05000260/LER-1980-029-03, /03L-0:on 800722,while Performing Surveillance Insp 4.1.A-7,reactor Low Level Switch LIS-3-203C Did Not Operate within Tech Spec Limits.Caused by Instrument Drift. Switch Inspected & Recalibr

/03L-0:on 800722,while Performing Surveillance Insp 4.1.A-7,reactor Low Level Switch LIS-3-203C Did Not Operate within Tech Spec Limits.Caused by Instrument Drift. Switch Inspected & Recalibr

ML18025B046
Person / Time
Site:	Browns Ferry
Issue date:	08/20/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18025B045	List: 05000260/LER-1980-029, Forwards LER 80-029/03L-0 05000260/LER-1980-029-03, /03L-0:on 800722,while Performing Surveillance Insp 4.1.A-7,reactor Low Level Switch LIS-3-203C Did Not Operate within Tech Spec Limits.Caused by Instrument Drift. Switch Inspected & Recalibr
References
LER-80-029-03L-01, LER-80-29-3L-1, NUDOCS 8008260537
Download: ML18025B046 (3)

LER-1980-029, /03L-0:on 800722,while Performing Surveillance Insp 4.1.A-7,reactor Low Level Switch LIS-3-203C Did Not Operate within Tech Spec Limits.Caused by Instrument Drift. Switch Inspected & Recalibr

Event date:
Report date:
2601980029R03 - NRC Website

text

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8 60 BI DOCKET NUMBER 69 EVENT DATE 74 75 AEPOAT DATE FVENT DESCRIPTION ANO PROBABLE CONSEQUENCES QIO L007j ~Durin normal o eration while erformin SI 4.1.A-7 reactor low water level switch ELIS-3-203C did not operate within T.S. Table 3.1.A limits.

There was no effect on the public health or safety.

Redundant switches in the same trip channel and

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~a redundant trip channel were operable.

Previous events:

260-804, 259-7824,

~259-741 and 259/7333.

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Barton Model 288 switch set oint had drifted 1.48 in.

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NRC USI I)I'llY

~ Tennessee Valley Authority Browns Ferry Nuclear Plant Form BF-17 BF I,"i.2 I/10/79 LER SUPPLEMENTAL INFORMATION BFRO 260 /

8029 Technical Specification Involved Reported Under Technical Specification 6.7 2.b(1)

Date of Occurrence 7/SS/SO Time of Occurrence 44 Unit Identification and Descri tion of'Occurrence:

Reactor low water level switch LIS-3-203C operated 1.48 in H20 below the T.S. limits when tested in accordance with SI 4.1;A-7 Conditions Prior to Occurrence:

PEr1$

Unit 2 at 97%

MWe Unit 3 at 98%

MWe Action specified in the Technical Specification Surveilldnce Requirements met duo~to ino arabia e4tui~mant.

Describe.

None Apparent Cause of Occurrence:

Setpoint drift 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.

Corrective'ct,ion:

The swi,tch was inspected, recalibrated and functionally tested for operability.

The switch will be replaced with an analog system in accordance with Design Change Request 1398.

Failure Data:

260/804, 259/7824, 259/741 and 259/7333.

~Retention:

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision: