ML19323A406

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Responds to NRC Re Violations Noted in IE Insp Repts 50-553/79-17 & 50-554/79-16.Corrective Actions:Craft Supervisors & Quality Inspectors Instructed to Conform to Specs.Other Actions Pending
ML19323A406
Person / Time
Site: Phipps Bend  Tennessee Valley Authority icon.png
Issue date: 03/14/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19323A403 List:
References
NUDOCS 8004210188
Download: ML19323A406 (3)


Text

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II March 14, 1980 i

Mr. James P. O'Reilly, Director 5

Office of Inspection and Enforcement 7j U.S. Nuclear Regulatory Commission p'

Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303 2

Dear Mr. O'Reilly:

As requested by F. W. Cantrell of your staff on March 7, 1980, enclosed

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is a revised response to noncompliance item 553/79-17-01, identified in C. E. Murphy's letter dated January 10, 1980, RII:BRC 50-553/79-17, 50-554/79-16. This respouse supersedes our previous response dated February 1, 1980, for noncompliance item 553/79-17-01. If you have any questions regarding this subject, please call Jim Domer at FTS 854-2014.

Very truly yours, TENNESSEE VALLEY AUTHORITY s

L. M. Mills, nager Nuclear Regulation and Safety Enclosure cc:.Mr. Victor Stello, Director (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

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An Equal Opportunity Employer 80042LO)l N

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ENCLOSURE REVISED RESPONSE TO NRC-0IE LETTER i

FROM C. E. MURPHY TO H. G. PARRIS DATED JANUARY 10, 1980

(

REFERENCE:

RII:BRC 50-553/79-17, 50-554/79-16)

This report is a revised response to the Notice of Violation described in Appendix A, Item A, of the OIE Inspection Report referenced above.

This is provided as requested by Inspector F. W. Cantrell in our telephone conversation with him on March 7, 1980. This report supersedes our previous report dated February 1,1980, on Infraction 553/79-17-01.

Our response to Infraction 553/79-17-02 is unchanged.

Noncompliance Item - Infraction 553/79-17-01 A.

As required by Criterion V of Appendix B to 10CFR50, and as implemented by paragraph 17.lA.5 of the FSAR, " Activities affecting quality shall be prescribed by documented instructions, procedures, and drawings... and shall be accomplished in accordance with these instructions, procedures, and drawings."

Paragraph 14.9 of process specification 1.M.1.2(b) of General Construction Specification G-29M, applicable to containment shell welding, limits the bead width resulting from weaving to 5/8-inch maximum for the gas metal arc (including flux cored) process.

Contrary to the above, on December 12, 1979, bead widths of 3/4-inch to 7/8-inch on containment shell welds IT 2301629 and IT 2301631, welded with the flux cored process, were observed.

Discussions with the inspection personnel revealed that weaving the full width of the joint until the joint is full has been the practice in the past.

This results in a bead width of one inch or greater at the top of the joint.

This is an infraction.

REVISED RESPONSE 1.

Corrective Steps Taken and Results Achieved All work on the two containment shell welds cited in the infraction was stopped. A quality control investigation report (QCIR) was written to document and follow this situation. All gas metal are flux core welding in accordance with General Construction Specification G-29M is now being accomplished with a 5/8-inch maximum weave width.

Disposition o.

these two welds was predicated on the results of test performed at TVA's Singleton Materials Engineering Laboratories (Singleton) to determine the effect of weave width larger than 5/8 inch.

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.' t The results of the initial test at Singleton on which the February 1, 1980, response was based indicated that the properties of the wcid and adjacent heat-affected zone met the applicable section of the ASME Code, Subsection KE, with the larger weave width. However, later test results failed to support the original conclusion. As a result of these later test findings, NCR PBN-067 has been deemed

" reportable" under 10CFR50.55(e).

This condition was reported to Inspector R. W. Wright on March 6, 1980.

In NCR PBN-067 R1, TVA has recommended the removal of the weld metal disposited in excess of the 5/8-inch maximum weave width requirement. However, the final decision on corrective actions will be determined by the Tech '

Engineer, General Electric /C. F. Braun.

2.

Action Taken to Prevent Recurrence Craft supervision and quality control inspectors were instructed on December 17, 1979, to conform to requirements of applicable specifications and codes on all work.

3.

Date When Full Compliance Was Achieved Full compliance on the welds made with excessive weave widths will not be attained until NCR PBN-067 R1 is dispositioned and corrective actions on those welds are accomplished.

If C. F. Braun accepts the TVA recommendation, the work is expected to be completed by September 30, 1980.

All gas metal arc flux core welding performed subsequent to December 17, 1979, has been in full compliance with General Construc*. ion Specification G-29M.

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