ML053190322

0000-0031-9433-MCAR, Rev. 0, Mixed Core Analysis Report for Hope Creek Extended Power Uprate.

ML053190322
Person / Time
Site:	Hope Creek
Issue date:	04/30/2005
From:	Harding M, Kingston R Global Nuclear Fuel
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LCR H05-01, LR-N05-0330 0000-0031-9433-MCAR, Rev 0
Download: ML053190322 (137)

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Attachment 4 LR-N05-0330 LCR H05-01 0000-0031-9433-MCAR, Rev. 0 Mixed Core Analysis Report (MCAR) for Hope Creek Extended Power Uprate

Global Nuclear Fuel A JoInt VetlIurs of GE.

CT aslba. l&

tchl 0000-0031-9433-MCAR Revision 0 April2005 0000-0031-9433-MCAR, Rev. 0 Mixed Core Analysis Report (MCAR) for Hope Creek Extended Power Uprate Approved: - _ W Approved: %  ?

M.FlE g ic2atkr.- R.tE.rA gston Fuel Engincefln-cic s Customer Account Leader

PSEG Hope Creek Mixed Core Analysis Report Proprietary Information Notice This document is the GNF non-proprietary version of the GNF proprietary report. From the GNF proprietary version, the information denoted as GNF proprietary (enclosed in double brackets) was deleted to generate this version.

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PSEG Hope Creek Mixed Core Analysis Report Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for PSEG Nuclear, LLC. The information contained in this report is believed by GNF-A to be an accurate and true representation of the facts known, obtained or provided to GNF-A at the time this report was prepared.

The only undertakings of GNF-A respecting information in this document are contained in the Contract between PSEG Nuclear, LLC, Global Nuclear Fuel - Americas, LLC and General Electric Company for Fuel Fabrication and Related Components and Services for Hope Creek Generating Station, and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with respect to any such unauthorized use, neither GNF-A nor any of the contributors to this document makes any representation or warranty (expressed or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.

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PSEG Hope Creek Mixed Core Analysis Report Table of Contents 1.0 Introduction and Summary .......................................................... 1

1.1 REFERENCES

............................................................ 2 2.0 Lattice Physics Comparison . ........................................................... 3

2.1 REFERENCES

. 3 3.0 CPPU Base Point Determination ............................................................ 4 3.1 CYCLE 13 SIMULATiON ............................................................ 4

3.2 REFERENCES

............................................................ 4 4.0 Fuel Rod Thermal-Mechanical Compliance .......................................................... 7 4.1 LIMITING THERMAL AND MECHANICAL OVERPOWERS AT OFF-RATED CONDITIONS ...... 7

4.2 REFERENCES

............................................................ 10 5.0 GE14 / SVEA 96+ Demonstration Cycle Analysis Description at the CPPU Condition .......................................................... 13 5.1 RELOAD BUNDLE DESIGNDESCRIPTION ............................................................ 13 5.2 CPPU CORE DESIGN DESCRIPTION . ........................................................... 14 5.2.1 Core ConfigurationDescription.14 5.2.2 Design Limits and Targets.................................................................................... 14 5.3 CPPU PERFORMANCE

SUMMARY

............ ........................................ 15

5.4 REFERENCES

................................................... 15 6.0 Safety Limit Minimum Critical Power Ratio (SLMCPR) ........................................... 35 6.1 DISCUSSION................................................................................................................... 35 6.2

SUMMARY

................................................... 37

6.3 REFERENCES

................................................... 37 7.0 Supplemental Reload Licensing Report (SRLR) at CPPU Condition ........................ 42 iv

PSEG Hope Creek Mixed Core Analysis Report List Of Tables TABLE 4.1 - THERMAL OVERPOWER

SUMMARY

FOR AOO's ........................................................ 11 TABLE 4.2 - MECHANICAL OVERPOWER

SUMMARY

FOR AOO's .................................................. 12 TABLE 5.1 - CORE DESIGN LIMITS .................................................................. 16 TABLE 5.2 - CORE DESIGN MARGIN TARGETS .................................................................. 16 TABLE 5.3 - CPPU RLP

SUMMARY

OF ROD PATTERN RESULTS ................................................... 17 TABLE 5.4 - CPPU RLP HOT EXCESS REACTIVITY .................................................................. 18 TABLE 5.5 - CPPU RLP COLD SHUTDOWN REACnVITY MARGIN ................................................ 19 TABLE 5.6 - CPPU RLP STANDBY LIQUID CONTROL SHUTDOWN MARGIN .................................. 20 TABLE 6.1 - COMPARISON OF THE HOPE CREEK GENERATING STATION CPPU AND CYCLE 13 SLMCPR .................................................................. 38 TABLE 6.2 - STANDARD UNCERTAINTIES ................................................................. 39 TABLE 6.3 - EXCEPTIONS TO THE STANDARD UNCERTAINTIES USED IN HOPE CREEK CPPU AND CYCLE 13 ................................................................. 39 List Of Figures FIGURE 3.1 - HOT CRITICAL EIGENVALUE TRENDS .................................................................. 5 FIGURE 3.2 - COLD CRITICAL EIGENVALUE TRENDS .................................................................. 5 FIGURE 3.3 - CYCLE 13 RLP ROD PATTERN THERMAL DESIGN RATIO RESULTS ........... ................. 6 FIGURE 5.1 - FRESH GE14 RELOAD BUNDLE 2830 CONFIGURATION ............................................ 22 FIGURE 5.2 - CPPU CORE LOADING (QUARTER CORE) ................................................................. 23 FIGURE 5.3 - CPPU REFERENCE LOADING PATTERN CONTROL ROD OPERATING SEQUENCE ....... 24 FIGURE 5.4 - CPPU RLP ROD PATTERN THERMAL DESIGN RATIO RESULTS ................................ 33 FIGURE 5.5 - CPPU RLP HOT EXCESS REACTIVITY ................................................................. 33 FIGURE 5.6 - CPPU RLP COLD SHUTDOWN MARGIN .................................................................. 34 FIGURE 5.7 - CPPU RLP STANDBY LIQUID CONTROL SYSTEM SHUTDOWN MARGIN ................... 34 FIGURE 6.1 - CCPU REFERENCE CORE LOADING PATTERN .......................................................... 40 FIGURE 6.2 - REFERENCE CORE LOADING PATTERN - CYCLE 13 .................................................. 41 V

PSEG;}ope Creek Mixed Core Analysis Report 1.0 Introduction and Summary The implementation of a new fuel design for a General Electric (GE) Boiling Water Reactor (B1WR) follows a two-step process. First, the new fuel desi n is submitted to and approved by the Nuclear Regulatory Commission (NRC) (( 3 )) via the GESTAR II Amendment 22 process. Then, plant-specific analyses are performed to justify use of the new fuel design in an upcoming plant reload. The (( (3) 1 analyses consist of one-time ((

1)) analyses and (( { 'I] analyses.

This report summarizes the results of the (( (3)j] analyses and evaluations for the HCGS Constant Pressure Power Uprate (CPPU) mixed core of GE14 and SVEA 96+ fuel.

HCGS will be loading GE14 fuel at a CPPU condition of 115% of the Current Licensed Thermal Power (CLTP), i.e., CPPU Rated Thermal Power (RTP) of 3840 MWt. The CPPU mixed core described in this report consists of approximately 50% GE14 and 50% SVEA 96+ fuel. The

(( 13))) analyses are documented in the plant and cycle unique Supplemental Reload Licensing Report (SRLR), which is included in this report as Section 7.0. The following information is provided in the SRLR:

• Plant-unique Items

• Reload Fuel Bundles

• Reference Core Loading Pattern

• Calculated Core Effective Multiplication and Control System Worth

• Standby Liquid Control System Shutdown Capability

• Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters

• Selected Margin Improvement Options

• Operating Flexibility Options

• Core-wide AOO Analysis Results

• Local Rod Withdrawal Error AOO Summary

• Cycle MCPR Values

• Overpressurization Analysis Summary

• Loading Error Results

• Control Rod Drop Analysis

• Stability Analysis Results

• Loss-of-Coolant Accident Results In addition to the SRLR, this report also presents the following information that supports the analyses:

• CPPU Base Point Determination

• Fuel Rod Thermal Mechanical Performance Summary for GE14 and SVEA 96+ at CPPU conditions

• CPPU Mixed Core Reload Bundle Design, Core Design and Performance Summary

• CPPU Safety Limit Minimum Critical Power Ratio Summary The Mixed Core Analysis Report for Hope Creek Reload 12 Cycle 13133 included a lattice physics comparison section and a benchmark of previous operating cycles section. These sections are not being repeated in this report; however, the codes and methods topic will be addressed in a codes and methods supplement of this report.

PSEG Hope Creek Mixed Core Analysis Report o )) analyses have been performed and documented in the Fuel Transition (3Hp Report for Hope Creek Generating Station.11'2 The fuel rod thermal-mechanical performance limits for SVEA-96+ and GE14 have been established and are applicable for CPPU RTP operation. The results of the fuel rod thermal-mechanical Anticipated Operational Occurrence evaluations for CPPU RTP are acceptable and demonstrate that compliance with fuel rod thermal-mechanical design and licensing limits will be maintained for CPPU RTP operation.

The CPPU mixed core reload bundle and core design has been completed. As indicated by the performance summary, all core operating and design margins have been dispositioned to be acceptable based on the CPPU reload bundle and core design.

The CPPU SLMCPR calculations, including a comparison to the SLMCPR calculated for Cycle 13 using GNF methods, have been completed. The calculated CPPU SLMCPR values of 1.07 for dual loop operation and 1.09 for single loop operation are appropriate for the Hope Creek CPPU mixed core.

The results presented in the SRLR have been determined using NRC approved methods in accordance with the basis provided in GeneralElectricStandardApplicationfor Reactor Fuel, NEDE-2401 1-P-A-14, June 2000 and the U. S. Supplement, NEDE-2401 1-P-A-14-US, June 2000. The results of the analyses and evaluations contained in the SRLR support the conclusion that HCGS can safely load and operate using GE14 fuel with SVEA 96+ fuel in the CPPU condition.

1.1 References

1. FulelTranisitionReport ForHope Creek GeneratingStation, NEDC-33 158P, Revision 4, March 2005.

2. Fuel TransitionReport ForHope Creek GeneratingStation Supplement 1, NEDC-33158P, Revision 0, March 2005.

3. Mixed Core Analysis Report (MCAR)for Hope CreekReload 12 Cycle 13, 0000-0029-7705-MCAR, Revision 0, April 2005.

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PSEG Hope Creek Mixed Core Analysis Report 2.0 Lattice Physics Comparison The Mixed Core Analysis Report for Hope Creek Reload 12 Cycle 13(11 included a lattice physics comparison section. This section is not being repeated in this report; however, the codes and methods topic will be addressed in a codes and methods supplement of this report.

2.1 References

1. Mixed Core Analysis Report (MCARP for Hope Creek Reload l2 Cycle 13, 0000-0029-7705-MCAR, Revision 0, April 2005.

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PSEG Hope Creek Mixed Core Analysis Report 3.0 CPPU Base Point Determination The operating history of the Hope Creek reactor is tracked by the 3D simulator (PANACI 1).

The results of this tracking are used to determine appropriate hot and cold eigenvalues for core design work as well as to evaluate thermal margin biases, which may exist between the simulator and the process computer. The tracking simulations also provide the base point (starting point) for core design work for the CPPU cycle. Benchmark comparisons from the previous cycles were reported in Section 3 of the Mixed Core Analysis Report for Cycle 13'1fand are not repeated here; however, the benchmark comparisons are still applicable for the selection of the CPPU base point.

3.1 Cycle 13 Simulation This section contains several figures summarizing the results for the current operating cycle, Cycle 13, which is the first loading of GE14 fuel. Figures 3.1 and 3.2 summarize the hot and cold design basis eigenvalues for Cycle 13 and CPPU.

The hot eigenvalue selected as Cycle 13 design basis is based on a combination of the data for previous cycles at Hope Creek as well as GNF's methods experience with similar size and power BWRs. The eigenvalue data for previous cycles is well behaved and relatively tightly packed.

GNF would expect the eigenvalue to behave as shown by the "GE14 Equilibrium" curve as the fraction of GE14 fuel is increased in future cycles.

The cold eigenvalue selected as the Cycle 13 and CPPU design bases are again based on a combination of cold critical measurements in the previous cycles as well as GNF's method experience with its BWR fleet. Generally the cold eigenvalue basis is selected to conservatively bound the measured data rather than fit through the data as with the hot eigenvalue.

Figure 3.3 shows the simulation of MFLCPR, MFLPD, and MAPRAT for Cycle 13. Table 5.2 shows the design basis margin for these thermal limits.

3.2 References

1. Mixed Core Analysis Report (MCAR) for Hope Creek Reload l2 Cycle 13, 0000-0029-7705-MCAR, Revision 0, April 2005.

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PSEG Hope Creek Mixed Core Analysis Report Figure 3.1 - Hot Critical Elgenvalue Trends (3)))

Figure 3.2 - Cold Critical Eigenvalue Trends 5

PSEG Hope Creek -. -

Mixed Core Analysis Report

((

{3)))

Figure 3.3 - Cycle 13 RLP Rod Pattern Thermal Design Ratio Results 6

PSEG Hope Creek Mixed Core Analysis Report 4.0 Fuel Rod Thermal-Mechanical Compliance The fuel rod thermal-mechanical performance limits for the SVEA 96+ and GE14C fuel designs for application in the Hope Creek Generating Station were established in the Cycle 13 MCAR111.

The fuel rod thermal-mechanical performance limits established in Reference [1] are applicable to CPPU RTP operation at HCGS with one addition. HCGS has implemented the ARTS/MELLLA bases as a prerequisite of the CPPU. Consequently, the ARTS based off-rated LHGR or MAPLHGR limits have been incorporated into HCGS's design and licensing basis (off-rated limits required to replace the APRM trip setdown requirement which was deleted as part of licensing and implementation of ARTS/MELLLA at HCGSI2 l). Therefore, Section 4.1 defines the limiting thermal and mechanical overpowers at off-rated conditions based on the ARTS off-rated limits.

The reference loading pattern (RLP) of the CPPU demonstration cycle shown in Section 5 must meet the criteria specified in Section 4.1 and in Reference [1]. Tables 4.1 and 4.2 provide a summary of overpower results based on the CPPU mixed core of SVEA 96+ and GEl 4 at CPPU RTP conditions including a comparison to the Cycle 13 mixed core results at CLTP. All acceptance criteria are met and compliance with the fuel rod thermal-mechanical design and licensing limits is ensured.

4.1 Limiting Thermal and Mechanical Overpowers at Off-Rated Conditions The method for determining thermal and mechanical overpowers defined in Section 4.2.2 of Reference [1] and the limits defined in Tables 4.4, 4.5, 4.6 and 4.7 of Reference [1] apply to evaluations of rated events. For off-rated events, the same basic limits apply, i.e., the fuel shall not experience fuel centerline melting and the cladding plastic strain during the event shall not exceed 1%. For the ARTS/MELLLA bases, these criteria are met by limiting the initial steady-state power from which the off-rated event can be initiated. With the removal of the APRM trip setdown requirement, steady-state operating limits for off-rated conditions are defined through the use of a reduction factor applied to the rated power fuel thermal-mechanical limits. These reduction factors are presented as a function of reactor power and flow. If the plant fuel thermal-mechanical bases are protected with the MAPLHGR, then the MAPFACp and MAPFACF reduction factors are used. If the plant fuel thermal-mechanical bases are protected with the LHGR, then LHGRFACp and LHGRFACF reduction factors are used. The resulting MAPLHGRp/MAPLHGRF or LHGRp/LHGRF limits are set such that an AOO initiated from the off-rated condition will not result in fuel melt or 1% cladding plastic strain.

