ML20050B168
| ML20050B168 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/26/1982 |
| From: | Mclendon G LOUISIANA POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, W3K82-1, NUDOCS 8204050064 | |
| Download: ML20050B168 (3) | |
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Louisiama, m ouAmoNo< s,ma, POWE R & L1G H T/ P o uox 6008. NEW O LEAM LOUISlANA 70174 * (504) 366 2345
'WOU ?$UU) u March 26, 1982 G D. McLENDON j
N O IM[!Qi/f; ap) eni r Vice Prescent h'U 'NW29EB2/]Illl i
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[Q Mr. John T. Collins, Regional Administrator, Region ~ 1V 97 U.
S. Nuclear Regulatory Commission Oc tit.g,g'Wg[ 'd 611 Ryan Plaza Drive, Suite 1000
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SUBJECT:
Waterford SES Unit No. 3 g
Docket No. 50-382 C4 Interim Report of Significant Construction Deficiency No. 48
" Design Application of Break Flanges at Elevated Temperatures"
Reference:
Telecon - L. L. Bass (LP&L) to L. Martin (NRC) dated 2/24/82
Dear Mr Collins:
In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copics of the Interim Report of Significant Construction Deficiency No. 48, " Design Application of Break Flanges at Elevated Temperatures."
If you have any questions, please advise.
Very truly yours, M
CDMcL/LLB/ncd Attachment cc:
1)
Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commiulon y
Washington, D. C. 20555 (with 15 copies of report) g/
2)
Director l
Office of Management
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Information and Program Control U. S. Nuclear Regulatory Commission
[/
Washington, D. C. 20555 (with I copy of report) i l
l 8204050064 820326 PDR ADOCK 05000382 S
PDR J
LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT NO. 3-Interim Report of Significant Construction Deficiency No. 48 Design Application of Break Flanges at Elevated Temperatures N. M Reviewed by
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[~ hO Date J. Gutfrrez - Q.' A. Siteppervisor March 22, 1982
I INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 48
" DESIGN APPLICATION OF BP.EAK FLANGES AT ELEVATED TEMPERATURES" INTRODUCTION This report is submitted pursuant to 10CFR50.55(e).
It describes a defect with the Reactor Coolant (RC), Safety Injection (SI), and Chemical and Volume Control (CH) system flanges.
The flange material that had been specified was not the material used in making the flanges.
This problem is considered re-portable under the requirements of 10CFR50.55(e).
To the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pur-suant to 10CFR21.
DESCRIPTION Class 1500 and Class 900 Type 304 flanges have been installed in systems where the maximum operating conditions exceed the pressure-temperature ratings of the installed flanges.
There are forty-eight (48) flanges which do not meet ASME code requirements.
Examination of the Station Piping Specification and the Waterford 3 Piping Line List indicated the correct flanges were specified in these documents for large bore isometrics.
The error was introduced in the preparation of the isometric drawings. A material conflict between the design drawings and the piping line list was noted on the small bore piping.
These documents were utilized to develop the small bore piping iscmetrics.
Under operating conditions approaching the design conditions, the stress level experienced by the flanges may reach a high enough value to cause distortion, resulting in leakage or malfunction of the joint.
SAFETY FPLICATIONS ~
The subject flanges are located in the Reactor Coolant, Safety Injection, and Chemical and Volume Control systems.
Failure of these flanges could cause a small LOCA, or degrade ope"ation or render inoperable a safety system.
There-fore, this deviation adversely affects the safety of the plant if left uncor-rected.
CORRECTIVE ACTION All affected flanges shall have material replacements made in order to satisfy joint pressure-temperature requirements.
Nonconformance Report W3-3302 S/1 has been issued to identify and track this work.
The corrective action shall be completed and a Final Report submitted to the USNRC by September 30, 1982.