LR-N03-0250, Core Operating Limits Report - Cycle 12

Core Operating Limits Report - Cycle 12

ML031681384
Person / Time
Site:	Hope Creek
Issue date:	06/06/2003
From:	Salamon G Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N03-0250
Download: ML031681384 (53)

Text

I; PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUN 0 6 2003 o PSEG Nuclear LLC LR-N03-0250 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 CORE OPERATING LIMITS REPORT - CYCLE 12 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO.60-354 In accordance with section 6.9.1.9 of the Hope Creek Technical Specifications, PSEG Nuclear LLC submits Revision 0 of the Core Operating Limits Report (COLR) for Hope Creek Cycle 12 (NFS-0226, Rev. 0) in Attachment 1 to this letter.

Should you have any questions, please contact Mr. Paul Duke at (856) 339-1466.

Manager - Nuclear Safety & Licensing Attachment 95-2168 REV. 7/99 o

Document Control Desk LR-N03-0260 JUN 0 6 2003 C

Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Ucensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 8B1 Washington, DC 20555 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625

Document Control Desk Attachment I LR-N03-0250 NFS-0226, Rev. 0

NFS-0226 Revision 0 Hope Creek Generating Station Core Operating Limits Report Cycle 1V/ Reload 11 Effective Date:

5

/

3 Prepared By:

Reviewed By:

xb*.

A Steven Bier, Nuclear Fuels Lead Engineer Concurrence By

'; I40;qC'o Donald Notigan, Supervisor Hope Creek Nuclear Fuels Approved By:

Page I of 50 Date:

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3

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3 Date:

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6 I

o3 Mike Mannion, Manager Nuclear Fuels/Reactor Engineering Date:._

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Date:'

Shie-Jeng P>lg, clear FueW5Senior Engineer

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NFS-0226 Revision ()

Table of Contents Section Description Page

1.0 INTRODUCTION

5 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR 6

2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 7

2.2 MINIMUM CRITICAL POWER RATIO 36 2.3 LINEAR HEAT GENERATION RATE 48

3.0 REFERENCES

50 Page 2 of 50

NFS-0226 Revision 0 List of Tables Table Description Page Table 2.1-1: APLHGR Data for Fuel Bundle HF09 (Two Recirculation Loop Operation) 9 Table 2.1-2: APLHGR Data for Fuel Bundle HF09 (Single Recirculation Loop Operation) 10 Table 2.1-3: APLHGR Data for Fuel Bundle PAIO (Two Recirculation Loop Operation) 13 Table 2.1-4: APLHGR Data for Fuel Bundle PAIO (Single Recirculation Loop Operation) 14 Table 2.1-5: APLHGR Data for Fuel Bundle PB10 (Two Recirculation Loop Operation) 17 Table 2.1-6: APLHGR Data for Fuel Bundle PB 10 (Single Recirculation Loop Operation) 18 Table 2.1-7: APLHGR Data for Fuel Bundle PCI I (Two Recirculation Loop Operation)_

21 Table 2.1 -8: APLHGR Data for Fuel Bundle PC 11 (Single Recirculation Loop Operation) 22 Table 2.1-9: APLHGR Data for Fuel Bundle PDI I (Two Recirculation Loop Operation) 25 Table 2.1-10: APLHGR Data for Fuel Bundle PDI I (Single Recirculation Loop Operation) _26 Table 2.1-11: APLHGR Data for Fuel Bundle PE12 (Two Recirculation Loop Operation) _29 Table 2.1-12: APLHGR Data for Fuel Bundle PE 12 (Single Recirculation Loop Operation)

.30 Table 2.1-13: APLHGR Data for Fuel Bundle PF12 (Two Recirculation Loop Operation)_

33 Table 2.1-14: APLHGR Data for Fuel Bundle PF12 (Single Recirculation Loop Operation) 34 Table 2.2-1: Nominal Scram Speed 36 Table 2.2-2: Hope Creek Cycle 12 MCPR Operating limits: Cycle Exposure S 9179MWd/MTU_

_ 37 Table 2.2-3: Hope Creek Cycle 12 MCPR Operating limits: Cycle Exposure > 9179MWd/MTU_

_ 38 Page 3 of 50

NFS-0'26 Revision 0 List of Figures Figures Description Page Figure 2.1- : Lattice Definitions for Fuel Bundle HFO9 8

Figure 2.1-2: APLHGR Limit for Fuel Bundle HF09 I I Figure 2.1-3: Lattice Definitions for Fuel Bundle PAO_

12 Figure 2.1-4: APLHGR Limit for Fuel Bundle PAO_

15 Figure 2.1-5: Lattice Definitions for Fuel Bundle PB 10 16 Figure 2.1-6: APLHGR Limit for Fuel Bundle PB 10 19 Figure 2.1-7: Lattice Definitions for Fuel Bundle PC I 1 20 Figure 2.1-8: APLHGR Limit for Fuel Bundle PC lI 23 Figure 2.1-9: Lattice Definitions for Fuel Bundle PDI 1 24 Figure 2.1-10: APLHGR Limit for Fuel Bundle PDI 1 27 Figure 2.1-11: Lattice Definitions for Fuel Bundle PE12 28 Figure 2.1-12: APLHGR Limit for Fuel Bundle PE12_

