ML20244C644

Summary of 890517 Meeting W/Seri in Rockville,Md Re Licensee Plans for Fuel Cycle 5,which Include Use of New Type of Fuel Assembly Developed by Advanced Nuclear Fuels Corp

ML20244C644
Person / Time
Site:	Grand Gulf
Issue date:	06/09/1989
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
GL-88-16, NUDOCS 8906150065
Download: ML20244C644 (18)

Text

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AfL TJO ff UNITED STATES y j ) y.q g

NUCLEAR REGULATORY COMMISSION 1-'.4g WASHINGTON, D. C. 20555 Ao June 9.-1989 Docket No. 50-416 i

FACILITY: Grand Gulf Nuclear Station, Unit 1 (GGNS-1)

LICENSEE: System Energy Resources, Inc., (SERI)

SUMMARY

OF MAY 17, 1989 MEETING WITH SERI REGARDING FUEL CYCLE 5 l

The NRC staff met with SERI in the NRC Rockville Office to hear and discuss the licensee's plans for GGNS-1 Fuel Cycle 5, which include use of a new type of fuel assembly being developed by Advanced Nuclear Fuels Corporation (ANF).

1 The fuel assembly consists of a 9 x 9 array of fuel rods, including 5_ water i

rods (9 x 9 - 5). Water enters the water rods at the bottom of the fuel I

assembly and discharges into the upper section of the fuel assembly. Four of j

these 9 x 9 - 5 assemblies are naw in the GGNS-1 core as lead test

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assemblies. The Cycle 5 reload license amendment will include several ANF topical reports to support new safety limits in the Technical Specifications (TS). Enclosure 1 is a list of attendees. Enclosure 2 is.a handout prepared by the licensee.

The licensee described the submittals and review schedule needed to support the use of the 9 x 9 - 5 fuel assemblies in Cycle 5 (Enclosure 2). Fuel will be received on site in July 1990. The refueling outage is scheduled for.

September - October 1990. Since there will be an increase in fuel enrichment j

and burnup, an environmental assessment on transportation will be needed..

1 Licensee expe:ts thermal hydraulic stability of.9 x 9 - 5 assemblies to be i

equivalent to present fuel assemblies (8 x 8 - 2).

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Page 8)pical reports will be used to support the Cycle 5 reload (Enclosure 2, Four to Three are currently scheduled for review in the present fiscal year; however, the CASM0/Microburn-B Neutronics Code may not be revie'wed by December 1989, as indicated in the schedule (Enclosure 2, Page 14). The staff I

advised the licensee that if review was not completed in time to license reload, it may be necessary to use already approved technology, with more conservative safety limits.

l In response to the licensee's request for additional guidance regarding implementation of GL 88-16 " Removal of Cycle-Specific Parameter Limits from Technical Specifications" the NRC Project Manager advised that TS changes recently made on Brunswick Unit 2 would be a good example to follow.

i 8906150065 890609 PDR ADOCK 05000416 t/l i

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• The licensee proposed'a' target date of October 7,1990 for the Cycle 5 reload amendment, based. on a reload. submittal 'on July 1,1990. Startup from the refueling outage is scheduled for October 21, 1990.

Original Signed By:

~Lester L. Kintner, Senior ~ Project Manager-Project Directorate 11-1 Division of-Reactor Projects I/II~

Enclosures:

As stated cc w/ enclosures:

See next page DISTRIBUTION DOC M

• Files NRC & Local PDRs PDII-I Reading J. Sniezek E. Adensam L. Kintner 0GC E. Jordan B. Grimes NRC Participants ACRS(10)

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R. Borchardt-i i

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[GGNS-1liTG

SUMMARY

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l PM: ' 11-1 D: 01 -1 LKintner:bd EA e sam 06/ /89 06/0 /89

Mr. W. T. Cottle System Energy Resources, Inc.

Grand Gulf Nuclear Station (GGNS) cc:

Mr. T. H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering GGNS General Manager and Support System Energy Resources, Inc.

System Energy Resources, Inc.

P. O. Box 756 P. O. Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGehee, Esquire Office of the Governor Wise, Carter, Child, Steen and State of Mississippi Caraway Jackson, Mississippi 39201 P. O. Box 651 Jackson, Mississippi 39205 Mr. Frank Spencer Assistant Attorney General Nicholas S. Reynolds, Esquire Attorney General's Office Bishop, Liberman, Cook, Purcell State of Mississippi and Reynolds P. O. Box 22947 1400 L Street, N.W.

Jackson, Mississippi 39225 Washington, D.C.

20005-3502 Mr. Ralph T. Lally Alton B. Cobb, M.D.

