ML023190406

Facility Operating License No. NPF-18, Cycle 9 Core Operating Limits Report

ML023190406
Person / Time
Site:	LaSalle
Issue date:	11/06/2002
From:	Barnes G Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EMF-2440, Rev 0
Download: ML023190406 (138)

Text

ExekIesn.

Exelon Generation Company, LLC www exeloncorp coM Nuclear LaSalle County Station 2601 North 21' Road Marseilles, IL 61341-9757 November 6, 2002 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 2 Facility Operating License No. NPF-18 NRC Docket No. 50-374

Subject:

Unit 2 Cycle 9 Core Operating Limits Report (COLR)

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

is submitting a revision to the Core Operating Limits Report (COLR). The revision incorporates relaxed thermal limits which may be applied when the core average scram time meets the more stringent criteria presented in the COLR. In addition, explicit thermal limits have been established for the equipment out of service (OOS) options of Main Turbine Bypass Valves OOS and Feedwater Heaters OOS.

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

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

Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - LaSalle County Station 10

SIEMENS EMF-2440 Revision 0 LaSalle Unit 2 Cycle 9 Plant Transient Analysis October 2000 Siemens Power Corporation Nuclear Division

Siemens Power Corporation

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-C0N-L:I ;:Z DOCUMENT SYSTEM DATE:-

ZZ&2 EMF-2440 Revision 0 LaSalle Unit 2 Cycle 9 Plant Transient Analysis Prepared:

D. B. McBumey, Engineer BWR Safety Analysis Diz8a Date Reviewed:

lDA A 9 P ?G D. G. Carr, Team Leader BWR Safety Analysis ito-

-00 Date Concurred:

P MuL nager 6

Prc Licesing Da

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Date Approved: -

3 Date ___I_

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

M. E. Garrett, Manage(

t Safety Analysis

/0 //o6 D Date Approved:

D. J.

lnver, anager Commercial Operations Date paj

Customer Disclaimer Important Notice Regarding the Contents and Use of This Document Please Read Carefully Siemens Power Corporation's warranties and representations concerning the subject matter of this document are those set forth in the agreement between Siemens Power Corporation and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such agreement, neither Siemens Power Corporation 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 A

b.

assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information.

apparatus, method, or process disclosed in this document.

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

In order to avoid impairment of rights of Siemens Power Corporation 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 Siemens Power Corporation or until after six (6) months following termination or expiration of the aforesaid Agreement and any extension thereof, unless expressly provided in the Agreement. No rights or licenses in or to any patents are implied by the furnishing of this document.

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Pacie i Nature of Changes Item Pape Description and Justification

1.

All This is a new document.

Siemens PowerCorportion

EMF-2440 LaSalle Unit 2 Cycle 9 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........................................ 3-2 3.1.2 Feedwater Controller Failure............

............................ 3-3 3.1.3 Loss-of-Feedwater Heating........................................ 3-4 32 MCPR Safety Limit...........................................................................................

.4 3.3 Power-Dependent MCPR and LHGR Limits

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

3-6 3.5 Nuclear Instrument Response.........................................

3-7 4.0 Transient Analysis for Thermal Margin - Extended Operating Domain.........................

4-'

4.1 Increased Core Flow........................................................................................4-1 4.2 Coastdown Analysis...................................................... 41 4.3 Combined Final Feedwater Temperature ReductionlCoastdown...................... 4-2 5.0 Transient Analysis for Thermal Margin - Equipment Out-of-Service............................. 5-1 5.1 Feedwater Heaters Out-of-Service (FHOOS)........................................ 5-1 5.2 Single-Loop Operation (SLO).........................................

5-2 5.2.1 Base Case Operation........................................ 5-2 5.2.2 Idle Loop Startup........................................

5-2 5.3 Turbine Bypass Valves Out-of-Service (TBV00S)......................................... 5-2 5.4 Recirculation Pump Trip Out-of-Service (No RPT)........................................ 5-3 5.5 Slow Closure of the Turbine Control Valve

........................................ 5-3 5.6 Combined FHOOSITCV Slow Closure and/or No RPT.

5-4 6.0 Transient Analysis for Thermal Margin - EODIEOOS Combinations............................ 6-1 6.1 Coastdown With EOOS................

6-1 6.1.1 Coastdown With Feedwater Heaters Out-of-Service.................

......... 6-1 6.1.2 Coastdown With One Recirculation Loop......................................... 6-1 6.1.3 Coastdown With TBVOOS......................................... 6-2 6.1 A Coastdown With No RPT.........................................

6-2 6.1.5 Coastdown With Slow Closure of the Turbine Control Valve.........................................

6-2 62 Combined FFTRlCoastdown With EOOS..............................

6-3 6.2.1 Combined FFTRlCoastdown With One Recirculation Loop..............................

6-3 62.2 Combined FFTRlCoastdown With TBVOOS...................................... 6-3 6.2.3 Combined FFTR/Coastdown With No RPT......................................... 6-4 6.2.4 Combined FFTRlCoastdown With Slow Closure of the Turbine Control Valve.........................................

6-4

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LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Pa-ne iii Pn0 iii Contents (Continued) 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-I Siemens Power Carpomoion

EMF-2440 LaSalle Unit 2 Cyce 9 Revision 0 Plant Transient Analysis Page iv Tables 1.1 EOD and EOOS Opera ting Conditions........................................................

1-3 2.1 EOC Base Case and EOOS MCPRp Umits and LHGRFACp Multipliers for TSSS Insertion Times.2-3 2.2 EOC Base Case MCPRp Umits and LHGRFACp Multipliers for NSS Insertion Times.2-5 2.3 Coastdown Operation Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times.2-6 2A FFTRlCoastdown Operation Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times........................................................ 2-8 3.1 LaSalle Unit 2 Plant Conditions at Rated Power and Flow............................................ 3-9 3.2 Scram Speed Insertion Times.........................................................

3-10 3.3 EOC Base Case LRNB Transient Results........................................................

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

3-12 3.5 Input for MCPR Safety Limit Analysis.....................

................................... 3-13 3.6 Flow-Dependent MCPR Resutts........................................................ 3-14 4.1 Coastdown Operation Transient Results........................................................

4-3 4.2 FFTRlCoastdown Operation Transient Results......................................................... 4-4 5.1 EOC Feedwater Heater Out-of-Service Analysis Results............................................. 5-5 5.2 Abnormal Recirculation Loop Startup Analysis Results................................................ 5-6 5.3 EOC Turbine Bypass Valves Out-of-Service Analysis Results.................

.................... 5-7 5.4 EOC Recirculation Pump Trip Out-of-Service Analysis Results...............

.................... 5-8 5.5 EOC Turbine Control Valve Slow Closure Analysis Results....................

5............

-9 5.6 EOC Recirculation Pump Trip and Feedwater Heater Out-of-Service Analysis Results........................................................

5-10 6.1 Coastdown Turbine Bypass Valves Out-of-Service Analysis Results...........

................ 6-5 6.2 Coastdown Recirculation Pump Trip Out-of-Service Analysis Results..........

............... 6-6 6.3 Coastdown Turbine Control Valve Slow Closure Analysis Results.............

.................. 6-7 6.4 FFTR/Coastdown Turbine Bypass Valves Out-of-Service Analysis Results.........

........ 6-8 6.5 FFeRlCoastdown Recirculation Pump Trip Out-of-Service Analysis Results........................................................

6. 9 6.6 FFTRlCoastdown Turbine Control Valve Slow Closure Analysis Results................... 6-10 7.1 ASME Overpressurization Analysis Results 102%P/105%F........................................ 7-2

-1 ienem Power Corporation

.EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page v Figures 1.1 LaSalle County Nuclear Station Power I Flow Map..................................................... 1-4 2.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode................

.................. 2-10 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-9B Fuel..................................... 2-11 3.1 EOC Load Rejection No Bypass at 1001105-TSSS Key Parameters....................... 3-15 32 EOC Load Rejection No Bypass at 1001105 -TSSS Vessel Water Level.................. 3-16 3.3 EOC Load Rejection No Bypass at 1001105-TSSS Dome Pressure........................ 3-17 3A EOC Feedwater Controller Failure at 100/1 05-TSSS Key Parameters.................... 3-18 3.5 EOC Feedwater Controller Failure at 1001105-TSSS Vessel Water Level.......................................................................................................................... 3-19 3.6 EOC Feedwater Controller Failure at 1001105-TSSS Dome Pressure..........-.......... 320 3.7 Radial Power Distribution for SLMCPR Determination............................................... 3-21 3.8 LaSalle Unit 2 Cycle 9 Safety Limit Local Peaking Factors SPCA9-391B-14G8.D-1DOM With Channel Bow (Assembly Exposure of 18,000 MWd/MTU)...................................

.................. 322 3.9 LaSalle Unit 2 Cycle 9 Safety Limit Local Peaking Factors SPCA9410B-19G8.0-100M With Channel Bow (Assembly Exposure of 17,500 MWd/MTU).....................................................

3-23 3.10 LaSalle Unit 2 Cycle 9 Safety Limit Local Peaking Factors SPCA9-383B-16G8.D0-OOM With Channel Bow (Assembly Exposure of 17,500 MWd/MT).....................................................

3-24 3.11 LaSalle Unit 2 Cycle 9 Safety Limit Local Peaking Factors SPCA9-396B-12GZ-1 0DM With Channel Bow (Assembly Exposure of 15,000 MWdMTUJ)...............................

...................... -25 3.12 EOC Base Case Power-Dependent MCPR Limits for ATRUM-9B Fuel -

TSSS Insertion Times................................................................................................ 3-26 3.13 EOC Base Case Power-Dependent MCPR Limits for GE9 Fuel -

TSSS Insertion Times.....................................................

3-27 3.14 EOC Base Case Power-Dependent MCPR Limits for ATRUM-9B Fuel -

NSS Insertion Times.....................................................

3-28 3.15 EOC Base Case Power-Dependent MCPR Limits for GE9 Fuel -

NSS Insertion Times.....................................................

3-29 3.16 EOC Base Case Power-Dependent LHGR Multipliers for ATRUM-9B Fuel - TSSS Insertion Times.....................................................

3-30 3.17 EOC Base Case Power-Dependent LHGR Multipliers for ATRUM-9B Fuel - NSS Insertion Tlimes.....................................................

3-31 4.1 Coastdown Power-Dependent MCPR Limits for ATRUM-9B Fuel................................ 4-5 4.2 Coastdown Power-Dependent LHGR Multipliers for ATRUM-9B Fuel............

............. 4-6 4.3 Coastdown Power-Dependent MCPR Limits for GE9 Fuel.......................................... 4-7 4A FFTR/Coastdown Power-Dependent MCPR Limits for ATRUM-9B Fuel...................... 4-8 4.5 FFTRlCoastdown Base Case Power-Dependent LHGR Multipliers for ATRUM-9B Fuel....................................................

4-9 4.6 FFTRlCoastdown Power-Dependent MCPR Limits for GE9 Fuel..............

................ 4-10

-.-

EMF-244D LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis PaQe vi Figures (Continued) 5.1 EOC Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel.........................................................

5-11 5.2 EOC Feedwater Heaters Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel...............

.......................................... 5-12 5.3 EOC Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel........................................................

5-13 5.4 Abnormal Idle Recirculation Loop Startup Power-Dependent MCPR Limits for ATRIUM-9B Fuel........................................................

5-14 5.5 Abnonnal Idle Recirculation Loop Startup Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel........................................................ 5-15 5.6 Abnormal Idle Recirculation Loop Startup Power-Dependent MCPR Limits for GE9 Fuel........................................................

5-16 5.7 EOC Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel........................................................

5-17 5.8 EOC Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel........................................................ 5-18 5.9 EOC Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel........................................................

5-19 5.10 EOC Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-91 Fuel........................................................ 5-20 5.11 EOC Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel........................................................ 5-21 5.12 EOC Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel........................................................

5-22 5.13 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel........................ 5-23 5.14 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel.................. 5-24 5.15 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel.................................... 5-25 5.16 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel........................................................

-26 5.17 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel........................................................

5-27 5.18 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip and Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel........................................................

5-28 Zaa Pg uppr

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EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page vii Figures (Continued) 6.1 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel.......................................................-

11 6.2 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel.......................................................

6-12 6.3 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Umits for GE9 Fuel.......................................................

6-13 6A Coastdown Recirculation Pump Trip Out-of-,Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel.......................................................

6-14 6.5 Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel.......................................................

6-15 6.6 Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel.......................................................

6-16 6.7 Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel.......................................................

6-17 6.8 Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel.......................................................

6-18 6.9 Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel.........

......... 6-19 6.10 FFTRlCoastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel...................................................... 6-20 6.11 FFTRlCoastdown Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel.................................................... 6-21 6.12 FFTRlCoastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel....................

.................................. 6-22 6.13 FFTRlCoastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel...................................................... 6-23 6.14 FFTRlCoastdown Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel.................................................... 6-24 6.15 FFTRiCoastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel...........................

6-25 6.16 FFTRlCoastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel............................

6-26 6.17 FFTRfCoastdown Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel...........................

6-27 6.18 FFTR/Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel...........................

6-28 i

Power Corporain

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page vii Figures (Continued) 7.1 Overpressurization Event at 1021105 - MSIV Closure Key Parameters.......................... 7-3 7.2 Overpressurization Event at 1021105 - MSIV Closure Vessel Water Level..........

........... 7-4 7.3 Overpressurization Event at 102/105 - MSIV Closure Lower-Plenum Pressure..................................................

7-5 7.4 Overpressurization Event at 102/105 - MSIV Closure Dome Pressure........................... 7-6 7.5 Overpressurization Event at 1021105 - MSIV Closure Safety/Relief Valve Flow Rates.

7-7

EMF-2440 Revision 0 Page ix LaSalle Unit 2 Cycle 9 Plant I ransient Analysis AOO CornEd CPR EFPH EOC EOD EOFP EOOS FFTR FHOOS FWCF Nomenclature anticipated operational occurrence Commonwealth Edison Company critical power ratio effective full power hours end of cycle extended operating domain end of full power equipment out-of-service final feedwater temperature reduction feedwater heater out-of-service feedwater controller failure heat flux ratio increased core flow ICF L2C9 LFWH LHGR LHGRFAC1 LHGRFACp LHGROL LPRM LRNB MCPR MCPRM MCPRp MELLLA MFC MSIV NSS PAPT RPT SLMCPR SLO SPC SRV SRVOOS SSLHGR LaSalle Unit 2 Cycle 9 loss-of-feedwater heating linear heat generation rate flow-dependent linear heat generation rate factors power-dependent linear heat generation rate factors linear heat generation rate operating limit local power range monitor generator load rejection with no bypass minimum critical power ratio flow-dependent minimum critical power ratio power-dependent minimum critical power ratio maximum extended load line limit analysis manual flow control main steam isolation valve nominal scram speed protection against power transient recirculation pump trip safety limit MCPR single-loop operation Siemens Power Corporation safety/relief valve safety/relief valve out-of-service steady-state LHGR D.....

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LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Paoe x Paoe x Nomenclature (Continued)

TBVOOS TCV TIP TIPOOS TSSS TSV TTNB ACPR turbine bypass valve out-of-service turbine control valve traversing incore probe tip machine(s) out-of-service technical specification scram speed turbine stop valve turbine trip with no bypass change in critical power ratio e-Power. Corporslion

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 1-1 1.0 Introduction This report presents results of the plant transient analyses performed by Siemens Power Corporation (SPC) as part of the reload safety analyses to support LaSalle Unit 2 Cycle 9 (L2C9) operation. The Cycle 9 core contains 348 fresh ATRIUMA-9B1 assemblies, 256 previously loaded ATRIUM-9B assemblies and 160 previously loaded GE9 assemblies. Those portions of the reload safety analysis for which Commonwealth Edison Company (ComEd) has responsibility are presented elsewhere. The appropriate operating limits for Cycle 9 operation must be determined in conjunction with results from ComEd analyses. The scope of the transient analyses performed by SPC 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 S-7). Parameters for the transient analyses are documented in Reference 8.

The Cycle 9 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 (AOCs). Power-dependent MCPR (MCPRp) limits are required in order to provide the necessary protection during operation at reduced power. Flow-dependent MCPR (MCPR1) limits provide protection against fuel failures during flow excursions initiated at reduced flow. Cycle 9 power-and flow-dependent MCPR limits are presented to protect both ATRIUM-9B and GE9 fuel.

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 ATRIUM is a trademark of Siemens.

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

, --,~~4~-kr."~Sieffam Power Comoratior

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 1-2 (LHGRFACp and LHGRFACf, respectively). These factors or multipliers are applied directly to the steady-state LHGR limit to ensure that the LHGR does not exceed the protection against power transient (PAPT) limit during postulated A0Os. Cycle 9 power-and flow-dependent LHGR multipliers are presented for ATRIUM-9B fuel.

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

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

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EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 1-3 Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions Increased core flow Maximum extended load line limit analysis (MELLLA)

Coastdown Final feedwater temperature reduction (FFTR)

Combined FFTRlcoastdown 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)

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

Turbine control valve (TCV) slow closure and/or no RPT Safety relief valve out-of-service (SRVOOS)

Up to 2 tip machines out-of-service or the equivalent number of TIP channels (100% available at startup)

Up to 50% of the LPRMs out-of-service TCV slow closure, FHOOS, and/or no RPT EOOS conditions are supported for EOD conditions as well as the standard operating domain. Each EOOS condition combined with I SRVOOS, up to 2 TIPOOS (or the equivalent number of channels) and/or up to 5D% of the LPRMs out-of-service is supported.

SietnetaPov"r-.orbnoation

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 1-4 110 100 90 80 la X

C.

70 60 50 40 30 20 10 0

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

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EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 2-1 2.0 Summary The determination of the thermal limits (MCPR limits and LHGRFAC multipliers) for LaSalle Unit 2 Cycle 9 is based on analyses of the limiting operational transients identified in Reference 9. Although the Reference 9 conclusions are based on I B-month cycles, the limiting operational transients identified remain valid for 24-month cycles. The transients evaluated are the generator load rejection with no bypass (LRNB), feedwater controller failure to maximum demand (FWCF) and loss-of-feedwater heating (LFWH). Thermal limts identified for Cycle 9 operation include both MCPR limits and LHGRFAC multipliers. The MCPR operating limits are established so that less than 0.1% of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions and are based on a two-loop operation MCPR safety limit of 1.11. LHGRFAC multipliers are applied directly to the LHGR limits at reduced power and/or flow conditions to protect against fuel melting and overstraining of the cladding during an AOO. Operating limits are established to support both base case operation and the EOOS scenarios presented in Table 1.1. Operating limits are also established for the EOD and combined EOD/EOOS conditions presented in Table 1.1.

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

Cycle 9 MCPRI, limits and LHGRFAC, multipliers for ATRIUM-9B fuel and MCPR, limits for GE9 fuel that support base case operation and operation in the EOD, EOOS and combined EODIEOOS scenarios are presented in Tables 2.1-2.4. Tables 2.1 and 2.2 present base case limits and multipliers for Technical Specifications scram speed (TSSS) insertion times and nominal scram speed (NSS) insertion times, respectively. Table 2.3 presents the limits and multipliers for coastdown operation. The combined FFTRlcoastdown limits and multipliers are identified in Table 2.4.

MCPRI limits for both ATRIUM-9B and GE9 that protect against fuel failures during a slow flow excursion event in manual flow control are presented in Figure 2.1. Automatic flow control is not supported for L2C9. The GE9 MCPRf limits include the effect of applying the MCPR penalty described in Reference 10. The MCPRI limits presented are applicable for all EOD and EOOS conditions presented in Table 1.1.

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 2-2 The Cycle 9 LHGRFAC1 multipliers for the ATRIUM-9B fuel are presented in Figure 2.2 and are applicable in all the EOD and EOOS scenarios presented in Table 1.1. Comparison of the Cycle 9 nodal power histories for the rated power pressurization transients with the approved bounding curves to show compliance with the 1% clad strain and centerline melt criteria for GE9 fuel is discussed in Reference 19.

The results of the maximum overpressurization analyses show that the requirements of the ASME code regarding overpressure protection are met for Cycle 9. The analysis shows that the dome pressure limit of 1325 psig is not exceeded and the vessel pressure does not exceed the limit of 1375 psig.

Si~Powercoprin

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 I

Page 2-3 Table 2.1 EOC Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times' EOOS EOD Power ATRIUM-9B Fuel GE9 Fuel Condition

(% rated)

MCPRp LHGRFACp MCPRp 0

2.70 0.78 2.70 Base 25 2.20 0.78 2.20 case 25 1.91 0.78 1.99 operation 60 1.46 1.00 1.52 100 1.A1 1.00 1.51 0

2.85 0.69 2.85 Feedwater 25 2.35 0.69 2.35 out-of-service 25 2.14 0.69 2.22 (FHOOS) 60 1.51 0.97 1.57 100 1.41 1.00 1.51 0

2.71 0.78 2.71 Single-loop 25 2.21 0.78 2.21 operation 25 1.92 0.78 2.00 (SLO) 60 1.47 1.00 1.53 100 1.42 1.00 1.52 0

2.70 0.76 2.70 Turbine 25 2.20 0.76 2.20 bypass valves 25 1.98 0.76 2.08 out-of-service (TBVOOS) 60 1.52 0.97 1.62 100 1.A3 0.99 1.52 0

Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 201F 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 powerMow map.

m

.,,c;.m

LaSalle Unit 2 Cycle 9 olfat" Tr~nc-sant Analhmia EMF-2440 Revision 0 Paae 2-4 a *a1 It & Idal

=1 iao

.~ -....

y Table 2.1 EOC Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times*

(Continued)

EOOSIE OD Power ATRIUM-9B Fuel GE9 Fuel Condition

(% rated)

MCPRp LHGRFACp MCPRp 0

2.70 0.78 2.70 Recirculation 25 2.20 0.78 2.20 pump trip 25 1.91 0.78 1.99 out-of-service 19

.819 (no RPT) 60 1.51 0.89 1.61 10D 1.51 0.89 1.61 0

2.70 0.70 2.70 Turbine control 25 2.20 0.70 2.20 valve (TCV) 25 2.10 0.70 2.10 slow closureso160.

19 AND/OR 60 1.69 0.66 1.95 no RPT 80 1.61 0.89 1.B4 100 1;53 0.89 1.63 0

2.85 0.68 2.85 TCV 25 2.35 0.68 2.35 slow closure/

25 2.14 0.68 2.22 FHOOS 80 1.69 0.86 1.95 no RPT 80 1.61 0.89 1.84 100 1.53 0.89 1.63 0

2.60 0.40 2.60 Idle 25 2.60 0.40 2.60 loop 25 2.60 0.40 2.60 startup 60 2.60 0.40 2.60 100 2.60 0.40 2.60 Umits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20F 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.

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 2.5 Table 2.2 EOC Base Case MCPRp Limits and LHGRFACP Multipliers for NSS Insertion Timese EOOS I EOD Power ATRIUM-9B Fuel GE9 Fuel Condition

(% rated)

MCPRp LHGRFACp MCPRp 0

2.70 0.79 2.70 Base 25 2.20 0.79 2.20 case 25 1.89 0.79 1.97 operation 60 1.44 1.00 1.51 100 1.39 1.00 1.48 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 De powerflfow map.

Sbmens Pov rtn

+- -

- -tJB.iYst

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Pae 2-6 Table 2.3 Coastdown Operation Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion' Times*

EOOS I EOD Power ATRIUM-98 Fuel GE9 Fuel Condition

(% rated)

MCPRp LHGRFACp MCPRp 0

2.70 0.75 2.70 Coastdown 25 2.20 0.75 2.20 base case 25 2.05 0.75 2.05 operation 60 1.48 0.99 1.54 100 1.42 1.00 1.52 0

2.71 0.75 2.71 Coastdown with 25 2.21 0.75 2.21 single-loop 25 2.06 0.75 2.06 operation 60 1.49 0.99 1.55 100 1.43 1.00 1.53 0

2.70 0.73 2.70 Coastdown with 25 2.20 0.73 2.20 turbine bypass valves 25 2.05 0.73 2.15 out-of-service 60 1.55 0.97 1.64 100 1.44 0.99 1.53 0

2.70 0.75 2.70 Coastdown with 25 2.20 0.75 2.20 recrculation pump trip 25 2.05 0.75 2.05 out-of-service 60 1.55 0.88 1.67.

(no__*_

100 1.55 0.88 1.67 Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equievaent number of TIP channels), up to a 20*F reduction in feedwater, and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.

Ait Pa r CogMm

LaSalle Unit 2 Cycle 9 Plantv Treneiant Aralvseic EMF-2440 Revision 0 Paae 2-7 I IUII L 1 *a01uu 7

Table 2.3 Coastdown Operation Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times (Continued)

EQOSIEOD Power ATRIUM-9B Fuel GE9 Fuel Condition

(% rated)

MCPRp-

LHGRFAC, MCPRp 0

2.70 0.68 2.70 Coastdown with 25 2.20 0.68 2.20 turbine control valve (TCV) 25 2.15 0.68 2.15 slow closure 0

1.70 0.85 1.96 noDRPT 80 1.62 0.88 1.85 100 1.55 0.88 1.67 0

2.60 0.40 2.60 Coastdown with 25 2.60 0.40 2.60 idle loop 25 2.60 0.40 2.60 startup 60 2.60 0.40 2.60 100 2.60 0.40 2.60 Urnits support operation wit any combination of 1 SRVOOS, up t 2 TIPOOS (or the equivalent number of TIP channels), up to a 200F reduction in feedwater temperature, and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the powerlflow map.

LaSalle Unit 2 Cycle 9 ns_-

A

^1; EMF-2440 Revision 0 Paae 2-8 PIant 1 ran5l5e tMCnaP dJYb Table 2.4 FFTRICoastdown Operation Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times*

EDOS EOD Power ATRIUM-9B Fuel GE9 Fuel Condition

(% rated)

MCPRp LHGRFACp MCPRP 0

2.85 0.65 2.85 FFTR/coastdown 25 2.35 0.65 2.35 base case 25 2.30 0.65 2.30 operation 60 1.56 0.97 1.59 100 1.42 1.00 1.52 0

2.86 0.65 2.86 FFTR/coastdown 25 2.36 0.65 2.36 with single-loop 25 2.31 0.65 2.31 operation 60 1.57 0.97 1.60 100 1.43 1.00 1.53 0

2.85 0.65 2.85 FFTR/coastdown 25 2.35 0.65 2.35 with turbine bypass valves 25 2.30 0.65 2.30 out-of-service 60 1.57 0.97 1.64 100 1.44 0.99 1.53 0

2.85 0.65 2.85 FFTR/coastdown 25 2.35 0.65 2.35 with recirculation pump trip 25 2.30 0.65 2.30 out-of-service 60 1.56 0.88 1.67 (no RPT) 100 1.55 0.88 1.67 Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.

eC._wb DrAr r'P.,uM4Iim

EMF-2440 Revision 0 Paae 2-9 LaSalle Unit 2 Cycle 9

__:_1 A __1 __-

Plant I ransent Analyrsis Table 2.4 FFTRlCoastdown Operation Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times (Continued)

EOOS / EOD Power ATRIUM-9B Fuel GE9 Fuel Condition

(% rated)

MCPRp LHGRFACp MCPRp 0

2.85 0.65 2.85 FFTR/coastdown 25 2.35 0.65 2.35 with turbine control 25 2.30 0.65 2.30 valve (TCV) slow closure 80 1.70 0.85 1.96 AnD/OR 80 1.62 0.88 1.85 100 1.55 0.88 1.67 0

2.60 0.40 2.60 FFTRlcoastdown 25 2.60 0.40 2.60 with idle 25 2.60 0.40 2.60 loop startup 60 2.60 0.40 2.60 100 2.60 OA0 2.60 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the powerlflow map.

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 2-1 0 0

10 20 30 40 SO 60 70 SW 60 100 110 Pbow 1 of fR_)

MCPRf GE9 Flow MCPRf (penalty

(% of rated)

ATRIUM-9B included) 0 1.60 1.66 30 1.60 1.66 105 1.11 1.11 Figure 2.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode Siefmen Power Comoraion

LaSalle Unit 2 Cycle 9 Olfztm Transentm Arkalvmie EMF-2440 Revision 0 Paoe 2-11 t

1*IL I 1 IZI I.

a A}

l Ti-I L) 32 40 50 60 70 Percent of Rated Flow Flow

(% rated)

LHGRFAC, 0

0.69 30 0.69 76 1.00 105 1.00 Figure 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-9B Fuel Sieme Power Corporation

EMF-2440 LaSalle Unit 2 Cycle 9 Revision D Plant Transient Analysis Page 3-1 3.0 Transient Analysis for Thermal Margin - Base Case Operation This section describes the analyses performed to determine the power-and flow-dependent MCPR and LHGR operating limits for base case operation at LaSalle Unit 2 Cycle 9.

COTRANSA2 (Reference 4), XCOBRA-T (Reference 11), XCOBRA (Reference 7) and CASMO-3GIMICROBURN-B (Reference 3) are the major codes used in the thermal limits analyses as described in SPC's THERMEX methodology report (Reference 7) and neutronics methodology report (Reference 3). COTRANSA2 is a system transient simulation code, which includes an axial one-dimensional neutronics model that captures the effects of axial power shifts associated with the system transients. XCOBRA-T is a transient thermal-hydraulics code used in the analysis of thermal margins for the limiting fuel assembly. XCOBRA is used in steady-state analyses. The ANFB critical power correlation (Reference 6) is used to evaluate the thermal margin of the fuel assemblies. Calculations have been performed to demonstrate the applicability of the ANFB critical power correlation to GE9 fuel at LaSalle using the Reference 12 methodology. Fuel pellet-to-cladding gap conductance values are based on RODEX2 (Reference 13) calculations for the LaSalle Unit 2 Cycle 9 core configuration.

3.1 System Transients System transient calculations have been performed to establish thermal limits to support L2C9 operation. Reference 9 identifies the potential limiting events that need to be evaluated on a cycle-specific basis. The potentially limiting transients for which SPC has analysis responsibility are the LRNB and FWCF events. Other transient events are either bound by the consequences of one of the limiting transients, or are part of ComEd's analysis responsibility.

Reactor plant parameters for the system transient analyses are shown in Table 3.1 for the 1 00%

power/1 00% flow conditions. Additional plant parameters used in the analyses are presented in Reference 8. Analyses have been performed to determine power-dependent MCPR and LHGR limits that protect operation throughout the powerlflow domain depicted in Figure 1.1. At LaSalle, direct scram and recirculation pump high-to low-speed transfer on turbine stop valve (TSV) and turbine control valve (TCV) position are bypassed at power levels less than 25% of rated. Reference 14 indicates that MCPR and LHGR limits need to be monitored at power levels greater than or equal to 25% of rated. As a result, all analyses used to establish base case MCPRp limits and LHGRFACp multipliers are performed with both direct scram and RPT operable for power levels at or above 25% of rated.

Sinw PFwer Cpon

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 3-2 The limiting exposure for rated power pressurization transients is at end of full power (EOFP) when the control rods are fully withdrawn. Off-rated power analyses were performed at earlier cycle exposures 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. 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 200F from the nominal feedwater temperature are considered base case operation, not an EOOS condition. As discussed in Reference 9, the reduced feedwater temperature is limiting for FWCF transients. As a result, the base case FWCF results are based on a 200F 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 scram speeds faster than the TSSS insertion times presented in Reference 14 scram speed-specific MCPRp limits and LHGRFACpmultipliers are provided. The NSS insertion times used in the analyses reported are presented in Reference 8 and reproduced in Table 3.2. The NSS MCPR, 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.

3.1.1 Load Reiection No Bvyass 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

-Qmanww Pnmr r-wnmration

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 3-3 increase in pressure causes a decrease in core void, 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 assumes 3-element feedwater level control; however, manual-or single-element feedw'ater level control will not significantly affect thermal limit or pressure results.

The generator load rejection without turbine bypass system (LRNB) is a more limiting transient than the turbine trip no bypass (TTNB) transient The initial position of the TCV is such that it closes faster than the turbine stop valve. This more than makes up for any differences in the scram signal delays between the two events. This has been demonstrated in calculations that support the Reference 9 conclusion that the TTNB event is bound by the LRNB event LRNB analyses were performed for several powerlflow conditions to support generation of the thermal limits. Table 3.3 presents the LRNB transient results for both TSSS and NSS insertion times for Cycle 9. 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%/6 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 will continue 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 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

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 3-4 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 powerlflow conditions to support generation of the thermal limits. Table 3.4 presents the base case FWCF transient results for both TSSS and NSS insertion times for Cycle 9. For illustration, Figures 3.4-3.6 are presented to show the responses of various reactor and plant parameters during the FWCF event initiated at 100% of rated power and 105% of rated core flow with TSSS insertion times.

3.1.3 Loss-of-Feedwater Heating ComEd has the analysis responsibility for the loss-of-feedwater heating (LFWH) event at rated conditions. At reactor power levels less than rated, the LFWH event is less limiting than the LFWH event at rated conditions for the following reasons:

At lower power/flow conditions with other core conditions such as control rod patterns and exposure unchanged, the initial MCPR is higher than the MCPR at rated power and flow. This results in additional MCPR margin to the MCPR safety limit.

The possible change in feedwater temperature during an LFWH event decreases as the reactor power decreases.

3.2 MCPR Safety Limit The MCPR safety limit is defined as the minimum value of the critical power ratio at which the fuel can be operated, with the expected number of rods in boiling transition not exceeding 0.1%

of the fuel rods in the core. The MCPR safety limit for all fuel in the LaSalle Unit 2 Cycle 9 core was determined using the methodology described in Reference 5. The effects of channel bow on core limits are determined using a statistical procedure. The mean channel bow is determined from the exposure of the fuel channels and measured channel bow data.

CASMO-3G is used to determine the effect on the local peaking factor distribution. Once the channel bow effects on the local peaking factors are determined, the impact on the core limits is determined in the MCPR safety limit analysis. Further discussion of how the effects of channel bow are accounted for is presented in Reference 5. The main input parameters and uncertainties used in the safety limit analysis are listed in Table 3.5. The radial power uncertainty includes the effects of up to 2 TIPOOS or the equivalent number of TIP channels (100% available at startup), up to 50% of the LPRMs out-of-service, and an LPRM calibration interval of 2500 EFPH as discussed in References 16 and 24. The channel bow local peaking

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis I

3-5 uncertainty is a function of the nominal and bowed local peaking factors and the standard deviation of the measured bow data.

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

Cycle 9 will not contain channels used for more than one fuel bundle lifetime.

The channel exposure at discharge will not exceed 48,000 MWd/MTU based on the fuel bundle average exposure.

The Cycle 9 core contains all CarTech-supplied channels.

Analyses were performed with input parameters (including the radial power and local peaking factor distributions) consistent with each exposure step in the design basis step-through. The analysis that produced the highest number of rods in boiling transition corresponds to a Cycle 9 exposure of 15,000 MWd/MTU. The radial power distribution corresponding to a Cycle 9 exposure of 15,000 MWd/MTU is shown in Figure 3.7. Eight fuel types were represented in the LaSalle Unit 2 Cycle 9 safety limit analysis: four SPC ATRIUM-9B fuel types loaded in Cycle 9 (SPCA9-391B-14G8.0-1O0M, SPCA9-41OB-19G8.D10DM, SPCA9-383B-16G8.G-10DM, and SPCA9-396B-12GZ-1 0DM); two ATRIUM-98 fuel types loaded in Cycle 8 (SPCA9-381B-13GZ7-80M and SPCA9-384B-GZ6-80M); and two GE9 fuel types loaded in Cycle 7 (GE91-P8CWB322-11GZ-10DM-150 and GE9B-P8CWB32O-9GZ-10DM-1IS).

The local power peaking factors, including the effects of channel bow, at 70% void and assembly exposures consistent with a Cycle 9 exposure of 15,000 MWdUMTU are presented in Figures 3.8 through 3.11 for the Cycle 9 SPC ATRIUM-9B fuel. The bowed local peaking factor data used in the MCPR safety limit analysis for fuel type SPCA9-391B-14GB.0-100M is at an assembly average exposure of 18,000 MWdIMTU. The data for fuel types SPCA94106-19G8.0-100M and SPCA9-383B-16G8.0-10OM is at an assembly average exposure of 17,500 MWdlMTU. The data is at an assembly average exposure of 15,000 MWdIMTU for fuel type SPCA9-396B-12GZ-100M.

The results of the analysis support a two-loop operation MCPR safety limit of 1.11 and a single-loop operation MCPR safety limit of 1.12 for all fuel types in the Cycle 9 core. These results are applicable for all EOD and EOOS conditions presented in Table 1.1 and support startup with uncalibrated LPRMs for an exposure range of BOC to 500 MWdIMTU.

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 3-6 3.3 Power-Dependent MCPR and LHGR Limits Figures 3.12 and 3.13 present the base case operation TSSS ATRIUM-9B and GE9 MCPRp limits for Cycle 9. Figures 3.14 and 3.15 present the ATRIUM-96 and GE9 MCPRp limits for base case operation with NSS insertion times. The limits are based on the,CPR results from the limiting system transient analyses discussed above and a MCPR safety limit of 1.11.

Relative to the TSSS MCPRp limits, using the faster NSS insertion times provide lower MCPRp limits.

The pressurization transient analyses provide the necessary information to determine appropriate multipliers on the fuel design LHGR limit for ATRIUM-9B fuel to support off-rated power operation. Application of the LHGRFACp multipliers to the steady-state LHGR limit ensures that the LHGR during AOOs 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-9B LHGRFACp multipliers for Cycle 9 TSSS and NSS insertion times are presented in Figures 3.16 and 3.17, respectively.

3.4 Flow-Dependent MCPR and LHGR Limits Flow-dependent MCPR and LHGR limits are established to support operation at off-rated core flow conditions. The limits are based on the CPR and heat flux changes experienced by the fuel during slow flow excursions. The slow flow excursion event assumes a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically attainable by the equipment. An uncontrolled increase in flow creates the potential for a significant increase in core power and heat flux. A conservatively steep flow run-up path was determined starting at a low-power/low-flow state point of 58.1 %P130%F increasing to the high-power/high-flow state point of 124.2%P/105%F.

MCPR, limits are determined for the manual flow control (MFC) mode of operation for both ATRIUM-9B and GE9 fuel. XCOBRA is used to calculate the change in critical power ratio during a two-loop flow rur-up to the maximum flow rate. The MCPRf limit is set so that the increase in core power resulting from the maximum increase in core flow is such that the MCPR safety limit of 1.11 is not violated. Calculations were performed for several initial flow rates to D,%~ fr~wrflatvin

EMF-2440 LaSalle Unit 2 Cycle 9 Revisin 0 Plant Transient Analysis Page 3-7 determine the corresponding MCPR values that put the limiting assembly on the MCPR safety limit at the high-flow condition at the end of the flow excursion.

Results of the MFC flow run-up analysis are presented in Table 3.6 for both the ATRIUM-9B and GE9 fuel. MCPRf limits that provide the required protection during MFC operation are presented in Figure 2.1. The Cycle 9 MCPRf limits were established such that they support base case operation and operation in the EOD, EOOS, and combined EODIEOOS scenarios. The MCPRf limits are valid for all exposure conditions during Cycle 9. Since a low-to high-speed pump upshift is required to attain high-flow rates, for initial core flows less than 30% of rated, the limit is conservatively set equal to the 3D% flow value. The MCPRf penalty described in Reference 10 has been applied to the GE9 MCPRf limits shown in Figure 2.1. The penalty is a function of core flow with a value of 0.0 at 100% of rated and increases linearly to 0.05 at 40%

of rated. The penalty continues to increase to 30% of rated core flow where a penalty of 0.06 is applied.

SPC has performed LHGRFACf analyses with the CASMO-3GIMICROBURN-B core simulator codes. The analysis assumes that the recirculation flow increases slowly along the limiting rod line to the maximum flow physically attainable by the equipment. A series of flow excursion analyses were performed at several exposures throughout the cycle starting from different initial powertflow conditions. Xenon is assumed to remain constant during the event. The LHGRFAC1 multipliers were established to ensure that the LHGR during the flow run-up does not violate the PAPT LHGR limit Since a low-to high-speed pump upshift is required to attain high-flow rates.

for initial core flows less than 30% of rated, the LHGRFACf multiplier is conservatively set equal to the 30% flow value. The LHGRFACf values as a function of core flow for the ATRIUM-9B fuel are presented in Figure 2.2. The Cycle 9 LHGRFAC, multipliers were established to support base case operation and operation in the EOD, EOOS, and combined EODIEOOS scenarios for all Cycle 9 exposure conditions.

3.5 Nuclear Instrument Response The impact of loading ATRIUM-91 fuel into the LaSalle core will not affect the nuclear instrument response. The neutron lifetime is an important parameter affecting the time response of the incore detectors. The neutron lifetime is a function of the nuclear and mechanical design of the fuel assembly, the in-channel void fraction, and the fuel exposure. The neutron lifetimes are similarfor the SPC and GE LaSalle fuel with typical values of 39(1O) to 40(10O) seconds siernes Power CorDoration

EMF-244D LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 3-8 for the ATRIUM-9B lattices and 41(104) to 43(106) seconds for the GE9 lattices as calculated with the CASMO-3G code at core average void and exposure conditions. Therefore, the neutron lifetimes for a full core of ATRIUM-9B fuel, a mixed core of ATRIUM-9B and GE9 fuel, and a full core of GE9 fuel are essentially equivalent Siemens Power Corpoion

LaSalle Unit 2 Cycle 9 pi-a Trin An~lv~ic EMF-2440 Revision 0 Paae 3-9 Fra 10 L lN l

l g-iu It57aIa Table 3.1 LaSalle Unit 2 Plant Conditions at Rated Power and Flow Reactor thermal power 3489 MWt Total core flow 108.5 Mlbmlhr Core active flow 93.7 Mlbm/hr Core bypass flow 14.8 Mlbmlhr Core inlet enthalpy 523.9 Btu/lbm Vessel pressures Steam dome 1001 psia Core exit (upper-plenum) 1013 psia Lower-plenum 1038 psia Turbine pressure 948 psia Feedwater / steam flow 15.145 Mlbmlhr Feedwater enthalpy 406.6 Btullbm Recirculating pump flow 15.83 Mlbmlhr (per pump)

Core average gap 1162 Btufhr*ft 2-°F coefficient (EOC)

Includes water channel flow.

_ Siem Power Comtalion

LaSalle Unit 2 Cycle 9 t1_oTe^n Aale&

EMF-2440 Revision 0 Paoe 3-10 Plan I ransMMI *,IELarval:>

Table 3.2 Scram Speed Insertion Times Control Rod TSSS NSS Position Time Time (notch)

(sec)

(sec) 48 (full-out) 0.000 0.000 48*

0.200*

0.200' 45 0.430 0.380 39 0.860 0.680 25 1.930 1.680 5

3.490 2.680 0 (full-in) 3.880 2.804 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 (Reference 22).

LaSalle Unit 2 Cycle 9 0l-n r--i.mnt Annhic.:

EMF-2440 Revision 0 Page 3-11 F-JO11L Table 3.3 EOC Base Case LRNB Transient Results Peak Peak Power/

ATRIUM-9B ATRIUM-9B GE9 Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR

(% rated)

(% rated)

TSSS Insertion Times 100 / 105 0.30 1.01 OAO 422 127 1001100 029 1.01 0.39 431 128 1DO /81 0.28 1.01 0.38 437 126 80 1105 0.29 1.04 0.39 324 100 801 57.2 0.29 1.05 0.39 265 96 60/105 0.27 1.06 0.36 245 73 60 /35.1 0.17 1.13 0.21 96 63 40 /105 0.23-1.13 0.27 10D*

46*

25/105 o.1r 1.22*

0.19*

44*

2r NSS Insertion Times 100/105 0.28 1.02 0.37 380 124 1 00/81 0.22 1.03 0.30 358 120 80/105 0.27 1.D4 0.36 302 98 80 / 57.2 0.20 1.09 0.26 218 90 60 / 105 0.26 1.07 0.35 236 73 60/35.1 0.13 1.18 0.14 76 60 40 /105 0.20 1.14 0.27 115 47 25 /105 0.15' 1.22 0.17 42*

27'

• The analysis results are from an earlier cycle exposure. The ACPR and LHGRFAC, results are conservatively used to establish the thermal limis.

EMF-2440 Revision 0 Paae 3-12 LaSalle Unit 2 Cycle 9

-_^A_l Plant Transient Analysis I

Table 3.4 EOC Base Case FWCF Transient Results Peak Neutron Peak Power/

ATRIUM-9B ATRIUM-9B GE9 Flux Heat Flux Flow ACPR LHGRFACp ACPR

(% rated)

(% rated)

TSSS Insertion Times 100/105 0.25 1.09 0.31 298 123 1001100 0.24 1.11 0.31 288 122 100/81 0.23 1.09 0.28 285 121 80 I 105 0.28 1.07 0.35 253 101 80 t57.2 0.19 1.16 0.23 154 91 601105 0.35*

1.02' 0.41 154-77' 60 /35.1 0.11 1.25 0.14 74 63 40/105 0.51*

0.94' 0.57' 104-58' 251 105 0.80-0.79' 0.88' 69r 44-NSS Insertion TImes 100/105 0.23 1.10 0.29 263 120 100/81 0.18 1.11 0.22 237 116 80 /105 0.27 1.10 0.33 235 99 80/57.2 0.15 1.20 0.17 131 88 60/105 0.33 1.05-0.40 188 79 60/35.1 0.11 1.28 0.13 65 63 40/105 0.48' 0.95*

0.55' 96' 57' 25/105 0.78' 0.79' 0.86' 66' 44-The analysis results are from an earlier cycle exposure. The ACPR and LHGRFACp results are conseratively used to establish the thermal limts.

Siemens Power Corporabon

LaSalle Unit 2 Cycle 9 ral__--&

^n A"

1-_

EMF-2440 Revision 0 Paoe 3-13 r'Wfla a r~l ansl rlmaa s*-a Table 3.5 Input for MCPR Safety Limit Analysis Fuel-Related Uncertainties Source Statistical Parameter Document Treatment ANFB correlation' ATRIUM-9B Reference 17 Convoluted GE9 Reference 12 Convoluted Radial power References 16 and 21 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' (Mlbmlhr) 22A 1.76 Convoluted Feedwater temperature ('IF) 426.5 0.76 Convoluted Core pressure (psia) 1031.35 0.50 Convoluted Total core flow (Mlbmlhr) 113.9 2.50 Convoluted Core power' (MWt)516729

• Additive constant uncertainties values are used.

I Feedwater flow rate and core power were increased above design values tD attain desired core MCPR for safety limit evaluation consistent with Reference 5 metodology CL..,.e Pvma_.

t vrowafi'n

LaSalle Unit 2 Cycle 9

-s__ -

A~l; EMF-2440 Revision 0 Page 3-14 Plant I ranslent PI IdlybI I

Table 3.6 Flow-Dependent MCPR Results 105%

Core, Maximum Core Flow Flow

(% rated)

GE9 ATRIUM-98 30 1.52 1.52 40 1.4 1.A6 50 1.41 1.42 60 1.37 1.38 70 1.31 1.32 80 1.26' 1.27 90 1.20 1.21 100 1.14 1.14 105 1.11 1.11

j. n.ane comUor rvnmr~ion

LaSalle Unit 2 Cycle 9 D01nt Trennemint Anniveie EMF-2440 Revision 0 Paoe 3-15 rFcVa I *CSaIS;t 0

IL 0

I-zIAJ U

0.

.0 1.0 20 0

4.0 TWE, SECONDS 5D Figure 3.1 EOC Load Rejection No Bypass at ID00105-TSSS Key Parameters cum.ne Pruo~ rbrw~wvmuIv

LaSalle Unit 2 Cycle 9 Dls-4+Ten Anmilmie EMF-2440 Revision 0 Paoe 3-16 r-ICxIIL 0Ix W

N En U) 0m z

J 3

LiJ

-J Lx 4:

>-J Lii U)

U)

TME, -SECONDS Figure 3.2 EOC Load Rejection No Bypass at 1001105-TSSS Vessel Water Level Siemens Power Cowporation v

I

LaSalle Unit 2 Cycle 9 EMF-2440 Revision C Paae 3-17 Plant Transient Analvysis rn 0.

U)

Lii in 0

I0 EL So TIME, SECONDS Figure 3.3 EOC Load Rejection No Bypass at 10 o105-TSSS Dome Pressure

LaSalle Unit 2 Cycle 9 rod_

__:_A r-elveie EMF-2440 Revision 0 Paoe 3-18

?-IBMt Iransi-FLem"nly so 0

IL 0

z ILi TIME, SECONDS Figure 3.4 EOC Feedwater Controller Failure at 1001105 -TSSS Key Parameters i

LaSalle Unit 2 Cycle 9 EMF-2440 Revision 0 Pane 3-19 Plant ranslern Analysis I

0 IT N

U) z IJ 0

Li

-J Ir

.-J Li U) in 150 TIME, SECONDS Figure 3.5 EOC Feedwater Controller Failure at 1001105-TSSS Vessel Water Level

^I_

Ifa_._ A

LaSalle Unit 2 Cycle 9 bIp#. Trreiwapnt Analvhic EMF-2440 Revision 0 Page 3-20 9e i A

l AL A AC3 B.- - ll6-w U)

En In IL 0

TIE, SECONDS Figure 3.6 EOC Feedwater Controller Failure at I 00D1 05-TSSS Dome Pressure Sioemm Power Corvombon

LaSalle Unit 2 Cycle 9 EMF-2440 Revision 0 Paoe 3-21 Plant 1 ransien Analysts I

200 175 150 un n

125 m

'o 100

.0 ED E

75 50 25 0

.0

.1

.3 A

.5

.6

.7

.8

.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radiol Power Peoking Figure 3.7 Radial Power Distribution for SLMCPR Determination C:-

M--

f

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Paae 322 C I 0

11 t

r 0

R 0

d C

0 r

n e

r nntrol Rod Corner 1.052 1.045 1.088 1.088 11.104 1.079 1.068 1.013 1.005 1.045 0.951 1.019 0.996 0.852 0.986 0.998 0.914 0.991 1.088 1.019 1.001 1.059 1.089 1.051 0.982 0.981 1.027 1.088 0.996 1.059 0.905 0.957 1.050 Internal 1.104 0.852 1.089 Water 1.068 0.807 1.035 Channel 1.079 0.986 1.051 1.025 0.942 1.039 1.06B 0.998 0.982 0.9D5 1.068 1.025 0.811 0.954 1.005 1.013 0.914 0.981 0.957 0.807 0.942 0.954 0.874 0.957 1.005 0.991 1.027 1.050 1.035 1.039 1.005 0.957 0.956 Figure 3.8 LaSalle Unit 2 Cycle 9 Safety Limit Local Peaking Factors SPCA-391B-14G8.0-I100M With Channel Bow (Assembly Exposure of 18,000 MWdIMTU)

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis I

Page 3-23 C

0 n

t r

0 R

0 d

C 0

r n

e r

0 n t r o I R o d C o r n e r 1.058 1.049 1.092 1.091 1.107 1.082 1.072 1.017 1.010 1.049 0.945 1.020 0.996 0.843 0.987 0.998 0.906 0.995 1.092 1.020 1.002 1.061 1.090 1.052 0.981 0.980 1.030 1.091 0.996 1.061 0.894 0.955 1.053 Internal 1.107 0.843 1.090 Water 1.067 0.797 1.036 Channel 1.082 0.987 1.052 1.024 0.941 1.041 1.072 0.998 0.981 0.894 1.067 1.024 0.800 0.952 1.007 1.017 0.906 0.980 0.955 0.797 0.941 0.952 0.865 0.960 1.010 0.995 1.030 1.053 1.036 1.041 1.007 0.960 0.960 Figure 3.9 LaSalle Unit 2 Cycle 9 Safety Limit Local Peaking Factors SPCA9410B-19G8.0-100M With Channel Bow (Assembly Exposure of 17,500 MWdIMTU)

LaSalle Unit 2 Cycle 9 A...... I.. _._

EMF-2440 Revision 0 Paoe 3-24 Plant 1 ranslent Analysis C

0 n

t r

0 R

0 d

C 0

r n

e r

o n t r o I R o d C o r n e r 1.017 1.017 1.068 1.083 1.107 1.074 1.048 0.985 0.970 1.017 0.986 1.024 1.000 0.885 0.992 1.004 0.956 0.965 1.068 1.024 0.890 1.063 1.091 1.055 0.990 0.989 1.009 1.083 1.OD0 1.063 0.944 0.966 1.055 Internal 1.107 0.885 1.091 Water 1.074 0.846 1.040 Channel 1.074 0.992 1.055 1.032 0.951 1.043 1.048 1.004 0.990 0.944 1.074 1.032 0.850 0.964 0.988 0.985 0.956 0.989 0.966 0.846 0.951 0.964 0.916 0.932 0.970 0.965 1.009 1.055 1.040 1.043 0.988 0.932 0.924 Figure 3.10 LaSalle Unit 2 Cycle 9 Safety Limit Local Peaking Factors SPCA9-383B-16G8.0-100M With Channel Bow (Assembly Exposure of 17,500 MWdIMTU)

LaSalle Unft 2 Cycle 9 DAPnnhilvse EMF-2440 Revision 0 Page 3-25 rFICI IL111IEII I

a aI C

0 n

t r

0 R

0 d

C 0

r n

e r

ontrol Rod Corner 1.025 1.058 1.062 1.117 1.100 1.108 1.043 1.026 0.979 1.058 0.934 1.018 0.852 1.003 0.845 0.999 0.903 1.005 1.062 1.018 1.003 1.067 1.092 1.058 0.984 0.983 1.006 1.117 0.852 1.067 1.046 0.823 1.056 Internal 1.100 1.003 1.092 Water 1.072 0.968 1.039 Channel 1.108 0.845 1.058 1.038 0.816 1.046 1.043 0.999 0.984 1.046 1.072 1.038 0.965 0.963 0.986 1.026 0.903 0.983 0.823 0.968 0.816 0.963 0.873 0.973 0.979 1.005 1.006 1.056 1.039 1.046 0.986 0.973 0.933 Figure 3.11 LaSalle Unit 2 Cycle S Safety Limit Local Peaking Factors SPCA9-396B-12GZ-10DM With Channel Bow (Assembly Exposure of 15,000 MWdMTU)

EMF-2440 Revision 0 Page 3-26 LaSalle Unit 2 Cycle 9

_. ~~

__F A

Plant -Transienl Ana sIs 2.15 2.05 1.35 1.75

.15 IAS 1.25 1.25 1.15 0

10 20 X

40 50 OD 70 s0 90 10 110 PCrI% of RN%

Power MCPRp

(%)

Limit 100 1.41 60 1.46 25 1.91 25 2.20 0

2.70 Figure 3.12 EOC Base Case Power-Dependent MCPR Limits for ATRUM-9B Fuel - TSSS Insertion Times as~CW.

(rowmw~

EMF-2440 LaSalle Unit 2 Cycle 9 Pane 3o27 Plant Transient Analysis I

0 10 20 30 40 50 K

70 so SO 100 110 Pur N d Rad)

Power MCPRp

(%)

Limit 100 1.51 60 1.52 25 1.99 25 2.20 0

2.70 Figure 3.13 EOC Base Case Power-Dependent MCPR Limits for GE9 Fuel - TSSS Insertion Times c biDor rhownnrwn

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 3-28 I

0 10 20 30 40 so s0 70 s0 so 100 110 Pomr M of Red)

Power MCPRp

(%)

Limt 100 1.39 60 1.44 25 1.89 25 2.20 0

2.70 Figure 3.14 EOC Base Case Power-Dependent MCPR Limits for ATRUM-9B Fuel - NSS Insertion limes

LaSalle Unit 2 Cycle 9 Dlsntv% rrsftnei~r% Annhms'te EMF-2440 Revision 0 Paqe 3-29 I Ica II II ED agoT Ilk A* as_

2.55' 245 225 215

. 2.05 1.35 1.75 1.15 1.55 lAS 1.25 0

10 2D 20 40 50 so 70 so 90 1M 110 Polmre (%f d Rug Power MCPRP

(%)

Limit 100 1.48 60 1.51 25 1.97 25 2.20 0

2.70 Figure 3.15 EOC Base Case Power-Dependent MCPR Limits for GE9 Fuel - NSS Insertion Times Sinem Power Corpon

LaSalle Unit 2 Cycle 9 Plant" TYgrse'apnt Analvhic EMF-2440 Revision 0 Paoe 3-30 I

I4I L

I I Iu5 a

-F '*

1.20 125 1.0~

1.15 1.10 L 1.006 OAS aILR I

U W:

U-Ua W

0.30 0.75 0.70 0.5 0.60 0

10 20 30 40 SO 00 To 80 90 100 110 Perl)

Power LHGRFACp

(%)

Multiplier 100 1.00 60 1.00 25 0.78 25 0.78 0

0.78 Figure 3.16 EOC Base Case Power-Dependent LHGR Multipliers for ATRUM-9B Fuel - TSSS Insertion Times sonwm Per c

_men

LaSalle Unit 2 Cycle 9 I-u_-_

A--I.._

EMF-2440 Revision 0 Paae 3-31 Plard I ransient AnalysisI LI 3

0 10 20 30 40 so 60 TO so s0 100 110 Pewnr.M-)

Power LHGRFACp

(%)

Multiplier 100 1.00 60 1.00 25 0.79 25 0.79 0

0.79 Figure 3.17 EOC Base Case Power-Dependent LHGR Multipliers for ATRUM-98 Fuel - NSS Insertion Times a.m; DCr.g.*.rejwyw ainn

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 4-1 4.0 Transient Analysis for Thermal Margin - Extended Operating Domain This section describes the development of the MCPR and LHGR limits to support operation in the following extended operating domains:

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

Power coastdown to 40% of rated power.

Final feedwater temperature reduction (FFTR) of up to 100°F and with ICF. Since IFT is typically used in connection with coastdown, analyses were performed to support combined FFTR/coastdown operation.

Results of the limiting transient analyses are used to determine appropriate MCPRp limits and LHGRFACp multipliers for ATRIUM-9B and GE9 fuel to support operation in the EOD scenarios.

MCPRp limits are established for both ATRIUM-9B and GE9 fuel while LHGRFACp multipliers are onlyestablished for the ATRIUM-9B fuel.

As discussed in Reference 9, the MCPR safety limit analysis for the base case remains valid for operation in the EODs discussed below. Also, the flow-dependent MCPR and LHGR analyses described in Section 3.4 were performed such that the results are applicable for all the EODs.

4.1 Increased Core Flow The base case analyses presented in Section 3.0 were performed to support operation in the powerlflow domain presented in Figure 1.1, which includes operation in the ICF region. The coastdown and combined FFTRlcoastdown analyses are performed in conjunction with ICF to conservatively maximize the exposure at which a given power level can be attained. As a result, the analyses performed support operation in the ICF extended operating domain for all exposures.

42 Coastdown Analysis Coastdown analyses were performed to ensure that appropriate MCPRp limits and LHGRFACp multipliers are applied to support coastdown operation. The analyses were performed for coastdown operation to 40% of rated power using a conservative coastdown rate equivalent to a 10% decrease in rated power per 1000 MWdIMTU increase in exposure. An additional 1000 MWdcUTU was added to the EOFP exposure prior to the start of coastdown to provide operation support for operation at up to 10% of rated power above the equilibrium xenon coastdown power level. The MCPRp limits and LHGRFACp multipliers are based on results of

EMF-244D LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 4-2 LRNB and FWCF analyses. The analyses were performed at cycle exposures consistent with the assumed coastdown rate. This corresponds to the highest exposure at whiz the power can be obtained. The base case coastdown ACPRs for both the ATRIUM-9B and GE9 fuel as well as the ATRIUM-9B LHGRFACp results are presented in Table 4.1 for the indicated powerfilow conditions. The ATRIUM-S9B MCPRp limits and LHGRFACp multipliers for coastdown operation are presented in Figures 4.1 and 4.2. The GE9 coastdown MCPRp limits are presented in Figure 4.3.

4.3 Combined Final Feedwater Temperature Reduction/Coastdown Analyses were performed to support FFTR with thermal coastdown to ensure that appropriate MCPRp limits and LHGRFAC, multipliers are established. The combined "F I coastdown analysis used a 1 00F feedwater temperature reduction applied at EOFP to extend full thermal power operation. The coastdown exposure extension discussed in Section 42 (1000 MWd/MTU to support operation at up to 10% of rated power above the equilibrium xenon power level) was then applied. LRNB and FWCF analyses were performed to establish MCPRN limits and LHGRFAC, multipliers. The Cycle 9 FFTRicoastdown ACPR results for both ATRIUM-9B and GE9 fuel as well as the LHGRFACp results are presented in Table 4.2 for the indicated power flow conditions. The ATRIUM-9B MCPRp limits and LHGRFACp multipliers for combined FFTRlcoastdown operation are presented in Figures 4.4 and 4.5. The GE9 coastdown MCPRp limits are presented in Figure 4.6.

LaSalle Unit 2 Cycle 9 rn 1~

EMF-244D Revision 0 Pame 4-3 Plant Iransentm,nlysis Table 4.1 Coastdown Operation Transient Results Power/ Flow ATRIUM GE9

(% rated I Event

% rated)

&CPR LHGRFACp ACPR LRNB 100 1 105 0.31 1.00 0.41 LRNB 80 /105 0.32 1.00 0.35 LRNB 60 / 105 0.31 0.99 0.35 LRNB 40 1105 0.31 0.96 0.31 LRNB 25 / 105 0.19 1.13 0.19 FWCF 100 1105 0.26 1.08 0.32 FWCF 80 1 105 0.29 1.08 0.31 FWCF 60 /105 0.34 1.08 0.36 FWCF 40 /105 0.44 1.12 0.44 FWCF 25 105 0.86 1.08 0.58

EMF-2440 Revision 0 Page 4-4 LaSalle Unit 2 Cycle 9 9__*_

____4A--t..-:-

-ant I ransient Analysis Table 4.2 FFTRICoastdown Operation Transient Results Power/ Flow ATRIUM GE9

(% rated I Event

% rated)

ACPR LHGRFACp ACPR LRNB 100 / 105 026 1.04 0.29 LRNB 80 105 0.25 1.04 0.30 LRNB 60 /105 027 1.01 0.28 LRNB 40 /105 0.25 0.99 0.25 LRNB 25 /105 0.14 1.18 0.15 FWCF 100 /105 0.26 1.09 0.28 FWCF 80 1 105 0.30 1.09 0.33 FWCF 60 /105 0.37 1.09 0.40 FWCF 40 / 105 0.50 1.07 0.50 FWCF 25/105 1.10 0.95 1.12

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 5 Plant Transient Analysis age 0

10 20 X

40 50 so 70 30 90 so 110 POWr (% of RMu Power MCPRp

(%)

Limit IOD 1.42 60 1A8 25 2.05 25 2.20 0

2.70 Figure 4.1 Coastdown Power-Dependent MCPR Limits for ATRUM-9B Fuel

LaSalle-Unit 2 Cycle 9 n~l__-

r;,-nhr EMF-2440 Revision 0 Page 4-6 TWrai I IdIIWIIIL ruaaany-&Q CL 0

If 20 30 40 so so 70 so 90 100 110 PrWer of Ratm Power LHGRFACV

(%)

Multiplier 100 1.00 60 0.99 25 0.75 25 0.75 0

0.75 Figure 4.2 Coastdown Power-Dependent LHGR Multipliers for ATRUM-9B Fuel Siemens Power Coroaton

LaSalle Unit 2 Cycle 9 MIAm_

___A li EMF-2440 Revision 0 Paoe 4-7 lwInt I ldIbIUM IiaLsYOi I

Ic 0

10 20 30 40 50 so 70 s0 90 100 110 POWW M of Red)

Power MCPRN

(%)

Limit 100 1.52 60 1.54 25 2.05 25 2.20 0

2.70 Figure 4.3 Coastdown Power-Dependent MCPR Umits for GE9 Fuel

.cmidme Pnawmr A

xrwnrwtim

LaSalle Unit 2 Cycle 9 Dl_"t Tr Arkft nhtete-EMF-2440 Revision 0 Page 4-8 rI It U ma.

I&moa if.

_-u _

285 2.75 2Mfi Uss 25 225 215 E 2.05 X~a I 0

10 20 30 40 50 50 70 so 90 10 11 Sud Bd Power MCPRp

%)

Limt 100 1.42 60 1.

25 2.30 25 2.35 0

2.85 Figure 4.4 FFTRlCoastdown Power-Dependent MCPR Limits for ATRUM-9B Fuel Siemens Power Comoration

LaSalle Unit 2 Cycle 9

__-^

EMF-2440 Revision 0 Page 4-9 Plant I ransien Analysis a} am

a. 1.lo o.r 0

10 20 X

40 SO 60 P Wm (%o iRd) 70 60 30 1

110 Power LHGRFACp

(%)

Multiplier 100 1.00 60 0.97 25 0.65 25 0.65 0

0.65 Figure 4.5 FFTRlCoastdown Base Case Power-Dependent LHGR Multipliers for ATRUM-SB Fuel

LaSalle Unit 2 Cycle 9 al__-

A__-

~lwi EMF-2440 Revision 0 Pame 4-10 r1'mi *rnia"

.u bt:Iru maIy.YO a.

0 10 2D 30 40 s0 W0 70 W0 90 100 110 Po(%ofPR)

Power MCPRp

()

Limit 100 1.52 60 1.59 25 2.30 25 2.35 0

2.85 Figure 4.6 FFTRlCoastdown Power-Dependent MCPR Limrts for GE9 Fuel r1

EMF-2440 Revision 0 LaSalle Unit 2 Cycle 9 Pane 5-0 Plant Transient Analysis 5.0 Transient Analysis for Thermal Margin - Equipment Out-of-SerVice This section describes the development of the MCPR and LHGR operating limits to support operation with the following EOOS scenarios:

Feedwater heaters out-of-service (FHOOS) - 1 000F feedwater temperature reduction.

1 recirculation pump loop (SLO).

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

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

Slow closure of I or more turbine control valves.

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

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

As discussed in Reference 9, the base case MCPR safety limit for two-loop operation remains applicable for operation in the EOOS scenarios discussed below with the exception of single-loop operation. Also, the flow-dependent MCPR and LHGR analyses described in Section 3.4 were performed such that the results are applicable in all the EOOS scenarios.

5.1 Feedwater Heaters Out-of-Service (FHOOS)

The FHOOS scenario assumes a 1000F reduction in the feedwater temperature. Operation with FHOOS is similar to operation with FFTR except that the reduction in feedwater temperature due to FHOOS can occur at any time during the cycle. The effect of the reduced feedwater temperature is an increase in the core subcooling which can change the power shape and core void fraction. While the LRNB event is less severe due to the decrease in steam flow, the FWCF event can get worse due to the increase in core inlet subcooling. FWCF analyses were performed for Cycle 9 to determine thermal limits to support operation with FHOOS. The ACPR and LHGRFACp results used to develop the EOC operating limits with FHOOS are presented in Table 5.1. The EOC MCPRp limits and LHGRFACp multipliers for ATRIUM-9B fuel for FHOOS

EMF-2440 LaSalle Unit 2 Cycle 9 Revtsion 2 Plant Transient Analysis Page 52 operation are presented in Figures 5.1 and 52, and the EOC FHOOS GE9 MCPRp limits are presented in Figure 5.3.

5.2 Single-Loop Operation (SLO) 52.1 Base Case Operation The impact of SLO at LaSalle on thermal limits was presented in Reference 9. The only impact is on the MCPR safety limit. As presented in Section 3.2, the single-loop operation safety limit is 0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The base case ACPRs and LHGRFACp multipliers remain applicable. The net result is an increase to the base case MCPRp limits of 0.01 as a result of the increase in the MCPR safety limit.

522 Idle LooD Startup The MCPRp limits and LHGRFACp multipliers for the startup of an idle recirculation pump are based on the results of the abnormal startup of the idle recirculation loop analysis and the SLO MCPR safety limit analysis. As discussed in Section 3.2, the single-loop operation safety limit is 1.12 or 0.01 higher than the two-loop operation limit. The process used for the abnormal startup of the idle recirculation loop analysis for L2C9 is presented in Reference 20. The responses of the system parameters for the L2C9 analysis are consistent with those presented in Reference

20. The Reference 20 results demonstrated that the lowest power (35%P147%F) conditions provide conservative results. Subsequently, the L2C9 analyses were performed at 35%P/47%F.

The limiting exposure was determined to be BOC. The &CPR and LHGRFACp results for the abnormal startup of the idle recirculation loop are presented in Table 52. Figures 5.4 and 5.5 present the ATRIUM-9B MCPRp limits and LHGRFACp multipliers for idle loop startup. The GE9 MCPRp limits for idle loop startup are presented in Figure 5.6.

5.3 Turbine Bypass Valves Out-of-Service (TBVOOS)

The effect of operation with TBVOOS is a reduction in the system pressure relief capacity, which makes the pressurization events more severe. While the base case LRNB event is analyzed assuming the turbine bypass system out-of-service, operation with TBVOOS has an effect on the FWCF event The FWCF event was evaluated for LaSalle Unit 2 Cycle 9 to support operation with TBVOOS. The ACPR and LHGRFACp results used to develop the EOC operating limits with TBVOOS are presented in Table 5.3. The EOC MCPR, limits and LHGRFACp cmn;t Pa cnmorwIM

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 5-3 multipliers for ATRIUM-9B fuel for TBVOOS operation are presented in Figures 5.7 and 5.8, and the EOC TBVOOS GE9 MCPRp limits are presented in Figure 5.9.

5.4 Recirculation Pump Trip Out-of-Service (No RP1)

This section summarizes the development of the thermal limits to support operation with the EOC RPT inoperable. When RPT is inoperable, no credit for tripping the recirculation pump on TSV position or TCV fast closure is assumed. The function of the RPT feature is to reduce the severity of the core power excursion caused by the pressurization transient The RPT accomplishes this by helping revoid the core, thereby reducing the magnitude of the reactivity insertion resulting from the pressurization transient Failure of the RPT feature can result in higher operating limits because of the higher positive reactivity in the core at the time of control rod insertion.

Analyses were performed for LRNB and FWCF events assuming no RPT. The ACPR and LHGRFACp results used to develop the EOC operating limits with no RPT are presented in Table 5.4. The EOC MCPRp limits and LHGRFACp multipliers for ATRIUM-98 fuel for operation with no RPT are presented in Figures 5.10 and 5.11, and the EOC no RPT GE9 MCPRp limits are presented in Figure 5.12.

5.5 Slow Closure of the Turbine Control Valve LRNB analyses were performed to evaluate the impact of a TCV slow closure. Analyses were performed closing 3 valves in the normal fast closure mode and I valve in 2.0 seconds. Results provided in Reference 23 demonstrate that performing the analyses with 1 TCV closing in 2.0 seconds protects operation with up to 4 TCVs closing slowly. Sensitivity analyses below 80% power have shown that the pressure relief provided by all 4 TCVs closing slowly can be sufficient to preclude the high-flux scram set point from being exceeded. Therefore, credit for high-flux scram is not taken for analyses at 80% power and below. The 80% power TCV slow closure analyses were performed both with and without high-flux scram credited. The ACPR and LHGRFACp results of the analyses performed are presented in Table 5.5.

The MCPRp limits and LHGRFACp multipliers are'established with a step change at 80% power.

At 80% power, the lower-bound MCPRp limits and upper-bound LHGRFACp multipliers are based on the analyses which credit high-flux scram; the upper-bound MCPRp limits and lower-bound LHGRFACp multipliers are based on analyses which do not credit high-flux scram. While

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 5&4 the TCV slow closure analysis is performed without RPT on valve position, It does not necessarily bound the LRNB no RPT or FWCF no RPT events at all power levels because the slow closing TCV provides some pressure relief until it completely closes. Therefore, the MCPRp limits and LHGRFACp multipliers for the TCV slow closure EOOS scenario are established using the limiting of the no RPT results reported in Section 5.4 and the TCV slow closure results.

The EOC MCPRp limits and LHGRFACp multipliers for ATRIUM-9B fuel for operation with TCV slow closure are presented in Figures 5.13 and 5.14 and the EOC TCV slow closure GE9 MCPRp limits are presented in Figure 5.15. The limits presented in Figures 5.13 through 5.15 protect the scenario of all 4 TCVs closing slowly.

5.6 Combined FHOOSITCV Slow Closure ndoar No RPT MCPRp limits and LHGRFACp multipliers were established to support operation with FHOOS.

