ML19098B467
| ML19098B467 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/10/1976 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Serial No. 894 | |
| Download: ML19098B467 (2) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RIOHMOND, VIRGINIA. 23261 Attn:
Mr. Robert W. Reid, Chief Operating Reactors Branch 4
Dear Mr. Rusche :
In a meeting between the Regulatory Staff and Vepco personnel in Bethesda on September 17, 1975 the results obtained from the analysis of the radiation material surveillance capsule, Capsule T, which was removed during the first refueling of Unit No. 1, Surry Power Station, were discussed.
At that meeting, we agreed that we would reconfirm the copper content in the weld material as reported in the Battelle report.
Contained hereinbelow are the results of the chemical analyses of samples removed from the surveillance capsule.
Six samples from two.irradiated weld metal Charpy specimens were analyzed for copper content.
The method involved a preliminary copper thiocyanate sep-aration following a volumetric postassium iodate titration.
The procedure was tested by analyzing NBS cast iron Standard Reference Material 6 g containing
.0.502 + 0.018 (2cr) per cent copper.
Eight analyses of this standard showed an average copper content of 0.476 + 0.013 (2cr) per cent.
This value is somewhat (5.2 per cent) lower than the NBS reported average value but is within the limits of precision of the two analyses.
Three samples were drilled from each decontaminated and ultrasonically cleaned Charpy specimen near the center notch area.
The copper content was de-termined to be as reported below:
Sample W2-A W2-B W2-C W8-C W8-D W8-E Sample Weight (g) 0.7558 0.7543 0.7545 0.7560 0.7598 0.7532 Copper, %
0.225 0.221 0.220 0.223 0.217 0.221 1388
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VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Benard C. Rusche Page 2 Change in copper concentration due to 63cu (n,y) 64cu (n,y) 66cu and 64Ni (n,y) 65Ni reactions were calculated to be negligible due to the relatively low cross section values involved.
Very truly yours,
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C. M. Stallings Vice President-Power Supply and Production Operations