RA13-053, Core Operating Limits Report, Cycle 15, Revision 1

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Core Operating Limits Report, Cycle 15, Revision 1
ML13262A272
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 08/28/2013
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
References
RA13-053
Download: ML13262A272 (36)
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Text

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 1 of 36 1

Core Operating Limits Report for LaSalle Unit 2 Cycle 15 Revision I

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 2 of 36 Table of Contents

1. References ...................................................................................................................................... 4
2. Terms and Definitions ...................................................................................................................... 5
3. General Information ......................................................................................................................... 6
4. Average Planar Linear Heat Generation Rate ............................................................................ 7
5. Operating Limit Minimum Critical Power Ratio ............................................................................ 8 5.1. Manual Flow Control MCPR Limits ..................................................................................... 8 5.1.1. Power-Dependent MCPR ............................................................................................... 8 5.1.2. Flow-Dependent MCPR ................................................................................................. 8 5.2. Scram Time .............................................................................................................................. 8 5.3. Recirculation Flow Control Valve Settings ............................................................................ 9
6. Linear Heat Generation Rate ................................................................................................... 13
7. Rod Block Monitor ............................... ! ....................................................................................... 16
8. Traversing In-Core Probe System ............................................................................................. 17 8.1. Description ............................................................................................................................. 17 8.2. Bases ..................................................................................................................................... 17
9. Stability Protection Setpoints .................................................................................................. 18
10. Modes of Operation ..................................................................................................................... 19
11. Methodology ................................................................................................................................ 20 Appendix A ........................................................................................................................................ 21 I

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 3 of 36 List of Tables 3-1 Cycle Exposure Range Definitions ........................................................................................................... 6 4-1 MAPLH G R for G NF2 Fuel ............................................................................................................................ 7 4-2 MAPLHGR for ATRIUM-1 0 Fuel ...................................................... ........... .................... 7 4-3 MAPLHGR SLO Multiplier for GNF2 and ATRIUM-10 Fuel, BOC to EOC .............................................. 7 5-1 Scram Times Required for Option A and Option B Application at Notch Position 39 ............................... 9 5-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for ATRIUM-10 and GNF2 Fuel ................ 10 5-3 Power-Dependent MCPR Multipliers (Kp) for ATRIUM-10 and GNF2 Fuel, DLO and SLO, BOC to EOC, O ption A and O ption B ................................................................................................................................ 11 5-4 DLO Flow-Dependent MCPR Limits (MCPRF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B .......................................................................................... 12 5-5 SLO Flow-Dependent MCPR Limits (MCPRF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B .......................................................................................... 12 6-1 LHG R Lim it for G NF2 Fuel .......................................................................................................................... 13 6-2 LHGR Limit for ATRIUM-10 Fuel ............................................ ............. ........................ 13 6-3 Power-Dependent LHGR Multipliers (LHGRFACp) for ATRIUM-10 and GNF2 Fuel, DLO and SLO, BOC to EO C ........................................................................................................................................................ 14 6-4 Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, Pressurization (1 TCV/TSV Closed or OOS), All Application Groups ................................................... 15 6-5 Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, No Pressurization (All TCV/TSV In-Service), All Application Groups .................................................... 15 7-1 Rod Block Monitor Setpoints ....................................................................................................................... 16 9-1 O PRM PBDA Trip Setpoints ....................................................................................................................... 18 10-1 Allowed Modes of Operation and EOOS Combinations ....................................................................... 19

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 4 of 36

1. References
1. Exelon Generation Company, LLC Docket No. 50-374 LaSalle County Station, Unit 2, License No. NPF-1 8.
2. NRC Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Conceming the Removal of Cycle-Specific Parameter Limits from Tech Specs, October 3, 1988.
3. Nuclear Fuels Letter NFM:MW:01 -0106, from A. Giancatarino to J. Nugent, "LaSalle Unit 1 and Unit 2 Rod Block Monitor COLR Setpoint Change," April 3, 2001.
4. GNF Report NEDC-32694P-A, Revision 0, "Power Distribution Uncertainties for Safety Limit MCPRF Evaluations," August 1999.
5. GE Nuclear Energy Document GE-NE-Al 300384-07-01, Revision 1, "LaSalle County Station Power Uprate Project Task 201: Reactor Power/Flow Map", September 1999.
6. GE Hitachi Nuclear Energy Report, GE-NE-0000-0099-8344-R1, Revision 1, "Exelon Nuclear LaSalle Units 1 and 2 Thermal Power Optimization Task T0201: Operating Power/Flow Map", November 2009.
7. GNF Report 0000-0156-1147-SRLR, Revision 1, "Supplemental Reload Licensing Report for LaSalle Unit 2 Reload 14 Cycle 15," January 2013.
8. GNF Report 0000-0156-1147-FBIR-P, Revision 0, "Fuel Bundle !nformation Report for LaSalle Unit 2 Reload 14 Cycle 15," January 2013.
9. AREVA Report ANP-2914(P), Revision 1, "Mechanical Design Report for LaSalle Units 1 and 2 MUR ATRIUM-10 Fuel Assemblies," AREVA NP Inc., June 2010.