The following expressions and definitions for determining the reduction factors assume protection is provided by the MAPLHGR. If the fuel thermal-mechanical basis is protected by the LHGR, the expressions and definitions are the same substituting LHGRFACp and LHGRFACF for MAPFACp and MAPFACF, respectively.

The thermal and mechanical overpowers for the events are defined in Section 4.2.2 of Reference

[1]. The required thermal and mechanical MAPLHGR reduction factors are then determined from:

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PSEG Hope Creek Mixed Core Analysis Report For P>PByp versus power:

MAPFACO =Min[1.O. OPhmit+100] (4.1)

P [ pp h+100]

MAPFACp =Min [10 o2°r ] (4.2)

For P>PBYp versus flow:

MAPFACh =Min[1.0, OpF +1]00 (4.3)

MFF rMlO, +I MAPIFAC'-' =Min [I.o0, (4.4) where:

PBYP = The reactor power level below which the turbine stop valve position scram is bypassed.

MAPFAC," = The MAPLHGR reduction factor versus power due to thermal overpower during the event for a particular fuel type.

MAPFACpk = The MAPLHGR reduction factor versus power due to mechanical overpower during the event for a particular fuel type.

MAPFACh = The MAPLHGR reduction factor versus flow due to thermal overpower during the event for a particular fuel type.

MAPFAC' = The MAPLHGR reduction factor versus flow due to mechanical overpower during the event for a particular fuel type.

Opat = The limit for thermal overpower for the event from Tables 4.4, 4.5, 4.6 or 4.7 of Reference [1) depending on the event being evaluated.

Opp = The thermal overpower for the event at reactor power P for a particular fuel type.

Opnt, = The limit for mechanical overpower for the event from Tables 4.4, 4.5, 4.6 or 4.7 of Reference [1) depending on the event being evaluated.

OPp e = The mechanical overpower for the event at reactor power P for a 8

PSEG Hope Creek Mixed Core Analysis Report particular fuel type.

OPF= The thermal overpower for the event at reactor flow F for a particular fuel type.

OPTS = The mechanical overpower for the event at reactor flow F for a particular fuel type.

Different equations for MAPFAC Th and MAPFACFh are defined for P < P Since the scram is bypassed under these conditions, the resulting transient is significantly different than would occur for the same event at rated conditions. Therefore, the off-rated basis for P 5 Pyp is to assure conformance to the absolute fuel rod thermal-mechanical limits rather than to assure that the off-rated transient is no more severe than the transient at rated conditions. Furthermore, it is unlikely that operation at this low power condition will extend for the long time periods required to adversely impact the overpower to 1% plastic strain. Therefore, conformance to thermal overpower limit assures conformance to the mechanical overpower limit and MAPFAC"" equals MAPFACTh for P 5 PBp. Also, for P 5 PByp, the limit for thermal overpower is taken as the thermal overpower limit for slow events from Tables 4.4 and 4.5 of Reference [1] for all events, since the event characteristics for fast events are different with the scram bypassed and the limits defined in Tables 4.6 and 4.7 of Reference [l] are not applicable.

For P 5 PB.p versus power:

MAPFACp =Min 1.0, OPTh 1 O+100 (4.5)

L QPP~ +00J MAPFACp'=Min[ 1.0, Opp =

Th1+00]"1+100 (4.6)

For P 5 PBYP versus flow:

MAPFAC~h =Mmn[l.O, Opt W+1001 (4.7)

F oP~Th+1001 MAPFAC,"'=Min 1.0, OPj + I00 (4.8) where:

OpTh = The limit for thermal overpower from Table 4.4 and Table 4.5 of Reference [1].

At each core power and flow point, the limiting initial steady-state MAPLHGR reduction factor 9

PSEG Hope Creek Mixed Core Analysis Report is then determined from:

MAPFACp=Min[MAPFACTh, MAPFACe] (4.9) from power dependent transient evaluations, and MAPFACF =Min [MAPFACTh, MAPFACr] (4.10) from flow dependent transient evaluations.

4.2 References

1. Mixed Core Analysis Report (MCAR) for Hope CreekReloadl2 Cycle 13, 0000-0029-7705-MCAR, Revision 0, April 2005.

2. Hope Creek GeneratingStationAPRM/RBM/Teclnzical Specifcations /Maxintim Extended LoadLine Limit Analysis (ARTS&MELLLA), NEDC-33066P, Revision 2, February 2005.

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PSEG Hope Creek Mixed Core Analysis Report Table 4.1 - Thermal Overpower Summary for AOO's (3)))

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PSEG Hope Creek Mixed Core Analysis Report Table 4.2 - Mechanical Overpower Summary for AOO's (3)))

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PSEG Hope Creek Mixed Core Analysis Report 5.0 GE14 / SVEA 96+ Demonstration Cycle Analysis Description at the CPPU Condition This section of the MCAR provides the results of the Reference Loading Pattern (RLP) core operation simulation of the CPPU RTP mixed core of GE14 and SVEA 96+ fuel. The RLP is developed to meet all design bases set for the CPPU cycle. The RLP is the basis for the licensing calculations that are documented in the Supplemental Reload Licensing Report (SRLR) that is reported in Section 7.0 of this report.

5.1 Reload Bundle Design Description The reload bundle nuclear design process is closely coupled with the core nuclear design process in demonstrating compliance with safety and performance criteria. An iterative process was used between bundle design and core design to obtain an optimal balance among performance objectives while satisfying all safety criteria.

This process resulted in a one-stream GE14 reload design strategy using a GEI4 bundle with axial and radial isotopic configurations shown in Figure 5.1. The average content and specific distributions of gadolinium and enriched uranium used for the GE14 bundle design was selected to accomplish the following goals:

1. Meet PSEG specified cycle energy and operating strategy for an 18-month operating cycle. The average enrichment of the fuel bundle was 3.96 wtt% U235. The gadolinium loading of 4.0 and 6.0 vet% Gd2O3 was chosen to compensate for the natural decrease in hot excess reactivity of the legacy fuel resulting in a rclatively flat overall core hot excess reactivity throughout the majority of the operating cycle and to control radial and axial power shapes without leaving significant amounts of undepleted gadolinium at the end of the cycle.

2. Maintain adequate thermal margins. Lattice enrichment and gadolinium distributions were optimized to obtain desired relative rod-to-rod thermal performance. This included analysis of the local power peaking factors used to calculate linear heat generation rates and the bundle R-factors used to calculate critical powver ratios. These parameters were minimized, consistent with other goals, throughout the bundle exposure range associated with expected high power operation for these GE14 designs. Relative powers for gadolinia rods were suppressed to provide adequate margin to mcet thcrmal-mcchanical design requirements.

3. Maintain adequate reactivity margins. To demonstrate one stuck rod sub-criticality, design margin to criticality is calculated with the 3D simulator (PANACEA) in conjunction with critical eigenvalue determinations at the reactor during plant startup. Reactivity control of the fresh fuel is accomplished through the choice of gadolinia design. Cold shutdown margin at beginning of cycle is influenced primarily by the number of gadolinia rods used, while cold shutdown margin later in the cycle is influenced primarily by the concentration of gadolinia used.

4. Provide a realistic SVEA 96+ / GE14 mixed core design basis at CPPU RTP that can be compared to the equilibrium GE14 core that was established as the core design basis for the HCGS Power Uprate Safety Analysis Reporti 11 . The fuel bundle design and target rod pattern specifications have been validated in accordance with GNF Technical Design Procedures to be acceptable for actual use in a mixed core reload. In addition, the fuel bundle design and target rod pattern specifications are comparable to the GE14 equilibrium fuel cycle that was utilized in Reference [1].

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PSEG Hope Creek Mixed Core Analysis Report 5.2 CPPU Core Design Description 5.2.1 Core Configuration Description Changing the design of the fuel utilized in a nuclear power reactor requires a wide range of analyses to support acceptance relative to operational and safety requirements. The purpose of the core design analysis is to demonstrate feasibility of operation, assure compliance with safety limits and provide operating state points for further safety analyses.

Hot operating analyses with projected control rod patterns were performed at different burn-up points through the CPPU cycle to demonstrate that the specified operating strategies can be supported and that all operating limits can be satisfied. These analysis conditions also provide the beginning state points for other safety analyses. Cold shutdown calculations have been performed throughout the cycle to demonstrate compliance with the stuck control rod criteria.

5.2.2 Design Limits and Targets The target core flow range is 97.0 - 105.0% rated flow. The critical kfr design target for hot, rated operation is shown in Figure 3.1. The distributed critical kfr design target for cold shutdown evaluations is shown in Figure 3.2. Core design limits are provided in Table 5.1 and parameters for tracking the core design limits are provided in Table 5.2.

The cold critical kff values are based on the local, cold, critical keff predicted for CPPU operation. The local cold critical kfrr= (distributed cold critical kff) - 0.003, where the distributed cold, critical kzir are based on observed plant data from in-sequence cold critical cases.

MCPR margin is tracked via the parameter MFLCPR; MLHGR (pellet power margin) is tracked via the parameter MFLPD; and, nodal power margin is tracked via the parameter MAPRAT, where:

MFLCPR= MCPR Operating Limit (5.1)

MCPR MFLPD = Peak LHGR (5.2)

LHGR Operating Limit MAPRAT= Maximum Average Planar LHGR (5.3)

MAPLHGR Operating Limit 14

> PSEG Hope Creek Mixed Core Analysis Report 5.3 CPPU Performance Summary The resultant CPPU RLP for the upper left quarter core loading configuration is provided in Figure 5.2a. The table below Figure 5.2 lists all fuel types and how many of each type are included in the CPPU core configuration.

Table 5.3 compares the calculated thermal limit core performance parameters to the Table 5.2 thermal limit design margin targets. Table 5.4 provides hot excess reactivity vs. cycle exposure.

Tables 5.5 and 5.6 compare cold shutdown and standby liquid control system (SLCS) reactivity performance parameters, respectively, to the Table 5.2 reactivity limit design margin targets.

Figure 5.3 provides the CPPU cycle core control blade configuration for the upper left quadrant",

calculated thermal marginsc and kejreigenvalue as a function of cycle exposure. Figure 5.4 plots the thermal limit parameters vs. cycle exposure. Figure 5.5 plots core hot excess reactivity vs.

cycle exposure. Figures 5.6 and 5.7 plot cold shutdown and SLCS reactivity margins, respectively, versus cycle exposure.

As is seen in the above referenced tables and figures, all core operating and design margins are met by the CPPU RLP, except for MFLPD at BOC and for the 4500-7500 MWOD/ST exposure range. The MFLPD exceptions have been dispositioned to be acceptable based on the previous cycle benchmark comparison for MFLPD at these exposure points.

5.4 References

1. Safety Analysis ReportforHope CreekConstaitiPressutrePower Uprate, NEDC-33076P, Class III (Proprietary), March 2005.

• The RLP was evaluated on a quarter-core basis.

b All control blade patterns are quartcr-core mirror symmetric.

'Minimum margin in quarter-core reported.

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... -;PSEG Hope Creek Mixed Core Analysis Report Table 5.1 - Core Design Limits Minimum Critical Power Ratio (MCPR) - Design GE14 operating limit for RLP core design (Actual operating (( I') I BOCto 10 GWd/ST limits as determined by reload analyses are presented (( 3)11 after I0 Gltd/ST in Section 7.0) SVEA 96+

(( { BOC to 10 GWd/ST Maximum Linear Heat Generation Rate (MLHGR)

[after 10 GWd/ST Fuel Dependent Limit in kNV/ft

[I {I)) kNV/ft (GE14)

(( (3I)) kW/ft (SVEA 96+)

Cold Shutdown Margin - One Stuck Control Rod 1.0% Ak Boron Injection Shutdown Margin 1.0% Ak Peak Pellet Exposure (( 3'))) GWd/MTU (GE14) rr(( {3i G31d1 M (SVEA 96+)

Table 5.2 - Core Design Margin Targets MFLCPR 0.93 MFLPD_0.85 MAPRAT 0.89 Cold Shutdown Margin - One Stuck Control Rod 1.3% Ak Boron Injection Shutdown Margin 1.0% Ak Peak Pellet Exposure GWd/MTU (GE14)

[__ ~IT GWd/MTU (SVEA 96+)

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PSEG Hope Creek Mixed Core Analysis Report Table 5.3 - CPPU RLP Summary of Rod Pattern Results 17

PSEG Hope Creek Mixed Core Analysis Report Table 5.4 - CPPU RLP Hot Excess Reactivity 18

PSEG Hope Creek Mixed Core Analysis Report Table 5.5 - CPPU RLP Cold Shutdown Reactivity Margin

• ^* CARI AND SDM RESULTS ***

CASE CONVERGENCE: PASSED DESIGN CRITERIA: MET 11

{3)))

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PSEG Hope Creek Mixed Core Analysis Report Table 5.6 - CPPU RLP Standby Liquid Control Shutdown Margin SLCS ANALYSIS - PANACEA SLCS RESULTS PLANT NAME HOPE CREEK 1 EIS CODE KT1 CYCLE NUMBER :14 METHOD TYPE :11 PANACEA VERSION :PANAC1IV ANALYSIS TYPE  : STATEPOINT SDM REQUIREMENT :0.010 20

PSEG Hope Creek Mixed Core Analysis Report Table 5.6 - CPPU RLP Standby Liquid Control Shutdown Margin SDM REQUIREMENT (MOST RESTRICTIVE VALUE): 0.010 SDM REQUIREMENT USED (DTA OVERLAY) :0.010 Il 21

PSEG Hope Creek Mixed Core Analysis Report (3)))

Figure 5.1 - Fresh GE14 Reload Bundle 2830 Configuration 22

PSEG Hope Creek Mixed Core Analysis Report

((

Figure 5.2 - CPPU Core Loading (Quarter Core) 23

." PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence II (3)))

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PSEG -Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence

((

13) ))

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.3- A PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence

[1 (3)))

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. :>PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence II (3)jj 27

PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence

((

(3) ))

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PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence

((

(3) ))

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PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence

((

(3)))

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PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence

[3 (3) 11 31

PSEG Hope Creek Mixed Core Analysis Report Figure 5.3 - CPPU Reference Loading Pattern Control Rod Operating Sequence

((

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.- 1:1' PSEG Hope Creek . ....

