ML030990531

Cycle 10 Core Operating Limits Report (COLR)

ML030990531
Person / Time
Site:	LaSalle
Issue date:	03/28/2003
From:	Barnes G Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-88-016
Download: ML030990531 (25)

Text

Exekrn,.

Exelon Generation Company, LLC www exeloncorp coM N ucl e ar LaSalle County Station 2601 North 21' Road Marseilles, IL 61341-9757 March 28, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 2 Facility Operating License No. NPF-18 NRC Docket No. 50-374

Subject:

Unit 2 Cycle 10 Core Operating Limits Report (COLR)

The purpose of this letter is to advise you of Exelon Generation Company, LLC, review and approval of the LaSalle County Station Unit 2 Cycle 10 reload under the provisions of 10 CFR 50.59, "Changes, tests and experiments," and to transmit the Core Operating Limits Report (COLR) for Cycle 10. This report is being submitted consistent with Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications" and in accordance with LaSalle County Station Technical Specification 5.6.5.d.

The reload licensing analyses performed for Cycle 10 utilized NRC approved methodologies. The Unit 2 Cycle 10 core, which consists of NRC approved fuel designs developed by Framatome (formerly Siemens Power Corporation), was designed to operate within approved fuel design criteria provided in the Technical Specifications and related bases. The core operating characteristics are bounded by Updated Final Safety Analysis Report allowable limits.

LaSalle County Station has performed a detailed review of the relevant reload licensing documents and the associated bases and references.

Based on that review, the COLR was subjected to the 10 CFR 50.59 review process. The review process concluded that the reload does not require prior NRC review and approval.

Should you have any questions concerning this submittal, please contact Mr. Glen Kaegi, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, George P. Barnes Site Vice President LaSalle County Station Attachment AooJ cc:

Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - LaSalle County Station

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Section 1 Core Operating Limits Report for LaSalle Unit 2 Cycle 1 0

Technical Requirements Manual - Appendix J Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Issuance of Changes Summary LaSalle Unit 2 Cycle 10 il Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table of Contents References...........................................................

iv

1.

Average Planar Linear Heat Generation Rate (3.2.1).1-1 1.1 Technical Specification Reference.1-1 1.2 Description.

1-1

2.

Minimum Critical Power Ratio (3.2.2).2-1 2 1 Technical Specification Reference.2-1 2.2 Description.2-1

3.

Linear Heat Generation Rate (3.2.3).3-1 3.1 Technical Specification Reference.3-1 3 2 Description.3-1

4.

Control Rod Withdrawal Block Instrumentation (3.3.2.1).4-1 4 1 Technical Specification Reference.4-1 4.2 Description.4-1

5.

Traversing In-Core Probe System (3.2.1, 3.2.2, 3.2.3).5-1 5.1 Technical Specification Reference.5-1 5.2 Description.5-1 5 3 Bases.5-1

6.

Allowed Modes of Operation (B 3.2.2, B 3.2.3).6-1

7.

Methodology (5.6.5).7-1 LaSalle Unit 2 Cycle 10 iii Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report References

1.

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

2.

Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Concerning the Removal of Cycle-Specific Parameter Limits from Tech Specs, October 3, 1988.

3 EMF-2830 Revision 0, 'LaSalle Unit 2 Cycle 10 Reload Analysis," Framatome ANP, Inc, January 2003.

4.

Letter from A. Giancatarino to J. Nugent, OLaSalle Unit 1 and Unit 2 Rod Block Monitor COLR Setpoint Change," NFM.MW:01-0106, April 3, 2001.

5.

Letter from D. Garber to R. Chin, "POWERPLEX-Il CMSS Startup Testing", DEG:00.254, December 5, 2000.

6.

Letter from D. Garber to R. Chin "POWERPLEX-Il CMSS Startup Testing", DEG:00:256, December 6, 2000.

7.

Letter from J.H. Riddle to R. Chin 'TIP Symmetry Testing", JHR:97:021, January 20, 1997 and letter from D.Garber to R. Chin "TIP Symmetry Testing", DEG:99.085, March 23, 1999.

8.

EMF-2700 Revision 0, "LaSalle Unit 2 Cycle 10 Principal Transient Analysis Parameters," June 2002.

9.

