LR-N08-0100, Transmittal of Supplement Reload Licensing Report,
| ML081330014 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/02/2008 |
| From: | Keenan J Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N08-0100 0000-0078-1947-SRLR, rev 2 | |
| Download: ML081330014 (105) | |
Text
PSEG Nuclear LLC RO. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG NuclearL.L. C.
LR-N08-0100 May 02, 2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Supplemental Reload Licensing Report This letter provides the Supplemental Reload Licensing Report (SRLR) for Hope Creek Generating Station (HCGS) Cycle 15 extended power uprate (EPU) operation. The SRLR includes the results of the HCGS cycle-specific core analyses, and of the transient and accident analyses performed for the actual core design and for the current operating cycle at EPU conditions. HCGS will begin EPU operation after approval of the license amendment request currently under NRC review.
Results of other confirmatory analyses for HCGS cycle 15 EPU operation not contained in the SRLR are available for review in PSEG Nuclear's offices.
Should you have any questions regarding this transmittal, please contact Mr. Paul Duke at 856-339-1466.
Sincerely, Jeff eKee-an Manager - Licensing Attachment 0000-0078-1947-SRLR, Revision 2, Supplemental Reload Licensing Report for Hope Creek Unit 1, Reload 14 Cycle 15 EPU
LR-N08-01 00 May 2, 2008 Page 2 cc: S. Collins, Regional Administrator - NRC Region I J. Lamb, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE
Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 0000-0078-1947-SRLR Revision 2 Class I April 2008 Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 14 Cycle 15 EPU
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 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.
The results provided in this report incorporate the additional information and restrictions imposed by the final Safety Evaluation report for NEDC733173P, Applicability of GE Methods to Expanded Operating Domains.
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HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 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 Bill Cline. This document has been verified by Lynn Leatherwood.
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HOPE CREEK 0000-0078-1947-SRLR Relnaid 14 Revision 2 The basis for this report is General Electric StandardApplication for Reactor Fuel, NEDE-240 11-P-A-15, September 2005; and the U.S. Supplement, NEDE-2401 1-P-A-15-US, September 2005.
- 1. Plant-unique Items Appendix A: Analysis Conditions Appendix B: Decrease In Core Coolant Temperature Events Appendix C: ARTS Power and Flow Dependent Limits Appendix D: Option B Licensing Basis Appendix E: Reactor Recirculation Pump Seizure Event Appendix F: Feedwater Temperature Reduction Appendix G: NEDC-33173P Safety Evaluation - Supplementary Information Requirements Appendix H: List of Acronyms
- 2. Reload Fuel Bundles1 FuelType Cycle Number Loaded Irradiated:
SVEA96-P IOCASB360-12GZ-568U-4WR- 150-T6-2656 (SV96P) 11 1 SVEA96-PIOCASB360-12G5.0-568U-4WR-150-T6-2657 (SV96P) 11 3 SVEA96-P IOCASB361-14GZ-568U-4WR- I50-T6-2658 (SV96P) 12 148 SVEA96-P 1OCASB360-12G5.5/2G2.5-568U-4WR- 150-T6-2659 (SV96P) 12 64 GE] 4-P 1OCNAB402-4G6.0/16G4.0-1OOT- 150-T6-2757 (GE 14C) 13 56 GE 14-P 1OCNAB402-5G6.0/14G4.0-1OOT- 150-T6-2758 (GE 14C) 13 108 GEl4-PI OCNAB393-18G4.0-lOOT- 150-T6-2885 (GE14C) 14 136 GEI4-PI OCNAB393-18GZ- OOT-150-T6-2884 (GE14C) 14 20 New:
GEI4-PIOCNAB400-14GZ-1OOT-150-T6-3006 (GE14C) 15 28 GEl4-PI OCNAB398-17GZ- 1OOT-150-T6-3008 (GEl4C) 15 96 GEI4-P1OCNAB405-15GZ-1OOT-150-T6-3009 (GE14C) 15 56 GEl 4-P1OCNAB396-17GZ- 1OOT-150-T6-3007 (GEI4C) 15 48 Total: 764 The SV96P or SVEA96 designator is used to identify the SVEA-96+ fuel design throughout this report.
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HOPE CREEK 0000-0078-1947-SRLR R*Innid IAl Revision 2 Reload 14
- 3. Reference Core Loading Pattern Core Average Cycle Exposure Exposure 31942 MWd/MT 12549 MWd/MT Nominal previous end-of-cycle exposure: (28977 MWd/ST) (11384 MWd/ST)
Minimum previous end-of-cycle exposure (for cold 31611 MWd/MT 12218 MWd/MT shutdown considerations): (28677 MWd/ST) (11084 MWd/ST) 18915 MWd/MT 0 MWd/MT Assumed reload beginning-of-cycle exposure: (17159 MWd/ST) (0 MWd/ST)
Assumed reload end-of-cycle exposure (rated 31922 MWd/MT 13007 MWd/MT conditions): (28959 MWd/ST) (11800 MWd/ST)
Reference core loading pattern: Figure 1
- 4. Calculated Core Effective Multiplication and Control System Worth - No Voids, 201C Beginning of Cycle, keffective Uncontrolled 1.113 Fully controlled 0.952 Strongest control rod out 0.988 R, Maximum increase in strongest rod out reactivity during the cycle (Ak) 0.001 12125 MWd/MT (11000 MWd/ST)
Cycle exposure at which R occurs
- 5. Standby Liquid Control System Shutdown Capability Boron (ppm) Shutdown Margin (Ak)
(at 201C) (at 1601C, Xenon Free)
Analytical Requirement Achieved 660 >0.010 0.021 Page 5
HOPE CREEK 0000-0078-1947-SRLR Reoloacd 14 , Revision 2 Reload 14
- 6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 2 Operating domain: ICF (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 GEI4C 1.45 1.39 1.31 1.040 6.827 106.8 1.35 SV96P 1.45 1.45 1.31 0.990 7.083 104.2
- 1.36 Operating domain: ICF (HBB)
Exposure range : MOC to EOC (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 1.34 1.40 1.040 6.598 109.8 1.35 SV96P 1.45 1.40 1.40 0.990 6.867 106.6 1.36 Operating domain: MELLLA (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
Peaking Factors Fuel Bundle Bundle Initial Design Local Radial. Axial R-Factor Power Flow Design_ (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.36 1.29 1.040 6.648 96.6 1.35 SV96P 1.45 1.41 1.29 0.990 6.898 93.6 1.35 2 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.
Page 6
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: MELLLA (HBB)
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 1.32 1.36 1.040 6.450 99.0 1.35 SV96P 1.45 1.36. 1.36 0.990 6.644 95.9 1.37 Operating domain: ICF (UB)
Exposure range : MOC to EOC (Application Condition: 1, 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 1.27 1.040 6.962 105.3 1.35 SV96P 1.45 1.47 1.27 0.990 7.204 103.1 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 Design_ (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.39 1.26 1.040 6.814 94.8 1.34 SV96P 1.45 1.44 1.26 0.990 7.055 92.2 1.34 Operating domain: ICF & FWTR (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2 Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design_____(MWt) (1000 lb/hr) MCPR GEI4C 1.45 1.45 1.30 1.040 7.110 104.8 1.31 SV96P 1.45 1.51 1.30 0.990 7.374 101.8 1.31 Page 7
HOPE CREEK 0000-0078-1947-SRLR Revision 2 Reload 14 Operating domain: ICF & FWTR (HBB) - 1 Exposure range : MOC to EOC (Application Condition: 1, 2)
Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow.
Design (MWt) (1000 lb/hr) MCPR GEI4C 1.45 1.40 1.40 1.040 6.849 108.4 1.31 SV96P 1.45 1.45 1.40 0.990 7.085 104.9 1.32 Operating domain: MELLLA & FWTR (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design_____(MWt) (1000 lb/hr) MCPR GE 14C 1.45 1.42 1.29 1.040 6.947 94.6 1.29 SV96P 1.45 1.46 1.29 0.990 7.145 91.6 1.31 Operating domain: MELLLA & FWTR (HBB)
Exposure range : MOC to EOC (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 1.37 1.37 1.040 6.688 97.7 1.31 SV96P 1.45 1.41 1.37 0.990 6.884 94.1 1.32 Operating domain: ICF & FWTR (UB)
Exposure range : MOC to EOC (Application Condition: 1, 2 Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow.
Design_ (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.48 1.27 1.040 7.245 103.4 1.30 SV96P 1.45 1.53 1.27 0.990 7.465 100.9 1.31 Page 8
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revisinn 2 Operating domain: MELLLA & FWTR (UB)
Exposure range : MOC to EOC (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 1.45 1.26 1.040 7.088 93.1 1.29 SV96P 1.45 1.50 1.26 0.990 7.314 90.3 1.29 Operating domain: ICF with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 2 )
Peaking Factors Fuel " Bundle Bundle Initial Des Local Radial Axial R-Factor Power FlowI Design (MWt) (1000 lb/hr) MCPR GEI4C .1.45 1.37 1.31 1.040 6.727 107.4 1.38 SV96P 1.45 1.43 1.31 0.990 7.007 104.7 1.37 Operating domain: ICF 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 1.33 1.40 1.040 6.519 110.4 1.37 SV96P 1.45 1.38 1.40 0.990 6.766 107.4 1.38 Operating domain: MELLLA 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 1.34 1.29 1.040 6.579 97.0 1.36 SV96P 1.45 1.39 1.29 0.990 6.815 94.1 1.37 Page 9
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: MELLLA 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 1.31 1.36 1.040 6.404 99.3 1.36 SV96P 1.45 1.35 11.36 0.990 6.600 96.2 1.38 Operating domain: ICF with RPTOOS (UB)
-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 1.40 1.27 1.040 6.870 105.9 1.37 SV96P 1.45 1.45 1.27 0.990 7.103 103.8 1.37 Operating domain: MELLLA with RPTOOS (UB)
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 1.37. 1.26 1.040 6.714 95.5 1.36 SV96P 1.45 1.42 1.26 0.990 6.957 92.9 1.36 Operating domain: ICF & FWTR 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 1.42 1.30 1.040 6.969 105.7 1.34 SV96P 1.45 1.49 1.30 0.990 7.274 102.5 1.33 Page 10
HOPE CREEK 0000-0078-1947-SRLR R plnntI 14 Revision 2 Reload 14 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 GEI4C 1.45 1.37 1.40 1.040 6.726 109.2 1.34 SV96P 1.45 1.43 1.40 0.990 6.990 105.5 1.34 Operating domain: MELLLA & FWTR 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 1.40 1.29 1.040 6.847 95.2 1.32 SV96P 1.45 1.45 1.29 0.990 7.078 92.0 1.32 Operating domain: MELLLA & 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 MCPR (MWt) (1000 lb/hr)
GEI4C 1.45 1.35 1.37 1.040 6.594 98.3 1.33 SV96P 1.45 1.39 1.37 0.990 6.801 94.6 1.34 Operating domain: ICF & FWTR with RPTOOS (UB)
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 1.45 1.27 1.040 7.081 104.5 1.34 SV96P 1.45 1.50 1.27 0.990 7.340 101.8 1.33 Page I I
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: MELLLA & FWTR with RPTOOS:(UB)
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 1.43 *1.26 1.040 6.994 93.7 1.31 SV96P 1.45 1.48 1.26 0.990 7.213 90.9 1.31
- 7. Selected Margin Improvement Options 3 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 Table 7-1 Cycle Exposure Range Designation Name Exposure Range 4 BOC to MOC BOC 15 to EORI 5-2315 MWd/MT (2100.MWd/ST)
MOC to EOC EOR15-2315 MWd/MT (2100 MWd/ST) to EOC15 BOC to EOC BOC15 to EOC15 3 Refer to the GESTAR basis document identified at the beginning of this report for the margin improvement options currently supported therein.
4 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.
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HOPE CREEK 0000-007871947-SRLR Reload 14 Revision 2
- 8. Operating Flexibility Options 5.
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: No 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
Exposure range : BOC to MOC (Application Condition: 1,2) 2...
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 248 114 0.22 0.22 2 Load Rejection w/o Bypass 369 117 0.27 0.27 3 Turbine Trip w/o Bypass 319 115 0.26 0.26 4 5 Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility options currently supported therein.
6 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.
Page 13
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: ICF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Uncorrected ACPR Flux Q/A Event Fled
(%.rated). (%A
(%rated) GE14C SV96P Fig.
FW Controller Failure 306 119 0.23 0.24 5 Load Rejection w/o Bypass 427 122 0.27 0.28 6 Turbine Trip w/o Bypass 385 120 0.26 0.27 7 Operating domain: MELLLA (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 223 112 0.21 0.22 8 Load Rejection w/o Bypass 333 116 0.26 0.27 9 Turbine Trip w/o Bypass 287 113 0.25 0.26 10 Operating domain: MELLLA (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 2 )
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 274 117 0.22 0.24 11 Load Rejection w/o Bypass 386 120 0.27 0.29 12 Turbine Trip w/o Bypass . .... ...... 340 1 118 0;26- 0.28. 143.
Operating domain: ICF (UB)
Exposure range : MOC to EOC (Application Condition: 1, 2 )
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 220 111 0.21 0.21 14 Load Rejection w/o Bypass 337 115 0.27 0.27 15 Turbine Trip w/o Bypass 296 113 0.26 0.26 16 Page 14
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: MELLLA (UB)
Exposure range : MOC to EOC (Application Condition: 1,2)
Fu Uncorrected ACPR
-. Flux Q/A Event GE 14C SV96P Fig..
(%rated) (%rated)
FW Controller Failure 193 108 0.20 0.20 17 Load Rejection w/o Bypass 282 112 0.26 0.26 18 Turbine Trip w/o Bypass 261 109 0.24 .0.24 19 Operating domain: ICF & FWTR (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure _ 249 115 0.22 0.23 20 Operating domain: ICF & FWTR (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 313 120 0.23 0.24 21 Operating domain: MELLLA & FWTR (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
Uncorrected ACPR Event Flux Q/A ....
(%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 227 113 0.22 0.23 22 Operating domain: MELLLA & FWTR (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 292 119 0.23 0.25 23 Page 15
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: ICF & FWTR (UB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Uncorrected ACPR FluxeQ/ GE14C SV96P Fig.
Event (%rated) (%rated)
FW Controller Failure 229 113 0.22 0.22 24 Operating domain: 'MELLLA & FWTR (UB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Uncorrected ACPR
... Flux Q/A Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 199 110 0.20 0.21 25 Operating domain: ICF with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 275 117 0.25 0.24 26 Load Rejection w/o Bypass 406 120 0.29 0.29 27 Turbine Trip w/o Bypass 364 118 0.29 0.29 28 Operating domain: ICF with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 339 122 0.25 0.26 29 Load Rejection w/o Bypass 469 125 0.29 0.30 30 Turbine Trip w/o Bypass 434 124 0.29 0.29 31 Page 16
HOPE CREEK 0000-0078-1947-SRLR Reload 14 . Revision 2 Operating domain: MELLLA with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 241, 114 0.23 0.24 .32.
Load Rejection w/o Bypass 360 118 0.28 0.29 33 Turbine Trip w/o Bypass 319 116 0.28 . 0.28 .34 Operating domain: MELLLA with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 296 119 0.24 0.26 35 Load Rejection w/o Bypass 415 123 0.29 0.30 36 Turbine Trip w/o Bypass 373 121 0.28 0.29 3%7 Operating domain: ICF with RPTOOS (UB)
Exposure range : MOC to EOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 249 114 0.25 0.24 38 Load Rejection w/o Bypass 374 118 0.30 0.29 39 Turbine Trip w/o Bypass 341 117 0.29 0.28 . 40 Operating domain: MELLLA with RPTOOS (UB)
Exposure range : MOC to EOC (Application Condition: 2 )
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 215 111 0.23 0.22 41 Load Rejection w/o Bypass 304 115 0.28 0.28 42 Turbine Trip w/o Bypass 295 113 0.27 0.27 43 Page 17
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: ICF & FWTR with RPTOOS (HBB)
Exposure range BOC to MOC (Application Condition: 2)
Uncorrected ACPR Event Flux Q/A Event______________(%rated) (%rated) GEl4C SV96P Fig.
FW Controller Failure 277 118 0.25 0.25 44 Operating domain: ICF & FWTR with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A..
Event (%rated) (%rated) GE14C SV96P Fig.
FW Controller Failure 346 123 0.25 0.26 45 Operating domain: MELLLA & FWTR with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 246 115 0.24 0.24 1_46 Operating domain: MELLLA & FWTR with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 2)
Uncorrected ACPR Event Flux Q/A GE14C SV96P Fig.
(%rated) (%rated) GE_4CSV96P__ig FW Controller Failure -.314 121 0.25 0.26 47 Operating domain: ICF & FWTR with RPTOOS (UB)
Exposure range : MOC to EOC (Application Condition: 2)
Uncorrected ACPR Flux Q/A Event (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 258 116 0.25 0.25 48 Page 18
HOPE CREEK 0000-0078-1947-SRLR Reload 14 .. Revision 2 Operating domain: MELLLA & FWTR with RPTOOS (UB)
Exposure.range : MOC to EOC (Application Condition: 2) .
I. .Uncorrected ACPR Flux Q/A G Event . (%rated) (%rated) GEI4C SV96P Fig.
FW Controller Failure 220 112 0.23 0.23 49
- 10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary The ARTS based rod withdrawal error is an unblocked basis. The unblocked rod withdrawal error results in a ACPR of 0.26.
