LR-N03-0533, Revised Core Operating Limits Report, Cycle 12

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Revised Core Operating Limits Report, Cycle 12
ML033630551
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 12/17/2003
From: Mannon S
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N03-0533
Download: ML033630551 (53)
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 DEC 1 7 2003 O Nuclear PSEG LLC LR-N03-0533 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REVISED CORE OPERATING UMITS REPORT - CYCLE 12 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 In accordance with section 6.9.1.9 of the Hope Creek Technical Specifications, PSEG Nuclear LLC submits Revision 1 of the Core Operating Limits Report (COLR) for Hope Creek Cycle 12 (NFS-0226, Rev. 1) in Attachment 1 to this letter.

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

Sincerely, S. Mannon Manager - Nuclear Safety & Licensing Attachment AOo)(

95-2168 REV. 7/99

bocument Control Desk DEC 1 7 2003 LR-N03-0533 C Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. Boska, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B1 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

6ocument Control Desk LR-N03-0533 NFS-0226, Rev. 1

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/NFS-0226 Revision 1 Hope Creek Generating Station Core Operating Limits Report Cycle 12/ Reload 11 Effective Date: 0/d03 Prepared By: Atck, Ai?- - Date: At/3 / -

7 Steven Bier, Nuclear Fuels Lead Engineer Reviewed By: LAcI Date: / o/3/o 3 Shie-Jeen-ier Onguclear ~ucais Snior eirE- n-g-Engineer Concurrence By-. yLLtbA4 Date: 16/1/0 3 Donald Notigan, §&efvisor Hope Creek Nucleafuels AnnrnveA Rv- -'VYAwVK^A\.- Da)tt- 6/ 0 /00 -3 Mike Mannion, Manager Nuclear Fuels/Reactor Engineering Page 1 of 50

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'NFS-0226 Revision 1 Table of Contents Section Description Page

1.0 INTRODUCTION

5 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR 6 2.1 AVERAGE PLANAR LINEAR BEAT GENERATION RATE 7 2.2 MINIMUM CRITICAL POWER RATIO 36 2.3 LINEAR BEAT GENERATION RATE 48

3.0 REFERENCES

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'NPS-0226 Revision I 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 PA]0 (Two Recirculation Loop Operation)_ _ 13 Table 2.1-4: APLHOR Data for Fuel Bundle PA10 (Single Recirculation Loop Operation) 14 Table 2.1-5: APLHGR Data for Fuel Bundle PB 10 (Two Recirculation Loop Operation) 17 Table 2.1-6: APLHGR Data for Fuel Bundle PB10 (Single Recirculation Loop Operation) 18 Table 2.1-7: APLHOR Data for Fuel Bundle PCI I (Two Recirculation Loop Operation)_ _ 21 Table 2.1-8: APLHOR Data for Fuel Bundle PCI I (Single Recirculation Loop Operation) _ _ 22 Table 2.1-9: APLHOR Data for Fuel Bundle PD11 C(wo Recirculaton Loop Operation) _ 25 Table 2.1-10: APLHGR Data for Fuel Bundle PD1 I (Single Recircuation Loop Operation) 26 Table 2.1-1 1: APLHCGR Data for Fuel Bundle PE12 (Two Recirculation Loop Operation)_ __ 29 Table 2.1-12: APLHGR Data for Fuel Bundle PE12 (Single Recirculation Loop Operation) 30 Table 2.1-13: APLHGR Data for Fuel Bundle PF12 (Two Recirculation Loop Operation)_ _ 33 Table 2.1-14: APLHOR Data for Fuel Bundle PF12 (Single Recirculation Loop Operation) _ _ 34 Table 22-1: Nominal Scram Speed 36 Table 2.2-2: Hope Creek Cycle 12 MCPR Operating limits: Cycle Exposure S 9179MWd/TU_- 37 Table 2.2-3: Hope Creek Cycle 12 MCPR Operating limits: Cycle Exposure > 9179MWdMTU 38 Page 3 of 50