"Transient Analysis Evaluation for LaSalle 3 TCV Operation at Power Uprate and MELLLA Conditions," NFM:BSA-00-025, R.W. Tsai to D. Bost, April 13, 2000.

10 Letter from A W. Will to F. W. Trikur, "Operation at LaSalle Units I and 2 with One MSIV Out of Service", AWW:03 005, January 15, 2003.

11.

'LaSalle Units 1 and 2 Operation with One TSV OOS - Update Nuclear Fuels Memo NF-MW.02-0431," NF-MW.03-007, Carlos de la Hoz to Kirk Peterman, January 9, 2003.

12.

LaSalle County Station Power Uprate Project, Task 201: Reactor Power/Flow Map, GE-NE-A1300384-07-01, Revision 1, September 1999.

13.

"Operation with a Pressure Regulator Out of Service at LaSalle," NF-MW:03-0063, Carlos de la Hoz to Kirk Peterman, February 7, 2003.

LaSalle Unit 2 Cycle 10 iv Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

1.

Average Planar Linear Heat Generation Rate (3.2.1) 1.1 Technical Specification Reference Section 3.2 1.

1.2 Descrintion Tables 1-1 and 1-2 are used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for each fuel type. Limits given in Tables I-1 and 1-2 are for Dual Reactor Recirculation Loop Operation.

For Single Reactor Recirculation Loop Operation (SLO), the MAPLHGR limits given in Tables 1-1 and 1-2 must be multiplied by a SLO MAPLHGR multiplier. The SLO MAPLHGR multiplier forATRIUM-10 and ATRIUM-9B fuel is 0.90 (Reference 3 Page 7-1).

Table 1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for ATRIUM-10 Fuel Al 0-4025B-1 5GV80-1 0GM Al 0-3982B-1 5GV80-1 0GM A10-1786B-OGV-100M (Bundle types 20, 21 and 22)

(Reference 3 Section 7 2.1)

Average Planar Exposure MAPLHGR (GWdIMT)

(kW/ft) 0.0 12.5 150 12.5 55 0 9.1 64.0 7.6 Table 1-2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for ATRIUM-9B Fuel A9-381 B-i3GZ7-80M A9-3843B-1 1 GZ6-80M A9-391 B-14G8.0-100M A9-41 GB-1 9G8.0-1 0GM A9-383B-1 6G8.0-1 0GM A9-396B-12GZ-100M (Bundle types 14, 15, 16, 17, 18 and 19)

(Reference 3 Section 7.2 1)

Planar Average Exposure MAPLHGR (GWd/MT)

(kW/ft) 0.0 13.5 20.0 135 64.3 9.07 LaSalle Unit 2 Cycle 10 1-1 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

2.

Minimum Critical Power Ratio (3.2.2) 2.1 Technical Specification Reference Section 3.2.2.

2.2 Description Limits provided in this section are only valid up to the first sequence exchange (deep-shallow swap) for the cycle, due to potential Control Blade History (CBH) impacts which were not determined as part of the original Cycle 10 licensing analyses. A revision to this document to account for any potential CBH impact will be issued at a future date, prior to the first sequence exchange for Cycle 10.

TIP Symmetry Chi-squared testing shall be performed prior to reaching a cycle exposure of 500 MWd/MT to validate the MCPR calculation.

2.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 2.2.1.1 or 2 2.1.2, whichever is greater at any given power and flow condition.

2 2.1.1 Power-Dependent MCPR The power-dependent MCPR value, MCPRp, is determined from Tables 2-1 through 24, and is dependent on fuel type and scram speed, in addition to power level Table 2-1 or 2-2 is applicable to ATRIUM-1 0 fuel and Table 2-3 or 24 is applicable to ATRIUM-9B fuel 2.2.1.2 Flow-Dependent MCPR The flow dependent MCPR value, MCPRF, is determined from Table 2-5 for all fuel types.

2.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control is not allowed because MCPR Limits are not provided.

2.2.3 Nominal Scram Speeds To utilize the MCPR limits for Nominal Scram Speeds (NSS), the core average scram speed insertion time must be equal to or less than the following values (Reference 8 Section 7.7).

