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Part 1 of 2, LaSalle, Unit 1 Cycle 10A Core Operating Limits Report (COLR)
	ML023380689
Person / Time
Site:	LaSalle
Issue date:	11/26/2002
From:	; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
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Technical Requirements Manual Appendix I (Amendment 49)

LaSalle Unit I Cycle 1OA Core Operating Limits Report and Reload Transient Analysis Results Revision 1

Technical Requirements Manual - Appendix I L1C1OA Core Operating Limits Report Section 1 Core Operating Limits Report for LaSalle Unit 1 Cycle 10A

Manual - Appendix I Technical Requirements Technical Requirements Manual - Appendix I L1C10A Core Operating Limits Report Issuance of Changes Summary

- I I Affected Summary of Changes Revision Date Affected Pages Sections U oieuu All All flrieinI Iir I

I Unit I Cycle IOA 0 Ii talzuuz iv Updated Reference 16 to the control blade history letter References for LIC10A.

2-1 through 2-14 Updated MCPR(p) limits for fresh ATRIUM-10 fuel.

2.2.1 Renumbered tables.

Updated steady-state LHGR limits for fresh ATRIUM-10 I 9/2002 3.2 3-1, 3-2, and 3-3 fuel.

3.2 3-12 Deleted third bullet under Table 3-14.

6 6-2 Updated footnote 4 to be consistent with the updated I I application I of control blade history penalties. I I I ii Revision I I *sqle Unit I Cycle I0A

Technical Requirements Manual - Appendix I LIC10A Core Operating Limits Report Table of Contents IV References .........................................................................................................................

1-1

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

1-1 1.1 Technical Specification Reference ............................................................. 1-1 1.2 Description ................................................................................................

2-1

2. Minimum Critical Power Ratio (3.2.2) ..................................................................

2-1 2.1 Technical Specification Reference ............................................................. 2-1 2.2 Description ................................................................................................

3-1

3. Linear Heat Generation Rate (3.2.3) ....................................................................

3-1 3.1 Technical Specification Reference ............................................................. 3-1 3.2 Description ..........................................................................................

4-1

4. Control Rod Withdrawal Block Instrumentation (3.3.2.1) .................

4-1 4.1 Technical Specification Reference ............................................................. 4-1 4.2 Description .................................................................................................

5-1

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

5-1 5.1 Technical Specification Reference ............................................................. 5-1 5.2 Description ................................................................................................. 5-1 5.3 Bases .........................................................................................................

6-1

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

7-1

7. Methodology (5.6.5) ..............................................................................................

iii Revision I I _c-, j.-JlI Inif I rvrlp 1 (')A

Technical Requirements Manual - Appendix I LI C1 OA 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 I 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. JI1-03692-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-II 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 I and 2," December 1993 and June 1998, respectively.

11. EMF-2533 Revision 0, "LaSalle Unit I 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-1 87-13-0792 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.

16. Letter from D. E. Garber to F. W. Trikur, "Control Blade History Study for LaSalle Unit I Cycle 10A", DEG:02:110, July 17, 2002.

17. Letter from D. E. Garber to F. W. Trikur, "Licensing Letter Report for Impact of Revised Core Loading on LaSalle 1 Cycle 10 Licensing", DEG:02:094, May 23, 2002.

iv Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I L1C10A 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:

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

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

Page MAPLHGR multiplier for ATRIUM-10 and ATRIUM-9B fuel is 0.90 (Reference 3 7-1). The SLO MAPLHGR multipliers for GE9B fuel are shown In Table 1-5 (MAPFACp) product and Table 1-6 (MAPFACF). The SLO MAPLHGR limit for the GE9B fuel is thethe SLO of the MAPLHGR limit from Table 1-3 or 1-4 and the minimum of either 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 A10-4039B-15GV75-100M A10-4037B-16GV75-100M (Bundle types 10, 11, 20, 21, 22, 23, 24, 26, 27, 28, 29, 30, 31, 32, 41, 43, 45 and 49)

(Reference 3 Section 7.2.1)

Planar Average Exposure MAPLHGR (GWdlMT) (kW/ft) 0.0 12.5 15.0 12.5 55.0 9.1 64.0 7.6 Table 1-2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for ATRIUM-9B Fuel SPCA9-393B-16GZ-100M SPCA9-396B-12GZB-100M SPCA9-384B-1 1GZ-80M SPCA9-396B-12GZC-10DM (Bundle types 6, 7, 8 and 9)

(Reference 3 Section 7.2.1)

Planar Average Exposure MAPLHGR (GWdiMT) (kW/ft) 0.0 13.5 20.0 13.5 64.3 9.07 1-1 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C10 A Core Operating Limits Report.

Table 1-3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE9B Fuel GE9B-P8CWB342-10GZ-80M-150 (Bundle 3867, bundle type 5)

(References 5 and 12)

Planar Average Lattice Specific MAPLHGR limit (kWlft)

Exposure (GWdIST) 0 12.66 12.04 12.25 11.72 12.09 12.12 12.66 12.59 12.08 12.28 11.77 0.200 12.59 1.000 12.40 12.16 12.35 11.87 12.22 12A0 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 1-2 Revision 1 LaSalle Unit I Cycle 10A

Technical Requirements Manual- Appendix I LI C1 A Core Operating Limits Report Table 1-4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE9B Fuel GE9B-P8CWB343-12GZ-80M-150 (Bundle 3866, bundle type 4)

(References 5 end 12)

Planar Average Lattice Specific MAPLHGR limit (kW/ft)

Exposure (GWd/ST) 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 12.35 13.75 13.60 13.57 12.35 12.500 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 10.600 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 GE9B Fuel (References 5 and 10)

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.

t 1-3 Revision 1 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LICIQA Core Operating Limits Report Table 1-6 SLO MAPFACF multiplier 13) for GE9B Fuel (References 5 end 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.

1-4 Revision I LaSalle Unit 1 Cycle 1OA

Technical Requirements Manual - Appendix I LIC1OA Core Operating Limits Report

.2. Minimum Critical Power Ratio (3.2.2) 2.1 Technical Specification

Reference:

Section 3.2.2.

2.2

Description:

exposure of MCPR limits from BOC to Coastdown are applicable up to a core average (Reference 31,495.1 MWd/MTU (whicir is the licensing basis exposure used by FANP).

3). Limits beyond the EOC exposure are not provided.

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 from The power-dependent MCPR value, MCPRp, is determinedSection "Tables2-1 through 2-12, and is dependent on exposure (See 6, Note 4 for implementation details), fuel type and scram speed, In addition to power level. Tables 2-1, 2-2, and 2-5 through 2-10 are applicable to ATRIUM-10 fuel and Tables 2-3, 2-4, 2-11, and 2-12 are 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 2-13 for all fuel types In Cycle 10A.

2.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control is not supported for LIC10A.

2.2.3 Nominal Scram Speeds To utilize the MCPR limits for Nominal Scram Speeds (NSS), the core average values scram speed insertion time must be equal to or less than the following (Reference 11 Section 7.7).

Notch Position Timec 45 0.380 39 0.680 25 1.680 05 2.680 2-1 Revision I LaSalle Unit I Cycle I0A

Technical Requirements Manual - Appendix 1 LI C1 OA Core Operating Limits Report Table 2-1 MCPRP For BOC to Second Cycle IOA Sequence Exchange - Applicable to all ATRIUM-10 Fuel Exposure For Second Cycle 10A Sequence Exchange to the Final Sequence Exchange at 12,000 MWd/MT Cycle Applicable to all ATRIUM-10 Fuel Except Those Located in Cells 7B, 7C, 8A, 9A, 10B, and 1OC Nominal Scram Speeds (NSS)

(Reference 3 Table 5.1 and Reference 16 Table 5.1)

Core Thermal Power % of rated) 0 25 25(25.1) 60 80 80(80.1) 100 EOOS Combination MCPRP 2.70 2.20 2.07 1.52 1 Base Case Operation EOOS Case i 2.86 2.36 2.36 1.59 14 E Case 2 2.86 2.36 2.36 2.86 2.36 2.36 1.59 EOOS Case 3 2.21 2.08 1.53 1.44 Single Loop Operation (SLO) 2.71 2.37 2.37 1.60 1.48 SLO with EOOS Case 1 2.87 2.87 2.37 2.37 SLO with EOOS Case 2 2.37 2.37 1.60 1.48 SLO with EOOS Case 3 2.87

"* Values are Interpolated between relevant power levels.

thermal

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

"* Allowable EOOS conditions are listed InSection 6.

