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0000-0105-6621-SRLR, Rev. 0, Supplemental Reload Licensing Report for Hope Creek Unit 1, Reload 16 Cycle 17, Attachment 1
	ML102240344
Person / Time
Site:	Hope Creek
Issue date:	07/31/2010
From:	; Global Nuclear Fuel - Americas
To:	; Office of Nuclear Reactor Regulation
References
	LR-N10-0290 0000-0105-6621-SRLR, Rev 0
	Download: ML102240344 (103)
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LR-N10-0290 Attachment 1 GEH Report 0000-0105-6621-SRLR, Revision 0 Hope Creek Cycle 17 Supplemental Reload Licensing Report (SRLR)

GNF Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 0000-0105-6621-SRLR Revision 0 Class I July 2010 Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 16 Cycle 17

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by PSEG

("Recipient") in support of the operating license for Hope Creek (the "Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.

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

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Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF-A/GEH Nuclear Analysis personnel. The Supplemental Reload Licensing Report was prepared by J. Su. This document has been verified by George Baka.

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Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Table of Contents

1. Plant Unique Items 5

2. Reload Fuel Bundles 5

3. Reference Core Loading Pattern 6

4. Core Reactivity and Control System Worth - No Voids, 20'C 6

5. Standby Liquid Control System Shutdown Capability 6

6. Reload Unique GETAB AOO Analysis - Initial Condition Parameters 7

7. Selected Margin Improvement Options 12

8. Operating Flexibility Options 13

9. Core-wide AOO Analysis Results 14

10. Rod Withdrawal Error AOO Summary 19

11. Cycle SLMCPR and OLMCPR Summary 20

12. Overpressurization Analysis Summary 26

13. Fuel Loading Error Results 26

14. Control Rod Drop Analysis Results 27

15. Stability Analysis Results 27

16. Loss-of-Coolant Accident Results 31 Appendix A Analysis Conditions 86 Appendix B Thermal-Mechanical Compliance 87 Appendix C Decrease in Core Coolant Temperature Event 88 Appendix D Off-Rated Limits 89 Appendix E Scram Speed Licensing Basis 92 Appendix F Feedwater Temperature and Operating Dome Pressure Range 93 Appendix G NEDC-33173P-A Supplementary Information 94 Appendix H Reduced Feedwater Temperature BSP Regions 95 Appendix I Calculated BSP Region End Points 98 Appendix J GE14I Fuel Introduction 99 Appendix K List of Acronyms 100 Page 4

Hope Creek 0000-0105-6621 -SRLR PolnacI i1 Revision 0 R-Innij 11; The basis for this report is General Electric StandardApplication for Reactor Fuel, NEDE-2401 1-P-A-16, October 2007; and the U.S. Supplement, NEDE-2401 1-P-A-16-US, October 2007.

1. Plant Unique Items Appendix A: Analysis Conditions Appendix B:' Thermal-Mechanical Compliance Appendix C: Decrease in Core Coolant Temperature Event Appendix D: Off-Rated Limits Appendix E: Scram Speed Licensing Basis Appendix F: Feedwater Temperature and Operating Dome Pressure Range Appendix G: NEDC-33173P-A Supplementary Information Appendix H: Reduced Feedwater Temperature BSP Regions Appendix I: Calculated BSP.Region End Points Appendix J: GE141 Fuel Introduction Appendix K: List of Acronyms

2. Reload Fuel Bundles Fuel Type Cycle Loaded Number Irradiated:

GE 14-PIOCNAB402-5G6.0/14G4.0-1GOT- 150-T6-2758 (GE14C) 13 4 GE14-P1OCNAB393-18G4.0-100T-150-T6-2885 (GE14C) 14 80 GE14-P1OCNAB393-18GZ-100T-150-T6-2884 (GE14C) 14 16 GE14-P1OCNAB396-17GZ-100T-150-T6-3007 (GE14C) 15 48 GE 14-P 1OCNAB405-15GZ- 10OT- 150-T6-3009 (GE14C) 15 56 GE14-P1OCNAB398-17GZ- lOOT- 150-T6-3008 (GE14C) 15 96 GE14-P1OCNAB400-14GZ- 100T- 150-T6-3006 (GE14C) 15 28 GE14-P1OCNAB400-9G6.0/6G4.0-100T- 150-T6-3176 (GE14C) 16 176 GE14-P1OCNAB400-14GZ- 10OT-150-T6-3006 (GE14C) 16 52 New:

GE14I-PIOCCOB379-13GZ-100T-150-T6-3309 (GE14I) 17 12 GE14-P1OCNAB405-6G6.0/11G4.0-1OOT-150-T6-3313 (GE14C) 17 72 GE14-P1OCNAB402-12G6.0/2G4.0-lOOT- 150-T6-3312 (GE14C) 17 124 Total: 764 Page 5

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0

3. Reference Core Loading Pattern Core Average Cycle Exposure Exposure' 33432 MWd/MT 14467 MWd/MT Nominal previous end-of-cycle exposure: (30329 MWd/ST) (13124 MWd/ST)

Minimum previous end-of-cycle exposure (for cold 33101 MWd/MT 14136 MWd/MT shutdown considerations): (30029 MWd/ST) (12824 MWd/ST) 20404 MWd/MT 0 MWd/MT Assumed reload beginning-of-cycle exposure: (18510 MWd/ST) (0 MWd/ST)

Assumed reload end-of-cycle exposure (rated 33069 MWd/MT 12666 MWd/MT conditions): (30000 MWd/ST) (11490 MWd/ST)

Reference core loading pattern: Figure 1

4. Core Reactivity and Control System Worth - No Voids, 20'C Beginning of Cycle, keffective Uncontrolled 1.112 Fully controlled 0.954 Strongest control rod out 0.989 R, Maximum increase in strongest rod out reactivity during the cycle (Ak) 0.001 11.574 MWd/MT Cycle exposure at which R occurs (10500 MWd/ST)

5. Standby Liquid Control System Shutdown Capability Boron (ppm) Shutdown Margin (Ak)

( ).

(aton20'C)

(at (at 160'C, Xenon Free)

Analytical Requirement Achieved 660 >010.i0 0.021 Page 6

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0

6. Reload Unique GETAB AOO Analysis - Initial Condition Parameters 1 Operating domain: ICF (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)

Peaking Factors Fuel Bundle Bundle Initial Des Local Radial Axial R-Factor Power Flow Design _ (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.42 1.27 1.040 6.939 104.0 1.35 Operating domain: ICF (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2 )

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Inta Design___ _(MWt) (1000 lb/hr) MCPR GE14C 1.45 1.34 1.34 1.040 6.560 108.5 1.37 Operating domain: ICF (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2 )

Peaking Factors _

Bundle Bundle Initial Fuel Local Radial Axial R-Factor Power Flow Design (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.42 1.28 1.040 6.964 103.8 1.35 Operating domain: MELLLA (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.39 1.27 1.040 6.805 93.5 1.34 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Operating domain: ICF. & FWTR (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)

Peaking Factors Fuel Bundle - Bundle Initial Local Radial Axial R-Factor -Power Flow Design (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.52 .1.31 1.040 7.422 . 100.2 1.30 Operating domain: ICF & FWTR (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2 )

Peaking Factors Fuel Design___

GE14C Local 1.45 Radial 1.44

{(MWt)

Axial 1.33 R-Factor 1.040 Bundle Power 7.026 Bundle Flow (1000 lb/hr) 105.9 Initial MCPR 1.32 Operating domain: ICF & FWTR (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2 Peaking Factors

_ I(MWt)

Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow

_esign_ _ _ (1000 lb/hr) MCPR GE14C 1.45' 1.49 1.31 1.040 7.297 101.8 1.33 Operating domain: MELLLA & FWTR (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2 Peaking Factors Fuel Design____

GE14C Local 1.45 j(MWt)

Radial 1.47 Axial

.1.29 R-Factor

.1.040 Bundle Power 7.150 Bundle Flow (1000 lb/hr) 91.4 Initial MCPR 1.31 Operating domain: ICF with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2 )

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design__ __(MWt) (1000 lb/hr) MCPR GE14C 1.45 1.39 1.27 1.040 6.809 104.8 1.38 Page 8

Hope Creek 0000-0105-6621 -SRLR R~1nad ltq Revision 0 Reload 16 Operating domain: ICF with RPTOOS (HBB)

Exposure range_: MOC to EOC (Application Condition: 2 )

Peaking Factors Fuel Design Local Radial

{ Axial 1.34 R-Factor Bundle Power (MWt)

Bundle Flow (1000 lb/hlr) initial MCPR GE14C 1.45 1.32 1.34 1.040 6.483 108.9 1.39 Operating domain: ICF with RPTOOS (UB)

Exposure range_: MOC to EOC (Application Condition: 2)

Peaking Factors Fuel Des Local Radial I Axial R-Factor Bundle Power Bundle Flow Initial MCPR Design_____ _(MWt) (1000 lb/hr) .MCPR, GE14C 1.45 1.40 1.28 1.040 6.840 104.6 1.38 Operating domain: MELLLA with RPTOOS (UB)

Exposure range : MOC to EOC (Application Condition: 2)

Peaking Factors Fuel Bundle Bundle, Initial Des Local Radial Axial R-Factor Power Flow Design___ _(MWt) (1000 lb/hr) MCPR GE14C 1.45 1.37 1.27 1.040 6.715 94.0 1.36 Operating domain: ICF & FWTR with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2 )

Peaking Factors Fuel Design Local I Radial Axial R-Factor Bundle-Power (MWt)

Bundle Flow (1000 lb/hr)

Initial MCPR GE14C 1.45 1.50 1.31 1.040 7.330 100.9 1.32 Page 9

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Operating domain: ICF & FWTR with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2 )

Peaking Factors*

Fuel Bundle -Bundle Initial Design Local Radial Axial R-Factor Power Flow Design____ *_. (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.42 1.33 1.040 6.921 T -106.6 1.35 Operating domain: ICF & FWTR with RPTOOS (UB)

Exposure range : MOC to EOC (Application Condition: 2)

Peaking Factors "

Design GE14C.

