ML20246E517

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Forwards Rev 0 to Technical Data Rept 935, Results of 1988-7R Once-Through Steam Generator Eddy Current Exams, Following Completion of Eddy Current Insp of TMI-1 Steam Generator a & B Tubes,Per Tech Spec 4.19.5b
ML20246E517
Person / Time
Site: Crane Constellation icon.png
Issue date: 07/03/1989
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20246E521 List:
References
C311-89-2055, NUDOCS 8907120276
Download: ML20246E517 (1)


Text

_

GPU Nuclear Corporation

- NggIg7

. Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 :

717 944 7621 TELEX 84 2386 July 3,1989vriter's Direct Dial Number:

C311-89-2055 l

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemon:

Three Mile Island Nuclear Generating Station (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Post Eddy Current Inspection Report for Cycle 7 Following the completion of the Eddy Current Inspection of TMI-1 A and B steam generator tubes, Technical Specification 4.19.5a requires a report to be submitted, identifying the number of tubes repaired or removed from service, within 15 days of the completion of the inspection. Tube plugging was completed on July 9, 1988. The requisite information was provided to the NRC on July 22, 1988 (Reference 1).

Technical Specification 4.19.5b requires that the complete rescits of the steam generator tube inservice inspection be reported to the NRC including (a) number and extent of tubes inspected, (b) location and percent of wall thickness penetration for each indication of an imperfection; and (c) identification of tubes repaired or removed from service. TDR-935, "Results of the 1988-7R OTSG Eddy Current Examination", provides a comprehensive assessment of the 7R Eddy Current inspection results, and addresses the specific reporting requirements of Technical Spe:ification 4.19.5b.

Neither OTSG inspection was categorized as "C-3" and the special reporting requirements of Technical Specification 4.19,5.C did not Lpply.

This letter fulfills the requirements of Technical Specification 4,19 for Outnge 7R.

Sincerely,

?$f!2esde!@gg,,

gi11 o

d Vice President & Director, TMI-1 l

HDH/DJD/iml:2055 l

Reference:

(1) GPUN Letter C311-88-2079, H. D. Hukill to NRC Document Control Desk " Post Eddy Current Inspection Report for Cycle 7",

July 22, 1988 cc:

R. Hernan, W. Russell, J. Stolz, F. Young GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation I

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