ML20153E432

Summary of 880728 Meeting W/Util on Licensing Actions Re Third Fuel Reload.List of Attendees & Viewgraphs Encl

ML20153E432
Person / Time
Site:	Grand Gulf
Issue date:	09/01/1988
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20153E436	List: ML20153E432 ML20153E446
References
NUDOCS 8809060322
Download: ML20153E432 (25)

Text

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UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION

a WASHINGTON, D. C. 20555

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September 1, 1988 Occket No. 50-416 LICENSEE: Syster Energy Resources, Inc.

FACILITY: Grand Gulf Nuclear Station, Unit 1

SUMMARY

OF JULY 28, 1988 MEETING REGARDING THE THIRD FUEL RELOAD

/

The purpose of the meeting was to discuss licensing actions related to the third fuel reload. Participants are listed in Enclosure 1. Enclosure 2 is a handout prepared by the licensee. The third reload in preparation for fuel cycle 4 will consist of the replacement of the remainder of the General Electric fuel assemblies (248) and 28 Advanced Nuclear Fuel (ANF) assemblies with new ANF fuel assemblies. Four of the reload assemblies will be lead test assemblies (LTAs). The new fuel assemblies, except LTAs, will be 8x8 assemblies, having the same dimensions as previously used ANF and GE fuel. However, the new fuel will have a higher enrichment and will be designed to achieve a higher burnup(39,0' .WD/MT maximum and 35,000 MWD /MT batch average).

The LTAs will be a 9x9 array of fuel rods with two fuel rod diameters and five "injection" water rods (sneets 12-16, Enclosure 2). The injsetion" water rods are designed to acnieve a nigher critical heat flux due to more effective distribution of coolant. The LTAs will be locatect in a core region where they will not reach limiting thermal or hydraulic limits.

The staff advised the licensee that to satisfy the requirement of 10 CFR 51.52, an environmental assessment would be needed if expected burnup will exceed 33,000 MWO/MT average or if fuel enrichment will exceed 4% by weight. The staff advised tnat an environmental assessment for the Shearon Harris Plant has been issued for burnups to 60,000 MWD /MT and enrichments to 5%, and that it may be adopted by SERI for GGNS-1, if it is shewn to be applicable.

Spent fuel criticality will be recalculated to demonstrate that the 0.95 kaff limit is not reached for the higher enriched fuel. The analysis regarding no significant hazards considerations will address the reduced margin to criticality of the higher enriched fuel.

8809060322 0009014 6 g PDR ADOCK 050 ,

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i The methods of enalysis to be used for the third reload and limits in the Technical Specifications are similar to those used for previou: ANF reloads (sheets 4-11, Enclosure 20). The licensee said it would submit the reload application by December 9, 1988 and requested the amendment to be issued March 21, 1988 for an April 4, 1989 startup. The staff indicated this schedule appeared to be reasonable.

Sincerely,

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

Enclosures:

As stated cc w/encis:

See attached list (SY ENERGY RESOURCES, INC)

PM DRPR:NRR D .0RPR:NRR LKintner: dim EGAD nsam 084,7/88 08 88

DISTRIBUTION FOR MEETING

SUMMARY

DATED: September 1, 1988 Facility: GRAND GULF NUCLEAR STATION lDH:ksFFiisT7

~NRCPDR "''

Local PDR l P0ll-1 Reading l E. Adensali P. Anderson L. Kintner OGC E. Jordan (MNBB 3302)

B. Grimes (9A2)

ACRS (10)

B. Troskoski (17D19)

M. Hodges (8E23) cc: Licensee / Applicant Service List l

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Enclosure 1 ATTENCEES JULY 28. 1988 MEETING WITH SERI RE: THIRD CORE RELOAD NAME AFFILIATION Les Kintner NRC/PD21 Wayne Hodges NRC/RXSB Yosi Balas SERI/ Licensing Israel Nir System Services, Inc./MSU W. D. Hamilton System Services, Inc./MSU D. A. Adkisson ANF/ Reload Licensing R. S. Reynolds ANF/BWR Safety Licensing F. H. Smith System Services, Inc./MSU 4

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. Enclosure 2 AGENDA USNRC/SERI/ANF Cycle 4 Licensing Meeting ,

July 28, 1988 I. Introduction / Objectives o Agenda o Schedule II. Core Design o Cycle 4 Overview o Spent Fuel Criticality III. Cycle 4 8X8 High Burnup o Status of Approved Criteria / Design o Plant Specific Design Analysis IV. Cycle 4 Thermal Limits o Summary of Anticipated Changes / Reasons for Changes o Power Dependent Limits o Flow Dependent Limits V. 9X9 - 5 LTA o Program Objectives i o Design Description and Progress l 1

o Licensing Basis o TS Changes VI. Other TS Changes o GE References with ANF Core VII. Wrap Up l o Summary of TS Changes c Schedule I

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, J19 MISC 88072102 - 1

GRAND GULF CYCLE 4-!.ICENSING MEETING 0 MEETING PURPOSE:

INFORM NRC 0F PLAT 1NED CYCLE 4 ACTIVITIES / TECH SPEC CHANGES.