Local 1.45 Radial 1.48 Fuel Axial

.1.31

__ }(MWt)

R-Factor 1.040 Bundle-Power 7.202 Bundle Flow

(1000,lb/hr) 102.5 Initial MCPR 1.35 Operating domain: MELLLA & FWTR with RPTOOS (UB)

Exposure range : MOC to EOC (Application'Condition: 2)' ,

Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design , . (MWt) (1000 lb/hr) MCPR GE14C -.1.45 1.45 1.29 1.040 7.050 92.1 1.33 Operating domain: MELLLA (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2 Peaking Factors Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow

.__._,,_ _ ! _ (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.37 1.26 1.040. . 6.727 94.2 1.34 Operating domain: MELLLA (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Peaking Factors Fuel Bundle Bundle Initial Design Design__ Local Radial Axial R-Factor

__(MWt)

Power (1000Flowlb/hr) MCPR GE14C 1.45 1.31 1.33 1.040 6.399 97.8 1.36 Page 10

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Operating domain: MELLLA & FWTR (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)

Peaking Factors Fuel Bundle Bundle Initial Design Design__

Local Radial Axial R-Factor_ Power

"_ (MWt)

Flow (1000 Ib/hr) MCPR GE14C 1.45 1.48 1.30 1.040 7.241 90.4 1.29 Operating domain: MELLLA & FWTR (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Peaking Factors Fuel Bundle Bundle initial Local Radial Axial R-Factor Power Flow Design 1 (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.40 1.32 1.040 6.855 95.4 1.31 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Peaking Factors Fuel Bundle Bundle Initial Des Local Radial Axial R-Factor Power Flow Design (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.36 1.26 1.040 6.638 94.7 1.37 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2 )

Peaking Factors Fuel Bundle Bundle Initial Design Design___ Local

_(MWt)

Radial Axial R-Factor Power Flow (1000 lb/hr) MCPR GE14C 1.45 1.29 1.33 1.040 6.339 98.2 1.38 Page 11

Hope Creek 0000-0105-6621 -SRLR P cvlAemnn Operating domain: MELLLA & FWTR with RPTOOS (HEBB)

Exposure range : BOC to MOC (Application Condition: 2 )

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Inta Design__ __(MWt), (1000 lb/br) MCPR GE14C 1.45 .1.46 1.30 1.040 7.126 91.1 1.31 Operating domain: MELLLA & FWTR with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2 )

Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design (MWt) (1000 lb/hr) 'MCPR GE14C 1.45 1.39 1.31 1.040 6.765 96.0 1.34

7. Selected Margin Improvement Options 2 Recirculation pump trip: Yes Rod withdrawal limiter: No Thermal power monitor: Yes

Improved scram time: Yes (ODYN Option B)

Measured scram time: No Exposure dependent limits: Yes Exposure points analyzed: 2 2 Refer to the GESTAR basis document identified at the beginning of this report for the margin improvement options currently supported therein.

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Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Table 7-1 Cycle Exposure Range Designation Name Exposure Range 3 BOC to MOC BOC17 to EOR17-3216 MWd/MT (2917 MWd/ST)

MOC to EOC EOR17-3216 MWd/MT (2917, MWd/ST) to EOC17 BOC to EOC BOC17 to EOC17

8. Operating Flexibility Options 4 The following information presents the operational domains and flexibility options which are supported by the reload licensing analysis.

Extended Operating Domain (EOD): Yes EOD type: Maximum Extended Load Line Limit (MELLLA)

Minimum core flow at rated power: 94.8 %

Increased Core Flow: Yes Flow point analyzed throughout cycle: 105.0 %

Feedwater Temperature Reduction: Yes Feedwater temperature reduction during cycle: 60.0°F Final feedwater temperature reduction: 102.0°F ARTS Program: Yes Single Loop Operation: Yes Equipment Out of Service:

Safety/relief valves Out of Service: Yes (credit taken for 13 valves)

RPTOOS Yes 3 End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100% power/100% flow, and normal feedwater temperature. For plants without mid-cycle OLMCPR points, EOR is not applicable.

4 Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility options currently supported therein.

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Hope Creek 0000-0105-6621-SRLR Ppvidnn fl

9. Core-wide AOO Analysis Results 5 Methods used: GEMINI, GEXL-PLUS Operating domain: ICF (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)'

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 210 110 0.20 2 Load Rejection w/o Bypass 319 115 0.27 3 Turbine Trip w/o Bypass 292 112 0.26 4 Operating domain: ICF (HBB)

Exposure range : MOC to EOC, (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure. 307 119 0.23 5 Load Rejection w/o Bypass 442 123 0.28 6 Turbine Trip w/o Bypass 397 120 0.28 7 Operating domain: ICF (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A GE14C Fig.

(% rated) (% rated)

FW Controller Failure 218 111 0.21 8 Load Rejection w/o Bypass 332 115 0.27 9 Turbine Trip w/o Bypass 307 113 0.26 10 5Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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Hope Creek 0000-0105-6621 -SRLR Rolnnd 11t Revision 0 Reload 16 Operating domain: MELLLA (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 192 108 0.19 11 Load Rejection w/o Bypass 273 112 0.26 12 Turbine Trip w/o Bypass 263 110 0.24 13 Operating domain: ICF & FWTR (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 214 114 0.22 14 Operating domain: ICF & FWTR (HBB)

Exposure range :- MOC to EOC (Application Condition: 1, 2)

Uncorrected ACPR Flux Q/A Event (% rated) (% rated) GE14C Fig.

FW Controller Failure 321 123 0.24 15 Operating domain: ICF & FWTR (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux - Q/A GE14C Fig.

Event_ (% rated) (% rated)

FW Controller Failure 249 .117 . 0.24 16 Operating domain: MELLLA & FWTR (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux- Q/A GE14C Fig.

Event__ __ (% rated) (% rated)

FW Controller Failure 224 114 0.22 17 Page 15

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Operating domain: ICF with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A Event___________(% rated) (% rated) GE14C Fig.

FW Controller Failure 238 113 0.24 18 Load Rejection w/o Bypass 351 118 0.30 19 Turbine Trip w/o Bypass 335 116 0.29 20 Operating domain: ICF with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A Event_____________(% rated) (% rated) GE14C Fig.

FW Controller Failure 338 121 0.26 21 Load Rejection w/o Bypass 479 125 0.30 22 Turbine Trip w/o Bypass 440 124 0.30 23 Operating domain: ICF with RPTOOS (UB)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A Event (% rated) (% rated) GE14C Fig.

FW Controller Failure 250 114 0.24 24 Load Rejection w/o Bypass 365 118 0.30 25 Turbine Trip w/o Bypass 352 116 0.29 26 Operating domain: MELLLA with RPTOOS (UBI)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A GE14C Fig.

Event_ _ _ (% rated) (% rated)

FW Controller Failure 210 111 0.22 27 Load Rejection w/o Bypass 291 115 0.28 28 Turbine Trip w/o Bypass 295 113 0.27 29 Page 16

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Operating domain: ICF & FWTR with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 241 117 0.25 30 Operating domain: ICF & FWTR with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 351 126 0.27 31 Operating domain: ICF & FWTR with RPTOOS (UB)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR EFlux Q/A Event (% rated) (% rated) GE14C Fig.

FW Controller Failure 278 120 0.27 32 Operating domain: MELLLA & FWTR with RPTOOS (UB)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR Fnux Q/AG Event (% rated) (% rated) GE1C Fig.

FW Controller Failure 244 116 0.24 33 Operating domain: MELLLA (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 194 109 0.20 34 Load Rejection w/o Bypass 280 112 0.26 35 Turbine Trip w/o Bypass 264 110 0.25 36 Page 17

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Operating domain: MELLLA (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 281, 117 0.23 37 Load Rejection w/o Bypass 402 120 0.28 38 Turbine Trip w/o Bypass 357 118 "0.27 39 Operating domain: MELLLA & FWTR (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 198 112 0.21 40 Operating domain: MELLLA & FWTR (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 304 121 0.24 41 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 212 112 0.22 42 Load Rejection w/o Bypass 299 115 0.28 43 Turbine Trip w/o Bypass 295. 113 0.27 44 Page 18

Hope Creek 0000-0105-6621 -SRLR lRt1nnd 1 f Revision 0 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 300 119 0.25 45 Load Rejection w/o Bypass 429 123 0.30 46 Turbine Trip w/o Bypass 387 121 0.29 47 Operating domain: MELLLA & FWTR with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2 -

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 217 114 0.23 48 Operating domain: MELLLA & FWTR with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2)

Uncorrected ACPR Event Flux Q/A

(% rated) (% rated) GE14C Fig.

FW Controller Failure 326 123 0.25 49

10. Rod Withdrawal Error AOO Summary The ARTS based rod withdrawal error is an unblocked basis. The unblocked rod withdrawal error results are summarized below.

RWE Results:

RBM Setpoint (%) ACPR Unblocked 0.19 Page 19

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 8 9

11. Cycle SLMCPR and OLMCPR Summary 6 7 Two Loop Operation (TLO) safety limit: 1.08 Single Loop Operation (SLO) safety limit: 1.10 Stability MCPR Design Basis: See'Section 15 ECCS MCPR Design Basis: See Section 16 (Initial MCPR)

Non-pressurization Events:

Exposure range: BOC to EOC All Fuel Types Rod Withdrawal Error (Unblocked) 1.27 Loss of Feedwater Heating 1.23 Fuel Loading Error (Mislocated) Not Limiting Fuel Loading Error (Misoriented) 1.24 Rated Equivalent SLO Pump Seizure 10 1.29 6 Exposure range designation is defined in Table 7-1.

