ML19262A529

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Ack Receipt of Transmitting Rept BAW-1403 & Transmitting Revision 1.Concludes That Reasonable Assurance Exists That Mechanical Properties of 70XX & 80XX Matls within Acceptable Tolerance
ML19262A529
Person / Time
Site: Crane  Constellation icon.png
Issue date: 06/19/1973
From: Engelken R
US ATOMIC ENERGY COMMISSION (AEC)
To: Mallay J
BABCOCK & WILCOX CO.
Shared Package
ML19262A527 List:
References
NUDOCS 7911130536
Download: ML19262A529 (2)


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UNITED STATES y 4 7, ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20$45 5

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JUN 191973 Babcock & Wilcox Company ATTN:

J. F. Mallay Manager, Licensing P. O. Box 1260 Lynchburg, Virginia 24505 Gentlemen:

This will acknowledge receipt of your report number BAW-1403 transmitted with your letter dated April 30, 1973, and Revi-sion 1 thereto dated June 1973 transmitted with your letter dated June 5, 1973. We have reviewed this report and note that the various lots of 70XX and 80XX - ;3 metal with undocu-mented mechanical properties, have satisfactory chemistry documentation. Experience has demonstrated that the tensile and impact values of 80XX and 70XX materials rarely fail to meet the ASTM minimum requirements. We have therefore con-l cluded that there is reasonable assurance that the mechar,1 cal properties of these 70XX and 80XX =aterials will be within acceptable tolerance. We also recognize that to remove and replace this material at this point in time may prove to be more deleterious than the acceptance of the "as is" conditions.

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On this basis we have concluded that those =ajor components involved, are acceptable for their intended service.

As you are aware, the lack of documented mechanical properties for these lots of weld estals, is in nonconfor=ance with the ASME Boiler and Pressure Vessel Code to which these components were designed and fabricated. We understand that you intend to pursue this matter further with the cognizant code authorities.

The impicmentation and effectiveness of your corrective action to prevent recurrence will be reviewed and evaluated during our continuing inspection program.

Your letter of June 5, 1973, states that the weld records were complete for the reactor vessels manufactured for other NSS vendors.

Mr. Steinke of vour etaf f F fer ed us by tele-phone on June IJ, 1973, enat, during the time period covered, reactor vessels were the only reactor coolant systen com-ponents manufactured for other NSS vendors.

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