ML20215G472

SER Supporting Amend to License SNM-1097 Re Exemption from 10CFR20.203(f) Requirements

ML20215G472
Person / Time
Site:	07001113
Issue date:	06/11/1987
From:	Bidinger G, Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20215G465	List: ML20215G463 ML20215G472 ML20215G498
References
NUDOCS 8706230271
Download: ML20215G472 (1)

Text

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l JUN 111987 i

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DOCKET NO: 70-1113 LICENSEE: General Electric Company (GE) ~

l Wilmington, NC l

SUBJECT:

SAFETY EVALUATION' REPORT, AMENDMENT APPLICATION DATED MAY 22, i 1987, RE EXEMPTION FOR 10 CFR 20.203(F)

Background

10 CFR 20.203(f) establishes labeling requirements for containers of radioactive material. In the subject amendment GE proposes to post general ,

areas rather than label every container within the areas. l Discussion Certain containers do not lend themselves to the labeling. Such containers  ;

include fuel assemblies and laboratory vials. As an alternate approach, GE proposes to post areas with a sign which indicates that containers in the area l may contain radioactive material. The areas would be within the controlled access area. Only trained or escorted personnel are permitted in these areas.

Conclusion / Recommendation j The staff concludes that the exemption request and proposed alternate area.

posting would not cause undue risk to the public health and safety. Approval of the applicatim is recommended.

The Region II Principal Inspector has no objection to this action.

Original Signed By:

George H. Bidinger g 62 M b $706117001 3 Uranium Fuel Section '

P C Fuel Cycle Safety Branch Division of Fuel Cycle, Medical Academic, and Commercial Use Safety original Signed By:

Leland C. Rouse, Chief Fuel Cycle Safety Branch

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NAME:GHBidinger/vt/as:VLT arpe:LRdifse  :  :  : :

DATE:6/to /87 :6/l0/87 :6////87  :  :  : : l OFFICIAL RECORD COPY

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i GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNPESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT,. SOURCE, OR SPECIAL NUCLEAR MATERIAL 1

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U.S. Nuclear Regulatory Comission

' Division of Fuel Cycle, Medical, Academic, and Consnercial Use Safety Washington, DC 20555 .

May 1987 ENCLOSURE 2

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i The instructions in this guide, in conjunction with Table 1, specifydthein

. radionuclides and radiation exposure rate limits which should be use decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory control is considered on a case-by-case basis.

1. The licensee shall make a reasonable effort to eliminate residual contamination.

2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering. j

3. The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior-of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.

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4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may q include, but would not be limited to, special circumstances such as razing "

of buildings, transfer to premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests must: ,

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a. Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination,

b. Provide a detailed health and safety analysis which reflects that the j residual amounts of materials on surface areas, together with other J considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.

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5. Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1. A copy of the survey report shall be filed with the Division of Fuel Cycle, Medical, Academic, and Connercial Use Safety, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment.

The survey report shall:

a. Identify the premises,

b. Show that reasonable effort has been made to eliminate residual contamination.

c. . Describe the scope of the survey and general procedures followed.

d. State the findings of the survey in units specified in the instruction.

Following review of the report, the NRC will consider visiting the facilities to confirm the survey.

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