IDENTIFY CYCLE 4 ISSUES IDENTIFY AREAS POTENTIALL'Y REQUIRING CLARIFICATION.

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GGNS-1 CYC'tE

SUMMARY

CYCLE DESIGN ENERGY ENRICHED ZONE- BATCH SIZE 2 1110 GWDs 2,99 w/o 264 3 1420 GWDs. 3.21 w/o 288 4 1698 GWDs 3,61 w/o 276 o CYCLE 4 FRESH FUEL MAPLHGR LIMIT F

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SPENT FUEL CRITICALITY .

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CURRENT-BASIS: ,

! 3,5 w/o ENRICHED, UNIFORMLY DISTRIBUTED ,

- 4 "

GE 8x8 DIMENSIONS ,

. No CREDIT FOR AxlAt LEAKAGE No GAD i

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4 FiEV! SED BASIS: -

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, 3.61 w/o ENRICHED, CONSERVATIVE ENRICHMENT DISTRIBUTION ANF 8x8 DIMEtlSIONS -

1 No CREDIT FOR Ax!AL LEAKAGE No GAD i 2

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i CYCLE 4 8X8 HIGH BURNVP i

0 FRESH 8X8FUELh0BEINSERTEDINCYCLE4WILLBEDESIGNEDTO ALLOW HIGHER BURNUP.

O ANF'S APPROVED METHODOLOGY ENCOMPASSES ANTICIPATED END OF LIFE EXPOSURE (XN-NF-82-06( A)); HOWEVER, GENERIC DESIGil APPROVAL IS LOWER (XN-NF-85-67(A)).

i o APPROACH: GRAND GULF SPECIFIC ANALYSIS WILL BE PROVIDED AS '

l PART OF THE CYCLE 4 SUBMITTAL.

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4 GGNS-1 CYCLE 4 THERMAL LIMITS 0 BACKGROUND ANF LICENSING ANALYSIS (CYCLE 2)

SUPPORTED GE THERMAL llMITS (CYCLE 1)

CYCLE 4 IS THE.FIRST ALL ANF FUEL CORC ,

APPROPRIATE TO INSTALL LIMITS GENERATED BY ANF METHODS AND ANALYSES o APPPOACH ESTABLISH REVISED LIMITS BASED ON ALL ANF FUEL CORE AND ANF METHODOLOGY CONFIRM LIMITS FOR CYCLE 4 USING\THE CYCLE SPECIFIC TRANSIENT ANALYS!s RESULTS CONFIRM LIMITS FOR EACH SUBSEQUENT CYCLE USING CYCLE SPECIFIC TRAMSIENT ANALYSIS RESULT i

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POWER-DEPENDENT MCPR o CURRENT MCPR p LIMIT WAS GENERATED BASED ON: s GE ANALYSIS .-

GENERIC BWR-6 CURVES o ANALYSES To SUPPORT REVISED MCPR p LIMIT INCLUDE:

CRWE (GENERICALLY APPROVED)

PRESSURIZAT!oN TRANSIENTS (CYCLE SPECIFIC) ,

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LOFWH (PLANT SPECIFIC I o REVISED MCPR g LIMIT I -

CHANGES IN OFF-RATED LIMIT ABoVE 40% POWER ,

No CHANGE IN RATED LIMIT VALUE

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THERNAL Po#E ES%iP140%

2.2 FLOW > 50% -

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2.O MHERNA. POWER 25% $ PS40%

CCRE F.0W5 SO% ,,

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l. 6 THERW4. PCwER 4b% < P S 70%

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• HERNAL KMER P >7CFr.

} At L CORE FLOWS g  % i APPROXIMATE REVISED MCPet(p) m -

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1. 0 0 20 40 60 to 10 0 120 CORE THERMAL POWER (% RATED)P l FIG"RE 3.2.3-2 MCPR P

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.s ,' 6 FLOW-DEPENDENT TEERMAL LIMITS 0 CURRENT Flow-DEPENDENT LIMITS MCPR WAS GENERATED BASED OH GE BWR-6 GENERIC ANALYSIS F

