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Summary of 890214 Meeting W/Util & Westinghouse Re Licensee Reload Application.Licensee Proposed Tech Spec Changes Include Increased Peaking Factors,Positive Moderator Temp Coefficient & Increased Boron Concentration.Viewgraphs Encl
	ML20235R221
Person / Time
Site:	Callaway
Issue date:	02/23/1989
From:	Alexion T; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 8903030207
	Download: ML20235R221 (27)
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/. February 23, 1989 i Docket No. 50-483 LICENSEE: Union Electric C spany !

1 FACILITY: Callaway Plant

SUBJECT:

SUMMARI 0F MEET @ WITH UNION ELECTRIC COMPANY )

REGARDING CYCLE 4 RELOAD On February 14, 1989, the staff met with representatives from Union Electric Company and Westinghouse regarding the licensee's reload application. Meeting attendees are listed in Enclosure 1. Slides used are in Enclosure 2.

The licensee presented their reload application. The proposed reload will consist of 88 new Vantage 5 (V-5) fuel assemblies, together with 96 V-5 and 9 optimized fuel assemblies carried over from Cycle 3. Proposed technical

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specification changes include increased peaking factors, a positive moderator temperature coefficient (MTC), and increased boron and sodium hyroxide concentrations. The increased peaking factors are requested to allow more flexibility in the fuel management schemes and longer fuel cycles,. the positive MTC is requested to reduce the number of burnable absorbers needed with longer fuel cycles, the increased boron concentrations in the refueling water storage tank and in the accumulators are requested to support the positive MTC (and retain the required shutdown margin), and the increased sodium hydroxide concentration in the spray additive tank is requested to achieve the minimum long term post-loss-of-coolant-accident sump pH of 8.5 (in light of the increased boron concentrations discussed above).

The licensee also discussed the additional-design margin that would be available if WCAP-11837, " Extension of Methodology for Calculating Transition Core DNBR Penalties," was approved by the staff. The staff reiterated the position stated in its April 13, 1988 letter (and later by telecon) that the staff will not be able to complete its review of the WCAP in time for the Cycle 4 reload, due to higher priority work and the many other WCAP's ahead of WCAP-11837.

The staff asked several questions of a clarifying nature, including questions about the chrome electro-plating of the rod cluster control assemblies, the new debris-filter bottom nozzles for the fuel assemblies, the exit enthalpy equation provided on page 6 of the application, and the reallocation of the generic DNBR margin. All questions were appropriately answered by the licensee.

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8903030207 890223 PDR ADOCK 05000483 P PDC

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-2 The licensee concluded by stating that many of the Callaway Cycle 4 issues are similar to those previously approved on other plants and requested NRC approval by April 22, 1989. The staff replied by stating that no problen,s have been identified with the application at this time and it is expected that the staff can complete its review on the schedule requested.

J/

Thomas W. Alexion, Project Manager .'

Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation l

l 1

PDIll-3/MTG

SUMMARY

DISTRIBUTION Distribution

! Docket No' 50-4831 '

"NRC PDR' Local PDR ORAS HDenton CRossi Glainas DCrutchfield PDIII-3 r/f l PDill-3 s/f JHannon TAlexion PKreutzer OGC-WF EJordan BGrimes ACRS(10)

OPA LFMB DMossburg I

CALLAWAY MEETING

SUMMARY

OFC :P I-3:PD : : : :

PDIII-3:{M

__...:____ :PDIll-3:LA r ' ..:......_7____ :. ... ______: ____..._____:....________:____________:_...._____.

HAME :TAlei4 :PKredtzer :J inon : : : :

_____:...S4-___:..!_____..__:-_h__89 DATE :2/12/89 :2/n/89 I

2/ V 0FFICIAL RECORD COPY !

