05000327/LER-1980-199-03, /03L-0:on 801209,high Steamflow Safeguard Program & Steam/Feedwater Flow Mismatch Bistable Found Set Above Tech Spec Values.Caused by Low Actual Differential Pressure Produced at Flow Transmitter.Setpoints Recalibr

/03L-0:on 801209,high Steamflow Safeguard Program & Steam/Feedwater Flow Mismatch Bistable Found Set Above Tech Spec Values.Caused by Low Actual Differential Pressure Produced at Flow Transmitter.Setpoints Recalibr

ML19340F008
Person / Time
Site:	Sequoyah
Issue date:	01/07/1981
From:	Mcgriff J, Wilkey A TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19340F006	List: 05000327/LER-1980-199, Forwards LER 80-199/03L-0 05000327/LER-1980-199-03, /03L-0:on 801209,high Steamflow Safeguard Program & Steam/Feedwater Flow Mismatch Bistable Found Set Above Tech Spec Values.Caused by Low Actual Differential Pressure Produced at Flow Transmitter.Setpoints Recalibr
References
LER-80-199-03L, LER-80-199-3L, NUDOCS 8101160483
Download: ML19340F008 (2)

LER-1980-199, /03L-0:on 801209,high Steamflow Safeguard Program & Steam/Feedwater Flow Mismatch Bistable Found Set Above Tech Spec Values.Caused by Low Actual Differential Pressure Produced at Flow Transmitter.Setpoints Recalibr

Event date:
Report date:
3271980199R03 - NRC Website

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ed event OATE le il REPOR T oaf g og tVENT DESCnIPTION AND PROB ABLE CONSEQUENCES h o 2 1 With unit 1 in mode 5. an evaluation of start-uo calorimetric data identified that the l l o 13 l l hich steamflow safeguard program and the steam /feedwater flow mismatch bistable set-l f7i'T71 I tin o had been less conservative than the allowable values specified bv Technical l

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JS 36 37 40 41 42 43 as 43 CAUSE CESCnlPTION AND COR AECTIVE ACTIONS h li tol l The actual differential pressure produced at the steam flow transmitter for 75% rated )

gl steam _ low was less than expected. The calorimetric data was used to recalibrate the ;

gi hich steam flow program and the steam /feedwater flow mismatch bistable setpoints. A gij,[ l final calibration of the steam flow loops will be performed using data obtained from i,,.gl 100% power testing.

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Phone (riSi 842-8261 810116 De% reparer :

Tennessee Valley Authority Sequoyah Nuclear Plant LER SUPPLEMENTAL INFORMATION SQRO-50-327/80199 Technical Specification Involved:

2.2.1 and 3.3.2.1 Reported Under Technical Specification:

6.9.1.12.a Date of Occurrence: 12/09/80 Time of Occurrence: 1430 CST Identification and Description of Occurrenee:

An evaluation of start-up calorimetric data identified that the high steamflow safeguard program and the steam /feedwater flow mismatch bistable settings had been less conservative than the allowable values specified by the Technical Specifications.

Conditions Prior to Occurrence:

Unit in mode 5 at time of discovery.

Apparent Cause of Occurrence:

The actual differential pressure produced at the flow transmitter for 75%

rated steam flow was less than expected.

Analysis of Occurrence:

The differential pressure error at the flow transmitter resulted in an actual high steam flow setpoint of 121.5% rated steam flow and a mismatch setpoint of 48.3% rated steam flow at full load. Allowable technical specification values are 111.5% and 42.5% respectively.

Corrective Action

The calorimetric data was used to recalibrate the high steam flow and steam /

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feedwater flow mismatch setpoints to compensate for the transmitter inaccuracy.

A final calibration of the steam flow loops will be performed using data to

'8 be obtained during 100% power testing.

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