ML20010A339
| ML20010A339 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/29/1981 |
| 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, W3K-81-0275, W3K-81-275, NUDOCS 8108110331 | |
| Download: ML20010A339 (4) | |
Text
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IE HQs File Ocpq Dm #3 SD. TS(ej i
Louisiama m O<<AeO~Oe S1eur POWER & LIGHT PJ BOX 6008
- NEW ORLEANS LOUISIANA 70174 * (504) 366 2345
$YONENU D. L ASWELL July 29, 1981 vc. %,.o.n #o e %uw, W3K-81-0275 Q-3-A35.07.31 Q-3-A35.02.01 Mr. K. V. Seyfrit, Director, Region IV U. S. Nuclear Regulatory Commission Office of Inspection and Enforc2 ment 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
SUBJECT:
Waterford IES Unit No. 3 Docket No. 50-382 Interim Report of Significant Construction Deficiency No. 31
" Incorrect Friction Factor used in Design of Pipe Support Hangers"
Reference:
T.lecon - L. L. Bass (LP&L) to W. 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. 31, " Incorrect Friction Factor Used in Des, Support Hangera.,
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e If you have any questions, please advise.
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- 9 D. L. Aswell
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Attachment W
3 I sal cc:
- 1) Director Of fice of Inspection & Enforcement-b I
U. S. Nuclear Regulatory Commission j
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Washington, D. C. 20555 (with 15 copies of report)
- 2) Director Of fice of Management I
Information and Program Control 5
U. S. Nuclear Regulatory Commission Washington, D. C. 20555
/ I (with 1 copy of report) 8108110331 910729 '
PDR ADOCK 05000382 S
LOUISIANA POWER & LIGl;T COMPANY WATERFORD SES UNIT NO. 3 Interim Report of Significant Construction Deficiency No. 31 Incorrect Friction Factor Used in Design of Pipe Support Hangers Reviewed by_ ;
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J. II, t - Project Licensiy{; Engineer Date Reviewed by _
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R. A. Ilartnett - Q. A. Site Supervisor Date July 24, 1981 l
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r INTERIM REPORT SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 31 INCORRECT FRICTION FACTOR USED IN DESIGN OF PIPE SUPPORT liANGERS INTRODUCTION 1his report in submitted pursuant to 10CFR50.55(e).
It describes a deficiency in the acicction of friction factors used for the design of pipe supports supplied by Bergen Patterson. This problem is considered reportable under the requirements of 10CFR50.55(e). To the best of our knowledge, this problem has not been identified to the Nuclear Reguln-tory Commission pursuant to 10CFR21.
DESCRIPTION OF PROBLEM In the design of supports for the Waterford 3 Project, Bergen Patterson used a variety of friction factors and eventually decided on a factor of 0.6 to be applied in the design calsalations.
It has been determined that friction factors other than 0.6 result.1 in some supports which could not withstand design loads when the 0.3 factor was applied.
This deficiency has been reported via Nonconformance Report 'J3-2732 which identifies 289 pipe supports affected. At this time, we do not have a finite number of hangers af fected.
However, supplements to this Noncon-formance Report will identify the total number.
The systems af fected are as follows:
Safety-Related Non-Safety-Reinted Blowdown Air Evacuation j
Boron Management Auxiliary Steam Component Cooling Condensate l
Chemical Volume Control Circulating Water Containment Spray Demineralized Water Emergency Diesel Generator Extraction Steam i
Feedwater Fuel Oil Fuel Pool Cooling Fire Protection Main Steam
.leater Drain Reactor Coolant Lube 011 Safety injection Miscellanseus Drains Vent SAFETY IMPLICATIONS If this deficiency were Icft uncorrected, degradation of safety systems could pcssibly occur.
Such degradation vould occur by exceeding the design bending stresses of the subject pipe support structure. This deficiency also presents the potential for common mode failure within and between sys-tems.
Such failures are not analyzed in the FSAR.
., CORRECTIVE ACTION Nonconformance Report W3-2732 has been written to identify and disposition this condition. As of this time, Bergen Patterson han ce npleted a design re-review of 244 supports. Of these, Bergen Patterson has established that 108 supports require rework and 136 merely require paper work revisions (revised loads on hanger sketches). Rework of supports is being accom-plished on a start-up system basis by Tompkins-Beckwith, Inc., Waterford 3 Corrective action will be completed by turnover of the piping contractor.
system to LP&t..
The Bergen Patterson review is presently scheduled to be completed by July 31, 1981. Corrective action will be acconplished and a Final Report submitted on or before April 1, 1982.
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