ML20137C705
| ML20137C705 | |
| Person / Time | |
|---|---|
| Issue date: | 03/20/1997 |
| From: | Cwalina G NRC (Affiliation Not Assigned) |
| To: | Moore K BABCOCK & WILCOX CO. |
| References | |
| NUDOCS 9703250094 | |
| Download: ML20137C705 (3) | |
Text
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_ _ _.. _ _ _ _. _ _ _.. _ _ ~ _. _
March 20, 1997
~~Mr. Ken Moore, Manager Materials and Structural Analysis (MS OF50)
Framatome Technologies, Inc.
4 3315 Old Forest Road P.O. Box 10935 Lynchburg, VA 24506-0935
SUBJECT:
FUTURE NRC INSPECTION OF FRAMATOME TECHNOLOGIES, INC.
Dear Mr. Moore:
This letter confirms the dates of May 19, 1997, through May 21, 1997, for an NRC inspection of Framatome Technologies, Inc. This date was established in a telephone call between Mr. Barry Elliot of the NRC and yourself on February 28, 1997.
We plan to review your records pertaining to the chemistry of submerged arc welds used in reactor pressure vessels fabricated by Babcock & Wilcox. To facilitate the review, we request that you have the information listed in the enclosure available for our review on the first day of the inspection.
We look forward to your cooperation on this inspection.
If you have any questions, please contact Mr. Barry Elliot at (301) 415-2709.
Sincerely, ORIGINAL. SIGNED Gregory Cwalina, Chief Vendor Inspection Section Special Inspection Branch i
Division of Inspection and Support Programs
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Mr. Ken Moore, Manager Mat *erials and Structural Analysis (MS OF50)
Framatome Technologies, Inc.
3315 Old Forest Road P.O. Box 10935 Lynchburg, VA 24506-0935
SUBJECT:
FUTURE NRC INSPECTION OF FRAMATOME TECHNOLOGIES, INC.
Dear Mr. Moore:
This letter confirms the dates of May 19, 1997, through May 21, 1997, for an NRC inspection of Framatome Technologies, Inc. This date was established in a telephone call between Mr. Barry Elliot of the NRC and yourself on February 28, 1997.
We plan to review your records pertaining to the chemistry of submerged arc 4
welds used in reactor pressure vessels fabricated by Babcock & Wilcox.
To facilitate the review, we request that you have the information listed in the enclosure available for our review on the first day of the inspection.
We look forward to your cooperation on this inspection.
If you have any questions, please contact Mr. Barry Elliot at (301) 415-2709.
i Sincerely, ORIGlitALS027 BY Gregory C:. Cwalina, Chief Vendor Inspection Section Special Inspection Branch Division of Inspection and Support Programs j
Enclosure:
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Enclosure 4
j INSPECTION DOCUMENTATION During the NRC Vendor Inspection on May 19 through May 21, 1997, we request j
the following from Framatome Technologies, Inc.:
I 1.
Describe the records and the process for determining the chemistry (percent copper and nickel) of submerged arc reactor pressure vessel beltline welds and reactor pressure vessel material surveillance welds fabricated by Babcock & Wilcox.
i 2.
Provide the heat numbers for all copper coated weld wire used to l
fabricate submerged arc welds in beltline welds in PWR and BWR reactor vessels that were fabricated by Babcock & Wilcox.
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3.
For each capsule in the Babcock & Wilcox Owners Group Master Integrated Surveillance Program that has been withdrawn, identify whether chemistry i
data (percent copper and percent nickel) has been reported from either unirradiated or irradiated surveillance submerged arc weld metal.
[
Identify and provide the surveillance capsule report that contains the 4
data.
4.
For each heat number in Item 2, provide chemistry data (percent copper, i
percent nickel and the number of data points from each capsule, drop l
out, weld metal qualification test, etc.) from the following sources:
i (a) in-process testing such as weld metal qualification tests (b) drop out from vessel fabrication I
(c) reactor vessel surveillance welds j
(d) other fabrication sources i
j 5.
Using all of the data'provided in response to Item 4, provide the best-estimate chemistry for each heat of weld wire in the beltline of reactor vessels fabricated by Babcock & Wilcox.
Explain the method of determining the best-estimate values.
i 6.
Using all of the reactor vessel surveillance data provided in response to Item 4, provide the best-estimate chemistry for each reactor vessel l
surveiliance weld.
Explain the method of determining the best-estimate l
values.
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