Page 19
HOPE CREEK 0000*0078-1947-SRLR R eln~cl ia Retviqinn 2 Reload 14
- 11. Cycle MCPR Values 7 89 Two loop operation safety limit: 1.08 Single loop operation safety limit: 1.10 Stability MCPR Design Basis: See Section 15 ECCS MCPR Design Basis: See Section 16 (Initial MCPR)
SLO Pump Seizure OLMCPR: See Pump Seizure Appendix Non-nressurization Events:
Exposure range: BOC to EOC GE14C SV96P Loss of Feedwater Heating (11 0IF) 1.24 1.24 Control Rod Withdrawal Error (unblocked) 1.35 1.35 Fuel Loading Error (misoriented) 1.25 1.32 Fuel Loading Error (mislocated) Not Limiting 7 The two loop and single loop Safety Limit values include a +0.02 ACPR adder in accordance with extended operating domain licensing commitments. The OLMCPR values presented in the Non-pressurization and Limiting Pressurization Events summary tables have been adjusted to include an additional +0.01 ACPR adder in accordance with extended operating domain licensing commitments. OLMCPR values presented in the detailed Pressurization Events tables do NOT include this adjustment.
' Exposure range designation is defined in Table 7-1.
9 For single loop operation, the MCPR operating limit is 0.02 greater than the two loop value.
Page 20
HOPE CREEK 0000-0078-1947-SRLR Reload 14 .Reviqinn 2 Limiting Pressurization Events OLMCPR Summary Table: ..
Appl. Exposure Range Option A Option B Cond.
GE14C SV96P GEI4C SV96P 1 Equipment In Service BOC to MOC 1.49 1.49 1.38 1.38 MOC to EOC 1.59 1.61 1.42 1.44 2 RPTOOS BOC to MOC 1.51 1.51 1.40 1.40 MOC to EOC 1.61 1.62 1.44 1.45 Pressurization Events:"
Operating domain: ICF (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
. Option A Option B GE14C SV96P GE14C SV96P FW Controller Failure 1.42 1.42 1.31 1.31 Load Rejection w/o Bypass 1.48 1.48 1.37 1.37 Turbine Trip w/o Bypass 1.47 1.47 1.36 1.36 Operating domain: ICF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Option A Option B
. GE14C SV96P GE14C SV96P FW Controller Failure 1.53 1.55 1.36 .1.38 Load Rejection w/o Bypass 1.57 1.59 1.40 1.42 Turbine Trip w/o Bypass 1.57 1.59 1.40 1.42 10Each 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.
" 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 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: MELLLA (HBB)
Exposure range : BOC to MOC (.Application Condition: 1, 2)
Option A Option B f GEI4C SV96P GE14C SV96P FW Controller Failure 1.42 1.42 1.31 1.31 Load Rejection w/o Bypass 1.47 1.48 1.36 1.37 Turbine Trip w/o Bypass 1.46 1.47 1.35 1'.36 Operating domain: MELLLA (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Option A Option B GE]I4C SV96P GEI4C SV96P FW Controller Failure 1.52 1.55 1.35 1.38 Load Rejection w/o Bypass 1.57 1.60 1.40 1.43 Turbine Trip w/o Bypass 1.57 1.59 1.40 1.42 Operating domain: ICF (UB)
Exposure range : MOC to EOC (Application Condition: 1, 2 )
~ ~;' "Option A Option B
.. GE14C SV96P GE14C SV96P FW Controller Failure 1.51 1.52 1.34 1.35 Load Rejection w/o Bypass 1.58 1.58 1.41 1.41 Turbine Trip w/o Bypass 1.56 1.57 1.39 1.40 Operating domain: MELLLA (UB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
Option A Option B
<0 0~~00~,'<000 00o GE14C SV96P GE14C SV96P FW Controller Failure 1.50 1.50 1.33 1.33 Load Rejection w/o Bypass 1.56 1.57 1.39 1.40 Turbine Trip w/o Bypass 1.55 1.55 1.38 1.38 Operating domain: ICF & FWTR (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
. - . : ,: Option A Option B
., GE] 4C SV96P GE14C SV96P FW Controller Failure 1.43 1.43 1.32 1.32 Page 22
HOPE CREEK 0000-0078-1947-SRLR RP1lacd 14 Revkinn 2 Operating domain: ICF & FWTR (HBB)
Exposure range MOC to EOC (Application Condition: 1, 2),
Option A Option B
.. ,GE14C SV96P GE14C SV96P FW Controller Failure 1.53 1.55 1.36 1.38 Operating domain: MELLLA & FWTR (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 2)
,'." ,Option A Option B
.. GE 41C I SV96P GE14C SV96P FW Controller Failure 1.42 1.43 1.31 1.32 Operating domain: MELLLA & FWTR (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 2 )
K,.,. !,Option ,,, : A Option B K K :KK' *: GE14C SV96P GE14C SV96P FW Controller Failure 1.53 1.56 1.36 1.39 Operating domain: ICF & FWTR (UB)
Exposure range : MOC to EOC (Application Condition: 1, 2)
________Option A Option B
. . . . GEI4C SV96P GE14C SV96P FW Controller Failure 1.52 1.53 1.35 1.36 Operating domain: MELLLA & FWTR (UB)
Exposure range MOC to EOC (Application Condition: 1, 2 )
. ' .Option A Option B
..... .GE14C SV96P GE14C SV96P FW Controller Failure 1.50 1.51 1.33 1.34 Operating domain: ICF with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 2)
- K K - - '= Option A Option B K'GE14C SV96P GEI4C SV96P FW Controller Failure 1.45 1.45 1.34 1.34 Load Rejection w/o Bypass 1.50 1.50 1.39 1.39 Turbine Trip w/o Bypass 1.50 1.50 1.39 1.39 Page 23
HOPE CREEK 0000-0078-1 947-SPRLR Reloid 14 Reviqinn 2 Operating domain: ICF with RPTOOS (HBB) .
Exposure range : MOC to EOC (Application Condition: 2)
K Option A Option B GE14C SV96P GEI4C SV96P FW Controller Failure 1.55 1.57 1.38 1.40 Load Rejection w/o Bypass 1.60 1.61 1.43 1.44.
Turbine Trip w/o Bypass 1.59 1.61 1.42 1.44 Operating domain: MELLLA with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 2)
X 7 -Option A Option B
- -- GE14C SV96P GE14C SV96P FW Controller Failure 1.44 1.44 1.33 1.33 Load Rejection w/o Bypass 1.49 1.49 1.38 1.38 Turbine Trip w/o Bypass 1.48 1.49 1.37 1.38 Operating domain: MELLLA with RPTOOS (HBB)
Exposure range MOC to EOC (Application Condition: 2)
Option A Option B SGE14C SV96P GE14C SV96P FW Controller Failure 1.55 1.57 1.38 1.40 Load Rejection w/o Bypass 1.59 1.61. 1.42 1.44 Turbine Trip w/o Bypass 1.59 1.61 1.42 1.44 Operating domain: ICF with RPTOOS (UB)
Exposure range : MOC to EOC (Application Condition: 2) .................
Option A Option B
.- ,. , , ¢ :N GE14C SV96P GE14C SV96P FW Controller Failure 1,.55 1.55 1.38 1.38 Load Rejection w/o Bypass 1.60 1.61 1.43 1.44 Turbine Trip w/o Bypass 1.59 1.59 1.42 1.42 Page 24
HOPE CREEK 0000-0078-1947-SRLR R~1cnd 14l *Revision 2 Reload 14 Operating domain: MELLLA with RPTOOS (UB)
Exposure.range MOC toEOC .(Application Condition: 2).
~ij 2v A~> '<y2~Option A Option B GEI 4C SV96P GE14C SV96P FW Controller Failure 1.53 1.53 1.36 1.36 Load Rejection w/o Bypass s 1.59 1.59 1.42 1.42 Turbine Trip w/o Bypass 1.58 1.58 1.41 1.41 Operating domain: ICF & FWTR with RPTOOS (HBB)
Exposure range : BOC to MOC. (Application Condition: 2)
'7Option A, Option B GEI 4C SV96P GE14C SV96P FW Controller Failure 1.46 1.46 1.35 1.35 Operating domain: ICF & FWTR with RPTOOS (HBB)
Exposure XX range
+*.;***
Condition: 2)
A-1 Option A Option B A-GE14C SV96P GE14C SV96P FW Controller Failure 1.56 1.58 1.39 1.41 Operating domain: MELLLA & FWTR with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 2 )
A.Option A Option B A's :2*;*; - GE14C SV96P GEI4C SV96P FW Controller Failure 1.44 1.45 1.33 1.34 Operating domain: MELLLA & FWTR with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 2)
A" Option A Option B
- ' -AGE14C SV96P GE14C_ SV96P FW Controller Failure 1.55 1.57 1.38 1.40 Operating domain: ICF & FWTR with RPTOOS (UB)
Exposure range MOC to EOC (Application Condition: 2 )
<' A':'-..* '. A Option A Option B GE14C SV96P GE14C SV96P FW Controller Failure 1.56 1.56 1.39 1.39 Page 25
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Operating domain: MELLLA & FWTR with RPTOOS (UB)
Exposure range MOC to EOC (Application Condition: 2)
Option A Option B GE14C SV96P ,GEI4C SV96P FW Controller Failure 1.53 1.54 1.36 1.37.