Mixed Core Analysis Report (3)))

Figure 5.4 - CPPU RLP Rod Pattern Thermal Design Ratio Results Figure 5.5 - CPPU RLP Hot Excess Reactivity 33

PSEG Hope Creek Mixed Core Analysis Report

((

{31))

Figure 5.6 - CPPU RLP Cold Shutdown Margin (3) ]

Figure 5.7 - CPPU RLP Standby Liquid Control System Shutdown Margin 34

PSEG Hope Creek ': _

Mixed Core Analysis Report 6.0 Safety Limit Minimum Critical Power Ratio (SLMCPR)

This section of the MCAR provides the results of the SLMCPR evaluation of the Reference Loading Pattern that represents the CPPU RTP mixed core of GE14 and SVEA 96+ fuel, as reported in Section 5.0 of this report. The purpose of the evaluation is to determine the minimum allowable MCPR during the most limiting full core transients under which at least 99.9% of the rods in the core would be expected to avoid boiling transition. The minimum allowable MCPR established in this way is defined as the safety limit minimum critical power ratio (SLMCPR).

6.1 Discussion The Safety Limit Minimum Critical Power Ratio (SLMCPR) evaluations for the Ho e Creek CPPU cycle were performed using NRC approved methodology and uncertainties. 11 Table 6.1 summarizes the relevant input parameters and results for CPPU operation. Additional information is provided in response to NRC questions related to similar submittals regarding changes in Technical Specification values of SLMCPR. NRC questions pertaining to how GE14 applications satisfy the conditions of the NRC SER' 11have been addressed in Reference [2].

Other generically applicable questions related to application of the GEXLI4 correlation, and to the applicable range for the R-factor methodology, are addressed in Reference [3]. Items that require a plant/cycle specific response are presented below.

Previously, the SLMCPR was calculated on the upper boundary of the power/flow operating map only at 100% flow / 100% power (rated flow/rated power) with limiting control blade patterns developed at the rated flow/rated power point. This approach had been shown in NEDC-32601P-A to result in conservative SLMCPR evaluation values. As reported in Reference [4], recent SLMCPR evaluations performed by GNF have shown that limiting control blade patterns developed for less than rated flow at the rated power condition sometimes yield more limiting bundle-by-bundle MCPR distributions and/or more limiting bundle axial power shapes than the limiting control blade patterns developed at the rated flow/rated power evaluation point. Consequently, in addition to the rated flow/rated power evaluation point, an SLMCPR calculation has been performed for Hope Creek at a lower flow/rated power evaluation point. The assumed Hope Creek Cycle 13 minimum allowable core flow at rated power is 76.6%

rated flow. However, to account for future operation at lower flow/CPPU conditions, SLMCPR evaluations were performed at a reduced core flow rate of 94.8% rated flow at the CPPU condition for the same exposure points calculated for the rated flow/CPPU evaluations.

The core loading information for Hope Creek CPPU is provided in Figure 6.1. The actual core loading information for Hope Creek Cycle 13 is provided in Figure 6.2.

In general, the calculated safety limit is dominated by two key parameters: (1) flatness of the core bundle-by-bundle MCPR distributions, and (2) flatness of the bundle pin-by-pin power/

R-factor distributions. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR. The value of these parameters for Hope Creek CPPU is summarized in Table 6.1 as the MIP (MCPR Importance Parameter) and the RIP (R-factor Importance Parameter), respectively.

35

. .PSEG Hope Creek Mixed Core Analysis Report The impact of the fuel loading pattern differences on the calculated SLMCPR is correlated to the values of MIP and RIP. The calculated MIP value for the Hope Creek CPPU core at EOR using a limiting rod pattern is (( n3) ))

Pin-by-pin power distributions are characterized in terms of R-factors using the NRC approved methodology.15 3 For the Hope Creek CPPU cycle limiting case analyzed at EOR, the weighted RIP value, considering the participation of the contributing bundles, was calculated to be The revised power distribution methodology was used for the Hope Creek CPPU analysis. This methodology has been justified, reviewed and approved by the NRC (reference NEDC-32601P-A). When applying the revised model to calculate a lower SLMCPR, the conservatism that remains was reviewed, approved and documented by the USNRC. It was noted on page A-24 of NEDC-32601P-A ((

(3)))

The SLMCPR was calculated for the Hope Creek CPPU condition using the reduced power distribution uncertainties described in Reference [1].

Table 6.1 summarizes the relevant input parameters and results of CPPU operation evaluated at the condition of 94.8% rated flow/rated power. The SLMCPR values were calculated for Hope Creek using uncertainties that have been previously reviewed and approved by the NRC as listed in Table 6.2 and described in Reference [1] and, where warranted, higher plant-cycle-specific uncertainties as listed in Table 6.3. A ((

(3))) consistent with current GNF fuel operation. For the Hope Creek CPPU lower flow evaluations, the Core Flow Rate and Random effective TIP reading uncertainties were (3)))

These calculations use the GEXLI4 correlation for GE14 fuel and GEXL80 correlation for SVEA 96+ fuel (Reference [6]). ((

{3}))

The Two Loop and SLO SLMCPR values calculated for the Hope Creek CCPU cycle are shown in Table 6.1. The calculated SLO SLMCPR is 1.09.

36

JPSEG Hope Creek Mixed Core Analysis Report 6.2 Summary The calculated 1.07 SLMCPR and 1.09 SLO SLMCPR for Hope Creek CPPU operation are consistent with expectations given the ratios for MIP and RIP that have been calculated and the use of the reduced uncertainties described in Reference [1]. Correlations of MIP and RIP directly to the calculated SLMCPR have been performed for this plant/cycle which show that these values are appropriate when the approved methodology and the reduced uncertainties given in NEDC-32601P-A and NEDC-32694P-A are used.

Based on all of the information and discussion presented above, it is concluded that a 1.07 SLMCPR and 1.09 SLO SLMCPR for the Hope Creek CPPU core are appropriate for the cycle operation.

6.3 References

1. Letter, Frank Akstulewicz (NRC) to Glen A. Watford (GE), "Acceptance for Referencing of Licensing Topical Reports NEDC-32601P, Methodology and Uncertaintiesfor Safety Limit MCPR Evaluations;NEDC-32694P, Power Distribution UncertaintiesforSafety Limit MCPR Evaluation;and Amendment 25 to NEDE-24011-P-A on Cycle Specific Safety Limit MCPR," (TAC Nos. M97490, M99069 and M97491), March 11, 1999.

2. Letter, Glen A. Watford (GNF-A) to U. S. Nuclear Regulatory Commission Document Control Desk with attention to R. Pulsifer (NRC), "Confirmation of l0xl0 Fuel Design Applicability to Improved SLMCPR, Power Distribution and R-Factor Methodologies", FLN-2001-016, September 24, 2001.

3. Letter, Glen A. Watford (GNF-A) to U. S. Nuclear Regulatory Commission Document Control Desk with attention to J. Donoghue (NRC), "Confirmation of the Applicability of the GEXL14 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GE14 Fuel", FLN-2001-017, October 1, 2001.

4. Letter, Jason S. Post (GE Energy) to U.S. Nuclear Regulatory Commission Document Control Desk, "Part 21 Reportable Condition and 60-Day Interim Report Notification:

Non-conservative SLMCPR", MFN-04-081, August 24, 2004.

5. Letter, Thomas H. Essig (NRC) to Glen A. Watford (GE), "Acceptance for Referencing of Licensing Topical Report NEDC-32505P, Revision 1, R-Factor CalculationMethodfor GE1J, GE12 and GEJ3 Fiel," (TAC Nos. M99070 and M95081), January 11, 1999.

6. GEXL80 Correlationfor SVEA 96+ Fuel,NEDC-33107P, Revision 0, Class III, September 2003.

7. Letter, Glen A. Watford (GNF-A) to U. S. Nuclear Regulatory Commission Document Control Desk with attention to J. Donoghue (NRC), "Final Presentation Material for GEXL Presentation - February 11, 2002", FLN-2002-004, February 12, 2002.

37

;.&. PSEG Hope Creek Mixed Core Analysis Report Table 6.1 - Comparison of the Hope Creek Generating Station CPPU and Cycle 13 SLMCPR DESCRIPTION Hope Creek Hope Creek Hope Creek Hope Creek

______________ Cycle 13 Cycle 13 CPPU CPPU Number of Bundles in Core 764 764 764 764 Limiting Cycle Exposure Point' EOR EOR EOR EOR Cycle Exposure at Limiting Point 10472 10472 12125 12125 (MWd/MTU) (EOR-1467) (EOR-1467) (EOR-1 102) (EOR-1 102)

Core Flow, % Rated 100.0 76.6 100.0 94.8 Reload Fucl Typc GE14 GE14 GE14 GE14 Latest Reload Batch Fraction, % 21.5 21.5 33.0 33.0 Latest Reload Average Batch Weight % 4.02 4.02 3.96 3.96 Enrichment Core Fuel Fmction for GE14 ()21.5 21.5 54.5 54.5 Core Fuel Fraction for SVEA 96+ (O) 78.5 78.5 45.5 45.5 Core Avcragc Weight % Enrichment 3.63 3.63 3.81 3.81 Core MCPR (for limiting rod pattern) 1.42 1.38 1.40 1.42 MCPR Importance Parameter, MIP [1 {3Ij]

R-factor Importance Parameter, RIP [3II MIPRIP 13)))

Power distribution methodology RevisedNEDC-3260 1P-A Revised NEDC-3260 1P-A Power distribution uncertaintv Reduced NEDC-32694P-A Reduced NEDC-32694P-A Non-power distribution uncertainty Revised NEDC-32601P-A Revised NEDC-32601P-A Calculated Safety Limit MCPR (Two Loop) 1.05 1.06 1.06 1.07 Calculated Safety Limit MCPR (SLO) 1.06 1.07 1.09 1.09 a End of Rated (EOR) is defined as end-of-cycle all rods out, lOO116 power/ 100% flow and normal feedwater temperature. The actual analysis is performed prior to EOR in order to have sufficient control rod dernsityto force some bundles near to the OLUICPR.

38

PSEG Hope Creeks Mixed Core Analysis Report Table 6.2 - Standard Uncertainties Hope Creek Hope Creek Hope Creek Hope Creek DESCRIPTION Cycle 13 Cycle 13 CPPU CPPU 100% Flow 76.6% Flow 100% Flow 94.8% Flow Non-power Revised Revised Revised Revised Distribution NEDC- NEDC- NEDC- NEDC-32601P-Uncertainties 32601P-A 32601P-A 32601P-A A Core flow rate (derived 2.5 Two Loop 2.5 Two Loop 2.5 Two Loop 2.5 Two Loop from pressure drop) 6.0 SLO 6.0 SLO 6.0 SLO 6.0 SLO Individual channel flow 13) (3) 3 3 ]'3 area Individual channel friction 5.0 5.0 5.0 5.0 faictor Friction factor multiplier 3 31 13 I3 1"I Reactor pressure {3 3] I 3 (( "II "I I]

Core inlet tempcrature 0.2 0.2 0.2 0.2 Feedwater temperature (( (3I i (3) ]3 Feedwater flow rate (( (3))) ([ 3 131 (( (3) ]I Power Distribution Reduced NEDC- Reduced NEDC- Reduced NEDC- Reduced NEDC-Uncertainties 32694P-A 32694P-A 32694P-A 32694P-A GEXL R-factor "I(3 11 { 3,]I "I} ] [ 1 3, ]I Random effective TIP 1.2 Two Loop 1.2 Two Loop 1.2 Two Loop 1.2 Two Loop reading 2.85 SLO 2.85 SLO 2.85 SLO 2.85 SLO Systematic effective TIP (3[ ] 3 1 ] ] (31))

reading "I))

Integrated effective TIP [1() 3) (3) "3I reading Bundlc power (( (3j [ ] (( (3)j] 3]

Effective total bundle (( 3

) [ 13 )j [ (31j (( 131 power uncertainty _ ] _] _ __ ____[___________

Table 6.3 - Exceptions to the Standard Uncertainties Used in Hope Creek CPPU and Cycle 13 Reactor pressure 2.04 2.04 2.04 2.04 Core Flow Rate [ 3 i (3.

Random Effective TIP Reading IL13. 11-.3_

GEXLR-factor t3] If [1 '3J]1 ii 13 '1 39

PSEG Hope Creek Mixed Core Analysis Report 60 B EB 1 EfE 1BEE 58 955 .EIFEI EM EMEm l 56 EE1A1719E E G BElGE 1 54 [D El7 [3D7E- ORE112 WI IEl BEl E-E1s E-E1m mEPOI EE]I 48~~~ m w C ZrfG EEEl] ]l EG ] ED] l 8131E ElE13 46 40 44 1M1 B

[D

[ E1=EC3 D9W El E19l9 9WG 1E1100E] CJIEG21El EE3E1 ElG E11El El 5 ME]EEi512EHAMMwE]l Fip9 BGW _

42 95 5 999 1~ 9IS1 951 [E~I 9195 7E3 j9 99 l95lM OO919 9E11 E79 38 42 36 AF 01 M1_ __ E 3ElmEl EVE] El 9El 90

-E1Em70 -EIN-D 1El E-IFE ElF 34 32 ITI G 1 9[E E)ME 919 91G E19JE19 [19 9 [9E1E]E [

30 E 31999)991991991991 519~ ~ ~ SzmSmmzEm ~ ~ ~ ~

28 AG 91GG [9[EG89 919GF9l9G199I991 24 28 ITIP PBIP 17 [EIP E1 171 ENDC TCC ml 1i 1PlBr G1mIff]

wM EEN ~SE 1E]IM ElSBM lEJEJ 120 - - 0 -

E100 E1[ 1[D 7ENff[E1E1 MEm11 mEl Em1 3E1B[

16 1PM3 F1 G 0 G Mm QQm B 8 8EE G f EI 1 0 E 6 ElT EI9 El99ll GB G 99 5 E 2 BAl 179I Ej9 11 1 3 5 7 9 11 131t51t71t921 23 25272931 333537 3941 4345 47 49 51535557 59 Code A

__ IIJLoaded Bundle Name SVEA96-PI OCASB360-12GZ-568U-4WR-150-T6-2656 Number 40 Cycle Loaded 11 B SVEA96-P1 OCASB36D-1 2G5.0-568U-4WR-1 50-T6-2657 76 11 C SVEA96-Pl OCASB361 -14GZ-568U-4WR-1 50-T6-2658 168 12 D SVEA96-P1 OCASB360-12G5.5/2G2.5-568U-4WR-1 50-T6-2659 64 12 E GE14-P1 OCNAB402-4G6.0/16G4.0-1OOT-150-T6-2757 56 13 F GE14-P1 OCNAB402-5G6.0114G4.0-1OOT-150-T6-2758 108 13 G GE1 4-P1 OCNAB396-16GZ-1 OOT-1 50-T6-2830-LICENSING 252 14 Figure 6.1 - CCPU Reference Core Loading Pattern 40

PSEG Hope Creek Mixed Core Analysis Report 60 EIII ll iAI A A A A MO 8I8I8 58 MM[ , MM j An 56 8MMM MME E 54 ElI TEl ElElE ST ET E- El ET DElrbm ETl 7EIElt E 52 OlM EI1 so 0 E E9l' El-- 9 8 48 Egl E7E -E17-E] 1 -E17-E17-EE1OM]-lE lE 48 AlEEDES3SESDESEDEU CO: TE MM t ETS f3 42p mlE5 -I-[ 7-l R[ El3MIE0 El E-IEM M0 0 46 ElEl El1[El El El E] E)El [IE El r[ 50~ mEEO M3E rME lE3llmmEl 34 FE11[f F]I E]JE] QE)I MME E11[p] EJlS1EI ME EIIE E EEI MR MIME MMl MI2IE EElI 32 E E71 E]ll1111 El mE B 112 E 30 EEA]IUE] T E LI 01981 E10EI9P 9L319BI H~ TE]17117 ~MM QTF1 9IZ Em 918__9 TEl EISTElDO3L CE '8E9' IDT3L9 ElEl ULE '8 26 EIIEI [03 [DE]E El El El E1E E17E EmlE EIIE EIIE E-IE EIIE [DIE EN 24 3F,~g1C 18 It s MM T 8Egl~f[DI]I ElS Elm ElS DILI Elm

