ML19207B130
| ML19207B130 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/29/1979 |
| From: | Staffa R GEORGIA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7908230426 | |
| Download: ML19207B130 (1) | |
Text
.h.
Gemg a Pce Cc. c.aN 230 Pear-re s" -
t, Post 0"'ce 60 4545 A? 393 Gef; a ]
3 in;nre.n4s2 c.
s][y79 p(-.
' M 7, (ieorgiti Power Power Supply Engineering 3nd $yig4 p4 3
June 29, 1979 United States Nuclear Regulatory Commission
REFERENCE:
Office of Inspection and Enforcement RII: JPO Pegion II - Suite 3100 50-321 101 Marietta Street Atlanta, Georgia 30303 50-366 ATTENTION:
Mr. James P. O'Reilly Gentlemen:
The following information is submitted in response to IE Bulletin 79-12 and it's supplements.
A generic report and it's supporting data was forwarded on June 8, 1979, to the NRC per the requirements of IE Bulletin 78-12A, paragraph 1, from Com-bustion Engineering, the Hatch vessel manufacturer. (see attached letter ).
The two enclosed letters and their attachments contain the information required by the Bulleti. which is not covered by the vessel manufacturer's generic report.
These letters indicate that General Electric has reviewed the generic report, and that it adequately represents data for the Hatch 1 and 2 vessels.
Based on General Electric's review of the report, we are satis-fled that the generic report is adequate as prescribed in Bulletin 78-12B, paragraph 2.
In response to item four of Bulletin 78-12, we have reviewed our inven-tory and determined that no archive weld materials are available for verifi-cation purposes.
Very truly yours, m
)
[
l h/ / j o
/
f
/ \\ ((
// //t-f
- d. W. Staffa y
Itanaget of %iality Assurance
'93 JAB /bg Enclosures xc:
U. S. Nuclear Regulatory Commission
'$.U36 Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C.
20555 7908230#4 7/0'A9 n i -me m. v ~L..
' ~
C E Power Systems Tel 203rr88-1911 Combustion Engineenng. Inc.
Telex 9 9297 1000 Prospect mit Road Windsor. Connecticut 06095 POWER bm@ elm SYSTEMS June 8, 1979 LD-79-036 Mr. Harold D. Thornburg Division of Reactor Construction Inspection Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
I&E Bulletin 78-12, " Atypical Weld Material in Reactor Pressure Vessel Welds"
Dear Mr. Thornbt.rg:
Enclosed please find three (3) copies of a document entitled "Information Requested by I&L Bulletin 78-12, Atypical Weld Material in Reactor Pres-sure Vessel Welds."
This report is being submitted directly to the WRC by Combustion Engine-ering as permitted by Supplement A to the Bulletin.
It is expected that holders of Construction Permits and Operating Licenses will reference this' report in responding to the Bulletin on their individual dockets.
Should you have any questions, please feel free to call me or Mr. E. H.
Kennedy of my staff at (203)686-1911, extension 2828.
Very truly yours, COMBUSTION ENGINEERING, INC.
A. E.
cherer Licensing Manager AES:dag Enclosure
{
GENER AL h ELECTRIC
" " " " ^ " """""
ENGINEERING GENERAL ELECTRIC COMPANY 175 CURTNER AVE., SAN JOSE, CALIFORNIA 9512s DIVISION June 18,1979 Georgia Power Company Production Department P. O. Box 4545
- Atlanta, GA 30302 Gentlemen:
Subject:
Response to NRC IE Bulletin No. 78-12,78-12A and 78-12B
Reference:
Reactor Pressure Vessel:
Hatch #1 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 certi fication dated June 8,1979 has also been received.
We have reviewed C-E's report to the NP" and have not found any discrepancies germane to the problem described in Bulietin 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 pressu e vessels manuf actured by ther, was discovered, we conclude that it is very unlikely that other similar cond tions (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 fr verification of the generic search as outlined in IE Bulletin 78-12, Item 2.
Ve rulyyobr7 I
,,, J sfy.
Werher. E, Manager Quality Control Engineering 7 g gg Vessels, Internals & Heat Exchangers N/C 731. Ext. 56751 Attachment gs
C-E Power Systems Tel. 615/265 4631 Combustion Engineering. Inc.
911 W. Main Street Chattanooga. Tennessee 37402 POWER SYSTEMS June 8, 1979 I
/
/
I hereby certify that the record search required by I.E.
Bulletin 78-12 and 78-12A has been completed and that, to the best of my knowledge and belief, the report submitted to the NRC on June 8, 1979, entitled, Information Requested by NRC Inspection and Enforcement Bulletin No. 78-12, " Atypical Weld Material in Reactor Pressure Vessels", addresses all of the applicable materials used in the fabrication of the following reactor vessel:
C-E Contract No.:
3157 Utility / Site:
Southern Services Hatch 41 t
W. A. Stone, Jr., Manager Nuclear Quality Assurance Chattanooga Nuclear Operations 784199 e
GENER AL h ELECTRIC
"*"^a"""a" ENGINEERING GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CAUFORNIA 95125 DIVISION June 18, 1979 Georgia Power Company Production Department P. O. Box 4545 Atlanta, GA 30302 Gentlemen:
Subject:
Response to NRC IE Bullet.
-. 78-12,78-12A and 78-12B
Reference:
Reactor Pressure Vessel:
Hatch #2 In compliance with subject bulletin, General Electric NEBG requested Combusticn 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 gennane 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 requestin]
you to review your inventory and advise the NRC accordingly (Bulletin 78-12, Item 4).
We recommend 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.
Ye l
tru/yyor,
/.
We er'C.lohn, Manager Quality Control Engineering
,bmdO i
Vessels, Internals & Heat Exchangers M/C 731. Ext. 56751 Attachment 9s
C-E Power Systems Tel. 615/265 4631 Combustion Engineenng. Inc.
911 W Main Street Chattanooga. Tennessee 37402 rss POWER "J SYSTEMS June 8, 1979 I hereby certify that the record search required by I.E.
Bullet.in 78-12 and 78-12A has been completed and that, to the best of my knowledge and belief, the report submitted to the NRC on June 8, 1979, entitled, Information Requested by NRC Inspection and Enforcement Bulletin No. 78-12, " Atypical Weld Material in Reactor Pressure Vessels", addresses all of the applicable materials used in the fabrication of the following reactor vessel:
C-E Contract No.:
11570 Utility / Site:
Southern Services Hatch #2
. /
W. A.
Stone, Jr., Manager Nuclear Quality Assurance Chattanooga Nuclear Operations N'lr303.
%