ML20138A098

Summary of 851024 Meeting W/Util & Exxon Nuclear Corp Re Fuel Reload Scheduled to Begin on 860520 & End on 860820. Viewgraphs of Meeting Agenda,Objectives & Proposed Schedule Encl

ML20138A098
Person / Time
Site:	Grand Gulf
Issue date:	12/03/1985
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8512110548
Download: ML20138A098 (16)

Text

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Docket No. 50-416 DEC c 31985 LICENSEE: flississippi Power & Light Company (MP&L)

FACILITY: Grand Gulf Nuclear Station, Unit 1

SUMMARY

OF OCTOBER 24, 1985 MEETING REGARDING EXXON FUEL RELOAD The purpose of the meeting was to hear and discuss MP&L's plans for the first core reload using E u on fuel assemblies. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of slides prepared by the licensee for the meeting.

The Exxon Nuclear Corporation (ENC) fuel for the reload is similar to that used in other BWRs with jet pumps. One-third of the core will be reloaded.

The refueling outage is currently scheduled to begin May 20, 1986 and end Atgust 20, 1986. Except for the loss of coolant accident (LOCA) analysis, the reload licensing amendment will be submitted May 6, 1986. The LOCA erelysis will be submitted February 15, 1986.

In addition to core reload, core stability analyses and extended cperating domain analyses were discussed. License condition 2.C.(13) requires submittal of core stability analyses for operation beyond fuel cycle 1. These core stability analyses will be subnitted by January 1986. Analyses to extend the operating dcmain by increased coolant flow thrcugh the core will be subnitted in May 1986 with the reload analyses. Analyses to show acceptable performance for increased power at reduced ccolant flow rates will be submitted in October 1S86. During the startup test progran, tests were run with increased coolant flow. The schedule for testing with increased pcwer is constrained by the staff's review schedule for the Octcber 1986 submittal.

Technical Specification changes are listed on page 8 of Enclosure 2. Licensee will discuss the specific proposed changes with technical stuff prior to submittal thrcugh the NRC Project Manager.

L. L. Kintner, Project Manager 8512110548 851203 BWR Project Directorate No. 4 DR Division of BWR Licensing p ADOCK 05000416 PDR

Enclosures:

As stated DISTRIBUTION cc: See next page  ; Docket F_ile NRC PDR Local PDR PD#4 Reading EJordan PD# /PM PD#4/PD g{ BGrimes LKintner:lb WButler ACRS (16) 12/2./85 12/S/85 NRC Participants l

• kW reg j << ,o,, UNITED STATES l [ s3< p, NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 i

' g x.-.....f ljht; e lbos Occket No. 50-416 i

LICENSEE: Mississippi Power & Light Company (MP&L)

FACILITY: Grand Gulf Nuclear Station, Unit 1 .

SUMMARY

OF GCTOBER 24, 1985 MEETING REGARDING EXX0f4 FUEL RELOAD The purpose of the meeting was to hear and discuss itP&L's plans for the

first core reload using Exxon fuel assemblies. Enclosure 1 is a list of i attendees. Enclosure 2 is a copy of slides prepared by the licensee for l the meeting.

1 i The Exxon fiuclear Corporation (ENC) fuel for the reload is similar to that l used in other BWRs with jet pumps. One-third of the core will be reloaded.

The refueling outage is currently scheduled to begin hay 20, 1986 and end August 20, 1986. Except for the loss of coolant accident (LOCA) analysis, the reload licensing amendment will be submittec May 6, 1986. The LOCA

analysis will be submitted February 15, 1986.  !

In addition to core reload, core stability analyses and extended operating domain analyses were discussed. License condition 2.C.(13) requires submittal of core stability anelyses for operation beyond fuel cycle 1. These core stability analyses will be subnitted by January 1986. Analyses to extend the operating derrain by increased coolant flow through the core will be

, submitted in May 1966 with the reload analyses. Analyses to shcw acceptable perforr.ar.cc fcr ircreased power at reduced coolant flow rates will be subnitted i

in October 1966. During the startup test progran, tests were run with increased

coolant flow. The schedule for testing with increased power is constrained by the staff's review schedule for the October 1986 submittal.

) Technical Specification changes are listed on page 8 of Enclosure 2. Licensee

- will discuss the specific proposed changes with technical staff prior to submittal through the NRC Project Manager.

~

L. L. Kintner, Project Manager BWR Project Directorate No. 4

Division of BWR Licensing I Enc 1csures

! As stated cc: See next page

t i ,

I l' Mr. Jackson B. Richard j Mississippi Power & Lignt Company Grano Gulf fiuclear Staiton I'

l cc:

i Robert B.-McGehee, Esquire The Honorable Williara J. Guste, Jr.

l Wise, Carter, Child, Steen and Caraway Attorney General

P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Lcuisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds Esquire Bishop. Liberman, Cook, Purcell Mr. Oliver D. Kingsley, Jr.

