ML19318B748

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Ack Receipt of 800502 Final Deficiency Rept Re Weld Wire Documentation
ML19318B748
Person / Time
Site: Hope Creek  
Issue date: 06/04/1980
From: Robert Carlson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Martin T
Public Service Enterprise Group
References
NUDOCS 8006300005
Download: ML19318B748 (1)


Text

' *n te UNITED STATES d

h NUCLEAR REGULATORY COMMISSION REGION I E

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$31 PARK AVENUE t

KING OF PRUS$1 A, PENNSYLVANI A 19406 Docket Nos. 50-354 JW 04 m 50-355 Public Service Electric & Gas Company ATTN: Mr. T. J. Martin Vice President Engineering and Construction 80 Park Place Newark, NJ 07101 Gentlemen:

Subject:

Weld Wire Documentation (Your letter of May 2, 1980)

Thank you for your letter, referenced above, which forwarded a final report pursuant to 10 CFR 50.55(e) regarding the subject matter.

Your report will be reviewed and evallated, and should we require additional information concerning this matter, we will contact you.

Your cooperation with us is appreciated.

Sincerely, t

u Robert T. Carlson, Chief Reactor Construction and Engineering Support Branch cc:

E. N. Schwalje, Manager - Quality Assurance, Engineering and Construction Department 1800630oooy

a r w

L Thomas J. Martin Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-8316 Vice President Ervoneering and Construction May 2, 1980 Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

WELD WIRE DOCUMENTATION 10CFR50.55(e), PCfrENTIAL SIGNIFICANT DEFICIENCY NO. 1 AND 2 UNITS HOPE CREEK GENERATING STATION On August'31, 1979, a verbal report was made to Region 1, Office of Inspection and Enforcement representative Mr. L. Narrow, ad-vising of a potential significant item regarding a discrepancy in the procurement of weld wire.

This verbal report was provided in accordance with'the provisions of 10CFR50.55(e).

Supplemental information was submitted in writing to Region 1, Office of Inspection and Enforcement on September 26, 1980, January 18, 1980 and March 14, 1980.

The following information is a final report concerning Pittsburgh Des Moines' use of 8018-C3 weld filler metal.

The filler metal was used in post-weld, heat-treated weldments for NF applications, but was tested for only the as-welded condition.

The results of the investigation of the heats of filler metal follows:

A total of four heats of filler metal are involved:

I.D. A 2998 I.D. A 2138 I.D. A 3297 I.D. A 8913 I.D. A 2988 - Tests qualifying this heat in the-post-weld, heat-treated condition were performed by the electrode manufacturer.

I.D. A 2138 & I.D. A 8913 - Full-thickness coupons were removed from completed welds in the post-weld, heat-treated condition and were tested.

The results indicate that the filler metal meets ASME code and design specification standards, 8 C d Sc 7 0 5~ S 9 s

e

Boyce H. Grier 5/2/80 I.D. A 3297 - Although tests on this heat of weld filler material proved to exceed the required tensile strength, the welds con-taining this heat have been totally removed.

The design deficiency which led to the procurement of weld filler metal which was not tested in the post-weld, heat-treated condition has been corrected.

As reported in the January 18, 1980 interim report, PDM has issued a new electrode specification, ES-7.5.2, Rev. A which requires testing of E8018-C3 filler metal in both the as-welded and the post-welded, heat-treated condition.

Attendant PDM welding procedures WPS 70-71, Rev. A, WPS 70-72, Rev. B and WPS 73-73, Rev. H have been revised to reflect the specification requirement.

Should additional informatir,n be desired, we will be pleased to further discuss it with yot.

Very truly yours,

/

CC Office of Inspection & Enforcement Division of Reactor Construction Inspection Washington, DC