ML19269C020
| ML19269C020 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 12/17/1978 |
| From: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Zeff D BABCOCK & WILCOX CO. |
| References | |
| NUDOCS 7901190210 | |
| Download: ML19269C020 (7) | |
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UNITED STATES y
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WASHINGTON, D. C. 20555
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nce. !,- g73 FCPF:NK Docket 70-1201 SNM-ll68 i
Babcock & Wilcox Company Commercial Nuclear Fuel Plant ATTN: Mr. D. W. Zeff, Acting Manager Safety, Licensing & Safeguards P. O. Box 1260 Lynchburg, Virginia 24505 Gentlemen:
We have reviewed your amendment application dated October 13, 1978 associated with changes in action levels for contamination control, uranium oxide storage criteria, and with clarifications to your emergency plan training program.
Justification has neither been provided for the requested increases in co..cmainuc.un control action levels in jour con coMea u4 eu.5 (e.g., manufacturing, change rooms) nor for the decreased survey frequency in the cafeteria and locker rooms. A copy of Regulatory Guide 8.24, " Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication" dated November 1978 is enclosed for your guidance in preparing revised pages to your amendment applica-tion.
The enclosed Annex C, " 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 November 1976 is for your guidance in establishing criteria for release of waste or excess materials and equipment for disposal "in rcutine industrial fashion."
The proposed license condition for the storage of containers of uranium oxides should not be mcre general than the limitations imposed on the parameters associated with the demonstration of its nuclear criticality safety.
790119 0 2 /o
2 In order to meet our schedule for completion of the review of your amendment application, your response to the requested additional information should be received within 30 days after the date of this letter.
Sincerely, f
/ttu W. T. Crow, Section Leader Uranium Fuel Fabrication Section Division of Fuel Cycle and Material Safety
Enclosures:
Regulatory Guide 8.24 Annex C
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AfiNEX C GUIDELINES FOR DECO liTAMINATIO!! 0F FACILITIES At1D EQUIPMEtlT PRIOR TO RELEASE FOR UURESTRICTED USE OR TERf11 NATION CF LICEr!SES FOR BYPRCDUCT, SOURCE,
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OR SPECIAL NUCLEAR MATERIAL U. S. Nuclear Regulatory Ccamission Division of Fuel Cycle anc Material Safety Washington, D.C.
20555 NOVEMBER 1976 b
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The instructions in this guide in conjunction with Table I specify the f ' radioactivity and radiation exposure rate limits which should be used in accomplishing the decontamination and survey of surfaces or premises
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and equipment prior to abandonment or release for unrestricted use.
The limits in Table I do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considera-tions pertinent to their use may be different.
The release of such f acilities or items frca regulatory control will be 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 belcw the limits specified in Table I prior to applying the covering.
A reasonable effort must be made to minimize the contamination prior to use of any covering.
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The radioactivity on the interior -surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps,
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- ,,... ; i 2 : t' : t.cr ::... : '- i : c at' these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork.
Surfaces of premisas, equipment, or ; crap which ara li.'aly ta be cntamin.;t:1 but are of such size, construction, or location as to make the surface inaccessible for purpcses of measurement shall be presumed to be contaminated in excess of the limits.
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Upon request, tr.e 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 include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization
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to a long-term storage or standby status.
Such requests must:
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 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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Prior to release of premises for unrestricted use, the 1.icensee shall - ~
make a comprehensive radiation survey which establishes that contam-ination is within the limits specified in Table I.
A copy of the survey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC, Washington, D.C.
20555, and also the Director of the Regional Office of the Office of Inspection and Enforcement, USHRC, having jurisdiction.
The report should be filed at least 30 days prior to the planned date of abandonment.
The survey report shall:
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Identify the premises.
b.
Show that reasonable effort has been made to eliminate residual contami na tion.
c.
Describe the scope of the survey and general procedures folicwed.
State the findings of the survey in units specified in the d.
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4-Following review of the report, the NRC will consider visiting the f acilities to confirm the survey.
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TABLE I
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9.i t ACCEPTABLE.51 tWACE C0tlTAMIllATI0ll LEVELS
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HUCLIDES AVERAGE MAXIMUH REMOVABLE
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f.7-nat,U-235,U-238,and 5,000 dpm u7100 cm 15,000 dpm a/100 cm 1,000 dpm o/100 cm U
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associated decay products 7
P t' 2
2 2
r l'Transuranics, Ra-226, Ra-228, 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm L
Th-230, Th-228, Pa-231, Ac-227, I-125, I-129 2
2 2
y. ': Th-nat, Th-232, Sr-90, 1,000 dpm/100 cm 3,000 dpm/100 cm 200 dpm/100 cm
>l 0 Ra-223, Ra-224, U-232, I-126,
,.;;I-131, 1-133
'H-2 2
.. Beta-gamma emitters (nuclides 5,000 dpm SY/100 cm 15,000 dpm sy/100 cm 1,000 dpm BY/100 cm
,.~ with ay modes other than r
C alpha emission o" spontaneous
- fission) except SR-90 and others noted above.
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},-[ Where surface contamination by both alpha-and beta-ga, na-emitting nuclides exists, the limits established for alpha-I-
'and beta-gamma-emi tting nuclides shpuld apply independe. tly.
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{U'i As used in this table, dpm (disintegrations per minute means the rate of emission by radioactive material as de-r ((! termined by correcting the counts per minute observed b; an appropriate detector for background, efficiency, and geo-
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f h' CMeasurements of average contaminant should not be aver ged over more than 1 square meter. For objects of less surface
' area, the average should be derived for each such objec.
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2 a,j'dhtie maximum contamination level applies to an area of
,ot more than 100 cm,
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TABLE I
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'I:/,I'The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area
, with dry filter or sof t absorbent paper, applying moderate pressure, and assessing the amount of radioactive material
'l, on the wipe with an appropriate instrument of known ef ficiency. When removable contamination on objects of less surface
,- area is determined, the pertinent levels should be reduced propcrtionally and the entire surface should be wiped.
.,f(The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters
- g.should not exceed 0.2 mrad /hr at 1 cm and 1.0 mrad /hr at I cm, r espectively, measured through not more than 7 milli-7, grams per square centimeter of total absorber.
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