ML031950077

Cycle 10A Core Operating Limits Report (COLR)

ML031950077
Person / Time
Site:	LaSalle
Issue date:	07/03/2003
From:	Barnes G Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
-RFPFR
Download: ML031950077 (53)

Text

A ExekEnSM Exelon Generation Company, LLC www.exeloncorp.com Nuclear LaSalle County Station 2601 North 21"'Road MaTseilles, IL 61341-9757 July 3, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 1 Facility Operating License No. NPF-1 I NRC Docket No. 50-373

Subject:

Unit 1 Cycle 1OA Core Operating Limits Report (COLR)

Exelon Generation Company (EGC), LLC, in accordance with LaSalle County Station Technical Specifications (TS) Section 5.6.5, "Core Operating Limits Report,"

is submitting a revision to the Core Operating Limits Report (COLR). The revision is due to the implementation of new minimum critical power ratio (MCPR) operating limits and power-dependent limiting heat generation rate (LHGR) limit penalties for control blade history effects on the fresh fuel for LaSalle County Station Unit 1 Cycle 1OA operations. The penalties are applied to specific core locations to ensure that control blade history effects on fresh fuel assemblies are properly accounted for in the calculation of maximum nodal LHGR and MCPR.

Additionally, associated administrative changes have also been incorporated.

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

Respectfully, George P. Barnes Site Vice President LaSalle County Station Attachment cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - LaSalle County Station

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

Technical Requirements Manual -Appendix I LiCI oA Core Operating Limits Report Issuance of Changes Summary Affected Affected Pages Summary of Changes Revision Date Sections _ _ _ _ _ _ _

All Al Original Issue LaSa-le Unit I Cycle 1IA 0 52002 References iv Updated Reference 16 to the control blade history letter for LlCIOA.

2.2.1 2-1 through 2-14 Updated MCPR(p) limits for fresh ATRIUM-10 fuel.

Renumbered tables.

3.2 3-1, 3-2, and 3-3 Updated steady-state LHGR limits for fresh ATRIUM-lO 1 912002 fuel.

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

6 6-2 Updated footnote 4 to be consistent with the updated application of control blade history penalties.

References v Add Reference 18 to Include the revised LaSalle Unit I Cycle ICA CBH Study 2.2.1. 2-1 through 2-24 Updated MCPR(p) limits for fresh ATRIUM-10 fuel with calculated CBH penalties. Renumbered tables.

3.2 3-1 through 3-14 Updated steady-state LHGR limits forb frsh ATRIUm-i fuel with appropriate CBH penalty. 2 5/2003 8 6-Oand 8-2 Updated the allowed mode of operations table to Identify the appropriate POWERPLEX decks to be used and updated footnote 4 to be consistent with the application of the control blade history penalties.

Removed ELLLA from the table and added standard power-flow map. Also added a key for the table and note 9 to define standard power-flow map.

LaSalle Unit I Cycle I OA iI Revision 2

Technical Requirements Manual - Appendix I Li C1 OA Core Operating Limits Report Table of Contents References ............................................................ IV

1. Average Planar Unear Heat Generation Rate (32.1) . .1-1 1.1 Technical Specificaton Reference. 1-1 1.2 Descrption. 1-1

2. Minimum Critical Power Ratio (322)............................. ,., 241 2.1 Technical Specificaton Reference ., 2-1 2.2 Descripton . ,, 2-1

3. Unear Heat Generation Rate (32.3) .3-1 3.1 Technical Specificalion Reference. 31 3.2 Description ........ .......... -313. -.----- *-

4. Control Rod Withdrawal Block Instrumentat.n .............. 4.1 4.1 Technical Specification Reference ... .........................- 4-1 4.2 Description ............;.;.:.;.. x .;.'..-.'. . ' .............. 4-1

6. Traversing In-Core Probe System (32.1, 3.2.2, 3.2.3);, 6.1.

5.1 Technical Specifcaton'Reference. ............................. 6-i1 5.2 Descrption ............ , -1 6.3 Bases .. 6 1......