10, Exelon Transmittal ES1 200013, Revision 0, "LaSalle Unit 2 Cycle 15 Final Resolved OPL-3 Parameters,"

August 22, 2012.

11, GNF DRF A12-00038-3, Vol. 4, "Scram Times Verses Notch Position," G. A. Watford, May 22,1992.

12 GNF Transmittal CFL-EXN-HA2-12-173, transmitting results of DRF Section 0000-0155-9963, "LaSalle Unit 2 Cycle 15 Single LHGR Curve Determination (TSD NF-B483)," December 19, 2012.

13. LaSalle Transmittal SEAG 13-000010, Revision 0, "LaSalle L2C1 5 OPRM Successive Confirmation Count Setpoint and OPRM Amplitude," January 28, 2013.
14. GNF Report NEDC-33647-P, Revision 2, "GNF2 Fuel Design Cycle-Independent Analyses for Exelon LaSalle County Station Units 1 and 2," February, 2012.
15. GNF DRF Section 0000-0151-0765 Rev. 0, "Application of SLO MCPR", 2/12/13.

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 5 of 36

2. Terms and Definitions ARTS Average Power Range Monitor, Rod Block Monitor and Technical Specification Improvement Program ATRM10 AREVA ATRIUM-10 fuel type BOC Beginning of cycle BWR Boiling water reactor CFR Code of Federal Regulations COLR Core operating limits report CRD Control rod drive mechanism DLO Dual loop operation ELLLA Extended load line limit analysis EOC End of cycle EOOS Equipment out of service EOR1 5 End of rated operation for Cycle 15 FFWTR Final feedwater temperature reduction FWHOOS Feedwater heater out of service GNF Global Nuclear Fuels - Americas ICF Increased core flow Kp Power-dependent MCPR Multiplier L2C15 LaSalle Unit 2 Cycle 15 LHGR Linear heat generation rate LHGRFACF Flow-dependent LHGR multiplier LHGRFACp Power-dependent LHGR multiplier LPRM Local power range monitor MAPLHGR Maximum average planar linear heat generation rate MCPR Minimum critical power ratio MCPRF Flow-dependent MCPR MELLLA Maximum extended load line limit analysis MOC Middle of Cycle Point for Licensing Purposes MSIVOOS Main steam isolation valve out of service OLMCPR Operating limit minimum critical power ratio OOS Out of service OPRM Oscillation power range monitor PBDA Period based detection algorithm PLUOOS Power load unbalance out of service PROOS Pressure regulator out of service RPTOOS Recirculation pump trip out of service RWE Rod withdrawal error SLMCPR Safety limit minimum critical power ratio SLO Single loop operation SRVOOS Safety-relief valve out of service TBV Turbine bypa&s valve TBVOOS Turbine bypa-,. valve out of service TCV Turbine control valve TCVSC Turbine control valve slow closure TIP Traversing in-core probe TIPOOS Traversing in-core probe out of service TSV Turbine stop valve 3DM 3-D Monicore

NON-PROPRIErARY COLR LaSalle 2 Revision 9 Page 6 of 36 1

3. General Information Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values.

Rated core flow is 108.5 Mlbm/hr. Operation up to 105% rated flow is licensed for this cycle. Licensed rated thermal power is 3546 MWth.

For thermal limit monitoring above 100% rated power or 100% rated core flow, the 100% rated power and the 100% core flow values, respectively, can be used unless otherwise indicated in the applicable table.

The thermal limits provided in the COLR support SLO for all analyzed equipment out of service options.

Table 3-1 defines the three exposure ranges used in the COLR. The end of rated (EOR) exposure is defined as the cycle exposure corresponding to all rods out, 100% power/1 00% flow, and normal feedwater temperature.

The term (EOR - 3331 MWd/MTU) means the EOR exposure minus 3331 MWd/MTU of exposure. The value of the EOR exposure is based on actual plant operation and is thus determined from projections to this condition made near, but before, the time when the EOR15 - 3331 MWd/MTU exposure will be reached. For cycle exposure dependent limits at the exact MOC exposure, the more limiting of the BOC to MOC and the MOC to EOC limits should be used. This can be achieved by applying the MOC to EOC limits to the MOC point as all cycle exposure dependent limits in the MOC to EOC limit sets are the same as, or more limiting than, those in the BOC to MOC limit sets.

