ML20063M789
| ML20063M789 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/02/1982 |
| From: | Mclendon G LOUISIANA POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, W3K82-0565, NUDOCS 8209160117 | |
| Download: ML20063M789 (7) | |
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LOUISIANA f,42 oeunoNot smm POWER & LIG HT/ P O BOX 6000
- NEW ORLEANS. LOUISfANA 70174 * (504) 366 2345
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u September 2, 1982 G D. McLENDON Senior Vce President W3K82-0565 Q-3-A35.07.17 Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission
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- ]Ii 611 Ryan Plaza Drive, Suite 1000 ff I
Arlington, Texas 76012 s
h,SEP 4 1982 1
SUBJECT:
Waterford SES Unit No. 3 i
Docket No. 50-382 UL Interim Status Report of Significant Construct [on Deficiency No. 17
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" Base Metal Defects in Main Steam and Feedwater Containment Penetration Anchors" Seventh Interim Report
Reference:
LP&L Letter W3K82-0314 dated June 3, 1982
Dear Mr. Collins:
In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Interim Report of Significant Construction Deficiency No. 17. " Base Metal Defects in Main Steam and Feedwater Containmer' Penetration Anchors." A final report will be issued October 29, 1982.
If you have any questions, please advise.
Very truly yours, GDMcL/LLB/rd Attachment cc:
1)
Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with 15 copies of report) 2)
Director of Management Office of Management Information and Program Control 3
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U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with I copy of report)
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8209160117 820902 PDR ADOCK 05000382 s
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IDUISIANA POWER & LIGIT COMPANY WATEREORD SES UNIT NO. 3 Interim Status Report of Sienificant Construction Deficiency No.17 Base Metal Defects In Main Cteam And Feedwater Containment Penetration Anchors Reviewed by Jr /L R. J. MiGhise'rWte Manager Date
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/$f/ L Reviewed by J. Wills - Project' Superintendent
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/ Date J.pt ' Project Lic)tnsincf Ehgineet ~ h/'! h' fL
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Date Reviewed by
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A Reviewed by W. YdegcF 'Sf. Rdsident Engineer
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J. Gupferrez - Q.'A. Site Superv tor Date
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August 30, 1982
INTERIM STATUS REPORT SIGNIFICANT CONSTRUCTION DEFICIENCY NO.17 l
BASE METAL DEm;6 IN MAIN STEAM AND FEE [ MATER l
CDNTAINMENT PENETRATION ANCHORS INTRODUCTION This report is subnitted pursuant to 10CFR50.55(e). It describes deficiencies in the base metal of the plates in the Main Steam and Feedwater Anchors.
This condition is considered reportable under the requirements of 10CFR50.55(e).
To the best of our knowledge, this problem has not been reportcd to the Nuclear Regulatory Comnission pursuant to 10CFR21.
DESCRIPTION
'Ibupkins-Beckwith, the process piping installation contractor, has been attempt-ing to weld 2-3/4" thick bearing lugs to the base and legs of the No.1 and No. 2 Main Steam Penetration Anchors. Extensive cracking has occurred in the base plates. One of the lugs was ultrasonically tested and it appears that the crack may have propagated in the base metal along the entire length of the lug. Six lugs have been welded on the feedwater No. 3 penetration anchor and only minor visible cracking has been encountered. However, the base material specification ASME SA-36 is susceptible to lamellar tearing and there is concern that cracking belcu the surface may exist. To date, ultrasonic testing has not been performed on any of the No. 3 pmetration anchor lugs. Currently, all work is stopped on these anchors and three nonconformances (W3-1718, W3-1723, W3-2083) have been generated to document the visible cracks. In some instances the base material has been previously repaired due to cracking discovered in the area of Peden (supplier) shop welds. Additionally, problems have been encountered concerning distortion of the lugs as they cool down. The lugs tend to bend away from the fluted head, thus elbninating full bearing contact.
SAFETY IMPLICATIONS If this deficiency is left uncorrected, in the event of a pipe rupture, the anchors may not ha adequate to withstand the application of the full loads generated. It is therefore possible for an anchor to fail, perhaps resulting in subseque-t pipe ruptures. Thus, failure to correct this deficiency could invalidate assumptions made in the FSAR dealing with Pipe Rupture Analysis.
O)RRECTIVE ACTION The following action was taken to correct the deficiency:
1.
A procedure to repair cracks in the base metal was furnished to the field.
Direction was given for excavating the cracks and rewulding the base metal specifying a mimmum preheat and interpass temperature. After being allowed to cool slowly to ambient temperature, the repairs are examined by magnetic particle and ultrasonic test.
2.