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Mr. D. F. Schnell Callaway Plant Union Electric Company Unit No. 1 cc:

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Dr. J. O. Cermack Mr. Bart D. Withers CFA Inc. President and Chief 4 Professional Dr., Suite 110 Executive Officer Gaithersburg, MD 20879 Wolf Creek Nuclear Operating Corporation Gerald Charnoff, Esq. P. O. Box 411 Thomas A. Baxter, Esq. Burlington, Kansas 66839 Shaw, Pittman, Potts & Trowbridge 2300 N Street, N. W. Mr. Dan I. Bolef, President Washington, D. C. 20037 Kay Drey, Representative Board of Directors Coalition Mr. T. P. Sharkey for the Environment Supervising Engineer, St. Louis Region Site Licensing 6267 Delmar Boulevard Union Electric Company University City, Missouri 63130 Post Office Box 620 Fulton, Missouri 65251 U. S. Nuclear Regulatory Connission Resident Inspectors Office RRf1 Steedman, Missouri 65077 Mr. Alan C. Passvater, Manager Licensing and Fuels Union Electric Company Post Office Box 149 St. Louis, Missouri 63166 l l

Manager - Electric Department Missouri Public Service Connission 301 W. High Post Office Box 360

Jefferson City, Missouri 65102 l Regional Administrator U. S. NRC, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources P. O. Box 176 Jefferson City, Missouri 65102-

i ENCLOSURE 1 l

-(

CYCLE 4 RELOAD MEETING FEBRUARY 14, 1989 ATTENDANCE LIST 1 l

NAME ORGANIZATION i J

Tom Alexion NRC/PDlII-3 l Don Katze NRC/SRXB ,

Barb Samardzich Westinghouse /CNFD Glen Justis Union Electric / Nuclear Fuel Jack Reck Westinghouse / Nuclear Safety Daniel Fieno NRC/SRXB Jim Head Union Electric Dave Shafer Union Electric / Licensing I

1 1

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ENCLOSURE 2 e

M CALLAWAY CYCLE 4 FEBRUARY 14, 1989 NRC MEETING AGENDA P

I. INTRODUCTION

11. PLANT OPERATION UPDATE Ill. CYCLE 4 LICENSING OVERVIEW

, . IV. FUEL DESIGN V. PEAKING FACTOR INCREASES VI. DESIGN MARGINS Vll. PMTC A. BORON CONCENTRATION

, B. NA0H CONCENTRATION

, VIII. TECHNICAL SPECIFICATION CHANGES IX.

SUMMARY

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PLANT OPERATION UPDATE o CORE CONFIGURATION CYCLE 3 CYCLE 4 V5 V5 28 (3.6) 64 (3.6)

)

32 (3.8) 24 (4.0) '

I 36 (4.2) 96 (ONE CYCLE) ,

OFA 0FA j 84 3 9 (TWO CYCLES) !

LOPAR 13 o DESIGN TO 439 EFPD 440 EFPD

(+ 20 DAYS COASTDOWN) o CURRENT CYCLE PERFORMANCE (2/14/89)

- GENERATED 404.5 EFPD

- 88.5% CAPACITY FACTOR o PROJECTED CYCLE END DATES 1

CAPACITY FACTOR CYCLE END DATE 80% 3/29/89 :

85% 3/26/89 l 90% 3/24/89 i 95% 3/22/89 100% 3/20/89 i

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. I REFUEL 3 ACTIVITIES i

0 PROJECTED START 3/30/89 56 DAYS TOTAL LENGTH 0 REMOVE 5 STUCK RV STUDS f

0 INSPECT 2 0F 3 LOW PRESSURE TURalNES 0 INSPECT 2 0F 4 SG 0 REPLACE 2 0F 4 RCP SEALS 0 UT ALL FUEL ASSEMBLIES 1

0 INSPECT OR REPLACE ALL RCCAS O ATWS MITIGATION SYSTEM MODIFICATION O SG LEVEL TRIP CIRCUlTRY MODIFICATION

. i t

CYCLE 4 LICENSING OVERVIEW 0 LICENSE CHANGES PEAKING FACTOR INCREASES PMTC INCREASED BORON AND NA0H CONCENTRATION 0 50.59 CHANGES AXIAL BLANKETS DEBRIS FILTER BOTTOM N0ZZEL ENHANCED PERFORMANCE RCCAS b

