ML17055B376
| ML17055B376 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/03/1986 |
| From: | Haughey M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-66539, NUDOCS 8603130169 | |
| Download: ML17055B376 (52) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 3, 1986 VENDOR:
Westinghouse Electric Corporation
SUBJECT:
MEETING
SUMMARY
FOR FEBRUARY 19, 1986 MEETING WITH WESTINGHOUSE ELECTRIC CORPORATION TO DISCUSS WESTINGHOUSE CORE RELOADS IN BOILING WATER REACTORS On February 19, 1986, the NRC staff met with representatives of Westinghouse Electric Corporation QW) to discuss W core reloads for Boiling Water Reactors (BWR's).
Representatives were also present from Innovative Technologies Incorporated
( ITI) and Niagara Mohawk Power Corporation (NMPC).
W has recently made an agreement with NMPC to supply some of the fuel assemblies to be used in Nine Mile Point 2 (NMP-2). The number and location of the fuel assemblies in the NMP-2 1988 core reload had not yet been determined at the time of the meeting.
Other W commitments to provide fuel assemblies for BWR's include Browns Ferry 2
and Fitzpatrick, but NMP-2 is considered to be the lead plant.
W has entered into a licensing agreement with ASEA-Atom (of Sweden) to share technical information.
ASEA-Atom has experience in a number of BWR's in Europe, one of which, Liebstadt, is a General Electric (GE)
BWR.
ASEA-Atom has two fuel designs.
The W design is essentially the ASEA-C design modified to suit the GE-BWR design.
W stated that this design would result in a LOCA, benefit of a "couple of hundred degrees,"
The Critical Power Ratio (CPR) calculations have not yet been completed.
W presented a proposed schedule for submittal of W topical reports concerning W core reloads in BWRs.
The NRC staff stated that identification of the number and location of W fuel assemblies to be used in the NMP-2 1988 reload would govern the schedule and the urgency for the review of this issue.
If the use of W fuel assemblies in the 1988 reload is minimal, then other reviews may have priority.
NMPC and W were requested to identify the details of the use of W assemblies in the NMP-2 1988 reload.
NMPC stated concern that any problems with using W fuel be identified as early as possible so as not to affect the 1990 reload.
W identified a report on ECCS Evaluation Model, Goblin Series of Codes, as having been submitted to the NRC staff for review in 1983.
The staff was not familiar with that document.
W was requested to identify the specifics of that submittal (i.e. title, report number, date of cover letter, and whether a fee was submitted).
Since the submittal of that report would have preceded the NMP-2 involvement, some documentation to reference NMP-2 would be required.
In addition to the discussion on W fuel, ITI briefly discussed their fuel re-construction program.
The NRC recommended that ITI submit their reconstruction report to the NRC for information.
At that point ITI could discuss with the NRC whether the report should be submitted for NRC review.
8603i30i69 860303 PDR ADQCK 05000410 A
~'
l In summary, NMPC/
W are the NMP-2 1988 reload.
a working level meeting in BWRs.
to determine the details of the W fuel to be used in In addition W will be contactinq the NRC to set up to discuss tKe review schedule and details of W fuel Copies of the overheads presented durinq the meeting are included as enclosures 1 and 2.
A copy of the attendance list i's included as Enclosure 3.
cZ Mary F. Haughey, roiect Wanaqer RWR Proiect Directorate No.