- 12. Overpressurization Analysis Summary Psi Pdome Pv Plant (psig) (psig) (psig) Response MSIV Closure (Flux Scram) - ICF (HBB) 1262 1267 1288 Figure 50 MSJV (HBB) Closure (Flux Scram) - MELLLA 1263
__263__
1268 126_128_Fgur_5 1288 Figure 51
- 13. Loading Error Results Variable water gap misoriented bundle analysis: Yes 12 Misoriented Fuel Bundle ACPR GE 142P 1OCNAB396-17GZ- I OOT- I50-T6-3007 (GE I4C) 0.16 GE 14-PI OCNAB393-18G4.0-1OOT-150-T6-2885 (GE 14C) 0.07 GE14-PI OCNAB405-15GZ-1OOT-150-T6-3009 (GE14C) 0.10 GE 14-P 1OCNAB393-18GZ- OOT- 150-T6-2884 (GE 14C) 0.08 GE1 4-P1OCNAB398-17GZ-IOOT-150-T6-3008 (GEI4C) 0.16 GE1 4-PI OCNAB400-14GZ-IOOT-150-T6-3006 (GEl 4C) 0.14 SVEA96-P I OCASB361-14GZ-568U-4WR- 150-T6-2658 (SV96P) 0.23
- 14. Control Rod Drop Analysis Results This is a banked position withdrawal sequence plant, therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-2401 1-P-A-US.
12 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.
Page 26
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2
- 15. Stability Analysis Results 15.1 Introduction Hope Creek has implemented BWROG Long Term Stability Solution Option III using the Oscillation Power Range Monitor (OPRM) as described in Reference I 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 15 Option III stability evaluation. A Backup Stability Protection (BSP) evaluation is provided 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 provides the stability licensing bases for Hope Creek Cycle 15.
15.2 Option III Stability 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 Operating Limit Minimum Critical Power Ratio (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 15 using a DIVOM slope of 0.65 which was calculated in accordance with the BWROG regional mode DIVOM guidelines described in Reference 4 in Section 15.4. This DIVOM slope was calculated based on a radial peaking factor multiplier of 1.05 to add margin over the nominal rod patterns. Further evaluations may be necessary if the radial peaking during actual core operation is significantly different from that assumed. The Cycle 15 Option III evaluation provides adequate protection against violation of the Safety Limit MCPR (SLMCPR) for the two postulated reactor instability events as long as the plant OLMCPR is equal to or greater than the calculated OLMCPR(SS) and OLMCPR(2PT) for the selected OPRM setpoint in Table 15-1 and 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 15-3. For intermediate OPRM Amplitude Setpoints, the corresponding OPRM Successive Confirmation Count Setpoints may be obtained by using linear interpolation.
The OPRM setpoints for Two Loop Operation (TLO) are conservative relative to Single Loop Operation (SLO) and are therefore bounding.
Two sets of OPRM setpoints are provided. Table 15-1 assumes a 1.0 Hz corner frequency in the conditioning filter while Table 15-2 assumes a 1.5 Hz corner frequency for the conditioning filter.
Page 27
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 13 Table 15-1: OPRM Setpoint Versus OLMCPR (1.0 Hz Corner Frequency)
OPRM Amplitude OLMCPR(SS) OLMCPR(2PT)
Setpoint 1.04 1.2414 1.1097 1.05 1.2778 1.1423 1.06 1.3165 1.1769 1.07 1.3576 1.2136 1.08 1.4014 1.2527 1.09 1.4480 1.2944 1.10 1.4963 1.3375 1.11 1.5478 1.3836 1.12 1.6031 1.4330 1.13 1.6624 1.4861 1.14 1.7263 1.5432 OLMCPR Off-rated OLMCPR Rated OMP Power Accepance Acceptance @45% flow OLMCPR Criteria (see Section 11) 13 The setpoints in these tables include the 5% bypass voiding penalty imposed by the final Safety Evaluation report for NEDC-33173P, Applicability of GE Methods to Expanded OperatingDomains.
Page 28
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Table 15-2: OPRM Setpoint Versus OLMCPR14 (1.5 Hz Corner Frequency)
OPRM Amplitude OLMCPR(SS) OLMCPR(2PT)
Setpoint 1.04 1.2313 1.1006 1.05 1.2650 1.1308 1.06 1.3007 1.1627 1.07 1.3384 1.1964 1.08 1.3783 1.2321 1.09 1.4208 1.2700 1.10 1.4646 1.3092 1.11 1.5112 1.3509 1.12 1.5609 1.3953 1.13 1.6140 1.4428 1.14 1.6708 1.4935 OLMCPR Rated Power Accepance Off-rated OLMCPR OMP Acceptance @45% flow OLMCPR Criteria (see Section 11) 14 The setpoints in these tables include the 5% bypass voiding penalty imposed by the final Safety Evaluation report for NEDC-33173P, Applicability of GE Methods to Expanded OperatingDomains.
Page 29
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Table 15-3: Relationship between OPRM Successive Confirmation Count Setpoint and OPRM Amplitude Setpoint Successive Confirmation OPRM Amplitude Count Setpoint Setpoint 6 _1.04 8 Ž1.05 9 Ž1.06 10 Ž1.07 11 Ž1.08 12 Ž1.09 13 _>1.10 14 Ž1.11 15 Ž1.13 16 Ž1.14 17 Ž1.16 18 Ž1.18 19 Ž1.21 20 Ž 1.24 Page 30
HOPE CREEK 0000-0078-1947-SRLR V.~1-1A 1A a V.
15.3 Backup StabilityProtection The BSP region boundaries were calculated for Hope Creek Cycle 15 for normal feedwater temperature operation. The endpoints of the regions are defined in Table 15-4. The region boundaries, shown in Figure 15-1, are defined using the Generic Shape Function (GSF), in compliance with References 5 and 6 in Section 15.4.
Table 15-4: BSP Region Intercepts for Normal Feedwater Temperature Region Boundary Highest
%Power % Flow Core DR Channel Intercept DR Al 62.4 45.1 <0.799 <0.450 B1 44.7 35.0 <0.799 <0.431 A2 67.2 51.1 <0.800 <0.404 B2 32.2 36.3 <0.799 <0.380 The Cycle 14 BSP regions described in Reference 7 in Section 15.4 are bounding for Cycle 15 up to an exposure of 11600 MWD/ST. 15 The BSP results for the EPU analysis are bounded by the results for the CLTP analysis, and therefore, the intercepts in Table 15-4 are based on the CLTP analysis.
15 The BSP intercepts shown in Reference 7 are based on the CLTP rated power, not the EPU rated power; therefore, they need to be scaled by multiplying the percent powers by the ratio CLTP/EPU rated power.
Page 31
HOPE CREEK 0000-0078-1947-SRLR Reload 14 . .Revision 2 Core Flow (MIb/hr) 0 10 20 30 .40 50 60 -70 80 90 100 .110 120 110
-- 4000 100 N: Natural Circulaton M: Minim= PumpSpeed E 90 N:00.0..00.0% ower!
...... . 1000 N.N.....Flow lw. MFLLLA Boundary Line 3600 36er F: 000.0% Power 05101 10 low 3200 s0 70" 2800 0 " . . . . A2
- l -2400
- 60 Scran Regiwn 2SP 50-E 1600 40 40 - FP Controlled FErtryRegion 30 1200
- " 800 20 -V 10-- -400
" 10%Core Flo- 100Ml 0 1 .. . . . . . .. 0 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (%)
Figure 15-1: BSP Regions for Normal Feedwater Temperature Operation Page 32
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 15.4 References
- 1. BWR Owners' Group Long-Term Stability Solutions Licensing Methodology, NEDO-31960-A, November 1995.
- 2. Reactor Long-Term Stability Solution Option III: Licensing Basis Hot Channel Oscillation Magnitudefor Hope Creek, GENE-A 13-00381-04, Rev. 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. BWR Owners' Group Guidelines for Stability Interim Corrective Action, BWROG-94079, June 1994.
- 6. Backup Stability Protection (BSP) for Inoperable Option III Solution, OG 02-0119-260, July 2002.
- 7. MELLLA Backup Stability Protection Evaluationfor Hope Creek Cycle 14, GE-NE-0000-0044-3736-RO, January 2006.
Page 33
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2
- 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 Table 16.1-1.
1.
Table 16.1-1 Licensing Results Core-Wide Licensing Local Me-Wate Fuel Type Basis0 PCT Oxidation Reatio
( F) (OF) (%) Reaction
(%)
SVEA96 1540 < 1.00 < 0.10 GE14C 1380 < 1.00 < 0.10 The SAFER/GESTR-LOCA analysis results for SVEA96 fuel are documented in Section 5 of Reference I for SVEA96 in Section 16.4.
The SAFER/GESTR-LOCA analysis results for GE I4C fuel are documented in Section 5 of Reference 1 for GEI4C in Section 16.4.