7 For SLO, the MCPR operating limit is 0.02 greater than the two loop value.

8 The safety limit values presented include a 0.02 adder in accordance with' extended operating domain licensing commitments.

9 The OLMCPR values presented in the Limiting Pressurization Events summary table have been adjusted to include a 0.01 adder in accordance with extended operating domain licensing commitments. OLMCPR values presented in the detailed Pressurization Event tables do NOT include this adjustment.

10The cycle-independent OLMCPR for the recirculation pump seizure event for GE14C is 1.48 based on the cycle-specific SLO SLMCPR. When adjusted for the off-rated power/flow conditions of SLO, this limit corresponds to a rated OLMCPR of 1.29. This limit does not require an adjustment for the SLO SLMCPR.

Page 20

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Limitin2 Pressurization Events OLMCPR Summary Table: 11 Appl.

Cond. Exposure Range Option A Option B Cond.

GE14C GE14C 1 Equipment In Service BOC to MOC 1.49 1.38 MOC to EOC 1.60 .1.43 2 RPTOOS BOC to MOC 1.51 1.40 MOC to EOC 1.62 1.45 Pressurization Events: 12 Operating domain: ICF (HBB) --

Exposure range : BOC to MOC (Application Condition: 1, 2)

Option*A Option B GE14C GE14C FW Controller Failure 1.41 1.30 Load Rejection w/o Bypass 1.48. 1.37 Turbine Trip w/o Bypass 1.47 1.36 Operating domain: ICF (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Option A Option B GE14C GE14C FW Controller Failure 1.53 1.36 Load Rejection w/o Bypass 1.59 1.42 Turbine Trip w/o Bypass 1.58 1.41

" Each application condition (Appl. Cond.) covers the entire range of licensed flow and feedwater temperature unless specified otherwise. The OLMCPR values presented apply to rated power operation based on the two loop operation safety limit MCPR.

12 Application condition numbers shown for each of the following pressurization events represent the application conditions for which this event contributed in the determination of the limiting OLMCPR value.

Page 21

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Operating domain: ICF (UB)

Exposure range : MOC to EOC (Application Condition: 1,2)

Option A Option B GE14C GE14C FW Controller Failure 1.51 1.34 Load Rejection w/o Bypass 1.58 1.41 Turbine Trip w/o Bypass 1.57 1.40 Operating domain: MELLLA (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Option A Option B GE14C GE14C FW Controller Failure 1.49 1.32 Load Rejection w/o Bypass 1.56 1.39 Turbine Trip w/o Bypass 1.55 1.38 Operating domain: ICF-& FWTR (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2 )

Option A Option B GE14C GE14C FW Controller Failure 1.43 1.32 Operating domain: ICF & FWTR (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Option A Option B GE14C GE14C FW Controller Failure 1.55 1.38 Operating domain: ICF & FWTR (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

T Option A Option B GE14C GE14C FW Controller Failure 1.55 1.38 Page 22

Hope Creek 0000-0105-6621-SRLR Ro~lnad 16S Revision 0 Reload 16 Operating domain: MELLLA & FWTR (UB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Option A Option B GE14C GE14C FW Controller Failure 1.53 1.36 Operating domain: ICF with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Option A Option B GE14C GE14C FW Controller Failure 1.44 1.33 Load Rejection w/o Bypass - 1.50 1.39 Turbine Trip w/o Bypass 1.50 1.39 Operating domain: ICF with RPTOOS (HtBB)

Exposure range : MOC to EOC (Application Condition: 2 )

Option A Option B GE14C GE14C FW Controller Failure 1.56 1.39 Load Rejection w/o Bypass 1.61 1.44 Turbine Trip w/o Bypass 1.61 1.44 Operating domain: ICF with RPTOOS (UB)

Exposure range : MOC to EOC (Application Condition: 2)

Option A Option B GE14C GE14C FW Controller Failure 1.55 1.38 Load Rejection w/o Bypass 1.61 1.44 Turbine Trip w/o Bypass 1.60 1.43, Operating domain: MELLLA with RPTOOS (IJB)

Exposure range : MOC to EOC (Application Condition: 2)

Option A Option B GE14C GE14C FW Controller Failure 1.52 1.35 Load Rejection w/o Bypass 1.59 1.42 Turbine Trip w/o Bypass 1.58 1.41 Page 23

Hope Creek 0000-0105-6621-SRLR R~lnad 1t Revision 0 Reload 16 Operating domain: ICF & FWTR with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Option A Option B GE14C GE14C FW Controller Failure 1.46,, 1.35 Operating domain: ICF & FWTR with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2.).

Option A Option B GE14C GE14C FW Controller Failure 1.57 1.40 Operating domain: ICF & FWTR with RPTOOS (UB)

Exposure range : MOC to EOC (Application Condition: 2 )

Option A Option B GE14C GE14C FW Controller Failure 1.57 1.40 Operating domain: MELLLA & FWTR with RPTOOS (UB)

Exposure range .: MOC to EOC (Application Condition: 2 )

Option A Option B GE14C GE14C FW Controller Failure 1.55 1.38 Operating domain: MELLLA (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2)

Option A Option B GE14C GE14C FW Controller Failure 1.40 1.29 Load Rejection w/o Bypass 1.47 1.36 Turbine Trip w/o Bypass 1.46 1.35 Page 24

Hope Creek 0000-0105-6621-SRLR I? _; ; nflf

ý v" - I - #

Operating domain: MELLLA (HBB)

Exposure range : MOC to EOC ( Application Condition: 1, 2)

Option A Option B GE14C GE14C FW Controller Failure 1.53 1.36 Load Rejection w/o Bypass 1.58 1.41 Turbine Trip w/o Bypass 1.58 1.41 Operating domain: MELLLA & FWTR (HBB)

Exposure range : BOC to MOC (Application Condition: 1, 2 )

Option A Option B GE14C GE14C FW Controller Failure 1.42 1.31 Operating domain: MELLLA & FWTR (HBB)

Exposure range : MOC to EOC (Application Condition: 1, 2)

Option A Option B GE14C GE14C FW Controller Failure 1.54 1.37 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Option A Option B GE14C GE14C FW Controller Failure 1.43 1.32 Load Rejection w/o Bypass 1.49 1.38 Turbine Trip w/o Bypass 1.48 1.37 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2 )

Option A Option B GE14C GE14C FW Controller Failure 1.55 1.38 Load Rejection w/o Bypass 1.60 1.43 Turbine Trip w/o Bypass 1.60 1.43 Page 25

Hope Creek 0000-0105-6621-SRLR Ri*lnmd 1f*

Revision 0 Reload 16 Operating domain: MELLLA & FWTR with RPTOOS (HBB)

Exposure range : BOC to MOC (Application Condition: 2)

Option A Option B GE14C GE14C FW Controller Failure 1.44 1.33 Operating domain: MELLLA & FWTR with RPTOOS (HBB)

Exposure range : MOC to EOC (Application Condition: 2)

Option A Option B GE14C GE14C FW Controller Failure 1.55 1.38

12. Overpressurization Analysis Summary Event PsI Pdome Pv Plant (psig) (psig) (psig) Response MSIV Closure (Flux Scram) - ICF (HBB) 1261 1267 1288 Figure 50 MSIV Closure (Flux Scram) - MELLLA (HBB) 1263 1268 1288 Figure 51

13. Fuel Loading Error Results Variable water gap misoriented bundle analysis: Yes Misoriented Fuel Bundle ACPR GE 14-PIOCNAB400-9G6.0/6G4.0-10OT-I50-T6-3176 (GE14C) 0.14 GE14-P1OCNAB400-14GZ-10OT- 150-T6-3006 (GE14C) 0.15 GE14-P1OCNAB402-12G6.0/2G4.0-ZOOT-150-T6-'3'3'1 2( GE14C) 0.14 GE14-P1OCNAB405-6G6.0/ 1G4.0-1OOT-150-T6-3313 (GE14C) 0.16 GE14I-P1OCCOB379-13GZ-100T-150-T6-3309 (GE14I) 0.11 13Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

Page 26

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0

14. Control Rod Drop Analysis Results Banked Position Withdrawal Sequence is utilized at Hope Creek Generating Station Unit 1; therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-2401 1-P-A-US.

15. Stability Analysis Results 15.1 Stability Option III Solution Hope Creek has implemented BWROG Long Term Stability Solution Option III using the Oscillation Power Range Monitor (OPRM) as described in Reference 1 in Section 15.4. The plant specific Hot Channel Oscillation Magnitude (HCOM) (Reference 2 in Section 15.4) and other cycle specific stability parameters are used in the Cycle 17 Option III stability evaluation. Backup Stability Protection (BSP) regions are used by the plant in the event that the Option III OPRM system is declared inoperable.

The following Option III OPRM stability setpoint determination described in Section 15.2 and the implementation of the associated BSP Regions described in Section 15.3 provide the stability licensing bases for Hope Creek Cycle 17.

15.2 Detect and Suppress Evaluation A reload Option III evaluation has been performed in accordance with the licensing methodology described in Reference 3 in Section 15.4. The stability based OLMCPR is determined for two conditions as a function of OPRM amplitude setpoint. The two conditions evaluated are: (1) a postulated oscillation at 45% rated core flow quasi steady-state operation (SS), and (2) a postulated oscillation following a two recirculation pump trip (2PT) from the limiting rated power operation state point.

The OPRM-setpoint-dependent OLMCPR(SS) and OLMCPR(2PT) values are calculated for Cycle 17 in accordance with the BWROG regional mode DIVOM guidelines described in Reference 4 in Section 15.4. The Cycle 17 Option III evaluation provides adequate protection against violation of the SLMCPR for the two postulated reactor instability events as long as the plant OLMCPR is equal to or greater than OLMCPR(SS) and OLMCPR(2PT) for the selected OPRM setpoint in Table 15-2.