Table 3-1 Cycle Exposure Range Definiftions (Reference 7)

Nomenclature Cycle Exposure Range BOC to MOCBOCI 5 to (EOR1 5 - 3331 MWdlMTU) or BOC15 to (EOR15 - 3022 MWd/STU)

MOC to EOC (EOR15 - 3331 MWd/MTU) to EOC15 or I (EOR 15 - 3022 MWd/STU) to EOC 5 BOC to EOC BOC15 to EOC1 5

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 7 of 36 1

4. Average Planar Linear Heat Generation Rate The MAPLHGR values for the most limiting lattice of each fuel type as a function of average planar exposure are given in Tables 4-1 and 4-2. During single loop operation, these limits are multiplied by the fuel-dependent SLO multiplier listed in Table 4-3. The MAPLHGR values in Tables 4-1 and 4-2 along with the MAPLHGR SLO multipliers in Table 4-3 provide coverage for all modes of operation.

Table 4-1 MAPLHGR for GNF2 Fuel (Reference 7)

Avg. Planar Exposure MAPLHGR (GWdiMTU)/ (kW/FT)

(GWd/STU) 0.00/0.00 13.78 18.91 /17.15 13.78 67.00 / 60.78 6.87 70.00 / 63.50 5.50 Table 4-2 MAPLHGR for ATRIUM-10 Fuel (Reference 7)

Avg. Planar Exposure MAPLHGR (GWd/MTU)/ (kW/FT)

(GWd/STU) 0.00/0.00 12.81 23.611 / 21.41 12.81 61.10/55.42 9.10 70.40 / 63.86 7.30 Table 4-3 MAPLHGR SLO Multiplier for GNF2 and ATRIUM-10 Fuel, BOC to EOC (Reference 7)

SLO Fuel Type MAPLHGR Multiplier GNF2 0.78 ATRIUM-10 0.78

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 8 of 36

5. Operating Limit Minimum Critical Power Ratio 5.1. Manual Flow Control MCPR Limits The steady-state OLMCPRs given in Table 5-2 are the maximum values obtained from analysis of the pressurization events, non-pressurization events, and the Option III stability evaluation. MCPR values are determined by the cycle-specific fuel reload analyses in Reference 7. Table 5-2 is used in conjunction with the ARTS-based power and flow dependencies presented in the sections below.

5.1.1. Power-Dependent MCPR The power-dependent MCPR multiplier, Kp, is determined from Table 5-3, and is dependent only on the power level and the Application Group (EOOS). The product of the steady state OLMCPR and the proper Kp provides the power-dependent OLMCPR.

5.1.2. Flow-Dependent MCPR Tables 5-4 through 5-5 give the MCPRF limit as a function of the core flow, based on the applicable plant conditions. The MCPRF limit determined from these tables is the flow-dependent OLMCPR. Table 5-5, for SLO, was created by adjusting the Table 5-4 limits by the delta of the SLO and DLO SLMCPR values (0.03) as stated in Reference 7 and clarified in Reference 15.

The data in Table 5-4 is taken from Reference 7.

5.2. Scram Time Option A and Option B MCPR analyses and results are dependent upon core average control rod blade scram speed insertion times.

The Option A scram time is the Improved Technical Specification scram speed based insertion time. The core average scram speed insertion time for 20% insertion must be less than or equal to the Technical Specification scram speed insertion time to utilize the Option A MCPR limits. Reload analyses performed by GNF for Cycle 15 Option A MCPR limits utilized a 20% core average insertion time of 0.900 seconds (Reference 10).

To utilize the MCPR limits for the Option B scram speed insertion times, the core average scram speed insertion time for 20% insertion must be less than or equal to 0.694 seconds (Reference 10) (0.672 seconds at notch position 39, Reference 11). See Table 5-1 for a summary of scram time requirements related to the use of Option A and Option B MCPR limits.

If the core average scram insertion time does not meet the Option B criteria, but is within the Option A criteria, the appropriate steady state MCPR value may be determined from a linear interpolation between the Option A and B limits with standard mathematical rounding to two decimal places. When performing the linear interpolation to determine MCPR limits, ensure that the time used for Option A is 0.900 seconds (0.875 seconds to notch position 39, Reference 11). Note that making interpolations using the Table 5-2 data is conservative because the stability based OLMCPR sets the limit in many conditions. The Option A to Option B linear interpolation need not include the stability OLMCPR penalty on the endpoints when the calculation is made. However, the result of the linear interpolation is required to be 1.48 or greater for the steady state OLMCPR due to the OPRM PBDA setpoint (see Section 9 of the COLR and Reference 7).