Page 34
HOPE CREEK 0000-0078-1947-SRLR Reln~d 14 Revisinn 2 Reload 14 16.2 10CFR50.46 Error Evaluation The IOCFR50.46 errors applicable to the Licensing Basis PCT are shown in the table below.
Table 16.2-1 Impact on Licensing Basis Peak Cladding Temperature for SVEA96 IOCFR50.46 Error Notifications PCT Impact (OF) 2006-01 Impact of Top Peaked Power Shape on Small Break 0 LOCA Analysis Total PCT Adder (OF) 0 The SVEA96 Licensing Basis PCT remains below the 10CFR50.46 limit of 2200'F.
Table 16.2-2 Impact on Licensing Basis Peak Cladding Temperature for GE14C IOCFR50.46 Error Notifications Number Subject PCT Impact (OF) 2006-01 Impact of Top Peaked Power Shape on Small Break 0 LOCA AnalysisA0 Total PCT Adder (OF) 0 The GE14C Licensing Basis PCT remains below the IOCFR50.46 limit of 2200'F. ..
16.3 ECCS-LOCA Operating Limits The ECCS MAPLHGR operating limits for the new fuel bundles in this cycle are shown in the tables below. The MAPLHGR operating limits for the remaining fuel bundles are documented in Reference 2 for GEI4C and Reference 2 for SVEA96 in Section 16.4.
Page 35
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Table 16.3-1 MAPLHGR Limits Bundle Type: GE I4-P 1OCNAB396-17GZ- IOOT- 150-T6-3007 (GE I4C)
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 Table 16.3-2 MAPLHGR Limits Bundle Type: GEI4-PIOCNAB405-15GZ-1OOT-150-T6-3009 (GEI4C)
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 Table 16.3-3 MAPLHGR Limits Bundle Type: GE 14-P 1OCNAB398-17GZ- 1OOT- 150-T6-3008 (GE I4C)
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 Page 36
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Table 16.3-4 MAPLHGR Limits
-Bundle Type: GE 14-P 1OCNAB400-14GZ- lOOT- 150-T6-3006 (GE 14C)
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 Page 37
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Reload 14 The single loop operation multiplier on LHGR and MAPLHGR, and the ECCS Initial MCPR values applicable to each fuel type in the new cycle core are shown in the table below.
Table 16.3-5 Initial MCPR and Single Loop Operation LHGR and MAPLHGR Multiplier Fuel Type Initial MCPR Single Loop Operation LHGR and MAPLHGR Multiplier SVEA96 1.250 0.80 GE14C 1.250 0.80 16.4 References The SAFER/GESTR-LOCA analysis base reports applicable to the new cycle core are listed below.
References for SVEA96
- 1. SAFERIGESTR-LOCA Loss of Coolant Accident Analysis for Hope Creek Generating Station at Power Uprate,NEDC-33 172P, March 2005
- 2. Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 13 Cycle 14, 0000-0041-6021-SRLR, Rev. 1, March 2006 References for GE14C
- 1. SAFER/GESTR-LOCA Loss of Coolant Accident Analysis for Hope Creek Generating Station at Power Uprate, NEDC-33172P, March 2005
- 2. Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 13 Cycle 14, 0000-0041-6021-SRLR, Rev. 1, March 2006 Page 38
HOPE CREEK 0000-0078-1947-SRLR Reload 14 . Revision 2.
60 F] EC] ED] EC] ECEC] EE] EC] EC] FL] E_2-D]_EC]-D 60]
-58 O W] E ] L 56 El1 E]DEl EIL1EI ]Tr T r]
ENl l E]EK] [I DED ITI rff1ELE[F 54 52 F71 E] E] E l L] ][ ]tII*- ND E][ E K] [E]_lI[E] EC] II [N]Dz~l-L] E B]_*-
50 48 [)).
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52 I EjJ r 11 44 rjF[j EE] [El] K] [E]-**- FL] EN]
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3 PEEF XI'CITE] MR NP -E]NED 42 40 [] [] [J] ] [FE] [KE []DJ[J] El
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EN 9-1l 1E]WE; l ER-ERl II[D]
38 E]l-t-
- 6 ] EE]IE]I*1E] ] I] I* [ IEITIT* ]F E][D*FLME FNED] EO E 24 *2 20 El I*1E ON El M +/-l1 I--7 I1E]E]IEElIE]E E El 2 E EIFE1I PEl N El E IE]rrl7 l+/- D]NE EIE WE] ET 32 E ] [% ]I E [QIE []ED]EE] [CD EL EL]r_*-1 E ]F]_1]1- E] E E] [] N F]E [LD]
14 rCK]IF]I. 4E]FN ~~ ~ FEEElI ~ ~ ~ ~ ~~ E El EI[- E]_l[-
El_[ Flr-El El ED F-1][][
30 N' El E7 BED 9N 11 Ell EDE E5 MR7 1211R 10 23 27D E MR5 OE 73 ENE1 033 47 LEE 05 IQ
!535M575 ME]
18 ] E]E i rd % W1 E1I~NN NI E EI1 W 28SVEA96-P10CASB360 -12G.056U-WR1E]ycle 5-627 11) E 12)
(Cyle D E lE 2=VA6P0AB6-4Z58-W-5-6W N'E-265 'Ccl'2 N=G'14-P10CNAI39-17GE-1100ET E-15-630 I (Cyle 15)E Fue Type lE [] N][E B=SVEA96-P10CASB360-12G5.5/G.-568U-4WR-150-T6-265 (Cycle 9 11) K=E410 AB9-8 (Cycle .- 0T15T625 12)
E=GE 4-P OCNAB402-4G6.0/16G4.0-1 I 00T- 50-T6-2757 (Cycle 13) L=GE I 4-P10CNAB405-1 PT-5GZ-0 I 150-16-3009 (Cycle 15)
F=GEI 4-PIO0CNAB402-5G6.0/1 4G4.0-1 001-150-16-2758 (Cycle 13) M=GEI 4-P10OCNAB393- 18GZ-1 001-150-16-2884 (Cycle 14)
G=SVEA96-P10CASB36O-12G5.0-568-4WR-l 50-T6-2657 (Cycle 11) NGEI4-P1 0CNAB398-17GZ-1001-150-T6-3008. (Cycle 15)
FhSVEA96-P10CASB361 -1 4GZ-568U-4WR-1 50-16-2658 (Cycle 12) O=GE14-P10OCNAB400-14GZ- 1001-150-16-3006 (Cycle 15)
Figure 1 Reference Core Loading Pattern Page 39
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 U
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 1.0
'9 100.0 0.0 50.0 19 -1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (see) Time (see)
Figure 2 Plant Response to FW Controller Failure (MOC ICF (HBB))
Page 40
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 150.0 100.0 U
50.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Tine (sec) Time (sec) a Level(inch-REF-SEP-SKRT)
Vessel Steam Flow 200.0- Turbine Steam Row Feedwater Flow 100.0- 0 0.0 d1 I -1.0 t t'tt't*
-2.0 -
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tine (Sec)
Figure 3 Plant Response to Load Rejection w/o Bypass
Page 41
HOPE CREEK 0000-0078-1947-SRLR RpA-
- lnil1,i Revision 2 Reload 14 U
U Cs N
0.0 30 6. 0 0.0 3.0 6.0 Tine (see) Time (see)
-E- Level(inch-REF-SEP-SKRT)
-V-- Vessel Steam Row 1.0 200.0 Turbine Steam Row Feedwater Flow 1003.0 ao~o U
U.U+- A A n-
-10J0.0 -2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (see)
Figure 4 Plant Response to Turbine Trip w/o Bypass (MOC ICF (HBB))
Page 42
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 250.0 200,0 150.0 100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Ti-e (sec) Time (sec) 150.0-V 100.0-50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 5 Plant Response to FW Controller Failure (EOC ICF (HBB))
Page 43
HOPE CREEK 0000-0078-1947-SRLR RP1nAI d1. 1* ,-w;* ,-
Rplnnd 14 150.0 100.0 U
500 100.0 0.0 0.04 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) 1.0 S0.0 U
-9 -1.0 -
-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 6 Plant Response to Load Rejection w/o Bypass
Page 44
HOPE CREEK 0000-0078-1947-SRLR D 1)
U" ýv a UAL U U 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (see)
-*- Level(inch-REF-SEP-SKRT)
-*-- Vessel Steam Row o
20 0.0 Turbine Steam Raw Feedwater Flaw U
10(0.0 C U
2C U
U 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 7 Plant Response to Turbine Trip w/o Bypass (EOC ICF (HBB))
Page 45
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 200.0
- Neutron Flux/10
--- Avg Surface Heat Flux 6 Core Inlet Row 200.0- -s- Core Inlet Subcooling 150.0 150.0-100.0 100.0 50.0-0.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
- LeveI(inch-REF-SEP-SKRT)
--- Vessel Steam Row 150.0- Turbine Steam Row 1.0 Feedwater Row 100.0 0.0 1
50.0 S-1.0 u.u -2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 8 Plant Response to FW Controller Failure (MOC MELLLA (HBB))
Page 46
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 150.0 100.0 V
50.0 100.0 0.0 0.0 e 0.0 3.0 6 .0 0.0 3.0 6.0 Time (Sec)
Time (sec)
- Level(inch-REF-SEP-SKRT)
-*- Vessel Steam Row 2 0 0 .0 Turbine Steam Row 1.0 Feedwater Flow 100.0. o.0 U
w 0
A. * -1.0
- n UU ,* i .*, u /% , , p,
-1lJJ.U 1 I 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 9 Plant Response to Load Rejection w/o Bypass (MOC MELLLA (HBB))
Page 47
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 300.0 200.0 Va *0 lin n 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (se
-e- Level(inch-REF-SEP-SKRT)
-x- Vessel Steam Row 2000.0 -.- Turbine Steam ROw 1.0
-,- Feedwater Flow U
100. S0.0 1 -1.0
-1000
-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 10 Plant Response to Turbine Trip w/o Bypass (MOC MELLLA (HBB))
Page 48
HOPE CREEK 0000-0078-1947-SRLR R olnncI 1A Revision 2 Reload 14 4J 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 100.0 0 2
(5 U
Cs 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Ti-e (see)
Figure 11 Plant Response to FW Controller Failure (EOC MELLLA (HBB))
Page 49
ý-N,
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2
-a- Dome Press Rise (psi)
- -- Safety Valve Flow SRelief Valve Flow
-s- Bypass Valve Flow 200.0
.5 100.0-
- .- r-r..
