ML17212B388

Summary of 820113 Meeting W/Util & Exxon Nuclear Corp Re Use of Exxon Fuel During Cycle 6 Reload Operation.Meeting Agenda Encl

ML17212B388
Person / Time
Site:	Saint Lucie
Issue date:	01/21/1982
From:	Nelson C Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8202190016
Download: ML17212B388 (15)

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JAN 21 1982 On January 13, 1982 we met with FP&L and Exxon Nuclear (ENC) to discuss the use of Exxon fuel at St. Lucie Unit 1.

A list of attendees is attached as Enclosure l.

FP&L and ENC s0mlarized the work necessary to support the use of Exxon fuel at St. Lucie Unit 1 during Cycle 6 operation.

An outline of this work is presented in Enclosure 2.

St. Lucie 1 is currently operating in Cycle 5 and the Cycle 6 reload is scheduled for April 1983.

FP&L does not believe technical specifications changes will be necessary for Cycle 6 operati'on and intends to obtain NRC approv'al of the Exxon fuel relate8.topical reports prior to the reload.

The schedule for submittals and requested approvals is on the last page of Enclosure 2..

We indicated that our review of the fuel design related topical reports (RODEX2, Increased Fuel Exposure and 14X14 Fuel Mechanical Design) can be performed on a schedule,'consistent with Cj'cle 6 use of Exxon fuel.

While we could not quantify an exten',sion of the proposed schedules for ECCS and DNBR review we did indicate 'we may have a problem meeting those schedules.

>le also stated that examp'le problems, showing the application of the ECCS and DNBR Correlation methods to St. Lucie Unit 1, must be provided before we can complete our relIiew.

ENC indicated that the proposed NRC completion dates (are set by the use of these methods for D. C. Cook Unit 2.

The plant specific aspects supporting the use of this methodology <will be submitted in the order they are needed

'Cook then St. Lucie) with St< Lucre Unit 1 example probleins expected in June 1982 (ECCS) and July 1982 (DNBR).

We expect FP&L's February submittal to specify the schedule for St. Lucie Unit 1.

We alod FP&L what fuel management changes were being considered for Cycle 6 to reduce the rate of irradiation of reactor vessel materials.

FP&L will review this topic and discuss it with us at a later date.

OrigireI syne'y:

Christian C. Nelson, Project Manager Operating Reactors Branch ¹3 Division of Licensing

Enclosures:

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Florida Power and Light Company

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SUMMARY

OF MEETING WITH FLORIDA POWER AND LIGHT COMPANY (FP&L)

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NRG FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USG PO: 1991~5-960

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MEETING

SUMMARY

DISTRIBUTION Licensee:

Florida Power and Light Company

+Copies also sent to those people on service (cc) list for subject plant(s).

Docket File NRC PDR L PDR NSIC TERA ORBg3 Rdg uO1 shinsk i JHeltemes, AEOD BGrimes RCl ark Project Manager Licensing Assistant ACRS (10)

Mtg Summary Dist.

NRC Participants g Cps'ofe~kui~

Florida Power

& Light Company CC:

Harold F. Reis, Esquire Lowenstein, Newman, Reis

& Alexrad 1025 Connecticut Avenue, N.W.

Washington, D. C.

20036 Norman A. Coll, Esquire McCarthy, Steel, Hector

& Davis 14th Floor, First National Bank Building Miami Florida 33131 Indian River Junior College Library 3209 Virginia Avenue Fort Pierce, Florida 33450 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 U.S. Environmental Protection Agency Region IY Office ATTN:

Regional Radiation Representative 345 Courtland Street, N.E.

Atlanta, Georgia 30308 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.

4853 Cordell Avenue, Suite A-1

Bethesda, Maryland 20014 Mr. Jack Schreve Office of the Public Counsel Room 4, Holland Building Tal,lahassee, Florida 32304 Resident Inspector/St.

Lucie Nuclear Power Station c/o V.S.N.R.C.

P. 0.

Box 400 Jensen Beach, Florida 33457 Bureau of Intergovernmental Relations 660 Apalachee Parkway Tallahassee, Florida 32304 Regional Administrator Nuclear Regulatory Commission, Region II Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Enclosure 1

LIST OF ATTENDEES NRC C. Nelson R. Clark T. Novak L. Phillips-R. Meyer D. Fieno G.

N. Lauben J. Holonich FP&L D. Evans R. Kaminsky S.

Shepherd C. O'Farrill R. Hankel ENC G.

Cooke J.

Morgan M. Killgore S.

Jensen J.

Owsley

Enclosure 2

ST.

LUC IE UNIT 1 CYCLE 6 RELOAD LICENSING MEETING AGENDA INTRODUCTION 1.

