L-0312-451, Revised Radiation Safety Code & QC Manual

Revised Radiation Safety Code & QC Manual

ML20009D240
Person / Time
Site:	07000124
Issue date:	04/15/1981
From:	TELEDYNE ISOTOPES
To:
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ML20009D236	List: L-0312-451, Revised Radiation Safety Code & QC Manual ML20009D234 ML20009D237
References
18988, IWL-0312-451, IWL-312-451, NUDOCS 8107230311
Download: ML20009D240 (72)

Text

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WTELEDYNE ISOTOPES I

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I RADIATI0fl SAFETY CODE AtlD I

QUALITY C0tlTROL MANUAL l

APRIL 1981 I

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IWL-0312-451 Revised:

4/15/81 Approved:

Effective 109S3 Date:

5/1/81

l W TELEDYNE ISCrrOPES 7 Ante OF CONTENTS 11 I

I-MANAGEMENT POLICY AND ORGANIZATION I-1 1-

1.0 INTRODUCTION

I-1 1.1 Statement of Basic Policy I-1 1.2 Implementation of Policy I-1 1.3 Philosophy of Radiation Safety:

Risk vs. Benefit I-1 1.4 Organizational Chart I-2 I-2.0 RADIATION SAFETY COMMITTEE I-3 2.1 Responsibilities I-3 2.2 Membership 6 Qualifications I-3 2.3 Executive Subcommittee I-3 Table 2.2 Members of Radiation Safety Committee I-4 2.4 Safety Subcommittee I-5 2.5 Records I-5 2.6 Qualifications of the Company Health Physicist and the Radiation Safeti Officer I-5 Tabic 2.4 Members of Safety Subcommittee I-6 Resume - Donald F. Schut:

I-7 Resume - Eugene B. O'Brien I-8 I-3.0 llEALTH PHYSICS OFFICE I-9 3.1 Personnel I-9 3.2 Duties I-9 3.3 Records I-11 3.4 Reference hbterial I-11 3.S Professional Association I-11 I-4.0 PROCEDURE FOR REVISING RADIATION SAFETY CODE I-12 6 QUALITY CONTROL MANUAL 4.1 Writing a Procedure or Producing a Form I-12 4.2 Submission and Review I-13 II -

GENERAL PROCEDURES FOR CONTROLLING RADI0 ACTIVE MATERIALS II-1 RADIATION EXPOSURES II-1.0 INDOCTRINATION OF PERSONNEL EXPOSED TO IONIZING RADIATION II-2 1.1 Company Policy on Matters Involving Radiation Exposure II-2 I

1.2 Indoctrination of Personnel II-2 1.3 Rights 6 Responsibilities of Radiation Workers 6 the Company II-2 Regarding NRC Licensed Activities II-2 1.3.1 Exposure History 1.3.2 Notification of Violations During Inspections II-3 1.3.3 Notice of Violations, Adverse Conditicrs, or II-3 Potential Violations or Conditions Prior to an Inspection 1.3.4 Procedure for Reporting Violations and/or Potential II-3 Violations 1.3.5 Requirement for Posting NRC " Notice of Violations" Il-4

WTELEDYNE ISOTOPES TABLE OF CONTENTS (cont'd) ill II-2.0 MEDICAL EXAMINATIONS AND' EMERGENCIES II-5 2.1 Pre-Employment Medical Examination 11-5 I

2.2 Follow-up Medical Examination II-5 2.3 Termination Medical Examination II-5 2.4 Accidents Involving Radiation II-5 2.5 Emergencies G Decontamination of Equipment II-6 I

2.6 Fire II-6 2.7 Security II-6 II-3.0 LABORATORY PRACTICES IN SAFE IIANDLING OF RADIOACTIVE II-7 FMTERIAL 3.1 Personnel Directives II-7 3.2 Minor Spills II-7 3.3 Major Spills II-8 3.4 List of Persons to Call in Radiation Emergency II-9 3.5 Contamination Control 11-10 II-4.0 ORDER, TRANSFER, RECEIPT G SilIPMENT OF RADI0 ACTIVE MATERIAL II-11 4.1 Order II-11 4.2 Transfer 11-11 4.3 Receipt II-11 4.4 Shipment II-11 II-5.0 PERSONNEL MONITORING II-12 5.1 External Dosimetry II-12 5.2 Internal Dosimetry II-12 II-6.0 SURVEYS II-14 6.1 Area Surveys II-14 I

