ML20002B000

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Interim Deficiency Rept on Degradation of Fuel Pool Penetration Piping,Initially Reported on 801103.Contractor Was Directed to Identify & Investigate Problem.Final Rept Will Be Submitted by 810301
ML20002B000
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 12/03/1980
From: Davidson D
CLEVELAND ELECTRIC ILLUMINATING CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8012090300
Download: ML20002B000 (2)


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P o. Box 1300 o CLEVELAND, CHlo 44101 e TELEPHCNE (216) 622 9t100 e ILLUMIN ATING BLoo e SS PUBUC$oVARE Oalwyn R. Davidson smg e Ben iccaticn in me Nation viCE PAESiCENT SYSTEu ENGINEERING AND CONSTRUCfiCN December 3,1980 Mr. James G. Keppler j

Director of Region III Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE:

Perry Nuclear Power' Plant Docket Nos. 50-440; 50-441 Interim Report on Degradation of Fuel Pool Penetration Piping (G-41 System)

Dear Mr. Keppler:

This letter serves as an Interim Report as required by 10CFR50.55(e) concerning the degradation of the G-41 Sys tem, fuel pool penetration piping.

This was first reported by W. J. Kacer of the Cleveland Electric Illuminating Company to J.

Konklin of your office on November 3, 1980.

This report includes a description of the deficiency, a statement of possible safety implications, and the corrective action taken to date.

i Description of Deficiency While performing additional investigation to determine acceptability and f

provide adequate justification to a proposed "Use As Is" disposition to NCR's53-182 and 53-204, the following deficiency was identified.

During the process of making the attachment welds between the ' fuel pool liner and leak chase to the G-41 System (fuel pool cooling and clean-up),

there was an apparent misapplication of the welding procedure. This' resulted in an excessive heat input to the pipe material (SA 112-304 stainless steel) causing an oxidation and expulsion of base material from the inside diameter of the pipe. This resulted in a thinning of the pipe wall to varying deg.ees.

In one identified area, there is a cavity approx-imately.125 inches deep in a pipe with a nominal wall of.165 inches.

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  • f Mr. James G. Keppler

' 2-December 3, 1980 Statement of Possible Safety Implications This piping system is designated ASME Section III, Class 3.

The deficiency is Itaited to the penetration piping to the lower pools located in the fuel-handling area of the Intermediate Building.

This system has a design pres-i sure of 150_psig and operating temperature of 127'F (below 150*F when larger than average amounts of spent fuel are stored in the pool). The affected piping had been hydrostatically tested at 187.5 psig and accepted. The mat-

. erial specifications for SA 312 material requires minimum wall at any point shall not be more.chan 12.5 percent under the nominal wall thickness specified.

This deficiency would have gone undetected had it not been for the additional, more restrictive inspections requested to provide adequate basis for a "Use As Is" disposition to two Nonconfor=ance Reports which document a sof tware defi-ciency.

Corrective Action Taken to Date i

The Construction Quality Engineering Unit has initiated Nonconformance Report

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CQA-178 documenting known deficiencies in two penetrations and the indeterminate status of twenty-four additional assemblies.

This NCR has been dispositioned, directing the contractor responsible for the deficiency to investigate and fully identify the problem. He is also to provide a recommended disposition based on.nerallurgical sampling.

Evaluation of the proposed disposition to assure system reliability and safety will be complaced and a final report submitted by March 1, 1981.

Very truly yours, 1

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Dalwyn/. Davidsc:.

Vice President System Engineering and Construction t

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J. Hughes U.S. NRC -- Site i

Mr. Victor Stello', Director Office of Inspec lon and ' Enforcement 4

U. S. Nuclear Regulatory Commission I

Washington, DC 20555 U. S. Nuclear Regulatory Commission 9 i

c/o Document Management Branch Washington, DC 20555

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