ML20154N450

Summary of 880510 Meeting W/Connecticut Yankee Atomic Power Co & Northeast Utilities to Discuss Plans to Convert from Stainless Steel to Zircaloy Core.List of Attendees & Handout Encl

ML20154N450
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/24/1988
From:	Wang A Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8806020305
Download: ML20154N450 (41)

Text

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Docket No. 50-213 LICENSEE:

Connecticut Yankee Atomic Power Company FACILITY:

Haddam Neck Plant

SUMMARY

OF MAY 10, 1988 MEETING REGARDING ZIRCALOY CLADDING l

CONVERSION On May 10, 1988, the staff met with Connecticut Yankee Atomic Power Company (CYAPCO) to discuss their plans to convert from a stainless steel core to a zircaloy core; CYAPC0 presented a status of the conversion with major milestones. CYAPC0 asked for NRC feedback on their proposed scope and schedule with respect to technical approach and NRC resource capabilities to support CYAPCO's conversion effort.

CYAPC0 stated they are the last plant using stainless steel.

The conversion to zircaloy would have numerous economic benefits, lower tritium releases, bring Haddam Neck in line with all other plants with respect to fuel technologies, and move in the direction of improved safety. The zircaloy conversion will encompass analysis upgrades (small break LOCA, Non-LOCA transients and large break LOCA), fuel mechanical design to minimize design changes and maintain hydraulic compatibility, fuel cycle design and a review to confinn compliance with all regulatory requirements. CYAPC0 stated they propose to implement this conversion over the next 2 1/2 years with the first third of the core to be replaced with zircaloy fuel in cycle 17, January 1991.

The staff agreed that CYAPCO's proposed technical approach seemed reasonable.

The staff also agreed that conversion to zircaloy fuel is a prudent design change. However, the staff stated that any review of a topical by CYAPC0 to validate their large break LOCA methodology and then to review the plant specific analysis would require 3 to 4 years. The staff stated however, if CYAPC0 could have the analysis perfonned by a previously approved methodology, the staff could review the plant specific analysis in a relative short time.

Enclosed is CYAPCO's handout for the meeting and the attendance list.

M E P.*

Alan B. Wang, Project Manager Project Directorate I-4 Division of Reactor Projects I/II

Enclosures:

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AIAY 2 4 1933 Docket No. 50-213 LICENSEE:

Connecticut Yankee Atomic Power Company FACILITY:

Haddam Neck Plant SUB.1ECT:

SUMMARY

OF MAY 10, 1988 MEETING REGARDING ZIRCALOY CLADDING CONVERSION On May 10, 1988, the staff met with Connecticut Yankee Atomic Power Company (CYAPCO) to discuss their plans to convert from a stainless steel core to a zircaloy core; CYAPCO presented a status of the conversion with major milestones. CYAPCO asked for NRC feedback on their proposed scope and schedule with respect to technical approach and NRC resource capabilities to support CYAPCO's conversion effort.

CYAPC0 stated they are the last plant using stainless steel. The conversion to zircaloy would have numerous economic benefits, lower tritium releases, bring Haddam Neck in line with all other plants with respect to fuel technologies, and move in the direction of im The zircaloy conversion will encompass analysis upgrades (proved safety.

small break LOCA, Non-LOCA transients and large break LOCA), fuel mechanical design to minimize design changes and maintain hydraulic compatibility, fuel cycle design and a review to confim compliance with all regulatory requirements. CYAPC0 stated they propose to implement this conversion over the next 21/2 years with the first third of the core to be replaced with zircaloy fuel in cycle 17, January 1991.

The staff agreed that CYAPCO's proposed technical approach seemed reasonable.

The staff also agreed that conversion to zircaloy fuel is a prudent design change. However, the staff stated that any review of a topical by CYAPCO to validate their large break LOCA methodology and then to review the plant specific analysis would require 3 to 4 years. The staff stated however, if CYAPC0 could have the analysis perfomed by a previously approved methodology, the staff could review the plant specific analysis in a relative short time.

Enclosed is CYAPCO's handout for the meeting and the attendance list.

