ML20087F877
| ML20087F877 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/01/1984 |
| From: | Gerrets T LOUISIANA POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 32, W3K84-0454, W3K84-454, NUDOCS 8403190253 | |
| Download: ML20087F877 (3) | |
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P O W E R & LI G H T! R O BOX 6000
- NEW ORLEANS. LOUISIANA 70174 142 DELAHONDE STREET e (504) 366-2345 Eu?NivsY$
March 1, 1984 W3K84-0454 Q-3-A35.07.32 33@20WM3 Mr. John T. Collins Regional Administrator, Region IV MAR 81%4 U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 j
Arlington, Texas 76012
REFERENCE:
LP&L Letter W3K84-0246 dated February 3, 1984
Dear Mr. Collins:
SUBJECT:
Waterford SES Unit No. 3 Docket No. 50-382 Significant Construction Deficiency No. 32
" Stress Analysis For Welded Pipe Support Attachments Was Not Performed Prior lo Fabrication" Final Report In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final Report of Significant Construction Deficiency No. 32,
" Stress Analysis For Welded Pipe Support Attachments Was Not Performed Prior To Fabrication".
If you have any questions, please advise.
Very truly yours, h?AZd T. F. Gerrets Corporate Quality Assurance Manager TFG:CNH.SSTG Attachments cc: Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.
20555 (15 copies) hDRADOCK403190253 840301 05000382 I
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-March 1 1984
_. W3K84 0454 Page 2 cc: Director
' Office of Management Information and Program Control U.'S. Nuclear Regulatory Commission 3
Washington, D.C.
20555 Mr.'
E.-L. Blake
-Shaw, Pittman, Potts, & Trowbridge 1800 M Street, N.W.
- Washington, D.C.
20036 Mr. W. M. Stevenson Monroe & Lemann 1424 Whitney Building
~New Orleans, Louisiana 70130 e
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y FINAL REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 32 i
" STRESS ANALYSIS FOR WELDED PIPE SUPPORT ATTACHMENTS WAS NOT PERFORMED PRIOR TO FABRICATION"
' INTRODUCTION.
p This-report is submitted pursuant to 10CFR50.55(e).
It describes a deficiency in the design of welded pipe attachments by Bergen-Patterson, (Designers).
The local stress analysis'at the point along the pipe where's welded attachment is required for pipe supports was not performed prior to fabrication. This problem is considered reportable pursuant to the requirements of 10CFR50.55(e). To the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pursuant to 10CFR21.
DESCRIPTION OF PROBLEM In reviewing Bergen-Patterson feedback on local' stress analysis, it was-found that Bergen-Patterson had been active in this area but reduced their efforts to a minimum..Thus in many cases, the local strese ar.alysis was not performed prior to fabrication.
- The following systems were ultimately identified as being affected:
SAFETY RELATED NON-SAFETY RELATED Blowdown Air Evacuation
-Boron Management Condensate Component Cooling Extraction Steam Chemical Volume Control Fire Protection Containment Spray Feedwater Fuel Pool Heater Drain Safety Injection Instrument Air Main Steam Station Air Turbine Cooling SAFETY IMPLICATIONS If this deficiency were left uncorrected, possible degradation of
-safety-related systems could occur due to the failure of welded pipe support attachments.
' CORRECTIVE ACTION TAKEN Bergen-Patterson performed the stress analysis, this analysis identified eighty-five (85) supports that required revision and/or rework.
Nonconformance Report W3-2733 was issued to track this rework.
All corrective action has been completed, the supporting documentation has
'been reviewed and NCR W3-2733 has been closed.
This Report is being submitted as the Final Report.
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