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 9 of 36 Table 5-1 Scram Times Required for Option A and Option B Application at Notch Position 39 (References 10 and 11)

Notch Scram Time Required for Option A Scram Time Required for Option B Position* Application Application 39 _<0.875 sec. _<0.672 sec.

- The insertion time to a notch position is conservatively calculated using the CRD reed switch drop-out time per Reference 11.

5.3. Recirculation Flow Control Valve Settings Cycle 15 was analyzed with a maximum core flow runout of 105%; therefore the recirculation pump flow control valves must be set to maintain core flow less than 105% (113.925 Mlbm/hr) for all runout events.

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 10 of 36 1

Table 5-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for ATRIUM-10 and GNF2 Fuel (Reference 7)

DLO/ Exposure Optlon A Option B Application Group ApplicationGroup SLO Range GNF2 ATRM10 GNF2 ATRM10 BOC-MOC 1.50 1.48 (2) 1.48 (2) 1.48 (2)

Base Case DLO MOC-EOC 1.56 1.53 1.51 1.48 BOC-MOC 1.59 1.48 1.59 1.48 (2)

Base Case SLO(11 MOC-EOC 1.59 1.56 (3) 1.59 1.51 Base Case + TCVSC DL BOC-MOC 1.58 1.57 1.48 1.48 (2)

+ RPTOOS + PROOS MOC-EOC 1.64 1.68 1.54 1.51 Base Case + TCVSC SLO"1 BOC-MOC 1.61 1.60 1.59 1.49

+ RPTOOS + PROOS L' -

MOC-EOC 1.67 1.71 1.59 1.54 BOC-MOC 1.53 1.48 1.48 1.48 (2)

Base Case + TCVSC +DL TBVOOS (all 5 valves) MOC-EOC 1.59 1.53 1.54 1.50 Base Case + TCVSC + SLO( 1 ) BOC-MOC 1.59 1.51 1.59 1.48 TBVOOS (all 5 valves) MOC-EOC 1.62 1.56 1.59 1.53 Base Case + TCVSC + BOC-MOC 1.61 1.59 1.51 1.48 TBVOOS (all 5 valves) DLO

+ RPTOOS + PROOS MOC-EOC 1.68 1.71 1.58 1.54 Base Case + TCVSC + BOC-MOC 1.64 1.62 1.59 1.51 TBVOOS (all 5 valves) SLO')-

+ RPTOOS + PROOS MOC-EOC 1.71 1.74 1.61 1.57 (1) For single loop operation, the OLMCPR is the greater of (a) the OPRM based OLMCPR value of 1.48 or (b) 0.03 greater than the two loop limit. However, a minimum value of 1.59 is required for GNF2 fuel to protect the OLMCPR set by the single loop operation recirculation pump seizure event (Reference 7). The single loop operation recirculation pump seizure event is less limiting than the OPRM setpoint for ATRIUM-10 fuel.

(2) OLMCPR is set to reflect OPRM amplitude setpoint of 1.11 (OLMCPR of 1.48) (References 7 and 13). The OPRM amplitude setpoint and resultant OLMCPR are applicable to both DLO and SLO, without alteration.

(3) As part of the Kp improvement analysis (see Reference 7), a requirement is added that the ATRIUM 10 Option A Base Case MOC-EOC DLO OLMCPR have a minimum value of 1.53. The minimum SLO value needs to be increased by the SLO adder of 0.03 resulting in a value of 1.56.

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 11 of 36 1

Table 5-3 Power-Dependent MCPR Multipliers (Kp) for ATRIUM-10 and GNF2 Fuel, DLO and SLO, BOC to EOC, Option A and Option B (Reference 7)

Kp, MCPR Limit Multiplier (as a function of % rated power)

Application Group 0% P 25% P 45% P 60% P 85% P 85.01%P 100% P Base Case 1.338 1.338 1.191 1.191 1.061 1.061 1.000 Base Case + TCVSC

+ RPTOOS + 1.488 1.488 1.378 1.296 1.174 1.097 1.000 PROOS Base Case + TCVSC

+ TBVOOS (all 5 1.379 1.379 1.228 1.207 1.097 1.097 1.000 valves)

Base Case + TCVSC

+TBVOOS (all 5 1.488 1.488 1.378 1.296 1.174 1.097 1.000 valves) +

RPTOOS + PROOS

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 12 of 36 1

Table 5-4 DLO Flow-Dependent MCPR Limits (MCPRF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B (Reference 7)

