ML20072N841

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Resubmitted COLR Hope Creek Generating Station Cycle 6/ Reload 5
ML20072N841
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 02/24/1994
From:
Public Service Enterprise Group
To:
Shared Package
ML20072N824 List:
References
NFS-0090-01, NFS-0090-R00, NFS-90-1, NFS-90-R, NUDOCS 9409070019
Download: ML20072N841 (18)
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1 NFS-0090 '

Revision 0 l February 15, 1994 CORE OPERATING LIMITS REPORT HOPE CREEK GENERATING STATION CYCLE 6 / RELOAD 5 February 15, 1994 PREPARED BY : 8 7

C b~ DATE :

[ C. Lai Senior E ineer PEER REVIEW BY : ( -

DATE : 79 C . 'S . Bfennan /

Senio St ff Engineer CONCURRENCE BY :/ DATE . 2 /t y M y W M. Haun uclear Fue s Enginee APPROVED BY r//l

d // / s _ _ DATE :

/l2Y' E. S. Rosenfelf' Manager - Nucrear Fuel  ;

l 9409070019 940215 4 PDR ADOCK 0500 P

NFS-0090 1 Revision 0 l February 15, 1994 l

TABLE OF CONTENTS i EECTION TITLE PAGE j l

1.0 Introduction 6 2.0 Limiting Conditions for Operation 7 2.1 Maximum Average Planar Linear Heat 8 Generation Rate 2.2 Minimum Critical Power Ratio 13 2.3 Linear Heat Generation Rate 17 3.0 References 18  ;

Appendix A Appendix B I 2 ,

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NFS-0090 Revision 0 February 15, 1994 l l

i I

LIST OF FIGURES l l

NUMBER TITLE PAGE 2-1 MAPLHGR Versus Exposure for Fuel Bundle Type' 9 P8CRB300L l 2-2 MAPLHGR Versus Exposure for the Most Limiting 10 Lattice of Fuel Bundle Type P8CWB325-11GZ2 2-3 MAPLHGR Versus Exposure for the Most Limiting 11 Lattice of Fuel Bundle Type P8CWB325-11GZ1 2-4 MAPLHGR Versus Exposure for the Most Limiting 12 Lattice of Fuel Bundle Type P8CWB325-9GZ1 2-5 MCPR Versus Tau At Rated Flow For Fuel Bundle Type 14 GE9B From BOC To EOC 2-6 MCPR Versus Tau At Rated Flow For Fuel Bundle Type 15 GE7B From BOC To EOC _

2-7 K, Versus Core Flow 16  ;

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l NFS-0090 Revision 0 I

February 15, 1994 LIST OF TABLES NUMBER TITLE PAGE 2-1 LHGR Limits 15 A-1 Lattice Descriptions in Fuel bundle GE9B-P8CWB325- A-4  ;

11GZ1-80M-150-T A-2 Lattice Descriptions in Fuel bundle GE9B-P8CWB325- A-5 11GZ2-80M-150-T A-3 Composite MAPLHGR Versus Exposure for Lattice A-6 P8CWLO71-NOG-80M-T (Type 1) in Bundle GE9B-P8CWB325

-11GZ1-80M-150-T ,

A-4 Composite MAPLHGR Versus Exposure for Lattice A-7 P8CWL349-5G5.0/4G4.0-80M-T (Type 2) in Bundle GE9B-P8CWB325-11GZ1-80M-150-T A-5 Composite MAPLHGR Versus Exposure for Lattice A-8 P8CWL366-9G4.0-80M-T (Type 3) in Bundle GE9B- -

