ML20076F335
| 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) | |
Text
g m.
[
-((@lj
- iennessee Valley Authority Form BF 16.
~
Browns Ferry Nuclear Plant B F 15.' 2 US N R r rm m n,
W l 2.7 jg p
- g%
LER TELEPHONE AND TRBECOPh FOBg'g','
ifD
)U d
[?I' U. S. Nuclear Regulatory Commission NUC PR ARMS,.1570! CST 2-C.
F Belvin, MPB-MS (If.
Region II 83 ma A9 loactive material released); d (;
101 Marietta Street, NW - Suite-3100 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 il
' Receptionist, Plt Supt Office
~l Telecopy:
Date Time
. R. L. Lumpkin, Jr., 401UBB-C '
L. M. Mills, 400 CST 2-C G. Paulk, NRC
[
Telephon; Date _8L11/83 Time Shift Engineer F.' A. ' Szczepanski, 220 401B-C
{f '
Per. son Cor tacted Ross Bu chef W. C. Thomison,' BFNP Date of Occurrence 8/11/83 Time of Occurrence Unit 1
['
-c.
q.
~
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
-J t
1 f,
4 [i Identification and Description of Occurrence:
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..
system and the other on the reactor water cleanup system. Weld DSRWC-1-3
~
d (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
'I
- it O'her Related Events:
jk t
1I:
BFR0 50-260/80040
.i; 259/83023 a<.
wf 1-Corrective Action Taken or Planned:
j
~
. Additional welds'are being inspected and details of inspection findings and' f;l s
corrective actions.will be submitted periodically.
t i:
s
- Retention: ' Period'- Lifetime; Responsibility - Document Contro I ervisor = N il OidbALCopy P
>;g ix.wp
_..1 8308260015 830823 gM, yg !
- Revisio,n.
PDR ADOCK 05000259 2.
jj $ $;.1}
(y'hy,I S
'Y,
AHWM%m %%fjt%g
~
4 A_
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.
1
-~