ML19274F833

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Forwards Weld Wire Data Rept,In Response to IE Bulletins 78-12 & 12A & 790430 Certification.W/O Encl
ML19274F833
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/01/1979
From: Oehlkers W
CBI NUCLEAR CO.
To: Reinmuth G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML19274F832 List:
References
NUDOCS 7908090004
Download: ML19274F833 (1)


Text

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g p May 1, 1979 U. S. Nuclear Regulatory Com:nission Attn: Mr. G. W. Reinmuth, Assistant Director I;uclear Regulatory Committee Reactor Construction Inspection Division Bethesda MD 20555 RE: WELD WIRE DATA REPORT REQUIRED BY UUCLEAR REGULATORY BULLETIN 78-12, DATED 9/29/78 AND SUPPLEMENT 78-12A, DATED 22/14/78 Gentlemen:

Enclosed is the CDI Muclear Co. report required by the referenced HRC Bulletin 78-12. This report covers the following reactor vessel as indicated below:

CBIN G>E. CBIN G.E.

COUTRACT ? PROJECT COMTRACT ? PROJECT 72-2046 LaSal'a " 73-C119 TVA X17 C /2-2505 72-2647 Q Creek.ID Hanfora 11 73-Cl20 Allens Creek I 73-Cl21 TVA X19 72-C102 Nine Mile II 73-C123 TVA X18 73-C108 Perry I 73-C109 Grand Gulf I 73-Cl25 Skar3 i t I 74-Cl27 TVA X20 73-C110 Grand Gulf II 74-C129 River Rend II 73-C112 River Bend I 74-Cl31 TVA X21 73-Cll4 Perry II 74-C132 TVA X22 Should you have any questions, please do not hesitate to call.

Very truly yours,

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0809cycY y, c , n, ,1, , ,,,

HOA Coordinator

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The documentation and information required by NRC Bulletins 78-1.2  !

and 75-12A for CBIN CONTPACT i72-2505 Vessel Hope Creek II are contained in the attached report.

Welding consumables were re-reviewed against the original require-No deviations ments in accordance with the above listed documents.

were found.

Based upon our records, I certify, to the best of my knowledge, this report is correct.

OJA DW W. G. Oehlkers 4 -3 0 7 7 Date NOA Coordinator '

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Subject:

RESPONSE TO NRC IE BULLETIri tiO. 78-12,78-12A and 78-12B

Reference:

Reactor Pressure Vessel: Hope Creek II Gentlemen:

In compliance with subject bulletin, General Electric f4EBG requested Chicago Bridge and Iron liuclear Company (CBIN) tof conduct a records investi-gation 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 identify any other atypical weld deposit similar to the one described in Bulletin 78-12.

In response to our request, CBIN has prepared a repcrt and submitted it to the NRC, as evidenced by the attached letter dated .May 1,1979. The report _ __

contains the attach.ed certification dated 4/30/79.

We have reviewed CBIN's report to the NRC and have not found any discrepan-cies. Consequently, we concuc with their certification and conclude that it is very unlikely that other, similar conditions (i.e., atypical weld deposits) exist in any reactor pressure vessel welds.

CBIli, in a separate communication to us, has stated that they do not have any archive material. Consequently, we are requesting that you review your inventory and advise the NRC accordingly1 Bulletin ~78-12,' Item 4)7 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.

Very truly yours /' RECElv e ,_,

MAY llli -l-l

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V Werhet C.'Cohn, M'anager Quality Control Engineering 4"E9N3 c"**8k'#

Vessels, Internals & Heat Exchangers M/C 731 - E - 56751 '/) . f-- .