2-2 Revision 1 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C10 A Core Operating Limits Report Table 2-2 MCPRp For BOC to Second Cycle IOA Sequence Exchange - Applicable to all ATRIUM-1 0 Fuel For Second Cycle I0A Sequence Exchange to the Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure Applicable to all ATRIUM-1 0 Fuel Except Those Located in Cells 7B, 7C, 8A, 9A, 103B, and 1OC Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.2 and Reference 16 Table 5.1)

Core Thermal Power (% of rated)

EOOS Combination 0 25 25(25.1) 60 80 80(80.1) 100 MCPRp S~1.46 Base Case Operation 2.70 2.20 2.15 1.55 S~1.51 EOOS Case I 2.95 2.45 2.45 1.62 1.74 1.59 EOOS Case 2 2.95 2.45 2.45 1.82 EOOS Case 3 2.95 2.45 2.45 1.62 1.47 Single Loop Operation (SLO) 2.71 2.21 2.16 1.56

' 1.52 SLO with EOOS Case I 2.96 2.46 2.46 1.63 SLO with EOOS Case 2 2.96 2.46 I 2.46 1.83 1.75 1.60 2.46 2.46 1.63 1.52 SLO with EOOS Case 3 2.96

_________________________________ J- - .1 S Values are interpolated between relevant power levels.

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

0 Allowable EOOS conditions are listed in Section 6.

Revision I LaSalle Unit I Cycle 10A 2-3

Technical Requirements Manual - Appendix I LI C10 A Core Operating Limits Report Table 2-3 MCPRp For BO1C to Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure For ATRlUM-9B and GE9B Fuel Nominal Scram Speeds (NSS)

(Reference 3 Table 5.1)

Core Thermal Power % of rated)

EOOS Combination 0 25 25(25.1) 1 60 80 80(80.1) 100 MCPRP Base Case Operation 2.70 2.20 1.95 1.50 1.42 EOOS Case 1 2.70 2.20 2.15 1.58 1.45 EOOS Case2 2.70 2.20 2.15 1.52 EOOS Case 3 2.70 2.20 2.15 1.58 1.45 Single Loop Operation (SLO) 2.71 2.21 1.96 1.51 SLO with EOOS Case 1 2.71 2.21 2.16 1.59 1.46 SLO v~th EOOS Case 2 2.71 12.21 2.16 1.87 . 1.68 1.53 SLO with EOOS Case 3 2.71 2.21 2.16 1.59

"* 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.

2-4 Revision 1 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C10A Core Operating Limits Report Table 2-4 MCPRp For BOC to Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure For ATRIUM-9B and GE9B Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.2)

Core Thermal Power (% of rated)

EOOS Combination 0 25 25(25.1) 60 8o 80(80.1) 100 MCPR*,

Base Case Operation 2.70 2.20 1.96 1.54 1.44 EOOS Case 1 2.70 2.20 2.19 1.62 1.48 EOOS Case 2 2.70 2.20 2.19 1.59 EOOS Case 3 2.70 2.20 2.19 1.62 1.48 Single Loop Operation (SLO) 2.71 2.21 1.97 1.55 '1.45 SLO with EOOS Case 1 2.71 2.21 2.20 1.63 1.49 SLO with EOOS Case 2 2.71 2.21 2.20 1.87 1.74 1.

SLO with EOOS Case 3 2.71 2.21 2.20 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 I Cycle 10A 2-5 Revision 1

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2-5 MCPRP For Second Cycle 10A Sequence Exchange to Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure For ATRIUM-1 0 Fuel Located in 9A, 10B, and I OC Cells Nominal Scram Speeds (NSS)

(Reference 3 Table 5.1 and Reference 16 Table 5.1)

Core Thermal Power (%of rated)_

EOOS Combination 0 25 25(25.1) 60 80 80(80At) 100 MCPRP Base Case Operation 2.74 2.24 2.11 1.56 * * *1.47 EOOS Case I 2.90 2.40 2.40 1.63 EOOS Case 2 2.90 2.40 2.401.8.5 EOOS Case 3 2.90 2.40 2.40 1.63 15 Single Loop Operation (SLO) 2.75 2.25 2.12 1.57 SLO with EOOS Case I 2.91 2.41 2.41 1.64 1.52 SLO with EOOS Case 2 2.91 2.41 2.41 * .6 I 1.79 1.59 SLO with EOOS Case 3 2.-91 2.41 2.41 1.6 1.52

Values are interpolated between relevant power levels.

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

Allowable EOOS conditions are listed in Section 6.

2-6 Revision I I ^0*11^ I In; 4 tnA i 4n LidOQUdIt 1.1I 11. I JYI.'Io Iu

Technical Requirements Manual - Appendix I L1C10A Core Operating Limits Report Table 2-6 MCPRp For Second Cycle I0A Sequence Exchange to Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure For ATRIUM-IO Fuel Located in 9A, 10B, and IOC Cells Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.2 and Reference 16 Table 5.1)

Core Thermal Power (% of rated)

EOOS Combination 0 25 25(25.1) 60 80 80(80.1) 100 MCPRp_

Base Case Operation 2.74 2.24 2.19 1.59 1.50 EOOS Case I 2.99 2.49 2.49 1.66 J2.49 1.55 EQOS Case 2 j 2.99 2.49 1.86 1.78 1.63 EOOS Case 3 2.99 2.49 2.49 1.66 1.55 Single Loop Operation (SLO) 2.75 2.25 2.20 1.60 1.51 SLO with EOOS Case 1 3.00 2.50 2.50 1.67 ý 1.56 SLO with EOOS Case 2 3.00 2.50 2.50 1.64 SLO with EOOS Case 3 3.00 1 2.50 1.50 1.67 J1.56

"* Values are Interpolated between relevant power levels.

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

"* Allowable EOOS conditions are listed in Section 6.

2-7 Revision 1 LaSalle Unit 1 Cycle 10A

Technical Requirements Manual - Appendix I LI C1 A Core Operating Limits Report Table 2-7 MCPRp For Second Cycle 10A Sequence Exchange to Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure For ATRIUM-10 Fuel Located in 7B, 7C, and BA Cells Nominal Scram Speeds (NSS)

(Reference 3 Table 5.1 and Reference 16 Table 5.1)

Core Thermal Power (%of rated)

EOOS Combination 0 1 25 1 25(25.1) 1 40 1 40(40.1) 1 60 1 80 I 80(80.1) 1 100 MCPRp Base Case Operation 2.73 2.23 2.10 1 1.87 1.84 1.52 1 i*1.43*

EOOS Case 1 2.89 2.39 2.39 1.62 1.84 1.77 ] 1.57 EOOS Case 2 2.89 2.39 2.39 EOOS Case 3 2.89 2.39 2.39 S~1.50 Single Loop Operation (SLO) 2.74 2.24 2.11

.* 1.44 SLO with EOOS Case 1 2.90 2.40 2.40 1.51 SLO with EOOS Case 2 2.90 2.40 2.40 SLO with EOOS Case 3 2.90 2.40 2.40

Values are interpolated between relevant power levels.

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

"* Allowable EOOS conditions are listed In Section 6.

"* The 40% and 40(40.1)% values were determined from Interpolation of the Reference 3 values followed by application of the Reference 16 penalties.

2-8 Revision 1 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C1 A Core Operating Limits Report Table 2-8 MCPRp*

For Second Cycle I1A Sequence Exchange to Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure For ATRIUM-10 Fuel Located in 7B, 7C, and 8A Cells Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.2 end Reference 16 Table 5.1)

Values are interpolated between relevant power levels.

thermal

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

Allowable EOOS conditions are listed In Section 6.

Reference 3 values

The 40% and 40(40.1)% values were determined from Interpolation of the followed by application of the Reference 16 penalties.

Revision 1 2-9 LaSalle Unit I Cycle 10A

Technical LI C10 Requirements A Core Operating Manual Limits Report I

- Appendix Table 2-9 MCPRp For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-1 0 Fuel Nominal Scram Speeds (NSS)

(Reference 3 Table 5.3)

Core Thermal Power (% of rated)

EOOS Combination 25 25(25.1) 60 80 80(80.1) 100 MCPRP EOOS Case 1 2.86 2.36 2.36 1.59 1A7 EOOS Case 2 2.86 2.36 2.36 1.81 1.74 1.59 EOOS Case 3 2.86 2.36 2.36 159147 Single Loop Operation (SLO) 2.71 2.21 2.08 1.53 1.48 SLO with EOOS Case 1 2.87 2.37 2.37 1.60 1.48 SLO with EOOS Case 2 2.87 2.37 2.37 1.82 1.75 1.60 SLO with EOOS Case 3 2.87 2.37 2.37 1.60 1A8

Values are interpolated between relevant power levels.

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

Allowable EOOS conditions are listed In Section 6.

LaSalle Unit I Cycle 10A 2-10 Revision 1

Technical Requirements Manual - Appendix I LICI0A Core Operating Limits Report Table 2-10 MCPRP For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-10 Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.4)

Core Thermal Power (% of rated)

EOOS Combination 0 25 125(25.1)1 60 1 80 1 80(80.1) 100 MCPRp Base Case Operation 2.70 2.20 2.15 II 1.55 81.50 EOOS Case I 2.95 2.45 2.45 I 1.62 1.51 1.82 1.74 1.64 EOOS Case 2 2.95 2.45 2.45 EOOS Case 3 2.95 2.45 2.45 1.51 Single Loop Operation (SLO) 2.71 2.21 2.16 1.56 1.52 SLO with EOOS Case 1 2.96 2.46 2.46 1.63 1.8317 1.65 SLO with EOOS Case 2 2.96 2.46 2.46 Sol= 1.52 SLO with EOOS Case 3 2.96 2.46 2.46 1.63 0 Values are Interpolated between relevant power levels.

