ML20151N471

Summary of 880407 Meeting W/Util & Westinghouse Re Reload for Cycle 4.Meeting Attendees & Nonproprietary Presentation Encl

ML20151N471
Person / Time
Site:	Callaway
Issue date:	04/13/1988
From:	Alexion T Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8804250308
Download: ML20151N471 (17)

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. . April 13, 1988 Docket No. 50-483 . DISTRIBUTION:

' DOCRet rJIes ,NRC & Local PDRs LICENSEE: Union Electric Company PDIII-3 r/f XPerkins TAlexion OGC-WF1 FACILITY: Callaway Plant EJordan JPartlow ACRS(10) HRichings YGHsii

SUMMARY

OF MEETING WITH UNION ELECTRIC COMPANY REGARDING THE RELOAD FOR CYCLE 4 On April 7,1988, the NRC staff met with Union Electric Company and Westinghouse regarding the reload for Cycle 4. Meeting attendees are listed in Enclosure 1.

Non-proprietary slides presented by the licensee are in Enclosure 2. Proprietary slides presented are in Enclosure 3.

The Cycle 4 core is expected to have 88 new Vantage 5 (V-5) fuel assemblies, 96 once-burned V-5 fuel assemblies and 9 twice-barned optimized fuel assemblies.

Projected technical specification change proposals include a positive moderator temperature coefficient and increased nuclear enthalpy rise hot channel and heat flux hot channel factors. Other projected proposals include a revised fuel rod design methodology (PAD 3.4, described in WCAP-10851) and a revised V-5 DNB transition core cenalty (the WCAP will be submitted in May 1988).

Other proposed considerations include modification of the steam generator 10-10 level trip function (based on NRC-approved WCAP's-11325 and 11342) and elimina-tion of the negative flux rate trip function (described in WCAP-11394).

The licensee expects to submit the reload application by November 1, 1988 and is requesting NRC approval by April 22, 1989. The NRC staff made no commitment regarding the review of WCAP-10851, the V-5 DNB transiticq core penalty WCAP (which will be submitted in May), or WCAP-11394. The staff did, however, offer to provide feedback to the licensee regarding the rev!ews of the various WCAP's, hl Thomas W. Alexion, Project Manager Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc: With Enclosures 1 and 2 Enclosure 3 to licensee only See next page 8904250300 000413 DR ADOCK 0500 3 Office: LA/PDIII-3 PM/P h 3 SRXB/]h SRXB I

Surname: PKPeutzer Tfle? /tg HRicMngs YHsii/f Date: 4/j;/88 /p/ y/g88 f/p/88 Office: SR PD/P ' gIi-3 Surname: R KPdr os Date: g /f 68 q/p/88

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

Dr. J. O. Cermack Mr. Bart D. Withers CFA Inc. President and Chief 4 Professional Dr., Suite 110 Executive Officer Gaithersburg, "9 20879 Wolf Creek Nuclear Operating Corporation Gerald Charhoff, Esq. P. O. Box 411 Thomas A. Baxter, Esq. Burlington, Kansas 66839 Shaw, Pittman, Potts & Trowbridge 2000 N Street, N. W. Mr. Dan I. Bolef, Presioent Washington, D. C. 20037 Kay Drey, Representative Board of Directors Coalition Mr. T. P. Sharkey for the Environment Supervisor, Compliance St. Louis Region Union Electric Company 6267 Delmar Boulevard Post Off. ice Box 620 . University City, Missouri 63130 Fulton, Missouri 65251 U S. Nuclear Regulatory Commission Resident Inspectors Office RRt1 Steedman, Missouri 65077 Mr. Alan C. Passwater, Manager Licensing 6nd Fuels l

i Union Electric Company l Post Office Box 149 St. Louis, Missouri 63166 Manager - Electric Department Missouri Public Service Commission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 1

Regional Administrator l 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 l

ENCLOSURE 1 CYCLE 4 RELOAD MEETING APRIL 6, 1988 NAME ORGANIZATION Tom Alexion NRC/PDIII-3 Howard Richings NRC/SRXB Y. Gene Hsif NRC/SRXB Al Passwater IJnion Electric Co.

Dave Shafer Union Electric Co.

