05000219/LER-1979-022-03, /03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced

/03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced

ML19242B159
Person / Time
Site:	Oyster Creek
Issue date:	07/27/1979
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19242B153	List: 05000219/LER-1979-022, Forwards LER 79-022/03L-0 05000219/LER-1979-022-03, /03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced
References
LER-79-022-03L, LER-79-22-3L, NUDOCS 7908070589
Download: ML19242B159 (3)

LER-1979-022, /03L-0 on 790627:leak Detected on Emergency Svc Water Side of Containment Spray Heat Exchanger 1-2.Caused by Leaking Nipple Connection Between Water Box & Piping to Valve V-3-83,due to Corrosion.Nipple Replaced

Event date:
Report date:
2191979022R03 - NRC Website

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201-555-8785 Donald A. Ross

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Jersey Cantral Power & Ught Compcny Macison Avenue at Punch Bowl Road Mornstown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-22/3L-0 Report Date July 27, 1979 Occurrence Date June 27, 1979 Identification of Occurrence During emergency service water pump operability test, Containment Spray System I was found to be in a degraded mode. This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9 2.b.2.

Condi tions Prior to Occurrence The plant was operating at steady state power.

Power:

Generator, 653 MWe Reactor, 1907.3 MWt Flow:

Recirculating, 15.1 x 10" gpm Feedwater, 7.128 x 106 lb/hr 4

Stack Gas:

3.22 x 10 pCi/sec Descriction of Occurrence On Wednesday, June 27, 1979, at approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, while performing an emergency service water pump operability test after electrical maintenance, a leak was detected on the emergency service water side of containment spray heat exchanger (1-2).

A 3/4" threaded nipple connection between the waterbox and the piping leading to safety valve V-3-83 was found leaking.

Accarent Cause of Occurrence It appears that the 3/4" nipple failed due to corrosic.n.

Analysis of Occurrence Two separate primary containment spray system Icops are provided for reliability.

Each loop under the postulated accident conditions has the 541 i74 eersey Cartral P0wer ' _grt Ccmcary s 3 N'emter :t *re Gerer2: CLC. c it;.t es 3 rstam

Reportable Occurrence No. 50-219/79-22/3L-0 Page 2 July 27, 1979 heat removal capacity of removing fission product decay heat to maintain the primary containment pressure below the design pressure of 35 psig.

The safety significance of this event is considered to be minimal since Containment Spray System I was not considered to be inoperable but only degraded. Containment Spray System 11 was available for operation.

Corrective Action

The 3/4" nipple was replaced on the containment spray heat exchanger (1-2) waterbox. On March 1, 1979, a similar failure occurred on containment spray heat exchanger (1-4).

It was determined at that time that apparent cause of the leak > as a ttributed to improper installation of the 3/4" nippie at the waterbox conneetion. All four 3/4" nipples were replaced at that time (March 1979). The nipple that failed will be sent to GPU Labs f-further investigation to determine what type of corrosion caused the nipple to deteriorate. The 3/4" nipples on the waterbox,ide of the remaining containment spray heat exchangers will be replaced. Also, similar type nipples (carbon steel) on the waterbox side of 0.5e heat exchangers will be inspected.

Failure Data Similar event -- Reportable Occurrence No. 50-219/79-04/3L-0.

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