6. Allowed Modes of Operation (B 322, ..32. ..............................

23................... 6-1

7. M ethodology ~ o , ~......................

~~~~~ . .... .............................

............................. 7 -.

7. Methodology (5.z6.5)';.......

- .7-I LaSalle Unit I Cycle 1QA lII Revision 2

Technical Requirements Manual - Appendix I LiC1OA Core Operating Limits Report References

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

2. Letter from 0. M. Crutchfleld 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, 'LaSafte Unit I Cycle 10 Reload Analysis,' Framatome ANP, Inc., Januaiy 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. J1 1-03692-LHGR Revision 1, "ComEd GE91GEI0 LHGR Improvement Program,' [NDIT NFMOOOOOB7 Sequence 01, Febivary 2000.

8. Letter from A. Giancatarilno to J. Nugent, *LaSalle Unit I and Unit 2 Rod Block Monitor COLR Setpoint Change,0 NFM:MW:01-0108, April 3,2001.

7. Letter from D. Garber to R Chin. "PO'MRPLEX-11 CMSS Startup Testing", DEG:00:254, December 5. 2000.

. Letter from D. Garber to R Chin "POWERPLEX-Il CMSS Startup Testi, DEG:00:258, December 8, 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 1Cycle 10 Principal Transient Analysis Parameters,' April 2001.

12. 24A6180AA Revision 0, "Lattice-Dependent MAPLHGR Report for LaSalle County Station Unit I Reload 7 Cycle 8." December 1995.

13. NFM Calculation No. BSA-L-99-07, *LaSalle GE9 MAPFACf Thermal Limit Multiplier for 105%

Maximum Core Flow." October 1999.

14. GE-NE-187-13-0792 RevisIon 2, "Evaluation of a Postuiated Slow Turbine Control Valve Closure Event For LaSalle County Station Units I and 2," NDIT NFM-98-00148 Sequence 00, July 1998.

15. Letter from R Jacobs to Ri Tsal, NFM:BSA.99-087, "Review of LI C9 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 I AO.DEG:02:110, July 17, 2002.

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

18& Letter from A. W. Will to F.W.Trikur, "LaSalle Unit I Cycle I OA CBH Study - Revision 1",

AWW:03:048, April 18,2003.

LaSalle Unit I Cycle 1OA IV Revision 2

Technical Requirements Manual -,Appendix I LICIOA Core Operating Limits Report

1. Average Planar Unear Heat Generation Rate (3.1) 1.1 Technical Specification

Reference:

Section 3.2.1.

1.2

Description:

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

For Single Reactor Recirculation Loop Operation (SLO), the MAPLHGR limits given In Tables 1-1 through 1-4 must be multiplied by a SLO MAPLHGR multiplier. The SLO MAPLHGR multiplier for ATRIUM-10 and ATRIUMOB fuel Is 0.90 (Reference 3 Page 7-1). The SLO MAPLHGR multipliers for GE9B fuel are shown hI Table 1-5 (MAPFACp) and Table 1-6 (MAPFACF). The SLO MAPLHGR limit for the GE9B fuel Is the product of the MAPLHGR limit from Table 1-3 or-1,4 and the minimum of either the SLO MAPFACp or SLO MAPFACF as found InTables 16 and 1-6, respectively.

Table 1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for ATRiUMriO Fuel AlO-4039B-15GV7W5100M AI0-4037B-16GV7W5G0M (Bundle type: s 10, 11, 20, 21, 22, 23, 24, 26, 27,28, 29, 30, 31, 32, 41t, 43, 45 and 49)

• ' . 3Sec9on 72.1)i k .(Reforence Planar Average Exposure MAPLHGR

... >.. (GWd/MT) , - ' ' (kW/ft) 0.0 - 12.6 15.0 12.6 a55.0 9.1 64.0 7.6 Table 1-2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for ATRIUM-9B Fuel SPCA9-393B-1 6GZ-1 OOM SPCA9-396B-12GZB-100M SPCA9-384B-1 1GZ-80M SPCA9-396B-1 2GZG-100M (Bundle types 6, 7,8 and 9)

(Reference 3 Section 7.2.1)

Planar Average Exposure MAPLHGR (GWdIMT) l (kWMt) 0.0 13.5 20.0 13.5 64.3 - 9.07 LaSalle Unit I Cycle 10A 1 1 Revislon 2

Technical Requirements Manual - Appendix I LICIOA CoremOperating Limits Report Table 1-3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE9B Fuel GE9B-P8CWB342-1 OGZ-80M-1 50 (Bundle 3867, bundle type 5)

(Refences nd 12)

Planar Average Lattice Specific MAPLHGR limit (kWlt Exposure (GWdIS)_

0 12.68 12.04 12.25 11.72 1 12.09 .12.68 0.200 12.59 12.08 12.28 11.77 12.12 .-12.59 1.000 12.40 12.18 12.35 11.87 12.22 112.40 2.000 12.34 12.28 12.45 12.00 12.37 12.34 3.000 12.34 12.42 12.55 12.13 12.53 12.34 4.000 12.37 12.57 12.65 12.27 12.70 12.37 5.000 12.40 12.73 12.78 12.41 12.88 12.40 B.000 12.43 12.89. 12.87 12.56 13.07 12.43 7.000 12.48 .13.0B 12.98 12.72 13.27 12.40 8.000 12.48 .13.24 - 13.10 12.88 13.47 12.48 9.000 12.50 13.42 13.21 13.05 1 3.65 12.50 10.000 12.51 13.81 13.31 13.21 13.78 12.51 12.500 12.35 13.79 13.35 .13.31 13.82 12.35 15.000 11.98 13.50 13.08 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 .11.87 11.83 11.95 10.42 27.2158 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 B.000 8 8.000 8.000 8.000 8.000 Lattice No. 732 2087 2088 2089 2090 2091 LaSaile Unit I Cycle I OA 1-2 Revision 2

Technical Requirements Manual - Appendix I L1C1 OA Core Operating Limits Report Table 1-4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE9B Fuel GE9B-P8CWB343-1 2GZ-80M-1 50 (Bundle 3866, bundle type 4)

(Refeeces 6 and 12)

Planar Exposure Lattice Specific MAPLHGR limit (kWlft)

(GWdIST)_

0 12.66 1 11.69 1 11.37 1 10.92 12.66 0.200- 12.69 11.71 11.43- 10.99 12.69 1.000 12A.0 11.78 11.65 11.13 12.40 2.000 12.34 11.95 11.72 11.33 12.34 3.000 12.34 12.18 11.91 11.54 12.34 4.000 12.37 12.40 12.11 1.76 12.37 6.000 12.40 12.67 12.32 12.00 12.40 6.000 12A3 12.90 -123 12.24 12A3 7.000 12.46 13.05 12.76 12A9 12.46 8.000 12.48 13.21 12.98 12.75 12.48 9.000 12.60 13.37 13.13 I 13.01 12.60 10.000 12.61 13.64 13.30 13.22 12.61 12.600 12.35 13.76 13.60 13.67 12.35 15.000 11.98 13.48 1323' 13.21 11.98 20.000 1120 .12.71 12A0 12.37 11.20 25.000 10.42 11.92 11.60 11.67 10.42 27.2156 12.314 12.314 12.314,. 12.314 12.314 48.0808 10.800 - 10.800 10.800 10.800 10.800 58.9671 6.0000 6.000 6.000 6.000 Lattice No. 732 2083 2084 ' 2085 2086 Table 1-5 SLO MAPFACp multiplier for GE9B Fuel (iRefrenMs 6 nd 10)

Core Thermal MAPFACp Power (% of rated) multiplier 0 .776 OA_____

_______25 0.6082 _

100Q 1.0000 e 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.

Revision 2 LaSalle Unit I Cycle 10A 1-3

Technical Requirements Manual - Appendix I LICIOA Core Operating Limits Report Table 1-6 SLO MAPFACF multipfler for GE9B Fuel (Reference, Sand 13)

Core Flow MAPFAC,

(% of rated) multipiler 0 0.4872 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 MAPFACp multiplier for 105% rated core flow.

LaSalle Unit I Cycle IOA 14 Revision 2

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

2. Minimum Critical Power Ratio (3+/-2) 2.1 Technical Soecification

Reference:

Section 3.2.2.

2.2

Description:

MCPR limits from BOC to Coastdown are applicable up to a core average exposure of 31,495.1 MWdWWTU (which Is the licensing basis exposure used by FANP). (Reference 3). Umits beyond the EOC exposure are not provided.

2.2.1 Manual Flow Control MCPR Limits The Operating Umit 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-Deoendent MCPR The power-dependent MCPR value, MCPRp, Is determined from Tables 2-1 through 2-20, and Is dependent on exposure (See Section

6. Note 4 for implementation details), fuel type and scram speed, In addition to power level. Tables 2-1, 2-1a, 2-2, 2-2a, and 2-6 through 2-18 are applicable to ATRIUM-10 fuel and Tables 2-3, 2-4, 2-1I, and 2-20 are applicable to both ATRIUM-9B and GEB fuel types.

2.2.1.2 Flow-Deoendent MCPR The flow dependent MCPR value, MCPRF, Is determined from Table 2-21 for all fuel types InCycle IDA.

2.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control Is not supported for LICIOA.

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

Notch Position Time 45 0.380 39 0.680 25 1.680 05 _ 2.680 LaSalle Unit I Cyde 1OA 2-1 Revision 2

Technical Requirements Manual - Appendix I Li C1 OA Core Operating Limits Report Table 2-1 MCPRp For BOC to Second Cycle 1OA Sequence Exchange - Applicable to all ATRIUM-1 Fuel Nominal Scram Speeds (NSS)

(ReerenceTable 561 and Raherenc 1 Tabe 51)

___Core Thermal Power (% of rated)

EOOS Combinktion 0 1 2 1 25(2) TI8 60 I 80.1) 1100 MCPR, Baa. Case Opead 2.70 2.20 2.07 1.52,,

