ML20133L963

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Requests for 760728 Info to Support Application for Termination of License
ML20133L963
Person / Time
Site: 07000299
Issue date: 11/23/1976
From: Arnstrong E
MALLINCKRODT, INC.
To: Jonathan Brown
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20133G976 List: ... further results
References
FOIA-96-343 NUDOCS 9701220198
Download: ML20133L963 (14)
v • d • e


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l MALLINCKRODT, INC.

ST. LOUIS.

nawa ' r g} U 3.%,NOV2 91976 >

s November 23, 1976 9

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ro Radiosotopes Licensing Branch e

Division of Fuel Cycle and Material Safety i

Attn:

Mr. J. M. Brown, Jr.

Dear Sir:

To comply with your request dated July 28, ISr/6, we are sending the following infomation to support our appli-cation for "Temination of License".

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If anything else is needed, please contact me.

I apologize for the length of time involved.

Sincerely, Edward. Amstrong' Quality Control Department b

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MALLINCKRODT, INC.

ST.LOUls.

November 23, 1976 Mr E. Amstrong 25-1

SUBJECT:

DECONTAMINATION SURVEY OF FACILITIES FORMERLY USED IN ANALYZING ENRICHED URANIUM U 23y UNDER LICENSE S?N 276_

REF. 01169, UNITED STATES NUCLEAR REGULATORY COMMISSION.

I On September 28, 1976, a survey of alpha, beta, and gamma radiation was made in these premises to detemine the amount of ionizing radiation present and to determine if they are in compliance with the " draft" copy of the NRC guideline of 1975 (attached).

i l Results:

The survey results are summarized on the attached sheets.

Insofar as the guideline mentioned above is concerned, all areas are in compliance, j

The following will answer the directions contained in Sect. 5 of j

the cover letter that accompanies the NRC guidelines, (also attached).

5 (a) Identify the premises, j

The premises are described by room number and a sketch of each area is found on the accompanying survey sheets. All of these rooms are in Building 25, Plant 1 of Mallinckrodt, Inc., St. Louis Site.

Plant located at 3600 N. Second Street, St. Louis, Missouri, specifically City Block 1212.

(b) At the ressation of activities, all material was mentioned and returned to the supplier.--Combustion Engineering, Inc., of i

Hematite, Missouri, under their license SNE33 All areas were physically and chemically cleaned where indicated.

In Room 113, the Spectrographie Lab., an entire table and balance stands were replaced due to the inability to clean the contaminated surfaces.

(c) Scope of survey:

The object of the survey was to determine compliance with the before mentioned " guideline".

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The general procedure was to survey all surfaces on a three foot grid where ever possible, all surfaces were swept with a Geiger counter. Where alpha activity was encountered the entire area was wiped and the wipe checked for activity.

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.MALLINCKRODT, IN.

ST. LOUIS.

Table I Equipnent Used Luditan Model ika Geiger Counter. hp Eberline PAC 30 Gas Flow Proportional Counter.

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Symbols Location f

5 OK not detectable I

v' N.R Not Removeable Units (alpha)=d/m/100cea (beta) = mrad /hr.

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(gamma) = mrad /hr.

Sensitivity of Instruments 100d/m/100cm alpha 0.05 mrad /hr.

i beta A gamma 6

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MC1 10170 R 2/74

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MALLINCK RODT, INC.

ST. LOUIS.

Mr. E. Amstrong Page 2 i

(d) Findings of the survey:

These are sununarized on the attached sheets. All areas surveyed comply with the guideline.

f-W. J. McGrath i

Industrial Hygienist Mallinckrodt, Inc.

cci W. J. McGarth J. M. Brown, Jr.

H. J. McAlduff, Jr.

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Hallinckrodt..Inc.

ATTN: Mr. Edward J. Armstrong Quality control Department Mallinckrodt,and 2nd Streets St. Louis, Missouri 63147 i

Gentlemen:

i tour request dated July 13, 1976, for the termination of Special Nuclear Material License No. SMH-276, Docket No.70-299, should be supported i

i with a copy of the survey report required under Item 3 of the enclosed i

GUIDELINES FOR DEC0!ffAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSE FOR BYPRODUCT.

SOURCE, OR SPECIAL NUCLEAR MATERIAL, dated December 1975. Upon receipt of the requested information, we will continue our review of your j

application. Flease reference Control No. 01169 in your reply.

