RA20-044, Unit 2 - Unit 1 Cycle 19 Core Operating Limits Report

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Unit 2 - Unit 1 Cycle 19 Core Operating Limits Report
ML20254A159
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 09/10/2020
From: Hansett P
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA20-044
Download: ML20254A159 (23)
v • d • e


Text

RA20-044 10 CFR 50.4 September 10, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Unit 1 and Unit 2 Renewed Facility Operating License No. NFP-11 and NPF-18 NRC Docket No. 50-373 and 50-374

Subject:

Unit 1 Cycle 19 Core Operating Limits Report In accordance with LaSalle County Station (LSCS) Technical Specifications (TS) 5.6.5.d, "CORE OPERATING LIMITS REPORT (COLR)," attached is a copy of the Unit 1 COLR revision 19. The Unit 1 COLR Cycle 19 was revised to implement having up to 50% of traversing in-core probe (TIP) strings out of service in accordance with applicable design analyses and procedures.

There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Mr. Dan Mearhoff, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, tU~

Philip W. Hansett Plant Manager LaSalle County Station Attachments: LaSalle Unit 1 COLR revision 19 cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station

Core Operating Limits Report For LaSalle Unit 1 Cycle 19 Prepared By: -~~---

Kevin Smith, NF CM Date: 6/22/2020

~ Ll'Cht-u Reviewed By: Date: 6/24/2020 Kelly McClure, NF CM Reviewed By:

John Simmons, ESA 2020.06.25 07:56:03 -05'00' Reviewed By: Date: _ _ _ __

Karl Hachmuth, RE ft_ I~ I ~ Digitally signed by Kovacs, Ashley

-(.;<Jrl 11\J;~ ll~

1 ON: cn111Kovacs, Ashley Approved By: J ____;.;0*~~*~202~0.~~.2*~11~:16:~55-0~500

~*--- Date: _ _ _ __

Ashley Kovacs, NF CM Station Qualified Review By:

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. Date: _ _ _ __

Joshua Shea, RE Page 1of22

Table of Contents Page Revision History .................................................................................................................................... 3 List of Tables ................................................................................................................................. ........ 4

1. Terms and Definitions ....................................................................................................................... 5
2. General Information ........................................................................................................................... 7
3. MAPLHGR ...................................................................................................................................... ... 8
4. MCPR ............................. ... .... ..... .. ... .... ....... ...... ..... .. .................... .... .. .. ......................... ..................... 9 4.1. MCPR Limits ................................................ ............................................................................. 9 4.1.1. Power-Dependent MCPR ................................. ........ ............... ................ ...................... 9 4.1.2. Flow-Dependent MCPR .................. .............................................................................. 9 4.1.3. Safety Limit MCPR ........................................................................................................ 9 4.2. Scram Time ....... .............. ... ............................................ .................... ... .......... .... ..................... 10 4.3. Recirculation Flow Control Valve Settings ............. ................................................................. 1O
5. LHGR .............................................................................................................................................. 14
6. Rod Block Monitor .... ..... ......... .. .......................................... ............................................................. 17
7. Traversing In-Core Probe System ........ ... ...... .. .. .... ....... ... .. ............ .. ... ....... ..................... ...... ....... .. . 18 7.1. Description ......................................................................................................... ..................... 18 7.2. Bases .................. ....... .... ... ....................... ....... ............... ..................... .. ....................... ... ....... . 18
8. Stability Protection Setpoints ... ................. ......... ... ........................................................................ ... 19
9. Modes of Operation ......................................................................................................................... 20
10. Methodology .. ...... ..... .... ........ ........................ .......... ...... ...... ......... ... ....................................... .... .... 21
11. References .................................................................................................................................... 22 Page 2 of 22

Record of COLR LaSalle 1 Cycle 19 Revisions Revision Description 19 Implementation of fleet wide technical evaluation for 50%

TIP Strings Out-Of-Service.

