ML023380746

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Part 2 of 2, LaSalle, Unit 1 Cycle 10A Core Operating Limits Report (COLR)
ML023380746
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 11/26/2002
From:
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML023380746 (147)
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Text

Technical Requirements Manual - Appendix I L1C1OA Reload Transient Analysis Results Attachment 3 LaSalle Unit 1 Cycle 10A Plant Transient Analysis LaSalle Unit I Cycle IOA Revision 0

ARA6M ATO1: M-E-ANP EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Plant Transient Analysis January 2002 Framatome ANP. Inc.

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Framatome ANP, Inc.

ISSUED INFRA-ANP ON-UNE EMF-2689 DOCUMENT SYSTEM Revision 0 DATE: - -.2,L.*.

LaSalle Unit I Cycle 10 Plant Transient Analysis Prepared:

D. G. Carr, Team Leader BWR Safety Analysis Date ,/-/o1_

Reviewed:

i. m. mo se, Engineer Date BWR Safety Analysis Concurred:

D. E. Garber, Manager Date Customer Projects Concurred:

J.S. iMnW ager Date ProqtuULice ns in g Approved: 9 0,,,, 1 ý L/V1 -ýl i-Ax. 4*,J M. E. Garrett, Manager DOte BWR Safety Analysis Approved: /3 /

0. C. Brown, Manager Date BWR Neutronics Approved:

R. E. Collingham, Manager Date BWR Reload Engineering & Methods Development paj

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.

Inorder 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-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page i ri ILItI aitit*lmrII " L u a Nature of Changes Item Page Description and Justification

1. All This is a new document.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page ii Contents 1.0 Introduction ................................................................................................................ 1-1 2.0 Summary ............................................................................................................. 2-1 3.0 Transient Analysis for Thermal Margin - Base Case Operation ................................... 3-1 3.1 System Transients ........................................................................................... 3-1 3.1.1 Load Rejection No Bypass ................................................................. 3-3 3.1.2 Feedwater Controller Failure .............................................................. 3-3 3.1.3 Loss of Feedwater Heating ................................................................ 3-4 3.1.4 Control Rod W ithdrawal Error ............................................................ 3-4 3.2 MCPR Safety Limit ........................................................................................... 3-5 3.3 Power-Dependent MCPR and LHGR Limits ..................................................... 3-6 3.4 Flow-Dependent MCPR and LHGR Limits ....................................................... 3-7 3.5 Nuclear Instrument Response .......................................................................... 3-8 4.0 Transient Analysis for Thermal Margin - Extended Operating Domain ......................... 4-1 4.1 Increased Core Flow ........................................................................................ 4-1 4.2 MELLLA Operations ......................................................................................... 4-1 4.3 Coastdown Analysis .................................................................................... 4-1 4.4 Combined Final Feedwater Temperature Reduction/Coastdown ..................... 4-2 5.0 Transient Analysis for Thermal Margin - Equipment Out-of-Service ......................... 5-1 5.1 EOOS Case 1 .................................................................................................. 5-2 5.1.1 Feedwater Heaters Out-of-Service (FHOOS) ..................................... 5-2 5.1.2 Turbine Bypass Valves Out-of-Service (TBVOOS) ............................. 5-2 5.2 EOOS Case 2 .................................................................................................. 5-3 5.2.1 Recirculation Pump Trip Out-of-Service (No RPT) ............................. 5-3 5.2.2 Slow Closure of the Turbine Control Valve ......................................... 5-4 5.2.3 Combined FHOOS/TCV Slow Closure and/or No RPT ....................... 5-4 5.3 Single-Loop Operation (SLO) ........................................................................... 5-5 5.4 1 Stuck Closed Turbine Control Valve .............................................................. 5-5 6.0 Transient Analysis for Thermal Margin - EOD/EOOS Combinations ............................ 6-1 7.0 Maximum Overpressurization Analysis ................................................................... 7-1 7.1 Design Basis .................................................................................................... 7-1 7.2 Pressurization Transients ................................................................................. 7-1 8.0 References .................................................................................................................. 8-1 Appendix A Power-Dependent LHGR Limit Generation .............................................. A-1 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page iii Tables 1.1 EOD and EOOS Operating Conditions ........................................................................ 1-3 2.1 Base Case and EOOS MCPRp Limits and LHGRFACP Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU ......................................................... 2-3 2.2 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU ....................................................... 2-5 2.3 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC ......................................................... 2-7 2.4 Base Case and EOOS MCPRP Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC ....................................................... 2-9 3.1 LaSalle Unit 1 Plant Parameters for the System Transient Analyses at Rated Pow er and Flow ................................................................................................ 3-9 3.2 Scram Speed Insertion Times .................................................................................... 3-10 3.3 15,000 MWd/MTU Base Case LRNB Transient Results ............................................. 3-11 3.4 EOC Base Case LRNB Transient Results ............................ 3-12 3.5 15,000 MWd/MTU Base Case FWCF Transient Results ............................................ 3-13 3.6 EOC Base Case FWCF Transient Results ................................................................. 3-14 3.7 Loss of Feedwater Heating Base Case Transient Analysis Results ............................ 3-15 3.8 Input for MCPR Safety Limit Analysis ......................................................................... 3-16 3.9 Flow-Dependent MCPR Results ................................................................................. 3-17 5.1 EOOS Case 1 Analysis Results - 15,000 MWd/MTU .................................................. 5-7 5.2 EOOS Case 1 Analysis Results - EOC ....................................................................... 5-9 5.3 EOOS Case 2 Analysis Results - 15,000 MWd/MTU ..................... 5-11 5.4 EOOS Case 2 Analysis Results - EOC ...................................................................... 5-13 5.5 1 TCV Stuck Closed Analysis Results - 15,000 MWd/MTU ........................................ 5-15 5.6 1 TCV Stuck Closed Analysis Results - EOC ............................................................. 5-18 7.1 ASME Overpressurization Analysis Results 102%P/105%F ........................................ 7-2 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page iv Figures 1.1 LaSalle County Nuclear Station Power / Flow Map ...................................................... 1-4 2.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode ................................... 2-11 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-10 and ATRIUM-9B F uel ............................................................................................................................ 2-12 3.1 EOC Load Rejection No Bypass at 100/105 -TSSS Key Parameters ........................ 3-18 3.2 EOC Load Rejection No Bypass at 100/105 - TSSS Vessel Water Level ................... 3-19 3.3 EOC Load Rejection No Bypass at 100/105 -TSSS Dome Pressure ........................ 3-20 3.4 EOC Feedwater Controller Failure at 100/105- TSSS Key Parameters ..................... 3-21 3.5 EOC Feedwater Controller Failure at 100/105 - TSSS Vessel Water Level ........................................................................................................................... 3-22 3.6 EOC Feedwater Controller Failure at 100/105 -TSSS Dome Pressure ..................... 3-23 3.7 Radial Power Distribution for SLMCPR Determination ................................................ 3-24 3.8 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors AlO-4039B 15GV75 With Channel Bow (Assembly Exposure of 1000 MWd/MTU) ....................... 3-25 3.9 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors A10-4037B 16GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU) ......................... 3-26 3.10 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times ............................................................... 3-27 3.11 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times ............................................................... 3-28 3.12 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times ............................................................. 3-29 3.13 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times ............................................................. 3-30 3.14 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-1 0 Fuel - NSS Insertion Times ............................................................... 3-31 3.15 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times ............................................................... 3-32 3.16 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times ............................................................. 3-33 3.17 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times ............................................................. 3-34 3.18 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times .............................................. 3-35 Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page v 4

3.19 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times .............................................. 3-36 3.20 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRILUM-10 Fuel - TSSS Insertion Times ............................................ 3-37 3.21 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times ............................................ 3-38 3.22 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times .............................................. 3-39 3.23 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times .............................................. 3-40 3.24 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-1 0 Fuel - TSSS Insertion Times ............................................ 3-41 3.25 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times ............................................ 3-42 5.1 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-IO Fuel - NSS Insertion Times ..................................................... 5-21 5.2 BOC to 15,000 MWd/MTU EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times .............................................. 5-22 5.3 BOC to 15,000 MWd/MTU EOOS Case :1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times .................................................... 5-23 5.4 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times .............................................. 5-24 5.5 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-1 0 Fuel - TSSS Insertion Times ................................................... 5-25 5.6 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel- TSSS Insertion Times ............................................ 5-26 5.7 BOC to 15,000 MWdIMTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times ................................................... 5-27 5.8 BOC to 15,000 MWd/MTU EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS' Insertion Times ............................................ 5-28 5.9 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-A0 Fuel - NSS Insertion Times ..................................................... 5-29 5.10 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times .............................................. 5-30 5.11 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times ................................................... 5-31 5.12 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times .............................................. 5-32 Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page vi 5.13 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel- TSSS Insertion Times ................................................... 5-33 5.14 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times ............................................ 5-34 5.15 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times ................................................... 5-35 5.16 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times ............................................ 5-36 5.17 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times ..................................................... 5-37 5.18 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times .............................................. 5-38 5.19 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times .................................................... 5-39 5.20 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times .............................................. 5-40 5.21 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel- TSSS Insertion Times ................................................... 5-41 5.22 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times ............................................ 5-42 5.23 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times ................................................... 5-43 5.24 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times ............................................ 5-44 5.25 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times ..................................................... 5-45 5.26 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR 5-46 Multipliers for ATRIUM-10 Fuel - NSS Insertion Times ........................................

5.27 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR 5-47 Limits for ATRIUM-9B Fuel - NSS Insertion Times ....................................................

5.28 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR 5-48 Multipliers for ATRIUM-9B Fuel - NSS Insertion Times ........................................

5.29 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR 5-49 Limits for ATRIUM-10 Fuel - TSSS Insertion Times ...................................................

5.30 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR 5-50 Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times ............................................

5.31 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times ................................................... 5-51 5.32 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel- TSSS Insertion Times ............................................ 5-52 Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page vii 5.33 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times ................. 5-53 5.34 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times ................. 5-54 5.35 BOC to 15,000 MWd/MTU I TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Tim es ......................................................................................................................... 5-55 5.36 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion T imes ......................................................................................................................... 5-56 5.37 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times ................. 5-57 5.38 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times ................. 5-58 5.39 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel- TSSS Insertion T im es ......................................................................................................................... 5-59 5.40 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion T im es ........................................................................................................................ 5-60 Overpressurization Event at 102/105 - MSIV Closure Key Parameters .......................... 7-3 7.1 Overpressurization Event at 102/105 - MSIV Closure Vessel Water Level ..................... 7-4 7.2 7.3 Overpressurization Event at 102/105 - MSIV Closure Lower-Plenum P ressure ...................................................................................................................... 7-5 Overpressurization Event at 102/105 - MSIV Closure Dome Pressure .......................... 7-6 7.4 7.5 Overpressurization Event at 102/105 - MSIV Closure Safety/Relief Valve Flow R ates .................................................................................................................. 7-7 Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe viii r*

ri'dlL II lranom

FWCF feedwater controller failure HFR heat flux ratio ICF increased core flow LI010 LaSalle Unit 1 Cycle 10 LHGR linear heat generation rate LHGRFACf flow-dependent linear heat generation rate factors LHGRFACp power-dependent linear heat generation rate factors LHGROL linear heat generation rate operating limit LOFH loss of feedwater heating LPRM local power range monitor LRNB generator load rejection with no bypass MAPFACf flow-dependent maximum average planar linear heat generation rate multiplier MAPFACp power-dependent maximum average planar linear heat generation rate multiplier MCPR minimum critical power ratio MCPRf flow-dependent minimum critical power ratio MCPRp power-dependent minimum critical power ratio MELLLA maximum extended load line limit analysis MFC manual flow control MSIV main steam isolation valve nominal scram speed NSS NRC Nuclear Regulatory Commission, U.S.

PAPT protection against power transient RPT recirculation pump trip Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Page ix Nomenclature (Continued)

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

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 1-1 1.0 Introduction This report presents results of the plant transient analyses performed by Framatome ANP, Inc.

(FRA-ANP) as part of the reload safety analyses to support LaSalle Unit 1 Cycle 10 (LICO) operation. The Cycle 10 core contains 346 fresh ATRIUMw-10* assemblies, 372 previously loaded ATRIUM-9B assemblies, and 46 previously loaded GE9 assemblies (all in peripheral locations). Those portions of the reload safety analysis for which Exelon has responsibility are presented elsewhere. The scope of the transient analyses performed by FRA-ANP is presented in Reference 1.

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

Parameters for the transient analyses are documented in Reference 8.

The Cycle 10 transient analysis consists of the calculation of the limiting transients identified in Reference 9 to support base case operationt for the power/flow map presented in Figure 1.1.

Results are also presented to support operation in the extended operating domain (EOD) and equipment out-of-service (EOOS) scenarios identified in Table 1.1. The analysis results are used to establish operating limits to protect against fuel failures. Minimum critical power ratio (MCPR) limits are established to protect the fuel from overheating during normal operation and anticipated operational occurrences (AOOs). Power-dependent MCPR (MCPRp) limits are required in order to provide the necessary protection during operation at reduced power. Flow dependent MCPR (MCPRf) limits provide protection against fuel failures during flow excursions initiated at reduced flow. Cycle 10 power- and flow-dependent MCPR limits are presented to protect both ATRIUM-10 and ATRIUM-9B fuel. Since the GE9 fuel is in low power peripheral locations for LICI0, the ATRIUM-9B MCPR limits can be used for the GE9 fuel. This conclusion is based on a MCPR evaluation of these assemblies in the design-basis step through.

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

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Plant Transient Analysis Page 1-2 Protection against violating the linear heat generation rate (LHGR) limits at rated and off-rated conditions is provided through the application of power- and flow-dependent LHGR factors directly to (LHGRFACp and LHGRFACf, respectively). These factors or multipliers are applied against the steady-state LHGR limit to ensure that the LHGR does not exceed the protection power transient (PAPT) limit during postulated AQOs. Cycle 10 power- and flow-dependent the GE9 LHGR multipliers are presented for ATRIUM-10 and ATRIUM-9B fuel. In addition, MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

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

report The results of the plant transient analyses are used in a subsequent reload analysis limits and (Reference 15) along with core and accident analysis results to justify plant operating set points.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 1-3 Plant Transient Analysis Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions Increased core flow (ICF)

Maximum extended load line limit analysis (MELLLA)

Coastdown - Currently not supported for LIC10 Final feedwater temperature reduction (FFTR) - Currently not supported for LICIO Combined FFTR/coastdown - Currently not supported for LIC10 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) of TIP Up to 2 TIP machines out-of-service or the equivalent number 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 operating domain. Each EOOS conditions are supported for EOD conditions as well as the standard EOOS condition combined with I SRVOOS, up to 2 TIPOOSLPRMs (or the equivalent number of channels),

up to 50% of the out-of-service is supported.

1 stuck closed turbine control valve and/or Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 1-4 110 100 90 80 70 60 0

(D 50 0..

40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 Percent of Rated Flow Figure 1.1 LaSalle County Nuclear Station Power I Flow Map Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 2-1 Plant Transient Analysis 2.0 Summary The determination of the thermal limits (MCPR limits and LHGRFAC multipliers) for LaSalle in Unit 1 Cycle 10 is based on analyses of the limiting operational transients identified (LRNB),

Reference 9. The transients evaluated are the generator load rejection with no bypass error (CRWE) feedwater controller failure to maximum demand (FWCF), control rod withdrawal include and loss of feedwater heating (LOFH). Thermal limits identified for Cycle 10 operation established so both MCPR limits and LHGRFAC multipliers. The MCPR operating limits are boiling transition that less than 0.1% of the fuel rods in the core are expected to experience a two-loop during an AOO initiated from rated or off-rated conditions and are based on support a two-loop operation MCPR safety limit of 1.11. Even so, the results of the analysis limit of 1.10 for all operation MCPR safety limit of 1.09 and a single-loop operation MCPR safety the LHGR limits at fuel types in the Cycle 10 core. LHGRFAC multipliers are applied directly to of the reduced power and/or flow conditions to protect against fuel melting and overstraining to support cladding during an AOO. Exposure dependent operating limits are established MWd/MTU to operation from beginning of cycle (BOC) to 15,000 MWd/MTU and from 15,000 MWd/MTU.