31 Figure 2.1-13: Lattice Definitions for Fuel Bundle PF12 32 Figure 2.1-14: APLHGR Limit for Fuel Bundle PF12 35 Figure 2.2-1: Flow Dependent MCPR Limit 39 Figure 2.2-2: Power Dependent MCPR Limit: NSS, Cycle Exposure S 9179MWd/MTU, EOC-RPT Operable 40 Figure 2.2-3: Power Dependent MCPR Limit: TSSS, Cycle Exposure 5 9179MWdMTU, EOC-RPT Operable 4 1 Figure 2.24: Power Dependent MCPR Lirnit: NSS, Cycle Exposure S 9179MWd/MTU, EOC-RPT Inoperable 42 Figure 2.2-5: Power Dependent MCPR Limit: TSSS. Cycle Exposure 5 9179MWd/MTU, EOC-RPT Inoperable 43 Figure 2.2-6: Power Dependent MCPR Limit: NSS, Cycle Exposure > 9179MWdUMTU, EOC-RPT Operable 44 Figure 2.2-7: Power Dependent MCPR Limit: TSSS, Cycle Exposure > 9179MWd/MTU, EOC-RPT Operable 45 Figure 2.2-8: Power Dependent MCPR Limit: NSS, Cycle Exposure > 9179MWd/MTU. EOC-RPT Inoperable 46 Figure 2.2-9: Power Dependent MCPR Limit TSSS, Cycle Exposure > 9179MWd/MTU, EOC-RPT Inoperable 47 Figure 2.3-1: Exposure Dependent LHGR Limits 49 Page 4 of 50

NFS-0226 Revision 0

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit Cycle 12/ Reload 11 operation. In addition, this report will provide cycle information on single recirculation loop operation, nominal scram speed and determination of the Core Maximum Fraction of Limiting Power Density. Finally, this report also provides a reference to the most recent revision of the implemented approved methodology. The limits presented here correspond to the core thermal limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR), Power dependent MCPR (MCPRp), Flow dependent MCPR (MCPRr) and Linear Heat Generation Rate (LHGR).

These operating limit values have been determined using NRC approved methods contained in the Reference Safety Report for Boiling Water Reactor Reload Fuel [11, CENPD-300-P-A (Revision 0), and GESTAR-II 5], NEDE-2401 1-P-A (Revision 13) and are established such that all applicable fuel thermal-mechanical, core thermal-hydraulic, ECCS, and nuclear limits such as shutdown margin, and transient and accident analysis limits are met.

Hope Creek Technical Specifications Section 3.2 references this report as the source for certain LIMITNG CONDITIONS FOR OPERATION. These are included in section 2 of this document. Hope Creek Technical Specification 6.9.1.9 also requires that this report, including any mid cycle revisions, shall be provided, upon issuance, to the NRC.

This document is specific to Hope Creek Generaing Station Unit I Cycle 12 / Reload II and shall not be applicable to any other core or cycle design. The thermal limits contained in this report are applicable whether the Crossflow' correction factor is applied or not applied.

This report is applicable for Cycle 12 operation from the date of issuance through the end of effective full power capability or a cycle exposure of 13324MWd/MTU, whichever occurs first [2]. End of effective full power capability is reached when 100% rated power can no longer be maintained by increasing core flow (up to 105% of rated core flow), at rated feedwater temperatures, in the all-rods-out configuration.

Page 5 of 50

NFS- 0226 Re%-sion 0 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR The TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR presented in this section are referenced by the Hope Creek Technical Specifications.

Tech. Spec.

Title 2.1 Safety Limit Bases 3/4.2.1 Average Planar Linear Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 3/4.4.1 Recirculation System Recirculation Loops 3/4.2b Power Distribution Bases 3/4.2.lb Average Planar Linear Heat Generation Rate 6.9.1.9 Administrative Controls, Core Operating Limits Report Page 6 of 50

NFS-0226 Revision 0 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION:

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits specified in Table 2.1-1, Table 2.1-3, Table 2.1-5, Table 2.1-7, Table 2.1-9, Table 2.1-11 and Table 2.1-13.

When the Technical Specification Section 3/4.4.1 ACTION statement a.l.d is entered from that section's LCO, reduce the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit to a value specified in Table 2.1-2, Table 2.1-4, Table 2.1-6.

Table 2.1-8, Table 2.1-10, Table 2.1-12 and Table 2.1-14.

When hand calculations are required, all AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE EXPOSURE shall not exceed the limits specified in Figures 2.1-2, 2.14, 2.1-6, 2.1-8, 2.1-10, 2.1-12 and 2.1-14.

Page 7 of 50 NOTE Figures 2.1-2, 2.14, 2.1-6, 2.1-8, 2.1-10, 2.1-12 and 2.1-14 graphically represent the liniting column of Tables 2.1-1 through 2.1-14.

6 inches 6 inches 132 inches 6 inches 2656 (NATU) 2124 (NATU) 2655 2124 (NATU)

NATU = Natural Uranium Lattices, which are not included in the determination of the most limiting lattice APLHGR values.

1. These lattice designators (prefixed with LT) are used in the Core Monitoring System.

Figure 2.1-1: Lattice Definitions for Fuel Bundle HFO9 (Reference 6)

Page 8 of 50 NFS-0226 Revision 0 LT33' LT11 LT32 LTI 1

NFS-02'6 Revision 0 Table 2.1-1: APLHGR Data for Fuel Bundle HF09 (Two Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kw/ft)'

GWD/STU MWD/MTU

1. 2124

1. 2655

1. 2656 Limiting 0.00 0.0 11.89 11.87 11.89 11.87 0.20 220.5 11.92 11.91 11.92 11.91 1.00 1102.3 12.05 12.03 12.05 12.03 2.00 2204.6 12.27 12.21 12.27 12.21 3.00 3306.9 12.34 12.40 12.49 12.40 4.00 4409.2 12.37 12.62 12.69 12.62 5.00 5511.5 12.40 12.85 12.73 12.85 6.00 6613.8 12.43 13.01 12.76 13.01 7.00 7716.1 12.46 13.15 12.79 13.15 8.00 8818.4 12.48 13.30 12.81 13.30 9.00 9920.7 12.50 13.43 12.83 13.43 10.00 11023.0 12.52 13.50 12.85 13.50 12.50 13778.8 12.36 13.49 12.73 13.49 15.00 16534.5 11.98 13.17 12.34 13.17 20.00 22046.0 11.20 12.54 11.56 12.54 25.00 27557.5 10.42 11.75 10.78 11.75 35.00 38580.5 8.87 10.30 9.23 10.30 45.00 49603.5 6.00 9.03 6.76 9.03 46.61 51378.2 5.18 8.29 8.29 47.85 52745.1 7.71 5.31 7.71 52.05 57374.7 5.77 5.77