Notch Position Time 1

45 0.380 39 0.680 25 1.680 05 2.680 LaSalle Unit 2 Cycle 10 2-1 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 2-1 MCPRp for ATRIUM-10 Fuel BOC - First Cycle-10 Sequence Exchange Nominal Scram Speeds (NSS)

(Reference 3 Table 5.1)

Core Thermal Power (% of rated)

EOOS Combination 0

25 25(25.01) 60 100 MCPRp Base Case Operation 2 70 2 20 1.98 1 45 1 40 Single Loop Operation (SLO) 2.71 2.21 1 99 1 46 1 41

• Values are interpolated between relevant power levels.

• For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power MCPRp should be applied.

• Allowable EOOS conditions are listed in Section 6.

LaSalle Unit 2 Cycle 10 2-2 Revision 0

Technical Requirements Manual - Appendix J L2CIO Core Operating Limits Report Table 2-2 MCPRp for ATRIUM-10 Fuel BOC - First Cycle-1 0 Sequence Exchange Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5 2)

Core Thermal Power (% of rated) 0 l

25 l 25(25.01) l 60 l

80 l

80(80.01) l 100 EOOS Combination MCPRp Base Case Operation 2.70 2 20 2 05 1 48 FHOOS Only 2.92 2 42 2 42 1 60 EOOS Case 1 2 92 2 42 2.42 1 60 EOOS Case 2 2 92 2 42 2.42 Single Loop Operation (SLO) 2 71 2.21 2 06 1 49 SLO with FHOOS Only 2 93 2 43 2 43 1 61 i

52 _

48A 1 43 1 53 1 49 SLO with EOOS Case I 2 93 2 43 2 43 SLO with EOOS Case 2 j 2.93 2.43 J 2 43 1.73

• Values are interpolated between relevant power levels.

• For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power MCPRp should be applied.

• Allowable EOOS conditions are listed in Section 6.

LaSalle Unit 2 Cycle 10 2-3 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 2-3 MCPRp for ATRIUM-9B Fuel BOC - First Cycle-10 Sequence Exchange Nominal Scram Speeds (NSS)

(Reference 3 Table 5 1)

Core Thermal Power (% of rated)

EOOS Combination 0

25 25(25.01) 60 100 MCPRp Base Case Operation 2 70 2 20 1 91 1 45 1 40 Single Loop Operation (SLO) 2.71 2 21 1.92 1.46 1 41

• Values are interpolated between relevant power levels.

• For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power MCPRp should be applied.

• Allowable EOOS conditions are listed in Section 6.

LaSalle Unit 2 Cycle 10 2-4 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 2-4 MCPRp for ATRIUM-9B Fuel BOC - First Cycle-10 Sequence Exchange Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5 2)

EOOS Combination Core Thermal Power (% of rated) 0 l

25 l 25(25.01) 60 80 l 80(80.01) l 100 MCPRp Base Case Operation 2 70 2 20 1 97 1 49 FHOOS Only 279 2 29 229 1 56 EOOS Case 1 2 79 2 29 2 29 1 58 EOOS Case 2 J

2.79 2 29 2 29 W

l l lR M

! l 1 40 E N E ~i~iE R 1 41 l

.lg~gllWS 1 41 Hufl 1

42_

1.76 1.58 1.50 Single Loop Operation (SLO) 2.71 2 21 1.98 1 50 SLO with FHOOS Only f 2.80 2 30 230 1 57 SLO with EOOS Case 1 2.80 2.30 2 30 1 59 SLO with EOOS Case 2 j

2.80 j

2.30 2 30

• Values are interpolated between relevant power levels.

For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power MCPRp should be applied.

e Allowable EOOS conditions are listed in Section 6.

LaSalle Unit 2 Cycle 10 2-5 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 2-5 MCPRF limits for All Fuel (Reference 3 Figure 5 1)

Flow (% of rated)

MCPRF 105 1.11 100 1.19 30 1.63 0

1.63

• Values are interpolated between relevant flow values.

• Values are applicable to all Operating Domains and EOOS conditions in Section 6.

• For thermal limit monitoring at greater than 105% rated core flow, utilize the MCPRF limit for 105% rated core flow.

LaSalle Unit 2 Cycle 10 2-6 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

3.