The relationship between the OPRM Successive Confirmation Count Setpoint and the OPRM Amplitude Setpoint is provided in Reference 3 in Section 15.4 and Table 15-1. For intermediate OPRM Amplitude Setpoints, the corresponding OPRM Successive Confirmation Count Setpoints have been obtained by using linear interpolation.

The OPRM setpoints for TLO are conservative relative to SLO and are, therefore, bounding.

Page 27

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Table 15-1 Relationship between OPRM Successive Confirmation Count Setpoint and OPRM Amplitude Setpoint Successive OPRM Confirmation Amplitude Count Setpoint Setpoint 6 > 1.04 8 >1.05 9 >1.06 10 >1.07 11 > 1.08 12 >1.09 13 >1.10 14 >1.11 15 >1.13 16 >1.14 17 >1.16 18 >1.18 19 >1.21 20 >1.24 Page 28

Hope Creek 0000-0105-6621 '-SRLR Relnnd 16 Re~viwinn 0 Table 15-2 OPRM Setpoint Versus OLMCPR14 OPRM Amplitude OLMCPR(SS) OLMCPR(2PT)

Setpoint 1.05 1.281 1.235 1.06 1.307 1.261 1.07 1.337 1.290 1.08 1.369 1.321 1.09 1.394 1.345 1.10 1.410 1.360 1.11 1.427 1.376 1.12 1.444 1.393 1.13 1.461 1.410 1.14 1.479 1.427 OLMCPR Off-rated Rated Power Acceptance OLMCPR OLMCPR (see Criteria @45% flow Section 11) 15.3 Backup Stability Protection The BSP region boundaries were calculated for Hope Creek Cycle 17 for normal and reduced feedwater temperature operation. The endpoints of the regions are defined in Table 15-3. The region boundaries, shown in Figure 52, are defined using the Generic Shape Function (GSF). See Reference 5 in Section 15.4.

14 The OLMCPR values presented in the OPRM Setpoint Versus OLMCPR table have been adjusted to include a 0.01 adder in accordance with extended operating domain licensing commitments in Reference 6 (in Section 15.4) to prevent a setpoint credit as described by MFN08-693.

Page 29

Hope Creek 0000-0105-6621 -SRLR R~lnnd1 1t*

Revision 0 Reload 16 Table 15-3 BSP Region Intercepts for Normal Feedwater Temperature Region Boundary Power Flow. Core Highest

(%) (%)M DR DR Intercept ,:DR Al 58.2 40.0 < 0.799 < 0.437 B1 44.7 35.0 < 0.798 < 0.447 A2 66.4 50.0 < 0.799 < 0.404 B2 32.2 36.3 < 0.790 < 0.391 Appendix H contains the BSP region boundaries for reduced feedwater temperature operation. Appendix I contains the calculated BSP region end points and decay ratios for Nominal Feedwater Temperature.

The OPRM Trip-Enabled Region for Nominal Feedwater Temperature and FWHOOS is confirmed to be less than or equal to 60% rated core flow and greater than or equal to 26.1% rated power. Also, the OPRM Trip-Enabled region for up to 88°F FFWTR is confirmed to be less than or equal to 60% rated core flow and greater than or equal to 26.1% rated power.

15.4 References

1. BWR Owners' Group Long-term Stability Solutions Licensing Methodology, NEDO-3.1960-A, November 1995 (including Supplement 1).

2. Reactor Long-Term Stability Solution Option III: Licensing Basis Hot: Channel Oscillation Magnitude for Hope Creek, GENE-A 13-00381-04, R 1, September 2004.

3. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, Licensing Topical Report, NEDO-32465-A, August 1996.

4. Plant-Specific Regional Mode DIVOM Procedure Guideline, GE-NE-0000-0028-9714-Ri, June 2005.

5. Backup Stability Protection (BSP) for Inoperable Option III Solution, OG-02-0119-260, July 2002.

6. Final Safety Evaluation by the Office of Nuclear Reactor Regulation, Licensing Topical Report NEDC-33173P,Applicability of GE Methods to Expanded Operating Domains,July 2009.

Page 30

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0

16. Loss-of-Coolant Accident Results 16.1 10CFR50.46 Licensing Results The ECCS-LOCA analysis is based on the SAFER/GESTR-LOCA methodology. The licensing results applicable to each fuel type in the new cycle are summarized in the following table.

Table 16.1-1 Licensing Results Core-Wide Licensing Local Me-Wate Fuel Type Basis PCT Oxidation Reatio

(°F) (OF) (%)Reaction

(%) (%)

GE14C 1380 < 1.00 < 0.10 GE14I 1380 < 1.00 < 0.10 The SAFER/GESTR-LOCA analysis results are documented in Section 5 of Reference 1 for GE14C in Section 16.4.

This core contains GE141 Isotope Test Assemblies (ITAs), and the GE14C Licensing Results are applicable to these ITAs as described in the Technical Evaluation documented by Reference 1 for GE141 in Section 16.4.

16.2 10CFR50.46 Error Evaluation The 10CFR50.46 errors applicable to the Licensing Basis PCT are shown in the following table.

Table 16.2-1 Impact on Licensing Basis Peak Cladding Temperature for GE14C 10CFR50.46 Error Notifications PCT Impact (OF) 2006-01 Impact of Top Peaked Power Shape on Small Break 0 LOCA AnalysisT0 Total PCT Adder ('F) 0 The GE14C Licensing Basis PCT remains below the 10CFR50.46 limit of 2200 OF.

Page 31

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 The GE14C 10CFR50.46 errors are applicable to the GE141 ITAs as described in the Technical Evaluation documented by Reference 1 for GE14I in Section 16.4, and the GE14I Licensing Basis PCT remains below 2200 'F.

16.3 ECCS-LOCA Operating Limits The ECCS-LOCA MAPLHGR operating limits for the fuel bundles in this cycle are shown in the tables below.

Table 16.3-1 MAPLHGR Limits Bundle Type(s): GE14-P10CNAB400-9G6.0/6G4.0-10OT-150-T6-3176 (GE14C)

GE 14-P 1 CNAB400-14GZ- 1GOT- 150-T6-3006 (GE 14C)

GE14-P10CNAB402-12G6.0/2G4.0-1GOT-150-T6-3312 (GE14C)

GE14-P10CNAB405-6G6.0/11G4.0-100T-150-T6-3313 (GE14C)

GE14I-P10CCOB379-13GZ- 10OT- 150-T6-3309 (GE14L)

GE14-P1OCNAB402-5G6.0/14G4.0-10OT-150-T6-2758 (GE14C)

GE14-P10CNAB396-17GZ-1GOT-150-T6-3007 (GE14C)

GE 14-P10CNAB393-18G4.0-lOOT- 150-T6-2885 (GE14C)

GE14-P10CNAB405-15GZ-1GOT-150-T6-3009 (GE14C)

GE14-P10CNAB393-18GZ-100T-150-T6-2884 (GE14C)

GE 14-P10CNAB398-17GZ-100T- 150-T6-3008 (GE14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 16.00 14.51' 12.82 21.09 19.13 12.82 63.50 57.61

8.00 70.00 63.50 5.00 The single loop operation multiplier on LHGR and MAPLHGR, and the ECCS-LOCA analytical initial MCPR value, applicable to each fuel type in the new cycle core are shown in the table below.

Page 32

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Table 16.3-2 Initial MCPR and Single Loop Operation Multiplier on LHGR and MAPLHGR Single Loop Operation Fuel Type Initial MCPR Multiplier on LHGR and MAPLHGR GE14C 1.250 0. 80, GE14I 1.250 0.80 The ECCS-LOCA MAPLHGR limits bound a feedwater temperature reduction of 102 'F for both the GE14C and GE14I fuel types.

The GE14C 10CFR50.46 initial MCPR and single loop operation multiplier on LHGR and MAPLHGR are applicable to the GE141 ITAs as described in the Technical Evaluation documented by Reference 1 for GE141 in Section 16.4.

16.4 References The SAFER/GESTR-LOCA analysis base reports applicable to the new cycle core are listed below.

References for GE14C

1. SAFER/GESTR-LOCA Loss of Coolant Accident Analysis for Hope Creek Generating Station at Power Uprate NEDC-33172P, Revision 0, March 2005.

References for GE141

1. Safety Analysis Report to Support,Introduction of GE14i Isotope Test Assemblies (ITAs) in Hope Creek Generating Station, NEDC-33529P, Rev. 0, December 2009; and Errata and Addenda Number 1, June 10, 2010.

