ML20217P916

Safety Evaluation Accepting Amend 41 to License SNM-0696

ML20217P916
Person / Time
Site:	07000734
Issue date:	03/02/1998
From:	Weber M NRC
To:
Shared Package
ML20217P908	List: ML20217P904 ML20217P909 ML20217P916
References
NUDOCS 9803110212
Download: ML20217P916 (2)

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UNITED STATES NUCLEAR REGULATORY COMMISSION O f WASHINGTON, D.C. 2006H001 yo

,,,g March 2, 1998 DOCKET NO: 70-734 LICENSEE: General Atomics (GA)

San Diego, Califomia

SUBJECT:

SAFETY EVALUATION REPORT: APPLICATION DATED JULY 17, 1997, GROUP 9 LABORATORIES RELEASED FOR UNRESTRICTED USE I

BACKGROUND in correspondence dated July 17,1997, GA requested their license be amended to remove

authorized activities at the Group 9 Laboratories (Building 2 Laboratories 441,439/41,511/513, 517, and 645 from the license), and release the laboratories for unrestricted use. GA l conducted a survey of the racilities and provided the results of that survey in their submittal.

l- The licensee used the same methodology as used during the previous decontamination and decommissioning of the Group 6, Group 7, and Group 8B Laboratories.

DISCUSSION i GA has completed the decontamination of the Group 9 Laboratories. .They submitted a final L report entitled, "Decentamination of Selected General Atomics' Science Laboratories for Release to Unrestricted Use (Group 9)," dated July 16,1997, in accordance with 10 CFR 70.38(j), and requested the laboratories be released for unrestricted use in a letter dated July 17,1997. The decontamination and radiological survey techniques used were the same rigorous procedures as those used for the Group 6, Group 7, and Group 8B laboratories l survey, which have been previously reviewed by NRC and released for unrestricted use.

l Tht. emsee's survey data showed that any remaining residual radioactivity in the Group 9 l- Labocatories was well below the criteria established in " Guidelines for Decontamination of

FaciMies and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source or Special Nuclear Material," dated April 1993, as incorporated in General

l. Atomics Materials License SNM-696. These criteria are consistent with NRC's Site

Decommissioning Management Plan Action Plan Criteria (57FR13389). The State of Califomia l

has approved the release of the Group 9 laboratories. Inspectors from Region IV performed a l confirmatory survey (Insoection Report 70-734/97-02, dated June 11,1997, Section 1.5) and determined the following:

"The licensee's final sunrey plan and final survey results were reviewed for determining the final status of the subject areas and their suitability for release to unrestricted use status. No residual radioactive contamination above NRC guidelines was detected during the inspector's surveys."

This decommissioning action was conducted in accordance with an NRC approved 9903110212 990302' PDR ADOCK 07000734 C PDRS

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decommissioning plan that was submitted and approved prior to July 21,1997. Therefore, in accordance with 10 CFR 20.1401(b), the criteria in Subpart E of 10 CFR Part 20 do not apply.

Additional clean-up of these areas will only be required if, based on new ,'nformation, the NRC determines that the release criteria established in " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated April 1993, were not met, and residual radioactivity remaining at the site could result in a significant threat to public health and safety.

ENVIRONMENTAL REVIEW Based on the information submitted by GA, and the NRC Regional inspector, the staff has determined that the following conditions have been met:

1. - There is no significant change 5 the types or significant increase in the amounts of any effluents that may be released offsite,

2. There is no significant increase in individual or cumulative occupational radis. tion exposure, 6

3. There is no significant construction impact,

4. There is no significant increase in the potential for or consequences from radiological accidents.

4 Accordingly, pursuant to 10 CFR 51.22(c)(11), this action qualifies for a categorical exclusion and neither an environmental assessment nor an environmental impact statement is warranted for this action.

CONCLUSION The staff concludes that GA's request release the Group 9 laboratories for unrestricted use meets regulatory requirements and that there is reasonable assurance that the proposed action will not adversely impact upon the health and safety of the public or the environment.

The Region IV Principal Inspector has no objection to this propo a Princioal Contributor 'J Charles E. Gaskin g t, g y?

Hearther Astwood

( Susan Chotoo