ML20154B896
| ML20154B896 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 03/27/1972 |
| From: | Stiede W COMMONWEALTH EDISON CO. |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20154B886 | List: |
| References | |
| FOIA-85-782 1702, NUDOCS 8603040488 | |
| Download: ML20154B896 (1) | |
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March 27, 1972 l
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Mr. Roger S. Boyd, Assistant Director
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Subject:
Structural Integrity of the Quad-Cities Tori
Dear Mr. Boyd:
This is i'. response to your letter of March.13 in which you reque', Led an evaluation of the structural components of the Quad-Cities tori.
In _ July _1971, an evaluation was made of the structural components and on the basis of this evaluation, modifications were made to the supporting structure and anchorages of the piping within the tori.
This modification has been completed and is the same as that proposed for the Monticello plant.
Should you have any additional questions, please let me know.
Very truly yours,
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Wayne L.
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OCG Connonwealth Edison Company CO (2)-
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ATTN:
Mr. Byron Lee, Jr.
FWilliams' Assistant to the President HSmith.
P.O. Box 767 ACRS (16)
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Calcago, 1111noin 60690 Centlemen:
A recent inspection made by Northern States rouer Company at their Monticello plant revealed structural damage to bafflen and other struc~
l tural components installed in the torun-shaped suppression pool from
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the dynamic effects resulting froni the normal reactor coolant systen olowdown tiirough the relief valve discharge linea into the suppression pool. Tac.iorthern States Pouer Company, assisted by the General Electric Courany, in addition to renoving the baffles, has taken correctivo steps regarding the other structural damage incAuding the anchorages for the blowdown discharge pipes.
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j Ue appreciate that the Quad Citica Unita 1 and 2 tori do not have j
baffles. Ilowever, in order that ue may access the structural safety in the tori of the Quad Cities plants, please provide us with your evaluation I
of the effects of all blowdown forceu into the torus on the vent pipe l
anchorages and other torus structural components and a proposed course of action to avoid any safety prob 1ctus in the event these offccta exceed
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acceptable structural design criteria. Please let us la.ou uithin tuo
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uecka your senedule for the c~bmittal of ti.c requented inforuation.
f Sincerely, Original signed by:
l Roger S. Boyd Ro;;u r S. Loyd, Acuintant Director
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for aoilina, inter Reactors Divisiva of Reactor Licensiar cc: John 11 Rove Ishan, Lincoln 6 ueale Counselorn at Law e
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