Page 33

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 60 [H]IH]E H[H]_r- ID

[HE] BHE]BH

[H* rHj [E] [H]

58 5*5*..rq*.El rEl O ] F OFE OFEaD~_] iffa]*** rWrEr *L* r]

E*r~*r~~~r 54 oABD[PEI PE ej e j L

~~[j []E-j EEA] [A][E]

EI] E 50 EJAEl jjI1 52 [ [ F[_A] EL][A] [D] [K] .[D]

G] E] [B]E"FC]a [BE [DE][GE [D ]E _EK D)) -LA

[L]EA]

M ]

46 WEtL K2 A 3*~F48 44 ~~FIIE [-[ IE E

- 2 [WIPF21[I M][dF]WEW E]OFEI EIFID[lE] W-E]WIW E] ]M WILE] ME FIF LeoF1-je ESEIIIFI 48 [ [H] [A][E]r5 rl] [B]' [D] [AE] G[A]rE Cl]EK] EA] [A]E] EC] _[A]PG--[A._FD]K [BEFLLD] [L] A [E]

34 BqF C Cl c I*j KGB]FI 2* FWO M EGI[ F+/-1F[ III[1[ ]E 38 *F rq*+ E]cE ]F E**L _1[

3

l [O] [AC))DL DC AD MG M MC DA K] EA] B [] E]IG] [A] ED rE0ElE M l0214EElE E]--J FE E~l

]El E *lrl FI* 0cW*EIME]rrE]M 2]

36 14 2l 6P Elfl[]

H ] [DA] F_2D] *_IFKJfi]G A

L[L] [K]LOA E_*_D GA F2]

A A EC] [A] [] [DK K

[D ][_IDF~* ][

AD BE B0 1E em

I.LA

]__* DD IID[ E ][ ! 0G

[E] FI C +]ED K F2]

FK fIlO]F+/-]

6~~~~[E Al AD K A FA EAll 22 tEItIF1 EllFGAD 1 3 5 7 9 111315 171921 23 25 27293133 35 3*7394143 4547 49 5153 5557 59 Fuel Type A=GE4-P0 ICNAB400-9G6.0/6G4.0- 0T-150-T6-3176 (Cycle 16) G=GE1 4-P1CNAB396-7GZ1 -1150-T6-3007 (Cycle 15)

B=GEI4-P10OCNAB400-14GZ-100OT-1 50-T6-3006 (Cycle 16) H=GE14-P10OCNAB393- 18G4.0- 100T-150-16-2885 (Cycle 14)

C=GE14-P10OCNAB402-12G6.0/2G4.0-1lO0T-1 50-T6-33 12 (Cycle 17) I=GE14-P 10CNAB405-15GZ-1l0OT-1 50-T6-3009 (Cycle 15)

D=GE14-P10CNAB405-6G6.0/ll1G4.0-100OT-1 50-T6-33 13 (Cycle 17) J=GEL4-P10OCNAB393-1 8GZ-100T-1 50-16-2884 (Cycle 14) 15)

E=GE4I-P10CCOB379-13GZ- l OT-1 50-T6-3309 (Cycle 17) K=GEl 4-P1CNAB398-17GZ-100T-150-T6-3008 (Cycle F=GE14-P10OCNAB402-5G6.0/t4G4.0-100OT-150-T6-2758 (Cycle 13) L=GE14-P10OCNAB400-14GZ-100OT-1I50-T6-3006 (Cycle 15)

Figure 1 Reference Core Loading Pattern Page 34

Hope Creek 0000-0105-6621-SRLR v ý U" I A1;A ID i,;

ý, a I

U1.

n AIN100.0 50.0 0.0 o.0 10.0 0.0 10.0 20.0 Tune (see) Twne (see) 150.0 10100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Tune (sec) Tune (sec)

Figure 2 Plant Response to FW Controller Failure (MOC ICF (HBB))

Page 35

Hope Creek 0000-0105-6621-SRLR pfln ei 1; Revision 0

-*- Dome Press Rise (psi)

--- SetyValveFlow Relief Valve Row s- Bypass Valve Row 20 00 Ga Ga 100.0+

0.0 3.0 6.0 0.0 3.0 6.0 Tine (Se) Time (see)

-a- Level(inch-REF-SEP-SKRT) x-*-Vessel Steam Row 200.0t 1.0

-s Turbine Steam Row s Feedwater Row

0 100.0 a 0.0 4,

(5 U

S-1.0

-IUU.U +

0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 3 Plant Response to Load Rejection w/o Bypass (MOC ICF (HBB))

Page 36

Hope Creek 0000-0105-6621-SRLR Revision 0 Reload 16 EJ U 00.0O o.o L-0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tr- (Se) a-- Level(inch-REF-SEP-SKRT)

-x- Vessel Steam Raw 200.0+ Turbine Steam Raw 1.0

-* Feedwater Flaw 100.0 o.o 0.0 04 IT4 - U

-inxnn 0.0 3.0 6.0 0.0 3.0 6.0 Time (se) Tuie (sec)

Figure 4 Plant Response to Turbine Trip w/o Bypass (MOC ICF (HBB))

Page 37

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 0.0 10.0 20.0 0.0 10.0 20.0 Ti- (se) Tur (se) 150.0 1.0

,0100.0 0.0 U

0 -1.0

-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Tuie (sec) Tune (se)

Figure 5 Plant Response to FW Controller Failure (EOC ICF (HBB))

Page 38

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 100.0 o0.0 0.0 3.0 6.0 0.0 3.0 6.0 Tume (sec) Trim (sec) e(inch-REF-SEP-SKRT) --- " ..

se! Steam Flow RetN.o binie Steam Flow 1.0 -A- ram Reatt dlater Flow 0.0-40 04 -1.0

-2.0 1 0.0 3.0 &0 0.0 3.0 6.0 Time (sec) Tune (sec)

Figure 6 Plant Response to Load Rejection w/o Bypass (EOC ICF (HBB))

Page 39

Hope Creek 0000-0105-6621-SRLR D 1 14 1I I 150.0 100.0 N

'N 50.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) T'- (S-)

200.0 1.0 S0.0 06 41 0.0 -9 -1.0o

-2.0 0.0 3.0 6.0 0,0 3.0 6.0 Time (Sec) Tune (sec)

Figure 7 Plant Response to Turbine Trip w/o Bypass (EOC ICF (HBB))

Page 40

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 200.0 100.0 0.0 10.0 0.0 10.0 20.0 Tome (sec) Tune (sec) 150.0

.0100.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tume (sec)

Figure 8 Plant Response to FW Controller Failure (EOC ICF (UB))

Page 41

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 150.0 300.0 100.0 200.0 U U 100.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (se") Tmw (se) 1.0 100.0 0.0 U- 0

-1.0

-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (seM)

Figure 9 Plant Response to Load Rejection w/o Bypass (EOC ICF (UB))

Page 42

Hope Creek 0000-0105-6621-SRLR D1,lAm"4QAiwftVOLJA~

1 A, RPairknn n "U

U 100.0 0.0 -E 0.0 3.0 6.0 0.0 3.0 6.0 Tune (Sec) T*me (sec)

'4 6

U 6

0 6.

2C U

U 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tnne (sec)

Figure 10 Plant Response to Turbine Trip w/o Bypass (EOC ICF (UB))

Page 43

Hope Creek 0000-0105-6621 -SRLR IAlnýA 1A, PQpiAQnn n 4, 4, 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) T7ne (sec) i I

-e- Void ReactMt Doppler Reacti 150.0 1.0 - Scram Reactivity Total Reactivity 4'

100.0 04 0.0 R Q 4- E Cg

0. U=

U 50.0

-1.0 +

0U0 10.0 20.0 0.0 10,0 20.0 Tum (sec) Tmne (sec)

Figure 11 Plant Response to FW Controller Failure (EOC MELLLA (UB))

Page 44

Hope Creek 0000-0105-6621 -SRLR D,*1 1A 1i, L',,,,fl~~at.

D a A

U 11lfJ~

'6 100.0-0.0 0.0 3.0 6. 0 0.0 3.0 6.0 Time (sec) Time (Sec)

-a- LeveI(inch-REF-SEP-SKRT)

-o Vessel Steam Row 200.0- -,- Turbine Steam Raw 1.0 sFeedwer Flow 60.0 PO 100.0 U.U + a I A - a -1.0

-IAJ.U F -2.0 0.0 3aO 6.0 0.0 3.0 6.0 Time (sec) Tmle (sec)

Figure 12 Plant Response to Load Rejection w/o Bypass (EOC MELLLA (UB))

Page 45

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 U

100.0 0.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) T e (Sec)

'4 U

100.0 0 Ul a

0

'4 0.0 3.0 6.0 0.0 3.0 6.0 Tine (sec) Tune (sec)

Figure 13 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA (UB))

Page 46

Hope Creek 0000-0105-6621-SRLR Rel1oad 16 Revision 0 4,

0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tim (sec) Tme (sec)

I, 2

0 44 4,

0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tune (sec) TuMe (sec)

Figure 14 Plant Response to FW Controller Failure (MOC ICF & FWTR (HBB))

Page 47

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 300.0 200.0

-e- Dome Press Rise (psi) afetyVaWv

Relief Valve Flow Flow 250.0 -- Bypass Valve Raw 150.0 200.0 150.0 100.0 100.0 50.0 50.0 0'

0.0 0.0 .9".- a ý MM 4 K -1 0 1 ! 0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tine (sec) Time (sec) 150.0 1.0 a

,100.0 ta. 0.0 U

50.0 C4 -1.0 0U0 -2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 T'mne (sec) Tm- (sec)

Figure 15 Plant Response to FW Controller Failure (EOC ICF & FWTR (HBB))

Page 48

Hope Creek 0000-0105-6621-SRLR R~lnnA 1fi Revision 0 Reload 16 300.0 250.0 150.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tme (sec) 150.0 10100.0 50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tmre (see)

Figure 16 Plant Response to FW Controller Failure (EOC ICF & FWTR (UB))

Page 49

Hope Creek 0000-0105-6621 -SRLR Relnad 1tf Revision 0 Reload 16 200.0 150.0 U

100.0 50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Ti-e (sec) 150.0- 1.0

,0100.0- 0.0 0

51.0 * -1.0 0.0 -2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0

'Tie (sec) Tnme (sec)

Figure 17 Plant Response to FW Controller Failure (EOC MELLLA & FWTR (UB))

Page 50

Hope Creek 0000-0105-6621-SRLR Rpilnnd 1A Revision 0 200.0 100.0 0.0 10.0 20.0 0.0 10.0 20.0 Tume (Sec) Tune (sec) 150.0 a

4..