TCV slow closure and/or no RPT. The TCV slow closure &CPR and LHGRFACp results with FHOOS become less limiting than the TCV slow closure event with nominal feedwater temperature since the initial steam flow with FHOOS is lower and produces a less severe pressurization event. Subsequently, no TCV slow closure with FHOOS analyses were performed. The TCV slow closure results with nominal feedwater temperature are considered in determining the combined FHOOSITCV slow closure and/or no RPT MCPRp limits and LHGRFACp multipliers. The limits were developed based on the limiting of either the TCV slow closure analysis results discussed in Section 5.5 or the analyses with both FHOOS and no RPT presented in Table 5.6.

The EOC MCPRp limits and LHGRFACp multipliers for ATRIUM-9B fuel with FHOOSJTCV slow closure and/or no RPT are presented in Figures 5.16 and 5.17, and the EOC GE9 MCPRp limits for the same EOOS scenario are presented in Figure 5.18. The limits presented in Figures 5.16 through 5.18 protect the scenario of all 4 TCVs closing slowly.

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 i

Page 5-5 Table 5.1 EOC Feedwater Heater Out-of-Service Analysis Results Power/ Flow ATRIUM GE9

(% rated /

Event

% rated)

ACPR LHGRFACp ACPR FWCF 100 / 105 0.26 1.08' 0.31 FWCF 100/81 0.23 1.11 0.28 FWCF 80 /105 0.30 1.03' 0.36 FWCF 60 1105 0.40' 0.97s 0.464 FWCF 40/105 0.62*

0.87' 0.69o FWCF 25/105 1.03*

0.69*

1.11-The analysis results presented are from an earlier cycle exposure. The,CPR and LHGRFACp results are conservatively used to establish the thermal limits.

I,werCorvort-on

EMF-2440 Revision 0 Pane 5-6 LaSalle Unit 2 Cycle 9 Plant Transient Analysis Table 6.2 Abnormal Recirculation Loop Startup Analysis Results Power I Flow FCV ATRIUM-9B

(% rated I Position TC PR

% rated)

________FAC 35 /47 27% open a

ACPR results for ATRIUM-9B fuel are conservatvely applicable for GE fuel.

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

EMF-2440, Revision 0 Paoe 5.7 LaSalle Unit 2 Cycle 9 Plant Transient Analysis Table 5.3 EOC Turbine Bypass Valves Out-of-Service Analysis Results Power I Flow ATRIUM GE9

(% rated I Event

% rated)

ACPR LHGRFACp ACPR FWCF 100 /105 0.32 1.02 0.41 FWCF 100/81 0.31 0.99 0.41 FWCF 80/ 105 0.35 1.00*

0.45 FWCF 80 /57.2 0.31 1.05 0.41 FWCF 60/105 0.41*

0.9r 0.51 FWCF 60135.1 0.18 1.14 0.25 FWCF 40/105 0.58*

0.90' 0.668 FWCF 251105 0.87*

0.76*

0.97' The analysis results presented are from an earlier cycle exposure. The &CPR and LHGRFACp results are conservatively used to establish the thermal limits.

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 PaQe 58 Table 5.4 EOC Recirculation Pump Trip Out-of-Service Analysis Results Power I Flow ATRIUM GE9

(% rated /

Event

% rated)

ACPR LHGRFACp ACPR LRNB 100 1105 0.40 0.89 0.50 LRNB 100181 0.32 0.91 0.47 LRNB 80/105 0.35 0.94 0.47 LRNB 80/57.2 0.30 0.97 0.44 LRNB 60/105 0.32 0.99 0.44 FWCF 100/105 0.31 0.97 0.40 FWCF 100/81 0.26 0.99 0.35 FWCF 80/105 0.33 1.00' 0.43 FWCF 60/105 0.38 0.9r OA8 FWCF 401105 0.51*

0.91' 0.59' FWCF 25 /105 0.78' 0.79' 0.87*

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

SmnI, f Skimnr&mT~

Poftion

EMF-2440 Revision 0 Pane 5-9 LaSalle Unit 2 Cycle 9 Plant Transient Analysis Table 5.5 EOC Turbine Control Valve Slow Closure Analysis Results Slow Power J Flow ATRIUM-9B GE9 Valve

(% rated I Event Characteristics

% rated)

ACPR LHGRFACp hCPR LRNB I TCV closing at 2.0 sec 100/105 0.42 0.93 0.52 LRNB I TCV closing at 2.0 sec 100/ 81 0.33 0.97 0.49 LRNB 1 TCV closing at 2.0 see 80/ 105 0.40 0.96 0.49 LRNB I TCV closing at 2.0 sec 80157.2*

0.50 0.97 0.73 LRNB 1 TCV closing at 2.0 sec 80/1W 0.52 0.86O 0.62 LRNB 1 TCV closing at 2.0 sec 80 / 57.2" 0.58 0.9?

0.84 LRNB 1 TCV closing at 2.0 sec 6011051 0.61*

0.83*

0.71$

LRNB I TCV closing at 2.0 sec 60/ 35.11t 0.63W 0.94 0.86 LRNB I TCV closing at 2.0 sec 40 /105t 0.78 0.77$

0.84 LRNB I TCV closing at 2.0 sec 251 1051 0.99 0.70*

0.97s Scram inifiated by high-neutron flux.

I Scram inatited by high dome pressure s The analysis results presented are from an earlier cycle exposure. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.

EMF-2440 Revision 0 Page 5-10 LaSalle Unit 2 Cycle 9 Plant I ransiVem Mnalysiso Table 5.6 EOC Recirculation Pump Trip and Feedwater Heater Out-of-Service Analysis Results Power I Flow ATRIUM-9B GE9

(% rated I Event

% rated)

&CPR LHGRFACp ACPR FWCF 1001105 0.30 0.98 0.39 FWCF 100/81 0.25 1.03 0.33 FWCF 80/105 0.35 0.98*

OA3 FWCF 60/105 0.42 0.94 0.51 FWCF 401105 0.61' 0.55*

0.70C FWCF 251105 1.01-0.68*

1.09

.I The analysis results presented are from an earlier cycle exposure. The hCPR and LHGRFACp results are conservatively used to establish the thermal limits.

LaSalle Unit 2 Cycle 9 rb--LTeon Andftlvoem EMF-2440 Revision 0 Page 5-1I rriat I d!

I' i1 Guyana 245 235' 225'

• , 115 c2U X-2X5 E 1is 1.25 1.75 Is

'IS IAS 1'6 125 448 A.;

0 10 2D 30 40 50 o0 70 so 9o POMr (% d RMO IOD 110 Power MCPRp

(%)

Limit 100 1.41 60 1.51 25 2.14 25 2.35 0

2.85 Figure 5.1 EOC Feedwater Heaters Out-of-Service Power-Dependent MCPR ULmits for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 5-12 0

a.

SI a

10 20 30 40 50 60 70 00 s0 100 110 Por

(%cIf t d)

Power LHGRFACp

(%)

Multiplier 100 1.00 60 0.97 25 0.69 25 0.69 0

0.69 Figure 6.2 EOC Feedwater Heaters Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 to-__

Ah EMF-2440 Revision 0 Paae 5-13 riant I ransiet Analysi._

eL a.

Af-0 10 20 30 40 50 O

70 so 90 100 110 PWN Rad)

Power MCPRp

(%)

LinIt 100 1.51 60 1.57 25 2.22 25 2.35 0

2.85 Figure 5.3 EOC Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 5-14 9 A-r -

25 2AS 215 2055 E1M 1.75 145 1.55 135 1.15 I

kF L_1 I -

OLPCR a

10 29 30 40 so 60 Pwr (%ofRd) 70 30 3

100 110 Power MCPRp

(%)

Umit 100 2.60 6D 2.60 25 2.60 25 2.60 0

2.60 Figure 6A Abnornal Idle Recirculation Loop Startup Power-Dependent MCPR Limits for ATRIUM-9B Fuel Q.....

Do aae a

of.n un ruHA

EMF-2440 Revision 0 Paqe 5-IS LaSalle Unit 2 Cycle 9 f-lidn 1IIZ~.I rnLenz InIyOI I

1.25

.20, 1.15 1.10 1.05 1.00 0A5 a 0.30 0J0 0.75 0.70 O5 0.3 0.55 r

i I

• -Me Leap RnSn I 1 -LHGRFAC oxS a

.. I a

10 20 30 40 50 so T0 so 90 100 l10 Power d%

af r Power LHGRFACp

(%/6)

Multiplier 100 0.40 60 0.40 25 0.40 25 0.40 0

0.40 Figure 6.5 Abnormal Idle Recirculation Loop Startup Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel Siem Power Corporation

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 5-16 t5 Mr.

2.45 2.15 205 D.

1.75 1.5 lAS 1.35 125 a

i e Lop Ro

-OLL.R 1.15 ',

0 l0 2D 30 40 10 e

Powerp o ROe 70 00 s0 100 110 Power MCPRp

(%)

Limit 100 2.60 60 2.60 25 2.60 25 2.60 0

2.60 Figure 5.6 Abnonmal Idle Recirculation Loop Startup Power-Dependent MCPR Limits for GE9 Fuel

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 5-17 2.45 2Z6 2MU 2.15 1.5 1.75 lAS 1.5 0

10 20 30 40 SO so 70 o0 90 100 110 PaW 1% d MadO Power MCPRp

(%)

Limit 100 1.43 60 1.52 25 1.98 25 2.20 0

2.70 Figure 5.7 EOC Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 Dln T4r~;ncint Anntuese EMF-2440 Revision 0 Paae 5-18 rgaul I iscxIsol*a.

a 0

4c I2; 0

l0 20 30 40 SO G0 70 80 90 100 110 Pevar (% o Rd)

Power LHGRFACp

(%)

Multiplier 100 0.99 60 0.97 25 0.76 25 0.76 0

0.76 Figure 5.8 EOC Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel

n CDo~

roewwwrit

LaSalle Unit 2 Cycle 9 rbal,l an:lvl. 8Anlveie EMF-2440 Revision 0 Paoe 5-19 I MI IL I I CII EItI

".9-~

CL 1.3 155 1.75 155 1.35 125 0

10 2D 30 40 50 60 70 00 g0 100 110 Power MCPRO

(%)

Umit 100 1.52 60 1.62 25 2.08 25 2.20 0

2.70 Figure 5.9 EOC Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for GES Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 5-20 21U 1.18 1.75

.X5 0

10 2D 30 40 50 0

70 K

s0 1X0 110 p

do R

Power MCPRp

(%)

Litn 100 1.51 60 1.51 25 1.91 25 2.20 0

2.70 Figure 6.10 EOC Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 5-21 40'I'.

U0, 1.15.

1.10 I

I

• FWAMF LUHGACp

..a

~03 0

S W 1.00.

I0.30 5 a,0 0.30 0.75 0.70 0.65 aln 0

10 20 30 40 50 0

70 O0 W

100 110 POerM Power LHGRFACp

(%)

Multiplier 100 0.89 60 0.89 25 0.78 25 0.78 0

0.78 Figure 5.11 EOC Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel Siemes Power Corpomaon

LaSalle Unit 2 Cycle 9 Dra Tne-r A-I.M&W.

EMF-2440 Revision 0 Pace 5-22 riouI I i

4IUDfIVuL I*U IO N

0 tO 20 30 40 so o

70 s0 90 100 110 Pest (%d IN d Power MCPRO

(%)

UnIt 100 1.61 60 1.61 25 1.99 25 2.20 0

2.70 Figure 6.12 EOC Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel

LaSalle Unit 2 Cycle 9 PIlat Trouneient Anagvskh EMF-2440 Revision 0 Pane 5-23 I 14PI IL 4 I --

1 -

a.

a.

I.,1a a

10 20 30 40 50 so 70 60 90 100 110 Par% dof id Power MCPRp

(%)

umit 100 1.53 80 1.61 80 1.69 25 2.10 25 2.20 0

2.70 Figure 5.13 EOC Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel

_toP __:_

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 5.24 1.30 125 1oDo 1.15 am oLs 0.?5 0.75

• 0.70 0.65t 0.10 LR FNOWRPT

• FYCF No RPLT UK; WACO l

a S

5 S

0 10 20 30 40 50 OD 70 so 90 1M 110 Power LHGRFACp

(%)

Multiplier 100 0.89 80 0.89 80 0.86 25 0.70 25 0.70 0

0.70 Figure 6.14 EOC Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel a

91_

LaSalle Unit 2 Cycle 9 Plmnt 'rrftmeivnn Anniaie~k EMF-2440 Revision 0 Pae 5-25

• 1 & IO S

4 N

1

...6.. C-Ct U

0 10 20 30 40 so 0

70 W

600 1110 Poem

%od Power MCPRp (5M)

Limit 100 1.63 80 1.84 80 1.95 25 2.10 25 2.20 0

2.70 Figure 5.15 EOC Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel Siemen Po^we Cmporatio

LaSalle UnIt 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Paoe 5-26 2ZS

. 21S 1J5 0

10 20 30 40 so 3

10 so s0 1X 110 Part%

S dRa4 Power

MCPR,

(%)

Limit 100 1.53 80 1.61 80 1.69 25 2.14 25 2.35 0

2.85 Figure 5.16 EOC Turbine Control Valve Slow Closure andlor Recirculation Pump Trip and Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for ATRIUM-91 Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 I

Page 5-27 30 I 125 12 1.10 1.05 0.3 ESK 025I 3 0.90 cm 5 amto 0.75 0.70

• SbwTCV cka~w

• FVCFb RP w HOOS

-LHGRFACp aU I

aa S

S 00 0.65 0.60 0

la 20 30 40 50 60 Pemr (% d Awd 70 so 90 100 110 Power LHGRFACp

(%)

Multiplier 100 0.89 80 0.89 80 0.86 25 0.68 25 0.68 0

0.68 Figure 5.17 EOC Turbine Control Valve Slow Closure andlor Recirculation Pump Trip and Feedwater Heaters Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 5-28 ass 275 2M5 245 2W3 2J5 a,12s 1.35 1.75 1.65 1.55.

1255 1.25

\\

• FVHF No RPT 'uh FHOOS aa 9;

9:

aU a

U 1.,15 0

10 20 30 40 50 60 Poe(%

d d Ra 70 s0 90 100 110 Power MCPRp

(%)

iumit 1DO 1.63 80 1.84 80 1.95 25 2.22 25 2.35 0

2.85 Figure 5.18 EOC Turbine Control Valve Slow Closure andlor Recirculation Pump Trip and Feedwater Heaters Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 6-1 6.0 Transient Analysis for Thermal Margin - EODIEOOS Combinations This section describes the transient analyses performed to determine the tv',CPR and LHGR operating limits to support operation in the coastdown and combined FF Tl ncoastdown extended operating domains in conjunction with the following EOOS scenarios:

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

1 recirculation pump loop (SLO).

