Text

LaSalle County, Unit 1 - Cycle 10 Reload and Core Operating Limits Report
	ML020600456
Person / Time
Site:	LaSalle
Issue date:	02/06/2002
From:	Barnes G P; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	-RFPFR, GL-88-016
	Download: ML020600456 (244)
	v • d • e

Exelon,.

Exelon Generation Company, LLC www.exeloncorp.com Nuclear LaSalle County Station 2601 North 21'Road Marseilles, IL 61341-9757 February 6, 2002 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 1 Facility Operating License No. NPF-1 1 NRC Docket No. 50-373

Subject:

LaSalle County Station Unit 1 Cycle 10 Reload and Core Operating Limits Report LaSalle County Station Unit 1, which has completed its ninth cycle of operation, is currently in the process for startup of Cycle 10. The purpose of this letter is to advise you of Exelon Company's review and approval of the 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 the upcoming cycle consistent with Generic Letter 88-16, "Removal of Cycle Specific Parameter Limits From Technical Specifications." This report is being submitted 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 1 Cycle 10 core, which consists of NRC approved fuel designs developed by Framatone (formally Siemens Power Corporation (SPC)) and General Electric Company (GE), 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 (UFSAR) allowable limits. Exelon has performed a detailed review of the relevant reload licensing documents and the associated bases and references.

Based on that review, an evaluation was prepared as required by 10 CFR 50.59. This evaluation concluded that the reload does not require NRC review and approval.

A oD)

February 6, 2002 U.S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. William Riffer, Regulatory Assurance Manager, at (815) 415-2800.

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

-NRC Region III NRC Senior Resident Inspector

-LaSalle County Station Technical Requirements Manual Appendix I (Amendment

47) LaSalle Unit 1 Cycle 10 Core Operating Limits Report and Reload Transient Analyses Results Revision 0 Technical Requirements Manual- Appendix I LICIO Core Operating Limits Report Section 1 Core Operating Limits Report for LaSalle Unit 1 Cycle 10 Technical Requirements Manual -Appendix I Technical Requirements Manual -Appendix I LlCl0 Core Operating Limits Report Issuance of Changes Summary LaSalle Unit 1 Cycle 10 ii Revision 0 Technical Requirements Manual -Appendix I Li C10 Core Operating Limits Report Table of Contents R e fe re n c e s ...... .........................................................

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iv 1. Average Planar Linear Heat Generation Rate (3.2.1) ..........................................

1-1 1.1 Technical Specification Reference

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1-1 1 .2 D e s c riptio n .......................................

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1-1 2. Minim um Critical Power Ratio (3.2.2) ..................................................................

2-1 2.1 Technical Specification Reference

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2-1 2 .2 D e sc riptio n .......................................

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2 -1 3. Linear Heat Generation Rate (3.2.3) ....................................................................

3-1 3.1 Technical Specification Reference

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3-1 3 .2 D e s c riptio n .......................................

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3 -1 4. Control Rod W ithdrawal Block Instrumentation (3.3.2.1)

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4-1 4.1 Technical Specification Reference

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4-1 4 .2 D e sc riptio n .................................................................................................

4 -1 5. Traversing In-Core Probe System (3.2.1, 3.2.2, 3.2.3) ........................................

5-1 5.1 Technical Specification Reference

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5-1 5 .2 D e s c riptio n .................................................................................................

5-1 5 .3 B a s e s ...............................................

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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 1 Cycle 10 iii Revision 0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report References

1. Exelon Generation Company, LLC Docket No. 50-373 LaSalle County Station, Unit 1, License No. NPF-11. 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-2690 Revision 0, "LaSalle Unit 1 Cycle 10 Reload Analysis," Framatome ANP, Inc., January 2002. 4. EMF-2563 (P) Revision 1, "Fuel Mechanical Design Report Exposure Extension for ATRIUM-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units," August 2001. 5. J11-03692-LHGR Revision 1, "ComEd GE9/GE10 LHGR Improvement Program," [NDIT NFM0000067 Sequence 00], February 2000. 6. Letter from A. Giancatarino to J. Nugent, "LaSalle Unit 1 and Unit 2 Rod Block Monitor COLR Setpoint Change," NFM:MW:01-0106, April 3, 2001. 7. Letter from D. Garber to R. Chin, "POWERPLEX-II CMSS Startup Testing", DEG:00:254, December 5, 2000. 8. Letter from D. Garber to R. Chin "POWERPLEX-Il CMSS Startup Testing", DEG:00:256, December 6, 2000. 9. 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. 10. NEDC-31531 P and Supplement 1, "ARTS Improvement Program Analysis for LaSalle Units 1 and 2," December 1993 and June 1998, respectively.

11. EMF-2533 Revision 0, "LaSalle Unit 1 Cycle 10 Principal Transient Analysis Parameters," April 2001. 12. 24A5180AA Revision 0, "Lattice-Dependent MAPLHGR Report for LaSalle County Station Unit 1 Reload 7 Cycle 8," December 1995. 13. NFM Calculation No. BSA-L-99-07, "LaSalle GE9 MAPFACf Thermal Limit Multiplier for 105% Maximum Core Flow," October 1999. 14. GE-NE-187-13-0792 Revision 2, "Evaluation of a Postulated Slow Turbine Control Valve Closure Event For LaSalle County Station Units 1 and 2," NDIT NFM-98-00146 Sequence 00, July 1998. 15. Letter from R. Jacobs to R. Tsai, NFM:BSA:99-087, "Review of L1C9 Transient Analysis Results for Compliance with the Fuel Mechanical Limits for GE9 Fuel," September 21, 1999.LaSalle Unit 1 Cycle 10 iv Revision 0 Technical Requirements Manual -Appendix I LIC10 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

Description:

Tables 1-1 through 1-4 are used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for each fuel type. Limits given in Tables 1-1 through 1-4 are for Dual Reactor Recirculation Loop Operation.

For Single Reactor Recirculation Loop Operation (SLO), the MAPLHGR limits given in Tables 1-1 through 1-4 must be multiplied by a SLO MAPLHGR multiplier.

The SLO MAPLHGR multiplier for ATRIUM-10 and ATRIUM-9B fuel is 0.90 (Reference 3 Page 7-1). The SLO MAPLHGR multipliers for GE9B fuel are shown in Table 1-5 (MAPFACp) and Table 1-6 (MAPFACF).

The SLO MAPLHGR limit for the GE9B fuel is the product of the MAPLHGR limit from Table 1-3 or 1-4 and the minimum of either the SLO MAPFACp or SLO MAPFACF as found in Tables 1-5 and 1-6, respectively.

Table 1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for ATRIUM-10 Fuel Al 0-4039B-1 5GV75-1 00M Al 0-4037B-1 6GV75-1 00M (Bundle types 10 and 11) (Reference 3 Section 7.2.1)Maximum Planar Average Exposure MAPLHGR (GWd/MT) (kWIft) 0.0 12.5 15.0 12.5 55.0 9.1 64.0 7.6 Table 1-2 Average Planar Linear Heat Generation Rate (MAPLHGR) for ATRIUM-9B Fuel SPCA9-393B-1 6GZ-1 OM SPCA9-396B-1 2GZB-1 OOM SPCA9-384B-1 1 GZ-80M SPCA9-396B-1 2GZC-1 OM (Bundle types 6, 7, 8 and 9) (Reference 3 Section 7.2.1)Planar Average Exposure MAPLHGR (GWd/MT) (kWlft) 0.0 13.5 20.0 13.5 64.3 9.07 LaSalle Unit 1 Cycle 10 1-1 Revision 0 Technical Requirements Manual -Appendix I LIC10 Core Operating Limits Report Table 1-3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE9B Fuel GE9B-P8CWB342-1 OGZ-80M-1 50 (Bundle 3867, bundle type 5) (References 5 and 12) Planar Average Exposure Lattice Specific MAPLHGR limit (kWIft) (GWd/ST) 0 12.66 12.04 12.25 11.72 12.09 12.66 0.200 12.59 12.08 12.28 11.77 12.12 12.59 1.000 12.40 12.16 12.35 11.87 12.22 12.40 2.000 12.34 12.28 12.45 12.00 12.37 12.34 3.000 12.34 12.42 12.55 12.13 12.53 12.34 4.000 12.37 12.57 12.65 12.27 12.70 12.37 5.000 12.40 12.73 12.76 12.41 12.88 12.40 6.000 12.43 12.89 12.87 12.56 13.07 12.43 7.000 12.46 13.06 12.98 12.72 13.27 12.46 8.000 12.48 13.24 13.10 12.88 13.47 12.48 9.000 12.50 13.42 13.21 13.05 13.65 12.50 10.000 12.51 13.61 13.31 13.21 13.76 12.51 12.500 12.35 13.79 13.35 13.31 13.82 12.35 15.000 11.98 13.50 13.06 13.05 13.51 11.98 20.000 11.20 12.79 12.47 12.45 12.79 11.20 25.000 10.42 11.95 11.67 11.63 11.95 10.42 27.2156 12.314 12.314 12.314 12.314 12.314 12.314 48.0808 10.800 10.800 10.800 10.800 10.800 10.800 58.9671 6.000 6.000 6.000 6.000 6.000 6.000 Lattice No. 732 2087 2088 2089 2090 2091 LaSalle Unit 1 Cycle 10 1-2 Revision 0 Technical Requirements Manual -Appendix I LIC10 Core Operating Limits Report Table 1-4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE9B Fuel GE9B-P8CWB343-12GZ-80M-1 50 (Bundle 3866, bundle type 4) (References 5 and 12) Planar Average Lattice Specific MAPLHGR limit (kW/ft) Exposure (GWdIST) 0 12.66 11.69 11.37 10.92 12.66 0.200 12.59 11.71 11.43 10.99 12.59 1.000 12.40 11.78 11.55 11.13 12.40 2.000 12.34 11.95 11.72 11.33 12.34 3.000 12.34 12.16 11.91 11.54 12.34 4.000 12.37 12.40 12.11 11.76 12.37 5.000 12.40 12.67 12.32 12.00 12.40 6.000 12.43 12.90 12.53 12.24 12.43 7.000 12.46 13.05 12.76 12.49 12.46 8.000 12.48 13.21 12.98 12.75 12.48 9.000 12.50 13.37 13.13 13.01 12.50 10.000 12.51 13.54 13.30 13.22 12.51 12.500 12.35 13.75 13.60 13.57 12.35 15.000 11.98 13.48 13.23 13.21 11.98 20.000 11.20 12.71 12.40 12.37 11.20 25.000 10.42 11.92 11.60 11.57 10.42 27.2156 12.314 12.314 12.314 12.314 12.314 48.0808 10.800 10.800 10.800 10.800 10.800 58.9671 6.000 6.000 6.000 6.000 6.000 Lattice No. 732 2083 2084 2085 2086 Table 1-5 SLO MAPFACp multiplier for (References 5 and 10)GE9B Fuel Core Thermal MAPFACp Power (% of rated) multiplier 0 0.4776 25 0.6082 100 1.0000

Values are interpolated between relevant power levels.

For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power MAPFACp multiplier should be applied.LaSalle Unit 1 Cycle 10 1-3 Revision 0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report Table 1-6 SLO MAPFACF multiplier for GE9B Fuel (References 5 and 13) Core Flow MAPFACF (% of rated) multiplier 0 0.4672 25 0.6373 78.28 1.0000 105 1.0000 "* Values are interpolated between relevant flow values. "* For core thermal monitoring at greater than 105% rated core flow, utilize MAPFACF multiplier for 105% rated core flow.LaSalle Unit 1 Cycle 10 1-4 Revision 0 Technical Requirements Manual -Appendix I L1C10 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) implications 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. TIP Symmetry Chi-squared testing shall be performed prior to reaching 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 2-4, and is dependent on fuel type and scram speed, in addition to power level. Table 2-1 or 2-2 is applicable to ATRIUM-10 fuel and Table 2-3 or 2-4 is applicable to both ATRIUM-9B and GE9B fuel types. 2.2.1.2 Flow-Dependent MCPR The flow dependent MCPR value, MCPRF, is determined from Table 2 5 for all fuel types in Cycle 10. 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 11 Section 7.7).Time Notch Position (ie (sec) 45 0.380 39 0.680 25 1.680 05 2.680 LaSalle Unit 1 Cycle 10 2-1 Revision 0 Technical Requirements Manual -Appendix I LIC10 Core Operating Limits Report Table 2-1 MCPRpfor ATRIUM-10 Fuel BOC -First Cycle 10 Sequence Exchange Nominal Scram Speeds (NSS) (Reference 3 Table 5.1)EOOS Combination Core Thermal Power (% of rated) 0 25 25(25.1) 60 80 80(80.1) 100 MCPRp Base Case Operation 2.70 2.20 2.07 1.52 EOOS Case 1 2.86 2.36 2.36 1.59 EOOS Case 2 2.86 2.36 2.36 EOOS Case 3 2.86 2.36 2.36 1.59 Single Loop Operation (SLO) 2.71 2.21 2.08 1.53 SLO with EOOS Case 1 2.87 2.37 2.37 1.43 1.47 1.54 1.47 1.44 1.48 1.55 1.48 SLO with EOOS Case 2 2.87 2.37 2.37 SLO with EOOS Case 3 2.87__________________

A 4 2.37 2.37* 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 1 Cycle 10 2-2 Revision 0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report Table 2-2 MCPRpfor ATRIUM-10 Fuel BOC -First Cycle 10 Sequence Exchange Technical Specification Scram Speeds (TSSS) (Reference 3 Table 5.2)EOOS Combination Core Thermal Power (% of 0 1 25 1 25(25.1)Base Case Operation 2.70 2.20 2.15 1.55 EOOS Case 1 2.95 2.45 2.45 1.62 EOOS Case 2 2.95 2.45 2.45 EOOS Case 3 2.95 2.45 2.45 1.62 Single Loop Operation (SLO) 2.71 2.21 2.16 1.56 SLO with EOOS Case 1 2.96 2.46 2.46 1.63 SLO with EOOS Case 2 2.96 2.46 2.46 SLO with EOOS Case 3 2.96 2.46 2.46 1.63 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 1 Cycle 10 0 S 0 2-3 Revision 0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report Table 2-3 MCPRpfor ATRIUM-9B and GE9B Fuel BOC -First Cycle 10 Sequence Exchange Nominal Scram Speeds (Reference 3 Table 5.1)EOOS Combination Core Thermal Power (% of rated) 25 25(25.1) 60 80 80(80.1) 100 MCPRP Base Case Operation 2.70 2.20 1.95 1.50 EOOS Case 1 2.70 2.20 2.15 EOOS Case 2 2.70 2.20 2.15 EOOS Case 3 2.70 2.20 2.15 1.58 1.86 1.67 1.58 Single Loop Operation (SLO) 2.71 2.21 1.96 1.51 SLO with EOOS Case 1 2.71 2.21 2.16 SLO with EOOS Case 2 2.71 2.21 2.16 SLO with EOOS Case 3 2.71 2.21_________

&2.16 1.59 1.87 1.68 1.59 1.42 1.45 1.52 1.45 1.43 1.46 1.53 1.46* 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 1 Cycle 10 Revision 0 2-4 Technical Requirements Manual -Appendix I L1CIO Core Operating Limits Report Table 2-4 MCPRpfor ATRIUM-9B and GE9B 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 25(25.1) 60 80 80(80.1) 100 MCPRp Base Case Operation 2.70 2.20 1.96 1.54 EOOS Case 1 2.70 2.20 2.19 EOOS Case 2 2.70 2.20 2.19 EOOS Case 3 2.70 2.20 2.19 1.62 1.86 1.73 1.62 Single Loop Operation (SLO) 2.71 2.21 1.97 1.55 SLO with EOOS Case I 2.71 2.21 2.20 SLO with EOOS Case 2 2.71 2.21 2.20 SLO with EOOS Case 3 2.71 2.21 2.20 1.63 1.87 1.74 1.63 1.44 1.48 1.59 1.48 1.45 1.49 1.60 1.49* 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 1 Cycle 10 2-5 Revision 0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report Table 2-5 MCPRF limits for ATRIUM-10, ATRIUM-9B, and GE9B Fuel (Reference 3 Figure 5.1)Flow (% of rated) J MCPRF 0 1.63 30 1.63 100 1.19 105 1.11

Values are interpolated between relevant flow values. Values presented in Table 2-5 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 1 Cycle 10 2-6 Revision 0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report 3. Linear Heat Generation Rate (3.2.3) 3.1 Technical Specification

Reference:

Section 3.2.3. 3.2

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) implications 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, 3-2, 3-3 or 3-4 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 3-5 or 3-6 for ATRIUM-10 fuel, Table 3-7 or 3-8 for ATRIUM-9B fuel or Table 3-9 or 3-10 for GE9B fuel. The applicable flow dependent LHGR Factor (LHGRFACF) is determined from Table 3-11 for ATRIUM-10 and ATRIUM-9B fuels or Table 3-12 for GE9B fuel. Table 3-1 Steady-State LHGR Limits for ATRIUM-1 0 Fuel Al 0-4039B-1 5GV75-1 0OM Al 0-4037B-1 6GV75-1 OM (Bundle types 10 and 11) (Reference 3 Section 7.2.3) Average Planar LHGR Limit Exposure (GWdIMT) (kWlft) 0.0 13.4 15.0 13.4 55.0 9.1 64.0 7.3 LaSalle Unit 1 Cycle 10 3-1 Revision 0 Technical Requirements Manual -Appendix I LlC1 0 Core Operating Limits Report Table 3-2 Steady-State LHGR Limits for ATRIUM-9B Fuel SPCA9-393B-16GZ-100lM SPCA9-396B-1 2GZB-1 0OM SPCA9-384B-1 1 GZ-80M SPCA9-396B-1 2GZC-1 OOM (Bundle types 6, 7, 8 and 9) (Reference 3 Section 7.2.3) Average Planar L G ii ExposureLHGR Limit Exposure (kWlft) (GWdlMT) 0.0 14.4 15.0 14.4 64.3 7.9 Table 3-3 LHGR Limits for GE9B Fuel GE9B-P8CWB343-12GZ-80M-150 (Bundle 3866, bundle type 4) (Reference 5 Page 47) Average Planar LHGR Limit Exposure (kW/ft) (GWdIMT) 0.00 14.40 12.33 14.40 27.86 12.31 49.76 10.80 61.18 6.00 Table 3-4 LHGR Limits for GE9B Fuel GE9B-P8CWB342-1 OGZ-80M-1 50 (Bundle 3867, bundle type 5) (Reference 5 Page 47) Average Planar LHGR Limit Exposure (kWlft) (GWd/MT) 0.00 14.40 12.71 14.40 27.52 12.31 49.54 10.80 60.95 6.00 LaSalle Unit 1 Cycle 10 Revision 0 3-2 Technical Requirements Manual -Appendix I LIC10 Core Operating Limits Report Table 3-5 LHGRFACp for ATRIUM-10 Fuel BOC -First Cycle 10 Sequence Exchange Nominal Scram Speeds (NSS) (Reference 3 Table 5.1)EOOS Combination Base Case Operation EOOS Case 1 EOOS Case 2 EOOS Case 3 Single Loop Operation (SLO) SLO with EOOS Case 1 SLO with EOOS Case 2 SLO with EOOS Case 3 Core Thermal Power (% of rated) 0 25 60 80 100 LHGRFACp multiplier 0.75 0.75 1.00 10 0.66 0.66 0.94 0.94 0.95 0.65 0.65 0.88 0.89 0.66 0.66 0.77 0.77 0.83 0.75 0.75 1.00 10 0.66 0.66 0.94 0.94 0.95 06 0.65 m R0.88 0.89 0.66 0.66 0.77 0.77 0.83"* 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 1 Cycle 10 3-3 Revision 0 I Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report Table 3-6 LHGRFACp for ATRI UM-10 Fuel BOC -First Cycle 10 Sequence Exchange Technical Specification Scram Speeds (TSSS) (Reference 3 Table 5.2)EOOS Combination Base Case Operation 0.74 0.74 EOOS Case 1 0.64 0.64 EOOS Case 2 0.64 0.64 EOOS Case 3 0.64 0.64 Single Loop Operation (SLO) 0.74 0.74 SLO with EOOS Case 1 0.64 0.64 SLO with EOOS Case 2 0.64 0.64 SLO with EOOS Case 3 0.64 0.64 1.00 0.94 0.95 0.87 0.87 0.77 0.83 S~1.00 0.94 0.95 0.87 0.87 0.77 0.83 0.77 0.77 1 0.77"* 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 1 Cycle 10 Core Thermal Power (% of rated) 0 25 40 60 80 100 3-4 Revision-0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report Table 3-7 LHGRFACp for ATRIUM-9B Fuel BOC -First Cycle 10 Sequence Exchange Nominal Scram Speeds (NSS) (Reference 3 Table 5.1)EOOS Combination LHGRFACp multiplier Base Case Operation 0.77 0.77 0.69 EOOS Case 1 EOOS Case 2 0.67 0.67 1.00 la 1.00 0.90 0.90 0.90 W , 0.79 0.79 0.77 0.77 0.80 1.00 1.00 0.90 0.90 0.90 S 0.79 0.79 0.69 EOOS Case 3 Single Loop Operation (SLO) 0.77 0.77 0.69 SLO with EOOS Case 1 SLO with EOOS Case 2 0.67 0.67 0.77 0.80 0.77 0.69 0.69 SLO with EOOS Case 3 4 ________ 4 ________"* 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 1 Cycle 10 0.69 0.69 0.69 Core Thermal Power (% of rated) 0 25 60 80 100 Revision 0 3-5 Technical Requirements Manual -Appendix I L1CIO Core Operating Limits Report Table 3-8 LHGRFACp for ATRIUM-9B Fuel BOC -First Cycle 10 Sequence Exchange Technical Specification Scram Speeds (TSSS) (Reference 3 Table 5.2)EOOS Combination Base Case Operation 0.76 0.76 EOOS Case 1 0.69 0.69 EOOS Case 2 0.67 0.67 EOOS Case 3 0.69 0.69 Single Loop Operation (SLO) 0.76 0.76 SLO with EOOS Case 1 0.69 0.69 SLO with EOOS Case 2 0.67 0.67 0.77 0.77 0.69 SLO with EOOS Case 3 0.69* 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 1 Cycle 10 Core Thermal Power (% of rated) 0 25 40 60 80 100 I I S~1.00 0.91 0.92 0.76 0.76 0.77 0.80 S~1.00 0.91 0.92 0.76 0.76 0.77 0.80 0.77 1 Revision 0 3-6 Technical Requirements Manual- Appendix I L1C10 Core Operating Limits Report Table 3-9 LHGRFACp multipliers for GE9B Fuel except TCV Slow Closure (References 3, 5, 10 and 15)0 Core Thermal LHGRFACp Power (% of rated) Multiplier 0 0.4776 25 0.6082 100 1.0000 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.Table 3-10 LHGRFACp multipliers for GE9B Fuel for TCV (References 3, 5, 14 and 15)Core Thermal LHGRFACp Power (% of rated) Multiplier 0 0.2000 25 0.4000 100 1.0000 0 Slow Closure values are interpolatea oetween relevant power levels. For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFACp multiplier should be applied.LaSalle Unit 1 Cycle 10 3-7 Revision 0 Technical Requirements Manual -Appendix I LIC10 Core Operating Limits Report Table 3-11 LHGRFACF multipliers for ATRIUM-10 and ATRIUM-9B Fuel (Reference 3 Figure 5.2)Core Flow LHGRFACF (% of rated) Multiplier 0 0.72 30 0.72 68 1.00 105 1.00

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 presented in Table 3-11 are applicable to all Operating Domains and EOOS conditions in Section 6. Table 3-12 LHGRFACF multipliers for GE9B Fuel (References 3, 5, 13 and 15) Core Flow LHGRFACF (% of rated) Multiplier 0 0.4672 25 0.6373 78.28 1.0000 105 1.0000 "* 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 presented in Table 3-12 are applicable to all Operating Domains and EOOS conditions in Section 6.LaSalle Unit 1 Cycle 10 3-8 Revision 0 Technical Requirements Manual -Appendix I L1CIO 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

Description:

The Rod Block Monitor Upscale Instrumentation Setpoints are relationships shown below (Reference 6): ROD BLOCK MONITOR UPSCALE TRIP FUNCTION Two Recirculation Loop 0.66 Wd + 54% Operation 0.66_W__+_54%

Single Recirculation Loop 0.66 Wd + 48.7% Operation determined from the 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 I Cycle 10 4-1 Revision 0 Technical Requirements Manual -Appendix I L1C10 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 7, 8 and 9) 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 1 Cycle 10 5-1 Revision 0 Technical Requirements Manual -Appendix I LIC10 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-....

Equipment Out of Service 7POWERPLEX Options ei4 ELLLA MELLLA ICF 7 Coastdown 3 Thermal Limit Set Number 4 Base Case Operation

-NSS Yes Yes Yes No 1 EOOS Case 1 -NSS FHOOS 5 or TBVOOS 2 Yes Yes Yes No 2 Except FHOOS8 Except FHOOS8 EOOS Case 2 -NSS Any combination of TCV slow Yes Yes Yes No 3 closure, no RPT or FHOOS 5 Except FHOOS8 Except FHOOS' EOOS Case 3 -NSS TBVOOS with 1 TCV stuck Yes Yes Yes No 4 closed Single Loop Operation (SLO) -NSS Yes No 6 N/A No 5 SLO with EOOS Case 1 -NSS FHOOS 5 or TBVOOS 2 Yes No 6 N/A No 6 Except FHOOS 8 SLO with EOOS Case 2 -NSS Any combination of TCV slow Yes No 6 N/A No 7 closure, no RPT or FHOOS5 Except FHOOS _ SLO with EOOS Case 3 -NSS TBVOOS with 1 TCV stuck Yes No 6 N/A No 8 closed Base Case Operation

-TSSS Yes Yes Yes No 9 EOOS Case 1 -TSSS FHOOS 5 or TBVOOS 2 Yes Yes Yes No 10 Except FHOOS8 Except FHOOS' EOOS Case 2 -TSSS Any combination of TCV slow Yes Yes Yes No 11 closure, no RPT or FHOOS 5 Except FHOOS 6 Except FHOOS8 EOOS Case 3 -TSSS TBVOOS with 1 TCV stuck Yes Yes Yes No 12 closed Single Loop Operation (SLO) -TSSS Yes No 6 N/A No 13 SLO with EOOS Case 1 -TSSS FHOOS 5 or TBVOOS 2 Yes No 6 N/A No 14 Except FHOOS8 SLO with EOOS Case 2 -TSSS .Any combination of TCV slow Yes No 6 N/A No 15 closure, no RPT or FHOOS 5 Except FHOOS __ SLO with EOOS Case 3 -TSSS TBVOOS with 1 TCV stuck Yes No 6 N/A No 16 closed Each OOS Option may be combined with 1 SRVOOS, 1 TCV stuck closed (except TBVOOS conditions), a 20°F reduction in feedwater temperature (without feedwater heaters considered OOS), up to 2 TIP OOS (or the equivalent number of TIP channels, 42% of the total number of channels with 100% available at startup), and up to 50% of the LPRMs OOS with an LPRM calibration frequency of LaSalle Unit 1 Cycle 10 6-1 Revision 0 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report 1250 Effective Full Power Hours (EFPH) (1000 EFPH +25%) (Reference 3 Tables 1.1 and 5.1 through 5.4). 2 All EOOS options support 1 TCV stuck closed except EOOS Case 1 TBVOOS. If TBVOOS is being utilized while 1 TCV is stuck closed, utilize EOOS Case 3 with the applicable scram speed (Reference 3 Tables 1.1 and 5.1 through 5.4). 3 Coastdown limits are not provided.

Coastdown limits will be provided in a later revision to this document.

4 All EOOS scenarios and all applicable limits provided are applicable from the beginning of the cycle 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.

s 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.

6 The SLO boundary was not moved up with the incorporation of MELLLA. The power-flow boundary for SLO at power uprated conditions remains the ELLLA boundary for pre-uprate conditions.

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.LaSalle Unit 1 Cycle 10 6-2 Revision 0 Technical Requirements Manual -Appendix I L1C10 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 1 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 T M Spacer on 9x9-IX/X BWR Fuel Design," July 28,1993.