EOC. EOC for LaSalle Unit I Cycle 10 is defined as a core exposure of 31,495.1 scenarios Operating limits are established to support both base case operation and the EOOS presented in Table 1.1. Operating limits are also established for the EOD and combined EOD/EOOS conditions presented in Table 1.1.

in Base case MCPRP limits and LHGRFACp multipliers are based on results presented operating limits for Section 3.0. Results presented in Sections 4.0-6.0 are used to establish the operation in the EOD, EOOS, and combined EOD/EOOS scenarios.

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

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

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

a MCPRf limits for both ATRIUM-10 and ATRIUM-9B that protect against fuel failures during flow slow flow excursion event in manual flow control are presented in Figure 2.1. Automatic and control is not supported for LlC10. The MCPRf limits presented are applicable for all EOD EOOS conditions presented in Table 1.1.

The Cycle 10 LHGRFACf multipliers for ATRIUM-10 and ATRIUM-9B fuel are presented in 1.1.

Figure 2.2 and are applicable in all the EOD and EOOS scenarios presented in Table The power excursion experienced by low-power peripheral fuel assemblies during an anticipated operational occurrence is very mild compared to centrally orificed fuel assemblies.

Since GE9 fuel will only be in peripheral locations, the MCPR safety limit will not be challenged by the GE9 fuel assemblies and using the ATRIUM-9B MCPR limits for the GE9 fuel provides the necessary protection. In addition, the GE9 MAPFACf and MAPFACp multipliers used in in Cycle 9 remain applicable. This conclusion is based on an evaluation of these assemblies the design-basis step-through.

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

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Paae 2-3 I

RIamIL I I dli nlIClL i' I 0 Table 2.1 Base Case and EOOS MCPRp Limits and LHGRFACP Multipliers for NSS Insertion Times BOC to 15,000 MWdlMTU*,t EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.70 0.75 2.70 0.77

  • 25 2.20 0.75 2.20 0.77 Base case 25 2.07 0.75 1.95 0.77 operationl 60 1.52 1.00 1.50 1.00 100 1.43 1.00 1.42 1.00 0 2.86 0.66 2.70 0.69 EOOS 25 2.36 0.66 2.20 0.69 Case 1 25 2.36 0.66 2.15 0.69 1.59 0.94 1.58 0.90 (FHOOS t OR 60 TBVOOS) 80 -. 0.94 - 0.90 100 1.47 0.95 1.45 0.90 0 2.86 0.65 2.70 0.67 EOOS Case 2ý 25 2.36 0.65 2.20 0.67 25 2.36 0.65 2.15 0.67 (Any combination of 80 1.81 0.88 1.86 0.79 TCV slow closure, 80 1.74 0.88 1.67 0.79 no RPT OR FHOOS) 100 1.54 0.89 1.52 0.79 0 2.86 0.66 2.70 0.69 25 2.36 0.66 2.20 0.69 TBVOOS 25 2.36 0.66 2.15 0.69 with 1 stuck 60 1.59 0.77 1.58 0.77 closed TCV 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 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

With or without 1 stuck closed TCV.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 2-4 iPIE nt I ransleni Ana*ysis Table 2.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU*.t (Continued)

ATRIUM-10 Fuel ATRIUM-9B Fuel EQOS Power Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0.7 211 U.-i,,

0 2.71 0.75 2.71 U.77 2.21 2.21 25 0.75 0.77 Single-loop 2.08 1.96 operation* 25 0.75 0.77 1.53 1.51 (SLO) 60 1.00 1.00 1.44 1.00 1.43 1.00 100 I~~ -I i - I 0 2.87 0.66 2.71 0.69 0.66 2.21 0.69 25 2.37 SLO with EOOS 0.69 2.37 0.66 2.16 Case I 25 0.94 1.59 0.90 60 1.60 (FHOOS* OR 0.94 0.90 TBVOOS) 80 0.95 1.46 0.90 100 1.48 0.65 2.71 0.67 0 2.87 0.65 2.21 0.67 SLO with EOOS 25 2.37 Case 2ý 0.65 2.16 0.67 25 2.37 0.88 1.87 0.79 (Any combination of 80 1.82 0.88 1.68 0.79 TCV slow closure, 80 1.75 no RPT OR FHOOS) 0.89 1.53 0.79 100 1.55 I 0.69 0 2.87 0.66 2.71 0.69 2.37 0.66 2.21 25 0.69 SLO with 25 2.37 0.66 2.16 0.69 TBVOOS 0.77 1.59 AND 1 stuck 60 1.60 0.77 closed TCV 80 0.77 0.77 1.48 0.83 1.46 0.80 100 I ___________________ L_________________ 4 (or the equivalent

  • Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS for conditions with number of TIP channels), up to a 20°F reduction in feedwater temperature (except regions of and MELLLA FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, the power/flow map.

and MAPFACp SGE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf multipliers used in Cycle 9 remain applicable.

With or without I stuck closed TCV.

Framatome ANP, Inc

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 2-5 Plant Transient Analysis Table 2.2 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU*. I ATRIUM-10 Fuel ATRIUM-9B Fuel EOOS Power MCPRp LHGRFACp

(% rated) MCPRp LHGRFACp Condition 2.70 0.76 0 2.70 0.74 2.20 0.76 25 2.20 0.74 Base 2.15 1.96 0.76 25 0.74 case 1.54 1.00 operation t 60 1.55 1.00 1.46 1.44 1.00 100 1.00 2.95 2.70 0.69 0 0.64 2.20 0.69 25 2.45 0.64 EOOS 2.19 0.69 Case 1 25 2.45 0.64 1.62 1.62 0.89 60 0.94 (FHOOSt OR - 0.91 80 0.94 TBVOOS) 0.95 1.48 0.92 100 1.51 2.95 0.64 2.70 0.67 0

2.45 0.64 2.20 0.67 EOOS 25 Case 2ý 2.45 0.64 2.19 0.67 25 0.87 1.86 0.76 80 1.82 (Any combination of 1.73 0.76 TCV slow closure, 80 1.74 0.87 no RPT OR FHOOS) 1.59 0.87 1.59 0.76 100 2.95 0.64 2.70 0.69 0

0.64 2.20 0.69 25 2.45 2.45 0.64 2.19 0.69 25 TBVOOS 0.77 - 0.77 40 with 1 stuck 0.77 1.62 0.77 closed TCV 60 1.62 0.77 - 0.77 80 1.51 0.83 1.48 0.80 100 up to 2 TIPOOS (or the equivalent

  • Limits support operation with any combination of I SRVOOS, temperature (except for conditions with number of TIP channels), up to a 20OF reduction in feedwater in the standard, ICF, and MELLLA regions of FHOOS), and up to 50% of the LPRMs out of service the power/flow map.

and the GE9 MAPFACf and MAPFACp SGE9 fuel assemblies will use the ATRIUM-9B MCPR limits multipliers used in Cycle 9 remain applicable.

SWith or without I stuck closed TCV.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 2-6 l-mant I ranslentmr-ia~lysil '=

Table 2.2 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times BOC to 15,000 MWdlMTU*'t (Continued)

EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.71 0.74 2.71 0.76 2.21 0.74 2.21 0.76 Single-loop 25 operationt 25 2.16 0.74 1.97 0.76 (SLO) 60 1.56 1.00 1.55 1.00 100 1.47 1.00 1.45 1.00 0 2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 SLO with EOOS Case 1 25 2.46 0.64 2.20 0.69 1.63 0.94 1.63 0.89 (FHOOSt OR 60 80 - 0.94 -- 0.91 TBVOOS) 100 1.52 0.95 1.49 0.92 0 2.96 0.64 2.71 0.67 SLO with EOOS 25 2.46 0.64 2.21 0.67 Case 2t 25 2.46 0.64 2.20 0.67 (Any combination of 80 1.83 0.87 1.87 0.76 TCV slow closure, 80 1.75 0.87 1.74 0.76 no RPT OR FHOOS) 100 1.60 0.87 1.60 0.76 0 2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 SLO with 25 2.46 0.64 2.20 0.69 TBVOOS 40 -- 0.77 -- 0.77 AND 1 stuck 60 1.63 0.77 1.63 0.77 closed TCV 80 - 0.77 -- 0.77 100 1.52 0.83 1.49 0.80

  • Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent with conditions number of TIP channels), up to a 20°F reduction in feedwater temperature (except for in the standard, ICF, and MELLLA regions of FHOOS), and up to 50% of the LPRMs out of service 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-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 2-7 riani I rIdlienI L t%"U IOY0 Table 2.3 Base Case and EOOS MCPRP Limits and LHGRFAC. Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC*'t EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.70 0.75 2.70 0.76 25 2.20 0.75 2.20 0.76 Base case 25 2.07 0.75 1.95 0.76 operationt 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 1.59 0.94 1.58 0.90 (FHOOSt OR 60 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 25 2.36 0.65 2.20 0.67 Case 21 25 2.36 0.65 2.15 0.67 (Any combination of 80 1.81 0.84 1.86 0.79 TCV slow closure, 80 1.74 0.84 1.67 0.79 no RPT OR FHOOS) 100 1.59 0.84 1.58 00 2.86 0.65 2.70 0.79 0 2.86 0.65 2.70 0.69 25 2.36 0.65 2.20 0.69 TBVOOS 25 2.36 0.65 2.15 0.69 with 1 stuck 0.77 60 1.59 0.77 1.58 closed TCV 80 - 0.77 - 0.77 100 1.47 0.83 1.45 0.80

  • Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent with number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions of service in the standard, ICF, and MELLLA regions of FHOOS), and up to 50% of the LPRMs out 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-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 2-8 Plant Transient Analysis Table 2.3 Base Case and EOOS MCPRp Limits and LHGRFACB Multipliers for NSS Insertion Times 15,000 MWdlMTU to EOC*'t (Continued)

ATRIUM-10 Fuel ATRIUM-9B Fuel EQOS Power Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.71 0.75 2.71 0.76 Single-loop 25 2.21 0.75 2.21 0.76 operationt 25 2.08 0.75 1.96 0.76 60 1.53 1.00 1.51 1.00 (SLO) 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 1.60 0.94 1.59 0.90 (FHOOSt OR 60 80 -- 0.94 - 0.90 TBVOOS) 100 1.48 0.95 1.46 0.90 0 2.87 0.65 2.71 0.67 SLO with EOOS 25 2.37 0.65 2.21 0.67 Case 2 ý 25 2.37 0.65 2.16 0.67 (Any combination of 80 1.82 0.84 1.87 0.79 TCV slow closure, 80 1.75 0.84 1.68 0.79 no RPT OR FHOOS) 100 1.60 0.84 1.59 0.79 0 2.87 0.65 2.71 0.69 SLO with 25 2.37 0.65 2.21 0.69 25 2.37 0.65 2.16 0.69 TBVOOS AND 1 stuck 60 1.60 0.77 1.59 0.77 closed TCV 80 - 0.77 - 0.77 100 1.48 0.83 1.46 0.80 the equivalent

  • Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or for conditions with number of TIP channels), up to a 20OF reduction in feedwater temperature (except and MELLLA regions of FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, the power/flow map.

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

With or without 1 stuck closed TCV.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 2-9

" ans en " z mant "ld 't # A0 l~

nl~ oic~

Table 2.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC* t EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.70 0.74 2.70 0.76 25 2.20 0.74 2.20 0.76 Base case 25 2.15 0.74 1.96 0.76 operationt 60 1.55 1.00 1.54 1.00 100 1.50 1.00 1.44 1.00 0 2.95 0.64 2.70 0.69 EOOS 25 2.45 0.64 2.20 0.69 Case 1 25 2.45 0.64 2.19 0.69 60 1.62 0.94 1.62 0.89 (FHOOSt OR TBVOOS) 80 -- 0.94 -- 0.91 100 1.51 0.95 1.48 0.92 0 2.95 0.64 2.70 0.67 EOOS 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, 80 1.74 0.82 1.73 0.76 no RPT OR FHOOS) 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 -- 0.77 100 1.51 0.83 1.48 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 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 MAPFAC, multipliers used in Cycle 9 remain applicable.

SWith or without 1 stuck closed TCV.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 2-10 rPlant I ais~~~l en "al 12O Table 2.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWdIMTU to EOC*'.

(Continued)

EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition (% rated) MCPRp LHGRFACp MCPRp LHGRFACp 0 2.71 0.74 2.71 0.76 2.21 0.74 2.21 0.76 Single-loop 25 operationt 25 2.16 0.74 1.97 0.76 (SLO) 60 1.56 1.00 1.55 1.00 100 1.51 1.00 1.45 1.00 0 2.96 0.64 2.71 0.69 SLO with EOOS 25 2.46 0.64 2.21 0.69 Case 1 25 2.46 0.64 2.20 0.69 (FHOOS' 60 1.63 0.94 1.63 0.89 OR TBVOOS) 80 - 0.94 -- 0.91 100 1.52 0.95 1.49 0.92 0 2.96 0.64 2.71 0.67 SLO with EOOS 25 2.46 0.64 2.21 0.67 Case 2:

25 2.46 0.64 2.20 0.67 (Any combination of 80 1.83 0.82 1.87 0.76 TCV slow closure, 80 1.75 0.82 1.74 0.76 no RPT OR FHOOS) 100 1.65 0.82 1.66 0.76 100 2.96 0.64 2.6 0.76 0 2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 SLO with 25 2.46 0.64 2.20 0.69 TBVOOS 40 --- 0.77 0.77 AND I stuck 60 1.63 0.77 1.63 0.77 closed TCV 80 - 0.77 - 0.77 100 1.52 0.83 1.49 0.80

  • Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent with number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions and MELLLA regions of FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, 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-2689 Revision 0 LaSalle Unit I Cycle 10 Page 2-11

'Plant Transient Analysis U

110 10 20 30 40 50 60 0

Flow (% rated)

Flow MCPRI MCPRf

(% of rated) ATRIUM-10 ATRIUM-9B*

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

  • GE9 fuel assemblies will use the ATRIUM-9B MCPR limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 2-12 Plant Transient Analysis U.

C, z

60 70 80 90 100 110 0 10 20 30 40 50 Flow(% red)

Flow

(% rated) LHGRFACf*

0 0.72 30 0.72 68 1.00 105 1.00 Figure 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-10 and ATRIUM-9B Fuel GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 3-1 Plant Transient Analysis 3.0 Transient Analysis for Thermal Margin - Base Case Operation This section describes the analyses performed to determine the power- and flow-dependent 10.

MCPR and LHGR operating limits for base case operation at LaSalle Unit I Cycle and COTRANSA2 (Reference 4), XCOBRA-T (Reference 11), XCOBRA (Reference 7),

limits CASMO-3G/MICROBURN-B (Reference 3) are the major codes used in the thermal

7) and analyses as described in FRA-ANP's THERMEX methodology report (Reference simulation neutronics methodology report (Reference 3). COTRANSA2 is a system transient of code, which includes an axial one-dimensional neutronics model that captures the effects thermal axial power shifts associated with the system transients. XCOBRA-T is a transient XCOBRA hydraulics code used in the analysis of thermal margins for the limiting fuel assembly.
6) is used to is used in steady-state analyses. The ANFB critical power correlation (Reference power evaluate the thermal margin of the ATRIUM-9B fuel assemblies and the SPCB critical gap correlation (Reference 12) is used for the ATRIUM-10 fuel. Fuel pellet-to-cladding LaSalle Unit 1 conductance values are based on RODEX2 (Reference 13) calculations for the Cycle 10 core configuration.