6.2 Decontamination II-14 II-7.0 INSTRUMENT CALIBRATION II-15 I

7.1 General II-15 7.2 Gamma Calibration 11-15 l

7.3 Beta Calibration 11-15 7.4 Alpha Calibration 11-15 II-8.0 RADIOACTIVE WASTE PACKAGING S DISPOSAL II-16 8.1 Training 6 Retraining of Personnel Involved with Safe II-16 I

Packaging of Radioactive Material l

Tabic 8.2 Radioactive hbterial Packaging Guide II-17 8.2 Classification of Radioactive Waste to be Packaged for II-18 I

Shipment 8.2.1 Characteristics of bbterial to be Packaged 11-18 i

l 8.2.2 Type of Material (Proper Shipping Names)

II-18 l g 8.2.3 Determination of Shipment Specification 11-18 E

8.3 Packaging Procedures for Radioactive Waste 11-19 8.3.1 General 11-19 8.3.2 Dry Solid Material 11-20 I

8.3.3 Small Volume Liquid Waste, Scintillation Vials 11-20 or Other SVL's

8. 3. 4 Large Volume Liquid Waste 11-21 I

8.3.5 Animal Carcasses or Biological Naste 11-21 8.3.6 Liquid Special Nuclear Mnterial 11-22 I

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TTELEDYNE ISOTOPES TABLE OF CONTENTS (cont'd) iv I

II-9.0 INTERSTATE OPERATIONS II-24 Tabic 9.0 List of Licensing Officials in Agreement States II-25 II-10.0 SECTIONS I 6 II FORMS 11-28 I

III-3.0 SPECIAL PROCEDURES FOR NRC LICENSE NO. SNM-107 LICENSED III-1 ACTIVITIES I

3.1 Introduction III-1 l

3.2 Training and Retraining III-1 3.3 Radiation Survey Program III-1 E

331 h'ecktY survers Itt-1 3

3.3.3 Air Monitoring III-3 3.3.4 Effluent Ifold-up and Release III-4 3.4 Shipments III-5 3.5 Records Management III-5 3.6 Material Control Provisions III-5 3.7 General Safety Rules III-5 3.7.2 General Safety Instructions for Glove Box Use III-6 III-3.4 FORMS SPECIFIC FOR SNM-107 LICENSED ACTIVITIES III-8 I

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I TTELEDYNE ISOTOPES I-1 I

RADIATION SAFETY CODE AND QUALITY CONTROL MANUAL I

SECTION I - MANAGEMENT POLICY AND ORGANIZATION I

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1.0 INTRODUCTION

I-1.1 Statement of Basic Policy The basic policy underlying this Radiation Safety Code and Quality Control Manual is that the health and safety of personnel working I

with ionizing radiation and the release of radioactive contaminants to the environment are of paramount importance to Teledyne Isotopes. All decisions, rules and recommendations will be made with the basic premise that levels of I

rediation exposure are to be minimized to the lowest that can be reasonably achieved (ALARA).

I-1.2 Implementation of Policy The policy is enunciated by a Radiation Safety Committee composed of members drawn from various Company departments who use or manage the use I

of sources of ionizing radiation. The implementation of decisions of the Radiation Safety Committee is the responsibility of the llealth Physics Office.

I-1.3 Philosophy of Radiation Safety: Risk versus Benefit I

The benefits to be derived from the use of ionizing radiation may require some risk of exposure to radiation.

In such instances it is neces-sary to strike a balance between risk and benefit in keeping with basic company policy. This decision is part of the function of the Radiation Safety Committee together with the IIcalth Physics Office. Though strict objective criteria cannot be drawn up to apply in all circumstances, objec-tive guidelines and established regulations will be followed wherever I

possible.

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I TTELEDYt!E 33 ISOTOPES 1-2 RADIATION SAFETY C05t!ITTEE I0 I-2.1 Responsibilitics 1he Radiation Safety Committee is responsibic to the President of Taledync Isotopes. The responsibilitics of this Committee are:

1)

Formulate special Company policy in the area of radiation safety.

2)

Make decisions on the uses of and approve the users of ionizing radiation.

3)

Approve new facilitics for u n of ionizing radiation by the Company.

4)

Approve changes for existing facilitics.

5)

Enforce the safety requirements of international, federal, state, and local rgencies as well as the proceduras and policies as set forth by I

the P.adiation Safety Code and Quality Control >!anual.