EOOS C ,se , 28, 2.8 2.38 1.59, EOOS Cae 2 2.8 2.38 2.30 131 ~~1.74 l 1S54 EOOS Ca"3 2_G 2.38 2.38 1.9 Si& Loop Opera"on (SLO) 2.71 2.21 2.08 153 _ 1~~~~~A4 SLOwth EOOS Caca" 2I87 2.37 2.37 150m 1~~~~~~A8 SLOwiEOOS Case 2.87 2.37 2.37 l 182 ~~1.7e I 155, SLO wMd EOOS Case 3 287 2.37 2.37 1._0 1_~~~~ ' I14

. Values are Interpolated between relevant power levels.

For Utmal limit monitrWng at greater than 100% core themal power, the 100% core hermal 0 power MCPRp should be applied.

Allowable EOOS conditions are lsted InSection 6.

LaSalle "-it I Cycle I1A 2-;t Revi&- 2

Technical Requirements Manual - Appendix I LI C10 A Core Operating Limits Report Table 2-1a MCPRp For Second Cycle 1OA Sequence Exchange to the Sequence Exchange at 8,800 MWd/MT Cycle Exposure -

Applicable to all ATRIUM-10 Fuel Except Those Located In Celh 7B, 7C, 8A, 9A, 10B, and 1OC Nominal Scram Speeds (NSS)

(Rrnce3Tebte&1 aid ence 18 Tae6.1)

. -. . . - ' G~~~~~rC Themna Poer (%of rated E00 Comblnation - 25 2l51) l 0 l 80.1) 100 I

. . ' ' -- ' - ~~~~~MCPs Base Case Opem~on 2.7 . 2.20 2.07 152_

EOOSa Cse12 2i" :_1 E0OS Case 2 72J 1.81 1.74 Ef00S Came 3 A 22" 7 sIrte Loop opetafln(sL6) 2.71 2.21 2.0 OM 53 SLOw EOOS Case 27 .8 27 2. 1

$LOwh EOOS Case 3 27 2.37 2.37 1.8

• Vahies are interpolated between relevant powr levels.

• For thermal flmtt monitoring at greeter than 100% core thermal powet,Hle 100% core thermal power MCPRf shomdd be appled.

• Allowabe EQOS conditbons ar lIted InSection B.

LaSalle Unit I Cycle 10A 2-3 Revision 2

Technical Requirements Manual - Appendix I L1 C1 OA Core Operating Limits Report Table 2-2 MCPRp For BOC to Second Cycle IOA Sequence Exchange - Applicable to all ATRIUM-10 Fuel technIcal Specification Scram Speeds (TSSS)

(Rame 3 Table 52 and Reece 16 Tabl 5.1)

Y Core Thannal rated)

EOOS Comblinalon 0 - 25 l 24251) l 60 Il 80 s80.1) l 100' MCPR.

I .~~~~

70 2.20 I.

2.15 1.56 EOOS Ca"e 1 2.96 246 24. 1.6 _18 17 IAQ EOOS Ca 2 296 2 46 245

- ~,..~I I EOOS Case 3 2.95 2.45 245 1.62 Sing Loop Operaon (SLO) 1_ 2.71 221 _J 2.16 1 .58 SLO wih EOOS Case 1 2.98 2.46 2A4 1.63 SLO wi E00S Ca 2 , 2M

' j 2.48 _Iz 1.83 1.76 I.60

_ 162~~~~~~

SLO with EO58Case 3 2.D6 248 2A8 i-I-I . 7: . . 7. . _

... .. .. .. : .7 S Values are Interpolated between relevant power levels. -

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

0 Alowabe EOOS conditions are Usted In Section 6.

LaSalle "-it I Cyclb IA 2-4 Revision 2

Technical RequirementsiManual - Appendix I LIC1OA Core Operating Limits Report Table 2-2a MCPRP For Second Cycle 10A Sequence Exchange to the Sequence Exchange at 8,800 MWdIMT Cycle Exposure -

Applicable to all ATRIUM-10 Fuel Except Those Located In Cels 7B, 7C, 8A, OA, 10B, and 10C Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 2 a Remeren 10 Tab 5.1)

• Vatues ae interpoled between relevant power levels. -

• For fermalimit montorin at greater ftn 100% core thermal power, the10%corethermal power MCPRp should be applied.

• AlNwble EOOS conditions ar listed InSection '.

LaSalle Unit I Cycle 10A 2-5 Revision 2

Technical Requirements Manual - Appendix I L1C1 OA Core Operating Limits Report Table 2-3 MCPR, For BOC to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) -

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

(Refrec 3 Tabe 5.1)

Core Thermal Power (% of rated)

EOOS CombiaUon 0 2- 25(25 1) 60 80 80(80.1) 100 UMCPR I BaseCasOpenfwi T 2.70 '2.20 1.95 1.50 I.Q I EOO$ Cne . 70 2.20 2.15 1.58 11." I IM 1.67 Im EOOS Case 2 2.70 2.20 2.15 - I EOOS Case 3 2.70 2.20 2.15 1.58 Single Loop Operaton (SLO) 2.71 2.21 1.m - 1.51 I1.0 SLO with EOOS Case I 2.71 221 2.18 . IAO SLO wiWE FOOS Case 2 2.711 2.21 2.16 , 1.87 11.6 im I .... ,. I SLO with EOOS Case 3 2.71 2.21 2.16 U

S Values are Interpolated between relevant power levels.

S For thml limit monitoring at greater than 100% core themal power, the 100% core therma Power MCPRp should be applied.

S Allowable EOOS conditions are listed InSection 6.

LaSalle V"~1Cycle1I0A2- 2-6 Revislon 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2-4 MCPRp For BOC to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) -

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

(Referee 3 Table 52)

Core Thermal Power (% of rated)

EOOS Ceb attO h l 2S5 25(25.1). 8-(80.1) 60 l 100

~' .25. .;..,...

Ba" Cese Operel.on  ; zm . 0 1." _

EOOS Case IIZ70 2.20' 2.10 - 168 EOOSC 21 2 2.70.. 220 1. 1^

EOOS Case 3 .. 2.70 220 2.10 1.02O SlngleLoopOper"on(SLO). . . 2.71 221 - 1.97 1.5A SLOwihEOOS Case" 2.71 221 220 1..4 SLOwIh EOOS Case 2 2.71 2.21 -2.20 1.1 S* wIt OOS Ca" 3 2.71 221 220 1.63

• Values aem1 interplolae between relevant power levels

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

• Aflowable EOOS conditions are listed InSection 6.

LaSafle Unit I Cycle IOA 2-7 Revision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2-5 MCPRP For Second Cycle I OA Sequence Exchange to Sequence Exchange at 8,800 MWd/MT Cycle Exposure -

For ATRIUM-10 Fuel Located In OA, 10B, and 10C Cells Nominal Scram Speeds (NSS)

(Rwen 3 Table .1 and Refee 1 Tabl 5.1)

Core Thermal Power % of rated)

EOOS Combkluoe 0 25 25(I) Go60 so80 l8(80.1) F 100 ase C OOpeuo 2.74 2.24 2.11 EOOS Case 1 2.00 2.40 2.40 6151 EOOS Ca"e 2.90 4 2. I ; 1.68 EOOS Case S40 3 2D0 _ 2.40 1S1 Sgle Loop Operon (SLO) 275 2.25 2.12 1.5_ 1A SLO WWI EOOS Case 1 2.01 2A1 2.41 1.64 2 SLOwMl EOOS-Cae2 2.91 2.41 2.41 _M SLOwMMEOOS Case3 2.91 2.41 241 1152

• Values are interpolated between relevant power levels.

• For tUerma lWit monitoaing at greater than 100% core thermal power, th 100% core thermal power MCPRP multiplier should be applied.

• Allowable EOOS conditions are Usted InSection 6.

LaSalle I Cycle 1OA 24 Revis' '

Technical Requirements Manual - Appendix I LCI OA Core Operating Umits Report Table 2-8 MCPRp For Second Cycle 1OA Sequence Exchange to Sequence Exchange at 8,800 MWd/MT Cycle Exposure -

For ATRIUM10 Fuel Located in9A. 1OB, and IOC Cells Technical Specification Scram Speeds (TSSS)

(Reere 3 Tbe 52 and Relence 13 Ta6.ble)5.

2S Thermal Power (% of rated) 5Core 1.

300 C6imbfrtatlen 0 2I 25(25.I1n) I 0 80 I 80Iso 80e.1) I 100 MCPRp

. nase CaseOpern -224

[274 - 2.19 f - .59 IM

_ .I I. 1 EOOS Case t 2.9 249 2A9 I 1.68 i.55 EOO case 2 2.099 2A9 2.9 In 1.78 IM I : . I' I EOOS Case 3 2.49 2Z49

.1.68 2.99 :1i.

1.65 I Skngl LoopOperaft (31O), .2 2.20 1.6t 1.51

_________ _II

.2.5

• _ I SLO. wOS00 Cesae t 3.00 2.50 .2.0. ~1A?.

6 SLO wfth EOOS Ca"o2. 3.00__20 - 2 - 1.87 1.79 1.04 SLO wiEOOS Cae" 3 3.00 2.50 250 1.8

.~ ~ - - - a_.

0 Values are Interpolated between relevnt power levels.

For thermal nmnt mon g at greater than 100Y core tmal power, the 100% cor therrmal 0 power MCPRp mulipier should be applied.

Allowabl EOOS condiftons e shd InSection 6.

. .T 2-7 Table 2-7

- . I.- -

LaSalle Unit I Cycle i1A I - -- .

24 Revislon 2

Technical Requirements M/anual - Appendix I LI C1 OA Core Operating Limits Report MCPRp For Second Cycle IOA Sequence Exchange to Sequence Exchange at 8,800 MWd/MT Cycle Exposure -

For ATRIUM-10 Fuel Located In 7B, 7C, and 8A Cells Nominal Scram Speeds (NSS)

(Rermnce 3 Tabe 5.1 and Ruwaw 16 T 51) 1*

EOO ComblmaUon Core Themnal Pow"r (% of rated) 0 1 25 1 2 1) 40 1 40(40.1) 1 60 I 80 80(80.1) I 100 9 Y W

.MP Bus Cae Opera.on, 2.73 2.23 - 2.10 ' 1A3 EOOS Ca" 1 2.80 2.39 239W 1580 EOOS Case 2 2.89 2.3 2.3 1.57 EOOS Ca"e 3 2.89 2. 239 1.50 Sinl Loop Operato (SLO) 2.74 2.24 2.11 144 SLO wh EOOSCawI 2.90 2_4 2A40 1.61 SLOwit EOOS Ca2 2.90 2.40 2.4 158 SLO wih EOOS Case3 2.90 2.40 2.4 1.51 S Values are interpolated between relevant power beve.

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

S Allowable EOOS conditions are Usted InSection 6.

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

LaSalle ' 1 Cycle IA 2-1' RevWsr ?

Technical Requirements-Manual - Appendix I LI CI OA Core Operating Limits Report Table 2-8 MCPRp For Second Cycle IOA Sequence Exchange to Sequence Exchange at 8,800 MWd/MT Cycle Exposure -

For ATRIUM-10 Fuel Located In 78, 7C, and 8A Cells

- Technical Specification Scram Speeds (TSSS)

(Reftene 3 Tabe 62 an RMeme 16 Tae 5L1)

Y Core Thermal Power (% of rated)

