ML19259D026

Forwards Response to IE Bulletin 78-12B Re Atypical Weld Matl in Reactor Pressure Welds.No Evidence of Weld Matl in welds.C-E Ltr Describing Results of Investigation Encl

ML19259D026
Person / Time
Site:	Fermi
Issue date:	06/27/1979
From:	Hines E DETROIT EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19259D027	List: ML19259D026 ML19259D028
References
EF2-46-909, NUDOCS 7908280437
Download: ML19259D026 (5)

Text

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_dward Hines ASS V3*f V'Cff P?f 5 0ent e Cud.y AS%rd^Ce Detroit Edison w,

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June 27, 1979 EF2-46,906 Mr. James G. Keppler I

Regional Director Directorate of Regulatory Operations Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Detroit Edison's Response to IE Bulletin 78-12B This is a response to your letter of March 19, 1979, Docket No. 50-341, IE Bulletin 78-12B, which describes " Atypical Weld Material in Reactor Pressure Vessel Welds."

Detroit Edison's response is contained in the enclosed memorandum EF2-45,356, dated June 26, 1979.

Please inform us if you require additional action by Detroit Edison regarding this matter.

Sincerely yours, Mk ,

TGB/Im Enclosure cc: Mr. John G. Davis, Acting Director Office of Inspection and Enforcement Division of Reactor Inspection Programs U.S. Nuclear Regulatory Commission Washington D.C. 20555 n -,

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1 Detroit Edison ENRICD FEPMI UNIT 2 PRTECT EtEINEERIBU June 26, 1979 EF2 - 45356

'Ib: R. W. Barr Project Quality Assurance Director 206 Engineering Construction-Troy From: W. F. Colbert d Project Engineer - EF2 318 Engineering Construction-Troy

References:

1. IE Bulletin 78-12, Septanber 29, 1978

2. EF2-42217, October 3.7, 1978

3. 'IDEC-3564, February 27, 1979

4. TDEC-3624, June 21, 1979

Subject:

" Atypical Weld Material in RPV Welds, IE Bulletin 78-12" _

The subject bulletin was issued following discovery that scme weld to used on scme B&W vessels was incorrect in chanical content and may have an adverse effect on NDT limitations for those vessels.

The bulletin basically requests each licensee to verify the weld wire used on his vessel.

Such detailas required for this verification is not part of the records package given to the licensee at the time he receives the vessel but is retained in archive files by the vessel manufacturer.

Since this bulletin was issued to ALL licensees, the most expeditious way to assemble this information was for licensees to request the NSSS suppliers to go to the vessel fabricators for the information.

Reference 2 is Edison's request to General Electric for this service.

General Electric found that vessels of the vintage of Fermi 2 did not have the exact records needed for the response. Several meetings were held between General Electric, Ocmbustion Engineering, and the NRC to determine the best means to satisfy the concern. These meet-ings resulted in issuance cf Briletin 78-12A and 12B and extensions of de.adlines. 'Ihese meetings are reported to Edison in Reference 3.

Basically, the verification process became generic rather than specific for each vessel.

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Meno to: June 26, 1979 R. W. Barr EF2 - 45356 One step in the verification process was a search for any archive material. Canbustion had no such material fran the Fermi 2 vessel no such material was shipped to Edison with the vessel; our inspection agent, Southwest Research Institute, has no such material. There-fore, no archive material is available for further verification of Fermi 2 weld metal. Our reply to the NPC is to give this inforrra-tion.

Reference 4 notifies Edison that the verification process has now been cmpleted. The information was transmitted directly from Cmbustion to the NRC on June 8, 1979. General Electric, acting on our behalf, reviewed the Canbustion transmittal and concurred that it is very unlikely atypical weld deposits exist in any RPV welds.

Reference 4 includes three attachments which give the references and verification necessary for our response to IE Bulletin 78-12.

WFC/MLB/dk D D Attachnent: 'IDEC-3624 cc: E. Lusis T. G. Byrd G. J. Butterworth Document Control (RESPONSE 'IO ACI' ION ITEMS EF2-41155 AND EF2-44501) oV o a f ()

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, GENERAL h ELECTRIC NUCLEAR ENERGY PROJECTS DIVISION GENERAL ELECTRIC MC381,(409 COMPANY)175 925-2588 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 June 21, 1979 TDEC- 3624 Mr. W. F. Colbert, Project Engineer Enrico Fermi 2 Project The Detroit Edison Company Documentation Control - Room 361 2000 Second Avenue Detroit, MI 48226

SUBJECT:

TRANSMITTAL 0F GE VERIFICATION PACKAGE FOR NRC IE BULLETINS NOS. 78-12,78-12A AND 78-12B " ATYPICAL WELD MATERIAL IN RPV WELDS"

Reference:

TDEC-3564, dated 2/27/79 General Electric Company is pleased to transmit the specific vessel verification information required by the subject NRC bulletins which are not covered by the vessel manufacturer's generic report.

In order for Detroit Edison to comply with the required response action to NRC IE Bulletins78-12A Item 2 and 78-12B Item 2, we recommend that you use the documents attached; namely (1) GE verification letter dated June 18,1979, (2) Combustion Engineering letter LD-79-036, dated June 8,1979 and (3) Combustion Engineering Certification dated June 8, 1979.

We feel the documents transmitted herewith along with the Combustior Engineering generic report transmitted to the NRC on June 8,1979 com-pletes GE's response to the subject NRC IE bulletins.

If you have any questions concerning these documents, please do not hesitate to call this office.

Very truly ours, J

C. M nson Pro Manager Enr's Fermi 2 Project

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CMJ:bjr/1132 I"7 1' '

Attachments cc: D. R. Swanson, GE, Detroit F. Gregor, Edison H. A. Konkle, GE Site D. R. Pankratz, GE Site File: Bil/6A

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GENER AL h ELECTRIC ENGINEERING GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 DIVISION June 18,1979 Gentlemen:

Subject:

Response to NRC IE Bulletin No. 78-12,78-12A and 78-12B

Reference:

Reactor Pressure Vessel: Fermi #2 In compliance with subject bulletin, General Electric NEBG requested Combustion Engineering, Inc. (C-E) to conduct a records investigation of low alloy, high tensile weld deposits used in all reactor pressure vessels built in their, or their supplier's, facilities. The purpose of this investigation was to iden-tify any other atypical weld deposit similar to the one described in Bulletin 78-12.

In response to our request, C-E has prepared a report and submitted it to the NRC on June 8, 1979 as evidenced by the attached copy of the transmittal letter.

The attached certification dated June 8,1979 has also been received.

We have reviewed C-E's report to the NRC and have not found any discrepancies germane to the problem described in Bulletin 78-12. Based on our review and C-E's statement in the report that no evidence of the use of atypical weld material in pressure vessels manufactured by them was discovered, we conclude that it is very unlikely that other similar conditions (i.e., atypical weld deposits) exist in any of their reactor pressure vessel welds.

C-E states in the body of their report that they do not have any archive material which could be used for verification purposes. Consequently, we are requesting you to review your inventory and advise the NRC accordingly (Bulletin 78-12, Item 4).

We recomend that you use this letter and the attached certification to satisfy the NRC request for verification of the generic search as outlined in IE Bulletin 78-12, Item 2.

Ver uly y r

~ h/, / f/Ls' - _-

r C." C6hn', Manager Quality Control Engineering '

nf9 Vessels, Internals & Heat Exchangers ni]/

/I d iC M/C 731, Ext. 56751 Attachment gs,