3. ANF-524 (P)(A) Revision 2 and Supplements 1 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 I(P)(A) and Supplement 2(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998. 14. NEDE-24011-P-A-14, "General Electric Standard Application for Reactor Fuel (GESTAR)," June 2000. 15. EMF-CC-074 (P) Volume 4 Revision 0, "BWR Stability Analysis:

Assessment of STAIF with Input from MICROBURN-B2, August 2000.LaSalle Unit 1 Cycle 10 Revision 0 7-1 Technical Requirements Manual -Appendix I L1C10 Core Operating Limits Report 16. ANF-1 125 (P)(A) and ANF-1125(P)(A)

Supplements 1 and 2, "ANFB Critical Power Correlation," Advanced Nuclear Fuels Corporation, April 1990. 17. ANF-1125 (P)(A) Supplement 1 Appendix E, "ANFB Critical Power Correlation Determination of ATRIUM T M-9B Additive Constant Uncertainties," September 1998. 18. EMF-1125 (P)(A) Supplement 1 Appendix C, "ANFB Critical Power Correlation Application for Co Resident Fuel," August 1997. 19. Commonwealth Edison Topical Report NFSR-0085 Revision 0, "Benchmark of BWR Nuclear Design Methods," November 1990. 20. Commonwealth Edison Topical Report NFSR-0085 Supplement 1 Revision 0, "Benchmark of BWR Nuclear Design Methods -Quad Cities Gamma Scan Comparisons," April 1991. 21. Commonwealth Edison Topical Report NFSR-0085 Supplement 2 Revision 0, "Benchmark of BWR Nuclear Design Methods -Neutronic Licensing Analyses," April 1991. 22. 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.

23. 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. 24. 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. 25. ANF-91-048 (P)(A) Supplement 1 and Supplement 2, "BWR Jet Pump Model Revision for RELAX," October 1997. 26. 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. 27. XN-NF-80-19 (P)(A) Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors -Neutronic Methods for Design and Analysis," March 1983.LaSalle Unit 1 Cycle 10 7-2 Revision 0 Technical Requirements Manual -Appendix I Section 2 LaSalle Unit 1 Cycle 10 Reload Transient Analysis Results Technical Requirements Manual -Appendix I LI C10 Reload Transient Analysis Results Table of Contents Preparer ExelonfNFM Framatome-ANP Framatome-ANP Document Supplemental Licensing Report Information Reload Analysis Plant Transient Analysis LaSalle Unit I Cycle 10 Attachment 1 2 3 Revision 0 Technical Requirements Manual -Appendix I LIC 10 Reload Transient Analysis Results Attachment 1 LaSalle Unit 1 Cycle 10 Supplemental Licensing Report Information LaSalle Unit I Cycle 10 Revision 0 NUCLEAR FUEL MANAGEMENT TRANSMITTAL OF DESIGN INFORMATION 0 SAFETY RELATED Originating Organization NFM ID# NFM0200004 fl NON-SAFETY RELATED 0 Nuclear Fuel Management Sequence 0 0 REGULATORY RELATED E5 Other (specify)

Page I of 7 Station: LaSalle Unit: 1 Cycle: 10 Generic: X To: Kirk W. Peterman (LaSalle)

Subject:

LaSalle Unit I Cycle 10 Supplemental Licensini Lport Information Frank W. Trikur .".Preparer Preparer's Signature Date Anthony D. Giancatarino 6'~ -9~ . NFM Department Head "- -Approver ignature Date Status of Information:

0 Verified 0 Unverified LI Engineering Judgement Action Tracking #. for Method and Schedule of Verification for Unverified DESIGN INFORMATION:

Description of Information:

The information included in this transmittal are LaSalle Cold Shutdown Margin information, fuel type exposure limits, and the applicable LICIO GE-9 thermal limits (LHGR, LHGRFACr, LHGRFACp, MAPFACr, and MAPFACp).

Purpose of Information:

Provide documentation of reload limits (e.g. SDM, thermal limits, fuel exposure) for the LI C I0 reload design. Sources of Information:

Reference

1. EMF-2563(P), Rev. 1, Fuel Mechanical Design Report Exposure Extension for ATRIUM-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units. Reference

2. EMF-2589(P), Rev. 0, Mechanical and Thermal Hydraulic Design Report for LaSalle Units I & 2, ATRIUM-l 0 Fuel Assemblies.

Reference

3. "CornEd GE9/GE]0 LHGR Improvement Program", JlI 1-03692-LHGR, Rev. I, February 2000. Reference

4. "ARTS Improvement Program Analysis for LaSalle County Stations Unit I and 2", NEDC-3153 I P, December 1993 and Supplement I, June 1998. Reference S. "Project Task Report, LaSalle County Station, Power Uprate Evaluation, Task 407: ECCS Performance" GE-NE-A1300384-39-01, Rev.,& September 1999 ,it) ,ZI Reference

6. "Evaluation of a Postulated Slow Turbine Control Valve Closure Event for LaSalle County Nuclear Station, Units I and 2, GE-NE-187-13-0792, Revision 2, July 1998. Reference

7. NFM Calculation No. BSA-L-99-07, "MAPFACf Thermal Limit Multiplier for 105% Maximum Core Flow" Reference

8. "Fuel Design Report for LaSalle Unit 2 Cycle 9 ATRIUM-9B Fuel Assemblies", EMF-2404(P), Revision 1, September 2000. Supplemental Hardcopy Distribution:

LaSalle Central File Cantera Records Management Supplemental Electronic Distribution:

Norha Z. Plumey Jeff K. Nugent NFM ID#: NFM0200004 Sequence 0 Page 2 of7 Core Reactivity Characteristics All values reported below are with zero xenon and are for 68 0 F moderator temperature.

The MICROBURN-B cold BOC K-effective bias is 1.0050 (Reference 11). The shutdown margin calculations are based on the short cycle 9 exposure of 19100 MWd/MTU.BOC Cold K-Effective, Strongest Rod Out BOC Shutdown Margin, % AK Minimum Shutdown Margin, % AK Cycle Exposure(s) of Minimum Shutdown Margin, MWD/MT Reactivity Defect (R-value)

Total, % AK 0.99325 1.17 1.17 0.0 0.0 NFM ID#: NFM0200004 Sequence 0 Page 3 of7 Maximum Exposure Limit Compliance Note that the projected exposures listed below are based on the nominal Cycle 9 (Cycle N-I) exposure, 19600 MWD/MT, and the licensing basis Cycle 10 (Cycle N) cycle exposure of 18600 MWD/MT. The exposure limits are identified in References 1, 2 and 8./ / ~C2 Exposure GE9B GE9B ATRIUM-98 ATRIUM-9B ATRIUM-9B ATRIUM-9B ATRIUM-10 ATRIUM-10 Criteria Projected Exposure (100-mil)

(100-mil)

(80-mil) (80-mil) Projected Exposure Exposure Limit Projected Exposure Projected Exposure Exposure Limit (GWD/MT) (GWD/MT) Exposure Limit Exposure Limit (GWD/MT) (GWD/MT) Peak Fuel (GWD/MT) (GWD/MT) (GWD/MT) (GWD/MT) Peak Fuel Assembly N/A N/A 45.8 50.5 43.7 48.0 23.2 54.0 Peak Fuel Batch 38.1 42.0 N/A N/A N/A N/A N/A N/A Peak Fuel Rod N/A N/A 49.5 57.9 47.3 55.0 26.4 58.7 Peak Fuel Pellet 57.2 65.0 " 63.1 69.4 60.5 66.0 34.8 70.4 NFM ID#: NFM0200004 Sequence 0 Page 4 of 7 GE9B Thermal Limits The following tables contain the GE9B thermal limits (LHGR, LHGRFACf, LHGRFACp, MAPFACf, and MAPFACp).

These limits were reviewed and approved previously for use in LaSalle Unit I Cycle 9 and previously presented in the Cycle 9 COLR. The GE9 fuel that currently resides in the LaSalle Unit 1 Cycle 10 core are located on the core periphery and in non-limiting locations.

It was evaluated that the previous GE9 Cycle 9 thermal limits are therefore applicable to the GE9 fuel used in Cycle 10. LHGR Limit The LHGR Limit is the product of the LHGR Limit in the following tables and the minimum of either the power dependent LHGR Factor*, LHGRFACp or the flow dependent LHGR Factor, LHGRFACF.

The LHGR Factors (LHGRFACp and LHGRFACF) for the GE fuel is determined from Tables 3 and 4 and Figure 1. The following LHGR limits apply for the entire cycle exposure range: (References 3, 4, and 5) Table 1. GE9B-P8CWB343-12GZ-80M-150 (bundle 3866 in Reference

3) Nodal Exposure (GWd/MT) LHGR Limit (KW/ft) 0.00 14.40 12.33 14.40 27.86 12.31 49.76 10.80 61.18 6.00 Table 2. GE9B-P8CWB342-1OGZ-80M-150 (bundle 3867 in Reference

3) Nodal Exposure (GWd/MT) LHGR Limit (KW/ft) 0.00 14.40 12.71 14.40 27.52 12.31 49.54 10.80 60.95 6.00* For thermal limit monitoring cases at greater than 100% power, the 100% power LHGRFACP limits should be applied'9. /o-.

NFM ID#: NFM0200004 Sequence 0 Page 5 of 7 LHGRFAC, Table 3. Power Dependent LHGR Multipliers for GE Fuel (formerly MAPFACp) (References 3 and 4)25>P No Thermal Limit Monitoring Required; If official monitoring is desired, the equations for >25% Power may be extrapolated for 25>P, provided the official monitoring is only performed with the TCVITSV closure scrams and RPT enabled.

25<P<100 LHGRFACp = 1.0+0.005224(P-100) 100

P No Thermal Limit Monitoring Required; If official monitoring is desired, the equations for >25% Power may be extrapolated for 25>P. 25<P<100 LHGRFACp = 1.0+0.008(P-1

00) 100<P LHGRFACp = 1.0 P = % Rated Thermal Power Power (LHGRFACp)

Value LHGRFACf NFM ID#: NFM0200004 Sequence 0 Page 6 of`7 Figure 1. Flow-Dependent LHGR Multiplier for GE Fuel (formerly MAPFACF (Reference 4, 3, and 7)III IN For 105% Maximum Attainable Core Flow LHGRFACF = The Minimum of EITHER 1.0 OR (0.6807 x (WTt100)+0.4672) WT =% Rated Core Flow I I _______U 40 45 50 55 60 65 70 Core Flow (% Rated)75 80 85 90 95 100 0.9 U 0. t9 0.8 0.5 S0.7 LL 0.6 0. 0.5 9 0.4 0.3 30 35 105 NFM ]Db: NFM0200004 Sequence 0 Page 7 of 7 TOP/MOP Requirements for GE9 Fuel All GE9 fuel that is being utilized in the LaSalle Unit 1 Cycle 10 reload design are located on the core periphery and therefore not in any bounding or limiting locations. Because these assemblies are in low power locations they will not challenge any margin to the MOP/TOP limits. O'0Z S? o/ Technical Requirements Manual -Appendix I L 1C 10 Reload Transient Analysis Results Attachment 2 LaSalle Unit 1 Cycle 10 Reload Analysis LaSalle Unit 1 Cycle 10 Revision 0 2FRAMATOME AN P EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis January 2002 dvanced 'ucl-Framatome ANP, Inc. 188M 9I FRA-ANP ON-L ,.i LaSalle Unit I Cycle 10 Reload Analysis Prepared: --

J. MHaun, Engineer BWR Neutronics Prepared:

65 Concurred: Concurred: Approved: Ii D. G. Carr, Team Leader J. S. fonm,"Man gar Prod! Licensing D. E. Garber, Manager Commercial Operations Pu. k-. 0rwn Lange O u. C. Drown, Manager BWR Neutronics Approved: 6,ow i M. E. Garrett, Manager BWR Safety Analysis Approved: ývj'2 J. R. Tady, Manager Product Mechanical Engineering ro. 6.A4 Approved: R. E. Collingham, Manager BWR Reload Engineering & Methods Development /2-A,/01A Date Iat/ ,. D/3.-LI Date Date D at Date Dak Date Date sp Framatome ANP, Inc.Framatome ANP, Inc.EMF-2690 Revision 0 Customer Disclaimer Important Notice Regarding the Contents and Use of This Document Please Read Carefully Framatome ANP, Inc.'s warranties and representations concerning the subject matter of this document are those set forth in the agreement between Framatome ANP, Inc. and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such agreement, neither Framatome ANP, Inc. nor any person acting on its behalf: a. makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method, or process disclosed in this document will not infringe privately owned rights; or b. assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this document. The information contained herein is for the sole use of the Customer. In order to avoid impairment of rights of Framatome ANP, Inc. in patents or inventions which may be included in the information contained in this document, the recipient, by its acceptance of this document, agrees not to publish or make public use (in the patent use of the term) of such information until so authorized in writing by Framatome ANP, Inc. or until after six (6) months following termination or expiration of the aforesaid Agreement and any extension thereof, unless expressly provided in the Agreement. No rights or licenses in or to any patents are implied by the furnishing of this document. EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Pagei Nature of Changes Item Page Description and Justification

1. All This is a new document.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page ii Contents 1.0 Introduction ................................................................................................................. 1-1 2.0 Fuel Mechanical Design Analysis ................................................................................ 2-1 3.0 Therm al-Hydraulic Design Analysis ............................................................................. 3-1 3.2 Hydraulic Characterization ............................................................................... 3-1 3.2.1 Hydraulic Com patibility ....................................................................... 3-1 3.2.3 Fuel Centerline Tem perature ............................................................. 3-1 3.2.5 Bypass Flow ....................................................................................... 3-1 3.3 MCPR Fuel Cladding Integrity Safety Lim it (SLM CPR) .................................... 3-1 3.3.1 Coolant Thermodynam ic Condition .................................................... 3-1 3.3.2 Design Basis Radial Power Distribution ............................................. 3-2 3.3.3 Design Basis Local Power Distribution ............................................... 3-2 3.4 Licensing Power and Exposure Shape ............................................................. 3-2 4.0 Nuclear Design Analysis .............................................................................................. 4-1 4.1 Fuel Bundle Nuclear Design Analysis .............................................................. 4-1 4.2 Core Nuclear Design Analysis .......................................................................... 4-2 4.2.1 Core Configuration ............................................................................. 4-2 4.2.2 Core Reactivity Characteristics for Short EOC9 Window .................... 4-2 4.2.4 Core Hydrodynam ic Stability .............................................................. 4-2 5.0 Anticipated Operational Occurrences .......................................................................... 5-1 5.1 Analysis of Plant Transients at Rated Conditions ............................................. 5-1 5.1.1 15,000 MW d/MTU Cycle Exposure .................................................... 5-1 5.1.2 EO C Licensing Exposure ................................................................... 5-1 5.2 Analysis for Reduced Flow O peration .............................................................. 5-2 5.3 Analysis for Reduced Power O peration ............................................................ 5-2 5.4 ASME Overpressurization Analysis .................................................................. 5-2 5.5 Control Rod W ithdrawal Error .......................................................................... 5-2 5.6 Fuel Loading Error ........................................................................................... 5-3 5.6.1 Mislocated Fuel Assem bly .................................................................. 5-3 5.6.2 Misoriented Fuel Bundle .................................................................... 5-3 5.7 Determ ination of Therm al M argins ................................................................... 5-3 6.0 Postulated Accidents ................................................................................................... 6-1 6.1 Loss-of-Coolant Accident ................................................................................. 6-1 6.1.1 Break Location Spectrum ................................................................... 6-1 6.1.2 Break Size Spectrum ......................................................................... 6-1 6.1.3 MAPLHG R Analyses .......................................................................... 6-1 6.2 Control Rod Drop Accident .............................................................................. 6-2 7.0 Technical Specifications .............................................................................................. 7-1 7.1 Lim iting Safety System Settings ....................................................................... 7-1 7.1.1 MCPR Fuel Cladding Integrity Safety Lim it ........................................ 7-1 7.1.2 Steam Dom e Pressure Safety Lim it ................................................... 7-1 7.2 Lim iting Conditions for O peration ..................................................................... 7-1 Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page iii 7.2.1 Average Planar Linear Heat Generation Rate .................................... 7-1 7.2.2 Minimum Critical Power Ratio ............................................................ 7-2 7.2.3 Linear Heat Generation Rate ............................................................ 7-2 8.0 M ethodology R eferences ............................................................................................. 8-1 9.0 A dditional R eferences ................................................................................................. 9-1 Tables 1.1 EOD and EOOS Operating Conditions ........................................................................ 1-2 3.1 Licensing Basis Core Average Axial Power Profile and Licensing Axial P ow e r R atio ................................................................................................................. 3-3 4.1 N eutronic Design Values ............................................................................................. 4-4 5.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU' ............................................................... 5-5 5.2 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU' ..................................................... 5-7 5.3 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC' ............................................................... 5-9 5.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC .................................................... 5-11 6.1 Simplified Shutdown Sequence from an Al Rod Pattern ............................................. 6-3 6.2 Simplified Shutdown Sequence from an A2 Rod Pattern ............................................. 6-4 Figures 3.1 Radial Power Distribution for SLMCPR Determination ................................................. 3-4 3.2 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors A10-4039B 15G V 75 W ith C hannel Bow ......................................................................................... 3-5 3.3 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors A10-4037B 16G V 75 W ith Channel Bow ......................................................................................... 3-6 4.1 LaSalle Unit 1 Cycle 10 Reference Loading Map ......................................................... 4-5 5.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode ................................... 5-13 5.2 Flow Dependent LHGR Multipliers for ATRIUM-10 and ATRIUM-9B Fuel ................. 5-14 5.3 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRI UM-10 Fuel -NSS Insertion Times ............................................................... 5-15 Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page iv 5.4 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ............................................................... 5-16 5.5 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times ............................................................. 5-17 5.6 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times ............................................................. 5-18 5.7 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Tim es ............................................................... 5-19 5.8 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ............................................................... 5-20 5.9 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-1 0 Fuel -TSSS Insertion Times ............................................................. 5-21 5.10 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times ............................................................. 5-22 Framatome ANP, Inc. LaSalle Unit 1 Cycle 10 Reload Analysis AOO BOC BPWS CRDA CRWE EFPH EOC EOD EOFP EOOS FFTR FHOOS FRA-ANP FWCF ICA ICF LFWH LHGR LHGRFAC LOCA LPRM LRNB MAPFAC MAPLHGR MCPR MELLLA MSIV NRC NSS PAPT PCT RPT SLMCPR SLO SRVOOS anticipated operational occurrence beginning of cycle banked position withdrawal sequence control rod drop accident control rod withdrawal error effective full power hours end of cycle extended operating domain end of full power equipment out of service final feedwater temperature reduction feedwater heater out of service Framatome ANP, Inc. feedwater controller failure interim corrective actions increased core flow loss of feedwater heating linear heat generation rate LHGR multiplier loss of coolant accident local power range monitor load rejection no bypass MAPLHGR multiplier maximum average planar linear heat generation rate minimum critical power ratio maximum extended load line limit analysis main steam isolation valve Nuclear Regulatory Commission, U.S. nominal scram speed protection against power transient peak clad temperature recirculation pump trip safety limit minimum critical power ratio single-loop operation safety/relief valve out of service Framatome ANP, Inc.Nomenclature EMF-2690 Revision 0 Page v EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page vi TBVOOS turbine bypass valves out of service TCV turbine control valve TIP traversing in-core probe TIPOOS traversing in-core probe out of service TSSS technical specification scram speed UFSAR updated final safety analysis report ACPR change in critical power ratio Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 1-1 1.0 Introduction This report provides the results of the analysis performed by Framatome ANP, Inc. (FRA-ANP), as part of the reload analysis in support of the Cycle 10 reload for LaSalle Unit 1. This report is intended to be used in conjunction with the FRA-ANP topical Report XN-NF-80-19(P)(A), Volume 4, Revision 1, Application of the ENC Methodology to BWR Reloads, which describes the analyses performed in support of this reload, identifies the methodology used for those analyses, and provides a generic reference list. Section numbers in this report are the same as corresponding section numbers in XN-NF-80-19(P)(A), Volume 4, Revision 1. Methodology used in this report which supersedes XN-NF-80-19(P)(A), Volume 4, Revision 1, is referenced in Section 8.0. The NRC Technical Limitations presented in the methodology documents, including the documents referenced in Section 8.0, have been satisfied by these analyses. The Cycle 10 core consists of a total of 764 fuel assemblies, including 346 unirradiated ATRIUMTm-10 assemblies, 372 irradiated ATRIUM T M-9B assemblies and 46 irradiated GE9 assemblies. The reference core configuration is described in Section 4.2. The design and safety analyses reported in this document were based on the design and operational assumptions in effect for LaSalle Unit 1 during the previous operating cycle. The effects of channel bow are explicitly accounted for in the safety limit analysis. The extended operating domain (EOD) and equipment out of service (EOOS) conditions presented in Table 1.1 are supported. ATRIUM is a trademark of Framatome ANP, Inc.Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 1-2 Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions Increased Core Flow Maximum Extended Load Line Limit Analysis (MELLLA) Equipment Out of Service (EOOS) Conditions* Feedwater Heaters Out of Service (FHOOS) Single-Loop Operation (SLO) -Recirculation Loop Out of Service Turbine Bypass Valves Out of Service (TBVOOS) EOC Recirculation Pump Trip Out of Service (No RPT) Turbine Control Valve (TCV) Slow Closure and/or No RPT Safety Relief Valve Out of Service (SRVOOS) Up to 2 TIP Machine(s) Out of Service or the Equivalent Number (42% of the total number of channels) of TIP Channels (100% available at startup) Up to 50% of the LPRMs Out of Service TCV Slow Closure, FHOOS and/or No RPT 1 Stuck Closed Turbine Control Valve EOOS conditions are supported for EOD conditions as well as the standard operating domain. Each EOOS condition combined with 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), 1 stuck closed turbine control valve and/or up to 50% of the LPRMs out of service is supported. Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 2-1 2.0 Fuel Mechanical Design Analysis Applicable FRA-ANP Fuel Design Reports References 9.2, 9.3, and 9.14 To assure that the power history for the ATRIUM-10 and ATRIUM-9B fuel to be irradiated during Cycle 10 of LaSalle Unit 1 is bounded by the assumed power history in the fuel mechanical design analyses, LHGR operating limits have been specified in Section 7.2.3. In addition, ATRIUM-10 and ATRIUM-9B LHGR limits for Anticipated Operational Occurrences have been specified in References 9.2 and 9.14 and are presented in Section 7.2.3. GE9 Fuel Mechanical Design Limits will be furnished by Exelon.Framatome ANP, Inc. EMF-2690 Revision 0 Pace 3-1 LaSalle Unit 1 Cycle 10 Reload Analysis 3.0 Thermal-Hydraulic Design Analysis 3.2 Hydraulic Characterization

3.2.1 Hydraulic

Compatibility Component hydraulic resistances for the fuel types in the LaSalle Unit 1 Cycle 10 core have been determined in single-phase flow tests of full-scale assemblies.

The hydraulic demand curves for ATRIUM-10 and ATRIUM-9B fuel in the LaSalle Unit 1 core are provided in Reference

9.2 Figures

4.2 and 4.3. 3.2.3 Fuel Centerline Temperature Applicable Reports ATRIUM-10 ATRIUM-9B Reference 9.2, Figure 3.2 Reference 9.3, Figure 3.3 3.2.5 Bypass Flow Calculated Bypass Flow at 100%P/100%F (includes water channel flow)13.7 Mlbm/hr Reference 9.4 3.3 MCPR Fuel Cladding Integrity Safety Limit (SLMCPR)Two-Loop Operation Single-Loop Operation*

3.3.1 Coolant

Thermodynamic Condition Thermal Power (at SLMCPR) Feedwater Flow Rate (at SLMCPR) Core Exit Pressure (at Rated Conditions)

Feedwater Temperature Reference 9.4 1.11 1.12 5446.6 MWt 23.6 Mlbm/hr 1031.35 psia 426.5 0 F Includes the effects of channel bow, up to 2 TIPOOS (or the equivalent number of TIP channels), a 2500 EFPH LPRM calibration interval, cycle startup with uncalibrated LPRMs (BOC to 500 MWd/MTU), and up to 50% of the LPRMs out of service.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 3-2 3.3.2 Desigqn Basis Radial Power Distribution Figure 3.1 shows the radial power distribution used in the MCPR Fuel Cladding Integrity Safety Limit analysis.

3.3.3 Design

Basis Local Power Distribution Figures 3.2 and 3.3 show the ATRIUM-10 local power peaking factors used in the MCPR Fuel Cladding Integrity Safety Limit analysis.

Al 0-4039B-1 5GV75 Figure 3.2 A10-4037B-16GV75 Figure 3.3 3.4 Licensing Power and Exposure Shape The licensing axial power profile used by FRA-ANP for the plant transient analyses bounds the projected end of full power (EOFP) axial power profile. The conservative licensing axial power profile as well as the corresponding axial exposure ratio are given in Table 3.1. Future projected Cycle 10 power profiles are considered to be in compliance when the EOFP normalized power generated in the core is greater than the licensing axial power profile at the given state conditions when the comparison is made over the bottom third of the core height.Framatome ANP, Inc.

Unit "1 Cycle 10 Reload Analysis Table 3.1 Licensing Basis Core Average Axial Power Profile and Licensing Axial Power Ratio State Conditions for Power Shape Evaluation Power, MWt 3489.00 Core Pressure, psia 1020.00 Inlet Subcooling, Btu/Ibm 18.35 Flow, MIb/hr 108.50 Control State ARO Licensing Axial Power Profile Node Power Top 25 24 23 22 21 20 19 18 17 16 15 14 13 12 11 10 9 8 7 6 5 4 3 2 Bottom 1 0.199 0.387 0.883 1.132 1.351 1.507 1.597 1.630 1.613 1.632 1.560 1.478 1.388 1.295 1.198 1.094 0.982 0.864 0.745 0.634 0.536 0.461 0.405 0.331 0.098 Licensing Axial Power Ratio (EOFP, ARO) Average Bottom 8 ft 112 ft = 1.1335 Framatome ANP, Inc.EMF-2690 Revision 0 Paae 3-3 La a l Unit.. .. .I ... ..............

Ana v --

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis 0 L E z 200 175 150 125 100 75 50 25 0.0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radial Power Peaking Figure 3.1 Radial Power Distribution for SLMCPR Determination Framatome ANP, Inc.LaSalle Unit 1 Cycle 10 Reload Analvsis akfu EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 3-5 CONTROL 0 N T R 0 L R 0 D C 0 R N E R ROD CORNER Figure 3.2 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors A10-4039B-15GV75 With Channel Bow (Assembly Exposure of 1000 MWd/MTU)Framatome ANP, Inc.1.057 1.212 1.130 1.268 1.225 1.252 1.226 1.234 1.172 1.013 1.212 .000 0.540 1.036 .000 0.512 0.971 0.536 .000 1.156 1.130 0.540 0.901 .0.904 0.499 0.892 0.948 0.920 0.538 1.214 1.268 1.036 0.904 0.924 1.058 1.151 1.121 1.003 0.999 1.134 1.225 .000 0.499 1.058 1.114 0.529 1.248 Internal 1.252 0.512 0.892 1.151 Water 1.203 .000 1.152 Channel 1.226 0.971 0.948 1.121 1.066 0.541 1.167 1.234 0.536 0.920 1.003 1.114 1.203 1.066 0.534 1.162 1.151 1.172 .000 0.538 0.999 0.529 .000 0.541 1.162 .000 1.084 1.013 1.156 1.214 1.134 1.248 1.152 1.167 1.151 1.084 1.022 EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 3-6 CONTROL ROD 0 N T R 0 L R 0 D C 0 R N E R CORNER Figure 3.3 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors Al 0-4037B-1 6GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU)Framatome ANP, Inc.1.061 1.225 1.141 1.282 1.240 1.271 1.246 1.255 1.191 1.021 1.225 .000 0.526 1.030 .000 0.504 0.983 0.528 .000 1.176 1.141 0.526 0.868 0.844 0.487 0.891 0.955 0.928 0.530 1.238 1.282 1.030 0.844 0.482 1.003 1.143 1.127 1.014 1.013 1.155 1.240 .000 0.487 1.003 1.126 0.522 1.273 Internal 1.271 0.504 0.891 1.143 Water 1.217 .000 1.173 Channel 1.246 0.983 0.955 1.127 1.076 0.533 1.189 1.255 0.528 0.928 1.014 1.126 1.217 1.076 0.527 1.183 1.173 1.191 .000 0.530 1.013 0.522 .000 0.533 1.183 .000 1.103 1.021 1.176 1.238 1.155 1.273 1.173 1.189 1.173 1.103 1.033 EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 4-1 4.0 Nuclear Design Analysis 4.1 Fuel Bundle Nuclear Design Analysis The detailed fuel bundle design information for the fresh ATRIUM T M-10 fuel to be loaded in LaSalle Unit 1 Cycle 10 is provided in Reference 9.1. The following summary provides the appropriate cross-references.