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

0 Allowable EOOS conditions are listed InSection 6.

2-11 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I Ll Cl OA Core Operating Limits Report Table 2-11 MCPRp For Final Sequence Exchange at 12,000 MWdlMT Cycle Exposure to Coastdown (EOC)

For ATRIUM-9B and GE9B Fuel Nominal Scram Speeds (NSS)

(Reference 3 Table 5.3)

Core Thermal Power (%of rated) oos Combnaton 0 I25 I25(25.1) 60 80 80(80.1) l 100 MCPRP Base Case Operation 2.70 2.20 1.95 1.50 1.43 EOOS Case 1 2.70 2.20 2.15 1.58 1.45 EOOS Case 2 2.70 2.20 2.15 1.86 1.67 1.58 EOOS Case 3 2.70 2.20 2A5 1.58 1.45 2.21 1.96 1.51 1.44 Single Loop Operation (SLO) 2.71 2.71 2.21 2.16 1.59 1.46 SLO with EOOS Case 1 2.71 2.21 2.16 1*_._*187 * **1.68 1.59 SLO with EOOS Case 2 2.71- i 2.21 2-16 - t59 1.46 SLO with EOOS Case 3 -

Values are Interpolated between relevant power levels. thermal

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

Allowable EOOS conditions are listed InSection 6.

S. Revision I

. .. . m *a

A 2-12 LaSalle Unit I Cycle 1u0

Technical Requirements Manual - Appendix I L1C10A Core Operating Limits Report Table 2-12 MCPRp For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-9B and GE9B Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.4)

Core Thermal Power (% of rated)

EOOS Combination 0 25 25(25.1) 60 80 80(80.1) 100 MCPRP Base Case Operation 27 .0 19 .414 EOOS Case 1 2.70 2.20 2.19 1.62 1.48 EOOS Case 2 2.70 2.20 2.19 1.86 1.73 1.65 EOOS Case 3 2.70 2.20 2.19 1.62 .48 Single Loop Operation (SLO) 2.71 2.21 1.97 1.55 1.45 SLO with EOOS Case 1 2.71 2.21 2.20 1.63 SLO with EOOS Case 2 2.71 2.21 2.20 1.87 1.74 1.66 SLO with EOOS Case 3 2.71 2.21 2.20 1.63-- 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 LHGRFACp multiplier should be applied.

Allowable EOOS conditions are listed in Section 6.

LaSalle Unit I Cycle 10A 2-13 Revision 1

Technical Requirements Manual - Appendix I LICI1A Core Operating Limits Report Table 2-13 MCPRF limits for ATRIUM-10, ATRIUM-9B, and GE9B Fuel (Reference 3 Figure 5.1)

Flow (% of rated) MCPRF 0 1.63 30 1.63 100 1.19 105 1.11

"* Values are Interpolated between relevant flow values.

" Values presented 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.

2-14 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I L1 C10 A Core Operating Limits Report Table 2-14 MCPRP For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-10 Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.4)

Core Thermal Power (% of rated)

EOOS Combination 0 25 25(25.1) 60 80 80(80.1) 100 Base Case Operation 2.70 f2.20 2.5 15 1.50 EOOS Case I 2.95 2.45 2.45 1.62 1.51 EQOS Case 2 - J 2.95 2.45 24 1.82 1.74 1.64 EOOS Case 3 1 2.95 2.45 1 2.45 1.51 Single Loop Operation (SLO) 2.71 2.21 2.16 1.56 1.51 SLO with EOOS Case 1 2.96 2.46 2.46 1.63 1.52 SLO with EOOS Case 2 2.96 2.46 2.46 1.65 SLO with EOOS Case 3 2.96 2.46 2.46 1.63 1.52

Values are interpolated between relevant power levels.

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

Allowable EOOS conditions are listed in Section 6.

LaSalle Unit I Cycle 1OA 2-15 Revision 0

Technical Requirements Manual - Appendix I LC101A Core Operating Limits Report Table 2-15 MCPRP For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-9B and GE9B Fuel Nominal Scram Speeds (NSS)

(Reference 3 Table 5.3)

Core Thermal Power (% of rated)

EOOS combination 0 25 25(25.1) 60 80 80(80.1) 100 MCPRP Base Case Operatfon 2.70 220 1.95 1.50 1.43 EOOS Case 1 2.70 2.20 2-15 1.58 1.45 EOOS Case 2 2-70 2.20 2-15 EOOS Case 3 2.70 2-20 2.15 1.45 Single Loop Operation (SLO) 2.71 2.21 1.96 1.51 1.44 SLO with EDOS Case 1 2.71 2.21 2.16 1.59 14 SLO with EOOS Case 2 2.71 2.21 2.16 1.87 1.68 1.59 SLO with EOOS Case 3 2.71 2.21 2.16 1.59 m i 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 multiplier should be applied.

Allowable EOOS conditions are listed in Section 6.

LaSalle Unit 1 Cycle 10A 2-16 Revision 0

Technical Requirements Manual - Appendix I LI C1 A Core Operating Limits Report Table 2-16 MCPRp For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-9B and GE.9B Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.4)

Core Thermal Power (% of rated)

EOOS Combination 0 25 25(25.1) - 60 I 80 1 80(80.1) 100 MCPRP Base Case Operation 2.70 2.20 1.96 1.54 ** 1.44 EOOS Case 1 2.70 2.20 2.19 1.62 1.48 EOOS Case22.70 2.20 2.19 1.86 1.73 1.65 EOOS Case 3 2.70 2.20 2.19 1.62 1.48 1.97 1.55 1.45 Single Loop Operation (SLO) 2.71 2.21 2.71 2.21 2.20 1.63 1.49 SLO with EOOS Case 1 1.87 1.74 i 1.66 SLO with EOOS Case 2 2.71 2.21 2.20 "

1.4 SLO with EOOS Case 3 2.71 2.21 2.20 1 1.63 Values are interpolated between relevant power levels.

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

0 Allowable EOOS conditions are listed In Section 6.

LaSalle Unit 1 Cycle I0A 2-17 Revision 0

Technical Requirements Manual - Appendix I L1CI0A Core Operating Limits Report Table 2-17 MCPRF limits for ATRIUM-10, ATRIUM-9B, and GE9B Fuel (Reference 3 Figure 5.1)

Flow (% of rated) MCPRF 0 1.63 30 1.63 100 1.19 105 1.11

"* Values are interpolated between relevant flow values.

" Values presented in Table 2-17 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.

2-18 Revision 0 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I L1C1OA Core Operating Limits Report

3. Linear Heat Generation Rate (3.2.3) 3.1 Technical Specification

Reference:

Section 3.2.3.

3.2

Description:

The LHGR Limit is the product of the LHGR Limit from Tables 3-1, 3-2a, 3-2b, 3-3, 3-4 or 3-5 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 3-6, 3-7, 3-8 or 3-9 for ATRIUM-10 fuel, Table 3-10, 3-11, 3-12 or 3-13 for ATRIUM-9B fuel or Table 3-14 or 3-15 for GE9B fuel.

The applicable flow dependent LHGR Factor (LHGRFACF) is determined from Table 3-16 for ATRIUM-10 and ATRIUM-9B fuels or Table 3-17 for GE9B fuel.

Table 3-1 Steady-State LHGR Limits for all ATRIUM-10 Fuel Except those Located in Cell Locations 7B, 7C, 8A, and 10A Al 0-4039B-1 5GV75-1 0DM Al 0-4037B-1 6GV75-1 00M (Bundle types 10, 11, 20, 24, 26, 27, 28, 29,31, 32, 41, 45 and 49)

(Reference 3 Section 7.2.3)

Average Planar LHGR Limit Exposure (kWtft)

(GWd/MT) 0.0 13.4 15.0 13.4 55.0 9.1 64.0 7.3 Table 3-2a Steady-State LHGR Limits for ATRIUM-10 Fuel Located in Cell Locations 7B, 7C, and 8A Al 0-4039B-1 5GV75-1 0DM Al 0-4037B-1 6GV75-1 0DM (Bundle types 21, 22, 23, and 43)

(Reference 3 Section 7.2.3 end Reference 16 Section 2.0)

Average Planar LHGR Limit Exposure (kW/ft)

(GWd/MT) 0.0 13.3 15.0 13.3 55.0 9.0 64.0 7.2 3-1 Revision 1 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I L1C1OA Core Operating Limits Report Table 3-2b Steady-State LHGR Limits for ATRIUM-10 Fuel Located in Cell Locations 10A Al 0-4039B-1 5GV75-1 00M (Bundle type 30)

(Reference 3 Section 7,2.3 and Reference 16 Section 2.0)

Average Planar LHGR Limit Exposure (kW/ft)

(GWdIMT) 0.0 13.0 15.0 13.0 55.0 8.7 64.0 6.9 Table 3-3 Steady-State LHGR Limits for ATRIUM-9B Fuel SPCA9-393B-16GZ-100M SPCA9-396B-12GZB-100M SPCA9-384B-1 1 GZ-80M SPCA9-396B-12GZC-100M (Bundle types 6, 7, 8 and 9)

(Reference 3 Section 7.2.3)

Average Planar LHGR Limit Exposure (kWLft)

(GWdIMT) ___

0.0 14.4 15.0 14.4 64.3 7.9 Table 3-4 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)

(GWd/MT) 0.00 14.40 12.33 14.40 27.85 12.31 49.76 10.80 61.18 6.00 3-2 Revision I LaSalle Unit I Cycle IOA

Technical Requirements Manual - Appendix I LIC10A Core Operating Limits Report Table 3-5 LHGR Limits for GE9B Fuel GE9B-P8CWB342-1 OGZ-80M-150 (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 3-3 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LIC1 OA Core Operating Limits Report S

Table 3-6 LHGRFACp For BOC to Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure For ATRIUM-10 Fuel .

Nominal Scram Speeds (NSS)

(Reference 3 Table 5.1)

OS Case 2 0.65 0.

