Reference 7). The allowable value is clamped with a maximum value not to exceed the allowable value for a recirculation loop drive flow (Wd) of 100%.

Page 15 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

7. Traversing In-Core Probe System (References 2, 4, and 11) 7.1. Description COLR LaSalle 2, Revision 21 When the traversing in-core probe (TIP) system (for the required measurement locations) is used for recalibration of the LPRM detectors and monitoring thermal limits, the TIP system shall be operable with the following:

1. Movable detectors, drives and readout equipment to map the core in the required measurement locations, and

2. Indexing equipment to allow all required detectors to be calibrated in a common location.

The following applies for use with 3DM:

At any time, including BOC, the total number of failed and/or bypassed LPRMs does not exceed 25%

(Reference 4). In addition, no more than 22 TIP channels can be OOS (failed or rejected) (Reference 2).

Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable calibration functions.

7.2. Bases The operability of the TIP system with the above specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core. The normalization of the required detectors is performed internal to the core monitoring software system.

Page 16 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

8. Stability Protection Setpoints Technical Specification Section 3.3.1.3 COLR LaSalle 2, Revision 21 Table 8-1 OPRM PBDA Trip Setpoints (Reference 7)

PBDA Trip Amplitude Setpoint (Sp) 1.15 Corresponding Maximum Confirmation Count Setpoint (Np) 16 The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system.

The OPRM PBDA trip settings are applicable when the OPRM system is declared operable, and the associated Technical Specifications are implemented.

Page 17 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

9. Modes of Operation COLR LaSalle 2, Revision 21 The allowed modes of operation with combinations of equipment out-of-service are as described below. Power level restrictions associated with EOOS are shown in Table 9-2.

Table 9-1 Allowed Modes of Operation and EOOS Combinations (Reference 7)

Equipment Out of Service Options <1l <2J <3J <4l <5l <6l <7>

Short Names Base Case BASE_DLO _ OPTB(A)

Base Case + SLO BASE_SLO _OPTB(A)

Base Case + TCVSC + RPTOOS + PROOS + MSROOS EOOS1_DLO_OPTB(A)

Base Case + TCVSC + RPTOOS + PROOS + MSROOS + SLO EOOS1_SLO_OPTB(A)

Base Case+ TCVSC + TBVOOS (all 5 valves)

EOOS2_DLO _ OPTB(A)

Base Case+ TCVSC + TBVOOS (all 5 valves)+ SLO EOOS2_SLO _OPTB(A)

Base Case+ TCVSC + TBVOOS (all 5 valves) + RPTOOS + PROOS +

EOOS3_DLO_ OPTB(A)

MSROOS Base Case+ TCVSC + TBVOOS (all 5 valves)+ RPTOOS + PROOS +

EOOS3_SLO_OPTB(A)

MSROOS +SLO Base Case + MSROOS EOOS4_DLO_OPTB(A)

Base Case + MSROOS + SLO EOOS4_SLO _ OPTB(A)

(1) Base case includes 1 SRVOOS + 1 TCV/TSV 00S + FWHOOS/FFWTR + 1 MSIVOOS + 1 TBVOOS + PLUOOS (Reference 7).

(2) The 1 TBVOOS in the Base Case assumes one of TBVs #1-4 are not credited for pressure control and one of TBVs #1-5 are not credited for fast opening (Reference 12). The #5 TBV is not available for pressure relief and thus cannot be used as one of the credited valves to open in pressure control (Reference 12).

(3) The 5 TBVOOS application conditions assume three of TBVs #1-4 are not credited for pressure control and all five of TBVs #1-5 are not credited for fast opening (Reference 12). The #5 TBV is not available for pressure relief and thus cannot be used as one of the credited valves to open in pressure control (Reference 12).

(4) The+ sign that is used in the Equipment Out of Service Option I Application Group descriptions designates an "and/or

(Reference 6).

(5) All EOOS Options are applicable to the entire range of licensed flow and feedwater temperature (MELLLA, ICF, FFWTR, and coastdown) unless otherwise specified (Reference 7). SLO is not applicable to MELLLA or ICF (Reference 14).

(6) All EOOS options in Table 9-1 can be used in Option A or B (Reference 7).

(7) MSR is considered to be in-service when second stage reheat is receiving full flow (Reference 15).