]E ElE ElE [DIE]M mETE SE10 m El SE l El EIF 12 EIIJ El ElEl El ElEl El El EIE EE ElEl Elm El 4 0E ME lF EVE I 28 [DE I EJ MEJ[i MMl[ IMlIEM EhEIM I M2E] EIhE][ E311M M3E EI[ E jE 1626 E B B7m0~ S10 BT Sm FSm E, 0TE I E]

au~SIBFH DE I t 20 I110DTM @]E MlEl OM MIDE EIM 13EI EI EI 9 170M 12 E'l ElE Dl DEl Efi ElcmEIZ 00]ElElE 1 3 5 7 9 11 1315 17 19212325 27 2931 33 3537 394143 45 47 495153 5557 59 Code Bundle Name Number Cydle Loaded Loaded A[SVEA96-PIOCASB326-1 l Z-5G8U-4WR-1lS-T6-2654 89 10 B SVEA96-PlOCASB326-1 1G4 .5-568U-4W-150-T6-2655 38 10 C SVEA96-PlOCASB360-12GZ-568U-4WR-150-T6-2656 166 11l D SVEA96-P1 OCASB360-l2G5.0-568U-4WR-150-T6-2657 69 11 E SVEA96-PlOCASB361-14GZ-568U-4WVR-l50-T6-2658 164 12 F SVEA96-Pl OCASB360-12G5.5/2G2.5-568U-4WR-150-T6-2659 62 12 G GE14-PlOCNAB402-4&6.0/16G4.0-1lT-150-T6-2757 56 13 H GE14-P1OCNAB102-5G6.0/14G4.0-OOT-150-T6-2758 108 13 I SVEA96-PIOCASB326-1 1GZ-568U-4WR-150-T6-2654 2 10 J SVEA96-PIOCASB326-1 IG4.5-568U-4WR-150-T6-2655 2 10 K SVEA96-PlOCASB360-12G5.0-568U-4WR-150-T6-2657 2 11 L SVEA96-PlOCASB361-14GZ-568U-4WR-150-T6-2658 4 12 M SVEA96-PIOCASB360-12G5.5/2G2.5-568U-4WR-150-T6-2659 2 12 Figure 6.2 - Reference Core Loading Pattern - Cycle 13 41

PSEG Hope Creek Mixed Core Analysis Report 7.0 Supplemental Reload Licensing Report (SRLR) at CPPU Condition A copy of the CPPU SRLR follows this analysis. The SRLR sections, tables, figures, appendices and page numbering are self contained as in the original report and therefore have not been modified to be consistent with Sections 1.0 - 7.0 of the MCAR. Accordingly, individual SRLR sections, tables and figures are not contained in the MCAR Table of Contents, List of Tables or List of Figures. The CPPU operation cycle in the SRLR is referred to as Cycle 14.

42

tos -

Global Nuclear Fuel A Jon! Vbntur d GE, Toshi, & Hitacf 0000-0031-9425-MCAR-SRLR Revision 0 Class I April 2005 0000-0031-9425-MCAR-SRLR, Rev. 0 Mixed Core Analysis Report Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 13 Cycle 14 Extended Power Uprate Approved: Ein/. Sevi Approved: X M. E. Hardingil~ R. E. Kingston Fuel Engineering Services Customer Account Leader

HOPE CREEK I .. ; 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Important Notice Regarding Contents of This Report Please Read Carefully The analyses in this document are not intended for the reload licensing of the actual Hope Creek Generating Station Unit 1 Cycle 14, and thus is not represented as fully conforming to the GESTAR-I1 analysis bases.

This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for PSEG Nuclear LLC (PSEG) and the U.S. Nuclear Regulatory Commission (USNRC). The information contained in this report is believed by GNF-A to be an accurate and true representation of the facts known, obtained or provided to GNF-A at the time this report was prepared.

The only undertakings of GNF-A respecting information in this document are contained in the contract between PSEG and GNF-A for nuclear fuel and related services for the nuclear system for Hope Creek Generating Station Unit I and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with respect to any such unauthorized use, neither GNF-A nor any of the contributors to this document makes any representation or warranty (express or implied) as to the completeness, accuracy or usefulness of privately owned rights; nor do the) assume any responsibility for liability or damage of any kind which may result from such use of such information.

Page 2

HOPE CREEK I I .. 0000-0031-9425-MCAR-SRLR ..... ....

Reload 13 Rev. 0 Acknowledgement

'Nuclear Fuel Engineering' and 'Nuclear and Safety Analysis' groups performed the engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report.

Jin Su prepared this Supplemental Reload Licensing Report, and J. Rea was the verifier of this document.

Page 3

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 The basis for this report is General Electric StandardApplicationfor Reactor Fuel, NEDE-2401I-P-A-14, June 2000; and the U.S. Supplement, NEDE-2401 1-P-A-14-US, June 2000.

1. Plant-unique Items Appendix A: Analysis Conditions Appendix B: List of Acronyms Appendix C: Decrease In Core Coolant Temperature Events Appendix D: Reactor Recirculation Pump Scizure Event Appendix E: Power and Flow Dependent Limits

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

SVEA96-PIOCASB360-12GZ-568U-4WR-150-T6-2656 11 40 SVEA96-P 1OCASB360-12G5.0-568U-4WR- 150-T6-2657 11 76 SVEA96-P 1OCASB361 -14GZ-568U-4WR-150-T6-2658 12 168 SVEA96-P1OCASB360-12G5.5/2G2.5-568U-4WR- 150-T6-2659 12 64 GE 14-P 1OCNAB402-4G6.0/16G4.0- 1OOT-150-T6-2757 (GE 14C) 13 56 GE]4-PIOCNAB402-5G6.0114G4.0-1OOT-150-T6-2758 (GE14C) 13 108 New:

GE14-P I OCNAB396-16GZ-I OOT-150-T6-2830-LICENSING (GE14C) 14 252 Total: 764

3. Reference Core Loading Pattern Nominal previous cycle core average exposure at end of cycle: 29646 MWd/MT (26895 MWd/ST)

Minimum previous cycle core average exposure at end of cycle 29646 MWd/MT from cold shutdown considerations: (26895 MWVd/ST)

Assumed reload cycle core average exposure at beginning of 16290 M\Nd/MT cycle: (14778 MWd/ST)

Assumed reload cycle core average exposure at end of cycle 29518 MWd/MT (rated conditions): (26778 MWd/ST)

Reference core loading pattern: Figure 1 Page 4

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0

4. Calculated Core Effective Multiplication and Control System Worth - No Voids, 20 0 C Beginning of Cycle, keffective Uncontrolled 1.106 Fully controlled 0.945 Strongest control rod out 0.984 R, Maximum increase in cold core reactivity with exposure into cycle, Ak 0.003

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

(at 20 0C) (at 160'C, Xenon Free) 660 0.032

6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters

'Operating domain: ICF (HBB)

Exposure range  : BOC14 to EOR14-2646 MWdIMT (2400 MIdIST)

Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power Bundl low MCPR

_ __ _ __ _ __ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ( MW t) ( 1 0 l / r )C P GE14C 1.45 1.44 1.24 1.040 7.049 105.3 1.33 SVEA96+ 1.45 1.50 1 1.24 0.990 7.327 102.3 1.32 Operating domain: ICF (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (1000 lb/hr) lItCPR

_ __ _ __ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ ( M W t) _ _ _ _ _ _ _

GE14C 1.45 1.38 1.34 1.040 6.775 108.9 1.33 SVEA96+ 1.45 1.43 1.34 0.990 7.008 1055 134 l End of Rated (EOR) is defined as cnd-of-cyclc all rods out, 100% powcr/100% flow, and nonnal fccdwatcr temperature.

Page 5

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: MIELLLA (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/lUT (2400 MWdlST)

=____l_______ Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (1000 lblhr) AICPR GE14C 1.45 1.40 1.22 1.040 6.854 95.4 1.33 SVEA96+ 1.45 1.45 1.22 0.990 7.088 92.3 1.33 Operating domain: MELLLA (HBB)

Exposure range  : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (00Ibh) MP

_ __ _ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ (M W t) (1 0 lb h ) MP GE14C 1.45 1.35 1.30 1.040 6.613 98.3 1.34 SVEA96+ 1.45 1.39 1.30 0.990 6.810 94.8 1.35 Operating domain: ICF (UB)

Exposure range : BOC14 to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power Bundl low Inta

_ __ __ _ _ __ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (M W t) (1 0 lb h )C P GE14C 1.45 1.42 1.22 1.040 6.950 106.5 1.34 SVEA96+ 1.45 1.46 1.22 0.990 7.176 103.7 1.35 Operating domain: MELLLA (UB)

Exposure range  : BOC14 to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (lOO0Iblhr) MCPR

_ __ __ _ _ __ __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (M Wt) (1 0 lb r)C P GE14C 1.45 1.39 1.21 1.040 6.822 95.8 1.33 SVEA96+ 1.45 1.44 T 1.21 0.990 7.044 92.7 1.33 Page 6

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: ICF & MFWT- (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST)

___ _ Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor PoWerrICPR(1000Pob/fr)

_ _ _ _ _ _ _ _ _ _ (MW t) ( 0 0I /i ) M P GE14C 1.45 1.49 1.24 1.040 7.294 103.5 1.29 SVEA96+ 1.45 1.53 1.24 0.990 7.510 100.6 1.30 Operating domain: 1CF & MFWT (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWdIST) to EOC14 Peaking Factors _

Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (1000 Ib/hr) MCPR GE14C 1.45 1.42 1.33 1.040 6.977 107.5 1.30 SVEA96+ 1.45 1.47 1.33 0.990 7.182 103.9 1.32 Operating domain: MELLLA & MFWT (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/AIT (2400 MWd/ST)

Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power l l I le/o n ta

_ _ _ _ __ _ __ _ _ __ _ __ _ _ __ _ _ _ _ _ _ _ (M W t) (1 0 lb r)C P GE14C 1.45 1.45 1.23 1.040 7.094 93.7 1.29 SVEA96+ 1.45 1.50 1.23 0.990 7.322 90.4 1.29 Operating domain: MELLLA & MFWT (HBB)

Exposure range  : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (1000lb/hr) MCPR

_ __ _ __ _ __ __ _ ____ _ _ _ _ _ _ _ _ _ _ _ (IM Wt) (1 0 GE14C 1.45 1.39 1.30 1.040 6.810 97.1 1.30 SVEA96+ 1.45 1 1.43 T 1.30 0.990 7.015 93.2 1.31 2 MWT, minimum feedwater temperature, is allowed by plant Technical Specifications as low as 409 IF at rated power.

Page 7

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: ICF & MFWT (UB)

Exposure range : BOC14 to EOC14 Peaking Factors Bundle Bu d e F o nt a Fuel Design Local Radial Axial R-Factor Power Bundle Flow Initial

___-(MWt) (1000 lb/hr) MCPR GE14C 1.45 1.46 1.23 1.040 7.150 105.1 1.31 SVEA96+ 1 1.45 1 1.51 1.23 0.990 7.371 102.0 1.31 Operating domain: MELLLA & MFWT (UB)

Exposure range : BOC14 to EOC14 Peaking Factors T Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power ( CPR

_ __ _ __ __ _ _ _ ~(MW t) ( 1 0 l b r)C P GE14C 1.45 1.44 1.22 1.040 7.049 94.4 1.29 SVEA96+ 1.45 1.48 1.22 0.990 7.254 91.1 1.30 Operating domain: ICF with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST)

Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power Budl Fo MCPR

_____ ~~~(M W t) (1 0 lb r) M P GE14C 1.45 1.41 1.24 1.040 6.904 106.3 1.36 SVEA96+ 1.45 1.46 1.24 0.990 7.159 103.4 1.36 Operating domain: ICF with RPTOOS (HBB)

Exposure range : EOR14-2646 MWdlMT (2400 MWd/ST) to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (10001b/hr) MCPR GE14C 1.45 1.35 1.34 1.040 6.645 109.7 1.37 SVEA96+ 1.45 1.41 1.34 0.990 6.896 106.3 1.37 Page 8

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWdlMT (2400 MWd/ST)

_ _ Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (1000 Ib/hr) lICPR

_ _ _ _ _ _ _ __ __ __ _ __ __ _ _ _ _ _ _ _( M NN t) ( 1 0 I b r) M P GE14C 1.45 1.37 1.22 1.040 6.739 96.1 1.35 SVEA96+ 1.45 1.42 1.22 0.990 6.962 93.1 1.35 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Peaking Factors Bundle Bundle Flow" Initial Fuel Design Local Radial Axial R-Factor Power Bundl low MCPR

_ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (M X t ) ( 1 0 I b r)C P GE14C 1.45 1.34 1.30 1.040 6.564 98.6 1.35 SVEA96+ 1.45 1.38 1.30 0.990 6.747 95.2 1.36 Operating domain: ICF with RPTOOS (UB)

Exposure range  : BOC14 to EOC14 Peaking Factors B undle Bu d e F o In t a Fuel Design Local Radial Axial R-Factor Power (1000 Flow MCPR

___ ____ __ _ _ _ __ _ __ _ __ __ __ _ (M wVt) (1 000 lbfh r) M CPR GE14C 1.45 1.38 1.22 1.040 6.791 107.6 1.38 SVEA96+ 1.45 1.43 1.22 0.990 7.024 104.8 138 Operating domain: MELLLA with RPTOOS (UB)

Exposure range  : BOC14 to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power l(Olb/hr) MCPR

_ __ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ( MW t) ( 1 0 l b h )M P GE14C 1.45 1.37 1.21 1.040 6.716 96.5 1.36 SVEA96+ 1.45 1.41 i 1.21 0.990 6.919 93.6 1.36 Page 9

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: ICF & MFWT with RPTOOS (H1BB)

Exposure range BOC14 to EOR14-2646 MWdI/T (2400 MWdlST)

Peaking Factors B undle Bu d e F o In t a Fuel Design Local Radial Axial R-Factor PowBundlerlow Initial

__ _ ___ __ __ __ _ _ __ __ _ (M W t) (1000 Iblhr) M CPR GE14C 1.45 1.45 1.24 1.040 7.122 104.6 1.33 SVfEA96+ 1.45 1.51 1.24 0.990 7.377 101.5 1.33 Operating domain: ICF & MFWT with RPTOOS (HBB)

Exposure range : EOR14-2646 MWdlMT (2400 MWd/ST) to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power 10 bh) MP GE14C 1.45 1.40 1.33 1.040 6.848 108.4 1.33 SVEA96+ 1.45 1.44 1.33 0.990 7-070 104.7 1.34 Operating domain: MELLLA & MFWT with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST)

Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (I Fol I nitial

_ _ __ __ _ _ __ _ __ __ _ _ _ _ _ _ _ _ _ _ _ ( M Wt) ( 1 0 l b r )C P GE14C 1.45 1.43 1.23 1.040 6.999 94.3 1.31 SVEA96+ 1.45 1.48 1.23 0.990 7.219 91.0 1.31 Operating domain: MELLLA & MFWT with RPTOOS (HBB)

Exposure range : EOR14-2646 MWd1MT (2400 MWd/ST) to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power B dI l l Inta

_ __ _ _ __ _ __ _ _ _ _ _ _ _ _ _ (M W t) _ _ _ _ _ _ _

GE14C 1.45 1.37 1.30 1.040 6.734 97.6 1.32 SVEA96+ 1.45 1.42 1.30 0.990 6.947 93.6 1.33 Page 10

HOPE CREEK I 0000-0031-9425-MCAR-SRLR

?Pplfan2 1* Rev. 0 Operating domain: ICF & MFWT with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power I(1000lCPR b/hr)

_ _____ _ ___ _ __ _ _ __ __ ___ ___ ___ (M W t) (1 0 lb r)C P GE14C 1.45 1.44 1.23 1.040 7.036 105.9 1.34 SVEA96+ 1.45 1.48 1.23 0.990 7.262 102.7 1.34 Operating domain: MELLLA & MFWT with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Peaking Factors Bundle Bundle Flow Initial Fuel Design Local Radial Axial R-Factor Power (1000 lb/hr) A1CPR

_ __ __ _ _ _ __ __ _ _ _ _ __ _ _ _ _ _ _ _ (M Wt) (1 0 lb r) M R GE14C 1.45 1.42 1.22 1.040 6.937 95.1 1.32 SVEA96+ 1.45 1.46 1.22 0.990 7.120 91.9 1.33

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 3

Refer to GESTAR for those margin improvement options that are referenced and supported within GESTAR.

