ML022660057

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Core Operating Limits Report - Cycle 11/Reload 10, Revision 1
ML022660057
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/11/2002
From: Salamon G
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LRN-02-0317 NFS-0202, Rev 1
Download: ML022660057 (53)
v • d • e


Text

PSEG Nuclear LLC P 0 Box 236, Hancocks Bridge, New Jersey 08038-0236 SEP 112002 O PSEG NuclearLLC LRN-02-0317 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Gentlemen:

CORE OPERATING LIMITS REPORT-CYCLE II/RELOAD 10, REVISION 1 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 11/Reload 10 (NFS-0202, Rev. 1) in Attachment 1 to this letter.

Ifyou have any questions or require additional information, please contact Mr.

Michael Mosier at (856) 339-5434.

Sincerely, C_ý4 kl- G. Salamon Manager - Nuclear Safety & Licensing Attachment

()

(D

-7 95-2168 REV 7/99

Document Control Desk 2 SEP 1 1 2002 LRN-02-0317 C: Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. George Wunder, Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B3 Washington, DC 20555-0001 USNRC Senior Resident Inspector (X24)

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

ATTACHMENT 1 HOPE CREEK GENERATING STATION CORE OPERATING LIMITS REPORT CYCLE 1 1/RELOAD 10 REVISION 1

NFS-0202 Revision I Hope Creek Generating Station Core Operating Limits Report Cycle 11/ Reload 10 Effective Date: - 21 SIDI 2-

) I Prepared By: 4ja 1.

  • Approved Date: 8 /

Steven Bier, Nuclear Fuels Lead Engineer Senio Approved Date: P /102 Reviewed By: --

Shie-JenSenior Engineer Approved By: Anw V Approved Date: d8 (/0,o 2.

Donald Notigan, Supe*i or Hope Creek Nuclear Fuels Page 1 of 50

NFS-0202 Revision I 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-0202 Revision I List of Tables Table Description Page Table 2.1-1: APLHGR Data for Fuel Bundle HE08 (Two Recirculation Loop Operation) 9 Table 2.1-2: APLHGR Data for Fuel Bundle HE08 (Single Recirculation Loop Operation) - 10 Table 2.1-3: APLHGR Data for Fuel Bundle HD08 (Two Recirculation Loop Operation) 13 Table 2.1-4: APLHGR Data for Fuel Bundle HD08 (Single Recirculation Loop Operation) 14 Table 2.1-5: APLHGR Data for Fuel Bundle HF09 (Two Recirculation Loop Operation) _17 Table 2.1-6: APLHGR Data for Fuel Bundle HF09 (Single Recirculation Loop Operation) 18 Table 2.1-7: APLHGR Data for Fuel Bundle PAl0 (Two Recirculation Loop Operation) _21 Table 2.1-8: APLHGR Data for Fuel Bundle PAl0 (Single Recirculation Loop Operation) 22 Table 2.1-9: APLHGR Data for Fuel Bundle PB 10 (Two Recirculation Loop Operation) 25 Table 2.1-10: APLHGR Data for Fuel Bundle PB I0 (Single Recirculation Loop Operation) _ 26 Table 2.1-11: APLHGR Data for Fuel Bundle PC 1I (Two Recirculation Loop Operation) 29 Table 2.1-12: APLHGR Data for Fuel Bundle PCI 1 (Single Recirculation Loop Operation) 30 Table 2.1-13: APLHGR Data for Fuel Bundle PD1 1 (Two Recirculation Loop Operation) - 33 Table 2.1-14: APLHGR Data for Fuel Bundle PD1 1 (Single Recirculation Loop Operation)_ 34 Table 2.2-1: Nominal Scram Speed 36 Table 2.2-2: Hope Creek Cycle 11 MCPR Operating limits: Cycle Exposure < 8664MWdIMTU __ 37 Table 2.2-3: Hope Creek Cycle 11 MCPR Operating limits: Cycle Exposure > 8664MWd/MTU _ 38 Page 3 of 50

