Text

Cycle 17 Core Operating Limits Report (COLR)
	ML16070A129
Person / Time
Site:	LaSalle
Issue date:	03/10/2016
From:	Trafton W; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RA16-011
	Download: ML16070A129 (22)
	v • d • e

LaSalle County Station 2601 North 21 Road Marseilles, Illinois 61341 Exeton Generation RA16-011 10 CFR 50.4 March 10, 2016 U. S. Nuclear Regulatory Commission AHN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Unit 1 Facility Operating License No. NPF-1 1 NRC Docket No. 50-373

Subject:

Unit 1 Cycle 17 Core Operating Limits Report (COLR)

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 COLR for Unit 1.

This report was revised for LSCS Unit 1, Cycle 17.

Exelon Generation Company, LLC makes no new or revised regulatory commitments in this letter.

Should you have any questions concerning this letter, please contact Mr. Guy V. Ford, Jr.,

Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, William J. Trafton Site Vice President LaSalle County Station

Attachment:

Core Operating Limits Report for LaSalle Unit 1 Cycle 17, Revision 0 cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector LaSalle County Station

COLR LaSalle 1 Revision 16 Core Operating Limits Report for LaSalle Unit I Cycle 17 Revision 0 LaSalle Unit 1 Cycle 17 Page 1 of 21

COLR LaSalle 1 Revision 16 Table of Contents Page Revision History 3 List of Tables 4

1. References 5

2. Terms and Definitions 6

3. General Information 7

4. Average Planar Linear Heat Generation Rate 8

5. Operating Limit Minimum Critical Power Ratio 9 5.1. Manual Flow Control MCPR Limits 9 5.1.1. Power-Dependent MCPR 9 5.1.2. Flow-Dependent MCPR 9 5.2. Scram Time 10 5.3. Recirculation Flow Control Valve Settings 10

6. Linear Heat Generation Rate 14

7. Rod Block Monitor 17

8. Traversing In-Core Probe System 18 8.1. Description 18 8.2. Bases 18

9. Stability Protection Setpoints 19

10. Modes of Operation 20

11. Methodology 21 LaSalle Unit 1 Cycle 17 Page 2 of 21

COLR LaSalle I Revision 16 Revision History Record of COLR LaSalle I Cycle 17 Revisions Revision Description 16 Initial issuance for Li Cl 7.

LaSalle Unit 1 Cycle 17 Page 3 of 21

COLR LaSalle 1 Revision 16 List of Tables Table 3-1 Cycle Exposure Range Definitions 7 Table 4-1 MAPLHGR for GNF2 Fuel 8 Table 4-2 MAPLHGR SLO Multiplier for GNF2 Fuel, BOC to EOC 8 Table 5-1 Scram Times Required for Option A and Option B Application at Notch Position 39 10 Table 5-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for GNF2 Fuel 11 Table 5-3 Power-Dependent MCPR Multipliers (Kp) for GNF2 Fuel, DLO and SLO, SOC to EOC, Option A and Option B 12 Table 5-4 DLO Flow-Dependent MCPR Limits (MCPRF) for GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B 13 Table 5-5 SLO Flow-Dependent MCPR Limits (MCPRF) for GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B 13 Table 6-1 LHGR Limit for GNF2 Fuel 14 Table 6-2 Power-Dependent LHGR Multipliers (LHGRFACp) for GNF2 Fuel, DLO and SLO, SOC to EOC 15 Table 6-3 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2 Fuel, BOC to EOC, Pressurization (1 TCVITSV Closed or 005), All Application Groups 16 Table 6-4 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2 Fuel, SOC to EOC, No Pressurization (All TCVITSV In-Service), All Application Groups 16 Table 7-1 Rod Block Monitor Setpoints 17 Table 9-1 OPRM PBDA Trip Setpoints 19 Table 10-1 Allowed Modes of Operation and EOOS Combinations 20 LaSalle Unit 1 Cycle 17 Page 4 of 21

COLR LaSalle 1 Revision 16

1. References

1. Exelon Generation Company, LLC Docket No. 50-373 LaSalle County Station, Unit 1, Facility Operating License No. NPF-11.

2. NRC Generic Letter 88-16, from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Removal of Cycle-Specific Parameter Limits from Technical Specifications, October 3, 1988.