1. See Figure 2.1-1 for the Lattice Definitions for this fuel assembly.

Page 9 of 50

NFS-0226 Revision 0 Table 2.1-2: APLHGR Data for Fuel Bundle HF09 (Single Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kw/ft)'

GWD/STU MWDIMTU

1. 2124

1. 2655

1. 2656 Limiting 0.00 0.0 10.23 10.21 10.23 10.21 0.20 220.5 10.25 10.24 10.25 10.24 1.00 1102.3 10.36 10.35 10.36 10.35 2.00 2204.6 10.55 10.50 10.55

[0.50 3.00 3306.9 10.61 10.66 10.74 10.66 4.00 4409.2 10.64 10.85 10.91 10.85 5.00 5511.5 10.66 11.05 10.95 11.05 6.00 6613.8 10.69 11.19 10.97 11.19 7.00 7716.1 10.72 11.31 11.00 11.31 8.00 8818.4 10.73 11.44 11.02 11.44 9.00 9920.7 10.75 11.55 11.03 11.55 10.00 11023.0 10.77 11.61 11.05 11.61 12.50 13778.8 10.63 11.60 10.95 11.60 15.00 16534.5 10.30 11.33 10.61 11.33 20.00 22046.0 9.63 10.78 9.94 10.78 25.00 27557.5 8.96 10.11 9.27 10.11 35.00 38580.5 7.63 8.86 7.94 8.86 45.00 49603.5 5.16 7.77 5.81 7.77 46.61 51378.2 4.45 7.13 7.13 47.85 52745.1 6.63 4.57 6.63 52.05 57374.7 4.96 4.96

1. See Figure 2.1-1 for the Lattice Definitions for this fuel assembly.

Page 10 of 50

N FS-0226 Re% ision 0 Figure 2.1-2: APLHGR Limit for Fuel Bundle HFO9 Page 11 of 50 E

C,

-jc 600 0

20(M 3000X 4000D bwpR P=%DI

6 inches 24 inches 114 inches 6 inches LT41 (NATU)

LT 43 LT 42 LT 41 (NATU)

NATU = Natural Uranium Lattices, which are not included in the determination of the most limiting lattice APLHGR values.

1. These lattice designators (prefixed with LT) are used in the Core Monitoring System.

Figure 2.1-3: Lattice Definitions for Fuel Bundle PAIO (Reference 7)

Page 12 of 50 NFS-0226 Revision 0

NFS-0226 Revision 0 Table 2.1-3: APLHGR Data for Fuel Bundle PA1O (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)

MWDIMTU LT 41,42 LT 43 Limiting 0

9.1 9.1 9.1 350 9.1 9.1 9.1 1000 9.2 9.2 9.2 7000 9.2 9.2 9500 9.2 8.9 8.9 10000 9.1 8.9 14000 8.5 8.5 8.5 18000 8.0 8.0 8.0 22000 7.6 7.6 7.6 24000 7.7 7.7 7.7 26000 8.4 8.4 8.4 28000 8.4 8.4 8.4 34000 8.4 8.4 8.4 42000 8.4 8.4 8.4 52000 8.2 8.2 8.2 54000 8.1 8.1 8.1 59000 7.9 7.9 7.9

1. See Figure 2.1-3 for the Lattice Definitions for this fuel assembly.

Page 13 of 50

NFS-0226 Revision 0 Table 2.1-4: APLHGR Data for Fuel Bundle PA1O (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWDIMTU LT 41, 42 LT 43 Limiting 0

8.2 8.2 8.2 350 8.2 8.2 8.2 1000 8.3 8.3 8.3 7000 8.3 8.3 9500 8.3 8.0 8.0 10000 8.2 8.0 14000 7.7 7.7 7.7 18000 7.2 7.2 7.2 22000 6.8 6.8 6.8 24000 6.9 6.9 6.9 26000 7.6 7.6 7.6 28000 7.6 7.6 7.6 34000 7.6 7.6 7.6 42000 7.6 7.6 7.6 52000 7.4 7.4 7.4 54000 7.3 7.3 7.3 59000 7.1 7.1 7.1

1. See Figure 2.1-3 for the Lattice Definitions for this fuel assembly.

Page 14 of 50

0 1000 2000D 30000 40000 9000 AP Raw BqMrn AM=

Figure 2.14: APLHGR Limit for Fuel Bundle PA1O Page 15 of 50 NFS-0226 Revision 0 Eao E

C3 7O c.4 600

NFS-02216 Revision 0 6 inches 138 inches 6 inches NATU = Natural Uranium Lattices, which are not included in the determination of the most limiting lattice APLHGR values.

