ML18283B414

LER 1978-002-00 for Browns Ferry Nuclear Plant, Unit 3, Bendix Connectors of Type Used Inside Primary Containment Have Failed a Post-Aging Environmental Test at Wyle Laboratory Testing Facility

ML18283B414
Person / Time
Site:	Browns Ferry
Issue date:	02/28/1978
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
LER 1978-002-00
Download: ML18283B414 (6)

Text

a uN/~t/~e' REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC: ORIELLY J P ORG: FOX H S DOCDATE: 02/28/78 NRC TN VALLEY AUTH DATE RCVD: 03/03/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT (RO 50-296/78-002> ON 02/14/78 CONCERNING

, BENDIX CONNECTORS OF THE TYPE USED INSIDE THE PRIMARY CONTAINMENT HAVE FAILED A POST-AGING ENVIRON TEST AT WYLE LAB TESTING FACILITY.

1 PLANT NAME:BROWNS FERRY UNIT 3 REVIEWER INlTIAL: X JM DISTRIBUTOR INITIAL:

+www++++w++++++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)

'OR ACTION: BR CHIE FAR+4W/ NCL INTERNAL: EG LE++W/ENCL NRC PDR++W/ENCL I 5 E++W/2 MIPC++W/3 ENCL SCHROEDER/IPPOLI T044 W/ENCL HOUSTON++W/ENCL NOVAK/CHECK4+W/ENCL GR IMES++W/ENCL KNIGHT++@/ENCL BUTLER44W/ENCL HANAUER++W/ENCL TEDESCO~+W/ENCL EISENHUT44 W/ENCL BAER44W/ENCL SHAO++W/ENCL VOLLMER/BUNCH++W/ENCL KREGER/J. COLLINS+4W/ENCL ROSA++W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR S ATHENS AL44W/ENCL T I C++W/ENCL NSIC+4W/ENCL ACRS CAT B++W/16 ENCL DISTRIBUTlON: LTR 45 ENCL 45 CONTROL NBR: 780660019 S I ZE: 1P+1P THE END

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i TENNESSEE VALLEY AUTHORlT GHATTANooGA. T(@fkkjkggkfb'r

($]AlA'jTgtt Pj(jl [) (()Py FFB SS >978 Nr. James . O'Railly, Diroctox U.S ~ Nucla r Regulatory Comatission Office of nsQaction and Enforcamant Region II ": g~>.z>roy 230 Peacht aa Street, NM.>> Suite 1217

,Atlanta, orgia 30303 Dear Nr. O'Reilly!

TENNESSEE VALLEY AUTHORITY - BROGANS FERRY NUCLEAR PLANT'UNIT'3,-

DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPRAS - REPORTABLE OCCURRENCE REPORT BFRO-50-296/782 The enclosed report provides details concerning tho Bendix'connectors og tho typo uood inside tho primary containmont ehich have failed a post-aging environmental toot at ~le Laboratory tooting facility, This report is submitted in accordance with Brows Faxry unit. 3 Technical Specification 6.7.2.a.(9).

Vary truly yours, TENNESSEE PAISLEY AUTHORITY H. S. Fax.

Director of Pemr Production,,

Enclosure cc (Enclosure):

Director (3)

Office of khnagemont Information and ogram Control U.S. Nuclear 'Rogulatory Commissiod Mashington>> DC 20555 Director (40)

Offico of Inspection and Enforcement U.S. Nuclear Regulatory Commission Mashington>> DC 20555 (OT C

An Equal Opportunity Employer

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NBC FORM 366 077I "'6 LICENSEE EVENT REPORT 4

CONTROL BLOCK: ~I 6 Qi IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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LICENSEE CODE 14 LICENSE NUMBE R 25 26 LICENSE TYPE 30 57 CAT 58 CON'T 6 7 0 2 1 4 8 B 0 2 2 8 7 8 QB DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO

~02 Bend.ix connectors of the t used inside the rimar conta me h e

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~O 3 4 POSt-aging environmental test at Wyle Laboratory testin fa il been reported to NRC ' Washington Of fice . There i s no hazard to the public health or.

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'XX 9 SYSTEM CODE 10 Qll CAUSE CODE

~B 11 Q12 CAUSE SUBCODE

~B 12 Q13 X 13 COMPONENT CODE X X X X X 18 Q14 COMP.

SUBCODE

~Z 19 Q10 VALVE SUBCODE

~Z 20 Q10 SEOUENTIAL OCCURRENCE

', REPORT ~ REVISION Q17 LERIRO IIII'0117 EVENT YEAR

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~00 24 REPORT No.

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~O1 28 CODE 29 TYPE

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~31 NO.

~0 32 I,ACTION, TAKEN ACTION FUTURE EFFECT ON PLANT SHUTDOWN METHOD HOURS Q22 ATTACHMENT SUBMITTED NPRDX FORM SUB.

PRIME COMP.

SUPPLIER COMPONENT MANUFACTURER QIB ~XQ19 ~ZQ20 ~ZQ21 0 0 0 0 ~N Q23 ~NQ24 ~N Q25 B 2 0 0 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 It appears that the method of a in was the cause of the failures. A retest r ram

~has been prepared and was forwarded to NRC's Washington Office on Rebruar 24 1978.

r A final retest report and corrective action commitment will be completed and submitted to NRC by March 20, 1978. Copies of these reports will be submitted to Region II offices.

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FACILITY STATUS

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~O~fJQ29 OTHER STATUS N A

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~3O METHOD OF DISCOVERY

~CQ31 est DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 80 ACTIVITY CONTENT 6

RELEASED OF RELEASE AMOUNT OF ACTIVITY N A Q N A LOCATION OF RELEASE Q

~Z Q33 ~ZQ34 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3B 7 ~00 0 Q07 ~ZQ20 N A 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 0 ~00 0 Q40 N A 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43

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~ZQ2 9 10 N/A 80 PUBLICITY ISSUED DESCRIPTION Q ,NRC USE ONLY

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~re 9 10 N/A 68 69 44 80, 40 0

NAME OF PREPARER PHONE:

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