Page II

HOPE CREEK I .: .0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0

8. Operating Flexibility Options 4 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: +° y e S Single-loop operation: Yes Equipment Out of Service:

Safety/relief valves Out of Service: Yes (credit taken for 13 of 14 valves)

RPTOOS Yes

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

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST)

Uncorrected ACPR Event Flux (%QNABR) GE14C SVEA96+ Fig.

FW Controller Failure 218 112 0.22 0.22 2 Turbine Trip w/o Bypass 284 112 0.26 0.26 3 Load Reject w/o Bypass 281 112 0.26 0.25 4 4 Refer to GESTAR for those operating flexibility options that are referenced and supported within GESTAR.

41 0P° d colJ_~rn e4 be"*2QS b &FJP51610o.

Page 12

HOPE'CREEK I 0000-0031-9425-MCAR SRLR Reload 13 Rev. 0 Operating domain: MELLLA (UB)

Exposure range : BOC14 to EOC14 Uncorrected ACPR Event (% NBR) (% NBR) GE14C SVEA96+ Fig.

FW Controller Failure 201 110 0.22 0.22 17 Turbine Trip wl/o Bypass 258 111 0.26 0.26 18 Load Reject vto Bypass 254 110 0.26 0.26 19 Operating domain: ICF & MFUT (HBB)

Exposure range : BOC14 to EOR14-2646 MWdlMT (2400 MWdlST)

Uncorrected ACPR Event (%FNR) (%QNABR) GE14C SVEA96+ Fig.

FW Controller Failure 219 113 0.22 0.23 20 Operating domain: ICF & MFWT (HBB)

J Exposure range : EOR14-2646 MWdlMT (2400 MNdIST) to EOC14

_ __ Uncorrected ACPR J Event l u(%NBR) l(%NBR) GE14C SVEA96+ Fig.

FW Controller Failure 305 120 T 0.24 0.25 21 Operating domain: MELLLA & MFN'T (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWdIST)

Uncorrected ACPR Event Flux Q(A GE14C SVEA96+ Fig.

___ ____ ___ (% NBR) (% NBR)14 FW Controller Failure 198 110 0.21 0.22 22 Operating domain: MELLLA & MFWT (HBB)

Exposure range : EOR14-2646 MWdlMT (2400 MWdlST) to EOC14 Uncorrected ACPR Event Flux FWControllerailure271 N0R) (%QIAN0.R) 11(%

GE14C SVEA96+ Fig.

23 FWA Controller Failurc 271 117 0.23 j 0.25 23 Page 14

HOPE:GREEK 1 0000-0031-9425-MCAR-SRLR Plnl1 Rev. 0 Operating domain: ICF & MFNVT (U`B)

Exposure range : BOC14 to EOC14 Uncorrected ACPR Event NBR) u(% (%QNBR) GE14C SVEA96+ l Fig.

FU' Controller Failure 248 115 0.24 0.24 124 Operating domain: MELLLA & MFWT (UB)

Exposure range : BOC14 to EOC14 I Uncorrected ACPR Event Flux QIA GE14 SVEA96+ Fig.

______ ___ ___ ___ ___ ___ (% N BR) (% NBR)14 FW Controller Failure 210 II I 0.22 0.23 25 Operating domain: ICF with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST)

Uncorrected ACPR Event Flux(% NB) GE14C SVEA96+ Fig.

FW Controller Failure 246 115 0.25 0.25 26 Turbine Trip wv/o Bypass 328 116 0.29 0.29 27 Load Reject v/o Bypass 334 115 029 0.28 28 Operating domain: ICF with RPTOOS (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Uncorrected ACPR Event (% NBR) (% NBR) GE14C SVEA96+ Fig.

FW Controller Failure 325 121 0.26 0.27 29 Turbine Trip Nv/o Bypass 405 122 0.29 0.30 30 Load Reject v/o Bypass 395 122 0.29 0.30 31 Page 15

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWdIMT (2400 MWd/ST)

Uncorrected ACPR Event Fl ux (% NBR) GE14C SVEA96+ Fig.

FU' Controller Failure 218 112 0.24 0.24 32 Turbine Trip w/o Bypass 290 114 0.28 0.28 33 Load Rcjcct w/o Bypass 289 113 0.28 0.27 34 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Uncorrected ACPR Event Flux (% NBR) GE14C SVEA96+ Fig.

FW Controller Failure 278 118 0.25 0.26 35 Turbine Trip w/o Bypass 345 119 0.28 0.29 36 Load Reject Wv/o Bypass 350 119 0.28 0.29 37 Operating domain: ICF with RPTOOS (UB)

Exposure range : BOC4 to EOC14 Uncorrected ACPR Event / F( R) (% NBR) GE14C SVEA96+ Fig.

FW Controller Failure 269 117 0.27 0.27 38 Turbine Trip iv/o Bypass 356 119 0.31 0.31 39 Load Reject w/o Bypass 364 118 0.31 0.30 40 Operating domain: MELLLA with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Uncorrected ACPR Event Flux (% NBR) GE14C SVEA96+ Fig.

FW Controller Failure 221 113 0.24 0.24 41 Turbine Trip w/o Bypass 292 114 0.29 0.29 42 Load Reject w/o Bypass 290 114 0.28 0.28 43 Page 16

HOPE CREEK I 1..

a,L1 ,ItI.

0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: ICF & MFWNT with RPTOOS (H1BB)

Exposure range : BOC14 to EOR14-2646 MWdIMT (2400 MWd/ST)

Uncorrected ACPR Event F(%lNBR) (% NBR) GE14C SVEA96+ Fig.

FW Controller Failure 246 116 0.26 0.25 44 Operating domain: ICF & MFWT with RPTOOS (HBB)

Exposure range : EOR14-2646 MWdIMT (2400 MWdIST) to EOCI4 Uncorrected ACPR Event NBR)

( Flux NBR)

Q(% GE14C SVrEA96+ Fig.

FWV Controller Failure 337 123 0.26 0.27 45 Operating domain: MELLLA & MFWT with RPTOOS (HBB)

Exposure range  : BOC14 to EOR14-2646 MWdlMT (2400 MVYd/ST)

Uncorrected ACPR Event (% lR (/ NBR) GE14C SVEA96+ F.

FW Controller Failure 218 112 1 0.24 0.24 46 Operating domain: MELLLA & MFWT with RPTOOS (HBB)

Exposure range : EOR14-2646 MWdlMT (2400 MWd/ST) to EOC14 Uncorrected ACPR Event NBR)

Fu(% Q(%ANBR) GE14C SVEA96+ Fig.

FW Controller Failure 292 119 0.25 0.26 47 Operating domain: ICF & MFWVT with RPTOOS (UB)

Exposure range : BOC14 to EOCI4 Uncorrected ACPR Eventx (%NBR) (%QNBR) GE14C SVEA96+ Fig.

FW Controller Failure 278 118 0.27 0.27 48 Page 17

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: MELLLA & MFWT with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Uncorrected ACPR Event Flux QIA GE14C SVEA96+ Fig.

(% NBR) (% NBR) GIC SE9+ Fg FWV Controller Failure 232 114 1 0.25 0.25 149

10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary Assuming the worst channel response and 50% availability of the LPRMs yields a ACPR of 0.21 for all RBM setpoints including the unblocked response.

11. Cycle MCPR Values 5 Safety limit: 1.07 Single loop operation safety limit: 1.09 ECCS OLMCPR Design Basis: See Section 16 (Initial MCPR)

Non-nressurization events:

Exposure range: BOC14 to EOC14 GE14C SVEA96+

Loss of Feedwater Heating (11 0IF) 1.21 1.21 Control Rod Withdrawal Error (unblocked) 1.28 1.28 Fuel Loading Error (misoriented) 1.19 1.29 5 For single-loop operation, thc MCPR operating limit is 0.02 greater than the tlvo-loop v alue.

Page 18

.Aus HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev 0 Limiting Pressurization Events OLMCPR Summarv Table: 6 Pressurization events: 8 Operating domain: ICF (HBB)

Exposure range : BOC14 to EOR14-2646 MWdIMT (2400 MWd/ST)

Application condition: 1, 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.42 1.41 1.31 1.30 Turbine Trip wv/o Bypass 1.46 1.45 1.35 1.34 Load Rcjcct v/o Bypass 1.45 1.45 1.34 1.34 Operating domain: ICF (HBB)

Exposure range : EOR14-2646 MWdIMT (2400 MWd/ST) to EOC14 Application condition: 1, 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.52 1.54 1.35 1.37 Turbine Trip w/o Bypass 1.56 1.58 1.39 1.41 Load Reject v/o Bypass 1.56 1.57 1.39 1.40 6

Each application condition (Appl. Cond.) covers the entire range of licensed flow and feedwater temperature unless specified othen'ise. The OLMCPR values presented apply to rated power operation.

7 One SRV out-of-service allowed.

8 The application condition number(s) shown for each of the following pressurization events represents the application condition(s) for which this event contributed in the determination of the limiting OLMCPR value.

Page 19

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev 0 Operating domain: MELLLA (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWdlST)

Application condition: 1, 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.41 1.41 1.30 1.30 Turbine Trip w/o Bypass 1.45 1.45 1.34 1.34 Load Reject w/o Bypass 1.45 1.45 1.34 1.34 Operating domain: MELLLA (HBB)

Exposure range : EOR14-2646 MWdIMT (2400 MWd/ST) to EOC14 Application condition: 1, 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FWV Controller Failurc 1.52 1.54 1.35 1.37 Load Reject w/o Bypass 1.56 1.58 1.39 1.41 Turbinc Trip %v/oBypass 1.55 1.58 1.38 1.41 Operating domain: ICF (UB)

Exposure range : BOC14 to EOC14 Application condition: 1, 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.53 1.53 1.36 1.36 Turbine Trip iv/o Bypass 1.57 1.58 1.40 1.41 Load Reject v/o Bypass 1.57 1.57 1.40 1.40 Operating domain: MELLLA (UB)

Exposure range : BOC14 to EOC14 Application condition: 1, 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.51 1.52 1.34 1.35 Turbine Trip wv/o Bypass 1.55 1.56 1.38 1.39 Load Reject w/o Bypass 1.55 1.56 1.38 1.39 Page 20

HOPE CREEK I .::- . 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: ICF & MIFVT (HBB)

Exposure range : BOC14 to EOR14-2646 MWdlMT (2400 MWdlST)

Application condition: 1, 2 Option A Option B GE14C_ SVEA96+ GE14C lSA A96+

FW' Controller Failure 1.42 1.42 1.31 1.31 Operating domain: ICF & MFWT (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Application condition: 1,2 Option A Option B GE14C SVEA96+ GE14C SN'EA96+

FW' Controller Failure 1.53 1.55 1.36 1.38 Operating domain: MELLLA & MFWT (HBB)

Exposure range : BOC14 to EOR14-2646 MWdlMT (2400 MWd/ST)

Application condition: 1, 2 Option A Option B GE14C SVEA96+ GE14C lSVEA96+

FW Controller Failure 1.41 1.41 1.30 1.30 Operating domain: MELLLA & MFWT (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWdlST) to EOC14 Application condition: 1, 2 Option A Option B GE14C l SVEA96+ GE14C SVEA96+

FU' Controller Failure 1.52 1.55 1.35 1.38 Operating domain: ICF & MFNN'T (UB)

Exposure range : BOC14 to EOC14 Application condition: 1,2 Option A Option B GE14C l SVEA96+ GE14C SVEA96+

FW Controller Failure 1.53 1.54 1.36 1.37 Page 21

HOPE CREEK I I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: MELLLA & MFWT (UB)

Exposure range : BOC14 to EOC14 Application condition: 1,2 Option A Option B GE14C SVEA96+ GE14C SVEA96 FW Controller Failure 1.51 1.53 1.34 1.36 Operating domain: ICF with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWdIST)

Application condition: 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FWY Controller Failure 1.45 1.45 1.34 1.34 Turbine Trip wv/o Bypass 1.49 1.49 1.38 1.38 Load Rcjcct v/o Bypass 1.49 l 1.48 1.38 l 1.37 Operating domain: ICF with RPTOOS (HBB)

Exposure range : EOR14-2646 MWdIMT (2400 MWd/ST) to EOC14 Application condition: 2 OptionA Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.55 1.57 1.38 1.40 Turbine Trip %v/oBypass 1.59 1.60 1.42 1.43 Load Reject lv/o Bypass 1.58 1.60 1.41 1.43 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWdlMT (2400 MWdlST)

Application condition: 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FU' Controller Failure 1.43 1.43 1.32 1.32 Turbine Trip w/o Bypass 1.48 1.48 1.37 1.37 Load Reject v/o Bypass 1.47 1.47 1.36 1.36 Page 22

HOPE CREEK I 0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0 Operating domain: MELLLA with RPTOOS (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Application condition: 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.54 1.56 1.37 1.39 Turbine Trip w/o Bypass 1.58 1.59 1.41 1.42 Load Reject w/o Bypass 1.58 1.59 1.41 1.42 Operating domain: ICF with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Application condition: 2 Option A Option B GE14C SVEA96+ GE14C SV'EA96+

FW' ControllcrFailurc 1.56 1.57 1.39 1.40 Turbine Trip w/o Bypass 1.60 1.61 1.43 1.44 Load Rcjcct Wlo Bypass 1.60 1.61 1.43 1.44 Operating domain: MELLLA with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Application condition: 2 Option A Option B l GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.53 1.54 1.36 1.37 Turbine Trip v/o Bypass 1.58 1.59 1.41 1.42 Load Reject w/o Bypass 1.58 1.58 1.41 1.41 Operating domain: ICF & MFWT with RPTOOS (HBB)

Exposure range BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST)

Application condition: 2 Option A Option B GE14C SSVEA96+ GE14C SNAEA96+

FW Controller Failure 1.45 1.45 1.34 1.34 Page 23

I.

