ML20040G475
| ML20040G475 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Summer  |
| Issue date: | 01/20/1982 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Atomic Safety and Licensing Board Panel |
| References | |
| TASK-AS, TASK-BN-82-02, TASK-BN-82-2 BN--82-02, BN--82-2, NUDOCS 8202160079 | |
| Download: ML20040G475 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION r.
j W ASHINGTON, D. C. 20S55
'+,....,o gy2 0W MEMORANDUM FOR: The Atomic Safety and Licensing Board for Virgil C. Summer Nuclear Station FROM:
Robert L. Tedesco, Assistant Director-for. Licensing Division of Licensing
SUBJECT:
BOARD NOTIFICATION - PREHEATER TYPE STEAM GENERATOR (BN-82-02)
Enclosed is a memorandum dated December 7, 1981, providing a summary of a meeting held on November 20, 1981, with the Duke Power Company and Westinghouse Corporation.
Information was presented regarding the results of testing of the Model D steam generator (similar to those at the Virgil C.
Summer Nuclear Station) at two foreign reactors.
Also enclosed is a letter from the Duke Power Company dated December 29, 1981, describing the results of its sequence of plant operation and steam generator inspection.
To date, no indication of steam generator tube wear has been observed at the McGuire plant. The staff is closely monitoring the McGuire operation and steam generator test program and is evaluating information from the plant and the Westinghouse test program as it relates to the Virgil C. Summer Nuclear Station. We will keep the Board informed.
E'fl+ w Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosures:
1.
Summary of Meeting held on November 20, 1981, dated December 7, 1981 2.
Letter from Duke Power Company to NRC dated December 29, 1981 820216.079 820120 PDR ADOCK 05000369 P
Mr. T.
C.'
Nichols, Jr.
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Vice President & Group Executive Nuclear Operations South Carolina Electric & Gas Company P. 0.' Box 764 Columbia, South Carolina.29218
' cc:
Mr. Henry Cyrus Senior Vice President South Carolina Public Service Authority 223 North Live 0ak Drive Moncks Corner', South Carolina 29461 J. B. Knotts, Jr., Esq.
Debevoise & Liberman 1200 17th Street', N. W.
Washington, D. C.
20036 Mr. Mark B. Whitaker, Jr.
Group Manager - Nuclear Engineering & Licensing 56uth Carolina Electric & Gas Company P. O. Box 764 29218 Columbia, South Carolina Mr. Brett~ Allen Bursey Route 1, Box 93C Little Mountain, South Carolina 29076.
Resident Inspector / Summer NPS c/o U. S. NRC Route 1, Box 64 Jenkinsville, South Carolina 29065 Dr. John Ruoff Post Office Box 96 Jenkinsville, South Carolina 29065 Mr. James P. O'Reilly U.' S. NRC, Region'II 101 Marietta Street Suite 3100 Atlanta, Georgia 30303 J
DISTRIBUTION OF BOARD NOTIFICATION V.C. Summer Docket No. 50-395 ACRS Members Dr. John H. Buck Dr. Robert C. Axtmann Mr. Brett Allen Bursey Mr. Myer Bender George Fischer, Esq.
Dr. Max W. Carbon Herbert Grossman, Esq.
Mr. Jesse C. Ebersole Dr. Frank F. Hooper Mr. Harold Etherington Joseph B. Knotts, Jr., Esq.
Dr. William Kerr Christine N. Kohl, Esq.
Dr. Harold W. Lewis Mr. Gustave A. Linenberger Dr. J. Carson Mark Mr. Randolph R. Mahan Mr. William M. Mathis Alan S. Rosenthal, Esq.
Dr. Dade W. tioeller Richard P. Wilson, Esq.
