05000327/LER-1980-066, Forwards LER 80-066/03L-0

Forwards LER 80-066/03L-0

ML19324A081
Person / Time
Site:	Sequoyah
Issue date:	06/13/1980
From:	Calhoun J TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19324A082	List: 05000327/LER-1980-066, Forwards LER 80-066/03L-0 05000327/LER-1980-066-03, /03L-0:on 800516,containment Isolation Valves FCV1-7,-14,-25 & -32 Determined Not Protected Against Steam Jet Resulting from Crack in Loop 1 Main Steam Riser.Caused by Design Error.Action Initiated to Install Proper Supports
References
NUDOCS 8006200451
Download: ML19324A081 (1)

LER-1980-066, Forwards LER 80-066/03L-0

Event date:
Report date:
3271980066R00 - NRC Website

text

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a TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 1750 Chestnut Street Tower II June 13, 1980 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Hr. O'Reilly:

TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 1 - DOCKET NO. 50-327 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT SQRO-50-327/8066 The enclosed report provides decails concerning the failure to provide supports and protective devices for steam generator blowdown lines to protect against a crack in the main steam riser. This report is submitted in accordance with Sequoyah unit 1 Technical Specification 6.9.1.13.b.

l Very truly yours, TEtDIESSEE VALLEY AUTHORITY J. R. Calhoun Director of Nuclear Power

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Enclosure (3) cc (Enclosure):

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Connaission Washington, DC 20555 Director (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Comunission Washington, DC 20555 Mr. Bill Lavallee i

Nuclear Safety Analysis Center Palo Alto, California 94303 Mr. W. T. Cottle, NRC Inspector, Sequoyah p%\\

88888009 5 )

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