.1 and Reynolds Vice President, Nuclear Operations 1200 17th Street, N.W. Mississippi Pcwer & Light Company Washington, D. C. 20036 P.O. Box 23054 Jackson,itississippi 39205 Mr. Ralph T. Lally Manager of Quality Assurance Office of the Governor Middle South Services, Inc. State of Mississippi i P.O. Box C1000 Jackson, Mississippi 39201  ;

I New Orleans, Louisiana 70161 Attorney General j Mr. Larry F. Dale, Cirector Gartin Building Nuclear Licensing and Safety Jackson, Mississippi 39205 f l Mississippi Power & Light Company '

P.O. Box 23054 Mr. Jack Mcflillan, Director Jackscn, Mississippi 39205 Solid Waste .

I Mississippi State Board of Health  !

j Mr. R. W. Jackson, Project Engineer 880 Lakeland Bechtel Power Corporation Jackson, Mississippi 39206

! 15740 Shady Grove Road ,

! Gaithersburg, Maryland 20700 Alton B. Ccbb, M.D.  !

State Health Officer 1l Mr. F. css C. Butcher State Board of health i Senior Resident Inspector P.O. Box 1700 U.S. Iluclear Regulatory Commission Jackson, Mississippi 39205 j Route 2, Box 399

Port Gibson, !!ississippi 39150 President l Claiborne County Board of Supervisors j Regional Administrator, Region II Port Gibson, Mississippi 39150 i U.S. Nuclear Regulatory Comission.

l 101 Marietta Street, N.W., Suite 2900 i Atlanta, Georgia 30323 Mr. J. E. Cross, General Manager i Grand Gulf fiuclear Station i Mississippi Power & Light Company P.O. Box 756

[ Port Gibson, Mississippi 39150 i

i f

l l

Enclosure 1 Attendees likC - hP&L heeting October 24, 1985 Exxon Reload Name Affiliation L. Phillips NRC/DS!/CPB L. Kintner NRC/DL/LB-4 W. Hodges NRC/DSI/RSC D. Fieno NRC/DSI/CPB H. Richings NRC/DSI/CFB Yosi Balas MP&L hl James B. Lee MP&L/ Nuclear Fuels Sections J. G. Cesare MP&L/Mgr Nucl Licer. sing D. A. Lcchbaurr MP&L/ Reactor Engineering St.ction M. Aboul-Fetoub MSS / Plant System Analysis Gary N. Ward ENC / Reload Licensing J. C. Chandler ENC BWR Safety Analysis

.a .

Enclosure ?

GGNS-1 CYCLE 2 RELOAD OVERVIEW OCTOBER 24, 1985

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J13 MISC 85102201 - 1

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! AGENDA I RELOAD C0 ORDINATION MEETING i GGNS-1 CYCLE I (XN-1) RELOAD i

OCTOBER 214, 1985

BETHESDA, MARYLAND

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INTRODUCTION - PURPOSE AND OBJECTIVES MPal J. G. CESARE/

OF THE MEETING Y. BALAS  ;

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I EXXON NUCLEAR METHODOLOGY TO BE APPLIED MP&L/ ENC Y. BALAS/

AND ANALYSES TO BE PERFORMED (0UTLINED/ J. C. CHANDLER

, LIST)

GENERIC ANALYSES APPLICABLE TO GGNS-1 (LIST) MPaL/ ENC Y. BALAS/  !

J. C. CHANDLER I

i CORE STABILITY (STATUS AND OBJECTIVES) MP&L Y. BALAS i (LICENSE CONDITION 2.C.13(A))

I l TECHNICAL SPECIFICATIONS (LIST OF SECTIONS MPal Y. BALAS/

i EXPECTED TO BE EFFECTED) D. A. LOCHBAUM !

I i EXTENDED OPERATING DOMAIN MP8L J. G. CESARE i

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I SCHEDULE MPsL/ ENC Y.-BALAS/ l J. C. CHANDLER s i I l OPEN DISCUSSION ADJOURN 4

, J13 MISC 85102201 - 2

OBJECTIVES o INTRODUCE / IDENTIFY KEY PERSONNEL To NRC STAFF s 0 IDENTIFY EXPECTED GGNS-1 CYCLE 2 LICENSE MODIFICATIONS o DISCUSS SPECIAL CONSIDERATIONS CORE STABILITY EXTENDED OPERATING DOMAIN o REVIEW LICENSING SUBMITTAL CONTENT 0 ESTABLISH LICENSING SCHEDULE J13 MISC 85102201 - 3 9

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GGNS-1 CYCLE 2 o BWR/6 REACTOR MARK lli CONTAINMENT o COMMERCIAL OPERATION BEGINNING 7/1/85 0 INITIAL CORE: 800 GE P8x8R FUEL ASSEMBLIES o RELOAD CORE: 264 ENC 8x8 FUEL ASSEMBLIES BALANCE GE P8x8R o ENC RELOAD FUEL SIMILAR AS USED IN OTHER JET PUMP - BWR'S J'

J13 MISC 85102201 - 4

0 EXXON NUCLEAR METHODOLOGY & SAFETY ANALYSIS

- SAME METHODOLOGY AS SUSQUEHANNA, DRESDEN, AND WNP-2.

