ML20072F542

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Responds to IE Bulletin 82-03, Stress Corrosion Cracking in Thick Wall,Large Diameter Stainless Steel Recirculation Sys Piping. Cracks Found in 10 Welds.Description of Augmented Insp & Tabular Summary of Welds Inspected Encl
ML20072F542
Person / Time
Site: Dresden Constellation icon.png
Issue date: 03/23/1983
From: Rybak B
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
REF-SSINS-6820 6251N, IEB-82-03, IEB-82-3, NUDOCS 8303240330
Download: ML20072F542 (19)
v • d • e


Text

9 C'x Commonwealth Edison

[ [ f one First National Plaza, Chicago, Iflinois

' > } Address R: ply to: Post Office Box 767

/ Chicago. Illinois 60690 ,-

March 23, 1983 Mr. James G. Kepuler, Regional Administrator Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Dresden Station Unit 2 I.E. Bulletin 82-03 NRC Docket No. 50-237 References (a): R. C. DeYoung letters to All Licensees dated October 14 and 28, 1982.

(b): T. J. Rausch letter to J. G. Keppler dated December 1, 1982.

(c): T. J. Rausch letter to D. G. Esienhut dated January 7, 1983.

(d): B. Rybak letter to H. R. Denton dated March 1, 1983.

(e): B. Rybak letter to H. R. Denton dated March 18, 1983.

Dear Mr. Keppler:

Reference (a) transmitted I.E' Bulletin 82-03 which addresses stress corrosion cracking in thick wall, large diameter stainless steel piping at BWR plants. The Commonwealth Edison Company response to this bulletin on various items are contained in Reference (b) through (d) leaving only Item 2 open. This letter is our response to Item 2.

Attachment 1 is a description of the augmented inspection performed on Unit 2 and Attachmeat 2 provides tabular summary of the welds inspected. Crack indications were found in ten welds, our repair program is contained in References (e) and (f).

To the best of my knowledge and belief the statements con-tained herein and in the attachments are true and correct. In some respects these statements are not based on my personal knowledge but upon information furnished by other Commonwealth Edison and contrac-tor employees. Such information has been reviewed in accordance with Company practice and I believe it to be reliable.

(([(5 I !

8303240330 830323 DR ADOCK 050002g

Aarch 23, 1983 J. G. Keppler Please address any questions you may have concerning this matter to this office.

One (1) signed original of this letter is also being provided to the Document Control Desk as requestec.

Very truly yours, h, ' /(

B. $7bak Nuclear Licensing Administrator 1m Attachments cc: Resident Inspector - Dresden

' R. Gilbert - NR W US NRC Document Control Desk l

1 6251N

. ATTACHNENT 1 ,

AUGMENTED INSERVICE INSPECTION Dresden Unit 2 January, 1983 The planned inservice inspection for Dresden Unit 2 during the refueling outage which began in January, 1983, was influenced by ASME Section XI requirements,' prior NRC commitments, and by I.E. Bulletin 82-03 Rev. 1. The furnace sensitized safe ends on the reactor pressure vessel were to be volumetrically examined in their entirety including the circumferential nozzle-to-safe end and safe end-to-piping welds. The Commonwealth Edison response to I.E. Bulletin 82-03 Rev. 1, dated December 1, 1982, identified a total of 23 welds to be ultrasonically examined in the recirculation system. The sample consisted of 12 safe end-to-piping welds and 11 circumferential butt welds. This sample was enlarged to 30 by the addition of four welds in the 16-inch diameter branch lines

.which connect to the 28-inch recirculation piping and of 3 welds in the ring header.

The sample employed is summarized in the Table and individual welds are shown along with their respective SRI numbers on the included isometric drawings.

RESULTS As previously presented, a crack indication was found in the 28-inch diameter furnace sensitized safe end on nozzle N18. We consider furnace sensitized stainless steal to be a separate material category and that the presence of this crack indication does not require additional inspections of 28-inch diameter piping. The other eleven large diameter furnace sensitized safe ends were examined ultrasonically with no crack indications being found.

No crack indications were found in the 28-inch, 22-inch, and 16-inch diameter piping welds. As part of the examination of the furnace sensitized safe ends, no crack indications were found at the 12-inch riser piping connections to these safe ends. Of the four weld joints selected from the remaining 30 riser welds, two elbow weld joints contained crack indications.

