SVP-05-026, Core Operating Limits Report for Plant Cycle 19

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Core Operating Limits Report for Plant Cycle 19
ML051120192
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 04/15/2005
From: Tulon T
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVP-05-026
Download: ML051120192 (28)
v • d • e


Text

s Exelon Generation Company, LLC www.exeloncorp.com Exeltnm lean NEux Quad Cities Nuclear Power Station 22710 206' Avenue North Cordova, IL61242-9740 SVP-05-026 April 15, 2005 U. S. Nuclear Regulatory Commission ATTN
Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Unit 1 Renewed Facility Operating License No. DPR-29 NRC Docket Number 50-254

Subject:

Core Operating Limits Report for Quad Cities Unit 1 Cycle 19 Quad Cities Nuclear Power Station Unit 1 was shutdown for Refuel Outage 18 (Q1 R1 8) on March 21, 2005. In accordance with Technical Specifications Section 5.6.5.d, enclosed is the Core Operating Limits Report (COLR) for Quad Cities Unit 1 Cycle 19.

Should you have any questions concerning this letter, please contact Mr. W. J. Beck at (309) 227-2800.

Respectfully, Ti rhy J. Tulon Site Vice President Quad Cities Nuclear Power Station Attachment A: Core Operating Limits Report for Quad Cities Unit 1 Cycle 19 cc: Regional Administrator- NRC Region IlIl NRC Senior Resident Inspector - Quad Cities Nuclear Power Station

  • 40° V

Attachment A Core Operating Limits Report for Quad Cities Unit 1 Cycle 19

COLR Quad Cities 1 Revision 0 Page 1 Quad Cities Unit 1 Cycle 19 Core Operating Limits Report Revision 0

COLR Quad Cities 1 Revision 0 Page 2 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 . ......................................... s8 5.1. Manual Flow Control MCPR Limits .......................................... s8 5.1.1. Power-DependentMCPR .......................................... s8 5.1.2. Flow-DependentMCPR M8 ..........................................

5.2. Automatic Flow Control MCPR Limits ......................................... 8 5.3. Scram Time ........................................... 9 5.4. Recirculation Pump Motor Generator Settings ......................................... 9

6. Linear Heat Generation Rate . . ..................................13
7. Rod Block Monitor .......................................... 24
8. Modes of Operation ..................... 25
9. Methodology . . . 26

COLR Quad Cities 1 Revision 0 Page 3 List of Tables Table 4-1 MAPLHGR for bundle(s):

GE1 4-P1 ODNAB409-17GZ-1 DOT-1 45-T6-2825 GE1 4-P1 ODNAB408-15GZ-1 DOT-1 45-T6-2826 GE1 4-P1 ODNAB1 94-4G7.0-1 DOT-1 45-T6-2647 GE1 4-P1 ODNAB411-14GZ-1 DOT-1 45-T6-2564 GEI 4-P1 ODNAB409-15GZ-1 DOT-1 45-T6-2565 ................................................... 7 Table 4-2 MAPLHGR SLO multiplier ................................ ............................... 7 Table 5-1 MCPR Option A Based Operating Limits ........................................................ 10 Table 5-2 MCPR Option B Based Operating Limits ........................................................ 10 Table 5-3 MCPR(P) for GE Fuel ............................................................... 11 Table 5-4 MCPR(F) Limits for GE Fuel All EOOS except TCV Stuck Closed DLO or SLO Operation.............................................................................................................. 12 Table 5-5 MCPR(F) Limits for GE Fuel with TCV Stuck Closed DLO or SLO Operation ......... 12 Table 6-1: LHGR Limit for GE14-Pl ODNAB411-14GZ-1 DOT-1 45-T6-2564 ......... ................ 13 Table 6-2: LHGR Limit for GE14-P1ODNAB409-15GZ-100T-145-T6-2565 .......................... 14 Table 6-3: LHGR Limit for GE14-P1ODNAB194-4G7.0-100T-145-T6-2647 ......................... 14 Table 6-4: LHGR Limit for GE14-P1 ODNAB409-17GZ-100T-145-T6-2825 ........................... 15 Table 6-5: LHGR Limit for GE1 4-P10DNAB408-15GZ-1 DOT-1 45-T6-2826 .......................... 15 Table 6-6: LHGR Limit for GE1 4-P1ODNAB1 94-4G7.0-1 DOT-1 45-T6-2647, Lattice 5977 ........ 16 Table 6-7: LHGR Limit for GE1 4-P1ODNAB409-17GZ-1 DOT-1 45-T6-2825, Lattice 6828 ........ 17 Table 6-8: LHGR Limit for GE14-P1ODNAB408-15GZ-1OOT-145-T6-2826, Lattice 6834 ........ 18 Table 6-9: LHGR Limit for GE1 4-P1ODNAB411-14GZ-1 DOT-1 45-T6-2564, Lattice 5571 ........ 19 Table 6-10: LHGR Limit for GE14-P1ODNAB409-15GZ-100T-145-T6-2565, Lattice 5577....... 20 Table 6-11: LHGR Limit for GE14-P1ODNAB409-15GZ-100T-145-T6-2565, Lattice 5576....... 21 Table 6-12 LHGRFAC(P) for GE Fuel ............................................................... 22 Table 6-13 LHGRFAC(F) Multipliers, All Cases except TCV Stuck Closed ............. ............ 23 Table 6-14 LHGRFAC(F) Multipliers for TCV Stuck Closed ............................................... 23 Table 6-15 LHGR SLO Multiplier ............................................................... 23

