ML20037B338
| ML20037B338 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/29/1975 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009150608 | |
| Download: ML20037B338 (3) | |
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Local PCR ORB-2 Reading KRGoller Docket Mc. 50-10 TJCarter Attorney, 0GC OI&E (3)
DLZiemann C
Sn'.:calth Edison C rp:ny PW0'Connor ATiii:
I'r. J. S. Abel RDiggs Mucic?.r Licencing Aolinistrator -
JKnight Ccilir.g '..'ater Reactors ACRS (16)
Pcat Offica Box 767 Chicago, Illinois 60690 Gentlemen:
We have reviewed the Dresden Unit 1 Spent Fuel Shipping Cask Analyses sutnitted !!ay 23, 1974 and the supplement thereto submitted July 2,1974.
We have concluded that the information provided in your submittals is not sufficient to ccraplete our evaluation of a postulated spent fuel shipping cask drop accident at Dresden Unit 1.
The infomation requested in the Attachment is nee.ded so that we can continue our review of ycur sutxnittal. To enable us to maintain our review schedule please subnit the requested additional infomation by i' arch 21,1975.
Sincerely, Orfginal signed by Denn.is L. 7iemITemann, Chief Dennis L.
Operating Reactors Branch #2 Division of Reactor Licensing
Enclosures:
1.
Request for Additional Information 2.
Document (B) cc w/encls:
John W. Rowe, Esquire
' Anthony 2. Roisman, Esquire Ishan, Lincoln & Beale Berlin, Roisman and Kessler Counselors at Law 1712 N Street, N. W.
One First flational Plaza Washington, D. C.
20036 Chicaco, Illinois 60670 Morris Public Library 604 Liberty Street 90091 50[Of pnv., % m innie snacn x7403: esp hY
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RE0 VEST FOR ADDITICHAL INFO?ftATION
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-1.
The three points of vertical cask motion are the transport area, the washdown area, and the. cask loading pool, For cask handling
. operations, provide a description, with the aid of drawings, of l
how the following will be incoporated in your design:
(a) What prevents the cask from being raised more than 12 inches above the refueling floor height?
(b) How will east-west trolley travel be lir.ited to the cask travel path shown in your analysis?
(c)
How will north-south bridge travel be limited to the cask travel path shown in your analysis?
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(a)
Provide a discussion and sketch of how you plan to maintain an adequate water level for cooling the spent fuel storage pool, in the event the spent fuel cask frups and penetrates the cask loading pool bottom.
(b)
Provide an analysis of the rate of water loss from the fuel storage pool in the event that the cask drops and penetrates the cask loading pool floor.
Analyze the loss of water without.
the fuel storage pool gate in place if you propose to move the cask without the gate in place.
3.
For those cask drop accidents which you conclude will not result in penetration of the cask loading pool floct, your analysis should show that considering the loads due to a cast drop together with other design loads, the safety margins for t:;e cask loading pool are similar to the safety margins provided in the enclosed Document (B),
by the Structural Engineering Branch Division of Reactor Licensing entitled " Structural Design Criteria for Evrivating the Effects of High Energy Pipe Breaks on Category 1 Structsres Outside the Contai nment".
i The inforraation that you furnish should be es complete as indicated in the " Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants" (Revision 1), Sections 3.3; 3.5; 3.7; and 3.8.3.
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Therefore, (a)
Provide a statement that when cask drop loads are included the design criteria and the design nethods for the cask loading l
pool and its appurtenances satisfy the requiremants of Document (B) cited above; (b)
Furnish all the ';srtinent information listed in the Standard I
Fonaat in Sections cited above, especially the information on loading combination equations, codes, design methods, seismic effects, thermal gradients, etc.
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