1. These lattice designators (prefixed with LT) are used in the Core Monitoring System.

Figure 2.1-5: Lattice Definitions for Fuel Bundle PB 10 (Reference 7)

Page 16 of 50 LT 41 (NATU)

LT43 LT41 (NATU)

NFS-0226 Revision 0 Table 2.1-5: APLHGR Data for Fuel Bundle P 10 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwft)'

MWDIMTU LT 41 LT 43 Limiting 0

9.1 9.1 9.1 350 9.1 9.1 9.1 1000 9.2 9.2 9.2 7000 9.2 9.2 9500 9.2 8.9 8.9 10000 9.1 8.9 14000 8.5 8.5 18000 8.0 8.0 8.0 22000 7.6 7.6 7.6 24000 7.7 7.7 7.7 26000 8.4 8.4 8.4 28000 8.4 8.4 8.4 34000 8.4 8.4 8.4 42000 8.4 8.4 8.4 52000 8.2 8.2 8.2 54000 8.1 8.1 8.1 59000 7.9 7.9 7.9

1. See Figure 2.1-5 for the Lattice Definitions for this fuel assembly.

Page 17 of 50

NFS-0226 Revision 0 Table 2.1-6: APLHGR Data for Fuel Bundle PB 10 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)

MWD/MTU LT 41 LT 43 Limiting 0

8.2 8.2 8.2 350 8.2 8.2 8.2 1000 8.3 8.3 8.3 7000 8.3 8.3 9500 8.3 8.0 8.0 10000 8.2 8.0 14000 7.7 7.7 7.7 18000 7.2 7.2 7.2 22000 6.8 6.8 6.8 24000 6.9 6.9 6.9 26000 7.6 7.6 7.6 28000 7.6 7.6 7.6 34000 7.6 7.6 7.6 42000 7.6 7.6 7.6 52000 7.4 7.4 7.4 54000 7.3.

7.3 7.3 59000 7.1 7.1 7.1

1. See Figure 2.1-5 for the Lattice Definitions for this fuel assembly.

Page 18 of 50

0 1moo 2xm 4M0 DM-W Figure 2.1-6: APLHGR Limit for Fuel Bundle PB 10 Page 19 of 50 NFS-0226 Revision O lao E

-Jcc a

I~~~~~~~~~~~~~~~~~~~~~~~~

. ~ ~

6 inches 36 inches 102 inches 6 inches LT 41 (NATU)

LT 46 LT 44 LT 41 (NATU)

NATU = Natural Uranium Lattices, which are not included in the determination of the most limiting lattice APLHGR values.

Figure 2.1-7: Lattice Definitions for Fuel Bundle PC11 (Reference 8)

Page 20 of 50 NFS-0'6 Revision 0

NFS-0126 Revision 0 Table 2.1-7: APLHGR Data for Fuel Bundle PCI I (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU LT 41 LT 44 LT 46 Limiting 0

9.1 11.0 11.0 11.0 350 9.1

[i1.0 11.0

[

11.0 1000 9.2 11.0 11.0 11.0 7000 X

10.8 10.8 10.8 9500 9.2 10.7 10.7 10.7 10000 9.1 10.7 10.7 10.7 14000 8.5 10.4 10.4 10.4 18000 8.0 10.0 10.0 10.0 22000 7.6 9.6 9.6 9.6 24000 7.7 9.4 9.4 9.4 26000 8.4 9.3 9.3 9.3 28000 8.4 9.2 9.2 9.2 34000 8.4 9.1 9.1 9.1 42000 8.4 8.9 8.9 8.9 54000 8.1 8.5 8.5 8.5 59000 7.9 8.1 8.1 8.1

1. See Figure 2.1-7 for the Lattice Definitions for this fuel assembly.

Page 21 of 50

NFS-0226 Revision 0 Table 2.1-8: APLHGR Data for Fuel Bundle PC 1I (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwlft)'

MWD/MTU LT 41 LT 44 LT 46 Limitin 0

8.2 9.9 9.9 9.9 350 8.2 9.9 9.9 9.9 1000 8.3 9.9 9.9 9.9 7000 9.7 9.7 9.7 9500 8.3 9.6 9.6 9.6 10000 8.2 9.6 9.6 9.6 14000 7.7 9.3 9.3 9.3 18000 7.2 9.0 9.0 9.0 22000 6.8 8.6 8.6 8.6 24000 6.9 8.4 8.4 8.4 26000 7.6 8.3 8.3 8.3 28000 7.6 8.2 8.2 8.2 34000 7.6 8.1 8.1 8.1 42000 7.6 8.0 8.0 8.0 54000 7.3 7.6 7.6 7.6 59000 7.1 7.2 7.2 7.2

1. See Figure 2.1-7 for the Lattice Definitions for this fuel assembly.

Page 22 of 50

NFS-0226 Revision 0 Figure 2.1-8: APLHGR Limit for Fuel Bundle PC I I Page 23 of 50 9.5 i%

_-Two Loop Operation SIngle Loop Operaon 0

10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWdIMTU)

NFS-0226 Revision ()

6 inches 36 inches 102 inches 6 inches NATU = Natural Uranium Lattices, which are not included in the determination of the most limiting lattice APLHGR values.

Figure 2.1-9: Lattice Definitions for Fuel Bundle PDI I (Reference 8)

Page 24 of 50 LT 41 (NATU)

LT 46 LT 45 LT 41 (NATU)

NFS-02 26 Revision 0 Table 2.1-9: APLHGR Data for Fuel Bundle PDI I (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU LT 41 LT 45 LT 46 Limiting 0

9.1 11.0 11.0 11.0 350 9.1 11.0 11.0 11.0 1000 9.2 11.0 11.0 11.0 7000 10.8 10.8 10.8 9500 9.2 10.7 10.7 10.7 10000 9.1 10.7 10.7 10.7 14000 8.5 10.4 10.4 10.4 18000 8.0 10.0 10.0 10.0 22000 7.6 9.6 9.6 9.6 24000 7.7 9.4 9.4 9.4 26000 8.4 9.3 9.3 9.3 28000 8.4 9.2 9.2 9.2 34000 8.4 9.1 9.1 9.1 42000 8.4 8.9 8.9 8.9 54000 8.1 8.5 8.5 8.5 59000 7.9 8.1 8.1 8.1