Dr. David Okrent Atomic Safety and Licensing Board Dr. Milton S. Plesset Panel Mr. Jeremiah J. Ray Atomic Safety and Licensing Appeal Dr. Paul G. Shewmon Panel Dr. Chester P. Siess Docketing and Service Section Mr. David A. Ward Document Management Branch I
JAN 2 01982 BOARD NOTIFICATION DISTRIBUTION
' Docket
- File T LB#1 Reading Board Notification File D. Eisenhut NRC PDR z
Local PDR DL Branch Chiefs W. Kane B. J. Youngblood M. Rushbrook R. H. Vollmer it. Jambor R. Matson.
S. Hanauer B. Snyder R. Hartfield, MPA OELD OIE (1)
H. R. Denton/E. Case
'PPAS (H. Thompson)
W. J. Dricks V. Stello S. Goldberg, ELD J. O'Reilly, Region II J. Sniezed, IE Hqrs.
E. Blackwood, IE Hqrs.
R. L. Tedesco
Dpb Uh.J y 7. No e Done 1 %w r. u L.osrawy
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>>>on Mr. Harold R. Denton. Direstur Office of Nuclear Reactor RegulatSten U. S. Nucl ear Regul a t or y Comm i v:n i..n Wechington, D. C.
20555 Attention:
Ms. E. C. Adennam. Chief Licensing Branch No. 4 Ras McGuire Nuclear 5t at ion Docket No. 50-369 Dear Mr. Dentont On October 31, 1981 Duke Pouer Company notified the NRC Staff of tube degradation on a non-domestic Vestinghouse plant with Mode) D steam generatore similar to those et McGuire Nuclear Station.
Subsequently a meeting was held on November 20, 1981 in Bethesda to brief the Staf f on the det alla of the problem as well se Duke Power -
Company's plans for operat ion of McGuire.
In particular Mr. H. B. Tucker outlined c planned sequence of plant operation, steam generator tube inspection and instru-smentation installation.
The purpose of this letter is to update the NRC Staff on the status of this effort to date and v.n plans for future operation.
Eddy current testing was performed on the
'A' Steam Cenerator to determine if a threshold power level existed at which tube vibration in the preheater was initia-tcd.
Rows 49, 48 and 4 7 were examined.
This testing was conducted after two weeks operation at approximately 50I power and again af ter nne week operation at. 75% power.
hio testing was conducted by Babcock and Wilcox Company personnel utilizing a.590" diemeter differential probe.
A Zetec HII-12 multi-frequency apparatus was employed ct frequencies of 130 kha, 200 khr, 400 khz and 550 khs.
Since thie ex==ination was looking for wear damage at tube support plate Ioentions both 130-550 kha and 200-400 khr mixed outputs w re used to eliminate the support plate signal leaving only dofoct signals for analysis.
An ASME Section XI type calibration standard was used.
Recults of both of these inspections (i.e. efter operation at 50% and 75% power) wero reviewed by Rabcock and Wilcow, Duke Power Company, WestinAhouse and EP3.1 NDT personnel.
A comparison wi th tha reaults of the preservice inspection was made.
No wear type indications were observed.
During the November outage. t.hree transducers were s.ounted around the feedwater nonale on each steam generator.
These transducera are intended to provide an early indication of any grosa, mechanical vibration inalde the prehester and will eventuall ha used in conjunction with the internal instrumentation when installed.
To date no cignals have been noted which correlate to preheater/ tube vibration.
Resonance peak which have been observed were caused by flow turbulence rather than any mechanical vibration phenomenon.
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Mr. Harold R. Denton December 29, 1981 Pcg3 2 Currently, the unit is in the startup phase.
Plans are to increase power to 90%,
hold at that level for up to 4 days then increase to 100% for one day.
Power opera-tion would then continue for up to 6 weeks at power levels up to approximately 75%.
The unit will then be shutdown, eddy current examination performed on all 4 steam generators and internal instrusientation enounted in one steam generator as described in our November 20, 1981 meeting in Bethesda. This operating plan represents our bect efforts to balance testing and operational needa with a prudent course of actio:
to osaure the integrity of the steam generators.