Reevaluation of the Main Steam and Feedwater Anchor loads was performed by the Ebasco rechanical Nuclear Department with the result that the size of the anchor lug and stiffner welds could be reduced.
SCD #17 Page 2 3.
The configuration of anchor lugs and stiffners was revised to minimize the crection and welding problems encountered in the original design.
4.
The design was changed to utilize a higher strength steel (from A441 to h588) for certain plate assenblies with special procurement requirements restricting the sulfur and carbon contents.
5.
The welding procedure was modified to incorporate welding techniques which were designed to minimize residual stresses in the welded plates thereby reducing the possibility of lamellar tearing of the base metal and dis-tortion on the plates.
The only corrective action renaining is the welding of the top crosspiece of the East Main Steam Anchor. Corrective action will be complete by October 29, 1982.
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IOUISIANA POWER & LIGff COMPANY WATEREDRD SES UNIT NO. 3 Interim Status Report of Sirnificant Construction Deficiency No. 17 Base N al Defects In Main Steam And Feedwater Containment Penetration Anchors
((J//fA Reviewed by R. J. Mflhise'rWte Manager Date
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Reviewed by J. Wills - Project Superintendent
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/Date M
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2-Reviewed by sf J.pt 'Pr6 ject Licpsincf E&gincet Date b
Mh Reviewed by l
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W. YdegcF 'St. R6stdent Engineer
/Date Reviewed by
/d J.Guflerrez-Q.'A.SiteSuperv) hor Date August 30, 1982 g
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INTERIM STATUS REPORT SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 17 BASE MUTAL DEFECTS IN MMN STENi AND FEEDNATER CONTAINMENT PENETPATION ANCHORS INTRODUCTION This report is subnitted pursuant to 10CFR50.55(e). It describes deficiencies in the base netal of the plates in the Main Steam and Feedwater Anchors.
This condition is considered reportable under the requirements of 10CFR50.55(e).
To the best of our knowledge, this problem has not been reported to the Nuclear Regulatory Conmission pursuant to 10CFR21.
DESCRIPTION Tompkins-Beckwith, the process piping installation contractor, has been attempt-ing to weld 2-3/4" thick bearing lugs to the base and legs of the No.1 and No. 2 Main Steam Penetration Anchors. Extensive cracking has occurred in the base plates. One of the lugs was ultrasonically tested and it appears that the crack may have propagated in the base metal along the entire length of the lug. Six lugs have been w lded on the feedwater No. 3 penetration anchor and only minor visible cracking has been encountered. However, the base material specification ASME SA-36 is susceptible to lamellar tearing and there is concern that cracking below the surface may exist. To date, ultrasonic testing has not been performed on any of the No. 3 penetration anchor lugs. Currently, all work is stopped on these anchors and three nonconformances (W3-1718, W3-1723, W3-2083) have been generated to document the visible cracks.
In some instances the base material has been previously repaired due to cracking discovered in the area of Peden (supplier) shop m lds. Additionally, problems have been encountered concerning distortion of the lugs as they cool down. The lugs tend to bend away from the fluted head, thus eliminating full bearing contact.
SAFETY IMPLICATIONS If this deficiency is left uncorrected, in the event of a pipe rupture, the anchors may not be adequate to withstand the application of the full loads generated. It is therefore possible for an anchor to fail, perhaps resulting in subsequent pipe ruptures. Thus, failure to correct this deficiency could invalidate assumptions made in the FSAR dealing with Pipe Rupture Analysis.
CORRECr1VE ACTION The folloaing action was taken to correct the deficiency:
1.
A procedure to repair cracks in the base metal was furnished to the field.
Direction was given for excavating the cracks and rewelding the base metal specifying a minimum preheat and interpass temperature. After being allow d to cool slowly to ambient tmperature, the repairs are examined by magnetic particle and ultrasonic test.
2.
Reevaluation of the Main Steam and Feedwater Anchor loads was performed by the Ebasco Mechanical Nuclear Department with the result that the size of the anchor lug and stiffner w lds could be reduced.
. '. ~ '
SCD #17 Page 2 3.
The configuration of anchor lugs and stiffners was revised to min 2mize the crection and welding problems encountered in the original design.
4.
'Ihe design was changed to utilize a higher strength steel (frcxn A441 to A588) for certain plate assemblies with special procurement requirements restricting the sulfur and carbon contents.
5.
The welding procedure was nodified to incorporate welding techniques which were designed to minimize residual stresses in the welded plates thereby reducing the possibility of lamellar tearing of the base metal and dis-tortion on the plates.
The only corrective action remaining is the welding of the top crosspiece of the East Main Steam Anchor. Corrective action will be complete by October 29, 1982.
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