3 Division of BWR Licensina cc:
See next page QB
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AGENDA NRC/WESTINGHOUSE YiEETING ON BWR FEBRUARY 19'986 INTRODUCT ION JOHN NcADOO NFD BWR FUEL SUPPLY ALLAN NcFARLANE NIAGARA MOHAWK DAVE GREENE THE W QUAD+ FUEL ASSENBLY
'DICK SHANK LICENSING DOUG BEVARD ITI INNOVATIVE TECHNOLOGY INC, GEORGE NASCHE SUNNARY NICK LIPARULO
e, e
W ENTRY INTO BWR RELOAD FUEL MARKET EXCHANGE AGREEMENT WITH ASEA-ATOM IN 1980 A-A HAS 11 BWRs IN OPERATION A-A HAS DELIVERED 12i000 BWR FUEL ASSEMBLIES INNOVATIVE WATERCROSS DESIGN WITH TECHNICAL AND ECONOMIC BENEFITS PROVEN PRODUCT RELIABILITY
WATERCROSS F UEL EXPERIENCE 266 ASSEMBLIES NOW IN OPERATION IN SWEDEN LEAD ASSEMBLIES IN 5TH CYCLE EXTENSIVE POST-IRRADIATION EXAMINATION NO NEGATIVE INDICATIONS ASEA-ATOM COMMITMENTS INCLUDE:
DEMOS IN 6 A-A BUILT BWRs 1 AEG/KWU BWR (KRUMMEL) 1 GE BWR (LIEBSTADT)
RELOAD BATCHES IN 7 A-A BWRs IN SWEDEN ASEA-ATOM WILL TRANSITION ENTIRELY TO WATERCROSS DESIGN
0 0
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M CONM I TNENTS M
HAS THE FOLLOWING BMR FUEL ORDERS 4 ASSENBLIES IN TVA's BROWNS FERRY 2 (4/85) 4 ASSEMBLIES IN NYPA's FITZPATRICK (11/86)
LEAD ASSEMBLIES AND RELOADS IN NNPC's NINE NILE POINT 2 (BEG1NNI NG 9/88)
RELOADS IN LILCO'S SHOREHAN (2/91)
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M BMR FUEL ORGAN I ZAT I ON MATER REACTOR DIVISIONS NUCLEAR FUEL DIVISION NUCLEAR TECHNOLOGY DIVISION BWR FUEL NUCLEAR SAFETY BMR DESIGN BWR
& NANUFACTURING PROGRAN NANAGENENT BMR TECHNOLOGY RISK ASSESSNENT SAFEGUARDS ENGINEERING BWR CORE ENGINEERING
/
BMR
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BMR BMR ENGINEERING ------LOCA SERVICES (NON-LOCA)
ASEA-ATON COMPUTER CODES OPERATING EXPERIENCE TEST RESULTS
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LIFTING HANDLE UPPER SUPPORT FIXTURE WATER CROSS FUEL RODS (Ar I
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TOP NOZZLE ATTACHMENTSTUDS IIZII g...)I E
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CHANNEL WATER CROSS BOTTOM NOZZLE SUPPORT STRAP AND SCREWS V
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TOP TIE PLATE FUEL RODS
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LIFTING HANDLE UPPER SUPPORT FIXTURE TOP TIE PLATES I,
TIE RODS FUEL RODS AFID EXPANSION SPRINGS
TIE PLATES IltiiI Ii'I "lil,:
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QUAD+ BENEFITS ECONOMICS o
IMPROVED U AND SWU UTILIZATION PERFORMANCE o
IMPROVED CRITICAL POWER PERFORMANCE o
IMPROVED STABILITY o
IMPROVED VOID COEFFICIENT o
INCREASED CYCLE LENGTH o
IMPROVED KW/FT MARGINS
QUAD+ LICENSING STATUS SUBMITTAL DAT
~TA~S
~SR IT M
6/82 SUBMITTED RECEIVED NUCLEAR DESIGN CODES DESCRIPTION TOPICAL:
PHOENIX/POLCA 6/82 SUBMITTED RECEIVED THERMAL-HYDRAULI CS CODE:
CONDOR 1/83 3/83 SUBMITTED SUBMITTED 9/85 SUBMITTED 1/86 6/86 SUBMITTED 8/86 9/86 9/86 6/87 6/87 6/87 6/87 10/85 INFORMATION FUEL ROD MODEL:
GOBLIN SERIES OF CODES NUCLEAR DESIGN CODES QUALIFICATION COMPUS ON-LINE MONITORING SOFTWARE PROGRAM 8X8 CPR CORRELATION CHANNEL HYDRODYNAMICS STABILITY CODE AND METHODOLOGY TRANSIENT ANALYSIS METHODS QUAD+ CPR CORRELATION LOCA EVALUATION METHOD (APP K)
LOCA 'EVALUATION MODEL SENSITIVITY STUDIES BWR FUEL ROD ANALYSIS METHODS LOCA APP, K.
