ML20154C010
| ML20154C010 | |
| Person / Time | |
|---|---|
| Site: | Catawba, McGuire, 05000000 |
| Issue date: | 02/26/1986 |
| From: | Berlinger C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8603040533 | |
| Download: ML20154C010 (34) | |
Text
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MEMORANDUM FOR:
DISTRIBUTION FROM:
Carl H. Berlinger, Chief Reactor Systems Branch, PWR-A
SUBJECT:
SUMMARY
OF JANUARY 22, 1986 MEETING REGARDING B&W'S PLAN FOR LICENSING FUEL IN DUKE PLANTS On January 22, 1986, NRR staff met with representatives of Babcock & Wilcox Company and Duke Power Company to discuss the B&W plan for licensing fuel loading in Duke Power Company's plants having Westinghouse NSSS. The attendees are listed in Enclosure 1.
In the meeting, a Duke representative gave a brief perspective of Duke Power Company's plan to have B&W fuel loaded in the Westinghouse NSSS plants. B&W representatives gave an overview of their fuel program and licensing activity, details of B&W fuel design and experience, details of the B&W fuel analytical program, and licensing schedule. Enclosure 2 contains an outline of the B&W presentation with proprietary infomation deleted.
The staff gave no comitments on the review schedule in the absence of an official submittal, but identified the NRC contact as Carl Berlingar, Chief, Reactor Systems Branch, Division of PWR Licensing-A.
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} Carl H. Berlinger, Chief Reactor Systems Branch, PWR-A
Enclosure:
As stated
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FEB28 g MEMORANDUM FOR:
DISTRIBUTION FROM:
Carl H. Berlinger, Chief Reactor Systems Branch, PWR-A
SUBJECT:
SUMMARY
OF JANUARY 22, 1986 MEETING REGARDING B&W'S PLAN FOR LICENSING FUEL IN DUKE PLANTS On January 22, 1986, NRR staff met with representatives of Babcock & Wilcox Company and Duke Power Company to discuss the B&W plan for licensing fuel loading in Duke Power Company's plants having Westinghouse NSSS. The attendees are listed in Enclosure 1.
In the meeting, a Duke representative gave a brief perspective of Duke Power Company's plan to have B&W fuel loaded in the Westinghouse NSSS plants. B&W representatives gave an overview of their fuel program and licensing activity, details of B&W fuel design and experience, details of the B&W fuel analytical program, and licensing schedule. Enclosure 2 contains an outline of the B&W presentation with proprietary information deleted.
The "taff gave no comitments on the review schedule in the absence of an official submittal, but identified the NRC contact as Carl Berlinger, Chief, Reactor Systems Branch, Division of PWR Licensing-A.
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H. Berlinger, Chief Re ctor Systems Branch, PWR-A
Enclosure:
As stated
FEB 28 188 ENCLOSURE 1 NAME ORGANIZATION Frank McPhatter B&W Jim Taylor B&W Walton Jensen NRC/RSB Jerry Wilson NRC/RSB Dave Hood NRC/PWR-A/ PAD-4 Gene Hsit NRC/PWR-A/RSB K. Jabbour NRC/PWR-A/ PAD-4 T. Novak NRC/NRR/PWR-A Neal Rutherford Duke Power Company Carl Berlinger NRC/NRR/PWR-A(RSB)
Ernie Coppola B&W/ Fuel Project Manager Ken Canady Duke Power Joe Cudlin B&W Jim Taylor B&W Mike Hannah B&W Ray King B&W George Meyer B&W Barclay Andrews FSV Gary Hanson B&W R. O. Sharpe Duke Power Company Walter Brooks NRC/PWR-A/RSB Marvin Dunenfeld NRC/PWR-A/RSB Shih-Liang Wu NRC/PWR-A/RSB B. Sheron NRC/DSR0 Ernie Rossi NRC/PWR-A
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B&W/ DUKE /NRC MANAGEMENT MEETING JANUARY 22, 1986
~
AGENDA I.
INTRODUCTION AND MEETING OBJECTIVE J. H. TAYLOR /B&W
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II. DUKE POWER COMPANY PERSPECTIVE K. S. CANADY/DPC
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III. OVERVIEW 0F FUEL PROGRAN AND LICENSING M. A. HANNAH/B&W ACTIVITIES IV. DETAILS OF B&W FUEL DESIGN AND EXPERIENCE R. A. KING /B&W' V.
