Regulatory Guide 10.5

Guide for the Preparation of Applications for Type a Licenses of Broad Scope for Byproduct Material

ML13350A214
Person / Time
Issue date:	09/30/1976
From:	NRC/OSD
To:
References
RG-10.005
Download: ML13350A214 (8)

U.S. NUCLEAR REGULATORY COMMISSION September 1976

• REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 10.5 GUIDE FOR THE PREPARATION OF APPLICATIONS

FOR TYPE A LICENSES OF BROAD SCOPE FOR BYPRODUCT MATERIAL

1. INTRODUCTION 1.3 Items Requiring Separate Applicamtions

1.1 Purpose of Guide a. Gamma Irradiatiuniaciliticvs,%-

A\ separate appqlicati,.n bb`uld he .,,tdllilled f*,i This guide describes [he type and extent of iiifornia- sAl seourac aplicatio.natdl he IOU curkls chiied for oi'

scald sourrcs tia tLY*t*;iwnact lion needed by the NRC staff to evaluate an application 7 for a Type A specific license of broad scope for gamma irradiaton' aspell&Uns is availnbg upn byproduct material (reactor-produced radionuclides). request. ,; .

This type of license is provided for under Title 10, Code of Federal Regulations. Part 33. "Specific Licenses of b. Products ibted to4the Public Broad Scope for Byproduct Material." A bt 1 i does atithotii, the TheType A specific license of broad scope is intended distributiot *thIe piblic of iroducts citaiiting* ,adio- to accommodate those institutions involved in an exten. nucI'quest the Raduisutopes Licensing, sive radioactive material program where the demand is -Wan * ti ul Fuel Cycle :nd Materi:l Satctv.

great for a variety of radionuclides for many uses. Thii -*i&ec tz~inuclear Material Safety and Safegzuards. will type of license is tile most comprehensive" issued an%.. u'It' the type of ilttormitatiori that the a;plicant may be written to cover a wide range of radiunuclid&. Z, Ig"ul1 itubiit in support ot0such alt applica'iii.

(e.g., all radionuclides with atomic numbers I th 9ugJt '4' Source and Special Nuclear Materials

83) for use under the control of a radiatiu committee. The license may authorize an use " Separate applicatiOns shlould be suhi,,itted for byproduct radioactive material by anyon* a an* these materials in accordance with Part 40. "Liiccusime Of with review and approval procedures e*'IshiteJ ..le Source Ma*etria]l." and Part 70. "Special NutcleJ iMte- radiation safety committee. Therefom kindivi als are rial'" of 1O CFR. Source maJclrial is delit*ed ill ptagrla)h not namted on the license as users of ra .,aterial 4U.4(h) of 10 Ci:R Part 40 3s ( I) uranium orit ir imhll, nor are radionuclides limited to narrow. ciric uses. or any conibination theretit', isl ajny phvyic:rl to chlemical This type of license is intended for use by licensees that Iforml (or (2) ores that containl hy weight 1/20 of tire cannot operate under e limited specific license percent (0.05" ) or itlore odl(a) turaiiuilll. (1h)th10rium1. or Without seriously inc 1.1 their progrtamlls. (c) any cumbinalion Ihlertel'.. Source material doe,, nort withou siously inc ni therinclude special nuclear material.

1.2 tiSpiecial Aplicale ntuclear material is defined in liarapsaph In addition o 10 R Part 33. other regulations 70.4(ni) of 10 CFR Part 70 as (I) plu Iniium. uraniutim pertainintir t f license arc found in 10 CFR 233. uranium enriched in tie isotope 233 or ill Ihe Part 19 ! s, ructions. and Reports to Workers: isotope 235. and any other material that ihc Co(irrrris- lnspectiom 10 CFR Part 20, "Standards for Protection sion pursuant ito the provisions of Section 51 of fie Against Ra n:" 10 CFR Part 30. "Rules of General Attmic FInergy Act utif 1954, as amended. delerriiiics itt Applicability to Licensing of Byproduct Material:" and be special nuclear material hut dtles 11o1 iclitde soiricc

10 CFR Part 170, "Fees for Facilities and Materials material or (2) any material artificially enriched hy any Licenses Under the Atomic Energy Act of 1954. as orie of the foregoing but ducs ritn include source Amended." ma ItCrial.