EOOS Cembbhon 0 l 25; 2525.1) 40 I 40(41) 1 30 80(1m.1) 100 4

MWP'1 Base Case Operaflo 2.73 .223, -2.18 Tj IM 1.9 0 _ R ~~1.46 EOOSCase 2.93 2.4 2.48 1.54 EOOS Cse 2 2.98 2.48 - .48 1.85 1.77 1.62 EOOS Case 3 2.98 2.48 Z24 1.54 1.94 1.9 1 1.85 Snl Loop OpDMon (SLO) 2.74 ,2.24 - 2.19 - ~~1.47 SLOwWl9 EOOS Cae 1 2.99 -2.49 2.49 1.86 1.55 SLO WM EOOS Case 2 29o 2A9 2.49 1.86I 1.78 1.63 SLO WfttEOOS Case 3 2.9 2.49 2.49 1.55

• Vae are interpolated between relevant power levfs '

• For theffnal limit montoring at greater than 100% core termal power, te 100% core themal power MCP mufltpfier should be applied.

• Allowable EOOS condItions are ivsted In Section 6.

• The 40% and 40(40.1)%o values were determined fom herpolation of the Reference 3 values followed by apptication of the Reference 13 penalties.

LaSalle Unit I Cycle IOA 2-11 Revislon 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2-9 MCPRp For Sequence Exchange at 8,800 MWdlMT Cycle Exposure to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis)

Applicable to all ATRIUM-10 Fuel Except Those Located InCalls 7C, IOA, and 10C Nominal Scram Speeds (NSS) f (Rghree 3 Tabe 5.1)

Core Thermal Power (% of rated)

EOOS Ccoanblumon 0 25 25(21)l 60- 80 l 080.1) I 100

- w Ca"e OpmUw 70on 2.i 1.52 1A3 EOOS Case I . _ . 1A7 M EOOS Case 2 2.2a32 _ 1.81 1.74 EOOS Case 3 2. 2.3 2.3 1.j7 Shgb Loop OpUaUo (SLO) ,2.71 2.21 208 1.53 _1 SLOwit EOOS Ca"i 2.87 . 7 1.0 I.48 SW wWI EOOS Cae 2 2.87 2.37 2371.75 SLO wit EOOS Cne3 2.87 2.37 2.37 10A8

• Values are Interpolated between relevant power levels.

• For themal limit monitorg at greater than 100% core temalpower, the 1oo% core thmal power MCPRp multioier should be applied.

• Allowable EOOS conditions are listed in Section 6.

LaSalle "Iit I Cycle IOA 2-1? Revision 2

Technical Requirements Manual - Appendix I Li C1 OA Core Operating Limits Report Table 2-10 MCPRp For Sequence Exchange at 8,800 MWd/MT Cycle Exposure to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis)

Applicable to all ATRIUM-10 Fuel Except Those Located In Cells 7C, IOA, and IOC Technical Specification Scram Speeds (TSSS)

(Rfwene 3 Table 52)

- Core Thermal Power (% of rated)

EOS e0b0e1o -o .  :

25 . I123(251) I 60 ~- I 80 I NW801) I100 I

MCPR6 I Boe Case Operflon  : 2.70 *220 2.15 1.5 . 1AG EOO Csse 1 2.95 245 2A.45 f1l IJ51 EOOS Cas 2 2.95 2.45 2.45 1.82 IZ9 ,

EOOS Cte 3' 2.95 2.45 2.45 12 1.51

.,l Loop . . .-,, ., ..lie Slnteoopefln(WV 2.'71" '2.21" 2.185 ' 1.58~ IA7 SLO whtEOOS Case I 2.96 2.46 2.48 SLO wltEOOS Cese 2 12 I I 2.48

.~ I 2.48 1.83 CM SLOwlh EOOS Case 3 2.9 2.48 2.408 1.63 Im

.~ ~ - . a

. Values are Interpolated between relevant power levels.

0 For thermal llmKt monitoit at greater than 100% cre ftemal power, the 100% cor thermal power MCPRp riultpler should be appl.

0 Aflowable EOOS conditions are llsted In Section 6.

LaSalle Unit I CycleI 10A 2-13 Revision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2- 11 MCPRp For Sequence Exchapge at 8,800 MWd/MT Cycle Exposure to 12,405.6 MWd/MT

-Cycle Exposure (MOC Ucensing Basis)

For ATRJUM-10 Fuel Located In Coal 10C Nominal Scram Speeds (NSS)

(Reenc 3Tab 5.1. Rleac 18 Tabe 43)

Core Thermal Power (%of rated) 5005 CoXbmblnllo 0 128 252.1 0 60 60(80.) T 100 v S~~~CP4- '

Laop Opei asine L 2.73 2.23 2.11 i.58

_;4 E008 EOOSCasel 3 1 Case 2.89 24 2.40 1._0 EOOS Case 2 2.89 2.W 9 1 8_ 1.77. 1.57 EOOSCa" 23 2wS9 2.W i - 1. 1.GD Ski Loop Opwadon (SLO) 2.74 2.24 2.11, 1,.58, 1-4' SLOwIh EOOS Case 1 2.9 2.40 2_40 .3, 1.1 SLOvit EOOS G~a2 2.S0 2 40 2AO _ . 1.78 1XA SLO wi EOOS Ca 3 2.90 2.40 2.40 l1.3

• Values are Interpolatd between relevant power levels.

• For themal limit monitori at greater than 100% core thera power, the 100% core thermal power MCPRp multiplier should be applied.

• Allowable EOOS conditions are listed InSection 6.

LaSalle 't I Cycle 1OA 2-1,* Revsir- 2

Technical Requirements Manual - Appendix I L1C1 OA Core Operating Limits Report Table 2-12 MCPRp For Sequence Exchange at 8,800 MWd/MT Cycle Exposure to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis)

For ATRIUM-10 Fuel Located In Cell IOC Technical Specification Scram Speeds (TSSS)

(Reference3 Tbe .2 Reference 18 Ta9 4.3)

- - - --- - Core Thermal Power % of rated)

EOOS CombhnatOn 25 .l 2Z.) l 0' l e l 80.1) l 100 ase CeseOperaflon 2i3 2.23 I4A _

EOOS Case I 98 2.4 -48 2.S 1.5 EOOSC"92 2.08 248 2.481.77 l 1-0 EOOS3 Cse 3 2.98 2.8 2.48 1.65 S!e Loop Operaflon (SLO) 2.74 2.24 2.19 1.

SLO wUh EOOS Case I 209 2.49 -2.9 .88 SLO WthEOOSCMse2 2.D9 249 249 1.88 1.78 1.63 SO Wit EOOS Cae 3 2.09 2.49 2.9 1.06

• Values are Interpolated between relevant power levels.

• For themal llmft monitoring at great than 100% core-themal power, the 100% core thermal power MCPRp multiplier should be appled,.

• Aflowable EOOS conditons are Isted in Section .

LaSalle Unit I Cycle IOA 2-15 Revision 2

Technical Requirements Manual - Appendix I LICIOA Core Operating Limits Report Table 2-13 MCPRp For Sequence Exchange at 8,800 MWd/MT Cycle Exposure to 12,405.6 MWdlMT Cycle Exposure (MOC Licensing Basis)

For ATRIUM-10 Fuel Located In Cells 7C and IOA Nominal Scram Speeds (NSS)

(Refere 3 Tab"l1. RePerno 1B Table 4.3)

Core Thermal Power % of rated EOOS CombhlaUon 0 26 l 261) 60 l IW80(80.1) 100 Base ce opado 2.71 221 2 EOOSCase1 2I87 2d7 2 37 1.60 EOOS Camo 2 2.87 2.37 18 1.75 1S5 E0O0 Case 3 2.87 2.37 2 37 _ AS Shge LOOp Operlo (SLO) 2.72 2.22 2.0 1.54 AS SLOwith EOOS Ca" 1 2M8 2.38 2.W 1. 11 SLO wih EOOS Case 2 2.68 2.38 2.38 SLO wth EOOS Cae 3 2.88 2.38 2.38 .1.4

. Values are interpolated between relevant power eves.

• For thdermal lmnit monitoring at greater than 100% core themal power, the 100% coe hermal pOWe MCPFR muliplwet should be applied.

• Allowable EOOS conditions are listed InSection 6.

LaSalle 'l"ICycleelOA 2-1? Revisir- 2

Technical RequiremeniManual - Appendix I L1C1 OA Core Operating Limits Report Table 2-14 MCPRp For Sequence Exchange at 8,800 MWd/MT Cycle Exposure to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis)

For ATRIUM-10 Fuel Located InCells 7C and 10A Technical Specification Scram Speeds (TSSS)

(Rfrec 3Tae 5.2 Refrne 18 Tae 4.3)

. . ' Core Thirmal Power (% of rated)

.-EOOSComb!at1on 0 25 25(25.1) 6 l 0 80(80.1) 100 One Omse eai 2.71 221 -Z1i 1. _5 E0S Case 1 26 2.46 2.46 1.83 _ _

EO0S OCe 2 2.6 2.46 2I46 - _ In EOS Case 3 2.5 2.46 2A6 A1 _6 StngteLoop OpenqtvonSLO) 27 2 2.1722 7 tt SLOwlh EOOS Case 2.97 247 247 1.64 SLO wffhEOOS Case 2 2.97 2.47 2.47 1.70 1A1 SLOwIhEOOS Case3 2.97 2.47 2.47 1.64

• Values are Interpolated beteen relevent power levels.

• For themial limit monitorg at greater than 100% coe tmal power, the 100% coe thermal power MCPRN multipiler should be applied.

• Allowable EOOS conditions ar listed InSection 6.

LaSalle Unit I Cycle 10A 2 Rtevision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2-15 MCPRp For 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC) -

Applicable to all ATRIUM-b Fuel Except Those Located In Cells 7C, GA, and 98 Nominal Scram Speeds (NSS)

(Refeence 3 Table 3)

Core Theral Power (% of rated)

EOOS Combknatlon 0 25 25(251) 60 A so I 80(80.1) 100 BaeCas Opeadon 2.70 2.20 2.07 1.52 EOOS Case1 ll 231 2 T EOOS Cas 2 2.86 2W 2W _. 1.74 1.6 EOOS Case 3 2M 2.3B 2.68 1.47 Sgle Loop Opeabon (SLO) 2.71 2.21 2.08 153_

SLOwith EOOS Cuse 1 2.87 2.37 1.00 _A8 SLO wivih OOS Case 2 2.87 2.7J 2.37 .82 1.75 1.0 SLO wit EOOS Caa 3 2.87 2.37 2.37 1.60

• Values are Interpolated between relevant power evels.

• 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 InSection 6.

LaSalle I 1'it 1 Cycle I OA 2-18 Revisirv Z

Technical RequirementisManual - Appendix I LICIOA Core Operating Limits Report Table 2-16 MCPRp For 12,405.6 MWd/IMT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC) -

Applicable to ATRIUM-10 Fuel Except Those Located In Cells 7C, 9A, and 9B Technical Specification Scram Speeds (TSSS)

(ReQce 3Teble 5A)

- Core TheM PoWer (% o rated)

EOOS Combinaflen . j0 I .; 2s 1 25(25.1) 1 . G0o . I 80 1 o(so.1) 100 iwMcpn,

'C. , jI DM 0196OP60116 t 2.70 _ _ . 0__[ 215