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

Recirculation pump tnp out--service (no RPT).

a Slow closure of 1 or more turbine control valves and/or no RPT.

Each of the EOOS scenarios presented also includes the failure of I SRV.

Results of the limiting transient analyses are used to establish MCPRp limits and LHGRFACp multipliers to support operation in the combined EODIEOOS scenarios. All combined EODIEOOS analyses were performed with TSSS insertion times.

As discussed in Reference 9, the base case MCPR safety limit for two-loop operation remains applicable for operation in the combined EODIEOOS scenarios with the exception of single-loop operation. Also, the flow-dependent MCPR and LHGR analyses described in Section 3.4 remain applicable in all the combined EODIEOOS scenarios.

6.1 Coastdown With EOOS The impact of EOOS scenarios on coastdown operation is discussed below. The MCPRp limits and LHGRFACp values established for nominal coastdown operation remain applicable for coastdown operation with I safety/relief valve out-of-service, up to 2 TIPOOS (or the equivalent number of TIP channels) and up to 50% of the LPRMs out-of-service (Reference 9).

6.1.1 Coastdown With Feedwater Heaters Outd-of-Service The discussion and results presented in Section 4.3 for combined FFT1ER/coastdown operation are applicable to coastdown operation with FHOOS.

6.1.2 Coastdown With One Recirculation Loon The impact of SLO at LaSalle on thermal limits was presented in Reference 9. The only impact is on the MCPR safety limit. As presented in Section 3.2, the single-loop operation safety limit is

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 6-2 0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The base case coastdown ACPRs and LHGRFACp multipliers remain applicable. The net result is an increase to the base case coastdown MCPRI) limits of 0.01 as a result of the increase in the MCPR safety limit.

6.1.3 Coastdown With TBVOOS The exposure extension during coastdown can make the effects of the pressurization transients more severe. The TBVOOS assumption also increases the severity of pressurization events.

The nominal coastdown analysis for the load rejection event is performed assuming the turbine bypass system is inoperable. Therefore, the impact of the TBVOOS on the load rejection event is included in the nominal coastdown results.

The FWCF event was evaluated to ensure appropriate MCPRp limits and LHGRFACp values are established to support coastdown operation with TBVOOS. The results of the Cycle 9 coastdown FWCF with TBVOOS analyses for both ATRIUM-9B and GE9 fuel are presented in Table 6.1. Figures 6.1 and 6.2 show the ATRIUM-9B MCPRp limits and LHGRFACp multipliers that support coastdown operation with TBVOOS. The coastdown with TBVOOS MCPRp limis for GE9 fuel are presented in Figure 6.3.

6.1.4 Coastdown With No RPT To ensure that appropriate MCPRp limits and LHGRFACp multipliers are established to support coastdown operation with no RPT, analyses were performed for LRNB and FWCF events with RPT assumed inoperable. The results of the Cycle 9 coastdown no RPT analyses for both ATRIUM-91 and GE9 fuel are presented in Table 6.2. Figures 6.4 and 6.5 show the ATRIUM-9B MCPRp limits and LHGRFACp multipliers that support coastdown operation with no RPT. The coastdown with no RPT MCPRp limits for GE9 fuel are presented in Figure 6.6.

6.1.5 Coastdown With Slow Closure of the Turbine Control Valve The slow closure of the turbine control valve event changes the characteristics of the LRNB event in that no direct scram or RPT occurs on valve position. The effect of the increase in exposure resulting from coastdown operation can make the event more severe. The ACPR and LHGRFACp results are presented in Table 6.3. While the TCV slow closure analysis is performed without RPT on valve position, it does not necessarily bound the LRNB no RPT or FWCF no RPT events at all power levels because the slow closing TCV provides some pressure relief until It j

Ok...

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 6-3 completely closes. Therefore, the MCPRp limits and LHGRFACp multipliers for the coastdown with TCV slow closure scenario are established using the limiting of the coastdown no RPT results reported in Section 6.1.4 or the TCV slow closure results.

Figures 6.7 and 6.8 present the ATRIUM-9B coastdown with TCV slow closure and/or no RPT MCPRp limits and LHGRFACp multipliers and Figure 6.9 presents the coastdown with TCV slow closure and/or no RPT GES MCPRp limits.

62 Combined FFTRPCoastdown WMth EOOS The impact of EOOS scenarios on combined FFTR/coastdown operation is discussed below.

The FFTR/coastdown MCPR, limits and LHGRFACp values established for combined FFTR/coastdown operation remain applicable for FFTRicoastdown operation with I safety/relief.

valve out-of-service, up to 2 TIPOOS (or the equivalent number of TIP channels) and up to 50%

of the LPRMs out-of-service (Reference 9).

6.2.1 Combined FFTRICoastdown With One Recirculation LoOo The impact of SLO at LaSalle on thermal limits was presented in Reference 9. The only impact is on the MCPR safety limit As presented in Section 32, the single-loop operation safety limit is 0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The base case FFTRicoastdown ACPRs and LHGRFACp multipliers remain applicable. The net result is an increase to the base case FFTR/coastdown MCPRp limits of 0.01 as a result of the increase in the MCPR safety limit.

6.2.2 Combined FFTR/Coastdown With TBVOOS The exposure extension and decrease in core inlet enthalpy during combined FFTR/coastdown operation can make the effects of the pressurization transients more severe. The TBVOOS assumption also increases the severity of pressurization events. The nominal FFTR/coastdown analysis for the load rejection event is performed assuming the turbine bypass system is inoperable. Therefore, the impact of the TBVOOS on the load rejection event is included in the nominal FFTR/coastdown results.

The FWCF event was evaluated to ensure appropriate MCPRp limits and LHGRFACp values are established to support combined FFTR/coastdown operation with TBVOOS. The results of the Cycle 9 FFTR/ coastdown FWCF with TBVOOS analyses for both ATRIUM-9B and GE9 fuel are

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 6-4 presented in Table 6.4. Figures 6.10 and 6.11 show the ATRIUM-91 MCPRp limits and LHGRFACp multipliers that support combined FFTRicoastdown operation with TBVOOS. The FFTRlcoastdown with TBVOOS MCPRp limits for GE9 fuel are presented in Figure 6.12.

6.2.3 Combined FFTRJCoastdown With No RPT To ensure that appropriate MCPRp limits and LHGRFACp multipliers are established to support FFTRIcoastdown operation with no RPT, analyses were performed for LRNB and FWCF events with RPT assumed inoperable. The results of the Cycle 9 FFTR/coastdown no RPT analyses for both ATRIUM-9B and GE9 fuel are presented in Table 6.5. Figures 6.13 and 6.14 show the ATRIUM-9B MCPRp limits and LHGRFACp multipliers that support combined FFTRicoastdown operation with no RPT. The FFTRlcoastdown with no RPT MCPRp limits for GE9 fuel are presented in Figure 6.15.

6.2.4 Combined FFTRICoastdown With Slow Closure of the Turbine Control Valve Slow closure of the turbine control valve changes the characteristics of the LRNB event in that no direct scram or RPT occurs on valve position. While the decrease in steam flow due to the FFTR tends to lessen the severity of the event, the FFTRlcoastdown exposure extension may have the opposite effect. The ACPR and LHGRFACp results are presented in Table 6.6. While the TCV slow closure analysis is performed without RPT on valve position, it does not necessarily bound the LRNB no RPT or FWCF no RPT events at all power levels because the slow closing TCV provides some pressure relief until it completely closes. Therefore, the MCPRp limits and LHGRFACp multipliers for the combined F F Tlcoastdown with TCV slow closure scenario are established using the limiting of the FFTR/coastdown no RPT results reported in Section 62.3 or the TCV slow closure results.

Figures 6.16 and 6.17 present the ATRIUM-S9B combined FFTR/coastdown with TCV slow closure and/or no RPT MCPRp limits and LHGRFACp multipliers and Figure 6.18 presents the FFTR/coastdown with TCV slow closure and/or no RPT GE9 MCPR,, limits.

I - -

lcipfnmz P&AwCamrnfion

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 I

Page 6-5 Table 6.1 Coastdown Turbine Bypass Valves Out-of-Service Analysis Results Power I Flow ATRIUM GE9

(% rated /

Event

% rated)

ACPR LHGRFACp ACPR FWCF 100 / 105 0.33 1.01 0.42 FWCF 80/105 0.37 1.01 0.40 FWCF 60 /105 0A2 1.00 OA6 FWCF 40/105 0.54 1.00 0.55 FWCF 25/105 0.86 1.08 0.88

. I - -

Mm LaSalle Unit 2 Cycle 9 s__

!--A A --

I._

EMF-2440 Revision 0 Paoe 6-6 Plant I ransiem Analysis._

Table 6.2 Coastdown Recirculation Pump Trip Out-of-Service Analysis Results Power / Flow ATRIUM GE9

.(% ratedlI Event

% rated) ICPR LHGRFACp ACPR LRNB 100 / 105 0.44 0.89 0.56 LRNB 801105 OA2 0.91 0.45 LRNB 601105 0.39 0.91 OA7 LRNB 401105 0.39 0.87 0.41 LRNB 25 /105 0.29 1.01 0.28 FWCF 1001105 0.32 0.96 OA2 FWCF 80 1 105 0.35 0.98 0.38 FWCF 601105 0.39 0.99 0.44 FWCF 401105 0.47 0.97 0.48 FWCF 25/105 0.86 1.06 0.88

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-244D Revision 0 Page 6-7 Table 6.3 Coastdown Turbine Control Valve Slow Closure Analysis Results Slow Power I Flow ATRIUM-9B GE9 Valve

(% rated J Event Characteristics

% rated)

ACPR LHGRFACp ACPR LRNB 1 TCV closing at 2.0 sec 100 / 105*

0.44 0.93 0.55 LRNB I TCV closing at 2.0 sec 80/105-0.45 0.94 OA8 LRNB 1 TCV closing at 2.0 sec SO/105l 0.52 0.95 0.55 LRNB 1 TCV closing at 2.0 sec 60/105t 0.59 0.96 0.61 LRNB 1 TCV closing at 2.0 sec 401105?

0.79 0.87 0.78 LRNB 1 TCV closing at 2.0 sec 25/1051 0.99 0.74 0.93 Scram initiated by high-neutron flux.

I Scram initiated by high dome pressure 0"

flwrW4n

LaSalle Unit 2 Cycle 9 In[--&

ln,^n Anmkivsi EMF-2440 Revision 0 Page 6-8 raaI IL II 43I II uA It.

a Table 6A FFTRlCoastdown Turbine Bypass Valves Out-of-Service AnalysisResults Power I Flow ATRIUM GE9

(% ratedlI Event

% rated)

ACPR LHGRFACp ACPR FWCF 100 /105 0.32 1.03 0.35 FWCF 801 105 0.36 1.03 0.40 FWCF 601105 0.44 1.01 0.47 FWCF 401105 0.60 1.07 0.59 FWCF 251105 1.10 0.95 1.12 sk

_

LaSalle Unit 2 Cycle 9 Does Tn1ont Annhmbi EMF-2440 Revision 0 Page 8 VIaclI I Table 6.5 FFTR/Coastdown Recirculation Pump Trip Out-of-Service Analysis Results Power I Flow ATRIUM GE9

(% rated /

Event

% rated)

ACPR LHGRFACp ACPR LRNB 100 /105 0.39 0.92 0.41 LRNB 801 105 0.38 0.94 0.44 LRNB 601105 0.40 0.92 0.41 FWCF 100 /105 0.32 0.97 0.34 FWCF 80/105 0.36 0.98 0A1 FWCF 60/ 105 0.43 0.96 0.46 FWCF 40 /105 0.56 0.91 0.56 FWCF 25/105 1.10 0.95 1.12

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revaision 0 Page 6-10 Table 6.6 FFTRICoastdown Turbine Control Valve Slow Closure Analysis Results Slow Power I Flow ATRIUM-91 GE9 Valve

(% rated /

Event Characteristics

% rated)

ACPR LHGRFACp

&CPR LRNB 1 TCV closing at 2.0 sec 100/105W 0.39 0.96 0.40 LRNB 1 TCV closing at 2.0 sec 801105' 0.38 0.98 0.42 LRNB 1 TCV dosing at 2.0 sec 80/105t 0.49 0.98 0.52 LRNB 1 TCV dosing at 2.0 sec 60/ 105t 0.60 0.94 0.58 LRNB 1 TCV closing at 2.0 sec 40 / 1051 0.72 0.83 0.71 LRNB 1 TCV closing at 2.0 sec 251/105 1 0.98 0.76 0.83 Scram initated by high-neutron flux.

t Scram itiated by high dome pressure

LaSalle Unit 2 Cycle 9 D1anf 'rr-rea~n#i Anfthmic EMF-2440 Revision 0 Paoe 6-1 1 r gal IL II Calz

• 6I~IIll VI UI 275 2.5 2M4 2AS 225 215 1.75 1.65 1.75 ASS IAS 0

¶0 2D 30 40 50 60 70 s0 so 100 110 Por %do Pian)

Power MCPR 9

(%)

Limit 100 1.44 60 1.55 25 2.05 25 2.20 0

2.70 Figure 6.1 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9S Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 6-12 06 0

-a 0

1l 20 30 40 s0 60 70 0

90 Ica Powr (% of Rated)

Power LHGRFACp

(%)

Multiplier 100 0.99 60 0.97 25 0.73 25 0.73 0

0.73 Figure 6.2 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 1l_

S___

Att A

I C

EMF-2440 Revision 0 Pae 6-13 Piant 1r jj1 IL e

I 1 QID 0

10 20 30 40 50 0

TO 30 60 100 110 Pwl (%OfRd)

Power MCPRp

(%)

Limit 100 1.53 60 1.64 25 2.15 25 2.20 0

2.70 Figure 6.3 Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 6-14 WM5 -

255 2W, Hes5 2.15 2M, 2ZS 1.5 1.35 M 20 1.5 4A5 IS5 a

a LRM I.FY<CF X

I OLMR :

a 11s

• 

a 10 34 30 so 0

0 70 30 O0 10D t10 Pa w(% dFd)

Power MCPRp

(%)

Limit 100 1.55 60 1.55 25 2.05 25 220 0

2.70 Figure 6.4 Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-91 Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 I

Page 6-15 1.30 1.12I 1.10 i 1.05 U-1.00.

IA, W Om, 0.35 0.75.