COLR Quad Cities 1 Revision 0 Page 4

1. References
1. Exelon Generation Company, LLC, Docket No. 50-254, Quad Cities Nuclear Power Station, Unit 1 Facility Operating License, License No. DPR-29.
2. Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Concerning the Removal of Cycle-Specific Parameter Limits from Tech Specs, October 3, 1988.
3. GNF Document, 0000-0028-1626-SRLR, Rev. 0, "Supplemental Reload Licensing Report for Quad Cities 1 Reload 18 Cycle 19," January 2005 (TODI NF0500036, Revision.0).
4. GE Document, GE-NE-J11-03912-00-01-R2, "Dresden 2 and 3 Quad Cities 1 and 2 Equipment Out-Of-Service and Legacy Fuel Transient Analysis," September 2003 (TODI NFM0100091 Sequence 02).
5. GNF Letter, FRL02EX-01 3, "Quad Cities Unit 1 Cycle 18 and Dresden Unit 3 Cycle 18 Pellet Based LHGR Limits", September 30, 2002.
6. GE DRF C51-00217-01, "Instrument Setpoint Calculation Nuclear Instrumentation, Rod Block Monitor, Commonwealth Edison Company, Quad Cities 1 & 2," December 14, 1999.
7. Quad Cities TODI QDC-04-31.01, "OPL-3 for Quad Cities Unit 1 Cycle 19 (Revision 1),"

November 19, 2004.

8. GE Design Basis Document, DB-001 2.03, Revision 0, "Fuel-Rod Thermal-Mechanical Performance Limits for GE1 4C," May 2000.
9. NF Calculation, BNDG:02-001, Revision 0, "Determination of Generic MCPRF Limits," May 17, 2002.
10. GE Document, NEDE-2401 1-P-A-1 4, "General Electric Standard Application for Reactor Fuel,"

June 2000.

11. Nuclear Fuels TODI NF0400194, Revision 0, "Q1C19 FRED," August 10,2004.
12. Nuclear Fuels Letter, NF-MW:02-0413, "Approval'of GE Evaluation of Dresden and Quad Cities Pressure Regulator Out of Service Analysis," October 22, 2002.
13. Nuclear Fuels Letter, NF-MW:02-0081, "Approval of GE Evaluation of Dresden and Quad Cities Extended Final Feedwater Temperature Reduction," August 27, 2002.
14. GNF Letter, MJM-EXN-EE1 036, "QC1 Cl 8A Pellet Based LHGR Limits for the Fresh Fuel Bundle Type 2647," November 17, 2004.
15. Nuclear Fuels Letter, NF-MW:03-069, "Dresden and Quad Cities Operation with One TSV OOS,"

July 28, 2003.

16. GNF Letter, MJM-EXN-EE1-04-047, "TSD B207: Quad Cities 1 C19 LHGR Limits", December 17, 2004.
17. GNF Document 0000-0014-8357-SRLR, Rev. 0, "Supplemental Reload Licensing Report for Quad Cities 1 Q1 Ml 6 Cycle 18A", May 2003 (TODI NF0300045, Revision 0).
18. GE Document, GE-NE-0000-0034-6539-RO, "Dresden/Quad Cities Clarification on Required Turbine Bypass Capacity for PRC 04-23 issue", November 17, 2004.
19. GNF Letter, MJM-EXN-EXO-04-038, "Exelon Power Load Unbalance (PLU) Evaluation - Final",

November 22, 2004.

