ML18024B194

Forwards LER 79-021/01T-0

ML18024B194
Person / Time
Site:	Browns Ferry
Issue date:	12/21/1979
From:	Calhoun J TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024B195	List: ML18024B194 ML18024B196
References
NUDOCS 7912280503
Download: ML18024B194 (4)

Text

ENNESSEE VALLEY AUTHOR Y CHATTANOOGA. TENNESSEE ST401 716 Edney Building

'ecember 21, 1979 Mr. James . O'Reilly, Director U.S. Hucl egul tory Commission Office of Inspecti n and Enforcement Region IX 101 Marietta St et, Suite 3100 Atlanta, Georgia 30303 Dear Mr OtReilly I

TENNESSEE VALLEY AUTHORITY - BROMNS PERRY NUCLEAR PLANT UNIT 3 - DOCKET HO. 50-296 -

PACILIXY OPERATING LICENSE DPB;68 REPORTABLE OCCURMrNCE REPORT BPRO-50-296/7921 /

The enclosed report provides details concerning the differentia1 pressure between the dryvell and pressure suppression chamber which could not be maintained at greater than 1.3 psig trith unit 3 at 200 Kfe following unit return to service follo1rlng refueling outage. This report iS submitted in accordance with Brogans Perry unit 3 Technical Specification 6.7.2.a.3.

Very'ruly yours, TENNESSEE VALLEY AUTHORITY J. R. Calhoun Director of Nuclear Power Enclosure (3) cc (Enclosure):

Director (3) p Office of Management Infoxmation and Program Control U.S. Nuclear Regulatory Commissi n washington, DC 20555 Mrectox (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission llashington, DC 20555 R. P. Sullivan, NRC Inspector, Brogans Perry

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TENNESSEE VAL.LEY AUTHGR/TY CHATTANOOGA. TENNESSEE 37AQs .

716 Edney Building December 21, 1979 Hr. James . O'Reilly, Director U.S. Nucle egul tory Commission Office of Inspecti n and Enforcement Region IX 101 Marietta St et, Suite 3100 Atlanta, Georgia 30303

Dear 1fr. O'Reilly:

TEN1KSSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 3 DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR-68 - REPORTABLE OCCURRIBiCE REPORT BFRO-50-296/7921 The enclosed report provides details concerning the differential pressure between the drywell and pressure suppression chamber which could not be maintained at greater than 1.3 psig with unit 3 at 200 Mfe following unit return to service following refueling outage. This report. is submitted in accordance with Browns Ferry unit 3 Technical Specification 6.7.2.a.3.

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

Director (3)

Office of i~fanagement Information and Program Control U.S. Nuclear Regulatory Commissi n Washington, DC 20555 Director (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 R. F. Sullivan, NRC Inspector, Browns Ferry QQbk S

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