ML20205T674
| ML20205T674 | |
| Person / Time | |
|---|---|
| Site: | 07001489 |
| Issue date: | 06/11/1986 |
| From: | Axelson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Pflaum J GOODYEAR AEROSPACE CORP. (SUBS. OF GOODYEAR TIRE |
| References | |
| NUDOCS 8606160138 | |
| Download: ML20205T674 (2) | |
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'JUN 11 1986 Goodyear Aerospace Corporation License No. SNM-1461 ATTN: J. V. Pflaum, CIH Industrial Hygienist Senior Corporate Industrial Hygiene and Safety Department 131 G 1 1210 Massillon Road Akron, Ohio 44315-0001
Dear Mr. Pflaum:
This refers to the confirmatory survey of your Wingfoot Lake Advanced Technology Center by Oak Ridge Associated Universities (0RAU) during the week of May 12-16, 1986.
As was discussed with you during the survey and in subsequent telephone conversations with this office, several areas were identified that exceeded maximum release levels of 15,000 dpm per 100 cm2 (specifically,the decontamination areas and grid block C-42). While the ORAU survey report has not yet been finalized, it is our understanding that the referenced areas will either be further decontaminated or physically removed to meet the NRC facility release criteria established in Policy and Guidance Directive FC 83-23, Enclosure 2, " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material" (copy enclosed).
Subsequent to these activities, we request that you provide us with a final close-out survey of the facility including:
- a. A diagram of your facility with survey results keyed to specific locations.
- b. The name of the person performing the survey.
- c. The date the survey was performed.
- d. The instrument (s) used.
- e. Background readings.
- f. The date that the survey instrument was last calibrated.
Following our review of your final survey, we will (1) arrange for ORAU representatives to confirm that all previously excessive areas meet NRC release d
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4 Goodyear Aerospace Corporation 2 JUN 11 1988 criteria, and (2) continue with our licensing action to release the Wingfoot Lake Advanced Technology Center for unrestricted use.
Should you have questions concerning the above, please contact this office.
Your cooperation with us is appreciated.
Sincerely, Willia L. A5Ie son, Chief Nuclear Materials Safety and Safeguards Branch
Enclosure:
As stated cc w/ enclosure:
J. D. Berger, ORAU DCS/RSB (RIDS) bec w/ enclosure:
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GUIDELINES FOR DECONTANINATION OF FACILITIES AND EQUIPMENT .
PRIOR TO RELEASE FOR U RESTRICTED USE OR TERMINATION.,0F LICENSES FOR. BYPRODUCT, S'00RCE, _...._,
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A U. S. Nuclear Regulatory Comission Division of Fuel Cycle and Material Safety
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. D.C. 20555 July 1982 i S
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The instructions in this guide , in conjunction .with Table 1, specify the 4 radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior j .to abandonment or release for unrestricted use. The limits in Table 1 l
do not a'pply to premises,- equipment, or scrap containing induced radio-l activity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from
, regulatory contro'1 is considered on a case-by-case basis. ,
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! 1. The licensee shall make a reasonable effort to eliminate residual
! contamination. , . ,
i l 2. Radioactivity on equipment or surfaces shall not.be covered by l paint, plating, or other covering material unless contamination levels, as determined by a survey *and documented, are below the l
i limits specified in Table 1 prior to the application of the
- j covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.
- 3. The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be detemined by making measurements at all traps, and other appropriate access points, provided that contam-i ination at these l'ocations is likely to.be representative of j 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 j
1 measurement shall be presumed to be contaminated in excess of j the limits.
i l 4 Upon request, the Co nission may authorize a licensee to relinquish
! possession or control of premises, equipment, or scrap having l
surfaces contaminated with materials in excess of the limits specified.
This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of 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 l
that the residual amounts of materials on surface areas, ~
together with other 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 it A copy of
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the survey report shall be filed with the Division of Fuel Cycle and' Material Safety, USNRC, Washington, D.C. 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 reason'able effort b'as been made to eliminate .~ ' I. ' .~ . '
residual contamination.
- c. Describe the scope of the surfey and seneral procedures followed. ,
- d. Statethekindingsofthesurveyinunitsspecifiedin the instruction.
Fellowing review of the report, the NRC will consider visiting the facilities to, confirm the survey.
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ACCEPTABLE SURFACE CONTAMINATION LEVEL 5 .
8 AVERAGEbcf MAKIMunb d ( REMOVABLEbef tiUCL 10[5 j
U-nat U-235, U-238, and 1,000 dpm'o/100 cm2 assnClated decay product % 5,000 dpm a/100 cm 2 15,000 dpm a/100 cm2 ,
Transuranics, Ra-226 Ra-228 20 dpe/100 ce2 Ih-230, lh-228, pa-231, 100 dpm/100 cm 2 300 dpm/100 cm2 Ac-221, 1-125, 1-129 ,
f Th-nat, lh-232, Sr-90, 1000 dpm/100 cm2 3000 dpm/100 cm2 200 dps/100 cu i Ra-22), Ra-224, U-232, 1-126, 1-131, 1-133 ..
Beta-garwa emitters (nuclides with decay modes other than 1000 dpa sy/100 cm2 alpha emission or spontaneous 5000 dpm sy/100 cm 2 15,000 dpm ay/100 cm2 fissinn) ence;it Sr-90 and
- others noted above.
- Where surf ace contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha- and beta-gamma-emitting nuclides should apply.independenLly, b As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factort associated with the instrumentation.
Cit asurements of average contaminant should not be averaged over more than I square meter, for objects of less surface area, the average should be derived for each such object. .
dihe maximum contamination level applies to an area of not more than 100 cm2 ,
'The amount of removable radioactive material per 100 cm2 of surface area should 'he determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. Uhen removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should t,e wiped. ,
I Tbc average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed '
O.2 mrad /hr at I cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per squara centimeter of total absorber. .
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