NFS-0202 Revision 1 List of Figures Figures Description Page Figure 2.1-1: Lattice Definitions for Fuel bundle HE(08 8 11 Figure 2.1-2: APLHGR Limit for Fuel Bundle HE08 Figure 2.1-3: Lattice Definitions for Fuel bundle HDI08 12 Figure 2.1-4: APLHGR Limit for Fuel Bundle HD08 15 Figure 2.1-5: Lattice Definitions for Fuel bundle BF(09 16 Figure 2.1-6: APLHGR Limit for Fuel Bundle HF09 19 Figure 2.1-7: Lattice Definitions for Fuel bundle PA]10 20 Figure 2.1-8: APLHGR Limit for Fuel Bundle PAl0 23 Figure 2.1-9: Lattice Definitions for Fuel bundle PB] 10 24 Figure 2. 1-10: APLHGR Limit for Fuel Bundle PB 11 27 Figure 2.1-11: Lattice Definitions for Fuel bundle PC 28 Figure 2.1-12: APLHGR Limit for Fuel Bundle PCI. 31 Figure 2.1-13: Lattice Definitions for Fuel bundle PI 32 Figure 2.1-14: APLHGR Limit for Fuel Bundle PDI 35 Figure 2.2-1: Flow Dependent MCPR Limit 39 Figure 2.2-2: Power Dependent MCPR Limit: NSS, Cycle Exposure < 8664MWdIMTU, EOC-RPT Operable 40 Figure 2.2-3: Power Dependent MCPR Limit: TSSS , Cycle Exposure < 8664MWd/MTU, EOC-RPT Operable 41 Figure 2.2-4: Power Dependent MCPR Limit: NSS, Cycle Exposure < 8664MWdIMTU, EOC-RPT Inoperable 42 Figure 2.2-5: Power Dependent MCPR Limit: TSSS Cycle Exposure < 8664MWdIMTU, EOC-RPT Inoperable 43 Figure 2.2-6: Power Dependent MCPR Limit: NSS, Cycle Exposure > 8664MWd/MTU, EOC-RPT Operable 44 Figure 2.2-7: Power Dependent MCPR Limit: TSSS , Cycle Exposure > 8664MWdIMTU, EOC-RPT Operable 45 Figure 2.2-8: Power Dependent MCPR Limit: NSS, Cycle Exposure > 8664MWd/MTU, EOC-RPT Inoperable 46 Figure 2.2-9: Power Dependent MCPR Limit: TSSS , Cycle Exposure > 8664MWdIMTU, EOC-RPT Inoperable 47 Figure 2.3-1: LHGR versus Rod Nodal Exposure 49 Page 4 of 50

NFS-0202 Revision I

1.0 INTRODUCTION

The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit 1 Cycle 11/ Reload 10 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 (LHGR).

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-Il [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 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 MINIMUM 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 the failure of LPRM 16-41C, which resulted in a degraded RBM channel

'A' for the partially inserted control rod 14-47, as documented in corrective action order 70025990.

This document is specific to Hope Creek Generating Station Unit 1 Cycle 11 / Reload 10 and shall not be applicable to any other core or cycle design. The thermal limits contained in this report are applicable whether the CrossflowTM correction factor is applied or not applied.

This report is applicable for cycle 11 operation from the date of issuance through the end of effective full power capability or a cycle exposure of 12626MWd'MTU, whichever occurs first [2] and for coastdown operation at reduced power to a cycle exposure of 13616MWdMTU. 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-0202 Revision I 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-0202 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 a.1.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.

Page 7 of 50

NFS-0202 Revision 1 6 inches 2408 (NATU) LT311 6 inches 2124 (NATU) LT11 18 inches 2405 LT28 18 inches 2407 LT30 42 inches 2406 LT29 54 inches 2405 LT28

,4'.J-A IklArIl'. l I"I.44 6 inches e-I e,+Qi4mI ) L,,,

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 HE08 Page 8 of 50

NFS-0202 Revision 1 Table 2.1-1: APLHGR Data for Fuel Bundle HE08 (Two Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kw/ft) 1 GWD/STU MWD/MTU #2124 #2405 #2406 #2407 #2408 Limiting 0.00 0.0 12.66 12.68 12.10 11.63 12.72 11.63 0.20 220.5 12.59 12.71 12.14 11.69 12.74 11.69 1.00 1102.3 12.40 12.79 12.24 11.85 12.83 11.85 2.00 2204.6 12.34 12.91 12.40 12.07 12.86 12.07 3.00 3306.9 12.34 13.02 12.57 12.32 12.86 12.32 4.00 4409.2 12.37 13.14 12.76 12.59 12.89 12.59 5.00 5511.5 12.40 13.26 12.95 12.86 12.92 12.86 6.00 6613.8 12.43 13.38 13.15 13.12 12.94 13.12 7.00 7716.1 12.46 13.51 13.36 13.36 12.97 13.36 8.00 8818.4 12.48 13.63 13.54 13.53 12.99 13.53 9.00 9920.7 12.50 13.62 13.62 13.62 13.00 13.62 10.00 11023.0 12.52 13.59 13.59 13.59 13.01 13.59 12.50 13778.8 12.36 13.57 13.57 13.57 12.92 13.57 15.00 16534.5 11.98 13.48 13.49 13.48 12.53 13.48 20.00 22046.0 11.20 12.65 12.87 12.86 11.75 12.65 25.00 27557.5 10.42 11.85 12.13 12.10 10.97 11.85 35.00 38580.5 8.87 10.28 10.49 10.55 9.43 10.28 45.00 49603.5 6.01 8.96 9.10 9.16 7.18 8.96 46.61 51378.2 5.18 8.26 8.39 8.44 8.26 48.53 53494.6 7.43 7.55 7.57 5.38 7.43 52.23 57573.1 5.82 5.82 52.92 58333.7 5.60 52.98 58399.9 5.59

