ML20076J584

Telecopy Ro:On 830826,cracks Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Total Welds to Be Inspected Increased from 53 to 79.Updated Insp Results Encl

ML20076J584
Person / Time
Site:	Browns Ferry
Issue date:	08/28/1983
From:	Coffey J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8309070257
Download: ML20076J584 (3)

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U. S. Nuclear Regulatory Commission A..W. Crevasse,gs1%B-Region II .

101 Marietta Street, NW Receptionist, Pit Supt 0 L. M. Mills, 400 CST 2-C g

Suite 3100 Shift Engineer

' Atlanta, Georgia.30303 F. A. Szczepanski, 220 401B-C W. C. Thomison, BFN BFRO-50-259/83049R10 D. L. Williams, W10B85C-K Reported under Technical' Specification 6.7 2.a.(3)

Telecoor Date: 8/26/83 .I1ma: -1300 Date of Occurrence: 8/26/83 T h of Occurrana : 0800 Unit.1 Technical Specification Involved: 3.6.0 Conditions Prior to Occurrence Unit 1 in refueling outage Unit 2 at 3139 Mit Unit 3 at 3081 MWt E

Identification and Descrintion 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 appromately 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.

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TELECOPY TO NRC August 28, 1983 Corrective Action Because of the additional weld cracks discovered the total number of welds 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 dissimiliar metal (carbon steel to stainless steel) circumferential butt welds that fall within the scope of Section II. 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 CS System and RHR discharge piping.

Uodate Item To date the attached are our inspection results.

Welds DRHR-1-11, 1-2, TRHR-1-190, and RCRD-1-49 were inspected 8/23/83 and found to be okay.

Welds DCS-1-1,1-3,1-12 (core snray) could not be UT'ed due to physical configuration. Weld DHS-1-1 (head spray) was PT'ed on the'I.D. , since it could not be UT'ed due to physical configuration.

Welds DCS-1-1 A, DRWC-1-4E, DSHS-1-1, and 1-2 were inspected 8/24/83 and found to be okay.

Welds CS-1-69 (core spray) has 'two indications that are approximately 3" long between 12:00 and 1:00 and 9" long between 6:00 and 9:00 with a through-wall depth of approximately 275. THis is a 12-inch, 304 stainless stell, schedule 80 pipe. The cracking is on the elbow sido of the elbow to valve weld at valve FCV-75-53 (flow control valve).

Weld DCS-1-2 (core gpray) has an intermittent indication on the elbow side of weld that is 360 in length and approximately 35% through-wall in depth.

This is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is on the elbow side of the elbow to valve weld at valve FCV-75-25 (flow control valve).

Weld DRWC-1-1 A (reactor water cleanup) has a through-wall crack located at the 3:00 position. The crack is on the riser side of the weld which i extends in a axial direction and approximately 1/16" long. This is a 6-inch, 304 stainless forged weldolet.

I l [.'h.A. Coffpy icting Power Plant Superintendent Browns Ferry Nuclear Plant

ATTACHMENT - BFRC 50-259/8'4049R10 Total Inspection Inspection Inspection Welds with Under Reauired Comolete Satisfactory Cracks Evaluation a

Core Spray 34 34 30 4 0 e

RWCU 14 14 11 3 0 RHR (Class 1) 1 1 1 0 0 RHR (Head Spray) 27 27 27 O O RHR (Discharge) 2 2 2 0 0 CRD 1 1 1 0 0 TOTAL 79 79 72 7 0 This is an update of the event first reported previously on 8/11/83, and includes all the results through 0800 on 8/25/83 This information was provided verbally to Region II on 8/26/83 This concludes all the inspection.

o Denotes three welds on core spray and one weld on head spray and one weld on reactor water cleanup were PT'ed instead of UT'ed due to physical configuration.