20. FANP Letter, NJC:04:031/FAB04-496, "Startup with TIP Equipment Out of Service," April 20, 2004 (EC 348897-00)

COLR Quad Cities 1 Revision 0 Page 5

2. Terms and Definitions APLHGR Average planar linear heat generation rate APRM Average power range monitor BOC Beginning of cycle DLO Dual loop operation ELLLA Extended load line limit analysis EOC End of cycle EOOS Equipment out of service EOR End of rated conditions (i.e. cycle exposure at 100% power, 100% flow, all-rods-out)

FFTR Final Feedwater Temperature Reduction FWHOOS Feedwater heater out of service GE14 GE14C fuel GNF Global Nuclear Fuel ICF Increased core flow LHGR Linear heat generation rate LHGRFAC(F) Flow dependent LHGR multiplier LHGRFAC(P) Power dependent LHGR multiplier LPRM Local power range monitor MAPFAC(F) Flow dependent MAPLHGR multiplier MAPFAC(P) Power dependent MAPLHGR multiplier MAPLHGR Maximum average planar linear heat generation rate MCPR Minimum critical power ratio MCPR(F) Flow dependent MCPR MCPR(P) Power dependent MCPR MELLLA Maximum extended load line limit analysis MSIV Main Steam Isolation Valve OLMCPR Operating limit minimum critical power ratio PLUOOS Power load unbalance out of service PROOS Pressure regulator out of service RBM Rod block monitor RPTOOS Recirculation Pump Trip Out of Service SLMCPR Safety limit minimum critical power ratio SLO Single loop operation SRVOOS Safety-relief valve out of service TBPOOS Turbine bypass valve out of service TCV Turbine control valve TCVOOS Turbine control valve out of service TSV Turbine Stop Valve TSVOOS Turbine Stop Valve out of service TIP Traversing Incore Probe

COLR Quad Cities 1 Revision 0 Page 6

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 98 Mlb/hr. Operation up to 108% rated flow is licensed for this cycle. Licensed rated thermal power is 2957 MWth.

MCPR(P) and MCPR(F) values are independent of scram time.

LHGRFAC(P) and LHGRFAC(F) values are independent of scram speed.

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.

COLR Quad Cities 1 Revision 0 Page 7

4. Average Planar Linear Heat Generation Rate The MAPLHGR values for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Table 4-1. During single loop operation, these limits are multiplied by the SLO multiplier listed in Table 4-2.

Table 4-1 MAPLHGR for bundle(s):

GE14-PI ODNAB409-17GZ-1 OOT-145-T6-2825 GE14-Pl ODNAB408-15GZ-100T-145-T6-2826 GE14-Pl ODNAB194-4G7.0-1 DOT-145-T6-2647 GE14-Pl ODNAB411-14GZ-1 OOT-145-T6-2564 GE14-PlODNAB409-15GZ-1 OOT-145-T6-2565 (References 3 and 17)

Avg. Planar Exposure MAPLHGR (GWd/MT) (kW/ft) 0.00 11.68 16.00 11.68 44.09 9.16 55.12 8.09 63.50 6.97 70.00 4.36 Table 4-2 MAPLHGR SLO multiplier (Reference 3)

Fuel Type Multiplier GE14 0.77

COLR Quad Cities 1 Revision 0 Page 8

5. Operating Limit Minimum Critical Power Ratio 5.1. Manual Flow Control MCPR Limits The OLMCPR is determined for a given power and flow condition by evaluating the power-dependent MCPR and the flow-dependent MCPR and selecting the greater of the two.

5.1.1. Power-Dependent MCPR For operation at less than 38.5% of rated core thermal power, the OLMCPR as a function of core thermal power (MCPR(P)) is shown in Table 5-3. For operation at greater than 38.5% of rated core thermal power, the OLMCPR as a function of core thermal power is determined by multiplying the applicable rated condition OLMCPR limit shown in Table 5-1 or 5-2 by the applicable MCPR multiplier K(P) given in Table 5-3. For operation at exactly 38.5% of rated core thermal power, the OLMCPR as a function of core thermal power is the maximum of either of the two aforementioned methods evaluated at 38.5% of rated core thermal power.

5.1.2. Flow-Dependent MCPR Tables 5-4 and 5-5 give the MCPR(F) limit as a function of the flow based on the applicable plant condition.- The MCPR(F) limit determined from these tables is the flow dependent OLMCPR.

5.2. Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.

COLR Quad Cities 1 Revision 0 Page 9 5.3. Scram Time Option A and Option B refer to scram speeds.

Option A scram speed is the Improved Technical Specification scram speed. The core average scram speed insertion time for 20% insertion must be less than or equal to the Technical Specification scram speed to utilize Option A MCPR limits. Reload analyses performed by (GNF) for Cycle 19 Option A MCPR limits utilized a 20% core average insertion time of 0.900 seconds (Reference 7).

