ML20076F691

Telecopy Ro:On 830812,indications Found on Pipe Welds for Core Spray & Reactor Water Cleanup.Addl 29 Welds Will Be Inspected Increasing Total Number of Welds to Be Inspected to 82

ML20076F691
Person / Time
Site:	Browns Ferry
Issue date:	08/17/1983
From:	Coffey J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8308260127
Download: ML20076F691 (6)

Text

USNRC Fi~ D 3 ATt ' C '7mFCOPNTh NRC Aug. 17, 1983 83 AUG 23 A 9 : U U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW Suite 3100 Atlanta, Georgia 30303 BFRO-50-259/83049R5 Reported under Technical Specification 6.7.2.a.(3)

Telecony Date 8/17/83 Time 1500 Date of Occurrence: 8/12/83 Time of Occurrence: 1400 Unit 1 Technical Specification Involved: 36G 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 415 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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• TEfECOPY TO NRC Aug. 17, 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 status). 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.

Uodate Item To date the attached are our inspection results.

f.k A. Coffey Acting Power Plant Superintendent Browns Ferry Nuclear Plant

ATTACHMENT - BFR0 50-259/89049R5 Total Inspection Inspection Inspection Welds with Under Reauired Comolete Satisfactory Cracks Evaluation .

HPCI 5 0 0 0 0 Core Spray 34 25 23 2 0 BWCU 14 4 2 2 0 RHR (Class 1) 1 0 0 0 0 RHR (Head Spray) 27 0 0 0 0 RHR (Discharge) 2 0 0 0 0 CRD 1 0 0 0 0 TOTAL 84 44 40 4 0 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 RWCU DRWC 1-4 DSRWC 1-7 UNDER EVALUATION None This is an update of the event first reported previously on 8/11/83, and includes all the results through 1330 on 8/17/83 This information was provided verbally to Ross Butcher on 8/17/83 '

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, .TELECOPY TO NRC U S,', x ,, Aug, ,16,f ',1.9 83 AT.

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U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW3 MC 23 A g . 4 g -

Suite 3100 Atlanta, Georgia 30303 BFRO-50-259/83049R4 Reported under Technical. Specification 6 7 2.a.(3)

,Telecoov Date 8/16/83 Time 1500 Date of Occurrence: 8/12/83 Time of occurrence: 1400 Unit 1 Technical Specification Involved: 3.6.G ggRQLLifins Prior to occurreAqq Unit 1 in refueling outage Unit,2 at 3139 Wt 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 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 (nanual isolation valve).

Weld DSRWC-1-2 (rcactor 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, i ' c,'; oy y JQ(ild -

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. ,.- TELECOPY TO NRC Aug. 16, 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 status). 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.

Uodate Itga To date the attached are our inspection results.

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h A. Cof e Acting Power Plant Superintendent Browns Ferry Nuclear Plant s

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ConDlete Satisfactory Cracks Evaluation .q

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HPCI 3' O O O O

, Core Spray 34 24 2C 2 2 '

HWCU 14 3 1 , 2~ ,

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l' RHR (Head Spray) 27 15 15. 0 0 i, , e-RHR (Discharge) 2 0 0 0 0 l.u SATISFACTORY 1

Core Spray DCS i-6, 9, 14, 15,18, 16, 17, 5 lacs 1-4, 5, 6, 8, 9, 10, 11, 12, 13, 3, 1, 2 i RHR (Head Spray) DHS 1-2, 3 DSHS 1-1A, 3, 4, 5, 6, 7, 8, 9, 10,'11, 12, 13, 14 RWCU DRWC 1-4 UNDER EVALUATl.QR Core Spray DSCS 1-7 +

DCS 1-4 1 RWCU None RHR (Head Spray) None

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This is an update of the event first reported previously on 8/11/83, and includes all the results through 1330 on 8/16/83 This information was provided verbally to Floyd Cantrell on 8/16. .

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