USNRC REGULATORY GUIDES Commnents s~hould te sent to the Secretary ot the Con,,n,..wr U SNuflty.,

Reglatry -ds A*

%.*dtodowbirandmae dtedbletothepubic Rliul~ltoey Commissioan Wacth-ngton. DC MW~.5Alterma~n Duchot,,. and mnethods acceptable to the NIIC *fttall of iplemtenting specific pa's, of the ewScto Conmmit, on I eegcetatlo..e,to doeh,,eato techn~qvet used by the %fell in evalu the g..od*% ar. .%sued.. the tolt,,*.ng ton broad divisions Atn4 , sicifoc oroblerat OrpoitfulAtod Accidents. at to povaide guidance to appl#

cants Regultiory C-das DC not sub~tltutey to, *egtalions,. And com'pliance I Poe... R.., tots 6 Products

.,dhth a.t nsot #ifeqioed Malthadi and solut,GPI. .1-tle,*at lyo-, those set "It in 2 Ste%*a,ch arndTest Reacqa-y I ~np~it, this guideeillt be acceptable. of their provide &bag,%toe the finllng%,eocu.Wotto 3 Nuett and Arat.'at, Fa.1i.t.eo a Oct,aptoa Healith this .ctUAnte Of te~ntE'u4"C? i aPe-1 AI Me~

OF,Can%0 b, the Co-In,pe,t 4 1nv-ari-entat and Siting 9 Armtlo.1~ tpy Comment% anid *uqqe-t-On* ti, .ltp,acernewst - these guide, ae rok,ioAgod -5 Mate.ats anti Plant pflt'.tet,, 10 Ge,,,.,a At tt tmime,,:-d yu.odet wnil he ,.aited. at appooptsele. to Accommodate cam Zeat,iad;to reIe 10 -. ,-n-aMAl~or, or .. ec I o-mment, o.

tw~e Cop..cs 0t published guide% m'ay he obtained by, --iont request ind.cat~n9 the tfit& 'do, 04&~..ed .. the. ob.1.t t*O mril'tt allt*# it& issuiance wilt be os- dntwvao dete tl.,U Nuctear faegutatoiry Commission, Washingtonr. 0 C

t.Cute'tv uitt ne.taat.rig the need tor i'etn eoa,...Von 1055. Ateton Doirecto,. Office of Standard, Dsi,ototniont

1.4 As Low As Is Reasonably Achievable (ALARA) with all attachments, should be retained by. the appli- cant, since the license will require as a condition that the Paragraph 20.1(c) of 10 CFR states the "...persons licensee follow the statements and representations set engaged in activities under licenses issued by the Nuclear forth in the application .;nd any supplement to it.

Regulatory Commission pursuant to the Atomic Energy Act of 1954, as amended, and the Energy Reorganiza- 4. CONTENTS OF AN APPLICATION

tion Act of 1974 should, in addition to complying with the requirements set forth in this part, make every Most items of Form NRC.313 are self-explanatory reasonable effort to maintain radiation exposures, and (see instrucions with the forn). The following com- releases of radioactive materials in effluents to tun- ments apply to the indicated items of (lie form.

restricted areas, as low as is reasonably achievable."

Regulatory Guide 8.10, "Operating Philosophy for Itcen 4. State that radioactive materials are to be Maintaining Occupational Radiation Exposures As Low used by individuals designated by the radiation safety As Is Reasonably Achievable," provides the NRC staff committee, and state the name of the chairman of the position on this important subject. License applicants committee.

should give consideration to the ALARA philosophy, as Item 6(a). The usual entry is: "Any byproduct described in Regulatory Guide 8.10, in the development material with atonic numbers I through 83." If alpha.

of plans for work with licensed radioactive materials. particle emitters are to be excluded, it should be so stated. If radionuclides with atomic numbers above 83 are include-d, they should be specifically identified.**

Z LICENSE FEES

Item 6(b). Possession limits should be stated. A

An application fee is required for most types of possession limit is that quantity of" radioactive material licenses. The applicant should refer to § 170.31, that a licensee nmay have in his possession at any one