0.0 3.0 6.0 0.0 3.0 Time (see) Time (sec) 5..
S
,0 100.0 0
2 0
54 4) 0.0 3.0 6.0 0.0 3.0 Time (see) Time (see)
Figure 12 Plant Response to Load Rejection w/o Bypass (EOC MELLLA (HBB))
Page 50
'A.
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 300.0 V 'a U
100.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
E3 Level(inch-REF-SEP-SKRT)
-Y- Vessel Steam Flow 200.0+ Turbine Steam Raw 1.0 Feedwater Flow 100.0 0.0 a g a
S-1.0
-1U.U 1 Ii i -2.0 0,0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 13 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA (HBB))
Page 51
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 200.0 150.0 A100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 "0100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 14 Plant Response to FW Controller Failure
( EOC ICF (UB))
Page 52
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 150.0 100.0 4"
50.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
- Levei(inch-REF-SEP-SKRT)
-x-- Vessel Steam Raw 200.0 Turbine Steam Row Feedcwater Flow
- 1100.0-S0.0 U
C -
4"
^^
S-1.0 0.0+ / 1 / AN
-2.0-0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 15 Plant Response to Load Rejection w/o Bypass (EOC ICF (UB))
Page 53
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 100.0 6 0.0 6 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
E3 Level(inch-REF-SEP-SKRT)
--x- Vessel Steam Flow 200.0 + -s Turbine Steam Row Feedwater Flow S
Ga 100.0 S 0
0.
C Ga
[111 Ga
-10.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 16 Plant Response to Turbine Trip w/o Bypass (EOC ICF (UB))
Page 54
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 100.0 50.00 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 17 Plant Response to FW Controller Failure (EOC MELLLA (UB))
Page 55
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 150.0 100.0 U U 50.0-0.0 3.0 6 .0 0.0 3.0 6.0 Time (sec) Time (sec)
-a- Level(inch-REF-SEP-SKRT)
-M--essel Steam Row 200.04 --- Turbine Steam Row 1.0 Feedwater Flow 100.0 S0.0 U-U.Uf .
S-1 .0-
-'IUU.U i 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 18 Plant Response to Load Rejection w/o Bypass (EOC MELLLA (UB))
Page 56
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Reviion 2
,U 100.0 0.0 -*
0.0 3.0 6.0 0,0 3.0 Time (see) Time (sec)
- Level(inch-REF-SEP-SKRT)
-*- Vessel Steam Flow 200.0+
- Turbine Steam Flow 1.0 Feedwater Flow Va 100.0 S0.0 C
- -1.0 V
-2.0 0.0 3.0 6.0 00 3.0 6.0 Time (sec) Time (sec)
Figure 19 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA (UB))
Page 57
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 250.0 200.0 150.0 N
100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Ti- (sec) Time (sec)
, Level(inch-REF-SEP-SKRT)
- ---Vessel Steam Row 150.0
- Turbine Steam Raw o Feedwater Row I.)
100.0 C a
U U
50.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (see) Time (sec)
Figure 20 Plant Response to FW Controller Failure (MOC ICF & FWTR (HBB))
Page 58
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 V.
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (see) 150U0 10100.0 0 20 Q
50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (see) Time (sec)
Figure 21 Plant Response to FW Controller Failure (EOC ICF & FWTR (HBB))
Page 59
HOPE CREEK 0000-0078-1947-SRLR R *lAncd hi Revision 2 Rel-ad 14
-E- Dome Press Rise (psi)
--- Safety Valve Flow Relief Valve Flaw Bypass Valve Flow 150.0+
U 100,0+
If 50.0 4 0.0 10.0 20.0 0.0 10,0 20.0 Tine (sec) Ti=e (sec) 150.0 Eter Ra -w- Total Reactivity
[4 100.0 50.0 9 -1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Tinm (sec) Tinm (sec)
Figure 22 Plant Response to FW Controller Failure (MOC MELLLA & FWTR (HBB))
Page 60
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 "U
U 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 1.0 10100.0 0.0
-1.0
-2.01 0.0 10,0 20.0 0.0 10.0 20.0 Time (see) Time (see)
Figure 23 Plant Response to FW Controller Failure (EOC MELLLA & FWTR (HBB))
Page 61
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 N
0.0 1O.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 1.0 i0.0 10100.0 4-1.0
-2.01 0.0 10.0 20.0 0.0 10.0 20.0 Tine (see) Time (sec)
Figure 24 Plant Response to FW Controller Failure (EOC ICF & FWTR (UB))
Page 62
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 U
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 10100.0 0.0 50.0 9 -1.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 25 Plant Response to FW Controller Failure (EOC MELLLA & FWTR (UB))
Page 63
HOPE CREEK 0000-0078-1947-SRLR RP1nd 1A P *xt*cm "9 U 4) 0.0 10.0 200 0.0 10.0 20.0 Tine (sec) Time (Sec) 150.0 1.0 U
V 100.0 0.
C,3 50.0 S-1.0-0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 26 Plant Response to FW Controller Failure (MOC ICF with RPTOOS (HBB))
Page 64
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 300.0 200.0 100.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) 200.0 0
100.0 U
0.0
-100.0 0.0 3.0 6.0 0.0 3.0 6.0 Tin- (sec) Tie (sec)
Figure 27 Plant Response to Load Rejection w/o Bypass (MOC ICF with RPTOOS (HBB))
Page 65
HOPE CREEK 0000-0078-1947-SRLR Rpe~n~id 14-Revision 2 Reload 14 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) 4)
C C.
a (5
U 4) 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 28 Plant Response to Turbine Trip w/o Bypass (MOC ICF with RPTOOS (HBB))
Page 66
HOPE CREEK 0000-0078-1947-SRLR V. ,,; e;rr IMI,-0 A 1 A ,I,'*%'~~~~ /LI"I *.*¥llll[ ~~~1)
-- A, N
0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec) Time (sec) 150.0
,0100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (see)
Figure 29 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (HBB))
Page 67
HOPE CREEK 0000-0078-1947-SRLR RP1,lnrl 1It V5 2
100.0 0.0 L 0.0 30 6 .0 0.0 10 6.0 Time (sec) Time (sec)
- Level(inch-REF-SEP-SKRT)
-*-- Vessel Steam Row 200.0 + Turbine Steam Row 1.0
--.-- Feedwater Flow
.5 100.0 0 0.0 4) 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 30 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (HBB))
Page 68
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 U U N
0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tine (sec)
--e Level(inch-REF-SEP-SKRT)
Vessel Steam Row 200.0- Turbine Steam Row 1.0 Feedwater Flow 100.0 S0.0 U.U + A . - A
- -1.0
-IUU.U
- 0.0 3.0 6.0 0.0 3.0 Time (sec) Time (sec)
Figure 31 Plant Response to Turbine Trip w/o Bypass (EOC ICF with RPTOOS (HBB))
Page 69
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 U U 0.0 10.0 20.0 0,0 10.0 20.0 Tilyr (sec) Time (sec) 150.0
'9 100.0-U-
0.0 100 20.0 0.0 10.0 20.
TimE (sec) Ti-- (sec)
Figure 32 Plant Response to FW Controller Failure (MOC MELLLA with RPTOOS (HBB))
Page 70
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 N
100.0
-6 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
-a- LeveI(inch-REF-SEP-SKRT)
-*- Vessel Steam Row 200.04 Turbine Steam Raw 1,0 Feedwater Flow 4t:
100.0 0.0 P -1.0 1000 - -2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (see) Time (sec)
Figure 33 Plant Response to Load Rejection w/o Bypass (MOC MELLLA with RPTOOS (HBB))
Page 71
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 10 100.0 0.0 -L 0.0 3.0 6.0 0.0 3.0 6.0 Time (see) Time (sec) 1.0 04 -1.o
-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 34 Plant Response to Turbine Trip w/o Bypass (MOC MELLLA with RPTOOS (HBB))
Page 72
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Reload 14 PC 'a 4J N.