Assembly Average Enrichment (ATRIUM-10 fuel) A10-4039B-15GV75-100M (FT10) 4.039 Al 0-4037B-1 6GV75-1 OOM (FT1 1) 4.037 Radial Enrichment Distribution Al OT-4307L-1 5G65 Reference 9.1, Figurn AlOB-451OL-13G75 Reference 9.1, Figurn AlOB-4504L-15G75 Reference 9.1, Figure Al OT-4306L-1 6G65 Reference 9.1, Figur( Al OT-4305L-1 6G75 Reference 9.1, Figure Al OB-4507L-1 5G75 Reference 9.1, Figur Al OB-4504L-1 6G75 Reference 9.1, Figurf Axial Enrichment Distribution Reference 9.1, Figures 2 Burnable Absorber Distribution Reference 9.1, Figures 2 Non-Fueled Rods Reference 9.1, Figures 2 Neutronic Design Parameters Tal Fuel Storage LaSalle New Fuel Storage Vault Referen The LSA-2 Reload Batch fuel designs meet the fuel design limitations defined in Table 2.1 of Reference 9.5 and therefore can be safely stored in the vault. LaSalle Unit 1 Spent Fuel Storage Pool (BORAL Racks) Referen The LSA-2 Reload Batch fuel designs meet the fuel design limitations defined in Table 2.1 of Reference 9.6 and therefore can be safely stored in the pool. LaSalle Unit 2 Spent Fuel Storage Pool (Boraflex Racks) Referen The LSA-2 Reload Batch fuel designs can be safely stored as long as the fuel assembly reactivity limitations defined in Reference 9.7 are met.wt% wt%eD.3 eD.2 eD.1 eD.6 SD.9 eD.8 9D.5-.1-2.2 .3-2.5 .3-2.4 ble 4.1 ice 9.5 ce 9.6 ce 9.7 Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 4-2 4.2 Core Nuclear Design Analysis 4.2.1 Core Configuration Figure 4.1 Core Exposure at EOC9, MWd/MTU 30498.7 (nominal value) Core Exposure at BOC10, MWd/MT 12896.0 (from nominal EOC9) Core Exposure at EOC10, MWd/MTU 31495.1 (licensing basis to EOFP) Core Exposure at EOC9, MWd/MTU 29998.6 (short window) Note: Analyses in this report are applicable for EOFP up to a core exposure of 31495.1 MWd/MTU.

4.2.2 Core Reactivity Characteristics for Short EOC9 Window Cold SDM values to be provided by Exelon. Standby boron liquid control system (SLCS) reactivity, with 1571 ppm equivalent boron: Cold conditions, bias adjusted k-eff (max.) 0.89416 Shutdown margin, (%Ak) 10.5 Note: LaSalle SLCS has B10 enriched to 45%. The SLCS analysis assumes 1571 ppm boron which is equivalent to 660 ppm with boron enriched to 45% B-1 0. 4.2.4 Core Hydrodynamic Stability Reference 8.8 and 9.15 LaSalle Unit 1 utilizes the BWROG Interim Corrective Actions (ICAs) to address thermal hydraulic instability issues. This is in response to Generic Letter 94-02. When the long term solution OPRM is fully implemented, the ICAs will remain as a backup to the OPRM system. In order to support the ICAs and remain cognizant of the relative stability of one cycle compared with previous cycles, decay ratios are calculated at various points on the power to flow map and at various points in the cycle. This satisfies the following functions:

Framatome ANP, Inc.

EMF-2690 Revision 0 Paae 4-3 LaSalle Unit 1 Cvcle 10 Reload Analysis* Provides trending information to qualitatively compare the stability from cycle to cycle.

Provides decay ratio sensitivities to rod line and flow changes near the ICA regions.

Allows Exelon to review this information to determine if any administrative conservatisms are appropriate beyond the existing requirements.

The NRC approved STAIF computer code was used in the core hydrodynamic stability analysis performed in support of LaSalle Unit 1 Cycle 10. The power/flow state points used for this analysis were chosen to assist Exelon in performing the three functions described above. The Cycle 10 licensing basis control rod step-through projection was used to establish expected core depletion conditions.

For each power/flow point, decay ratios were calculated at multiple cycle exposures to determine the highest expected decay ratio throughout the cycle. The results from this analysis are shown below.Power* (%) Flow (%) Global Regional 31.6 31.5 0.44 0.37 40.1 45.0 0.25 0.22 61.9 45.0 0.67 0.63 65.9 50.0 0.56 0.51 69.9 55.0 0.48 0.42 73.6 50.0 0.75 0.68 74.9 55.0 0.58 0.50 78.1 55.0 0.61 0.55 78.2 60.0 0.51 0.41 82.4 60.0 0.53 0.47 For reactor operation under conditions of power coastdown, single-loop operation, final feedwater temperature reduction (FFTR) and/or operation with feedwater heaters out of service, it is possible that higher decay ratios could be achieved than are shown for normal operation.

Note: % power is based on 3489 MWt as rated. % flow is based on 108.5 MIb/hr as rated.Framatome ANP, Inc.Paae 4-3 EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 4-4 Table 4.1 Neutronic Design Values Number of Fuel Assemblies 764 Rated Thermal Power, MWt 3489 Rated Core Flow, Mlbm/hr 108.5 Core Inlet Subcooling, Btu/Ibm 18.35 Moderator Temperature, OF 548.8 Channel Thickness, inch 0.100 Fuel Assembly Pitch, inch 6.0 Wide Water Gap Thickness, inch 0.261 Narrow Water Gap Thickness, inch 0.261 Control Rod Data* Absorber Material B 4 C Total Blade Support Span, inch 1.580 Blade Thickness, inch 0.260 Blade Face-to-Face Internal Dimension, inch 0.200 Absorber Rod OD, inch 0.188 Absorber Rod ID, inch 0.138 Percentage B 4 C, %TD 70 The control rod data represents original equipment control blades at LaSalle and were used in the neutronic calculations.

Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 4-5 J: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 I: 1 15*5 6 7 7 6 7 7 6 7 7 6 6 5l 410 9 108106 610 810910 9106 5 5 56101110 6710 6 1 0 10 710 6 10 7 10 11 1065 6 456861060710 710 661 710 10 106 65 8 4 8 10 11 10 [1J 68 10 [ 119 10 10 9 10 8 10 11 10 85 9 5 6 10 9 10 6 10 8 10 6 10 7 11 6 10 10 6 11 7 10 6 10 8 10 6 10 9 10 6 5 10 6 10 6 10 7 10 7 10 6 10 7 11 6 10 6 6 10 6 11 7 10 6 10 7 10 7 10 6 10 6 11 6 9 10 9 10 7 10 6 10 7 10 6 10 7 10 10 7 10 6 10 7 1109 10 7 10[8 10 9 6 1 6 10 11 6 10 6 10 6 10 7 11 6 10 6 10 7 10 6 10 7 8 66 5 6 13 7 89 10 6 10 6 10 1 6 10 6 16 7 9 10 6 10 6[106[610

[ 06 10 6 10 [6 10 597 17 6 10 11 10 7 10 6 10 6 10 7 10 6 10 6 6 10 6 10 7 10 6 10 6 10 7 10 11 10 6 18 7 8 10 8 10 7 10 9 11 6 10 6 10 6 10 10 6 10 6 10 6 11 9 10 7 10 8 10 8 7 19 6 10 6 10 7 10 7 10 6 10 7 11 6 10 6 6 10 6 11 7 10 6 10 7 10 7 10 6 10 6 20 6 9 j17910 7 1J1 107[J 610 7 j 7110[j6710170610

~ 7 10[ r 9-1096 21 6 106 1 10 7 10 6 10 7 11 6 10 6 1 1 7 10 6 10 7 10 7 6 10 6 22 5610 106 10 6 7 10 6110 6110101610 61 10 106109 810 23 5 6 10 1 0 7110 6 10 710 10 6 61 10 9 10 7 10 1 10 6 5 24 5 lT76110 610 6107610-6 106r6-10106 10 6107610 671706 O6-1065 25 4591068 106 10610 1100666 1071 0761016106865409 25 6 10 11 10 7 7 10 6 10 7 10 10 7 10 6 10 7 10 11 10 6 5 27 6 109 11 10910810610810 10 910 28 8 10 10 6 10 11 10 1 1 10 10 11 10 6 10 8 5 4 29 55 6 10 9 108 10 99 10 8 1019 10 6 4 6 6 101 10, 5 Fuel Number Load "lveBundle Name of Bundles ID Ranuqe Cycle 4 GE9B-P8CWB343-12GZ-80M-150 13 YJD661-YJD764 8 5 GE9B-P8CWB342-10GZ-80M-150 33 YJD517-YJD660 8 6 SPCA9-393B-16GZ-100M 208 19A001-19A208 9 7 SPCA9-396B-12GZB-100M 88 19B209-19B296 9 8 SPCA9-384B-11GZ-80M 36 28B257-28B292 9 9 SPCA9-396B-1 2GZC-100 M 40 189C297-1 9C336 9 10 A 40-4039B-15GV15 296 30A001-30A296 10 11 A10-4037B-16GV75 50 30B297-30B346 10 Figure 4.1 LaSalle Unit I Cycle 10 Reference Loading Map Framatome ANP, Inc.

EMF-2690 Revision 0 P::l C% q-1 PýV~ -LaSalle Unit 1 Cycle 10 Reload Analvsis 5.0 Anticipated Operational Occurrences Applicable Disposition of Events Reference

9.8 Reference

9.4 5.1 Analysis of Plant Transients at Rated Conditions Limiting Transients:

Load Rejection No Bypass (LRNB) Feedwater Controller Failure (FWCF) Loss of Feedwater Heating (LFWH) Control Rod Withdrawal Error (CRWE)5.1.1 15,000 MWd/MTU Cycle Exposure Transient LRNB* FWCF LRNB" FWCF" LFWH CRWE Scram Speed TSSS TSSS NSS NSS Peak Neutron Flux (% Rated) 415 342 306 266 Peak Heat Flux (% Rated) 122 122 120 117 Peak Lower Plenum Pressure (psig) 1203 1166 1196 1160 ACPR ATRIUM-10/

ATRIUM-9B 0.35/0.33 0.33/0.30 0.32/0.31 0.29/0.25 0.21/0.21 0.19/0.19 5.1.2 EOC Licensing Exposure Transient LRNB t FWCF" LRNB t FWCF* LFWH CRWE Scram Speed TSSS TSSS NSS NSS Peak Neutron Flux (% Rated) 516 395 513 366 Peak Heat Flux (% Rated) 135 128 132 126 Peak Lower Plenum Pressure (psig) 1216 1177 1207 1168 ACPR ATRIUM-10

/ATRIUM-9B 0.39/0.33 0.33'/0.30' 0.36/0.32 0.29/0.27 0.21/0.21 0.19/0.19 Based on 100%P/105%F conditions.

Based on 100%P/81%F conditions.

The analysis results are from an earlier exposure in this cycle.Framatome ANP, Inc.t EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-2 5.2 Analysis for Reduced Flow Operation Reference

9.4 Limiting

Transient:

Slow Flow Excursion MCPRf Manual Flow Control Figure 5.1 ATRIUM-10 and ATRIUM-9B Fuel LHGRFACf Figure 5.2 ATRIUM-10 and ATRIUM-9B Fuel MCPRf and LHGRFACf results are applicable at all Cycle 10 exposures and in all EOD and EOOS scenarios presented in Table 1.1. 5.3 Analysis for Reduced Power Operation Reference

9.4 Limiting

Transient:

Load Rejection No Bypass (LRNB) Feedwater Controller Failure (FWCF) MCPRp Base Case Operation Tables 5.1-5.4 Figures 5.3-5.10 LHGRFACP Base Case Operation Tables 5.1-5.4 MCPRp, EOOS Conditions Tables 5.1-5.4 LHGRFACP, EOOS Conditions*

Tables 5.1-5.4 MAPFACP -All Operating Conditions*

<To be furnished by Exelon.> 5.4 ASME Overpressurization Analysis Reference

9.4 Limiting

Event MSIV Closure Worst Single Failure Valve Position Scram Maximum Vessel Pressure (Lower Plenum) 1346 psig Maximum Steam Dome Pressure 1321 psig 5.5 Control Rod Withdrawal Error The control rod withdrawal error event is analyzed at rated conditions, assuming no xenon and unblocked conditions.

The analysis further assumes that the plant is operating in the A2 or Al rod sequence.

The results bound low power operation.

The limiting ACPR for the CRWE analysis is 0.19. LHGRFACp values presented are applicable to FRA-ANP fuel. GE MAPFACP limits will continue to be applied to GE9 fuel at off-rated power.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-3 The core design complies with FRA-ANP's 1 % plastic strain and centerline melt criteria via conformance to the PAPT (Protection Against Power Transient)

LHGR limit. 5.6 Fuel Loading Error 5.6.1 Mislocated Fuel Assembly FRA-ANP has performed fuel mislocation error analyses for LaSalle Unit 1 Cycle 10. Based on these analyses, the offsite dose criteria (a small fraction of 10 CFR 100) is conservatively satisfied.

5.6.2 Misoriented

Fuel Bundle FRA-ANP has performed a bounding fuel misorientation analysis, which includes cores that load ATRIUM-9B and ATRIUM-10 fuel assemblies.

The analyses were performed assuming the limiting assembly was loaded in the worst orientation (rotated 1800) while producing sufficient power to be on the MCPR limit if it had been oriented correctly.

The analyses demonstrate that the small fraction of 10 CFR 100 offsite dose criteria is conservatively satisfied.

5.7 Determination

of Thermal Margins The results of the analyses presented in Sections 5.1-5.3 are used for the determination of the operating limit. Section 5.1 provides the results of analyses at rated conditions.

Section 5.2 provides for the determination of the MCPR and LHGR limits at reduced flow (MCPRf, Figure 5.1; LHGRFACf, Figure 5.2). Section 5.3 provides for the determination of the MCPR and LHGR limits at conditions of reduced power (Figures 5.3-5.10, Tables 5.1-5.4).

Exposure dependent limits are presented for base case operation and the EOD and EOOS scenarios presented in Table 1.1. Operating limits for the EOOS conditions are divided into three different scenarios.

EOOS Case 1 limits support operation with FHOOS or with the turbine bypass valves inoperable.

Case 1 limits also support operation with FHOOS and 1 stuck closed TCV. EOOS Case 2 limits support operation with any combination of TCV slow closure, no RPT or FHOOS. The Case 2 limits also support the same EOOS scenarios in combination with 1 stuck closed TCV. A third set of EOOS limits are provided to support operation with the turbine bypass valves inoperable in conjunction with 1 stuck closed TCV. Limits for single-loop operation with the same EOOS conditions are also provided.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis Pa e5 Cycle 10 power- and flow-dependent MCPR limits are presented for both ATRIUM-1 0 and ATRIUM-9B fuel. Since the GE9 fuel is in low power peripheral locations for L1C10, the ATRIUM-9B MCPR limits can be used for the GE9 fuel. LHGR and MAPLHGR limits for all three fuel types are discussed in Section 7.0.Framatome ANP, Inc.

EMF-2690 Revision 0 On,, 'nR LaSalle Unit 1 Cycle 10 Reload Analysis* Table 5.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU *,t Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition

(% rated) MCPRp LHGRFACp MCPRP LHGRFACp 0 2.70 0.75 2.70 0.77 Base 25 2.20 0.75 2.20 0.77 case 25 2.07 0.75 1.95 0.77 operation 60 1.52 1.00 1.50 1.00 100 1.43 1.00 1.42 1.00 0 2.86 0.66 2.70 0.69 EOOS 25 2.36 0.66 2.20 0.69 Case 1 25 2.36 0.66 2.15 0.69 (FHOOS* OR TBVOOS) 60 1.59 0.94 1.58 0.90 80 -- 0.94 -- 0.90 100 1.47 0.95 1.45 0.90 0 2.86 0.65 2.70 0.67 EOOS Case 2O 25 2.36 0.65 2.20 0.67 25 2.36 0.65 2.15 0.67 (Any combination of 80 1.81 0.88 1.86 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.88 1.67 0.79 100 1.54 0.89 1.52 0.79 0 2.86 0.66 2.70 0.69 25 2.36 0.66 2.20 0.69 TBVOOS with 1 stuck 25 2.36 0.66 2.15 0.69 closed TCV 60 1.59 0.77 1.58 0.77 80 -0.77 -- 0.77 100 1.47 0.83 1.45 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

S With or without 1 stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 Page 5-6 LaSalle Unit 1 Cycle 10 Reload Analysis Table 5.1 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTUt (Continued)

ATRIUM-10 Fuel ATRIUM-9B Fuel Power EOOS Condition

(% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.71 0.75 2.71 0.77 25 2.21 0.75 2.21 0.77 Single-Loop Operationt 25 2.08 0.75 1.96 0.77 60 1.53 1.00 1.51 1.00 100 1.44 1.00 1.43 1.00 0 2.87 0.66 2.71 0.69 SLO with 25 2.37 0.66 2.21 0.69 EOOS Case 1 25 2.37 0.66 2.16 0.69 60 1.60 0.94 1.59 0.90 (FHOOS* OR TBVOOS) 80 -- 0.94 -- 0.90 100 1.48 0.95 1.46 0.90 0 2.87 0.65 2.71 0.67 SLO with EOOS Case 2* 25 2.37 0.65 2.21 0.67 25 2.37 0.65 2.16 0.67 (Any combination of 80 1.82 0.88 1.87 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.88 1.68 0.79 100 1.55 0.89 1.53 0.79 0 2.87 0.66 2.71 0.69 25 2.37 0.66 2.21 0.69 SLO with TBVOOS and 25 2.37 0.66 2.16 0.69 1 stuck closed TCV 60 1.60 0.77 1.59 0.77 80 -- 0.77 -- 0.77 100 1.48 0.83 1.46 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. 1 GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 Page 5-7 LaSalle Unit 1 Cycle 10 Reload Analysis Table 5.2 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWdlMTU ", Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition

(% rated) MCPRP LHGRFACP MCPRP LHGRFACp 0 2.70 0.74 2.70 0.76 Base 25 2.20 0.74 2.20 0.76 case 25 2.15 0.74 1.96 0.76 operation 60 1.55 1.00 1.54 1.00 100 1.46 1.00 1.44 1.00 0 2.95 0.64 2.70 0.69 EQOS 25 2.45 0.64 2.20 0.69 Case 1 25 2.45 0.64 2.19 0.69 OR TBVOOS) 60 1.62 0.94 1.62 0.89 80 -- 0.94 -- 0.91 .100 1.51 0.95 1.48 0.92 0 2.95 0.64 2.70 0.67 EOOS Case 2O 25 2.45 0.64 2.20 0.67 25 2.45 0.64 2.19 0.67 (Any combination of 80 1.82 0.87 1.86 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.87 1.73 0.76 100 1.59 0.87 1.59 0.76 0 2.95 0.64 2.70 0.69 25 2.45 0.64 2.20 0.69 25 2.45 0.64 2.19 0.69 TBVOOS with 1 stuck 4 07 closed TCV 40 -- 0.77 -- 0.77 60 1.62 0.77 1.62 0.77 80 -- 0.77 -- 0.77 100 1.51 0.83 1.48 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 Page 5-8 LaSalle Unit 1 Cycle 10 Reload Analysis Table 5.2 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTUt (Continued)

Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition

(% rated) MCPRp LHGRFACP MCPRp LHGRFACP 0 2.71 0.74 2.71 0.76 25 2.21 0.74 2.21 0.76 Single-Loop Operationo 25 2.16 0.74 1.97 0.76 60 1.56 1.00 1.55 1.00 100 1.47 1.00 1.45 1.00 0 2.96 0.64 2.71 0.69 SLO with 25 2.46 0.64 2.21 0.69 EOOS Case 1 25 2.46 0.64 2.20 0.69 61.30.94 1.63 0.89 (FHOOSt OR TBVOOS) 60 1.63 80 -- 0.94 -- 0.91 100 1.52 0.95 1.49 0.92 0 2.96 0.64 2.71 0.67 SLO with EOOS Case 2ý 25 2.46 0.64 2.21 0.67 25 2.46 0.64 2.20 0.67 (Any combination of 80 1.83 0.87 1.87 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.87 1.74 0.76 100 1.60 0.87 1.60 0.76 0 2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 25 2.46 0.64 2.20 0.69 SLO with TBVOOS and 1 stuck closed TCV 40 -- 0.77 -- 0.77 60 1.63 0.77 1.63 0.77 80 -- 0.77 -- 0.77 100 1.52 0.83 1.49 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

With or without I stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 Pan e 5-9 LaSalle Unit 1 Cycle 10 Reload Analvsis Table 5.3 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC 1 Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition

(% rated) MCPRn LHGRFACp MCPRP LHGRFACp 0 2.70 0.75 2.70 0.76 Base 25 2.20 0.75 2.20 0.76 case 25 2.07 0.75 1.95 0.76 operation¢ 60 1.52 1.00 1.50 1.00 100 1.47 1.00 1.43 1.00 0 2.86 0.66 2.70 0.69 EOOS 25 2.36 0.66 2.20 0.69 Case 1 25 2.36 0.66 2.15 0.69 (FHOOS* OR 60 1.59 0.94 1.58 0.90 TBVOOS) 80 -- 0.94 -- 0.90 100 1.47 0.95 1.45 0.90 0 2.86 0.65 2.70 0.67 EOOS Case 2O 25 2.36 0.65 2.20 0.67 25 2.36 0.65 2.15 0.67 (Any combination of 80 1.81 0.84 1.86 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.84 1.67 0.79 100 1.59 0.84 1.58 0.79 0 2.86 0.65 2.70 0.69 25 2.36 0.65 2.20 0.69 TBVOOS with 1 stuck 25 2.36 0.65 2.15 0.69 closed TCV 60 1.59 0.77 1.58 0.77 80 -- 0.77 -- 0.77 100 1.47 0.83 1.45 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 Page 5-10 LaSalle Unit 1 Cycle 10 Reload Analysis Table 5.3 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC*,t (Continued)

Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition

(% rated) MCPRp LHGRFACp MCPRn LHGRFACp 0 2.71 0.75 2.71 0.76 25 2.21 0.75 2.21 0.76 Operationt 25 2.08 0.75 1.96 0.76 60 1.53 1.00 1.51 1.00 100 1.48 1.00 1.44 1.00 0 2.87 0.66 2.71 0.69 SLO with 25 2.37 0.66 2.21 0.69 EOOS Case 1 25 2.37 0.66 2.16 0.69 61.00.94 1.59 0.90 (FHOOS' OR TBVOOS) 60 1.60 80 -- 0.94 -- 0.90 100 1.48 0.95 1.46 0.90 0 2.87 0.65 2.71 0.67 SLO with EOOS Case 2t 25 2.37 0.65 2.21 0.67 25 2.37 0.65 2.16 0.67 (Any combination of 80 1.82 0.84 1.87 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.84 1.68 0.79 100 1.60 0.84 1.59 0.79 0 2.87 0.65 2.71 0.69 25 2.37 0.65 2.21 0.69 SLO with TBVOOS and 25 2.37 0.65 2.16 0.69 1 stuck closed TCV 60 1.60 0.77 1.59 0.77 80 -- 0.77 -- 0.77 100 1.48 0.83 1.46 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

$ With or without 1 stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 Paqe 5-11 LaSalle Unit 1 Cycle 10 Reload Analvsis Table 5.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC't Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition

(% rated) MCPRp LHGRFACp MCPRP LHGRFACp 0 2.70 0.74 2.70 0.76 Base 25 2.20 0.74 2.20 0.76 case 25 2.15 0.74 1.96 0.76 operation 60 1.55 1.00 1.54 1.00 100 1.50 1.00 1.44 1.00 0 2.95 0.64 2.70 0.69 EGOS 25 2.45 0.64 2.20 0.69 Case 1 25 2.45 0.64 2.19 0.69 61.20.94 1 .62 0.89 (FHOOS' OR TBVOOS) 60 1.62 80 -- 0.94 -- 0.91 100 1.51 0.95 1.48 0.92 0 2.95 0.64 2.70 0.67 EOOS Case 2O 25 2.45 0.64 2.20 0.67 25 2.45 0.64 2.19 0.67 (Any combination of 80 1.82 0.82 1.86 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.82 1.73 0.76 100 1.64 0.82 1.65 0.76 0 2.95 0.64 2.70 0.69 25 2.45 0.64 2.20 0.69 25 2.45 0.64 2.19 0.69 TBVOOS with 1 stuck closed TCV 40 -- 0.77 -- 0.77 60 1.62 0.77 1.62 0.77 80 -- 0.77 -- 0.77 100 1.51 0.83 1.48 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 PaQe 5-12 LaSalle Unit 1 Cycle 10 Reload Analysis Table 5.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC *, (Continued)

Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition

(% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.71 0.74 2.71 0.76 25 2.21 0.74 2.21 0.76 Single-Loop Operationt 25 2.16 0.74 1.97 0.76 60 1.56 1.00 1.55 1.00 100 1.51 1.00 1.45 1.00 0 2.96 0.64 2.71 0.69 SLO with 25 2.46 0.64 2.21 0.69 EOOS Case 1 25 2.46 0.64 2.20 0.69 60 1.63 0.94 1.63 0.89 (FHOOS¢ OR TBVOOS) 80 -- 0.94 -- 0.91 100 1.52 0.95 1.49 0.92 0 2.96 0.64 2.71 0.67 SLO with EOOS Case 2ý 25 2.46 0.64 2.21 0.67 25 2.46 0.64 2.20 0.67 (Any combination of 80 1.83 0.82 1.87 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.82 1.74 0.76 100 1.65 0.82 1.66 0.76 0 2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 25 2.46 0.64 2.20 0.69 SLO with TBVOOS and 1 stuck closed TCV 40 -- 0.77 -- 0.77 60 1.63 0.77 1.63 0.77 80 -- 0.77 -- 0.77 _ 100 1.52 0.83 1.49 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

¢ With or without 1 stuck closed TCV.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis Page 5-13 1.65 1.60 1.55 1.50 1.45 1.40 C. 2 1.35 1.30 1.25 1.20 1.15 1.10 0 10 20 30 40 50 60 70 80 90 100 110 Flow (% rated)Flow MCPRf MCPRf (% of rated) ATRIUM-10 ATRIUM-9B*

0 1.63 1.63 30 1.63 1.63 100 1.19 1.19 105 1.11 1.11 Figure 5.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode GE9 fuel assemblies will use the ATRIUM-9B MCPR limits.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-14 1.10 1.00 0.90 S0.80 -J 0.70 0.60 0.50 0 10 20 30 40 50 60 70 80 90 100 11C Flow (% rated)Flow (% rated)0 30 68 105 LHGRFACf 0.72 0.72 1.00 1.00 Figure 5.2 Flow Dependent LHGR Multipliers for ATRIUM-10 and ATRIUM-9B Fuel GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-15 2.75 2.65 2.55 2.45 2.35 2.25 2.15 S2.05 a. 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 70 60 90 100 110 Power (% rated)Power MCPRP (%) Limit 100 1.43 60 1.52 25 2.07 25 2.20 0 2.70 Figure 5.3 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-16 a. a.2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRP (%) Limit 100 1.42 60 1.50 25 1.95 25 2.20 0 2.70 Figure 5.4 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis Page 5-17 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 C. W 2.05 a, M 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRp (%) Limit 100 1.46 60 1.55 25 2.15 25 2.20 0 2.70 Figure 5.5 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-18 0. 0.0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRP (%) Limit 100 1.44 60 1.54 25 1.96 25 2.20 0 2.70 Figure 5.6 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-19 C.0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRp (%) Limit 100 1.47 60 1.52 25 2.07 25 2.20 0 2.70 Figure 5.7 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-20 a. 0. U 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRp (%) Limit 100 1.43 60 1.50 25 1.95 25 2.20 0 2.70 Figure 5.8 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-21 a. 0.0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRp (%) Limit 100 1.50 60 1.55 25 2.15 25 2.20 0 2.70 Figure 5.9 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-22 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 C. S2.05 a. 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRp (%) Limit 100 1.44 60 1.54 25 1.96 25 2.20 0 2.70 Figure 5.10 15,000 MWdlMTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0 cil a -U LaSalle Unit 1 Cycle 10 Reload Analysis 6.0 Postulated Accidents 6.1 Loss-of-Coolant Accident 6.1.1 Break Location Spectrum References 9.9 and 9.10 6.1.2 Break Size Spectrum References 9.9 and 9.10 6.1.3 MAPLHGR Analyses ATRIUM-9B Fuel: The MAPLHGR limits presented in Reference 9.11 are valid for LaSalle Unit 1 ATRIUM-9B (LSA-1) fuel for Cycle 10 operation.