TOPICAL REPORTS J13 MISC 85102201 - 5 5-1

. ..- - - = . - - - . - - .

EXXON GENERIC RELOAD DOCUMENTS METHODOLOGY REPORT STATUS NUCLEAR DESIGN ANALYSIS XN-NF-80-19 (A), VOL. 1 APPROVED THERMAL HYDRAULIC DESIGN ANALYSIS XN-NF-80-19, VOL. 3 UNDER REVIEW MECHANICAL DESIGN ANALYSIS XN-NF-81-21 (A), REV. 1 APPROVED PLANT TRANSIENT ANALYSIS XN-NF-79-71 fte. g 2_ , JufpA t r. M UNDER REVIEW STATISTICAL ANALYSIS XN-NF-81-22 (A) APPROVED CRITICAL POWER METHODOLOGY XN-NF-524 (A) APPROVED CRITICAL POWER CORRELATION XN-NF-512 (A) APPROVED LOCA/ECCS METHODOLOGY (EXEM/BWR) XN-NF-80-19 (A), VOL. 2 APPROVED FUEL ROD HEATUP ANALYSIS (H'JXY) XN-CC-33 (A) APPROVED FUEL THERMAL-MECHANICAL ANALYSIS XN-NF-81-58 (A), REv. 2 APPROVED CLAD SWELLING AND RUPTURE MODEL XN-NF-82-07 (A) APPROVED GECERIC RELOAD APPLICATION XN-NF-80-19 (P), VOL. 4, REV. I UNDER REVIEW REV. O HAS BEEN APPROVED FOR BWR 3-5 POWER DEPENDENT MCPR XN-NF-825 UNDER REVIEW G7 -

nrwrecociniinc _ oi

CORE STABILITY ASSURANCE o GGNS-1 OPERATING LICENSE CONDITION 2.C.13(A) o UTILIZE DETECT / SUPPRESS o EARLIER SUBMITTAL J13 MISC 85102201 - 6 7

TECHNICAL SPECIFICATION CHANGES o SECTIONS OF TECH SPEC EXPECTED TO CHANGE 1.0 DEFINITIONS 2.0 SAFETY LIMITS 3/4.1.2 REACTIVITY ANOMALIES 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3/4.2.2 APRM SETPOINTS 3/4/2.3 MINIMUM CRITICAL POWER RATIO 3/4/2.4 LINEAR HEAT GENERATION RATE 3/4/3.7.7 TIP SYSTEf1 l

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EXTENDED OPERATING DOMAIN o IMPLEMENTATION PLAN UNDER REVIEW o DEFINE EXTENDED POWER / FLOW OPERATING DOMAIN s

o ENC TO PERFORM SAFETY EVALUATION FOR OPERATION IN EXTENDED DOMAIN o PROPOSED SCHEDULE FOR SUBMITTING SAFETY ANALYSIS TO NRC INCREASED CORE FLOW (ICF) MAY, 1986 EXTENDED LOAD LINE (ELL) OCTOBER, 1986 o COMPLETE GGNS-1 STARTUP TESTING IN ICF REGION 4

J13 MISC 85102201 - 8 [

l i-l l A. BATVRAL CIRCULATION 3 ADW MCIRC. PUMP SPED TALTE MINIMUM POSITION 101 OPENINC)

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.C. SDW MCIRC. PUMP SPEED TALVE MAXIMLH P051710N

! D. RATD REC 1RC. PUMP SPED TALTE WINIMUM 7051710N (01 OP DINC) l E. ANALYTICAL IDWER LIMIT OF AUTOMATIC 1 DAD FOLLOWING REC 10N l'

.F. ANALYTICAL WPPER LIMIT OF AUTOMATIC LOAD FULIAWING REC 10N. BATO =

POWER F1AW i

S. SDWEST ALIAWABLE PIAW AT RATD POWER (1001 P. 732F)

. .E . 31 CME 57 ALIAWA31.E FIDW AT RATO POWER (1001 P. ROSI F) l l i RAGFK: EX7DDED 14AD LINE REC 10N

! FM1JF: INCREASD CORE FIAW REC 10M l e

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j 731 ROD LINE I

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CAVITATION '

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COM FLOW (1)

FIGURE ntSstsstPri l MX1 MUM EXTENDED OPERATING ODMIN POWER

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! LICENSE AMENDMENT PACKAGE 1

i I O COVER LETTER /NO SIGNIFICANT HAZARDS DETERMINATION i

l 0 PROPOSED TECH SPEC CHA'NGES l

RELOAD i

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CORE STABILITY i

i 0 ENC RELOAD ANALYSIS REPORTS i

i

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l J13 MISC 85102201 - 9

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PROPOSED SCHEDULE O SUBMITTAL FOR LICENSING MAY 6, 1986 AMENDMENT o SUBMITTAL MEETING MAY 20, 1986 o END OF CYCLE 1 MAY 20, 1986 o NRC APPROVAL AUGUST 18, 1986 o CYCLE 2 STARTUP AUGUST 20, 1986 J13 MISC 85102201 - 10

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