-HOPE CREEK I 0000-0031 -942S MCAR-SRLR Reload 13 Rev. 0 Operating domain: ICF & MFWT with RPTOOS (HBB)

Exposure range : EOR14-2646 MVdIMT (2400 MWd/ST) to EOC14 Application condition: 2 OptionB OptionA O GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.55 1.57 1.38 1.40 Operating domain: MELLLA & MFWT with RPTOOS (HBB)

Exposure range : BOC14 to EOR14-2646 MWd/MT (2400 MWdIST)

Application condition: 2 Option A J Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.43 1.44 1.32 1.33 Operating domain: MELLLA & MFWT with RPTOOS (HBB)

Exposure range : EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 Application condition: 2

_ Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.54 1.56 1.37 1.39 Operating domain: ICF & MFWT with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Application condition: 2 Option A Option B GE14C SVEA96+ GE14C SEA96+

FWV Controller Failure 1.56 1.57 1.39 1.40 Operating domain: MELLLA & MFWT with RPTOOS (UB)

Exposure range : BOC14 to EOC14 Application condition: 2 Option A Option B GE14C SVEA96+ GE14C SVEA96+

FW Controller Failure 1.54 1.55 1.37 1.38 Page 24

HOPE CREEK I  ;:0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0

12. Overpressurization Analysis Summary Event Psi Pdome Pv Plant (psig) (psig) (psig) Response MSIV Closure (Flux Scram) (ICF) 1258 1263 1284 Figure 50 MSIV Closure (Flux Scram) (MELLLA) 1258 1264 1284 Figure 51

13. Loading ErrorResults Variable water gap misoriented bundle analysis: Yes 9 Misoriented Fuel Bundle ACPR GE14-P I OCNAB402-4G6.0/16G4.0-OOT-150-T6-2757 (GE14C) 0.08 GE14-P I OCNAB402-5G6.0/14G4.0-OOT-150-T6-2758 (GE14C) 0.12 GE 14-P 1OCNAB396- 16GZ- IOOT- 150-T6-2830-LICENSING (GE 14C) 0.12

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 Introduction Hope Creek has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range Monitor-OPRM) as described in Reference I in Section 15.4. Plant specific analysis incorporating the Option III hardware is described in Reference 2 in Section 15.4.

Should the Option Ill OPRM system be declared inoperable, the Backup Stability Protection (BSP) solution will constitute the stability licensing basis for Hope Creek Cycle 14 operation.

15.2 Stability Option III Reload validation has been performed in accordance with the licensing basis methodology described in Reference 3 in Section 15.4. The stability based MCPR Operating Limit is provided for tvo conditions as a function of OPRM amplitude setpoint in the following table. The two conditions evaluated are for a postulated oscillation at 45% rated core flow steady state operation (SS) and following a two recirculation pump trip (2PT) from the limiting full power operation state point. Current power and flow dependent limits provide adequate protection against violation of the Safety Limit MCPR for postulated reactor 9 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

Page 25

HOPE CREEK I 10000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 instability as long as the operating limit is greater than or equal to the specified value for the selected OPRM setpoint.

The BWVROG Plant-Specific Regional Mode DIVOM Procedure Guideline (Reference 4 in Section 15.4) recommends that a plant specific DIVOM slope be used for Option III OPRM setpoint determination.

The stability-based OLMCPR wvas calculated for Cycle 14 based on the plant-specific DIVOM slope of 0.802 (Reference 5 in Section 15.4). The Option III reload validation calculation demonstrated that reactor stability does not produce the limiting OLMCPR for Cycle 14 as long as the selected OPRM setpoint produces values for OLMCPR(SS) and OLMCPR(2PT) which are less than the corresponding acceptance criteria.

Two sets of OPRM setpoints are provided. Table 15.2-1 assumes a 1.0 Hz comer frequency in the conditioning filter while Table 15.2-2 assumes a 1.5 Hz corner frequency for the conditioning filter.

Table 15.2-1 OLMCPR Results as a Function of OPRM Setpoint (1.0 Hz Corner Frequency, DIVOMI Slope = 0.802)

OPM1' 1 Hz Corner 51 Hz Corner' SFIeF n frequency

_'Setpoint _^.;, OLMCPR(SS) OLMCPR(2PT) 1.05 0.200 1.274 1.145 1.06 0.238 1.322 1.188 1.07 0.276 1.374 1.235 1.08 0.315 1.432 1.286 1.09 0.353 1.493 1.341 1.10 0.391 1.559 1.401 1.11 0.428 1.629 1.464 1.12 0.465 1.706 1.533 1.13 0.502 1.791 1.609 1.14 0.539 1.885 1.693 1.15 0.576 1.989 1.787

'Acceptance O RadLPwr

~Criteria iOLCPROLMP 0 Ai is the licensing basis HCOM with 1.5 Hz comer frequency filtering effect for OPRM setpoint i, in accordance with Reference 2 of Section 15.4.

The off-rated OLMCPR is the mnaximum of the K, adjusted 1CPR or the MCPRfat 45% core flow.

Page 26

HOPE CREEK I .- 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Table 15.2-2 OLMCPR Results as a Function of OPRM Setpoint (1.5 Hz Corner Frequency, DIVOM Slope = 0.802)

5 Hz Corner 1.5 Hz Corner OPRM 12 Frequency Frequency

- etpoint _-_ _ OLMCPR(SS) OLMCPR(2PT) 1.05 0.189 1.261 1.133 1.06 0.225 1.306 1.173 1.07 0.261 1.353 1.216 1.08 0.297 1.405 1.262 1.09 0.333 1.460 1.312 1.10 0.369 1.520 1.365 1.11 0.404 1.583 1.422 1.12 0.439 1.651 1.484 1.13 0.474 1.726 1.551 1.14 0.509 1.808 1.625 1.15 0.544 1.898 1.705 iOff-rated Acceptance Rtdoer C Crite a ~OLMCPR 'flowa@45% RtePo OLMCPR.'r 12 4 is the licensing basis HCOM with 1.5 lIz comer frequency filtering effect for OPRI setpoint i, in accordance with Reference 2 of Section 15.4.

13The off-rated OLMCPR is the maximurn of the K, adjusted MCPR or the hfCPRfat 45%, core flow.

15.3 Backup Stability Protection GE SIL-380 recommendations, BWVROG Interim Corrective Actions (Reference 6 in Section 15.4) and Backup Stability Protectionfor Inoperable Option Ill Solution (Reference 7 in Section 15.4) have been included in the Hope Creek Cycle 14 operating procedures. Regions of restricted operation defined in Attachment I to NRC Bulletin No. 88-07, Supplement 1, (Reference 8 in Section 15.4) and expanded in Reference 6 in Section 15.4 and Reference 7 in Section 15.4 are used for Hope Creek Cycle 14 backup stability protection evaluation (Reference 9 in Section 15.4). The standard ICA stability regions are expanded as appropriate to offer stability protection as described in Reference 7 in Section 15.4 and Reference 10 in Section 15.4 for Hope Creek Cycle 14 MELLLA operation. The Hope Creek Cycle 14 stability analyses discussed above are applicable to the MELLLA operation domain as specified in Reference 9 in Section 15.4.

Page 27

HOPE CREEK I - 0000-0031-9425-MCAR-SRLRt Reload 13 Rev. 0 15.4 References

1. BWQR Owners' Group Long-Term Stability Solutions Licensing Methodology, NEDO-31960-A, November 1995.

2. Licensing Basis Hot Channel Oscillation Magnitude for Hope Creek, GENE-A 13-00381-04, Revision 1, September 2004.

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

4. Plant-SpecificRegionalMode DIVOM Guideline, GE-NE-0000-0028-9714-RO, June 2004.

5. MELLLA Option 111 Stability Evaluation for Hope Creek at CPPU Conditions, GE-NE-0000-0038-6654-RO, April 2005.

6. BWYR Owners' Group Guideline for Stability Interim Corrective Action, BWROG-94079, June 6, 1994.

7. Backup Stability Protection (BSP) for Inoperable Option III Solution, GE to BWVR Owners' GroupDetect andSuppress II Committee, OG 02-0119-260, July 17,2002.

8. Power Oscillations in Boiling Water Reactors, NRC Bulletin 88-07, Supplement 1, December 30,1988.

9. MELLLA Backup Stability ProtectionEvaluationfor Hope Creek Cycle 14 at CPPUConditions, NEDC-33179P-R1, March 2005.

10. Review of BWR2 Owners' Group Guidelines for Stability Interim Corrective Action, BWROG-02072, November 20,2002.

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 Moeta-Water Fuel Type Basis PCT Oxidation Reactio (OF) (%) Reatio 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 1 for SVEA96+ in Section 16.4.

The SAFER/GESTR-LOCA analysis results for GE14C fuel are documented in Section 5 of Reference 1 Page 28

HOPE CREEK I h 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 for GE14C in Section 16.4.

16.2 10CFR50.46 ErrorEvaluation The I OCFR50.46 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+

10CFR50.46 Error Notifications Number SubjectPCT Impact No Errors 0 Total PCT Adder (OF) O There are no 10CFR50.46 errors associated with the SVEA96+ Reference I analysis. Therefore, no changes to the Licensing Basis PCT for SVEA96+ are necessary.

Table 16.2-2 Impact on Licensing Basis Peak Cladding Temperature for GE14C 10CFR50.46 Error Notifications Number Subject PCT Impact

- No Errors 0 Total PCT Adder (OF) 0 There are no IOCFR50.46 errors associated with the GE14C Reference I analysis. Therefore, no changes to the Licensing Basis PCT for GE]4C are necessary.

Page 29

2.i ..: ' HOPE CREEK I 0000:0031 -9425-MCAR-SRLR Reload 13 Rev. 0 16.3 ECCS-LOCA Operating Limits The ECCS MAPLHGR operating limits for all fuel bundles in this cycle are shown in the tables below.

Table 16.3-1 MAPLHGR Limits for GE14C Bundlc Typc: GE 14-P 1OCNAB402-4G6.0/16G4.0-1 OOT- 150-T6-2757 (GE14C)

GE 14-P 1OCNAB402-5G6.0/14G4.0-IOOT-150-T6-2758 (GE14C)

GE14-P 1OCNAB396- 16GZ-l OOT-150-T6-2830-LICENTSING (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/IMT GWd/ST kWMft 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 for SVEA96+

Bundle Types: SVEA96-P 1OCASB360- 12GZ-568U-4WR-150-T6-2656 (SVEA96+)

SVEA96-P 1OCASB360- 12G5.0-568U-4WR-150-T6-2657 (SVEA96+)

SVEA96-PIOCASB361-14GZ-568U-4WR-150-T6-2658 (SVEA96+)

SVEA96-PI OCASB360- 12G5.5/2G2.5-568U-4U'R-150-T6-2659 (SVEA96+)

Average Planar Exposure MAPLHGR Limit GWd/MT GWdIST kW/ft 0.00 0.00 12.85 3.68 3.34 12.85 16.00 14.51 10.97 65.00 58.97 7.24 Page 30

HOPE CREEK I 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 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 16.3-3 Initial MCPR and Single Loop Operation PLHGR and MAPLHGR Multiplier Single Loop Operation FuelType Initial MCPR PLHGR and MAPLHGR Fuel__ _ TyeMultiplier SVEA96+ 1.250 0.80 GEl4C 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+ and GE14C SAFERIGESTR-LOCA Loss of Coolant Accident Analysis for Hope Creek Generating Station at Power Up-rate, NEDC-33172P, March 2005.

Page 31

HOPE CREEK I - 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 60 1 [EAE E [ [

58 56 1B[E [N1 El1 Elm [El SE [ 321[ ; El1 [El 54 El R071 BEl NIT D 0R 0El 0 F21TOElE 52 E 0 B 0B [ mw [G D[E 50 ImTm~m~fl ~ 2mmmesImlelm 48 ms 44 mmmms ~ _B_LEiE LE _j m1-j_ m1Lj1U1ELj§ _--1 2 1 46 1 1 FGG F2]

C G Lg EL E] [E][

40 [1El [El m DID N m210 BID E1 DD BIDEW [El El 40 36 El[ 1 §1 [S=m 5mmB mE [DjE] ffB [E] 1 42 [1 1l l 1 1EmmSmmmsm M1Fl rGlm 1 38 l 11m m 1 lmm n frim1 l 26 EA] 0 F] I E)ID E][C EG] [D [E] F E] [023) C [,E] EC] [E] [tGMBO[C;_TBE ffEi [g FT][A 24 mLE 1 nXEl [El m El [smED 19 IC +

22El m~ ID19 ml ~ m1 m1 ml [El [El Fm212e~ 1 36 320 [E) E [E] [F EG] FRC] FEC)[g G B D3[C

[E]B MC [CD m[CDB Og1DEC]BB[G ][CDBM 1[G [F1E) 1[E]

24 E][]E[ EJ2 E 16 mlE [E rq lEl 19 S Elm [ DS [El El ONmE 28E]*0 n+G EIE [FE] E]LE][E]3 [CD210 EID ]E [ElE m[0tS1[ [g [E][CD[1B LE 8~1 l l l lmBBEmEEElE [ I[El IE 2NE 0 _]JB LE]iE[D B Elm M Ino BI E~l ElmEElo ElS A0 A AG AFB B IDIMD[ECC D10E lElBDEB 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 IFuel Type A = SVEA96-PlOCASB360-12GZ-568U4WNR-150-T6-2656 (Cycle 11)

B = SVEA96-PIOCASB360-12G5.0-568U-4WR-150-T6-2657 (Cyclc 11)

C = SVEA96-PIOCASB361-14GZ-568U-4WR-150-T6-2658 (Cycle 12)

D = SVEA96-PIOCASB360-12G5.5/2G2.5-568U-4WR-150-T6-2659 (Cyrcle 12)

E = GE14-PIOCNAB402-4G6.0/16G4.0-lOOT-150-T6-2757 (Cycle 13)

F = GE14-PIOCNAB402-5G6.0/14G4.0-IOOT-150-T6-2758 (Cycle 13)

G = GE14-PIOCNAB396-16GZ-lOOT-150-T6-2830-LICENSING (Cycle 14)

Figure 1 Reference Core Loading Pattern Page 32

HOPE CREEK I  :.O.

t0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0

.0 1M.0-0 50.0.

0.0 a0o s0 IN 1S0 0.0 50 100 150 Tirm (sec) Tiffe (sec) 150O Z;

0 0.

500o O 5 T0 IQO 150 00 50 100 150 TlrrL (see) Tine (sec)

Figure 2 Plant Response to FW Controller Failure (BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST) ICF (HBB))

Page 33

HOPE CREEK 1 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 V1000.