OS Case 3 0.66 0.66 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.

3-4 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual -Appendix I L1C10A Core Operating Limits Report Table 3-7 LHGRFACp Exposure For BOC to Final Sequence Exchange at 12,000 MWd/MT Cycle For ATRIUM-10 Fuel Technical Specification Scram5.2)Speeds (TSSS)

(Reference 3 Table EOOS Combination 0 I 40 Power 25 Thermal Core 1 60(% of rated) 8O 1 100 LHGRFACp multiplier 0.74 0.74 1.00 1.00 Base Case Operation 0.64 0.64 a 0.f94 0.94 " 0.95 EOOS Case 1 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 0.77 I .U

"* 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.

Revision I 3-5 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C10 A Core Operating Limits Report Table 3-8 LHGRFACp Cycle Exposure to Coastdown (EOC)

For Final Sequence Exchange at 12,000 MWd/MT Fuel For ATRIUM-10 Nominal Scram Speeds (NSS)

(Reference 3 Table 5.3)

(% of rateld Core Thermal Power

=15 7 60 1o 80 I 0o EOOS Combination

-LHGRFACp rutiplier 0.75 0.75 1.00 1.00 Base Case Operation 0.66 0.94 0.94 0.95 EOOS Case 1 0.66 0.65 0.84 0.84 EOOS Case 2 0.65 0.65 0.77 0.77 0.83 EOOS Case 3 0.65 0.75 1.00 1.00 Single Loop Operation (SLO) 0.75 0.95 0.94 0.94 0.66 0.66 SLO with EOOS Case 1 0.84 0.84 0.65 0.65 SLO with EOOS Case 2 0.77 0.83 0.65 0.65 0.17 S31- with EOOS Case 3 levels.

between relevant power

"* Values are interpolated than at greater

"* For thermal limit monitoring power, the 100% core 100% core thermal multiplier should be thermal power LHGRFACp applied.

Allowable EOOS conditions are listed in Section 6.

,0-0 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LIC10A Core Operating Limits Report Table 3-9 LHGRFACp For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-10 Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.4) 0 25 40 60 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 0.64 0.64 0.77 0.77 0.17 SLO with EOOS Case 3

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.

3-7 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LICI0A Core Operating Limits Report Table 3-10 LHGRFACp For BOC to Final Sequence Exchange at 12,000 MWdIMT Cycle Exposure For ATRIUM-9B Fuel Nominal Scram Speeds (NSS)

(Reference 3 Table 5.1)

"* 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.

3-8 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C1 A Core Operating Limits Report Table 3-11 LHGRFACp MWd/MT Cycle Exposure For BOC to Final Sequence Exchange at 12,000 For ATRIUM-9B Fuel Technical Specification 3Scram Speeds (TSSS)

(Reference Table 5.2)

Core 'ThermlPwr( f rated_.).,

LHRApmultilier 0.76 1.00 *1.00 Base case operation 0.76 0.89 0.91 0.92 EOOS Case 1 0.69 0.69 0.6 07 EOOS Case 2 0.67 0.67 0* 0.77 01 0.77 0.80 EOOS Case 3 0.69 0.69 1.00 1.00 0.76 0.76 Single Loop Operation (SLO) '0.91 0.92 0.69 0.69 ** . 0.89 SLO with EOOS Case 1

,0.76 0.76 0.67 0.67 SLO with EOOIS Case 2 0.77 0.77 0.77 0.80 SL1O with EOOS Case 3 0.69 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.

6.

Allowable EOOS conditions are listed In Section Revision I 11-tj LaSalle Unit 1 Cycle I0A

Technical Requirements Manual - Appendix I LIC10A Core Operating Limits Report Table 3-12 LHGRFACp Cycle Exposure to Coastdown (EOC)

For Final Sequence Exchange at 12,000 MWd/MT Fuel For ATRIUM-9B Nominal Scram Speeds (NSS)

(Reference 3 Table 5.3)

Core Thermal Power M%of rted 0 25 LHGRFACp 60 multiplier80.0 10(

EOOS Combination 0.76 1.00 1.0 Base Case Operation 0.76 0.69 0.90 0.90 0.9 EOOS Case 1 0.69 0.67 0.79 0.7 EOOS Case 2 0.67 EOOS Case 3 0.69 0.6g 0.77 0.77 0.1 Single Loop Operation (SLO) 0.76 0.76 1.00 1.(

0.69 0.70 0.70 0.1 SLO with EOOS Case 1 0.69 SLO with EEOOS C~asee 22 0.67 0.67 0.79 0.10 SSLO %w*thEEOOSS Casee 33 0.69 0.69 0.77 0.77 0.1

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.

Revision I I II-a 4 r riw I nflA 3-10

Technical Requirements Manual - Appendix I L1 CI OA Core Operating Limits Report Table 3-13 LHGRFACp For Final Sequence Exchange at 12,000 MWd/MT Cycle Exposure to Coastdown (EOC)

For ATRIUM-9B Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.4)

I ~r ~mirwe 7 IIIU Ct*rD ] h*rmRI I*owBr I'/n Ol (id[lf*Ol EOOS Combination 0 1 25 1 40 1I 60 -l 1 80 1100 LHGRFACp multiplier Base Case Operation 0.76 0.76

- : 0.89 ' 0.91 0.92 EOOS Case 1 0.69 0.69 S0.76 0.76 EOOS Case 2 0.67 0.67 0.77, 0.77 0.77 0.80 EOOS Case 3 0.69 0.69 single Loop Operation (SLO) 0.76 0.76 S0.89 ,0.91 0.92 0.69 SLO with EOOS Case 1 0.69 0.67 0.67 07 0.76 SLO with EOOS Case 2 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 3-11 Revision 1 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI CI OA Core Operating Limits Report Table 3-14 LHGRFACp multipliers for GE9B Fuel except TCV Slow Closure (References 3. 5, 10 and 15)

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 3-15 LHGRFACp multipliers for GE9B Fuel for TCV Slow Closure (References 3, 5,14 and 15)

Core Thermal LHGRFACp Power (% of rated) Multiplier 0 0.2000 25 0.4000 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.

Ce, a-Revision I i cqnl1in IlInit I Cvcle 10OA 14

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 3-16 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 3-16 are applicable to all Operating Domains and EOOS conditions In Section 6.

Table 3-17 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 3-17 are applicable to all Operating Domains and EOOS conditions in Section 6.

3-13 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LIC10A 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 determined from the relationships shown below (Reference 6):

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

Operation Single Recirculation Loop 0.66 Wd + 48.7%

Operation The setpoint may be lower/higher and will still comply with the Rod Withdrawal Error (RWE) Analysis because RWE is analyzed unblocked. The allowable value is clamped, with a maximum value not to exceed the allowable value for a recirculation loop flow (Wd) of 100%.

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

4-1 Revision 0 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C1 A 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 I Cycle 10A 5-1 Revision 0

Technical Requirements Manual - Appendix I LC10OA Core Operating Limits Report 6*. Allowed Modes of Operation (B 3.2.2, B 3.2.3) as described The Allowed Modes of Operation with combinations of Equipment Out-of-Service are below:

KL(IUN-I 1 OPERATING REGION iuyvr-lr Limit Lr-&-V MELLLA ICFT Coastdown3 Thermal Equipment Out of Service ELLLA Set Number Options A Yes Yes Yes No 1. 17, 33' Base Case Operationf-NSS EOOS Case 1 - NSS 2.18,34 Yes Yes Yes No FHOOS or.TBVOOSe Except FHOOS 8

Except FHOOSe EOOS Case 2 - NSS No 3,19.35 Any combination of TCV slow Yes -Yes yes 5 Except FHOOSO closure, no RPT or FHOOS Except FHOOSs EOOS Case 3 - NSS 4,20,36 Yes Yes yes No TBVOOS with I TCV stuck closed Yes Nos N/A No 5,21.37 Single Loop Operation (SLO)- NSS SLO wmth E0OS case I- N55 No6 N/A No 6,22,38 FHOOS orTBVOOS2 Yes SLO with EOOS Case 2 - NSS "ExceptFHOOSe NoP N/A No 7.23. 39 Any combination of TCV slow Yes FHOOS 8 ExceptYst SLO closure, with EOOS Caseor3 FHOOS5 no RPT - NSS AN .44 Yes No N/A No 8. 24, 40 TEVOOS with I TCV stuck closed yes Yes No 9, 25, 41 Base Case Operation-rTSSS Yes EOOS Case I -TSSS Yes No 10,26.42 FHOOS 5 or TBVOOS 2 Yes Yes Except FHOOSs Except FHOOS8 EOCOS -Case2 -'I'SSS Yes Yes Yes No 11,27,43 Any combination of TCV slow RPT or FHOOS5 Except FHOOSs Except FHOOS _

EOOS Case 3no- "iSSS closure, yes Yes Yes No 12.28,44 TBVOOS with I TCV stuck

-dcosed Yes Nos N/A No 13,29.45 Single Loop Operation (SLO) - TSSS SLO with EOOS Case I - "ISSS N No N/A "No 14,30.46 FHOOS' or TBVOOSe Yes Except FHOOSs SLO with EOOS Case 2 - TSSS N0 / o15',31, 47 Any combination of TCV slow Yes No6 N/A No closure, no RPT or FHOOS5 Except FHOOS _

ISLO with E0OS Case 3 -TI'SSS No 16.32,48 Yes Noi N/A TBVOOS with I TCV stuck closed closed (except TBVOOS Each OOS Option may be combined with 1 SRVOOS, 1 TCV stuck considered OOS),

feedwater heaters conditions), a 20"F reduction in feedwater temperature (without of channels with 42% of the total number up to 2 TIP OOS (or the equivalent number of TIP channels, frequency of OOS with an LPRM calibration 100% available at startup), and up to 50% of the LPRMs 6-1 Revision I LaSalle Unit I Cycle IOA

Technical Requirements Manual - Appendix I LICI0A 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 I TBVOOS. If TBVOOS is being utilized while I 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 not be required based on current bumup projections. Feedwater heaters OOS (FHOOS) may be intentionally entered to maintain core thermal power provided the end of cycle exposure corresponding to a core average exposure of 31,495.1 MWd/MTU Is not exceeded.

