PNO-III-87-056A, on 870413,operators Manually Scrammed Unit from 3% Power Due to Steam Leak from Drain Line in Condenser Bay.Caused by Weld Failure During Excessive Turbulence.Parts of Line Replaced,Rerouted & Secured W/Addl Supports

PNO-III-87-056A:on 870413,operators Manually Scrammed Unit from 3% Power Due to Steam Leak from Drain Line in Condenser Bay.Caused by Weld Failure During Excessive Turbulence.Parts of Line Replaced,Rerouted & Secured W/Addl Supports

ML20215H782
Person / Time
Site:	Perry
Issue date:	04/28/1987
From:	Knop R, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
References
PNO-III-87-056A, PNO-III-87-56A, NUDOCS 8705070047
Download: ML20215H782 (1)

PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-III-87-56A Date April 28,1987bg8 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without v:rification or evaluation, and is basically all that is known by the Region III staff on this date.

Facility: Cleveland Electric Illuminating Licensee Emergency Classification:

Company Notification of an Unusual Event Perry Alert Perry, OH 44081 Site Area Emergency General Emergency X Not Applicable

Subject:

STEAM LEAK FROM STEAM DRAIN LINE----(UPDATE)

On April 13, 1987, reactor operators manually scrammed the unit from 3 percent power because of a steam leak from a drain line in the condenser bay in the turbine building. The leak was from a 3-inch drain line which was severed from a 24-inch drain line manifold when a weld failed. The weld failure was caused by movement of the 24-inch drain line manifold due to excessive turbulence and the restriction of thermal growth of the 3" drain line. The licensee replaced portions of the 24-inch manifold with heavier steel and installed a throttling valve in the 3-inch line that had previously failed. In addition the 3-inch line was increased to a 6-inch line at the juncture to the 24-inch manifold. A 6-inch line was rerouted to the manifold to reduce stresses and additional supports were added to the manifold and piping for restraint purposes.

.The plant resumed operation on April 26, 1987. Preliminary indications are that the fix was successful in reducing vibrations to the manifold. The plant successfully passed the R: actor Core Isolation Cooling System (RCIC) test and is continuing into its Power Ascension program.

A Regional based inspector will be reviewing the drain line modifications this week.

The State of Ohio will be notified.

This information is current as of 10:00 a.m., April 29, 1987.

RFW CONTACT: R. C. Knop R. F. Warnick FTS 388-5547 FTS 388-5575 DISTRIBUTION:

H. St. EDO NRR E/W Willste Mail: ADM:DMB Chairman Zech PA IE NMSS 00T:Trans only  :

Comm. Roberts ELD OIA RES l Comm. Asselstine AE00 NRC Ops Ctr /.M i Comm. Bernthal /

Comm. Carr Regional Offices ACRS SP/J: 3g

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CA RIII Resident Office POR Licensee: /.7,.L (Corp. Office - Reactor Lic. Only)

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