05000296/LER-1980-051-03, /03L-0:on 801116,redundant Drywell Hydrogen Sensor 3-H2E-76-39A Would Not Calibr to Ref Gas.Sensor Declared Inoperative.Caused by Sensor 47E226428G2 Failure.Unit Shut Down for Refueling 801123 & Sys Replaced

/03L-0:on 801116,redundant Drywell Hydrogen Sensor 3-H2E-76-39A Would Not Calibr to Ref Gas.Sensor Declared Inoperative.Caused by Sensor 47E226428G2 Failure.Unit Shut Down for Refueling 801123 & Sys Replaced

ML19345D756
Person / Time
Site:	Browns Ferry
Issue date:	12/15/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19345D750	List: 05000296/LER-1980-051, Forwards LER 80-051/03L-0 05000296/LER-1980-051-03, /03L-0:on 801116,redundant Drywell Hydrogen Sensor 3-H2E-76-39A Would Not Calibr to Ref Gas.Sensor Declared Inoperative.Caused by Sensor 47E226428G2 Failure.Unit Shut Down for Refueling 801123 & Sys Replaced
References
LER-80-051-03L-01, LER-80-51-3L-1, NUDOCS 8012160559
Download: ML19345D756 (2)

LER-1980-051, /03L-0:on 801116,redundant Drywell Hydrogen Sensor 3-H2E-76-39A Would Not Calibr to Ref Gas.Sensor Declared Inoperative.Caused by Sensor 47E226428G2 Failure.Unit Shut Down for Refueling 801123 & Sys Replaced

Event date:
Report date:
2961980051R03 - NRC Website

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Tennessee Valley Authority Fona BF-17 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLDENTAL INFORMATION BFRO 296 / 8051 Technical Specification Involved 3.7.H Reported Under Technical Specification 6.7.2.b (2)

Date of Occurrence 11/16/80_ Time of Occurrence 0820 Unit 3

Identification and Description of Occurrence:

Hydrogen sensor 3-H E-76-39A would not calibrate to the reference gas.

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Conditions' Prior to Occurrence:

f thit 1 at 96% power.

Unit 2 refueling Unit 3 at 76% power.

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

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One system was operable and reactor was shutdown within the 30 day limit established by T.S.3.7.H.3.

apparent Cause of Occurrence:

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Sensor f ailure.

Analysis of Occurrence:

There was ne damage to the plant equipment. 'Ihere was no activity release, no personnel exposure or injury and no effect on the health or safety of the public.

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Corrective Action

The. hydrogen analyzing system will be changed to a new designed system while the reactor is down.

i r-Failure Data:

296/8037, 260/8036, 259/7930, 260/796, 259/7815 and 260/7821".

• Retention:

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision:

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