05000296/LER-1980-029-03, /03L-0:on 800802,Surveillance Procedure 2.1 Performed W/Computer Valve Improperly Set Resulting in Use of Previous Day Values for Max Average Planar Linear Heat Generation Rate.Caused by Personnel Error

/03L-0:on 800802,Surveillance Procedure 2.1 Performed W/Computer Valve Improperly Set Resulting in Use of Previous Day Values for Max Average Planar Linear Heat Generation Rate.Caused by Personnel Error

ML19331E212
Person / Time
Site:	Browns Ferry
Issue date:	09/04/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19331E210	List: 05000296/LER-1980-029, Forwards LER 80-029/03L-0 05000296/LER-1980-029-03, /03L-0:on 800802,Surveillance Procedure 2.1 Performed W/Computer Valve Improperly Set Resulting in Use of Previous Day Values for Max Average Planar Linear Heat Generation Rate.Caused by Personnel Error
References
LER-80-029-03L-02, LER-80-29-3L-2, NUDOCS 8009090328
Download: ML19331E212 (2)

LER-1980-029, /03L-0:on 800802,Surveillance Procedure 2.1 Performed W/Computer Valve Improperly Set Resulting in Use of Previous Day Values for Max Average Planar Linear Heat Generation Rate.Caused by Personnel Error

Event date:
Report date:
2961980029R03 - NRC Website

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'O I: VENT DESCRIPTION AND PRCBA8tE CONSEOUENCES h 10 6 :1 l During preconditioning, Surveillance Instruction 2.1 was performed with the computer g l terninal value improperly set.

This resulted in computer using previous day's value Q W jfor its MALPHCR limits. The previous day's value was more limiting than the present I

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Surveillance Instruction gj l 2.1 has been revised to require STA signoff for complete and valid PI and OD6-4.

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Tennessee Valley Authority Form BF-17 Brownr. Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION BFRO 296 /_ 8029 Technical Specification Involved 3.5.I Reported Under Technical Specification 6.7.2.b(3)

Date of Occurrence 8/2/80 Time of Occurrence 1426 Unit 3

!_dentification and Description of' Occurrence:

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During performance of SI 2.1, the value wheel was not set at 0 on process computer terminal as specified by SI; when OD6-4 was demanded for MAPLHGR calculation the wrong value was computed. A lower limit was used in computer carried over from previous day, thus, thermal limits were not exceeded.

_Cor.ditions ~ Prior to Occurrence:

Unit 1 0 98%

Unit 2 @ 61%

Unit 3 0 77%

Action specified in the Technical Specification Surveillance Requirements a:".

dua to inoperable equipment.

Describe.

NA Apparent Cause of Occurrence:

Personnel f ailed to set value wheel to 0 for OD 6-4.

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 he,alth or safety of the public.

Corrective Action

ST Z 1 nas oeen Esvised to include a signoff by the STA verifying that the attached PI and OD 6-4 are complete and valid.

F_aqure Data:

None

• Retention :

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision:

_Go