ML20002B985

Forwards LER 80-045/03L-0

ML20002B985
Person / Time
Site:	Cooper
Issue date:	11/26/1980
From:	Lessor L NEBRASKA PUBLIC POWER DISTRICT
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20002B986	List: ML20002B985 ML20002B989
References
CNSS800699, NUDOCS 8101070489
Download: ML20002B985 (2)

Text

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SEE COOPER NUCLEAR STATION 69%kad

~ Nebraska Public Power District "

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CNSS800699 November 26, 1980 v:

Mr. K. V. Seyfrit, Director u -

U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Dear Sir:

This report is submitted in accordance with Section 6.7.2.B.2 of the Technical Specifications for Cooper Nuclear Station and discusses a reportable occurrence that was discovered on November 2,1980. A li-censee event report form is also enclosed.

Report No.: 50-298-80-45 Report Date: November 26, 1980 Occurrence Date: November 2, 1980 Facility: Cooper Nuclear Station Brownville, Nebraska 68321 Identification of Occurrence:

A condition which resulted in operation in a degraded mode per-mitted by a limiting condition for operation established in Section 3.6.H.3 of the Technical Specifications.

Conditions Prior to Occurrence:

Reacter power was at approximately 95% of rated thermal power.

i Description of Occurrence:

During routine inspection, station personnel discovered hydraulic shock suppressor RH-S-43 inoperable.

l Designation of Apparent Cause of Occurrence:

The apparent cause of this occurrence has been attributed to im-proper installation of the shock suppressor during the 1980 re-fueling outage. The shock suppressor was installed with reservoir i connecting pipe at top of the reservoir instead of at the bottom allowing the oil inlet port to become open with no fluid supply.

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Mr. K. V. Seyfrit November 26, 1980 Page 2.

Analysis of Occurrence:

RH-S-43 is a hydraulic shock suppressor installed to allow thermal i growth of the containment spray piping during normal operation and to provide a restraint to pipe movement during a seismic event.

This snubber does not provide a pipe support function during normal operation. There were no recorded seismic events prior to dis-j covery of this occurrence.

RH-S-43 is mounted in i vertical position and is located between two normally closed valves on the "B" containment spray line. If a seismic event had caused failure of this section of line, the drywell integrity would not have been impaired and the balance of the "B" RHR Loop would have remained operable. The redundant containment spray was also operable. This occurrence had no ad-verse effect on the public health and safety.

Corrective Action:

The shock suppressor was correctly oriented and stroked to insure cylinder operability. This occurrence has been reviewed with appropriate station personnel.

Sincerely, L. C. Lessor Station Superintendent Cooper Nuclear Station

! LCL:cg Attach.

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