CALCULATION BASIC SAFETY REPORT
nnovstive echnologies incorporated
'NCORPORATED SEPTEMBER 30i 1985 50X OWNERSHIP BY WESTINGHOUSE AND ASEA-ATOM EACH.
ITI HAs 100'CCESS TO THE NUCLEAR TECHNOLOGY OF BOTH PARENTS.
- FUEL, HOWEVER, IS NOT AN ITI PRODUCT, PRIMARY PURPOSE OF THE COMPANY TO IDENTIFY AND DEVELOP BWR PRODUCTS AND SERVICES FOR WORLDWIDE MARKET,
'MPLINENTATION IN THE UNITED STATES BY WESTINGHOUSE x LicENsiNG x QA/QC X CONTRACTING
'TI THRUST IS TO OFFER A BROAD SPECTRUM OF
- PRODUCTS, ENGINEERING SERVICES AND FIELD SERVICES WITH SIGNIFICANT TECHNOLOGICAL BASE.
t nnoVatiVe echnoIogies jncozyorated CURRENT DEVELOPMENT FOCUS FUEL RECONSTRUCTION H2 CHEMISTRY MINITEST MATERIALS MONITORING SYSTEM-H2 ADDITION SYSTEM s IGSCC NDE/ISI STRUCTURAL. RELIABILITYAND RISK ANALYSIS WELD OVERLAY MECHANICAL'STRESS IMPROVEMENT PROCESS PIPE CLAMP H2 CHEMISTRY IASCC INSPECTION ROBOTICS CHEMISTRY MONITORING SYSTEMi RENEWAL PARTS/REPLACEMENT COMPONENTS REFUELING SERYICES Z INK ADDITION
- I8C, PROCESS COI'1PUTERSr SIMULATORS
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jncorporafed 0
ASEA-ATOM HAS BEEN NNKING itITH FUEL RECONSTRUCTION SINCE 1978 0, THE METHOD NAS DEVELQ%I) F$KN A FUEL REPAIR CAMPAIGN IN 1975 1976 0
THE RECONSTRUCTION IS PERFORMED ON DISCHARGED FUEL BUNDLES IN THE BURN-UP RANGE 20.000 24i000 $$/NTU TO PROLONG THE OPERATIONAL LIFE OF THE FUEL 0
REOPTINIZE DISTR IRJTIOK OF FISSLE MATERIAL REARRAHKHEMT QF flKLtINS O
REOPTI~IZE 'SEW'mcee 4KTRCSVCE ADITI'ONAL~TE% %ASS
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nnm&he hnologies gncorporateQ Ham OSKARSHANX 2 RINGHALS 1 BARSEBECK 1 FOR~RK 1 FORSNARK 2 TOTAL 212 52 76 50 1978 1981 198LI 1984 1985 0
- THE RECONSTRUCTED BUNDLE CAN NE CSED FGR
- 3. VS 3 ADDITIONAL CYCI ES 0
AN ADDITIONALSATCtMISE EXPOSURE CF 2,800 TG 3,000 M)/NTU NAY SE OBTAINED, DEPENDING ON THE ORIGINAL BUNDLES 0
THE FUEL CYCLE COST BENEFIT OF 6 - 7X IS OBTAINED, NINUS THE COST FOR THE RECONSTRUCTION iKNK 0
THE APPROXIMATE bGRK SCOPE FOR A TYPICAL TbO-BUNDLE RECONSTRUCTION lS 2O MIN(NRS
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0 ONE IRRADIATED FUEL ASSEMBLY IS IltSERTED INTO A HOYABLE FIXTURE 0
SCNE RODS MITH THE HIGHEST SURNUP ARE REMOVED FROM THE BUNDLE BOUNDARY 0
CENTRAL RODS ifITH LONER SVRNUP ARE TRANSFERRED TO THE BOUNDARY t
POS ITIONS 0
MATER RM6 ARE INSERTED INTO THE VACANT CENTRAL POSITIONS 071'l2
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nnmMjve pchnologigg gncormndea 0
Tb6 IRRADIA'ttEQ FUEL ASSEMBLIES 4QTM RATHER HIGH BURNUP ARE INSERTED llOQ A SPECI~AI NOVABLE 7'INURE 0
THE RODS bGVH H'IGHEST BURNUP IN ONE BUNDLE A ARE TRANSFERRED TO THE OTHER UNDLE 8 AND THE RODS HITH THE 4.04EST BURNUP IN BUNDLE m ARE llSERIIED INTO BUNDLE:A
,0 IN ORDER 70 ALSO OPTI'SIZE THE REACTIVITY QF BUNDLE I RNE FUEL RM6 1N 'THE lSSEN3LY CENTER ARE:REPLACED MITS blATER RODS"
nnovstive echnologies incorporated MR.
