ML19270H539

Submits Info to Support Amend of Matl/Byproduct License 37-07855-02 to Authorize Use of Byproduct Matl for Fabrication of Sources

ML19270H539
Person / Time
Site:	Three Mile Island
Issue date:	04/24/1973
From:	John Miller METROPOLITAN EDISON CO.
To:	Brinkman R US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19270H523	List: ML19270H527 ML19270H528 ML19270H529 ML19270H530 ML19270H531 ML19270H532 ML19270H533 ML19270H539 ML19270H540 ML19270H541 ML19270H543
References
NUDOCS 7911040171
Download: ML19270H539 (4)

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\s , mornm nxun M ETR O PO LITA N E D l 5 O N CO::1 ?A N Y sui:::va n v o c asucnn. rucuc undnes cospoaa rion POST OFFICE BOX 480 MIDDLETOWN. PENNSYLVANIA 17057 T ELEP HON C 717-944-4041 April 24, 1973 United States Atonic Encrcy Commission Attn:  !:r. Robert E. Brinkna.n

!!aterials Bra:ich Divi:.icn of !k terial Liccnsing Washington, D.C. 20545 1:c : By-Product Material License }!o. 37-07855-02 Gentlemen-Uc uish to anend Ey-Product Material License No. 37-07855-02 to authorize the ese of licensed by-product material for the fabrication of sources.

In support of our request for the amendn.cnt regarding scaled cali-bration scureca under Condition 9, Part A and B of the Metropolitan Edison Company':, By-PrcGuct Material License, the following information is pre.sented-

1. Conditienc Gl., '!A, and 8A of Ey-Product !!aterial License No. 37-n7855-02 z.2cthorizes !!ctropolitan Edison Company's .

Three ".U.e Islv.o I;uclear Station to have in its possession any b:f-product r:terial with Atomic Nos. 1 through 83 includ.ve, in eny chemical cad /or physical form, not to exec. ? 100 milli.c.n les per nuclide nor 500 millicuries toti1.

2. Metropalitan Edit.cn Company personnel, at Three Mile Island wich a utilin- the by-product material purchased under Conc.ia v:is GA. 7e.. and 8A of the license, to fabricate sour e' in exactly the same gcometry that will ultimately be uned to ceunt aamples. These fabricated sources will be usm. to develop a set of geometry, cfficiency, and self-

~ abscra tion corv .t!ca factors to enable routine calibration of _ Vium io.i_dc crystal and associated multi-channel anal.. . On ;.c calibratt.d, the sodium iodido crystal and multi-channel c icer will be used for radionuclide analysis of 15 me, gar.. : . l envirea in tal samples.

3. Up v  ; nroval c.f this amen 'm:n t , the followine, procedures and pre m Nas".. .,elhored 1 n during the fabricat.icn of ca .cn -

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3.1 Receipt of Source Material - The method of receipt, date, and description of the contents ,

will be recorded. $

3.1.1 Each radioactive source will be smeared for removable contamination. Records of the smear survey will be maintained.

3.1.2 Each source will be numbered and recorded in the Health Physics Source Inventory Log.

3.2 Storage of Source Material - All sources, when not being used, will be stored under lock and key in the Environmental Lab. The key will be under the administrative control of the Radiation Protec-tion Supervisor. When the permanent laboratories in Unit #1 are completed, the sources will be stored in the Health Physics Laboratory or the Shielded Count Room, located on clcvation 30G'-0" in the control tower. .

3.3 Source Preparation and Handling 3.3.1 The persons who handle radioactive sources at TMI are trained in Health Physics Practices. These personnel will wear monitoring devices, Film Badges, and Desimeters while handling radioactive sources.

All personnel exposures are recorded in proper logs located in the Environmental Lab or the 306' eleva-tien of the control tower. When sealed sources are opened, a By dose rate survey, and air sample will be taken.

3.3.2 Protective clothing, consisting of rubber gloves, lab coats, and shoc covers will be worn at all times during the preparation of the radioactive calibration sources.

3.3.3 All sources will be opened under a ventilation hood.

The area where the open source material is handled "

will be barricaded and posted with a " Caution Radio-active Materials Arca" sign. In addition, this work area will have plastic and absorbant paper placed on all exposed surfaces.

3.3.4 The sources uhen placed in planchets or other suitable containers, will be scaled with apoxy resin e ament and then sprayed with Krylen plastic spray or cquivalent.

For other types of sources a lid uill be cemented to the source centainer to prevent spillage during transport from the scurce storarc area to the source preparaticn area and vice versa.

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3.3.5 After scaling the scurce centainers, a smear sample will be taken of each prepared source for detection of removable contamination. Th,e detection '

limit of instrumentation used will be greater than

.005 microcuries.

3.4 Disposal of Radioactive Waste Resultinc from Source Preparation 3.4.1 Liquid waste which is expectec to amount to approxi-mately 10 to 15 gal. (Average nctivity 1 X 10-6 uci/ml) will be stored in the Heat Exchanger Vault - Source Storage Cage. (Sce origina) applicatica dated October 28,, 1971, for description of the ;ource atorage cage).

3.4.2 Solid Waste consisting of abcorbant paper and kimwipes, wil. be placed in 55 gal. drums with ccaled covers which are stored in the Heat Exchanger Vault.

5.0 Radiological Surveys -

5.1 A Beta-Gamma dose rate and cr.: car survey will be con-ducted in the laboratory source preparation area after the cources are prepared. In addition , a Eeta-Gamraa dose rate and secar survey vill be concucted once per week of the entire laboratory. Once per quarter each source container and manufar:ured co..rce will be leak tested for radioactive surface contami.:: tion. The survey detection limit of cen:aninatien is equal to or greater than .005 microcurier. -

5.2 A Beta-Gamma survey and swipe survey vill be conducted once per week in and around the sourca "torage cage in the Heat Exchanger Vault.

6.0 Source Inventory - A source _nventory ,111 he conducted once per month. Records of the inventcry will be kept in the Radiation Protection 't.,erviso;'s office.

In addition to tha preceding inforr.'atier. , we wish in add the name of Joseph J. Colitz to Condition 12 of the lice. ,1 which Mrcsses the personnel authorized to use and supervise tha use of B -n sduct :' rial. 1:r. Joseph J. Colit=, the Station Engineer, was ascign;' 'a the "Ji "ile Island Nuclear Station for the past five years as S r; 'vicor c: C mrations. He has a B.E. degree in Mechan'. cal Engineering and >

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• c cne eenth course in nuclear engineering at the University cf 1 :'. ican . ec plcted an eight (8) week course on PWI Technology and Three .* m Islm -Ign prena.ted by Babcock and Wilcox Co nany and has attended J _ al EJ - ic Comnany and Bailey Meter Company i.aursas on Thraa !!ile ~ equ; r. He 'm nine (9) years' cxperience in power plant crero  ;.

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he has completed a course in Civil Defense, where he gained experience in the proper use of Film Badges, Dosimeters, GM Survey Instruments, and .

Ion Chamber Instruments. He was responsible for initiating the Crawford Station Civil Defence !!cnitoring Plan. Mr. Colitz also completed the Reactor Operator Training Program at Saxton Nuclear Experimental Corpor-ation and subsequently obtained an AEC Reactor Operator's License.

Due to construction and l'icensing delays, we request the expiration date of our By-Product Material License be extended from November 30, 1973, to November 30, 1974.

Sincerely,

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y'. G. Miller Vice President JGM:lcw 077,9

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