4 Three sets of thermal limits are provided. The first set of thermal limits, from 1 through 16, are provided for use from the beginning of cycle until the second Cycle IOA sequence exchange (from Al to A2) at approximately 6000 MWd/MTU. The second set of thermal limits, from 17 through 32, are provided for use from the second Cycle 10A sequence exchange (from Al to A2) at approximately Cycle 10A 6000 MWd/MTU until approximately 12.000 MWd/MTU defined as where the final sequence exchange (from Al to A2) takes place. The final sequence exchange may not take place any later than 12,200 MWd/MTU. The third set of thermal limits, from 33 through 48, are applicable from approximately 12,000 MWd/MTU defined as where the final Cycle 10A sequence exchange (from Al to A2) takes place to the end of cycle. The licensing basis end of cycle burnup corresponds to a core average exposure of 31,495.1 MWd/MTU. Note that the nominal exposures at the beginning the and end of the sequence exchanges may be adjusted by +/-200 MWd/MTU without affecting magnitude of the control blade history penalties included In the thermal limit sets (Reference 16). The thermal limit sets are to be changed when the sequence exchange is performed and not at the specific cycle exposures.

5 Feedwater heaters OOS (FHOOS) supports a reduction of up to 1001F in' feedwater temperature.

FHOOS may be an intentionally entered mode of operation or an actual OOS condition. Feedwater the end heaters OOS (FHOOS) may be intentionally entered to maintain core thermal power provided exceeded.

of cycle exposure corresponding to a core average exposure of 31,495.1 MWd/MTU is not MELLLA. The power-flow boundary for r The SLO boundary was not moved up with the incorporation of SLO at power uprated conditions remains the ELLLA boundary for pre-uprate conditions.

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

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

100%

6-2 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report

7. Methodology (5.6.5)

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

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

2. Letter from Ashok C. Thadini (NRC) to R.A: Copeland (SPC), "Acceptance for Referencing of ULTRAFLOWTM 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 I 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 I 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 I and 2; Volume 1 Supplement 4, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," February 1987 and June 1988, respectively.

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

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

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

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

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

--... December 1991, March 1992, and May 1992, respectively.

13. EMF-85-74 (P)(A) Revision 0 and Supplement 1(P)(A) and Supplement 2(P)(A), "RODEX2A (BWR)

Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.

14, 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.

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

Advanced Nuclear Fuels Corporation, April 1990.

LaSalle Unit 1 Cycle 10A 7-1 Revision 1

Technical Requirements Manual - Appendix I LIC10A Core Operating Limits Report

17. ANF-1125 (P)(A) Supplement I Appendix E, "ANFB Critical Power Correlation Determination of ATRIUM TM-9B Additive Constant Uncertainties," September 1998.

18. EMF-1 125 (P)(A) Supplement I 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 I 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 I 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 I and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis," March 1983.

7-2 Revision I LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I Section 2 LaSalle Unit 1 Cycle 10A Reload Transient Analysis Results

Technical Requirements Manual - Appendix I Li C1 OA Reload Transient Analysis Results Table of Contents Attachment Preparer Document 1 Exelon/NFM Supplemental Licensing Report Information 2 Framatome-ANP Reload Analysis 3 Framatome-ANP Plant Transient Analysis 4 Framatome-ANP Transmittal of CBH Effects on Fresh Fuel for LaSalle Unit I Cycle 10 5 Framatome-ANP Licensing Letter Report for Impact of Revised Core Loading on LaSalle 1 Cycle 10 Licensing Revision 0 LaSalle Unit I Cycle 10A

Technical Requirements Manual - Appendix I Ll C1OA Reload Transient Analysis Results Attachment 1 LaSalle Unit 1 Cycle IOA Supplemental Licensing Report Information LaSalle Unit I Cycle I OA Revision 0

NUCLEAR FUEL MANAGEMENT TRANSMITTAL OF DESIGN INFORMATION 0 SAFETY RELATED Originating Organization NFM ID# NFM0200004 0l NON-SAFETY RELATED 0 Nuclear Fuel Management Sequence 0

[ REGULATORY RELATED El Other(specify) Page I of 7 Station- LaSalle Unit: I Cycle: 10 Generic: X To: Kirk W. Peterman (LaSalle)

Subject:

LaSalle Unit 1 Cycle 10 Suolemental Licensine Wyort Inrormationr FrnW/.Tnk-" L Preparer Preparer's Signature Date Anthony D.Giancatarino 66L1- 9-Z NFM Department Head */" Approveir~ignature Date Status of Information: Verified El Unverified El Engineering Judgement Action Tracking I 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, LHGRFACf, LHGRFACp, MAPFACr, and MAPFACp).

Purpose of Information: Provide documentation of reload limits (e.g. SDM, thermal limits, fuel exposure) for the LICIO reload design.

Sources of Information: Reference I. EMF-2563(P), Rev. I, 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-10 Fuel Assemblies.

Reference 3. "CoinEd GE9/GEIO LHGR Improvement Program", J l1-03692-LHGR, Rev. I, February 2000.

Reference 4. "ARTS Improvement Program Analysis for LaSalle County Stations Unit I and 2", NEDC-31531 P, December 1993 and Supplement 1, June 1998.

Reference 5. "Project Task Report, LaSalle County Station, Power Uprate Evaluation, Task 407: ECCS Performance" GE-NE-Al300384-39-01, Rev.,$, September 1999 ,'O ,d4r-r.

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 Distnbution- LaSalle Central File Cantera Records Management Supplemental Electronic Distribution: Norha Z. Plumey Jeff K. Nugent

NFM ID#: NFM0200004 Sequence 0 Page 2 of 7 Core Reactivity Characteristics 0

All values reported below are with zero xenon and are for 68 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 0.99325 1.17 BOC Shutdown Margin, % AK 1.17 Minimum Shutdown Margin, % AK 0.0 Cycle Exposure(s) of Minimum Shutdown Margin, MWD/MT 0.0 Reactivity Defect (R-value) Total, % AK

NFM ID#: NFM0200004 Sequence 0 Page 3 of 7 Maximum Exposure Limit Compliance (Cycle N-I)

Note that the projected exposures listed below are based on the nominal Cycle 9 MWDIMT, and the licensing basis Cycle 10 (Cycle N) cycle exposure of 18600 exposure, 19600 MWD/MT. The exposure limits are identified in References 1, 2 and 8.

ATRIUM-9B ATRIUM-9B ATRIUM-9B ATRIUM-9B ATRIUM-10 ATRIUM-I0 Exposure GE9B GE9B Exposure Exposure (100-mil) (100-miu) (80-mil) (80-mil) Projected Criteria Projected Exposure Limit Exposure Limit Projected Exposure Projected Exposure Exposure Limit Exposure Limit (GWD/MT) (GWD/MT)

(GWDIMT) (GWD/MT)

(GWDIMT) (GWD/MT) (GWD/MT) (GWD/MT)

Peak Fuel 48.0 23.2 54.0 Assembly N/A N/A 45.8 50.5 43.7 Peak Fuel N/A N/A N/A Batch 38.1 420 N/A N/A N/A Peak Fuel 26.4 58.7 NIA N/A 49.5 57.9 47.3 55.0 Rod Peak Fuel 70.4 57.2 65.0 63.1 69.4 60.5 66.0 34.8 Pellet

NFM ID#: NFM0200004 Sequence 0 Page 4 of 7 GE9B Thermal Limits The following tables contain the GE9B thermal limits (LHGR, LHGRFACt, LHGRFACp, MAPFACf, and MAPFACp). These limits were reviewed and approved previously for use in LaSalle Unit 1 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 (KWIft) 0.00 14.40 12.33 14.40 27.86 12.31 49.76 10.80 61.1B 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 1 /.o, ?