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

Page 9 of 50

NFS-0202 Revision I Table 2.1-2: APLHGR Data for Fuel Bundle HE08 (Single Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kw/ft)'

GWD/STU MWD/MTU #2124 #2405 #2406 #2407 #2408 Limiting 0.00 0.0 10.89 10.90 10.41 10.00 10.94 10.00 0.20 220.5 10.83 10.93 10.44 10.05 10.96 10.05 1.00 1102.3 10.66 11.00 10.53 10.19 11.03 10.19 2.00 2204.6 10.61 11.10 10.66 10.38 11.06 10.38 3.00 3306.9 10.61 11.20 10.81 10.60 11.06 10.60 4.00 4409.2 10.64 11.30 10.97 10.83 11.09 10.83 5.00 5511.5 10.66 11.40 11.14 11.06 11.11 11.06 6.00 6613.8 10.69 11.51 11.31 11.28 11.13 11.28 7.00 7716.1 10.72 11.62 11.49 11.49 11.15 11.49 8.00 8818.4 10.73 11.72 11.64 11.64 11.17 11.64 9.00 9920.7 10.75 11.71 11.71 11.71 11.18 11.71 10.00 11023.0 10.77 11.69 11.69 11.69 11.19 '11.69 12.50 13778.8 10.63 11.67 11.67 11.67 11.11 11.67 15.00 16534.5 10.30 11.59 11.60 11.59 10.78 11.59 20.00 22046.0 9.63 10.88 11.07 11.06 10.11 10.88 25.00 27557.5 8.96 10.19 10.43 10.41 9.43 10.19 35.00 38580.5 7.63 8.84 9.02 9.07 8.11 8.84 45.00 49603.5 5.17 7.71 7.83 7.88 6.17 7.71 46.61 51378.2 4.45 7.10 7.22 7.26 7.10 48.53 53494.6 6.39 6.49 6.51 4.63 6.39 52.23 57573.1 5.01 5.01 52.92 58333.7 4.82 52.98 58399.9 4.81

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

Page 10 of 50

NFS-0202 Revision I 0 10000 2= 3= 4MO Figure 2.1-2: APLHGR Limit for Fuel Bundle HE08 Page 11 of 50

NFS-0202 Revision I 6 inches 2404 (NATU) LT27' 6 inches 2124 (NATU) LT11 18 inches 2403 LT26 60 inches 2402 LT25 54 inches 2401 LT24 6 inches Z[1Z4 (NAI U) L I II 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 HDO8 Page 12 of 50

NFS-0202 Revision 1 Table 2.1-3: APLHGR Data for Fuel Bundle HD08 (Two Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kw/ft) 1 GWD/STU MWD/IMTU #2124 #2401 #2402 #2403 #2404 Limiting 0.00 0.0 12.20 12.05 11.80 12.09 12.20 11.80 0.20 220.5 12.23 12.10 11.83 12.14 12.23 11.83 1.00 1102.3 12.35 12.21 11.93 12.26 12.35 11.93 2.00 2204.6 12.34 12.35 12.08 12.41 12.50 12.08 3.00 3306.9 12.34 12.49 12.23 12.57 12.65 12.23 4.00 4409.2 12.37 12.63 12.39 12.73 12.79 12.39 5.00 5511.5 12.40 12.78 12.55 12.89 12.85 12.55 6.00 6613.8 12.43 12.93 12.66 13.05 12.88 12.66 7.00 7716.1 12.46 13.07 12.77 13.22 12.90 12.77 8.00 8818.4 12.48 13.20 12.88 13.38 12.92 12.88 9.00 9920.7 12.50 13.33 12.99 13.51 12.94 12.99 10.00 11023.0 12.52 13.48 13.10 13.59 12.95 13.10 12.50 13778.8 12.36 13.61 13.16 13.62 12.85 13.16 15.00 16534.5 11.98 13.29 12.87 13.29 12.46 12.87 20.00 22046.0 11.20 12.62 12.26 12.63 11.68 12.26 25.00 27557.5 10.42 11.84 11.66 11.94 10.90 11.66 35.00 38580.5 8.87 10.42 10.36 10.50 9.36 10.36 45.00 49603.5 6.01 9.20 9.00 9.24 7.03 9.00 46.61 51378.2 5.18 8.45 8.20 8.49 8.20 48.28 53219.0 7.68 7.36 7.71 5.36 7.36 51.23 56470.8 5.89 5.89 52.25 57595.2 5.84 52.27 57617.2 5.84

