ML19253A807

LER 79-017/03L-0:on 790809,advised That Reactor Water Level Indications Can Be 29 Inches Less than Indicated by Present Procedures,Due to GE re-evaluation of post-LOCA Conditions. Has Resulted in Design Change Request Re Setpoint Change

ML19253A807
Person / Time
Site:	Browns Ferry
Issue date:	09/07/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19253A805	List: ML19253A804 ML19253A807
References
LER-79-017-03L-01, LER-79-17-3L-1, NUDOCS 7909110419
Download: ML19253A807 (2)

Text

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68 69 EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB A8LE CONSEQUENCES h o 2 l Due to G. E. reevaluation of POST-LOCA conditions, GE SIL 299, High Drywell Tempera- 1 o 3 l ture Effect on Reactor Vessel Water Level Instrumentation, the reactor water level in-1 j

o 4 l dications can be 29 inches less than indicated by present procedures. There was no o s l hazard to the public health or safety. There have been no previous occurrences. Re- l o s l dundant systems are not applicable. I I

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@ lN 42 l@ ej u CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i 1 IThe reevaluation of hi2h drywell te cerature effects on the reactor vessel water level I i 1 I instrumentation has resulted in a design chance recuest 1875 submitted reauestine a I i i setpoint change for LIS-3-58A-D. l

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• B F 15. 2 1/10/79 LER SUPPLDENTAL INFOILMATION BFRO 259 / 7917 Technical Specification Involved Table 3.2.B Reported Under Technical Specification 6. 7. 2.b (1)

Date of Occurrence 8/9/79 Time of Occurrence 3:30 p.m. Unit 1 Identification and Description of Occurrenle:

Due to GE reevaluation of POST-LOCA conditions, GE SIL 299, High Dryvell Temperature Effect on Reactor Water Level Instrumentation, the reactor water level indications can be 29 inches less than present setpoint.

CondP uns Prior 'o Oecarren._ -

Normal Operation.

Action specifieu in the Techtiical Specificatics. Surveillance Requirements met duy to inoperable equipment. Describe.

None Apparent Cause of Occurrence:

Heating of the water lega of the Reactor Water Level instruments during a LOCA condition could. result in a 29-inch error indication in the instruments.

Analysis of Occurrence:

None i

Cor: ective Action : ,

Design change request 1875, has been submitted requesting a setpoint change for LIS-3-58A-D, from >/= 378 vessel inches to >/= 407 vessel inches.

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? Reten tian : P-rmd - Life tirae , Responsibility - Administrative Supervisor

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