Sincerely, f

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/p yJ. M. Brown, Jr.

i Radioisotopes Licensing Branch Division of Fuel Cycle and Material Safety 1

Enclosures Guide As Stated

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LUIDELINES FOR DECONTAMINATI0t! Of FACI!ITIEE A'!D EQUIP"Ein PRIOR TO RELEA50 FOR UNRESTRICTED USE OR TEl&tINATION OF LICENSES 10R BYPRODUCT, 50Vi CE, i

7 OR SPECI AL NUCLEAR 11ATERIAL U.S. Nuc1 car Regulatory Co.rmission l

Division of fuel Cycle and !bte. ial Safety Washington, D. C. 20555 DECEMBER, 1975 s

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~j, j e-instructions in this guide in conjunction with Tabl'e I specify the 9 radioactivity and radiattun exposure rate limits which should be used in

, / acc.omplishing the oecontamination and survey of surfaces or premises and M),

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equipnent prior to abandonment or release for unrestricted use.

The limits in it.ble I do not apply to' premises, equipment, or scrap containing induced

.redioact.fvity for which thc_ radiological considerations pertinent to their i

"use may be different.. The release of such facilities or items from regula-tory control.will be considered on a case-by-case basis.

d 1.

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

2.

Radioactivity ori equipacnt or surfaces shall not be covered by paint.

plating, or. Other covering matrial unless contamination levels, as 7

determined by a survey and documented, are below the limits specified i

in Tables I prior to applying the covering. A reasonable effort must i

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.S all be determined by making measurements at all traps, and h

other appropriate access points, provided that contamination at these 1

locations is likely to be representative of contamination on the in-

' terior of the pipes, drain lines, or ductwork.

Surfaces of premises,

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equipment, or scrap which are likely to be contaminated but are of i

such size, construction, or location as to make the surface inacces-sible for purposes of m?asurement'shall be presumeti to be contaminated in excess of the limits.

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 r.:ay include, but would not be limited to, special circumstances such

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as razing of buildings, transfer of premises to another organization continuir.g work with radioactive materials, or conversion of facilities.

to a long-term storage or standby status. Such requests must:

a.

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

2 b.

Provide'a detailed health and safety analysis which re'lects that the residual amounts of materials on surface areas, together with 1

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.

e 5.

Prior to release of premises for unrestricted use, the licensee shall 1

raake a comprehensive radiation survey which establishes that contam-ination is within the limits specified in Table 1.

A copy of the survey report shall be filed with the Chief Materials Branch, Division 2-4

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TABLE I ACCEPTABLE SURFACE CONTAMINATION LEVELS l

NUCLIDESa C

AVERAGE MAXIMUM g

REMOVABLE U-nat U-235, U-238, and

. associated decay products 5,000 dpm a/lCO cm2 15,000 dpm a/100 cm2 l

1,000 dpm a/100 cn2 Transuranics, Ra-226, Ra-228, 233, Th-228, Pa-231, 100 dpm/100 cr2 300 dp n/100 cm2 20 dpm/100 cm2 e-227, I-125, 1-129 1

Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232,1-126, 1000 dpm/100 cm2 1-131, I-133 3000 dpm/100 cm2 200 dpm/100 cm2 Beta-gacma emitters (nuclides with decay modes other. than 5000 dpm Sy/100 cm2 alpha emission or.-spontaneous 15,000 dpa By/100 cm2 1000 dpm Sy/100 cm2 fission) except/SR-90 and others noted above.

"Where surface contamination by both alpha-and beta-ganuna-emitting r.uclides exists, the limits established for al h bsta-gamma-emitting'nuclides should apply independently.

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' As used in this table, dpa (disintegrations per minute) means the rate of emission by radioactive material as determined y correcting the counts per minute observed by an appropriate detector for background, efficiency 4asociated with the instrumentation.

, and geometric factors

" Measurements of average contaminant should not be averaged over more than 1 square meter For objects of less surface area, the average should be derived for each such object.

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The maximum contamination level applies to an area of not more than 100 cm,

2 The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with 2

I dry filter or sof t absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency.

When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.

5-average.r.d mu irun radiatin, 1 vels associatyd with surrec crem.iaation re sul t ina, f rem beta-gamma cmitters should nc

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en :md 1.0 era l/hr at I rm, n ngues t ively, me.unred t hrour,h not more than 7 milligrams per square

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'rP of fuel Cycle and Miterial Safety, USNRC, Washinqton, D.C. 20555, and also the Director of the Regional Office of the Offira of Inspection and Enforce-reent, USNRC, having jurisdiction.

The report should be filed at least 30 t'

days prior to the planned date of abandonment.

The survey report shall:

a.

Identify.the premfses.

b.

Snow 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 tie instruction.

folloding review of the report, the NRC will consider visiting the facill-tics to confirm the survey,

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