3. Exelon Nuclear Fuels Letter NFM:MW:01 -01 06, from A. Giancatarino to J. Nugent, LaSalle Unit I 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. GE Nuclear Energy Document GE-NE-Al 300384-07-01, Revision 1, LaSalle County Station Power Uprate Project Task 201: Reactor Power/Flow Map, September 1999.

6. GE Hitachi Nuclear Energy Report, GE-NE-0000-0099-8344-R1, Revision 1, Exelon Nuclear LaSalle Units 1 and 2 Thermal Power Optimization Task T0201: Operating Power/Flow Map, November 2009.

7. GNF Report 001 N4873, Revision 0, Supplemental Reload Licensing Report for LaSalle Unit 1 Reload 16 Cycle 17, January 2016.

8. GNF Letter MFN 13-029, from B. R. Moore to Document Control Desk, GNF2 Advantage Generic Compliance with NEDE-2401 1-P-A (GESTAR II), NEDC-33270P, Revision 5, May 2013, May 24, 2013.

(ADAMS Accession No. ML13148A318)

9. Exelon Transmittal ES1500023, Revision 0, LaSalle 1 Cycle 17 Final Resolved OPL-3 Parameters, September 17, 2015.

10. GNF Letter DRF A12-00038-3, Vol. 4, from G.A. Watford to Distribution, Scram Times versus Notch Position, May 22, 1992.

11. GEH Nuclear Energy DRF Section 0000-0151-0765, Revision 0, Application of SLO SLMCPR, February 12, 2013.

12. NRC Letter from D. M. Skayto I. M. Johnson, Issuance of Amendments (TAC NOS. M95156 and M95157), October 29, 1996.

LaSalle Unit 1 Cycle 17 Page 5 of 21

COLR LaSalle 1 Revision 16

2. Terms and Definitions ARTS Average Power Range Monitor, Rod Block Monitor and Technical Specification Improvement Program BOC Beginning of cycle BWR Boiling water reactor COLR Core operating limits report CRD Control rod drive mechanism DLO Dual loop operation ELLLA Extended load line limit analysis EOC End of cycle EOOS Equipment out of service EOR17 End of rated operation for Cycle 17 FFWTR Final feedwater temperature reduction FWHOOS Feedwater heater out of service GNF Global Nuclear Fuels Americas ICE Increased core flow Power-dependent MCPR Multiplier L1C17 LaSaIle Unit 1 Cycle 17 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 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 OCS Out of service OPRM Oscillation power range monitor PBDA Period based detection algorithm PLUCOS Power load unbalance out of service PROOS Pressure regulator out of service RPTOOS Recfrculation 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 TCVIS All Turbine Control Valves/Turbine Stop Valves in-service TCVSC Turbine control valve slow closure TIP Traversing in-core probe TIPOOS Traversing in-core probe out of service TSV Turbine stop valve 3DM 3D Monicore LaSalle Unit 1 Cycle 17 Page 6 of2l

COLR LaSalle 1 Revision 16

3. General Information Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values.

Rated core flow is 108.5 Mlbm/hr. Operation up to 105% rated flow is licensed for this cycle. Licensed rated thermal power is 3546 MWth.

For thermal limit monitoring above 100% rated power or 100% rated core flow, the 100% rated power and the 100% core flow values, respectively, can be used unless otherwise indicated in the applicable table.

Table 3-1 defines the three exposure ranges used in the COLR. The end of rated (EOR) exposure is defined as the cycle exposure corresponding to all rods out, 100% power/i 00% flow, and normal feedwater temperature.

The term (EDR 2211 MWU/ST) means the EOR exposure minus 2211 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 EOR1 7 2211 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 MDC to EOC limits should be used. This can be achieved by applying the MDC 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 3-1 Cycle Exposure Range Definitions (Reference 7)

Nomenclature Cycle Exposure Range BOC to MDC BOC17 to fEORI7 2211 MWd/ST)

MDC to EOC (EOR17 2211 MWU/ST) to EOC17 SOC to EOC 60C17 to EOC17 LaSalle Unit 1 Cycle 17 Page 7 of 21

COLR LaSalle 1 Revision 16

4. Average Panar Linear Heat Generation Rate Technical Specification Sections 3.2.1 and 3.4.1 MAPLHGR values as a function of average planar exposure are given in Table 4-1. During SLO, these limits are multiplied by the SLO multiplier listed in Table 4-2. The MAPLHGR values in Table 4-1 along with the MAPLHGR SLO multiplier in Table 4-2 provide coverage for all modes of operation.