DETAILS OF B&W FUEL ANALYTICAL PROGRAM J. J. CUDLIN/B&W AND LICENSING SCHEDULE VI. CONCLUDING DISCUSSION ALL 5
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Agenda 1
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Introduction and Meeting-Objective J.H. Taylor / &Y B
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Duke Power Company Perspective' K.S. Canady/DPC i
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Overview of Fuel Pr.ogram and Licensing Activities M.A. Hannah B&Y
/
IV.
Details of B&Y Fuel Design and Experience R.A. King /B&Y i
Y.
Details of B&Y Fuel Analytical l
Program and IJcensing Schedule J.J. Cudlin/B&Y i
l VI.
Concluding Discussion All l
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Meeting Objectives
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e Inform NRC Management of B&W's Plan for Licensing w,
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Fuel in Duke Power's McGuire and Catawba Units f
e Obtain NRC Concurrence With This Plan So That the i
Licensing Review Process Can Commence e
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Overview of Fuel Program T
1 and Licensing Activites esackground il e Fuel Design & Experience
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!j e B&W Ana:ytical Programs
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. e Licensing Strategy
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e Schedule e Summary
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Background
e B&W Met With NRC Staff February 15, 1985 to Discuss
't Plans for Fuel in W NSSS
<8 e Staff Concurred With Plan, But Said B&W Needed Customer Before Resources Could Be Committed To Review Process e B&W Received a Contract From Duke Power for Catawba
- 1
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and McGuire Reload Fuel Beginning in 1990 I
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i B&W Fuel Experience s B&W Has Been Designing and Manufacturing Commerical Nuclear Fuel for Over 25 Years e 428715 x 15 Fuel Assemblies Have Been Irradiated in B&W Designed NSSS (0conee Class) e 41615 x 15 Fuel Assemblies Have Been Irradiated in Y Designed NSSS (Conn Yankee) e B&W Fuel Integrity Matches the Industry Average (99.996% in 1985) i I
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e Ndelear Fuel Industries of Japan Entered fato A License Agreement Yith B&Y in 1976 For Design -
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e NFI Supplies 40% of Japanese PWR Market Including Y 14 x 14,15 x 15, and 17 x 17 Designs e Of the 1014 Reload Fuel Assemblies Irradiated to Date, No Leakers Have Been Detected i
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I 1 1 B&W Fuel Assembly Design Er?erience j Operating l e Incorporates B&W Standard Design Features Experience Grid Restraint US Japan / Top & Bottom Spring Fuel Support US/ Japan Rods Seated on Lower End Fitting US Japan / R, Keyable Grid Fuel Rod Support US/ Japan / Dished Chamfered Fuel Pellets US Japan / / [- Zircaloy Intermediate Grids US 1 e Other Design Features I Reconstitutable US/ Japan ~ Mixing Vanes US/ Japan Leaf Springs US/ apan J e ,r. ,.,.,---.----------n-..,,-. -_-.--..------n
C Design Qualification 1. Full Size Prototype Testing e Flow Testing e Fuel Assembly Structural e Component Structural e Reactor Thermal-Hydraulic Demonstration Program e Four Fuel Assemblies
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' e McGuire Unit 2, Cycle 4 - Mid 1987 e Target Burnup: 45,000 mwd /mtU (4 Cycles? e Post Irradiation Eram (PIE) After Each Cycle
h B&Y Topicals Applicable to Westinghouse NSSSs i Discipline Topical gxte Use Core Thermal-Hydraulics 101411 TACO 2 Fuel Rod Performance iI 101291. LYN 11 Core DNB Analysis
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r 101301 LYNI2 Core DNB Analysis ,t 10156 LYNIT Core DN3 Analysis .3 b' Nuclear Analysis 10115A NUIJF Cross Section Calculation 4 ' k};l 10118A PDQ Depletion Studies h! 10118A PDQ Reactivity & Power Distribution 10119A PDQ Nuclear Uncertainty .1, 10125A FIDE Maneuvering l 10152A N00DI2 Multidimensional Studies i ,j '. Mechanical Design 10064A CROY Creep Collapse Analysis ICC3 k Safety Analysis 10148 REFIDD3 Reflood Hydraulics 10155 FDAM2 Core Mixture Imel 1 - - - + - . _ - _. - - _ _,. _ ~ _, - _ - _ _ _,., _,,,., _ _. -. _ _ _ _,., _,,.