1. See Figure 2.1-9 for the Lattice Definitions for this fuel assembly.

Page 25 of 50

NFS-0226 Revision 0 Table 2.1-10: APLHGR Data for Fuel Bundle PDI I (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU LT 41 LT 45 LT 46 Limiting 0

8.2 9.9 9.9 9.9 350 8.2 9.9 9.9 9.9 1000 8.3 9.9 9.9 9.9 7000 9.7 9.7 9.7 9500 8.3 9.6 9.6 9.6 10000 8.2 9.6 9.6 9.6 14000 7.7 9.3 9.3 9.3 18000 7.2 9.0 9.0 9.0 22000 6.8 8.6 8.6 8.6 24000 6.9 8.4 8.4 8.4 26000 7.6 8.3 8.3 8.3 28000 7.6 8.2 8.2 8.2 34000 7.6 8.1 8.1 8.1 42000 7.6 8.0 8.0 8.0 54000 7.3 7.6 7.6 7.6 59000 7.1 7.2 7.2 7.2

1. See Figure 2.1-9 for the Lattice Definitions for this fuel assembly.

Page 26 of 50

NFS-0226 Revision 0 Figure 2.1-10: APLHGR Limit for Fuel Bundle PDL 1 Page 27 of 50

6 inches 36 inches 102 inches 6 inches LT41 (NATU)

LT 47 LT 49 LT 41 (NATU)

NATU = Natural Uranium Lattices, which are not included in the determination of the most limiting lattice APLHGR values.

Figure 2.1-11: Lattice Definitions for Fuel Bundle PE12 (Reference 9)

Page 28 of 50 NFS-0'26 Revision 0

NFS-02'6 Revision 0 Table 2.1-11: APLHGR Data for Fuel Bundle PE12 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/f)'l MWD/MTU LT 41 LT 47 LT 49 Limiting 0

9.1 11.0 11.0 11.0 350 9.1 11.0 11.0 11.0 1000 9.2 11.0 11.0 11.0 7000 10.8 10.8 10.8 9500 9.2 10.7 10.7 10.7 10000 9.1 10.7 10.7 10.7 14000 8.5 10.4 10.4 10.4 18000 8.0 10.0 10.0 10.0 22000 7.6 9.6 9.6 9.6 24000 7.7 9.4 9.4 9.4 26000 8.4 9.3 9.3 9.3 28000 8.4 9.2 9.2 9.2 34000 8.4 9.1 9.1 9.1 42000 8.4 8.9 8.9 8.9 54000 8.1 8.5 8.5 8.5 59000 7.9 8.1 8.1 8.1

1. See Figure 2.1-11 for the Lattice Definitions for this fuel assembly.

Page 29 of 50

NFS-0'26 Revision 0 Table 2.1-12: APLHGR Data for Fuel Bundle PEI2 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwlft)'

j MWD/MTU LT 41 LT 47 LT 49 Limiting 0

8.2 9.9 9.9 9.9 350 8.2 9.9 9.9 9.9 1000 8.3 9.9 9.9 9.9 7000 9.7 9.7 9.7 9500 8.3 9.6 9.6 9.6 10000 8.2 9.6 9.6 9.6 14000 7.7 9.3 9.3 9.3 18000 7.2 9.0 9.0 9.0 22000 6.8 8.6 8.6 8.6 24000 6.9 8.4 8.4 8.4 26000 7.6 8.3 8.3 8.3 28000 7.6 8.2 8.2 8.2 34000 7.6 8.1 8.1 8.1 42000 7.6 8.0 8.0 8.0 54000 7.3 7.6 7.6 7.6 59000 7.1 7.2 7.2 7.2

1. See Figure 2.1-11 for the Lattice Definitions for this fuel assembly.

Page 30 of 50

NFS-0226 Revision 0 11.5 11.0 10.5 10.0 9.5 E

a 9.0 0.

8.5 8.0 7.5 7.0 2000D 30000 40000 50000 60000 Average Planar Exposum (MWdfMTU)

Figure 2.1-12: APLHGR Limit for Fuel Bundle PE12 Page 31 of 50 a

6 inches 36 inches 102 inches 6 inches LT 41 (NATU)

LT 47 LT 48 LT 41 (NATU)

NATU = Natural Uranium Lattices, which are not included in the determination of the most limiting lattice APLHGR values.

Figure 2.1-13: Lattice Definitions for Fuel Bundle PF12 (Reference 9)

Page 32 of 50 N FS-0226 Revision 0

NFS-0226 Revision 0 Table 2.1-13: APLHGR Data for Fuel Bundle PFI2 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwlft)l MWD/MTU LT 41 LT 47 LT 48 Limiting 0

9.1 11.0 11.0 11.0 350 9.1 11.0 11.0 11.0 1000 9.2 11.0 11.0 11.0 7000 10.8 10.8 10.8 9500 9.2 10.7 10.7 10.7 10000 9.1 10.7 10.7 10.7 14000 8.5 10.4 10.4 10.4 18000 8.0 10.0 10.0 10.0 22000 7.6 9.6 9.6 9.6 24000 7.7 9.4 9.4 9.4 26000 8.4 9.3 9.3 9.3 28000 8.4 9.2 9.2 9.2 34000 8.4 9.1 9.1 9.1 42000 8.4 8.9 8.9 8.9 54000 8.1 8.5 8.5 8.5 59000 7.9 8.1 8.1 8.1

1. See Figure 2.1-13 for the Lattice Definitions for this fuel assembly.

Page 33 of 50

NFS-0"6 Revsion 0 Table 2.1-14: APLHGR Data for Fuel Bundle PF12 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU LT 41 LT 47 LT 48 i Limiting 0