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

Page 13 of 50

NFS-0202 Revision I Table 2.1-4: APLHGR Data for Fuel Bundle HD08 (Single Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kw/ft) 1 GWD/STU MWD/MTU #2124 #2401 #2402 #2403 #2404 Limiting 0.00 0.0 10.49 10.36 10.15 10.40 10.49 10.15 0.20 220.5 10.52 10.41 10.17 10.44 10.52 10.17 1.00 1102.3 10.62 10.50 10.26 10.54 10.62 10.26 2.00 2204.6 10.61 10.62 10.39 10.67 10.75 10.39 3.00 3306.9 10.61 10.74 10.52 10.81 10.88 10.52 4.00 4409.2 10.64 10.86 10.66 10.95 11.00 10.66 5.00 5511.5 10.66 10.99 10.79 11.09 11.05 10.79 6.00 6613.8 10.69 11.12 10.89 11.22 11.08 10.89 7.00 7716.1 10.72 11.24 10.98 11.37 11.09 10.98 8.00 8818.4 10.73 11.35 11.08 11.51 11.11 11.08 9.00 9920.7 10.75 11.46 11.17 11.62 11.13 11.17 10.00 11023.0 10.77 11.59 11.27 11.69 11.14 11.27 12.50 13778.8 10.63 11.70 11.32 11.71 11.05 11.32 15.00 16534.5 10.30 11.43 11.07 11.43 10.72 11.07 20.00 22046.0 9.63 10.85 10.54 10.86 10.04 10.54 25.00 27557.5 8.96 10.18 10.03 10.27 9.37 10.03 35.00 38580.5 7.63 8.96 8.91 9.03 8.05 8.91 45.00 49603.5 5.17 7.91 7.74 7.95 6.05 7.74 46.61 51378.2 4.45 7.27 7.05 7.30 7.05 48.28 53219.0 6.60 6.33 6.63 4.61 6.33 51.23 56470.8 5.07 5.07 52.25 57595.2 5.02 52.27 57617.2 1 5.02 r

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

Page 14 of 50

NFS-0202 Revision 1 14.00 13.00 12.00 11.00 E

3 &00 S00 a.

7.00-6.00-5.00 4.00 010000 300

... 40000

-vr~Ram Ex=OVM Figure 2.1-4: APLHGR Limit for Fuel Bundle HDO8 Page 15 of 50

NFS-0202 Revision I 6 inches 2656 (NATU) LT33' 6 inches 2124 (NATU) LT1 1 132 inches 2655 LT32 6 inches 1 2124 (NATU) I LT11 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 HF09 Page 16 of 50

NFS-0202 Revision 1 Table 2.1-5: APLHGR Data for Fuel Bundle HF09 (Two Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kwlft) 1 GWD/STU MWD/MTU #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 2.1-5 for the Lattice Definitions for this fuel Assembly.

Page 17 of 50

NFS-0202 Revision 1 Table 2.1-6: APLHGR Data for Fuel Bundle HF09 (Single Recirculation Loop Operation)

Lattice Exposure Lattice APLHGR Limit (Kw/ft) 1 GWD/STU MWD/MTU #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 4.96

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

Page 18 of 50

NFS-0202 Revision I Y~laoD I.1 .1 E

a.D 0 1000D 20030000 40000 AWRmw Bpm" OMYM Figure 2.1-6: APLHGR Limit for Fuel Bundle IF09 Page 19 of 50

NFS-0202 Revision I 6 inches LT 41 (NATU) 24 inches LT 43 114 inches LT 42 6 inches LT41 (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 PAl0 Page 20 of 50

NFS-0202 Revision I Table 2.1-7: APLHGR Data for Fuel Bundle PAl0 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft) 1 MWD/MTU 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

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

Page 21 of 50

NFS-0202 Revision 1 Table 2.1-8: APLHGR Data for Fuel Bundle PAl0 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU 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

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

Page 22 of 50

NFS-0202 Revision 1

.. *ao \ ' _.i Ev --- 5--

7.0.

