ML20199C472

Responds to 860602 Request for Addl Info Re Termination Survey of Rockwell Intl Research Reactor L-85 Prior to Initiation of Insp for Termination of License.Bldg T093 Used Under License R-118.Reactor Room Will Be Resurveyed

ML20199C472
Person / Time
Site:	05000375
Issue date:	06/13/1986
From:	Remley M ROCKWELL INTERNATIONAL CORP.
To:	Berkow H Office of Nuclear Reactor Regulation
References
86RC08005, 86RC8005, NUDOCS 8606180169
Download: ML20199C472 (3)

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• '* I Rocketdyne Division Rockwell international Corporation Rockwell i Canoga $rYorn*a784 International Telex: 698478 ROCKETDYN CNPK 1

June 13,1986 In reply refer to 86RC08005 Mr. Herbert N. Berkow, Director Standardization and Special Projects Directorate U.S. Nuclear Regulatory Commission l Washington, D.C. 20555

Subject:

Response to " Request for Additional Information on the Termination Survey of the Rockwell International Research Reactor L-85," Docket No. 50-375

Dear Mr. Berkow:

Your letter of June 2,1986, transmitted a number of issues that still needed to be resolved before representatives of the Nuclear Regulatory Commission could initiate the final inspection of the facility for termination of the license and release of the facility for unrestricted use.

Our responses and proposed actions on the issues are summarized below.

The issues are identified in the same manner as in the enclosure to your letter.

A. We have determined that only Building T093 was used under the authorization in our NRC license R-ll8.

B. Four locations' measured in the sampling inspection showed surface activity exceeding the limit appropriate for Sr-90 (1000 dpm/100 cm2). These will be sampled (by removing small amounts of surface material) and analyzed specifically for Sr-90 and other radionuclides. If it is shown that sig-nificant Sr-90 activity is present (greater than 5% of total activity), the Sr-90 surface contamination limit will be invoked. In that case, additional decontamination work and a new final survey will be performed to assure compliance with this limit.

8606180169 860613' 5 g PDR ADOCK 0000

86RC08005 June 13,1986 Rockwell Page 2 International C. " Natural background" will be determined by measurements made in a nearby, uncontaminated building of similar construction and age. Table 1 (of the Dismantling Order), which was inadvertently omitted from our revised report, will be added to the report.

D. The "NRC guidance" referenced is NUREG/CR-2082, " Monitoring for Compliance With Decommissioning Termination Survey Cri-teria." We understand now that, in spite of the sponsorship by NRC, this report does not represent an NRC staff post-tion. Therefore, this reference will be omitted from the report. The sampling inspection serves to provide a docu-mented demonstration that the area satisfies the acceptance criteria. It is started only after a complete " scan" of the area shows no significant activity. This scan is essen-tially the same as the 100% beta-gamma scan that the NRC contractor performed at our Building 001 during the confirm-atory survey. It is done to assure that all necessary decontamination work has been performed before the start of the documented sampling inspection survey.

E. The reactor room will be resurveyed using a Reuters-Stokes l RS-111 HPIC.

F. We will provide results of our measurements after the areas mentioned on page 33.8 are covered with concrete and advise j you so that you can confirm our measurements.

We believe the above actions and reports will resolve the issues and the facility can be inspected for release. If you have questions or need further information, please call me at (818) 700-4270.

Sincerely y ,

M. . Remley, Direct Nuclear Safety & Lice ing Rocketdyne Division l 7290A/slw 1

l Distribution - Page 3 04479RC

86RC08005

" Rockwell p,"glf,1986 International cc: Sacramento County Board of Supervisors 827 7th Street, Room 424 Sacramento, CA 95814 Office of Intergovernmental Management - State of California 140010th Street, Room 108 Sacramento, CA 95814 California Department of Health Attention: Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, CA 95814 l

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