18 Initial issuance for L 1C19.

Page 3 of22

List of Tables Table 2-1 Cycle Exposure Range Definitions ......... .... .. .. .......... ... ..................... ... .... ......... ...... .. ..... .. .. .. 7 Table 3-1 MAPLHGR versus Average Planar Exposure, GNF2 Fuel. ......................... ... ..................... 8 Table 3-2 MAPLHGR SLO Multiplier, GNF2 Fuel .. .............................................................................. 8 Table 4-1 Scram Times Required for Option A and Option B Application at Notch Position 39 ..... ... 10 Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR), GNF2 Fuel ......... ... ... ........ .. .. . 11 Table 4-3 Power Dependent MCPR Multipliers (KP), GNF2 Fuel .. ............... .... ... ..... .. .... .............. ..... 12 Table 4-4 DLO Flow Dependent MCPR Limits (MCPRF), GNF2 Fuel ....................................... .... .. .. 13 Table 4-5 SLO Flow Dependent MCPR Limits (MCPRF), GNF2 Fuel .... ............. .... ............... .. ......... 13 Table 4-6 Cycle Specific SLMCPR (MCPRgg,go;.) .... .. .. .. ..... .. ... ................. ... .............. ............. .. ........... 13 Table 5-1 LHGR Limit, GNF2 Fuel. .. ................... .... .. ........ ... .................. .. .......................... .......... ...... 14 Table 5-2 Power Dependent LHGR Multipliers (LHGRFACP), GNF2 Fuel, DLO and SLO .. .... ... ... ............ ... ......... .. ........ .... .. ................... ............... .. ....... .. .................. . 15 Table 5-3 Flow-Dependent LHGR Multipliers (LHGRFACF), GNF2 Fuel, BOC to EOG, Pressurization (Application Groups with 1 TCV/TSV Closed or OOS) .............................. 16 Table 5-4 Flow-Dependent LHGR Multipliers (LHGRFACF), GNF2 Fuel, BOC to EOG, No Pressurization (Application Groups with TCV/TSV In-Service) .. .... ....... .. ...... .. .. .. ........ . 16 Table 6-1 Rod Block Monitor Setpoints ............................ ............. ........... ................... .................... .. 17 Table 8-1 OPRM PBDA Trip Setpoints .. .. ............. .......... ...... ...... .. .. .. .. ............... .. ..... ......... ... ............. 19 Table 9-1 Allowed Modes of Operation and EOOS Combinations .... .. .... .. ............ .. ............. ........ .. .. .20 Page 4 of 22

COLR LaSalle 1 Rey 19

1. Terms and Definitions ARO All Rods Out ARTS Average Power Range Monitor, Rod Block Monitor and Technical Specification Improvement Program BOC Beginning of cycle CRD Control rod drive DLO Dual loop operation EOC End of cycle EOOS Equipment out of service EOR End of rated - Cycle exposure corresponding to all rods out, 100% power/100%

flow, and normal feedwater temperature.

FFWTR Final feedwater temperature reduction FWHOOS Feedwater heater out of service GNF Global Nuclear Fuels - Americas ICF Increased core flow KP Power-dependent MCPR multiplier L 1C19 LaSalle Unit 1 Cycle 19 LHGR Linear heat generation rate LHGRFACF Flow-dependent LHGR multiplier LHGRFACp Power-dependent LHGR multiplier LPRM Local power range monitor MAPLHGR Maximum average planar linear heat generation rate MCPR Minimum critical power ratio MCPRss.so;. Limiting MCPR value such that 99.9% of the fuel in the core is not susceptible to boiling transition.

MCPRF Flow-dependent MCPR MELLLA Maximum extended load line limit analysis MOC Middle of Cycle Point for Licensing Purposes 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 RPTOOS Recirculation pump trip out of service RWE Rod withdrawal error SLMCPR Safety limit minimum critical power ratio SLO Single loop operation SRVOOS Safety/relief valve out of service TBV Turbine bypass valve TBVOOS Turbine bypass valve out of service TCV Turbine control valve Page 5 of22

COLR LaSalle 1 Rey 19

1. Terms and Definitions (continued)

TCVIS All Turbine Control Valves/Turbine Stop Valves in-service TCVSC Turbine control valve slow closure TIP Traversing in-core probe TSV Turbine stop valve 3DM 30 Monicore Page 6 of 22

COLR LaSalle 1 Rev 19

2. General Information (Reference 7)

The data provided in this report is valid for:

  • Maximum Extended Load Line Limit down to 82.8% of rated core flow during full power operation o Rated core flow is 108.5 Mlbm/hr (Reference 6)
  • ICF to 105% of rated core flow
  • Coastdown to 40% rated power o Rated core thermal power is 3546 MWth 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.