Limiting Break: 1.1 ft 2 Break Recirculation Pump Discharge Line High Pressure Core Spray Diesel Generator Single Failure ATRIUM-10 Fuel: The MAPLHGR limits presented in Reference 9.12 are valid for LaSalle Unit 1 ATRIUM-10 (LSA-2) fuel for Cycle 10 operation.

Limiting Break: 1.0 ft 2 Break Recirculation Pump Suction Line High Pressure Core Spray Diesel Generator Single Failure The ATRIUM-9B PCT results reported in Reference 9.13 remain applicable for Cycle 10. The ATRIUM-9B MAPLHGR limits have been extended to a planar exposure of 64.3 GWd/MTU as shown in Section 7.2.1. The ATRIUM-10 PCT results reported in Reference 9.12 are applicable for Cycle 10. The LOCA/heatup analysis results for LaSalle Unit 1 Cycle 10 are presented below (References 9.12 and 9.13). (Note that the MCPR value used in the LOCA analyses for both ATRIUM-10 and ATRIUM-9B fuel is less than the rated power MCPR limits presented in Section 5.0.)ATRIUM-9B Fuel ATRIUM-10 Fuel Maximum PCT ("F) 1827 1807 Peak Local Metal-Water Reaction (%) 0.79 0.69 The maximum core wide metal-water reaction for both ATRIUM-10 and ATRIUM-9B fuel is <0.16%. The peak local metal water reaction result is consistent with the limiting PCT analysis results reported in Reference 9.13.Frarnatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 6-2 6.2 Control Rod Drop Accident LaSalle is a banked position withdrawal sequence (BPWS) plant. In order to allow the site the option of inserting control rods using the simplified shutdown control rod sequences shown in Figures 6.1 and 6.2, a CRDA was performed for the simplified sequences.

The results from these simplified sequence analyses (one each for operating in A2 or Al sequence), bound those where BPWS guidelines are followed.

The CRDA analysis demonstrate that the maximum deposited fuel rod enthalpy is less than the NRC limit of 280 cal/g and that the predicted number of fuel rods which exceed the damage threshold of 170 cal/gm is less than 850 for FRA-ANP fuel and 770 for GE fuel (in LaSalle UFSAR Chapter 15 radiological assessment).

Maximum Dropped Control Rod Worth, %Ak 1.12 Doppler Coefficient, Ak/k/°F -1OE-6 Effective Delayed Neutron Fraction 0.00543 Four-Bundle Local Peaking Factor 1.35 Maximum Deposited Fuel Rod Enthalpy, cal/gm 203 Number of Rods Greater than 170 cal/g 286 Framatome ANP, Inc.

EMF-2690 Revision 0 La~ale nit1 Ccle10 elod Aalyis 1j:, -L LaSalle Unit 1 Cycle 10 Reload Analvsis Table 6.1 Simplified Shutdown Sequence from an Al Rod Pattern Rod Group Insertion Comment 7 or 8 48-00 Either group 7 or 8 may be inserted first. 10 48-00 Groups 7 and 8 must be fully inserted prior to inserting any Group 10 rod. 9 48-00 Group 10 must be fully inserted prior to inserting any Group 9 rod. 5 or 6 48-00 Groups 5 and 6 may be inserted without banking anytime after Groups 7 and 8 have been inserted and before Group 4 is inserted.

4 48-00 Groups 5 through 10 must be fully inserted prior to inserting any Group 4 rod. 3 48-00 Group 4 must be fully inserted prior to inserting any Group 3 rod. 2 48-00 Group 3 must be fully inserted prior to inserting any Group 2 rod. 1 48-00 Group 2 must be fully inserted prior to inserting any Group 1 rod.Framatome ANP, Inc.

EMF-2690 Revision 0 Pacie 6-4 LaSalle Unit 1 Cycle 10 Reload Analysis Table 6.2 Simplified Shutdown Sequence from an A2 Rod Pattern Rod Group Insertion Comment 9 or 10 48-00 Either group 9 or 10 may be inserted first. 8 48-00 Groups 9 and 10 must be fully inserted prior to inserting any Group 8 rod. 7 48-00 Group 8 must be fully inserted prior to inserting any Group 7 rod. 5 or 6 48-00 Groups 5 and 6 may be inserted without banking anytime after Groups 9 and 10 have been inserted and before Group 4 is inserted.

4 48-00 Groups 5 through 10 must be fully inserted prior to inserting any Group 4 rod. 3 48-00 Group 4 must be fully inserted prior to inserting any Group 3 rod. 2 48-00 Group 3 must be fully inserted prior to inserting any Group 2 rod. 1 48-00 Group 2 must be fully inserted prior to inserting any Group 1 rod.Frarnatorne ANP, Inc.

LaSalte Unit 1 Cycle 10 Reload L a ... .........

..-.-... a l rage ,- I 7.0 Technical Specifications

7.1 Limiting

Safety System Settings 7.1.1 MCPR Fuel Cladding Integrity Safety Limit MCPR Safety Limit (all fuel) -two-loop operation 1.11 MCPR Safety Limit (all fuel) -single-loop operation 1.12 7.1.2 Steam Dome Pressure Safety Limit Pressure Safety Limit 1325 psig 7.2 Limiting Conditions for Operation

7.2.1 Average

Planar Linear Heat Generation Rate References 9.11, 9.12 and 9.16 ATRIUM-10 Fuel MAPLHGR Limits ATRIUM-9B Fuel MAPLHGR Limits Average Planar Average Planar Exposure MAPLHGR Exposure MAPLHGR (GWd/MTU) (kW/ft) (GWd/MTU) (kW/ft) 0.0 12.5 0.0 13.5 15.0 12.5 20.0 13.5 55.0 9.1 64.31 9.07 64.0 7.6 GE9 Fuel MAPLHGR Limits < To be furnished by Exelon. >Single Loop Operation MAPLHGR Multiplier for ATRIUM-10 and ATRIUM-9B Fuel is 0.90 References 9.11 and 9.12 Includes the effects of channel bow, up to 2 TIPOOS (or the equivalent number of TIP channels), a 2500 EFPH LPRM calibration interval, cycle startup with uncalibrated LPRMs (BOC to 500 MWd/MTU) and up to 50% of the LPRMs out of service.

Exposure extended to 64.3 GWd/MTU to support exposure extension for ATRIUM-9B fuel presented in Reference 9.14.Framatome ANP, Inc.EMF-2690 Revision 0 EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 7-2 7.2.2 Minimum Critical Power Ratio Flow Dependent MCPR Limits: Manual Flow Control Power Dependent MCPR Limits: Base Case Operation

-NSS Insertion Times Base Case Operation

-TSSS Insertion Times EOD and EOOS Operation

7.2.3 Linear

Heat Generation Rate ATRIUM-10 Fuel Steady-State LHGR Limits Figure 5.1 Figures 5.3, 5.4, 5.7 and 5.8 Figures 5.5, 5.6, 5.9 and 5.10 Tables 5.1-5.4 References 9.2 and 9.14 ATRIUM-9B Fuel Steady-State LHGR Limits Average Planar Average Planar Exposure LHGR Exposure LHGR (GWd/MTU) (kW/ft) (GWd/MTU) (kW/ft) 0.0 13.4 0.0 14.4 15.0 13.4 15.0 14.4 55.0 9.1 64.3 7.9 64.0 7.3 GE9 Fuel Steady-State LHGR Limits < To be furnished by Exelon. >The protection against power transient (PAPT) linear heat generation rate curves for ATRIUM-10 and ATRIUM-9B fuel are identified in References 9.2 and 9.14, respectively.

Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 7-3 ATRIUM-10 Fuel PAPT LHGR Limits ATRIUM-9B Fuel PAPT LHGR Limits Average Planar Average Planar Exposure LHGR Exposure LHGR (GWd/MTU) (kW/ft) (GWd/MTU) (kW/ft) 0.0 18.1 0.0 19.4 15.0 18.1 15.0 19.4 55.0 12.2 64.3 10.6 64.0 9.8 ....LHGRFACf and LHGRFACp multipliers are applied directly to the steady-state LHGR limits at reduced power, reduced flow and/or EOD/EOOS conditions to ensure the PAPT LHGR limits are not violated during an AOO. LHGRFAC Multipliers for Off-Rated Conditions

-ATRIUM-10 and ATRIUM-9B Fuel: LHGRFACf LHGRFACP Figure 5.2 Tables 5.1-5.4 MAPFAC Multipliers for Off-Rated Conditions

-GE9 Fuel: MAPFACf MAPFACP"< To be furnished by Exelon. > "< To be furnished by Exelon. >Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 8-1 8.0 Methodology References See XN-NF-80-19(P)(A)

Volume 4 Revision 1 for a complete bibliography.

8.1 ANF-913(P)(A)

Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2:

A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990. 8.2 ANF-524(P)(A)

Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990. 8.3 ANF-1 125(P)(A) and ANF-1 125(P)(A), Supplements 1 and 2, ANFB Critical Power Correlation, Advanced Nuclear Fuels Corporation, April 1990. 8.4 EMF-1 125(P)(A)

Supplement 1 Appendix C, ANFB Critical Power Correlation Application for Co-Resident Fuel, Siemens Power Corporation, August 1997. 8.5 ANF-1 125(P)(A)

Supplement I Appendix E, ANFB Critical Power Correlation Determination of A TRIUMrm-9B Additive Constant Uncertainties, Siemens Power Corporation, September 1998. 8.6 EMF-2209(P)(A)

Revision 1, SPCB Critical Power Correlation, Siemens Power Corporation, July 2000. 8.7 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, Advanced Nuclear Fuels Corporation, November 1990. 8.8 EMF-CC-074(P)

Volume 4 Revision 0, BWR Stability Analysis:

Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 9-1 9.0 Additional References 9.1 EMF-2624(P)

Revision 1, Neutronic Design LaSalle Unit I Cycle 10 ATRIUMT-10 Fuel, Framatome ANP, Inc., September 2001. 9.2 EMF-2589(P)

Revision 0, Mechanical and Thermal-Hydraulic Design Report for LaSalle Units I and 2 A TRIUM T M-10 Fuel Assemblies, Framatome ANP, Inc., July 2001. 9.3 EMF-2249(P)

Revision 1, Fuel Design Report for LaSalle Unit I Cycle 9 A TRIUMrM-9B Fuel Assemblies, Siemens Power Corporation, September 1999. 9.4 EMF-2689 Revision 0, LaSalle Unit I Cycle 10 Plant Transient Analysis, Framatome ANP, Inc., January 2002. 9.5 EMF-2554(P), Criticality Safety Analysis forA TRIUM T M-10 Fuel, LaSalle Units I and 2 New Fuel Storage Vault, Framatome ANP, Inc., June 2001. 9.6 EMF-2556(P)

Revision 0, Criticality Safety Analysis for ATRIUM"-1O Fuel, LaSalle Unit I Spent Fuel Storage Pool (BORAL Rack), Framatome ANP, Inc., September 2001. 9.7 EMF-2650(P)

Revision 0, Criticality Safety Analysis for Fuel, LaSalle Unit 2 Spent Fuel Storage Pool (Boraflex Rack), Framatome ANP, Inc., November 2001. 9.8 Letter, D. E. Garber (FRA-ANP) to F. W. Trikur (Exelon), "Disposition of Events Summary for the Introduction of ATRIUM-10 T M-10 Fuel at LaSalle County Station," DEG:01:179, October 30, 2001. 9.9 EMF-2174(P), LOCA Break Spectrum Analysis for LaSalle Units I and 2, Siemens Power Corporation, March 1999. 9.10 EMF-2639(P)

Revision 0, LaSalle Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM T 1,-O Fuel, Framatome ANP, Inc., November 2001. 9.11 EMF-2175(P), LaSalle LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM T M-9B Fuel, Siemens Power Corporation, March 1999. 9.12 EMF-2641 (P) Revision 0, LaSalle Units I and 2 LOCA-ECCS Analysis MAPLHGR Limit forATRlUMTM,10 Fuel, Framatome ANP, Inc., November 2001. 9.13 Letter, D. E. Garber (SPC) to F. W. Trikur (Exelon), 'Transmittal of 10 CFR 50.46 Reporting for LaSalle Units, Condition Report 9008, and CMR 2156," DEG:01:108, July 17, 2001. 9.14 EMF-2563(P)

Revision 1, Fuel Mechanical Design Report Exposure Extension for A TRIUMTx9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, Framatome ANP, Inc., August 2001.Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 9-2 9.15 Correspondence, S. A. Richards (NRC) to J. F. Mallay (SPC), "Supplement to Safety Evaluation and Technical Evaluation Report Clarifications for EMF-CC-074(P)

Volume 4 Revision 0, BWR Stability Assessment for STAIF with Input from MICROBURN-B2," November 30, 2000. 9.16 Letter, D. E. Garber (FRA-ANP) to F. W. Trikur (Exelon), "Responses to Exelon Comments -Extended Exposure for ATRIUM-9B Fuel," DEG:01:136, September 6, 2001.Framatome ANP, Inc.

EMF-2690 LaSalle Unit I Cycle 10 Reload Analysis Revision 0 Distribution D.G. Carr, 23 D. E. Garber (9) M.E. Garrett, 23 J. M. Haun, 34 J. M. Moose, 23 P. D. Wimpy, 34 Notification List (e-mail notification)

O.C. Brown M.T. Cross Framatome ANP, Inc.

Technical Requirements Manual -Appendix I L 1C 10 Reload Transient Analysis Results Attachment 3 LaSalle Unit 1 Cycle 10 Plant Transient Analysis LaSalle Unit I Cycle 10 Revision 0 jFRAMATOMEANP LaSalle Unit 1 Cycle 10 Plant Transient Analysis January 2002 EMF-2689 Revision 0 v'anceci Sv nce Framatome ANP, Inc.

Framatome ANP, Inc.ISSUED IN FRA-ANP ON-UNE DOCUMENT SYSTEM DATE:

LaSalle Unit 1 Cycle 10 Plant Transient Analysis Prepared: Reviewed:

Concurred:

Approved:

Approved: ccw_'D. G. Carr, Team Leader BWR Safety Analysis BWR Safety Analysis D. E. Garber, Manager Customer Projects M. E. Garrett, Manager BWR Safety Analysis 0. C. Brown, Manager BWR Neutronics R. E. Collingham, Manager BWR Reload Engineering

& Methods Development paj EMF-2689 Revision 0 Date /Dt 2 Date If;/o -z Date Date Date Date Date Customer Disclaimer Important Notice Regarding the Contents and Use of This Document Please Read Carefully Framatome ANP, Inc.'s warranties and representations concerning the subject matter of this document are those set forth in the agreement between Framatome ANP, Inc. and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such agreement, neither Framatome ANP, Inc. nor any person acting on its behalf: a. makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method, or process disclosed in this document will not infringe privately owned rights; or b. assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this document.

The information contained herein is for the sole use of the Customer.

In order to avoid impairment of rights of Framatome ANP, Inc. in patents or inventions which may be included in the information contained in this document, the recipient, by its acceptance of this document, agrees not to publish or make public use (in the patent use of the term) of such information until so authorized in writing by Framatome ANP, Inc. or until after six (6) months following termination or expiration of the aforesaid Agreement and any extension thereof, unless expressly provided in the Agreement.

No rights or licenses in or to any patents are implied by the furnishing of this document.

LaSalle Unit I Cycle 10 Plant Transient Analysis Nature of Changes Item Page Description and Justification

1. All This is a new document.Framatome ANP, Inc.EMF-2689 Revision 0 Paae i EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page ii Contents 1.0 Introduction

.................................................................................................................

1-1 2.0 Summary .....................................................................................................................

2-1 3.0 Transient Analysis for Thermal Margin -Base Case Operation

...................................

3-1 3.1 System Transients

...........................................................................................

3-1 3.1.1 Load Rejection No Bypass .................................................................

3-3 3.1.2 Feedwater Controller Failure ..............................................................

3-3 3.1.3 Loss of Feedwater Heating ................................................................

3-4 3.1.4 Control Rod W ithdrawal Error ............................................................

3-4 3.2 MCPR Safety Limit ...........................................................................................

3-5 3.3 Power-Dependent MCPR and LHGR Limits .....................................................

3-6 3.4 Flow-Dependent MCPR and LHGR Limits .......................................................

3-7 3.5 Nuclear Instrument Response ..........................................................................

3-8 4.0 Transient Analysis for Thermal Margin -Extended Operating Domain .........................

4-1 4.1 Increased Core Flow ........................................................................................

4-1 4.2 MELLLA Operations

.........................................................................................

4-1 4.3 Coastdown Analysis .........................................................................................

4-1 4.4 Combined Final Feedwater Temperature Reduction/Coastdown

.....................

4-2 5.0 Transient Analysis for Thermal Margin -Equipment Out-of-Service

.............................

5-1 5.1 EOOS Case 1 ..................................................................................................

5-2 5.1.1 Feedwater Heaters Out-of-Service (FHOOS) .....................................

5-2 5.1.2 Turbine Bypass Valves Out-of-Service (TBVOOS) .............................

5-2 5.2 EOOS Case 2 ..................................................................................................

5-3 5.2.1 Recirculation Pump Trip Out-of-Service (No RPT) .............................

5-3 5.2.2 Slow Closure of the Turbine Control Valve .........................................

5-4 5.2.3 Combined FHOOS/TCV Slow Closure and/or No RPT .......................

5-4 5.3 Single-Loop Operation (SLO) ...........................................................................

5-5 5.4 1 Stuck Closed Turbine Control Valve ..............................................................

5-5 6.0 Transient Analysis for Thermal Margin -EOD/EOOS Combinations

............................

6-1 7.0 Maximum Overpressurization Analysis ........................................................................

7-1 7.1 Design Basis ....................................................................................................

7-1 7.2 Pressurization Transients

.................................................................................

7-1 8.0 References

..................................................................................................................

8-1 Appendix A Power-Dependent LHGR Lim it Generation

...............................................

A-1 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page iii Tables 1.1 EO D and EOO S O perating Conditions

........................................................................

1-3 2.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU .........................................................

2-3 2.2 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU .......................................................

2-5 2.3 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC .........................................................

2-7 2.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC .......................................................

2-9 3.1 LaSalle Unit 1 Plant Parameters for the System Transient Analyses at R ated Pow er and Flow ................................................................................................

3-9 3.2 Scram Speed Insertion Tim es ....................................................................................

3-10 3.3 15,000 MWd/MTU Base Case LRNB Transient Results .............................................

3-11 3.4 EOC Base Case LRNB Transient Results ..................................................................

3-12 3.5 15,000 MWd/MTU Base Case FWCF Transient Results ............................................

3-13 3.6 EOC Base Case FWCF Transient Results .................................................................

3-14 3.7 Loss of Feedwater Heating Base Case Transient Analysis Results ............................

3-15 3.8 Input for M CPR Safety Lim it Analysis .........................................................................

3-16 3.9 Flow -Dependent M CPR Results .................................................................................

3-17 5.1 EOOS Case 1 Analysis Results -15,000 MWd/MTU ..................................................

5-7 5.2 EOOS Case 1 Analysis Results -EOC .......................................................................

5-9 5.3 EOOS Case 2 Analysis Results -15,000 MWd/MTU .................................................

5-11 5.4 EOOS Case 2 Analysis Results -EOC ......................................................................

5-13 5.5 1 TCV Stuck Closed Analysis Results -15,000 MWd/MTU ........................................

5-15 5.6 1 TCV Stuck Closed Analysis Results -EOC .............................................................

5-18 7.1 ASME Overpressurization Analysis Results 102%P/105%F

........................................

7-2 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page iv Figures 1.1 LaSalle County Nuclear Station Power / Flow Map ......................................................

1-4 2.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode ...................................

2-11 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-10 and ATRIUM-9B F u e l ............................................................................................................................

2 -1 2 3.1 EOC Load Rejection No Bypass at 100/105 -TSSS Key Parameters

........................

3-18 3.2 EOC Load Rejection No Bypass at 100/105 -TSSS Vessel Water Level ...................

3-19 3.3 EOC Load Rejection No Bypass at 100/105 -TSSS Dome Pressure ........................

3-20 3.4 EOC Feedwater Controller Failure at 100/105 -TSSS Key Parameters

.....................

3-21 3.5 EOC Feedwater Controller Failure at 100/105 -TSSS Vessel Water Le ve l ...........................................................................................................................

3 -2 2 3.6 EOC Feedwater Controller Failure at 100/105- TSSS Dome Pressure .....................

3-23 3.7 Radial Power Distribution for SLMCPR Determination

................................................

3-24 3.8 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors A10-4039B 15GV75 With Channel Bow (Assembly Exposure of 1000 MWd/MTU) .......................

3-25 3.9 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors A10-4037B 16GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU) .........................

3-26 3.10 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times ...............................................................

3-27 3.11 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ...............................................................

3-28 3.12 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times .............................................................

3-29 3.13 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times .............................................................

3-30 3.14 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times ...............................................................

3-31 3.15 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ...............................................................

3-32 3.16 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times .............................................................

3-33 3.17 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times .............................................................

3-34 3.18 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times ..............................................

3-35 Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page v 3.19 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times ..............................................

3-36 3.20 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times ............................................

3-37 3.21 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times ............................................

3-38 3.22 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times ..............................................

3-39 3.23 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times ..............................................

3-40 3.24 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times ............................................

3-41 3.25 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel- TSSS Insertion Times ............................................

3-42 5.1 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times .....................................................

5-21 5.2 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times ..............................................

5-22 5.3 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ....................................................

5-23 5.4 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times ..............................................

5-24 5.5 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times ...................................................

5-25 5.6 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times ............................................

5-26 5.7 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times ...................................................

5-27 5.8 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times ............................................

5-28 5.9 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times .....................................................

5-29 5.10 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times ..............................................

5-30 5.11 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ....................................................

5-31 5.12 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times ..............................................

5-32 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page vi 5.13 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel- TSSS Insertion Times ...................................................

5-33 5.14 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times ............................................

5-34 5.15 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times ...................................................

5-35 5.16 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times ............................................

5-36 5.17 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-1 0 Fuel -NSS Insertion Times .....................................................

5-37 5.18 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times ..............................................

5-38 5.19 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ....................................................

5-39 5.20 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times ..............................................

5-40 5.21 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel- TSSS Insertion Times ...................................................

5-41 5.22 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-1 0 Fuel -TSSS Insertion Times ............................................

5-42 5.23 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times ...................................................

5-43 5.24 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times ............................................

5-44 5.25 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times .....................................................

5-45 5.26 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times ..............................................

5-46 5.27 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times ....................................................

5-47 5.28 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times ..............................................

5-48 5.29 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times ...................................................

5-49 5.30 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times ............................................

5-50 5.31 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times ...................................................

5-51 5.32 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times ............................................

5-52 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page vii 5.33 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times .................

5-53 5.34 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times .................

5-54 5.35 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion T im e s .........................................................................................................................

5-5 5 5.36 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion T im e s .........................................................................................................................

5-5 6 5.37 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times .................

5-57 5.38 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times .................

5-58 5.39 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion T im e s .........................................................................................................................

5-5 9 5.40 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion T im e s .........................................................................................................................

5-6 0 7.1 Overpressurization Event at 102/105 -MSIV Closure Key Parameters

..........................

7-3 7.2 Overpressurization Event at 102/105 -MSIV Closure Vessel Water Level .....................

7-4 7.3 Overpressurization Event at 102/105 -MSIV Closure Lower-Plenum P ressu re ......................................................................................................................

7-5 7.4 Overpressurization Event at 102/105 -MSIV Closure Dome Pressure ..........................

7-6 7.5 Overpressurization Event at 102/105 -MSIV Closure Safety/Relief Valve F low R ates .................................................................................................................

7-7 Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis Nomenclature anticipated operational occurrence critical power ratio effective full power hours end of cycle extended operating domain end of full power equipment out-of-service final feedwater temperature reduction feedwater heater out-of-service Framatome ANP, Inc. feedwater controller failure heat flux ratio increased core flow L1C10 LHGR LHGRFACf LHGRFACp LHGROL LOFH LPRM LRNB MAPFACf MAPFACp MCPR MCPRf MCPRP MELLLA MFC MSIV NSS NRC PAPT RPT LaSalle Unit 1 Cycle 10 linear heat generation rate flow-dependent linear heat generation rate factors power-dependent linear heat generation rate factors linear heat generation rate operating limit loss of feedwater heating local power range monitor generator load rejection with no bypass flow-dependent maximum average planar linear heat generation rate multiplier power-dependent maximum average planar linear heat generation rate multiplier minimum critical power ratio flow-dependent minimum critical power ratio power-dependent minimum critical power ratio maximum extended load line limit analysis manual flow control main steam isolation valve nominal scram speed Nuclear Regulatory Commission, U.S. protection against power transient recirculation pump trip Framatome ANP, Inc.EMF-2689 Revision 0 Page viii AOO CPR EFPH EOC EOD EOFP EOOS FFTR FHOOS FRA-ANP FWCF HFR ICF EMF-2689 Revision 0 Page viii EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page ix Nomenclature (Continued)

SLMCPR safety limit MCPR SLO single-loop operation SRV safety/relief valve SRVOOS safety/relief valve out-of-service SSLHGR steady-state LHGR TBVOOS turbine bypass valve out-of-service TCV turbine control valve TIP traversing incore probe TIPOOS tip machine(s) out-of-service TSSS technical specification scram speed TSV turbine stop valve TTNB turbine trip with no bypass ACPR change in critical power ratio Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 1-1 1.0 Introduction This report presents results of the plant transient analyses performed by Framatome ANP, Inc. (FRA-ANP) as part of the reload safety analyses to support LaSalle Unit 1 Cycle 10 (LIC1O) operation.

The Cycle 10 core contains 346 fresh ATRIUMTM-10*

assemblies, 372 previously loaded ATRIUM-9B assemblies, and 46 previously loaded GE9 assemblies (all in peripheral locations).

Those portions of the reload safety analysis for which Exelon has responsibility are presented elsewhere.

The scope of the transient analyses performed by FRA-ANP is presented in Reference

1. The analyses reported in this document were performed using the plant transient analysis methodology approved by the Nuclear Regulatory Commission (NRC) for generic application to boiling-water reactors (Reference 2). The transient analyses were performed in accordance with the NRC technical limitations as stated in the methodology (References 3-7, 12). Parameters for the transient analyses are documented in Reference

8. The Cycle 10 transient analysis consists of the calculation of the limiting transients identified in Reference 9 to support base case operationt for the power/flow map presented in Figure 1.1. Results are also presented to support operation in the extended operating domain (EOD) and equipment out-of-service (EOOS) scenarios identified in Table 1.1. The analysis results are used to establish operating limits to protect against fuel failures.

Minimum critical power ratio (MCPR) limits are established to protect the fuel from overheating during normal operation and anticipated operational occurrences (AOis). Power-dependent MCPR (MCPRp) limits are required in order to provide the necessary protection during operation at reduced power. Flow dependent MCPR (MCPRf) limits provide protection against fuel failures during flow excursions initiated at reduced flow. Cycle 10 power- and flow-dependent MCPR limits are presented to protect both ATRIUM-10 and ATRIUM-9B fuel. Since the GE9 fuel is in low power peripheral locations for L1C1O, the ATRIUM-9B MCPR limits can be used for the GE9 fuel. This conclusion is based on a MCPR evaluation of these assemblies in the design-basis step through.