A:

100.0 0.0 B 0.0 30 6.0 0.0 3.0 6.0 Timre (sec) Time (sec)

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

- Vessel Steam Flow x(o.O & Turbine Steam Flow

-.-- Feedwater Flow

'9 C

ZICX D0.0 is: E Ix 0 U

W_

U' 0.0

-100.0 , ,

0.0 3.0 6.0 3.0 Tine (sec) Tine (sec)

Figure 3 Plant Response to Turbine Trip w/o Bypass (BOC14 to EOR14-2646 MWdIMT (2400 MWd/ST) ICF (HBB))

Page 34

HOPE CREEK I 0000-0031-9425-MCAR-SRLR I '; ' 'j*s!

Reload 13 Rev. 0 Qo ao 80 00 30 60 Tine (sec) Tine (sec)

-0 MO

.2 co S Ix 0 C.

.10 co 30 so 00 30 60 Tirn (sec) Tine (see)

Figure 4 Plant Response to Load Reject w/o Bypass (BOC14 to EOR14-2646 MVd/MT (2400 IMWdST) ICF (HBB))

Page 35

HOPE CREEK I * .- - 1 E

0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 150.0 C)

O0 0-Go iQo 15.0 0.0 50 100 150 Time (sec) Time (sec) 1500s

.8 IMO 0

C6 Ix

.1 C) 500s 00 5.0 1O 150 00 50 1ao 150 Tirm (sec) Tinr (sec)

Figure 5 Plant Response to F'W Controller Failure (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 ICF (HBB))

Page 36

HOPE CREEK I 0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0

~Im.0 m .0 2m 0-Imo

_ o004 00 a3 60 00 so 60 Tine (sec) Tine (sec) 0

.0 Irno 0.

co 10 0 U

0 .

00 30 so 00 30 60 Tire (sec Tine (sec)

Figure 6 Plant Response to Turbine Trip w/o Bypass (EOR14-2646 MWdIMT (2400 MWd/ST) to EOC14 ICF (HBB) )

Page 37

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR*

Reload 13 Rev. 0 Qo ao 60 0.0 ao 60 Tirw (sec) Tine (see) 0

.0 icCoo.

a w) E 0

a:)

X a

00 30 60 00 30 60 Tine (sec) Tins (sec)

Figure 7 Plant Response to Load Reject w/o Bypass (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 ICF (HBB))

Page 38

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 an 10.0 150 0.0 10.0 150 Tirwe (sec) Tirre (sec)

M.

00 5.0 1Qo 150 a0 100 150 Tire (see) Tine (sec)

Figure 8 Plant Response to FW Controller Failure (BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST) MELLLA (HBB))

Page 39

HOPE CREEK I >0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 0 3.0 60 00 ao 60 Tine (sec) Time (sec)

- Level(inch-REF-SEP-SKRT)

Vessel b Steam Flow 2000 -t- Turbine Steam Raw

_ Feedvater Row V3 c

.0 1000 00.0 -a a0 E

U~

0 00 I VV 60 oo.

o0 30 ao so Tim! (sec) Timn (sec)

Figure 9 Plant Response to Turbine Trip w/o Bypass (BOC14 to EOR14-2646 MWdlMT (2400 MWd/ST) MELLLA (HBB))

Page 40

-HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0

-e- Vessel Press Rise (psi)

-; Safety Valve Flow 300.0 4 a Relief Valve Flow

_ Bypass Valve Flow

• 0 200.0 a:

100.01 0.0 3.0 6.0 0.0 3.0 6.0 Tirre (see) Tlne (sec) to

-0100.0.

C) w C,

0.1 (0

a) 00 3.0 6.0 0.0 3.0 6.0 Time (sec) Tlne (sec)

Figure 10 Plant Response to Load Reject w/o Bypass (BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST) MELLLA (HBB))

Page 41

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 150.0

• 0 100.D Cr e

0.0 5.0 10.0 15.0 0.0 5.0 10.0 150 Time (sec) Time (sec) 150.0 Zn

.4 0

C.

E 0

U

-50 50.0 r-00 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Time (sec)

Figure 11 Plant Response to FW Controller Failure (EOR14-2646 MWdIMT (2400 MWd/ST) to EOC14 MELLLA (HBB)1)

Page 42

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 150.0 m,

00 30 60 0.0 a0 Tirne (sec) Tine (sec)

I.

!Z 2

.46-0 E

a:

00 a0 co 00 a0 Tium (sec) Tirn (see)

Figure 12 Plant Response to Load Reject wlo Bypass (EOR14-2646 MWd/MT (2400 MWdIST) to EOC14 MELLLA (HBB))

Page 43

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 150.0-cmo It eQ Go 30 s0 00 30 60 Time (sec) Tire (sec)

C) c0.

C)

E 0

To) a, 0).

00 30 60 00 30 60 Tinm (sec) Tinm (sec)

Figure 13 Plant Response to Turbine Trip wlo Bypass (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 MELLLA (HBB))

Page 44

HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 It cro C)

It Q0 50 100 150 0.0 100. 150 Tine (sec) Tirm (sec) 1500

.Eicoo, E

0 m.

QO 50 1Q0 150 no 50 1Q0 150 Tirre (sec) Tine (sec)

Figure 14 Plant Response to FW Controller Failure (BOC14 to EOC14 ICF (UB))

Page 45

HOPE CREEK I 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 1M.0

- ia a iCoo 10 00 00 30 60 00 ao SO Tine (sec) Timr (sec) 401 1to 0.

00 a3 W0 0o 30 60 Tinm (sec) Tine (sec)

Figure 15 Plant Response to Turbine Trip w/o Bypass (BOCA4 to EOC14 ICF (UB))

Page 46

HOPE CREEK I '!-0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0 Qo 30 00 a0 Time (sec) Tirre (sec) 2mo -

CI a

E 0

U 001

.1tO0 00 30 Q0 00 30 Time (sec) Tirm (sec)

Figure 16 Plant Response to Load Reject w/o Bypass (BOC14 to EOC14 ICF (UB))

Page 47

HOPE CREEK I 0000-003 1-9425-MCAR-SRLR alenda 11- Rev. 0 As,. ;

W&

Nn~ \

-*Ate SuLrfac~e HetF LD 6 Core Inlet Flov_

i Cate riet~bCcding 1.o 0: I nn I.

QO so 100 IS O 0.0 SO 100 150 Time (sec) Tine (sec) r-0 it E

0 2:

al) 00 50 10o 1SO 00 1M0 1SO Tirm (sec) Thin (sec)

Figure 17 Plant Response to FW Controller Failure (BOC14 to EOC14 MELLLA (UB))

Page 48

HOPE CREEK 1 r*

s.;. 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 00 ao 60 00 ao Tine (sec) Tine (sec)

-e- Leve(irich-REF-SEP-SKRT)

-* Vessel Steam Rw~

2000 4 -&-Turbne Steam RaN

-+*- Feed~ater Raw Z'

.0 Ino - aE on C

a) 0 U

00 , .

lV' CLO n

.2.0-00 ao i0 00 ao Tine (sec) Tine (sec)

Figure 18 Plant Response to Turbine Trip w/o Bypass (BOC14 to EOC14 MELLLA (UB))

Page 49

HOPE CREEK I '., I. 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0

.0 2mo imo oo Go 30 6-0 ci 3o 60 Tine (sec) Time (sec)

'4

-0 1000 I.

2 E m 0 m

.1 C).

o0 30 6.0 no aD 60 Tirm (sec) Tinm (sed)

Figure 19 Plant Response to Load Reject w/o Bypass (BOC14 to EOC14 MELLLA (UB))

Page 50

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 150.0-

,X 750 250

= -250 -

00 50 150 0.0 100 150 Tine (sec) Time (sec) 1t00 0-

-8 I= - c E

m it

.1-1I U

w 00 1O0 150 00 5.0 10O 15.0 Tine (sec) Tine (sec)

Figure 20 Plant Response to FWV Controller Failure (BOC14 to EOR14-2646 MWd!MT (2400 MWd/ST) ICF & MFWT (HBB))

Page 51

HOPE CREEK I --; 0000-003 1-9425-MCAR-SRLR .-- - ;

Reload 13 Rev. 0 150.0

= 750 C) 250

= -250 _

0o 50 100 150 0.0 50 100 150 Tine (sec) Tirme (sec) 1500 saco Z;

C E0l0 -

a E

0 C-)

C) 00 saoL Q0 iQO 150 00 50 1o0 15.0 Tine (sec) Tine (sec)

Figure 21 Plant Response to FW Controller Failure (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 ICF & MFWT (HBB))

Page 52

HOPE CREEK I 0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0 X 750 250

= -250 -

GO so 100. 150 00 100 150 Time (sec) Tine (sec) 4I c

0 (3

U 00 50 IGO 150 GO 50 100 15.0 Tinr (sec) Tkne (sec)

Figure 22 Plant Response to FW Controller Failure (BOC14 to EORI4-2646 AIWdIMT (2400 MWd/ST) MELLLA & MFWT (HBB))

Page 53

HOPE CREEK I .. - . 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 15o.0 3.0 500 l00 50 100 150 0.0 10.0 150 Tine (sec) Tine (sec)

S.2 E

0 mU 00 10 150 GO 10O 15.0 Tine (sec) Tine (sec)

Figure 23 Plant Response to FW Controller Failure (EOR14-2646 MVWd/MT (2400 MWd/ST) to EOC14 MELLLA & MFWT (HBB))

Page 54

HOPE CREEK I 0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0 150.0

• 0i0n.o QO 50 100 150 0.0 100 150 Time (sec) Tine (sec) 0 C.)

a.

G0 1O0 150 GO 100 15.0 Tire (sec) Tine (sec)

Figure 24 Plant Response to FW Controller Failure (BOC14 to EOC14 ICF & MFWT (UB))

Page 55

HOPE CREEK I -ii - I, 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0

• u 750

@1 250

= -250 -

00 50 100 ISO GO 100 Tine (sec) 1ine (sec) 1.0 VU U

.10

-0.0_

- 10 s 150 0 n0 50 100 10o 15.0 Tine (sec) Tine (sec)

Figure 25 Plant Response to FW Controller Failure (BOC14 to EOC14 MELLLA & MFWT (UB))

Page 56

.'ni HOPE CREEK I 0000-003 I-9425-MCAR-SRLR Reload 13 Rev. 0 Im.0 -

0 Ci c.o no o10 150 on0 so ioo iso Tint (sec) Tirre (sec) 1500 C}

E 0

500 to 5.0 1io Iro co 5o0 1o 150 Tine (sec) Time (sec)

Figure 26 Plant Response to FvV Controller Failure (BOC14 to EOR14-2646 MWdIMT (2400 MWdIST) ICF with RPTOOS (HBB))

Page 57

HOPE CREEK I 0000-0031-9425-MCAR-SRLR . .e -

Reload 13 Rev. 0 a Vessel Press Rse (psi) mSafetVaive RaN 30o . ReliefValve V Row

_ Bypass Valve ROw

.0 2nO.

a) 1mo4 nn Go an a0 00 ao 60 Time (sec) Tirre (sec) a)

-0 1000 a) c c

E 0

X Go a0 60 Go ao 60 Tirm (sec Tlrm (sec)

Figure 27 Plant Response to Turbine Trip w/o Bypass (BOC14 to EOR14-2646 MWd/MT (2400 MWdIST) ICF with RPTOOS (HBB))

Page 58

- - HOPE CREEK I 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 1.Z GO a3 60 00 ao Tine (sec) Tine (seq)

V, 0

C) a.

'U E 0

C, a,

GO a0 eo 00 a0 TimE (see) Tine (see)

Figure 28 Plant Response to Load Reject w/o Bypass (BOC14 to EOR14-2646 MWdJMT (2400 MWdIST) ICF with RPTOOS (HBB))

Page 59

HOPE CREEK I 0000-0031-9425-MCAR-SRLR P01Relnd l]1 Rev. 0 150.0 00 so 100 150 0.0 50 100 150 Tine (sec) Tine (sec)

E 0

U IV-1.0

~ 1Q so ~ ~ . os A5 a 5 00 5.0 1T0 150 00 5.0 1(10 la 0 Time (sec) Tine (sec)

Figure 29 Plant Response to FW Controller Failure (EOR14-2646 MWdIMT (2400 MWdIST) to EOC14 ICF with RPTOOS (HLBB))

Page 60

HOPE CREEK I %0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 iao QO 30 60 0a 30 60 Tine (see) Time (sec)

- a, i1oo.

IQ I.

£c E

C.?

U

'U

@1 GO 30 60 (0 a0 Tine (sec) Time (see)

Figure 30 Plant Response to Turbine Trip w/o Bypass (EOR14-2646 MWdIMT (2400 MWd/ST) to EOC14 ICF with RPTOOS (HBB))

Page 61

HOPE CREEK I -- 1 0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0 QO 30 60 00 30 so Time (sec) Tirm (sec) a

.0 1000 w

w E i: 0 a: U a:

CI.

a0 30 60 00 30 80 Tirm (sec) Turn (sed)

Figure 31 Plant Response to Load Reject w/o Bypass (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 ICF with RPTOOS (HBB) )

Page 62

HOPE CREEK I 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 125.0

- 100.0 ,a 75.0 cm I= .-

e-25.0

-25.0 00 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tirm (sec) Tirm (sec) 0.

a) 0 U

Z) w go 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tine (sec)

Figure 32 Plant Response to FW Controller Failure (BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST) MELLLA with RPTOOS (HBB))

Page 63

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR.

Reload 13 .

Rev. 0

-010 w

Qo 30 so 00 30 Time (sec) Tine (sec) 0

.1 irO

• 0 0

0 0 .

ao 30 so0 00 a TimD (see) Trme (sec)

Figure 33 Plant Response to Turbine Trip w/o Bypass (BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST) MELLLA with RPTOOS (HBB))

Page 64

HOPE CREEK I 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 150.0 oVIMo C, 2a1 121 Q0 30 a0 00 30 60 Tirre (sec) Tine (sec)

V; Ci C

V010 Ci E

0 C.

Ci, GO 30 60 Go ao 60 Tim! (sec) Tirn (see)

Figure 34 Plant Response to Load Reject w/o Bypass (BOC14 to EOR14-2646 MWd/MT (2400 MWd/ST) MELLLA with RPTOOS (HBB))

Page 65

HOPE-CREEK I 0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0

-100.0

~m0 0J Go -

no so 10O 15.0 0.0 To IGO 1so Time (sec) Tirre (sec) c 2

0 cE a:

0 00 100 150 Q0 1I0 150 Tine (sec) Tine (sec)

Figure 35 Plant Response to FW Controller Failure (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 MELLLA with RPTOOS (HBB))

Page 66

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 1m.0.

-0 IMO -

0 m

Ix IA 10 30 60 00 ao 6o Tirn (sec) Tinm (sec) zz E

0 ci Go 30 610 G0 a3 Tine (sec) ine (see)

Figure 36 Plant Response to Turbine Trip w/o Bypass (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 MELLLA with RPTOOS (HBB))

Page 67

.;,:HOPECREEK I 0000-003 1-9425-MCAR-SRLR Dr-1,vaA 12 Rev. 0

--. 1 ... ...

- Vessel Press Rise (psi)

-SafetVaveRoe 150.0 Relief Vave Flao

_ Bypss Valve Row imo .2 ~

ic:

iwo

-0 00 (Uo 00 30 ao Tine (sec) Tire (sec) 0 Iwo-

.m 0 8.

E 0

C.

