ML20076F335

Telecopy RO 50-259/83-49:on 830811,pipe Weld Cracking Indications Revealed by Addl Ultrasonic Insps.Possibly Caused by Corrosion.Addl Welds Inspected.Insp Repts to Be Submitted Periodically

ML20076F335
Person / Time
Site:	Browns Ferry
Issue date:	08/23/1983
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RO-50-259-83-49, NUDOCS 8308260015
Download: ML20076F335 (2)

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~ *iennessee Valley Authority Form BF 16.

Browns Ferry Nuclear Plant B F 15.' 2

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LER TELEPHONE AND TRBECOPh FOBg'g',' --

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)U d U. S. Nuclear Regulatory Commission NUC PR ARMS, .1570! CST 2-C.

Region II -

101 Marietta Street, NW - Suite- 3100 83 ma A9 F Belvin, MPB-MS (If.

loactive material released); d (;

[?I' Atlanta, Georgia ~ 30303 T. G. Campbell,1760 CST 2-C: d j; T. L. Chinn , . BFNP ' -j ;

L J. F. Cox, W11B85C-K t C. W. Crawford, 670 CST 2-C .%

BF(E)RO-50-- '259 / 83049 P. Duncan, W11C127C-K . ir d S. Goldman, E12A4C-K -[i Reported under Technical Specifications 6.7.2. a(3) G . R. ' Hall, 6204 MIB-K

' Receptionist , Plt Supt Office ~l il Telecopy: Date Time . R . L. Lumpkin , Jr. , 401UBB-C ' !.

L. M. Mills, 400 CST 2-C

• Telephon; Date _8L11/83 Time G. Paulk, NRC Shift Engineer

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• F.' A. ' Szczepanski, 220 401B-C  !

Per. son Cor tacted Ross Bu chef W. C. Thomison,' BFNP .*

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Date of Occurrence 8/11/83 Time of Occurrence

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Technical Specification involved: 3.6.c  !.

Lt Conditions Prior to Occurrence: 'N O

Unit 1 - Refueling Outage Unit 2 - 3139 MWt 4}

Unit 3 - 3081 MWt Ul

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Identification and Description of Occurrence:  : [i 7

Additional ultrasonic inspections of_ piping welds (on the. reactor system pressure. , [ =

boundary headspray, core spray, and reactor water cleanup systems,) revealed ,  ;

indications of. cracking. Cracking was confirmed on two welds; one on.the core spray.. ~

d system and the other on the reactor water cleanup system. Weld DSRWC-1-3 ,

(Reactor Water Cleanup) has two indications that are approximately 5" long ~ ,j f (Continuation on next page) ' '

Apparent Cause of Occurrence:

Cracks appear to be intergranular stress corrosion cracking.  : fl

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it O'her t Related Events: jk BFR0 50-260/80040 1I:

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w f1-Corrective Action Taken or Planned:

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. Additional welds'are being inspected and details of inspection findings and' s f;l corrective actions.will be submitted periodically.  : :

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BFRO-50-259/8304 9 Identification and Description of Occurrence: (Continued)

- between 11:30 and 2:30, and 1-1/2" long between 8:30 and 9:30 with a through wall depth of greater than 80-percent. This is a 6-inch, 304 stain-less steel, schedule 80 pipe. The cracking is between the inboard and outboard automatic-isolation valves.

Weld DCS-1-7 (core spray) has an intermittent indication on the pipe side of i the weld that is 360-degrees in length and approximately 41-percent through wall depth. This is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is between the reactor vessel and the manual isolation valve.

Issuance of this prompt report confirms discussions with NRC, Region II on

! this date.

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