I-2.2 Membership 6 Qualifications The Committee is composed of members from the following Divisions, Sections, or Areas of Responsibility:

1) Health Physics

2) Services

3) Products

4) Administration Membership mcy be changed as necessary. The present membership of this ICommitteeisshowninTableI-2.2.

The overall Company organization is shown in l

Figure I-2.1.

All members of the Radiation Safety Committee must have a college IcVel degree and be familiar with radiation safety procedures and regulations. All I

members of the Radiation Safety Committee must also be of management 1cyc1 or highet, or a menber of the IIcalth Physics Department with a minimum of 2 years experience.

1-2.3 Executive Subcommittee An Executive Subcommittee comprised of the Chairman, the Company llcalth I

Physicist, R.S.O. and Alternate R.S.O. is authori:cd to act on behalf of the committee for approval of necessary actions between regular meetings of the Radiation Safet y Committee. A quorum shall consist of either the Chairman or I

ompany llcalth I'hysicist and the R.S.O. or Alternate R.S.O.

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I-4 WTELEDYNE ISOTOPES TABLE I-2.2 MEMBERS OF RADIATION SAFETY COMMITTEE I

Donald F. Schutz, Chairman President.

Jack E. Ross, C.H.P.

Manager, Plum Brook Operations Company Health Physicist Steven A.. Black Manager, Radiological Services Radiation Safety Officer Douglas M. Eagleson Health Physics Department Alternate Radiation Safety Ofilcer

'J. David Martin Manager, Environmental Services Vice President I

Carl H. Distenfeld Manager, Nuclear Instrumentation Vice President Lewis F. Casabona Manager, Nuclear Fuci Services Senior Scie'ntist

' Eugene B.0'Brien Mancger, Administration 6 Finance Vice President 1

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l WTELEDYNE ISOTOPES I-5 I-2.4 Safety Subccmmittee A Safety Subcommittee comprised of various representatives of operational departments will make recommendations to the R.S.C. for implementation of safety programs beyond the specific scope of radiation safety but within the requirements for general health and safety. The Safety Subcommittee is chaired by the Manager, Personnel Department, and membership is presented in Table I-2.4.

I I-2.5 Records The Radiation Safety Committee is required to keep minutes of all I

quarterly meetings.

I-2.6 Qualifications of the Company 11ealth Physicist and the Radiation Safety Officer 2.6.1 The Company IIcalth Physicist must have a B.S. degree in IIcalth Physics I

or related field and have 4-5 years of practical health physics experience. lie must also be certified by the American Board of Ilealth Physics or have 8-10 years practical experience.

2.6.2 The Radiation Safety officer must have a B.S. or A.B. in IIcalth Physics or related fic1d, and have 3-5 years practical licalth Physics experience.

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W TELEDYNE ISOTOPES 1-6 TABLE I-2.4 MEMBERS OF SAFETY SUBC05NITTEE Ann Alston Supervisor, Radiation Chemistry George Ascione Supervisor, llealth Physics R G D Andrew Carmichael Supervisor, Gas Analysis Georgiana Kalechitz Supervisor, Potassium Argon Lab Steve Kaminsky Assistant Scientist Doris McThomas Personnel Manager llelsn Principe Administrative Assistant Alan Skaar Electronic Maintenance 6 Development Cindy Valdes-Pages Assistant Scientist Robert Pavese Building Manager I

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I-7 TTELEDYNE ISOTOPES DONA 1.D F. SCIIUTZ, Ph. D.

RESUME I

PRESIDENT Dr. Schutz is President of Tcledyne Isotopes.

In this capacity ha has overall responsibility for all activities of Teledyne Isotopes including pruh ets, services and research in thermoluminescent dosimetry, sodium iodide crystal manufacture, radiological waste disposal, environmental radicactivity B

monitoring, nuclear fuel analysis, geochronometry, tracer applications, and isotope geochemistry.