8.2 9.9 9.9 9.9 350 8.2 9.9 9.9 9.9 1000 8.3 9.9 9.9 9.9 7000 9.7 9.7 9.7 9500 8.3 9.6 9.6 9.6 10000 8.2 9.6 9.6 9.6 14000 7.7 9.3 9.3 9.3 18000 7.2 9.0 9.0 9.0 22000 6.8 8.6 8.6 8.6 24000 6.9 8.4 8.4 8.4 26000 7.6 8.3 8.3 8.3 28000 7.6 8.2 8.2 8.2 34000 7.6 8.1 8.1 8.1 42000 7.6 8.0 8.0 8.0 54000 7.3 7.6 7.6 7.6 59000 7.1 7.2 7.2 7.2

1. See Figure 2.1-13 for the Lattice Definitions for this fuel assembly.

Page 34 of 50

NFS-0226 Re\\usion )

Figure 2.1-14: APLHGR Limit for Fuel Bundle PF12 Page 35 of 50

NFS-0226 Re%ision 0 2.2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit specified in Table 2.2-2 and Table 2.2-3.

The Technical Specification Scram Speed (TSSS) is defined by Hope Creek Technical Specification 3.1.3.3. The Nominal Scram Speed (NSS) is defined in reference [41 and is repeated below in Table 2.2-1.

Table 2.2-1: Nominal Scram Speed Position Inserted from Average Scram Insertion Time fully withdrawn (seconds)

Notch 45 0.375 Notch 39 0.673 Notch 25 1.399 Notch 5 2.526 The Operating limit MCPR is the maximum of the 'Full Power,' 'Power Dependent' and

'Flow Dependent' values presented in Tables 2.2.2 and 2.2.3 for the various operating conditions.

The MCPR limit is a function of core average scram speed, Cycle Exposure, EOC-RPT operability and Main Turbine Bypass operability.

EOC-RPT system operability is defined by Hope Creek Technical Specification 3.3.4.2.

Main Turbine Bypass operability is defined by Hope Creek Technical Specification 3.7.7.

Page 36 of 50 NOTE The Operating Limit MCPR determined with NSS shall be used when the control rod insertion time is less-than or equal-to that documented in Table 2.2.1. If the control rod insertion time is greater-than that assumed for the NSS then the Operating Limit MCPR shall be determined with the TSSS.

NFS-0226 Revision 0 Table 2.2-2: Hope Creek Cycle 12 MCPR Operating limits:

Cycle Exposure S 9179MWd/MTU Main Turbine Bypass Operable Cycle Exposure S 9179MWd/MTU Conditions Limit SVEA-96+

(3)

GE91B NSS"')

Full Power 1.35 1.56 EOC-RPT Operable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent(2)

Figure 2.2.2 Figure 2.2.2 TSSS(°'

Full Power 1.37 1.56 EOC-RPT Operable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent(2)

Figure 2.2.3 Figure 2.2.3 NSS")

Full Power 1.35 1.56 EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent(2)

Figure 2.2.4 Figure 2.2.4 TSSS(l)

Full Power 1.40 1.56 EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent(2)

Figure 2.2.5 Figure 2.2.5

1.

The TSSS MCPR values are based on the required speed of Technical Specification 3.1.3.3. The NSS MCPR values are based on the Westinghouse transient analysis performed using the control rod insertion times shown in Table 2.2-1. Administrative controls have been established to control the determination of the MCPR operating limit with regard to scram speed.

2.

Power dependent MCPR limits are provided for core thernal powers greater than or equal to 25% of rated power at all core flows. A step change in the power dependent MCPR limits occurs at 30% of rated power because direct scram on turbine control valve closure is automatically bypassed below 30% of rated power.

3.

Fuel design PAlO. PB 10, PCI 1. PDI 1. PE 12, and PF12 are SVEA-96+ fuel assemblies.

4.

Fuel design HFO9 represents GE9B fuel assemblies.

Page 37 of 50

NFS-0226 Revision 0 Table 2.2-3: Hope Creek Cycle 12 MCPR Operating limits:

Cycle Exposure > 91 79M dK/MTU See note I in Table 2.2-2 See note 2 in Table 2.2-2

3.

Fuel design PA1O. PBIO, PCI1, PDI I PE12. and PF12 are SVEA-96+ fuel assemblies.

4.

Fuel design HF09 represents GE9B fuel assemblies.

Page 38 of 50 Main Turbine Bypass Operable 9179MWd/MTU < Cycle Exposu re < 13324MWd/MTU Conditions Limit SVEA.96+ '

GE9B 4

NSS" Full Power 1.39 1.56 EOC-RPT Operable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent 2 )

Figure 2.2.6 Figure 2.2.6 TSSS")

Full Power 1.43 1.56 EOC-RPT Operable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent(2)

Figure 2.2.7 Figure 2.2.7 NSS")

Full Power 1.41 1.56 EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent(2)

Figure 2.2.8 Figure 2.2.8 TSSS"'

Full Power 1.45 1.59 EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent(2)

Figure 2.2.9 Figure 2.2.9 1.

2.

NFS-0226 Revision 0 1.60 --

Two and Single Recirculation Loop Operation 110 20 30 40 50 60 70 Percent of Rated Core Flow Initfal Flow OI l

OLMCPRf CI Iniotiate Flow)

SVEA-96+

GE91B of_Rated_Flow)

OLMCPR OLMCPR 20 1.36 1.50 40 1.34 1.45 60 1.32 1.40 80 1.28 1.30 100 1.15 1.20 109 1.10 1.10 80 90 100 Figure 2.2-1: Flow Dependent MCPR Limit Page 39 of 50 E

0.

U C

a E

IL

NFS-0226 Re% sion 0 Main Turbine Bypass Operable Two an Recirculatlon I Nominal Scram EOC-RPT Opera!