'1 100.0 a 0

a 0

U U

0.0 10.0 20.0 0.0 10.0 20.0 Tune (sec) TMme (se)

Figure 18 Plant Response to FW Controller Failure (MOC ICF with RPTOOS (HBB))

Page 51

Hope Creek 0000-0105-6621-SRLR RPlArl hfq Revision 0 R-InnA It; 150.0 100.0 P0 50.0 100.0 0.0 E3 1-0.0 -- -- -

0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tmre (sec)

,eI(inch-REF-SEP-SKRT) Void eactvty ssel Steam Raw Dopp4) Reactmty 200.0 tbine Steam Fow 1.0 - Scram ReactMty

,dwater Flow Total R tity 100.0 0

U 0.0 -1.0

-100.0 -2.0 1 0.0 3.0 6.0 0.0 3.0 6.0 Time (WC) Tune (sec)

Figure 19 Plant Response to Load Rejection w/o Bypass (MOC ICF with RPTOOS (HBB))

Page 52

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 300.0 E-- Dome Press Rise (psi)

Safety Valve Flow

- Relief Valve Bypass Valve Raw 200.0t B

100.0 1-0.0 3.0 6.0 0.0 3.0 6.0 Timn (sec) Tune (se) 1.0 0,

S-1.01 0.0 3.0 6.0 0.0 3.0 6.0 Timn (sec) T'n (se)

Figure 20 Plant Response to Turbine Trip w/o Bypass (MOC ICF with RPTOOS (HBB))

Page 53

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 N

0.0 10.0 20.0 0,0 10.0 20.0 Time (See) Tume (see) 150.0 100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Tine (se) Trine (see)

Figure 21 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (HBB))

Page 54

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0

-300.0

-*- Dome Press Rise (psi)

SafetyVave Flow

Relief Valve Flow

--- Bypass Valve Row 200.0 9

9

'N 100.0 0.0 -8 0.0 3.0 6.0 0.00 3.0 6.0 TMm (sec) Tune (sec) 64 a

9 100.0 a

C C

U U

9 9

0.0 3.0 6.0 0.0 3.0 6.0 Time (see) Tune (see)

Figure 22 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (HBB))

Page 55

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 150.0 100.0 N

50.0 100.0 0.0 -0.0 --

0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tme (see) to 100.0 1.0 Ul U

-2.0 0.0 3.0 6.0 0.0 10 6.0 Time (sec) T-me (see)

Figure 23 Plant Response to Turbine Trip w/o Bypass (EOC ICF with RPTOOS (HBB))

Page 56

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 200.0 19100.0 0.0 10.0 20.0 0.0 10.0 20.0 Tum (sec) Tim (see) 150.0 10100.0 0.0 10.0 20.0 0.0 10.0 20.0 Tum (sec) TYme (see)

Figure 24 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (UB))

Page 57

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 100.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Tine (sec) Tune (sec)

/el(inch-REF-SEP-SKRT) wVodid Mty sse Steam Raw Rteactd bine Steam Row 1.0 - Scram Reactivity xdwater Row a Total R tMty g o.o*

100.0 U= 0.

U

-1.0

-2.0 0.0 3.0 60 0.0 3.0 6.0 Tine (sec) TIne (sec)

Figure 25 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (UB))

Page 58

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 150.0

-E- Dome Press Rise (psi)

Safety Valve Flow

- Relief Vae Raow

- Bypass Vale Row 100.0 200.0}

PC 100.0 +

0.0 3.0 6.0 0.0 3.0 6.0 Thm (sec) Tune (sec) 1.0 4) 100.0- 0.0 0

44 -. 0 0.0 3.0 6.0 0.0 3.0 6.0 Tite sec) Tun (sec)

Figure 26 Plant Response to Turbine Trip w/o Bypass (EOC ICF with RPTOOS (UB))

Page 59

Hope Creek 0000-0105-6621-SRLR RPlnMI 16 Revision 0 Reload 16 PC 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 100.0 50.0-0.0 10.0 20.0 0.0 10.0 20.0 Tune (Sec) T'me (s)

Figure 27 Plant Response to FW Controller Failure (EOC MELLLA with RPTOOS (UB))

Page 60

Hope Creek 0000-0105-6621-SRLR Relnnrl 16 Reviqinn 0 Reload 16 150.0 100.0 50.0 100.0 0.0 1 3 0.0 --L M0 0.0 3.0 6.0 0.0 3.0 6.0 "fne (Sec) 'Tr- (se) el(inch-REF-SEP-SKRT) Void Mty

,sel Steam Flw React'l MyO 200.0 Scraf extjvtty tine SteamFlow 1.0 a 3d~ater Flow, Total 100.0 0 0.0 8

0.0 -1.0

-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tu (sec)

Figure 28 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with RPTOOS (UB))

Page 61

Hope Creek 0000-0105-6621-SRLR RPna~d 16~

Revision 0 Reload 16 150.0 100.0 "0 Uo 50.0 0.0 3.0 6 .0 0.0 3.0 6.0 Time (see) Trune (se) 200.01

-E- Level(inch-REF-SEP-SKRT)

-*- Vessel Steam Flow

°to

-*- Turbine Steam Flow Feedwater Flow 1.0 U

6 100.0-

-0.

U 0o1.0

-2ot I

0.0 3.0 6.0 0.0 3.0 6.0 Time (sc) T,,e (see)

Figure 29 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA with RPTOOS (UB))

Page 62

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 150 Tim (sec) TMun (Se) 150.0-0100.0.

50.0-0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tume (sec) Tim (sec)

Figure 30 Plant Response to FW Controller Failure (MOC ICF & FWTR with RPTOOS (HBB))

Page 63

Hope Creek 0000-0105-6621-SRLR Revision 0 Reload 16 300.0 250.0 200.0 10150.0 100.0 50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tine (se) Tmne (sec) 150.0

£4 100.0 0 0

U 4,

50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tire (se) T-ne (se)

Figure 31 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (HBB))

Page 64

Hope Creek 0000-0105-6621-SRLR RPJla~d 16 Revision 0 Reload 16 U

0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) TLmr(sec) 100.0 QI 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tum (sec)

Figure 32 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (UB))

Page 65

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 150.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tune (sec) 150.0-100.0 C a

0 U

50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sem) T'rne (see)

Figure 33 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (UB))

Page 66

Hope Creek 0000-0105-6621-SRLR 1pAxlcinn 1)

ý m" 250.0 200.0 150.0 100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Tim (sec) Tim (sec) 0.0 10.0 20.0 0,0 10.0 20.0 Tim (sec) Trum (sec)

Figure 34 Plant Response to FW Controller Failure (MOC MELLLA (HBB))

Page 67

Hope Creek 0000-0105-6621-SRLR PPna1A~ uS Revision 0 R-Innd loý

-*-*- Dome Safety Press Rise (psi)

Valve Flow

-- Relief Valve Flow s Bypass Valve Flow 200.0 100.0 4-0.0 3.0 6. 0 0.0 3.0 6.0 Time (sec) T'- (S-)

-a- Level(inch-REF-SEP-SKRT)

-x-- Vessel Steam Row 200.01 1.0

- Turbine Steam Row s Feedwater Flow C 0.0 100.0-U 6

UU- P4 -1.U n ui n, ' ,, ,.

0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Trme (sec)

Figure 35 Plant Response to Load Rejection w/o Bypass (MOC MELLLA (HBB))

Page 68

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 150.0 300.0 100.0 200.0

,U ,U 100.0 0.0 0.0 3.0 6 *.0 0.0 3.0 6.0 Tnne (Sec) Tun (sec)

-a-- Level(inch-REF-SEP-SKRT)

-)-- Vessel Steam Flow 200.0 -s- Turbine Steam Row 1.0

-- Feedwat Flow U 100.0 0.0 N.

A*

nn4. il 0 -1.0

-1(](I.(

I i i 0.0 3.0 6.0 0.0 3.0 6.0 Time (See) Tuie (sec)

Figure 36 Plant Response to Turbine Trip w/o Bypass (MOC MELLLA (HBB))

Page 69

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tum (sec)

-*-- Void ReactMty

DopplerReactMity ReactMty 150.0- 1.04

Scram Total Reactmty tI j 10I00.0 0.0 U

50.0 -1.0 0.0 -2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (se) Time (sec)

Figure 37 Plant Response to FW Controller Failure (EOC MELLLA (HBB))

Page 70

Hope Creek 0000-0105-6621-SRLR R Pla~d 16q I Revikion 0 Reload 16 150.0 100.0 50.0 100.0 0.0 B- 0.0o 0.0 3.0 6.,0 0.0 3.0 6.0 Tmne (sec) Tune (sec)

-e- Level(inch-REF-SEP-SKRT) x-- Vessel Steam Raw 200.04 -- s Turbine Steam Row 1.0

-- Feedwater Flow S0.0 U

U.U == ; ,* == S-1.0

-1u0.1] + 0.

0.0 60 0.0 3.0 6.0 3.0 6 Time (sec) Tum (sec)

Figure 38 Plant Response to Load Rejection w/o Bypass (EOC MELLLA (HBB))

Page 71

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 M

100.0

-E 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tune (sec) a-- Level(inch-REF-SEP-SKRT)

Vessel Steam Row 200.0+ - Turbine Steam Row 1.0 s Feedwater FRow Q

'B 100.0 0.0 04 S U.U .+- I .4 =-

v-v

-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tire (sec)

Figure 39 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA (HBB))

Page 72

Hope Creek 0000-0105-6621 -SRLR 1Dl-,* 1A RPvivinn A*

R-vi-zi-n 0 200.0 150.0 100.0 50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tume (sec) Tune (Sec)

Void Reac 1.0 Scram Reactivity

-.- Total Reactivty

'4 0.0 U

0 -1.0

-2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tune (Se) Tine (sec)

Figure 40 Plant Response to FW Controller Failure (MOC MELLLA & FWTR (HBB))

Page 73

Hope Creek 0000-0105-6621-SRLR R~lnacl 1f Revision 0 Reload 16

-a- r'&on Rux/ 10

-& Co

-x-Inlet Seat CoreSurface Flow Rux 250.0 4 s- Core inlet Subcooling 200.0 4 d

14150.0 100.0 50.04 I I"I ] [] -

^^

U.U01 I I i 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) T'ur (sec) 150.0

,0100.0 0 a

0 U

a 4.)