00 30 S0 00 ao Tine (sec) Tirm (sec)

Figure 37 Plant Response to Load Reject w/o Bypass (EOR14-2646 MWd/MT (2400 MWcd/ST) to EOC14 MELLLA with RPTOOS (HBB))

Page 68

HOPE CREEK 1 . - ..:

0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 llJ -

-.4-A/e Stiface I-hat Rux

&-Corelrdet~aw

-. Care iriet Sicoding

.1w00 a)

.C 5J0 I ofl I 50 100 150 0.0 1ao 150 Time (sec) Tine (sec)

C13e 4#

E 0

icc I

C) 00 5.0 Qo 15e0 00 50 iQO 1e0 Time (sec) Time (sec)

Figure 38 Plant Response to FW Controller Failure (BOC14 to EOC14 ICF with RPTOOS (UB))

Page 69

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 15 o.o

=100.0

-B V

1co a

no q 0 0 30 a.0 00 30 Time (sec) TimD (sec)

- Leve(irch-REF-SEP-SKF)

. 1o.o -* Vessel Steam RON CD 6 Turbne Steam Row 1.0

+ Feedvater Row zz r 100a 100 a)

E 0

M C.,

Mo

+_ ^A W-1.0

-Vv 0an Qo 30 fio no ao Tlne (sec) Tinr (sec)

Figure 39 Plant Response to Turbine Trip w/o Bypass (BOC14 to EOC14 ICF with RPTOOS (UB))

Page 70

HOPE CREEK I .,:;

- 0000-003 1-9425-MCAR-SRLR . * -

Reload 13 Rev. 0 00 30 60 CO 3o 60 Time (sec) Tirm (seq)

!Z 0

Ci 0

C, 2)

GO 30 &n GO a0 60 Tire (sec) Tirm (see)

Figure 40 Plant Response to Load Reject w/o Bypass (BOC14 to EOC14 ICF with RPTOOS (UB))

Page 71

HOPE CREEK I .:* - -'.0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 150.O 10.

00 10Q0 150 0.0 50 100 150 Time (sec) Tiffe (sec) 1500 E

0 5E10DO-L) 00 iQ.O ISO 00 so 100 10 Tirm (sec) Thmr (sec)

Figure 41 Plant Response to FW Controller Failure (BOC14 to EOC14 MELLLA with RPTOOS (UB))

Page 72

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 150.0

-0 1mo CD m

it

,z 50.0 80 00 G0 ao s0 00 30 60 Tine (sec) Tine (sec)

IV m

c V0 icco C,

E 0

a)

B,.

Q0 a0 60 G0 30 Tine (sec) Tine (sec)

Figure 42 Plant Response to Turbine Trip w/o Bypass (BOC14 to EOC14 MELLLA with RPTOOS (UB))

Page 73

HOPE CREEK I . I.. .

0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 010 10 c

GO ao a 60 00 an 60 Tine (sec) Tine (sec) 0`

C.)

e Level tmch-REF-SEP-SR)

- Vessel Steam FRoN 200n 4 - Twbne Steam Flow 0.0 0

-_- FeedNate Flow

.0 icon _s 1.0- .

C, UU . F+ f. ^-

-1U.U .

no an 60 n0 an 60 Tine (sec) Tinm (see)

Figure 43 Plant Response to Load Reject w/o Bypass (BOC14 to EOC14 MELLLA with RPTOOS (UB))

Page 74

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 150.

vcJ D = 750 250

-250 -

GO 5.0 100 150 0.0 50 10.0 150 Tine (sec) Tin (sec) 1500 1co iZ I.

m E

0 U

Cr .

Q0 IGO 150 00 100 15.0 Tine (sec) Tihre (sec)

Figure 44 Plant Response to FW Controller Failure (BOCI4 to EOR14-2646 MWd/MT (2400 MWd/ST) ICF & MFWT with RPTOOS (HBB) )

Page 75

HOPE CREEK 1 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 GO 5.0 10.0 ISO 0.0 100 150 Tine (sec) Tirre (sec) a, Q0 1QO 150 G0 0ao 15.0 Tine (sec) Time (sec)

Figure 45 Plant Response to FW Controller Failure (EOR14-2646 MWd/MT (2400 MWd/ST) to EOC14 ICF & MFWT with RPTOOS (HBB))

Page 76

,"HOPE CREEK 1 0000-0031-9425-MCAR-SRLR P 0-lnn ri 1; Rev. 0 00 50 100 150 0.0 00 150 Tine (sec) Tirre(sec)

.-e Vdd Reaclivit

.-w- Dopoer Reacldy 1.0 a~ Scram Reactvty

-.-Total Reacbvfty 0.0 n 1SQO. A_

E 0

C.)

co 2'

.5

'V4-.0 l l l 00 1QO 150 QO 1IQO 15.0 Tine (sec) Tire (sec)

Figure 46 Plant Response to FM Controller Failure (BOC14 to EOR14-2646 MWdIMT (2400 MWd/ST) MELLLA & MFWT with RPTOOS (HBB))

Page 77

HOPE CREEK I .4 ..

,.4 ... i-.. 'I'. 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0

-01W0 w

500 Go 5.0 100 150 0.0 10.0 150 Tine (sec) Tire (sec) 15O0 r-E 0

C.)

B zGi Qo 10O 150 (l 100 150.

Tirn (sec) Tine (sec)

Figure 47 Plant Response to FW Controller Failure (EOR14-2646 MWd/MT (2400 MWdIST) to EOC14 MELLLA & MFWT with RPTOOS (HBB))

Page 78

_- a HOPE CREEK I 0000-003 1;9425-MCAR-SRLR Reload 13 Rev. 0

• ~70 25.0

- -250 +-

00 50 10.0 15i0 QO0 100 150 Tirn (sec) Tinr (sec) 0 c.

a, Lu C'

00 1MO 150 GO 5.0 IQO 15.0 Tine (sec) Time (sec)

Figure 48 Plant Response to FW Controller Failure (BOCI4 to EOC14 ICF & MFWT with RPTOOS (UB))

Page 79

HOPE CREEK I 0000-0031 -9425-MCAR-SRLR Reload 13 Rev. 0 m 750 250

=-250 m _

00 50 100 150 it 0.0 100 150 Tire (sec) Tine (sec) 2O

-1.0 l E

=== Go 1o 150 00 ao 15.0 Time (sec) Tine (sec)

Figure 49 Plant Response to FW Controller Failure (BOC14 to EOC14 MELLLA & MFWT with RPTOOS (UB))

Page 80

It .. ' :, HOPE CREEK I 'I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 00 1.0 20 30 4.0 5.0 6.0 70 to en 00 1.0 20 10 40 0.0 60 7.0 sO to Time (sec) Time (sec) 00 10 2.0 00 40 10 6.0 70 60 CO 00 1O 0 2.0 3 4to 50 to 7.0 a0 .0 Time (sec) Time (sec)

Figure 50 Plant Response to MSIN' Closure (Flux Scram) - ICF Page 81

- ;-HOPE CREEK I 0000-003 1-9425-MCAR-SRLR Reload 13 Rev. 0 07O,

-Vessel Ress Rise (pe)

-*-SafetyValve Flow 3M0 -a- Refief Valve Flw

-46SS Vave Faw 25M0 X 17510 1s0 710

~~~~~. . . _1.....

1.0 20 30 40 5.0 5o 70 a 9O0 lnme (sec) Time (sec) 2oo o,

-e-Level - Indcatove Sep Sldrt

• -Vessel Seam Fkw 1750 Turtine Steam Flw Feewaer Flow

• o5o0 1250 J 1000 Sao0 004

.250

-00 '

00 1.0 20 00 4.0 50 Mo 7.0 o 0o0 1.0 20 3.0 4.0 5.0 ae 70 e0 0.0 Time (sec) Thie (sec)

Figure 51 Plant Response to MSIV Closure (Flux Scram) - MELLLA Page 82

--"HOPE CREEK I 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Appendix A Analysis Conditions To rcflcct actual plant paramncters accuratcly, the values showvn in Tablc A-I were used.

Table A-I Analysis Value 14 Parameter ICF l C & MELLLA MEMLLLT&

Thermal power. MWt 3840.0 3840.0 3840.0 3840.0 Core flow. Mlblhr 105.0 105.0 94.8 94.8 Reactorpressure (core mid-plane), psia 1036.0 1030.1 1034.0 1028.1 Inlet enthalpv. Btu/lb 526.3 522.4 523.8 519.6 Non-fuel power ftaction 0.036 0.036 0.036 0.036 Steam flow. Mlb/hr 16.80 16.28 16.78 16.27 Dome pressure, psig 1005.0 999.4 1005.0 999.4 Turbine pressure, psig 945.8 943.6 946.0 943.7 No. of Safetv/Relief Valves' 5 14 14 14 14 Relief mode lowest setpoint, psig 1141.2 1141.2 1141.2 1141.2 Safctv mode lowest sctpoint. psig - - -

14 These analysis values were also applied for RPTOOS condition for ICF and MELLLA.

15 One SRV is allowed to be out of service.

Page 83

HOPE CREEK I 0000-03 1-9425-MCAR-SRLR Reload 13 Rev. 0 Appendix B List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective

%NBR Percent Nuclear Boiler Rated 2RPT Two Rccirculation 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 Cvcle BSP Backup Stability Protection BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPPU Constant Pressure Power Up-rate CPR Critical Power Ratio DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decav Ratio ECCS Emergencv Core Cooling System EEOC Extended End of Cycle ELLLA Extended Load Line Limit Analvsis EOC End of Cvcle EOR End of Rated (All Rods Out 100%YoPower/ 100%Flow /NFVT)

ER Exclusion Region FFWTR Final Feedwatcr Temperature Reduction FMCPR Final MCPR FOM Figure of Mcrit FWCF Feedwater Controller Failure FWTR Feedwater Temperature Reduction GDC General Design Criterion GESTAR General Electric Standard Application for Reactor Fuel GETAB Gcncal Electric Thermal Analvsis Basis GSF General Shape Function HAL Haling Bum HBB Hard Bottom Bum HBOM Hot Bundle Oscillation Magnitude HCGS Hope Creek Generating Station HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line Page 84

HOPE CREEK1 i ' 0000-0031 -9425-MCAR-SRLR.--.

Reload 13 Rev. 0 Acronym Description HPCI High Pressure Coolant Injection ICA Interim Corrective Action ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix LHGR Linear Heat Generation Rate LHGRFAC Linear Heat Generation Rate 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 MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MELLLA Maximum Extended Load Line Limit Analvsis MELLLA+ MELLLA Plus MFWT Minimum Feedwvater Tcmpcrature MOC Middle of Cvcle MRB Maximal Region Boundaries MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Servicc MTU Metric Ton Uranium MWd Megawatt dav MNYd/ST Mcgawatt 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 Burn NTR Nornal Trip Reference OLMCPR Operating Limit MCPR OOS Out of Service OPRM Oscillation Power Range Monitor Pdome Peak Dome Pressure PsI Peak Steamn Line Pressure Pv Peak Vcsscl Pressure PCT Peak Clad Temperature P-E Peak Hot Excess PLHGR Peak Linear Heat Generation Rate PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Dowxnscalc PROOS Pressure Regulator Out of Service Q/A Heat Flux RBM Rod Block Monitor Page 85

HOPE CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Acronym Description RC Reference Cycle RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RTP Rated Thermal Power RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cvcle SL Safetv Limit SLMCPR Safetv Limit Minimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report SRV Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Stcadv State STU Short Tons (or Standard Tons) of Uranium TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbinc Control Valve Out of Scrvice TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Referencc Function TTHBP Turbine Trip with Half Bypass TINBP Turbine Trip without Bypass UB Under Bum Page 86

HOPE CREEK 1 J' 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Appendix C Decrease In Core Coolant Temperature Events The Loss-of-Feedwater event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is permitted in GESTAR II. The transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BW'R Simulator Code; therefore, those items are not included in this document. The OLMCPR result is showvn in Section 11.

In addition, the Inadvertent HPCI start-up event without a Level 8 turbine trip was shown to be bounded by the LFWH event in accordance with Determination of Limiting Cold Water Event, NEDC-32538P-A.

The Cycle 13 SRLR Rev. 1 (Reference C-1) indicated the Inadvertent HPCI with a Level 8 turbine trip is non-limiting. The Inadvertent HPCI with a Level 8 turbine trip was confirmed as non-limiting for Cycle 14.

References:

C-1. 0000-0031-0596-SRLR, Supplemental Reload Licensing Report for Hope Creek Unit 1 Reload 12/Cycle 13, Revision 1, December 2004.

Page 87

HOPE:CREEK 1 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Appendix D Reactor Recirculation Pump Seizure Event The reactor recirculation pump seizure event was analyzed for Single Loop Operation (SLO) at HCGS (Reference D-1). This analysis was performed for the HCGS Cycle 13 transition cycle with GE14 and SVEA96+ fuel in the core and transient analysis inputs consistent with the Reload 12/Cycle 13 analyses.

The SLO operating limit minimum critical power ratio (OLMCPR) of 1.51 is required so that the reference SLO safety limit minimum critical power ratio (SLMCPR) of 1.12 is protected in the event of a seizure of the recirculation pump in the active loop. If the cycle-specific SLMCPR changes then the SLO OLMCPR may be adjusted by the following factor.

(Cycle Specific SLMCPR/ 1.12)

Thus, for HCGS Cycle 14 with a SLO SLMCPR of 1.09 the SLO OLMCPR required is:

1.51 * (1.09/1.12)= 1.47 In order to protect the required SLO OLMCPR of 1.47 (based on a SLO SLMCPR of 1.09) the following two loop operation (TLO) limit must be maintained consistent with the post ARTS implementation applied in Cycle 13.

As long as the TLO full power OLMCPR is 1.28 or greater, the proposed Hope Creek K(p) curve bounds operation in SLO. If the full power OLMCPR is lower than 1.28 and is not bounded by the cycle specific off-rated limits, then the condition specific SLO OLMCPR of 1.47 should be applied for GE14 fuel and SVrEA96+ fuel.

References:

D-1. NEDC-33 158P, Fuel TransitionReportfor Hope Creek GeneratingStation, Revision 4, March 2005.

Page 88

HOPE CREEK I . 0000-0031-9425-MCAR-SRLR Reload 13 Rev. 0 Appendix E Power and Flow Dependent Limits The potentially limiting anticipated operational occurrences (AOOs) and accident analyses were evaluated to support HCGS operation with ARTS off-mted limits as well as operation at CPPU RTP.

Analyses were performed to determine the limiting MCPR requirement based on the HCGS fuel and core configuration at CPPU and the off-rated power and flow dependent MCPR and LHGRFAC limit curves (Rcfcrcncc E-l).

A disconnect between the performance of the turbine protection systems and the transient analysis assumptions for a generator load rejection event was identified for the operating domain between Pbypass and the point at which the Power Load Unbalance (PLU) system is enabled. For HCGS, a generator load rejection below the PLU power level would generate a delayed turbine trip. Analyses were performed to show that the generic K(P) and LHGRFAC(P) limits bound this event in the range bctwcen Pbypass and the PLU enabling power level (Reference E-1).

References:

E-l. NEDC-33158P, Fuel Transition Report for Hope Creek Generating Station, Supplement 1, March 2005.

Page 89