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'NFS-0226 Revision I List of Figures Figures Description Page Figure 2.1-1: Lattice Definitions for Fuel Bundle HF09_ 8 Figure 2.1-2: APLHGR Limit for Fuel Bundle HFO9 11 Figure 2.1-3: Lattice Definitions for Fuel Bundle PA10 12 Figure2.1-4: APLH(R Limit for Fuel Bundle PA10 _ 15 Figure2.1-5: Lattice Definitions for Fuel Bundle PB10_ 16 Figure 2.1-6: APLHGR Limit for Fuel Bundle PB 10 19 Figure 2.1-7: Lattice Definitions for Fuel Bundle PCI 1 20 Figure 2.1-8: APLHGR Limit for Fuel Bundle PCI__ 23 Figure 2.1-9: Lattice Defiutions for Fuel Bundle PD1 1 24 Figure2.1-10: APLHGRLimitforFuel BundlePDI_ 27 Figure 2.1-11: Lattice Definitions for Fuel Bundle PE12 28 Figure 2.1-12: APLHOR 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 5 9179MWdMWV, EOC-RPT Operable 40 Figure 2.2-3: Power Dependent MCPR Limit: TSSS, Cycle Exposure 5 9179MWd/MTU, EOC-RPT Operable 41 Figure 2.24: Power Dependent MCPR Limit: NSS. Cycle Exposure S 9179MWd/MTU, EOC-RPT Inoperable 42 Figure 2.2-5: Power Dependent MCPR Limit: TSSS, Cycle Exposure S 9179MWd'TU, EOC-RPT Inoperable 43 Figure 2.2-6: Power Dependent MCPR Limit: NSS, Cycle Exposure > 9179MWd/MTU, EOC.RPI Operable 44 Figure 2.2-7: Power Dependent MCPR Limit: TSSS. Cycle Exposure > 9l79MWdMTU EOC-RPT Operable 45 Figure 2.2-8: Power Dependent MCPR Limit: NSS, Cycle Exposure > 9179MWd/TU, EOC-RPT Inoperable- 46 Figure 2.2-9: Power Dependent MCPR Limit: TSSS, Cycle Exposure > 9l70MWd/MTU, EOC-RPT Inoperable 47 Figure 2.3-1: Exposure Dependent LHGR Limits 49 Page 4of50

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'NFS-0226 Revision 1

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit 1 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 (MCPRf) and linear Heat Generation Rate (LHOR).

These operating limit values have been determined using NRC approved methods contained in the Reference Safety Report for Boiling Water Reactor Reload Fuel [1], CENPD-300-P-A (Revision 0), and GESTAR-ll [5], NEDE-2401 I-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 LIMiTING 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.

In addition, the operating limit LCO values or Related Reload Licensing Analysis Information in section 2.2 MINIBUM CRiTICAL POWER RATIO also include a conservative penalty to account for the potential effects of a condition being evaluated or pending resolution through a corrective action program. The conservative penalty is associated with a degraded condition within the control rod drive system, which results in rod withdrawal speeds in excess of the design specification for the system. This degraded condition is documented in corrective action order number 70033715.

This document is specific to Hope Creek Generating Station Unit 1 Cycle 121 Reload 11 and shall not be applicable to any other core or cycle design. The thermal limits contained in this report are applicable whether the Crossflowm 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'U, 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.

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'NFS-0226 Revision 1 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 314.4.1 Recirculation System Recirculation Loops 314.2b Power Distribution Bases 3/4.2.1b Average Planar Linear Heat Generation Rate 6.9.1.9 Administrative Controls, Core Operating Limits Report Page 6 of 50

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'NFS-0226 Revision 1 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 al.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, 2.1-4, 2.1-6, 2.1-8, 2.1-10,2.1-12 and 2.1-14.

NOTE Figures 2.1-2, 2.1-4, 2.1-6, 2.1-8, 2.1-10, 2.1-12 and 2.1-14 graphically represent the limiting column of Tables 2.1-1 through 2.1-14.

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'NFS-0226 Revision 6 inches 2656 (NATU) LT33 6 Inches 2124 (NATU) LT1 1 132 inches 2655 LT32 6 Inches 2124 (NATU) LT1 1 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)

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'NFS-0226 Revision I Table 2.1-1: APLHGR Data for Fuel Bundle HF09 (Two Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kwlft) 1 GWD/ISTJUMWD/KMU #2124 #2655 #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.

