05000219/LER-1979-032-03, /03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended

/03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended

ML19259D391
Person / Time
Site:	Oyster Creek
Issue date:	10/10/1979
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19259D385	List: 05000219/LER-1979-032, Forwards LER 79-032/03L-0 05000219/LER-1979-032-03, /03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended
References
LER-79-032-03L, LER-79-32-3L, NUDOCS 7910180419
Download: ML19259D391 (3)

LER-1979-032, /03L-0:on 790914,leaks Discovered in Both Containment Spray Sys.Caused by Corrosion Accelerated by Galvanic Action.Matl Change in Nipple Recommended

Event date:
Report date:
2191979032R03 - NRC Website

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e EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O

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Durinq normal operation, a worker discovered a leak in the area of the I

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1 (1-3) ' containment spray heat exchanger.

Investigation reveased that a 3/4" l

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Additionally, slight leaks were discovered at' l

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the point where the AP transmitter instrument lines tap off the ESV l

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outlet pipe on the (1-1) and (1-4) heat exchangers.

Safety significance

j is considered minimal since the exchangers were not inoperable.

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nipples on the (1-1), (1-2) and (1-4) exchangers were replaced.

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1 Jersey Central Power & Light Company M

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(201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-32/3L-0 Report Date October 10, 1979 Occurrence Date September 14, 1979 Identification of Occurrence During the normal working da-it was observed that both containment spray systems had developed small fpe leaks.

This event is considered to be a reportable occurrence as deiined in the Technical Specifications, paragraph 6.9.2.b.2.

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

Power:

Reactor,1889.8 MWt Generator, 638 MWe 6

Flow:

Feedwater, 7 07 x 10 lb/hr 4

Recirculation, 15.2 x 10 gpm 4

Stack Gas:

3.85 x 10 pci/sec Description of Occurrence On Friday, September 14, 1979, at approximately 11: 30 a.m., a worker in the area of the (1-3) containment spray heat exchanger noticed water leaking.

An investigation revealed that a 3/4" carbon steel threaded nipple connected between the water box and the relief valve on the service water side was leaking.

Additionally, a slight leak was noticed at the point wnere the AP transmitter instrument line taps off the (1-1) containment spray heat exchanger emergency service water outlet pipe.

At approximately 2:30 p.m., there was a similar leak discovered on the (1-4) containment spray heat exchanger at the point where the AP transmitter instrument line taps off the ESV outlet pipe.

7 r1 11 a s Jersey Certral Power & Light Company is a Member of the General Pubhc Utihties System

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Reportable Occurrence No. 50-219/79-32/3L-0 Page 2 October 10, 1979 Apparent Cause of Occurrence All three of the leaks were caused by corrosion accelerated by galvanic action between 90/10 CuNi and SA106 Grade B carbon steel.

Analysis of Occurrence The containment spray cooling system consists of two independent cooling loops, each capable of removing fission product decay heat from the primary containment.

The safety significance of this eve.1t is to be considered minimal since the containment spray systems were not inoperable.

The leaks discovered would not prevent the equipment from performing its design function.

Corrective Action

Since this was not the first time this type of incident has occurred, analysis from a previous nipple failure resulted with a recommendation to change material selection for replacement nipples to 90/10 CuNi or stainless steel.

In addition to repairing the three leaks with stainless steel nipples, the relief valve nipples on (1-1), (1-2), and (1-4) containment spray heat exchangers were changed on September 14, 1979, to stainless steel as a preventive measure.

The AP transmitter instrument line nipples on (1-2) and (1-3) containment spray heat exchangers have been changed to stainles.s steel with approval from Generation Engineering.

Also, an engineering request has been submitted to examine all lines connected to the containment spray heat exchangers to study material compatibility and make appropriate recommendations for a permanent solution.

Failure Data

Similar Events

RO No. 50-219/79-04/3L-0 R0 No. 50-219/79-22/3L-O j i i i