Table 4-1 MAPLHGR for GNF2 Fuel (Reference 7)

Avg. Planar MAPLHGR Exposure (kW/FT)

(GWd/ST) 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 Table 4-2 MAPLHGR SLO Multiplier for GNF2 Fuel, BOC to EOC (Reference 7)

SLO Fuel Type MAPLHGR Multiplier GNF2 0.78 LaSalle Unit 1 Cycle 17 Page 8 of 21

COLR LaSalle 1 Revision 16

5. Operating Limit Minimum Critical Power Ratio Technical Specification Sections 3.2.2, 3.3.4.1, 3.4.1, and 3.7.7 5.1. Manual Flow Control MCPR Limits The rated OLMCPRs given in Table 5-2 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 5-2 is used in conjunction with the ARTS-based power (Kp) and flow (MCPRF) dependencies presented in Tables 5-3, 5-4, and 5-5 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.

5.1.1. Power-Dependent MCPR The power-dependent MCPR multiplier, K, is determined from Table 5-3, and is dependent only on the power level and the Application Group (EOOS). The product of the rated OLMCPR and the proper K provides the power-dependent OLMCPR.

5.1.2. Flow-Dependent MCPR Tables 5-4 through 5-5 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.

LaSalle Unit 1 Cycle 17 Page 9 of 21

COLR LaSalle 1 Revision 16 5.2 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. The core average scram speed insertion time for 20% insertion must be less than or equal to the Technical Specification scram speed insertion time to utilize the Option A MCPR limits. Reload analyses performed by GNF for Cycle 17 Option A MCPR limits utilized a 20% core average insertion time of 0.900 seconds (Reference 9).

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 5-1 for a summary of scram time requirements related to the use of Option A and Option B MCPR limits.

lithe 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 5-1 Scram Times Required for Option A and Option B Application at Notch Position 39 (References 9 and 10)

Notch Scram Time Required for Option A Scram Time Required for Option B Position* Application Application 39 0.875 sec. 0.672 sec.

The insertion time to a notch position is conservatively calculated using the CRD reed switch drop-out time per Reference 10.

5.3. Recirculation Flow Control Valve Settings Cycle 17 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.

LaSalle Unit 1 Cycle 17 Page 10 of 21

COLR LaSalle 1 Revision 16 Table 5-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for GNF2 Fuel (Reference 7)

Application Group DLO/ SLO Exposure Range Option A Option B BOC-MOC 1.42 1.38 Base Case DLO MOC-EOC 1.43 1.39 BOC-MOC 1.59 1.59 Base Case SLO MOC-EOC 1.59 1.59 BOC-MOC 1.47 1.39 Base Case + TCVSC DLO

+ RPTOOS + PROOS 1.45 MOC-EOC 1.53 BOC-MOC 1.59 1.59 Base Case + TCVSC SLO

+ RPTOOS + PRODS 1.59 MOC-EOC 1.59 BOC-MOC 1.45 1.41 Base Case + TCVSC + OLD TBVOOS (all 5 valves) 1.46 1.42 MOC-EOC BOC-MOC 1.59 1.59 Base Case + TCVSC + SLO TBVOOS (all 5 valves) 1.59 1.59 MOC-EOC Base Case + TCVSC ÷ BOC-MOC 1.50 1.42 TBVOOS (all 5 valves) DLO

+ RPTOOS + PRODS MOC-EOC 1.56 1.48 Base Case + TCVSC -I- BOC-MOC 1.59 1.59 TBVDOS (all 5 valves) SLO

+RPTOQS+PROOS MOC-EOC 1.59 1.59 BOC-MOC 1.42 1.38 Base Case with TCVIS DLO MOC-EOC 1.43 1.39 BOC-MOC 1.59 1.59 Base Case with TCVIS SLO MOC-EOC 1.59 1.59 Base Case + TCVSC + 1.50 1.42 BOC-MOC TBVOOS (all 5 valves)

+ RPTOOS + PRODS DLO with TCVIS MOC-EOC 1.56 1.48 Base Case + TCVSC + BOC-MOC 1.59 1.59 TBVOOS (all 5 valves) SLO

÷ RPTOOS ÷ PRODS 1.59 MOC-EOC 1.59 with TCVIS LaSalle Unit 1 Cycle 17 Page 11 of 21

COLR LaSalle 1 Revision 16 Table 5-3 Power-Dependent MCPR Multipliers (Kp) for GNF2 Fuel, DLO and SLO, SOC to EOC, Option A and Option B (Reference 7)