"Schedule of Fees for Materials Licenses," of 10 CFR time. For example, a total of one curie with a limit of 10

Part 170 to determine the amount of the fee that must millicuries for each radionuclide between atomic num- accompany the application. Review of the application bers I and 83, inclusive, may be adequate. If the will not begin until the proper fee is received by the applicant requires higher possession limits for certain NRC. radiunuclides, such needs should be clearly stated. It may also be necessary to limit the quantity of more

3. FILING AN APPLICATION hazardous radionuclides such as strontium 90. The possession limits for radionuclides with atomic numbers A license application for Type A licenses of broad above 83 should be stated separately from those scope should be submitted on Form NRC.313,* "Appli- requested for atomic numbers I through 83. The total cation for Byproduct Material License" (see the ap- possession limit (i.e., the total quantity of all radio.

pendix to this guide). All items on the application form nuclides that the applicant desires to possess at any one should be comp:cted in sufficient detail for the NRC time) should include those radionuclides with atomic staff to determine that the applicant's equipment, numbers above 83. The requested possession limit facilities, and radiation protection program are adequate should be commensurate with the applicant's needs and to protect health and minimize danger to life and facilities for safe handling. Stored wastes should be property. included in vstablishing both individual and total posses.

sion limits.

Since the space provided on Form NRC-313 is Item 7. Describe the type and extent of use of limited, the applicant should append additional sheLts to radioactive materials at each address given in Item l(b).

provide complete information. Each separate sheet or Such descriptions may be given in general terms but document submitted with the application should be should characterize each use*** to the extent necessary identified by a heading indicating the appropriate item for a determination by the NRC staff of the suitability of number (Form NRC-313) and its purpose, e.g.. radiation safety instructions, etc.

"Source or special nuclear material should not be Included.

The application should be completed in triplicate. Separate applications should be submitted for these materials in accordance with 10 CFR Parts 40 and 70.

The original and one copy should be mailed to:

Radiuisotopes Licensing Branch, Division of Fuel Cycle *"*A broad specific license does not authorize the use of and Material Safety, Office of Nuclear Material Safety radlonuclides in the field whete release of tadioactive material to the environment is involved. Approval of requests and Safeguards, U.S. Nuclear Regulatory Comnission, for such uses is dependent upon supporting Information Washington, D.C. 20555. One copy of the application, specific to such uses. Upon request, the Radioisotopes Licensing Branch, Division or Fuel Cycle and Material Safety, Office of'Nuclear Material Sarety and Safeguards.

• Form NRC-313 was formerly designated Form AEC-313. will describe the type of information necessary for an Existing copies or Form AEC-31 3 may still be used. applicant proposing such uses.

10.5-2

the equipment, facilities, and personnel training and 1It,: 12. Describe fully the personnel monitoring experience. program, including the types of monitoring devices to he used, the criteria to be used in determining the need for lictis 8 and 9. In addition to the information each type or device. the name of the organization requested in Item 14 and specified below, the criteria furnishing Film badge or thermoluminescent dosimeter and procedures for training and detcrmining an accept. (TLD) service, and the frequency for changing badges.

able level of knowledge of all persons who will work in rings, etc. If pocket chambers or pocket dosimeters arc or frequent a restricted area (i.e., users of radionuclides, used, state the useful range, frequency of reading. and technicians, health and safety personnel, janitorial work- the procedures for maintaining and calibrating the ers, etc.) should be described (refer to § 19.12 of 10 devices.

CFR Part 19). The maintenance of records of all The applicant should show that the need for bio- training, testing, and competency determinations should assays has been thoroughly considered and should be specified in the application.

establish the adequacy of the proposed bioassay pro- Item 10. List the minimum number of radiation gram in relation to the proposed program of use of surveying, monitoring, and measuring instruments that radioactive material. Bioassays are normally requited the applicant will have available for the safe use of when individuals work with millicurie quantities of radioactive material in accordance with Commission hydrogen 3, iodine 125, or iodine 131 depending on the regulations. The applicant should specify the type of type of work. equipment, and procedures followed.

instruments that will be made available to individual Other materials may also be used in physic:. or chemical users. forms and under conditions that present an opportunity for uptake by the body through ingestion, inhalation, or Instruments should be listed by characteristics (i.e., absorption. A bioassay program to determine and detector type, radiation detected, detection range, win. control the uptake of radioactive material should be dow thickness, etc.) and intended use (i.e., measuring, considered and discussed in relation to each such surveying, monitoring, etc.). material, procedure, etc.