NFM ID#: NFM0200004 Sequence 0 Page 5 of 7 LHGRFAC2 Table 3. Power Dependent LHGR Multipliers for GE Fuel (formerly MAPFACp) (References 3 and 4)

Power (LHGRFACp) Value 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 TCV/TSV 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-100) I 00<P LHGRFACp = 1.0 P = % Rated Thermal Power q zp" NFM ID#: NFM0200004 Sequence 0 Page 6 of 7 LHGRFACf Figure 1. Flow-Dependent LHGR Multiplier for GE Fuel (formerly MAPFACF (Reference 4, 3, and 7) 1 0.9 L. , 0.8 ,t-I ~t t l ! , , , , '

t~,]"; ...' .. . '. ..'. . . .. . .. . . .l l J l For 105% Maximum Attainable Core Flow 2 0.7 LHGRFACF = The Minimum ol EITHER 1.0

.5 RN OR {0.6807 x (WTI100)+0.4672) "C,

0.6 4W44 44 WT =%Rated Core Flow C. 0.5 L6 04 0.3 I

J~l I ILl lI I I II IIIi _-- 1l 11 1 1 1 1 I I I I I I I I 1t l r I II l l i ] .1 l l ! l l l .. .l l l l q l .. l... . . . . . . . .. I . I I . . I .. i!rHAi+/-LLiHW 95 100 105 60 65 70 75 80 85 90 95 100 105 30 35 40 45 50 55 Core Flow (% Rated) ,7-0. ti NFM IDN. NFM0200004 Sequence 0 Page 7 of 7 TOPIMOP 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. S?,Z Technical Requirements Manual - Appendix I LI C10 Reload Transient Analysis Results Attachment 2 LaSalle Unit 1 Cycle 10 Reload Analysis LaSalle Unit I Cycle 10 Revision 0 Technical Requirements Manual - Appendix I LIC 10 Reload Transient Analysis Results Attachment 3 LaSalle Unit 1 Cycle 10 Plant Transient Analysis LaSalle Unit I Cycle 10 Revision 0 Technical Requirements Manual - Appendix I L1ClOA Reload Transient Analysis Results Attachment 2 LaSalle Unit 1 Cycle 10A Reload Analysis LaSalle Unit I Cycle IOA Revision 0 I fRA. M^-T-9M kEA-NP EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis January 2002 Framatome ANP. Inc. FrmtoeAPIc Framatome ANP, Inc. SSUEW If FRA-AP ON-i'..-" EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis Prepared: i*-Aj / Date J. M aun, Engineer BA Neutronics Prepared: mL 1 Q1 & ýj -, CCAI"" D. G. Carr, Team Leader Date BWR Safety ApaJyhis Concurred: Date ým, manager Licensing Concurred: D' E. Garber, Manager Date Commercial Operations Approved: Poo.k 0. drown/),r cC.e 0.i~ u.C.. brown, manager Date BWR Neutronics Approved: DcMojy4'A 6, 6V-1 r4.6. (AMtOft I*/ M. E. Garrett, Manager BWR Safety Analysis ra-6A Daj Approved: J. R. Tdhdy, Manager Date Product Mechanical Engineering Approved: Date R. E. Collingham, Manager BWR Reload Engineering & Methods Development sp Framatome ANP, Inc. 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 I Cycle 10 Reload Analysis Page i 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 Therm odynamic 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 EOC Licensing Exposure ................................................................... 5-1 5.2 Analysis for Reduced Flow Operation .............................................................. 5-2 5.3 Analysis for Reduced Power Operation ............................................................ 5-2 5.4 ASM E 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 Margins ................................................................... 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 MAPLHGR Analyses .......................................................................... 6-1 6.2 Control Rod Drop Accident .............................................................................. 6-2 7.0 Technical Specifications .............................................................................................. 7-1 7.1 Limiting 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 Limiting Conditions for Operation ..................................................................... 7-1 Framatome ANP, Inc. EMF-2690 Revision 0 "LaSalle Unit 1 Cycle 10 Reload Analysis Page idi 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 References ............................................................................................. 8-1 19.0 Additional References ................................................................................................. 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 er R atio ................................................................................................................. 3-3 4.1 Neutronic 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 Al0-4039B 15GV75 With Channel Bow ......................................................................................... 3-5 3.3 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors Al 0-4037B 16GV75 With 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 ATRIUM-1 0 Fuel - NSS Insertion Times ............................................................... 5-15 Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit I 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-A0 Fuel- NSS Insertion Times ............................................................... 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-10 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. EMF-2690 Revision 0 I II I mit '1 (vc.IA 10 RInd AnIvsi Paae v I nqnlla Hn;f 1 C 4cle 10 Reload Analv4;is Nomenclature AOO anticipated operational occurrence BOC beginning of cycle BPWS banked position withdrawal sequence CRDA control rod drop accident CRWE control rod withdrawal error EFPH effective full power hours EOC end of cycle EOD extended operating domain EOFP end of full power EOOS equipment out of service FFTR final feedwater temperature reduction FHOOS feedwater heater out of service FRA-ANP Framatome ANP, Inc. FWCF feedwater controller failure ICA interim corrective actions ICF increased core flow LFWH loss of feedwater heating LHGR linear heat generation rate LHGRFAC LHGR multiplier LOCA loss of coolant accident LPRM local power range monitor LRNB load rejection no bypass MAPFAC MAPLHGR multiplier MAPLHGR maximum average planar linear heat generation rate MCPR minimum critical power ratio MELLLA maximum extended load line limit analysis MSIV main steam isolation valve NRC Nuclear Regulatory Commission, U.S. NSS nominal scram speed PAPT protection against power transient PCT peak clad temperature RPT recirculation pump trip SLMCPR safety limit minimum critical power ratio SLO single-loop operation SRVOOS safety/relief valve out of service Frarnatome ANP, Inc. EMF-2690 Revision 0 Page vi LaSalle Unit 1 Cycle 10 Reload Analysis I 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 in used in this report which supersedes XN-NF-80-19(P)(A), Volume 4, Revision 1, is referenced 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 ATRIUMT-10° assemblies, 372 irradiated ATRIUM*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 I 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 I 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 Page 3-1 LaSalle Unit 1 Cycle 10 Reload Analysis I 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 I 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 Reference 9.2, Figure 3.2 ATRIUM-9B Reference 9.3, Figure 3.3 3.2.5 Bypass Flow Calculated Bypass Flow 13.7 Mlbm/hr Reference 9.4 at 100%P/100%F (includes water channel flow) 3.3 MCPR Fuel CladdingIntegrity Safety Limit (SLMCPR) Two-Loop Operation* 1.11 Reference 9.4 Single-Loop Operation 1.12 3.3.1 Coolant Thermodynamic Condition Thermal Power (at SLMCPR) 5446.6 MWt Feedwater Flow Rate (at SLMCPR) 23.6 Mlbm/hr Core Exit Pressure (at Rated Conditions) 1031.35 psia Feedwater Temperature 426.50 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 I Cycle 10 Reload Analysis Page 3-2 3.3.2 Design 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 Desiqn Basis Local Power Distribution Fuel Figures 3.2 and 3.3 show the ATRIUM-10 local power peaking factors used in the MCPR Cladding Integrity Safety Limit analysis. A10-4039B-15GV75 Figure 3.2 Al 0-4037B-1 6GV75 Figure 3.3 3.4 Licensing Powerand Exposure Shape the The licensing axial power profile used by FRA-ANP for the plant transient analyses bounds power projected end of full power (EOFP) axial power profile. The conservative licensing axial 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 at the normalized power generated in the core is greater than the licensing axial power profile given state conditions when the comparison is made over the bottom third of the core height. Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis Page 3-3 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, Mlb/hr 108.50 Control State ARO Licensing Axial Power Profile Node Power Top 25 0.199 24 0.387 23 0.883 22 1.132 21 1.351 20 1.507 19 1.597 18 1.630 17 1.613 16 1.632 15 1.560 14 1.478 13 1.388 12 1.295 11 1.198 10 1.094 9 0.982 8 0.864 7 0.745 6 0.634 5 0.536 4 0.461 3 0.405 2 0.331 Bottom 1 0.098 Licensing Axial Power Ratio (EOFP, ARO) Average Bottom 8 ft 112 ft = 1.1335 Framatome ANP, Inc. EMF-2690 Revision 0 I _Qýllc 1 I Ini t (vrCle 10 Reloaid Analysis Paqe 3-4 J= 200 175 150 U) -o 125 C m 4-0 100 L .(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 3.1 Radial Power Distribution for SLMCPR Determination Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit 1 Cycle 10 Reload Analysis Page 3-5 CONTROL ROD CORNER 0 N T 1.057 1.212 1.130 1.268 1.225 1.252 1.226 1.234 1.172 1.013 R 0 L .000 0.512 0.971 0.536 .000 1.156 1.212 .000 0.540 1.036 R 0 D 1.130 0.540 0.901 .0.904 0.499 0.892 0.948 0.920 0.538 1.214 C 0 R 1.268 1.036 0.904 0.924 1.058 1.151 1.121 1.003 0.999 1.134 N E R 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 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. EMF-2690 Revision 0 -LaSalle Unit I Cycle 10 Reload Analysis Page 3-6 CO NT ROL ROD CORNER 0 N T 1.061 1.225 1.141 1.282 1.240 1.271 1.246 1.255 1.191 1.021 R 0 L .000 1.176 1.225 .000 0.526 1.030 .000 0.504 0.983 0.528 R 0 D 0.868 0.844 0.487 0.891 0.955 0.928 0.530 1.238 1.141 0.526 C 0 R 1.282 1.030 0.844 0.482 1.003 1.143 1.127 1.014 1.013 1.155 N E R 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 Figure 3.3 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors AIO-4037B-16GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU) Framatome ANP, Inc. 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*-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-15GV75-1OOM (FT10) 4.03M)wt% Swt% A10-4037B-16GV75-1OOM (FT11) 4.031 Radial Enrichment Distribution Al OT-4307L-1 5G65 Reference 9.1, Figur ee D.3 D.2 AlOB-451OL-13G75 Reference 9.1, Figur e D.1 Al OB-4504L-1 5G75 Reference 9.1, Figur e D.6 Al OT-4306L-1 6G65 Reference 9.1, Figur e D.9 A1OT-4305L-16G75 Reference 9.1, Figur e D.8 Al OB-4507L-1 5G75 Reference 9.1, Figur D.5 e Al OB-4504L-1 6G75 Reference 9.1, Figur 1-2.2 Axial Enrichment Distribution Reference 9.1, Figures 2. 3-2.5 Burnable Absorber Distribution Reference 9.1, Figures 2. 3-2.4 Non-Fueled Rods Reference 9.1, Figures 2. le 4.1 Neutronic Design Parameters Tab Fuel Storage LaSalle New Fuel Storage Vault Referen' ce 9.5 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 ce 9.6 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 ce 9.7 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. Framatome ANP, Inc. EMF-2690 Revision 0 LaSalle Unit I 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 BOCI0, MWd/MT 12896.0 (from nominal EOC9) Core Exposure at EOCI0, 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-10. 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 IS.,, g,,;t 1 r',rI lfl . - Pdrir1 . AnIvck Pace 4-3 sat ,s..s.