Flow

(% Rated) MCPRF 0.0 1.91 30.0 1.72 105.0 1.25 Table 5-5 SLO Flow-Dependent MCPR Limits (MCPRF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B (References 7 and 15)

Flow

(% Rated) MCPRF 0.0 1.94 30.0 1.75 105.0 1.28

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 13 of 36 1

6. Linear Heat Generation Rate The linear heat generation rate (LHGR) limit is the product of the exposure dependent LHGR limit from Table 6-1 or Table 6-2 and the minimum of: the power dependent LHGR Factor, LHGRFACp, or the flow dependent LHGR Factor, LHGRFACF as applicable. The LHGRFACp multiplier is determined from Table 6-3. The LHGRFACF multiplier is determined from either Table 6-4 or Table 6-5. The SLO multipliers in Tables 6-4 and 6-5 have been limited to a maximum value of 0.78, the SLO LHGR multiplier for GNF2 and ATRIUM-10 fuel.

Table 6-1 LHGR Limit for GNF2 Fuel (References 8 and 12J See Appendix A (1)

Table 6-2 LHGR Limit for ATRIUM-1 0 Fuel (Reference 9)

Peak Pellet Exposure LHGR Limit (GWd/MTU) / (GWd/STU) (kW/ft) 0.0 /0.0 13.4 17.7/16.06 13.4 I 61.1 /55.43 9.1 70.4/63.87 7.3 I (1) The only LHGR limits required to be used to monitor GNF2 fuel for L2C15 are the U02 pin limits (Reference 12). Gadolinia containing pins are non-limiting in L2C15 for the GNF2 fuel designs.

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 14 of 36 1

Table 6-3 Power-Dependent LHGR Multipliers (LHGRFACp) for ATRIUM-10 and GNF2 Fuel, DLO and SLO, BOC to EOC (Reference 7)

LHGRFACp (as a function of % rated power)

Application Group 0% P 25% P 45% P 60% P 85% P 100% P Base Case 0.608 0.608 0.713 0.791 0.922 1.000 Base Case + TCVSC

+ RPTOOS + 0.608 0.608 0.713 0.761 0.831 1.000 PROOS Base Case + TCVSC

+ TBVOOS (all 5 0.608 0.608 0.713 0.791 0.922 1.000 valves)

Base Case + TCVSC

+ TBVOOS (all 5 0.608 0.608 0.713 0.761 0.822 1.000 valves) +

RPTOOS + PROOS

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Table 6-4 Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, Pressurization (1 TCV/TSV Closed or OOS), All Application Groups (Reference 7)

Flow

(%

(% Rated) DLO LHGRFACF SLO LHGRFACF 0.0 0.110 0.110 30.0 0.410 0.410 67.0 0.78 0.78 89.0 1.000 0.78 105.0 1.000 0.78 Table 6-5 Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, No Pressurization (All TCVITSV In-Service), All Application Groups (Reference 7)

Flow Fo

(% Rated) DLO LHCRFAC; SLO LHGRFACF 0.0 0.250 0.250 30.0 0.550 0.550 53.0 0.78 0.78 75.0 1.000 0.78 105.0 1.000 0.78

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 16 of 36 1

7. Rod Block Monitor The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 3):

Table 7-1 Rod Block Monitor Setpoints Rod Block Monitor Upscale Trip Function Allowable Value Two Recirculation Loop 0.66 Wd + 54.0%

Operation Single Recirculation Loop 0.66 Wd + 48.7%

Operation I The setpoint may be lower/higher and will still comply with the rod withdrawal error (RWE) analysis because RWE is analyzed unblocked. The allowable value is clamped with a maximum value not to exceed the allowable value for a recirculation loop drive flow (Wd) of 100%.

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

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 17 of 36

8. Traversing In-Core Probe System 8.1. Description When the traversing in-core probe (TIP) system (for the required measurement locations) is used for recalibration of the LPRM detectors and monitoring thermal limits, the TIP system shall be operable with the following:
1. movable detectors, drives and readout equipment to map the core in the required measurement locations, and
2. indexing equipment to allow all required detectors to be calibrated in a common location.

The following applies for use with 3DM (References 4, 7):

The total number of failed and bypassed LPRMs does not exceed 25%. In addition, no more than 14 TIP channels can be OOS (failed or rejected).

Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable calibration functions.

8.2. Bases The operability of the TIP system with the above specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core. The normalization of the required detectors is performed internal to the core monitoring software system.

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 18 of 36 1

9. Stability Protection Setpoints I The OPRM PBDA trip settings are shown in Table 9-1 and were taken from the Reference 13 transmittal.