PROPRIETARY Topical Reaorts t '1 ~ 9, 9 i i il t g i i -Q i e } -I i i l f l -I 1 s r l l l 1 1 i t i
l Licensing Strategy i e e Submit Codes and Methods Topicals on a Schedule '~ That Yill Permit Their Approval Prior to the Start ~ of Application Analyses (McGuire 2 Cycle 6 in 1989) -I e Have Online Review for Safety and ECCS Areas to l Ll Facilitate Schedule and Make Most Efficient Use l l l of Resources _. - -. _ _. _ _ _, _ _ _ _. _ - _ _. _ _ _ _. _ _ ~
.-...mnn, 4., M' A r~ w e*t*e-*r >.- r.' Schedule of Fuel Program and L i c o n s l'n g Aot1v1tlea 1986 1987 1988 1989 1990 l .I 4. Prototype Testing l Demo Assembly Irr3diation Codes E Methods Topicals 1 6 i McGuire 2 Cycle 6 Analyses t 1 ist Batch Irradiation i NRC Review I l e G e
t i ' ij' Summary ,[ e The B&Y Fuel Assembly Design Is A Combination of + s; Design Features Proven Through Operation in the US an'd Japan s f a B&Y's Analytical Capability Is Yell Established and i Modifications to Make Them Applicalbe to Y NSSS I ~ t Are in Progress '{ e B&Y and Duke Power Have Established a Licensing Plan for fuel s Q Inserting B&YeIn Catawba and McGuire That Should Allow Effective Utilization of Resourcesat B&Y, Duke, and the NRC h ,.-y, .,_m_,m__ ,_-m.,_.,.
l i I a E 3 3]1 Design Description k. ((- Development Overview .J _,fi Test Program Description y ~ Demonstration Program i I: 9 % e e r---g w. yv. ea w,--,,y-m--,..yc.m.- --,, - - -. -.,,----y.-.,---ew-- y----.
Reload Fuel Assembly l L 1 af e g w. l -\\ 2 REMOVASLE UPPER/ f ll l L J; ENO FITTING ^ sw+vxw, w r w ie.:.uw aaaa4 T[~~j'((i ~ AUMsuiRTIO uPMR ,= t i E N O 4 R10 (IN C 0 4 4 U Ch m 5 p -[ i [W YW Y"" 'J.~.s TOP VIEW r 'vT {. y'I11m^^Jg7'*'
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,1 ..l ,f ]~,x - - w M 'l 1--a > e 2 --a s k-,ii E 2 ra n -.1 1 r I. as... ..s I'*Ii'I: F 'IIIIII, 1,311a1 ._m. N N .A 11IiII a# y qg -gFUEL 200 ASSEM0LY' - t. CROSS SECTION i .i.J....., IIYIIIIIIIIIII 'T 111IIJJl1IIIII A ye,-- rrr I us.. 6... TERutDIATE SPACE R GRtOS (ZlRCALOY 4) IIII!IIuIIIIIIIy 1111 a I I _I I A EI'II y--- -7r i \\ ~ m _ a,, tervrrrJPerh*"* ' " I fI ll l e'ssaisnam diTTfN b = = BOTTOM VIEW l l
Fuel Assembly Design e Compatible With Resident Fuel Assemblies, Reactor Intenals, Control Comonents and Storage / andling Equipment. H Operating ' e Incprporates B&W Standard Design Features Experience [ Grid Restraint US Japan / Top & Bottom Spring Fuel Support US Japan / h;_ Rods Seated on lower End Fitting US Japan / Keyable Grid Fuel Rod Support / US Japan / 5 Dished Chamfered Fuel Pellets / US Japan / [ Zircaloy Intermediate. Grids US i e Other Design Features Reconstitutable US Japan / s Mixing Vanes US Japan / i l l ~-
I PROPRIETARY Fuel Assembly Design Comparison Reload B&Y Design Assembly B&W Design Licensee Parameter Design Mk-B NFI y Rod Array 's No. Rods t No. Guide Thimbles No. Instrument Tubes ) No. Spacer Grids ] Fuel length (In.) .l Rod Pitch (In.) Materials j Fuel Clad , Guide Thimble 2 Instrument Tube Intermediate Grids End Grids Fuel Rods l Outside Diameter (In.) Clad Thickness (In.) Dia. Gap (In.) Fuel Density %
PROPRIETARY Comparison of Fuel Assembly Deslas T.B. McGuire: Units 1 & 2 oristnal canent av Desian D=lsn Amschi7 Faraustar IcPAR gA Delan End Array 1 No. Fas! Ends No. Guide Thtables i No. hstranent Tab.s No. Specar Grhis 1 l Pnel he Pitch On.) i i 2==mbly hampe (k.) I Fast staek tansth i i Amt cad Oulds thhnble s hatrumet Tabe klarmadiate Grhls 2 End Grids 'Fas! Ends: Outside Dia. cad h Dia. Gap i !=gth Dame (2 Tb.orsth.1) r . cnid, ru,.u nyp.e s.eum on/ ton.) Imer s u. on/t(h.)