DNBR MARGIN REALLOCATION j 0 WCAP-11837 TRANSITION CORE DNBR PENALTY REDUCTION

. i CALLAWAY CYCLE 4 FUEL DESIGN FEATURES O AXIAL BLAm mis TOP e BOTrm 6" OF ENtICHED FUEL IS REPLACED WITH NATURAL URANIIN ELDtINATEs REGIONS OF UroEntrrILIZATION AT TOP APD BOTTm OF ASSDELY BLAmsTs REDUCE POWER AT EPOS OF ROD RESULTING IN j DECREASED L.EAKAGE O

DEBRIS FILTER BOTTm Nnni =

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REDUCED DIAPETER HOLES IN BOTTOM Nn771 F - SArg AP AS I PREVIOUS DESIGN REDUCED PROBABILITY OF DEBRIS IMXJCED FUEL DAMA O

ENHANCED RCCA DESIGNS THIN CHOE ELECTRO-PLATING ON RODLET CLADDING T WEAR RESISTANCE SLIGHT REDUCHON IN RODLET DIAfETER AT BOTTOM OF 1

HELP MINIMIZE CLADDING INTERACHON.

i ACTIVE FUEL LENGTH DESCRIPTION

" BLANKET 6 IN. NON-COATED, ENRICHED FUEL l

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/ 120 IN. IFBA COATED, ENRICHED FUEL

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1 PEAKING FACTOR INCREASE 1 e ONE TECHNICAL SPECIFICATION LIMIT BASED ON VANTAGE-5 FUEL 3/4 2.3 NUCLEAR ENTHALPY RISE HOT CHAtitlEL FACTOR l F$H I 1.59 (1+0.3(1-P)3 3/4 2.2 HEAT FLUX HOT CHANNEL FACTOR - Fg (z)

[2.501 Fg (z) 5 p (K(z)] FOR P > 0.5 e OPTIMIZED FUEL ASSEMBLIES - CYCLE 4

- STILL LIMITED TO CURRENT TECH. SPEC VALUES (1.49F)H, 2.32 Fg )

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- VERIFICATION OF SAFETY ANALYSIS LIMITS COMPLETED FOR CYCLE 4 DESIGN: ALL OFA PEAKING FACTORS

" 1.49 F)g AND 2.32 F g e CHANGE TO TECH SPEC BASES 1

1

REVISION 2'~'

ig 1R_..DISTRlDU110N LIM 115 -

3/4.2.2 ittAI rifix H01 CHANNEL FACTOR - Fg

LIMIT]NC CONDITION FOR OPERATION 3.2.2 F 4(Z) shall be limited by the following relationships:

2.50 Fq (Z) 1 ( ) [K(Z)] for P > 0.5, and

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Fq (Z) 1 (L44') [K(Z)] for P 10.5..

S.00 Wwre:

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, , THERMAL POWER , and RATED THERMAL POWER K(Z) = the function obtained from Figure 3.2-2 for a given core height location.

t APPLICABILITY: MODE 1.

AC110N:

With Fq (Z) exceeding its limit:

a.

Reduce THERMAL POWER at least IX for each 1%g F (Z) exceeds the limit T within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% F q (Z) exceeds the limit; and

b. Identify and correct the cause of the out of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION a. , above; THERMAL POWER may then be increased provided Fg (Z) is demonstrated through incore mapping to be within its limit.

CALLAWAY - UNIT 1 3/4 2-4 "

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CALLAWAY - UNIT 1 3/4 2-5 -

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E- 1 POWER DISTRIBUTION LIMITS .

3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F g LIMITING CONDITION FOR OPERATION 3.2.3 F shall be limited by the following relationship: ,

/. 89 I F

i 1A1T [1 + 0.3 (1-P)]

l where P = THERMAL POWER RATED THERMAL POWER Fh=MeasuredvaluesofFhobtainedbyusingthemovableincore detectors to obtain a power distribution map. The measured i valuesofFhshallbeusedsinceanuncertaintyof4%for I inceremeasurementofFhhasbeenincludedintheabovelimit.

