05000259/LER-1980-048-03, /03L-0:on 800602,at Steady State Power,Leak Found Between Root Valve & Main Fire Header on Sensing Line PS-26- 44 During Running of SI 4.11.A.Caused by Crack in Half Inch Schedule 40 Carbon Steel Nipple Threads Due to Corros

/03L-0:on 800602,at Steady State Power,Leak Found Between Root Valve & Main Fire Header on Sensing Line PS-26- 44 During Running of SI 4.11.A.Caused by Crack in Half Inch Schedule 40 Carbon Steel Nipple Threads Due to Corrosion

ML19320A993
Person / Time
Site:	Browns Ferry
Issue date:	07/01/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19320A990	List: 05000259/LER-1980-048, Forwards LER 80-048/03L-0 05000259/LER-1980-048-03, /03L-0:on 800602,at Steady State Power,Leak Found Between Root Valve & Main Fire Header on Sensing Line PS-26- 44 During Running of SI 4.11.A.Caused by Crack in Half Inch Schedule 40 Carbon Steel Nipple Threads Due to Corros
References
LER-80-048-03L, LER-80-48-3L, NUDOCS 8007090006
Download: ML19320A993 (2)

LER-1980-048, /03L-0:on 800602,at Steady State Power,Leak Found Between Root Valve & Main Fire Header on Sensing Line PS-26- 44 During Running of SI 4.11.A.Caused by Crack in Half Inch Schedule 40 Carbon Steel Nipple Threads Due to Corrosion

Event date:
Report date:
2591980048R03 - NRC Website

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60 61 DOLKET Nuv8tR tA Of EVENT DATE 74 75 REPORT D ATE 90 EVENT DESCRIPTION AND PROBAOLE CONSEQUENCES h l With all three tnits at steady state power, a leak was detected between the root valve.

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j There was no danger to the health or safety of the public, and no significant resulting i,,,;g g ; chain of events. Diesel fire pump was proven operable and placed in service. There gg have been no previous similar occurrences. See Technical Specification 3.ll.A.3.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS lIt was found that a crack existed n the threads of a one-half inch schedule 40

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The nipple was replaced with a stainless

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. Browns Fcrry Nucl:ar Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION 3.11.A.3 BFRO 259 / 8048 Technical Specification Involved Reported Under Technical Specification

6. 7. 2.b (2)

Date of Occurrence 6/2/80 Time of Occurrence 1625 C "" "

Unit Identification and Description of Occurrence:

While running SI 4.11.A, a leak was detected between the root valve and the main fire header at PS-26-44.

This is common to all three units.

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Conditions" Prior to Occurrence:

Unit 1 - 82% steady state power Unit 2 - 96% steady state power Unit 3 - 100% steady state power Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment.

Describe.

S1 4.11. A.1.b was run. The diesel fire pumps were put into service while A, B, and C fire pumps were isolated.

Apparent Cause of Occurrence:

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It was found that a crack had developed in the threads of a 1/2-inch schedu1e 40 carbon steel nipple due t.o corrosion.

Analysis of Occurrence:

There was no danger to the health or safety of the public, no release of activity, no damage to plant or equipment, and no resulting significant chain of events.

Corrective Action

The nipple was replaced with a stainless steel nipple.

3 Failure Data:

NA i

• Retention:

criod - Lifetime; Responsibility - Administrative Supervisor

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• Revision: -

][/

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