ML20080D572
| ML20080D572 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/18/1983 |
| From: | Coffey J TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8308300504 | |
| Download: ML20080D572 (3) | |
Text
m TELECOPY TO NRC 4
p.g Aug. 18, 1983 h/i 9
' O/y/,
U. S. Nuclear Regulatory Commission 0 28 4 O.* g g Region II 101 Marietta Street, NW Suite 3100 Atlanta, Georgia 30303 BFRO-50-259/83049R6 Reported under Technical Specification 6.7 2.a.(3)
Telecony Date 8/18/83 Time 1500 Date of Occurrence: 8/12/83 Time of occurrence:
1400 Unit 1 Technical Specification Involved:
3.6.0 Conditions Prior to Occurrence Unit 1 in refueling outage Unit 2 at 3139 N t Unit 3 at 3081 W t Identification and Descriotion of Occurrence Weld DCS-1-7 (core spray) has an intermittent indication on the pipe side of the veld that is 360-degrees in length and approximately 41% through wall depth. This is a 12-inch, 304 stainless steel, schedule 80 pipe.
The cracking is between the manual isolation valve and the testable check valve (inboard containment isolation valve).
Weld DSRWC-1-3 (reactor water cleanup) has two indications that are approx-imately 5" long 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%. This is a 6-inch, 304 stainless steel, schedule 304 pipe. The cracking is between the inboard and outboard containment isolation valves.
Weld DCS-1-8 (core spray) has two indications that are approximately 9" long between 12:30 and 3:30 and 3" long between 9:30 and 10:30 with a through-wall depth of approximately 30%. This is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is on the reactor vessel side of the pipe-to-valve weld on valve HCV-75-27 (manual isolation valve).
Weld DSRWC-1-2 (reactor water cleanup) has a indication that is approximately 3" long between 12:00 and 1:00 with a through-wall depth of greater than 50%. This is a 6-inch, 304 stainless steel, schedule 80 pipe.
The cracking is between the inboard and outboard containment isolation valves.
bob PDR ADOCK 05000259 0991C 8308300504 830818 S
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7 TFLFCOPY TO NRC Aug. 18, 1983 Corrective Action Because of the additional weld cracks discovered, an additional 29 welds will be inspected. This will increase the total number of welds to be inspected from 53 to 82 (see attachment for the number of welds per system and the inspection statu ?).
This includes all stainless steel welds greater than 1" diameter in all safety-related systems. These 82 welds are composed of Class 1 and 2 stainless steel and dissimiliar metal (carbon steel to stainless steel) circumferential butt welds that fall within the scope of Section XI.
This will consist of:
Class 1, stainless steel welds on the CS System, RWCU System and on the RHR head spray line.
Class 1 and 2, dissimiliar metal (carbon steel to stainless steel) welds.
Class 2, stainless steel portion of the HPCI System, CS System and RHR discharge piping.
UDdate Item To date the attached are our inspection results.
[. f, C#/
.A.CodNy Acting Power Plant Superintendent Browns Ferry Nuclear Plant i
l
i o.
ATTACHMENT - BFR0 50-259/89049R6
. q Total Inspection Inspection Inspection Welds with Under Reauired Comolete Satisfactory Cracks Evaluation HPCI 5
0 0
0 0
Core Spray 34 27 23 2
2 WCU 14 6
4 2
0 RHR (Class 1) 1 0
0 0
0 RHR (Head Spray) 27 15 15 0
0 RER (Discharge) 2 0
0 0
0 CRD 1
0 0
0 0
TOTAL 84 48 42 4
2 SATISFACTORY Core ~ Spray DCS 1-6, 9, 14, 15,18, 16, 17, 5, 4 DSCS 1-4, 5, 6, 8, 9, 10, 11, 12, 13, 3, 1, 2, 7, 13 RHR (Head Spray)
DHS 1-2, 3 DSHS 1-1A, 3,-4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14
- WCU DW C 1-4 DS WC 1-7, 4 TWC 1-1 l
UNDER EVALUATION l
Core Spray DCS 1-1A, 2 l
ESTIMATED COMPLETION DATE August 25, 1983 i
This is an update of the event first reported previously on 8/11/83, and includes all the l
results through 1330 on 8/18/83 This information was provided verbally to Floyd Cantrell
. cn 8/13/83
._.