3.1 System Transients support LIC10 System transient calculations have been performed to establish thermal limits to on a operation. Reference 9 identifies the potential limiting events that need to be evaluated the LRNB, cycle-specific basis. The potentially limiting transients evaluated for Cycle 10 include of FWCF, CRWE, and LOFH events. Other transient events are bound by the consequences one of the limiting transients.

3.1 for the 100%

Reactor plant parameters for the system transient analyses are shown in Table are presented in power/100% flow conditions. Additional plant parameters used in the analyses and LHGR Reference 8. Analyses have been performed to determine power-dependent MCPR 1.1. At limits that protect operation throughout the power/flow domain depicted in Figure stop valve LaSalle, direct scram and recirculation pump high- to low-speed transfer on turbine than 25% of (TSV) and turbine control valve (TCV) position are bypassed at power levels less at power rated. Reference 14 indicates that MCPR and LHGR limits need to be monitored to establish base levels greater than or equal to 25% of rated. As a result, all analyses used and RPT case MCPRp limits and LHGRFACp multipliers are performed with both direct scram operable for power levels at or above 25% of rated.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-2 The limiting exposure for rated power pressurization transients is typically at end of full power (EOFP) when the control rods are fully withdrawn. To provide additional margin to the operating limits earlier in the cycle, analyses were also performed to establish operating limits at 15,000 MWd/MTU. Off-rated power analyses were performed at cycle exposures prior to EOC to ensure that the operating limits provide the necessary protection.

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

The term, recirculation pump trip (RPT), is used synonymously with recirculation pump high- to low-speed transfer as it applies to pressurization transients. During the high- to low-speed transfer, the recirculation pumps trip off line and coast. When they reach the low-speed setting, the pumps reengage at the low speed. The time it takes for the pumps to coast to the low speed condition is much longer than the duration of the pressurization transients. Therefore, a recirculation pump trip has the same effect on pressurization transients as a recirculation pump high- to low-speed transfer.

Reductions in feedwater temperature of less than 20°F from the nominal feedwater temperature are considered base case operation, not an EOOS condition. The reduced feedwater temperature is limiting for FWCF transients. As a result, the base case FWCF results are based on a 20°F reduction in feedwater temperature.

The results of the system pressurization transients are sensitive to the scram speed used in the calculations. To take advantage of average scram speeds faster than those associated with the Technical Specifications surveillance times, scram speed-dependent MCPRp limits and LHGRFAC, multipliers are provided. The NSS insertion times and the average scram speeds associated with the Technical Specifications surveillance times (identified as TSSS times) used in the analyses reported are presented in Reference 8 and reproduced in Table 3.2. The NSS MCPRp limits and LHGRFACp multipliers can only be applied if the scram speed surveillance tests meet the NSS insertion times. System transient analyses were performed to establish MCPRp limits and LHGRFACp multipliers for base case operation for both NSS and TSSS insertion times.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-3 3.1.1 Load Reiection No Bypass The load rejection causes a fast closure of the turbine control valve. The resulting compression wave travels through the steam lines into the vessel and creates a rapid pressurization. The increase in pressure causes a decrease in core voids, which in turn causes a rapid increase in power. The fast closure of the turbine control valve also causes a reactor scram and a recirculation pump high- to low-speed transfer which helps mitigate the pressurization effects.

Turbine bypass system operation, which also mitigates the consequences of the event, is not credited. The excursion of the core power due to the void collapse is terminated primarily by the reactor scram and revoiding of the core. The analysis assumed single-element feedwater level control; however, three-element feedwater level control will have an insignificant impact on thermal limit or pressure results. For manual feedwater level control, the feedwater control system response is slower than the pressurization event. As a result, using manual feedwater level control will also have an insignificant impact on thermal limit or pressure results.

The generator load rejection without turbine bypass system (LRNB) is a more limiting transient than the turbine trip no bypass (TTNB) transieni. The initial position of the TCV is such that it closes faster than the turbine stop valve. This more than makes up for any differences in the scram signal delays between the two events.

LRNB analyses were performed for several power/flow conditions to support generation of the thermal limits. Tables 3.3 and 3.4 present the LRNB transient results for both TSSS and NSS insertion times for Cycle 10. For illustration, Figures 3.1-3.3 are presented to show the responses of various reactor and plant parameters during the LRNB event initiated at 100% of rated power and 105% of rated core flow with TSSS insertion times.

3.1.2 Feedwater Controller Failure The increase in feedwater flow due to a failure of the feedwater control system to maximum demand results in an increase in the water level and a decrease in the coolant temperature at the core inlet. The increase in core inlet subcooling causes an increase in core power. As the feedwater flow continues at maximum demand, the water level continues to rise and eventually reaches the high water level trip set point. The initial water level is conservatively assumed to be at the lower level operating range at 30 inches above instrument zero to delay the high level trip and maximize the core inlet subcooling that results from the FWCF. The high water level trip causes the turbine stop valves to close in order to prevent damage to the turbine from Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-4 excessive liquid inventory in the steam line. The valve closures create a compression wave that travels to the core causing a void collapse and subsequent rapid power excursion. The closure of the turbine valves initiates a reactor scram and a recirculation pump high- to low-speed transfer. In addition, the turbine bypass valves are assumed operable and provide some pressure relief. The core power excursion is mitigated in part by the pressure relief, but the primary mechanisms for termination of the event are reactor scram and revoiding of the core.

FWCF analyses were performed for several power/flow conditions to support generation of the thermal limits. Tables 3.5 and 3.6 present the base case FWCF transient results for both TSSS and NSS insertion times for Cycle 10. For illustration, Figures 3.4-3.6 are presented to show the responses of various reactor and plant parameters during the FWCF event initiated at 100%

of rated power and 105% of rated core flow with TSSS insertion times.

3.1.3 Loss of Feedwater Heatinq During the loss of feedwater heating (LOFH) event, there is an assumed 145°F decrease in the feedwater temperature. The result is an increase in core inlet subcooling, which collapses voids thereby increasing the core power and shifting the axial power distribution toward the bottom of the core. As a result of the axial power shift and increased core power, voids begin to build up at the bottom of the core, acting as negative feedback to the void collapse process. The negative feedback moderates the core power increase. The MICROBURN-B code is used to determine the change in MCPR and LHGR during the event. Analyses were performed for several cycle exposures to ensure that appropriate limits are set. Although there is a substantial increase in core thermal power during the event, the increase in steam flow is much less because a large part of the added power is used to overcome the increase in inlet subcooling.

The increase in steam flow is accommodated by the pressure control system via the TCVs or the turbine bypass valves so no pressurization occurs. The LOFH results are presented in Table 3.7. The PAPT LHGR limit was not exceeded in any of the analyses. PAPT LHGR limits are presented in References 21 and 22.

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

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

3.2 MCPR Safety Limit ratio at which the The MCPR safety limit is defined as the minimum value of the critical power 0.1%

fuel can be operated, with the expected number of rods in boiling transition not exceeding 1 Cycle 10 of the fuel rods in the core. The MCPR safety limit for all fuel in the LaSalle Unit of channel core was determined using the methodology described in Reference 5. The effects channel bow is bow on core limits are determined using a statistical procedure. The mean data.

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

the core limits is channel bow effects on the local peaking factors are determined, the impact on effects of channel determined in the MCPR safety limit analysis. Further discussion of how the and bow are accounted for is presented in Reference 5. The main input parameters uncertainties used in the safety limit analysis are listed in Table 3.8. The radial power of the total uncertainty includes the effects of up to 2 TIPOOS or the equivalent number (42%

the LPRMs out number of channels) of TIP channels (100% available at startup), up to 50% of 16 and of-service, and an LPRM calibration interval of 2500 EFPH as discussed in References local

19. The channel bow local peaking uncertainty is a function of the nominal and bowed peaking factors and the standard deviation of the measured bow data.

bow and relies on The determination of the safety limit explicitly includes the effects of channel the following assumptions:

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

fuel

  • The channel exposure at discharge will not exceed 50,000 MWd/MTU based on the bundle average exposure.
  • The Cycle 10 core contains all CarTech-supplied channels.

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

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

EMF-2689 Revision 0 LaSalle Unit I Cycle 10

'Plant Transient Analysis Page 3-6 exposure of 500 MWd/MTU is shown in Figure 3.7. Eight fuel types were represented in the LaSalle Unit 1 Cycle 10 safety limit analysis: two. ATRIUM-10 fuel types loaded in Cycle 10 9

(Al 0-4039B-1 5GV75 and Al0-4037B-16GV75); four ATRIUM-9B fuel types loaded in Cycle (SPCA9-384B-1 I GZ-80M, SPCA9-393B-1 6GZ-1 00M, SPCA9-396B-1 2GZB-1 00M, and SPCA9-396B-12GZC-IOOM); and two GE9 fuel types loaded in Cycle 8 (GE9B-P8CWB343 12GZ-80M-150 and GE9B-P8CWB342-1OGZ-80M-150).

The local power peaking factors, including the effects of channel bow, at 70% void and in assembly exposures consistent with a Cycle 10 exposure of 500 MWd/MTU are presented data Figures 3.8 and 3.9 for the Cycle 10 ATRIUM-10 fuel. The bowed local peaking factor used in the MCPR safety limit analysis for fuel type Al 0-4039B-1 5GV75 is at an assembly an average exposure of 1000 MWd/MTU. The data for fuel type Al0-4037B-16GV75 is at assembly average exposure of 500 MWd/MTU.

single The results of the analysis support a two-loop operation MCPR safety limit of 1.09 and a the loop operation MCPR safety limit of 1.10 for all fuel types in the Cycle 10 core. However, and TLO and SLO MCPR safety limits used to establish the MCPR operating limits are 1.11 1.12 respectively, since they are the values currently in the Technical Specifications. These safety results are applicable for all EOD and EOOS conditions presented in Table 1.1. A MCPR of limit of 1.10 is needed to support startup with uncalibrated LPRMs for an exposure range BOC to 500 MWd/MTU in both TLO and SLO.

3.3 Power-DependentMCPR and LHGR Limits Figures 3.10 and 3.11 present the base case operation NSS ATRIUM-10 and ATRIUM-9B 3.12 and MCPRp limits for Cycle 10 for the BOC to 15,000 MWd/MTU exposure range. Figures with TSSS 3.13 present the ATRIUM-10 and ATRIUM-9B MCPRp limits for base case operation to insertion times for the BOC to 15,000 MWd/MTU exposure range. The 15,000 MWd/MTU and 3.15 for EOC MCPRp for ATRIUM-10 and ATRIUM-9B fuel are presented in Figures 3.14 are based NSS insertion times and Figures 3.16 and 3.17 for TSSS insertion times. The limits and a MCPR on the ACPR results from the limiting system transient analyses discussed above safety limit of 1.11.

The pressurization transient analyses provide the necessary information to determine fuel to appropriate multipliers on the fuel design LHGR limit for ATRIUM-10 and ATRIUM-9B the steady-state support off-rated power operation. Application of the LHGRFACp multipliers to Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Plant Transient Analysis Page 3-7 LHGR limit ensures that the LHGR during AQOs initiated at reduced power does not exceed the PAPT limits. The method used to calculate the LHGRFACp multipliers is presented in Appendix A. The results of the LRNB and FWCF analyses discussed above were used to determine the base case LHGRFACp multipliers. The base case ATRIUM-10 and ATRIUM-9B and 3.19 for LHGRFACP multipliers for BOC to 15,000 MWd/MTU are presented in Figures 3.18 NSS insertion times and Figures 3.20 and 3.21 for TSSS insertion times. The 15,000 presented in MWd/MTU to EOC LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel are Figures 3.22 and 3.23 for NSS insertion times and Figures 3.24 and 3.25 for TSSS insertion times.

In order to support operation of POWERPLEX-Il CMSS* below 25% core thermal power, representative limits are provided and have no impact on licensing since there is no requirement to monitor limits below 25% power.

3.4 Flow-DependentMCPR and LHGR Limits core Flow-dependent MCPR and LHGR limits are established to support operation at off-rated fuel flow conditions. The limits are based on the CPR and heat flux changes experienced by the during slow flow excursions. The slow flow excursion event assumes a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow potential physically attainable by the equipment. An uncontrolled increase in flow creates the path for a significant increase in core power and heat flux. A conservatively steep flow run-up was determined starting at a low-power/low-flow state point of 56.2%P/30%F increasing to the high-power/high-flow state point of 124.2%P/105%F.

MCPRf limits are determined for the manual flow control (MFC) mode of operation for both ATRIUM-10 and ATRIUM-9B fuel. XCOBRA is used to calculate the change in critical power the ratio during a two-loop flow run-up to the maximum flow rate. The MCPRf limit is set so that the MCPR increase in core power resulting from the maximum increase in core flow is such that rates to safety limit of 1.11 is not violated. Calculations were performed for several initial flow safety determine the corresponding MCPR values that put the limiting assembly on the MCPR limit at the high-flow condition at the end of the flow excursion.

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

Framatorne ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 3-8

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

to high The MCPRf limits are valid for all exposure conditions during Cycle 10. Since a low-of speed pump upshift is required to attain high-flow rates, for initial core flows less than 30%

rated, the limit is conservatively set equal to the 30% flow value.

core FRA-ANP has performed LHGRFACf analyses with the CASMO-3G/MICROBURN-B along the simulator codes. The analysis assumes that the recirculation flow increases slowly of flow limiting rod line to the maximum flow physically attainable by the equipment. A series from excursion analyses were performed at several exposures throughout the cycle starting the event.

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

3.5 Nuclear Instrument Response The impact of loading ATRIUM-10 fuel into the LaSalle core will not affect the nuclear the time instrument response. The neutron lifetime is an important parameter affecting and response of the incore detectors. The neutron lifetime is a function of the nuclear exposure.

mechanical design of the fuel assembly, the in-channel void fraction, and the fuel of 39(10.6) to The neutron lifetimes are similar for the FRA-ANP fuel types with typical values 40(10-6) seconds for the ATRIUM-9B lattices and 37(10.6) to 43(10.6) seconds for the code.

ATRIUM-10 bottom and top lattices, respectively, as calculated with the CASMO-3G ATRIUM-10 Therefore, the neutron lifetimes are essentially equivalent as the core transitions to fuel.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Paae 3-9

-A .

Plant I ransient Analysis - -9 Table 3.1 LaSalle Unit I Plant Parameters for the System Transient Analyses at Rated Power and Flow Reactor thermal power (MWt) 3489 Total core flow (Mlbm/hr) 108.5 Core active flow* 94.8 Core bypass flow* t 13.7 Core inlet enthalpy*

(Btu/Ibm) 523.9 Vessel pressures (psia)

Steam dome 1001 Core exit (upper-plenum)* 1013 Lower-plenum* 1038 Turbine pressure (psia) 957 Feedwater/steamn flow (Mlbm/hr) 15.145 Feedwater enthalpy*

(Btu/ibm) 406.6 Recirculating pump flow (per pump)

(Mlbm/hr) 15.83 Core average gap coefficient (EOC)*

(Btu/hr-ft 2 _OF) 1959

  • Calculated values.

t Includes water channel flow.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 3-10 4.