Manager of Quality Assurance State Health Officer Middle South Utilities System State Board of Health Services, Inc.

P. O. Box 1700 639 Loyola Avenue, 3rd Floor Jackson, Mississippi 39205 New Orleans, Louisiana 70113 President Mr. John G. Cesare Claiborne County Board of Supervisors Director, Nuclear Licensing Port Gibson, Mississippi 39150 System Energy Resources, Inc.

P. O. Box 23054 Regional Administrator, Region II Jackson, Mississippi 39205 U. S. Nuclear Regulatory Commission 101 Marietta Street Mr. C. B. Hogg, Project Manager Suite 2900 Bechtel Power Corporation Atlanta, Georgia 30323 P. 0. Box 2160 Houston, Texas 77252-2166 Mr. H. O. Christensen Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 399 Port Gibson, Mississippi 39150 l

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ENCLOSURE 1 i

Attendees i

May 17,1989 Meeting NRC-SERI NAMES AFFILIATION L. L. Kintner NRC Project Manager M. W. Hodges

. NRC Chief, Reactor Systems Branch Y. Balas SERI R. S. Reynolds ANF*

R. A. Copeland ANF*

1. Nir MSU/SSI**

T. C. Krysinski ANF*

F. H. Smith MSU/SSI**'

Steve Bennett SERI NL i

• Advanced Nuclear Fuels Corporation

• • Middle South Utilities, System Services, Inc.

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ENCLOSURE 2 l

l NRC/SERI MEETING GRAND GULF CYCLE 5 LICENSING ACTIVITIES MAY 17, 1989 l

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4 AGENDA 1,

INTRODUCTION' A)-

MEETING l0BJECTIVEs & AGENDA B)

SCHEDULE 11.

CYCLE 5 DESIGN

SUMMARY

A)

CYCLE 5 OVERVIEW B) 9x9-5 RELOAD FUEL C)

TECH SPECS IMPACT D)

SAFETY ANALYSES Ill.

CYCLE 5 SAFETY ANALYSES A)

NEW METHODOLOGIES 0

CASM0/MICR0 BURN-B 0

COTRANSA 2 0

ANFB 0

REVISED METHODOLOGY FOR SAFETY LIMITS B)

ANALYSES AND SCOPE O

NEUTRONICS o

TRANSIENTS 0

LOCA-0 MECHANICAL DESIGN O

LICENSING IMPACT C)

CRITICALITY D)

-STATUS OF ANALYSES AND TOPICALS l

VI.

SCHEDULE A)

ANF' GENERIC AND PLANT SPECIFIC DOCUMENTS B)

RELOAD SUBMITTAL C)

GENERAL SCHEDULE V.. WRAP-UP/

SUMMARY

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c PURPOSE 10F MEETING ~

INFORM THE NRC ON1THE CURRENT. PLANT STATUS' AND CYCLE 5 LSCHEDULE ~

x INFORM THE NRC OF THE PLANNED CHANGES FOR CYCLE S 1

REVIEW WITH THE NRC THE SUBMITTALS TO SUPPORT THE CYCLE.5l CHANGES.

AND THE REVIEW SCHEDULES tlECESSARY.T0' SUPPORT THE CYCLE 5 STARTUP' DATE

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SCHfDULE - KEY DATES CYCLE 5 FUEL RECEIPT AT SITE 3

JULY 1990 E0C 4 SEPTEMBER 1990 BOC 5 OCTOBER 1990 m

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CYCLE 5 OVERVIEW

, l FUEL TYPE.-

FIRST FULL RELOAD'.9x9-5 ENERGY APPROXIMATELYLEQU'ALL To-CYCLE li '

DESIGN DISCHARGE BURNUP-INCREASE FROM :3 11 TO 36 L GwD/MT.

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i ENRICHMENT; SLIGHT INCREASE

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.i 9x9-5 DESCRIPTION-l l

DESIGN FEATURES' j

TWO FUEL ROD DIAMETERS FIV'E INJECTION WATER RODS PERFORMANCE CHANGE RELATIVE TO CURRENT'8x8 EXPERIENCE l

BETTER CRITICAL POWER PERFORMANCE DUE TO MORE EFFECTIVE DISTRIBUTION.0F.C00LANT IMPROVED LOCA PERFORMANCE ~ DUE TO LOWER LHGR, GREATER HEAT TRANSFER AREA j

MORE MANEUVERING FLEXIBILITY ALLOWED DUE TO' LOWER LHGR.