~~~~1. - I .., I I 6005 Case 1 2.95: 24S .

25S i.62

-, I 1682~~~~~~~~~

1 .5 1;4 EOOS Case 2 2.95 2.45 2A5 EOOS Cae 3 2.95 2A5: 2.45 StngeLPOP O(SLO) i 2.71 2.21 Lie1 I'

- - ~~~~~1.62 SLOwlt EOOS CaseI 2. 2.45 2.- 13 SLO wfth E00S Case 2 2.9 2.4 24 idJ3 1.75 I 1.

SLOWiEOOS Cas 3 2.95 2.46 2.46 1.63 162

. Values arm hnterpolated between relevant power levels.

a For ftermal llmft monitorng at greater than 100%oore thermal power, the 100% core thermal power MCPRp multIplIer should be applied. . .. .. ; .

S Allowable EOOS conditions are listed In Section 8.

LaSalle Unit 1 Cycle 2-10 Revislon R10A 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2-17 MCPRp For 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC) -

For ATRIUM-10 Fuel Located InCalls 7C, 9A, and 9B Nominal Scram Speeds (NSS)

(Refe 3 Tabe 5.3, Reonce 18 Tabe 4.3)

Core Thomal Power % of rated)

EO0S Combknlion O 25 l2551) 60 80 l8(0.1)l 100 ae case Operaton 2.71 221 20 1.53 _8 EOOS Case t 2.0 2.37 2.37. 1.48 EOOS Cos 2 2.87 2.37 AA2 1.76 EOOS Ca 3 2.87 2.37 2.37 1.60 Singe Loop Opeatn (SLO) 2.72 2.22 2.09 1.4 SLO with EOOS Case 1 2.8 2.38 2.38 1.6I SLO WIhEOOSCa"s2 2.88 2.3 2.38 1.8 1.76 1.61 SLO with EOS Case 3 2.88 2.38 2.38 1.61

• Values are interpolated between relevant power levels.

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

• Allowable EOOS conditons are isted InSection 6.

LaSalle -~it I Cycle 1OA Revis'- - 2

Technical Requirements Manual - Appendix I Li C1 OA Core Operating Limits Report Table 2-18 MCPRp For 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC) -

For ATRIUM-10 Fuel Located In Cells 7C, 9A, and 9B Technical Specification Scram Speeds (TSSS)

(Reerence S3Tabl A. Reeence 18 Tebh 4.3)

.,CoreThermalP ower(%ofrated)

EMOS Cemb: Un b 0 eo 25 25251) . 8lo 8080.1) I 100 ase C.sopea 2z71 2.21 2.16 1.*86

-EOOS Case 1, 2.0 2.48 2.46 1.83 EOOS Case 2 Z2s 2.46 14.63 1.75 lA EOOS Cse 3 2.0 2.468 2A6 1.63 .

'. -1.

Sfige Loop Opeon (80) .- 2.72 2.22 117 1.7 SLOwfth EOOSCese 1 2.97 2.47 2.47 1.66 SLO wlf EOOS Case 2 2.07 247 2.47 1-1 =l1 SL0 WM E0S Case 3 2.97 247 2.47 1.04

• Values are Interpolated between relevant power levels.

• Forthermallinmitmntodingtgaterth 10%cothmalpowerthe100%core tmal power MCPRp multiplier shomdd be applied.

• A llow EOOSondt are ed InSectione.

LsSagle Unit I Cycle 10A 2-21 Revision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 2-19 MCPRp For 12,405.6 MWdlMT Cycle Exposure (MOC Ucensing Basis) to Coastdown (EOC) -

For ATRIUM-SB and GE9B Fuea Nominal Scram Speeds (NSS)

(Raewruce 3 Tab 5.3)

Core Thermal Power (% of rated)

EOOS ComblmUon 0 25 2X1) 60 80 80(80.1) 10 Base CseOpeRUI 2.70 2.20 1.96 1.50 1A3 EOOS Case I 2 70 _ 2.20 216, _

EOOS Case 2 Z70 Z20 _ 1.07 158 EOOS Ca 3 2.70 2.20 2.15 15 Singe Loop Opetakon (SLO) 2.71 2.21 19 1.51 SLOwh EOOS Case 1 271 2.21 2.16 1.59 SLO w EOOS Case2 2.71 Z21 2.10 1f7 Iw SLO ith EOOS Case 3 2.71 2.21 2.10 1. 1A

• Values are Interpolated between relevant power levels.

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

• Allowable EOOS conditons are Usted In Section 8.

LaSalle "it I Cycle IOA 2-r Revis'-- 2

Technical Requirements Manual - Appendix I L1 C1 OA Core Operating Limits Report Table 2-20 MCPRr For 12,405.6 MWdIMT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC) -

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

(Reen 3Table5.4)

Core Thermal Power (% of rated)

EOOS CMbt 6 7 0 2S5 2W(5.1) 0. 80 10(80.1) 100

~~MCIR, B.e Cse,Qperaf.o .2.70 2.20 1.06 1.4 EOOS Case I 2.70 2.20 2.19 1.6218 EOOS Case 2 2.70 220 - 210 I." 1.73 1.65 EOOS Cases .2.70 220 2.19 _1.6 Shg Loop e -(SLO) 2.71 221 1.7 15AS SLOwfti EOOSCese 1 2.71 2.21 2.20 13 1A9 SLOwi EOOS Cmse2 2.71 2.21 20 1.O71.74 1.86 SLOwlthiEOOS Cnse3 2.71 2.21 2.20 61A9

• Values are Interpolated between relevent power levels.

• For thermlmit montorng atgrer than 100%co tem pw, th 100% cot ma power MCPRp multplier should be applied.

• Allowable EOOS conditions are listed InSection 6.

LaSalle Unit I Cycle 10A 2-23 Revision 2

Technical Requirements Manual - Appendix I LIC1OA Core Operating Limits Report Table 2-21 MCPRFlimits for ATRIUM-1 0, ATRIUM-9B, and GE9B Fuel (Reference 3 Fgure 5.1)

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

• Values are interpzolatedi between relevant low 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.

. ~~~~~~~~.

LaSalle Unit 1 Cycle 1OA 2-24 Revision 2

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

3. Linear Heat Generation Rate (32.3) 3.1 Technical Specification

Reference:

Section 3.2.3.

3.2 Descriltion

The LHGR Umit Is the product of the LHGR Limit from Tables 3-1, 3-2a, 3-2b, 3-3a, 3-3b, 3-4a, 3-4b, 3-5, 3-6 or 3-7 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 3-8, 3-9, 3-10 or 3-11 for ATRIUM-10 fuel, Table 3-12 3-13, 3-14 or 3-15 for ATRIUM-9B fuel or Table 3-16 or 3-17 for GE9B fuel. The applicable flow dependent LHGR Factor (LHGRFACF) Is determined from Table 3-18 for ATRIUM-10 and ATRIUM-9B fuels or Table 3-19 for GE9B fuel.