Linear Heat Generation Rate (3.2.3) 3.1 Technical Specification Reference Section 3.2.3.

3.2 Descrintion-Limits provided in this section are only valid up to the first sequence exchange (deep-shallow swap) for the cycle, due to potential Control Blade History (CBH) impacts which were not performed as part of the original Cycle 10 licensing analyses A revision to this document to account for any potential CBH impact will be issued at a future date, prior to the first sequence exchange for Cycle 10.

The LHGR Limit is the product of the LHGR Limit from Tables 3-1 or 3-2 and the minimum of either the power dependent LHGR Factor, LHGRFACp, or the flow dependent LHGR Factor, LHGRFACF. The applicable power dependent LHGR Factor (LHGRFACp) is determined from Table 3-3 or 3-4 for ATRIUM-1 0 fuel or Table 3-5 or 3-6 for ATRIUM-9B fuel. The applicable flow dependent LHGR Factor (LHGRFACF) is determined from Table 3-7 for all fuel types.

Table 3-1 Steady-State LHGR Limits for ATRIUM-10 Fuel Al 0-4025B-1 5GV80-1 OOM Al 0-3982B-1 5GV80-1 OOM A10-1 786B-OGV-1 00M (Bundle types 20, 21 and 22)

(Reference 3 Section 7.2 3)

Average Planar Exposure LHGR Limit (GWd/MT)

(kW/ft) 0.0 13.4 15.0 13 4 55.0 9.1 64.0 7.3 LaSalle Unit 2 Cycle 10 3-1 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 3-2 Steady-State LHGR Limits for ATRIUM-9B Fuel A9-381 B-1 3GZ7-80M A9-384B-1 1 GZ6-80M A9-391 B-14G8.0-1OOM A9-41 OB-1 9G8.0-1 OOM A9-383B-1 6G8.0-1 OOM A9-396B-1 2GZ-1 OOM (Bundle types 14, 15, 16, 17, 18 and 19)

(Reference 3 Section 7.2 3)

Average Planar Exposure LHGR Limit (GWd/MT)

(kW/ft) 0.0 14.4 15.0 14.4 64.3 7.9 LaSalle Unit 2 Cycle 10 3-2 Revision 0

Technical Requirements Manual - Appendix J L2CIO Core Operating Limits Report Table 3-3 LHGRFACp for ATRIUM-10 Fuel BOC - First Cycle-10 Sequence Exchange Nominal Scram Speeds (NSS)

(Reference 3 Table 5 1)

Core Thermal Power (% of rated)

EOOS Combination 0

l 25 i

60 l

100 LHGRFACp multiplier Base Case Operation 0 79 0 79 1.00 1.00 Single Loop Operation (SLO) 0 79 0 79 1.00 1 00

• Values are interpolated between relevant power levels.

• For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFACp multiplier should be applied.

• Allowable EOOS conditions are listed in Section 6.

LaSalle Unit 2 Cycle 10 3-3 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 3-4 LHGRFACpforATRIUM-10 Fuel BOC - First Cycle-1 0 Sequence Exchange Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5 2)

Core Thermal Power (% of rated)

EOOS Combination 0

1 25 1

60 l

80 80 (80.01) l 100 multiplier 4-Base Case Operation 0 78 0 78 FHOOS Only 0 65 0 65 0 95 EOOS Case 1 0 65 0 65 0.95 EOOS Case 2 0 65 0 65 Single Loop Operation (SLO) 0 78 0 78 1.00 SLO with FHOOS Only 0 65 0 65 0 95 1 00 1.00 1 00 0 95 1.00 1.00 1.00 0.95 SLO with EOOS Case 1 0 65 0.65 SLO with EOOS Case 2 0 65 [ 0.65

• Values are interpolated between relevant power levels.

• For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFACp multiplier should be applied.

• Allowable EOOS conditions are listed in Section 6 LaSalle Unit 2 Cycle 10 3-4 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 3-5 LHGRFACp for ATRIUM-9B Fuel BOC - First Cycle-10 Sequence Exchange Nominal Scram Speeds (NSS)

(Reference 3 Table 5 1)

Core Thermal Power (% of rated)

EOOS Combination 0

25 l

60 100 LHGRFACp multiplier Base Case Operation 0 79 0 79 1 00 1.00 Single Loop Operation (SLO) 0.79 0 79 1 00 1 00

• Values are interpolated between relevant power levels.

