ML20235H142
| ML20235H142 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/07/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 3308K, NUDOCS 8707150028 | |
| Download: ML20235H142 (2) | |
Text
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One First National Plaza, Chicago, Illinois Address Riply to: Post Oft:ce Box 767 Chicago, Illinois 60690 0767 July 7, 1987 Mr. Thomas E. Murley, Director i
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 l
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Subject:
Braidwood Nuclear Station Units 1 & 2~
J ASME Code Case N-340 NRC Docket Nos.-50-456 and 50-457 I
References (a): March 2, 1983 T.R. Tramm letter to H.R. Denton (b): May 3, 1983 B.J. Youngblood letter to
)
I D.L. Farrar (c): November 2, 1984 D.H. Smith letter to H.R. Denton
Dear Mr. Denton:
Reference (a) informed you of our intent to utilize ASMB Code Case N-340 at our Byron and Braidwood generating stations and requested i
acknowledgement of its acceptability. This code case, which was approved by ASMS on June 17, 1982, provides alternate rules for examination of weld edge preparation and ultrasonic examination of a completed weld. ' Reference (b) provided the NRC position that the Code Case was not acceptable for generic use.
It was indicated however, that the use of the Code Case would be acceptable if the reason for not performing edge examinations in accordance with the ASMS Section III Code and justification for applying the Code case were explained. Reference (c) provided the reasons and justifications to utilize Code Case N-340 for the instances presented for Braidwood Station Unit 1.
The purpose of this letter is to provide supplemental information to reference (c) addressing additional welds where Code Case N-340 was used at Braidwood Station.
8707150028 870707 PDR ADOCK 05000456 P
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,~s T.E. Murley July 7,'1987 l
In addition to the welds described in reference (c) four (4)
I additional Braidwood Station primary loop weld edge preparations were not Liquid Penetrant examined prior to welding.
Two (2) are in Unit 1 and two' j
(2) are in Unit 2.
The machined weld edge preparations, or the weld edge surfaces exposed after removal of the Steam Generator shipping caps, were inadvertently not examined.
For each weld, the testing requirements of the code case and other examinations, such as Radiography, required by the ASME Section III code were accomplished. The use of the code case eliminated the need for extensive repairs and the subsequent possibility of stainless' steel sensitization.
l This is being provided for-your information.
Please address any questions concerning this matter to this office, j
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Very truly yours, l
J l
dCL Q
S. C. Hunsader i
Nuclear Licensing Administrator I
cc:
J. Stevens i
Braidwood Resident Inspector l
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1 3308K.
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