YQMf y

Alan B. Wang, Project Manager Project Directorate I-4 Division of Paactor Projects I/II

Enclosures:

As stated a

s 4

Mr. Edward J. Mroczka Connecticut Yankee Atomic Power Company Haddam Neck Plant CC' Gerald Garfield, Esquire R. M. Kacich, Manager Day, Berry and Howard Generation Facilities Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President D. O. Nordquist Nuclear Operations Manager of Quality Assurance Northeast Utilities Service Company Northeast Nuclear Energy Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region !

Department of Environmental Protection V. S. Nuclear Regulatory Comission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Bradford S. Chase, V:: der Secretary Board of Selectmen Energy Division Town Hall Office of Policy and Management Haddam, Connecticut 06103 80 Washington Street Hartford, Connecticut 06106 J. T. Shedlosky, Resident Inspector Haddam Neck Plant D. B. Miller, Station Superintendent c/o V. S. Nuclear Regulatory Comission Haddam Neck Plant Post Office Box 116 Connecticut Yankee Atomic Power Company East Haddam Post Office RFD 1, Post Office Box 127E East Haddam, Connecticut 06423 East,Hampton, Connecticut 06424 G. H. Bouchard, Unit Superintendent Haddam Neck Plant RFD #1 Post Office Box 127E East Hampton, Connecticut 06424 o

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ATTENDANCE LIST MAY 10, 1988 NAME COMPANY PHONE Jack Stanford Connecticut Yankee 203-267-2556 x452 Marty VanHaltern NU 203-665-5321 Bill Herwig NV.

203-665-3198 Gene Krineik NU 203-665-5865 Don Katze NRR/ DEST /SRXB 301-492-0886 Tom Shediosky NRC Region I, Sr. Res.

203-267-2571 Y. Gene Hsii NRC/SRXB 301-492-0887 Alan Wang "NRC/PM 301-492-1313 Steve Vick NU 203-665-5537 Richard Kacich NU 203-665-3298 Don B. Miller CYAPCO 203-267-2556 John F. Stolz NRC/NRR/PDI-4 301-492-1300 John A. Blaisdell NU 203-665-5869 Bob Jones NRC/NRR/ DEST 301-492-3232 Wayne Hodges NRC/NRR/ DEST 301-492-0895 Rudy Karsch NRC/NRR/DOEA 301-492-1178 1

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t-4 gv7 -

a MEETING WITH THE NRC

~

ON HADDAM NECK PLANT ZlRCALOY CLADDING CONVERSION Connecticut Yankee Atomic Power Company and Northeast Utilities May 10,1988 i 1-J

,s NU PARTICIPANTS I

i l

Don Miller CY StationSuperintendent I

l Richard Kacich Manager, Licensing l

John Blaisdell

Manager, Safety Analysis Bill Herwig Reactor Engineer Marty VanHaltern LOCA Analysis Engineer Gene Krinick Nuclear Fuels Engineer Steve Vick CY Licensing Engineer Jack Stanford CY Reactor Engineer b= May 10,1988 '

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AGENDA introduction R.M. Kacich Program Overview D.B. Miller, Jr.

Technical Program W.M. Herwig J.A. Blaisdell M.L. VanHaltern 1

Summary R.M. Kacich l

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May 10,1988 -

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1 PURPOSE s Present summary of zircaloy conversion plans and milestones a Distinguish analysis upgrades from zircaloy conversion m Obtain NRC feedback on scope and schedule

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BACKGROUND Haddam Neck -- one of two U.S. plants a

with stainless steel clad fuel a

Stainless steel fuel technology less developed and not high priority with fuel vendors a

Plant uniqueness contributes to increased effort required to resolve licensing issues l

- May 10,1988 e 5-

4 s

l LONG-TERM, COMPREHENSIVE PLAN m Experience with Lead Test Assemblies m Submittal to NRC on January 8,1988 i

a Comprehensive in-house reanalysis m No hardware modifications planned l

l l

May 10,1988 -

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l

MAJOR MILESTONES Meetings with NRC Early 1988 LOCA Topical Reports January 1989

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l LOCA reanalysis results July 1989 License amendment request July 1939 Cycle 17 technical report July 1990 Cycle 17 start-up with zircaloy January 1991 1

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i PROGRAM OVERVIEW u importance of conversion a Motives and benefits a Compatability with other CY initiatives I

t May 10,1988 '

