ML19242B484

Forwards LER 79-017/03L-0

ML19242B484
Person / Time
Site:	Cooper
Issue date:	07/19/1979
From:	Lessor L NEBRASKA PUBLIC POWER DISTRICT
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19242B485	List: ML19242B484 ML19242B488
References
CNSS-790360, NUDOCS 7908080596
Download: ML19242B484 (2)

Text

1 COOPE R NUCLE A R ST ATION P.O. BO x 95, B R OWN VILLE, NE8R ASKA 68321 Nebraska Public Power District TELE-O~E m e:m n

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CNSS790360 July 19, 1979 Mr. E. V. Seyfrit U.S. Nuclear Regulatory Como ssion Office of Inspection and Enforcement Region IV 611 Ryan Plaza Suite 1000 Arlington, Texas 76011

Dear Sir:

This report is submitted in accordance with Section 6.7.2.B.3 of the Technical Spccifications for Cooper Nuclear Station and discusses a

aportable occurrence that was discovered on June 20, 1979. A licensee event report form is also enclosed.

Report No. 50-298-79-17 Report Date: July 19, 1979 Occurrence Date: June 20, 1979 52'41 306 Facility: Cooper Nuclear Station Brownville, Nebraska 68321 Identification of Occurrence:

An observed inadequacy in the implementation of an administrative procedural control required by Technical Specificaticn rable 4.2.3, Item 19.

Conditions Prior to Occurrence:

The reactor was at steady state power level of approximately 95% cf rated ther=al power.

Description of Occurrence:

During a review of Surveillance Procedure 5.2.2.1.10, it was ob-served that the procedure did not include monthly functional testing and a daily instrument check of loss of voltage relays 27/lF1, 27/lG1, 27/1FA1, 27/lGB1, 27/ETl and 27/ET2.

Designation of Apparent Cause of Occurrence:

Incenplete procedure updating to include all Technical Specifi-cations.

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Mr. K. V. Seyfrit July 19, 1979 Page 2.

Analysis or Occurrence:

In April 1979, compliance with a NRC Cafety Evaluation and Staff Position concerning emergency power systems for operating reactors was achieved. Additional undervoltage relays were installed to monitor emergency bus voltages. A corresponding Technical Spec-ification change dictating increased test frequency requirements for all emergency bus relays was implemented when the cinor design change was completed. The increased functional and daily checks of the subject relays were inadvertently'omitted from Surveillance Procedures 6.2.2.1.0 and 6.2.4.1 when these procedures were revised to reflect the Technical Specification change. The subject relays had been previously functionally tested once oer refueling cycle, with another procedure, 6.3.4.3, Core Spray, RER, and Diesel Gen-erator Auto Start and Loading. Frocedure 6.3.4.3 was performed satisfactorily during the April 1979 outage. The additiona. e-lays, installed in April 197E, were operable and the functi~.al and daily checks for these relays were verified correct in the ap-plicable surveillance procedure.

This occurrence preranted no adverse consequences from the stand-point of public heal?h and safety.

Corrective Action:

Surveillance Procedures 6.2.2.1.10 and 6.2.4.1 have been revised to include functional tests and daily instrument checks as required by Technical Specificaticas and the required tests and daily checks have been performed on the subject relays. This occurrence has been reviewed by the station personnel involved.

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

524 307