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

NHs, PURM 366 U. S. NUCLE AR REGULATORY COMMISSION (7 77)

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LICENSEE EVENT REPORT (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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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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Breawns Ferry fluelear Plant

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LER SUPPLDENTAL INFOILMATION BFRO 259 / 7917 Technical Specification Involved Table 3.2.B

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Reported Under Technical Specification 6. 7. 2.b (1)

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

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Identification and Description of Occurrenle:

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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.

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CondP uns Prior 'o Oecarren._ -

Normal Operation.

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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

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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.

F.ulure Data: b'

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

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• Revision: \f /Q/

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