Text

Rev 0 to COLR Hope Creek Generating Station,Cycle 5/Reload 4
	ML20115H297
Person / Time
Site:	Hope Creek
Issue date:	09/10/1992
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML20115H287	List: ML20115H284; ML20115H297;
References
	NFU-145, NFU-145-R, NFU-145-R00, NUDOCS 9210270076
	Download: ML20115H297 (16)
	v • d • e

_ _ _ _

NFU-145 Revision 0 Sttptember 2, 1992 I

I CORE OPERATING LIMITS REPORT HOPE CREEK GEt r: RATING STATION CYCLE 5 / RELOAD 4 Septembeff 2, 1992 rREPARED BY ;

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9210270076 021020 PDR ADOCK 05000354 P.

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September 2, 1992

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TITLE PAGE 1.0 Introduction 4

1 2-O Limiting Cond4eions for Operation-5 2.1 Maximum Average-Planar Linear Heat 6

Generation Rate 2.2 Minimum Critical Power Ratio 11 2.3 Linear Heat Gener' tion Rate

- 15 3.0 References 16 i

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NFU-145 Revision 0 September 2, 1992 LIST OF FIGURES

. NUMBER TITLE p]s33 2-1 MAPLHGR Versus Exposure for Fuel Bundle Type 7

P8CRB299EA 2-2 MAPLHGR Versus Exposure for Fuel Bundle Type 8

P8CRB300L 2-3 MAPLHGR Versus Exposure for the Most Limiting 9

Lattice of Fuel Bundle Type P8CWB325-11GZ1 2-4 MAPLHGR Versus Exposure for the Most Limiting 10-Lattice of Fuel Bundle Type P8CWB325-11GZ2-2-5 MCPR Versus Tau At Rated Flow For Fuel Bundle Type 12 GE9B From BOC To EOC ll 2-6 MCPR Versus Tau At Rated Flow For Fuel Bundle Type-13 G37B From BOC To'EOC 2-7 K, Versus Core Flow 14 l

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_ _ _ _ _ _ _ _ _. ~. - _. _ _ _ _ ~ - _... _ _ _ _ _ _ _

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l NFU-14 5 Re"ision 0 Septenber 2, 1992 t

L_Q IRIRQ MCTION The purpose of this report is to, ovide a description of the Core Operating Limits for the Hope Cr n. Genertting Station-Unit 1 Cycle 5 egecation.

The specific pai

.er limits are

_ Average Planar Linear Heat Generation Rite (APLaGR); Minimum Critical Power Ratio (MCPR); Flea adjustment Factor, K,; uinear Heat Generation Rate (LHGR). These values have been determined using NRC-approved 1-methodology and are established such that all applicable limits of the plant safety analysis are met.

1 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 f or certain LIMITING CONDITIONS FOR OPERATION.

These are included in section 2 of this document.

This documer.t is specific to Hope Creek Cycle 5 /-Reload 4 and shall not be applicable to any other core or cycle design.

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NFU 145 Revision 0 September 2, 1992 L.Q kI141 TING CQNDITIORS FOR OR D ATION The LIMITING CONDITIONS FOR OPERATION presented in this section are referenced by the Hope Creek Technical Specifications.

Ie.ch. Spec Ticle 3/4.2.1 Average Planar Linsat Heat Generation Rate 3/4.2.3

-Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generatica Rate i

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NFU 145 Revision 0 l

September 2, 1992 221 MEPJfGE PLANAR LU(EMLJ1 FAT _fIHERATION RATE LIMITING CONDITION FOR OPERATION: ALL AVERAGE PLANAR LINEAR HFJtT -

I GENERATION RATES (APLHGRs) for bundle type P8CRB299HA,

, id P8CRB300L as a function of AVERAGE PLANAR EXPOSURE shall not exct ed the limits shown in Figure 2 1 and 2 2, respectively. When-hand calculation 9 are required, the APLHGRs for each lattice type (excluding r.atiaral Uranium) in bundle P8CWB325 11GZ1 as a function of AVERAGE PCAMAR 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 PIJdiAR EXPOSURE shall not exceed the limits shown in Figure 2 4.

The limits of thesa figures shall be reduced to a value of 0.86 times the two reci-culation loop operation limit when in single recirculation loop m'eration, f

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O NPU+145 Revision 0 September 2, 1992 1

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NFU-145 Revision 0 September 2, 1992

222, MlHIMWLCRIT! CAL POWEILRATIO 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.

It *equires an adjustment to the K, values for bundle flows below i

0.4 Mlb/f t hr and incorporation of a 3% adjustment f actor if inlet subcooling exceeds 70 Btu /lbm.

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

3 The CPR 1imit is a function of Core Average Exposure, and core average scram speed, r (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.

Main Turbine Bypass must be operable per Technical Specification 3.7.7-tem 11

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Wonual Flow Control Scoop Tube Setpoint Cor.brution Poefttoned Such That These 1

Are Wanknum Core Fbw Volues.

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4 NFU 145 Revision 0 September 2, 1992 2.J IdfRAILliFAI_GELEEATlDN RATE LIMITING CONDITION FOR OPERATION : The LINEAR HEAT GENERATION RATE (LHGR) for each type of fuel shall not exceed the applicable limits:

F1el_ Type ISGR Limit (Kw/ft)

GE7B-P 8CRB29 911A 13.4 GE7B P8 COB 300L 13.4 GE9B P8CWB325-11GZ1 14.4 GE98-P8CWB325-11GZ2 14.4

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15

NFU 145 Revision 0 September 2, 1992 M

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.

3.

" Qualification of the One Dimensional Core Transient Model for Boiling Water Reactors", NEDO-24154, October 1978.

4.

" Supplemental Reload Licensing Submittal for Hope Creek 4

Generating Station Unit 1, Reload 4 Cycle 5", General Electnc Company, 23A7162, Rev 0, July, 1992.

g a

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.

s LAST PAGE 16 i

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ML20115H297

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