ML20080E077

Telecopy Ro:On 830812,cracks Found on Welds DCS-1-7, DSRWC-1-3,DCS-1-8 & DSRWC-1-2.Cause Not Stated.Total Number of Welds to Be Inspected Increased from 53 to 79

ML20080E077
Person / Time
Site:	Browns Ferry
Issue date:	08/22/1983
From:	Coffey J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8308300714
Download: ML20080E077 (3)

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! TM FCOPY TO NRC 4

INC p's Aug. 22, 1983 I

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U. S. Nuclear Regulatory Commission 02$

Region II 101 Marietta Street, NW 4 O .' g l Suite 3100 l Atlanta, Georgia 30303

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BFRO-50-259/83049R8 l l

Reported under Technical Specification 6.7.2.a.(3)

Telecony Date 8/22/83 .Ilme. 1100 Date of Occurrence: 8/12/83 Time of occurrence: 1400 Unit 1 Technical Specification Involved: 3.6.G Conditions Prior to Occurrence Unit 1 in refueling outage Unit 2 at 3139 MWt Unit 3 at 3081 MWt Identification and Descriotion of Occurrence Weld DCS-1-7 (core spray) has an intermittent indication on the pipe side )

of the weld that is 360-degrees in length and approximately 41% through {

wall depth. This is a 12-inch, 304 stainless steel, schedule 80 pipe. The i 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).

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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.

8308300714 830822 i PDR ADOCK 05000259 OFF4Cl AL C0py l S PDR '

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TRLRCOPY TO NRC l Aug. 22, 1983 Sgrrective Action I

j Because of the additional weld cracks discovered the total number of welds l to be inspected has been increased from from 53 to 79 (see attachment for the number of welds per system and the inspection status). This includes '

all stainless steel welds greater than 1" diameter in all safety-related systems. These 79 welds are composed of Class 1 and 2 stainless steel and i

dissimiliar metal (carbon steel to stainless steel) circumferential butt {

welds that fall within the scope of Section XI. This will consist of:

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. 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.

Uodate Item To date the attached are our inspection results. (Five (5) welds in HPCI have been deleted, all these were carbon steel welds).

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.A.CoffMy Acting Power Plant Superintendent Browns Ferry Nuclear Plant l

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