ML20010C195

Interim Rept of Significant Const Deficiency 32 Re Stress Analysis for Welded Pipe Support Attachments Not Performed Prior to Fabrication.Corrective Action Underway.Final Rept Will Be Submitted by 820401

ML20010C195
Person / Time
Site:	Waterford
Issue date:	08/10/1981
From:	Aswell D LOUISIANA POWER & LIGHT CO.
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, W3K81-0286, W3K81-286, NUDOCS 8108190235
Download: ML20010C195 (4)

Text

D H6 S0.5.5Le}

=

I E1605 fhc W y I l OUISIANA m Oeu nONOe S1neer POWER & LIGHT P O BOX 6008

• NEW ORLEANS. LOUISIANA 70174 . (504) 366-2345 UtauS$EYS D. L ASWELL Vce Pres. dent-Power Productaan August 10, 1981 Q-3-A35.07.32 Q-3-A35.02.01 W3K81-0286 Mr. K. V. Seyfrit, Director, Region IV U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Interim Report of Significant Construction Deficiency No. 32

" Stress Analysis Welded Pipe Support Attachments Was Not Performed Prior to Fabrication"

Reference:

Telcon - L. L. Bass (LPGL) to W. G. Hubacek (NRC) on July 7,1981

Dear Mr. Seyfrit :

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Interim Report of Significant Construction Deficiency No. 32, " Stress Analysis for Welded Pipe Support Attachments Was Not Performed Prior to Fabrication." g

'9 If you have any questions, please advise. [

D Very truly yours, Sy \ %g\y $

/ ~{

y N I.

D. L. Aswell i DLA/LLB/grf N[g* .

/g \

Attachment

{[

cc: 1) Director S Of fice of Inspection & Enforcement U. S. Nuclear Regulatory Commission f[

Washington, D. C. 20555 (with 15 copies of report)

2) Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with 1 copy of report) 8108190235 810810 i'DR ADOCK 05000382 S PDR

r

{ -

t LOUISI ANA POWER & LIGHT COMPANY WATERFORD SES UNIT NO. 3 Interim Report of Significant Construction Deficiency No. 32 Stress Analysis for Welded Pipe Support Attachments Was Not Performed Prior to Iabrication Reviewed by _ (

R . J . ' .i iser - Site Manager /

• Date keviewed by J[LTWils-ProjectSuperintendent ' ' Date Reviewed by

! Proje j ' [/. #M ""

J/ Hart LgensingEngineer Date

/

Reviewed by 4 R. X. Ilartnett - Q. A. Site Supervisor

[-7"M Date August 5, 1981 i

c . . .

?

= .

INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY No. 32

" STRESS ANALYSIS FOR WELDED PlPE SUPPORT ATTACHMENTS WAS NOT PERFORMED PRIOR TO FABEICATION" INTRODUCTION This report is submitted pursuant to 10CFR50.55(e) . It describes a deficiency in the design of welded pipe attachments by Bergen-Paterson. The local stress analysis at the point along the pipe where a welded attachment is required for pipe supports was not performed prior to fabrication. This problem is considered reportable under the requirements of 10CFR50.55(c) . To the best of our knowledge, this problem has not been identified to the Nuclear Regu-latory Comnission pursuant to 10CFR21.

DESCRIPTION OF PROBLEM

'Ihis deficiency was detected in the Fall of 1980 when Ebasco Engineering noticed that Ebasco was submitting information about the stress analysis to Bergen-Paterson but was not receiving feedback on the analysis from Bergen-Paterson. Subsequent followup by Ebasco showed that during 1977 and 1978, Bergen-Paterson had been active in this area but reduced their efforts to a minimum dur?ng the latter part of 1979.

At this time the following systems have been identified as being affected:

Safety-Related Non-Safety-Related Blowdown Air Evacuation Baron Management Auxiliary Steam Component Cooling Condensate Chemical Volume Control Circulating Water Containment Spray Demineralized Water Diesel Generator Extraction Steam Fuel Pool Fire Protection Reactor Coolant Feedwater Safety injection Heater Drain Sampling Instrument Air Vent Misc. Drain Waste Management Main Steam Nitrogen Station Air Turbine Cool Identification of all the systems af fected is not possible at this time since the total number of hangers still requiring analysis is not known.

Sup,)lements to Nonconformance Report W3-2733 will identify additional hangers requiring analysis.

1 1

i l

SAFETY IMPLICATIONS If this deficiency were left uncorrected, possible degradation of safety-related systems could occur due to the failure of welded pipe support a t ta chmen ts .

CORRECTIVE ACTION 1

Nonconformance Report W3-2733 has been issued to document this deficiency I and has been issued to Tompkins-Beckwith, Inc., for completion of repairs.

Corrective action status is outlined as follows:

Approximately 718 supports are known to require analysis.

(1) Bergen-Paterson has, to date, identified 55 suppc.:ts which failed in local stress analysis and require modification.

(2) Rework is being accomplished on a start-up system basis and will be completed by the turnover date of the system to LP6L.

l Corrective action will be completed and a Final Report submitted en or '

before April 1, 1982.

l

- _ - - - _ _ -