05000327/LER-1980-016-03, /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary

/03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary

ML19309C867
Person / Time
Site:	Sequoyah
Issue date:	04/03/1980
From:	Record D TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19309C865	List: 05000327/LER-1980-016, Forwards LER 80-016/03L-0 05000327/LER-1980-016-03, /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary
References
LER-80-016-03L, LER-80-16-3L, NUDOCS 8004090336
Download: ML19309C867 (2)

LER-1980-016, /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary

Event date:
Report date:
3271980016R03 - NRC Website

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".-"-t At the completion of fuel loading but with core alterations still Dij L__ underway, upper internals were installed and RCCA drag testing was p.. r L.. performed; SI-65 (which fulfills LCO 3.9.2 and 3.9.5) was not... _ _ _ _

f_~h } L._ performed._,LCO 3. 9.2 and 3. 9.5 were not fulfilled from the evening (g.3 y shift of 3/5/80 until the day shift of 3/7/80. There was no danger to the health and safety of the public. Previous occurrences - none.

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n, Lra i Licensed operators were instructed to perform S1-65 during Core FTjL Alterations,.

Previously, they misinterpreted,the Tech. Specs. and This was

{~E] L_-.though,t SI-65 was applicable only during fuel movement.

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6 Tann2e ss Valley Authority Sequoyah Nuclear Plant LER SUPPLEPENTAL INFORMATION SQRO-50-327/8016 Technical Specifications Involved 3.9.2 and 3.9.5 Reported Under Technical Specification 6.9.1.13.c Date of Occurrence: 3/5/80 Evening Shift until 3/7/80 Day Shift - Unit 1 Identification and Description of Occurrence:

Operations personnel, in reviewing Technical Specifications, determined the plant had not performed SI-65 (which fulfills 3.9.2 and 3.9.5) during a

Core Alterations.

Conditions Prior to Occurrence:

Unit 1 in Mode 6 following initial core loading. Upper internals installed and RCCA drag testing in progress.

Action specified in the Technical Specification Surveillance Requirements met due to inoperable equiptent. Describe.

N/A Apparent Cause of Occurrence:

l Misinterpretation of Technical Specification requirements.

l Analysis of Occurrence:

There was no hazard to the public health or safety.

Corrective Action

SI-65, which satisfies Surveillance Requirements 4.9.2.a and 4.9.5, was immediately initiated.

Failure Data:

N/A i

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