ML20141D976
| ML20141D976 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/02/1986 |
| From: | Miosi A COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20141D981 | List: |
| References | |
| 1506K, NUDOCS 8604080341 | |
| Download: ML20141D976 (1) | |
Text
r CN Commonwealth Edison l
) One First Nationti Plaza, Chicago Ithno s (T 7 Address R;pfy to. Post Othee Box 767
/ Chicago. Ilhnois 60690 April 2, 1986 Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC. 20555
Subject:
Braidwood Station, Unit 2 Reactor Vessel Nozzle Analysis NRC Docket No. 50-457
Dear Mr. Denton:
Enclosed please find two (2) copies of the ASME Code Evaluation of the Braidwood Unit 2 Reactor Pressure Vessel Inlet Nozzle "F" dated February 28, 1986, and performed by the General Electric Company.
This analysis was performed because of the rejectable surface planar indication in the inlet nozzle "F"
to shell weld (weld number WR-19) found during the Combustion Engineering ultrasonic examination of the Unit 2 reactor vessel preservice inspection.
This report demonstrates that the ASME Code Section III requirements are maintained when including the effects of a grindout of up to one (1) inch in depth with a three (3) to one (1) tapering, without weld repair.
The results of this analysis are being forwarded for your review and approval.
Additional copies can be provided without the color graphics.
If you have any questions concerning this matter please contact this office.
G Very truly yours, 8604080341Ohh57 PDR ADOCK O PDR ha Nfle:
A W
A.
D. Miosi Nuclear Licensing Administrator
/klj cc:
J.A.
Stevens
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