Table 3-1 Steady-State LHGR Umits for all ATRIUM-10 Fuel Except those Located In Cell Locations 76, 7C, 8A, and IOA Applicable from BOC to the Sequence Exchange at 8,800 MWd/MT Al 0-4039B-1 5GV75-1 0DM and Al 0-40371-1 6GV75-1 0DM (Bundle types 10, 11, 20, 24, 26, 27, 28, 29, 31, 32, 41, 45, and 49)

(Reference 3 Section 723)

Average Planar LHGR Umit Exposure (WIM (GWdIMT) (kWt) 0.0 13.4 15.0 13A 55.0 9.1 64.0 7.3 Table 3-2a Steady-State LHGR LUmits for ATRIUM-10 Fuel Located InCell Locations 7B, 7C, and 8A Applicable from BOC to the Sequence Exchange at 8,800 MWd/MT Al 0-4039B-1 5GV75-1 0DM and Al 04037B-1 6GV75-1 0DM (Bundle types 21, 22, 23, and 43)

(Reference S Section 72.3 and Reference 16 Section 2.0)

Average Planar LHGR Umit Exposure (kWM) 0.0 133 15.0 13.3 55.0 9.0 64.0 7.2 LaSalle Unit I Cycle I0A 3-1 Revision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 3-2b Steady-State LHGR Limits forATRIUM-10 Fuel Located in Cell Locations 10A Applicable from BOC to the Sequence Exchange at 8,800 MWd/MT Al0-4039B-15GV75-100M (Bundle type 30)

(Reference 3 Sectwon 72.3 and Reference 16 Section 2.0)

Average Planar LHGR Limit Exposure k/)

(GWdlMT) 0.0 13.0 15.0 13.0 55.0 8.7 64.0 8.9 Table 3-3a Steady-State LHGR Limits for all ATRIUM-10 Fuel Except those Located In Cell Locations 8A, 9D, IOA,0OB, and 10C Applicable from Sequence Exbhange at 8,800 MWd/MT to 12,405.6 MWd/MT (M6C Licensing Basis)

Al0-4039B-15GV75-10 OM and A10-4037B-16GV75-IOOM (Bundle types 10, 11, 20, 21, 22,24,28,27,29, 31,43, 45, and 49)

(Reference 3 SeCon 7.23 and ReferenCE 18 Table 42)

Average Planar LHGR Limit Exposure k/)

(GWdJIT). (kWf) 0.0 .13.4 15 .0 13.4 55.0. 9.1.

84.0 7.3.

Table 3-3b Steady-State LHGR Limits for ATRIUM-1 0 Fuel Located InCell Locations 8A, 9D,1 OA, 10B, and 10C Applicable from the Sequence Exchange at 8,800 MWd/MT to 12,405.6 MWd/MT (MOC Licensing Basis)

Al 0-4039B-1 5GV75-1 OOM and Al 0-3037-1 6GV75-1 OOM (Bundle types 23, 28, 30, 32, and 41)

(Reference 3 Section 723 and Reference 18Table4.2)

Average Planar LHIGR Limit

'Exposure k/)

(GWdnM (kWl) 0.0 13.0 15.0 13.0 55.0 8.7 84.0 8.9 LaSalle Unit 1Cycle IOA 3-2 Revision 2

Technical Requirements Manual - Appendix I LICtOA Core Operating Limits Report Table 3-4a Steady-State LHGR Limits for all ATRIUM-10 Fuel Except those Located In Cell Locations 8A, and 9D Applicable from 12,405.6 MWd/MT (MOC Licensing Basis) to EOC Al 0-4039B-1 5GV75-1 OOM and Al 0-4037B-1 6GV75-1 OOM (Bundle types 10, 11, 20, 21, 22, 24, 26, 27, 29, 30, 31, 32, 41, 43, 45, and 49)

(Reference S Secdon 723 and Reference 18 Table 42)

Average Panar LHGR Umit Exposure kM (GWdaMT(kt) 0.0 13.4 16.0 13.4 55.0 9.1 64.0 7.3 Table 3-4b Steady-State LHGR Limits for ATRIUM-10 Fuel Located in.Cell LocatIons,8A,-and 9D Applicable from 12,405.6 MWdlMTJ "(WOlicensIng Basis) to EOC A10n4039B-15GV7W 14M

• (Bundle typs 23, and 28) eRefernce 3 Section 72.3 an Reece-186 ible 4.2)

AverageEposurePlanar LHGR

- mit (GWdMT) (kWQ)

. 0.0 13.0

- 15.0 - 13.0 55.0 8.7 64.0 ~ 6.9

. j Table'3-5, Steady-State.LHGR Limits for A~l1UM-9B Fuel SPCA9-393B-16GZ-diOM SP0A9-396B-1l2GZB-1OOM SPCA9-384B-1 I GZ-80M

• . SPCA9-396B-12GZC-iOOM (Bundle types 6, 7, 8 and 9)

(Reference 3 Secdon 7.23)

Average Planar LHGR Umit Exposure LhG/mt (GWdIMT) (kn 0.0 14.4 15.0 14.4 64.3 7.9 LaSalle Unit I Cycle 10A 3-3 Revison 2

Technical Requirements Manual - Appendix I LI C1 A Core Operating Limits Report Table 3-6 LHGR Limits for GEOB Fuel GE9B-P8CWB343-1 2GZ-80M-1 50 (Bundle 3866, bundle type 4)

(Reference 5 Page 47)

Average Planar LHGR Umit Exposure Limi (GWdlMT (kWlft) 0.00 14.40 12.33 14.40 27.88 12.31 49.78 10.80 81.18 8.00 Table 3-7 LHGR- Limits for GE9B Fuel GE9B-P8CWB342-1 OGZ-80-1 50 (Bundle 3867, bundle type 5)

(Reference 5 Page 47)

Average Planar LHGR Limit Exposure k/)

(GWdINM) - kWf) 0.00 14.40 12.71 14.40 27.52 12.31 49.54 10.80, 60.95 6.00 LaSalle Unit I Cycle I OA 34 Revision 2

Technical Requirements Maniual - Appendix I L11C OA Core Operating Limits Report Table 3-8 LHGRFACp For BOC to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) -

For ATRIUM-10 Fuel Nominal Scram Speeds (NSS)

(Refernce STable .1)

Core Thermal Power (% of rated EOOS Combination 0 1 25 60 1 80 1 100 LHGRFAC, mullUpler Base Case Operation [ 0.75 j 0.75 1.00 1.00 EOOS Case I 08 0.66 I

0.94 0.0s4 T 0.95 EOOS Case 2 I 0.5 0.65 0.6 0 .89 EOOS Case 3. O8 :0.6 SiWle Loop Operation (SLO) 0.7 0.75 1.00 SLO with EOOS Case1I,1 0.68 0.94 ~0.05 SLO with EOOS Case 2 I

[

.- .. .I

.OA5 I00.65.

SLOwIth EOOS Case 3 0.6 0.6 . 0.7 , . 0.77 0.83

_________________________ & __ I

• - Values are Interpolated between relevarant power levels.

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

• Allowable EOOS conditions are listed In Section 6.

LaSalle Unit I Cycle IQA 35 Revision 2

Technical Requirements Manual - Appendix I LICIOA Core Operating Limits Report Table 3-9 LHGRFACp For BOC to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) -

ForATRIUM-10 Fuel Technical Specification Scram Speeds (TSSS)

(Reference 3 Table 5.2)

Core Thermal Power (% of rated)

EGOS Combination 0 25 40 60 80 100 LHGRFACP multiplier Base Case Operation 0.74 EOOS Case 1 0.84 0.84 7 0.7 0. 0.95 EOOS Case 2 i 0640 T EOOS Case 3 0.54 Single Loop Operation (SLO) 0.74 SLO sMth EOOS Case 1 0.84 SLO with EOOS Case 2 0.64 0.834 _ 0.87 0.87 SLO witl EOOS Case 3 0.64 0.64 0.77 0.77 0.77 0.83 s _

e Values are interpolated between relevant power levels. ,

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

• Allowable EOOS conditions are listed In Section 8.

LaSalle Unit 1 Cycle 1OA 3-6 Revision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 3-10 LHGRFACp For 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC)

- For ATRIUM-10 Fuel Nominal Scram Speeds (NSS)

(Refrence 3 Table 6.3)

Core Thermal Power (% of rated)

EOOS Combination 0o T 25 1 60 TI ' 100 L)HGRFAC, multiplier Base Case Operation 0.75 J0.735 1.00 1.00 EOOS Case I 0.66 0.68 0.94 0.95 I

EOOS Case 2 j 0.65 0.65 0.84 0 ,

I I... O."

EOOS Case 3 ' 0.65 0.65_ 0.77 0.77 083 Single Loop Operation (SLO) I 0.5 0T 075 1.00 SLO with EOOS Case I 0.66 O.W..I 4.94 0.94 0.95 SLO With EOOS Case 2 -

1 S Oih S ae 0.65 OA0S

[ Ao65 _ 084 0.84 SLO with EOOS Case 3 0.65 0.6S 'on 0.77 0a83

... I . . .