ATRIUM is a trademark of Framatome ANP. t Base case operation is defined as two-loop operation within the standard operating domain, including the ICF and MELLLA regions, with all equipment in-service.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 1-2 Protection against violating the linear heat generation rate (LHGR) limits at rated and off-rated conditions is provided through the application of power- and flow-dependent LHGR factors (LHGRFACp and LHGRFACf, respectively).

These factors or multipliers are applied directly to the steady-state LHGR limit to ensure that the LHGR does not exceed the protection against power transient (PAPT) limit during postulated AQOs. Cycle 10 power- and flow-dependent LHGR multipliers are presented for ATRIUM-10 and ATRIUM-9B fuel. In addition, the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

Results of analyses that demonstrate compliance with the ASME Boiler and Pressure Vessel Code overpressurization limit are presented.

The results of the plant transient analyses are used in a subsequent reload analysis report (Reference

15) along with core and accident analysis results to justify plant operating limits and set points.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 1-3 Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions Increased core flow (ICF) Maximum extended load line limit analysis (MELLLA) Coastdown

-Currently not supported for LIC10 Final feedwater temperature reduction (FFTR) -Currently not supported for L1C10 Combined FFTR/coastdown

-Currently not supported for L1C10 Equipment Out-of-Service (EOOS) Conditions*

Feedwater heaters out-of-service (FHOOS) Single-loop operation (SLO) -recirculation loop out-of-service Turbine bypass valves out-of-service (TBVOOS) EOC recirculation pump trip out-of-service (no RPT) Turbine control valve (TCV) slow closure and/or no RPT Safety relief valve out-of-service (SRVOOS) Up to 2 TIP machines out-of-service or the equivalent number of TIP channels (100% available at startup) Up to 50% of the LPRMs out-of-service TCV slow closure, FHOOS, and/or no RPT 1 stuck closed turbine control valve

EOOS conditions are supported for EOD conditions as well as the standard operating domain. Each EOOS condition combined with 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of channels), 1 stuck closed turbine control valve and/or up to 50% of the LPRMs out-of-service is supported.

Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis (' 0c 0o 15 W 110 100 90 80 70 60 50 40 30 20 10 0 0 10 20 30 40 50 60 70 Percent of Rated Flow Figure 1.1 Framatome ANP, Inc.80 90 100 110 120 EMF-2689 Revision 0 Pm a 1-A P2n0 LaSalle County Nuclear Station Power / Flow Map EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 2-1 2.0 Summary The determination of the thermal limits (MCPR limits and LHGRFAC multipliers) for LaSalle Unit 1 Cycle 10 is based on analyses of the limiting operational transients identified in Reference

9. The transients evaluated are the generator load rejection with no bypass (LRNB), feedwater controller failure to maximum demand (FWCF), control rod withdrawal error (CRWE) and loss of feedwater heating (LOFH). Thermal limits identified for Cycle 10 operation include both MCPR limits and LHGRFAC multipliers.

The MCPR operating limits are established so that less than 0.1 % of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions and are based on a two-loop operation MCPR safety limit of 1.11. Even so, the results of the analysis support a two-loop operation MCPR safety limit of 1.09 and a single-loop operation MCPR safety limit of 1.10 for all fuel types in the Cycle 10 core. LHGRFAC multipliers are applied directly to the LHGR limits at reduced power and/or flow conditions to protect against fuel melting and overstraining of the cladding during an AOO. Exposure dependent operating limits are established to support operation from beginning of cycle (BOC) to 15,000 MWd/MTU and from 15,000 MWd/MTU to EOC. EOC for LaSalle Unit 1 Cycle 10 is defined as a core exposure of 31,495.1 MWd/MTU.

Operating limits are established to support both base case operation and the EOOS scenarios presented in Table 1.1. Operating limits are also established for the EOD and combined EOD/EOOS conditions presented in Table 1.1. Base case MCPRp limits and LHGRFACP multipliers are based on results presented in Section 3.0. Results presented in Sections 4.0-6.0 are used to establish the operating limits for operation in the EOD, EOOS, and combined EOD/EOOS scenarios.

Cycle 10 MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel that support base case operation and operation in the EOD, EOOS and combined EOD/EOOS scenarios are presented in Tables 2.1-2.4. Tables 2.1 and 2.2 present the limits and multipliers for nominal scram speed (NSS) insertion times and Technical Specifications scram speed (TSSS) insertion times for the Cycle 10 BOC-1 5,000 MWd/MTU exposure range. Tables 2.3 and 2.4 present the NSS and TSSS limits and multipliers for the Cycle 10 15,000 MWd/MTU EOC exposure range. Operating limits for the EOOS conditions are divided into three different scenarios.

EOOS Case 1 limits support operation with FHOOS or with the turbine bypass valves inoperable.

Case 1 limits also support operation with FHOOS and 1 stuck closed TCV. EOOS Case 2 limits support operation with any combination of TCV slow closure, no RPT or Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 2-2 FHOOS. The Case 2 limits also support the same EOOS scenarios in combination with 1 stuck closed TCV. A third set of EOOS limits are provided to support operation with the turbine bypass valves inoperable in conjunction with 1 stuck closed TCV. Limits for single-loop operation with the same EOOS conditions are also provided.

MCPRf limits for both ATRIUM-10 and ATRIUM-9B that protect against fuel failures during a slow flow excursion event in manual flow control are presented in Figure 2.1. Automatic flow control is not supported for LIClO. The MCPRf limits presented are applicable for all EOD and EOOS conditions presented in Table 1.1. The Cycle 10 LHGRFACf multipliers for ATRIUM-10 and ATRIUM-9B fuel are presented in Figure 2.2 and are applicable in all the EOD and EOOS scenarios presented in Table 1.1. The power excursion experienced by low-power peripheral fuel assemblies during an anticipated operational occurrence is very mild compared to centrally orificed fuel assemblies.

Since GE9 fuel will only be in peripheral locations, the MCPR safety limit will not be challenged by the GE9 fuel assemblies and using the ATRIUM-9B MCPR limits for the GE9 fuel provides the necessary protection.

In addition, the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

This conclusion is based on an evaluation of these assemblies in the design-basis step-through.

The results of the maximum overpressurization analyses show that the requirements of the ASME code regarding overpressure protection are met for Cycle 10. The analysis shows that the dome pressure limit of 1325 psig is not exceeded and the vessel pressure does not exceed the limit of 1375 psig. The results of the maximum overpressurization analyses are presented in Table 7.1.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 431 )Table 2.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU*, t EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRP LHGRFACp MCPRp LHGRFACp 0 2.70 0.75 2.70 0.77 Base 25 2.20 0.75 2.20 0.77 case 25 2.07 0.75 1.95 0.77 operationt 60 1.52 1.00 1.50 1.00 100 1.43 1.00 1.42 1.00 0 2.86 0.66 2.70 0.69 EOOS 25 2.36 0.66 2.20 0.69 Case 1 25 2.36 0.66 2.15 0.69 (FHOOSt OR 60 1.59 0.94 1.58 0.90 TBVOOS) 80 --- 0.94 --- 0.90 100 1.47 0.95 1.45 0.90 0 2.86 0.65 2.70 0.67 EOOS Case 2t 25 2.36 0.65 2.20 0.67 25 2.36 0.65 2.15 0.67 (Any combination of 80 1.81 0.88 1.86 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.88 1.67 0.79 100 1.54 0.89 1.52 0.79 0 2.86 0.66 2.70 0.69 25 2.36 0.66 2.20 0.69 TBVOOS 25 2.36 0.66 2.15 0.69 with 1 stuck closed TCV 60 1.59 0.77 1.58 0.77 80 --- 0.77 --- 0.77 100 1.47 0.83 1.45 0.80* Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 rage 44q Table 2.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU*t (Continued)

EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRP LHGRFACP MCPRP LHGRFACp 0 2.71 0.75 2.71 0.77 Single-loop 25 2.21 0.75 2.21 0.77 operation*

25 2.08 0.75 1.96 0.77 (SLO) 60 1.53 1.00 1.51 1.00 100 1.44 1.00 1.43 1.00 0 2.87 0.66 2.71 0.69 SLO with EOOS 25 2.37 0.66 2.21 0.69 Case 1 25 2.37 0.66 2.16 0.69 (FHOOS* OR 60 1.60 0.94 1.59 0.90 TBVOOS) 80 --- 0.94 --- 0.90 100 1.48 0.95 1.46 0.90 0 2.87 0.65 2.71 0.67 SLO with EOOS 25 2.37 0.65 2.21 0.67 Case 22 25 2.37 0.65 2.16 0.67 (Any combination of 80 1.82 0.88 1.87 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.88 1.68 0.79 100 1.55 0.89 1.53 0.79 0 2.87 0.66 2.71 0.69 SLO with 25 2.37 0.66 2.21 0.69 TBVOOS 25 2.37 0.66 2.16 0.69 AND 1 stuck 60 1.60 0.77 1.59 0.77 closed TCV 80 --- 0.77 --- 0.77 100 1.48 0.83 1.46 0.80* Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. SGE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACP multipliers used in Cycle 9 remain applicable.

t With or without 1 stuck closed TCV.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 0 r P .........ir-- A na £S-.J Table 2.2 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU* t EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRn LHGRFACP MCPRp LHGRFACp 0 2.70 0.74 2.70 0.76 Base 25 2.20 0.74 2.20 0.76 case 25 2.15 0.74 1.96 0.76 operation*

60 1.55 1.00 1.54 1.00 100 1.46 1.00 1.44 1.00 0 2.95 0.64 2.70 0.69 EOOS 25 2.45 0.64 2.20 0.69 Case 1 25 2.45 0.64 2.19 0.69 (FHOOS* OR 60 1.62 0.94 1.62 0.89 TBVOOS) 80 --- 0.94 --- 0.91 100 1.51 0.95 1.48 0.92 0 2.95 0.64 2.70 0.67 EOOS Case 2O 25 2.45 0.64 2.20 0.67 25 2.45 0.64 2.19 0.67 (Any combination of 80 1.82 0.87 1.86 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.87 1.73 0.76 100 1.59 0.87 1.59 0.76 0 2.95 0.64 2.70 0.69 25 2.45 0.64 2.20 0.69 TBVOOS 25 2.45 0.64 2.19 0.69 with I stuck 40 --- 0.77 --- 0.77 closed TCV 60 1.62 0.77 1.62 0.77 80 -- 0.77 --- 0.77 100 1.51 0.83 1.48 0.80* Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 P~ni. 2-R Table 2.2 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWdlMTU*t (Continued)

ECOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRP LHGRFACp MCPRp LHGRFACp 0 2.71 0.74 2.71 0.76 Single-loop 25 2.21 0.74 2.21 0.76 operationt 25 2.16 0.74 1.97 0.76 (SLO) 60 1.56 1.00 1.55 1.00 100 1.47 1.00 1.45 1.00 0 2.96 0.64 2.71 0.69 SLO with EOOS 25 2.46 0.64 2.21 0.69 Case 1 25 2.46 0.64 2.20 0.69 (FHOOSt OR 60 1.63 0.94 1.63 0.89 TBVOOS) 80 --- 0.94 --- 0.91 100 1.52 0.95 1.49 0.92 0 2.96 0.64 2.71 0.67 SLO with EOOS 25 2.46 0.64 2.21 0.67 Case 22 25 2.46 0.64 2.20 0.67 (Any combination of 80 1.83 0.87 1.87 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.87 1.74 0.76 100 1.60 0.87 1.60 0.76 0 2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 SLO with 25 2.46 0.64 2.20 0.69 TBVOOS AND 1 stuck 40 -- 0.77 --- 0.77 closed TCV 60 1.63 0.77 1.63 0.77 80 --- 0.77 --- 0.77 100 1.52 0.83 1.49 0.80* Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACP multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.S*Pane 2-6 LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Plant Transient Aage 9-7 Table 2.3 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC*' t EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.70 0.75 2.70 0.76 Base 25 2.20 0.75 2.20 0.76 case 25 2.07 0.75 1.95 0.76 operation*

60 1.52 1.00 1.50 1.00 100 1.47 1.00 1.43 1.00 0 2.86 0.66 2.70 0.69 EOOS 25 2.36 0.66 2.20 0.69 Case 1 25 2.36 0.66 2.15 0.69 (FHOOSý OR 60 1.59 0.94 1.58 0.90 TBVOOS) 80 --- 0.94 --- 0.90 100 1.47 0.95 1.45 0.90 0 2.86 0.65 2.70 0.67 EOOS Case 2ý 25 2.36 0.65 2.20 0.67 25 2.36 0.65 2.15 0.67 (Any combination of 80 1.81 0.84 1.86 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.84 1.67 0.79 100 1.59 0.84 1.58 0.79 TBVOOS with 1 stuck closed TCV 0 25 25 60 80 100 2.86 2.36 2.36 1.59 1.47 0.65 0.65 0.65 0.77 0.77 0.83 0.83 1.45 2.70 2.20 2.15 1.58 0.69 0.69 0.69 0.77 0.77 0.80 0.80* Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 lOnU n _J Table 2.3 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC*' t (Continued)

EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.71 0.75 2.71 0.76 Single-loop 25 2.21 0.75 2.21 0.76 operation*

25 2.08 0.75 1.96 0.76 (SLO) 60 1.53 1.00 1.51 1.00 100 1.48 1.00 1.44 1.00 0 2.87 0.66 2.71 0.69 SLO with EOOS 25 2.37 0.66 2.21 0.69 Case 1 25 2.37 0.66 2.16 0.69 (FHOOS* OR 60 1.60 0.94 1.59 0.90 TBVOOS) 80 --- 0.94 --- 0.90 100 1.48 0.95 1.46 0.90 0 2.87 0.65 2.71 0.67 SLO with EOOS 25 2.37 0.65 2.21 0.67 Case 22 25 2.37 0.65 2.16 0.67 (Any combination of 80 1.82 0.84 1.87 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.84 1.68 0.79 100 1.60 0.84 1.59 0.79 0 2.87 0.65 2.71 0.69 SLO with 25 2.37 0.65 2.21 0.69 TBVOOS 25 2.37 0.65 2.16 0.69 AND 1 stuck 60 1.60 0.77 1.59 0.77 closed TCV 80 --- 0.77 --- 0.77 100 1.48 0.83 1.46 0.80* Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 Table 2.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC* t EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.70 0.74 2.70 0.76 Base 25 2.20 0.74 2.20 0.76 case 25 2.15 0.74 1.96 0.76 operation*

60 1.55 1.00 1.54 1.00 100 1.50 1.00 1.44 1.00 0 2.95 0.64 2.70 0.69 EOOS 25 2.45 0.64 2.20 0.69 Case 1 25 2.45 0.64 2.19 0.69 (FHOOSt OR 60 1.62 0.94 1.62 0.89 TBVOOS) 80 --- 0.94 --- 0.91 100 1.51 0.95 1.48 0.92 0 2.95 0.64 2.70 0.67 EOOS Case 2* 25 2.45 0.64 2.20 0.67 25 2.45 0.64 2.19 0.67 (Any combination of 80 1.82 0.82 1.86 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.74 0.82 1.73 0.76 100 1.64 0.82 1.65 0.76 0 2.95 0.64 2.70 0.69 25 2.45 0.64 2.20 0.69 TBVOOS 25 2.45 0.64 2.19 0.69 with 1 stuck 40 --- 0.77 --- 0.77 closed TCV 60 1.62 0.77 1.62 0.77 80 --- 0.77 --- 0.77 100 1.51 0.83 1.48 0.80

Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

With or without 1 stuck closed TCV.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 2-10 Table 2.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC*. t (Continued)

EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition

(% rated) MCPRp LHGRFACp MCPRp LHGRFACn 0 2.71 0.74 2.71 0.76 Single-loop 25 2.21 0.74 2.21 0.76 operation*

25 2.16 0.74 1.97 0.76 (SLO) 60 1.56 1.00 1.55 1.00 100 1.51 1.00 1.45 1.00 0 2.96 0.64 2.71 0.69 SLO with EOOS 25 2.46 0.64 2.21 0.69 Case 1 25 2.46 0.64 2.20 0.69 (FHOOS* 60 1.63 0.94 1.63 0.89 ORTBVOOS) 80 --- 0.94 --- 0.91 100 1.52 0.95 1.49 0.92 0 2.96 0.64 2.71 0.67 SLO with EOOS 25 2.46 0.64 2.21 0.67 Case 22 25 2.46 0.64 2.20 0.67 (Any combination of 80 1.83 0.82 1.87 0.76 TCV slow closure, 80 1.75 0.82 1.74 0.76 no RPT OR FHOOS) 100 1.65 0.82 1.66 0.76 0 2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 SLO with 25 2.46 0.64 2.20 0.69 TBVOOS 40 --- 0.77 --- 0.77 AND 1 stuck closed TCV 60 1.63 0.77 1.63 0.77 80 --- 0.77 --- 0.77 100 1.52 0.83 1.49 0.80

Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map. t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

With or without 1 stuck closed TCV.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 Z2'u ..0 10 20 30 40 50 60 70 80 90 100 110 Flow (% rated)Flow MCPRf MCPRf (% of rated) ATRIUM-10 ATRIUM-9B*

0 1.63 1.63 30 1.63 1.63 100 1.19 1.19 105 1.11 1.11 Figure 2.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode

GE9 fuel assemblies will use the ATRIUM-9B MCPR limits.Framatome ANP, Inc.0. C)1.65 1.60 1.55 1.50 1.45 1.40 1.35 1.30 1.25 1.20 1.15 1.10 LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Pevs i-10 1.10 1.00 0.90 0.80 0.70 0.60 0.50 0 10 20 30 40 50 60 70 80 90 100 110 Flow (% rated)Flow (% rated) LHGRFACf*

0 0.72 30 0.72 68 1.00 105 1.00 Figure 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-10 and ATRIUM-9B Fuel

GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Pevin 01 3.0 Transient Analysis for Thermal Margin -Base Case Operation This section describes the analyses performed to determine the power- and flow-dependent MCPR and LHGR operating limits for base case operation at LaSalle Unit 1 Cycle 10. COTRANSA2 (Reference 4), XCOBRA-T (Reference 11), XCOBRA (Reference 7), and CASMO-3G/MICROBURN-B (Reference

3) are the major codes used in the thermal limits analyses as described in FRA-ANP's THERMEX methodology report (Reference

7) and neutronics methodology report (Reference 3). COTRANSA2 is a system transient simulation code, which includes an axial one-dimensional neutronics model that captures the effects of axial power shifts associated with the system transients.

XCOBRA-T is a transient thermal hydraulics code used in the analysis of thermal margins for the limiting fuel assembly.

XCOBRA is used in steady-state analyses.

The ANFB critical power correlation (Reference

6) is used to evaluate the thermal margin of the ATRIUM-9B fuel assemblies and the SPCB critical power correlation (Reference

12) is used for the ATRIUM-10 fuel. Fuel pellet-to-cladding gap conductance values are based on RODEX2 (Reference

13) calculations for the LaSalle Unit 1 Cycle 10 core configuration.

3.1 System

Transients System transient calculations have been performed to establish thermal limits to support L1C10 operation.

Reference 9 identifies the potential limiting events that need to be evaluated on a cycle-specific basis. The potentially limiting transients evaluated for Cycle 10 include the LRNB, FWCF, CRWE, and LOFH events. Other transient events are bound by the consequences of one of the limiting transients.

Reactor plant parameters for the system transient analyses are shown in Table 3.1 for the 100% power/1 00% flow conditions.

Additional plant parameters used in the analyses are presented in Reference

8. Analyses have been performed to determine power-dependent MCPR and LHGR limits that protect operation throughout the power/flow domain depicted in Figure 1.1. At LaSalle, direct scram and recirculation pump high- to low-speed transfer on turbine stop valve (TSV) and turbine control valve (TCV) position are bypassed at power levels less than 25% of rated. Reference 14 indicates that MCPR and LHGR limits need to be monitored at power levels greater than or equal to 25% of rated. As a result, all analyses used to establish base case MCPRp limits and LHGRFACp multipliers are performed with both direct scram and RPT operable for power levels at or above 25% of rated.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-2 The limiting exposure for rated power pressurization transients is typically at end of full power (EOFP) when the control rods are fully withdrawn.

To provide additional margin to the operating limits earlier in the cycle, analyses were also performed to establish operating limits at 15,000 MWd/MTU. Off-rated power analyses were performed at cycle exposures prior to EOC to ensure that the operating limits provide the necessary protection.

All pressurization transients assumed only the 11 highest set point safety relief valves (SRVs) were operable, consistent with the discussion in Section 7.0. In order to support operation with 1 SRV out-of-service, the pressurization transient analyses were performed with the lowest set point SRV out-of-service, which makes a total of 10 SRVs available.

The term, recirculation pump trip (RPT), is used synonymously with recirculation pump high- to low-speed transfer as it applies to pressurization transients.

During the high- to low-speed transfer, the recirculation pumps trip off line and coast. When they reach the low-speed setting, the pumps reengage at the low speed. The time it takes for the pumps to coast to the low speed condition is much longer than the duration of the pressurization transients.

Therefore, a recirculation pump trip has the same effect on pressurization transients as a recirculation pump high- to low-speed transfer.

Reductions in feedwater temperature of less than 20°F from the nominal feedwater temperature are considered base case operation, not an EOOS condition.

The reduced feedwater temperature is limiting for FWCF transients.

As a result, the base case FWCF results are based on a 20°F reduction in feedwater temperature.

The results of the system pressurization transients are sensitive to the scram speed used in the calculations.

To take advantage of average scram speeds faster than those associated with the Technical Specifications surveillance times, scram speed-dependent MCPRp limits and LHGRFACP multipliers are provided.

The NSS insertion times and the average scram speeds associated with the Technical Specifications surveillance times (identified as TSSS times) used in the analyses reported are presented in Reference 8 and reproduced in Table 3.2. The NSS MCPRp limits and LHGRFACp multipliers can only be applied if the scram speed surveillance tests meet the NSS insertion times. System transient analyses were performed to establish MCPRp limits and LHGRFACp multipliers for base case operation for both NSS and TSSS insertion times.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-3 3.1.1 Load Rejection No Bypass The load rejection causes a fast closure of the turbine control valve. The resulting compression wave travels through the steam lines into the vessel and creates a rapid pressurization.

The increase in pressure causes a decrease in core voids, which in turn causes a rapid increase in power. The fast closure of the turbine control valve also causes a reactor scram and a recirculation pump high- to low-speed transfer which helps mitigate the pressurization effects.

Turbine bypass system operation, which also mitigates the consequences of the event, is not credited.

The excursion of the core power due to the void collapse is terminated primarily by the reactor scram and revoiding of the core. The analysis assumed single-element feedwater level control; however, three-element feedwater level control will have an insignificant impact on thermal limit or pressure results. For manual feedwater level control, the feedwater control system response is slower than the pressurization event. As a result, using manual feedwater level control will also have an insignificant impact on thermal limit or pressure results.

The generator load rejection without turbine bypass system (LRNB) is a more limiting transient than the turbine trip no bypass (TTNB) transient.

The initial position of the TCV is such that it closes faster than the turbine stop valve. This more than makes up for any differences in the scram signal delays between the two events. LRNB analyses were performed for several power/flow conditions to support generation of the thermal limits. Tables 3.3 and 3.4 present the LRNB transient results for both TSSS and NSS insertion times for Cycle 10. For illustration, Figures 3.1-3.3 are presented to show the responses of various reactor and plant parameters during the LRNB event initiated at 100% of rated power and 105% of rated core flow with TSSS insertion times. 3.1.2 Feedwater Controller Failure The increase in feedwater flow due to a failure of the feedwater control system to maximum demand results in an increase in the water level and a decrease in the coolant temperature at the core inlet. The increase in core inlet subcooling causes an increase in core power. As the feedwater flow continues at maximum demand, the water level continues to rise and eventually reaches the high water level trip set point. The initial water level is conservatively assumed to be at the lower level operating range at 30 inches above instrument zero to delay the high level trip and maximize the core inlet subcooling that results from the FWCF. The high water level trip causes the turbine stop valves to close in order to prevent damage to the turbine from Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-4 excessive liquid inventory in the steam line. The valve closures create a compression wave that travels to the core causing a void collapse and subsequent rapid power excursion.

The closure of the turbine valves initiates a reactor scram and a recirculation pump high- to low-speed transfer.

In addition, the turbine bypass valves are assumed operable and provide some pressure relief. The core power excursion is mitigated in part by the pressure relief, but the primary mechanisms for termination of the event are reactor scram and revoiding of the core. FWCF analyses were performed for several power/flow conditions to support generation of the thermal limits. Tables 3.5 and 3.6 present the base case FWCF transient results for both TSSS and NSS insertion times for Cycle 10. For illustration, Figures 3.4-3.6 are presented to show the responses of various reactor and plant parameters during the FWCF event initiated at 100% of rated power and 105% of rated core flow with TSSS insertion times. 3.1.3 Loss of Feedwater Heating During the loss of feedwater heating (LOFH) event, there is an assumed 145 0 F decrease in the feedwater temperature.

The result is an increase in core inlet subcooling, which collapses voids thereby increasing the core power and shifting the axial power distribution toward the bottom of the core. As a result of the axial power shift and increased core power, voids begin to build up at the bottom of the core, acting as negative feedback to the void collapse process. The negative feedback moderates the core power increase.

The MICROBURN-B code is used to determine the change in MCPR and LHGR during the event. Analyses were performed for several cycle exposures to ensure that appropriate limits are set. Although there is a substantial increase in core thermal power during the event, the increase in steam flow is much less because a large part of the added power is used to overcome the increase in inlet subcooling.

The increase in steam flow is accommodated by the pressure control system via the TCVs or the turbine bypass valves so no pressurization occurs. The LOFH results are presented in Table 3.7. The PAPT LHGR limit was not exceeded in any of the analyses.

PAPT LHGR limits are presented in References 21 and 22. 3.1.4 Control Rod Withdrawal Error The control rod withdrawal error (CRWE) transient is hypothesized as an inadvertent reactor operator initiated withdrawal of a control rod. This withdrawal increases local power and core thermal power. This results in lowering the core MCPR. The CRWE transient is typically terminated by control rod blocks initiated by the rod block monitor, however, in determination of Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-5 the limiting ACPR for LI C1 0, no credit was taken for the rod block monitor. The limiting CRWE ACPR is 0.19 and the limiting fraction of LHGR is 1.22. A limiting fraction of LHGR less than 1.35 ensures that the PAPT LHGR limits for ATRIUM-10 and ATRIUM-9B fuel are not exceeded.

3.2 MCPR Safety Limit The MCPR safety limit is defined as the minimum value of the critical power ratio at which the fuel can be operated, with the expected number of rods in boiling transition not exceeding 0.1% of the fuel rods in the core. The MCPR safety limit for all fuel in the LaSalle Unit 1 Cycle 10 core was determined using the methodology described in Reference

5. The effects of channel bow on core limits are determined using a statistical procedure.

The mean channel bow is determined from the exposure of the fuel channels and measured channel bow data. CASMO-3G is used to determine the effect on the local peaking factor distribution.

Once the channel bow effects on the local peaking factors are determined, the impact on the core limits is determined in the MCPR safety limit analysis.

Further discussion of how the effects of channel bow are accounted for is presented in Reference

5. The main input parameters and uncertainties used in the safety limit analysis are listed in Table 3.8. The radial power uncertainty includes the effects of up to 2 TIPOOS or the equivalent number (42% of the total number of channels) of TIP channels (100% available at startup), up to 50% of the LPRMs out of-service, and an LPRM calibration interval of 2500 EFPH as discussed in References 16 and 19. The channel bow local peaking uncertainty is a function of the nominal and bowed local peaking factors and the standard deviation of the measured bow data. The determination of the safety limit explicitly includes the effects of channel bow and relies on the following assumptions:

Cycle 10 will not contain channels used for more than one fuel bundle lifetime.

The channel exposure at discharge will not exceed 50,000 MWd/MTU based on the fuel bundle average exposure.

The Cycle 10 core contains all CarTech-supplied channels.

Analyses were performed with input parameters (including the radial power and local peaking factor distributions) consistent with each exposure step in the design-basis step-through.