Carole Leach Westinghouse-Nuclear Safety Al Abels Westinghouse-Nuclear Safety Barb Samardzich Westinghouse-CNFD l

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- . ENCLOSilRE 2 CALLAWAY CYCLE 4 APRIL 6, 1988 NRC MEETING AGENDA I, INTRODUCTION II, PLANT OPERATION UPDATE Ill, CYCLE 4 LICENSING OVERVIEW AND SUBMITTAL SCHEDULE A. LICENSING SUBMITTAL

SUMMARY

1 PMTC 2 FUEL ROD DESIGN

3. VANTAGE 5 TRANSITION CORE PENALTY

4. PEAKING FACTOR INCREASES B. TECHNICAL SPECIFICATION CHANGES IV, CYCLE 4 RELOAD CONSIDERATIONS A. VANTAGE 5 TRANSITION CORE PENALTY B. PEAKING FACTOR INCREASES V. OTHER CONSIDERATIONS A. SG LO-LO LEVEL TRIP SETPOINT AND LOGIC MODIFICATIONS B. NEGATIVE FLUX RATE TRIP REMOVAL VI.

SUMMARY

A. LICENSING SCHEDULE B. NRC COMMENTS t

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PLANT OPERATION UPDATE 0 CYCLE 3 CONFIGURATION VANTAGE 5 28 (3,6) 32 (3,8) 36 (4.2) 0FA 84 LOPAR 13 0 DESIGN TO 440 EFPD 0 CURRENT CYCLE PERFORMANCE (4/1/88)

GENERATED 119 EFPD 90% CAPACITY rACTOR 0 PROJECTED CYCLE END DATE CAPACITY FACTOR CYCLE END DATE 85% 4/15/89 90% 3/24/89 95% 3/17/89

SCHEDULE CONSIDERATIONS 11/1/88 -

CYCLE 4 SUBMITTAL To NRC 3/17/89 -

REFUEL 3 EARLY START DATE 4/22/89 -

CYCLE 4 REQUESTED APPROVAL DATE 5/8/89 -

CYCLE 4 EARLY RESTART DATE i

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9 CYCLE 4 CHANGES CYCLE 4 CONFIGURATION j VANTAGE-5 t 64 (3,6) (NEW) 124 (4.0) (NEW) 96 (ONCE BURNED)  :

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i 9 (TWICE BURNED)

P O POSITIVE MODERATOR TEMPERATURE COEFFICIENT 0 REVISED PEAKING FACTCRS (F0, F-DELTA-H) 0 INCORPORATE AXIAL BLANKETS 0 ALL IFBA CORE I

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POSITIVE MODERATOR TEMPERATURE COEFFICIENT (PMTC)

CURRENT TECH SPEC LIMIT:

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

PROPOSED AMENDMENT:

+$ PCM/*F MTC FROM 0 TO 70% RATED THERMAL POWER, RAMP DOWN LINEARLY TO 0 PCM/*F MTC AT 100% POWER

, PURPOSE:

FUEL CYCLE COST ADVANTAGC FUEL CYCLE DESIGN FLEX 1BILITY LICENSING SUBMITTAL PACKAGE:

FSAR CHAPTER 15 SAFETY EVALUATION (VS LICENSING SUBMITTAL) 1 RWST/ ACCUMULATOR BORON CONCENTRATION INCREASE O POST-LOCA HOT LEG SWITCHOVER TIME o POST-LOCA SUMP AND CONTAINMENT SPRAY PH CONSIDERATIONS

TECH SPEC CHANGES CONCLUSION

CURRENT CHAPTER 15 ANALYSES REMAIN APPLICABLE MAGNITUDE / TYPE OF TECH SPEC CHANGES ARE SIMILAR TO PREVIOUSLY APPROVED LICENSING AMENDMENTS FOR OTHER H NSSSS PROPOSED AMENDMENT SUPPORTS INTENDED CYCLE 4 FUEL CYCLE DESIGN AND OPERATION

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CYCLE 4 FUEL R0D DESIGN 0 SECOND CYCLE OF VANTAGE-5 FUEL ANALYZED AT UPRATED CONDITIONS 0 REQUIRE REVISED FUEL ROD DESIGN METHODOLOGY - PAD 3.4

! WCAP 10851:

"IMPROVED FUEL PERFORMANCE MODELS FOR WESTINGHOUSE FUEL ROD DESIGN AND SAFETY EVALVATION"

! O WCAP 108b1 NRC REVIEW IN PROGRESS l (CRGR COMMITTEE REVIEW) l J

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CYCLE 14, TRANSITION CORE PENALTY DNB o REDUCEVANTAGb-5IRANS('l10NCOREPENALTYBASEDON CYCLE 4 CORE INJENTORY l 0 fidFIRE9CE NESTINGHOUSE REPORT OC i u REMAINS 50Y (SAME As CYCLE 3) l 1

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4 PEAKING FACTOR INCREASES NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (F-DELTA-H) 0FA VANTAGE 5 TSL SAL TSL SAL CURRENT (CYCLE 3) 1.49 1,55 1,49 1.65 PROPOSED (CYCLE 4) 1,49 1,55 1,59 1.65 TECHNICAL SPECIFICATIONS WILL USE A SINGLE VALUE OF 1.59 FOR CYCLE 4.