Table 2-1 defines the three exposure ranges used in the COLR. The term (EOR19 - 4361 MWd/ST) means the projected Cycle 19 EOR exposure minus 4361 MWd/ST of exposure. 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.

Table 2-1 Cycle Exposure Range Definitions (Reference 7)

Nomenclature Cycle Exposure Range BOC to MOC BOC19 to (EOR19-4361 MWd/ST)

MOC to EOC (EOR 19 - 4361 MWd/ST) to EOC 19 BOC to EOC BOC19 to EOC19 Page 7 of22

COLR LaSalle 1 Rev 19

3. MAPLHGR Technical Specification Sections 3.2.1 and 3.4.1 MAPLHGR values as a function of average planar exposure are given in Table 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 modes of operation.

Table 3-1 MAPLHGR versus Average Planar Exposure GNF2 Fuel (Reference 7)

Average Planar MAPLHGR Limit Exposure (kW/ft)

(GWd/ST) 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 Table 3-2 MAPLHGR SLO Multiplier GNF2 Fuel (Reference 7)

SLO Fuel Type MAPLHGR Multiplier GNF2 0.78 Page 8 of22

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 and flow dependent MCPR values 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.

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.

4.1.3. Safety Limit MCPR The cycle-specific SLMCPR, known as MCPRss.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 MCPR limits.

Page 9 of22

COLR LaSalle 1 Rev 19 4.2. Scram Time 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 insertion time for 20% insertion must be less than or equal to 0.694 seconds (Reference

9) (0.672 seconds at notch position 39, Reference 10). 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. When performing the linear interpolation to determine MCPR limits, ensure that the time used for Option A is 0.900 seconds (0.875 seconds to notch position 39, Reference 10).

Table 4-1 Scram Times Required for Option A and Option B Application at Notch Position 39 (References 9 and 10)

Notch Position* Option A Option B 39 ~ 0.875 sec. ~ 0.672 sec.

  • The insertion time to a notch pos1t1on 1s calculated using the CRD reed switch drop-out insertion fraction per Reference 10 and interpolation with scram time values per Reference 9.

4.3. Recirculation Flow Control Valve Settings Cycle 19 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 10 of 22

Table 4-2 Operating Limit Minimum Critical Power Ratio (OLMCPR)

GNF2 Fuel (Reference 7)

DLO/ Exposure Application Group Option A Option B SLO Range BOC-MOC 1.41 1.37 DLO MOC-EOC 1.45 1.41 Base Case BOC-MOC 1.59 1.59 SLO MOC-EOC 1.59 1.59 BOC-MOC 1.47 1.39 DLO Base Case + TCVSC MOC-EOC 1.51 1.43

+ RPTOOS +

PROOS BOC-MOC 1.59 1.59 SLO MOC-EOC 1.59 1.59 BOC-MOC 1.44 1.40 DLO Base Case + TCVSC MOC-EOC 1.48 1.44

+ TBVOOS (all 5 valves) BOC-MOC 1.59 1.59 SLO MOC-EOC 1.59 1.59 BOC-MOC 1.50 1.42 Base Case + TCVSC DLO

+ TBVOOS (all 5 MOC-EOC 1.54 1.46 valves) + RPTOOS + BOC-MOC 1.59 1.59 PROOS SLO MOC-EOC 1.59 1.59 BOC-MOC 1.41 1.37 DLO Base Case with MOC-EOC 1.45 1.41 TCVIS BOC-MOC 1.59 1.59 SLO MOC-EOC 1.59 1.59 BOC-MOC 1.50 1.42 DLO Base Case + TCVSC MOC-EOC 1.54 1.46

+ TBVOOS (all 5 valves)+ RPTOOS + BOC-MOC 1.59 1.59 PROOS with TCVIS SLO MOC-EOC 1.59 1.59 Page 11of22

Table 4-3 Power Dependent MCPR Multipliers (KP)

GNF2 Fuel (Reference 7)

Core Thermal Power (% rated) 0 25 45 60 s 85 > 85 100 Application Group Kp, Operating Limit MCPR Multiplier Base Case 1.156 1.156 1.156 1.156 1.045 1.045 1.000 Base Case + TCVSC