1 4 LEAD FUEL ASSEMBLIES OF THIS DESIGN ARE' INCLUDED IN. CYCLE 4 j

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9x9 5 C LATTICE l

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CLEANUP l

CYCLE 5 SPECIFIC GL 88-16 SAFETY ANALYSIS

-l LICENSING CONTINUITY NEW METHODOLOGIES

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NEW METHODOLOGIES FOR CYCLE 5 CASM0/MICR0 BURN-B NEUTRONICS

' CODES (XN-NFi80-19(P),

!VOL...'1,'

SUPPLEMENT 3)

COTRANSA2 SYSTEM RESPONSE CODE-(ANF-913(P), AND SUPPLEMENTS).

ANFB CHF CORRELATION (ANF-1125(P)', AND SUPPLEMENT 1)

REVISED SAFETY LIMIT METHODOLOGY (ANF-521(P), REVISION 2)

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i ANALYSES AND SCOPE l

1; WORKSCOPE FOR CYCLE 5 INCLUDES A REANALYSIS OF THE APPROPRIATE I

EVENTS CONSISTENT WITH THE CURRENT ME0D.

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-1 NEUTRONICS ANALYSIS 1

1 COLD SHUTDOWN MARGIN STANDBY LIOUID CONTROL

. LOSS OF FEEDWATER HEATlf1G FLOW EXCURSION EVENT CONTROL R0D DROP ACCIDENT ROD WITHDRAWAL ERROR ~

MISLOADED BUNDLE ANF PERFORMING THE NEUTRONIC/ CYCLE DESIGN ACCORDING -T0 THE 1

ACCEPTED NEUTRONIC METHODOLOGY BUT'USING CASM0/MICR0 BURN-B INSTEAD 1

0F XFYRE/XTGBWR l

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I TRANSIENT ANALYSIS LOAD REJECTION W/0 BYPASS 1

FEEDWATER CONTROLLER FAILURE l

SINGLE LOOP OPERATION' l

OVERPRESSURIZATION TRANSIENT SYSTEM RESPONSE WILL BE ANALYZED USING THE COTRANSA2 CODE (ANF-913-(P) AND SUPPLEMENTS).

j CHF PERFORMANCE WILL BE DETERMINED USING THE EXTENDED ANFB CHF i

' CORRELATION (ANF-1125(P) AND SUPPLZMENT 1)

[i SAFETY LIMITS WILL BE DE ERMINED USING THE REVISED SAFETY LIMIT.

METHODOLOGY (ANF-524(P), hdVISION 2),

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ANALYSES AND SCOPE

.(CONTINUED)

LOCA ANALYSIS PERFORM THE LIMITING BREAK HEATUP'. ANALYSIS' TO ESTABLISH THE MAPLHGR VALUES FOR.-THE-9X9-5.

. ESTABL I SH MAPLHGR VALUES' FOR SINGLE LOOP OPERATION ANALYSES WILL USE THE APPROVED EXEM/BWR METHODOL OGY WITH REVISED SPRAY HEAT TRANSFER COEFFICIENTS FOR THE. 9x9-5 FUEL DESIGN.

(XN-NF-929(P), AND SUPPLEMENTS).

MECHANICAL ANALYSIS THE GENERIC MECHANICAL DESIGN REPORT USES APPROVED. CODES AND PERFORMED IN A SIMILAR MANNER AS PREVIOUSLY ACCEPTED. MECHAt'ICAL DESIGN REPORTS (ANF-88-152(P))

THE LHGR LIMIT FOR THE EXISTING 8X8 DESIGN WILL BE: RAISED'AT THE HIGHER EXPOSURE END TO BE CONSISTENT WITH THE CYCLE REQUIREMENTS.

THE APPROVED CODES AND THE METHODOLOGY REPORTED IN ' PREVIOUSLY-ACCEPTED MECHANICAL DESIGN REPORTS WILL'BE USED.

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O LICENSING IMPACT 9f9 1.

REVISED LHGR CURVE FOR M FUEL 2.

MAPFAC WILL BE REPLACED BY LHGR FACTOR 3.

REMOVAL OF SLO SPECIFIC MAPLHGR LIMITS 4.

OTHER TS LIMITS, SPECIFIC TO 9X9-5, AS NEEDED 5.

N CONJU JCTION WITH GL 88-16 THESE LIMITS MAY. BE TAKEN OUT I

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N CRITICALITY I

THE CRITICALITY-ANALYSIS FOR_THE FUEL ~ STORAGE RACKSM WILL L USE A -

BOUNDING BUNDLE DESIGN IN ORDER TO MINIMIZEL THE' NEED l FOR FUTURE SUBMITTALS.

THE SPENT FUEL RACKS WILL. BE 'MODELED USING SIMILARL METHODOLOGY.TO THAT USED IN SUPPORT.OF THELCYCLE 4: RELOAD; THE ANALYSIS. WILL USE THE - MAXIMUM REACTIVITY ~ POINT' IN THE FUEL ASSEMBLIES' LIFETIME CONSIDERING BURNUP'AND BURNABLE POISON.