To utilize the MCPR limits for the Option B scram speed, the core average scram insertion time for 20% insertion must be less than or equal to 0.694 seconds (Reference 7). If the core average scram insertion time does not meet the Option B criteria, but is within the Option A criteria, the appropriate 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 a linear interpolation to determine MCPR limits, ensure that the time used for Option A is 0.900 seconds.

5.4. Recirculation Pump Motor Generator Settings Cycle 19 was analyzed with a maximum core flow runout of 110%; therefore the recirculation pump motor generator scoop tube mechanical and electrical stops must be set to maintain core flow less than 110% (107.8 Mlb/hr) for all runout events (Reference 11). This value is consistent with the analyses of References 3 and 4.

COLR Quad Cities 1 Revision 0 Page 10 Table 5-1 MCPR Option A Based Operating Limits (References 3 and 4)

Cycle E posure

< EOR - 2659 > EOR - 2659 EOOS Combination Fuel Type MWdWMT MWdWMT BASE GE14 1.55 1.66 BASE SLO GE14 1.56 1.67 TBPOOS GE14 1.73 1.75 TBPOOS SLO GE14 1.74 1.76 TCV SLOW CLOSURE GE14 1.62 1.66 TCV SLOW CLOSURE SLO GE14 1.63 1.67 PLUMOS GE14 1.64 1.66 PLUOMS SLO GE14 1.65 1.67 TCV STUCK CLOSED GE14 1.55 1.66 TCV STUCK CLOSED SLO GE14 1.56 1.67 Table 5-2 MCPR Option B Based Operating Limits (References 3 and 4)

Cycle Ex posure

< EOR - 2659 > EOR - 2659 EOOS Combination Fuel Type MWdWMT MWdIMT BASE GE14 1.44 1.49 BASE SLO GE14 1.45 1.50 TBPOOS GE14 1.56 1.58 TBPOOS SLO GE14 1.57 1.59 TCV SLOW CLOSURE GE14 1.45 1.49 TCV SLOW CLOSURE SLO GE14 I 1.46 1.50 PLUOOS GE14 1.47 1.49 PLUOOS SLO GE14 1.48 1.50 TCV STUCK CLOSED GE14 1.44 1.49 TCV STUCK CLOSED SLO GE14 1.45 1.50

COLR Quad Cities 1 Revision 0 Page 11 Table 5-3 MCPR(P) for GE Fuel (Reference 4)

Core Core Thermal Power (% Rated)

EOOS Combination Flow 0 l 25 l 38.5 38.5 l 45 60 l 70 l 70 100

(% Operating Limit Rated) MCPR Operating Limit MCPR Multiplier, Kp S60 3.16 2.58 2.27__ N/A WA 1.00 Base Case - -. 1.32 1.28 1.15

>60 3.77 2.99 2.56

  • 60 3.17 2.59 2.28 Base Case SLO 3.7

-60 2.00 228 1.32 1.28 1.15 NIA N/A 1.00

__ __ _ _ __ __ _ _ _ >60 3.78 3.00 2.57_

  • 560 5.55 3.77 2.82 TBPOOS - - - 1.37 1.28 1.15 N/A NWA 1.00

>60 6.79 4.62 3.45

  • 560 5.56 3.78 2.83 TBPOOS SLO S30 6.80 4.63 3.46 1.37 1.28 1.15 NWA NWA 1.00 TCV Slow Closure S60 5.55 3.77 2.82 1.64 WIA 1.45 1.26 1.11 1.00
  • 560

>60 5.55 6.79 3.77 4.62 2.82 3.45 TCV Slow Closure SLO 1.64 N/A 1.45 1.26 1.11 1.00

  • 60

>60 5.56 6.80 3.78 4.63 2.83 3.46 ClsrowSL7 PLUOOS 2. 1.64 N/A 1.45 1.26 1.11 1.00

>60 6.79 4.62 3.45 PLUOOS SLO 5.56

-60 3.78 2.83 1.64 NWA 1.45 1.26 1.11 1.00

>60 6.80 4.63 3.46 TCV Stuck Closed S60 3.16 2.58 2.27 1.32 1.28 1.15 N/A N/A 1.00

  • 60 3.16 2.58 2.27 N/A10 TCV StuckClosedSL- - 1.212811 N/A TCVStuckClosedSLO 3-0 9 1.32 1.28 1.15 N/A N/A 1.00

