ML19344B335

Forwards LER 80-016/01T-0

ML19344B335
Person / Time
Site:	Cooper
Issue date:	07/17/1980
From:	Lessor L NEBRASKA PUBLIC POWER DISTRICT
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19344B336	List: ML19344B335 ML19344B337
References
CNSS800441, NUDOCS 8008260642
Download: ML19344B335 (2)

Text

e COOPER NUCLEAR STATION Nebraska Public Power District "' *

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CNSS800441 July 17, 1980 Mr. K. V. Seyfrit 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.a of IE Bulletin No. 80-17 and discusses a reportable occurrence that took place on

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July 7, 1980. The occurrence was discussed with Mr. Bob Spangler on July 7, 1980. The initial report was telecopied to your office on July 9, 1980. A licensee event report form is also enclosed.

keport No. 50-298-80-16 Report Date: July 17, 1980 Occurrence Date: July 7, 1980 Facility: Cooper Nuclear Station Brownville, Nebraska 68321 Identification of Occurrence:

As requred by IE Bulletin No. 80-17, prompt notification shall be given when HPCI, RCIC, SLCS, RPT/RHR/ pool cooling or main steam bypass are less than fully operable. Surveillance tests and pre-ventive maintenance lasting less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> need not be re-ported.

j Conditions Prior to Occurrence:

i Steady state power operation at approximately 99* reactor power.

Description of Occurrence:

On July 7, 1980, the "D" RHR Service Water Booster Pump was taken out of service for preventive maintenance. The pump was returned to service approximately 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> later.

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Mr. K. V. Seyfrit July 17, 1980 Page 2.

Designation of Apparent Cause of Occurrence:

Normal end of life of components of the subject pump as per ASME,Section XI, Inservice Testing of Pumps and Valves, was determined to be the cause of degraded operability of the pump. Monthly testing had placed the ramp in the alert range which requires the testing frequency to la doubled until corrective action is taken and new reference values with appropriate ranges are generated.

Analysis of Occurrence:

During the maintenance, the redundant loop and the other pump in the same loop were operable in the event the RHR System was needed.

This occurrence presented no adverse consequences from the stand-point of public health and safety.

Corrective Action:

Pump was overhauled and the appropriate surveillance test was run to prove operability.

Sincerely, L. C. Lessor Station Superintendent Cooper Nuclear Station LCL:cg Attach.

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