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/NPS-0226 Revision I Table 2.1-2: APLHGR Data for Fuel Bundle EHFO9 (Single Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kwlft)'

GWD/STU MWDM #2124 #2655 #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 10.50 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 1 4.96

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

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'NFS-0226 Revision 1 a

Figure 2.1-2: APLHGR Lint for Fuel Bundle HFO9 Page 11 of 50

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'NFS-0226 Revision 1 6 Inches LT 41 (NATU) 24 inches LT 43 114 Inches LT 42 6 Inches 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 PA10 (Reference 7)

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'NFS-0226 Revision I Table 2.1-3: APLHOR Data for Fuel Bundle PA10 (Iwo Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)

MW MU LT 41, 42 LT 43 Liiting 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.

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'NFS-0226 Revision 1 Table 2.1-4: APLHGR Data for Fuel Bundle PA10 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

/WtMTU 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 7.1

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

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/NFS-0226 Revision 1 le I

0 IMOD ) .3O 400o AirapwwBNVM^

Figure 2.1-4: APLHGR Limit for Fuel Bundle PA10 Page 15 of 50

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'NFS-0226 Revision 1 6 inches LT 41 (NATU) 138 inches LT 43 6 inches LT41 (NATU)

NATU = Natural Uranium attices, 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 PB10 (Reference 7)

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/NFS-0226 Revision 1 Table 2.1-5: APLHGR Data for Fuel Bundle PB10 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR L t (w/ft)

M"/WMT 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 8.5 18000 8.0 8.0 8.0 22000 7.6 7.6 7.6 24000 7.7 7.7 7.7 26000 8A 8.4 8.4 28000 8.4 8.4 8.4 34000 8.4 8.4 8A 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.

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'NFS-0226 Revision 1 Table 2.1-6: APLHGR Data for Fuel Bundle PB10 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwft)'

MD_ 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.

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'NFS-0226 Revision I I

5 0 10000 2000 30000 4 6=o am0 AWP"BapWnU4 Figure 2.1-6: APLHGR Limit for Fuel Bundle PB 10 Page 19 of 50

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/ NFS-0226 Revision 6 inches LT 41 (NATU) 36 inches LT 46 102 inches LT 44 6 Inches 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 PCI 1 (Reference 8)

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'NFS-0226 Revision 1 Table 2.1-7: APLHGR Data for Fuel Bundle PC 1 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwlft)'

MWD/MTU LT 41 LT 44 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 2.1-7 for the Lattice Definitions for this fuel assembly.

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'NFS-0226 Revision 1 Table 2.1-8: APLHGR Data for Fuel Bundle PC1I (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwlft)_

MWD/MTU LT 41 LT 44 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 2.1-7 for the Lattice Definitions for this fuel assembly.

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'NFS-0226 Revision 1 115 11S 105 10.0 Lo 7.5 7.0 0 10000 20000 30000 40000 50000 Average Planar Exposure QAWdWM Figure 2.1-8: APLHGR Limit for Fuel Bundle PCI 1 Page 23 of 50

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'NFS-0226 Revision 1 6 inches LT 41 (NATU) 36 inches LT 46 102 inches LT 45 6 inches LT 41 (NATU)

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 PD1 1 (Reference 8)

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'NFS-0226 Revision 1 Table 2.1-9: APLHGR Data for Fuel Bundle PD1I (Two Recirculation Loop Operation)

Exposure' Lattice APLHGR Limit (K ILft)l 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. 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.

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'NFS-0226 Revision 1 Table 2.1-10: APLHGR Data forFuel Bundle PD11 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ftjl 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.

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/NFS-0226 Revision I 11.5 14 t

9 m

I a 200 30000 40000 Average Manhr Exposure (MWdIMTU)

Figure 2.1-10: APLHGR Limit for Fuel Bundle PD1 I Page 27 of 50

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/NFS-0226 Revision 1 6 inches LT 41 (NATU) 36 inches LT 47 102 inches LT 49 6 inches I ILT 41 (NATU) J 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)

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/NFS-0226 Revision 1 Table 2.1 APLHGR Data for Fuel Bundle PE12 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwift)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

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' NFS-0226 Revision 1 Table 2.1-12: APLHGR Data for Fuel Bundle PE12 (Single Recirculation Loop Operation)

Exposure Lattice APLHR Linit (Kw/ft)

MWDM1U 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 8A 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