RaImdlL I IdllInIlL en "ca yIs Table 3.2 Scram Speed Insertion Times Control Rod TSSS NSS Position Time Time (notch) (sec) (sec) 48 (full-out) 0.00 0.00 48* 0.20* 0.20*

45 0.53 0.38 39 0.85 0.68 25 1.90 1.68 5 3.45 2.68 0 (full-in) 7.00 7.00

  • As indicated in Reference 8, the delay between scram signal and control rod motion is conservatively modeled. Sensitivity analyses indicate that using no delay provides slightly conservative results.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 3-11 Plant Transient Analysis Table 3.3 15,000 MWd/MTU Base Case LRNB Transient Results Peak Peak ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Power/ (% rated)

Flow ACPR LHGRFACp ACPR LHGRFACp (% rated)

TSSS Insertion Times 0.35 1.03 0.33 1.00 415 122 100/105 100/100 0.34 1.02 0.33 1.00 390 122 100/81 0.35 1.03 0.31 1.00 318 121 80/105 0.35 1.04 0.34 1.00 335 97 0.37 1.07 0.32 1.00 217 95 80/57.2 0.32 1.07 0.33 1.00 219 72 60/105 0.18 1.16 0.23 1.11 108 66 60/35.1 0.25 1.14 0:26 1.08 99 46 40/105 0.19 1.22 0.18 1.19 42 27 25/105 NSS Insertion Times 100/105 0.32 1.03 0.31 1.00 306 120 0.31 1.02 0.30 1.00 323 120 100/100 100181 0.29 1.03 0.23 1.00 308 117 0.32 1.06 0.30 1.00 284 94 80/105 0.25 1.12 0.18 1.06 169 89 80/57.2 0.30 1.08 0.30 1.00 195 70 60/105 0.09 1.23 0.10 1.20 79 61 60/35.1 0.24 1.15 0.24 1.10 94 45 40/105 0.18 1.22 0.17 1.20 41 27 25/105 Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Plant Tr~n~k~nt An~lv~i* Paqe 3-12 Pin Trnn,,cint Ana;**IL lys~isr=

Table 3.4 EOC Base Case LRNB Transient Results Peak Peak Power/ ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp (% rated) (% rated)

TSSS Insertion Times 1.00 0.33 1.00 415* 122*

100/105 0.35*

100/100 0.34 1.00 0.33 1.00 460 132 100/81 0.39 1.00 0.33 1.00 516 135 80/105 0.35* 1.02 0.34* 1.00 335* 97*

80/57.2 0.39 1.00 0.36 1.00 313 105 60/105 0.32* 1.06 0.33* 1.00 219* 72*

60/35.1 0.34 1.06 0.31 1.07 163 74 40/105 0.25* 1.14* 0.26* 1.08* 99* 46*

25/105 0.20 1.22* 0.18* 1.19* 42 28 NSS Insertion Times 100/105 0.33 1.00 0.32 1.00 435 128 100/100 0.34 1.00 0.32 1.00 439 129 100/81 0.36 1t00 0.32 1.00 513 132 80 /105 0.32* 1.03 0.30* 1.00 284* 94*

80/57.2 0.34 1.03 0.30 1.00 277 101 60 /105 0.30* 1.07 0.30* 1.00* 195* 70*

60/35.1 0.27 1.09 0.23 1.09 138 70 40/105 0.24* 1.15* 0.24* 1.10* 94* 45*

25/105 0.18* 1.22* 0.17* 1.20* 41* 27*

  • The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Pl~nf Tr~n*i~nnf AnRlv.*i. Paae 3-13 Pinnf Transient Analysis Table 3.5 15,000 MWd/MTU Base Case FWCF Transient Results Peak Peak Power/ ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp (% rated) (% rated)

TSSS Insertion Times 100/105 0.33 1.06 0.30 1.00 342 122 100/100 0.32 1.07 0.29 1.00 321 121 100/81 0.31 1.09 0.27 1.03 221 117 80/105 0.37 1.03 0.35 1.00 268 101 80/57.2 0.32 1.13 0.24 1.09 149 92 60/105 0.44 1.00 0.43 1.00 184 80 60/35.1 0.12 1.20 0.16 1.18 85 65 40/105 0.60* 0.91* 0.57 0.88 88* 57*

25/105 1.04* 0.74* 0.85 0.76 59* 44*

NSS Insertion Times 100/105 0.29 1.09 0.25 1.03 266 117 100/100 0.28 1.09 0.24 1.03 245 116 100/81 0.25 1.10 0.20 1.03 209 113 80/105 0.34 1.05 0.31 1.00 226 98 80/57.2 0.20 1.16 0.17 1.15 118 87 60/105 0.41 1.01 0.39 1.00 165 78 60/35.1 0.12 1.23 0.12 1.22 65 63 40 / 105 0.56 0.93 0.55 0.89 101 59 25 / 105 0.96* 0.75* 0.84 0.77 55* 43*

  • The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-26890 Revision LaSalle Unit I Cycle 10 Paae 3-14 I

Plant I ranslent Analysis Table 3.6 EOC Base Case FWCF Transient Results Peak Peak ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Power/

ACPR LHGRFACp ACPR LHGRFACp (% rated) (% rated)

Flow TSSS Insertion Times 0.33* 1.05 0.30* 1.00* 342* 122*

100/105 0.32* 1.06 0.29* 1.00* 321* 121*

100/100 0.31* 1.05 0.27* 1.03 221* 117*

100/81 80/105 0.37* 1.03* 0.35* 1.00* 268* 101*

0.34 1.08 0.30 1.07 217 100 80/57.2 0.44* 1.00* 0.43* 1.00 184* 80*

60/105 0.60* 0.91* 0.57* 0.88* 88* 57*

40 /105 1.04* 0.74* 0.85* 0.76* 59* 44*

25/105 NSS Insertion Times 0.29 1.06 0.27 1.03 366 126 100/105 0.29 1.06 0.26 1.03 345 125 100/100 100/81 0.28 1.05 0.24 1.03 273 123 0.31" 1.00* 226* 98*

80/105 0.34* 1.05 80/57.2 0.29 1.10 0.25 1.08 192 97 0.41" 1.01* 0.39* 1.00* 165* 78*

60/105 0.56* 0.93* 0.55* 0.89* 101* 59*

40/105 0.84* 0.77* 55* 43*

25/105 0.96* 0.75*

results are

  • The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 3-15 P-lant I ransien/rAnalyslis Table 3.7 Loss of Feedwater Heating Base Case Transient Analysis Results ACPR (ATRIUM-10 Power and

(% rated) ATRIUM-9B Fuel) 100 0.21 90 0.22 80 0.23 70 0.24 60 0.26 50 0.29 40 0.33 25 0.45 Framatome ANP, Inc.

EMF-26890 Revision LaSalle Unit 1 Cycle 10 Paae 3-16

+

RamI L I Id IInIIIL IgYOll .l MHO Table 3.8 Input for MCPR Safety Limit Analysis Fuel-Related Uncertainties Source Statistical Parameter Document Treatment Critical power correlation*

ATRIUM-10 Reference 12 Convoluted ATRIUM-9B Reference 17 Convoluted Radial power References 10 and 16 Convoluted Local peaking factor Reference 5 Convoluted Assembly flow rate (mixed core) Reference 5 Convoluted Channel bow local peaking Function of nominal and bowed local Convoluted peaking and standard deviation of bow data (see Reference 18)

Nominal Values and Plant Measurement Uncertainties Uncertainty (%) Statistical Parameter Value (Reference 8) Treatment Feedwater flow rate t (Mlbm/hr) 23.6 1.76 Convoluted Feedwater temperature (OF) 426.5 0.76 Convoluted Core pressure (psia) 1031.35 0.50 Convoluted Total core flow (Mlbm/hr) 113.9 2.50 Convoluted 5446.6 -

Core power t (MWth)

Additive constant uncertainties values are used.

t Feedwater flow rate and core power were increased above design values to attain desired core MCPR for safety limit evaluation consistent with Reference 5 methodology.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 3-17 maInIi. I I IZI ItII HIaIY.

YO*1 Table 3.9 Flow-Dependent MCPR Results Core 105%

Flow Maximum Core Flow

(% rated) ATRIUM-10 ATRIUM-9B 30 1.58 1.58 40 1.52 1.51 50 1.46 1.46 60 1.40 1.41 70 1.34 1.35 80 1.27 1.28 90 1:22 1.22 100 1.17 1.15 105 1.11 1.11 Framatome ANP. Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Pl~nt Tr~n~k~nI An~lvcdi. Paae 3-18 PIn T-.

I ns i ent,..,wAnavsi 0

I-Q:

w 0

t*

h z

LU CL w.

30 TIME, SECONDS LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 07*46"04 NOS-10079. JOB D-08112 Figure 3.1 EOC Load Rejection No Bypass at 1001105- TSSS Key Parameters Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 3-19 0

m z

-J

--1 w

I-J (n

W

-J

(/,

TIME, SECONDS LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 0746804 NOS-10079. JOB D-O8112 Figure 3.2 EOC Load Rejection No Bypass at 100/105 - TSSS Vessel Water Level Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 3-20 nI......A I .e ne 1.~.n-n RiaIIL I l101 lI: U I iCmoyo al o Li bJ

(/1 w

ci w

0 0

TIME, SECONDS LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 074 04 N0S-10079. JOB D-08112 Figure 3.3 EOC Load Rejection No Bypass at 1001105-TSSS Dome Pressure Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analvsis Page 3-21 AMA f CORE POWER HEAT FLUX CORE FLOW STEAM FLOW 3000.

_FEED -FLOW w

0 LiJ 200 0 0

I-z w -----------

L) 1000.

.0-

-.-. 1 1

.0 100 15.0 260 250 TIME, SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 094145 NO-10115. JOB ,-08156 Figure 3.4 EOC Feedwater Controller Failure at 1001105 - TSSS Key Parameters Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 01 n+ r *1 +nAnofic,~ Paae 3-22 r ia1*. i icS l i, i-1 i - ig i*}%fl,5 0

w LI.J I-z m

Z

-J Ld w

I Ld

-J (I)

(/n wd 100 1 TIME. SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 0941"45 NOS-10115. "ie ,-08156 Figure 3.5 EOC Feedwater Controller Failure at 1001105 - TSSS Vessel Water Level Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Pl~nt Tr~nn*ient Analysis Paqe 3-23 Pln Trnsen An............isw-a (n

U, I0 0~

0 r0 150 TIME, SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 09-41-45 NOS-t011 . JO0 1"-08156 Figure 3.6 EOC Feedwater Controller Failure at 1001105 - TSSS Dome Pressure Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Page 3-24 "Plant Transient Analysis 200 I I I I I I I I I I i I I I i 175 150 U)

C,

"-0 125 n

m O 100 C)

.03 E 75 z

50 25 0

FkFU Jfl 1.0 1.1 1.2 1.3

-. I 1.4 I

1.5 1.6

.0 .1 .2 .3 .4 .5 .6 .7 .8 .9 Radial Power Peaking Figure 3.7 Radial Power Distribution for SLMCPR Determination Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 3-25 r- l":ll I 0"QI~l;I U glll"l,

" I 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 0.000 1.156 1.212 0.000 0.540 1.036 0.000 0.512 0.971 0.536 R

0 D 0.904 0.499 0.892 0.948 0.920 0.538 1.214 1.130 0.540 0.901 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 0.000 0.499 1.058 1.114 0.529 1.248 Internal 1.252 0.512 0.892 1.151 Water 1.203 0.000 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 0.000 0.538 0.999 0.529 0.000 0.541 1.162 0.000 1.084 1.013 1.156 1.214 1.134 1.248 1.152 1.167 1.151 1.084 1.022 Figure 3.8 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors A10-4039B-15GV75 With Channel Bow (Assembly Exposure of 1000 MWdlMTU)

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Pacae 3-26 Dlnnf Trancinf AnnI -ic I UIIol, 1., Ii /t L iiZ= iq, CONTROL 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 0.000 1.176 1.225 0.000 0.526 1.030 .000 0.504 0.983 0.528 R

0 D 1.141 0.526 0.868 0.844 0.487 0.891 0.955 0.928 0.530 1.238 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 0.000 0.487 1.003 1.126 0.522 1.273 Internal 1.271 0.504 0.891 1.143 Water 1.217 0.000 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 0.000 0.530 1.013 0.522 0.000 0.533 1.183 0.000 1.103 1.021 1.176 1.238 1.155 1.273 1.173 1.189 1.173 1.103 1.033 Figure 3.9 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors A10-4037B-16GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU)

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 3-27 F11 IL Ir i f~~rA~ in* o r-lC2"ll II Q V"l " z,/i-IIIf I*,

285 2.75 265 2.55 2.45 2.35 225 2.15

. 2.05 a.

S1.95~

1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 10 20 30 40 50 60 70 80 90 100 110 0

Power (%rated)

Power MCPRp

(%) Limit 100 1.43 60 1.52 25 2.07 25 2.20 0 2.70 Figure 3.10 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Paae 3-28 SA I r1amIL dll ranJU IL11IOYOI~

C.

0.

U 10 20 30 40 50 60 70 80 90 100 110 0

Power (% rated)

Power MCPRp M% Limit 100 1.42 60 1.50 25 1.95 25 2.20 0 2.70 Figure 3.11 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B3 Fuel - NSS Insertion Times Framnatomne ANP. Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 3-29 Plant Transient Analysis

  • LRNB 285 a FWCF 2.75 a FWCFwITCVStuck 2.65 - OLMCPR 2 55 2.45 2.35 2.25 2.15 I" 2.05

=.1.95 1.85 1.75 1 65 1.55 1.45 1.35 1.25 1.15 90 100 110 40 50 60 70 80 0 10 20 30 Po,;er (% rated)

MCPRp Power

(%) Limit 100 1.46 60 1.55 25 2.15 25 2.20 0 2.70 Figure 3.12 BOC to 15,000 MWdlMTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 3-30

,,o f 6 _r  ; #nAnni IOc rra"lL I Ol*) VI, ItA*yIJ.IJ Yim 2.85 2.75 265 2.55 2.45 2.35 2.25 2.15

. 205

  • 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 10 20 30 40 50 60 70 80 90 100 110 0

Power (% rated)

Power MCPRp

(%) Limit 100 1.44 60 1.54 25 1.96 25 2.20 0 2.70 Figure 3.13 BOC to 15,000 MWdlMTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 3-31 rPlantI anI =llIOl]

mCI*I*I 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 Z.05 1.95 1.85 1.75 1.65 1.55 145 1.35 125 1.15 50 60 70 80 90 100 110 0 10 20 30 40 PoWer (%ratoo Figure 3.14 15,000 MWdlMTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 3-32 Plant Transient Analysis 0.

0.

0 50 60 70 80 90 100 110 0 10 20 30 40 Power (% rated)

Power MCPRp

(%) Limit 100 1.43 60 1.50 25 1.95 25 2.20 0 2.70 Figure 3.15 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 3-33 Olonf Trnnciont Anal .L= is 2 85 2.75 265 2.55 2.45 2.35 2.25 2.15 0- 2.05 0.

  • 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power MCPRp

(%) Limit 100 1.50 60 1.55 25 2.15 25 2.20 0 2.70 Figure 3.16 15,000 MWdlMTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Paae 3-34 Plant Transient Analv-,is 2.75 2.65 255 2.45 235 2.25 2.15 2.05 C.

a. 1.95 U

1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power MCPRp

(%) Limit 100 1.44 60 1.54 25 1.96 25 2.20 0 2.70 Figure 3.17 15,000 MWdlMTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10

'Plant Transient Analysis Page 3-35 0.

U 0.

50 60 70 80 90 100 110 0 10 20 30 40 Power (% rated)

Power LHGRFACp N% Multiplier 100 1.00 60 1.00 25 0.75 0 0.75 Figure 3.18 BOC to 15,000 MWdlMTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Paae 3-36 1.400 1.350 1 300 1 250 1.200 1.150

00. 1.100

, 1050

"* 1000 0 950 0900 0850 0800 0750 0 700 0 10 20 30 40 50 60 70 80 90 100 110 Power (1/ rated)

Power LHGRFACp

(%) Multiplier 100 1.00 60 1.00 25 0.77 0 0.77 Figure 3.19 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Plant Transient Analysis Page 3-37 0.