P8CWB325-11GZ1-80M-150-T A-6 Composite MAPLHGR Versus Exposure for Lattice A-9 P8CWL366-2G5.0/9G4.0-80M-T (Type 4) in Bundle GE9B-P8CWB325-11GZ1-80M-150-T A-7 Composite MAPLHGR Versus Exposure for Lattice A-10 P8CWL349-9G4.0-80M-T (Type 5) in Bundle GE9B-P8CWB325-11GZ1-80M-150-T A-8 Composite MAPLHGR Versus Exposure for Lattice A-11 P8CWLO71-11GE-80M-T'(Type 6) in Bundle GE9B-P8CWB325-11GZ1-80M-150-T A-9 Composite MAPLHGR Versus Exposure for Lattice A-12 P8CWLO71-NOG-80M-T (Type 1) in Bundle GE9B-P8CWB325-11GZ2-80M-150-T A-10 Composite MAPLHGR Versus Exposure for Lattice A-13 P8CWL350-9G5.0-80M-T (Type 2) in Bundle GE9B-P8CWB325-11GZ2-80M-150-T 4

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l NFS-0090 Revision 0 February 15, 1994 I

NUMBER TITLE PAGE ,

A-11 Composite MAPLHGR Versus Exposure for Lattice A-14 P8CWL366-7G5.0/2G4.0-80M-T (Type 3) in Bundle GE9B-P8CWB325-11GZ2-80M-150-T A-12 Composite MAPLHGR Versus Exposure for Lattice A-15 P8CWL366-9G5.0/2G4.0-80M-T (Type 4) in Bundle GE9B-P8CWB325-11GZ2-80M-150-T A-13 Composite MAPLHGR Versus Exposure for Lattice A-16 P8CWL350-7G5.0/2G4.0-80M-T (Type 5) in Bundle GE9B-P8CWB325-11GZ2-80M-150-T A-14 Composite MAPLHGR Versus Exposure for Lattice A-17 P8CWLO71-11 gel-80M-T (Type 6) in Bundle GE9B-P8CWB325-11GZ2-80M-150-T B-1 Lattice Descriptions in Fuel bundle GE9B-P8CWB324- B-3 9GZ1-80M-150-T B-2 Composite MAPLHGR Versus Exposure for Lattice B-4 732 & 1757 (Type 1 and 5) in Bundle GE9B- _

P8CWB324-9GZ1-80M-150-T B-3 Composite MAPLHGR Versus Exposure for Lattice B-5 1046 (Type 2) in Bundle GE9B-P8CWB324-9GZ1-80M-150-T B-4 Composite MAPLHGR Versus Exposure for Lattice B-6 1047 (Type 3) in Bundle GE9B-P8CWB324-9GZ1-80M-150-T B-5 Composite MAPLHGR Versus Exposure for Lattice B-7 1770 (Type 4) in Bundle GE9B-P8CWB324-9GZ1-80M-150-T 5

NFS-0090 Revision 0 February 15, 1994

1.0 INTRODUCTION

The purpose of this report is to provide a description of the Core Operating Limits for the Hope Creek Generating Station Unit 1 Cycle 6 operation. The specific parameter limits are : Average Planar Linear Heat Generation Rate (APLHGR) ; Minimum Critical Power Ratio (MCPR); Flow Adjustment Factor, K,; and Linear Heat Generation Rate (LHGR). These values have been determined using NRC-approved methodology (REF.1) and are established such that all applicable limits, namely; fuel thermal-mechanical, core thermal-hydraulic, ECCS, and nuclear limits such as shutdown margin, and transient and accident analysis limits; of the plant safety analysis are met.

This report is intended to be used for operation of the Hope Creek reactor core and for the training of the operations staff with respect to the cycle specific aspects of core operation.

The Hope Creek Technical Specifications references this report as the source for certain LIMITING CONDITIONS FOR OPERATION.

These are included in section 2 of this document.

This document is specific to Hope Creek Cycle 6 / Reload 5 and shall not be applicable to any other core or cycle design. _

i 1

1 6

4 NFS-0090 Revision 0 February 15, 1994 2.0 LIMITING CONDITIONS FOR OPERATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced by the Hope Creek Technical Specifications.