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FuEi 555mtsi[U$2I$I57f53fing/ Manufacturing Major Milestones 1985 1986 1987 1988 1989 1990 i...........i........ l.. ...i,,1.... ......i.......... MAJOR MILESTONE: j r M NO TEST PROGRAM ] m -4 i m DEMONSTRATION I PROGRAM FIRST FUEL FABRICATION 9 4
Test Program Objective: Perform Mechanical Hydraulic Tests to Support Licensing / and Qualify Design for Full Batch Implementation (1990) Test Hardware: Full Size Prototype Fuel Assembly and Control i.} Components Flow Testing i. e nP and Lift L e Life and Year e Control Rod Thimble Plug / II Fuel Assembly Structural e Lateral, Arial, Torsional Stiffness f a Frequency and Damping 9 j Component Structural ~ j e Spacer Grid Seismic e Joint Strengths e Misc. Hardware i i Reactor Thermal-Hydraulic e Critical Heat Flux (CHF) e Laser Doppler Velocimeter (LDV)
Demonstration Program e-l e Four Fuel Assemblies i j } e MdUnire Unit 2, Cycle 4 - Mid 1987 ~ e Target Burnup: 45,000 Mid mtU (4 Cycles) ~ /
- j e Post Irradiation Eram (PIE) After Each Cycle
.f - Precharacterized - Detailed Visucl (Video & Photo) l - Fuel Assembly Growth j - Fuel Rod Growth Shoulder Gap Closure / I - Spacer Grid Elevations - Holddown Spring Set 9
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o j'. Summary s p V V y, e Fuel Assembly Design Based on Proven Technology j! and Design Experience y I e Comprehensive Test Program and Demonstration -n Irradiation Provide.' Verification of Design for Full i l Batch Implementation I 4 -,y_.,.._____-
YeGuire Unit 2/ Cycle S Reload Licensing P:.an I e Major Activities l e Sc:1edu:.e 4 I e Questions 4 s. o E N i + Y JJ Cudlin NRC B&W Fuel Engineering 1 22 86 / / e v w
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=. _._ _ McGuire Unit 2 Cycle 6 / ? i Reload licensing Plan i .~ - Major Activities s [. b i 2 ~ ~ e Methods and Code Develo.a. ment .w jf e Preparation and Submittal of To;pical Re: ports I1 i e NRC Review
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PROPRIETARY McGuire Unit 2 Cycle 6 / Reload Ideensing Plan ~.. Topical Reports 3 _? =l I ~ v P' i I h W Me E a 's 5 I I l..
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I -{;g ;. { k 'l r li, I i-a i 1985 1986 1987 1988 1989 1990 I I l ll l l lll ll l] Licensing CHF M Operating Limits Methods TR Mechanical, SCO, and Transient Analysis TR's i ECCS Code TR's ECCS Evaluation Model TR Design Limits Analysis Reload Report E Review i EkHine and Phot-94mittel) i BGW Activity m E Activity g 9 l t i e iteure unit P/ Cycle 6 Licensing Plan
McGuire Unit 2 Cycle 6 / Reload Licensing Plan !g.. W, ues". ions 'j. L ifi e Wi:.:. the.GC Su;p;por
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w ~, e Wi:.:. t:1e XRC :?rovid.e On-Line : Review in i j t:1e Core "/d anE. ECCS Safe;y Areas? / -) e Will ';:le X:RC ::t.entify Contacts for Iic:(-Off Meetings in All Some Areas? / l .-_ -_.._ _ - _--. _ -..,_.-.__-,}}