ML19347E616
| ML19347E616 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 04/30/1981 |
| From: | John Thomas North Carolina State University, RALEIGH, NC |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105130135 | |
| Download: ML19347E616 (2) | |
Text
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North Carolina StateUniversity 3l Box,a*7. Raleigh 2765o d,
Osaddec=ans April 30, 1981 N"6\\
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e' Mr. Robert W.
Re id, Chief Operating Reactors Branch #4
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Division of Licensing
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U.S. Nuclear Regulatory Commission lp >
t Washington, D.
C.
20555
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Dear Mr. Reid:
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/ hi In response to your letter of 6 March 1981, provided guidance criteria for the release of our R-3 acility to unrestricted use, the attached addendum to our Dismantling Plan is submitted for your consideration.
A telephone conversation with your staff indicated that details of the procedure for the general survey of our facility needed to be arranged with the Inspection and Enforcement Section, Reg. II.
We are pursuing this suggestion.
Our interest in pursuing the dismantling of the R-3 reactor is the pressing need for full utilization of the area represented by the Burlington Nuclear Laboratory.
Our study of the future utilization of this site varies from complete demolition of the reactor and the building, thru the demolition of the reactor only with building rencvation, to partial reactor demolitio.s wig subsequent renovation.
The first priority on this site is the pending Microelectronics Center which has been submitted to our Legislature for their consideration.
Sincerely, A//o>o A
"ML Joab L. Thomas
/
Chancellor
Enclosure:
Addendum to Dismantling Plan cc:
Dr.
P.
J.
Turinsky, w/ attach.
Dr. R.,G. Coe rell, w/ attach.
Mr.
R.
D. Cross, w/ attach.
Subscribed and sworn to before me this 30W day of Cloul0 1981.
Mcu i
u Notary Publip /
My <mnksion expires [//f,/8I
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y ADDENDUM TO DISMANTLING PLAN FOR THE R-3,10 KW REACTOR DATED 15 MARCH 1980 The Dismantli.; Plan tor the R-3,10 KW reactor dated 15 March 1980 appitcable criteria is amended as follows:
a.
Surface contamination. Table 1 of Reg. Guide 1.86 shall be used to determine whether or not surfaces within this facility are acceptable for rolesse to unrestricted use.
b.
Radioactive Material other than surface contamination (Co-60. Eu-152, Cs-137).
The radiation level from concrete biological shield, components, structures, etc. shall be less than SE - 6 R/hr above natural background measured at i meter from the surface.
If the distance attain-abit from the surface is less than i meter, the dose rate shall be adjusted appropriately.
c.
General.
The Nuclear Engineering Department is in contact j
with Dr. C. Julian, Region II, Atlanta, Ga., to agree on procedures that will be mutually acceptable.
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