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/ NFS-0226 Revision 1 0 10000 20000 20000 40000 50000 60000 Average Planar Exposure (MW MTU)

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

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'NFS-0226 Revision 1 6 Inches LT 41 (NATU) 36 inches LT 47 102nches LT48 6 nches 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

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'NFS-0226 Revision 1 Table 2.1-13: APLHGR Data for Fuel Bundle PF12 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kwlft)'

MWD/MTU LT 41 LT 47 LT 48 Lhiting 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 9A 9.4 9A 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

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'NFS-0226 Revision 1 Table 2.1-14: APLHGR Data for Fuel Bundle PF12 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR LImit (Kwlft)'

MWDIMTU LT 41 LT 47 LT 48 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

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/ NFS-0226 Revision 11.5 11.0 10.5 10.0 1

8.5 8.0 7.5 7.0 0 20000 3W 0000 0000 60000 Averuge Planar Exposura (MWdJM Figure 2.1-14: APLHGR Linit for Fuel Bundle PF12 Page 35 of 50

ALL CTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20031023

/NFS-0226 Revision 1 2.2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MIDMUM 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. A conservative penalty has been added to the values in Table 2.2-2 and Table 2.2-3 to account for a degraded condition in the control rod drive system as documented in corrective action order number 70033715.

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 4] 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 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.

The Operating limit MCPR is the maximum of the 'ull 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

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  • NFS-0226 Revision 1 Table 2.2-2: Hope Creek Cycle 12 MCPR Operating limits:

Cycle Exposure < 9179MWd/MTU Main Turbine Bypass Operable Cycle Exposure 5 9179MWdIMTU Conditions Limit SVEA-96+ I) GE9BI (4)

NSS(^) Full Power MP85 1.6415) -

EOC-RPT Operable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power DependentP2 Figure 2.2.2 Figure 2.2.2 TSSS(t) Full Power 1.48t5) 1.64(5 EOC-RPI Operable Flow Dependent Figure 2.2.1 Figure 2.2.1 PowerDependent12 Figure 2.2.3 Figure 2.2.3 NSS Full Power 1.48' 1.64')

EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Fligure 2.2.1 Power Dependente2) Figure 2.2.A Figure 2.2.4 TSSS t1 " Full Power 1.49 ) 1.64('

EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power DependentO Figure 2.2.5 Figure 2.2.5

1. The TSSS MCPR values are based on tho required speed of Techtical 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 detemination of the MCPR operating limit with regard to scram speed.
2. Power dependent MCPR limits are provided for core thermal 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 PA10, PB 10. PCII, PD1 , PE12, and PF12 are SVEA-96+ fUel assemblies.
4. Fuel design HR)9 represents GE9B fuel assemblies.
5. As stated In section 2.2, a conseivadve MCPR penalty has been applied to this value to account for a degraded condition within the control rod drive system, as documented in corrective action order number 70033715.

Page 37 of 50

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'NFS-0226 Revision 1 Table 2.2-3: Hope Creek Cycle 12 MCPR Operating limits:

Cycle Exposure > 9179MWd/TU

  • Main Turbine Bypass Operable 9179MWdIMTU < Cvde Exnosure S 13324MWdIMTU Conditions Limit SVEA-96+ 3 GE9B (4)

NSS"1 Full Power 1.48w) 1.64(5)

EOC-RP1 Operable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent") Figure 2.2.6 Figure 2.2.6 TSSSP Full Power - i--) 1.64(5 EOC-RPT Operable Plow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependene) Figure 2.2.7 Figure 2.2.7 NSS`" Full Power 1.48") 1.64)

EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Figure 2.2.1 PowerDependent2) Figure 2.2.8 Figure 2.2.8 TSSS") Full Power 1.48(" 1.64" EOC-RPT Inoperable Flow Dependent Figure 2.2.1 Figure 2.2.1 Power Dependent2) Figure 2.2.9 Figure 2.2.9

1. Scenote I Table 2.2-2
2. See note 2 in Table 2.2-2
3. Fuel designPA1O. PB10, PCII, PD11, PEi2, andPF12 are SVEA-96+ fl assmblics.

FI

5. As stated in section 2.2, a conservative MCPR penalty has been applied to this value to account for a degraded condition within the control rod drive system, as documented In corrective action order number 70033715.