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 51100.0 0.0-50.0
-1.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 35 Plant Response to FW Controller Failure
( EOC MELLLA with RPTOOS (HBB))
Page 73
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 300.0 200.0 V.
50.0 100.0 0.0 t
- 0. 0.0 0 3.0 6.0 0.0 3.0 Time (sec) Time (sec)
-*-- Level(inch-REF-SEP-SKRT)
-*-- Vessel Steam RFow 200.0- - Turbine Steam Row 1.0 Feedwater Flow 100.0
'I Q -1.0 E
0.0 - I - 6 A S-1.0
-100.0 I 0.0 3.0 6.0 0.0 30 6.0 Time (sec) Time (sec)
Figure 36 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with RPTOOS (HBB))
Page 74
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 150.0 300.0
-- Neutron Flux/ 10 -e-- Dome Press Rise (psi)
-*- Avg Surface Heat Flux -.
- Safety Valve Row
- Core Inlet Flow 6 Relief Valve Flow Bypass Valve Flow 100.0 200.0 50.0 100.0 0.0 0.
0.0-0.0 3,0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
E3 Level(inch-REF-SEP-SKRT) 8 d eactit.
200.0 Vessel Steam Raw .0Reactivty 2o0.0 A Turbine Steam Row 1. Sc Reacti Feedwater Flow Total eactivty 0,0- -1.0
-100.01 -2,0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 37 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA with RPTOOS (HBB))
Page 75
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 200.0 150.0 100.0 50,0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 1.0 100.0 0.0 U
o
- -1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 38 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (UB))
Page 76
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 IV 10D.0 0.0 -E 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
-a- Levei(inch-REF-SEP-SKRT)
- Vessel Steam Row 200.0 Turbine Steam Row 1.0 Feedwater Flow U
100J.0 S0.0 4 -1.0
-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tite (see)
Figure 39 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (UB))
Page 77
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 0.0 3.0 6.0 0.0 3.0 6.0 Tine (sec) Time (sec)
-E- Level(inch-REF-SEP-SKRT)
Vessel Steam Raw V--x-200.0 4 6 Turbine Steam Row Feedwater Flow
'4 100.0 0.0
-IA.VU i -2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tinm (sec)
Figure 40 Plant Response to Turbine Trip w/o Bypass (EOC ICF with RPTOOS (UB))
Page 78
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 200.0 150.0 U
100.0 0.0 0.0 10.0 20,0 0.0 10.0 20.0 Time (sec) Tine (see) 150.0 1.0 100.0
-1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (see) Time (sec)
Figure 41 Plant Response to FW Controller Failure (EOC MELLLA with RPTOOS (UB))
Page 79
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 10 100.0 0.0 -E 0,0 3.0 6. 0 0.0 3.0 6.0 Time (see) Time (see)
B Level(inch-REF-SEP-SKRT)
--x- Vessel Steam RFow 1.0 200.0 Turbine Steam Raw Feedwater Flow 100.0 0.0-nn
-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (see) Time (sec)
Figure 42 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with RPTOOS (UB))
Page 80
HOPE CREEK 0000-0078-1947-SRLR R~ln~ d1,1 Revision 2 RpIr-ti 14 150.0 100.0 4.
50.0 100.0 0.0 0.0 -kE 0.0 3,0 6 .0 0.0 3.0 6.0 Time (sec) Time (sec)
-*- Level(inch-REF-SEP-SKRT)
- Vessel Steam Raw 200.0- Turbine Steam Row 1.0 Feedwater Flow "U 100.0-0 10 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 43 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA with RPTOOS (UB))
Page 81
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 U 'a N.
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 1.0
,0100.0 0 0.0 tU S
- -1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (see)
Figure 44 Plant Response to FW Controller Failure (MOC ICF & FWTR with RPTOOS (HBB))
Page 82
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 N
0.0 10,0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 U
50100.0 C a
C U
U U
50.0 0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec) Time (sec)
Figure 45 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (HBB))
Page 83
HOPE CREEK 0000-0078-1947-SRLR Urv 3 VII 200.0 150.0
'U~
'4 100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 'i'4Hm a N-lOW 1.0 - ,.rwri r'*,cuViy ater Row -- Total Reactivity 100.0 0.
50.0
-1.0
-2.01 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 46 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with RPTOOS (HBB))
Page 84
HOPE CREEK 0000-0078-1947-SRLR R lnnct 1/i 1D.-,;-, I Reload 14 0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec) 150.0 U
- IX.
1100.0 0.0 . ,
-10
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (see)
Figure 47 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (HBB))
Page 85
HOPE CREEK 0000-0078-1947-SRLR DI* t A*
-I1A D h;icurr, I
'a 'a U
0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec) Tine (sec)
-*- Level(inch- REF-SEP-SKRT)
- --- Vessel Steam Row 150.O 6 Turbine Steam Flow 1.0
-*- Feedwater Row
'a 1~.0 0.0 U
N 0 -1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (see) Time (sec)
Figure 48 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (UB))
Page 86
HOPE CREEK 0000-0078-1947-SRLR 0* 1.*,A 1A D ey ; s ; on "1 "0
N 0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec) Tine (sec) 150.0 ; ,L JI I lUVV 1.0 =,.
II I rCOLUVIlky ater Row -.- Total Reacvity 100.0 0.0
- ~ -1.0
-2.0-0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec) Time (sec)
Figure 49 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (UB))
Page 87
HOPE CREEK 0000-0078-1947-SRLR R elnacl 14 Revision 2 Reload 14 0.0 4.0 8.0 0.0 4.0 8.0 Tiun (sec) Time (sec) 1.0 0.0 4J
'N U
g -1.0
-2.0 0.0 4.0 8.0 0.0 4.0 Tine (sec) Time (sec)
Figure 50 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)
Page 88
HOPE CREEK 0000-0078-1947-SRLR RP1lA~d lhi Revision 2 Reload 14 3W.30 MO.l0 U
N
~10H.
B1B0.0 - E 0.0 4.0 8.0 0.0 4.0 8.0 Time (sec) Time (sec)
-e- Level(inch-REF-SEP-SKRT) - Void Reactivity
-s- Messel Steam Raw 10--y- Doppler Reacivit
--a- Turtbne Steam Raow 6 mo s Feedwater Flow I RR
-.0 0 C4 .
-2.0 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 89
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 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 1030.1 1028.1 Inlet enthalpy, Btu/lb 526.3 523.8 522.4 519.6 Non-fuel power fraction 0.036 0.036 0.036 0.036 Steam flow, Mlb/hr 16.80 16.78 16.28 16.27 Dome pressure, psig 1005.0 1005.0 999.4 999.4 Turbine pressure, psig 945.8 945.9 943.6 943.7 Table A-2 Pressure Relief and Safety Valve Configuration Page 90
HOPE CREEK 0000-0078-1947-SRLR Reload 14 ... Revision 2 Appendix B Decrease In Core Coolant Temperature Events The Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is permitted in GESTAR 11. 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 SRLR Section 11.
In addition, the Inadvertent HPCI start-up event was determined to be non-limiting.
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HOPE CREEK 0000-0078-1947-SRLR Reload 14a Revision 2 Reload 14 Appendix C ARTS Power and Flow Dependent Limits The off-rated power and flow dependent limits in Reference C-I have been verified for Hope Creek Cycle 15 EPU with the exception of the MCPRf limit. For MCPRf, the MCPR is set to the ECCS initial MCPR limit for flows greater than 80.8%. The Safety Limit MCPR for Hope Creek Cycle 15 EPU is 1.08 and the reference Safety Limit MCPR used in Reference C-I is 1.07.
Power Dependent MCPRp and Kp Limits Analyses performed in support of Reference C-I confirmed that the Kp limits provided bound the range between Pbypass and the PLU enabling power level.
Operating Limit MCPRp = Kp
- Operating Limit MCPR( 100)
For P < 24%, No Thermal Limits Required Pbypass = 24% Rated Power Kp for >_24% P POWER LIMIT 24.0 1.561 45.0 1.280 60.0 1.150 100.0 1.000 Power Dependent LHGRFACp Limits Analyses performed in support of Reference C-I confirmed that the LHGRFACp limits provided bound the range between P-bypass and the PLU enabling power level.
LHGRp = LHGRFACp
- LHGRstd For P < 24%; No Thermal Limits Required Pbypass = 24% Rated Power Page 92
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 LHGRFACp for >24% P POWER LIMIT 24.0 0.603 100.0 1.000 Flow Dependent MCPRf Limits Flat portion of MCPRf limit curve is changed from 1.20 (Reference C-I) to 1.25 consistent with ECCS-LOCA Initial Operating MCPR. The MCPRf limit curve is not adjusted for the 0.01 OLMCPR adder (extended operating domain licensing commitments) as the MCPRf curve exceeds the required MCPR by more than the 0.01 at all flow conditions.