Item 11. Describe the instrument calibration pro. The criteria to be used in determining the need for cedure. State the frequency, and describe the methods bioassays, the type and frequency of bioassays that will and procedures for calibration of survey and monitoring be performed, and the bioassay procedures should be instruments, as well as any other instruments and specified and described in detail. If a commercial systems used In the radiation protection program, such bioassay service is to be used, the name and address of as measuring instruments used to assay sealed.source the firm should be provided.

leak-test samples, contamination samples (e.g., air sam- pies, surface "wipe" samples), and bioassay samples (see Bioassavs may not be substituted for other elements Item 12). of a safety program such as air monitoring and disper.

sion control (hoods, glove boxes. etc.) and (or well.

An adequate calibration of survey instruments usually thought-out and well-executed handling procedures.

cannot be performed with built.in check sources.

Electronic calibrations that do not involve a source of Item 13. A general description should be providcd of radiation are also not adequate to determine the proper facilities and equipment (e.g., buildings, hood ventilation functioning and response of all components of an and filtering systems, general air and stack monitoring instrument. systems, remote handling equipment) and access control methods used in association with the handling and Daily or other frequent checks of survey instruments storage of byproduct material.

should be supplemented every 6 months with a two. Minimum facilities should be described, and an point calibration on each scale of each instrument with explanatory sketch should be included of each area (i.e..

the two points separated by at least 50% of the scale. site, building, laboratory, room) where especially haizard- Survey instruments should also be calibrated after repair. ous materials are used and stored or where especially hazardous operations are performed.

A survey instrument may be considered properly calibrated at one point when the exposure rate measured Radionuclides to be used in specific areas may be by the Instrument differs from the true exposure rate by identified by their characteristics (i.e., beta emitter.

less than 10% of full scale. gamma emitter, etc.) in lieu of specific atomic and mass numbers.

If the applicant is contracting out the calibration or instruments, the name, address, and license number of NOTE: Information submitted in support of a license the calibrating firm should be given along with the application will become part of any license that is issued.

frequency of calibration for each type of instrument. This means that the licensee may be required to obtain a

10.5-3

license amendment prior to making changes to his consideration of the adequacy of facilities and equip- facilities or equipment. ment; operating, handling, and emergency procedures;

and tile experience and training of the proposed users of Item 14. All components of the application that the material.

contribute to the radiation protection program should be discussed in a narrative that establishes their relation- (d) Procedures used for controlling and main- ships, interfaces, and contributions to the overall radi- taining inventories, procurement of radioactive material, ation safety program. The relationships of the radiation individual possession limits, total possession limit, trans- safety committee, the radiological safety officer, and fer of radioactive material within the institution, and management should be included. An o:ganizational chart transfer of radioactive material to persons outside the or charts may be helpful In this regard. institution.

The application should demonstrate that the appli- (e) Methods employed for maintaining records cant can comply with license requirements and NRC of tihe committees proccedings and safety evaluations of rules and regulationts and should clearly show an active proposed uses of radioactive material.

and continuing involvement in program control by management. (f) Periodic review of the safety program, including review of records required to be maintained.

a. Radiation Safety Committee b. Radiological Safety Officer*

Paragraph 33.1 3(c) (1) of 10 CFR Part 33 requires that a radiation safety committce be established. This Paragraph 33.1 3(c) (2) of 10 CFR Part 33 requires commitlee should be composed of such p-rsons as a that a radiological safety officer be appointed. The radiological safety officer, a representative of manage- radiological safety officer should be responsible for ment. and other persons trained and experienced in the safe use of radioactive materials. One of the main overall radiation protection within the institution. A

description of his training and experience in radiation Ii functions of the radiation safety committee is to protection and with radiation and radioactive material administer the institution's radioactive material program. should be provided. A statement should be included The committee should have the authority and responsi- delineating his duties, responsibilities, and authority for bility for approval and disapproval of all proposals for carrying out the radiation safety program. The extent of radionuclide use prior to purchase of the materials. his responsibility and authority will depend on the scope The following information concerning the commit- of the proposed program; however, the following should be considered:

tee should be submitted:

(1) General surveillance over all activities involv-

(1) A list of members of the committee. ing radioactive material, including routine monitoring and special surveys of all areas in which radioactive

(2) A description of each member's training and material is used.

experience with radiation and radioactive material.

(2) Determining compliance with rules and regula-

(3) A specific and detailed description of the tions, license conditions, and the conditions of project control functions of the committee and tile administra- approval specified by the radiation safety committee.

live procedures by which these functions are carried out, including the following: (3) Monitoring and maintaining absolute and other special filter systems associated with the use, (a) Responsibilities, duties, and authority of storagec or disposal of radioactive material.

the committee.

(4) Furnishing consulting services on all aspects of (b) Frequency at which the full committee (or radiation protection to personnel at all levels of respons.

quorum) meets to discuss and act on proposals for the ibility.

use of radionuclides. If less than the full committee is empowered to act for the committee, the number of (5) Receiving, delivering, and opening all ship- members constituting a quorum, as well as their names ments of radioactive material arriving at the institution or fields of expertise, should be specified. and receiving, packaging, and shipping all radioactive material leaving the institution.

(c) Procedures and criteria established for mak- ing safety evaluations of proposed uses of radioactive Thie terms "radiologist afety officer" and "radiation protec.

material. The procedures and criteria should include tion offim.:" are synonymous

10.5.4

(6) Distributing and processing personnel mioni. (I) Process fur obtaining ipermission it)to,, radio.

toring equipment. dctermining die need for and evalua. active materials at the inritutinito.

I tion of bivassays: keeping personnel c 1IWsuWe and bioassay records; and notifying individuals and dicir supervisors of exposures approaching niaximniu perntis- (2) Care, selection, and use of protective upparel sibic amounts ane recommending appropriale remedial and other equipment and facilities.**

action.

(7) Conducting trainiing programs and otherwise (3) Limitalimns and conditions (special equip- instructing personMel in the proper procedures for the ment, facilities, and procedures) relative to haiidlirg,- use of radioactive material p[rior t) use. at periodic liquid, gaseous, finely divided or tncontaimcd tadio.wtivc materials* and the equipment to use in working witi intervals (rtfrcshej training), and as required by changes them. For example. the types of materials and opera- in procedures, equipment, regulations. etc.

tions that should be confined to ventilated equipmentnt with filte r.d exhaust systems (e.g.. radiochemical fltine

(8) Supervising and coordinm'ing the radioactive hoods or glove boxes) and the types and amounts of waste disposal program, including keening waste storage shielding and re"-.., li:bndling equipment to be used and disposal records and mtonitoring effluents.

with hard beta- a,n dj,, eamnta-emitting materials shotld

(9) Storing all radioactive materials not in current be defined.

use, including wastes.

(4) Special e.,uip-nent, procedutes. -nd ptecau.

(10) Performing leak tests on all scaled sources. tions to be used in %,.orking with neutron and lplia- particle etiitiers and radionuclides that decay by (I I) Maintaining an inventory of all radioisotopes spontaneous fission.

at the institution and limiting the quantity of radio- nuclides at the institution to the amounts authorized by the license. (5) Surveying and monitoring procedures a. be followed during day.to-day operations.

