ML20210E037
| ML20210E037 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/22/1973 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Alexanderson E POWER REACTOR DEVELOPMENT CO. |
| Shared Package | |
| ML20210D960 | List: |
| References | |
| NUDOCS 8609220085 | |
| Download: ML20210E037 (1) | |
Text
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CNt UNITED STATES g g 7 4,4 b
ATOMIC ENERGY COMMISSION p-1 was unerow.o.c. nous
- " 57' E
Dockat No. 50-16 B
Power Reactor Development Company ATTH:
Eldon Alexanderson General Manager 1911 First Street Detriot, Michigan 48226 g
, Gentlemen:
By application dated November 30, 1972, you informed us of your intention to decomission Femt 1 and requested an amendment to Provisional Operating License No. DPR-9 to delete authority for nuclear operation h
of the plant, and to extend the expiration of your license to June 30, 3
1973. An amendment was issued on January 1,1973, which accomplished the requested actions.
As discussed with you*, PRDC is requested to submit by February 1,1973, a schedule for retirement activities at the Fermi 1 facility. The retirement schedule should include plans for the removal and offsite g
disposal of primary and secondary sodium and the blanket material. We have determined that long term storage of the sodium and the blanket material et the Femi 1 site is unacceptable.
Sincerely.
3 ly4,l kr h
nald J.
kovholt g
Assistant Director for Operating Reactors Directorate of Licensing cc:
David E. McGiffert, Esquire Covington & Burling 888 - 16th Street, N. W.
- The discussion occurred on Washington, D. C.
20006 January 22, 1973 by telephone.
Alex 8609220085 860915 PDR ADOCK 05000016 P
PDR I
4.20 N
i L_-
TABLE 3 Ia CALCUIATED ACTIVITY OF STAINLESS STEEL WITHIN THE REACTOR VESSEL (NEG1LECTS BIANKET SUBASSEMBLIES) l (June 1,1973)
Ls, l
l Activity Source (Curies)
Component Co-58 Fe-59 Co-60 Cr-51 Totsi l
Control & Safety Rod Channels Portion in Core 21 L
.9 L
30 Portion in Blanket 1
L
.9 L
10 Portion between Blanket and holddown L
L
.9 L
1 l
Holddown Mechanism Inner Region 1
1 158 L
158 Outer Region (R > 41,ca)
L L
70 L
70 l
Shield Bars 12
.3 105
.1 117 l
Thermal Shield Lower -
Upper 1
.2 88
.1 89 L
L 9
L 9
i l
Holddown Colusn L
L 4
L 4
Safety Rods - Poison Section Lower L
L L
L Middle L
L L
L B
Upper L
L L
L Rotating Plug L
L L
L i
Support Plates
.7
.3 965
.1 975 Support Structure
.1
.1 35 L
35 Support Structure Shielding
.2
.1 35 L
35
[
Plow Baffles L
L 2
L 2
Conical Plow Guide L
L L
L Lower Reactor Head Shielding L
L 18 L
18 Transfer Rotor L
L L
L 4
CHN L
L 6
L 6
Reactor Vessel
- Negligible -
I Total 36
<2 1514
<2 41550 I
L = less than 0.1 curies I
I I
4.19
_-