ML20115H297

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


Text

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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 ; xd /h I  % DATE :

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REVIEWED BY : . hU2: 6 .ri- DATE : 9!' h REVIEWED BY .1._ u w, - DATE 2_ #/!I!f L APPROVED BY : <

- DATE : /C<

2-j i 9210270076 021020 PDR ADOCK 05000354 P. PDR

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t' NFU-145 i i Revision 0 l September 2, 1992 -i i

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c TABLE OF CONTENTS s

S ECTIOt{ ' 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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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 I Revision 0 September 2, 1992 I

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.

l Ie.ch. Spec Ticle  !

l 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  ;

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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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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 0.4 Mlb/f ti 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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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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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 4. " Supplemental Reload Licensing Submittal for Hope Creek 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.

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