MAPFAC WAS GENERATED BASED ON ANF BWR-6 ANALYSIS F

BOTH LIMITS f,RE BASED ON OPERATOR-CONTROLLED MAXIMUM CORE FLOW SETTINGS OF 102.5% AND 107% OF RATED CORE Flow 0 GENERAL APPROACH TO REVISE LIMITS GENERATE LIMITS BASED ON ALL AflF FUEL AND METHODOLOGY EllMINATE THE OPERATOR-CONTROLLED CORE FLOW SETTING BY ASSUMING MAXIMUM ACHIEVABLE CORE FLOW FOR THE LIMITING EVENT GENERATE LinlTS BASED ON:

1. fwo-LGOP FLOW RUNOUT EVENT FOR NON LOOP MANUAL OPERATION

2. ONE-LOOP FLOW RUNOUT EVENT FOR Le9P MANUAL OPERATION NOTE: THE ONE-LOOP FLOW RUNOUT EVENT IS THE ONLY CREDIBLE FLOW RUNOUT EVENT IN THE LOOP MANUAL OPER/, TING 1 MODE.

BY RESTRICTING OPERATIONS TO THE LOOP MANUAL MODE, FLOW RUNOUT (AND THEREFORE DELTA-CPR) WILL BE LESS SEVERE.

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FLOW-DEPENDENT THERMAL LIMITS (CONT.)

0 ANALYSIS TO SUPPORT REVISED FLOW-DEPENDENT LIMIT ESTABLISH BOUNDING LIMITS BASED ON AVAILABLE ANF RESULTS FOR GGNS CYCLES 2 AND 3 AND ANTICIPATED CYCLE DEPENDENT VARIAT!ONS FOR:

, 1. LOOP MANUAL OPERATIONS

2. NON LOOP MANUAL OPERATIONS PERFORM CYCLE 4 SPECIFIC ANALYSIS TO CONFIRM LIMITS AF.E BOUNDING O REVISED FLOW-DEPENDENT LIMITS ,

REVISED MCPR VS, CURRENT LIMITS F

REVISED MAPFAC F

vs. CURRENT LIMITS .

1 CYCLE 3 SPECIFIC ANALYSIS CONFIRMED LIMITS j i j

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CYCLE 3 CONFIRMATION or AEVISED FLOW DEPENDENT MCPR LIMIT 1.80 1.70- ,

- NON IACP MANUAL 1.80- WP MAL A NIM ANF CYCLE 3 1.50- , O m ANF CYCLE 3 "1

<3 40- 4 o

1.30- ,

a 1.20- , ,,

1.10-1.00 i , , , , , , i i 20 30 40 50 la 70 80 to 100 110 120 COREFLOW(1)

CYCLE 3 CONFIRMATION OF REVISED FLOW DEPENDENT MAPTAC LIMIT 1.10 1.00- - -

0.90- .

'i k0*00~ A HM ANF CYCLE 3

=

0 m ANF CYCLE 3 0.70- '

LOOP MANUAL O.60- -+- NON IDOP MANUAL 0.50 , , , , , , , , ,

20 30 40 50 60 70 80 to 100 110 120 COR[ FLOW (1)

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FLOT l[ PENS [uT RCPR LlulTS COWPAtlSou

1. 8 0 --

1.70- -.- NON LOOP WANUAL ,

LOOP NANUAL 1.60-N,N s _

N -+- f /$ 10 7 1.50- s'N s' s

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+ f/$ 102.5

• E 1.40- 'N, N y N s's s 1.30- N s N s 1.20- N 1.10-1.00 , , , , i i i i i 20 30 40 50 to 70 80 to 100 110 120 CORE FL05 (I) . .

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/i - v"A FLOW OEPENDENT WAPTAC LlWITS C0WPAtl50N 1.10 1.00- ,: -  :

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2 0.80- /# l C / /,'/ , '

r', -+-- N O N L O O P W A N U A L 0.70-A,y,'[,# LOOP WANUAL

,,'/ + T/$ 102 0.60- r

-+- t / $ 10 2. 5 0.50- , , , , , , , , ,

20 30 40 50 60 10 80 to 100 110 120 CORCFLOW(!) i

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J 9X9-5 DESIGN

SUMMARY

,' O PERFORMAtitE. RELATIVE TO 8X8:

filGHER CRii! CAL POWER DUE TO MORE EFFECTIVE DISTRIBUTION OF COOLANT.  :

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- li4P?0 VEL LOCA PEFF0F.MANCE DUE TO LOWER LHGR, GREATER hFfci IRANSFER AREA, rl0RE INERT SURFACE.

O Dt! SIGN FN .MES:

Two FUEL Ron DIAMkTERS (.443" & .417").

FIVE "INJECTION" WATER RODS.