50.0 0.0 00 5.0 10.0 15.0 0.0 5.0 10.0 15.0 T* e (se) Tine (see)

Figure 41 Plant Response to FW Controller Failure (EOC MELLLA & FWTR (HBB))

Page 74

Hope Creek 0000-0105-6621-SRLR R~lnad 1~~

Revision 0 Reload 16 0.0 10.0 20.0 0.0 10.0 20.0 Titm (see) Time (see) 150.0-

"0100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Tiue (se") TiW (see)

Figure 42 Plant Response to FW Controller Failure (MOC MELLLA with RPTOOS (HBB))

Page 75

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 0.0 3.0 6.0 0.0 3.0 6.0 Ti- (sec) T- (sec) 200.0 6

U 100.0 6 0

a 0

U U

0.0

-100.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (seC) Tlme (sec)

Figure 43 Plant Response to-Load Rejection w/o Bypass (MOC MELLLA with RPTOOS (HBB))

Page 76

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 "U

0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) T , (se,)

U C

04l 2

0 U

C.?

U 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) I"- (sec)

Figure 44 Plant Response to Turbine Trip w/o Bypass (MOC MELLLA with RPTOOS (HBB))

Page 77

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 250.0 2*0.0 150.0 100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tine (see) 150.0 10100.0 U

50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (Sec) T'mE (see)

Figure 45 Plant Response to FW Controller Failure (EOC MELLLA with RPTOOS (HBB))

Page 78

Hope Creek 0000-0105-6621-SRLR RAlnnrl lA Revision 0 300.0 200.0 U

100.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Tmr (sec) Time (sec) 1.0 100.0 0.0

-1.0

-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 46 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with RPTOOS (HBB))

Page 79

Hope Creek 0000-0105-6621-SRLR P*Pnnei 11f Revision 0 150.0 100.0 5 .

50.0 100.0 0.0 o0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Thne (sec) 200.0 1.0 100.0 @ 0.0 430 0.0 C4 -1.0-

-100.0 -2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (See) Time (see)

Figure 47 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA with RPTOOS (HBB))

Page 80

Hope Creek 0000-0105-6621-SRLR R~1nad 1i Revision 0 Reload 16 300.0 250.0 200.0 4 150.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.O Time (sec) Trnu (s) 150.0 U

'0 100.0 0 2

U U

0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (am) Tine (sec)

Figure 48 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with RPTOOS (HBB))

Page 81

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 300.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Time (sec) 150.0 10100.0 50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tir- (S-) Tine (sec)

Figure 49 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (HBB))

Page 82

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 100.0 8.0 0.0 0.0 4.0 8.0 0.0 4.0 8.0 Tume (sec) T-me (sec) a a

0 2

U 0.0 4.0 &0 0.0 4.0 8.0 Time (sec) Tmr (sec)

Figure 50 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)

Page 83

Hope Creek 0000-0105-6621-SRLR

]?.,lnA 1 A, 1'nrc*.- nn 100.0

.. .. ... . 0.0 E 0.0 4.0 8.0 0.0 4.0 8.0 Time (sec) Tum (sec)

- Level(inch-REF-SEP-SKRT) -- a Void ReactMty x* Vessel Steam, Flo .0-Dppe

-t-- Turbine Steam Raww" Scm R

-.- Feessater Flow [A 110.0 Q

04 -1.0

-2.0 0.0 4.0 8.0 0.0 4.0 8.0 Time (see) Time (see)

Figure 51 Plant Response to MSIV Closure (Flux Scram) - MELLLA (HBB)

Page 84

Hope Creek 0000-0105-6621-SRLR Re~lnna 1ft Revision 0 Reload 16 110.00 e Natural Circulation Line a Extended Operating Domain 100.00 BSP Scram Region Boundary I I

---I-- BSPControlled Entry Region Boundary ,

90.00 80.00 I I II" I 70.00 OR 60.00 - - - - I 0 I IF I

0.

II I 4FI

.. L - - -..- II- I I - - - - - -I j I

50.00 -I I I I F FI

- - - .[ - - -

E) 40.00 30.00 i F F I-F I III I F / I 20.00 I L I 10.00 0.00 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (0/4 Figure 52 BSP Region Boundaries for Normal Feedwater Temperature Operation Page 85

Hope Creek 0000-0105-662 1-SRLR Reload 16 Revision 0 Appendix A Analysis Conditions The reactor operating conditions used in the reload licensing analysis for this plant and cycle are presented in Table A-1. The pressure relief and safety valve configuration for this plant are presented in Table A-2. Additionally, the operating flexibility options listed in Section 8 are supported by the reload licensing analysis.

Table A-1 Reactor Operating Conditions Analysis Value Parameter ICF LCF ICF LCF NFWT NFWT RFWT RFWT Thermal power, MWt 3840.0 3840.0 3840.0 3840.0 Core flow, Mlb/hr 105.0 94.8 105.0 94.8 Reactor pressure (core mid-plane), psia 1036.0 1034.0 1013.4 1011.6 Inlet enthalpy, Btu/lb 526.3 523.8 511.0 507.3 Non-fuel power fraction 0.036 0.036 0.036 0.036 Steam flow, Mlb/hr 16.80 16.78 14.75 14.73 Dome pressure, psig 1005.0 1005.0 983.6 983.6 Turbine pressure, psig 945.8 945.9 937.3 937.4 Table A-2 Pressure Relief and Safety Valve Configuration Number of Lowest Setpoint Valve Type Valves (psig)

Safety/Relief Valve 14 1141.2 Page 86

Hope Creek 0000-0105-6621 -SRLR R~lnnct 1~ Revision 0 Reload 16 Appendix B Thermal-Mechanical Compliance A thermal-mechanical compliance check is performed for all analyzed transients to assure that the fuel will operate without violating the thermal-mechanical design limits. These limits are designed such that reactor operation within these limits provides assurance that the fuel will not exceed any thermal-mechanical design or licensing limits during all modes of operation. The fuel thermal-mechanical limits are met for the current cycle.

Page 87

Hope Creek 0000-0105-6621-SRLR R~~1nnd 1I Revision 0 Reload 16 Appendix C Decrease in Core Coolant Temperature Event The Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is consistent with the approved methodology. The transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, those items are not included in this document. The OLMCPR result is shown in Section 11.

In addition, the Inadvertent HPCI start-up event was determined to be non-limiting.

Page 88

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Appendix D Off-Rated Limits Off-Rated Power Dependent Limits The cycle-independent power dependent limits are documented in Reference D-1. The power dependent limits provided in Reference D-1 have been validated for this cycle. Above Pbypass (24% rated power),

the power dependent limits consist of Kp and LHGRFACp multipliers. The Kp and LHGRFACp multipliers are applied as follows:

Operating Limit MCPRp = Kp

Operating Limit MCPR(100%P)

LHGRp = LHGRFACp

LHGRstd Analyses performed in support of Reference D-1 confirmed that the Kp and LHGRFACp multipliers bound the range between Pbypass and the PLU enabling power level. No thermal limits are requiredfor below Pbypass.

Kp Limits for: Equipment In Service Limits for Power>24.0%

Power (%) Limit, Kp 24.0 1.561 45.0 1.280 60.0 1.150 100.0 1.000 Kp Limits for: RPTOOS Limits for Power Ž24.0%

Power (%) Limit, Kp 24.0 1.561 45.0 1.280 60.0 1.150 100.0 1.000 LHGRFACp Limits for: Equipment In Service Limits for Power >24.0%

Power (%) Limit 24.0 0.603 100.0 1.000 Page 89

Hope Creek 0000-0105-6621-SRLR Reload 16, Revision 0 LHGRFACp Limits for: RPTOOS Limits for Power > 24.0%

I "Power 24.0()Limit 0.603 100.0 1.000 Off-Rated Flow Dependent Limits The cycle-independent flow dependent limits are documented in Reference D-1. The flow dependent limits provided in Reference D-1 have been validated for this cycle. The flow dependent limits consist of an absolute MCPRf limit and LHGRFACf multiplier.

The MCPRf limits provided in Reference D-1 are based on a SLMCPR of 1.07; therefore, the MCPRf limits are adjusted for the cycle-specific SLMCPR in Section 11. The MCPRf limits do not include the

+0.01 OLMCPR adder (extended operating domain licensing commitments) because the existing off-rated limits are confirmed to be sufficiently conservative.

MCPRf Limits for:

Equipment In Service Limits for a Maximum Runout Flow of 109.0%

Flow (%) Limit

..... MCPRf

.30.0 '1.55 89.2. 1.20 109.0 1.20 MCPRf Limits for:

RPTOOS Limits for a Maximum Runout Flow of 109.0% ....

Flow (%) Limit

__ MCPRf 30.0 1 1.55 89.2 . 1.20 109.0 - 1.20 LHGRFACf Limits for:

Equipment In Service Limits for a Maximum Runout Flow of 109.0% . ....

Flow (%) . Limit 30.0 , 0.500 50.0 . 0.782 82.2 t 1.000 109.0 1 1.000 Page 90

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 LHGRFACf Limits for:

RPTOOS Limits for a Maximum Runout Flow of 109.0%

Flow (%) Limit 30.0 0.500 50.0 0.782 82.2 1.000 109.0 1.000 References for Appendix D D-1 Fuel Transition Report for Hope Creek Generating Station, NEDC-33158P, Supplement 1, Revision 1, April 2005.

Page 91

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Appendix E Scram Speed Licensing Basis Hope Creek Generating Station plans to implement the Technical Specification Improvement Program (TSIP) Option A scram speed in Cycle 17. The reload transient analyses. provided in this report support both the 67B and TSIP scram'speeds.

Page 92

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Appendix F Feedwater Temperature and Operating Dome Pressure Range The reload transient analyses provided in this report are performed using a FFWTR/FWHOOS of 102 0F/60 0 F. FFWTR/FWHOOS of 102 0F/60'F is not currently licensed for Hope Creek Generating, Station and shall not be implemented until licensed. The reload transient, analyses do, not by themselves, allow plant operation with FFWTR/FWHOOS of 102°F/60 0F.

