ML20079J233

Final Rept of Significant Const Deficiency 48 Re Design Application of Break Flanges at Elevated Temps in Rcs,Safety Injection & Chemical & Vol Control Sys.Flanges W/Matl Not Meeting ASME Code Requirements Replaced W/Correct Matl

ML20079J233
Person / Time
Site:	Waterford
Issue date:	12/17/1982
From:	Maurin L LOUISIANA POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, W3I82-0122, W3I82-122, NUDOCS 8212280143
Download: ML20079J233 (2)

Text

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Xea I! O LOUISIANA 24a ocLAnoNoe Stater -

P O W F R & L 1 G H T! P O BOX 6008 NEW ORLEANS. LOUISIANA 70,74 * (504) 366 2345

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u December 17, 1982 t. v. MAURiN Voce Presx1ent Nuclear Operatens W3I82-0122 Q-3-A35.07.48 Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Significant Construction Deficiency No. 48

" Design Application of Break Flanges at Elevated Temperatures" Final Report

REFERENCE:

LP&L Letter W3I82-0052 dated September 30, 1982

Dear Mr. Collins:

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final 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,

)W/tytr2' L. V. Maurin LVM/WAC:keh h-N Attachment cc: 1) Director 3) E. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with 15 copies of report)

2) Director 4) W. Stevenson Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with I copy of report) r212280143 821217

, PDR ADOCK 05000382 S PDR

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m i; -FINAL REPORT OF' ,

SIGNIFICANT CONSTRUCTION DEFICIENCY No. 48

'" DESIGN APPLICATION OF BREAK FLANGES AT ELEVATED, TEMPERATURES"

~ INTRODUCTION l

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. reportable under the requirements of 10CFR50.55(e).

To the best of our knowledge, this problem has not beenLidentified to-the Nuclear Regulatory Commission pursuant to 10CFR21.

DESCRIPTION.

1 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 isometrics.

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 leakase or malfunction of the joint.

SAFETY IMPLICATIONS 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 operation or render inoperable a safety system.

Therefore, this deviation could adversely affect the safety of the piant if left uncorrected.

CORRECTIVE ACTION The following corrective action was taken to correct this deficiency:

1) Nonconformance Report (NCR-W3-3302 S/1) was issued to identify, disposition and track all flanges that were not within allowable design limits.

2) Deficient material noted on NCR-W3-3302 S/1 was replaced with correct material, as per disposition of the NCR.

3) All corrective action is completed and the NCR (W3-3302 S/1) has been reviewed, accepted and closed on September 25, 1982.

This report is submitted as the Final Report.

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