KEY: SAL = SAFETY ANALYSIS LIMIT TSL = TECH SPEC LIMIT

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HEAT FLUX HOT CHANNEL FACTOR Fo(Z)

CURRENT: FQ AS A FUNCTION OF CORE HEIGHT - 3 SEGMENT ENVELOPE MAX Fo = 2.32 PROPOSED: FQ AS A FUNCTION OF CORE HEIGHT - 2 SEGMENT ENVELOPE MAX Fo = 2.50 TECHNICAL SPECIFICATIONS WILL USE A SINGLE VALUE OF 2.50 FOR CYCLE 4.

EXPECTED / POTENTIAL TECH SPEC CHANGES

1. PMTC 3/4.1 REACTIVITY CONTROL SYSTEMS 3.1.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC AS A FUNCTION OF POWER) 3.1.2.5 BORATED WATER SOURCE - SHUTDOWN (RWST BORON CONCENTRATION) 3.1.2,6 BORATED WATER SOURCE - OPERATING (RWST BORON CONCENTRATION) 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3,5,1 ACCUMULATORS (ACCUMULATOR BORON CONCENTRATION) 3.5.5 REFUELING WATER STORAGE TANK i:

(RWST BORON CONCENTRATION) 3/4,6 CONTAINMENT SYSTEMS 3,6,2,2 SPRAY ADDITIVE SYSTEM (CHEMICAL ADDITION TANK NA0H SOLUTION VOL UME) .

2 (CHEMICAL ADDITION TANK NA0H SOLUTION % WElGHT)

I 3/4,9 REFUELING OPERATIONS

! 3,9,1 BORON CONCENTRATION (MODE 6 RCS MINIMUM BORON CONCENTRATION)

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I EXPECTED / POTENTIAL TECH SPEC CHANGES

2. PEAKING FACTOR INCREASES

-3/4.2 POWER DISTRIBUTION LIMITS 3.2.2 - HEAT FLUX HOT CHANNEL FACTOR (Fo As A FUNCTION OF CORE HEIGHT) 3.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (F-DELTA-H) 4

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i OTHER CONSIDERATIONS l

h 1 STEAM' GENERATOR LO-L0 LEVEL-TRIP FUNCTION o TRIP TIME DELAY AS A FUNCTION OF POWER LEVEL CONCEPT: NRC APPROVED WCAP-11325 0 ENVIRONMENTAL ALLOWANCE MODIFIER ,

CONCEPT: NRC APPROVED WCAP-11342 IMPLEMENTATION: MODIFICATION OF Ex! STING 7300 PROCESS i EQUIPMENT SCHEDULE: 7/1/88 LICENSING SUBMITTAL  !

REFUEL 3 OUTAGE PLANT MODIFICATIONS 4

NRC APPROVAL REQUESTED - 1/1/89 l OPERABLE IN CYCLE 4 i

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NEGATIVE FLUX RATE TRIP FUNCTION O DISABLE TRIP FUNCTION CONCEPT: WCAP-11394 SUBMITTED BY H FOR NRC REvlEW 7/87 SCHEDULE: CONCURRENT WITH 11/88 LICENSING SUBMITTAL REFUEL 3 CUTAGE, PLANT MODIFICATIONS REQUEST NRC APPROVAL 3/1/89 APPLICABLE FOR CYCLE 4 OPERATION e

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SUMMARY

e CYCLE 4 SCHEDULE SUBMITTAL 11/1/88 APPROVAL DATE 4/22/89 e CYCLE 4 ISSUES

- PMTC - USED IN V5 SUBMITTAL, SIMILAR TO PREVIOUSLY APPROVED PLANTS PEAKING FACTORS USED IN V5 LICENSING SUBMITTAL PAD 3.4-RELIES ON GENERIC APPROVAL OF WCAP 10851 DNB TRANSITION CORE PENALTY-RELIES ON APPROVAL OF NEW WESTINGHOUSE TOPICAL REPORT

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