• For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFACp multiplier should be applied.

• Allowable EOOS conditions are listed in Section 6.

LaSalle Unit 2 Cycle 10 3-5 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 3-6 LHGRFACp for ATRIUM-9B Fuel BOC - First Cycle-10 Sequence Exchange Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5 2)

EOOS Combination Core Thermal Power (% of rated) 0 25 1

60 1

80 I 80 (80.01) F 100 LHGRFACp multiplier Base Case Operation 078 078 1 00 FHOOS Only 0 67 0 67 0 93 EOOS Case I 0 67 067 0.93 EOOS Case 2 l

0 67 l

0 67 0.79 1

0 86 1.00 1.00 1.00 0 90 1.00 1.00 1.00 0 90 Single Loop Operation (SLO) 0 78 078 1.00 SLO with FHOOS Only 067 0 67 l

0 93 SLO with EOOS Case 1 0 67 067 0 93 SLO with EOOS Case 2 l

0 67 l

0 67 079 1

086 I

• Values are interpolated between relevant power levels.

• For thermal limit monitoring at greater than 100% core thermal power, the power LHGRFACp multiplier should be applied a Allowable EOOS conditions are listed in Section 6.

100% core thermal LaSalle Unit 2 Cycle 10 3-6 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report Table 3-7 LHGRFACF multipliers for All Fuel (Reference 3 Figure 5 2)

Flow LHGRFACF

(% of rated)

Multiplier 105 1.00 60 1.00 30 0.85 0

0.85

• Values are interpolated between relevant flow values.

• For thermal limit monitoring above 105%

rated core flow, utilize the 105% rated core flow LHGRFACF multiplier.

• Values are applicable to all Operating Domains and EOOS conditions in Section 6.

LaSalle Unit 2 Cycle 10 3-7 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

4.

Control Rod Withdrawal Block Instrumentation (3.3.2.1) 4.1 Technical Specification Reference Table 3.3.2.1-1

4.2 Descrintion

The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 4):

ROD BLOCK MONITOR ALLOWABLE VALUE UPSCALE TRIP FUNCTIO ALWBEVLU Two Recirculation Loop 0.66 Wd + 54%

Operation Single Recirculation Loop 0.66 Wd + 48.7%

Operation__

The setpoint may be lower/higher and will still comply with the Rod Withdrawal Error (RWE) Analysis because RWE is analyzed unblocked.

The allowable value is clamped, with a maximum value not to exceed the allowable value for a recirculation loop flow (Wd) of 100%.

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

LaSalle Unit 2 Cycle 10 4-1 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

5.

Traversing In-Core Probe System (3.2.1, 3.2.2, 3.2.3) 5 1 Technical Specification

Reference:

Technical Specification Sections 3.2.1, 3.2.2, 3.2.3 for thermal limits require the TIP system for recalibration of the LPRM detectors and monitoring thermal limits.

5.2

==

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 of the SUBTIP methodology.

With one or more TIP measurement locations inoperable, the TIP data for an inoperable measurement location may be replaced by data obtained from a 3-dimensional BWR core monitoring software system adjusted using the previously calculated uncertainties, provided the following conditions are met.

1. All TIP traces have previously been obtained at least once in the current operating cycle when the reactor core was operating above 20% power, (References 5, 6 and 7) and

2. The total number of simulated channels (measurement locations) does not exceed 42% (18 channels).

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

5 3 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 Substitute TIP data, if needed, is 3-dimensional BWR core monitoring software calculated data which is adjusted based on axial and radial factors calculated from previous TIP sets.

Since the simulation and adjustment process could introduce uncertainty, a maximum of 18 channels may be simulated to ensure that the uncertainties assumed in the substitution process methodology remain valid.

LaSalle Unit 2 Cycle 10 5-1 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

6.