Additional sampling consisted of four elbow welds with crack indications found at one weld joint, followed by examination of all remaining elbow welds. A total of nine of the 20 elbow weld l Joints contained crack indications. '

1174B

TABLE AUGMENTED INSERVICE INSPECTION Dresden Unit 2

. January, 1983 l l Butt Welds l Crack System / Category l Diameter l Examined I Total l Indications

. Furnace Sensiti7ed SE l 28" l 2 l 2 l 1 (FSSE) i I I I i 12" l 10 l 10 l None 1 l l l Recirc Outlet l 28" l 61 1 33 i None

~l l l I Recirc Ring Header I 22" l 4 l 10 1 None l I I I I Sweepolet i 22 1 8 l None LPCI 16" 2 63 None I

Shutdown Cooling 16" 2 , 63 I None i I I I Recirc Inlet I 12" l 144 l 404 1 2

-l l I I 1st Additional Sample I 12" l 4 l 26 l 1 I I I I 2nd Additional Sample i 12" l 17 l 22 l 6 I I I I 4

1 Includes two piping to safe end welds 2 Adjacent to end caps 3 Up to isolation valve 4 Includes ten piping to safe end welds l

1174B l

_ _ _ ___\

+

AUGMENTED INSERVICE INSPECTION'(cont'd)

The original riser sample included two weld connections to the ring header (one cross and one sweepolet). Although no indications.

t were found, the sample.was increased to a total of 3 riser-to-sweepolet and 2 riser-to-cross weld-joints. No crack indications were found at the ring header connections.

The weld numbers for all inspected welds are circled on the isometric drawings and their respective. SRI numbers are noted. .The weld mark on the individual piping lines is circled for weld joints having crack indications.

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ATTACHMENT 2 Dresden Unit 2 Response to I.E. Bulletin 82-03 Rev. 1 Item 2: Results of Recirculation System Inspections A total of 54 circumferential welds on recirculation piping and branch piping connections were ultrasonically inspected during this 1983 Refueling Outage.

The results of these UT inspections are tabulated in Table R-1.

Item 3: Corrective Actions The following welds require corrective action as a result of cracks discovered during the ultrasonic examination:

28" Recire. Weld Safeend-elbow weld #PS2/201-1.

12" Recire. Welds Elbow pipe Weld #

PD2-D4 PD7-Dil PD2-D5 PD9-D8 PD3-D2 PD19-D13 PD4-D23 PDl9-D14 '

PD5-D20 See letters and attachments dated March 1,1983 and March 14, 1983 from J. J. Mcdonald, SNED, to D. Farrar for the repair program and corrective action for the above welds.

When cracks were found during the examination, additional inspections were conducted in accordance with IWB 2430 of ASME Code Section XI.

l i

Table R-l

~

DRESDEN NUCLEAR POWER STATION .

UNIT NO. 2, STATE NUMBER 82900 JANUARY, 1983 INSERVICE INSPECTION ASME . RESULTS IATRcnRY COMPONFNT METHOD RYTENT OF RYAMINATION INDICATION NO. SCAN TYPE PERCENT DAC EVALUATION -

B-J Recire 28" UT -

^

Tee-Cross Weld #PDID/L5 1 4* 80 I.D. Geom.

2 5 100 I.D. Geom.

3 5 63 I.D. Geom. -

4 .2 320- I.D. Geom.

, S 3 . 125 I.D. Geom.

Pipe-Tee Weld '#PDID/D12 ,

NRI Pipe-Valve Wel,d , l' 3 50 I.D. Geom.

  1. PS2-Tee /20,2-4B Pipe-Pipe Weld 1 2 75 1.D. Geom. ,
  1. PSI /PS2 Tee Recire. 22"

~

Sweepolet Weld #22X , NRI '

CAP-Pipe' Weld #L5-D3 1 4 60 Spot ind. .

2 3 100 I.D. Geom. L 3 3 100 . I.D. Geom.

i Pipe-Cross Weld.#LS-D6A .

NRI Cross-Pipe Weld #L5/L4 -

NRI .'

Sweepol'et Weld h22X- - '

NRI . .

Pipe-Cap Weld #Ll/D24 1 2 120 I.D. Geom.

2 2 50 0.D. Geom.

o o

e

DRESDEN NUCLEAR POWER STATION .

UNIT NO. 2, STATE NUMBER 82900 JANUARY, 1983 INSERVICE INSPECTION ASME .

RESULTS t CATRCnRY COMPONENT METHOD RYPENT OF RYAMTNATION INDICATION NO. SCAN TYPE PERCENT DAC EVALUATION B-J Recire. 12" UT -

Pipe-Red Weld #PD2/L5' -

NRI

. Pipe-Sweepolet Weld NRI

  1. PD191/L2 ,

Elbow-Pipe Weld'#PD19-D13 1 5 60 AxialC(ack' 2 5, . .50- Axial Crack Pipe-Elbow Weld #fD19-D14 l' 2' 150 circum. Crack

. Pipe-Elbow We'id #PD5-D'20 1 3 60 I.D. Geom.