(12) The authority to terminate immediately a project that is found to be a threat to health or

(6) Emergency procedures and instructions con- I property.

cerning spills, fires, release or loss of material, and

(13) Maintaining other records not specifically accidental contarnination of personnel. including decon- lamination procedures and those persons to he notified designated above, eg., receipt, transfer, and survey records as required by §30.51 of IOCFR Part 30. in an emergency.

c. Radiation Protection Procedures (7) Posting and control of access to restricted areas, radiation areas, 'high radiation areas. etc. (see A formal set of rules, instructions, and procedures §20.203 of 'OCFR.Part 20).

for procurement, disposal, and safe handling of radio- nucildes within the institution should be established by (8) Requirements for material storage and safe.

the radiation safety committee. A copy of these rules guarding: labeling containers: processing and storing con- and procedures in the form in which they will be given taminated articles, including 6gassware: and identifying to all personnel under the jurisdiction of the committee areas where radioactive material is used and stored (see should be submitted.* Where instructions are given with §20.203 of 10 CFR Part 20).

respect to an action necessary for compliance with NRC

regulations (e.g., waste disposal), such instructions should be specific and not consist of a simple reference to the regulations. **A complete description of respirator), protectivn devi's and procedures for fitting, sanitizing, and repairing should be The written radiation protection procedures included. Credit for respiratory protection cannot bXetaken should be clear and concise and should cover the unless approved by the Commission pursuant to §20.10.3 of following: 10 CFR Part 20.

• Although a specific set of rules and procedures Is desired as a *nThosc applications or operations that present unusual basis for evaluating the license application, the applicant may hazards because of the nature or the material, the quantity specify that certain portions of the documents may be revised involved, and the type of operation and that may require without prior notification of the NRC staff. Those sections specialized facilities should be covered in separate instruc- containing specific dates. references to particular pieces of tions rather than incorporating these instructions in the main

• equipment, etc., may be considered in this category. body or the radiation protection procedures.

10.5-5

(9) Care and use of personnel monitoring devices, e. Treatment or disposal by incineration In confor- where to obtain them, and where and when to record mance with §20.305 of 10 CFR Part 20.

exposure results.

f. Other methods specifically approved by the NRC

(10) Requirements for bio3ssays, if any, and the pursuant to §20.302 of 10 CFR Part 20.

procedures for providing bioassay samples.

(11) Transporting radioactive material between 5. AMENDMENTS TO A LICENSE

buildings and rooms.

Licensees are required to conduct dheir programs in

(12) Acceptable and unacceptable levels of con- accordance with statements, representations, and pro- tandnation (fixed and removable) for equipment, facili- cedures contained in the license applicatlun and sup- ties, clothing, skin, etc., in both restricted and un- portive documents. The license must therefore be restricted areas and protective action (i.e., decontamina- amended if the licensee plans to make any changes in tion, disposal. etc.) to be taken with respect to facilities, equipment (including monitoring and survey unacceptable levels. instruments), procedures, personnel, or byproduct material to be used.

(13) Requirements and procedures for leak-testing sealed sources. Applications for license amendments may be filed either on the application form or in letter form. The

(14) Requirements and procedures for waste dis- application should identify the license by number and posal, inluding limitations on disposal of liquid, should clearly describe the exact nature of the changes, gaseous, and solid wastes. If radionuclides will be additions, or deletions. References to previousiy submit- administered to animals, instructions for cleaning animal ted information and documents should be clear and quarters and handling animal excreta and carcasses specific and should identify the pertinent information should be included. by date. page, and paragraph.

(IS) Requirements and procedures for the development and maintenance of records with respect to the receipt, use, and disposal of radioactive material.

6. RENEWAL OF A LICENSE

(16) Requirements and procedures for picking up, receiving, and or-cning packages (see § 20.205 of 10 CFR An application for renewal of a license should be filed Part 20). at least 30 days prior to the expiration date. This will ensure that the license does not expire until final action Item 15. A specific method for disposing of by. on the application has been taken by the NRC staff as product material waste should be described. A licensee provided for in paragraph 30.37(b) of 10 CFR Part 30.

may dispose of waste in the following ways:

a. Transfer to a person properly licensed to receive Renewal applications should be filed on Form NRC-313, appropriately supplemented, and should con.

such waste. tain complete and up-to-date information about the b. Release into a sanitary sewer in conformance with applicant's current program.

§20.303 of 10CFR Part 20.

In order to facilitate the review process, the applica- c. Burial in soil in conformance with §20.304 of 10 tion for renewal should be submitted without reference CFR Part 20. to previously submitted documents and information. If such references cannot be avoided, they should be clear d. Release into the air or water in conformance with and specific and should identify the pertinent informa.

