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NFU-145 -

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CORE OPERATING LIMITS REPORT l

HOPE CREEK GENERATING STATION

CYCLE 5 / RELOAD 41

January 31, 1994

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'CPREPARED BY / DATE .

2_ /V / b/ .6 A SOM DATE :REVIEWED BY -

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DATEREVIEWED BY : -~ ~ ,-

A/7/9Y,/ -- DATE :APPROVED BY -

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9403150412 940308 , . ,

PDR ADOCK 05000354 E

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F TABLE OF CONTENTS'

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3 .SECTION TITLE PAGE .j

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1.0 Introduction 4 jL .

i 2.0 Limiting Conditions for Operation 5 1j

2.1 Maximum Average Planar Linear Heat 6-

Generation Rate.

; 2.2 Minimum Critical Power Ratio 11i

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; 2.3 Linear Heat Generation Rate 15

3.0 References 16 ,

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NFU-145 !

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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.|

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

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2-4 MAPLHGR Versus Exposure for the Most Limiting 10Lattice of Fual Bundle Type P8CWB325-11GZ2

2-5 MCPR Versus Tau At 105%-Fl.ow For Fuel Bundle Type. .12 qGE9B 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

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NFU-145 - I

Revision 1January 31, 1994

I1.O INTRODUCTION

The purpose of this report is to provide a description of theCore 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 - - |'

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 staffwith respect to the cycle specific aspects of core operation.

The Hope -Creek Technical Specifications references thisreport 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 4and shall not be applicable to any ather core or cycle design.

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NFU-145Revision 1January 31, 1994

LQ LIMITING CONDITIONS FOR OPERATION

The LIMITING CONDITIONS FOR OPERATION presented in thissection 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

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NFU-145Revision 1January 31, 1994

2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE

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LIMITING CONDITION FOR OPERATION: ALL AVERAGE PLANAR LINEAR HEATGENERATION RATES (APLHGRs) for bundle type P8CRB299HA, andP8CRB300L 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 (excludingnatural 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 0.86times the two recirculation loop operation limit when in singlerecirculation loop operation.

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is,32.2)(tu,te.:b i 12.2)

"-' A (2s,is.si

12 -- e ', %#C (0.2,5 t.4| p

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(i.t n.s) %,

cr 11 ; ; -mO N'E \ sd" %4 N N2 q (45.s.s)

10-%

%

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0 5 10 15 20 25 30 35 40 45 qxg

Average Planar Exposure, GWD/ST $$@C H- e

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% O tn

w"Fig. 2-1 MAPLHGR Versus Exposure for Fuel Bundle Type P8CRB299HA yvHW

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;is,12.2)(1a,3 2.1F 2AtQ

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(s.32.0) ' %{2st1.si%12- - r

5(0.2.11.4+ i / %

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's %'s % (sat 1.0>(1.11S) s

c: 1 1 -- -

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N$ \.E (4s.o.s)

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g_ _

80 5 10 15 20 25 30 35 40 45

Average Pianor Exposure, GWD/ST qyzw co na < c:C H- e

mmh

Fig. 2-2 MAPLHGR Versus Exposure for Fuel Bundle Type P8CRB300L Q & fnu"HH

HW

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(l2.$.13.01|III|

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(10.12.94 i

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% 'lli / s

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(25.88.J) % gg5\

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0 5 10 15 20 25 30 35 40 45 50 55

Average Planar Exposure, GWD/ST qxa> c ma<c

Fig. 2-3 MAPLHGR Versus Exposure for the Most Umiling Lattice g ||:,n r. Aof Fust Bundle Type P8CWB325-11GZ1 % O us

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(ASILE) % ( 6 25>39- - s'

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Average Planor Exposure, GWD/ST c. :o zmemEj.9

Fig. 2-4 MAPLHGR Versus Exposure for the Most Limiting Lattice mm-of Fuel Bundle Type P8CWB325-11GZ2 H- 4

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2.2 MINIMUM CRITICAL POWER RATIOi

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.

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It requires an adjustment to the K, values for bundle flows below ~ !z0.4 Mlb/f t -hr and incorporation of a 3% adjustment factor if inlet

subcooling exceeds 70 Btu /lbm. I'

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3 The CPR limit i's shown in Figure 2-5 for GE9B bundles and in Figure |2-6 for GE7B bundles. j

The CPR limit is a function of Core Average Exposure, and core.

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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..

| Main Turbine Bypass must be operable.per Technical Specificationi 3.7.7. ,

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1.39

1.38

1.37

1.36|EOC-RPT INOPERABLEl

1.35!1.34- y-1.33- -#1.32- p

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H 1.29w1.28

1.27- -

1.26 EOC-RPT AND MA N1.25 BYPASS OPERABLE

1.24

1.23

1.22,

1.21

1.2 m$$0 0.2 0.4 0.6 0.8 1

Tau E19*ErE

Fig. 2-5 MCPR Versus Tou AT 105% flow For Fuel Bundle gmType 98 for Cycle Extension Operation w

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1.39

1.38

1.37 iEOC-RP1 INOPERABLEi1.36

/1.35/

1.34- p#1 33- #

1.32- p"a: 1.31- pp #0- M #1 '3 _ #b) # h2 1.29 - #H

\"1.2s - #

1.27 \1.26 EOC-RPT AND MAIN1.25 BYPASS OPERABLE

1.24

1.23

1.22

1.21

1.2O O.2 0.4 0.6 0.8 1

Tau4 :o z

Fig. 2-6 MCPR Versus Tau At 105% Flow For Fuel Bundle @QyType 78 For Cycle Extension Operation g;4

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1.4 g iAUTOMATIC FLOW CONTROLI CI For 40%<F<100% Kf= WAX (1.0,(A+B(F/100))),,7_g ,

Ij2.0P | I Iefor Ff 40% Kf= (A+B(F,,100)) (1.0+0.0032(40-F) i

107 \1.3g.0P^ 3 vong A - g102.s e '

Arc t.44to -0.441

117.0 1.40$ -0.4411

\ - \ Il12.0 1.3793 -0.441

1.2 107.0 1.352s -0.441

102.5 1 -0.441+M

e %A 1.1 %

x N .1

Wanual Flow Control Scoop Tube SetpointCollbrution Poe1 Honed Such That TheseAre Waximum Core Flow Volues.

S$$1

@ $. Y0.920 30 40 50 60 70 80 90 100 110 m 02 e

M e- ACore Flow, % of Roted Core Flow <gmMe

Fig. 2-7 Kf Versus Core Flow -

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| - 2.3 LINEAR HEAT GENERATION RATE

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LIMITING CONDITION FOR OPERATION : The LINEAR HEAT GENERATION RATE,

(LHGR) for each type of fuel shall not. exceed the applicablelimits:-

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

GE7B-P8CRB300L 13.4 -iGE9B-P8CNB325-11GZ1 14.4

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GE9B-P8CWB325-11GZ2 14.4'

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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. ~|1

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

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

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

|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 jCompany, 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.

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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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