Table 0-1 OPRM PBDA Trip Setpoints (References 7 and 13)

Corresponding Maximum PBDA Trip Amplitude Setpoint (Sp) Confirmation Count Setpoint (Np) 1.11 14 The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system.

The OPRM PBDA trip settings are based, in part, on the cycle specific OLMCPR and the power dependent MCPR limits. Any change to the OLMCPR values and/or the power dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA trip settings.

The OPRM PBDA trip settings are applicable when the OPRM system is declared operable, and the associated Technical Specifications are implemented.

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 19 of 36 1

10. Modes of Operation The allowed modes of operation with combinations of equipment out-of-service are as described below (Reference 7).

Table 10-1 Allowed Modes of Operation and EOOS Combinations (Reference 7)

Equipment Out of Service Options (1)(2)(4)(5) Short Name Base Case (Option A or B) (3) Base Base Case + SLO (Option A or B) Base SLO Base Case + TCVSC + RPTOOS + PROOS (Option A or B) Combined EOOS 1 Base Case + TCVSC + RPTOOS + PROOS + SLO (Option A or B) Combined EOOS 1 SLO Base Case + TCVSC + TBVOOS (all 5 valves) (Option A or B) Combined EOOS 2 Base Case + TCVSC + TBVOOS (all 5 valves) + SLO (Option A or B) Combined EOOS 2 SLO Base Case + TCVSC + TBVOOS (all 5 valves) + RPTOOS + PROOS Combined EOOS 3 (Option A or B)

Base Case + TCVSC + TBVOOS (all 5 valves) + RPTOOS + PROOS + SLO Combined EOOS 3 SLO (Option A or B)

(1) Base case Includes 1 SRVOOS + 1 TCV/TSV 0OS + FWHOOS/FFWTR + 1 MSIVOOS + 2 TBVOOS + PLUOOS, and also includes 1 TIPOOS (up to 14 TIP channels not available) any time during the cycle, including BOC, and up to 25% of the LPRMs out-of-service. The FWHOOS/FFWTR analyses cover a maximum reduction of 100°F for the feedwater temperature.

A nominal LPRM calibration interval of 2000 EFPH (2500 EFPH maximum) is supported for L2C15.

(2) TBVOOS (all 5 valves) is the turbine bypass system out of service which means that 5 TBVs are not credited for fast opening and 3 TBVs are not credited to open In pressure control. For the 2 TBVOOS condition that is a part of the base case, the assumption is that both of the TBVs do not open on any signal and thus remain shut for the transients analyzed (i.e. 3 TBVs are credited to open in pressure control). The MCFL is currently set at 126.6 and will only allow opening of TBV's #1,

  1. 2, #3, and #4 during a slow pressurization event. The MCFL does not use the TBV position feedback signal to know how many TBVs have opened or how far each has opened. The #5 TBV is not available based on the current MCFL setpoint and thus cannot be used as one of the credited valves to open in pressure control.

(3) With all TCV/TSV In-Service, the Base Case should be used with the LHGRFACF values from Table 6-5 (Reference 7).

With 1 TCV/TSV 0OS, the Base Case must be used with the LHGRFACF values from Table 6-4. The one Stuck Closed TCV and/or TSV EOOS conditions require power level S185% of rated. The one MSIVOOS condition is also supported as long as thermal power is maintained s 75% of the rated.

(4) The + sign that is used in the Equipment Out of Service Option / Application Group descriptions designates an "and/or".

(5) All EGOS Options (Reference 7 Application Groups) are applicable to ELLLA, MELLLA, ICF and Coastdown realms of operation with the exception that SLO is not applicable to MELLLA or ICF (References 5 and 6). The MOC to EOC exposure range limit sets are generated by GNF to include application to coastdown operation (Methodology Reference 19).

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 20 of 36

11. Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1. XN-NF-81-58 (P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," March 1984.
2. ANF-524 (P)(A) Revision 2 and Supplements 1 and 2, "ANF Critical Power Methodology for Boiling Water Reactors," November 1990 [XN-NF-524 (P)(A)].
3. ANF-913 (P)(A) Volume 1 Revision 1, and Volume 1 Supplements 2, 3, 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," August 1990.
4. XN-NF-84-105 (P)(A), Volume 1 and Volume 1 Supplements 1 and 2; Volume 1 Supplement 4, "XCOBRA-T:

A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," February 1987 and June 1988, respectively.