APPLICABILITY: MODE 1 ACTION:

N With F g exceeding its limit:

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either: I

)

1. RestoretheFhtowithintheabovelimits,or

2. Reduce THERMAL POWER TO LESS THAN 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux-High Trip .

Setpoint to < 55%

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of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . l b.

Demonstrate through in-core flux mapping that Fh is within

, its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and

c. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a or b, above; subsequent POWER OPERATION may pro-l caed provided that Fh is demonstrated through inecore flux ,

mapping to be within its limit at a nominal 50% cf RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95% or greater RATED THERMAL POWER.

1 CALLAWAY - UNIT 1 3/4 2-8 Amencment No. 15

l Insert to Tech Spec Bases 3/4 2.2 and 3/4 2.3 margin Discussion:

INSERT 2 Specifications 3.2.2 and 3.2.3 contain the E g and F-delta-H limits applicable to VANTAGE 5 fuel. l The OFA fuel is analyzed to lower limits since it will have experienced i burnup, thereby reducing the attainable OFA-specific hot )

channel factors such that the expected peak power levels and peak radial power of the OFA fuel will be much less than that necessary to approach the OFA F and F-delta-H analysis limits. Q l

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CALLAWAY CYCLE 4 DESIGN MARGINS !

DNB MARGIN VANTAGE-5 FUEL 17.4%

OPTIMIZED FUEL 6.3%

(TECH. SPEC. BASES 3/4 2.2 AND 3/4 2.3)

PENALTIES:

j ROD B0w TRANSITION CORE PENALTY (V-5 ONLY)

FLOW ANOMALY REMAINING MARGIN:

<1/2% FOR VANTAGE-5 FUEL I

USE OF TRANSITION CORE PENALTY BASED ON WCAP 11837 I

METHODOLOGY (<2% VS. CURRENT 12.5%) WOULD PROVIDE SIGNIFICANT MARGIN FOR CYCLE 4 OPERATION / DESIGN FLEXIBILITY

1 PEAK CLAD TEMPERATURE 0

CALCULATED (INCLUDING 50 F TRANSITION CORE 0

PENALTY): 2064 F VS 22000 F LIMIT i

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i POSITIVE MODERATOR TEMPERATURE COEFFICIENT (PMTC)

CURRENT TECH SPEC LIMIT i

0 PCM/*F MTC OR LESS AT ALL TIMES WHILE REACTOR IS CRITICAL PROPOSED AMENDMENT

+5 PCM/*F MTC FROM 0 TO 70% RATED THERMAL POWER, RAMP DOWN LINEARLY TO O PCM/*F MTC AT 100% POWER PURPOSE FUEL CYCLE COST ADVANTAGE FUEL CYCLE DESIGN FLEXIBILITY LICENSING SUBMITTAL PACKAGE FSAR CHAPTER 15 SAFETY EVALUATION (V5 LICENSING SUBMITTAL PRESENTED REVISED ANALYSES (FALL 1987))

AFFECTED TRANSIENTS LOSS OF LOAD / TURBINE TRIP LOSS OF NONEMERGENCY AC POWER TO STATION AUXILIARIES

LOSS OF MAIN FEEDWATER*

FEEDWATER SYSTEM PIPE BREAK

PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW COMPLETE LOSS OF FORCED REACTOR COOLANT FLOW REACTOR COOLANT PUMP SHAFT BREAK (LOCKED ROTOR)

RCCA WITHDRAWAL FROM SUBCRITICAL RCCA WITHDRAWAL AT POWER RCCA MISOPERATION (DROPPED ROD) 30 ROM DILUTION RCCA EJECTION RCS DEPRESSURIZATION

TRANSIENTS _AFFECIED, EY THE SG LOW-LOW LEVEL REACTOR ?@8@ 789@

CONCLUSIONS CURRENT CHAPTER 15 ANALYSES REMAIN APPLICABLE MAGNITUDE / TYPE OF TECH SPEC CHANGES ARE SIMILAR TO PREVIOUSLY APPROVED LICENSING AMENDMENTS FOR OTHER WESTINGHOUSE NSSSS 1