§20.106 of 1OCFR Part 20. tion by date, page, and paragraph.

10.5-6

APPENDIX

farm~ A(C-3l53 UN"ID 10SIA**S AtOPA INCI"416 COMM/5lOr,0

• 1 42.131

11) CFi I0 APPLICATION FOR BYPRODUCT MATERIAL LICENSE 11r "ft- gNST$RUCTIONS -Conigtl.l fierm I lrh'ovh l6 dl Ihs .%a,*'a Appsl-cal-oEOr 4, Ittt"Call.of to, wow~@s,of a hCOM1a Wo-Ml0,¶A C0¶fltd m v '-

caml VIoll aptplcallons filed *-th thitComm~uwom wah respect to ftems 6 tlhot.gft IS may bre-i'itwo'soled b, reference pl'0.ded tefffemces A'S Cfs~f and sapOcitic Ue supplarmeftal shoots whereE necessary nerm tb mull be cc-pletled on all Appi-CUl-ont &#&. t.0 too-as 10 U S AloC-c Energy 0romra,t- soon. WasI¶hm~lof. 0 C .20$45 Aflonl,oni Ue#1t~ras stanch D,'erloral# of Lwloflliq Upon applo.81o01.So*pihti.of. h q Ohs SAVI,tiam inm-u~~ an AEC

Byproduct Materral Li~qnso An AEC l,v'odwct 1641wr,81 L~corse -s issued .n occordamcs .Ili th~egr.a ornel Contarled .' Life 10, Cod* of Fad.

• SICRotgualtins. Pall 30 Old the Licence. -S lu"tdl 10 Tun '0 Code of Fedwa1 RegulAhorr Pall 20 $Ad the I-cetw to* pro.I-a-s 0; T~tke10 Codf of Fedsirst Reguelations, Part 110 Thet1cors ta feaeteottfi ShOW14 be Stated let Item T6 anidme gooarophtotoo encltioda (546 Note 'n lerst'.,ctuof SP-eels I lei P~lt Alit)STRIEV LOA0011SOO0 APOLtCANI ji l..ro, t.-. "toils' pe b. S111111 taS$LS At -.. C. .. II , .,C~~I

.t $1*C1 sofl Stei..fP o.Cd,~Ar..m. d.'.e. '.1ýI- l. 1.4I. 10 C %

2 01?Altffltt4 It) QU1 *vf#O0V1 .Aft&IAI I 0PEIAIOUS liCINS1 t.(JAleis1 ( 0'i0' *m0i w00W -4.%~o 0d 9 -. -Ce 1

4 INDIVIDUAl U31#131tM.No.. 0,.4 frI e -he.,,

A..I .. #i or*dw.), 5 NAIapATtOf 0*o07WPO,. 0111CIN lNo-t.05 P.-~~ -~.'

.a oof.bippid.0 ao'w' G..# rto'a-9 -4 O*.P.-O 11 I. 0-d 9 OrW J5 ws.. fmr .. d... . £9. -. ,-.o o A-$ 1-0-9 rfd -ow-o.

6 tei dIPIOoucf u"llsimA tl6-04 tbi 0CNEMICAL AP40,OC PH111ICAL001" Ap40 MAI-vwl HIJA4IS Of MItCURIIl Of I -C. Cn.1-CAt AND )A 04 trrr end i1 .. 0b" of l'ot I OCLtI 9015 VHAt IOU WtL~ P0$54$$ At AV Ot.1 ISfi 91ooil 4 i0 5-'...,..-t.~-.

of -11.'- Goo . 0l' i

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04"... If b~pu.4. I-'.W - ft t...

o .0 .. ebd ... -',.U 0. ~Iw* -~d 1Oe .0.

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-- oe-04- do... I0. o ~v.-

asfed o.e .-. d)

(Confiftwed ileanamiet Glde

10.5-7

APPENDI X- (Continued)

1 TRAINING AND EXP~QENCi OF EACH INDIVIDUAL NAM!OD IN ITEM * , ve.o '..'

a P,,Xoo.s o~d 0533et 03 *of~'o- * ~

4

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