ILI so40 0 10000 20000 3000 4000D S)00 6)0M Figure 2.1-8: APLHGR Limit for Fuel Bundle PAl0 Page 23 of 50

NFS-0202 Revision I 6 inches LT 41 (NATU) 138 inches LT 43 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 PB 10 Page 24 of 50

NFS-0202 Revision I Table 2.1-9: APLHGR Data for Fuel Bundle PB10 (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU 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 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

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

Page 25 of 50

f NFS-0202 Revision I Table 2.1-10: APLHGR Data for Fuel Bundle PBLO (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft) 1 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

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

Page 26 of 50

NFS-0202 Revision 1 10L0-*-- - - i-----------------

- 1 7.0

&0 0 10000 20000 30000 4000D 60000 AmragW RnarEqp=" W*:M*

Figure 2.1-10: APLHGR Limit for Fuel Bundle PB10 Page 27 of 50

NFS-0202 Revision I 6 inches LT 41 (NATU) 36 inches LT 46 102 inches LT 44 6 inches LT41 (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 PC 11 Page 28 of 50

NFS-0202 Revision I Table 2.1-11: APLHGR Data for Fuel Bundle PCI I (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU LT 41 LT 44 LT46 Limiting 0 9.1 9.2 9.2 9.2 350 9.1 9.2 9.2 9.2 1000 9.2 9.2 9.2 9.2 9500 9.2 9.2 9.2 9.2 10000 9.1 9.1 9.1 9.1 14000 8.5 8.7 8.7 8.7 18000 8.0 8.2 8.2 8.2 22000 7.6 7.8 7.8 7.8 24000 7.7 7.7 7.7 7.7 26000 8.4 8.4 8.4 8.4 28000 8.4 8.4 8.4 8.4 34000 8.4 8.4 8.4 8.4 42000 8.4 8.4 8.4 8.4 54000 8.1 8.1 8.1 8.1 59000 7.9 7.9 7.9 7.9

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

Page 29 of 50

NFS-0202 Revision I Table 2.1-12: APLHGR Data for Fuel Bundle PCI 1 (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)'

MWD/MTU LT 41 LT 44 LT46 Limiting 0 8.2 8.3 8.3 8.3 350 8.2 8.3 8.3 8.3 1000 8.3 8.3 8.3 8.3 9500 8.3 8.3 8.3 8.3 10000 8.2 8.2 8.2 8.2 14000 7.7 7.8 7.8 7.8 18000 7.2 7.4 7.4 7.4 22000 6.8 7.0 7.0 7.0 24000 6.9 6.9 6.9 6.9 26000 7.6 7.6 7.6 7.6 28000 7.6 7.6 7.6 7.6 34000 7.6 7.6 7.6 7.6 42000 7.6 7.6 7.6 7.6 54000 7.3 7.3 7.3 7.3 59000 7.1 7.1 7.1 7.1

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

Page 30 of 50

NFS-0202 Revision 1 10.0 9.0 S8.0

-J 7.0 6.0 5.0 0 10000 20000 30000 40000 60000 Average Planar Exposure (MWd/MTU)

Figure 2.1-12: APLHGR Limit for Fuel Bundle PCI11 Page 31 of 50

NFS-0202 Revision 1 6 inches LT 41 (NATU) 36 inches LT 46 102 inches LT 45 6 inches LT41 (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 PD 11 Page 32 of 50

NFS-0202 Revision I Table 2.1-13: APLHGR Data for Fuel Bundle PD 1I (Two Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft)

MWD/MTU LT 41 LT 45 LT46 Limiting 0 9.1 9.2 9.2 9.2 350 9.1 9.2 9.2 9.2 1000 9.2 9.2 9.2 9.2 9500 9.2 9.2 9.2 9.2 10000 9.1 9.1 9.1 9.1 14000 8.5 8.7 8.7 8.7 18000 8.0 8.2 8.2 8.2 22000 7.6 7.8 7.8 7.8 24000 7.7 7.7 7.7 7.7 26000 8.4 8.4 8.4 8.4 28000 8.4 8.4 8.4 8.4 34000 8.4 8.4 8.4 8.4 42000 8.4 8.4 8.4 8.4 54000 8.1 8.1 8.1 8.1 59000 7.9 7.9 7.9 7.9

1. See Figure 2.1-13 for the Lattice Definitions "forthis fuel Assembly.

Page 33 of 50

NFS-0202 Revision I Table 2.1-14: APLHGR Data for Fuel Bundle PDI I (Single Recirculation Loop Operation)