>60 3.78 3.00 2.57

COLR Quad Cities 1 Revision 0 Page 12 Table 5-4 MCPR(F) Limits for GE Fuel All EOOS except TCV Stuck Closed DLO or SLO Operation (Reference 9)

Flow l MCPR(F)

(% rated)_l Limit 110.0 1.22 100.0 1.22 0.0 1.86 Table 5-5 MCPR(F) Limits for GE Fuel with TCV Stuck Closed DLO or SLO Operation (Reference 9)

Flow l MCPR(F)

(% rated) Limit 110.0 1.27 108.9 1.27 0.0 l 1.97

COLR Quad Cities 1 Revision 0 Page 13

6. Linear Heat Generation Rate The maximum LHGR shall not exceed the zero exposure limit of 13.4 KW/ft for the following fuel bundles (Reference 8).

GE1 4-P1 ODNAB409-17GZ-1 DOT-1 45-T6-2825 GE1 4-P1 ODNAB408-1 5GZ-1 DOT-1 45-T6-2826 GE1 4-P1 ODNAB1 94-4G7.0-1 OOT-1 45-T6-2647 GE1 4-P1 ODNAB411-14GZ-1 DOT-1 45-T6-2564 GE1 4-P1 ODNAB409-15GZ-1 DOT-1 45-T6-2565 The linear heat generation rate (LHGR) limit is the product of the exposure dependent LHGR limit from Tables 6-1 through 6-11 and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), the flow dependent LHGR Factor, LHGRFAC(F), or the single loop operation (SLO) multiplication factor where applicable. The LHGRFAC(P) is determined from Table 6-12.

The LHGRFAC(F) is determined from Table 6-13 or 6-14. The SLO multiplication factor can be found in Table 6-15.

Table 6-1: LHGR Limit for GE14- P1ODNAB411-14GZ-1iOT-145-T6-2564 (Reference 5)

Lattices 5567, 5568, 5569, 5570, 5572 and 5573 LHGR Limit kW/ft 5567: P1 ODNAL071 -NOG-1 OOT-T6-5567 5568: P1 ODNAL458-6G7.0/8G6.0-1 OOT-T6-5568 5569: P1ODNAL458-6G7.O/7G6.0-1 OOT-T6-5569 5570: PlODNAL451-6G7.017G6.O-1 OOT-E-T6-5570 5572: P1 ODNAL071 -NOG-10OT-V-T6-5572 5573: P1ODNAL071-14GE-10OT-V-T6-5573 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/ft) 0.0000 13.4000 16.0000 13.4000 63.5000 8.0000 70.0000 1 5.0000

COLR Quad Cities 1 Revision 0 Page 14 Table 6-2: LHGR Limit for GEI 4-PI ODNAB409-15GZ-1 OOT-1 45-T6-2565 (Reference 5)

Lattice 5567, 5574, 5575, 5572, and 5578 LHGR Limit kWMft 5567: P1 ODNAL071 -NOG-10OT-T6-5567 5574: P1 ODNAL456-13G7.012G6.0-10OT-T6-5574 5575: P1 ODNAL456-12G7.0/2G6.0-10OT-T6-5575 5572: P1 ODNAL071 -NOG-10OT-V-T6-5572 5578: P1 ODNAL071 -15GE-1 OOT-V-T6-5578 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/ft) 0.0000 13.4000 16.0000 13.4000 63.5000 8.0000 70.0000 5.0000 Table 6-3: LHGR Limit for GEl 4-P1 ODNAB1 94-4G7.0-1 OOT-1 45-T6-2647 (Reference 14)

Lattices 5976, 5978, 5979, 5980, 5981 and 5982 LHGR Limit kWMft 5976: P1ODNAL071-NOG-10OT-T6-5976 5978: P1 ODNAL212-4G7.0-1 OOT-T6-5978 5979: P1 ODNAL216-4G7.0-1OOT-E-T6-5979 5980: P1 ODNAL256-4G7.0-1 OOT-V-T6-5980 5981: P1 ODNAL071 -NOG-1 OOT-V-T6-5981 5982: P1 ODNAL071-4GE-1 OOT-V-T6-5982 U02 Pellet Burnup LHGR Limit (GWdlMTU) (kW/ft) 0.0000 13.4000 16.0000 13.4000 63.5000 8.0000 70.0000 5.0000

COLR Quad Cities 1 Revision 0 Page 15 Table 6-4: LHGR Limit for GE14-P1ODNAB409-17GZ-10OT-145-T6-2825 (Reference 16)