C,,

50 60 70 80 90 100 110 0 10 20 30 40 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 1.00 60 1.00 25 0.74 0 0.74 Figure 3.20 BOC to 15,000 MWdlMTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 3-38 Plant Transient Analysis 1.400

  • LRNB 1.350

-LHGRFACp 1.250 1.200 1.150 UC. 1.100 S1.050 C,

z:

-J 1_

0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 1.00 60 1.00 25 0.76 0 0.76 Figure 3.21 BOC to 15,000 MWdlMTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 3-39 Dlof,' Tr LnAMnMAnli ik I- Ca" II, ]II, 'I ,£t l,, Z=

]*

1.400 1.350 1.3OO 1.250 1,200 1.150

a. 1.100 C.

U. 1.050 1.000 0.950 0.900 0.850 0800 0.750 A 7rV*

07 60 70 80 90 100 110 0 10 20 30 40 50 Power (% rated)

Power LHGRFAC,

(%) , Multiplier 100 1.00 60 1.00 25 0.75 0 0.75 Figure 3.22 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Page 3-40

.'Plant Transient Analysis 1.400 1.350.

  • LRNB

-LHGRFACf 1.250 1.200 1.150

a. 1.100 S1.050 1_no i.J 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 1.00 60 1.00 25 0.76 0 0.76 Figure 3.23 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Pane 3-41 DIght f Trrncnont AncIvki U" Z=

C.

I.

II 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 1.00 60 1.00 25 0.74 0 0.74 Figure 3.24 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10

"'Pl~nf Tr~nnld.nt An~ilvsis Page 3-42 Pinnt Transient Analysis C

C.

-r.

0 0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 1.00 60 1.00 25 0.76 0 0.76 Figure 3.25 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Page 4-1 Plant Transient Analysis 4.0 Transient Analysis for Thermal Margin - Extended Operating Domain operation in This section describes the development of the MCPR and LHGR limits to support the following extended operating domains:

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

0 MELLLA power operation (refer to Figure 1.1).

  • Coastdown is currently not supported for LaSalle Unit 1 Cycle 10.
  • Final feedwater temperature reduction (FFTR) is currently not supported for LaSalle Unit 1 Cycle 10.

limits and Results of the limiting transient analyses are used to determine appropriate MCPRp in the EOD LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel to support operation ATRIUM-10 and scenarios. MCPRp limits and LHGRFACp multipliers are established for both ATRIUM-9B.

remains valid for As presented in Reference 9, the MCPR safety limit analysis for the base case LHGR analyses operation in the EODs discussed below. Also, the flow-dependent MCPR and for all the EODs.

described in Section 3.4 were performed such that the results are applicable 4.1 IncreasedCore Flow operation in the The base case analyses presented in Section 3.0 were performed to support region. As a power/flow domain presented in Figure 1.1, which includes operation in the ICF result, the analyses performed for the base case support operation in the ICF extended operating domain.

4.2 MELLLA Operations operation in the The base case analyses presented in Section 3.0 were performed to support the MELLLA region. As power/flow domain presented in Figure 1.1, which includes operation in MELLLA operating a result, the analyses performed for the base case support operation in the domain.

4.3 Coastdown Analysis Coastdown operation is currently not supported for LaSalle Unit 1 Cycle 10.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

-Plant Transient Analysis Page 4-2 4.4 Combined FinalFeedwaterTemperature ReductionlCoastdown Combined FFTR/coastdown operation is currently not supported for LaSalle Unit 1 Cycle 10.

Framatome ANP, Inc.

EMF-2689 Revision0 Page 5-1 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 5.0 Transient Analysis for Thermal Margin - Equipment Out-of-Service operating limits to support This section describes the development of the MCPR and LHGR operation in the following EOOS scenarios:

reduction.

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

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

  • Slow closure of I or more turbine control valves.
  • 1 stuck closed TCV.
  • 1 recirculation pump loop (SLO).

number of TIP Operation with 1 SRV out-of-service, up to 2 TIPOOS (or the equivalent by the base case thermal channels) and up to 50% of the LPRMs out-of-service is supported EOOS scenarios is presented in limits presented in Section 3.0. No further discussion for these include the same EOOS this section. The EOOS analyses presented in this section also scenarios protected by the base case limits.

applicable for operation in the The base case MCPR safety limit for two-loop operation remains operation. Also, the flow EOOS scenarios discussed below with the exception of single-loop were performed such that the dependent MCPR and LHGR analyses described in Section 3.4 results are applicable in all the EOOS scenarios.

two cases. The limits provided Most of the equipment out of service scenarios are divided into The limits for EOOS for EOOS Case I are applicable for operation with FHOOS or TBVOOS.

no RPT or FHOOS.

Case 2 support operation with any combinationmof TCV slow closure, cases were performed to Analyses for the limiting events and EOOS conditions for the two stuck closed is supported in ensure that the limits provide the necessary protection. One TCV SLO with and without combination with the other EOOS scenarios and is discussed separately.

the other EOOS conditions is also discussed separately.

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

performed with both NSS and TSSS insertion times.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-2

,'Plant Transient Analysis 5.1 EOOS Case 1 The limits also The EOOS Case I limits are applicable for operation with FHOOS or TBVOOS.

5.4). The support operation with FHOOS combined with 1 TCV stuck closed (See Section EOOS MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel for the Figures 5.9-5.16 Case 1 scenarios are presented in Figures 5.1-5.8 for 15,000 MWd/MTU and for EOC.

5.1.1 Feedwater Heaters Out-of-Service (FHOOS) 0 Operation with The FHOOS scenario assumes a 100 F reduction in the feedwater temperature.

temperature FHOOS is similar to operation with FFTR except that the reduction in feedwater reduced feedwater due to FHOOS can occur at any time during the cycle. The effect of the power shape and core temperature is an increase in the core subcooling which can change the event is less severe void fraction. Previous analysis (Reference 23) has verified that the LRNB the FWCF event with FHOOS due to the decrease in steam flow and is nonlimiting. However, were performed for can get worse due to the increase in core inlet subcooling. FWCF analyses ACPR and Cycle 10 to determine thermal limits to support operation with FHOOS. The FHOOS are LHGRFACp results used to develop the 15,000 MWd/MTU operating limits with the EOC operating presented in Table 5.1. The ACPR and LHGRFACp results used to develop limits with FHOOS are presented in Table 5.2.

5.1.2 Turbine Bypass Valves Out-of-Service (TBVOOS) relief capacity, The effect of operation with TBVOOS is a reduction in the system pressure LRNB event is which makes the pressurization events more severe. While the base case TBVOOS has an analyzed assuming the turbine bypass system out-of-service, operation with Unit I Cycle 10 to effect on the FWCF event. The FWCF event was evaluated for LaSalle to develop the support operation with TBVOOS. The ACPR and LHGRFACp results used 5.1. The ACPR and 15,000 MWdIMTU operating limits with TBVOOS are presented in Table are presented in LHGRFACp results used to develop the EOC operating limits with TBVOOS Table 5.2.

heating event.

The TBVOOS condition can also affect the response of the loss of feedwater as well as During the event, the colder feedwater results in an increase in the inlet subcooling in core thermal an increase in the thermal power. Although there is a substantial increase Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-3 Plant Transient Analysis is used power, the increase in steam flow is much less because a large part of the added power in steam to overcome the increase in inlet subcooling. However, there can be a small increase flow. Ifthe flow. The turbine control valves will open to accommodate any increase in steam turbine bypass steam flow increases beyond the total capacity of the turbine control valves, the the system valves open to provide pressure relief. With the turbine bypass valves inoperable, the TCVs. A would pressurize if the steam flow were to increase above the total capacity of that in review of the maximum steam flow obtained in the base case LOFH analyses showed capacity. As a some of the rated power cases, the steam flow did increase above the TCV total result, LOFH analyses were performed using the transient methodology (COTRANSA2 only at high

/XCOBRAT) to account for the effects of pressurization. Analyses were performed sufficient power levels (100% and 80% of rated) since at lower power levels, the TCVs have results capacity to accommodate the increase in steam flow. The LOFH ACPR and LHGRFACp in used to develop the 15,000 MWd/MTU operating limits with TBVOOS are presented the same results Table 5.1. Since the limiting exposure for the LOFH event is early in the cycle, were used to develop the EOC operating limits with TBVOOS.

5.2 EOOS Case 2 TCV slow closure, The EOOS Case 2 limits are applicable for operation with any combination of no RPT or FHOOS. The limits also support operation with the same EOOS conditions points and combined with I TCV stuck closed (See Section 5.4). The spectrum of power/flow analyses events performed to establish the EOOS Case 2 limits is based on previous 0 and ATRIUM-9B (Reference 20). The MCPRp limits and LHGRFACp multipliers for ATRIUM-1 for 15,000 MWd/MTU fuel for the EOOS Case 2 scenarios are presented in Figures 5.17-5.24 and Figures 5.25-5.32 for EOC.

5.2.1 Recirculation Pump Trip Out-of-Service (No RPT')

with the This section summarizes the development of the thermal limits to support operation recirculation pump on EOC RPT inoperable. When RPT is inoperable, no credit for tripping the is to reduce the TSV position or TCV fast closure is assumed. The function of the RPT feature The RPT severity of the core power excursion caused by the pressurization transient.

of the reactivity accomplishes this by helping revoid the core, thereby reducing the magnitude can result in insertion resulting from the pressurization transient. Failure of the RPT feature Framatome ANP, Inc.

EMF-2689 Revision 0

,LaSalle Unit I Cycle 10 Page 5-4 "PlantTransient Analysis control

.higher operating limits because of the higher positive reactivity in the core at the time of rod insertion.

ACPR and Analyses were performed for LRNB and FWCF events assuming no RPT. The no RPT are LHGRFACp results used to develop the 15,000 MWd/MTU operating limits with EOC operating presented in Table 5.3. The ACPR and LHGRFACp results used to develop the limits to support no RPT operation are presented in Table 5.4.

5.2.2 Slow Closure of the Turbine Control Valve Analyses were LRNB analyses were performed to evaluate the impact of a TCV slow closure.

Results performed closing 3 valves in the normal fast closure mode and 1 valve in 2.0 seconds.

closing in provided in Reference 20 demonstrate that performing the analyses with 1 TCV below 2.0 seconds protects operation with up to 4 TCVs closing slowly. Sensitivity analyses slowly can be 80% power have shown that the pressure relief provided by all 4 TCVs closing credit for sufficient to preclude the high-flux scram set point from being exceeded. Therefore, TCV slow high-flux scram is not taken for analyses at 80% power and below. The 80% power The ACPR closure analyses were performed both with and without high-flux scram credited.

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

the lower The MCPRp limits are established with a step change at 80% power. At 80% power, upper-bound bound MCPRp limits are based on the analyses which credit high-flux scram; the EOOS Case 2 MCPRp limits are based on analyses which do not credit high-flux scram. The limits protect the scenario of all 4 TCVs closing slowly.

5.2.3 Combined FHOOS/TCV Slow Closure andlor No RPT of The EOOS Case 2 limits were established to support operation with any combination results FHOOS, TCV slow closure or no RPT. The TCV slow closure ACPR and LHGRFACp feedwater with FHOOS become less limiting than the TCV slow closure event with nominal less severe temperature since the initial steam flow with FHOOS is lower and produces a were pressurization event. Subsequently, no TCV slow closure with FHOOS analyses RPT as the performed. Analyses were performed for the FWCF event with FHOOS and no and analysis results are potentially limiting, especially at low power levels. The ACPR Framatome ANP, Inc.

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

5.3 Single-Loop Operation(SLO)

The impact of SLO at LaSalle on MCPR limits and LHGRFACp multipliers was presented in Reference 9. The base case ACPRs and LHGRFACp multipliers remain applicable. The only impact is on the MCPR safety limit. As presented in Section 3.2, the single-loop operation net safety limit is 0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The in the result is an increase to the base case MCPRp limits of 0.01 as a result of the increase MCPR safety limit. The same situation is true for the EOOS scenarios. Adding 0.01 to the corresponding TLO EOOS MCPR limits results in SLO MCPR limits for the EOOS conditions.

The TLO EOOS LHGRFACp multipliers remain applicable in SLO.

5.4 1 Stuck Closed Turbine Control Valve With 1 of the turbine control valves assumed stuck closed, the other 3 TCVs will be further open when operating at a given power level. In addition, the highest attainable power is decreased because of the decreased steam flow capacity of the TCVs. With the valves further open, TCV valves closure events such as the LRNB and slow closure events, are less severe than with the is further closed because the pressurization occurs over a longer time. While the FWCF event not impacted during the turbine stop valve closure portion of the event, it may be impacted during the overcooling phase. At some power level between 80% and 100% of rated, the TCVs during will be in the full open position with no ability to accommodate an increase in steam flow the overcooling phase. The result is an increase in pressurb prior to the turbine stop valve closure and a more severe event. Operation of the turbine bypass valves during the overcooling phase is not credited. Operation with 1 stuck closed TCV is supported in conjunction with the other EOOS conditions. As a result, FWCF analyses with 1 stuck TCV were performed for base case operation and the EOOS conditions where the FWCF is the are only limiting event (i.e. FHOOS, TBVOOS, no RPT and FHOOS with no RPT). Analyses is such performed at 80% and 100% power since at lower power levels, the initial TCV position the that there is enough capacity left to accommodate the increase in steam flow during TCV overcooling phase. The ACPR and LHGRFACp analysis results for the FWCF with 1 stuck Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

.'Plant Transient Analysis Page 5-6 closed for base case and the EOOS conditions at 15,000 MWd/MTU and EOC are presented in Tables 5.5 and 5.6, respectively.

The 1 stuck closed turbine control valve condition may also impact the loss of feedwater heating event when combined with the TBVOOS condition. Any increase in steam flow causes the system to pressurize ma king the event more severe. LOFH analyses were performed to support operation with 1 TCV stuck closed and TBVOOS for 80% and 100% of rated power.

Analyses are only performed at 80% and 100% power since at lower power levels, the initial TCV position is such that there is enough capacity left to accommodate the increase in steam flow. The ACPR and LHGRFACp LOFH with 1 stuck TCV closed and TBVOOS analysis at 15,000 MWd/MTU and EOC are presented in Tables 5.5 and 5.6, respectively.