Page 38 of 50

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/NFS-0226 Revision 1

__tial Flow MCPR.

(% of Rated Flow) SVEA.96+ GE9B 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 1.10 1.10 Figure 2.2-1: Flow Dependent MCPR Limit Page 39 of 50

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'NFS-0226 Revision 1 Main Turbine Bypass Operable 2.80 2.70 2.60 Two and Sngle 20 latibon Loop Operaton_

2A0<I I lNomlinal Scram Speed r2.30 wfC1TOperabl 2.20 Expoeum S 9179 IAWdIM 2.10 22.0

~1.90 1.80 14 1.30-1.10 20 30 40 50 80 70 80 90 100 Percent et Rated Power 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 ows, Power < 30%, 30 2.57 2.66 Bypass Direct Scram I 25 2.57 2.66 Figure 2.2-2: Power Dependent MCPR Limit:

NSS, Cycle Exposure: 9179MWdMTU, EOC-RPT Operable Page 40 of 50

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' NFS-0226 Revision I Notes Initial Power MCPRp

(% of Rated) SVEA-96+ GE9B 100 1.37 1.45 AlD CoreFlows, Power 230%, 90 1.40 1.46 Credit Direct Scraxns 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 Limit:

TSSS, Cycle Exposure

  • 9179MWdIfTU, EOC-RPr Operable Page 41 of 50

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/NFS-0226 Revision 1 Main Turbine Bypass Operable 2.80 2.70 2.60 Two and Single

2.60 .l Radrculatlon Loop Operation
2A0-2.30 Nominal Scram Speed EOC-RPT Inoperable 220 ExposurS ; 170 MWdMTU 2.10

.200

1. 0 1.70_

&1.60 _ _" _ .W 1.0 1 -aGE913 ==

1.30.

1.10 20 30 40 50 60 70 80 g0 100 Pwcaui of Rated Power Notes Inial.Power MCPBR (o of Rated) SVEA-96i- GE9B 100 1.26 1.41 Al Core Flows, Power 30%, 90 1.29 1.41 Credit Direct Scrams 45 1.61 1.62

_ _ _ __ ___ __ ___ __ ___ _ _ _ _ 30 1 .8 8 1.8 6 All Core Flows, Power < 30%, 30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-4: Power Dependent MCPR Limit:

NSS, Cycle Exposure < 9179MWdMTU, EOC-RPT Inoperable Page 42 of 50

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'NFS-0226 Revision 1 Main Turbine Bypass Operable 2.80 2.70 . -