Allowed Modes of Operation (B 3.2.2, B 3.2.3)

The Allowed Modes of Operation with combinations of Equipment Out-of-Service are as described below:

--- OPERATING REGION- --

Equimen Outof ervie 3

POWERPLEX Equipment Out of Service ELLLA MELLLA ICF7 Coastdown3 Thermal Limit Options1" 0' 1 Set Number 4'2 Base Case Operation - NSS Yes Yes Yes No 1

Single Loop Operation (SLO) - NSS Yes No" N/A No 2

Base Case Operation -TSSS Yes Yes Yes No 3

FHOOS5 Only - TSSS No8 No8 Yes No 4

EOOS Case I - TSSS FHOOS orTBVOOS9 Yes Yes Yes No 5

Except FHOOS8 Except FHOOS8 EOOS Case 2 - TSSS Any combination of TCV slow Yes Yes Yes No 6

closure9 12, no RPT or FHOOS5 Except FHOOS8 Except FHOOS8 Single Loop Operation (SLO) - TSSS Yes No8 N/A No 7

SLO FHOOS5 Only - TSSS No8 No' N/A No 8

SLO with EOOS Case 1 - TSSS FHOOS5 or TBVOOS9 Yes No' N/A No 9

Except FHOOS8 SLO with EOOS Case 2 - TSSS Any combination of TCV slow Yes No" N/A No 10 closure9,12, no RPT or FHOOS5 Except FHOOS 8 One TCV Stuck Closed Yes Yes Yes No See Note 9 One TSVOOS 1 1 Yes Yes Yes No See Note 11 1 Each OOS Option may be combined with 1 SRVOOS, up to a 20 0F reduction in feedwater temperature (without feedwater heaters considered OOS), up to 2 TIP machines OOS (or the equivalent number of TIP channels, i.e, 42% of the total number of channels) with 100% available at startup, and/or up to 50% of the LPRMs OOS with an LPRM calibration frequency of 1250 Effective Full Power Hours (EFPH) (1000 EFPH +25%) (Reference 3 Tables 1.1 and 5.1 through 5.2) 2 In general, a more conservative thermal limit set that bounds the operating conditions can be used for thermal limit monitoring. However, using a more conservative thermal limit set will impose additional operating restrictions that are not required 3 Coastdown limits are not provided.

4 All EOOS scenarios and all limits provided are applicable from the beginning of the cycle (BOC) until the first Cycle-10 sequence exchange only. Applicable limits for operation beyond the first Cycle-10 sequence exchange will be transmitted in a later revision to this document.

LaSalle Unit 2 Cycle 10 6-1 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report 5 Feedwater heaters OOS (FHOOS) supports a reduction of up to 100OF in feedwater temperature.

FHOOS may be an intentionally entered mode of operation or an actual OOS condition.

6The SLO boundary was not moved up with the incorporation of MELLLA. (MELLLA FCL is - 114.8%.)

The power-flow boundary for SLO at power uprated conditions remains the ELLLA boundary for pre-uprate conditions (Reference 12). (ELLLA FCL is - 104.3%.)

7 ICF is analyzed up to 105% rated core flow.

8 If operating with FHOOS (alone or in combination with other EOOS), operation in the ELLLA or MELLLA region is supported by current transient analyses, but is administratively limited to less than 100% flow control line due to stability concerns.

9 Operation prior to coastdown is only allowed when less than 10.5 million Ibm/hr steam flow and when average position of 3 open TCVs is less than 50% open, with FCL <103%, and the MCFL setpoint >

120%. TCV Stuck Closed may be in combination with any EOOS except TBVOOS, TCV Slow Closure, or TSVOOS. If in combination with other EOOS(s), thermal limits may require adjustment for the other EOOS(s) as designated in Sections 1, 2, and 3 (Reference 9)

'° A single MSIV may be taken OOS (shut) under any and all OOS options as long as core thermal power is maintained

• 75% of 3489 MWt (Reference 10).

" A single TSV may be taken OOS (shut) and is bounded by operation with 1 TCV stuck closed.

Therefore, operation with 1 TSVOOS is subject to the restrictions given for 1 TCV stuck closed in Note 9. The combination of 1 TSVOOS and 1 TCV stuck closed is not allowed. (Reference 11) 12 For temporary operation with a pressure regulator out of service (PROOS), the TCV slow closure limits should be applied (Reference 13). The combination of PROOS and TCV slow closure is not allowed LaSalle Unit 2 Cycle 10 6-2 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

7.