In most cases, the results in Tables 5.5 and 5.6 were used in establishing the base case, EOOS Case I and EOOS Case 2 operating limits. The inclusion of the I TCV stuck closed condition with other limits has little or no impact, with one exception being the combined I TCV stuck closed and TBVOOS scenario. Results for I TCV stuck closed are included with the base case limits presented in Figures 3.10-3.25. Results for EOOS Case I with 1 TCV stuck closed are presented in Figures 5.1-5.16. Results for EOOS Case 2 with 1 TCV stuck closed are presented in Figures 5.17-5.32. The EOOS Case I MCPRp limits protect the combined I TCV stuck closed with TBVOOS MCPR results. However, the LHGRFACp results for the combined 1 TCV stuck closed and TBVOOS are much lower than the TBVOOS results. Therefore, separate sets of operating limits were established. The LHGRFACp multipliers for ATRIUM-1O and ATRIUM-9B fuel for the 1 TCV stuck closed with TBVOOS condition are presented in Figures 5.33-5.36 for 15,000 MWd/MTU and Figures 5.37-5.40 for EOC.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 5-7 Dlnnf Tr~ncnint AnIv is I l r-ll'--l*Pl l~i l lL*ea e~.L Table 5.1 EOOS Case I Analysis Results - 15,000 MWd/MTU FHOOS With NSS Insertion Times 100/105 0.30 1.07 0.27 1.01 100/81 0.25 1.10 0.22 1.08 80/105 0.37 1.02 0.34 0.97 FWCF 80/57.2 0.24 1.09 0.19 1.08 60/105 0.47 0.96 0.45 0.92 40/105 0.69* 0.86* 0.66 0.83 25/105 1.25* 0.66* 1.04 0.69 FHOOS With TSSS Insertion Times 100/105 0.34 1.04 0.31 0.97 100/81 0.32 1.08 0.28 1.03 80/105 0.40 1.00 0.37 0.95 FWCF 80/57.2 0.35 1.09 0.26 1.08 60/105 0.49 0.95 0.48 0.91 40/105 0.76* 0.83* 0.69 0.82 25/105 1.34* 0.64* 1.08* 0.69 TBVOOS With NSS Insertion Times 100/105 0.34 1.03 0.33 0.93 100/81 0.33 1.00 0.28 0.90 FWCF 80 / 105 0.40 1.01 0.38 0.94 80 /57.2 0.28 1.10 0.22 1.04 60/105 0.48 0.97 0.47 0.91 25/105 0.92 0.77 0.92 0.74

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10

  • ,Plnnt Tr~nn~nt AnnlvIsi Page 5-8 Pl-qnf Transient Analvqis Table 5.1 EOOS Case 1 Analysis Results - 15,000 MWd/MTU (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated 1% rated) ACPR LHGRFACp ACPR LHGRFACp 1h TBVOOS With TSSS Insertion Times 100 /105 0.38 1.02 0.36 0.93 100/81 0.39 1.01 0.34 0.92 80/105 0.43 0.99 0.42 0.91" 80/57.2 0.41 1.06 0.35 0.99 60/105 0.51 0.95 0.51 0.89 25/105 0.95 0.77 0.94 0.74 100/105 0.23* 1.01* 0.22* 1.01*

100/81 0.23* 0.95* 0.23* 0.95*

LOFH 80/105 0.25* 1.05" 0.24* 1.05*

0.28* 0.94* 0.27* 0.94*

80/57.2

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-9 Table 5.2 EOOS Case I Analysis Results - EOC Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACp ACPR LHGRFACp FHOOS With NSS Insertion Times 100/105 0.30 1.06 0.28 1.01*

100/81 0.28 1.09 0.25 1.06 80/105 0.37* 1.02* 0.34* 0.97*

FWCF 80/57.2 0.30 1.09* 0.26 1.08*

60/105 0.47* 0.96* 0.45* 0.92*

40/105 0.69* 0.86* 0.66* 0.83*

1 25/105 1.25* 0.66* 1.04* 0.69*

FHOOS With TSSS Insertion Times 100/105 0.34* 1.04* 0.31* 0.97*

100/81 0.32* 1.08* 0.28* 1.03*

80/105 0.40* 1.00* 0.37* 0.95*

FWCF 80/57.2 0.35* 1.09* 0.30 1.07 601105 0.49* 0.95* 0.48* 0.91" 401105 0.76* 0.83* 0.69* 0.82*

1 25 / 105 1.34* 0.64* 1.08* 0.69*

TBVOOS With NSS Insertion Times 100 /105 0.34 1.00 0.33 0.93*

100 / 81 0.36 0.95 0.33 0.90*

FWCF 80 / 105 0.40* 1.00 0.38* 0.94*

80/57.2 0.38 1.00 0.34 0.99 1 60/105 0.48* 0.97* 0.47 0.91"

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

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

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I C I % rated) ACPR LHGRFACp ACPR LHGRFACp TBVOOS With TSSS Insertion Times 100/105 0.38* 1.00 0.36* 0.93*

100/81 0.39 0.95 0.34 0.92*

FWCF 80/105 0.43* 0.99* 0.42* 0.91*

80/57.2 0.43 1.00 0.39 0.98 60/105 0.51* 0.95* 0.51* 0.89*

100/105 0.23* 1.01* 0.22* 1.01*

0.23* 0.95* 0.23* 0.95*

100/81 0.25* 1.05* 0.24* 1.05*

80/105 0.94* 0.27* 0.94*

80/57.2 0.28*

The ACPR and LHGRFACp

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

results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 5-11 Manti[ I [ slenl I,'a t I1ys s*

Table 5.3 EOOS Case 2 Analysis Results - 15,000 MWdIMTU Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated

/ % rated) ACPR LHGRFACp ACPR LHGRFACp TCV Slow Closure With NSS Insertion Times 100/ 105t 0.43 0.90 0.41 0.81 011/l00t 0.42 0.89 0.40 0.80 100 / 81t 0.39 0.91 0.41 0.82 80 / 1 0 5 t 0.39 0.95 0.41 0.88 80/57.2t 0.63* 0.98 0.56 0.90 LRNB 80/ 1051 0.59* 0.88* 0.62 0.82 80/ 57.21 0.70* 0.91 0.75 0.83 60/ 1051 0.68 0.84 0.71 0.79 60/ 35.1 0.59 0.93 0.69 0.88 40/ 1051 0.84 0.77 0.84 0.75 1 25/1051 1.19* 0.67* 1.02 0.69 TCV Slow Closure With TSSS Insertion Times 100 / 105t 0.48 0.88 0.48 0.78 100/ 100t 0.48 0.87 0.48 0.77 100/ 81t 0.43 0.87 0.45 0.76 80 1/105 0.45 0.93 0.44 0.85 80/57.2t 0.63* 0.97 0.62 0.88 LRNB 80/ 105* 0.59* 0.88 0.62 0.82 80/ 57.21 0.71* 0.90 0.75 0.83 60 / 1051 0.69 0.84 0.71 0.79 60/ 35.1' 0.64 0.90 0.75 0.86 40 / 105 t 0.85 0.77 0.86 0.74 1 25/105 1 1.19* 0.67* 1.03 0.68

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

t Scram initiated on high neutron flux.

SScram initiated on high dome pressure.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I jycle 10 Page 5-12

-'Plant Transient Analvsis Table 5.3 EOOS Case 2 Analysis Results - 15,000 MWd/MTU (Continued)

Power I Flow ATRIUM-10 ATRIUM-9B Event (% rated L ACLHGRFACp 1% rated) ACPR LHGRFAC ACPRG No RPT With NSS Insertion Times 100/105 0.37 0.95 0.39 0.84 0.30 0.91 0.34 0.79 LRNB 100/81 80/105 0.35 0.99 0.37 0.89 1 80/57.2 0.24 1.05 0.22 0.97 FWCF 100/105 0.32 1.01 0.32 0.92 No RPT With TSSS Insertion Times 100/105 0.41 0.89 0.40 0.81 0.35 0.93 0.36 0.81 LRNB 100/81 80 / 105 0.39 0.95 0.40 0.87 1 80/57.2 0.37 1.01 0.35 0.93 FWCF 100/105 0.37 0.96 0.36 0.90 FHOOSINo RPT With NSS Insertion Times 100 / 105 0.33 1.01 0.32 0.93 FWCF 80 / 105 0.39 0.97 0.38 0.91 25/105 1.22* 0.65* 1.04 0.67 FHOOSINo RPT With TSSS Insertion Times 100 / 105 0.37 0.97 0.36 0.90 FWCF 80 / 105 0.42 0.95 0.42 0.88 25 / 105 1.26* 0.64* 1.06 0.67

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10

_-1 A...1.....A  ?..

Paae 5-13 Plant I ranslent Analysis--.

Table 5.4 EOOS Case 2 Analysis Results - EOC Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I % rated) ACPR LHGRFACE ACPR LHGRFACp TCV Slow Closure With NSS Insertion Times 100 / 105l 0.48 0.90* 0.47 0.81*

100 / 81? 0.47 0.84 0.42 0.81 80/ 105? 0.45 0.94 0.43 0.88*

80 / 5 7 .2t 0.63* 0.92 0.56 0.90*

80/ 105$ 0.59* 0.88* 0.62* 0.82*

LRNB 80/ 57.2' 0.70* 0.86 0.75* 0.83*

60/ 1105 0.68* 0.84* 0.71* 0.79*

60/ 35.11 0.59* 0.93* 0.69* 0.88*

40/ 1051 0.84* 0.77* 0.84* 0.75*

25/1051 1.19* 0.67* 1.02* 0.69*

TCV Slow Closure With TSSS Insertion Times 100 / 105t 0.50 0.88* 0.49 0.78*

100 / 81t 0.47 0.84 0.45 0.76*

80 / 105t 0.46 0.93* 0.45 0.85*

80 / 57.2t 0.63* 0.94 0.62* 0.88*

80/ 1051 0.59* 0.88* 0.62* 0.82*

LRNB 80 157.21 0.71* 0.86 0.75* 0.83*

60/ 1051 0.69* 0.84* 0.71* 0.79*

60/ 35.11 0.64* 0.90* 0.75* 0.86*

0.77* 0.86* 0.74*

40/ 105i 0.85*

25 / 105' 1.19* 0.67* 1.03* 0.68*

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

t Scram Initiated on high neutron flux.

Scram initiated on high dome pressure.

Framatome ANP, Inc.

EMF-26890 Revision LaSalle Unit I Cycle 10 Page 5-14 111 Plant i ranslent Analysm Table 5.4 EOOS Case 2 Analysis Results - EOC (Continued)

Power I Flow ATRIUM-10 ATRIUM-9B Event (%rated C e% rated) ACPR LHGRFACp ACPR LHGRFACp h h No RPT With NSS Insertion Times 100/105 0.48 0.87 0.47 0.84*

100/81 0.41 0.84 0.41 0.79*

80/105 0.43 0.91 0.42 0.89*

80/57.2 0.35 0.93 0.30 0.90 FWCF 100/105 0.38 0.93 0.34 0.91 No RPT With TSSS Insertion Times 100 /105 0.53 0.84 0.54 0.81*

100/81 0.49 0.82 0.42 0.80 80/105 0.47 0.89 0.48 0.87 80/57.2 0.39 0.92 0.35 0.90 FWfVF I4n IIl 0 0.43 0.90 0.42 0.88 J

w w vB in i vv i/ g * ~

105_____ 0.43____

FHOOSINo RPT With NSS Insertion Times

- I I 0.92 100/ 105 0.37 0.93 0.35 0.97* 0.39 0.91 80/105 0.39*

FWCF 0.67 1.22* 0.65* 1.04*

25 /105 I I - -

FHOOSINo RPT With TSSS Insertion Times 0.90*

100/105 0.41 0.92 E7*

FWCF 80/105 0.42* 0.95*

1.26* 0.64*

25/105 and LHGRFACp

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-15 DInf Trnnc~knf Annlvkic llU L II l*] ~ l 1

  • I 1 Table 5.5 1 TCV Stuck Closed Analysis Results - 15,000 MWdIMTU Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated

/% rated) ACPR LHGRFACp ACPR LHGRFACp Base CaselI TCV Stuck Closed With.NSS Insertion Times 100/105 0.30 1.08 0.27 1.02 FWCF 801105 0.35 1.04 0.32 1.00 Base Casell TCV Stuck Closed With TSSS Insertion Times 100/105 0.34 1.05 0.31 1.00 100/81 0.31 1.08 0.27 1.03 80/105 0.39 1.02 0.36 1.00 80/57.2 0.32 1.13 0.24 1.09 FHOOSI1 TCV Stuck Closed With NSS Insertion Times 1001105 0.33 1.05 0.29 1.00 100/81 0.26 1.10 0.24 1.06 80/105 0.39 1.00 0.36 0.95 1 80/57.2 0.26 1.15 0.21 1.12 FHOOSI1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.36 1.02 0.33 0.96 100/81 0.33 1.06 0.29 1.01 FWCF 80/105 0.42 0.98 0.39 0.93 1 80/57.2 0.36 1.09 0.28 1.05 Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-16

'0 r'::ICI. I CH V1" "** 10rli;l~~i Table 5.5 1 TCV Stuck Closed Analysis Results - 15,000 MWdlMTU (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated

/% rated) ACPR LHGRFACp ACPR LHGRFACp b*

TBVOOSI1 TCV Stuck Closed With NSS Insertion Times 100/ 105 0.36 1.02 0.34 0.93 100/81 0.33 1.00 0.28 0.90 FWCF 80/105 0.41 1.00 0.39 0.93 80/57.2 0.29 1.10 0.22 1.04 LOFH 80/57.2 0.42* 0.90* 0.35* 0.91*

TBVOOSI1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.40 1.01 0.37 0.93 100/81 0.39 1.01 0.34 0.92 FWCF 80/105 0.45 0.98 0.43 0.90 80/57.2 0.41 1.06 0.35 0.99 100 /105 0.36* 0.95* 0.32* 0.95*

100 /81 0.36* 0.83 0.31 0.80 LOFH 80/105 0.42* 0.93* 0.38* 0.93*

80/57.2 0.44* 0.77 0.37* 0.77 No RPTI1 TCV Stuck Closed With NSS Insertion Times 1100/105 0.34 1.01 0.33 0.93 FWCF 80/105 0.38 0.99 0.38 0.91 No RPTI1 TCV Stuck Closed With TSSS Insertion Times FWCF 100/105 0.38 0.98 0.37 0.89 FWF 80/105 0.42 0.96 0.42 0.88

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-26890 Revision LaSalle Unit I Cycle 10 Paae 5-17 Plant Transtent Analysis Table 5.5 1 TCV Stuck Closed Analysis Results - 15,000 MWdIMTU (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (%rated 1% rated) ACPR LHGRFACp ACPR LHGRFACp FHOOSINo RPTI1 TCV Stuck Closed With NSS Insertion Times 100/105 0.35 0.99 0.34 0.92 FWCF 80/105 0.41 0.95 0.41 0.89 FHOOSINo RPTI1 TCV Stuck Closed With TSSS Insertion Times 100/ 105 0.39 0.97 0.38 0.88 FWCF 80/105 0.44 0.93 0.44 0.87 Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Pa-qe 5-18 N

Table 5.6 1 TCV Stuck Closed Analysis Results - EOC Power I Flow ATRIUM-10 ATRIUM-9B Event (% rated 1% rated) ACPR LHGRFACp ACPR LHGRFACp h h Base Casell TCV Stuck Closed With NSS Insertion Times 100/105 0.30 1.05 0.28 1.02' FWCF 80/105 0.35* 1.04* 0.32* 1.00" Base Casell TCV Stuck Closed With TSSS Insertion Times 100/105 0.34* 1.04 0.31' 1.00*

100/81 0.31 1.05 0.27* 1.03*

FWCF 80/105 0.39* 1.02* 0.36* 1.00*

80 /57.2 0.34 1.08 0.30 1.07 FHOOSI1 TCV Stuck Closed With NSS Insertion Times 100 / 105 0.33* 1.05' 0.30 1.00*

100/81 0.29 1.08 0.27 1.05 FWCF 80/105 0.39* 1.00* 0.36* 0.95*

1 80/57.2 0.31 1.11 0.27 1.08 FHOOSII TCV Stuck Closed With TSSS Insertion Times 100/105 0.36* 1.02* 0.33* 0.96*

100/81 0.33* 1.06" 0.29* 1.01' FWCF 80/105 0.42* 0.98* 0.39* 0.93*

0.36* 1.09' 0.30 1.05' 80/57.2

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-19 Plant T ransient Analysis--,.