Exposure Lattice APLHGR Limit (Kw/ft) 1 MWD/MTU LT 41 LT 45 LT46 Limiting 0 8.2 8.3 8.3 8.3 350 8.2 8.3 8.3 8.3 1000 8.3 8.3 8.3 8.3 9500 8.3 8.3 8.3 8.3 10000 8.2 8.2 8.2 8.2 14000 7.7 7.8 7.8 7.8 18000 7.2 7.4 7.4 7.4 22000 6.8 7.0 7.0 7.0 24000 6.9 6.9 6.9 6.9 26000 7.6 7.6 7.6 7.6 28000 7.6 7.6 7.6 7.6 34000 7.6 7.6 7.6 7.6 42000 7.6 7.6 7.6 7.6 54000 7.3 7.3 7.3 7.3 59000 7.1 7.1 7.1 7.1

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

Page 34 of 50

NFS-0202 Revision 1 E

C,

-I a.

4 0 1000D X) 3oooo4 kma Powa rpzma WAM Figure 2.1-14: APLHGR Limit for Fuel Bundle PDL11 Page 35 of 50

NFS-0202 Revision 1 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, or shall be greater than 1.45 for any control rod withdrawal while the position of rod 14-47 is above notch 44. The conservative requirement for MCPR greater than 1.45 for any control rod withdrawal while the position of rod 14-47 is above notch 44 is due to the degradation of RBM channel 'A' for this rod as described in notification 20107097.

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 'Full Power,' 'Power Dependent' and

'Flow Dependent' values presented in Tables 2.2.2 and 2.2.3 for the various operating conditions, or 1.45 for any control rod withdrawal while the position of rod 14-47 is above notch 44.

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

NFS-0202 Revision I Table 2.2-2: Hope Creek Cycle 11 MCPR Operating limits:

Cycle Exposure _ 8664MWdIMTU Main Turbine Bypass Operable Cycle Exposure

  • 8664MWdIMTU Limit SVEA-96+ (3) GE9B (4)

Conditions NSS") Full Power 1.31') 1.31")

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"1 Full Power 1.35(5) 1.45 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 1.31'" 1.3115)

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") Full Power 1.3815) 1.52 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 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 PAl0, PB 10, PCI 1, and PD1I are SVEA-96+ fuel assemblies.
4. Fuel design HD08, HE08 and HF09 are GE9B fuel assemblies.
5. As stated in section 2.2, an MCPR limit of 1.45 is applicable for withdrawal of any control rod while the position of rod 14-47 is above notch 44. This conservative penalty is due to the RBM degradation described in notification 20107097.

Page 37 of 50

NFS-0202 Revision I Table 2.2-3: Hope Creek Cycle 11 MCPR Operating limits:

Cycle Exposure > 8664MWd/MTU Main Turbine Bypass Operable 8664MWdIMTU < Cycle Exposure < 12626MWdIMTU Limit SVEA-96+ (3) GE9B (4)

Conditions NSS"1 Full Powert5 ) 1.4016) 1.52 I

EOC-RPT Operable Flow Dependent(5 ) Figure 2.2.1 Figure 2.2.1 Power Dependent(2,5 ) Figure 2.2.6 Figure 2.2.6 TSSS(') Full Power(5) 1.47 1.61 EOC-RPT Operable Flow Dependent(5) Figure 2.2.1 Figure 2.2.1 Power Dependent(2' 5) Figure 2.2.7 Figure 2.2.7 NSSt1 Full Power(-)

Flow Dependent(5) 1.431"1 Figure 2.2.1 1.57 Figure 2.2.1 I

EOC-RPT Inoperable Power Dependent( 2,5) Figure 2.2.8 Figure 2.2.8 TSSS"' 1 Full Power(") 1.50 1.67 EOC-RPT Inoperable Flow Dependent(5) Figure 2.2.1 Figure 2.2.1 Power Dependent (2") Figure 2.2.9 Figure 2.2.9

1. See note I in Table 2.2-2
2. See note 2 in Table 2.2-2
3. Fuel design PAl0, PB 10, PC1 1, and PD1 I are SVEA-96+ fuel assemblies.
4. Fuel design HD08, HE08 and HF09 are GE9B fuel assemblies.
5. All full-power and power-dependent MCPR LCO values shall be increased by 0.02 for coastdown operation at reduced power to a cycle exposure of 13616MWD/MTU. The flow-dependent MCPR LCO values remain applicable during coastdown operation.
6. As stated in section 2.2, an MCPR limit of 1.45 is applicable for withdrawal of any control rod while the position of rod 14-47 is above notch 44. This conservative penalty is due to the RBM degradation described in notification 20107097.