Operating Limit MCPRf= MAX(1.25, [A(F)*W(C)/100 + B(F)])
A(F) = -0.598 and B(F) = 1.733 MCPRf limits are based on a 1.08 SLMCPR and the equation coefficients have been scaled appropriately Max Runout Flow = 109.0%
FLOW LIMIT 30.0 1.55 80.8 1.25 109.0 1.25 Page 93
HOPE CREEK 0000-0078-1947-SRLR Reload 14 I Revision 2 Flow Dependent LHGRFACf Limits LHGRf = LHGRFACf* LHGRstd Max Runout Flow = 109.0%
FLOW LIMIT 30.0 0.500 50.0 0.782 82.2 1.000 109.0 1.000
References:
C-I. NEDC-33158P, Fuel TransitionReportfor Hope Creek GeneratingStation, Supplement 1, Revision 1, April 2005.
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HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Appendix D Option B Licensing Basis The NRC has concluded that a statistical approach (Option B) may be used for pressurization events analyzed with ODYN (References D-l and D-2). The GEMINI statistical scram speed is provided in Table D-1.
Table D-1 GEMINI Methods: CRD Control Fraction vs. Time in BWR/2-5 0% 5% 20% 50% 90% 100%
X (sec) 0.200 .324 .694 1.459 2.535 2.804 a (sec) - - .014 .016 .031 .070 - -
The NRC Staff requires that, "in order to take credit for conservatism in the scram speed performance, it must be demonstrated that there is insufficient reason to reject the plant-specific scram speed as being within the distribution assumed in the statistical analysis".
General Electric presents the following procedure as one that satisfies the Staff's objectives for scram conformance. It should be noted that some utilities using ODYN Option B might desire to establish their own conformance procedures.
The procedure consists of testing, at the 5 percent significance level, the scram surveillance data at the 20 percent insertion position which is generated several times each cycle as required in the Reactivity Control System Technical Specification (20 percent insertion is representative of that portion of the scram most affecting the pressurization transient). The unique rod notch position closest to 20 percent (and the appropriately adjusted time of insertion) is expected to be utilized in actual plant application of this generic concept. For most plants, the surveillance requirements are as follows:
(1) all control rods are measured at beginning of cycle (BOC), and (2) X% of control rods are measured every 120 days during cycle (X is plant-dependent and ranges from 10 to 50).
At the completion of each surveillance test performed in compliance with the technical specifications surveillance requirements, the average value of all surveillance data at the 20 percent insertion position generated in the cycle to date is to be tested at the 5 percent significance level against the distribution assumed in the ODYN analyses. The surveillance information which each plant, using this procedure, will have to retain throughout the fuel cycle is the number of active control rods measured for each Page 95
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 surveillance test (the first test is at the BOC and is denoted N1 ; the ith test denoted Ni and the average scram time to the 20 percent insertion position for the active rods measured in test i denoted r,.
The equation used to calculate the overall average of all the scram data generated to date in the cycle is:
n I N, v, i=1 ae n"N I=1i where:
n= number of surveillance tests performed to date in the cycle; ZN, total number of active rods measured to date in the cycle; and ni sum of the scram time to the 20 percent insertion position of all active Z Nir, rods measured to date in the cycle to comply with the Technical i=1 Specification surveillance requirements.
The average scram time, rave, is tested against the analysis mean using the following equation:
Tae <ýcB (2) where:
T*B/ + 1. 6 5 N1 (3)
The parameters ,u and c are the mean and standard deviation of the distribution for average scram insertion time to the 20 percent position used in the ODYN Option B analysis.
If the cycle average scram time satisfies the Equation 2 criterion, continued plant operation under the ODYN Option B operating limit minimum critical power ratio (OLMCPR) for pressurization events is permitted. If not, the OLMCPR for pressurization events must be re-established, based on a linear interpolation between the Option B and Option A OLMCPRs.
The equation to establish the new operating limit for pressurization events is given below:
OLMCPRNe,, = OLMCPRQp,,,B + 'rave rB AOLMCPR (4)
TA TB Page 96
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 where:\rave and rB are defined in Equations I and 3, respectively; TA = the technical specification limit on core average scram time to the 20 percent insertion position.,
AOLMCPR = the difference between the OLMCPR calculated using Option A and that using Option B for pressurization events.
The control fractions presented in Table D-1 are based on a ratio of distance inserted to control rod stroke.
Alternatively, scram times are expressed as a function of notch position. Table D-2 provides notch positions that correspond to approximately 20% control fraction. These notch positions and times can be used in equations 1 through 4.
Table D-2 GEMINI Methods: CRD Notch Positions for TB Determination Notch pPosition (pickup) / (dropout) a (pickup) a (dropout) 39 0.655 0.672 0.016 0.016 38 0.706 0.724 0.016 0.017 37 0.759 0.777 0.017 0.018 36 0.813 0.830 0.018 0.019
References:
D-1. Safety Evaluation for the General Electric Topical Report - Qualification of the One-DimensionalCore TransientModel for Boiling Water Reactors, NEDO-24154 and NEDE-24154-P, Volumes II, 11, and USNRC, 1 June 1980.
D-2. Revised Supplementary Information Regarding Amendment 11 to GE Licensing Topical Report, NEDE-2401 1-P-A, Letter, J. S. Charnley (GE) to H. N. Berkow (NRC), January 16, 1986.
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HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Appendix E Reactor Recirculation Pump Seizure Event The reactor recirculation pump seizure event is analyzed for Single Loop Operation (SLO) at HCGS (Reference E-1). This analysis was performed for the HCGS Cycle 13 transition cycle with GE14 and SV96P fuel in the core and transient analysis inputs that are consistent with the Reload 12/Cycle 13 analyses.
The SLO OLMCPR of 1.51 is required so~that the reference SLO SLMCPR of 1.12 is protected in the event of a seizure of the recirculation pump in the active loop. If the cycle-specific Safety Limit Minimum Critical Power Ratio (SLMCPR) changes then the SLO OLMCPR may be adjusted by the following factor:
(Cycle Specific SLMCPR / 1.12)
Thus, for HCGS Cycle 15 EPU with a SLO SLMCPR of 1.10 the SLO OLMCPR required is:
1.51 * (1.10/1.12) = 1.48 An additional 0.01 penalty is added to the SLO OLMCPR to support EPU operation (Reference E-2).
The resulting SLO OLMCPR is equal to 1.49. In order to protect the required SLO OLMCPR of 1.49 (based on a SLO SLMCPR of 1.10) the TLO full power OLMCPR of 1.30 or greater is necessary.
References:
E-I. Fuel Transition Report for Hope Creek Generating Station, NEDC-33158P, Revision 4, March 2005.
E-2. Final Safety Evaluation for NEDC-33173P Applicability of GE Methods to Expanded OperatingDomains, January 2008.
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HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Appendix F Feedwater Temperature Reduction The feedwater temperature reduction analysis provided in this report is intended to support the Hope Creek license condition 2.C 14. The feedwater heating capacity should be such that at 100% core power, feedwater temperature would be at least 409'F.
Normal operational variation in dome pressure (defined as +/- 10 psi) is acceptable as this.variation has a negligible effect on the OLMCPR.
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HOPE CREEK 0000-0078-1947-SRLR D* I .A 1A , =, ,'n -
Appendix G NEDC-33173P Safety Evaluation - Supplementary Information Requirements 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 15 at the EPU licensed power level, a 70% void profile was used for the calculation of bundle R-factors.
Limitations/Conditions 10 and 11 (Thermal/Mechanical Overpower)
The Thermal Overpower and Mechanical Overpower limiting results have been confirmed to have more than 10% margin to the design limits for all fuel types. Table G-l summarizes the percent margin to the Thermal Overpower and Mechanical Overpower limits.
Table G-1 Margin to Thermal Overpower and Mechanical Overpower Limits Criteria GE14 SVEA96 Thermal Overpower Margin 39% 13%
Mechanical Overpower Margin 39% 22%
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 4.5%.
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HOPE CREEK 0000-0078-1947-SRLR Reload 14 SI I., Revision 2 Appendix H List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 2RPT 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 CLTP Current Licensing Thermal Power 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 Bum HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection Page 101
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Acronym Description ICA Interim Corrective Action ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix Kf Off-rated flow dependent OLMCPR multiplier Kp Off-rated power dependent OLMCPR multiplier 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 NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NOM Nominal Bum NTR Normal Trip Reference OLMCPR Operating Limit MCPR OOS Out of Service OPRM Oscillation Power Range Monitor Pbypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed Pdome Peak Dome Pressure Page 102
HOPE CREEK 0000-0078-1947-SRLR Reload 14 Revision 2 Acronym Description Psi Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PHE Peak Hot Excess PLHGR Peak Linear 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 Burn Page 103