Methodology (5.6.5)

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.

XN-NF-81-58 (P)(A), Revision 2 and Supplements I and 2, 'RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," March 1984.

2.

Letter from Ashok C. Thadini (NRC) to R.A. Copeland (SPC), "Acceptance for Referencing of ULTRAFLOW'm Spacer on 9x9-IX/X BWR Fuel Design," July 28, 1993 3

ANF-524 (P)(A) Revision 2 and Supplements I and 2, "ANF Critical Power Methodology for Boiling Water Reactors," November 1990

4.

XN-NF-80-19 (P)(A) Volume 1 Supplement 3, Supplement 3 Appendix F, and Supplement 4,

'Advanced Nuclear Fuels Methodology for Boiling Water Reactors:

Benchmark Results for CASMO-3G/MICROBURN-B Calculation Methodology," November 1990.

5 XN-NF-85-67 (P)(A) Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.

6.

ANF-913 (P)(A) Volume 1 Revision 1, and Volume 1 Supplements 2, 3, 4, "COTRANSA2. A Computer Program for Boiling Water Reactor Transient Analyses," August 1990.

7.

XN-NF-84-105 (P)(A), Volume 1 and Volume 1 Supplements 1 and 2; Volume 1 Supplement 4, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," February 1987 and June 1988, respectively.

8 ANF-89-014 (P)(A) Revision 1 and Supplements 1 & 2, "Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 - IX and 9x9 - 9X BWR Reload Fuel," October 1991.

9.

EMF-2209 (P)(A), Revision 1, "SPCB Critical Power Correlation," July 2000.

10.

ANF-89-98 (P)(A), Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," May 1995.

11.

ANF-91-048 (P)(A), "Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR ECCS Evaluation Model," January 1993.

12.

Commonwealth Edison Company Topical Report NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods," Revision 0 and Supplements on Neutronics Licensing Analysis (Supplement 1) and La Salle County Unit 2 benchmarking (Supplement 2), December 1991, March 1992, and May 1992, respectively.

13 EMF-85-74 (P)(A) Revision 0 and Supplement 1(P)(A) and Supplement 2(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.

14.

EMF-CC-074 (P) Volume 4 Revision 0, "BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, August 2000.

15.

ANF-1125 (P)(A) and ANF-1125(P)(A) Supplements 1 and 2, "ANFB Critical Power Correlation,"

Advanced Nuclear Fuels Corporation, April 1990.

16 ANF-1125 (P)(A) Supplement 1 Appendix E, "ANFB Critical Power Correlation Determination of ATRIUMT'-9B Additive Constant Uncertainties," September 1998.

LaSalle Unit 2 Cycle 10 7-1 Revision 0

Technical Requirements Manual - Appendix J L2C10 Core Operating Limits Report

17.

Commonwealth Edison Topical Report NFSR-0085 Revision 0, "Benchmark of BWR Nuclear Design Methods," November 1990 18 Commonwealth Edison Topical Report NFSR-0085 Supplement 1 Revision 0, 'Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan Comparisons," April 1991.

19.

Commonwealth Edison Topical Report NFSR-0085 Supplement 2 Revision 0, "Benchmark of BWR Nuclear Design Methods - Neutronic Licensing Analyses," April 1991.

20 ANF-CC-33 (P)(A) Supplement 1 Revision 1 and Supplement 2, "HUXY: A Generalized Multirod Heatup Code with 10CFR50, Appendix K Heatup Option," August 1986 and January 1991, respectively.

21.

XN-NF-80-19 (P)(A) Volume 4 Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," June 1986.

22.

XN-NF-80-19 (P)(A) Volume 3 Revision 2, "Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," January 1987.

23.

ANF-91-048 (P)(A) Supplement 1 and Supplement 2, "BWR Jet Pump Model Revision for RELAX," October 1997.

24.

XN-NF-80-19 (P)(A) Volumes 2, 2A, 2B, and 2C, "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," September 1982.

25.

XN-NF-80-19 (P)(A) Volume I and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis," March 1983.

26.

EMF-2158(P)(A) Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors-Evaluation and Validation of CASMO-4/MICROBURN-B2," Siemens Power Corporation, October 1999.

LaSalle Unit 2 Cycle 10 7-2 Revision 0