+ RPTOOS + 1.244 1.244 1.178 1.164 1.077 1.045 1.000 PROOS Base Case + TCVSC

+ TBVOOS (all 5 1.244 1.244 1.178 1.164 1.077 1.045 1.000 valves)

Base Case + TCVSC

+ TBVOOS (all 5 1.244 1.244 1.178 1.164 1.077 1.069 1.000 valves) + RPTOOS +

PROOS Base Case with 1.156 1.156 1.156 1.156 1.045 1.045 1.000 TCVIS Base Case + TCVSC

+ TBVOOS (all 5 valves) + RPTOOS + 1.244 1.244 1.178 1.164 1.077 1.069 1.000 PRO OS with TCVIS Page 12 of 22

Table 4-4 DLO Flow Dependent MCPR Limits {MCPRF)

GNF2 Fuel (Reference 7)

Flow MCPRF

{%Rated) Limit 0.0 1.88 30.0 1.70 105.0 1.24*

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

Table 4-5 SLO Flow Dependent MCPR Limits (MCPRF)

GNF2 Fuel (Reference 7)

Flow MCPRF

(%Rated) 0.0 1.92 30.0 1.74 105.0 1.28 Table 4-6 Cycle Specific SLMCPR {MCPR99_9o;.)

(Reference 7)

Flow MCPR99.9%

DLO 1.10 SLO 1.13 Page 13 of 22

5. LHGR Technical Specification Sections 3.2.3 and 3.4.1 The LHGR limit is the product of the exposure dependent LHGR limit from Table 5-1 and the minimum of the power dependent LHGR Factor, LHGRFACp, or the flow dependent LHGR Factor, LHGRFACF.

as applicable. The LHGRFACP multiplier is determined from Table 5-2. The LHGRFACF multiplier is determined from Table 5-3 or Table 5-4. The SLO multipliers in Table 5-3 and Table 5-4 have been limited to a maximum value of 0.78, the SLO LHGR multiplier for GNF2 fuel.

Table 5-1 LHGR Limit GNF2 Fuel (References 5 and 8)

Peak Pellet Exposure I U02 LHGR Limit See Table B-1 of Reference 8 Peak Pellet I Gadollnia LHGR Exposure Limit See Table B-2 of Reference 8 Page 14 of 22

Table 5-2 Power Dependent LHGR Multipliers (LHGRFACP)

GNF2 Fuel DLO and SLO (Reference 7)

Core Thermal Power (% rated)

Application Group 0 25 45 60 85 100 LHGRFACp Multiplier Base Case 0.608 0.608 0.713 0.791 0.922 1.000 Base Case + TCVSC

+ RPTOOS + 0.608 0.608 0.703 0.761 0 .831 1.000 PRO OS Base Case + TCVSC

+ TBVOOS (all 5 0.608 0.608 0.713 0.791 0.922 1.000 valves)

Base Case + TCVSC

+ TBVOOS (all 5 0.608 0.608 0.703 0.761 0.822 1.000 valves) + RPTOOS +

PROOS Base Case with 0.608 0.608 0.713 0.791 0.922 1.000 TCVIS Base Case + TCVSC

+ TBVOOS (all 5 valves) + RPTOOS + 0.608 0.608 0.703 0.761 0.822 1.000 PROOS with TCVIS Page 15 of 22

Table 5-3 Flow-Dependent LHGR Multipliers (LHGRFACF)

GNF2 Fuel BOC to EOC, Pressurization (Application Groups with 1 TCV/TSV Closed or OOS)

(Reference 7)

Flow DLO LHGRFACF SLO LHGRFACF

(%Rated) 0.0 0.11 0.11 30.0 0.41 0.41 67.0 0.78 0.78 89.0 1.00 0.78 105.0 1.00 0.78 Table 5-4 Flow-Dependent LHGR Multipliers (LHGRFACF)

GNF2 Fuel BOC to EOC, No Pressurization (Application Groups with TCV/TSV In-Service)

(Reference 7)

Flow DLO LHGRFACF SLO LHGRFACF

(%Rated) 0.0 0.25 0.25 30.0 0.55 0.55 53.0 0.78 0.78 75.0 1.00 0.78 105.0 1.00 0.78 Page 16 of 22

COLR LaSalle 1 Rey 19

6. Rod Block Monitor Technical Specification Sections 3.3.2.1 and 3.4.1 The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below:

Table 6-1 Rod Block Monitor Setpoints (Reference 3)

Rod Block Monitor Upscale Trip Function Allowable Value Two Recirculation Loop o.66 wd + 54.0%

Operation Single Recirculation Loop o.66 wd + 48 .7%

Operation Wd - percent of recirculation loop drive flow required to produce a rated core flow of 108.5 Mlbm/hr.