PROPOSED AMENDMENT SUPPORTS INTENDED CYCLEI 4 FUEL CYCLE DESIGN AND OPERATION l

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RWST/ ACCUMULATOR BORON' CONCENTRATION INCREASE CURRENT TECH SPEC LIMIT BORON CONCENTRATION BETWEEN 2000 AND 2100 PPM (RWST)

BORON CONCENTRATION BETWEEN 1900 AND 2100 PPM (ACCUMULATORS)

PROPOSED AMENDMENT BORON CONCENTRATION BETWEEN 2350 AND 2500 PPM'(RWST)

BORON CONCENTRATION BETWEEN 2300 AND 2500 PPM (ACCUMULATORS)

PURPOSE FUEL CYCLE COST ADVANTAGE (LONGER CORE CYCLE)

IMPLEMENTATION OF A PMTC LICENSING SUBMITTAL PACKAGE FSAR CHAPTER 15 SAFETY EVALUATION (V5 LICENSING SUBMITTAL PRESENTED REVISED ANALYSES (FALL 87))

FSAR CHAPTER 6 SAFETY EVALUATION AFFECTED TRANSIENTS INADVERTENT OPENING 0F A STEAM GENERATOR RELIEF OR SAFETY VALVE STEAM SYSTEM PIPING FAILURE I FEEDWATER SYSTEM PIPE BREAK l

RCCA EJECTION INADVERTENT ECCS DURING POWER OPERATION STEAM GENERATOR TUBE RUPTURE SECONDARY SYSTEM PIPE RUPTURES - MASS / ENERGY RELEASES SMALL LOCA LARGE LOCA

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LOCA - RELATED DESIGN CONSIDERATIONS SHORT- AND LONG-TERM MASS / ENERGY RELEASES POST- LOCA LONG-TERM CORE COOLING HOT LEG SWITCHOVER TO PREVENT BORON PRECIPITATION RCCA EJECTION MASS RELEASES LOCA HYDRAULIC VESSEL AND LOOP FORCES CONCLUSIONS CURRENT CHAPTER 15 ANALYSES REMAIN APPLICABLE MAGNITUDE / TYPE OF TECH SPEC CHANGES ARE SIMILAR TO PREVIOUSLY APPROVED LICENSING AMENDMENTS FOR OTHER WESTINGHOUSE NSSSS PROPOSED AMENDMENT SUPPORTS INTENDED CYCLE 4 FUEL CYCLE DESIGN AND OPERATION l;

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O REASON FOR EVALUATION OF CONTAINMENT SPRAY INCREASED B0PON CONCENTRATION TO ACCOMODATE PMTC CHANGES. 2 0 CHANGES IN BORON CONCENTRATION RWST ACCUMULATORS PREVIOUS 2000 - 2100 PPM 1900 - 2100 PPM NEW (PMTC) 2350 - 2500' PPM 2300 - 2500 PPM i

0 RESULTING CHANGES REQUIRED FOR CONTAINMENT SPRAY a SAT NA0H CONCENTRATION NA0H VOLUME PREVIOUS 28 - 31 WT.% 4340 TO 4540 GALLONS NEW (PMTC) 31 - 34 WT,% 4340 TO 4540 GALLONS O TECHNICAL SPECIFICATION CHANGES TS 3,6,2.2(A) NEEDS TO BE REVISED TO REFLECT THE i INCREASED NA0H CONCENTRATION REQUIRED, NO SAT VOLUME CHANGES ARE REQUIRED.

1

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0 BASIS FOR EVALUATION OF CONTAINMENT SPRAY

]

i DETERMINE IF THE DESIGN BASIS AND SAFETY CRITERION OF FSAR SECTIONS 3.11(B).1.2, 6.2.2, 6.2.5, AND 6.5.2 ARE 1

MET, THE CS INJECTION PHASE MIXTURE HAS A PH IN THE RANGE OF 9.5 1 PH f 11,0, FOR REMOVAL OF 10 DINE FROM THE CONTAINMENT ATMOSPHERE, AT THE END OF THE CS INJECTION PHASE, THE CONTAINMENT SUMP SOLUTION PH 1 8,5, FOR LONG TERM RETENTION OF THE 10 DINES.