THIS ANALYSIS WILL BE P E R F O R ti E D C O N S I S T E N T. W I T H THE REQUIREMENTS OF' ANSI /ANS-57.2 - 1983.

I IHE ANALYSIS WILL CONSIDER THE EFFECTS 0F GAPS IN THE-BORAFLEX l-ABSORBER SHEETS.

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THE ANALYSIS WILL BE PERFORiiED AND SUBMITTED SEPARATELY FROM THE.

RELOAD ANALYSIS' BECAUSE FUEL. RECEIPT IS TYPICALLY SCHEDULED 3 - 4 MONTHS PRIOR TO STARTUP, 1

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9 LICENSINGSTATUS-0FANF-GENERICMETHODOLOGY TOPICAL REPORT STATUS 9x9-5 GENERIC-MECHANICAL DESIGN SUBMITTED IN NOVEMBER 1988, j

REPORT (ANF-88-152(P))

PNL PERFORMING REVIEW FOR j

NRC,-

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k CASM0/MICR0 BURN-B NEUTRONICS CODES SUBMITTED lN MARCH 1989,

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(XN-NF-80-19(P) VOL,.1, SUP 3) 7 1

ANFB ChlTICAL POWER CORRELATION AND SUBMITTED BASE CORRELATION EXTENSION FOR THE 9x9-5 DESIGN IN FEBRUARY 1988.

(ANF-1125(P), AND SUPPLEMENT 1)

SUBMITTED EXTENSION FOR I

9x9-5 DESIGN IN' APRIL 1989.

COTRANSA2 CODE DESCRIPTION AND SUBMITTED TO NRC~IN i

PEACH BOTTOM BENCHMARKS (ANF-913(P),

MAY 1988, ITS PERFORMING VOL, 1 AND SUPPLEMENTS)

TECHNICAL REVIEW FORLNRC, ANF RESPONDING TO NRC QUESTIONS AND REPERFORMING BENCHMARKS WITH MICR0 BURN.

INPUT, REVISED SAFETY LIMIT METHODOLOGY SUBMITTED TO NRC IN (ANF-524(P), REVISION 2)

APRIL-1989, REVISED SPRAY HEAT TRANSFER SUBMITTED IN SEPTEMBER COEFFICIENTS (XN-NF-929(P), AND 1986..INEL PERFORMING SUPPLEMENTS)

TECHNICAL REVIEW, ANF HAS RESPONDED T0 NRC QUESTIONS IN APRIL 1989 AND.MAY 1989, RL5 - 13

SUBMITTAL

SUMMARY

-AND SCHEDULE ITEM SCHEDULED SUBMITTAL DATE g 9x9-5 SPRAY HEAT TRANSFER SEPTEMBER 1986; RESPONSE'T0-COEFFICIENTS-(XN-NF-929(P) AND RAI SUBMITTED APRIL 1989 l

SUPPLEMENTS)

AND MAY 1989 COTRANSA2 SYSTEM RESPONSE CODE MAY 1988

-(ANF-913(P), AND SUPPLEMENTS)

/.NF 9x9-5 MECHANICAL DESIGN NOVEMBER-1988

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REPORT (ANF-88-152(P))

ANF CASM0/MICR0 BURN-B NEUTRONICS MARCH 1989 j

CODE (XN-NF-80-19(P), VOL, 1, SUPPLEMENT 3)

ANF CHF CORRELATION FOR 9x9-5 APRIL 1989 DESIGN (ANF-1125(P) AND SUPPLEMENT 1)

ANF REVISED SAFETY LIMIT APRIL 1989 l

METHODOLOGY-(ANF-524(P),

i REVISION 2) i NRC/SERI CYCLE 5 PLANNING MEETING MAY 1989 COTRANSA2 PEACH BOTTOM BENCHMARKS MAY 1989 USING MICR0 BURN NEUTRONICS GENERIC SERs ISSUED DECEMBER 1989-i NRC/SERI CYCLE-5 RELOAD MEETING JANUARY 1990 CRITICALITY ANALYSIS SUBMITTED MARCH 1990 CRITICALITY SER ISSUED JUNE 1990 CYCLE 5 RELOAD SUBMITTAL JULY 1990 FUEL RECEIPT AT GRAND GULF JULY 1990 OUTAGE BEGINS SEPTEMBER 1990 i

CYCLE 5 LICENSE RECEIVED OCTOBER 1990 CYCLE 5 STARTUP OCTOBER 1990 RL5 - 14