Exposure 9179 G

SVEA96

-- GE9B 30 40 50 60 70 Percent of Rated Power 80 id Single Loop Operation Speed ble I MWd/MTU 90 100 Notes Initial Power MCPRp

(% of Rated)

SVEA-96+

GE9B 100 1.25 1.38 All Core Flows, Power 30%,

90 1.28 1.39 Credit Direct Scrams 45 1.61 1.62 30 1.88 1.86 All Core Flows, Power < 30%,

30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-2: Power Dependent MCPR Limit:

NSS, Cycle Exposure S 9179MWd/MTU, EOC-RPT Operable Page 40 of 50 2.80 2.70 i 2.60-2.50 E3 2.40 c2.30 2.20 O 2.10 2.00 E 1.90 1.80

,1.70 1.60 01.50 1.40 1.30 1.20 1.10 20 e~~~

I.

NFS-) 226 Re% sion 0 Notes Initial Power MCPRp

(% of Rated)

SVEA-96+

GE9B 100 1.37 1.45 All Core Flows, Power > 30%,

90 1.40 1.46 Credit Direct Scrmms 45 1.68 1.65 30 1.93 1.88 All Core Flows, Power < 30%,

30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-3: Power Dependent MCPR Liniit:

TSSS, Cycle Exposure 5 9179MWd/WTU, EOC-RPT Operable Page 41 of 50 Main Turbine Bypass Operable 2.80 2.70, 2.60 2.50 1 Tvwo and Single E

Rerculation Loop Operation 3 2.40 cm 2 Tech. Spec. Scram Speed 2.30 EOC-RPT Operable 2.20 Exposure < 9179 MWdlMTU O 2.10 ---. _-____.__.___._.__.____

0. 2.00 E 1.90 11.80 1.60 1.5

+

SVEA-96+1_

1.50

-o-GEsB 1.40.

1.30 1.20 20 30 40 50 60 70 80 90 100 Percent of Rated Power

Nominal Scram Speed EOC-RPT Inoperable Exposure < 9179 MWdIMTU NFS-0226 Re% ision 1)

Main Turbine Bypass Operable 2.80 2.70 2.60 2.50

'E-2.40

.c 2.30 2.20 O 2.10 g 2.00 F 1.90 1 1.80 c 1.70 A1.60 E 1.50 X 1.40 1.30 1.20 1.10 C

p~~~~~~~~~~~~~~~~~~~~~~~~

100 80 50 60 70 Percent of Rated Power 20 30 40 90 Notes Initial Power MCPRp

(% of Rated)

SVEA-96+

GE9B 100 1.26 1.41 AU Core Flows, Power 2 30%,

90 1.29 1.41 Credit Direct Scrams 45 1.61 1.62 30 1.88 1.86 All Core Flows, Power < 30%,

30 2.57 2.66 Bypass Direct Scrans 25 2.57 2.66 Figure 2.24: Power Dependent MCPR limit:

NSS, Cycle Exposure < 9179MWd/MTU, EOC-RPT Inoperable Page 42 of 50 Two and Single Recirculation Loop Operation I

l

NFS-0226 Revision 0 Notes Initial Power MCPRp

(% of Rated)

SVEA-96+

GE9B 100 1.40 1.49 All Core Flows, Power > 30%,

90 1.41 1.49 Credit Direct Scrams 45 1.68 1.65 30 1.93 1.88 All Core Flows, Power < 30%,

30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-5: Power Dependent MCPR Limit:

TSSS, Cycle Exposure < 9179MWd/MTU, EOC-RPT Inoperable Page 43 of 50 Main Turbine Bypass Operable 2.80-2.70 Two and Single 2.60 Recirculatlon Loop Operation

._2.50 3 2.40 __

-Tech.

Spec. Scram Speed cn EOC-RPT Inoperable

'5 2.30 -

_. _- _.Exposure:S9179 MWdlMTU 2.20 0 2.10 CL 2.00-_

2 1.80

~1.60 p1.50 GE9B

=

0. 1.40 1.30 1.20-.

20 30 40 50 60 70 80 90 100 Percent of Rated Power

NFS-02'6 Revision 0 Notes Initial Power MCPRp

(% of Rated)

SVEA.96+

GE9B 100 1.39 1.52 All Core Flows, Power 2 30%,

90 1.40 1.53 Credit Direct Scrams 45 1.64 1.65 30 1.88 1.86 All Core Flows, Power < 30%,

30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-6: Power Dependent MCPR Limit:

NSS, Cycle Exposure > 9179MWdIMTU, EOC-RPT Operable Page 44 of 50 Main Turbine Bypass Operable 2.80 2.70 4 2.60 Two and Single

-2.50

_ a Recirculatlon Loop Operation

@ 2.40 Nominal Scram Speed a 230-EOC-RPTOperable i

Exposure > 9179 MWdMTU E2.20-0 2.10 m 2.00 -. ___

1.90

£,1.80 _____ _________

1.70 1.60 1.50 1.30 1.20 1.10 :....

20 30 40 50 60 70 80 90 100 Percent of Rated Power

NFS-02'6 Revision 0 Notes Initial Power MCPRp

(% of Rated)

SVEA-96+

GE9B 100 1.43 1.55 All Core Flows, Power > 30%,

90 1.44 1.55 Credit Direct Scrams 45 1.68 1.66 30 1.93 1.88 All Core Flows, Power < 30%,

30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-7: Power Dependent MCPR Limit:

TSSS, Cycle Exposure > 9179MWd/MTU, EOC-RPT Operable Page 45 of 50 Main Turbine Bypass Operable 2.80 2.70 2.60 5

Two and Single t Recirculation Loop Operation

~2.50~ -

-2 40 j Tech. Spec. Scram Speed

~2.40-EOC-RPT Operable c 2.30 Exposure >9179MWd/MTU E 2.20 O 2._1 0.._

0-Z 2.00 E1.90 --

O 210.