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MOTIVES FOR ZlRCALOY CONVERSION a S 7.5 Million / cycle savings in fuel costs e More reliable fuel e Upgrade fuel technologies e Route to longer cycles a Lower tritium releases during routine operation l

m Moves in the direction of improved safety l

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SELECTED CY INITIATIVES a Conversfon to Standard Tech Specs n Reduce personnel exposure l

n Enhanced containment leakage testing l

l m Zircaloy cladding conversion l

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= May 10,1988 -

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TECHNICAL F

OGRAM a Analysis Upgrades i

l m Fuel Mechanical Design I

m Fuel Cycle Design l

1 m Non-LOCA Transient Analysis a LOCA Analyses 1

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May 10,1988 -

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ANALYSIS UPGRADES SB-LOCA analysis submitted 1984 (approval expected soon) 1 RETRAN Topical submitted 1984 l

(approval expected soon)

VIPRE Topical approved 1986 l

Non-LOCA analysis submitted 1986 (approved soon)

Reload design topical submitted 1986 (approved 1987) l Cycle 15 designed and licensed in-house 1987 LB-LOCA methods &

January 1989 SB-LOCA supplement LB-LOCA analysis results July 1989

= May 10,1988 i 12

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l FUEL MECHANICAL DESIGN a Mechanical design performed by abcock and Wilcox l

m Use approved B&W standard design methodology a Decign burnup --50,000 MWD / MTU (peak rod) m Apply Lead Test Assembly Program experience l

m Minimize non-cladding design changes a Maintain hydraulic compatibility May 10,1988 '

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DESIGN COMPARISON r-A a r_ ea 1.649"q l

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TOP SPACER GRID INTERFACE a

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BOTTOM SPACER GRID INTERFACE

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.o40-Zire Assembly Steel Assembly May 10,1988 -

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'=2 COMPARISON OF FUEL ROD DESIGN PARAMETERS Tubular Spacer, Top &

Bonom of Fuel Column Typical Zire Rods n

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0.027' Diamerical Gap 0.0065*

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0.007' Fdi Gas Pressure 40 psJg 265 psig 265 psig l

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FUEL CYCLE DESIGN a Fuel cycle design performed by in-house using Westinghouse methodology n Out-in shuffle with 52 fresh feed a Cycle 17 design expected to be within current Tech Spec requirements for reactivity control systems and power distribution limits a Safety Analysis parameters (RSAC) developed us,ng standard reload i

procedures May 10,1988 -

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4 NON-LOCA TRANSIENT ANALYSIS a Non-LOCA transient analysis performed by Northeast Utilities a RETRAN / VIPRE methodology a Existing design basis to be evaluated as normal reload a Results to be submitted in Cycle 17 Reload Report May 10,1988 '

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Nv7 ZlRCALOY CONVERSION MILESTONES a Engineering evaluations begun 1981 m Lead Test Assemblies Program 1982 m License amendment request July 1989 m Cycle 17 technical report & reload July 1990 amendment request a Cycle 17 startup January 1991 l

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May 10,1988 i 21

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Haddam Neck LOCA Methoc's Upgrade Topics Covered Current LBLOCA Methods Description of ECCS UPI Phenomena New LBLOCA Methods Topical Report Content 1

1 i

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Current LB-LOCA Methodology Westinghouse IAC Model a Blowdown hydraulics - SATAN-V a Reflood hydraulics - CCNDES u Clad heatup - LOCTA-R2 l

l Reasons for upgrade effort I

a 1960's methodology l

u Difficult to assess plant changes e Tube plugging e ECCS flow e Coastdowns l

m Not applicable to zircaloy clad fuel 1

1 May 10,1988 23 1

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Upper Plenum injection Phenomena a Core cooling prior to lower plenum refill a Downward flow at core inlet a Pooling of water in upper plenum a Counter current flow limit a Condensation in upper plenum a Entrainment of water into hot legs and steam generators a Radially non-uniform core hydraulics and heat transfer May 10,1988 25

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%v7 NU Appendix K Model u Blowdown & reflood hydraulics - NULAPS-LB m Containment response - NULAPS-LB a Hot rod heatup & oxidation - NUFRAP-T6 i

e Core wide oxidation - NUCOM m Steady state fuel performance - B&W (TACO-2) t n Core physics - NUSCO analysis l

l May 10,1988 i 26 l

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z NULAP5-LB Features a RELAPS-MOD 2 (Cycle - 36.05) e Two fluid, six equation model e Point kinetics, ANS decay heat ('71 std) e Transient heat conduction solution e Dynamic pump model e Full controllogic capability e Transient fuel rod model(dynamic gap) e Cross flow model o Reflood model with fine mesh rezoning, 2-D conduction a Modifications to RELAP5-MOD 2 e Appendix K models and logic e Data transfer to NUFRAP-T6 e Error corrections e Conversion to IBM