5. EMF-2209 (P)(A), Revision 3, "SPCB Critical Power Correlation," September 2009.
6. ANF-89-98 (P)(A), Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," May 1995.
7. EMF-85-74 (P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.
8. EMF-CC-074 (P)(A) Volume 4 Revision 0, "BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2," August 2000.
9. ANF-CC-33 (P)(A) Supplement 1 Revision 1 and Supplement 2, "HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option," August 1986 and January 1991, respectively.
10. 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," June 1986.

11. XN-NF-85-67 (P)(A) Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel,"

September 1986.

12. XN-NF-80-1 9 (P)(A) Volume 3 Revision 2, "Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," January 1987.
13. XN-NF-80-1 9 (P)(A) Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis," March 1983.
14. EMF-2158 (P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors:

Evaluation and Validation of CASMO-4/MICROBURN-B2," Siemens Power Corporation, October 1999.

15. EMF-2245 (P)(A), Revision 0, "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel," August 2000.
16. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model," May 2001.
17. NEDO-32465-A, "BWR Owner's Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
18. ANF-1358 (P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors,"

September 2005.

19. NEDE-2401 1-P-A-1 9 (Revision 19), "General Electric Standard Application for Reactor Fuel," May 2012 and the U.S. Supplement NEDE-24011-P-A-19-US of May 2012.
20. NEDC-33106P-A Revision 2, "GEXL97 Correlation for ATRIUM-1 0 Fuel," June 2004.

NON-PROPRIETARY COLR LaSalle 2 Revision 9 Page 21 of.36 I Appendix A

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 22 of 36 Global Nuclear Fuel Global Nuclear Fuel OfGETuJo*bA& IhI:chl

  • Jaw: Ve=n*,;o 0000-01 56-11 47-FBIR-NP Revision 0 January 2013 Non-ProprietaryInformation-ClassI (Public)

FUEL BUNDLE INFORMATION REPORT FOR LASALLE UNIT 2 RELOAD 14 CYCLE 15 Copyright 2013 Global \,Vclear Fuel-Americas, LLC All Rights Resered

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 23 of 36 LaSalle 2 0000-0156-1 147-FBIR-NP R~n~ IA Reload 14 Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas. LLC (GNF-A) solely for use by Exelon ("Recipient") in support of the operating license for LaSalle 2 (the "Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.

The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract. is not authorized by GNF-A. In the event of any such unauthorized use. GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness. accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind wshich may result from such use of such information.

Information Notice This is a non-proprietary %ersion of the document 0000-0156-1147-FBIR-P. Revision 0. which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( I].

Page 2

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 24 of 36 LaSalle 2 0000-0 156-1 147-FBIR-NP Kevciuuu e s'o~na~n I. Introduction and Summary This report, which supplements the Supplemental Reload Licensing Report, contains thermal-mechanical linear heat generation rate (LHGR) limits for the GNF-A fuel designs to be loaded into LaSalle Unit 2 for Cycle 15. These LHGR limits are obtained from thermal-mechanical considerations only. Approved GNF-A calculation models documented in Reference I were used in performing this analysis.

LHGR limits as a function of exposure for each bundle of the core design are given in Appendix A. The LHGR values provided in Appendix A provide upper and lower exposure dependent LHGR boundaries which envelope the actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded to two places past the decimal.

Appendix B contains a description of the fuel bundles. Table B-I contains a summary of bundle-specific information, and the figures provide the enrichment distribution and gadolinium distribution for the fuel bundles included in this appendix. These bundles have been approved tfr use under the fuel licensing acceptance criteria of Reference I.

Page 3

COLR LaSalle 2 Revision 9 NON-PROPKIETARY Pagz 25 of 38 LaSalle 2 0000-0156-I 147-FBIR-NP D 1 4

2. References
1. General Electric Standard Application for Reactor Fuel. NEDE-2401I -P-A-19, May 2012; and the US Supplement. NEDE-2401 I-P-A-19-US. May 2012.

Page 4

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 26 of 36 LaSalle 2 0000-0156-1147-FBIR-NP Reload 14 Revision 0 Appendix A UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P IOCG2B408-12GZ- 120T2- 150-T6-4069 (GNF2)

Bundle Number. 4069 Peak Pellet Exposure U0 2 LHGR Limit GWdlMT (GWdiST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft

((

_____________________________ ))

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (( 1]

Page 5

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 27 of 36 LaSalle 2 0000-0156-I 147-FBIR-NP Relnad 14 Rev iqinn 0 UO2 Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI OCG2B410-17GZ- 120T2-150-T6-4070 (GNF2)

Bundle Number. 4070 Peak Pellet Exposure U0, LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia 2

