05000327/LER-1980-114-03, /03L-0:on 800703,several Discrepancies Found During Support & Hanger Insp Between as-built & as-analyzed Configuration.Cause Not Stated.Deviations Which Could Cause Pipe Failure Were Modified

/03L-0:on 800703,several Discrepancies Found During Support & Hanger Insp Between as-built & as-analyzed Configuration.Cause Not Stated.Deviations Which Could Cause Pipe Failure Were Modified

ML19330C764
Person / Time
Site:	Sequoyah
Issue date:	08/04/1980
From:	Swearingen J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19330C761	List: 05000327/LER-1980-114, Forwards LER 80-114/03L-0 05000327/LER-1980-114-03, /03L-0:on 800703,several Discrepancies Found During Support & Hanger Insp Between as-built & as-analyzed Configuration.Cause Not Stated.Deviations Which Could Cause Pipe Failure Were Modified
References
LER-80-114-03L, LER-80-114-3L, NUDOCS 8008110440
Download: ML19330C764 (2)

LER-1980-114, /03L-0:on 800703,several Discrepancies Found During Support & Hanger Insp Between as-built & as-analyzed Configuration.Cause Not Stated.Deviations Which Could Cause Pipe Failure Were Modified

Event date:
Report date:
3271980114R03 - NRC Website

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e-Tennessee Valley Authority Sequoyah Nuclear Plant LER SUPPLEMENTAL INFORMATION SQRO-50-327/80114 Technical Specification Involved:

6.9.1.13.C Reported Under Technical Specification 6.9.1.13.C Date of Occurrence:

7/3/80 Time of Occurrence: 0830 EDT Unit 1 Identifi ation and Description of Occurrence During support and hanger inspection in accordance with NRC Confirmation of Action Letter, the following supports were found to be improperly installed:

1-AFDH-6, 1-FPCH-526, 1-UHIH-31, 1-CVCH-458, 1-CVCH-460, 1-CVCH-461, 1-CCH-45, 1-AFDH-345, 1-RHRH-456, 1-AFDH-355, 1-AFDH-296, 1-RHRH-460, 1-CVCH-542, 1-AFDH-322, 1-SIH-77, 1-SGBH-80, 1-UHIH-91, 1-UHIH-115, 1-CVCH-145, 1-CVCH-84, and 1-SGBH-262.

Preliminary analysis from the Division of Engineering Design showed that these supports could cause a failure in the piping during a seismic event.

Conditions Prior to Occurrence Reactor was in mode 3, 4, or 5.

Action Specified in the Technical Specification Surveillance Requirements Met Due to Inoperable Ecuipment N/A.

Apparent Cause of Occurrance Improper design, installation,. or modification of various supports.

Analysis of Occurrence Supports could cause failure of piping during a seismic event. See response l

i to Confirmation of Action Letter for details on each individual support.

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Corrective Action

l Supports were modified or reworked as required.

Failure Data N/A.

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