The analysis that produced the highest number of rods in boiling transition corresponds to a Cycle 10 exposure of 500 MWd/MTU. The radial power distribution corresponding to a Cycle 10 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-6 exposure of 500 MWd/MTU is shown in Figure 3.7. Eight fuel types were represented in the LaSalle Unit 1 Cycle 10 safety limit analysis:

two ATRIUM-10 fuel types loaded in Cycle 10 (A10-4039B-15GV75 and A10-4037B-16GV75);

four ATRI UM-9B fuel types loaded in Cycle 9 (SPCA9-384B-1 1 GZ-80M, SPCA9-393B-1 6GZ-1 OOM, SPCA9-396B-1 2GZB-1 0OM, and SPCA9-396B-12GZC-100M);

and two GE9 fuel types loaded in Cycle 8 (GE9B-P8CWB343 12GZ-80M-150 and G E9B-P8CWB342-10GZ-80M-150).

The local power peaking factors, including the effects of channel bow, at 70% void and assembly exposures consistent with a Cycle 10 exposure of 500 MWd/MTU are presented in Figures 3.8 and 3.9 for the Cycle 10 ATRIUM-10 fuel. The bowed local peaking factor data used in the MCPR safety limit analysis for fuel type A10-4039B-15GV75 is at an assembly average exposure of 1000 MWd/MTU. The data for fuel type Al 0-4037B-1 6GV75 is at an assembly average exposure of 500 MWd/MTU.

The results of the analysis support a two-loop operation MCPR safety limit of 1.09 and a single loop operation MCPR safety limit of 1.10 for all fuel types in the Cycle 10 core. However, the TLO and SLO MCPR safety limits used to establish the MCPR operating limits are 1.11 and 1.12 respectively, since they are the values currently in the Technical Specifications.

These results are applicable for all EOD and EOOS conditions presented in Table 1.1. A MCPR safety limit of 1.10 is needed to support startup with uncalibrated LPRMs for an exposure range of BOC to 500 MWd/MTU in both TLO and SLO. 3.3 Power-Dependent MCPR and LHGR Limits Figures 3.10 and 3.11 present the base case operation NSS ATRIUM-10 and ATRIUM-9B MCPRp limits for Cycle 10 for the BOC to 15,000 MWd/MTU exposure range. Figures 3.12 and 3.13 present the ATRI UM-10 and ATRIUM-9B MCPRP limits for base case operation with TSSS insertion times for the BOC to 15,000 MWd/MTU exposure range. The 15,000 MWd/MTU to EOC MCPRp for ATRIUM-10 and ATRIUM-9B fuel are presented in Figures 3.14 and 3.15 for NSS insertion times and Figures 3.16 and 3.17 for TSSS insertion times. The limits are based on the ACPR results from the limiting system transient analyses discussed above and a MCPR safety limit of 1.11. The pressurization transient analyses provide the necessary information to determine appropriate multipliers on the fuel design LHGR limit for ATRIUM-10 and ATRIUM-9B fuel to support off-rated power operation.

Application of the LHGRFACp multipliers to the steady-state Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 LHGR limit ensures that the LHGR during AQOs initiated at reduced power does not exceed the PAPT limits. The method used to calculate the LHGRFACp multipliers is presented in Appendix A. The results of the LRNB and FWCF analyses discussed above were used to determine the base case LHGRFACp multipliers.

The base case ATRIUM-10 and ATRIUM-9B LHGRFACp multipliers for BOC to 15,000 MWd/MTU are presented in Figures 3.18 and 3.19 for NSS insertion times and Figures 3.20 and 3.21 for TSSS insertion times. The 15,000 MWd/MTU to EOC LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel are presented in Figures 3.22 and 3.23 for NSS insertion times and Figures 3.24 and 3.25 for TSSS insertion times. In order to support operation of POWERPLEXO-II CMSS* below 25% core thermal power, representative limits are provided and have no impact on licensing since there is no requirement to monitor limits below 25% power. 3.4 Flow-Dependent MCPR and LHGR Limits Flow-dependent MCPR and LHGR limits are established to support operation at off-rated core flow conditions.

The limits are based on the CPR and heat flux changes experienced by the fuel during slow flow excursions.

The slow flow excursion event assumes a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically attainable by the equipment.

An uncontrolled increase in flow creates the potential for a significant increase in core power and heat flux. A conservatively steep flow run-up path was determined starting at a low-power/low-flow state point of 56.2%P/30%F increasing to the high-power/high-flow state point of 124.2%P/1 05%F. MCPRf limits are determined for the manual flow control (MFC) mode of operation for both ATRIUM-10 and ATRIUM-9B fuel. XCOBRA is used to calculate the change in critical power ratio during a two-loop flow run-up to the maximum flow rate. The MCPRf limit is set so that the increase in core power resulting from the maximum increase in core flow is such that the MCPR safety limit of 1.11 is not violated.

Calculations were performed for several initial flow rates to determine the corresponding MCPR values that put the limiting assembly on the MCPR safety limit at the high-flow condition at the end of the flow excursion.

POWERPLEX is a trademark of Framatome ANP registered in the United States and various other countries.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-8 Results of the MFC flow run-up analysis are presented in Table 3.9 for both ATRIUM-10 and ATRIUM-9B fuel. MCPRf limits that provide the required protection during MFC operation are presented in Figure 2.1. The Cycle 10 MCPRf limits were established such that they support base case operation and operation in the EOD, EOOS, and combined EOD/EOOS scenarios.

The MCPRf limits are valid for all exposure conditions during Cycle 10. Since a low- to high speed pump upshift is required to attain high-flow rates, for initial core flows less than 30% of rated, the limit is conservatively set equal to the 30% flow value. FRA-ANP has performed LHGRFACf analyses with the CASMO-3G/MICROBURN-B core simulator codes. The analysis assumes that the recirculation flow increases slowly along the limiting rod line to the maximum flow physically attainable by the equipment.

A series of flow excursion analyses were performed at several exposures throughout the cycle starting from different initial power/flow conditions.

Xenon is assumed to remain constant during the event. The LHGRFACf multipliers were established to ensure that the LHGR during the flow run-up does not violate the PAPT LHGR limit. Since a low- to high-speed pump upshift is required to attain high-flow rates, for initial core flows less than 30% of rated, the LHGRFACf multiplier is conservatively set equal to the 30% flow value. The LHGRFACf values as a function of core flow for the ATRIUM-10 and ATRIUM-9B fuel are presented in Figure 2.2. The Cycle 10 LHGRFACf multipliers were established to support base case operation and operation in the EOD, EOOS, and combined EOD/EOOS scenarios for all Cycle 10 exposure conditions.

3.5 Nuclear

Instrument Response The impact of loading ATRIUM-10 fuel into the LaSalle core will not affect the nuclear instrument response.

The neutron lifetime is an important parameter affecting the time response of the incore detectors.

The neutron lifetime is a function of the nuclear and mechanical design of the fuel assembly, the in-channel void fraction, and the fuel exposure.

The neutron lifetimes are similar for the FRA-ANP fuel types with typical values of 39(10-6) to 40(106) seconds for the ATRI U M-9B lattices and 37(10-6) to 43(10-6) seconds for the ATRIUM-10 bottom and top lattices, respectively, as calculated with the CASMO-3G code. Therefore, the neutron lifetimes are essentially equivalent as the core transitions to ATRIUM-10 fuel.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 3.1 LaSalle Unit I Plant Parameters for the System Transient Analyses at Rated Power and Flow Reactor thermal power (MWt) 3489 Total core flow (Mlbm/hr) 108.5 Core active flow* 94.8 Core bypass flow*, t 13.7 Core inlet enthalpy* (Btu/lbm) 523.9 Vessel pressures (psia) Steam dome 1001 Core exit (upper-plenum)*

1013 Lower-plenum*

1038 Turbine pressure (psia) 957 Feedwater/steam flow (Mlbm/hr) 15.145 Feedwater enthalpy* (Btu/Ibm) 406.6 Recirculating pump flow (per pump) (Mlbm/hr) 15.83 Core average gap coefficient (EOC)* (Btu/hr-ft 2-OF) 1959 Framatome ANP, Inc.EMF-2689 Revision 0 Paqe 3-9* Calculated values. t Includes water channel flow.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 Paae 3-10 Table 3.2 Scram Speed Insertion Times Control Rod TSSS NSS Position Time Time (notch) (sec) (sec) 48 (full-out) 0.00 0.00 48* 0.20* 0.20* 45 0.53 0.38 39 0.85 0.68 25 1.90 1.68 5 3.45 2.68 0 (full-in) 7.00 7.00* As indicated in Reference 8, the delay between scram signal and control rod motion is conservatively modeled. Sensitivity analyses indicate that using no delay provides slightly conservative results.Framatome ANP, Inc.Parie 3-10 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0I Table 3.3 15,000 MWd/MTU Base Case LRNB Transient Results Peak Peak Power/ ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp (% rated) (% rated) TSSS Insertion Times 100/105 0.35 1.03 0.33 1.00 415 122 100/100 0.34 1.02 0.33 1.00 390 122 100/81 0.35 1.03 0.31 1.00 318 121 80/105 0.35 1.04 0.34 1.00 335 97 80/57.2 0.37 1.07 0.32 1.00 217 95 60/105 0.32 1.07 0.33 1.00 219 72 60/35.1 0.18 1.16 0.23 1.11 108 66 40/105 0.25 1.14 0.26 1.08 99 46 25/105 0.19 1.22 0.18 1.19 42 27 NSS Insertion Times 100/105 0.32 1.03 0.31 1.00 306 120 100/100 0.31 1.02 0.30 1.00 323 120 100/81 0.29 1.03 0.23 1.00 308 117 80/105 0.32 1.06 0.30 1.00 284 94 80/57.2 0.25 1.12 0.18 1.06 169 89 60/105 0.30 1.08 0.30 1.00 195 70 60/35.1 0.09 1.23 0.10 1.20 79 61 40/105 0.24 1.15 0.24 1.10 94 45 25/105 0.18 1.22 0.17 1.20 41 27 Framatome ANP, Inc.

LaSalle Unit I Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Paae 3-12 Table 3.4 EOC Base Case LRNB Transient Results Peak Peak Power/ ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACn (% rated) (% rated) TSSS Insertion Times 100/105 0.35* 1.00 0.33 1.00 415* 122* 100/100 0.34 1.00 0.33 1.00 460 132 100/81 0.39 1.00 0.33 1.00 516 135 80/105 0.35* 1.02 0.34* 1.00 335* 97* 80/57.2 0.39 1.00 0.36 1.00 313 105 60/105 0.32* 1.06 0.33* 1.00 219* 72* 60/35.1 0.34 1.06 0.31 1.07 163 74 40/105 0.25* 1.14* 0.26* 1.08* 99* 46* 25/105 0.20 1.22* 0.18* 1.19* 42 28 NSS Insertion Times 100/105 0.33 1.00 0.32 1.00 435 128 100/100 0.34 1.00 0.32 1.00 439 129 100/81 0.36 1.00 0.32 1.00 513 132 80/105 0.32* 1.03 0.30* 1.00 284* 94* 80/57.2 0.34 1.03 0.30 1.00 277 101 60/105 0.30* 1.07 0.30* 1.00* 195* 70* 60/35.1 0.27 1.09 0.23 1.09 138 70 40/105 0.24* 1.15* 0.24* 1.10* 94* 45* 25/105 0.18* 1.22* 0.17* 1.20* 41* 27** The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Pane 3-13 Table 3.5 15,000 MWdlMTU Base Case FWCF Transient Results Peak Peak Power/ ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp (% rated) (% rated) TSSS Insertion Times 100/105 0.33 1.06 0.30 1.00 342 122 100/100 0.32 1.07 0.29 1.00 321 121 100/81 0.31 1.09 0.27 1.03 221 117 80/105 0.37 1.03 0.35 1.00 268 101 80/57.2 0.32 1.13 0.24 1.09 149 92 60/105 0.44 1.00 0.43 1.00 184 80 60/35.1 0.12 1.20 0.16 1.18 85 65 40 /105 0.60* 0.91" 0.57 0.88 88* 57* 25 /105 1.04* 0.74* 0.85 0.76 59* 44* NSS Insertion Times 100/105 0.29 1.09 0.25 1.03 266 117 100/100 0.28 1.09 0.24 1.03 245 116 100/81 0.25 1.10 0.20 1.03 209 113 80/105 0.34 1.05 0.31 1.00 226 98 80/57.2 0.20 1.16 0.17 1.15 118 87 60/105 0.41 1.01 0.39 1.00 165 78 60/35.1 0.12 1.23 0.12 1.22 65 63 40 / 105 0.56 0.93 0.55 0.89 101 59 25 / 105 0.96* 0.75* 0.84 0.77 55* 43** The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.Pane 3-13 LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 3-14 Table 3.6 EOC Base Case FWCF Transient Results Peak Peak Power/ ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp (% rated) (% rated) TSSS Insertion Times 100/105 0.33* 1.05 0.30* 1.00* 342* 122* 100/100 0.32* 1.06 0.29* 1.00* 321* 121* 100/81 0.31* 1.05 0.27* 1.03 221* 117* 80/105 0.37* 1.03* 0.35* 1.00* 268* 101* 80/57.2 0.34 1.08 0.30 1.07 217 100 60 /105 0.44* 1.00* 0.43* 1.00 184* 80* 40 /105 0.60* 0.91* 0.57* 0.88* 88* 57* 25 /105 1.04* 0.74* 0.85* 0.76* 59* 44* NSS Insertion Times 100/105 0.29 1.06 0.27 1.03 366 126 100/100 0.29 1.06 0.26 1.03 345 125 100/81 0.28 1.05 0.24 1.03 273 123 80/105 0.34* 1.05 0.31* 1.00* 226* 98* 80/57.2 0.29 1.10 0.25 1.08 192 97 60/105 0.41* 1.01* 0.39* 1.00* 165* 78* 40 / 105 0.56* 0.93* 0.55* 0.89* 101* 59* 25 /105 0.96* 0.75* 0.84* 0.77* 55* 43** The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit I Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Pane 3-15 Table 3.7 Loss of Feedwater Heating Base Case Transient Analysis Results 2CPR (ATRIUM-10 Power and (% rated) ATRIUM-9B3 Fuel) 100 0.21 90 0.22 80 0.23 70 0.24 60 0.26 50 0.29 40 0.33 25 0.45 Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 PaneA 3-16 Table 3.8 Input for MCPR Safety Limit Analysis Source Statistical Parameter Document Treatment Critical power correlation*

ATRIUM-10 Reference 12 Convoluted ATRIUM-9B Reference 17 Convoluted Radial power References 10 and 16 Convoluted Local peaking factor Reference 5 Convoluted Assembly flow rate (mixed core) Reference 5 Convoluted Channel bow local peaking Function of nominal and bowed local Convoluted peaking and standard deviation of bow data (see Reference

18) Nominal Values and Plant Measurement Uncertainties Uncertainty

(%) Statistical Parameter Value (Reference

8) Treatment Feedwater flow ratet (Mlbm/hr) 23.6 1.76 Convoluted Feedwater temperature (OF) 426.5 0.76 Convoluted Core pressure (psia) 1031.35 0.50 Convoluted Total core flow (Mlbm/hr) 113.9 2.50 Convoluted Core powert (MWth) 5446.6 ..Additive constant uncertainties values are used. Feedwater flow rate and core power were increased above design values to attain desired core MCPR for safety limit evaluation consistent with Reference 5 methodology.

Framatome ANP, Inc.Fuel-Related Uncertainties t

LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-17 Table 3.9 Flow-Dependent MCPR Results Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-18 500.0 CORE POWER HEAT FLUX 400.0 CO _ F .LOW STEAM FLOW -FEED FLOW 300.0. I" IL 0 200.0 z C-LUJ -100.0.0 1.0 2.0 3.0 4.0 5.0 6.0 TIME, SECONDS LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 07:46-04 NOS-10079, JOB 0-08112 Figure 3.1 EOC Load Rejection No Bypass at 100/105 -TSSS Key Parameters Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 0 ILU N -In z LU Li (n (n LU I._ .-J LU hi CI-,U 3.0 TIME, SECONDS LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 07:46:04 NQS-10079.

JO ID-08112 Figure 3.2 EOC Load Rejection No Bypass at 100/105 -TSSS Vessel Water Level Framatome ANP, Inc.EMF-2689 Revision 0 D,-.' ," 'S.. ... I- -r liltl~ , I a 0-.

LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient AnalisRevision 0 SPag 32 1250.0 (I) 0 (1 LO LLu LAJ 0 0 LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 07:46:04 NOS-10079 JOBI [-08112 Figure 3.3 EOC Load Rejection No Bypass at 100/105 -TSSS Dome Pressure Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-21 400.0 300.0 -0 0 I z Uj Q of 0~CORE POWER HEAT FLUX -CORE- F'LOW ST fK-EAM FLOW--FEED 6FL OW 200.0-100.01 -" ... .--- ----- ---- --- ----\.01 i -100.0 0 5.0 10.0 15.0 2.0 25.0 TIME, SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 09:41:45 NOS-10115, J6 I0-08156 Figure 3.4 EOC Feedwater Controller Failure at 100/105- TSSS Key Parameters Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-22 70.0 0 L N I- 60.0 (A z LUJ G0 m Z 50.0-j LLJ LU -J En Li I-..J 40.0 LUJ C,) LU 30.05 .0 5.0 10.0 15.0 20.0 210 TIME, SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 09:41:45 N0S -10115. J0 10-08156 Figure 3.5 EOC Feedwater Controller Failure at 1001105 -TSSS Vessel Water Level Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 10.0 15.0 TIME, SECONDS 10/11/01 09:41:45 LSA CYCLE 10 100/105 TSSS FWCF NOS-10115.

JOB 1V-08156 Figure 3.6 EOC Feedwater Controller Failure at 100/105 -TSSS Dome Pressure Framatome ANP, Inc.EMF-2689 Revision 0 V) n a. Lj ,) 1100.0 0 lJ 0-ý2 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 200 175 150 U) "-o 125 C m o 100 ..0 E 75 z 50 25 0.0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radial Power Peaking Figure 3.7 Radial Power Distribution for SLMCPR Determination Framatome ANP, Inc.EMF-2689 Revision 0 Pm a 'q.DA PUr.. v A LaSalle Unit I Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-25, C C N T R 0 L R 0 D C 0 R N E R 1.252 0.512 0.892 1.151 1.226 0.971 0.948 1.121 ONTROL ROD CORNER 1.057 1.212 1.130 1.268 1.225 1.212 0.000 0.540 1.036 0.000 1.130 0.540 0.901 0.904 0.499 1.268 1.036 0.904 0.924 1.058 1.225 0.000 0.499 1.058 1.252 0.512 0.892 1.151 1.226 0.971 0.948 1.121 1.234 0.536 0.920 1.003 1.114 1.172 0.000 0.538 0.999 0.529 1.013 1.156 1.214 1.134 1.248 1.203 0.000 1.152 1.066 0.541 1.167 1.234 0.536 0.920 1.003 1.114 1.203 1.066 0.534 1.162 1.151 1.172 0.000 0.538 0.999 0.529 0.000 0.541 1.162 0.000 1.084 1.013 1.156 1.214 1.134 1.248 1.152 1.167 1.151 1.084 1.022 Figure 3.8 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors Al 0-4039B1-5GV75 With Channel Bow (Assembly Exposure of 1000 MWd/MTU)Framatome ANP, Inc.Internal Water Channel LaSalle Unit 1 Cycle 10 EM F-2689 Plant Transient Analysis Page 3-26 CONTROL ROD CORNER 0 N T R 0 L R 0 D C 0 R N E R 1.061 1.225 1.141 1.225 0.000 0.526 1.141 0.526 0.868 1.282 1.030 0.844 1.240 0.000 0.487 1.271 0.504 0.891 1.246 0.983 0.955 1.255 0.528 0.928 1.191 0.000 0.530 1.021 1.176 1.238 1.240 1.271.000 0.504 0.487 0.891 1.003 1.143 1.246 0.983 0.955 1.127 1.282 1.030 0.844 0.482 1.003 1.143 1.127 1.014 1.013 1.155 1.126 0.522 1.273 1.217 0.000 1.173 1.076 0.533 1.189 1.255 0.528 0.928 1.014 1.126 1.217 1.076 0.527 1.183 1.173 1.191 1.021 0.000 0.530 1.013 0.522 0.000 0.533 1.183 0.000 1.103 1.176 1.238 1.155 1.273 1.173 1.189 1.173 1.103 1.033 Figure 3.9 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors Al 0-4037B-1 6GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU)Framatome ANP, Inc.Internal Water Channel LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-27 2.85 2.75

LRNB *LRNI' 2.65

FWCF X CRWE 2.55 X LOFH 2.45 -E FWCF w/ TCV Stuck 2.35 2.25 2.15 2.05 1. S1.95 50 60 70 80 90 100 110 Power (% rated)Power (%) 100 60 25 25 0 MCPRp Limit 1.43 1.52 2.07 2.20 2.70 Figure 3.10 BOC to 15,000 MWdlMTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.

SEMF-2689 LaSalle Unit 1 Cycle 10 eMFs2689 Plant Transient Analysis Revision 0 Page 3-28 2.85 2.75 -LRNB 2.65 -FWCF 2.55 x CRWE X LOFH 2.45 -:0 FWCF w/TCV Stuck 2.35 -OLMCPR 2.25 2.15 2.05 2 1.95 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Figure 3.11 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.Power MCPRp (%) Limit 100 1.42 60 1.50 25 1.95 25 2.20 0 2.70 LaSalle Unit 1 Cycle 10 Plant Transient Analysis C. U 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Page 3-29 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRP (%) Limit 100 1.46 60 1.55 25 2.15 25 2.20 0 2.70 Figure 3.12 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15" 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPR. (%) Limit 100 1.44 60 1.54 25 1.96 25 2.20 0 2.70 4 70 80 90 100 110 Figure 3.13 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0---r- e O-3 u* LRNB 0 FWCF X CRWE X LOFH o FWCFw/TCV -OLMCPR r x

i Stuck i i[

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 GV -0 J~0 10 20 30 40 50 60 70 80 90 100 110 Powr (% rated)Figure 3.14 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.t* LRNB M FWCF o FWCF w/TCV : -OLMCPR M U Power MCPRP (%) Limit 100 1.47 60 1.52 25 2.07 25 2.20 0 2.70 Stuctk LaSalle Unit 1 Cycle 10 Di~m f _r I + Anahi ýi EMF-2689 Revision 0 Paae 3-32 0I 1II, I ! l IlAlyjiv 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Figure 3.15 15,000 MWdlMTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.Q. U 2 Power MCPRp M% Limit 100 1.43 60 1.50 25 1.95 25 2.20 0 2.70 LaSalle Unit 1 Cycle 10 Plant Transient Analysis C. U 2 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.10 0 10 20 30 40 50 60 Power (% rated)Power MCPRP (%) Limit 100 1.50 60 1.55 25 2.15 25 2.20 0 2.70 70 80 90 100 110 Figure 3.16 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 0 LRNB E FWCF o FWCF w/TCV Stuck I-OLMCPR I ° !Pa e 3-33 -a LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 0. a. U 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Paqe 3-34 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRp (%) Limit 100 1.44 60 1.54 25 1.96 25 2.20 0 2.70 Figure 3.17 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Pl~nf Tr~nnsiknt 1.400 1.350 1.300 1.250 1.200 1.150 CL I. IUU S1.050 -J 1.000 0.950 0.900 0.850 0.800 0.750 0.700 EMF-2689 Revision 0 Paae 3-35 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power LHGRFAC.

(%) Multiplier 100 1.00 60 1.00 25 0.75 0 0.75 Figure 3.18 BOC to 15,000 MWdlMTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.Plant Transient AnaIvsis LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150 CL 1.100 , 1.050 "J 1.000 0.950 0.900 0.850 0.800 0.750 0.700 J 0 10 20 30 40 50 60 Power (% rated)70 80 90 100 110 Figure 3.19 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Plant ...........

A -vqi P Ir-ag 3-3* LRNB a FWCF a FWCF w/ TCV Stuck -LHGRFACp UN Power LHGRFACp (%) Multiplier 100 1.00 60 1.00 25 0.77 0 0.77 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.400 1.350 1.300 1.250 1.200 1.150 o. 1.100 L) S1.050 -i 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 1.00 60 1.00 25 0.74 0 0.74 70 80 90 100 110 Figure 3.20 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0.rag 33* LRNB E FWCF o FWCF wI TCV Stuck -LHGRFACp

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150 0. 1.100 S1.050 "- 1.000 0.950 0.900 0.8501 0.800 0.750 0.700 0 10 20 30 40 50 60 Power (% rated)Power LHGRFAC, (%) Multiplier 100 1.00 60 1.00 25 0.76 0 0.76 70 80 90 100 110 Figure 3.21 BOC to 15,000 MWdlMTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 3-38* LRNB

FWCF 13 FWCF w/TCV Stuck j LHGRFACp i EMF-2689 Revision 0 P:;ip 1-10 LaSalle Unit I Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150 C. 1.100 U 1.050 -1.000 0.950 0.900 0.850 0.800 0.750 0.700 0 10 20 30 40 50 60 Power (% rated)Power (%) 100 60 25 0 0 LHGRFAC, Multiplier 1.00 1.00 0.75 0.75 0.75 70 80 90 100 110 Figure 3.22 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.* LRNB 0 FWCF m FWCF w/ TCV Stuck -LHGRFACp LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150 CL 1.100 S1.050 -J 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0 10 20 30 40 50 60 Power (% rated)Power LHGRFAC) (%) Multiplier 100 1.00 60 1.00 25 0.76 0 0.76 70 80 90 100 110 Figure 3.23 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Pa ep 3-40* LRNB

FWCF o FWCF w/ TCV Stuck -LHGRFACp UB EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 3-41 1 Ann 1.350 1.300 1.250-1.200 1.150 C. 1.100 L) S1.050 1.000 0.950 0.900 0.850 0.800 0.750-0 10 20 30 40 50 60 Power (% rated)70 80 90 100 110 Power LHGRFACp (%) Multiplier 100 1.00 60 1.00 25 0.74 0 0.74 Figure 3.24 15,000 MWdlMTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.* LRNB n FWCF 13 FWCF w/ TCV Stuck -LHGRFACp E 41Z 0.700 4 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.400 1.350 1.300 1.250 1.200 1.150 0. 1.100 " 1.050 J 1.000 0.950 0.900 0.850 0.800 0.750 0.700 EMF-2689 Revision 0 I f "t a 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power LHGRFACp (%) Multiplier 100 1.00 60 1.00 25 0.76 0 0.76 Figure 3.25 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.* LRNB w FWCF t3 FWCF w/TCV Stuck -LHGRFACp EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 4-1 4.0 Transient Analysis for Thermal Margin -Extended Operating Domain This section describes the development of the MCPR and LHGR limits to support operation in the following extended operating domains:

Increased core flow (ICF) to 105% of rated flow.

MELLLA power operation (refer to Figure 1.1).

Coastdown is currently not supported for LaSalle Unit I Cycle 10.

Final feedwater temperature reduction (FFTR) is currently not supported for LaSalle Unit 1 Cycle 10. Results of the limiting transient analyses are used to determine appropriate MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel to support operation in the EOD scenarios.

MCPRp limits and LHGRFACp multipliers are established for both ATRIUM-10 and ATRIUM-9B.

As presented in Reference 9, the MCPR safety limit analysis for the base case remains valid for operation in the EODs discussed below. Also, the flow-dependent MCPR and LHGR analyses described in Section 3.4 were performed such that the results are applicable for all the EODs. 4.1 Increased Core Flow The base case analyses presented in Section 3.0 were performed to support operation in the power/flow domain presented in Figure 1.1, which includes operation in the ICF region. As a result, the analyses performed for the base case support operation in the ICF extended operating domain. 4.2 MELLLA Operations The base case analyses presented in Section 3.0 were performed to support operation in the power/flow domain presented in Figure 1.1, which includes operation in the MELLLA region. As a result, the analyses performed for the base case support operation in the MELLLA operating domain. 4.3 Coastdown Analysis Coastdown operation is currently not supported for LaSalle Unit 1 Cycle 10.Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Pevin 0-9 4.4 Combined Final Feedwater Temperature ReductionlCoastdown Combined FFTRlcoastdown operation is currently not supported for LaSalle Unit 1 Cycle 10.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-1 5.0 Transient Analysis for Thermal Margin -Equipment Out-of-Service This section describes the development of the MCPR and LHGR operating limits to support operation in the following EOOS scenarios:

Feedwater heaters out-of-service (FHOOS) -1 00°F feedwater temperature reduction.