- 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 poi'nt, 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. EMF-2690 Revision 0 'LaSalle Unit I Cycle 10 Reload Analysis Page 4-4 Table 4.1 Neutronic Design Values Number of Fuel Assemblies 764 Rated Thermal Power, MWt 3489 "RatedCore 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 B4C 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 B4C, %TD 70 "Thecontrol 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 2 4 6 10 9 10 8 10 9 9 10 8 10 9 10 6 5 3 10 610 1110 1110 1011 1011 10 610 8 5 4 4 10 9 109108106 610 810910 9 10 6 5 5 5 6 10 11 10 7 10 6 10 7 10 10 7 10 6 10 7 10 11 10 6 5 6 51 6 10 10 71 1060 610 7 10 7 10 6 16 6 085 4 8 4 81o11 10[8O10 9 10[ 109[ 10 8o 10611 10 8 4 9 610 9 10 6 10 8 10 6 10 7 11 6 1010 6 11 7 10 6 10 8 10 6 10 9 10 6 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 69FI-O 1 7106107f 7 l106107 110 117 10[WT107 10W6h107 1079 109 6 12 710 61016 1117 1116106 10[6 6106[10J611 7 11161061101110 7 13 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 14 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 15 7910610 6106106 10 10611061611610 610 610 610 101610197 16 7 9 10 1106106106106116610 6 6 106 10 6 1016 1019 7 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 77 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 08 10 *1 8 7 19 20 6 910 910 710 610 1 6 0 1 1 7 0 1710U610 7101910!9 6 21 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 22 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 23 5 8 10 11 10o[F151 86 10 9 10[6 110 9 [TT71 10 8 [56110 11 10 8 4 24 25 26 56 L~~~ oj o 1 6 10 110 7 10 6 10 6 1 4568610610710710661071071061068654 6 10[6 5 610 1110 710 610 710 10 710 610 710 11106 5

o, o_

7 10110 1=

6 1065 27 5 610 910[9 1018 10F661108 10910 9106 5 28 4 5 8106101 10 1111010111 01110906 10 85 4 29 5 6 10 9 10 8 10 9 9 10 8 10 9 10 6 4 30 5 6 6 7 7 6'-7 7 6 7 7 6 5 _5j0 Fuel Number Load Type Bundle Name of Bundles ID Range Cycle 4 GE9B-P8CWB343-12GZ-80M-150 13 YJD661-YJD764 8 5 GE9B-P8CWB342-1OGZ-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 28B257-281B292 9 9 SPCA9-396B-12GZC-1OOM 40 19C297-19C336 9 10 A10-4039B-15GV75 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 I mit I (vri 10 RPIoAd Analysis Page 5-1 I QIk I n(Zn1lin Hnit I C .L cle 10 Reload Analysis 5.0 Anticipated Operational Occurrences Applicable Disposition of Events Reference 9.8 Reference 9.4 5.1 Analysis of Plant Transientsat 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 Peak Peak "Peak Lower Neutron Heat Plenum ACPR Scram Flux Flux Pressure ATRIUM-10/

Transient Speed (% Rated) (% Rated) (psig) ATRIUM-9B LRNB TSSS 415 122 1203 0.35/0.33 TSSS 342 122 1166 0.33/0.30 FWCF" LRNB* NSS 306 120 1196 0.32/0.31 FWCF" NSS 266 117 1160 0.29/0.25 LFWH 0.21/0.21 CRWE 0.19/0.19 5.1.2 EOC Licensing Exposure Peak Peak Peak Lower Neutron Heat Plenum ACPR Scram Flux Flux Pressure ATRIUM-10 Speed (% Rated) (% Rated) (psig) /ATRIUM-9B Transient LRNB t TSSS 516 135 1216 0.39/0.33 FWCF* TSSS 395 128 1177 0.33'/0.30' LRNBt NSS 513 132 1207 0.36/0.32 FWCF" NSS 366 126 1168 0.29/0.27 LFWH 0.21/0.21 CRWE 0.19/0.19 Based on 100%P/105%F conditions.

t Based on 100%P/81%F conditions.

The analysis results are from an earlier exposure in this cycle.

Framatome ANP, Inc.

EMF-2690 Revision 0 Page 5-2 LaSalle Unit I Cycle 10 Reload Analysis Reference 9.4 5.2 Analysis for Reduced Flow Operation Limiting Transient: Slow Flow Excursion Figure 5.1 MCPRf Manual Flow Control ATRIUM-10 and ATRIUM-9B Fuel Figure 5.2 LHGRFACf 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)

Tables 5.1-5.4 MCPRp Base Case Operation Figures 5.3-5.10 Tables 5.1-5.4 LHGRFACp Base Case Operation*

Tables 5.1-5.4 MCPRp, EOOS Conditions Tables 5.1-5.4 LHGRFACp, EOOS Conditions*

MAPFACP - All Operating Conditions*

Reference 9.4 5.4 ASME OverpressurizationAnalysis Limiting Event MSIV Closure Valve Position Scram Worst Single Failure 1346 psig Maximum Vessel Pressure (Lower Plenum) 1321 psig Maximum Steam Dome Pressure 5.5 Control Rod Withdrawal Error and The control rod withdrawal error event is analyzed at rated conditions, assuming no xenon Al unblocked conditions. The analysis further assumes that the plant is operating in the A2 or rod sequence. The results bound low power operation.

The limiting ACPR for the CRWE analysis is 0.19.

to LHGRFACp values presented are applicable to FRA-ANP fuel. GE MAPFACp limits will continue be applied to GE9 fuel at off-rated power.

Framatome ANP, Inc.

EMF-2690 Revision 0

.'LaSalle Unit I 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 Page 5-4.

Cycle 10 power- and flow-dependent MCPR limits are presented for both ATRIUM-10 and ATRIUM-9B fuel. Since the GE9 fuel is in low power peripheral locations for LICI0, 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 I iII unit I CvcIA IC) RInrI Anlvi Paee 5-5

,I -n-qalle

- Unit 1 Cvcle 10 Reload Analvsis Table 5.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU *,'

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 25 2.36 0.66 2.20 0.69 EQOS 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 2* 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 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.

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 LaSalle Unit I Cycle 10 Reload Analysis Page 5-6 Table 5.1 Base Case and EOOS MCPRP Limits and LHGRFACP Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU*'

(Continued)

Power ATRIUM-10 Fuel ATRIUM-9B Fuel 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 0.75 1.96 0.77 Operation t 25 2.08 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 2.37 0.66 2.21 0.69 SLO with 25 EOOS Case 1 25 2.37 0.66 2.16 0.69 (FHOOS* 60 1.60 0.94 1.59 0.90 (HO OR TBVOOS) 8 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 2.37' 0.65 2.21 0.67 EOOS Case 2ý 25 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.

"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 1 Cycle 10 Reload Analysis Page 5-7 Table 5.2 Base Case and EOOS MCPRp Limits and LHGRFACP Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU *,

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 25 2.45 0.64 2.20 0.69 EOOS Case 1 25 2.45 0.64 2.19 0.69 (FHOOS 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 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 0.87 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 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.

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 IA *PoIn2d AnIvk Paae 5-8 C1 i .JI IlL I I (in-fc 1.,;, I' ILOJOII CC211U H" ;*I tý Yýý I In Dininorl Anni Z= icz Table 5.2 Base Case and EOOS MCPRP Limits and LHGRFACP Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU *

(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 0.76 25 2.16 0.74 1.97 Operationt 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 (FHOOSt OR TBVOOS) 60 8 1.63 0.94 1.63 0.89 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 25 2.46 0.64 2.21 0.67 EOOS 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 25 2.46 0.64 2.20 0.69 SLO with TBVOOS and 40 - 0.77 - 0.77 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 "Limitssupport 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 I stuck closed TCV.

Framatome ANP, Inc.

EMF-2690 Revision 0

-'LaSalle Unit 1 Cycle 10 Reload Analysis Page 5-9 Table 5.3 Base Case and EOOS MCPRp Limits and LHGRFACP Multipliers for NSS 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 0.75 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 2* 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 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 MAPFACI and MAPFACp multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.

Framatome ANP, Inc.