Page 38 of 50

NFS-0202 Revision I Initial Flow MCPRt

(% Rated Flow) SVEA-96+ GE9B 20 1.29 1.50 40 1.28 1.45 60 1.27 1.40 80 1.22 1.30 100 1.15 1.20 109 1.10 1.10 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-1: Flow Dependent MCPR Limit Page 39 of 50

I NFS-0202 Revision I Main Turbine Bypass Operable 2.80 I 2.70 -- i" 2.60 Two and Single S2.50. S25-___ -- Recirculation Loop Operation E_

- 2.40 Nominal Scram Speed

._ 2.30. EOC-RPT Operable 2.20 Exposure < 8664 MWd/MTU 0 2.10t 02.00 1.90 1.80 1.70 0 1.60 1.50 -- SVEA-96+

IL"1.40 GE9B 1.30 1.20 1.10 30..5060708.9010 20 30 40 50 60 70 80 90 100 Percent of Rated Power Notes Initial Power MCPRp

(% of Rated) SVEA-96+ GE9B 100 1.22 1.29 All Core Flows, Power > 30%, 90 1.25 1.32 Credit Direct Scrams 45 1.63 1.67 30 1.91 1.97 All Core Flows, Power < 30%, 30 2.53 2.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-2: Power Dependent MCPR Limit:

NSS, Cycle Exposure < 8664MWd/MTU, EOC-RPT Operable Page 40 of 50

NFS-0202 Revision 1 Main Turbine Bypass Operable 2.80 2.70 2.60

  • 2.50 I Two and Single S2.50:

"S _Reirculation Loop Operation S2.40

_- 2.0 Tech. Spec. Scram Speed

'__2.30_ EOC-RPT Operable 2.20 0 2.10 _ _ -__ _ - 4_ /Exposure < 8664 MWd/MTU

a. 2.00 C.,

o1.80

-. - -F_ _ _

0 1160 SVA6+

  • o"0 -- cý---GE9B3 3 1.50 '

a.1.40 1.30 1.20 1.10 L. .. 1 .

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

(% of Rated) SVEA-96+ GE9B 100 1.35 1.45 All Core Flows, Power > 30%, 90 1.39 1.50 Credit Direct Scrams 45 1.70 1.74 30 1.96 2.02 All Core Flows, Power < 30%, 30 2.53 2.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-3: Power Dependent MCPR Limit:

TSSS, Cycle Exposure < 8664MWd/MTU, EOC-RPT Operable Page 41 of 50

NFS-0202 Revision I Main Turbine Bypass Operable 2.80-.

2.70 I 2.60 Two and Single Recirculation Loop Operation 2.50 _

-3 2.40 I Im Nominal Scram Speed E 2.30 - - EOC-RPT Inoperable 2.20 Exposure < 8664 MWd/MTU 0 2.10

m. 2.00 1.90 1.80 S1.70 0.

S1.60 -.-- SVEA-96+

1.50 --- GE9B 0

CL 1.40.

1.30 1.20 I 1.10 . .. .. .. .

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

(% of Rated) SVEA-96+ GE9B 100 1.23 1.31 All Core Flows, Power >_30%, 90 1.26 1.35 Credit Direct Scrams 45 1.63 1.67 30 1.91 1.97 All Core Flows, Power < 30%, 30 2.53 2.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal when the position of rod 14-47 is above notch 44.

Figure 2.2-4: Power Dependent MCPR Limit:

NSS, Cycle Exposure < 8664MWd/MTU, EOC-RPT Inoperable Page 42 of 50

NFS-0202 Revision 1 Main Turbine Bypass Operable 2.80

  • 2.70 Two and Single 2.60 ýFRecirculation Loop Operation 2.5011

..~3 2.40 2.40- '^Tech.

  • , Spec.

P Scram Speed DEOC-RPT Inoperable

.S 2.30 -- Exposure < 8664 MWd/MTU 2.20 CL o 2.10 9L 2.00 I1.90

'*1.80

  • 1.70 S1.60 -SVEA-96+

S1.50 cIGE =9B ~___

IL 1.40 1.30 1.20_

1.10 I. .. .. ..

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

(% of Rated) SVEA-96+ GE9B 100 1.38 1.52 All Core Flows, Power > 30%, 90 1.41 1.56 Credit Direct Scrams 45 1.70 1.74 30 1.96 2.02 All Core Flows, Power < 30%, 30 2.53 2.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-5: Power Dependent MCPR Limit:

TSSS, Cycle Exposure < 8664MWd/MTU, EOC-RPT Inoperable Page 43 of 50

NFS-0202 Revision I Main Turbine Bypass Operable 2.80-.