Tech. Soec Title 3/4.2.1 Average Planar Linear Heat Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 7

NFS-0090 Revision 0 February 15, 1994 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION: ALL AVERAGE PLANAR LINEAR HEAT-.

GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits specified in this report.

All APLHGRs for bundle type P8CRB300L as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figure 2-1.

When hand calculations are required, the APLHGRs for each lattice type (excluding natural Uranium) in bundle P8CWB325-11GZ2, P8CWB325-11GZ1 and P8CWB324-9GZ1 as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figure 2-2, Figure 2-3, and Figure 2-4, respectively. The limits of these figures shall be reduced to a value of 0.86 times the two recirculation loop operation limit when in single recirculation loop operation.

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NFS-0090 Revision 0 February 15, 1994 2.2 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION: The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the CPR limit times the k, curve.

The CPR limit is shown in Figure 2-5 for GE9B bundles and in Figure 2-6 for GE7B bundles. The K, curve is shown in Figure 2-7.

It requires an adjustment to the K, values for bundle flows below 0.4 Mlb/f t z -hr, this adjustment is incorporated in Fig. 2-7. It also requires the incorporation of a 3% adjustment factor if inlet subcooling exceeds 70 Btu /lbm.

The CPR limit is a function of Core Average Exposure, and core average scram speed, 7 (Tau), defined by Technical Specification 3.2.3.

End-of-Cycle Recirculation Pump Trip system status is defined operable or inoperable per Technical Specification 3.3.4.2, Mair Turbine Bypass must be operable per Technical Specification 3.7.7. _

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1.4 i I AUTouAftC FLOW CONTROL W C) for 40%<f<100% Kf = WAX (1.0,(A+B(F/100)))

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Wonual Flow Control Scoop Tube Setpoint Collbration Poeltloned Such That These Arw Womimum Core Flow Values.

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NFS-0090 Revision 0 February 15, 1994 2.3 LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION : The LINEAR HEAT GENERATION RATE (LHGR) for each type of fuel shall not exceed the applicable limits:

TABLE 2-1 LHGR Limits Fuel Tvoe LHGR Limit (Kw/ft)

GE7B-P8CRB300L 13.4 GE9B-P8CWB325-11GZ1 14 4 GE9B-P8CWB325-11GZ2 14.4 GE9B-P8CWB324-9GZ1 14.4 l

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i NFS-0090 i Revision 0 February 15, 1994

3.0 REFERENCES

1. " General Electric Standard Application For Reactor Fuel",

NEDE-24011-P-A, Revision 10, February, 1991.

2. R.B. Linford, " Analytical Methods of Plant Transient Evaluation for the GE BWR", NEDO-10802, February 1973.

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3. " Qualification of the One Dimensional Core Transient Model for j Boiling Water Reactors", NEDO-24154, October 1978. J
4. A.D.Vaughn (General Electric) to E.S. Rosenfeld (PSE&G),

"MAPLHGR Limits for Hope Creek Reload 1 Fuel Assemblies",

December 8, 1987, NFUI-87-552.

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5. A.D.Vaughn (General Electric) to E.S. Rosenfeld (PSE&G),

" Hope Creek Reload 3 GE9B Fuel Data", November 19, 1990, NFUI 90-437.

6. " General Electric Standard Application For Reactor Fuel",

Safety Evaluation Report For Application of Amendment 15, NEDE-24011-P-A, Revision 9, September, 1988.

7. NFU-VTDGE93-076-00, " Supplemental Reload Licensing Submittal for Hope Creek Generating Station Unit 1, Reload 5 Cycle 6",

General Electric Company, 23A7219, Rev 0, November, 1993.

8. NFU-VTDGE93-077-00, " Lattice-Dependent MAPLHGR Report for Hope Creek Generating Station Unit 1, Reload 5, Cycle 6",

23A7219AA, Rev.0, November, 1993 LAST PAGE 13 J

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