EMF-2690 Revision 0 IL.CA.JLII :Sdmit i C',rI lfl RcInrI Anlvi Paqe 5-10 I Q fin Hnif 1 r' r-ia in Polpad Analysis Table 5.3 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOCt (Continued)

Power ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.71 0.75 2.71 0.76 25 2.21 0.75 2.21 0.76 Single-Loop 0.76 25 2.08 0.75 1.96 Operationt 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 25 2.37 0.66 2.21 0.69 SLO with EOOS Case 1 25 2.37 0.66 2.16 0.69 (FHOOSt OR TBVOOS) 60 8 1.60 0.94 1.59 0.90 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 25 2.3i 0.65 2.21 0.67 EOOS Case 2t 2 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 80 1.75 0.84 1.68 0.79 RPT OR FHOOS) 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 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.

fuel assemblies will SGE9use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

or without I stuck closedSWith TCV.

Framatome ANP, Inc.

EMF-2690 Revision 0

.1 QlIc I mit I flvH In RA!nd AnIviL Paae 5-11 I

ý1nCZn11,m Hnif 1 C 2= le 10 Reload Anal sis 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 25 2.45 0.64 2.20 0.69 EQOS Case 1 25 2.45 0.64 2.19 0.69 (FHOOS' 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 0.82 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 40 - 0.77 -- 0.77 closed TCV 60 1.62 0.77 1.62 0.77 80 - 0.77 - 0.77 1 100 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.

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.

Framatorne ANP, Inc.

EMF-2690 Revision 0 I Inh 1 CnIi IA RcIncI AnIvi Paqe 5-12 I,lIc I 0C 0 11

ý'

H " if i r, I im in Moir-ri Anal z sis Table 5.4 Base Case and EOOS MCPRp Limits and LHGRFACP Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOCt (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 1.97 0.76 Operationt 25 2.16 0.74 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 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 25 2.46 0.64 2.21 0.67 EOOS 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, 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 40 - 0.77 0.77 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 "Limitssupport 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.

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 0.

rE 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 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

-L

-J 11C Flow (%rated)

Flow (% rated) LHGRFAC; 0 0.72 30 0.72 68 1.00 105 1.00 Figure 5.2 Flow Dependent LHGR Multipliers for ATRIUM-10 and ATRIUM-9B Fuel GE9 MAPFACI and MAPFACp multipliers used in Cycle 9 remain applicable.

Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis Page 5-15 2.85 2.75 265 255 245 235 225 215

" 205 1.

1.95 10 20 30 40 50 60 70 80 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 I Cycle 10 Reload Analysis Page 5-16 285 275 265 255 2.45 235 2.25 2.15 S2.05 a.

S1.95 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 1.42 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 5-17 285 2.75 2.65 2.55 2.45 2.35 2.25 2.15 S2.05 7 195 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 I Cycle 10 Reload Analysis Page 5-18 285 2.75 265 2.55 245 2.35 2.25 2.15

. 205

195 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 I 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 I Cycle 10 Reload Analysis Page 5-20 285 2.75 2.65 2.55 245 2.35 225 2.15

a. 205 it

1.95 1 85 1.75 1.65 1.55 1A5 1.35 1.25 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 I Cycle 10 Reload Analysis Page 5-21

-5 or 275 2 65 2.55 245 2.35 2.25 2.15 2.05 CL, 1.95 1.85 1.75 1 65 1.55 1 45 1.35 1.25 1..154 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 0.

205 195 1 85 1 75 1 65 1.55 1A5 1.35 1.25 S15 115 60 70 80 90 100 110 0 10 20 30 40 50 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 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2690 Revision 0

.I ~Qniin Hifd I rs- imn ReloPa~d Anal sis Paqe 6-1 6.0 Postulated Accidents 6.1 Loss-of-CoolantAccident 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 ft2 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 ft2 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.)

Maximum PCT Peak Local Metal-Water Reaction (OF) (%)

ATRIUM-9B Fuel 1827 0.79 ATRIUM-10 Fuel 1807 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.

Framatome 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 -10 E-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

.AnIiik PaQe 6-3

PoIur4 LaSal I I I+

Ld.dII Ia H";4 Lu UL 1 r' J.!, ý InIA*

I I ('u-Ie f Dolnorl Anal eic 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 I II I kit I Cvc.I 10 ReIo2d Analysis Paqe 6-4 I nqnlle Unit 1 CvcIe 10 Reload Anaivsis 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.

Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit I Cycle 10 Reload Analysis Page 7-1 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 ATRIUM-9B Fuel MAPLHGR Limits 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 6 4 .3 t 9.07 64.0 7.6 GE9 Fuel MAPLHGR Limits

< To be furnished by Exelon. >

Single Loop Operation MAPLHGR Multiplier References 9.11 and 9.12 for ATRIUM-10 and ATRIUM-9B Fuel is 0.90 "Includesthe 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 Page 7-2 LaSalle Unit I Cycle 10 Reload Analysis 7.2.2 Minimum Critical Power Ratio Flow Dependent MCPR Limits:

Figure 5.1 Manual Flow Control Power Dependent MCPR Limits:

Figures 5.3, 5.4, 5.7 and 5.8 Base Case Operation - NSS Insertion Times Figures 5.5, 5.6, 5.9 and 5.10 Base Case Operation - TSSS Insertion Times Tables 5.1-5.4 EOD and EOOS Operation References 9.2 and 9.14 7.2.3 Linear Heat Generation Rate ATRIUM-9B Fuel ATRIUM-10 Fuel Steady-State LHGR Limits Steadv-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 I Cycle 10 Reload Analysis Page 7-3 ATRIUM-10 Fuel ATRIUM-9B Fuel PAPT LHGR Limits 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:

LHGRFACI Figure 5.2 LHGRFACp Tables 5.1-5.4 MAPFAC Multipliers for Off-Rated Conditions - GE9 Fuel:

MAPFACf "<To be furnished by Exelon. >

MAPFACP "<To be furnished by Exelon. >

Framatome ANP, Inc.

EMF-2690 Revision 0 LaSalle Unit I 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 I and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Programfor Boiling Water Reactor TransientAnalyses, Advanced Nuclear Fuels Corporation, August 1990.

8.2 ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical PowerMethodology 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 CriticalPower Correlation,Advanced Nuclear Fuels Corporation, April 1990.

8.4 EMF-1 125(P)(A) Supplement 1 Appendix C, ANFB CriticalPower CorrelationApplication for Co-Resident Fuel, Siemens Power Corporation, August 1997.

8.5 ANF-1 125(P)(A) Supplement 1 Appendix E, ANFB CriticalPower Correlation Determination of ATRIUMTM-9B Additive Constant Uncertainties,Siemens Power Corporation, September 1998.

8.6 EMF-2209(P)(A) Revision 1, SPCB CriticalPower 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-3GIMICROBURN-B CalculationMethodology, Advanced Nuclear Fuels Corporation, November 1990.

8.8 EMF-CC-074(P) Volume 4 Revision 0, BWR StabilityAnalysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

Framatome ANP, Inc.

EMF-2690 Revision 0 Page 9-1 LaSalle Unit I Cycle 10 Reload Analysis 9.0 Additional References 9.1 EMF-2624(P) Revision 1, Neutronic Design LaSalle Unit I Cycle 10 ATRIUMm-10 Fuel, Framatome ANP, Inc., September 2001.

9.2 EMF-2589(P) Revision 0, Mechanicaland Thermal-HydraulicDesign Report for LaSalle Units I and 2 ATRIUMm-10 Fuel Assemblies, Framatome ANP, Inc., July 2001.

9.3 EMF-2249(P) Revision 1, Fuel Design Report for LaSalle Unit I Cycle 9 ATRIUMM9B Fuel Assemblies, Siemens Power Corporation, September 1999.

9.4 EMF-2689 Revision 0, LaSalle Unit I Cycle 10 Plant TransientAnalysis, Framatome ANP, Inc., January 2002.

2 9.5 EMF-2554(P), CriticalitySafety Analysis for ATRIUMT-10 Fuel, LaSalle Units 1 and New Fuel Storage Vault, Framatome ANP, Inc., June 2001.

9.6 EMF-2556(P) Revision 0, CriticalitySafety Analysis for A TRIUMTm-10 Fuel, LaSalle Unit I Spent Fuel Storage Pool (BORAL Rack), Framatome ANP, Inc., September 2001.

9.7 EMF-2650(P) Revision 0, CriticalitySafety Analysis for ATRIUMTM-10 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-1O -10 Fuel at LaSalle County Station,"

TM DEG:01:179, October 30, 2001.

9.9 EMF-2174(P), LOCA Break Spectrum Analysis for LaSalle Units 1 and 2, Siemens Power Corporation, March 1999.

for 9.10 EMF-2639(P) Revision 0, LaSalle Units 1 and 2 LOCA Break Spectrum Analysis ATRIUMTMLI0 Fuel, Framatome ANP, Inc., November 2001.

Fuel, 9.11 EMF-2175(P), LaSalle LOCA-ECCS Analysis MAPLHGR Limits for ATRIUMTM-9B Siemens Power Corporation, March 1999.

Limit 9.12 EMF-2641 (P) Revision 0, LaSalle Units I and 2 LOCA-ECCS Analysis MAPLHGR forATRIUMTM -1O 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 ATRIUMT1I-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, Framatome ANP, Inc., August 2001.

Framatome ANP, Inc.

EMF-2690 Revision 0 Page 9-2 LaSalle Unit I Cycle 10 Reload Analysis 9.15 Correspondence, S. A. Richards (NRC) to J. F. Mallay (SPC), "Supplement to Safety 4

Evaluation and Technical Evaluation Report Clarifications for EMF-CC-074(P) Volume 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 1 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.

ML023380689

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