ML20009C170

Forwards LER 81-008/03L-0.Detailed Event Analysis Encl

ML20009C170
Person / Time
Site:	Oconee
Issue date:	06/08/1981
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009C171	List: ML20009C170 ML20009C234
References
NUDOCS 8107200343
Download: ML20009C170 (2)

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V'cr Persiorgt TELtewowg; Anta 7e4 sec.- anooucv.o. June 8, 1981 3,3..e.3

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Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Gf -~

Region II / //> 77 101 Marieti.a Street, Suite 3100 /Q' g** .

Atlanta, Georgia 30303 JL .

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__ - JUL 17'1981*b v,,,mu mxess A Re: Oconee Nuclear Station . 6~ ,

ewmot Docket No. 50-270 \ry

Dear Mr. O'Reilly:

y , cs Please find attached Reportable Occurrence Report R0-270/31-08. This report is submitted pursuant to Oconee Nuclear Station Technic:a1 Specification 6.6.2.1.b(2), which concerns operation in a degraded rode permitted by a limiting condition for operation, and describes an ticident which is con-sidered to be of no sigriificance with res;ect to its effect on the health and safety of the public.

Very truly yours, I

h jw h n r -i er William O. Parker, Jr. /

JLJ:pw Atxachment cc: Director Mr. Bill Lavallee Office of Management & Program Analysis Nuclear Safety Analysis Center U.S. Nuclear Regulatory Commission P. O. Box 10412 j

i Washington, D. C. 20555 Palo Alto, CA 94303

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4 8107200343 810608 PDR ADOCK 05000270 ..

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DUKE POWER COMPANY OCONEE UNIT 2 i

! Report Number: R0-270/81-08 i Report Date: June 8, 1981 Occurrence Date: May 8, 1981 j=

Facility: Oconee Unit 2, Seneca, South Carolina

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, IdentlEicationofOccurrence: Solenoid Valve 2FDW-316 Inoperable conditions Prior to occurrence: 100% FP Description of Occurrence: At approximately 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on M ay 8, 1981 the " Auto /

Manual Select" solenoid valve for 2FDW-316 was discovered stuck in the manual position, thus disabling automatic level control of the B "0TSG" from the Emer-

gency Feedwater (EFW) system. This constitutes operation in a degraded mode per Technical Specification 3.4.1.c, and is thus reportable pursuant to Technical Specifica'ti6h'6. 6T2.1.b(2) .

Apparent Cause of Occurrence: The cause of this incident was the stuck Valcor

{ solenoid valve.

Valcor solenoid valves have exhibited a generic design flaw which causes coil l overheating and/or valve failure. Until a suitable replacement is found con-l tinued weekly testing will be required to identify failures as they occur.

f Analysis of Occurrence: Only one steam generator is required for a safe cool down of the RC System. This requirement was met by the operability of 2FDW-315 to "0TSG A". Additionally, manual operation of 2FDW-316 was not affected and operator control of EFW to Steam Generator was available. Thus, this incident was of no significance with respect to safe operation, and the health and safety of the public were not affected.

Corrective Action: The solenoid valve was replaced and functionally verified per procedure. All functions were normal.

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