S 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 IOA 3-7 Revision 2

Technical Requirements Manual - Appendix I LI C10A Core Operating Limits Report Table 3-11 LHGRFACp For 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC)

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

(Reference 3 Table 5A)

Core Thermal Power (% of rated)

EOOS Combinatlon I 0 1 25 1 40 1 60 1 80 I 100 Bass Case Operation 0.74 0.74 1.00 EOOS Case 1 0.64 0.34 0.94 0.95 EOO2Case 2 0.64 0.64 0.82 0.82 EOS Case 3 0.84 0.54 10.77 1 0.77 0.83 Sbge Loop Operation (SLO) 0.74 0.74 1.00 SLOMwii EO0 Cas 1 0.84 0.84 0.94 0.95 SLO wWh EOOS Case 2 0.4 0.84 0.82 0.82 SLOwitl E00S Case 3 0.64 0.641 0.77 I 0.77I 0.77 0.83

• Values are Interpolated between relevant power levels.

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

• Allowable EOOS conditions are listed In Secton 8.

LaSalle Unit I Cycle IOA 3-8 Revision 2

Technical Requirements Manual - Appendix I Li C1 OA Core Operating Limits Report Table 3-12 LHGRFACP For BOC to 12,405.6 MWdIMT Cycle Exposure (MOC Licensing Basis) -

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

(Reference 3 Table 6.1)

Y Core Thermal Power (% 0f rated)

EOOS Combination - o 1 25 T 60 I so0 100 LHGRFACp mull Uplher Base Case Operatiom 0.77 0.77 1.00 1.90 EOOS Case I 0.69 - 0.m9 0.90 0.90 0.90 EOOS Case 2 J 0.67 0.7 EOOS Case 3- _, 0.69 0.69 0.77 0.o77 0.80 SIngle op Opwin (SW),- J [ .77 0.77 .00

_~~O Ioo. .AW.

os

.ro SLOwff EOOS Case 1 l EOOS 10o67 8:L Cas 0.69 1

1Ž.6- . .10 0.90 -

. 0.79

~0.900 0.79 SL0wlthEOOSCcse3 S 0.

069 I o.0 . 0...80

! I' Values are interpolated between

'relevant power levels. -

a 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 IOA 3-9 Revision 2

Technical Requirements Manual - Appendix I Li C1 OA Core Operating Limits Report Table 3-13 LHGRFACp For BOC to 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) -

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

(Reference 3 Table 52)

Core Thermal Power (% of rated)

EOOS Combination o T 25 1 40 1 60 I 80 I 100 LHGRFACp multiplilw Base Case Operaion 0.76 0.78 _ ~~~~1.00_t.

EOOS Case 1 0.69 0.9 0.7 7 0.77 0 . 77 0 .9 2 EOOS Casa2 0.57 0.57 0.76 ECOS Case 3 0.89 0.69 0.77 0.77 0.80 Sigle Loop Oporamon (SLO) 0.7B 0.76 SLO wYi EOOS Case 1 0.69 0.89 0O9 0.92 SLO wihEOS Case 2 0.67 0.7 0.78 0.78 SLO with EOOS Case 3 0.89 0.69 0_7 0.77 _.8 I I -

• 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 llstod in Section 6.

LaSalle Unit I Cycle 1OA 3-10 Revision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 3-14 LHGRFACp For 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC) -

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

- ff(eference 3 Table 6.3)

• 1 - -- -- --- - -

Core Thermal Power (%Yof rated) d EOOS Combination 0 1 25 1 s01 100 LHGRFAC, multiplier Base Case Operation 0.768 0.76 1.00 1.00 EOOS Case I 0.69 0.E9 . 0.901 0.00 0.90-EOOSCse2 0.67 067: 0.79 -0.79 I, I . ., . I EOOS Case 3 0607.

0.69 0.69 - 0.7 0.77 OAO Single Loop Operation (SLO) ' 0.76 [ 0.76-:- - 1.00 1.00 SLO with EOOS Case I 0.69 0.69 o

-0.0 I 0.90 0.90

• SLO wthEOOSCase2 - 067 0.6 0.79 0.79 SLO with EOOS CaseI.I3 .M 0.69 .OAOI I. h Values are Interpolated between relevant power levels.

For thermal limit monitoring at preater than S

100YO core thermal power, the 100% core

-thermnal power LHGRFACp multiplier should be applied.

Allowable EOOS conditions are listed InSection 6.

LaSalle Unit I Cycle 10A1 3-11  ; Revision 2

Technical Requirements Manual - Appendix I Li C1 OA Core Operating Limits Report Table 3-15 LHGRFACp For 12,405.6 MWd/MT Cycle Exposure (MOC Licensing Basis) to Coastdown (EOC) -

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

(Reference 3 Table .4)

Y Core Thermal Power (% of rated)

E003 Combinatlon 0 r 25 1 40 1 60 I 80 I 100 LHGRFACp multiplier Basa Case OperaXon 0.76 _ <-1001.0 EoOS Case1 0.89 0.69 _ ~~~0.89 Q1 0.92 EOS Case 2 0.67 0_ 07 0.7 EOOS Case 3 0.69 H 0l79 m1f I 67 07 0.80 Singe,Loop Operaffon (SLO) 0.76 Q.78 _ D1 00 1.00

