ML19206A640

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Followup Rept on Possible Reportable Condition.While Preparing Wall for Placement of Fuel Transfer Tube Shield, Chipping Hammer Exposed Void in Fuel Handling Wall
ML19206A640
Person / Time
Site: Crane Constellation icon.png
Issue date: 11/14/1975
From: Arnold R
Metropolitan Edison Co
To: Knuth D
NRC/IE
References
GQL-1712, NUDOCS 7904200317
Download: ML19206A640 (2)


Text

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  • O **OColst NETROPOLITAN EDISON COMPANY 3C3r OmCE 3CX 5C A EAtlNG. *E?.NSYLV ANI A Et3 TELU*CNE t?5 - 9 3-2W November ik, 1975 GQ1 1712 Director of Nuclear Reactor Regulation Attn: Dr. D. F. Knuth, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Cc=sission k'ashingten D. C. 20555

Dear Dr. Knuth:

ThreeMileIslandNucle-St]ationUnit2 Docket No 20-320 On October 17, 1975, Mr. L. Narrew of your office was verbally notified of a situation which Metropolitan Edison Co. considered =ay be report-able in accordance with the require =ents of 10 CFR 50.55(e). This letter constitutes the required thirty day follow-up letter.

Description

'4hile preparing the south exterior wall of the Unit 2 Fuel Eandling Building for the concrete place =ent of the fuel transfer tube shield walls, one of the chipping b ers exposed a void in the Fuel Handling Building wall approxi=ately 14" above the east fuel transfer tube.

The void extended over an area approx 1=ately 3 inches in height by 6 feet wide and varies in depth from 3 feet to 5 feet. The void is located in a section of wall that had initially been a blockout fer the fuel transfer tube installation, k' hen cencrete was subsequently placed in the blockout, the inner top sectica of the bicckout failed to fill ccepletely, leaving the recently disecvered void.

Analysis of Safety I=clications The Fuel Handling Huilding was designed and constructed as a Seis=le Class I structure. Had the void remained undetected, it is possible that during a seisnic event, cracks might occur at the high stress concentration corner areas of the void; these cracks could then propagate throughout the structure. This would net have a signifier _nt effect en the structural integrity of the building nor would it ccepremise the health and safety of the public or the plant staff. Also, since this 5 c.c. ^.,

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  • Dr. D. F. Knuth, Director

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area is adjacent to the reactor building contain=ent vall and is protected with radiation shield walls, nn possibility of radiation streaming existed.

Corrective Actic.n The above condition was docu=ented on a site deviation report.

Exploratory chipping and cleaning of the void area has been ccepleted revealing that the void dces not extend beyond the blockout. The area of the void will be repaired in accordance with instructicns from the engineer. All repair work will be coupleted by Nove=ber 26, 1975. Further information and documentation associated with the repair will be available at the site for your inspection.

Very truly yours, f\\

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R. C. Abnold Vice President RCA: C'45 : t as cc:

Mr. J.P.0'Reilly Director, Office of Inspection and Enfurcement, Region I File:

20.1.1 / 7.7.3.6.2

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