05000219/LER-1980-002, Forwards LER 80-002/03L-0

Forwards LER 80-002/03L-0

ML19308D041
Person / Time
Site:	Oyster Creek
Issue date:	02/14/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19290D605	List: 05000219/LER-1980-002, Forwards LER 80-002/03L-0 05000219/LER-1980-002-03, /03L-0:on 800116,during Fuel Bundle Clip Insp,Fuel Bundle UD-3-023 Was Misoriented & Was Not Properly Seated in Core Cell Location.Caused by Personnel Error & Inadequate Procedural Controls.Procedure 205 Revised
References
NUDOCS 8002220390
Download: ML19308D041 (4)

LER-1980-002, Forwards LER 80-002/03L-0

Event date:
Report date:
2191980002R00 - NRC Website

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Jersey Central P;wer & Ught Company

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• • J (,, #.,q Madison Avenue at Punch Bowt Road Mornstown, New Jersey 07960 (201)455-8200 February 14, 1980 Mr. Boyce H. Grier, Director Of fice of Inspection and Enforcement Region i United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SUBJECT:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/80-2/3L This letter forwards three copies of a Licensee Event Report to report Reportabic Occurrence No. 50-219/80-2/3L in compliance with paragraph 6.6.1.a of the Technical Specifications.

Very truly yours, dfl e N Ivan R. Fi rocle Jr.

Vice Presi ent-eneration ck Enclosures cc:

Director (40 copies)

Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Director (3 copies)

Office of Management and Program Analysis United States Nuclear Regulatory Commission Washington, DC 20555 s 002220 6

3 Cr o Jersey Central Power & Lght Company is a Member of the Generaf Putec Utaties System 3

I I 10.0 Transportation Security 10.1 The licensee shall not import, export, transport in a single shipment or take delivery of a single shipment free on board at the point where it is delivered to an agent or carrier, quantities of special nuclear material as specified in 10 CFR Part 73.1(b)(2) until a detailed plan as described in 5 70.22(g) of 10 CFR Part 70 has been submitted, and approved by the Nuclear Regulatory Commission.

Sincerely,

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pt 4: MAcO4, y

George W. McCorkle, Chief Physical Security Licensing Branch Division of Safeguards l

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Mr.., James G. Kepple, DirGctor U. S. Wuclear Regulatory Commission Rbgion III d

January ll,1980 - QA-1247 Page 2

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Date When Full Compliance will be Achieved Full compliance will be achieved when the verification of the drywell steel is complete. This verification is scheduled to be completed March 15, 1980.

In order that records are correct, the following information is provided.

Reinforcing plates identified by Heat Number 801E04680 (3/8" thick) and AN-74292 (3/4" thick) are both A-36 materials and were installed in compliance with drawing requirements.

We trust that this letter is an adequate response to your IE-Investigation Report #79-32.

Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY fk hyne-E. A. BORGMANN SENIOR VICE PRESIDENT DCK:pa i

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