2.70 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

2.60 Two and Single Recirculation Loop Operation S2.50 "i 2.40-. - Nominal Scram Speed

.S 2.30 EOC-RPT Operable Exposure > 8664 MWd/MTUI 2.20 03.

o 2.10_,

n. 2.00

=E1.90

. 1.80 0 1.70

  • CL S1.60 1.50 SVEA-96 ____ ________

0 H -- oGE9

. 1.40 _

1.30 1.20 1.10 20 30 40 50 60 70 80 90 100 Percent of Rated Power Initial Power MCPRp

(% of Rated) SVEA-96+ GE9B 100 1.40 1.52 All Core Flows, Power > 30%, 90 1.43 1.56 Credit Direct Scrams 45 1.68 1.75 30 1.91 1.97 All Core Flows, Power < 30%, 30 2.53 2.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-6: Power Dependent MCPR Limit:

NSS, Cycle Exposure > 8664MWdAMTU, EOC-RPT Operable Page 44 of 50

NFS-0202 Revision I 2.80 2.70 T_ Main Turbine Bypass Operable

_ [ Two and Single 2.60 -- ,........,

-,2.50 Recirculation Loop Operation E,_2.40__ Tech. Spec. Scram Speed 2.30- EOC-RPT Operable r- 2.30- Exposure > 8664 MWd/MTU 0.

0 2.10

-. 2.00 S1.90 1.80 C S1.70

)1.70 _______

o 1.60 1..

GE9B _

1.50 0

1.20 1.10 20 30 40 50 60 70 80 90 100 Percent of Rated Power Notes Initial Power MCPRP

(% of Rated) SVEA-96+ GE9B 100 1.47 1.61 All Core Flows, Power > 30%, 90 1.50 1.63 Credit Direct Scrams 45 1.71 1.77 30 1.96 2.02 All Core Flows, Power < 30%, 30 2.53 5.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-7: Power Dependent MCPR Limit:

TSSS, Cycle Exposure > 8664MWd/MTU, EOC-RPT Operable Page 45 of 50

NFS-0202 Revision I Initial Power MCPRp

(% of Rated) SVEA-96+ GE9B 100 1.43 1.57 All Core Flows, Power > 30%, 90 1.46 1.61 Credit Direct Scrams 45 1.68 1.75 30 1.91 1.97 All Core Flows, Power <30%, 30 2.53 2.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-8: Power Dependent MCPR Limit:

NSS, Cycle Exposure > 8664MWd/MTU, EOC-RPT Inoperable Page 46 of 50

NFS-0202 Revision 1 Main Turbine Bypass Operable 2.80 2.70 ,

2.60- Two and Single --

S2.50 2_Recircualtion Loop Operation E 240 Tpech. Srpe. Scramn Speed S240 EOC-RPT Inoperable A 230 Exposure > 8664 MWd/MTU 1! 2.20_

0 2.10 I. 200 S1.90

. 1.80 C 1.70 SSVEA-96+ ______'

01.60

GE9B1 3 1.50 0

9L 1.40 1.30 120 1.10 . .

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

(% of Rated) SVEA-96+ GE9B 100 1.50 1.67 All Core Flows, Power > 30%, 90 1.52 1.69 Credit Direct Scrams 45 1.71 1.77 30 1.96 2.02 All Core Flows, Power < 30%, 30 2.53 2.64 Bypass Direct Scrams 25 2.59 2.70 As noted in section 2.2, a conservative limit of MCPR > 1.45 shall be used for any control rod withdrawal while the position of rod 14-47 is above notch 44.

Figure 2.2-9: Power Dependent MCPR Limit:

TSSS, Cycle Exposure > 8664MWd/MTU, EOC-RPT Inoperable Page 47 of 50

NFS-0202 Revision 1 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-0202 Revision I 16 15 13

~12 E 11

-- SVEA-96+ LHGR Limit 8 ---- GE9B LHGR Limit 7k 6

0 10000 20000 30000 40000 50000 60000 Rod Nodal Exposure (MWD/MTU)

LHGR Limit LHGR Limit Rod Nodal Exposure (kW / ft) (kW / ft)

(MWDJMTU) 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

NFS-0202 Revision I

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-2001-008-00, "HCGS Cycle 11 Reload Licensing Report," Westinghouse Electric Company LLC, WCAP-15717 Rev. 0, August 2001.
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-2001-006-00, "Conditions for Design: PSEG Nuclear LLC: Hope Creek: Cycle 11 Reload Analysis," Westinghouse Electric Company LLC, CE NPSD-885-P, Rev. 0, May 2001.
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.

Page 50 of 50

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