Lattice 6824, 6825, 6826, 6827, 6829, and 6830 LHGR Limit kWMtM 6824: P1 ODNAL071 -NOG-1OOT-T6-6824 6825: P1 ODNAL456-4G7.0/11 G6.012G3.0-1 OOT-T6-6825 6826: P1 ODNAL456-4G7.011 OG6.012G3.0-1 OOT-T6-6826 6827: P1 ODNAL448-14G6.012G3.0-1 OOT-E-T6-6827 6829: P1 ODNAL071-NOG-1 OOT-V-T6-6829 6830: P1 ODNAL071-17GE-100T-V-T6-6830 U02 Pellet Burnup LHGR Limit (GWdlMTU) (kWIft) 0.0000 13.4000 16.0000 13.4000 63.5000 8.0000 70.0000 5.0000 Table 6-5: LHGR Limit for GE1 4-P1 ODNAB408-15GZ-1 OOT-1 45-T6-2826 (Reference 16)

Lattice 6824, 6832, 6833, 6835, and 6836 LHGR Limit kW/ft 6824: P1 ODNAL071 -NOG-1 OOT-T6-6824 6832: P1 ODNAL455-14G6.O/1 G3.0-1 OOT-T6-6832 6833: P1 ODNAL448-13G6.011 G3.0-1 OOT-E-T6-6833 6835: P1 ODNAL071-NOG-1 OOT-V-T6-6835 6836: P1 ODNAL071 -15GE-1OOT-V-T6-6836 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/ft) 0.0000 13.4000 16.0000 13.4000 63.5000 1 8.0000 70.0000 5.0000

COLR Quad Cities 1 Revision 0 Page 16 Table 6-6: LHGR Limit for GE14-P1ODNAB194-4G7.0-100T-145-T6-2647, Lattice 5977 (Reference 14)

Lattice 5977 LHGR Limit kW/ft 5977: P1 ODNAL179-4G7.0-10OT-T6-5977 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/ft) 0.0 13.4000 13.2416 13.4000 14.4581 13.1829 15.6627 12.9384 16.8610 12.9122 18.0548 12.9207 19.2449 12.9377 21.6161 12.7615 22.2852 12.6855 28.3952 11.9909 34.7442 11.2691 41.2946 10.5244 47.9999 9.7621 54.8153 8.9873 61.7044 8.2041 68.6395 5.6279 70.0000 5.0000

COLR Quad Cities 1 Revision 0 Page 17 Table 6-7: LHGR Limit for GE14-P1ODNAB409-17GZ-100T-145-T6-2825, Lattice 6828 (Reference 16)

Lattice 6828 LHGR Limit kW/ft 6828: P1 ODNAL448-14G6.0/2G3.0-10OT-V-T6-6828 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/ft) 0.0 13.40 15.0498 13.40 16.3328 13.3622 17.6026 13.2178 18.8592 13.0750 20.1044 12.9334 22.5708 12.6530 26.2373 12.2362 32.2831 11.5489 38.2384 10.8718 44.0904 10.2066 49.8351 9.5415 55.4794 8.8812 61.0422 8.2765 66.5524 6.5912 70.0 5.00

COLR Quad Cities 1 Revision 0 Page 18 Table 6-8: LHGR Limit for GE14-P1ODNAB408-15GZ-100T-145-T6-2826, Lattice 6834 (Reference 16)

Lattice 6834 LHGR Limit kW/ft 6834: P1 ODNAL448-13G6.0/I G3.0-1 OOT-V-T6-6834 U02 Pellet Burnup LHGR Limit (GWdIMTU) (kW/ft) 0.0 13.40 14.7557 13.40 16.0380 13.3957 17.3111 13.2510 18.5741 13.1074 19.8276 12.9649 22.3110 12.6825 25.9974 12.2635 32.0720 11.5729 38.0552 10.8927 43.9337 10.2244 49.7028 9.5685 55.3685 8.9194 60.9492 8.2886 66.4736 6.6276 70.0 5.00

COLR Quad Cities 1 Revision 0 Page 19 Table 6-9: LHGR Limit for GE14-P1ODNAB411-14GZ-100T-145-T6-2564, Lattice 5571 (Reference 5)

Lattice 5571 LHGR Limit kW/ft 5571: P1 ODNAL451-6G7.017G6.0-1 OOT-V-T6-5571 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/ft) 0.0 13.4000 15.9983 13.4000 17.2727 13.2553 18.5367 13.1116 19.7907 12.9691 22.2716 12.6870 25.9479 12.2691 32.0006 11.5810 37.9622 10.9032 43.8209 10.2372 49.5719 9.5726 55.2216 8.8106 60.7884 8.1396 66.3010 6.7072 70.0000 5.0000