LHGR Limit GWd/MT (GWd/ST) kWift

(( _________________

___________________________]11 I Bounding gadolnia LHGR limit for all gdolinium concentrations occurring in this bundle desuin ((

1]

Page 6

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 28 of 36 LaSalle 2 0000-0156-1147-FBIR-NP Reload 14 Revision 0 UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P IOCG2B408-15GZ- 120T2-150-T6-4206 (GNF2)

Bundle Number 4206 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft

((_________________1 3 Bounding gadolinia LHGR limit for all gadolinium concenlrations occumng in this bundle design ((

11 Page 7

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 29 of 36 LaSalle 2 0000-01 56-I 147-FBIR-NP D *l*.4 IA e 0a UO 2 IGd Thermal-Mechanical LHGR Limits Bundle T) pe: GNF2-PI 0CG2B403- l6GZ- 12012.- 150-T6-4205 (GNF2)

Bundle Number. 4205 Peak Pellet Exposure U0 2 LHGR Limit GWd/NlT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4 GWdIMT (GWdIST) kW/ft I[ _________________

______________________________ ))

4 Bounding gadulinia LHGR limn for all gadolinium concenrations occurring in this bundle design [H

))

Page 9

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 30 of 36 LaSalle 2 0000-0156-1147-FBIR-NP Reloaa 14 .vy s UO 21Gd Thermal-Mechanical LHGR Limits Bundle Type- GN F2-PI0CG2B402-17GZ- 120T2-- 150-T6-4207 (GNF2)

Bundle Number 4207 Peak Pellet Exposure L'0z LHGR Limit GWd/MT (GWdIST) kW/ft Peak Pellet Exrposure Mlost Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft 5 Bounding gadolinia LHGR limit for all gadolinium concentrations occumng in this bundle design (( I]

Page 9

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 31 of 36 LaSalle 2 0000-0156-i 147-FBIR-NP Reload 14 Revision 0 Appendix B Fuel Bundle Information Table B-I Bundle Specific Information Exposure Weight Weight Max Fuel Bundle Enrichment of U0 2 of U Iý at at Nie k6 Bundle Number (wt% U-235) (kg) (kg) 20CC GWd/T)

____ ______ ___(GWd/ST)

GNF2-P I 0CG2R408-12GZ-120T22-150-T6-4069 (GNF2)

GNF2-P I 0CG2B410-17GZ-120T2-150-T6-4070 (GNF2)

GNF2-P I 0CG2B408-15GZ-120T2--150-T6-4206 (GNF2)

GNF2-P I0CG2B403-16GZ-120T2-150-T6-4205 (GNF2)

GNF2-P I0CG2B402-17GZ-120T2- 150-T6-4207 (GNF2)

'Maximum latlLe kLfor the must reactlie uncontrolled state plus a (( 1] adder for uncertaintles.

Page 10

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 32 of 36 LaSalle 2 0000-0156-I 147-FBIR-NP Kelon2 14 IRevijou V

((

11 FigureB-3 Enrichment and Gadolinium Distribution for EDB No, 4069 Fuel Bundle GNF2-PIOCG2B-I0-12GZ-]20T2-150-T6-4069 (GNF2)

Page II

COLR LaSalle 2 Revision S)

NON-PROPRIETARY Page 33 of 36 LaSalle 2 0000-0156-I 147.FBIR-NP R lc* IA Re]-a,' 14 Reyiýign (k 11 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 4070 Fuel Bundle GNF2-PIOCG2B4I0-17GZ-12OT2-1 50-T6-4070 (GNF2)

Page 12

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 34 of 36 LaSalle 2 00O0-0156-l 147-FBIR-NP Rel.nnrl 14 Revkinn il Reload 14 It 11 Figure B-3 Enrichment and.Gadolinium Distribution for EDB No. 4206 Fuel Bundle GNF2-PIOCG2B408-15GZ-120T2-150-T6-4206 (GNF2)

Page 13

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 35 of 36 LaSalle 2 0000-0 156-11 47-FBIR-NP DM*,JnA 3A M-A 14 . I

[I 11 Figure 13- Enrichment and Gadolinium Distribution ror EDB No. 4205 Fuel Bundle GNF2-PIOCG2B403-16GZ-12OT2-l 50-T6-4205 (GNF2)

Page 14

COLR LaSalle 2 Revision 9 NON-PROPRIETARY Page 36 of 36 LaSalle 2 0000-0156-I l47-FB[R-NP RpInn4 ll Repvision (I Reload 14 It 11 Figure B-A Enrichment and Gadolinium Distribution for EDB No. 4207 Fuel Bundle GNFZ-PIOCG2B402-17GZ-120T2-150-T6-4207 (GNF2)

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