2 4/5 50/75 Spot I~nd.

3 4/5 50 Spot Ind.

4 3 90 Circum.' Crack  ;

5 3 70 circua. Crack t

Elb'ow-PipeWe.ld#PD$-D21 1 3, ,60 0.D. Geom. [

2 3 '200 I.D. Geom.

Pipd-Elbd'w Weld #PD7-Dil 1 2 100 0.D. Geom.

2 3 50 .

Circum. Crack 3, 4/5 '80/50 Axial Crack 4 3 75 0.D. Geom.

  • ~ '

Elbon Pipe Weld #PD7-D12 1 2 - 50 0.D. Geom.

. 2 3 100+4 I.D. Geom.

3 -3/4/5 90/40/40 I.D., Geom.

~

~

Pipe-Elbow Weld'#PD4-D22 1 3 60 I.D. Geom.

Elbow-Pipe Weld #PD4-D23 1 2 100+1 Circum. Crack 2 2 100+7 Circum. Crack

~7 ' > - - -

3 2 75 0.D. Geom.

4 3 50 0.D. Geom.

5 3 . 80 I.D. Ge'om.

6 4 100 Axial Crack

- 1 1

2

DRESDEN NUCLEAR POWER STATION UNIT NO. 2, STATE NUMBER 82900 JANUARY, 1983 INSERVICE INSPECTION ASME . RESULTS CATRCnRY COMPONKNT METHOD RrrENT OF wirAMTNATION INDICATION NO. SCAN TYPE PERCENT DAC EVALUATION B-J Recire. 12" (Cont'd) UT Elb'w-Pipe o Weld'#PD4-D23 7 4* '

70 I.D. Geom.

{ (Cont'd) 8 4 75 1.D. Geom.

9 4 60 I.D. Geom.

l 10 .4 ' 80' I.D. Geom.

l

,' 11 4 , 50 I.D. Geom.

12 4 ,

65 I.D..Gegm.

13 5 90' I.D. Geom.

14 5.' 80 Axial Crack

, 15' 5 80 Axial Crack 16 5 100 Axial Crack

. '17 5 100 I.D. Geom.

Pipe-Elbow Weld #PD6-D18 1 2 60 0.D. Ge'm.

o i 2 3 70 0.D. Gedm.

,3 5 50 0.D. Geom.

Elb'ow-Pipe Weld /PD6-D19 1 3 ,70 0.D. Geom.

. Pipe-El' bow Weld #PDl-Dl5 1 3 60 I.D. Geom. '

' ~

2 2 55 I.D. Geom.

Elbow-Pipe Weld #PDl-Dl'6 NRI ,

Pipe-Elbow Weld #PD'8-D9 1 ,

2 , 50 I.D. Geom, 2 3 -

50 0.D. Geom.

Elbow-P'ipe Weld'#PD8-D10 1 2

. 75 - 0.D. Geom.

2 3 100 I.D. Geoms Pipe-Elbow' Weld #PD9-U7 -

1 3 50 I.D. Ge'om.

2 2 60 I.D. Geom.

o 0 -

3

DRESDEN NUCLEAR POWER STATION .

UNIT NO. 2, STATE NUMBER 82900 JANUARY, 1983 INSERVICE INSPECTION ASME . RESULTS l cATRt:nRY COMPONENT METHOD RYTENT OF RYAMINATION INDICATION NO. SCAN TYPE PERCENT DAC EVALUATION l

B-J Recirc. 12" (Cont'd) UT -

Elbow-Pipe Weld #PD9-D8 '

1 - -

2* *

. 60 0.D. Geom.

2 2 100+2 Circum. Crack 3 3 75 1.D. Geom.'

4 3 80- 0.D. Geom.

Pipe-Elbow Weld #PD2-D4 1 2 ,

75 0.D. Geom.

2 :2 .50- I.D. Geom.

3 e 3,' 100 0.D. Geom.

4' 4 50 Axial Crack 5 4 75 Axial Crack Elbow-Pipe Weld #PD2-D5 1 5 62 I.D. Geom.

2 4 50 I .D . Ge'om.

3 3 50 Mode Conver.

4 3 50 I.D. Geom.

'S 3

  • 50' I.D. Geom".

6 2~ 150 circum. Crack 7

7. 'l00 Circum. Crack Pipe-Elbdw Weld #PD3'DI. -

I 2 90 I.D. Geom.

2 2 80 .- 0.D. Geom.