Table 5.6 1 TCV Stuck Closed Analysis Results - EOC (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated I I I 1% rated) ACPR LHGRFACp ACPR LHGRFACp TBVOOSI1 TCV Stuck Closed With NSS Insertion Times 100/ 105 0.36* 1.00 0.34* 0.93*

100 / 81 0.36 0.95 0.33 0.90*

FWCF 80/105 0.41* 1.00* 0.39* 0.93*

80/57.2 0.38 1.02 0.34 1.00 TBVOOSll TCV Stuck Closed With TSSS Insertion Times 100/105 0.40* 1.01* 0.37* 0.93*

100/81 0.39 0.95 0.34 0.92*

80/105 0.45* 0.98* 0.43* 0.90*

80/57.2 0.43 1.00 0.39 0.99*

100/105 0.36* 0.95* 0.32* 0.95*

100/81 0.36* 0.83* 0.31* 0.80*

LOFH 80/105 0.42* 0.93* 0.38* 0.93*

80/57.2 0.44* 0.77* 0.37* 0.77*

No RPTII TCV Stuck Closed With NSS Insertion Times 0.38 0.93 0.35 0.91 FWCF 100/105 0.91*

80/105 0.38* 0.97 0.39 No RPTI1 TCV Stuck Closed With TSSS Insertion Times 0.43 0.90 0.43 0.88 FWCF 100 /105 80/105 0.42* 0.95 0.42* 0.88*

LHGRFACp

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 5-20

, l Trfnd;onf AnaIick Table 5.6 1 TCV Stuck Closed Analysis Results - EOC (Continued)

Power / Flow ATRIUM-10 ATRIUM-9B Event (% rated 1% rated) ACPR LHGRFACp ACPR LHGRFACp "FHOOSINoRPTil TCV Stuck Closed With NSS Insertion Times 100 /105 0.38 0.93 0.36 0.91 FWCF 0.95* 0.41* 0.89*

80/105 0.41-FHOOSINo RPTI1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.42 0.92 0.41 0.88*

100 /81 0.35 0.95 0.31 0.93 FWCF 80/105 0.44* 0.93* 0.44* 0.87*

80/57.2 0.33 1.05 0.29 1.03

  • The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 5-21 a":II II :Al1*"Q II l IiZ/*l

-aIa=

2.95

  • FWC No BypassI 2.85 FWCF NoBypasswITCVE tuck o

2.75

  • FWCF FHOOSwlTCVStu ck S+*

LOFH No Bypass 2.65

  • LOFH No Bypass wITCV S btuck

-OLMCPR 2.55 2.45 2.35 2.25 2.15 IL 2.05

E 1.95 1.85 1.75 1.65 1.55 1.45 1.35' 1.25-1.15 20 30 40 50 60 70 80 90 100 110 0 10 Power (% rated)

Power MCPRn

(%) Limit 100 1.47 60 1.59 25 2.36 25 2.36 0 2.86 Figure 5.1 BOC to 15,000 MWd/MTU EOOS Case I Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0

.'Plant Transient Analysis Page 5-22 a.

U 4

U 0

1 30 40 50 60 70 80 90 100 110 0 10 20 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.66 25 0.66 0 0.66 Figure 5.2 BOC to 15,000 MWdlMTU EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-23 Miad , IIrlI::ll*iem L"Il, 2 lyO*l 2.85

  • FWCF FI-OOS vdTCV Stuck
  • LOFH No Bypass 2.55
  • LOFH No Bypass W/ TCV Sbuck

-OMCP 2.45 235 2.25 2.15 I.

2.05 195 185 1.75 1.45

, I 1.35 1.25 1.15 30 40 50 60 70 80 90 100 110 0 10 20 Powr 0/6Md)

Power MCPRp

(%) Limit 100 1.45 60 1.58 25 2.15 25 2.20 0 2.70 Figure 5.3 BOC to 15,000 MWdlMTU EOOS Case I Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0

, ,'Plant Transient Analysis Page 5-24 1.300 1.250 S FWCF No B 1.200 + FWCF -HO'

-LHGRFACP 1.100 1.050 1.000 0.950 0.900 0850 0800 0750 0.700 0.650 0.600

.0 10 20 30 40 50 60 70 80 90 100 110 Power (%rW4 Power LHGRFACp

(%) Multiplier 100 0.90 60 0.90 25 0.69 25 0.69 0 0.69 Figure 5.4 BOC to 15,000 MWd/MTU EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Paae 5-25 Plant Transient Analysis 305

  • .yy- ro yp 2.95 FWCFFHOOS

+

2.85 o FWCF No Bypass vi TCV Stu 2.75

  • FWC*"FHOOS Ti' Stuckd No No LOFH %V A F*IWCF- Bypass Bypass 2.65 o LOFH No Bypass % Stuck TCV

-OLCPR 2.65 2.45 2.35 2.25 2.15 I 2.05 1.95 1.85 1.75 1.65 1.55 1.45 t A 1.35 1.25 1.15 70 80 9 .10 .i 20 30 40 50 60 TO so 90 100 110 0 10 P6~ r(% rxtd Power MCPRp

(%) I Limit 100 1.51 60 1.62 25 2.45 25 2.45 0 2.95 Figure 5.5 BOC to 15,000 MWdlMTU EOOS Case I Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

,'Plant Transient Analysis Page 5-26 I,

ml.

C,

,.I 0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.64 25 0.64 0 0.64 Figure 5.6 BOC to 15,000 MWd/MTU EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 5-27 r aidlI I I 1 I;I1I Ic." ln "caiyfl 2.85

+ FWCF FHOOS 2.75 flnF Nwk"RMn u T(V tc 2.65

  • LOFH No Bypass 2.55 -OLMCZPR 2.45 2.35 2.25 2.15 I.

2.05 1.95 1.85 1.75 1.65

.55 1.45 1.35 125-1.15 30 40 50 60 70 80 90 100 110 0 10 20 Power Mratsd)

Power MCPRp

(%) Limit 100 1.48 60 1.62 25 2.19 25 2.20 0 2.70 Figure 5.7 BOC to 15,000 MWd/MTU EOOS Case I Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-28 r"10"t 10"Ou" "ý Y:ý C,,

40 50 60 70 60 90 100 110 0 10 20 30 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.92 80 0.91 60 0.89 25 0.69 25 0.69 0 0.69 Figure 5.8 BOC to 15,000 MWdlMTU EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-29 1lOSfL

  • O*n

' An *h.Jie OH~l I1 I01 ýh.31;II,/t Ci . l]I 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 I. 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 125 1.15 30 40 50 60 70 80 90 100 110 0 10 20 Power (% rated)

Power MCPRp

(%) Limit 100 1.47 60 1.59 25 2.36 25 2.36 0 2.86 Figure 5.9 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Paae 5-30

- DInl Tr nek=nf Anol Cie*

[Iglll,~~~~~~~Pa Il5l-.lll/,li~~m -i-30 0.

I.

0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.66 25 0.66 0 0.66 Figure 5.10 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-26890 Revision LaSalle Unit I Cycle 10 Page 5-31 Mant I , ans en m zo CL 40 50 60 70 80 90 100 110 0 10 20 30 Pcdwer (% rated)

Power MCPRp

(%) Limit 100 1.45 60 1.58 25 2.15 25 2.20 0 2.70 Figure 5.11 15,000 MWdlMTU to EOC EOOS Case I Power-Dependent MCPR Linits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-32

-'Plant Transient Analysis 1.300 1250 1200 1.150 1.100 1.050 1.000 0.950 S0.900 0.850 0800 0.750 0.700 0.650 0.600 50 60 70 80 90 100 110 0 10 20 30 40 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.90 80 0.90 60 0.90 25 0.69 25 0.69 0 0.69 Figure 5.12 15,000 MWdlMTU to EOC EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5 HianiL Ii alnls dl IL "0iYQ l 305

  • FWtZF Bypass I FWCF No
  • LOFH NW Bypass 2.75
  • LoFHNo Byps %fTCSbxk Z65 -Wv'CPR 255 Z45 2.35 225 Z15 Z065 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 70 80 90 100 110

=A 20 30 40 50 60 70 80 90 100 110 0 10 Power(% rate Power MCPRp

(%) Limit 100 1.51 60 1.62 25 2.45 25 2.45 0 2.95 Figure 5.13 15,000 MWdIMTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Plznnt Tr~nnipnt Analvsis Page 5-34 Pinnf TrnnsientAnalysis a.}

C..

cc 0-I 0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 0.95 80 0.94 60 0.94 25 0.64 25 0.64 0 0.64 Figure 5.14 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-35

[I 01 Ca"~.f Tr I U"ý Incfn Anni

- Z:ý ic

+ oFWCF Na Brass dTCV St I 2.65

  • LOFH No Bypass W TCV StW 2.55 -OLMCPR 2.45 2.35 2.25 2.15 1.95 1.85 1.75 1.65 1.55 w!

1.45 1.35 A 125 1.15 50 60 70 80 90 100 110 0 10 20 30 40 Porw (%nte)

Power MCPRp

(%) Limit 100 1.48 60 1.62 25 2.19 25 2.20 0 2.70 Figure 5.15 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Page 5-36 1.

a, U-

=.,

30 40 50 60 70 80 90 100 110 0 10 20 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 0.92 80 0.91 60 0.89 25 0.69 25 0.69 0 0.69 Figure 5.16 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-37 Ij idlllt i IIIIIIL ln cayo -

2.95 A SlowTCV 2.85

  • FWa FlFAAOO 2.75
  • LRNB WoF7T 2.65
  • FWCF No RT v6 TCV ST*iTc 2.45 & FFHOOSNoRPTviTCV Stuck 2.35 225 2.j15.

1.85 1.75 1.65

+ A 155 1.35 125 1.15 20 30 40 50 60 70 80 90 100 110 0 10 PoW.r(%frat Power MCPRp

(%) Limit 100 1.54 80 1.74 80 1.81 25 2.36 25 2.36 0 2.86 Figure 5.17 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 5-38 1.300 A Slow TCV 1.250 + FWCF FHOOS

  1. LRNB No RPT 1200.

m FWCF No RPT 1.150 13 FWCF FHOOS No RPT o FWCF No RPT w/ TCV Stuck Stuck +

1.100 A FWCF FHOOS No RPT wI TCV 4,

-LHGRFACp 4,

1.050 d *

0. - IAU 0

I.

+, 9 C 0950 A A A

o.900 0l A 0850 A 0800 A

0 750 0700 A

0.650 I

50 60 70 80 90 100 110 0 10 20 30 40 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.89 60 0.88 25 0.65 25 0.65 0 0.65 Figure 5.18 BOC to 15,000 MWdlMTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-39 H'ai I I 1IO1h1 "t "L I amy~mo 2.85

  • SlowTCV 2.75

-OLMCPR 2.25 2.15 I

2.05 1.95 1.85 1.75 A 1.65 IM55 1.45 +

  • +

1.35 1.15~

40 50 60 70 80 90 100 110 0 10 20 30 Power %ratedi Power MCPRp

(%) Limit 100 1.52 80 1.67 80 1.86 25 2.15 25 2.20 0 2.70 Figure 5.19 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 01ln* Trrnn;=nf AnoraIiQ Paae 5-40 1.300

  • SlowTCV 4* FW*F FHOOS 1.200

-LHGRFACp 1.050 1.000

++

+ A

  • 4 AA 0850 0800 A A

0750 0700 0650-0600 30 40 5o 60 70 80 90 100 110 0 10 20 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.79 80 0.79 25 0.67 25 0.67 0 0.67 Figure 5.20 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-41

,,'Plant Transient Analysis 305

  • SlotTCV "2.95
  • LRNB No RPT 2.75

1.95 1.85 1.75 A

165 155 145 1.35 125 1.15 0 10 20 30 40 50 60 70 80 90 100 110 Power (%raed)

Power MCPRP

(%) Limit 100 1.59 80 1.74 80 1.82 25 2.45 25 2.45 0 2.95 Figure 5.21 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel- TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-42 1.300 A Slow TCV 1.250

+ FWCF FHOOS 1.200

+

-LHGRFACp 1.050

+

C. I.Y.AJJ

  • 0950
  • 0.900 ++ A 0.850 0 800 0.750 0.700 A

0.650-0.600 30 40 50 60 70 80 90 100 110 0 10 20 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.87 80 0.87 25 0.64 25 0.64 0 0.64 Figure 5.22 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel -TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paqe 5-43 Plmnf Transient Analvqis 2.85 A Slow TCV 2.75 + FWCF FHOOS 2.65 *LRNB No RPT

a 1.95 A 1.85.

1.75 1.65 1.55

  • I 1.45 + 4:

1.35 1.25 4

I-is 4 20 30 40 50 60 70 80 90 100 110 0 10 Power (%rated)

Power MCPRp

(%) Limit 100 1.59 80 1.73 80 1.86 25 2.19 25 2.20 0 2.70 Figure 5.23 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Frarnatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

.'Plant Transient Analysis Page 5-44 1.300 A Slow TCV 1.250

+ FWCF FHOOS 1.200

- LHGRFACp 1.050 C. 1.000 0.900 ++

A÷ 0.850.

A. .. A A 0800 0.750 0.700 0650 0.600 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.76 80 0.76 25 0.67 25 0.67 0 0.67 Figure 5.24 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-45 I'lI ,II r I la ll In 1 ilIl oQIfl 295 A Slow TCV 285' *+ FWCF FHOOS 2.75'

-OLMCPR 2.35 225 2.15

" 2.05 1.95

+ A 1.75 1.85 A - A 1.65 1.55 1.45-I H

-+

1.35 1.25 1.15 20 30 40 50 60 70 80 90 100 110 0 10 Power (% rated)

Power MCPRp

(%) Limit 100 1.59 80 1.74 80 1.81 25 2.36 25 2.36 0 2.86 Figure 5.25 15,000 MWdlMTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

,'Plant Transient Analysis Page 5-46 1_."*J30 IRM.

1.250 A Slow TCV

+ FWCFFHOOS 1.200

  • FWCF No RPTwI rVv Stuck +

a FWCF FHOOS No RPT 4' 1.050 -LHGRFACp +l

a. 1.000. t+

U

÷

  • 0.950, A 2A

., AA

-0.900.

A

+ A 0850. A 0800' AA 0.750' 0 700' A

0.650-06004-0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 0.84 80 0.84 25 0.65 25 0.65 0 0.65 Figure 5.26 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 5-47 r101iL I n fri-*

A Ile I-1"lllt I 0" V"li ' "ýll Z.lil~il, 2.85 A Slow TCV 2.75-

+ FWCF FHOOS 2.65 *LRNB No RPT 2.55

-OLMCPR 2.25 2.15

a. 2.05 a.

1.95 1.85 1.75 1.65

-I-1.55 1.45 A

÷ 4

a

+

1.35-1.25-1.15 10 20 30 40 50 60 70 80 90 100 110 0

Power (% rated)

Power MCPRp

(%) Limit 100 1.58 80 1.67 80 1.86 25 2.15 25 2.20 0 2.70 Figure 5.27 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

..,'Plant Transient Analysis Page 5-48 l300 1.250 A SowTCV

+ FWCF FHOOS 1.200 LR No RPT 1.150 a I=CF No RPT 1 FWCF FI-OOS No RPT 1.100 o FWCF No RPT W/TCV Sutk A FWCF FHOOS N RrPTr WTCV Stick 1.050 - LHGRFACp "4

1.000 A +i 0.950 0.900 A 0850 +

0 800 A 0.750 0.700 A 0650 0600 0 10) 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 0.79 80 0.79 25 0.67 25 0.67 0 0.67 Figure 5.28 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page_5-49 Plant I ranslewtIL-nlylls C.

110 Power (%rated)

Power MCPip M% Limit 100 1.64 80  ; 1.74 80 1.82 25 2.45 25 2.45 0 2.95 Figure 5.29 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-50

,'Plant Transient Analysis 1.300 1.250 A Slow TCV

+ FWCF FHOOS 1.200

  • FWCF No RPTwlTCV Stuck +

1.100 +

A FWCF FHOOS No RPTw/ TCV Stuck A +

1.050 - LHGRFACp

a. 1.000 ++

+A S0.950

- 0.900

  • J~I A

0.850

+

0.800 A

0.750 0.700 0650-0600 70 80 90 100 110 20 30 40 50 60 70 so 90 100 110 0 10 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.82 80 0.82 25 0.64 25 0.64 0 0.64 Figure 5.30 15,000 MWdlMTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel- TSSS Insertion Times Framatome ANP, Inc.