THE CS SOLUTION HAS A PH WITHIN THE EQ LIMITS OF 4 i PH 1 11, THE RATE AND TOTAL QUANTITY OF COMBUSTIBLE GAS I

GENERATION IN CONTAINMENT REMAINS UNCHANGED, SINCE THE UPPER LIMIT FOR THE CS PH IS NOT INCREASED, NA0H PRECIPITATION IN THE CS SPRAY ADDITIVE SYSTEM IS AV01DED BY LIMITING THE SOLUTION CONCENTRATION SO AS NOT TO EXCEED SOLUBILITY LIMITS AT AUXILIARY '

BUILDING TEMPERATURES. THE INCREASE IN NA0H CONCENTRATION WILL NOT INCREASE THE CORROSION RATE OF THE CSS,

ie

,b I .

O THE CRITERION ON THE PREVIOUS SLIDE CAN BE MET BY INCREASING THE NA0H CONCENTRATION IN THE SAT TO A RANGE OF 31% - 34% WT., WITH THE EXCEPTION OF THE INJECTION PHASE PH RANGE.

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0 UNDER WORST CASE CONDITIONS, THE MINIMUM PH OF THE CS INJECTION FLUID COULD BE 9.3.

4 0 AS DISCUSSED IN FSAR SECTION 6.5.2, A DESIGN MINIMUM PH = 9.5 IS INTENDED TO ENSURE A MINIMUM ELEMENTAL 10 DINE REMOVAL COEFFICIENT OF 10 PER HOUR - WHICH IS USED IN DETERMINING IF OFFSITE DOSE MEET 10CFR100 LIMITS.

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0 DECREASING THE DESIGN MINIMUM PH FROM 9.5 TO 9.3 DOES NOT APPRECIABLY AFFECT THE REMOVAL OF IODINE, AND THE MINIMUM REMOVAL COEFFICIENT OF 10 PER HOUR IS MAINTAINED.

O THEREFORE, THE DESIGN CRITERIA IS NOT ADVERSELY !

AFFECTED.

i 4

SUBMITTED TECH SPEC CHANGES

1. PMTC 3/4.1 REACTIVITY CONTROL SYSTEMS 3.1.1.3 MODERATOR TEMPERATURE COEFFICIENT l (MTC As A FUNCTION OF POWER) 3.1.2.5 BORATED WATER SOURCE - SHUTDOWN (RWST BORON CONCENTRATION) 3.1.2.6 B0 RATED WATER SOURCE - OPERATING (RWST BORON CONCENTRATION) 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3.5.1 ACCUMULATORS (ACCUMULATOR BORON CONCENTRATION) 1 3.5.5 REFUELING WATER STORAGE TANK (RWST BORON CONCENTRATION) 3/4.6 CONTAINMENT SYSTEMS 3.6.2.2 SPRAY ADDITIVE SYSTEM (CHEMICAL ADDITION TANK NA0H SOLUTION %

WEIGHT)

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SUBMITTED TECH SPEC CHANGES (CONTINUED) ir

2. PEAKING FACTOR INCREASES l 3/4.2 POWER DISTRIBUTION LIMITS 3.2.1 AXIAL FLUX DIFFERENCE 3.2.2 HEAT FLUX HOT CHANNEL FACTOR (FQ As A FUNCTION OF' CORE HEIGHT) 3.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (F-DELTA-H) 1

- 1

. ..,,4 l

1 SlMMR_Y l

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0 Cycts 4 Scum;LE 10/25/88 -

SueMrrrAL To IRC (UL)RC-1850) 3/30/89 -

REFUEL 3 START DATE 4/22/89 - Reabnim cycle 4 heneur APPROVAL 5/26/89 -

CYCLE 4 RESTART DATE o CYCLE 4 ISSUES FMTC - USED IN V5 sueMrTTAL, SMLAR TO PREVIOUSLY l APPROVED PLANTS. f 1

PEAKING FACTORS - USED IN V5 sueurrrAL, SMLAR To i

PREVIOUSLY APPROVED PLANTS.

l l

ML20235R221

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