Minor changes io this planned sequ onco may occur due to unformeen circumstances; however, we will keep you advised of cny significant departure f rom this plan.
Please advise if y u have any questions regarding this matter, i
V truly your J
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Mu:,~ O.
William O. Parker, J CAC/jfw cc Mr. P. R. Bemis Mr. James P. O'Reilly, Regional Administrator Senior Resident Inspector U.
S.
Nuclear Regulatory Consnission McGuire Nuclear Station Region II l
101 Marietta Street, Suite 3!00 Atlanta, Georgia 30303 l
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Docket flos: 50-369 and 50-370 LICENSEE:
DUKE POWER COMPANY FACILITY:
licGuire Nuclear Station. Units 1 and 2
SUBJECT:
Su!1 MARY CF MEETING HELD ON !!OYEMBER 20. 1981 A meeting was held with the licensee on tJovember 20. 1981 to discuss pmheater-type stean generator tube problems in foreign reactors as related to the operation of McGuire Unit No.1.
A list of attendees is shown on Enclosure 1.
The major briefing presentation was nade by Westinghous'e and included the results to date of testing of the Model D steam generator at two foreign reactors. These steam generators are of similar design (! odel D) to those in the McGuire Unit 1 pl a nt.
Eddy Current testing has revealed.that there are indications in the outer rows of tubes in essentially all steam generators s.o tested.. Westinghouse has initiated a program of testing and tube examination along with analytical evalu-ations to determine the initiator of this tube degradation phenomena. Westinghouse believes at this time that tube degradation can be attributed to excitation of the tubes fron high fluid velocities and/or non-uniforn velocity distribution.
'The licensee stated that ItcGuire Unit 1 was shut down on tiovenber 16. 1991 and that an operating plan for Unit I had been developed (see Enclosure 2). Rows 47, 48 and 49 in "A" Steam Generator (S/G) were Eddy Current tested. The results were negative with possibly one slight indication. The licensee has installed external vibrattori monitors (3 transducers per S/G) on each S/G. Upon cogletion. of this inspection effort, the unit will be restarted and a power level of 75% established, approx.
Ilovenber 23. Upon completion of. the traditional 75% plateau power ascension testing
( 2 weeks), the unit will be shutdown and S/G Eddy Current testing repeated on S/G "A".
During unit operation, nonitor instrumentation will be evaluated.
Interim operation on the above basis appears appropriate at this time.
I The licensee indicated that further operation at 90% power is contemplated to com-plete some ascension testing ( 1 week) provided no indications above 20% are dis-covered in S/G "A".
Following this week of testing, evaluation of the monitoring.
and evaluation of 50-90% power data, they would decide on escalation to 100% power for one day. Data evaluation at this time would detemine whether or not the licensee would plan to continue operation at an acceptable power level or shut c
l down at that time for further EC testing.
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'l Since the information presented by Westinghouse was proprietary. the licensee agreed to docu:nent the information pursuant to 10 CFR 2.79.0.
i Ralph A. Birke1. Project Manager Licensing Branch No. 4 Division of Licensing s
Enclosures:
1.
At'tendance List 2.
McGuire Nuclear Station.
Unit 1. Operating Plan o
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McGuire t
Mr. William 8. Parker. Jr.
Vice President - Steam Production Duke Power Company P.O. Box 2178 i
422 South Church Street Charlotte North Carolina 28242 l
cc: Mr. W. L. Porter Shelley Blum. Esq.
Mr. A. Carr 1716 Scales Street Duke Power Company Raleigh. North Carolina 27608 I
P.O. Box 2178 422 South Church Street Mr. Paul Bemis Charlotte. North Carolina 28242 Resident Inspector c/o U.S. Nuclear Regulatory Comission Mr. R. S. Howard P.O. Box 216 Power Systems Division Cornelius. North Carolina 28013 Westinghouse Electric Corp.