MASCHE DISPLAYED SEVEN COLORED OVERHEADS THAT PICTURED A RECONSTRUCTED FUEL BUNDLE IN DRAWINGS AND ALSO PICTURES OF THE FUEL RECONSTRUCTION EQUIPMENT IN POSITION IN A FUEL POOL.
NO COPIES OF THESE ARE AVAILABLE
SUMMARY
~ EXCITED ABOUT BWR FUEL BUSINESS e
ITI BWR SERVICE ARENA e GOOD PRODUCT DESIGN QUAD+
~ WESTINGHOUSE PVN LICENSING REPUTATION e PWRs BWRs e NRC REORGANIZATION e FIRST OF MANY PRODUCTIVE MEETINGS
~ NYPA DEMOS e BWR TOPICALS e NEED NRC SUPPORT e DOUG BEVARD FOCAL POINT
+ NIAGARA MOHAWK PARTICIPATION
~ NRC PARTICIPATION
~ ~
ENCLOSURE,3 NAME Mary F.
Haughey Larry Phillips Wayne Hodges Tim.Collins Howard Richings Rill Harris Dick Shank Mark Beaumont Augustine Cheuna Anders Micko Georqe Masche Don Hill John McAdoo Dave Greene Doug Revard Nick Lioarulo ORGANIZATION NRC (Licensing PM)
NRC/DBL/RSB NRC/DBL/RSB NRC/DBL NRC/DRL/RSB W-NFD W-NFD W-Bethesda
~7-NTD Nuclear Safety ITI ITI NMPC-Licensinq W-NTD NMPC-Fuels W-Nuclear Safety
P
Mr. B.
G. Hooten Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit 2 CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.W.
Washington, D.C.
20006 Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, New York 12223 Ezra I; Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York l0047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.
Box 99
- Lycoming, New York 13093 Mr. John W. Keib, Esq.
Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Mr. James Linville U.
S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Norman Rademacher, Licensing Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue Kino of Prussia, Pennsylvania 19406 Mr. Paul D.
Eddy New York State Public Service Comoission Nine Mile Point Nuclear Station-Unit II Post Office Box 63
- Lycoming, New York 13093 Don Hil1 Niagara Mohawk Power Corporation Suite 550 4520 East West HighWay
- Bethesda, Maryland 20814 Doug Bevard Nuclear Fuel Division Westinghouse Electric Corporation Box 355 Pittsburgh, PA 15230-0355 David Green Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202
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MEETING
SUMMARY
DISTRIBUTION
'ocke'.t<-'-No', s):
NRC PDR Local PDR BWD ¹3 r/f J. Partlow (Emergency Preparedness only)
E.
Adensam
- Attorney, OELD E. Jordan B. Grimes ACRS (10)
Pro,iect Manager E. Hylton NRC PARTICIPANTS CeT<5g>.o6 ~7 bcc:
Applicant 8 Service List