2.60 2.60 a ___,__ RectcRTWO and uatlon Slngbe Loop Operation 2.50 _ -

2.40 _ Tech Spoc SCram Speed 2.30 2.30 * . . _ EOCRPT Inoperable

~~~~~~~Exposure c 179 MWdllMr 2.20 __ _ _ _

2.10 2.00 1.90 1.80 i1.70 _

§1.60 . SVEA-0~r l 1.50 GE9

. 1.40 1.30 1.20 1.10 . .r 0 ...40 so 70 SD go 20 30 40 60 80 70 80 90 100 Percent of Rad Power Notes Initial Power MCPRp Nos(%of Rated) SVEA-96+ GE9B 100 1.40 1.49 All Core Flows, Power > 30%, 90 1A. 1.49 Credit Dlrect 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 S 9179MWd/MTU, EOC-RPT Inoperable Page 43 of 50

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20031023 NFS-0226 Revision I Main Turbine Bypass Operable 2.80 2.70 2.60 Two and Single 2.50 Recirculatlon Loop Operation 2.40 Nominal Scram Spe 2.30 E0C>RPT Operable 220 Expsure > 917a UW iW 2.10 2.00 . . -

1.80 11.70 1.50 1.30 1.20 20 30 40 50 60 70 80 90 100 Percent of Rated Power Initial Power MCPRp GE9B Notes (% of Rated) SVEA-96+

100 1.39 1.52 ABl Core Flows, Power 2 30E3o, 90 1.40 1.53 Credit Direct Scrams 45 1.64 1.65 30 1.88 1.86 All Core Flows, Power < 30%9 30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-6: Power Dependent MCPR Limit:

NSS, Cycle Exposure > 9179MWd'MTU, EOC-RFI Operable Page 44 of 50

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/NFS-0226 Revision 1 Main Turbine Bypass Operable 2.80 2.70 __

__ __ __ _ __ _ _ _ _ __ _ _ -~~~~~~ Two ad Single 260- , Recirculation Loop Operation 2.50_,,

20 25 Tch. Spec Scram Speed 2AO- ~~~~~~~~~~~EOC-RPT Opomable 2.30 -Exposure 9179 d U 2.20 2.10 I1.80 2.00 1.90 1.70-1.50' ImA 120 1.10 . . . . . . . . 7 0 100 20 30 40 so 60 70 80 go 100 Perct of Rated Power Notes Initial Power MCPR,

(% of Rated) SVEA-96+ GE9B 100 1.43 1.55 AU Core F1ows Power 30%, 90 1.44 1.55 Credit Direct Scrams - 45 1.68 1.66

_ _ ___ ___ __ ___ __ ___ _ _ _ _ 30 1.93 1 .8 8 ABl Core Flows, Power <30%, 30 2.57 2.66 Bypass Direct Scrams 25  ; 2.57 2.66 Figure 2.2-7: Power Dependent MCPR. Umit:

TSSS, Cycle Exposure > 9179MWd/TU, EOC-RPT Operable Page 45 of SO

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'NFS-0226 Revision I

.28 270 I -

I~~~~~~~~~pm,91n~ar 52 _ _ _ _ . _ _ _ _ _ _ _ T 20D 1.40 S1 -- J ~ B _ _ _ __ _ _ __ _ _ __ _ _ _ __ _ _

L im ~~ ~ ~ ~ ~ ) id _

Initlal Power MCPRp Notes (% of Rated) SVEA-96+ GE9B 100 1.41 1.55 All Core Flows, Power 2 30%, 90 1.42 1.56 Credit Direct Scrams - 45 1.64 1.66

.____ ___ _ __ __ 30

_ __ 1.88 1.86 AR Core Flows, Power < 30%, 30 2.57 2.66 Byass Direct Scrams 25 2.57 2.66 Figure 228: Power D~ependent MCPR Limit:

NSS, Cycle Exposure > 9179MW&%MTU, EOC-RPT Inoperable Page 46 of 50

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'NFS-0226 Revision 1 Main Turbine Bypass Operable 2.70 2.80 Two and Single

____ .____ Recircultlon Loop Operation

^240 Tech. Spec. Scram Speed

______ ______ ______ EOC.RPT inoperable 2M Exposure > 9179 MWWMU

.2.0, 1.70 1.30 1.20 1.10 .. .

20 30 40 60 EO 70 80 80 100 Percent of Rated Power InNsial Power MCPRp Notes (% of Rated) SVEA-96+ GE9B 100 1.45 1.59 All Core Flows, Power> 30%, 90 1.46 1.59 Credit Direct Scrams 45 1.68 1.67

__30 1.93 1.88 All Core Fows,, Power < 30%, 30 2.57 2.66 Bypass Direct Scrams 25 2.57 2.66 Figure 2.2-9: Power Dependent MCPR Limit:

TSSS, Cycle Exposure > 9179MWdMTU, EOC-RPT Inoperable Page 47 of 50

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'NFS-0226 Revision 1 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LHIR) shall not exceed the limit specified in Figure 2.3-1.

The CORE MAXIMUM FRACTON OF LIMITING POWER DENSITY as implemented in Technical Specification Section 3/4.2.2 shall use a FRACTION OF LlING 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

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+4- SVEA-96+ LHGR Umit e -U-GySB LHGR Limi 7

0 10000 20000 SCOOC 40000 50000 60000 Rod Nodal Exposure MWDIMTU)

I LHGR Limit LHGR Limit RodNodalExposure (kW/ft) (kW ft) 1)/MW ~~SVEA-96+ GE9B 0 13.4 14.4 14591 - - 14.4 16000 10.9 _ _ -

50000 8.3 ___

53000 Not Applicable 9.2 60000 Not Applicable 6.0 Figure 2.3-1: Exposure Dependent LHGR Limits Page 49 of 50

.~

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'NFS-0226 Revision 1

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 Creck: 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 I-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, February 2003.

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