EMF-26890 Revision LaSalle Unit I Cycle 10 Page 5-51 Plant Transient Analysis 285

a. 1.95 1.85 1.75*

1 65 1.55

.AS5 1.35 1.25 1.15 J 70 80 90 100 F 30 40 50 60 70 80 90 100 110 0 10 20 Power (% rated)

Power MCPRp

(%) Limit 100 1.65 80 1.73 80 1.86 25 2.19 25 2.20 0 2.70 Figure 5.31 15,000 MWdIMTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

,,Plant Transient Analysis Page 5-52

=

q 1-21M.-

I, 1.250 A Slow TCV

+ FWCFFHOOS 1.200 , LRNB No RPT m FWCF No RPT 1.150

1.050 -LHGRFACp

+

C. 1.000 -I S0.950 C,

+

  • 0900 I

A 0.850 4

.4-0.800 A A 0.750 A 0.700 0.650 n R"f 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.76 80 0.76 25 0.67 25 0.67 0 0.67 Figure 5.32 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Plant Transient Analysis Page 5-53 0.

U, 4

U.

40 50 60 70 80 90 100 110 0 10 20 30 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.66 25 0.66 0 0.66 Figure 5.33 BOC to 15,000 MWdlMTU I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Page 5-54 i

i %nn .

1.250 o FWCF No Bypass wI TCV Stuck o LOFH No Bypass w/ TCV Stuck 1.200

-LHGRFACp 1.150 1.100 1.050 0

a. 1.000 W 0.950 0 0 0, 0 0

"-' 0900-0.850 0 800 0 750 0.700-0.650-0600 0 10 20 30 40 50 60 70 80 90 100 110 Power(% rated)

Power LHGRFACp

(%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 Figure 5.34 BOC to 15,000 MWd/MTU I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-55 4 .nn 1.250 o FWCF No Bypass w/ TCV Stuck o LOFH No Bypass w/TCV Stuck 1.200

-LHGRFACp 1.150 1.100 0

1.050 0

Ua. 1000 0 0

S0950 0

"- 0.900.

0850.

0800.

0.750 0700 0 650 0600 20 30 40 50 60 70 80 90 100 110 0 10 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.64 25 0.64 0 0.64 Figure 5.35 BOC to 15,000 MWdlMTU I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-56 1.300 1.250 o FWCF No Bypass w/ TCV Stuck 1.200

  • LOFH No Bypass w/TCV Stuck

-LHGRFACp 1.150 1.100 1.050

,. 1000 0 0

8 0

"J 0900 0850

  • J0 0800 0.750 0.700 0650 n rnf I 50 60 70 80 90 100 110 0 10 20 30 40 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 Figure 5.36 BOC to 15,000 MWd/MTU I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel -TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 5-57 Plant Transient Analysis 1.300 1.250 o FWCF No Bypass w/ TCV Stuck o LONH No Bypass w/ TCV Stuck 1.200 -LHGRFACP 1.150 1.100 1.050 0

a 0 Uo. 1.000 0 0 0

0950 0

.' 0.900 0850 08001 0.750 0.700 0650 n AmA I 10 20 30 40 50 60 70 80 90 100 110 0

Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.65 25 0.65 0 0.65 Figure 5.37 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Uniti I Cycle 10 Paae 5-58 nl~~~~

1" iA,.J Ii-HI'itII. I Irlln l ilA ysi sa- -

1.300 1.250 o FWCF No Bypass w/TCV Stuck

  • LOFH No Bypass w/ Stuck TCV 1.200 -LHGRFACp 1.150 1.100 1.050 0

1.000 1L o 0 0

-J 0900 0 850 0.800 0.750 0.700-0650-0.600 0 10 20 30 40 50 60 70 80 90 100 110 Power(%rated)

Power LHGRFACp

(%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 Figure 5.38 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-59 1.300 1.250 o FWCF No Bypass w/ TCV Stuck

  • LONH No Bypass wl TCV Stuck 1.200

-LHGRFACp 1.150 1.100 1.050 0 0

. 1.000 0 9

c 0.950 0

  • J 0.900w 0.850 0.800 0.750 0.700 0 650-0.600 70 80 90 100 110 0 10 20 30 40 50 60 Power (% rated)

Power LHGRFACp

(%) Multiplier 100 0.83 80 0.77 40 0.77 25 0.64 25 0.64 0 0.64 Figure 5.39 15,000 MWdlMTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel- TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 5-60 1.300 1.250 o FWCF No Bypass w/ TCV Stuck o LOFH No Bypass w/TCV Stuck 1.200

- LHGRFACp 1.150 1.100 1.050 0.

CL 1.000 0 0

0.950 0 8 F,

... 0 0.900 0.850 0

0.800 0.750 0.700 0.650 fl~iOO4 0 10 20 30 40 50 60 70 80 90 100 110 Power (%rated)

Power LHGRFACp

(%) Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0 0.69 Figure 5.40 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

-Plant Transient Analysis Page 6-1 6.0 Transient Analysis for Thermal Margin - EOD/EOOS Combinations The limits presented in Section 5.0 support operation with ICF in conjunction with the EOOS scenarios presented in Table 1.1. Operation in the other EOD conditions (i.e. coastdown and FFTR/coastdown) is currently not supported for LaSalle Unit I Cycle 10.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 7-1 1

7.0 Maximum Overpressurization Analysis This section describes the maximum overpressurization analyses performed to demonstrate compliance with the ASME Boiler and Pressure Vessel Code. The analysis shows that the safety/relief valves at LaSalle Unit I have sufficient capacity and performance to prevent the pressure from reaching the pressure safety limit of 110% of the design pressure.

7.1 Design Basis The MSIV closure analysis was performed with the FRA-ANP plant simulator code COTRANSA2 (Reference 4) at a power/flow state point of 102% of rated power/105% flow. As indicated in Reference 1, the overpressurization analysis was performed at a cycle exposure of EOC + 1000 MWd/MTU. The following assumptions were made in the analysis.

The most critical active component (direct scram on valve position) was assumed to fail.

However, scram on high-neutron flux and high-dome pressure is available.

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

0 TSSS insertion times were used.

  • The initial dome pressure was set at the maximum allowed by the Technical Specifications (1035 psia).

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

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

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

Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 7-2

-Plant Transient Analysis Table 7.1 ASME Overpressurization Analysis Results 102%P/105%F "1,

Peak Peak Maximum Maximum Neutron Heat Vessel Pressure Dome Flux Flux Lower-Plenum Pressure Event (% rated) (% rated) (psig) (psig)

MSIV closure 340 138 1346 1321 Framatorne ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 7-3 F-lallL I 10"0lll V" "CA Y2 iý Ann nl-CORE POWER HEAT FLUX CORE FLOW STEAM FLOW 300.0 - FEED FLOW I-"

200.0-i.*

0

0. p ..

I

.0- '

VI

-100.0. -I I 7.0

.0 1!0 2:0 3.0 4"0 50 60 TIME, SECONDS LSA CYCLE 10 MSIV CLOSURE 11/01/01 9-503 NOS-11894, JOB D-19393 Figure 7.1 Overpressurization Event at 102/105 MSIV ClosureKey Parameters Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Page 7-4

11. r-"id L I I .'"1 V"i~ii "-l U Z.f~g 0

Ld z

._I LI LIJ

-J U,

LSA CYCLE 10 MSIV CLOSURE 11/01/01 io o-303 NOS-11894. JOe ID-19303 Figure 7.2 Overpressurization Event at 102/105 MSIV Closure Vessel Water Level Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 7-5 (n

0w 03 t.J LSA CYCLE 10 MSIV CLOSURE 11/01/01 09.35"03 NQS-1,8t4. JOB 0-19393 Figure 7.3 Overpressurization Event at 102/105 MSIV Closure Lower-Plenum Pressure Framatome ANP, Inc.

EMF-2689 Revision 0 LaSalle Unit I Cycle 10 Paae 7-6 4.

,I, R ILI I 0Dl mid I V"ItI "il"Q Q0 a

114 U) 03 U)

(L.

Uj CD LSA CYCLE 10 MSIV CLOSURE 11/01/01 0M.5-03 NOS-11894. JOB ID-1g393 Figure 7.4 Overpressurization Event at 1021105 MSIV Closure Dome Pressure Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10iQ Revision 0 I0nnf Trnnaiant Annlv Paae 7-7 l glI*)lBiI5 glLi l *4IZ= I indvi n SRV BANK 1 SRV BANK 2 SRV BANK 3 SRV BANK 4 SRV BANK 1500.0 (j)

S1000.0 0

-J

-/

"I,,,

500.0 t:I!

.0. I " .

1.0 2:0 3.0 40 50 60 7.0

.0 TIME, SECONDS LSA CYCLE 10 MSIV CLOSURE 11/01/01 og.3503 NOS-11804, JOB D-193g3 Number Opening of'% Pressure Bank SRVs (psia) 1 0. NA 2 2 1235.3 3 4 1245.6 4 4', 1255.9 5 0 NA Figure 7.5 Overpressurization Event at 102/105 MSIV Closure Safety/Relief Valve Flow Rates Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0

.,,'PlantTransient Analysis Page 8-1 8.0 References

1. Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit I Cycle 10 Calculation Plan," DEG:01:084, June 6, 2001.
2. XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors:Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
3. XN-NF-80-19(P)(A) Volume I Supplement 3, Supplement 3 Appendix F, and Supplement 4, Advanced Nuclear Fuels Methodology for Boiling Water Reactors:

Benchmark Results for the CASMO-3GIMICROBURN-B CalculationMethodology, Advanced Nuclear Fuels Corporation, November 1990.

4. 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.
5. ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF CriticalPower Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
6. ANF-:1 125(P)(A) and Supplement I and 2, ANFB CriticalPower Correlation,Advanced Nuclear Fuels Corporation, April 1990.
7. XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon NuclearMethodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
8. EMF-2533 Revision 0, LaSalle Unit I Cycle 10 PrincipalTransientAnalysis Parameters, Framatome ANP Richland, Inc., April 2001.
9. Letter, D. E. Garber (FRA-ANP) to F..W. Trikur (Exelon), "Disposition of Events Summary for the Introduction of ATRIUMmT-10 Fuel at LaSalle County Station,"

DEG:01:179, October 30, 2001.

10. Letter, D. E. Garber (SPC) to R. J. Chin (CoinEd), "Description of Measured Power Uncertainty for POWERPLEX0 Operation Without Calibrated LPRMs," DEG:00:061,

'March 7, 2000.

11. XN-NF-84-105(P)(A) Volume I and Volume I Supplements I and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-HydraulicCore Analysis, Exxon Nuclear Company, February 1987.
12. EMF-2209(P)(A) Revision 1, SPCB CriticalPower Correlation,Siemens Power Corporation, July 2000.
13. XN-NF-81-58(P)(A) Revision 2 and Supplements I and 2, RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

Framatome ANP, Inc.

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

14. LaSalle County Nuclear Station Units I and 2 Improved Technical Specifications,as amended.
15. EMF-2690 Revision 0, LaSalle Unit I Cycle 10 Reload Analysis, Framatome ANP, Inc.,

January 2002.

16. EMF-1 903(P) Revision 3, Impact of FailedlBypassedLPRMs and TIPs and Extended LPRM CalibrationIntervalon Radial Bundle Power Uncertainty,Siemens Power Corporation, March 2000.
17. ANF-1 125(P)(A) Supplement 1 Appendix E, ANFB CriticalPower Correlation Determinationof ATRIUMm-9B Additive Constant Uncertainties,Siemens Power Corporation, September 1998.
18. ANF-1 373(P), ProcedureGuide for SAFLIM2, Siemens Power Corporation, February 1991.
19. Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), "Extension of LPRM Calibration Interval to 2500 EFPH," DEG:00:088, April 17, 2000.
20. EMF-2277 Revision 1, LaSalle Unit I Cycle 9 Plant TransientAnalysis, Siemens Power Corporation, October 1999.
21. EMF-2589(P) Revision 0, Mechanical and Thermal-HydraulicDesign Report for LaSalle Units I and 2ATRIUM*m-10 FuelAssemblies,Framatome ANP Richland, Inc., July 2001.
22. EMF-2563(P) Revision 1, Fuel MechanicalDesign Report Exposure Extension for ATRIUMm-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, Framatome ANP Richland, Inc., August 2001.
23. EMF-95-205(P) Revision 2, LaSalle Extended OperatingDomain (EOD)and Equipment Out of Service (EOOS) Safety Analysis for A TRIUMm-9B Fuel, Siemens Power Corporation, June 1996.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0

-'Plant Transient Analysis Page A-1 Appendix A Power-Dependent LHGR Limit Generation The linear heat generation rate (LHGR) operating limit is established to ensure that the steady state LHGR (SSLHGR) limit is protected during normal operation and that the protection against

,power transient (PAPT) LHGR limit is protected during an anticipated operational occurrence (AOO). To ensure that the LHGR operating limit provides the necessary protection during operation at off-rated conditions, adjustments to the SSLHGR limits may be necessary. These adjustments are made by applying power and flow-dependent LHGR multipliers (LHGRFACp and LHGRFACf, respectively) to the SSLHGR limit. The LHGR operating limit (LHGROL) for a given operating condition is determined as follows:

LHGROL = min [LHGRFACp x SSLHGR, LHGRFACf x SSLHGR]

The power-dependent LHGR multipliers (LHGRFACp) are determined using the heat flux excursion experienced by the fuel during AQOs. The heat flux ratio (HFR) is defined as the ratio of the maximum nodal transient heat flux over the maximum nodal heat flux at the initiation of the transient. The HFR provides a measure of the LHGR excursion during the transient. The PAPT limit divided by the SSLHGR limit provides an upper limit for the HFR to ensure that the PAPT LHGR limit is not violated during an AOO. LHGRFACp is set equal to the minimum of the PAPT/SSLHGR ratio over HFR, or 1.0. Based on the ATRIUM-10 LHGR limits presented in Reference A.1 and the ATRIUM-9B LHGR limits presented in Reference A.2, LHGRFACp is established as follows:

PAPT = 1.35 SSLHGR HFR = Qmaxt memxo

[1.3510 LHGRFACP = min [HFR J In some cases, the established MCPR limit precludes operation at the SSLHGR limit. This allows for a larger LHGR excursion during the transient without violating the PAPT LHGR limit.

Framatome ANP, Inc.

EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page A-2 References A.1 EMF-2589(P) Revision 0, Mechanical and Thermal-HydraulicDesign Report for LaSalle Units I and 2 ATR/UMT 4-IO Fuel Assemblies, Framatome ANP Richland, Inc., July 2001.

A.2 EMF-2563(P) Revision 1, Fuel Mechanical Design Report Exposure Extension for ATRIUMm9B FuelAssemblies at Dresden, Quad Cities,and LaSalle Units, Framatome ANP Richland, Inc., August 2001.

Framatome ANP, Inc.

LaSalle Unit I Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Distribution D. G Carr, 23 D. E. Garber (9 copies)

M E Garrett, 23 J. M. Haun, 34 J. M. Moose, 23 E-Mail Notification D. B. McBurney

0. C. Brown J. G. Ingham R. R. Schnepp P. D. Wimpy Framatome ANP, Inc.

Technical Requirements Manual - Appendix I L1 C1OA Reload Transient Analysis Results Attachment 4 LaSalle Unit I Cycle IOA Transmittal of CBH Effects on Fresh Fuel for LaSalle Unit 1 Cycle 10 LaSalle Unit 1 Cycle 10A Revision 0

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