P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith
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EDS Nuclear Incorporated 220 Montgomery Street San Francisco, California 94104 Mr. J. E. Foughtaling NUS Corporation 2536 Countryside Boulevard Clearwater. Florida 33515 Mr. Jesse L. Riley, President The Carolina Environmental Study Group 854 Henley Place Charlotte North Carolina 28207 i
J. Michael McGarry III. Esq.
DeBevoise & Liberman 1200 Seventeenth Street N.W.
Washington D. C.
20036 l
Ms. M. J. Graham Resident Inspector McGuire NPS i
c/o U.S. Nuclear Regulatory Comission
.P.O. Box 216 Cornelius. North Carolina 28031 1
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ATTENDANCE LIST McGuire Nuclear Station. Units 1 and 2 November 20. 1981 DUKC POWER COMPANY Skip Copp H. B. Tucker C. W. Hendrix, Jr.
A. L. Sudduth WESTINGHOUSE CORP.
H. J. Connors
- 1. C. Ratsep H. A. Weaver N. P. Mueller B. H. Bowman Antonio Aldeanueva
- 0. J. Woodruff K. L. Huffman T. F. Timons Deryk R. Grain
~
NRC STAFF Ralph A. Birkel William V. Johnston Philip Itatthews Victor Genaroya Conrad McCracken E. G. Adensam K. N. Jabbour C. Y. Cheng W. J. Collins i
J. Rayan T. J. Kenyon R. L. Tedesco j
Nick Economos Alan Herdt l
Keith Wichman 1
Dennis Crutchfield Emett Hurphy l
E. Igne i
OTHERS Jose 1. Villadoniga -
l Consejo De Seguridad Nuclear - Spain Julian - Gorosarri -
Alanaraz Power *7' int -
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N,. A1,maraz, 1
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I FORu 318 (IMO) NACM 024o OFFICIAL RECORD COPY uso m i i_ m I
3 ItGUIRE f0 CLEAR STATION - UNIT 1 OPERATIf6 PIAN o C0iOUCT EC D#11tMTION "A" S/G R0WS 49,' 48,' 47,g o INSTALL EXTERIML INSTRLfGTATION "A" S/G o EVAUJATE EC EX#ilfMTION RESULTS IF ItalCATIONS <20% C0f(TINUE OPEPATION
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IF ItalCATIONS >20%, If&ECT 4 S/G, EVALUATE o ESCALATE TO 75% POWER, C0fPlflE TESTS, (~2 hEEKS)
- IGITOR INSTRUHTATION, EVALUATE o SHUTDOWN - C0000CT EC EXNilfMTION "A" S/G R0WS49,48,47,5 o EVALUATE EC E7#iltMT10N RESULTS IF IfoICATIONS <207. C0ffrit0E OPERATION IF INDICATIONS >20%, If&ECT 4 S/G, EVALIMTE 9
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10 GUIE NUCLEAR STATlai - LNIT 1 -
OPERATING PLAM o ESCALATE TO 9%, 00FPLETE TESTS Gh80 o IUilTOR ltGTRlPENTATION, EVAUJATE o EVAUJATE IB-93 POWER DATA
- IF SATISFACTORY, CONTINUE ORRATION
- IF UNSATISFACTORY, ORRATE AT REDUED POWER o ESCALATE POWER TO LOM 0%XIM111 DA'O o AT llilS PolNT EITHER:
- 1) gEJTgigglE POWER LEVEL. BASED GiIRTA
- 2) SHtflue 3R EC INSHCT Ob AND INSTALLATION OF ADDLT10hA_ INSTRLPENTAT 06
.r hMILE SHUTDOWN g
ECT INSECT 10N 14 S/G INSTALL INTERML INSTRlfBffATION 2 TEES,.1 S/G EVAL 1 RTE 50,- 10% PG4ER OPERATION PLUS OTER DATA o DETERilNE APPROPRIATE NEAR TERi OEPATING CONDITIQG US$ OF C0FBINED i%IN, AUXILIARY FEED N0ZZLES PodERLEVEL o RETURN To POWER e
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