ML20154D370

SER Accepting Amend 50 to License SNM-696 for General Atomics

ML20154D370
Person / Time
Site:	07000734
Issue date:	09/30/1998
From:	NRC
To:
Shared Package
ML20154D363	List: ML20154D359 ML20154D365 ML20154D370
References
NUDOCS 9810070204
Download: ML20154D370 (2)

Text

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, , pn Atg p  % UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665 4001 September 30, 1998 DOCKET NO: 70-734 LICENSEE: General Atomics (GA)

San Diego, California

SUBJECT:

SAFETY EVALUATION REPORT: APPLICATIONS DATED JULY 30, AND SEPTEMBER 4,1998, REQUEST TO RELEASE BUILDING 30 -

PHASE ll LABORATORIES FOR UNRESTRICTED USE A

B_CKGROUND By letter dated July 30,1998, GA notified the NRC of the completion of decommissioning of a portion of Building 30, designated as " Building 30 - Phase ll," and requested an amendment to release these areas for unrestricted use. In accordance with 10 CFR 70.38(j), the submittal included the results of a survey conducted by GA in a report entitled, " Final Radiological Survey of Rooms for Release to Unrestricted Use," dated July 29,1998. By letter dated September 4, 1998, GA submitted a revision to this report dated September 2,1998. The revision corrects errors in reported results and includes editorial changes .

DISCUSSION GA has completed the decontamination of the Building 30 - Phase ll areas, which had been used to store only state licensed material (irradiated parts and sealed p/y sources). The decontamination and radiological survey techniques were the same rigorous procedures as those used in the Group 6, Group 7, Group 8, Group 9 laboratories and Building 30 - Phase I rooms surveys, which have been previously reviewed by NRC and released for unrestricted use.

The licensee's survey data showed that any remaining residual radioactivity in the Building 30 rooms was well below the 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, as incorporated in GA Materials License i SNM-696. These criteria are consistent with NRC's Site Decommissioning Management Plan l Action Plan Criteria (57FR13389). J As documented in Inspection Report 70-734/98-01 dated February 13,1998, inspectors from Region IV reviewed GA's final survey plan and draft release report and determined that the licensee has implemented a program for the conduct and documentation of final surveys that follows the guidance contained in Draft NUREG/CR-5849, " Manual for Conducting Radiological Surveys in Support of License Termination," the licensee's site decommissioning plan, and the requirements of 10 CFR 70.38(j). In addition, the State of California performed confirmatory surveys of the areas with alpha and beta radiation detection equipment and found no I I

contamination.

9910070204 980930 PDR ADOCK 07000734 C PDR ,

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2 l This decommissioning action was conducted in accordance with an approved decommissioning l plan. Since the decommissioning plan was approved by the NRC prior to August 20,1999, the I criteria in Subpart E of 10 CFR Part 20 do not apply. l Additional clean-up of these areas will only be approved if, based on new information, the NRC determines that the release criteria established in " Guidelines for Decontamination of Facilities i 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. l 1

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

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

2. There is no significant increase in individual or cumulative occupational radiation exposure, l

3. There is no significant construction impact, and

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

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

CONCLUSION The staff concludes that GA's request to release the Building 30 - Phase ll rooms 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 proposed action.

Princioal Contributors Susan D. Chotoo Charles E. Gaskin