\\

2170-

~160-1.50 tL1.40-_-

1.30-_.l 1.20 -

1.10 20 30 40 50 60 70 80 90 100 Percent of Rated Power

NFS-0226 Revision 0 i80 260 T.o ardSne I

2I -

WO -.

l 1 T I

F~~~I~~A~~J'J I LLLjJ IE4C.FJI J I 24

wree MO

~~~~~~~~~~~~Expotem9179dWA1 p.10.-

.8D

.8, 1.60-

.=

5

-SVEAr9=

-i 80 90 100 40 50 70 Notes Initial Power MCPRp

(% of Rated)

SVEA-96+

GE9B 100 1.41 1.55 All Core Flows, Power > 30%,

90 1.42 1.56 Credit Direct Scrams 45 1.64 1.66 30 1.88 1.86 All Core Flows, Power < 30%,

30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-8: Power Dependent MCPR Limit:

NSS, Cycle Exposure > 9179MWd/MTU, EOC-RPIT Inoperable Page 46 of 50 2

'2 0

1 c

1 20

+

~~~~~~~~~~~~~~~~~~~~~~~~~~~I 1 sn:

,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

.. _V 1 4 1-*GE B Ftd

NFS-026 Revision 0 Main Turbine Bypass Operable 2.80 2.70 2.60 2.50 E 2.40

_c 2.30 t220 O 2.10 C. 2.00 E 1.90-1.

21.70 I

1.60 I

1.50 1.40 1.30 1.20 1.10 2.60 Two and Single Recircuaton Loop Operation

~2.40 -

Tech. Spec. Scram Speed EOC-RPT Inoperable

_ 2._0___

Exposure > 9179 MWdMTU 100 80 30 20 SVEA-96

-c GE9B sCI 60 7

Percent of Rated Power

.-i

---i 90 Notes Initial Power MCPRp

(% of Rated)

SVEA-96+

GE9B 100 1.45 1.59 AR Core Flows, Power > 30%,

90 1.46 1.59 Credit Direct Scrams 45 1.68 1.67 30 1.93 1.88 All Core Flows, Power < 30o, 30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-9: Power Dependent MCPR Linmit:

TSSS, Cycle Exposure > 9179MWd/MTU, EOC-RPT Inoperable Page 47 of 50

,~~~~~~~~~~~~~~~~~~~~~~~~

• I I

40 70

NFS-02'6 Revision 0 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit specified in Figure 2.3-1.

The CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY as implemented in Technical Specification Section 3/4.2.2 shall use a FRACTION OF LIMITING POWER DENSITY that is based on a specified LHGR equal to the exposure dependent LHGR in Figure 2.3-1 for the SVEA-96+ fuel assemblies and a constant LHGR of 14.4kw/ft for the GE9B fuel assemblies.

Page 48 of 50

NFS-0226 Revision 0 LHGR Limit LHGR Limit Rod Nodal Exposure (kW / ft)

(kW ft)

I)/M]'IJ)

SVEA-96+

GESIB 0

13.4 14.4 14591 14.4 16000 10.9 X

50000 8.3 53000 Not Applicable 9.2 60000 1

Not Applicable 6.0 Figure 2.3-1: Exposure Dependent LHGR Limits Page 49 of 50 16~

1 3 12 SVEA-96+ LHGR Limit 8

6-GE9B LHGR Limit 7 -

0 10000 20000 30000 40000 50000 60000 Rod Nodal Exposure (MWDIMTU)

NFS -0226 Revision 0

3.0 REFERENCES

1.

"Reference Safety Report for Boiling Water Reactor Reload Fuel," ABB Combustion Engineering Nuclear Operations, CENPD-300-P-A, Revision 0, July 1996.

2.

Nuclear Fuel Section Vendor Technical Document, NFVD-AB-2003-001-00, "HCGS Cycle 12 Reload licensing Report," Westinghouse Electric Company LLC, WCAP-16016 Rev. 0, February 2003.

3.

Nuclear Fuel Section Design Input File, HCA.5-0039, "Cycle 10 GE9B Operating Limit and COLR Related Information."

4.

Nuclear Fuel Section Vendor Technical Document, NFVD-AB-2003-003-00, "Conditions for Design: PSEG Nuclear LLC: Hope Creek: Cycle 12 Reload Analysis," Westinghouse Electric Company LLC, WCAP -16048 Rev. 0, April 2003.

5.

"General Electric Standard Application for Reactor Fuel," General Electric Company, NEDE-2401 1-P-A, Revision 13, August 1996, and the U.S. Supplement NEDE-2401 1-P-A-US, Revision 13, August 1996.

6.

Nuclear Fuel Section Vendor Technical Document, NFVD-GE-99004-00, "Lattice Dependent MAPLHGR Report for Hope Creek Generating Station Reload 8 Cycle 9" GE Nuclear Energy JI 1-03372MAPL Rev. 0, December 1998.

7.

Nuclear Fuel Section Vendor Technical Document, NFVD-AB-2000-003-00, "HCGS Cycle 10 Core Design Report" ABB Combustion Engineering Nuclear Power, CE NPSD-860-P Rev. 1, January 2000.

8.

Nuclear Fuel Section Vendor Technical Document, NFVD-AB-2001-007-01, "HCGS Cycle 11 Core Design Report" Westinghouse Electric Company LLC, CE NPSD-882-P Rev.1, July 2001.

9.

Nuclear Fuel Section Vendor Technical Document, NFVD-AB-2002-007-02, "HCGS Cycle 12 Core Design Report" Westinghouse Electric Company LLC, Rev.

2, Febnrary 2003.

Page 50 of 50