ML20037B002
| ML20037B002 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/06/1964 |
| From: | Bower D COMMONWEALTH EDISON CO. |
| To: | Lowenstein B US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8008280688 | |
| Download: ML20037B002 (7) | |
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- Mr. Robe rt Lowenstein, Dir3ctor Division of Licensing and Regulation 3h g m *., w. M U. S. Atomic Energy Commission b j-
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3et "Jocket No. 50-10' Ocar Mr. L:n.enstein :
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s ?ursuant to Paragraph 3.a. ( 5) of License 0?'-2, as snended (D?R-2),
Commenwealth Edison Company has requested that Appendix 'A" of 0?R-2 he atended to allow receipt sad operstien cf i special fuel :ssembly, desipated SA-1.
Design,.7escription and Hazards Evaluatien Dat't pertinent to this Mquest have been transmitted in cur letters of Tebruary 26, 1964 (amend :ents to ;?R-2) and Tebruary 27, 1964 (accroval to receive). Fewever, additional data and pmcedures were requested pursuant to a meeting held at 2athssda, Maryland, March 3,1964 The exhibits listed below and appanded hereto, detail this desired informatien.
Exhibit A
" Irradiated Tuol Il2=ent 3 hipping Cask
- nicading Procedure" which, for purposes of this submittal, are to be utill:ed with respect to 'destinghouse "lectric Corporation's '.73 Cask, 3ureau of Exolosives 'fo.
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Exnibit 3
" Irradiated Tual Assenbly SA-1 Handlin9, P rocedure".
In our opinion, the data transmitted in our earlier correspondence (referenced above) in conjunction with the procedures attached herewith, indicate that receipt and operation of special assembly SA-1 at Oresden will not involve hazards greater than or materially different from those considered by the Commission in authorizing License DPR-2, as anended, nor will receipt of special assembly SA-1 constitute a material alteratien to the facility.
Very truly yours, l
l COMMCW4EALTH 3DISCN COMPANY
- *y, r s By D. R. 3ower Submitted and swom to before Treasurer me this 6 Sit day of March,1964 by said D. a. Bewer.
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...o The follcwing operations will be perfor.ed by plant perscnnel under the direct supervisien of the Ohif In;;inear or his dosi;;nnted qualified alterna 3.
Radiatica protecticn persennel will r.cnitor activities as required.
1.
Inspec leaded cask a.d chipping strue:ure for cny avidence of dama ;e upon m.rrival at site.
2.
Re cve prc cc ive davices and unlock drain a.d ven:
valves.
3.
Ocnnec pressure 3ause :: ven: valve and read cask i.ternal pressure. Connect ?criable pctentiererer to thereccouple junctica bcx and read internal ter.periture.
If cask cres:ure is abeve at=cspheric, a sample of the cas or water uill be taken r.d analyzed to datermina tha athed of ventin.
Jeterrination of gas er water will be made by cracking ven; hose to fuel pcol overficu cha.ber which dischar;;es :c the collec:cr tank a: the radioactive waste building. The over-flow chamber is also exhausted by the fuel building exhaus:
syste=.
D.is assures tha: licensed limits for release to the envirens is no axceeded.
Cennect hese line to cask vent-and release pressure to fuel building exhaus systen if activity ct I@
is less than M?C.
If sample is above MFC, the gas will be S
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diluted to less than the ??C by controlled discharge to tha D
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y ventilatien stack.
If water is to be vented off, it will be MAR 9 1964 * ?0 y s. t usam terJ ::ss.s*4 discharged as described for flush water in Ite: _4 below.
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' IRRADIATED FUEL ASSE"31Y SA.1 !!MDlIE PSCC DUPS '.7 }'
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' '.. The channel "or SA-1* will~ be plac2d in an underwater fixture in the fuel handling pcol with sufficient' shielding water above the c; to preven:
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A dose rats measurenent vill be obtained with the first sub-e.'sa
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d devices to assure that t>.ov canr.o: inadvertently back out.
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'3 Reference - Subnittal for revised technical specifications of
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DPR-2 #acility's : license, dated Tehruary 27,195u.
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.e cir; p is in plac2, the S A-1 23se-bl/.till be handled as c;..ar 2resden fuel acce-blics.
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