ML19340E980

Special Rept 80-03:on 801016,during Mode 1 Power Operation, Fuse in Channel RB2 Blew,Actuating Eecs Subsystem.Caused by Failed Relay in Engineering Safeguards Cabinet 5B.Relay Was Replaced & Functionally Tested

ML19340E980
Person / Time
Site:	Crystal River
Issue date:	01/12/1981
From:	Hancock J, Poole D FLORIDA POWER CORP.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
3-011-09, CS-81-001, CS-81-1, RO-80-03, RO-80-3, TAC-43076, NUDOCS 8101160438
Download: ML19340E980 (2)

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Florida January 12, 1981 Power ca. ,o o .<n.

3-0-3-a-1 CS-81-001

1. 3-011-09 Mr. J. P. O'Reilly, Director Docket No. 50-302 U.S. Nuclear Regulatory Commission Licensee No. DPR-72 Office of Inspection & Enforcement Special Report 80-3 101 Marietta St., Suite 3100 Crystal River Unit #3 Atlanta, GA 30303 Occurrence Date:

October 16, 1980

Dear Mr. O'Reilly:

Enclosed please find Special Report 80-3 which is submitted in accordance with Technical Specification 6.9.2.

Should there be any questions, please contact us.

Very truly yours, FLORIDA POWER CORPORATION dy '

Ta' d g j J. A. Hancock Nucl_ ear Plant Manager Assistant Vice President Nuclear Operations VAH/rc Attach: (1)

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SPECIAL REPOR_T s Special Report No.: 80-3 Facility: Crystal River Unit 3 Report Date: January 12, 1981 Occurrence Date: October 16, 1980 Identification of Occurrence:

Actuation of an ECCS subsystem requiring action in accord-ance with the action statement of Technical Specification 3.5.2.

Conditions Prior to Occurrence:

Mode 1 power operation (97%).

Description of Occurrence:

At 0947 during nonnal operation channel 1 pressure module was in " test" giving a 1 of 3 condition for a routine sur-veillance test. A fuse in channel RB2 blew, giving the 2 of 3 condition required for actuation of ES channel "B".

Makeup pump 1B operated for less than a minute with suction valves closed before it was shut down. Other automatic ac-tions were manually overridden until the ES "B" actuation condition could be cleared by taking channel 1 pressure module out of the " test" mode. The transient caused ap-proximately 250 gallons of water from the borated water storage tank to be injected into the Reactor Coolant System with an attendant pressure increase from 2145 to 2185 psig.

The flowpath was through MUV-25 and MUV-26.

Designation of Apparent Cause:

The cause of this event is attributed to a failed relay (63Z30/2) in engineering safeguards cabinet 5B. .

Analysis of Occurrence:

There was no effect upon the health or safety of the general public.

Corrective Action:

The relay was replaced and functionally tested. All r,uclear-operators have been advised of the incident, the potential for damage to the makeup pump, and the required operator action.

Failure Data:

The total accumulated actuation cycles on MUV-25 is nineteen (19), and on MUV-26 is twenty (20).

/rc