ML20031H358

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Final Deficiency Rept Re Incorrect Welding Operations on Reactor Vessel Vent Sys,Initially Reported 810915.Weld Cut Out & Rewelded Per Procedure P43-P8-T-Ag
ML20031H358
Person / Time
Site: San Onofre 
Issue date: 10/14/1981
From: Papay L
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8110270404
Download: ML20031H358 (3)


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Docket No. 50-361-50 55(e) Report Southern Calibrnia Edison Company g6 R O. Box 800 2244 WALNUT GROVE AVENUE ROSEME AD, CALWORNIA 98770 T. PAPM vect Passiosser asa. spa.e474 October 14, 1981 Mr. R. H. Engelken, Director Office of Inspection and Enforcement

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.U. S. Nuclear Regulatory Commission

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Region V t

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Suite 202, Walnut Creek Plaza 1990 North California Boulevard OCT2 G 1986-)

Walnut Creek, California 94596 gggguma v5

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Dear Mr. Engelken:

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Subj ect:

Docket No. 50-361 San Onofre Nuclear Generating Station, Unit 2 In a letter to your office dated September 15, 1981 we identified a condition which we considered reportable in accordance with 10CFR50.55(e).

The condition involves the'use of an incorrect welding procedure during welding operations on the. reactor vessel vent system.

Enclosed in accordance with 10CFR50.55(e) are twenty-five (25) copies of a Final Report entitled " FINAL REPORT ON INCORRECT WELDING PROCEDURE ON THE REACTOR HEAD VENT, San Onofre Nuclear Generating Station, Unit 2."

If you have any questions regarding this report, we would be pleased to discuss this matter with you at your con-venience.

Very.truly yours,

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. Enclosures I

cc:

Victor Stello (NRC, Director I&E)

A. E. Chaffee (NRC, San Onofre' Units 2 and

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.g 61 130 IAI 0 311 8110270404 811014' 03f.GO311 PDR ADOCK 05000361' S

PDR I.

i FINAL REPORT ON INCORRECT WELDING PROCEDURE ON THE REACTOR HEAD VENT San Onofre Nuclear Generating Station, Unit 2 INTRODUCTION This report is submitted pursuant to 10CFR50.55(e)(3).

It describes a condition discovered during construction inspec -

tion.

This report includes a description of the condition, an analysis of the safety implication and a summary of the corrective action taken.

By letter dated September.15, 1981, Southern California Edison confirmed notification to the NRC l

of the reportable condition.

BACKGROUND During review of Nonconformance Reports (NCR's) for possible reportable conditions per 10CFR50.55(e), it was noted on a NCR that a weld had been performed on the reactor vessel vent system with an incorrect welding procedure.

The weld was made between dissimilar metals, (i.e. stainless steel to inconel) using weld procedure P8-T-Ag which is for welding stainless steel to stainless steel.

DISCUSSION The following discussion is responsive to 10CFR50.55(e)(3).

DESCRIPTION OF THE DEFICIENCY An incorrect welding procedure was used on weld "A" of Drawing S2-1201-ML-058, Sheet No. 1.

The procedure used was P8-T-Ag which is for welding stainless steel to stainless steel.

While the weld was actually inconel to stainless steel, no evidence of' weld failure could be determined from the inspection.

ANALYSIS OF SAFETY IMPLICATION Failure of this weld could allow a breach of the reactor coolant pressure boundary resulting in primary coolant spilling from the reactor vessel and could create a make-up or excessive radiation problem within the containment.

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O FINAL REPORT ON INCORRECT WELDING PROCEDURE Page Two ON THE REACTOR HEAD VENT San Onofre Unit 2 CORRECTIVE ACTION Weld "A" has been cut out and rewelded per procedure P43-P8-T-Ag (stainless steel to inconel).

All welding has been performed in accordance with Bechtel Work Plan Procedure / Quality Control Instruction (WPP/QCI) 200.

The old weld was cut back approx-imately 1/8" from weld edge to remove all incorrect weld filler metal.

Reference Bechtel NCR P-3325 which is related to the rework performed on this weld.

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