Turbine bypass system out-of-service (TBVOOS).

Recirculation pump trip out-of-service (no RPT).

Slow closure of 1 or more turbine control valves.

1 stuck closed TCV.

1 recirculation pump loop (SLO). Operation with 1 SRV out-of-service, up to 2 TIPOOS (or the equivalent number of TIP channels) and up to 50% of the LPRMs out-of-service is supported by the base case thermal limits presented in Section 3.0. No further discussion for these EOOS scenarios is presented in this section. The EOOS analyses presented in this section also include the same EOOS scenarios protected by the base case limits. The base case MCPR safety limit for two-loop operation remains applicable for operation in the EOOS scenarios discussed below with the exception of single-loop operation.

Also, the flow dependent MCPR and LHGR analyses described in Section 3.4 were performed such that the results are applicable in all the EOOS scenarios.

Most of the equipment out of service scenarios are divided into two cases. The limits provided for EOOS Case 1 are applicable for operation with FHOOS or TBVOOS. The limits for EOOS Case 2 support operation with any combination of TCV slow closure, no RPT or FHOOS. Analyses for the limiting events and EOOS conditions for the two cases were performed to ensure that the limits provide the necessary protection.

One TCV stuck closed is supported in combination with the other EOOS scenarios and is discussed separately.

SLO with and without the other EOOS conditions is also discussed separately.

Results of the limiting transient analyses are used to establish appropriate MCPRp limits and LHGRFACP multipliers to support operation in the EOOS scenarios.

All EOOS analyses were performed with both NSS and TSSS insertion times.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-2 5.1 EOOS Case 1 The EOOS Case 1 limits are applicable for operation with FHOOS or TBVOOS. The limits also support operation with FHOOS combined with 1 TCV stuck closed (See Section 5.4). The MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel for the EOOS Case 1 scenarios are presented in Figures 5.1-5.8 for 15,000 MWd/MTU and Figures 5.9-5.16 for EOC. 5.1.1 Feedwater Heaters Out-of-Service (FHOOS) The FHOOS scenario assumes a 1 00°F reduction in the feedwater temperature.

Operation with FHOOS is similar to operation with FFTR except that the reduction in feedwater temperature due to FHOOS can occur at any time during the cycle. The effect of the reduced feedwater temperature is an increase in the core subcooling which can change the power shape and core void fraction.

Previous analysis (Reference

23) has verified that the LRNB event is less severe with FHOOS due to the decrease in steam flow and is nonlimiting.

However, the FWCF event can get worse due to the increase in core inlet subcooling.

FWCF analyses were performed for Cycle 10 to determine thermal limits to support operation with FHOOS. The ACPR and LHGRFACp results used to develop the 15,000 MWd/MTU operating limits with FHOOS are presented in Table 5.1. The ACPR and LHGRFACp results used to develop the EOC operating limits with FHOOS are presented in Table 5.2. 5.1.2 Turbine Bypass Valves Out-of-Service (TBVOOS) The effect of operation with TBVOOS is a reduction in the system pressure relief capacity, which makes the pressurization events more severe. While the base case LRNB event is analyzed assuming the turbine bypass system out-of-service, operation with TBVOOS has an effect on the FWCF event. The FWCF event was evaluated for LaSalle Unit 1 Cycle 10 to support operation with TBVOOS. The ACPR and LHGRFACp results used to develop the 15,000 MWd/MTU operating limits with TBVOOS are presented in Table 5.1. The ACPR and LHGRFACp results used to develop the EOC operating limits with TBVOOS are presented in Table 5.2. The TBVOOS condition can also affect the response of the loss of feedwater heating event. During the event, the colder feedwater results in an increase in the inlet subcooling as well as an increase in the thermal power. Although there is a substantial increase in core thermal Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-3 power, the increase in steam flow is much less because a large part of the added power is used to overcome the increase in inlet subcooling.

However, there can be a small increase in steam flow. The turbine control valves will open to accommodate any increase in steam flow. If the steam flow increases beyond the total capacity of the turbine control valves, the turbine bypass valves open to provide pressure relief. With the turbine bypass valves inoperable, the system would pressurize if the steam flow were to increase above the total capacity of the TCVs. A review of the maximum steam flow obtained in the base case LOFH analyses showed that in some of the rated power cases, the steam flow did increase above the TCV total capacity.

As a result, LOFH analyses were performed using the transient methodology (COTRANSA2

/XCOBRAT) to account for the effects of pressurization.

Analyses were performed only at high power levels (100% and 80% of rated) since at lower power levels, the TCVs have sufficient capacity to accommodate the increase in steam flow. The LOFH ACPR and LHGRFACp results used to develop the 15,000 MWd/MTU operating limits with TBVOOS are presented in Table 5.1. Since the limiting exposure for the LOFH event is early in the cycle, the same results were used to develop the EOC operating limits with TBVOOS. 5.2 EOOS Case 2 The EOOS Case 2 limits are applicable for operation with any combination of TCV slow closure, no RPT or FHOOS. The limits also support operation with the same EOOS conditions combined with 1 TCV stuck closed (See Section 5.4). The spectrum of power/flow points and events performed to establish the EOOS Case 2 limits is based on previous analyses (Reference 20). The MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel for the EOOS Case 2 scenarios are presented in Figures 5.17-5.24 for 15,000 MWd/MTU and Figures 5.25-5.32 for EOC. 5.2.1 Recirculation Pump Trio Out-of-Service (No RPT) This section summarizes the development of the thermal limits to support operation with the EOC RPT inoperable.

When RPT is inoperable, no credit for tripping the recirculation pump on TSV position or TCV fast closure is assumed. The function of the RPT feature is to reduce the severity of the core power excursion caused by the pressurization transient.

The RPT accomplishes this by helping revoid the core, thereby reducing the magnitude of the reactivity insertion resulting from the pressurization transient.

Failure of the RPT feature can result in Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-4 higher operating limits because of the higher positive reactivity in the core at the time of control rod insertion.

Analyses were performed for LRNB and FWCF events assuming no RPT. The ACPR and LHGRFACp results used to develop the 15,000 MWd/MTU operating limits with no RPT are presented in Table 5.3. The ACPR and LHGRFACp results used to develop the EOC operating limits to support no RPT operation are presented in Table 5.4. 5.2.2 Slow Closure of the Turbine Control Valve LRNB analyses were performed to evaluate the impact of a TCV slow closure. Analyses were performed closing 3 valves in the normal fast closure mode and 1 valve in 2.0 seconds. Results provided in Reference 20 demonstrate that performing the analyses with 1 TCV closing in 2.0 seconds protects operation with up to 4 TCVs closing slowly. Sensitivity analyses below 80% power have shown that the pressure relief provided by all 4 TCVs closing slowly can be sufficient to preclude the high-flux scram set point from being exceeded.

Therefore, credit for high-flux scram is not taken for analyses at 80% power and below. The 80% power TCV slow closure analyses were performed both with and without high-flux scram credited.

The ACPR and LHGRFACp TCV slow closure analysis results used to establish the EOOS Case 2 operating limits at 15,000 MWd/MTU and EOC are presented in Tables 5.3 and 5.4, respectively.

The MCPRP limits are established with a step change at 80% power. At 80% power, the lower bound MCPRP limits are based on the analyses which credit high-flux scram; the upper-bound MCPRp limits are based on analyses which do not credit high-flux scram. The EOOS Case 2 limits protect the scenario of all 4 TCVs closing slowly. 5.2.3 Combined FHOOS/TCV Slow Closure and/or No RPT The EOOS Case 2 limits were established to support operation with any combination of FHOOS, TCV slow closure or no RPT. The TCV slow closure ACPR and LHGRFACP results with FHOOS become less limiting than the TCV slow closure event with nominal feedwater temperature since the initial steam flow with FHOOS is lower and produces a less severe pressurization event. Subsequently, no TCV slow closure with FHOOS analyses were performed.

Analyses were performed for the FWCF event with FHOOS and no RPT as the analysis results are potentially limiting, especially at low power levels. The ACPR and Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-5 LHGRFACp FWCF with FHOOS and no RPT analysis results used to establish the EOOS Case 2 operating limits at 15,000 MWd/MTU and EOC are presented in Tables 5.3 and 5.4, respectively.

5.3 Single-Loop Operation (SLO) The impact of SLO at LaSalle on MCPR limits and LHGRFACp multipliers was presented in Reference

9. The base case ACPRs and LHGRFACP multipliers remain applicable.

The only impact is on the MCPR safety limit. As presented in Section 3.2, the single-loop operation safety limit is 0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The net result is an increase to the base case MCPRp limits of 0.01 as a result of the increase in the MCPR safety limit. The same situation is true for the EOOS scenarios.

Adding 0.01 to the corresponding TLO EOOS MCPR limits results in SLO MCPR limits for the EOOS conditions.

The TLO EOOS LHGRFACp multipliers remain applicable in SLO. 5.4 1 Stuck Closed Turbine Control Valve With 1 of the turbine control valves assumed stuck closed, the other 3 TCVs will be further open when operating at a given power level. In addition, the highest attainable power is decreased because of the decreased steam flow capacity of the TCVs. With the valves further open, TCV closure events such as the LRNB and slow closure events, are less severe than with the valves further closed because the pressurization occurs over a longer time. While the FWCF event is not impacted during the turbine stop valve closure portion of the event, it may be impacted during the overcooling phase. At some power level between 80% and 100% of rated, the TCVs will be in the full open position with no ability to accommodate an increase in steam flow during the overcooling phase. The result is an increase in pressure prior to the turbine stop valve closure and a more severe event. Operation of the turbine bypass valves during the overcooling phase is not credited.

Operation with 1 stuck closed TCV is supported in conjunction with the other EOOS conditions.

As a result, FWCF analyses with 1 stuck TCV were performed for base case operation and the EOOS conditions where the FWCF is the limiting event (i.e. FHOOS, TBVOOS, no RPT and FHOOS with no RPT). Analyses are only performed at 80% and 100% power since at lower power levels, the initial TCV position is such that there is enough capacity left to accommodate the increase in steam flow during the overcooling phase. The ACPR and LHGRFACp analysis results for the FWCF with 1 stuck TCV Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-6 closed for base case and the EOOS conditions at 15,000 MWd/MTU and EOC are presented in Tables 5.5 and 5.6, respectively.

The 1 stuck closed turbine control valve condition may also impact the loss of feedwater heating event when combined with the TBVOOS condition.

Any increase in steam flow causes the system to pressurize making the event more severe. LOFH analyses were performed to support operation with 1 TCV stuck closed and TBVOOS for 80% and 100% of rated power. Analyses are only performed at 80% and 100% power since at lower power levels, the initial TCV position is such that there is enough capacity left to accommodate the increase in steam flow. The ACPR and LHGRFACp LOFH with 1 stuck TCV closed and TBVOOS analysis at 15,000 MWd/MTU and EOC are presented in Tables 5.5 and 5.6, respectively.

In most cases, the results in Tables 5.5 and 5.6 were used in establishing the base case, EOOS Case 1 and EOOS Case 2 operating limits. The inclusion of the 1 TCV stuck closed condition with other limits has little or no impact, with one exception being the combined 1 TCV stuck closed and TBVOOS scenario, Results for 1 TCV stuck closed are included with the base case limits presented in Figures 3.10-3.25.

Results for EOOS Case 1 with 1 TCV stuck closed are presented in Figures 5.1-5.16.

Results for EOOS Case 2 with 1 TCV stuck closed are presented in Figures 5.17-5.32.

The EOOS Case 1 MCPRP limits protect the combined 1 TCV stuck closed with TBVOOS MCPR results. However, the LHGRFACp results for the combined 1 TCV stuck closed and TBVOOS are much lower than the TBVOOS results. Therefore, separate sets of operating limits were established.

The LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel for the 1 TCV stuck closed with TBVOOS condition are presented in Figures 5.33-5.36 for 15,000 MWd/MTU and Figures 5.37-5.40 for EOC.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 5.1 EOOS Case I Analysis Results -15,000 MWd/MTU EMF-2689 Revision 0 Pacie 5-7 Pai -Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated / % rated) ACPR LHGRFACp ACPR LHGRFACP FHOOS With NSS Insertion Times FHOOS With TSSS Insertion Times 100 / 105 100/81 80 / 105 80 /57.2 60 / 105 40 1 105 25/105 0.34 0.32 0.40 0.35 0.49 0.76* 1.34" 1.04 1.08 1.00 1.09 0.95 0.83* 0.64*0.64* 1.08*0.31 0.28 0.37 0.26 0.48 0.69 1.08*0.97 1.03 0.95 1.08 0.91 0.82 0.69 0.69 TBVOOS With NSS Insertion Times 100 / 105 100 /81 80/105 80/57.2 60 / 105 25/105-I *1 0.34 0.33 0.40 0.28 0.48 0.92 0.92 1.03 1.00 1.01 1.10 0.97 0.77 0.7 0.207 0.33 0.28 0.38 0.22 0.47 0.92 0.93 0.90 0.94 1.04 0.91 0.74* The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACP results are conservatively used to establish the thermal limits.Framatome ANP, Inc.FWCF FWCF I LaSalle Unit 1 Cycle 10 Pl~nn Annlv~qi.EMF-2689 Revision 0 Paae 5-8 Table 5.1 EOOS Case 1 Analysis Results -15,000 MWdlMTU (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp TBVOOS With TSSS Insertion Times* The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.P Ilant Trn in Anal,.* ,,.vsi LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Plant~~~~~~

Trnin nlvi af Table 5.2 EOOS Case 1 Analysis Results -EOC Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp FHOOS With NSS Insertion Times 100/105 0.30 1.06 0.28 1.01* 100/81 0.28 1.09 0.25 1.06 80/105 0.37* 1.02* 0.34* 0.97* FWCF 80/57.2 0.30 1.09* 0.26 1.08* 60/105 0.47* 0.96* 0.45* 0.92* 40/105 0.69* 0.86* 0.66* 0.83* 25/105 1.25* 0.66* 1.04" 0.69* FHOOS With TSSS Insertion Times 100/105 0.34* 1.04* 0.31* 0.97* 100/81 0.32* 1.08* 0.28* 1.03* 80 / 105 0.40* 1.00* 0.37* 0.95* FWCF 80/57.2 0.35* 1.09* 0.30 1.07 60/105 0.49* 0.95* 0.48* 0.91" 40 / 105 0.76* 0.83* 0.69* 0.82* 25/105 1.34* 0.64* 1.08* 0.69* TBVOOS With NSS Insertion Times 100/105 0.34 1.00 0.33 0.93* 100/81 0.36 0.95 0.33 0.90* FWCF 80/105 0.40* 1.00 0.38* 0.94* 80/57.2 0.38 1.00 0.34 0.99 60 / 105 0.48* 0.97* 0.47 0.91"* The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Paae. 5-10 Table 5.2 EOOS Case I Analysis Results -EOC (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACP ACPR LHGRFACp TBVOOS With TSSS Insertion Times 100/105 0.38* 1.00 0.36* 0.93* 100/81 0.39 0.95 0.34 0.92* FWCF 80/105 0.43* 0.99* 0.42* 0.91* 80/57.2 0.43 1.00 0.39 0.98 60/105 0.51* 0.95* 0.51* 0.89* 100/105 0.23* 1.01* 0.22* 1.01* LOFH 100 / 81 0.23* 0.95* 0.23* 0.95* 80 / 105 0.25* 1.05* 0.24* 1.05* 1 80 / 57.2 0.28* 0.94* 0.27* 0.94** The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACP results are conservatively used to establish the thermal limits.Framatome ANP, Inc.Pane 5-10 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 Pane 5-1 1 Table 5.3 EOOS Case 2 Analysis Results -15,000 MWd/MTU Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated t % rated) ACPR LHGRFACp ACPR LHGRFACp TCV Slow Closure With NSS Insertion Times 100 / 105l 0.43 0.90 0.41 0.81 0/1 I 100I 0.42 0.89 0.40 0.80 100/81 0.39 0.91 0.41 0.82 80 / 105l 0.39 0.95 0.41 0.88 80 / 5 7 Y 2 0.63* 0.98 0.56 0.90 LRNB 80 / 105 0.59* 0.88* 0.62 0.82 80 / 57.2* 0.70* 0.91 0.75 0.83 60/ 1051 0.68 0.84 0.71 0.79 60/35.1 0.59 0.93 0.69 0.88 40 / 105l 0.84 0.77 0.84 0.75 25/l105 1.19* 0.67* 1.02 0.69 TCV Slow Closure With TSSS Insertion Times 100 / 105' 0.48 0.88 0.48 0.78 100/ 100o 0.48 0.87 0.48 0.77 100 / 81' 0.43 0.87 0.45 0.76 80 / 105t 0.45 0.93 0.44 0.85 80 / 5 7.2t 0.63* 0.97 0.62 0.88 LRNB 80 / 105t 0.59* 0.88 0.62 0.82 80 / 57.2t 0.71* 0.90 0.75 0.83 60/ 1051 0.69 0.84 0.71 0.79 60 / 35.1t 0.64 0.90 0.75 0.86 40 / 105' 0.85 0.77 0.86 0.74 25/1051 1.19* 0.67* 1.03 0.68

The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits. t Scram initiated on high neutron flux. Scram initiated on high dome pressure.Framatome ANP, Inc.* rPane 5-11 EMF-2689 Revision 0 Page 5-12 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 5.3 EOOS Case 2 Analysis Results -15,000 MWd/MTU (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp No RPT With NSS Insertion Times 100 / 105 0.37 0.95 0.39 0.84 LRNB 100/81 0.30 0.91 0.34 0.79 80 /105 0.35 0.99 0.37 0.89 80 / 57.2 0.24 1.05 0.22 0.97 FWCF 100/105 0.32 1.01 0.32 0.92 No RPT With TSSS Insertion Times 100 / 105 0.41 0.89 0.40 0.81 LRNB 100/81 0.35 0.93 0.36 0.81 80/105 0.39 0.95 0.40 0.87 80/57.2 0.37 1.01 0.35 0.93 FWCF 100/105 0.37 0.96 0.36 0.90 FHOOSINo RPT With NSS Insertion Times 100/105 0.33 1.01 0.32 0.93 FWCF 80 / 105 0.39 0.97 0.38 0.91 25 / 105 1.22* 0.65* 1.04 0.67 FHOOSINo RPT With TSSS Insertion Times 100/105 0.37 0.97 0.36 0.90 FWCF 80/105 0.42 0.95 0.42 0.88 25/105 1.26* 0.64* 1.06 0.67* The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 5-13 Table 5.4 EOOS Case 2 Analysis Results -EOC Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated / % rated) ACPR LHGRFACp ACPR LHGRFACp TCV Slow Closure With NSS Insertion Times 100 / 105t 0.48 0.90* 0.47 0.81* 100 / 81 0.47 0.84 0.42 0.81 80 / 105t 0.45 0.94 0.43 0.88* 80 / 5 7.2 0.63* 0.92 0.56 0.90* LRNB 80 / 105' 0.59* 0.88* 0.62* 0.82* 80 / 5 7.2* 0.70* 0.86 0.75* 0.83* 60 / 105' 0.68* 0.84* 0.71* 0.79* 60 / 35.11 0.59* 0.93* 0.69* 0.88* 40 / 105* 0.84* 0.77* 0.84* 0.75* 25 / 105t 1.19* 0.67* 1.02* 0.69* TCV Slow Closure With TSSS Insertion Times 100 / 105t 0.50 0.88* 0.49 0.78* 100 / 81t 0.47 0.84 0.45 0.76* 80 / 105t 0.46 0.93* 0.45 0.85* 80 / 57.2t 0.63* 0.94 0.62* 0.88* 80 / 105, 0.59* 0.88* 0.62* 0.82* LRNB 80 / 57.2t 0.71* 0.86 0.75* 0.83* 60 / 105t 0.69* 0.84* 0.71* 0.79* 60 1 35.1

0.64* 0.90* 0.75* 0.86* 40 / 105t 0.85* 0.77* 0.86* 0.74* 25 / 105t 1.19* 0.67* 1.03* 0.68** The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits. t Scram initiated on high neutron flux. SScram initiated on high dome pressure.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Plan Transien -n -r' ,-Table 5.4 EOOS Case 2 Analysis Results -EOC (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated / % rated) :ACPR LHGRFACp ACPR LHGRFACP No RPT With NSS Insertion Times 100 / 105 0.48 0.87 0.47 0.84* LRNB 100 / 81 0.41 0.84 0.41 0.79* 80/ 105 0.43 0.91 0.42 0.89* 80/57.2 0.35 0.93 0.30 0.90 FWCF 100 /105 0.38 0.93 0.34 0.91 No RPT With TSSS Insertion Times 100/105 0.53 0.84 0.54 0.81* LRNB 100 / 81 0.49 0.82 0.42 0.80 80/105 0.47 0.89 0.48 0.87 80/57.2 0.39 0.92 0.35 0.90 FWCF 100 / 105 0.43 0.90 0.42 0.88 FHOOSINo RPT With NSS Insertion Times 100 / 105 0.37 0.93 FWCF 80/105 0.39* 0.97* 25/105 1.22* 0.65*FHOOSINo RPT With TSSS Insertion Times 100 / 105 0.41 0.92 FWCF 80 / 105 0.42* 0.95* 25/105 1.26* 0.64** The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACP results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 P-~c 'k Table 5.5 1 TCV Stuck Closed Analysis Results -15,000 MWd/MTU Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp Base CaselI TCV Stuck Closed With NSS Insertion Times SWF 100/105 0.30 1.08 0.27 1.02 FWCF 80/105 0.35 1.04 0.32 1.00 Base Casell TCV Stuck Closed With TSSS Insertion Times 100/105 0.34 1.05 0.31 1.00 S100 / 81 0.31 1.08 0.27 1.03 FWCF 1081031.802 80/105 0.39 1.02 0.36 1.00 80/57.2 0.32 1.13 0.24 1.09 FHOOSII TCV Stuck Closed With NSS Insertion Times 100/105 0.33 1.05 0.29 1.00 100/81 0.26 1.10 0.24 1.06 FWCF 80/105 0.39 1.00 0.36 0.95 80/57.2 0.26 1.15 0.21 1.12 FHOOS/1 TCV Stuck Closed With TSSS Insertion Times 100 / 105 0.36 1.02 0.33 0.96 100/81 0.33 1.06 0.29 1.01 FWCF 80 / 105 0.42 0.98 0.39 0.93 80/57.2 0.36 1.09 0.28 1.05 Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 5-16 Table 5.5 1 TCV Stuck Closed Analysis Results -15,000 MWd/MTU (Continued)

Power / Flow ATRIUM-10 ATRILUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp TBVOOSI1 TCV Stuck Closed With NSS Insertion Times 100/105 0.36 1.02 0.34 0.93 100 /81 0.33 1.00 0.28 0.90 FWCF 80/105 0.41 1.00 0.39 0.93 80/57.2 0.29 1.10 0.22 1.04 LOFH 80 / 57.2 0.42* 0.90* 0.35* 0.91* TBVOOSI1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.40 1.01 0.37 0.93 100/81 0.39 1.01 0.34 0.92 FWCF 80 / 105 0.45 0.98 0.43 0.90 80 / 57.2 0.41 1.06 0.35 0.99 100/105 0.36* 0.95* 0.32* 0.95* 100/81 0.36* 0.83 0.31 0.80 LOFH 80/105 0.42* 0.93* 0.38* 0.93* 80 / 57.2 0.44* 0.77 0.37* 0.77 No RPTII TCV Stuck Closed With NSS Insertion Times 100/105 0.34 1.01 0.33 0.93 FWCF 80/105 0.38 0.99 0.38 0.91 No RPTI1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.38 0.98 0.37 0.89 FWCF 80 / 105 0.42 0.96 0.42 0.88* The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

EMF-2689 Revision 0 Page 5-17 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 5.5 1 TCV Stuck Closed Analysis Results -15,000 MWd/MTU (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated / % rated) ACPR LHGRFACp ACPR LHGRFACp FHOOS/No RPTI1 TCV Stuck Closed With NSS Insertion Times FWF 100 /105 0.35 0.99 0.34 0.92 80 / 105 0.41 0.95 0.41 0.89 FHOOSINo RPTI1 TCV Stuck Closed With TSSS Insertion Times FWCF0 /1105 0.39 0.97 0.38 0.88 80 /105 0.44 0.93 0.44 0.87 Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Pace 5-18 Table 5.6 1 TCV Stuck Closed Analysis Results -EOC Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated / % rated) ACPR LHGRFACp ACPR LHGRFACP Base CaselI TCV Stuck Closed With NSS Insertion Times 100/ 105 0.30 1.05 0.28 1.02* FWCF 80/105 0.35* 1.04* 0.32* 1.00* Base CaselI TCV Stuck Closed With TSSS Insertion Times 100/105 0.34* 1.04 0.31* 1.00* 100 /81 0.31 1.05 0.27* 1.03* FWCF 80 / 105 0.39* 1.02* 0.36* 1.00* 80/57.2 0.34 1.08 0.30 1.07 FHOOSII TCV Stuck Closed With NSS Insertion Times 100/105 0.33* 1.05* 100/81 0.29 1.08 FWCF 80/105 0.39* 1.00* 80/57.2 0.31 1 1.11 FHOOSI I TCV Stuck Closed With TSSS Insertion Times 100/105 0.36* 1.02* 100/81 0.33* 1.06* FWCF 80/105 0.42* 0.98* 80/57.2 0.36* 1.09** The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 5-19 Table 5.6 1 TCV Stuck Closed Analysis Results -EOC (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp TBVOOS/1 TCV Stuck Closed With NSS Insertion Times 100/105 0.36* 1.00 0.34* 0.93* 100/81 0.36 0.95 0.33 0.90* FWCF 80/105 0.41* 1.00* 0.39* 0.93* 80/57.2 0.38 1.02 0.34 1.00 TBVOOSI1 TCV Stuck Closed With TSSS Insertion Times 100 / 105 0.40* 1.01* 0.37* 0.93* FWCF 100/81 0.39 0.95 0.34 0.92* 80/105 0.45* 0.98* 0.43* 0.90* 80 / 57.2 0.43 1.00 0.39 0.99* 100 /105 0.36* 0.95* 0.32* 0.95* LOFH 100/81 0.36* 0.83* 0.31* 0.80* 80/105 0.42* 0.93* 0.38* 0.93* 80 / 57.2 0.44* 0.77* 0.37* 0.77* No RPTI1 TCV Stuck Closed With NSS Insertion Times FWCF 100 /105 0.38 0.93 0.35 0.91 80/105 0.38* 0.97 0.39 0.91" No RPTI1 TCV Stuck Closed With TSSS Insertion Times FWCF 100 / 105 0.43 0.90 0.43 0.88 80/105 0.42* 0.95 0.42* 0.88** The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 5-20 Table 5.6 1 TCV Stuck Closed Analysis Results -EOC (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp FHOOS/No RPTII TCV Stuck Closed With NSS Insertion Times FWCF 100 /105 0.38 0.93 0.36 0.91 80 /105 0.41 0.95* 0.41* 0.89* FHOOSINo RPTI1 TCV Stuck Closed With TSSS Insertion Times 100 /105 0.42 0.92 0.41 0.88* FWCF 100/81 0.35 0.95 0.31 0.93 80 /105 0.44* 0.93* 0.44* 0.87* 80 1 57.2 0.33 1.05 0.29 1.03* The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 a. 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.14-0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.47 60 1.59 25 2.36 25 2.36 0 2.86 70 80 90 100 110 Figure 5.1 BOC to 15,000 MWdlMTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-21 B FWC.F Nn + FWCFFHOOS o FWCF No Bypass wITCV Stuck x FWCF FHOOSw/TCV Stuck a LOFH No Bypass o LOFH No Bypass w/TCV Stuck -OLMCPR 2 Pane 5-21 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 S0.950"3j 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.66 25 0.66 0 0.66 70 80 90 100 110 Figure 5.2 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-22* FWCF No Bypass + FWCFFHOOS x FWCF FHOOS w/ TCV Stuck -LHGRFACp I 4.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.45 60 1.58 25 2.15 25 2.20 0 2.70 70 80 90 100 110 Figure 5.3 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-23 S* FWCF No Bypass + FWCFFHOOS o FWCF No Bypass w/ TCV Stuck X FWCF FHOOS; WTCV Stuck A LOFH No Bypass

LOFH No Bypass W/TCV Stuck -OLMCPR LaSalle Unit I Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 A 1.100 1.050 4 Win 0.950 .1 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.90 60 0.90 25 0.69 25 0.69 0 0.69 70 80 90 100 110 Figure 5.4 BOC to 15,000 MWdlMTU EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-24 a FWCF No Bypass + FWCFFHOOS K FWCF FHOOS w/ TCV Stuck -LHGRFACp +X + ++

LaSalle Unit 1 Cycle 10 Plant Transient Analysis I.3.05 2.95 285 2.75 2.65 2.55 245 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.51 60 1.62 25 2.45 25 2.45 0 2.95 70 80 90 100 110 Figure 5.5 BOC to 15,000 MWdlMTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-25 9 FWCF No Bypass + FWCF FHOOS o FWCF No Bypass W TCV Stuck K FWCF FHOOS Yd TCV Stuck A LOFH WNo Bypass o LOFH No Bypass w/ Stuck TCV -OLMCPR A Pane 5-25 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 ,6 1.000 , 0.950 " 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.64 25 0.64 0 0.64 70 80 90 100 110 Figure 5.6 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-26* FWCF No Bypass + FWCF FHOOS K FWCF FHOOS w/ TCV Stuck a LOFH No Bypass -LHGRFACp + + U 04 Paae 5-26 LaSalle Unit 1 Cycle 10 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.48 60 1.62 25 2.19 25 2.20 0 2.70 70 80 90 100 110 Figure 5.7 BOC to 15,000 MWdlMTU EOOS Case I Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-27* FWCF No Bypass + FWCF FHOOS V K FWCF FHOOS %Y TCV Stuck A LOFH No Bypass

LOFH No Bypass w/TCV Stuck -OLMCPR x h Pln Trnsen o Aov, .. sis..

