05000259/LER-1980-016, Forwards LER 80-016/01T-0

Forwards LER 80-016/01T-0

ML19294B153
Person / Time
Site:	Browns Ferry
Issue date:	02/22/1980
From:	Calhoun J TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19294B154	List: 05000259/LER-1980-016, Forwards LER 80-016/01T-0 05000259/LER-1980-016-01, /01T-0:on 800210,w/Unit 1 in Scheduled Refueling Outage & Units 2 & 3 at Steady Power,Div of Engineering Design Advised Degradation of Primary Sys Integrity Could Result from Line Break Followed by Sys Drainage
References
NUDOCS 8002270356
Download: ML19294B153 (2)

LER-1980-016, Forwards LER 80-016/01T-0

Event date:
Report date:
2591980016R00 - NRC Website

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~1 716 Edney Building FEB 2 21980 Mr. James P. O'Reilly, Director U.S. huclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 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-50-259/8016 The enclosed report provides details concerning water impingement on reactor building closed cooling water piping in the prinary containment during a postulated recirculation system line break, valve failure, and subsequent reactor building closed cooling water system drainage. The enclosed report is submitted in accordance with Browns Ferry unit 1 Technical Specification 6.7.2.A.9.

Very truly yours, TENNESSEE VALLEY AUTHORITY J. R. Calhoun Director of Nuclear Powe; Enclosure (3) cc (Enclosure):

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Comission

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Washington, DC 20555 l

Director (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission Washington, DC 20555 Mr. Bill Lavallee Nuclear Safety Analysis Center Palo Alto, California 94303 1

l Mr. R. F. Sullivan, NRC Inspector, Browns Ferry c'02270 g m:m

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o EVENT DESCRIPTION A L, PRG9 >\\8 C NS O ENCES

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[ With unit 1 in a scheduled refueling outage, unit 2 at steady state power of 1087 Wg o

g ; and unit 3 at 1100 We steady state power, notification was received from TVA's Divis ;

': that, should a Recirculation System line break be followed ;

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by a Reactor Building closed cooling water line break, valve failure, and system draing g

g age, degradation of primary system integrity could result. There was no danger to the; j y g, qq health and safety of the public. No previous occurrences. Redundancy dces not apply.l l

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o g,,, y g valuation determined two areas where postulated circumferential break locations E

in the recirculation system have potential for RBCCW line impingement.

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, y judgment that RBCCW integrity would not be lost due to impingement and no immediate corrective actions are required.

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