The reload transient analyses performed with a FFWTR/FWHOOS of 102 0F/60*F bound normal operational variation in feedwater heating capacity such that the feedwater temperature is at least 409°F at 100% rated power.

Normal operational variation in dome pressure (defined as +/-10 psi) is acceptable as this variation has a negligible effect on the OLMCPR.

Page 93

Hope Creek 0000-0105-6621-SRLR Relnaid 16 Revision 0 Reload 16 Appendix G NEDC-33173P-A Supplementary Information The safety evaluation for licensing topical report NEDC-33173P-A (Applicability of GE Methods to Expanded Operating Domains) concluded that the application of GE methods to expanded operating domains was acceptable subject to certain limitations and conditions. Several of these conditions request that additional, application-specific information: be provided. The information provided below responds to these requests for the identified items.

Limitation/Condition 6 (R-factor)

The plant specific R-factor calculation at a bundle level was performed consistent with lattice axial void conditions expected for the hot channel operating state applicable to this cycle of operation. For Hope Creek Cycle 17 at the EPU licensed power level, a 60% void profile was used for the calculation of bundle R-factors.

Limitations/Conditions 10 and 11 (Thermal/Mechanical Overpower)

As required by Limitation 10 the plant limiting Thermal and Mechanical Overpower results are provided in Table G-1. The results are summarized as a percent margin to both of these limits.

Table G-1 Margin to Thermal Overpower and Mechanical Overpower Limits Criteria GE14C Thermal Overpower Margin 39%

Mechanical Overpower Margin 39%

These results have been confirmed to meet the required 10% margin to the design limits for all fuel types as can be observed.

Limitation/Condition 17 (Steady State 5 Percent Bypass Voiding)

The bypass voiding condition was evaluated for the licensed core loading and confirmed that the bypass void fraction remained below 5 percent at all LPRM levels when operating at steady-state conditions within the licensed upper boundary. For a power/flow condition that conservatively bounded the licensed power/flow upper boundary, the bypass void fraction at the D level LPRM location was calculated to be 0.0%.

Page 94

Hope Creek 0000-0105-6621-SRLR R1o~lnad 1tq Reviqinn 0 Reload 16 Appendix H Reduced Feedwater Temperature BSP Regions The endpoints of the BSP regions for Reduced Feedwater Temperature operation are defined in Tables H-1 and H-2. Per PSEG's request, FFWTR BSP region boundaries are based on 343.6°F, which is 88°F reduction from the rated feedwater temperature 431.6°F. The region boundaries, shown in Figures H-1 and H-2, are defined using the Modified Shape Function (MSF). See Reference H-1.

Table H-1 BSP Region Intercepts for FWHOOS (Feedwater Temperature above 371.6°F )

Highest Region Boundary Power Flow Core Channel Intercept (%) (%) DR DR Al 64.7 47.9 0.800 0.416 B1 43.4 35.3 0.799 0.422 A2 71.5 56.5 0.799 0.374 B2 32.2 36.3 < 0.790 < 0.391 Table H-2 BSP Region Intercepts for FFWTR (Feedwater Temperature above 343.6°F)

Region Boundary Power Flow Core Highest Intercept (%) (%) DR DR Al 70.2 54.7 0.800 0.390 B1 41.0 35.6 0.800 0.375 A2 73.6 59.0 0.798 0.403 B2 32.2 36.3 < 0.772 < 0.395 Page 95

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 110.00

--- Natural Circulation Line 6 Extended Operating Domain 100.00 BSP Scram Region Boundary

-+-- BSP Controlled Entry Region Boundary 90.00 +

80.00 -b I I I I I I

- -I -

70.00 +

S I I Al A 0 60.00 +

I I 0.

III 50.00 -

CL I I I I - - -- - - - - - -J 40.00 ----------- --

30.00 -

20.00 10.00 -~-.~-4 I I I I 0n00 J [ . . . . I . . . . .

p . . . . - . . I . - . I 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (0/4 Figure H-I BSP Region Boundaries for FWHOOS Operation Page 96

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 110.00

--- Natural Circulation Une Domain , ,

6 Extended Operating 100.00

BSP Scram Region EBoundary '

BSP Controlled Entry Region Boundary 90.00 L" -

II I 80.00 I I I I iiiiii F 70.00

I . . i- --. . . . . .- .- .- .- -- - - - -- - I - -- - -]-

-I i I i 60.00 I If I I 0

0.

50.00 I F F F

-I I i F F F F I F

BI 40.00 10 2,0 4F 50..60 F

70 F .80 F 90_ 10 F

-I--

I 11F II

.. ..-... ..... I-30.00 20.00 10.00 0.00 . i . I I I I I I I:

0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (0/)

Figure H-2 BSP Region Boundaries for FFWTR Operation References for Appendix H H- 1. ODYSY Applicationfor Stability Licensing CalculationsIncluding Option I-D and II Long Term Solutions, NEDE-33213P-A, Revision 0, GE Hitachi Nuclear Energy (Proprietary), April 2009.

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Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Appendix I Calculated BSP Region End Points The BSP region end points reported in Section 15 represent the proposed BSP region. The proposed BSP region is conservative and bounds the calculated BSP region end points.

To support the initial introduction of GE141 Isotope Test Assemblies (ITAs), this appendix provides the calculated BSP region end points and decay ratios. These calculated power/flow points and decay ratios represent typical calculations for Hope Creek. The plant- and cycle-specific calculations provide reasonable assurance that the thermal hydraulic stability as prescribed by Option III with respect to the size of the BSP regions is maintained with ITAs in the Hope Creek core.

Table I-1 BSP Region Calculated Intercepts for Normal Feedwater Temperature Highest Region Boundary Power Flow Core Channel Intercept (%) (%) DR D DR Al 58.1 39.9 0.799 0.437 BI 47.7 34.6 0.798 0.447 A2 66.1 49.7 0.799 0.404 B2 39.2 35.7 0.790 0.391 Page 98

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Appendix J GEl41 Fuel Introduction Reference J-1 provided the results of the cycle-independent evaluations supporting the introduction of GE14i fuel in subject plant. These GE14I bundles, also referred to as GE14I Isotope Test Assemblies (ITAs), were designed for mechanical, nuclear and thermal-hydraulic compatibility with the GE14C fuel designs. The subject core was designed such that the ITAs would be placed in non-limiting locations with respect to thermal limit margins and shutdown margins. The analysis results reported in this report are applicable to GE14I unless otherwise specified. Section 11 of this report presents the GE14C cycle-dependent MCPR limits; an adder of 0.07 should be applied to these results for the GE141 ITAs.

References for Appendix J J-1. Safety Analysis Report to Support Introduction of GE14i Isotope Test Assemblies (ITAs) .in Hope Creek Generating Station, NEDC-33529P, Revision 0, GE Hitachi Nuclear Energy (Proprietary),

December 2009; and Errataand Addenda Number 1, June 10, 2010.

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Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Appendix K List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 2PT Two Recirculation Pump Trip ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service AOO ; Anticipated Operational Occurrence APRM Average Power Range Monitor ARTS APRM, Rod Block and Technical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection Btu British thermal unit BWROG Boiling Water Reactor Owners Group COLR' Core Operating Limits Report CPR Critical Power Ratio DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System ELLLA Extended Load Line Limit Analysis EOC End of Cycle (including all planned cycle extensions)

EOR End of Rated (All Rods Out 100%Power / 100%Flow / NFWT)

EPU Extended Power Uprate ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FWCF Feedwater Controller Failure FWHOOS Feedwater Heaters Out of Service FWTR Feedwater Temperature Reduction GDC General Design Criterion GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF Generic Shape Function HAL Haling Burn HBB Hard Bottom Burn HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection ICA Interim Corrective Action Page 100

Hope Creek 0000-0105-6621 -SRLR Reload 16 Revision 0 Acronym Description ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix Kf Off-rated flow dependent OLMCPR multiplier Kp Off-rated power dependent QLMCPR multiplier L L8 Turbine Trip on high water level (Level 8)

LCF Low Core Flow LHGR Linear Heat Generation Rate -

LHGRFACf Off-rated flow dependent LHGR multiplier LHGRFACp Off-rated power dependent LHGR multiplier.

LOCA Loss of Coolant Accident LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPFACf Off-rated flow dependent MAPLHGR multiplier MAPFACp Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRf Off-rated flow dependent OLMCPR MCPRp Off-rated power dependent OLMCPR.

MELLLA Maximum Extended Load Line Limit Analysis, MELLLA+ MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MSR Moisture Separator Reheater MSROOS Moisture Separator Reheater Out of Service MTU Metric Ton Uranium MWd Megawatt day MWd/ST Megawatt days per Standard Ton MWd/MT Megawatt days per.Metric Ton MWt Megawatt Thermal N/A Not Applicable NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature' NOM Nominal Burn NTR Normal Trip Reference OLMCPR Operating Limit MCPR :.

OOS Out of Service OPRM Oscillation Power Range Monitor Pbypass Reactor power level belowwhich the TSV position and the TCV fast closure scrams are bypassed Page 101

Hope Creek 0000-0105-6621-SRLR Reload 16 Revision 0 Acronym Description Pdome Peak Dome Pressure PsI Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PHE Peak Hot Excess PLHGR PeakLinear Heat Generation Rate PLU Power Load Unbalance PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Downscale PROOS Pressure Regulator Out of Service Q/A Heat Flux RBM Rod Block Monitor RC Reference Cycle RCF Rated Core Flow RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RV Relief Valve RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cycle SL Safety Limit SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report S/RV Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Steady State SSV Spring Safety Valve STU Short Tons (or Standard Tons) of Uranium TBV Turbine Bypass Valve, TBVOOS Turbine Bypass Valves Out'of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Reference Function; TSIP Technical Specifications Improvement Program TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service TT Turbine Trip TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Bum Page 102

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