LaSalle Unit 1 Cycle 10 I 'nn 1.250 1.200 1.150 1.100 1.050 CL 1.000 S0.950 -0.900 0.850 0.800 0.750 0.700 -0.650-0 10 20 30 40 50 60 Power (% rated)70 80 90 100 110 Power LHGRFACp (%) Multiplier 100 0.92 80 0.91 60 0.89 25 0.69 25 0.69 0 0.69 Figure 5.8 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-28.FWCF No Bypass + FWCF FHOOS )K FWCF FHOOS w/ TCV Stuck A LOFH No Bypass -LHGRFACp + ++0.600 Z Plnnt Trnncziant Anal sis 4 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2-25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.47 60 1.59 25 2.36 25 2.36 0 2.86 70 80 90 100 110 Figure 5.9 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 PaQe 5-29* FWCF NO Bypass + FWCF FHOOS o FWCF No Bypass W TCV Stuck

FWCF FHOOS w/TCV Stuck a LOFH No Bypass 0 LOFH No Bypass W/ TCV Stuck -OLMCPR LaSalle Unit 1 Cycle 10 Dilnt Tranoimnt Anli ick* FWCF No Bypass + FWCF FHOOS o FWCF No Bypass w/ TCV Stuck x FWCF FHOOS w/ TCV Stuck -LHGRFACp+ I 0 1.300 1.250 1.200 1.150 1.100 1.050 Q. 1.000 S0.950 -0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)70 80 90 100 110 Power LHGRFACp (%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.66 25 0.66 0 0.66 Figure 5.10 15,000 MWdlMTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-30 0 Z__I LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.45 60 1.58 25 2.15 25 2.20 0 2.70 70 80 90 100 110 Figure 5.11 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-31 a. 0. U* FWCF No Bypass + FWCF FHOOS o FWCF No Bypass w/ TCV Stuck K FWCF FHOOS w/ TCV Stuck & LOFH No Bypass o LOFH No Bypass w/ TCV Stuck -OLMCPR LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 Q. ,.. 0.950 C, -J 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)70 80 90 100 110 Power LHGRFACp (%) Multiplier 100 0.90 80 0.90 60 0.90 25 0.69 25 0.69 0 0.69 Figure 5.12 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paqe 5-32 FWCF No Bypass

FWCFFHOOS o FWCF No Bypass w/TCV Stuck K FWCF FHOOS w/TCV Stuck -LHGRFACp 0 oo 0 0 O LaSalle Unit 1 Cycle 10 Plant Transient Analysis 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.51 60 1.62 25 2.45 25 2.45 0 2.95 70 80 90 100 110 Figure 5.13 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-33 I.3.05 2.95 2.85 2.75 2.65 2.55 2.45 2-35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 FWCF No Bypass + FWCF FHOOS o FWCF No Bypass w TCV Stuck X FWCF FHOOS wd TCV Stuck a LOFH No Bypass o LOFH No Bypass w/ TCV Stuck -OLMCPR LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 1.050 .1.000 0 .' 0.900 0.850 0.800 0.750 0.700 0.650 -0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.64 25 0.64 0 0.64 70 80 90 100 110 Figure 5.14 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-34* FWCF No Bypass + FWCF FHOOS SFWCF FHOOS w/ TCV Stuck A LOFH No Bypass --LHGRFACp + A + ++

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 5-35 2.85 ___ 2 FWCF No Bypass 2.75 + FWCFFHOOS o FWCF No Bypass W TCV Stuck 2.65

FWCF FHOOS w( TCV Stuck t LOFH No Bypass 2.55 ' LOFH No Bypass w/ TCV Stuck -OLMCPR 2.45 2.35 Z25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 A 1.25 1.15 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power MCPRp (%) Limit 100 1.48 60 1.62 25 2.19 25 2.20 0 2.70 Figure 5.15 15,000 MWdlMTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.

LaSalle Unit I Cycle 10 Plant Transient Analysis 1.250 1.200 1.150 1.100 1.050 Q 1.000 , 0.950 3j 0.900 0.850 0.800 0.750 0.700 0.650 -0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACP (%) Multiplier 100 0.92 80 0.91 60 0.89 25 0.69 25 0.69 0 0.69 70 80 90 100 110 Figure 5.16 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-36* FWCF No Bypass + FWCF FHOOS x FWCF FHOOS w/ TCV Stuck A LOFH No Bypass --LHGRFACP +÷ * + St +1 -110()1 3nO

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 205 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.54 80 1.74 80 1.81 25 2.36 25 2.36 0 2.86 70 80 90 100 110 Figure 5.17 BOC to 15,000 MWdlMTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-37 A Slow TCV + FWCF FHOOS

LRNB No RPT M FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck

FWCF FHOOS No RPT w/ TCV Stuck -OLPR + A+

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 U. S0.950 C, "= 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.89 60 0.88 25 0.65 25 0.65 0 0.65 70 80 90 100 110 Figure 5.18 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-38& Slow TCV + FWCFFHOOS

LRNB No RPT m FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck 4 FWCF FHOOS No RPT w/ TCV Stuck + -- LHGRFACp + + U + 3 A A AA AA LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.52 80 1.67 80 1.86 25 2.15 25 2.20 0 2.70 70 80 90 100 110 Figure 5.19 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paqe 5-39 A Slow TCV + FWCF FHOOS # LRNB No RPT a FWCF No RPT o3 FWCF FHOOS No RPT o FWCF No RPT w/TCV Stuck A FWCF FHOOS No RPT W/ TCV Stuck -OLMCPR + +++

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.79 80 0.79 25 0.67 25 0.67 0 0.67 70 80 90 100 110 Figure 5.20 BOC to 15,000 MWdlMTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paqe 5-40.,i C,, 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0.650 0.600 A Slow TCV + FWCF FHOOS

LRNB No RPT E FWCF No RPT 0 FWCF FHOOS No RPT o FWCF No RPT w/TCV Stuck A FWCF FHOO$ No RPT w/ TCV Stuck + -LHGRFACp

++ A + AA AA LaSalle Unit 1 Cycle 10 Plant Transient Analysis 3.05 2.95 2.85 2.75 2.65 1.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power ( rated)Power MCPRp (%) Limit 100 1.59 80 1.74 80 1.82 25 2.45 25 2.45 0 2.95 70 80 90 100 110 Figure 5.21 BOC to 15,000 MWdlMTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-41*A Slow TCV S+ FWCF FHOOS

LRNB No RPT I FWC No RPT 0 FWCF FHOOS W RPT

FWCF No RPT wTC-V Stuck A FWCF FHOOS No RPT Wd TCV Stuk .-OLMCPR A A A LaSalle Unit I Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 S0.950-a 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.87 80 0.87 25 0.64 25 0.64 0 0.64 70 80 90 100 110 Figure 5.22 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-42 A Slow TCV + FWCF FHOOS

LRNB No RPT m FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck & FWCF FHOOS No RPT w/ TCV Stuck + + -LHGRFACp + ++ + U i A A AA LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Paae 5-43 IASlow TCV* LRNB No RPT a FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck A FWCF FHOOS No RPT w/ TCV Stuck OLMCPR A +9 +£ + +0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)Power MCPRp (%) Limit 100 1.59 80 1.73 80 1.86 25 2.19 25 2.20 0 2.70 Figure 5.23 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 I0 2.05 a. E 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 q

Slow TCV LaSalle Unit I Cycle 10 OI~lnt Troncrint AnnilIcie 1.300 1.250 1.200 1.150 1.100 1.050 a. 1.000 L 0.950 0 -J 0.900-0.850 0.800 0.750 0.700 0.650 z,-, , 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.76 80 0.76 25 0.67 25 0.67 0 0.67 70 80 90 100 110 Figure 5.24 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-44 A Slow TCV + FWCF FHOOS

LRNB No RPT 0 FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w] TCV Stuck z FWCF FHOOS No RPTw/ TCV Stuck -LHGRFACp + ++ A + t A LaSalle Unit 1 Cycle 10 Plant Transient Analysis C. M. CL 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95-1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRP (%) Limit 100 1.59 80 1.74 80 1.81 25 2.36 25 2.36 0 2.86 70 80 90 100 110 Figure 5.25 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-45 I A Slow TCV+ FWCF FHOOS *LRNB No RPT

FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w/TCV A FWCF FHOOS No RPT -OLMCPR + AU-I Stuck EMF-2689 Revision 0 PaQe 5-46 LaSalle Unit 1 Cycle 10 T~~~I~~I IL I lIIII ' I ;~y~1.300 1.250 1.200 1.150 1.100 1.050 o. 1.000 IL S0.950 C, "- 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)70 80 90 100 110 Figure 5.26 15,000 MWdlMTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.A Slow TCV + FWCF FHOOS

LRNB No RPT

FWCF NO RPT o FWCF FHOOS No RPT o FWCF No RPTw/ TCV Stuck + + SFWCF FHOOS No RPT + --LHGRFACp + 01 A + A AAI /"a. I,"l al LaSalle Unit 1 Cycle 10 Plant Transient Analysis A Slow TCV S+ FWCF FHOOS # LRNB No RPT m FWCF No RPT E3 FWCF FHOOS No RPT

FWCF No RPT W/ TCV Stuck

FWCF FHOOS No RPT w/ TCV Stuck -OLMCPR + A a ++0 10 20 30 40 50 60 Power (% rated)Power MCPRP (%) Limit 100 1.58 80 1.67 80 1.86 25 2.15 25 2.20 0 2.70 70 80 90 100 110 Figure 5.27 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-47 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 j 2.05 0. 1.95 1.85 1.75 1.65 1.55 1.45 -1.35 1.25 1.15 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 1 A(Yn 0.950 S0.900 0.850 0.800 0.750 0.700 0.650 0.600 EMF-2689 Revision 0 Page 5-48 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.79 80 0.79 25 0.67 25 0.67 0 0.67 Figure 5.28 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.* Saow TCV + FWCF FHOOS

LRNB No RPT

FWCF No RPT

FWCF FHOOS No RPT o FWCF No RPT W/ TCV Stuck

FWCF FHOOS No RPT w/ TCV Stuck + -LHGRFACp

++ + A A A AA LaSalle Unit 1 Cycle 10 Plant Transient Analysis 3.05 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 1x 2.15 S2.05 1.95. 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRp (%) Limit 100 1.64 80 1.74 80 1.82 25 2.45 25 2.45 0 2.95 70 80 90 100 110 Figure 5.29 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-49 A Slow TCV + FWCF FHOOS

LRNB No RPT a FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w/TCV Stuck & FWCF FHOOS No RPT w/ TCV Stuck --OLMCPR AA ++ A ,

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-50 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 .0.950"- 0.900 0.850 0.800 0.750 0.650 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.82 80 0.82 25 0.64 25 0.64 0 0.64 70 80 90 100 110 Figure 5.30 15,000 MWdlMTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.A Slow TCV + FWCF FHOOS

LRNB No RPT n FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck & FWCF FHOOS No RPT w/ TCV Stuck -LHGRFACp++ + A A A U I t "AA AA AA A ann I1 -I+0.700 LaSalle Unit 1 Cycle 10 Plant Transient Analysis C.2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 Power (% rated)Power MCPRP (%) Limit 100 1.65 80 1.73 80 1.86 25 2.19 25 2.20 0 2.70 70 80 90 100 110 Figure 5.31 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-51 A Slow TCV+ FWCF FHOOS

LRNB No RPT m FWCF No RPT c3 FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck a FWCF FHOOS No RPT w/ TCV Stuck -OLMCPR A + A A EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-52 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0.650 0.600 A Slow TCV + FWCFFHOOS

LRNB No RPT m FWCF NoRPT o FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck SFWCF FHOOS No RPT w/ TCV Stuck + -LHGRFACp

+ + AA ++ A A + t A A A 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)Figure 5.32 15,000 MWdlMTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.a. .J Power LHGRFACp N% Multiplier 100 0.76 82 0.76 25 0.67 25 0.67 0 0.67 I LaSalle Unit 1 Cycle 10 0i1nh Trnnoinnf Anol cie 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 S0.950-0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.66 25 0.66 0 0.66 70 80 90 100 110 Figure 5.33 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-53 o FWCF No Bypass w/TCV Stuck o LOFH No Bypass w/ TCV Stuck -LHGRFACp 0 0 o 0 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 1.050 CL 1.000 WU. " 0.950 "J 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 70 80 90 100 110 Figure 5.34 BOC to 15,000 MWdlMTU 1 TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 D¢ r, rA...- Ok o FWCF No Bypass w/ TCV Stuck o LOFH No Bypass w/ TCV Stuck -LHGRFACp 0 o 0 00 EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-55 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 S0.950 "J 0.900 0.850 0.800 0.750 0.700 0.650-0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.64 25 0.64 0 0.64 70 80 90 100 110 Figure 5.35 BOC to 15,000 MWdlMTU I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.o FWCF No Bypass w/TCV Stuck o LOFH No Bypass w/ TCV Stuck -LHGRFACp 0 0 0 0 00 o0 70 80 90 100 110 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 70 80 90 100 110 Figure 5.36 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-56 0. -I 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0.650 0.600 o FWCF No Bypass w/ TCV Stuck > LOFH No Bypass w/ TCV Stuck -LHGRFACp 0 0 0 8 0 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 CL 1.000 S0.950 ,I"J 0.900 0.850 0.800 0.750 0.700 0.650 0.600 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.65 25 0.65 0 0.65 70 80 90 100 110 Figure 5.37 15,000 MWdlMTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paae 5-57 o FWCF No Bypass w/ TCV Stuck o LOFH No Bypass w/ TCV Stuck -LHGRFACp 0 O o 0 0 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 0.950

0.900 0.850 0.800 0.750 0.700 0.650 -0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 70 80 90 100 110 Figure 5.38 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -NSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-58 o FWCF No Bypass wI TCV Stuck

LOFH No Bypass w/ Stuck TCV -LHGRFACp 0 0 0 0 0 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 0. I.UUU IL S0.950 o -' 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0 10 20 30 40 50 60 Power (%rated)Power LHGRFACp (%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.64 25 0.64 0 0.64 70 80 90 100 110 Figure 5.39 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Page 5-59 o FWCF No Bypass wI TCV Stuck o LOFH No Bypass w/ TCV Stuck -LHGRFACp 0 0 0 00 LaSalle Unit 1 Cycle 10 1.300 1.250 1.200 1.150 1.100 1.0501 IL n-1.000 0.950 0.900 0.850 0.650 0.600 0 10 20 30 40 50 60 Power (% rated)Power LHGRFACp (%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 70 80 90 100 110 Figure 5.40 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.EMF-2689 Revision 0 Paqe 5-60 o FWCF No Bypass w/ TCV Stuck o LOFH No Bypass w/ TCV Stuck -LHGRFACp 0 00 o 8 o PinntT nQientAnal sis .L 0.800 0.750 0.700-EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 6-1 6.0 Transient Analysis for Thermal Margin -EOD/EOOS Combinations The limits presented in Section 5.0 support operation with ICF in conjunction with the EOOS scenarios presented in Table 1.1. Operation in the other EOD conditions (i.e. coastdown and FFTRFcoastdown) is currently not supported for LaSalle Unit 1 Cycle 10.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 7-1 7.0 Maximum Overpressurization Analysis This section describes the maximum overpressurization analyses performed to demonstrate compliance with the ASME Boiler and Pressure Vessel Code. The analysis shows that the safety/relief valves at LaSalle Unit 1 have sufficient capacity and performance to prevent the pressure from reaching the pressure safety limit of 110% of the design pressure.

7.1 Design

Basis The MSIV closure analysis was performed with the FRA-ANP plant simulator code COTRANSA2 (Reference

4) at a power/flow state point of 102% of rated power/1 05% flow. As indicated in Reference 1, the overpressurization analysis was performed at a cycle exposure of EOC + 1000 MWd/MTU. The following assumptions were made in the analysis.

The most critical active component (direct scram on valve position) was assumed to fail. However, scram on high-neutron flux and high-dome pressure is available.

At Exelon's request, analyses were performed to determine the minimum number of the highest set-point SRVs required to meet the ASME and Technical Specification pressure limits. It was determined that having the 10 highest set-point SRVs operable will meet the ASME and Technical Specification pressure limits. In order to support operation with 1 SRV out-of-service, the plant configuration needs to include at least 11 SRVs. As per ASME requirements, the SRVs are assumed to operate in the safety mode. TSSS insertion times were used. The initial dome pressure was set at the maximum allowed by the Technical Specifications (1035 psia).

An MSIV closure time of 1.1 seconds was assumed in the analysis.

EOC RPT is assumed inoperable; ATWS (high-dome pressure)

RPT is available.

7.2 Pressurization

Transients Results of analysis for the MSIV closure event initiated at 102% power/1 05% flow are presented in Table 7.1. Figures 7.1-7.5 show the response of various reactor plant parameters to the MSIV closure event. The maximum pressure of 1346 psig occurs in the lower plenum at approximately 4.3 seconds. The maximum dome pressure of 1321 psig occurs at 4.4 seconds.

The results demonstrate that the maximum vessel pressure limit of 1375 psig and dome pressure limit of 1325 psig are not exceeded.Framatome ANP, Inc.

EMF-2689 Revision 0 Paqe 7-2 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 7.1 ASME Overpressurization Analysis Results 102%PI105%F Peak Peak Maximum Maximum Neutron Heat Vessel Pressure Dome Flux Flux Lower-Plenum Pressure Event (% rated) (% rated) (psig) (psig) MSIV closure 340 138 1346 1321 Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.0 3.0 4.0 TIME, SECONDS 11/01/01 09:35.03 LSA CYCLE 10 MSIV CLOSURE NOS-11894.

JOB ID-19393 Figure 7.1 Overpressurization Event at 1021105 MSIV Closure Key Parameters Framatome ANP, Inc.EMF-2689 Revision 0 Paqe 7-3 400.0,.300.0 -I 0 z C--w U.1 a_200.0 100.0-CORE POWER HEAT FLUX CORE FLOW STEAM FLOW FEED FLOW --- --------------------

'\I V'.0_Inn A.0 21.5.0 61.7.0 EMF-2689 Revision 0 Paae 7-4 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis O I-z 0 m I-bi --J 39: W UI 11/01/01 09:35:03 LSA CYCLE 10 MSIV CLOSURE NOS-11894.

J0B 10-19393 Figure 7.2 Overpressurization Event at 102/105 MSIV Closure Vessel Water Level Framatome ANP, Inc.i -Pane 7-4 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 03 1-J ILa -IJ TIME, SECONDS LSA CYCLE 10 MSIV CLOSURE 11/01/01 09:35:03 NQS-11894, ,J"f 10-19393 Figure 7.3 Overpressurization Event at 1021105 MSIV Closure Lower-Plenum Pressure Framatome ANP, Inc.EMF-2689 Revision 0 Page 7-5 EMF-2689 Revision 0 ki~c LaSalle Unit 1 Cycle 10 Plant Transient Analysis L U) (n) Li LLi 0 11/01/01 09:35-03 LSA CYCLE 10 MSIV CLOSURE NQS-11894, JOE ID-19393 Figure 7.4 Overpressurization Event at 102/105 MSIV Closure Dome Pressure Framatome ANP, Inc.

LaSalle Unit I Cycle 10 Plant Transient Analysis 1.0 2-0"3.0 4.0 TIME, SECONDS 11/01/01 09:3503 LSA CYCLE 10 MSIV CLOSURE NOS-11894, JOB ID-19393 Number Opening of Pressure Bank SRVs (psia) 1 0 NA 2 2 1235.3 3 4 1245.6 4 4 1255.9 5 0 NA Figure 7.5 Overpressurization Event at 102/105 MSIV Closure Safety/Relief Valve Flow Rates Framatome ANP, Inc.~17nAr n.1500.0 U) S1000.0 0 -. 0,.. 500.0-.0 SRV BANK 1 SRV BANK 2 SRV BANK 3 SRV BANK 4 SRV BANK 5 -j itll rqi, * , ,* I EMF-2689 Revision 0 Page 7-7 7.0.0 5.0 6.0 EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 8-1 8.0 References

1. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit 1 Cycle 10 Calculation Plan," DEG:01:084, June 6, 2001. 2. 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, Exxon Nuclear Company, June 1986. 3. 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 the CASMO-3GIMICROBURN-B Calculation Methodology, Advanced Nuclear Fuels Corporation, November 1990. 4. ANF-913(P)(A)

Volume 1 Revision 1 and Volume I Supplements 2, 3 and 4, COTRANSA2:

A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990. 5. ANF-524(P)(A)

Revision 2 and Supplements I and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990. 6. ANF-1 125(P)(A) and Supplement 1 and 2, ANFB Critical Power Correlation, Advanced Nuclear Fuels Corporation, April 1990. 7. XN-NF-80-19(P)(A)

Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987. 8. EMF-2533 Revision 0, LaSalle Unit 1 Cycle 10 Principal Transient Analysis Parameters, Framatome ANP Richland, Inc., April 2001. 9. Letter, D. E. Garber (FRA-ANP) to F. W. Trikur (Exelon), "Disposition of Events Summary for the Introduction of ATRIUM T M-10 Fuel at LaSalle County Station," DEG:01:179, October 30, 2001. 10. Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), "Description of Measured Power Uncertainty for POWERPLEX Operation Without Calibrated LPRMs," DEG:00:061, March 7, 2000. 11. XN-NF-84-105(P)(A)

Volume 1 and Volume I Supplements I and 2, XCOBRA-T:

A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987. 12. EMF-2209(P)(A)

Revision 1, SPCB Critical Power Correlation, Siemens Power Corporation, July 2000. 13. XN-NF-81-58(P)(A)

Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 8-2 8.0 References (Continued)

14. LaSalle County Nuclear Station Units 1 and 2 Improved Technical Specifications, as amended.

15. EMF-2690 Revision 0, LaSalle Unit 1 Cycle 10 Reload Analysis, Framatome ANP, Inc., January 2002. 16. EMF-1 903(P) Revision 3, Impact of Failed/Bypassed LPRMs and TIPs and Extended LPRM Calibration interval on Radial Bundle Power Uncertainty, Siemens Power Corporation, March 2000. 17. ANF-1 125(P)(A)

Supplement 1 Appendix E, ANFB Critical Power Correlation Determination of A TRIUMTM-9B Additive Constant Uncertainties, Siemens Power Corporation, September 1998. 18. ANF-1 373(P), Procedure Guide for SAFLIM2, Siemens Power Corporation, February 1991. 19. Letter, D. E. Garber (SPC) to R. J. Chin (CornEd), "Extension of LPRM Calibration Interval to 2500 EFPH," DEG:00:088, April 17, 2000. 20. EMF-2277 Revision 1, LaSalle Unit I Cycle 9 Plant Transient Analysis, Siemens Power Corporation, October 1999. 21. EMF-2589(P)

Revision 0, Mechanical and Thermal-Hydraulic Design Report for LaSalle Units I and 2 ATRIUMTM-10 Fuel Assemblies, Framatome ANP Richland, Inc., July 2001. 22. EMF-2563(P)

Revision 1, Fuel Mechanical Design Report Exposure Extension for A TRIUM T M-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, Framatome ANP Richland, Inc., August 2001. 23. EMF-95-205(P)

Revision 2, LaSalle Extended Operating Domain (EOD) and Equipment Out of Service (EOOS) Safety Analysis for A TRIUMTm-9B Fuel, Siemens Power Corporation, June 1996.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page A-1 Appendix A Power-Dependent LHGR Limit Generation The linear heat generation rate (LHGR) operating limit is established to ensure that the steady state LHGR (SSLHGR) limit is protected during normal operation and that the protection against power transient (PAPT) LHGR limit is protected during an anticipated operational occurrence (AOO). To ensure that the LHGR operating limit provides the necessary protection during operation at off-rated conditions, adjustments to the SSLHGR limits may be necessary.

These adjustments are made by applying power and flow-dependent LHGR multipliers (LHGRFACp and LHGRFACf, respectively) to the SSLHGR limit. The LHGR operating limit (LHGROL) for a given operating condition is determined as follows: LHGROL = min [LHGRFACp x SSLHGR, LHGRFACf x SSLHGR] The power-dependent LHGR multipliers (LHGRFACp) are determined using the heat flux excursion experienced by the fuel during AQOs. The heat flux ratio (HFR) is defined as the ratio of the maximum nodal transient heat flux over the maximum nodal heat flux at the initiation of the transient.

The HFR provides a measure of the LHGR excursion during the transient.

The PAPT limit divided by the SSLHGR limit provides an upper limit for the HFR to ensure that the PAPT LHGR limit is not violated during an AOO. LHGRFACp is set equal to the minimum of the PAPT/SSLHGR ratio over HFR, or 1.0. Based on the ATRIUM-10 LHGR limits presented in Reference A.1 and the ATRIUM-9B LHGR limits presented in Reference A.2, LHGRFACp is established as follows: PAPT = 1.35 SSLHGR HFR = QMaXt emaxO LHGRFACP = m 1 HFR 1.0 In some cases, the established MCPR limit precludes operation at the SSLHGR limit. This allows for a larger LHGR excursion during the transient without violating the PAPT LHGR limit.Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page A-2 References A.1 EMF-2589(P)

Revision 0, Mechanical and Thermal-Hydraulic Design Report for LaSalle Units I and 2 A TRIUM T I O Fuel Assemblies, Framatome ANP Richland, Inc., July 2001. A.2 EMF-2563(P)

Revision 1, Fuel Mechanical Design Report Exposure Extension for ATRIUM T x-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, Framatome ANP Richland, Inc., August 2001.Framatome ANP, Inc.

LaSalle Unit 1 Cycle 10 Plant Transient Analvsis Distribution D. D. M J. J.G E. E M. M.Carr, 23 Garber (9 copies) Garrett, 23 Haun, 34 Moose, 23 E-Mail Notification D. 0. J. R. P.B. McBurney C. Brown G. Ingham R. Schnepp D. Wimpy Framatome ANP, Inc.EMF-2689 Revikinn f)

ML020600456

Text

Subject:

Reference:

Description:

Reference:

Description:

2.2.1 Manual

2.2.3 Nominal

Reference:

Description:

4.1 Technical

Reference:

Description:

Reference:

Description:

5.3 Bases

Subject:

3.2.1 Hydraulic

9.2 Figures

3.3.1 Coolant

3.3.3 Design

9.8 Reference

9.4 Limiting

9.4 Limiting

9.4 Limiting

5.6.2 Misoriented

5.7 Determination

7.1 Limiting

7.2.1 Average

7.2.3 Linear

3.1 System

3.5 Nuclear

7.1 Design

7.2 Pressurization

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