ML20210E037

Requests Schedule for Retirement Activities at Facility,By 730201,per 730122 Telcon.Schedule Should Include Plans for Removal & Offsite Disposal of Primary & Secondary Sodium & Blanket Matl

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: ML20210D957 ML20210D971 ML20210D985 ML20210E006 ML20210E037 ML20210E061 ML20210E067
References
NUDOCS 8609220085
Download: ML20210E037 (1)

Text

._ _ _

l

, UNITED STATES g g 7 4,4 ,,

B!

b p- ATOMIC ENERGY COMMISSION CNt

- 1 was unerow.o.c. nous

• " 57' Dockat No. 50-16 E

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 of the plant, and to extend the expiration of your license to June 30, h 1973. An amendment was issued on January 1,1973, which accomplished 3 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 disposal of primary and secondary sodium and the blanket material. We g 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 Assistant Director for Operating Reactors g

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 l

Portion between Blanket and holddown Holddown Mechanism L L .9 L 1

. Inner Region 1 1 158 L 158 Outer Region (R > 41,ca) L L 70 L 70 l

l Shield Bars 12 .3 105 .1 117 Thermal Shield Lower - ,

1 .2 88 .1 89 i Upper L L 9 L l

9 Holddown Colusn L L 4 L 4 Safety Rods - Poison Section Lower L L L L Middle L L L L --

Upper L L L B Rotating Plug L 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 4

Transfer Rotor L L L L --

CHN L L 6 L 6 Reactor Vessel - Negligible -

Total 36 <2 1514 <2 41550 I

I L = less than 0.1 curies I

I I .. .

4.19

_ _-