ML20041A863

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Describes Sequence of Plant Operation & Steam Generator Insp Re Tube Degradation on Nondomestic Westinghouse Plant W/Model D Steam Generators Per 811120 Meeting
ML20041A863
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 12/29/1981
From: Parker W
DUKE POWER CO.
To: Adensam E, Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20041A859 List:
References
NUDOCS 8202220601
Download: ML20041A863 (2)


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w Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulatinn U. S. Nuclear Regulatory Commit aminn W:shington, D. C.

20555 Attention:

Ms. E. C. Adenaam. Chief Licensing Branch No. 4 Re McGuire Nuclear Statson 1

Docket No. 50-369 Dear Mr. Dentont On October 31, 1983 Duke Power Company notified the NRC Staf f of tube degradation on a non-domestic Westinghouse plant with Mode) D steam generatore similar to those at McGuire Nuclear Station.

Subsequently a meeting was held on November 20. 1981 La Bethesda to brief the Staff on the detalle of the problem as well se Duke Power Company's plans for operation of McCuire.

In particular Mr. M. B. Tucker outlined a planned sequence of plant operation. steam senerator tube inspection and instru-mentation installation.

The purpose of this letter is to update the NRC staff on i

the status of this effort to date and on plans for future operation.

Bddy current testing was performed on the ' A' St emm Cenerator to determine if a threshold power level existed at which tube vibration in the preheater was inicia-ted.

Rows 49, 48 and 4 7 were exa=Ined.

This testing was conducted after two weeks operation at approximately 50% power and again af ter one week operation at 75% power.

This testing was conducted by Babcock and Wilcox Company personnel utilizing a.590" diameter differentini probe.

A Zetec M1Z-12 multi-frequency apparatus was employed et frequencies of 130 khz. 200 khz. 400 khs and 550 khr.

Since this examination was looking for wear damage at tube support plate locatsons both 130-550 kha and 200-400 khz mixed outputs uere used to eliminate the support plate signal leaving only defect. signals for analysis.

An ASMK section XI type calibration standard was used.

Raoults of both of these inspections (i.e. ef ter operatic n at 50% and 75% power)

T were reviewed by sabcock and Wilcow, Duke Power Company. Wastinghouse and EFRI NDT l

personnel.

A comparison with the reaults of the preservice inspection was made.

No wear type indications were observed.

During the November outage. three transducers were mounted around the feedwater nosale om each steam generator.

These tranaducers are intended to provide en early

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indication of any gross secchanical vibration Analde the prehester and will eventuell be used in conjunction with the internal instrumentation when installed.

"Ib date no l

oignale 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.

0202220601 820129 PDR ADOCK 05000369 P-.-...-.

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Mr. Itarold R. Denton Deceanber 29 1981 Page 2 Currently, the unit is in the startup phase.

Plans are to increase power to 902, knold 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 752.

The unit will than be shutdown, eddy current examination performed on all 4 steam Generators and internal instrumentation enounted Sn one stema generator as described in our Movember 20, 1981 meeting in Bethesda. This operating plan represents our best efforts to balance testing and operational needs with a prudent course of actio:

to moeure the integrity of the et*** senerators.

Minor changes to this planned sequ-cnce may occur due to unforseen circumstances; however, we will keep you advised of c:Iy significant departure irom this plan.

Flesse advise if u have any questione regarding this matter.

V truly your,

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William O. Parkar. J GAC/jfw ces Mr. P. R. Besits Mr. James P. O'Reilly. Regional Administrator Senior Reeldent Inspector U. S. Nu _ lear Regulatory Coussission McGuire Nuclear Station Region II 101 m rietta Street, Suite 3100 Atlants. Coorgia 30303

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Docket Hos:'50-369 and 50-370 s

LICENSEE:

DUKE POWER COMPANY FACILITY; McGuire Nuclear Station. Units 1 and 2

SUBJECT:

SUMMARY

OF HEETING ilELD ON NOVEMBER 20. 1981

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A meeting was held with the licensee on Novernber 20. 1981, to discuss preheater-type steam generator tube problems in foreign reactors as related to the operation of McGuire Unit No.1. A list of attendees is snown 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

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steam generators are of similar design (Model D) to those in the.McGuire Unit 1 pl ant.

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 i

believes at this time that tube degradation can be attributed to excita. tion of the tubes fron hi h fluid velocities and/or non-uniforn velocity distribution..

0 The licensee stated that McGuire Unit 1 was shut down on Noveaber 16. 1981 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 vibratiori nonitors (3 transducers per S/G) on each S/G. Upon completion of this inspection effort, the unit will be restarted and a power level of-75% established, approx.

November 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, monitor instrumentation will be evaluated.

Interim l

operation on the above basis appears appropriate at this time.

6 The licensee in'dicated that further operation at 90% power is comtemplated to com-plete some ascension testing ( 1 week) provided no indications above 20% are dis-

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I 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 down at that time for further EC testing.