The setpoint may be lower/higher and will still comply with the 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 17 of 22

7. Traversing In-Core Probe System (References 2, 4, and 12) 7.1. Description 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%. In addition, no more than 22 TIP channels can be OOS (failed or rejected).

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 18 of 22

COLR LaSalle 1 Rev 19

8. Stability Protection Setpoints Technical Specification Section 3.3.1.3 Table 8-1 OPRM PBDA Trip Setpolnts (Reference 7)

Corresponding Maximum PBDA Trip Amplitude Setpoint (Sp)

Confirmation Count Setpoint (Np) 1.15 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 19 of 22

COLR LaSalle 1 Rev 19

9. Modes of Operation The allowed modes of operation with combinations of equipment out-of-service are as described below (Reference 7).

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

Equipment Out of Service Options <1>c2> <3><4>cs> cs> Short Names Base Case BASE_DLO_ OPTB(A)

Base Case + SLO BASE_SLO_ OPTB(A)

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

Base Case + TCVSC + RPTOOS + PROOS + 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 +

EOOS3_DLO_ OPTB(A)

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

EOOS3_ SLO_ OPTB(A)

PROOS + SLO Base Case with TCVIS BASE_TCVIS_DLO_ OPTB(A)

Base Case + SLO with TCVIS BASE_TCVIS_SLO_OPTB(A)

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

EOOS3_TCVIS_DLO _ OPTB(A)

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

EOOS3_TCVIS_SLO_OPTB(A)

PROOS + SLO with TCVIS (1) Base case includes 1SRVOOS+1 TCV/TSV OOS + FWHOOS/FFWTR + 1MSIVOOS+2 TBVOOS + PLUOOS. The one TCV and/or TSV OOS conditions require power level s 85% of rated. The one MSIVOOS condition is also supported if thermal power is maintained s 75% of rated (Reference 7).

(2) The 2 TBVOOS in the Base Case are not credited for fast opening or opening on pressure control (Reference 6). The assumption is that two TBVs do not open on any signal and thus remain shut for the transients analyzed (i.e. 3 TBVs are credited to open in pressure control) (Reference 9).

(3) For Application Conditions involving 5 TBVOOS, the 5 TBVs are NOT credited for fast opening and 3 TBVs will not open on pressure control (Reference 6). 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.

(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.

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

Page 20 of 22

COLR LaSalle 1 Rey 19

10. Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1. GNF Report NEDE-24011-P-A-29 (Revision 29), "General Electric Standard Application for Reactor Fuel (GESTAR II)," October 2019 and the U.S. Supplement NEDE-24011-P-A-29-US, October 2019.

Page 21 of 22

COLR LaSalle 1 Rev 19

11. References
1. Exelon Generation Company, LLC Docket No. 50-373 LaSalle County Station, Unit 1, Facility Operating License No. NPF-11.
2. GNF Report 005N6665, "Exelon BWR Fleetwide Technical Evaluation of 50% TIP Strings Out-of-Service on Methods Uncertainties," March 2020.
3. Exelon 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 004N8325, Revision 0, "Fuel Bundle Information Report for LaSalle Unit 1 Reload 18 Cycle 19," December 2019.
6. Exelon Transmittal NF194844, Revision 0, "LaSalle Unit 1 Cycle 19 FRED Form," July 26, 2019.
7. GNF Report 004N8324, Revision 0, "Supplemental Reload Licensing Report for LaSalle Unit 1 Reload 18 Cycle 19," December 2019.
8. GNF Document No. NEDC-33270P Revision 9, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)", December 2017.
9. Exelon Transmittal ES1900014, Revision 0, "LaSalle Unit 1Cycle19 Completed OPL-3 Form,"

October 2, 2019.

10. GNF Letter ORF A12-00038-3, Vol. 4, "Scram Times versus Notch Position," May 22, 1992.
11. Deleted.
12. NRC Letter, "Issuance of Amendments (TAC Nos. M95156 and M95157)," October 29, 1996.

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