05000259/LER-1981-014, Forwards LER 81-014/03L-0

Forwards LER 81-014/03L-0

ML20004B097
Person / Time
Site:	Browns Ferry
Issue date:	05/20/1981
From:	Green H TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20004B098	List: 05000259/LER-1981-014, Forwards LER 81-014/03L-0 05000259/LER-1981-014-03, /03L-0:on 810424,MSIVs 1-14,1-15,1-37,1-38,1-51 & 1-52 Exceeded Tech Specs Allowable Leak Rate During Testing.Caused by Slight Steam Erosion Due to Deterioration of Valve Seating Surfaces.Maint & Retest Performed
References
BFRO-50-259-810, NUDOCS 8105270233
Download: ML20004B097 (1)

LER-1981-014, Forwards LER 81-014/03L-0

Event date:
Report date:
2591981014R00 - NRC Website

text

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TENNESSEE VALLEY Au r1icRtTY CH ATTANOOG A, TrNN FSM F : si 1750 Chestnut Street Tower II May 20, 1981 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 3100 Atlanta, Cecrgia 30303

Dear Mr. O'Reilly:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 1 - DOCKET NO. 50-259 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT BFRO-50-259/81014 The enclosed report provides details concerning main steam isolation valves 1-14, 1-15, 1-26, 1-27, 1-37, 1-38, 1-51, and 1-52 which when tested exceeded the allowable leak rate of 11.5 standard cubic feet per hour. This report is submitted in accordance with Browns Ferry unit 1 Technical Specification 6.7.2.b(4).

Very truly yours, TENNESSEE VALLEY AUTHORITY H. J. Green Director of Nuclear Power Enclosure (3) cc (Enclosure):

Director (3) j Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Director (40)

Office of Inspection and Enforcemen ~

U.S. Nuclear Regulatory Commission Washington, DC 20555 I

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Mr. Bil'1 Lavallee

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Nuclear Safety Analysis Center l

Palo Alto, California 94303 b

Mr. R. F. Sullivan, NRC Inspector, Browns Ferry

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8105270 W l