K1,, MCPR Limit Multiplier (as a function of 3/4 rated power)

Application Group 0% P 25% P 45% P 60% P 85% P 85.01%P 100% P Base Case 1.156 1.156 1.156 1.156 1.045 1.045 1.000 Base Case + TCVSC + 1.244 1.244 1.178 1.164 1.077 1.045 1.000 RPTOOS + PROOS Base Case + TCVSC + 1.244 1.244 1.178 1.164 1.077 1.045 1.000 TBVOOS (all 5 valves)

Base Case + TCVSC +

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

+ RPTOOS + PROOS BaseCasewithTCVlS 1.156 1.156 1.156 1.156 1.045 1.045 1.000 Base Case + TCVSC +

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

+ RPTOOS + PROOS with TCVIS LaSalle Unit 1 Cycle 17 Page 12 of2l

COLR LaSalle 1 Revision 16 Table 54 DLO Flow-Dependent MCPR Limits (MCPRF) for GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B (Reference 7)

Flow MCPRF

(% Rated) 0.0 1.88 30.0 1.70 105.0 1.24 Table 5-5 SLO Flow-Dependent MCPR Limits (MCPRF) for GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B (References 7 and 11)

Flow IvICPRF

(% Rated) 0.0 1.90 30.0 1.72 105.0 1.26 LaSalle Unit 1 Cycle 17 Page 130121

COLR LaSalle 1 Revision 16

6. Linear Heat Generation Rate Technical Specification Sections 3.2.3 and 3.4.1 The LHGR limit is the product of the exposure dependent LHGR limit from Table 6-1 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 6-2. The LHGRFACF multiplier is determined from Table 6-3 or Table 6-4. The SLO multipliers in Table 6-3 and Table 6-4 have been limited to a maximum value of 0.78, the SLO LHGR multiplier for GNF2 fuel.

Table 6-1 LHGR Limit for GNF2 Fuel (Reference 8)

Peak Pellet Exposure I U02 LHGR Limit See Table B-i of Reference 8 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit See Table B-2 of Reference 8 LaSalle Unit 1 Cycle 17 Page 14 of 21

COLR LaSalle 1 Revision 16 Table 6-2 Power-Dependent LHGR Multipliers (LHGRFACp) for GNF2 Fuel, DLO and SLO, BOC to EOC (Reference 7)

LHGRFACP (as a function of 3/4 rated power)

Application Group 0% P 25% P 45% P 60% P 85% P 100% P Base Case 0.608 0.608 0.713 0.791 0.922 1.000 Base Case + TCVSC + 0.703 0.761 0.831 1.000 0.608 0.608 RPTOOS + PROOS Base Case + TCVSC + 0.608 0.608 0.713 0.791 0.922 1.000 TBVOOS (all 5 valves)

Base Case + TCVSC +

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

+ RPTOOS + PROOS BaseCasewithTCVlS 0.608 0.608 0.713 0.791 0.922 1.000 Base Case + TCVSC +

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

+ RPTOOS + PROOS with TCVIS LaSalle Unit 1 Cycle 17 Page 15 of 21

COLR LaSalle 1 Revision 16 Table 6-3 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2 Fuel, BOG to EOC, Pressurization (1 TCVITSV Closed or OOS), All Application Groups (Reference 7)

Flow DLO LHGRFACF SLO LHGRFACF

(% Rated) 0.0 0.110 0.110 30.0 0.410 0.410 67.0 0.78 0.78 89.0 1.000 0.78 105.0 1.000 0.78 Table 6-4 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2 Fuel, BOC to EOC, No Pressurization (All TCV/TSV In-Service), All Application Groups (Reference 7)

Flow DLO LHGRFACF SLO LHGRFACF

(% Rated) 0.0 0.250 0.250 30.0 0.550 0.550 53.0 0.78 0.78 75.0 1.000 0.78 105.0 1.000 0.78 LaSalle Unit 1 Cycle 17 Page 16 of 21

COLR LaSalle 1 Revision 16

7. 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 (Reference 3):

Table 7-f 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 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 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%.

LaSalle Unit 1 Cycle 17 Page 17 of 21

COLR LaSalle 1 Revision 16

8. Traversing In-Core Probe System (Reference 12) 8.1. Description When the traversing in-core probe (TIP) system (for the required measurement locations) is used for with recalibration of the LPRM detectors and monitoring thermal limits, the TIP system shall be operable 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 (Reference 4):

14 The total number of failed and/or bypassed LPRMs does not exceed 25%. In addition, no more than 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.