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N'v7 Modifications For Appendix K Compliance a Metal-water reaction rate Baker Just (zirc)

White (SS) m Clad swell & rupture, NUREG-0630 (zirc) flow blockage NUREG-0065 (SS) m CHF correlation MacBeth a Transition film boiling McDonough, Milich &

King a Film boiling Modified Dougall-Rohsenow a No return to nucleate Logic added i

boiling a Transition boiling exclusion Logic added (Tclad > Tsat + 300F) a Critical flow models Henry - Fauske, Moody a End of bypass CCFL model added m Hot assembly conditions NUFRAP-T6 data for heatup analysis transfer a Refill & reflood heat RELAPS-MOD 2 i

l transfer correlation

- May 10,1988 28

NUFRAP-T6 Features a FRAP-T6 e Detailed transient thermal /

machanical model of fuel and clad e Oxidation model(inside and outside clad) a Modifications to FRAP-TH e Stainless steel properties e White oxidation model for stainless e Data transfer to NUCOM e Error corrections e Conversion to IBM l

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NUCOM Features m Transient thermal / mechanical models a Boundary conditions from NUFRAP-T6 m Baker-Just and White oxidation correlations a inside clad oxidation after rupture a Multiple core regions a Stainless & zircaloy properties l

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May 10,1988 '

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SB-LOCA Topical Report Supplement a Descriation of code changes required to moc el zircaloy a Description of input assumptions a Re-analysis of worst break l

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i NULAP5-LB Validation Report

.m Description of code changes a Comparisons to data, correlations, benchmarks e Critical flow model-Marviken data o Cross flow model-analytical comparison (COBRA-IV simulation of FLECHT flow blockage test) e Flow blockage model-NUREG-0630 (zircaloy), NUREG-0065 (stainless) e Kinetics model-analytical comparison o Counter-current flow model-Creare data, comparison to correlations e Heat transfer models - FLECHT data, THTF data, comparison to correlations e Integral test comparisons - LOFT tests, CCTF tests e Containment model-analytical comparison (CONTEMPT predictions)

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a NUFRAPT-6 / NUCOM Validation Report NUFRAPT-6 m Description of code changes n Comparisons to data, correlations, benchmarks e Rod swell & rupture models - Treat data, PBF data, NRU data i

e Stainless steel properties -

verification of properties NUCOM a Description of code a Comparison to data, correlations, benchmarks e Baker-Just l

e White e NUFRAP-T6 l

l l

May 10,1988 33 l

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4 Reanalysis Topical Report a Description of Haddam Neck Model a Sensitivity Studies a Single Failure Analysis a 4-Loop Break Spectrum u 3-Loop Break Spectrum a Seismic LOCA Analysis

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SUMMARY

m Zircaloy conversion part of overall plan to bring Haddam Neck into industry mainstream a Moves in the direction of improved safety a Zircaloy conversion a comparitively small change to Haddam Neck design basis s Request NRC support of schedule implementation over 21/2 years away Discuss NRC review schedules l

Indication of acceptability of analysis scope l

a Confirmation of compliance submittal May 10,1988 35

T ras NRC REVIEW MILESTONES l

Jan 89 l

LOCA METHODS l

TOPICAL NRC REV i

Jul 89 Jan 91 l

I LOCA MODEL ANALYSIS RESULTS NRC REVIEW Jul 89 l

LICENSE AMENDMENT NRC REVIEW 4

Jul 90 RELOAD AMENDMENT NRC REVIEW i

CY CYCLE R

CYCLE 15 R

CYCLE 16 R

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1988 1989 1990 I

May 10,1988 36 i

2 sw -u3

,- a MEETING

SUMMARY

DISTRIBUTION

' Docket. File NRC & Local-PORs Gray File AWang OGC-WF SNorris EJordan JPartlow NRC Participants Tom Shediosky NRC Region !

Y. Gene Hsii John F. Stolz Bob Jones Wayne Hodges Rudy Karsch HBC1ayton

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