ML19350A445

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Forwards Guidance Re Radiation Levels for Release of Reactor Facility to Unrestricted Access.Nrc Agrees W/Licensee Plans to Forego Surveillance Testing,In View of 800310 Application to Dismantle Reactor
ML19350A445
Person / Time
Site: 05000375
Issue date: 02/27/1981
From: Reid R
Office of Nuclear Reactor Regulation
To: Remley M
EMVROCIE, ROCKWELL INTERNATIONAL CORP.
References
NUDOCS 8103160202
Download: ML19350A445 (3)


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February 27, 1981 Docket No. 50-375 O

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Dr. M. E. Remley, Director

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Dear Dr. Remley:

By application dated March 10, 1980 you requested authorization to dismantle your L-85 reactor and terminate license No. R-ll8'.

Recently you contacted Mr. Erickson of my staff with respect to our interpretation of certain surveillance requirements in your Technical Specifications (TSs) that required operation of the L-85 reactor to perform the surveillance.

In your discussion you stated that, since Rockwell did not intend.o operate the reactor again, it would not be prudent to perform any unnecessary surveillance tests which would cause any further buildup of fission and activation products in the reactor.

We agree that further operation of the reactor to perform the surveillance tests of TSs 4.lb, 4.lc, 4.2d(1) and 4.2d(3) is not desirable in view of your plans to dismantle.

In addition, we interpret the surveillance requirements of the above TSs to be a limiting conditions for operation.

Therefore, if you do not perform these surveillance tests in the time intervals specified, the reactor may not be brought critical or operated until specific authorization has been obtained from the NRC. Also, Rockwell would not be in violation of the TSs if the surveillance specified in TSs 4.lb, 4.lc, 4.2d(l) and 4.2d(3) is not done as long as the reactor is not brought critical or operated.

With respect to your dismantling plan, Enclosure #1 specifies Radiation Levels Acceptable for Release of Reactor Facility to Unrestricted Access.

Your " Contamination Limits" ii; your March 10, 1980 submittal are acceptable for surface contamination. You should, however, add limits for Radioactive Material other than Surface Contamination that are consistent with Enclosure #1.

Sincerely, 3,-

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a Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing

Enclosure:

As stated cc: See next page 8103160202

H Rockwell International Corporation cc w/ enclosure:

Energy Resources Conservation and Development Comission ATTN: Librarian 1111 Howe Avenu'e Sacramento, California 95825 Diractor Energy Facilities Siting Division Energy Resources Conservation &

Development Connission 1111 Howe Avenue Sacramento, California 95825 cc w/ enclosure (s) and incoming dtd.:

California Department of Health ATTN: Chief. Environmental Radiation Control Unit Radiologic Health Section 714 P Street, Room 498 Sacramento California 95814 1

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Enclosure RADIATION LEVELS FOR RELEASE OF REACTOR FACILITY TO UNRESTRICTED ACCESS Surface Contamination Surfaces must be decontaminated to levels consistent with Table 1 of Reg. Guide 1.86.

Radioactive Faterial Other Than Surface Contamination (Co 60. Eu 152, Cs 137)

Co 60 Eu 152 and Cs 137 that may exist in concrete, components, structures, and soil must be removed such that the radiation levg}

from these isotopes is less than SuR/hr above natural background'/

l as measured at one meter from surface.

General Site survey procedures acceptable to the NRC must be used.

I) Radiation from naturally occurring radioisotopes as measured at a comparaole uncontaminated structure or exterior soil surface.

.