ML20080P765

Discusses Installation of Insp Ports in Each Steam Generator Prior to Startup After First Refueling,Per Item 5.3.1 in Sser 4,NUREG-0422.Steam Generator Monitoring & Testing Programs in Effect & Acceptable Alternative Planned

ML20080P765
Person / Time
Site:	McGuire
Issue date:	02/14/1984
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0422, RTR-NUREG-422 NUDOCS 8402230106
Download: ML20080P765 (2)

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D DUKE POWER GOMPANY P.O. DOx 33189 CHAHLOTrE, N.G. 28242 HALH. TUCKER TELEPHONE vuon racerne v (704) 373-4531

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February 14, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S.' Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket No.'50-369

Dear Mr. Denton:

McGuire Nuclear Station Facility Operating License contains Condition No. 2.C.(6) entitled " Steam. Generator Inspection" which states:

" Prior to start-up after the first refueling, the licensee shall install inspection ports in each steam generator or have ai.

acceptable alternative for inspection. This condition references item 5.3.1 in SER Supplement 4, NUREG-0422."

This condition reflected the Staff concern regarding early detection of the

" denting" phenomenon which results in support plate deformation and eventual tube degradation. This requirement was specified over three years ago and since that time other-inspection techniques have been identified for detecting the onset of denting and more experience has been gained in steam generator operation which will minimize the potential for denting to occur. As a result, the Staff concluded in SER Supplement 6, NUREG-0422 (February 1983) that inspection ports were not required to be installed in the McGuire Unit 2 steam generators.

Duke Power Company has an aggressive program to control steam generator chemistry within specified limits. Tight chemistry control and inservice inspection serve to minimize damage to the steam generator tubes due to denting or other types of degradation. The primary inspection techniques are eddy current testing and profilometry measurements on steam generator 4 tubes. These inspection methods are capable of detecting denting, pitting, erosion, wastage, corrosion and cracking. The profilometry measurement will provide some predictive capability since it reveals any sludge or corrosion product buildup on the tubes which is most likely to occur at the tube sheet or support plate locations. These inspection methods and the scope of the inspections will be reviewed periodically to assure that appropriate, new state-of-the-art techniques are used in assessing conditions inside the steam generators. Of course, the inservice inspecticn program outlined in Technical Specification 3/4.4.5 will be followed as a minimum.

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Mr. Harold R. Denton, Director '

a , February 14, 1984.

Page 2-In' summary, it'is Duke Power Company's position that the steam generator monitoring and testing programs fn effect and planned are an acceptable

- altercative to inspection ports for McGuire Unit 1. This conclusion is (consistent with the position taken by the NRC Staff on McGuire Unit 2.

.Accordingly,'it.is concluded that License Condition 2.C.(6) has been satisfied.

Please. advise iffthere are any questions concerning this matter.

Very truly yours, d '/ un

.Hal B. Tucker GAC/php cc: Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station Mr.' James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street,'NW, Suite'2900 Atlanta, Georgia 30303

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