LRM S

4 SCF SLGWC 0.70 i 0am 0.00 0

10 20 30 40 so so PON r/of R 70 30 OD 100 11 Power LHGRFACp

(%)

Multiplier 100 0.88 60 0.68 25 0.75 25 0.75 0

0.75 Figure 6.5 Coastdown Recimculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 Dlest Tni~ntAnftlvmic EMF-2440 Revision 0 Paae 6-16 1aadLU I a c

el rl Iv5yo*;

15' 2.45' 2MS 15 X15 las 1.75 IAS lA5 0

10 20 30 40 so 60 70 so 90 100 10 Poaur Mof dRad)

Power MCPRp

(%)

Lmrit 100 1.67 60 1.67 25 2.05 25 2.20 0

2.70 Figure 6.6 Coastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Umits for GE9 Fuel Pjarnam Pemr cuprmvm

LaSalle Unit 2 Cycle 9 t1__4T_^_sr+ A-I.luei EMF-2440 Revision 0 Pnae 6-17 r'wId1 I [i MII~COIL rPamIIiYOIOIsa-I 0

10 20 20 40 50 so 70 MD 90 1O0 110 Poars(%of Rfd)

Power MCPRp

(%)

Limit 100 1.55 80 1.62 80 1.70 25 2.15 25 2.20 0

2.70 Figure 6.7 Coastdown Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Umlts for ATRIUM-9B Fuel DCaav nww~ rwrdwn3in

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 6-18

'Jo t2.

I=,

1.15 1.10, Um s

0.5 0M.

MlS

• sbO-cvC10.we

• LRN9NoRPT

• FVCF Wo R LHGFACP U

a a0 a

00

• 0 I

4 0.50 I O.7S 0.70 0.5 nan I 0

10 20 30 40 50 so 70 so 90 100 110 Power (% of Itnad)

Power LHGRFACp

(%)

Multiplier 100 0.8B 80 0.88 80 0.85 25 0.68 25 0.68 0

0.68 Figure 6.8 Coastdown Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 6-19 IL 0

10 2

30 40 0

g0 70 A0 s0 10 110 PeotW of lad)

Power MCPRp

(%)

Limit 100 1.67 80 1.85 80 1.96 25 2.15 25 2.20 0

2.70 Figure 6.9 Coastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 6-20 2a5 275 205 245M

2AS, 225 2.15 C.

^ 2X0 1.75 1.65 1A5 25.

1.15 FaF _

0 10 0

X 0

o K

Pasm l dofd TO so 90 100 110 Power MCPRp

(%)

Limit 100 1.44 60 1.57 25 2.30 25 2.35 0

2.85 Figure 6.10 FFTRlCoastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B Fuel

LaSalle Unit 2 Cycle 9 Dow+

TrenA;^nthAnavei EMF-2440 Revision 0 Page 6-21 Mam I I1na1 10 L

-1 Ban%&4Mya a.

V 0.60 0

10 20 30 40 50 so0 70 so 0

100 Ila Powr % of Rmd)

Power LHGRFACp

(%)

Multiplier 100 0.99 60 0.97 25 0.65 25 0.65 0

0.65 Figure 6.11 FFTR/Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis I

Page 6-22 ft en a

10 20 30 40 so so 70 0 o 100 1l0 POW" (%f dRaftm Power MCPRp (96)

Umit 1100 1.53 60 1.64 25 2.30 25 2.35 0

2.85 Figure 6.12 FFTR/Coastdown Turbine Bypass Valves Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel

LaSalle Unit 2 Cycle 9 Plfnt4 Traneiont Analwiak EMF-2440 Revision 0 Paoe 6-23 I

Coal It I * -l

l.

A. l-l.

2M5 2.7 2M5 245 2M 2M5 225' I M 215s an 1AS 1.35 1.55 lAS 125 1.25 0

IC 20 30 40 50 so 70 so 90 10t0 1o Parw

%ef Power MCPRp

(%)

Umit 100 1.55 60 1.56 25 2.30 25 2.35 0

2.85 Figure 6.13 FFTRlCoastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-9B3 Fuel ro.

LaSalle Unit 2 Cycle 9 DlI-t Arnic n

ft iv~el EMF-2440 Revision 0 Paoe 6-24 rla01L Ilull~blay>l,.__

IL S!

-a C

10 20 30 40 50 s0 t0 so 00 100 110 PoW@ (%of RMd)

Power LHGRFACp

(%)

Multiplier 100 0.88 60 0.88 25 0.65 25 0.65 0

0.65 Figure 6.14 FFTRlCoastdown Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipiers for ATRIUM-91 Fuel e

LaSalle Unit 2 Cycle 9 01,mntTrmnesianI Analv!:is.

EMF-2440 Revision 0 Paoe 6-25 aI 0

10 2D 30 40 0o W0 70 s0 90 100 110 P

%ofR pif Power MCPRp

(%)

Limit 100 1.67 60 1.67 25 '

2.30 25 2.35 0

2.85 Figure 6.15 FFTRlCoastdown Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel

LaSalle Unit 2 Cycle 9 Dye Stin&

Anoulvsei EMF-2440 Revision 0 Pane 6-26 r'ICSIR I6 0

10 2D 30 40 50 60 70 60 90 110 PMr (% dadf Power MCPRp

(%6)

Umit 100 1.55 80 1.62 80 1.70 25 2.30 25 2.35 0

2.85 Figure 6.16 FFTRlCoastdown Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for ATRIUM-91 Fuel

LaSalle Unit 2 Cycle 9 Dlet TeneantAnihtluia EMF-2440 Revision 0 Page 6-27 Wr 1IIL1 II 2

• IQ VU I IL I 61P5I IT ca. 1.0D O

INC.3 aI.O 0

10 20 30 40 50 SO 70 so 90 100 1110 Pamr % ofet Power LHGRFACp

(%)

Multiplier 100 0.8B 80 0.88 80 0.85 25 0.65 25 0.65 0

0.65 Figure 6.17 FFTRlCoastdown Turbine Control Valve Slow Closure andlor Recirculation Pump Trip Out-of-Service Power-Dependent LHGR Multipliers for ATRIUM-91 Fuel 44ovimPnmm Carmeinstia

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Paoe 6-28 ass 275 245 2W5 125 2.15 1*5 1.75 1U5 tJS 1.55 lAS 125 1.15 0

10 20 30 40 s0 W

70 so 10 10 10 wFlo 4V ory Power MCPRp

(%)

Limit 100 1.67 80 1.85 80 1.96 25 2.30 25 2.35 0

2.85 Figure 6.18 FFTRlCoastdown Turbine Control Valve Slow Closure and/or Recirculation Pump Trip Out-of-Service Power-Dependent MCPR Limits for GE9 Fuel Shmens Power C udporftn

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 7-1 7.0 Maximum Overpressurization Analysis This section describes the maximum overpressurfation analyses performed to demonstrate compliance with the ASME Boiler and Pressure Vessel Code. The analysis shows that the safety/relief valves at LaSalle Unit 2 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 SPC plant simulator code COTRANSA2 (Reference 4) at a powertflow state point of 102% of uprated power/I 05% flow. Reference 9 indicates that an EOFP + 1000 MWdFMTU exposure is limiting for the overpressurization analysis. 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 ComEd's request, analyses were performed to determine the minimum number of the highest set point SRVs required to meet the ASME and Technical Specification pressure limits. It was determined that having the 10 highest set point SRVs operable will meet the ASME and Technical Specification pressure limits. In order to support operation with 1 SRV out-of-service, the plant configuration needs to include at least 11 SRVs. As per ASME requirements, the SRVs are assumed to operate in the safety mode.

TSSS insertion times were used.

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

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

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

7.2 Pressurization Transients Results of analysis for the MSIV closure event initiated at 102% power/1 05% flow are presented in Table 7.1. Figures 7.1-7.5 show the response of various reactor plant parameters to the MSIV closure event. The maximum pressure of 1346.2 psig occurs in the lower plenum at approximately 4.4 seconds. The maximum dome pressure of 1319.9 psig occurs at 4.6 seconds. The results demonstrate that the maximum vessel pressure limit of 1375 psig and dome pressure limit of 1325 psig are not exceeded.

EMF-2440 Revision 0 Page 7-2 LaSalle Unit 2 Cycle 9 b_-_

A __1.;f Plant t ransienr Anglvsr' I

Table 7.1 ASME Overpressurization Analysis Results 102%PII05%F Peak Peak Maximum Maximum Neutron Heat Vessel Pressure Dome Flux Flux Lower-Plenum Pressure Event

(% rated)

(CA rated)

(psi)

(psig)

MSIV closure 373.7 136.6 1348.2 1319.9

LaSalle Unit 2 Cycle 9 mnM Tronciant Annahvsi EMF-2440 Revision 0 Pace 7-3 alK I at a a..

aD LAJ 9-0 I9-z a:

L Lo TIE, SECONDS Figure 7.1 Overpressurization Event at 1021105 -

MSIV Closure Key Parameter

.Ammwww Per Cadnnr~vi

LaSalle Unit 2 CYcle 9 EMF-2440 Revision 0 Paae 7-4 Plant I ranslent PAlMsisa 0

N I.-.

En 0

LiJ

-J

-J L&J Lncn wl TIE, SECONDS Figure 7.2 Overpressurization Event at 1021105 -

MSIV Closure Vessel Water Level

LaSalle Unit 2 Cycle 9 Ar.t:;

EMF-2440 Revision 0 Paoe 7-5 Plant I ransieni Atalyss_

vi IL t)

U)

IL z

LI a-Li 0

-J 4T S

TiE, SECONDS LO Figure 7.3 Overpressurization Eventat 102/105-MSIV Closure Lower-Plenum Pressure

LaSalle Unit 2 Cycle 9 Plant Transient Analysis EMF-2440 Revision 0 Page 7-6 U)

L Li it hLI D

' Oin TME, SECONDS Figure 7.4 Overpressurization Event at 1021105 -

MSIV Closure Dome Pressure I

-. q nmnw Penur r

_nnn utfi

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 7 Plant Transient Analysis Page 7-7

'AM N-J L&

In SRV BANK 1 SRV BANK 2 SRV BANK 3 SRV BANK 4 SRV BANK 5

. X'I

/1 I

I' I

I I

r D,

1.0 1.0 20 3.0 4.D

TIM, SECONDS 5:

60 7.0 LO Number of I Opening Bank SRVs Pressure (psia) 1 0

NA 2

2 1235.3 3

4 1245.6 4

4 1255.9 5

0 NA Figure 7.5 Overpressurzation Event at 1021105 -

MSIV Closure SafetylRelief Valve Flow Rates

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 8-1 8.0 References

1.

Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), "LaSalle Unit 2 Cycle 9 Calculation Plan,' DEG:0D:031, February 25, 2000.

2.

XN-NF-80-1 9(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

3.

XN-NF-80-19(P)(A) Volume 1 Supplement 3, Supplement 3 Appendix F, and Supplement 4, Advanced Nuclear Fuels Methodology for Boiling Water Reactors:

Benchmark Results for the CASMO-3G/MICROBURN-B Calculation Methodology, Advanced Nuclear Fuels Corporation, November 1990.

4.

ANF-913(P)(A) Volume I Revision I and Volume I Supplements 2, 3 and 4, COTRANSA2. A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.

5.

ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.

6.

ANF-1 125(P)(A) and Supplement 1 and 2, ANFB Critical Power Correlation, Advanced Nuclear Fuels Corporation, April 1990.

7.

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

8.

EMF-2323 Revision 0, LaSalle Unit 2 Cycle 9 Principal Transient Analysis Parameters, Siemens Power Corporation, March 2000.

9.

EMF-95-205(P) Revision 2. LaSalle Extended Operating Domain (EOD) and Equipment Out of Service (EOOS) Safety Analysis forATRILUMT-9B Fuel, Siemens Power Corporation, June 1996.

10.

EMF-95-049(P), Application of the ANFB Critical Power Correlation to Coresident GE Fuel at the Quad Cities and LaSalle Nuclear Power Stations, Siemens Power Corporation, October 1995.

11.

XN-NF-84-1 05(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

12.

EMF-1125(P)(A) Supplement 1 Appendix C, ANFB Critical Power Correlation Application for Co-Resident Fuel, Siemens Power Corporation, August 1997.

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.

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page 8-2 8.0 References (Continued)

14.

La Salle County Nuclear Station Unit 2 Technical Specifications, as amended.

15.

EMF-2437 Revision 0, LaSalle Unit 2 Cycle 9 Reload Analysis, Siemens Power Corporation, October 2000.

16.

EMF-1 903(P) Revision 3, Impact of FailedlBypassed LPRMs end TIPs and Extended LPRM Calibration Interval on Radial Bundle Power Uncertainty, Siemens Power Corporation, March 2000.

17.

ANF-1125(P)(A) Supplement 1, Appendix E, ANFB Critical Power Correlation Determination of ATRIUMm-9B Additive Constant Uncertainties, Siemens Power Corporation, September 1998.

18.

ANF-1373(P), Procedure Guide for SAFLIM2, Siemens Power Corporation, February 1991.

19.

Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), OLaSalle Unit 2 Cycle 9 Transient Power History Data for Confirming Mechanical Umits for GE9 Fuel," DEG:00:185, August 3, 20O0.

20.

Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), 'LaSalle Unit 2 Cycle 8 Abnormal Idle Recirculation Loop Startup Analysis," DEG:99:070, March 8, 1999.

21.

Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), *Description of Measured Power Uncertainty for POWERPLEX0 Operation Without Calibrated LPRMs,` DEG:00:061, March 7,200.

22.

Letter, J. H. Riddle (SPC) to R. J. Chin (ComEd), OScam Surveillance Requirements for MCPR Operating Limits,' JHR:96:397, October 8, 1996.

23.

EMF-2277 Revision 1, LaSalle Unit I Cycle 9 Plant Transient Analysis, Siemens Power Corporation, October 1999.

24.

Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), OExtension of LPRM Calibration Interval to 2500 EFPH," DEG:00:088, April 17, 20D0.

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Page AA 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 LHGRFACi, 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 A00s. 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 PAPTISSLHGR ratio over HFR, or 1.0. Based on the ATRIUM-9B LH-GR limits presented in Reference A-1, LHGRFACg, is established as follows:

PAPT 1.35 SSLHGR HFR=

LHGRFAC,

= min HFR 1.01 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 This approach was used to provide less restrictive LHGRFACp multipliers for some cases.

EMF-2440 LaSalle Unit 2 Cycle 9 Revision 0 Plant Transient Analysis Pape A-2 References A.1 EMF-24D4(P) Revision 1, Fuel Design Report for LaSalle 2, Cycle 9 ATRlUM~m-9B Fuel Assemblies, Siemens Power Corporation, September 2000.

LaSalle Unit 2 Cycle 9 v1_r__-l A--t.-h EMF-2440 Revision 0 ri n

1 IZ11=1 IL EU

.%nsleoalb Controlled Distribution Richland D. E. Garber (12 copies)

Uncontrolled Distribution E-Mail Notification D. G. Carr D. B. McBumey

0. C. Brown M. E. Garret J. M. Haun J. G. Ingham R. R. Schnepp P. D. Wffnpy Siemens Power Corpolbon