_ ~ ~~

.4

[

SLO with EOOS Case 1 0.69 LOwIth EOOSCaSe2 0.67 0j57_ ~ Q.7

~~~~~~0.76 SLO with EOOS Case 3 0.69 0.6 0.n 1- 0.77 0Q77 0.80

• 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 1OA 3-12 s 2 Revision

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

Table 3-16 LHGRFACp multipliers for GE9B Fuel except TCV Slow Closure (References 3. 5,10 ud 15)

Core Thermal LHGRFACp Power (% of rated) . Multiplier .

0 4OA776 25 0.6082

.100 *

• 1.0000 0 values are interpolated between relevant power levels.

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

Table 3-17 LHGRFACp multipliers for GE9B Fuel for TCV Slow Closure

-(Referes 3S5, 14 and 15)

Core Thermal LHGRFACp Power (% of rated) - Multiplier 0 0.2000 25 - 0.4000 100 D1.0000

• Values are Interpolated between relevant power levels.

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

e 8-V LaSalle Unit I Cycle I0As 3-13 Revision 2

Technical Requirements Manual - Appendix I LI C1 OA Core Operating Limits Report Table 3-18 LHGRFACF multipliers for ATRIUM-1 0 and ATRIUM-9B Fuel (Reference 3 Figure 52)

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 InTable 3-18 are applicable to all Operating Domains and EOOS conditions InSection 8.

Table 3-19 LHGRFACP multipliers for GE9B Fuel (Raftcw 3,5, 13 and 15)

Core Flow LHGRFACr

(% of rated) Multiplier 0 0.4872 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, utiize the 105% rated core flow LHGRFACF multiplier.

• Values presented I Table 3-19 are applicable to all Operating Domains and EOOS conditions In Section 8.

LaSalle Unit 1 Cycle IOA 3-1i4 Revision 2

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

4. Control Rod Withdrawal Block Instrumentation (3.321) 4.1 Technical Specification

Reference:

Table 3.32.1-1

4.2 DescrliDtion

The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 6):

ROD BLOCK MONiTOR ALLOWABLE VALUE UPSCALE TRIP FUNCTION TwoRecirculation Loop 0.66 Wd + 54%

Operation __________

Single Recirculation Loop , 48.7%

Operation I .6 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 damped, with-timaximum value not'to exceed the allowable value for a recirculation loop flow (We) of 100%.

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

LaSalle Unit I Cycle IOA 4-1 Revision 2

Technical Requirements Manual - Appendix I L1C10A Core Operating Limits Report

6. 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, Ifneeded, 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.

LaSalie Unit I Cycle IOA 61 Revision 2

Technical Requirements Manual - Appendix I L1C1 OA Core Operating Limits Report

6. Allowed Modes of Operation (B 32.2, B 32.3)

The Allowed Modes of Operation with combinatons of Equipment Out-of-Servioe are described below.

Standard' Equpmet Ot o Sevic MELLA Power-Flow 1C POWERPLEX I Optionsut fSeriviceonLL: Region OptionslA Region ~~~(100% Rod ReinSet Coastdowns Rion Thermal Umlt 4 Number

_ _ __ _ _ __ _ _ __ __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _L ine) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Base Case Operaeon - NSS Yes Yes Yes No 1,17,33.49 EOOS Case I - NSS TBMOOS2. or Yes Yes Yes No 2,18, 34. 60 FHOOSD N__

EOOS Case 2 - NSS Any combinalon ot Yes Yes Yes No TCV slow closure no RPT. 19.61 FHOOS' Ne EOOS Case 3 -NSS TBVOOS with 1 TCV stick Yes Yes Yes No 4.20,3B,52 dosed Slnpt Loop Operaton (SLO) - NSS No' Yes NIA No 5,21,37,63 SLO with EOOS Case I - NSS FHOOS'. o Noe Yes NWA No 6, 38, 64 T6VOOS' SLO wIth EOOS Case 2 - NSS Any combinaton a. No" Yes WA No TCV slow closure. no RPT. 7,23,39.55 FHOOSs SLO wthOOS Case 3 -NSS TBVOOS w1h I TCV stick NoP Yes N/A No 8.24.40,56 dosed Base Case Operatfon -TSSS Yes Yes Yes No 0.25.41.57 EOOS Case 1 - TSSS svoos.5 or Yes Yes Yes No 10,2B,42, 8 PHOOSD o EOOS Case 2 -TSSS Any combinaton ok Yes Yes Yes No TCV slow closure. no RPT. 11,27,43,59 FHOOSD Ne EOOS Case 3 - TSSS TBVOOS with I TCV stuck Yes Yes Yes No 12,28,44,60 dosed__

Single Loop Operaton (SLO) -TSSS No' Yes NIA No 13.29,45.61 SLO with EOOS Case 1 - TSSS FHOOS',or Noe Yes NWA No 14,30.46.02 TBVOOS2 SLO with EOOS Case 2 -TSSS Any combination of Noe Yes WA No TCV slow closure, no RPT. 15,31,47.63 FHOOS0 SLO wfth EOOS Case 3 - TSSS TBVOOS with I TCV stick No' Yes WA No 16,32 48.64 cdosed_ _ _ _ _ _ _ _ _

Key: NSS - Nominal Scram Speed, TSSS - Tech Spec Scram Speed, 0OS - Equipment Out Of Service, FHOOS - Feedwater Heater OOS, TBVOOS - Turbine Bypass Valve OOS, TCV -

LaSalle Unit I Cycle IDA 61 Revision 2

Technical Requirements Manual - Appendix I LI CIOA Core Operating Limits Report Turbine Control Valve, RPT - Recirculation Pump Trip, MELLLA - Maximum Extended Load Line Limit Analysis [above 100% Load Line (Flow Control Line, FCL) to MELLLA boundary], ICF

- Increased Core Flow (>100% core flow).

¶ Each OOS Option may be combined with I SRVOOS, I TCV stuck closed (except TBVOOS conditions), a 200 F reduction In feedwater temperature (without feedwater heaters considered OOS),

up to 2 TIP OOS (or the equivalent number of TIP channels, 42% of the total number of channels with 100% available at startup), and up to 50% of the LPRMs OOS With an LPRM calibration frequency of 1250 Effective Full Power Hours (EFPH) (1000 EFPH +25%) (Reference 3 Tables 1.1 and 5.1 through 5.4).

2 Ail EOOS options support 1 TCV stuck dosed except E00S 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 isnot exceeded.

4 Four sets of thermal limits are provided. The first set of thermal limits, from I through 16. are provided for use from the beginning of cycle until the second Cycle I OA 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 6000 MWd/MTU unti approximately 8800 MWdIMTU. This Is the defined as the approximate burnup where the pre-summer 2003 sequence exchange (from A2 to Al) takes place. The third set of thermal limits.

from 33 through 48, are provided for use from the pre-summer 2003 sequence exchange (from A2 to Al) at approximately 8800 MWd/MTU until approximately 12,405.8 MWd/MTU defined as the middle of cycle 'M0C) licensing basis. The fourth set of thermal limits, from 49 through 84, are applicable from approximately 12,405.6 MWdIMTU defined as the MOC licensing basis. The licensing basis end of cycle bumup corresponds to a core average exposure of 31,495.1 MWd/MTU. Note that the nominal exposures at the beginning and end of the sequence exchanges may be adjusted by +/-200 MWdOMTU without affecting the magnitude of the control blade history penalties Included In the thermal limit sets (Reference 18 and 18). The thermal limit sets are to be changed when the sequence exchange Is performed and not at the specific cycle exposures.

s Feedwater heaters OOS (FHOOS) supports a reduction of up to 100 0F In feedwater temperature.

FHOOS may be an Intentionally entered mode of operation or an actual 00S condition. Feedwater heaters 00S (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.

SLO boundary was not moved up with the incorporation of MELLLA and power uprate. The 100%

8The rod line (FCL) bounds this value.

ICF Is analyzed up to 105% rated core flow.

iff operating with FHOOS (alone or In combination with other EOOS), operation Inthe MELLLA region is supported by current transient analyses (UFSAR Chapter 15), but Is administratively limited to less than 100% rod line (FCL) due to thermal-hydraulic stability concerns.

9The Standard Power-Flow Region Is that part of the Power-Flow map region below 100% rod line (FCL) up to 100% core flow.

LaSalle Unit I Cycle ICA 6-2 Revision 2

Technical Requirements Manual - Appendix I LI CIOA Core Operating Limits Report T. Methodology (5.6.5)

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

1. XN-NF-81-68 (PXA), Revision 2 and Supplements 1 and 2, *RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, March 1984.

2. Letter from Ashok C. Thadini (NRC) to RA Copeland (SPC), "Acceptance for Referencing of ULTRAFLOWnT Spacer on 94-IUX BWR Fuel Deslgn, July 28, 1993.

3. ANF-524 (PXA) Revision 2 and Supplements I and 2, *ANF Critical Power Methodology for Boiling Water Reactors,' November 1990.

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

'Advanced Nuclear Fuels Methodology for Boiling Water Reactors: Benchmark Results for CASMO-3G/MICROBURN-1 Calculation Methodology,' November 1990.

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

6. ANF-913 (PXA) Volume 1 Revislo 1, and Votume 1 Supplements 2, 3, 4, 'COTRANSAt: A Computer Program for Boiling WaterReactor Translent Analyses,' August 1990.

7. XN-NF-84-105 (PXA), Volume i aid Volume i Supplements 1 and 2; Volume I Supplement 4, 4XCOBRA-T: A ComputerjCode for BWR TranslentiThermal-Hydraulic Core Anatysis,- February 1987 and June 1988, respectively.

8. ANF-89-014 (PXA) Revision I and Supplements 1 & 2. 'Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 -IX and gxg - OX BWR Reload Fuel,' October 1991.

9. EMF-2209 (PXA), Revision 1.`SPCB Critical Power Correlation,' July 2000.

10. ANF-89-98 (PXA), Revision 1 and Revision I Supplement 1, aGeneric Mechanical DesIgn Criteria for BWR Fuel Designs,' May 1995.

11. ANF-91-048 (PXA), 'Advanied Nuclear Fuels CorporatioX Methodology for Boiling Water Reactors EXEM BWR ECCS Evaluation Model,* January 1993 .- i

12. Commonwealth Edison Comparry Topical Report NFSR-0091, *Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods,' Revislon 0 and Supoements on Neutronics Licensing Analysis (Supplement 1) and La Salle County Unit 2 benchmarkiing (Supplement 2),

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

13. EMF-85-74 (PXA) Revislon 0 and Supplement 1(PXA) and Supplement 2(PXA), '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 (PXA) and ANF-1125(P)(A) Supplements I and 2, 'ANFB Critical Power Correlafion,'

Advanced Nuclear Fuels Corporation, April 1990.

17. ANF-1125 (PXA) Supplement I Appendix E, 'ANFB Critical Power Correlation Determination of ATRIUMtm-9B Additive Constant Uncertainties,' September 1998.

LaSalle Unit I Cycle IOA 7-1 Revislon 2

Technical Requirements Manual - Appendix I LICIOA Core Operating Limits Report

18. EMF-1125 (P)(A) Supplement I Appendix C, OANFB Critical Power Correlation Application for Con Resident Fuel.' August 1997.

19. Commonwealth Edison Topical Report NFSR-0085 Revision 0, mBenchmark of BWR Nuclear Design Methods,' November 1990.

20. Commonwealth Edison Topical Report NFSR-0085 Supplement 1 Revision 0, 'Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan Comparisons,' Aprii 1991.

21. Commonwealth Edison Topical Report NFSR-0085 Supplement 2 Revision 0, 'Benchmark of BWR Nuclear Design Methods - Neutronlc Licensing Analyses,' AprIl 1991.

22. ANF-CC-33(P)(A) Supplement I Revision 1 and Supplement 2, 'HUXY: A Generalized Multirod Heatup Code with 10CFR50; Appendix K Heatup Option,' August 1988 and January 1991, respectively.

23. XN-NF-80-19 (PXA) Volume 4 Revision 1, 'Exxon Nuclear Methodology for Boiling Water Reactors:

Appilcation of the ENC Methodology to BWR Reloads,' June 1988.

24. XN-NF-80-19 (PXA) Volume 3 Revision 2, 'Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX Thermal Limits Methodology Summary Description,' January 1987.

25. ANF-91-048 (PXA) Supplement I and Supplement 2, 'BWR Jet Pump Model Revision for RELAX,'

October 1997.

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

27. XN-NF480-19 (PXA) Volume 1 and Supplements I and 2, 'Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis,' March 1983.

LaSalle Unit I Cycle IOA 7-2 Revision 2