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2-Since the information presented by Westinghouse was proprietary, the licensee agreed to document the information pursuant to 10 CFR 2.79.0.

Ralph A. Birkel. Project Manager Licensing Branch No. 4 Division of Licensing

Enclosures:

1.

Attendance List 2.

McGuire Nuclear Station.

Unit 1. Operating Plan O

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McGuire i.

J Mr. William 8. Parker. Jr.

Vice President - Steam Production Duke Power Company P.O. Box 2178 422 South Church Street Charlotte. North Carolina 28242 cc: Mr. W. L. Porter onelley Blum. Esq.

Mr. A. Carr 1716 Scales Street Duke Power Company Raleigh', North Carolina 27608 P.O. Box 2178 422 South Church Street Mr. Paul Bemis Charlotte. North Carolina 28242 Resident Inspector c/o U.S. Nuclear Regulatory Commission 4

Mr. R. S. Howard P.O. Box 216 Power Systems Division Cornelius. North Carolir.a 28013 Westinghouse Electric Corp.

P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith EDS Huclear Incorporated

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220 Montgomery Street

~g-San Francisco, California 94104 Mr. J. E. Houghtaling NUS Corporation 2636 Countryside Boulevard Clearwater. Florida 33515 Mr. Jesse L. Riley President The Carolina Environmental Study Group 854 Henley Place Charlotte. North Carolina 28207 J. Michael McGarry. III. Esq.

DeBevoise & Liberman 1200 Seventeenth Street. N.W.

Washington, D. C.

20036 Ms. M. J. Graham i

Resident Inspector McGuire NPS c/o U.S. Nuclear Regulatory Commission P.O. Box 216 Cornelius, North Carolina 28031 e

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2 ATTENDANCE LIST McGuire Nuclear Station. Units 1 and 2 hovember 20. 1981 DUKE POWER COMPANY Skip Copp

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H. B. Tucker C. W. Hendrix. Jr.

A. L. Sudduth WESTINGHOUSE CORP.

H. J. Connors I. C. Ratsep M. A. Weaver N. P. Hueller B. H. Bowman Antonio Aldeanueva

0. J. Woodruff K. L. Huffman T. F. Timmons Deryk R. Grain

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NRC STAFF

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Ralph A. Birkel William V. Johnston Philip Itatthews Victor Densroya Conrad McCracken E. G. Adensam K. N. Jabbour C. Y. Cheng W. J. Collins J. Rayan T. J. Kenyon R. L. Tedesco Nick Economos Alan Herdt Keith Wichman Dennis Crutchfield Emett Murphy E. Igne OTHERS Jose I. V111adoniga -

Consejo De Seguridad Nuclear - Spain Julian - Gorosarri -

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ItGUIRE NUCLEAR STATION - UNIT 1 OPERATifE PLAN o CONDUCT EC DW11MTION "A"S/G R0WS49,'48,'47,I

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o INSTALL EXIERML INSRIBITATION "A" S/G o EVAulATE EC E)'A11 NATION RESULTS IF INDICATIONS <20% C0ffTINUE OPERATION IF INDICATIONS >20%, INSPECT 4 S/G, EVALUATE o ESCALATE TO 75% POWER, C0fPLETE TESTS, (~2 EEKS)

- IONITOR INSTRLISTATION, EVALUATE o SHlIII)0WN - CONDUCT EC EXAMINATION "A" S/G R0WS49,48,47,5 o EVALUATE EC EXAMINATION ESULTS IF INDICATIONS <20% CONTINUE OPERATION IF INDICATIONS >20%, INSPECT 4 S/G, EVALUATE O

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10 GUIE NUCLEAR STATION - UNIT 1 -

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o ESCALATE T0 93, CDPLETE TESTS (1 WEB 0 o IONITOR INSTRlPBiTATION, EVAll] ATE -

o EVALUATE 2-90% POWER DATA

- IF SATISFACTORY, CONTINUE OWRATION

- IF UNSATISFACTORY, OERAlE AT EDUCED POWER o ESCALATE POWER T0 t.00% 0%XIlUI1 DAY) o AT THIS POINT EITER:

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ECT INSECT 10N 11 S/G INSTALL INTERNAL INSTM13fTAT10N 2 TlBES,.1 S/G EVALUATE 50 - 100% POWER DERATION PLUS OTHE o DETERMINE APPROPRIATE NEAR TERM OERATI,NG CONDITIONS USE OF COMBINED l%IN, AUXILIARY FEED NQ7/lES POWER LEVEL O i1ETLEN TO POWER

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January 7, 1982 MEMORANDUM FOR: Darrell G. Eisenhut. Director Division of Licensing FROM:

Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

SUBJECT:

BOARD liOTIFICATION ON McGUIRE Attached for your approval '-. Board Notification on McGuire Nuclear Station, Units 1 and 2, regarding preheater type steam generators.

Original. signed by Robert L Tedesco Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

Enclosure:

Board Notification cp

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