ML19320A991

Forwards LER 80-013/03L-0

ML19320A991
Person / Time
Site:	Cooper
Issue date:	06/13/1980
From:	Lessor L NEBRASKA PUBLIC POWER DISTRICT
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19320A992	List: ML19320A991 ML19320A994
References
CNSS800363, NUDOCS 8007090005
Download: ML19320A991 (2)

Text

.-

, . I I COOPER NUCLEAR 5 TAT 1oN *

- P.o. BoM 98 BRoWNVILLE NEBRASKA 68321

Nebraska Public Power Distn.c t aLEmoNE em 82s nu CNSS800363 June 13, 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 6.7.2.B.3 of the Technical Specifications for Cooper Nuclear Station and discusses a reportable occurrence that was discovered on May 16, 1980. A licensee event report form is also enclosed.

Report No.: 50-298-80-13 Report Date: June 13, 1980 Occurrence Date: May 16, 1980 Facility: Cooper Nuclear Station Brownville, Nebraska 68321 Identification of Occurrence:

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

Conditions Prior to Occurrence:

Reactor shutdown for scheduled refueling.

Description of Occurrence:

During performance of Surveillance Procedure 6.3.10.7, Primary Containment Isolation Valve Timing, RHR-M0-57, the RHR discharge to radwaste inboard isolation throttle, failed to close in the time specified in the Technical Specifications.  !

Designation of Apparent Cause of Occurrence: 1 Machinery history records were reviewed and on February 7,1980, l the limit switches for the subject valve were adjusted increasing j the valve travel. The valve closure stroke time was not checked at -

that time to assure the Technical Specification requirements were

-met.

S 8007000C o g. b iP

b t

Mr. K. V. Seyfrit June 13, 1980 Page 2.

Analysis of Occurrence:

RHR-MO-57 is the inboard isolation valve on the RHR discharge to radwaste. There is a redundant isolation valve that was timed and found to be in a satisfactory range. It should be noted that these valves are normally closed valves. In the event an isolation signal was received, the valve would have closed, however, the time necessary to close was approximately 5 seconds longer than the Technical Specification limit and would not have greatly affected the availability of the RHR system.

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

Corrective Action:

Personnel involved have been reinstructed that upon completion of maintenance on valves that have limits placed on opening and/or closure time, that this value be confirmed prior to placing the valve into service. The stem travel on RHR-MO-57 has been adjusted so that the valve meets the specification.

Sincerely, N

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

l 1