05000296/LER-1980-048-03, /03L-0:on 801108,throttling Valve to RHR Seal Heat Exchanger 3B on Emergency Equipment Cooling Water Sys Found Shut & Could Not Be Opened Manually,Preventing Adequate Flow.Caused by Excessive Crud Entrapped in Valve Mechanis

/03L-0:on 801108,throttling Valve to RHR Seal Heat Exchanger 3B on Emergency Equipment Cooling Water Sys Found Shut & Could Not Be Opened Manually,Preventing Adequate Flow.Caused by Excessive Crud Entrapped in Valve Mechanism

ML19345D335
Person / Time
Site:	Browns Ferry
Issue date:	12/05/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19345D326	List: 05000296/LER-1980-048, Forwards LER 80-048/03L-0 05000296/LER-1980-048-03, /03L-0:on 801108,throttling Valve to RHR Seal Heat Exchanger 3B on Emergency Equipment Cooling Water Sys Found Shut & Could Not Be Opened Manually,Preventing Adequate Flow.Caused by Excessive Crud Entrapped in Valve Mechanis
References
LER-80-048-03L-02, LER-80-48-3L-2, NUDOCS 8012120517
Download: ML19345D335 (2)

LER-1980-048, /03L-0:on 801108,throttling Valve to RHR Seal Heat Exchanger 3B on Emergency Equipment Cooling Water Sys Found Shut & Could Not Be Opened Manually,Preventing Adequate Flow.Caused by Excessive Crud Entrapped in Valve Mechanism

Event date:
Report date:
2961980048R03 - NRC Website

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to13i i valve to 3B RHR seal heat exchanger to be shut anc' co.21d not be hand operated, thus _

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Tennessee Valley Authority Form BF-17 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLFJ1 ENTAL INFORMATION BFRO 296 / 8048 Technical Specification Involved 3.5.B Reported Under Technical Specification

6. 7. 2. b (2 )

Date of Occurrence 11/8/80 Time of Occurrence 1000 Unit 3

Identification and Description'of Occurrence.

During steady state operation, a flow-test on t.b EECW system revealed a throttling valve to 3B RHR-seal heat exchanger to be shut, thus preventing adequate flow.

Conditions ' Prior to Occurrence:

Unir 1 @ 1029 We.

I;ait 2 @ refueling outage.

t'ni t 3 @ 975 We.

Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.

Began running tests required per Technical Specification 4.5.B.5.

Stopped testing when flow was reestablished to heat exchanger.

Apparent Cause of Occurrence:

Crud buildup in valve operator.

Analysis of Occurrence:

There was no damage to plant equipment. There was no activity release, no personnel exposure or injury and no danger to the health or safety of the public. Loss of cooling water to the seal heat exchar.ger has been investigated, and preliminary findings are that this has no effect on the'LPCI mode of the pump. -Further investijiation is being made as to effect on pump containment cooling mode. (Technical Speci.fication 3.5.3.5)

Corrective Action

- Maintenance freed valve establishing adequate flow.

Failure Data:

None

• Retention :

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision: p

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