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-9x9 5 C LATTICE h

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INNER *a . . r')  ! ;Gf

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LARGE 'h DIAMETER O

,O o OUTER ROD W'l j V .

r RETURN FLOW SPACER N >,(f/f INJECTION WATER ROD FUEL BUNDLE -

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0 0 0000 LOWER 0000 O O TIE PLATE LARGE SMALL DIAMETER DIAMETER REGION REGION t

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i. 9x9-5 LEAD PROGRAM PROGRAM OBJECTIVES <

O DEMONSTRATE PERFORMANCE OF 9X9-5 DESIGN. l LICENSING BASES:

0 MECHANICAL, THERMAL-HYDRAULIC, AND NEUTRONIC COMPATIBILITY WITH CORESIDENT 8x8 FUEL.

9x9-5 LTAS WILL.BE NEUTRON!CALLY SIMILAR TO CYCLE 4 8x8 FUEL ASSEMBLIES (LOCAL PEAKING, REACTIVITY).

USE OPERATING LIMITS CONSISTENT WITH 8X8 FUEL (MCPR, l

MAPLHGR, MAPFAC). ,

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PLACED If1 NON-LittlTING LOCAT!Ofl.

j 0 ANALYSIS TOOLS: BASED ON CURRENTLY APPROVED METHODOLOGY (1.E., XN3 CHF CORRELATI0fl, 9X9 LHGR LIMITS, ETC.).

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9X9-5 LTAS NEUTRONIC DESIGN h

O LEADS WILL BE DESIGNED TO BE NEUTRON!CALLY "TRANSPARENT" TO THE CYCLE 4 8X8 ASSEMBLIES.

O DESIGN

SUMMARY

AVERAGE ENRICHMENT OF LTAS: 3.50% (vs. 3.61% FOR 8X8 '

FUEL DESIGN).

9 RODS WITH AXIALLY. DISTRIBUTED GADOLINIA (4.5 8 5.5 w/0 GD203) ,

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9X9-5 LTAS TECH SPEC' CHANGES o TECH SPEC CHANGES WILL BE JUSTIFIED BASED ON GRAND GULF SPECIFIC 8X8 LIMITS OR APPROVED 9x9 LIMITS.

- 9X9-5 MAPLHGR (NEW) - CONSISTENT WITH 8X8 LIMITS. [

MAPFAC (NO CHANGE) - USE CYCLE 4 8x8 FUEL CURVES. .

MCPR (No CHANGE) - USE CYCLE 4 8X8 FUEL LIMITS.  ;

LHGP. FOR 9X9-5 (NEW) - BASED ON "STANDARD" 9X9 LHGR llMIT (XN-NF-85-67). ,

TECH SPEC BASES - VARIOUS: MINOR CHANGES.

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.o...a OTHER TECH SPEC CHANGES O TECHNICAL SPECIFICATIONS WILL BE "CLEANED UP" OVER NEXT TWO CYCLES TO MINIMlZE REFERENCE TO GE FUEL & ANALYSES.

- EVEN THOUGH CYCLE 4 IS ALL ANF FUEL, NEED TO ALLOW FOR CONTINGENT REINSERT 10N OF GE FUEL ASSEMBLY.

NSSS AND OTHER SYSTEMS RELATED ANALYSES WILL REMAIN [

VALID.

O CYCLE 4 PHASE OF TECH SPEC "CLEAN UP" PROGRAM WILL BE *l LIMITED TO BASES, OTHER MINOR AREAS.

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' - EXTENSION OF 28,500 MWD /MTV LIMIT FOR APPLICATION OF GE MAPLHGR'S TO ANF FUEL DURING SLO.

O CYCLE 5 WILL REQUIRE CHANGES TO SUPPORT 9X9-5 RELCAD.

1 "CLEAN UP" PROGRAM WILL BE COMPLETED AT THAT TIME.

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TS CHANGE

SUMMARY

o CYCLE 4 FRESH FUEL MAPLHGR LIMITS o THERMAL LIMITS o LTA PROGRAM o "fLEAN-UP" PROGRAM l

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4 GRAND GULF CYCLE 4 SCHEDULE i o RELOAD SUBMITTAL To NRC: DEC. 9, 1988 I o MEETING WITH NRC: DEC. 20, 1988 o LICENSE ISSUED: MARCH 21, 1989  ;

i o CYCLE 4 STARTUP: APR. 4, 1989 1

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DISTRIBUTION FOR MEETING NOTICE DATED: September 1, 1988 Facility: GRAND GULF NUCLEAR STAION, UNIT 1 Docket or Central File NRC POR Local POR PO!!-1 Reading '

T. Murlcy/J. Snierek (12G18)

F.Miraglia(12G18)

5. Varga (14E4)

G. Lainas E. Adensam t P. Anderson L. Kintner W. Lanning (11E22)

OGC i E. Jordan (MN38-3302) ,

B. Grimes (9A2)

Receptionist ACRS (10)

GPA/PA

0. Morley (12E1)

V. Wilson (12H5)

8. Troskoski (17019) cc: Licensee / Applicant Service List l

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