Condition 1 MSIVOOS 1 TCV/TSV OOS Table 9-2 Power Level Restrictions (Reference 7)

Power Level Restrictions (% Rated)

S75%

S85%

Page 18 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

10. Methodology COLR LaSalle 2, Revision 21 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1.

GNF Report NEDE-24011-P-A-31 (Revision 31), "General Electric Standard Application for Reactor Fuel,"

November 2020 and the U.S. Supplement NEDE-24011-P-A-31-US, November 2020.

Page 19 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report

11. References COLR LaSalle 2, Revision 21

1.

Constellation Energy Generation, LLC Docket No. 50-374 LaSalle County Station, Unit 2, Facility Operating License No. NPF-18.

2.

GNF Report 005N6665, Revision 0, "Exelon BWR Fleetwide Technical Evaluation of 50% TIP Strings Out-of-Service on Methods Uncertainties," March 2020.

3.

Constellation Nuclear Fuels Letter NFM:MW:01-0106, "LaSalle Unit 1 and Unit 2 Rod Block Monitor COLR Setpoint Change," April 3, 2001.

4.

GE Nuclear Energy Report NEDC-32694P-A, Revision 0, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations," August 1999.

5.

GNF Report 007N9155, Revision 0, "Fuel Bundle Information Report for LaSalle Unit 2 Reload 20 Cycle 21,"

December 2024.

6.

Constellation TOOi NF240421, Revision 0, "LaSalle Unit 2 Cycle 21 FRED Form," July 09, 2024.

7.

GNF Report 007N9154, Revision 0, "Supplemental Reload Licensing Report for LaSalle Unit 2 Reload 20 Cycle 21," December 2024.

8.

GNF Document No. NEDC-33879P, Revision 5, "GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II)," August 2024.

9.

Constellation TOOi NF240507, Revision 0, "LaSalle Unit 2 Cycle 21 OPL-3," August 8, 2024.

10.

GNF Letter DRF A12-00038-3, Vol. 4, "Scram Times versus Notch Position," May 22, 1992.

11.

NRC Letter, Adam's Accession #ML021130098, "Issuance of Amendments (TAC Nos. M95156 and M95157)," October 29, 1996.

12.

Constellation TOOi ES1900018, Revision 2, "LaSalle GNF3 Nuclear Fuel Transition Design Inputs - F0900 Cycle-Independent Transient Analysis," November 13, 2020.

13.

GNF Report 005N5612, Revision 0, "LaSalle County Station Option B' Scram Speed Implementation Engineering Report," January 2020.

14.

GEH Report GE-NE-A13000384-07-01, "LaSalle County Station Power Uprate". September 1999.

15.

Constellation EC 630152, Revision 1, "GNF3 NFI F0900 MCFA and MSROOS Inputs," November 13, 2020.

Page 20 of 20

LaSalle County Station Unit 2 COLR Revision 22

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report COLR LaSalle 2, Revision 22 Prepared By:

Prepared By:

Reviewed By:

Approved By:

SOR By:

Core Operating Limits Report For LaSalle Unit 2 Cycle 21 P *,tts, JO h n w*, 11 *,am N Digitally signed by Pitts, John William N Date: 2025.02.24 20:08:49 -06'00' John Pitts, NF CM G Utowskl. Thomas M Digitally signed by Gutowski, Thomas M.

1

Date: 2025.02.24 21:14:35 -05'00' Thomas Gutowski, NF CM

~M'Cbw.

2025.02.24 21 :12:02

-05'00' Kelly McClure, NF CM

/ lj_. -4?

(__~Y/ll{J,p wl/4 Chris Butler, ESA

/I 2025-02-24

~

~ ~

20:37-06:00 Aaron Wise, RE Digitally signed by Butler, Christopher James Date: 2025.02.24 21 :17:10-05'00' Digitally signed by Mccoskey, Kristin Date: 2025.02.24 21:57:02-06'00' Kristin Mccoskey, NF CM

~ ~

~;;;-0~~~5J 08:09-06:00 Eric Rash*, RE Page 1 of 20

Constellation Energy Generation - Nuclear Fuels L2C21 Core Operating Limits Report Table of Contents COLR LaSalle 2, Revision 22 Page Revision History.................................................................................................................................. 3 List of Tables....................................................................................................................................... 4