REACTOR SCHFDULE 2.

PURPOSE OF MEETING CONTENT OF CYCLE 6 APPLICATION AND SUPPORTING METHODOLOGY 1

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FUEL MECHANICAL DESIGN 2.

NEUTRONICS 3.

THERMAL-HYDRAULICS ECCS 5.

PLANT TRANSIENTS 6

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ROD EJECTION LICENSING PLAN AND SCHEDULE

FUEL NECHAN ICAL DESIGN FUEL NEARLY IDENTICAL TO ENC FUEL USED IN NAINE YANKEE AND SIMILAR TO THAT USED IN FORT

CALHOUN, DESIGN ANALYSIS PIITH RODEX2 WHICH IS UNDER REVIEW ENC TOPICAL REPORT WILL BE SUBMITTED FOR

REVIEW,

REACTOR PHYSICS ANALYSIS NETHODS APPROVED ST.

LUCIE ANALYSIS PREVIOUS CYCLE ANALYSIS FOR BENCHNARKING/ESTABLISHING EXPOSURE HISTORY COEFFICIENTS FOR SAFETY ANALYSES REACTIVITY PREDICTIONS ROD HORTHS CORE BURNUP POWER DISTR I BUT ION PREDICTIONS

THERMAL-HYDRAULIC DESIGN METHODOLOGY THERMAL-HYDRAULIC CONDITIONS DNBR CORRELATION UNCERTAINTIES TO BE CONVOLUTED PRESSURE DROP TESTING ROD BOW EFFECT APPROVED BEING REVISED COMPLETED UNDER REY I Ew APPL ICAT ION TO ST.

LUCIE REVISED DNB CORRELATION UNCERTAINTIES CONVOLUTED

ECCS ANAl YS IS METHODOLOGY RELAPSE-EM (BLONDONN)

REFLEX (REFLOOD)

TOODEE2 (HEATUP)

RODEX2 (STORED ENERGY)

SMALL BREAK MODEL (I I K 3.30 OF NUREG-0737)

APPROVED BEING REVISED BEING REVISED UNDER REV IELV BEING DEVELOPED ST.

LUC IE ANALYSIS LARGE BREAK SIMILAR TO FT.

CALHOUN

PLANT TRANSIENT ANALYSIS PTS/PMR2 CODE (AS APPLIED FOR FT.

CALHOUN)

APPROVED FOR SPECIFIC PREVIOUS APPLICA-TIONSS ST.

LUCIE ANALYSIS LIMITING TRANSIENTS WILL BE IDENTIFIED, ABOUT 7 WILL BE ANALYZED.

AS APPROPRIATELY UNCERTAINTY CONVOLUTION MAY BE PERFORMED FOR LIMITING TRANSIENTS.

ROD EJECTION ACCIDENT METHODOLOGY ANALYSIS CODE (XTRAN)

GENERIC ANALYSIS APPROVED APPROVED FOR SPEC IF IC PREVIOUS APPLICATIONS ST, LUCIE ANALYSIS REFERENCE GENERIC ANALYSIS.

LICENSING SCHEDULE ITEM ACTION DATE ORGANIZATION LETTER ADVISING NRC OF CYCLE 6 PLANS AND REFERENCING ENC TOPICAL REPORTS 2/82 FPRL ENC TOFICAL REPORTS ALREADY SCHEDULED FUEL ROD THERMAL-MECHANICAL RESPONSE EVALUATION MODEL (RODEX2)

APPROVAL TARGETED BY NRC 8/81 6/82 ENC JUSTIFICATION FOR INCREASED FUEL EXPOSURE (RESPONSE TO NRC LETTER TO ENC DTD. 8/17/81) 2/82 ENC MODIFIED ECCS EVALUATION MODEL (ENC INITIATED ACTION TO MODIFY ITS ECCS EVALUATION MODEL IN MID-1981'NC LETTER TO NRC DTD. 9/21/81)

APPROVAL TARGETED BY NRC 1/82 0/82 ENC MODIFIED DNBR CORRELATION FOR PNR'S WHICH INCORPORATES VARIOUS FUEL TYPES AND APPRO-PRIATE METHODOLOGY FOR APPLYING THE MODEL 2-6/82 APPROVAL REQUESTED BY NRC 9/82 ENC ENC TOPICAL REPORT BEING SCHEDULED 10X14 FUEL MECHANICAL DES IGN REPORT FOR C.E.

REACTORS 12/82 ENC COMPLETION OF ST.

LUCIE CYCLE 6 SAFETY ANALYSIS FOR OPERATION WITH ENC FUEL REACTOR STARTUP CYCLE 6 12/82 0/83 ENC FPRL

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