COLR Quad Cities 1 Revision 0 Page 20 Table 6-10: LHGR Limit for GE14-P1ODNAB409-15GZ-10OT-145-T6-2565, Lattice 5577 (Reference 5)

Lattice 5577 LHGR Limit kWlft 5577: P1 ODNAL448-12G7.0/2G6.0-10OT-V-T6-5577 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/lt) 0.0 13.4000 14.8933 13.4000 16.1803 13.3795 17.4565 13.2344 18.7218 13.0906 19.9762 12.9480 22.4568 12.6660 26.1333 12.2480 32.1885 11.5596 38.1530 10.8816 44.0146 10.2152 49.7684 9.3907 55.4205 8.7352 60.9892 8.1212 66.5031 6.6140 70.0000 5.0000

COLR Quad Cities 1 Revision 0 Page 21 Table 6-11: LHGR Limit for GE14-PlODNAB409-15GZ-100T-145-T6-2565, Lattice 5576 (Reference 5)

Lattice 5576 LHGR Limit kWlft 5576: P1 ODNAL448-12G7.012G6.0-10OT-E-T6-5576 U02 Pellet Burnup LHGR Limit (GWdIMTU) (kW/ft) 0.0 13.4000 14.9599 13.4000 16.2535 13.3712 17.5365 13.2253 18.8087 13.0807 20.0704 12.9373 22.5658 12.6536 26.2623 12.2333 32.3461 11.5417 38.3361 10.8607 44.2214 10.1917 49.9984 9.4847 55.6748 8.8349 61.2700 8.2535 66.8131 6.4709 70.0000 5.0000

COLR Quad Cities 1 Revision 0 Page 22 Table 6-12 LHGRFAC(P) for GE Fuel (Reference 4)

Core Thermal Power (% Rated)

EOOS Combination Core Flow 0 25 38.5 l 38.5 l 70 70 80 100 LHGRFAC(P) Multiplier Base Case All 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 Base Case SLO All 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 TBasOCseSL All 0.22 0.39 0.48 0.54 N/A N/A WA8 1.00

>60 0.22 0.39 0.48 TBPOOS . . 0.54 N/A N/A N/A 1.00

>60 0.33 0.39 0.42 TBPOOS SLO 60 02 .3 042 0.54 N/A N/A N/A 1.00 TCV Slow Closure S60 0.22 0.39 0.48 0.54 0.73 0.78 N/A 1.00

>60 0.33 0.39 0.42 TCV Slow Closure S60 0.22 0.39 0.48 SLO >60 0.33 0.39 0.42 04 7 08 A_

PLUOOS S60 0.22 0.39 0.48 0.54 0.73 0.78 N/A 1.00

>60 0.33 0.39 0.42 PLUOOS SLO S60 0.22 0.39 0.48 0.54 0.73 0.78 N/A 1.00

>60 0.33 0.39 0.42 TCV Stuck Closed All 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 TCV Stuck Closed All 0.50 0.56 0.59 0.68 N/A N/A 0.86 1.00 SLO

I  :

COLR Quad Cities 1 Revision 0 Page 23 Table 6-13 LHGRFAC(F) Multipliers, All Cases except TCV Stuck Closed (Reference 4)

Flow LHGRFAC(F)

(% rated) Multiplier l 100.0 1.00 80.0 1.00 50.0 0.77 40.0 0.64 30.0 0.55 0.0 0.28 Table 6-14 LHGRFAC(F) Multipliers for TCV Stuck Closed (Reference 4)

Flow' LHGRFAC(F)l

(% rated) Multiplier ]

100.0' 1.00 98.3- 1.00 80.0- 0.86 50.0 0.63 40.0 0.50 30.0 0.41 0.0 0.14 Table 6-15 LHGR SLO Multiplier (Reference 3)

I Fuel Typel 0.

GE14 . 0.77

COLR Quad Cities 1 Revision 0 Page 24

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

ROD BLOCK MONITOR UPSCALE TRIP FUNCTION ALLOWABLE VALUE Two Recirculation Loop 0.65 Wd + 56.1%

Operation Single Recirculation Loop 0.65 Wd +51.4%

Operation__ _ _ _ _ _ _ _ _ _ _

The setpoint may be lower/higher and will still comply with the rod withdrawal error (RWE) analysis because RWE is analyzed unblocked.

The allowable value Is clamped with a maximum value not to exceed the allowable value for a recirculation loop drive flow (Wd) of 100%

Wd - percent of recirculation loop drive flow required to produce a rated core flow of 98.0 Mlb/hr.

