ML20248F032

Forwards Rept of AOs at Licensed Facilities for First Calendar Quarter 1989.Plug Failure Resulted in Steam Generator Tube Leak at North Anna Unit 1 & Steam Generator Ruptured at McGuire Unit 1.W/o Encl

ML20248F032
Person / Time
Site:	North Anna, McGuire, 05000000
Issue date:	09/14/1989
From:	Carr K NRC COMMISSION (OCM)
To:	Quayle J SENATE, PRESIDENT OF THE SENATE
References
NUDOCS 8910060181
Download: ML20248F032 (1)

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

/ September 14, 1989 CHAIRMAN The Honorable J. Danforth Quayle President of'the Senate Washington, D. C. 20510

Dear Mr. President:

I'am enclosing the Nuclear Regulatory Commission (NRC) report on abnormal occurrences at licensed nuclear facilities, as required by-Section 208 of the Energy Reorganization Act of 1974 (PL 93-438), for the first calendar quarter of 1989. In the context of the Act, an abnormal occurrence is an un-scheduled incident or event that the Commission determines is significant from the standpoint of public health or safety.

For this reporting period, there were two a'onormal occurrences at nuclear power plants licensed to operate, The first had

' generic implications and -involved a plug fo'1ure resulting in a steam generator ~ tube leak at North Anna Unit 1. The second involved.a steam generator tube rupture at McGuire Unit 1.

There were three abnormal occurrences under other NRC-issued licenses. Two involved medical therapy misadministration and one invo'.ved a medical diagnostic misadministration. There were no abnormal-occurrences reported by the Agreement States.

The report also contains information updating some previously reported abnormal occurrences.

In addition to this report, we will continue to disseminate information on reportable events. These event reports are routinely distributed on a timely basis to the Congress, industry, and the general public.

Sincerely, x_-1 .

Kenneth M. Carr

Enclosure:

Report to Congress on Abnormal Occurrences (NUREG-0090, Vol. 12, No. 1) j i 8910060181 s90934 PDR i 0 A COMMS NRCC CORRESPONDENCE PNU

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