3 3 70-' O.D. Geom, 4 2 80 0.D. Geom.

5' ,

3 50 I.D. Geom,.

Elbow-Pipe Weld dPD3-D2 1 2 50 0.D. Geom.

2 2

  • 50 - I.D., Geom.

3 3 50 I.D. Geom.

~

4 3 80 0 D. Geom.

, 5 4 l$0 Axial Crack 6 4 50 Axial Crack 7 4 100- Axial Crack-

~' - >

8 5 40 Axial Crack 4

w

DRESDEN NUCLEAR POWER STATION .

UNIT NO. 2, STATE NUMBER 82900 JANUARY, 1983 INSERVICE INSPECTION ASME , RESULTS EATRrDRV COMPONRNT METHOD RYTENT OF EXAMINATION INDICATION NO. SCAN TYPE PERCENI DAC EVALUATION. i B-J Recirc. 12" (Cont'd) UT - -

Pipe-Sweepolet Weld

  • I $. 2' >

100 I.D. Geom.

  1. PD3-L5 2 2 90 I.D. Geom.

. 3 2 90 0.D. Geom.-

4 3 100+1, I.D. Geom.

Pipe-Red'ucer Weld #PD-I-L2 ,

NRI ,

Pipe-Sweepolet, Weld 1 .2.' 55 0.D. Geom.

  1. PD4-L1 ,

2' 2 100+4 Mode Conver.

3 3 100+2 I.D. Geom.

Shutdown Cooling 16" '

Tee-Elbow ' Weld # 16-8 1 2 100 I.'D. Ge6m. f Tee-Pipe W' eld # 16-11, 'l '2 150- Mode Conv6r.  ;

1 Low Pressure Cooling

  • Injection - 16" Elbow-Valve Weld # 16-14 .. NRI Elbow-ValveWeldd16-1i 1 3 '159 0.D. Geom.

Isolation . .

Condenser - 12" -

Elbow-Valve Weld # 12-10 NRI . ,

Elbow-Pipe: Weld # 12-11 NRI .

. . = .-.. '

4 5

DRESDEN NUCLEAR POWER STATION .

UNIT NO. 2, STATE NUMBER 82900 JANUARY, 1983 INSERVICE INSPECTION ASME . RESULTS CATECORY (IOMPONENT METHOD EXTENT OF EXAMINATION INDICATION NO. SCAN TYPE PERCENI DAC EVALUATION B-J Furnace Sensitized UT -

Safe End Welds ,

Recire. 28" SE-Pipe Weld # PSI-2/201-1 NRI SE-Elbow' Weld #PS2L201-1 1 2 100 Circum. Crack 2 2 ' 75- I.D. Gedm.

3 .3* .50 I.D. Geom.

4' 2 50 Spot Ind.

5 2 50 Spot Ind.

6 2 40 Spot Ind.

7 2 55 Spot Ind.

8 2 40 Spot Ind.

9 2 50 Spot Ind.

. 10 2 35 Spot Ind.

Il 2 SC Spot Ind.'

12 2 50 Spot Ind.

13 2' '50 Spot Ind.

14 2 60 Spot Ind.

Recire. 12" .. ,

SE-PipeWeld#PD4I201-1 1 2 63 I.D. Geom.

2 2 50 I.D. Geom.

SE-Pipe Weld #PD5/20.1-1 FRI -

SE'-Pipe Weld #PD6/201-1 1 2 . 62 I.D. Geom.

SE-Pipe Weld #PDl/201-1 NRI SE-Pi'pe Weld #PD19/201-1 1 2 45 I.D. Geom.

i _:_2 . _ - - , 2 3 70 I.D. Geom. i

. 1 SE-Pipe Weld- #PD7/201-f 1 2 . 65 1.D. Geom.

I 1

, 6 I

DRESDEN NUCLEAR POWER STATION .

UNIT NO. 2, STATE NUMBER 82900 JANUARY, 1983 INSERVICE INSPECTION

~

ASME , RESULTS CATKcnRY COMPONRNT METHOD x11miT OF RYAMINATION INDICATION NO. SCAN TYPE PERCENT DAC EVALUATION B-J Recire. 12" (Cont'd) UT -

SE-Pipe Weld #PD8/201'l ' '

1 - -

2* 80 0.D. Geom.

SE-Pipe Weld #PD9/201-1 1 :2 75 1.D. Geom.-

SE-Pipe geld #PD2/,201-1 1 '2 . 45 1.D. Geom.

2 3 ,

100 1.D. Geom.

SE-Pipe Weld #PD3/201-1

  • NRI -

. e e

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4

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9 e

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.7

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