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

LaSalle Unit 1 Cycle 17 Page 18 of 21

COLR LaSalle 1 Revision 16

9. Stability Protection Setpoints Technical Specification Section 3.3.1.3 Table 9-i OPRM PBDA Trip Setpoints (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.

LaSalle Unit 1 Cycle 17 Page 190121

COLR LaSalle 1 Revision 16 JO. Modes of Operation The allowed modes of operation with combinations of equipment out-of-service are as described below (Reference 7).

Table 10-1 Allowed Modes of Operation and EOOS Combinations (Reference 7)

(1) (2) (3) (4)

Equipment Out of Service Options Short Name Base Case (Option A or B) Base Base Case + SLO (Option A or B) Base SLO Base Case + TCVSC + RPTOOS + PROOS (Option A or B) Combined EOOS 1 Base Case + TCVSC + RPTOOS + PROOS + SLO (Option A or B) Combined BOOS 1 SLO Base Case + TCVSC -i- TBVOOS (all 5 valves) (Option A or B) Combined BOOS 2 Base Case ÷ TCVSC + TBVOOS (all 5 valves) + SLO (Option A or B) Combined BOOS 2 SLO Base Case + TCVSC + TBVOOS (all 5 valves) + RPTOOS ÷ PROOS Combined EOOS 3 (Option A or B)

Base Case + TCVSC + TBVOOS (all 5 valves) + RPTOOS + PROOS + SLO Combined EOOS 3 SLO (Option A or B)

Base Case with TCVIS (Option A or B) Base TCVIS Base Case + SLO with TCVIS (Option A or B) Base SLO TCVIS Base Case + TCVSC + TEVOOS (aN 5 valves) + RPTOOS + PROOS with Combined EOOS 3 TCVIS (Option A or B) TCVIS Base Case + TCVSC + TBVOOS (all 5 valves) + RPTOOS + PRODS + SLO Combined BOOS 3 SLO with TCVIS (Option A or B) TCVIS (1) Base case includes 1 SRVOOS + 1 TCVITSV 005 + FWHOOS/FFWTR + 1 MSIVOOS + 2 TBVOOS + PLUOOS, and also includes 1 TIPOOS (up to 14 TIP channels not available) any time during the cycle, including BOC, and upto 25% of the LPRMs out-of-service (failed or rejected) (Reference 4). The one Stuck Closed TCV and/or TSV EOOS conditions require power level 85% ot rated. The one MSIVOOS condition is also supported as long as thermal power is maintained 75% of the rated (Reference 7). The FWHOOS/FFWTR analyses cover a maximum reduction of 100°F for the feedwater temperature.

A nominal LPRM calibration interval of 2000 EFPH (2500 EFPH maximum) is supported for LICJ7.

(2) TBVOOS (all 5 valves) is the turbine bypass system out of service which means that 5 TBV5 are !i2 credited for fast opening and 3 TBVs are j credited to open in pressure control. For the 2 TBVOOS condition that is a part of the base case, the assumption is that both of the TBV5 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). The MCFL is currently set at 126.6 (Reference 9) and will only allow opening of TBVs #1, #2, #3, and #4 during a slow pressurization event. The MCFL does not use the TBV position feedback signal to know how many TBVs have opened or how far each has opened. The #5 TBV is not available based on the current MCFL setpoint and thus cannot be used as one of the credited valves to open in pressure control.

(3) The ÷ sign that is used in the Equipment Out of Service Option / Application Group descriptions designates an and/or.

(4) All EOOS Options (Reference 7 Application Groups) are applicable to ELLLA, MELLLA, ICE and Coastdown realms of operation with the exception that SLO is not applicable to MELLLA or CF (References 5 and 6). The MOC to EOC exposure range limit sets are generated by GNF to include application to coastdown operation (Methodology Reference 1).

LaSalle Unit 1 Cycle 17 Page 20 of 21

COLR LaSalle 1 Revision 16

11. 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-22 (Revision 22), General Electric Standard Application for Reactor Fuel, November 2015 and the U.S. Supplement NEDE-2401 1-P-A-22-US, November 2015.

2. BWR Owners Group Report NEDO-32465-A (Revision 0), BWR Owners Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications, August 1996.

LaSalle Unit 1 Cycle 17 Page 21 of 21