C- i COLR Quad Cities 1 Revision 0 Page 25

8. Modes of Operation The allowed modes of operation with combinations of equipment out-of-service are as described below:

Equipment Out of 2 3 Service Standard ICF l MELLLA Coastdown 4 Options' ' Stadad___sMEL_____tow Base Case Yes Yes Yes Yes Base Case SLO Yes No Yes Yes TB POOS Yes Yes Yes Yes TBPOOS SLO Yes No Yes Yes TCV Slow Yes Yes Yes Yes TCV Slow Closure SLO6 Yes No Yes Yes PLUOOS7 Yes Yes Yes Yes PLUOOS SLO' Yes No Yes Yes TCV Stuck Closed8 Yes Yes Yes Yes TCV Stuck Closed SLO8 Yes No Yes Yes

1. Each OOS Option may be combined with up to 18 TIP channels OOS provided the requirements (as clarified In Reference
20) for utilizing SUBTIP methodology are met and up to 50% of the LPRMs OOS with an LPRM calibration frequency of 2500 Effective Full Power Hours (EFPH) (2000 EFPH +25%). For operation under all limit sets a 1200F reduction In feedwater temperature throughout the cycle was analyzed and Is subject to the restrictions In Reference 13 (Final Feedwater Temperature Reduction or Feedwater Heaters OOS).
2. A single MSIV may be taken OOS (shut) under any and all OOS Options, so long as core thermal power Is maintained :75%

of 2957 MWth (Reference 3).

3. Each EOOS option except TBPOOS requires the opening profile for the Turbine Bypass Valves provided In Reference 7 to be met These conditions also support 1 Turbine Bypass Valve OOS (TBPOOS) If the assumed opening profile (Reference 7) for the remaining 8 Turbine Bypass Valves Is met. Ifthe opening profile Is not met with 8 or 9 operating Turbine Bypass Valves, or If more than one Turbine Bypass Valve Is 0OS, utilize the TBPOOS condition. For operation with three or more TBPOOS, utilize the TBPOOS condition above 42% rated power and the PLUOOS condition at or below 42% of rated power (References 18 and 19).
4. Coastdown operation Is defined as any cycle exposure beyond the full power, all rods out condition with plant power slowly lowering to a lesser value while core flow Is held constant (Reference 10 Section 4.3.1.2.8). Up to a 15% overpower is analyzed per Reference 4.
5. Increased Core Flow (ICF) Issupported to 108% of rated core flow.
6. For operation with a pressure regulator out-of-service (PROOS), the TCV Slow Closure limits should be applied (Reference 3) and the operational notes from Reference 12 reviewed. PROOS and TCV Slow Closure Is not an analyzed out-of-service combination.
7. If the Base Case limit set Is being used and the PLU Is taken OOS for surveillance and the reactor Is maintained at 280%

rated core thermal power and 280% of rated core flow during the PLUOOS period, an administrative limit on MFLPD and MFLCPR can be used instead of the PLUOOS thermal limit set. The MFLPD administrative limit to be used Is 0.98 for all scram speeds. The MFLCPR administrative limit Is 0.94 for Option A scram times, 0.97 for Option B scram times, and 0.97 for scram times less than or equal to 0.714 seconds but greater than the Option B time.

8. For operation with a Turbine Stop Valve out-of-service (TSVOOS), the TCV Stuck Closed limits should be applied (Reference 15). TSVOOS and TCV Stuck Closed Is not an analyzed out-of-service combination.

COLR Quad Cities 1 Revision 0 Page 26

9. 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. NEDE-2401 1-P-A-14, June 2000 and the U.S. Supplement NEDE-2401 1-P-A-US, June 2000, "General Electric Standard Application for Reactor Fuel".
2. Commonwealth Edison Company Topical Report NFSR-0091, "Benchmark of CASMO/

MICROBURN BWR Nuclear Design Methods," Revision 0 and Supplements on Neutronic Licensing Analysis (Supplement 1) and La Salle County Unit 2 benchmarking (Supplement 2), December 1991, March 1992, and May 1992, respectively.

3. Commonwealth Edison Topical Report NFSR-0085, Revision 0, "Benchmark of BWR Nuclear Design Methods," November 1990.
4. Commonwealth Edison Topical Report NFSR-0085, Supplement 1 Revision 0, "Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan Comparisons," April 1991.
5. - Commonwealth Edison Topical Report NFSR-0085, Supplement 2 Revision 0, "Benchmark of BWR Nuclear Design Methods - Neutronic Licensing Analyses," April 1991.
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