ML20064F718

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Rev 1 to Core Operating Limits Rept for Hope Creek Generating Station Cycle 5/Reload 4
ML20064F718
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 01/31/1994
From:
Public Service Enterprise Group
To:
Shared Package
ML20064F705 List:
References
NFU-145, NFU-145-R01, NFU-145-R1, NUDOCS 9403150412
Download: ML20064F718 (16)
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NFU-145 -

Revision 1 January 31, 1994 i

.i CORE OPERATING LIMITS REPORT l HOPE CREEK GENERATING STATION CYCLE 5 / RELOAD 4 1

January 31, 1994 I

PREPARED BY /

C DATE .

REVIEWED BY -

6 A SOM DATE : 2_ /V / b/ .

REVIEWED BY :

-~ ~ , DATE -

?/V/N APPROVED BY -

/ -- DATE : A/7/9Y, 9403150412 940308 ,.,

E PDR ADOCK 05000354 p PDR

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l' NFU-145 i

' Revision 1 l January 31, 1994 .j i ,

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F TABLE OF CONTENTS 1

l SECTION TITLE PAGE .j

3. .i 1

1.0 Introduction 4 j

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i 2.0 Limiting Conditions for Operation 5 1 j

2.1 Maximum Average Planar Linear Heat 6-Generation Rate

2.2 Minimum Critical Power Ratio 11 i

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2.3 Linear Heat Generation Rate 15 3.0 References 16 ,

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NFU-145  !

Revision 1 January 31, 1994-i l

I LIST OF FIGURES NUMBER TITLE PAGE 1

2-1 MAPLHGR Versus Exposure for Fuel Bundle Type 7 P8CRB299HA 2-2 MAPLHGR Versus Exposure for Fuel Bundle Type 8 P8CRB300L

.l 2-3 MAPLHGR Versus Exposure for the Most Limiting 9 Lattice of Fuel Bundle Type P8CWB325-11GZ1 1

2-4 MAPLHGR Versus Exposure for the Most Limiting 10 Lattice of Fual Bundle Type P8CWB325-11GZ2 2-5 MCPR Versus Tau At 105%-Fl.ow For Fuel Bundle Type. .12 q GE9B For Cycle Extension Operation l'

2-6 MCPR Versus Tau At 105% Flow For Fuel Bundle 137)e -13 GE7B For Cycle Extension Operation 2-7 K, Versus Core Flow 14 1

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-I NFU-145 Revision 1 January 31, 1994 I

1.O INTRODUCTION The purpose of this report is to provide a description of the Core Operating Limits for the Hope Creek Generating Station Unit 1 .i extended operation for cycle 5. The specific parameter limits are

Average Planar Linear Heat Generation Rate (APLHGR); Minimum- ,

Critical Power Ratio (MCPR) ; Flow Adjustment Factor, K,; and Linear - -l Heat Generation Rate (LHGR). These values have been determined using NRC-approved methodology and are established such that all  ;

applicable 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 5 / Reload 4 and shall not be applicable to any ather core or cycle design.

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NFU-145 Revision 1 January 31, 1994 LQ LIMITING CONDITIONS FOR OPERATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced by the Hope Creek Technical Specifications.

Tech. Spec 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 5

NFU-145 Revision 1 January 31, 1994 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION: ALL AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for bundle type P8CRB299HA, and P8CRB300L as a function of AVERAGE PLANAR EXPOSURE shall not exceed ,

the limits shown in Figure 2-1 and 2-2, respectively. When. hand -

calculations are required, the APLHGRs for each lattice type-(excluding natural Uranium). in bundle P8CWB325-11GZ1 as a function -

of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in .

Figure 2-3; and the APLHGRs- for each lattice type (excluding natural Uranium) in bundle P8CWB325-11GZ2 as a function of AVERAGE  :

PLANAR EXPOSURE shall not exceed the limits shown in Figure 2-4.

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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. NFU-145 Revision 1-January 31, 1994 4 i 1-s 2.2 MINIMUM CRITICAL POWER RATIO i

LIMITING CONDITION FOR OPERATION: The MINIMUM CRITICAL POWER RATIO  !

] (CPR) shall be equal to or greater than the CPR limit times the k,

shown in Figure 2-7.

-1 It requires an adjustment to the K, values for bundle flows below ~!

0.4 Mlb/f tz -hr and incorporation of a 3% adjustment factor if inlet

' subcooling exceeds 70 Btu /lbm. I 3

The CPR limit i's shown in Figure 2-5 for GE9B bundles and in Figure l 2-6 for GE7B bundles. j The CPR limit is a function of Core Average Exposure, and core  !

. average scram speed, 7 (Tau), defined by Technical Specification- 1 3.2.3.

. End-of-Cycle Recirculation Pump Trip system status is' defined

operable or inoperable per Technical Specification 3.3.4,2..

l Main Turbine Bypass must be operable.per Technical Specification i 3.7.7. ,

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1.4 1.39 1.38 1.37 1.36 lEOC-RPT INOPERABLEl 1.35 1.34-  ! y 1.33- -

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Fig. 2-5 MCPR Versus Tou AT 105% flow For Fuel Bundle gm w

Type 98 for Cycle Extension Operation ye H

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4 1.4 g i AUTOMATIC FLOW CONTROL I CI For 40%<F<100% Kf= WAX (1.0,(A+B(F/100)))

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Arc t.44to -0.441 117.0 1.40$ -0.441 1

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107.0 1.352s -0.441 102.5 1 -0.441

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Wanual Flow Control Scoop Tube Setpoint Collbrution Poe1 Honed Such That These Are Waximum Core Flow Volues.

S$$ 1 0.9 @ $. Y 20 30 40 50 60 70 80 90 100 110 m 02 e M e- A Core Flow, % of Roted Core Flow <gm Me Fig. 2-7 Kf Versus Core Flow -

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'NFU-145 Revision 1. ,

[- January 31, 1994 l l

b L.

4 l - 2.3 LINEAR HEAT GENERATION RATE i

, LIMITING CONDITION FOR OPERATION : The LINEAR HEAT GENERATION RATE (LHGR) for each type of fuel shall not. exceed the applicable limits:

i Fuel Type LHGR Limit (Kw/ft) l l GE7B-P8CRB299HA 13.4 GE7B-P8CRB300L 13.4 -i

, GE9B-P8CNB325-11GZ1 14.4 GE9B-P8CWB325-11GZ2 14.4 R

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l NFU-145 Revision 1 January 31, 1994 I

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3.0 REFERENCES

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" General Electric Standard Application For Reactor Fuel", i NEDE-24011-P-A, Revision 10, February, 1991. ~

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2. R.B. Linford, " Analytical Methods of Plant Transient  ;

Evaluation for the GE BWR", NEDO-10802, February 1973. I i

3. " Qualification of the One Dimensional Core Transient Model for i l

Boiling Water Reactors", NEDO-24154, October 1978.

4. " Supplemental . Reload Licensing Submittal for Hope Creek j Generating Station Unit 1, Reload 4 Cycle 5", General Electric j Company, 23A7162, Rev 0, July, 1992.

5 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.

6. L.F. Rubino (General Electric) to E.S. Rosenfeld (PSE&G),

" Extended Operation Transient Analysis - Hope Creek Cycle'5",

December 16, 1993, NFSI 93-751.

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