ML19254F911

LER 79-025/03L-0:on 790806,10,000 Gallons of Torus Water Drained & Ability of Primary Containment Degraded.Caused by Isolation Valve Left Open After Water Samplings.Change to Sampling Procedure Submitted on Use of Valve

ML19254F911
Person / Time
Site:	Oyster Creek
Issue date:	11/13/1979
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19254F909	List: ML19254F908 ML19254F911
References
LER-79-025-03L, LER-79-25-3L, NUDOCS 7911190393
Download: ML19254F911 (3)

Text

(PLEASE PRINT oR TYPE ALL REQUIRED INFORMATION)

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1 l N iLf0EtJSEE J l 0 CODE l C l P l 1 l@l 0 l 0 LICENSE l - l 0NUMBER l 0 l 0 l 0 l0 l- l 0 l LICENSE 25 01@264l1l1l1I1l@l TYPE 30 l

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8 60 61 DOOKET NUMBER 68 69 EVENT DATE EVENT DES,CRIPTION AND PROBABLE CONSEQUENCES h O 2 l Durino normal operation, one-inch isolation valve on the torus sample O 3 l line was found in the open position. The valve, located on the suction l 0 4 l side of "C" containment spray pump, ups open for a period of seven days. l 0is ; Approximately 10,000 gallons of torus water was drained to the 1-7  ;

floor drain sump and pumped directly into the radwaste facility. During c is I i g c 7ii 'this time, the ability of primary containment to function as intended  ;

O68 I was degraded. j EC E 9

, SYSTEM CAUSE CAUSE COMP. VALVE OCLE 000E SUB000E COMP:NENT CODE SL'E 000 E SUECODE 019 l S l A l@ l A l@ l C l@ lZ lZlZj Zj Z l Z @ Z l@ lZ l@ 20 S S 10 11 12 13 18 19

_ SEQUENTI AL OCCURRENCE REFORT REVISION EVENT YEAR REPORT NO. CODE' T'.'P E N O.

LEn no O" Ol.g 17 19 l l-l 101215l l/l 10 l 3 l lL l 30 l-l 31 l0l 32 21 22 23 24 26 27 28 29 A N A O ON PLANT M MOURS SB I FOR1 8. SUPPLIE MANU ACTURER lFl@lGl@ [_Z_J@ l_ Z@ l0 l0 0 l0 l l41 Y l@ l42Y l@ lZ l@ lZ l 9 l 9 l 9 lg 33 34 3b 36 37 40 43 44 47 CAUSE DESCRIPT ON AND CORRECTIVE ACTIONS 1 Ol The valve was left open after the completion of torus water sampling. l 1 i l The valve was closed and locked in the closed position. Additionally, a 1 i 7 l threaded cap has been installed on the pipe utilized to take the sample.  ;

i a L Also, a change to the sampling procedure has been submitted which  ;

1 A l addresses the use of the subject valve. .

8 9 80 STA 5  % POWER OTHER STATUS 015 O RY DISCOVERY DESCRIPTION NA NA 1 s l E l@ l 0 l 9 l9 l@l l lA l@l l ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 6

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Jersey Central Power & Light Company N-p(

, i$cy Madison Avenue at Punch Bowl Road Mw - - *

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Morristown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence 'No.' '50-219/79-25/1T-0 Report Date .

November 13, 1979 Occurrence Dates July 30, 1979 August 6, 1979 Identification of Occurrence Violation of the Technical Specifications, paragraph 3.5. A.3, when primary containment was not fully maintained for one week by the failure to close a torus sample line isolation valve after completion of torus water sampling.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.a.6.

Conditions Prior to Occurrence The plant was operating at steady state power. The major parameters at the time of occurrence were:

Power: Generator, 640 MWe Reactor, 1918.4 MWt Flow: Recirculating, 15.2 x 10'+ gpm Feedwater 7.178 x 106 lb/hr Stack Gas: 2 79 x 100 pei/sec Description of Occurrence On August 6, 1979, at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, a one-Inch isolation val"e on the torus sample line was found in the "open" position. The valve located on the suction side of "C" containment spray pump was opened for a period of seven days. Approximately 10,000 gallons of torus water was drained to the 1-7 floor drain sump and pumped directly to the radwaste facility. g} 2@h Apparent Cause of Occurrence it is suspected that a chemical technician failed to close the isolation valve after completion of sampling the torus water.

Jersey Central Power & Lsht Company is a Member of the Genera: Pubhc Utst,es System

Reportable Occurrence No. 50-219/79-25/IT-0 .Page 2 November 13, 1979 Analysis of Occurrence The primary containment system is designed to limit off-site dose resulting from the rupture of any pipe witit hreak areas- from zero up to twice the cross sectional area of a recirculation line to well below 10 CFR 100 guideline limits. The reactor and all its systems are designed to operate safely to preclude failures which could release unacceptable amounts of fission products.

As backup, the pressure absorption containment will contain any radioactive material which might escape from the reactor. The ability of primary contain-ment to perform its intended function with the torus sample line valve in the "open" position was degraded.

Corrective Action The valve was immediately closed and locked in the closed position. Additio, ally, a threaded cap has been Installed on the pipe utilized to take the sample. A change to the torus sampling procedure has been submitted which specifically addresses the unlocking, opening, closing, and locking of the subject valve.

Failure Data Not applicable.

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