From 1970 to 197S Dr. Schutz was Vice President of the company in charge of the Westwood Laboratories. Prior assignments have included Manager of the Nuclear Geochemistry Department at Teledyne Isotopes from 1968 to 1970, with responsibility for projects for the study of radioactive products B

of underground nuclear explosions carried out for the' Nuclear Monitoring Research Office of the Defense Advanced Research Projects Agency (DAPSA),

the Arms Control and Disarmament Agency (ACDA), and the Atomic Energy com-I mission. His responsibility ranged from laboratory studies of inert gas extraction and radio-assay techniques to engineering development of sampling and detection systems. He has participated in and directed numerous field I

operations at the Nevada Test Site and at various off-site nuclear test areas in Mississippi, New Mexico, Colorado, Nevada, and Alaska. More recently Dr. Schutz has been principal investigator on Department of Energy projects I

concerned with the application of nuclear techniques to the exploration for uranium ore deposits.

Prior to joining Teledyne Isotopes in 1964, Dr. Schutz was a Re-I.

search Staff Geologist in the Department of Geology at Yale University. His work in that capacity was primarily concerned with development of analytical techniques for determination of trace elements in seawater and stream water I

by neutron activation, X-ray fluorescent and emission spectrographic analysis.

The techniques developed were applied to a worldwide sampling of seawater which included samples taken by Dr. Schutz in the Antarctic during the summer of 1963-1964.

At Rice University Dr. Schut: completed a statistical study of regional variations in the chemical cc: position of basaltic rocks.

During f.

the su=mers of 1955 to 1956 Dr. Schut: worked for the Bear Creek Mining Company on geochemical prospecting projects in the states of Maine and Arizona, and prior to that he worked for States Exploration Company in Texas.

Dr. Schutz received the B.S. (cum laude) in Geology from Yale Uni-versity in 1956 and M.A. in Geology from Rice University in 1958. He re-f ceived his Ph. D. in Geology from Yale University in 1964 upon completion of a thesis which dealt with development of methods for applying neutron activation analysis to detemine the geographical and vertical distribution of trace cle-ments in seawater.

Professional and technical memberships include Sigma Xi, Geochemical Society, American Geophysical Union, American Nuclear Society, Air Pollution f

Control Association, Society of Petroleum Engineers of A.I.M.E., Society of Petroleum Exploration, American Association of Petroleum Geologists, and Geological Society of America.

Dr. Schut: recently served on a Task Advisory Group for evaluation of the options for Further Decommissioning of the Plum Brook Reactor Facility, lie is Chairman of the Radiation Safety Committee.

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I-8 TTELEDYNE ISOTOPES RESUME

'I Eugene B. O'Brien, B'.s.

Vice President - Administration and Finance Mr. O'Brien is Vice President of Administration and Finance at f

the Westwood Laboratories of Teledyne leotopes.

His responsibilities include supervision of Program Planning and Control, Contracts Adminis-tration, Personnel, Building Services, Purchasing, Shipping and the f

general administration of the Profit Center.

He is responsible for the coordination and monitoring of performance of each operational depart-Prior to joining Teledyne Isotopes in 1967, Mr. O'Brien worked as a Senior Contracts Administrator at Thiokol Chemical.

During this period he was involved extensively with the administration of research f

and service contracts with various agencies of the U. S. Government.

Between 1958 and 1963 Mr. O'Brien held various engineering administration positions with Curtiss Wright Corporation.

As a Program Planner he was responsible for preparing program cost analysis reports for customers and management.

He is experienced in all 000, DOE and f

NASA cost reporting techniques.

Mr. O'Brien received his B.S. degree in Business Administration from Fairleigh Dickinson University.

He has also attended flewark College f

of Engineering for various Engineering courses, including Pert courses.

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ISOTOPES I-3.0 IIEALTil Pl!YSICS OFFICE I-3.1 Personnel This office is staffed by a qualified person in the field of Ilealth Physics and radiation protection. This person's title is Company llealth Physicist and performs or oversees the work of the person designated as Radiation Safety Officer (RS0) on the various licenses. The RSO is assisted by sufficient staff to carry out the Radiation Safety Program as set forth in this manual.

I-3.2 Duties The duties of this office are:

1) Approve all requests for purchase or use of radioisotopes (IlVL-ilP-04).

2) Survey all radioisotopes received by or shipped by Teledyne Isotopes (IWL-ilP-05).

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3) Maintain radiation histories of all Teledyne Isotopes personnel working with or exposed to sources of ionizing radiation (IWL-lip-11 6 NRC Form 4 or equivalent).

4) Periodically survey and make recommendations concerning Teledyne Isotopes radiologically controlled areas.

5) Dispose of all radioactive waste generated on Teledyne Isotopes property or under Teledyne Isotopes licenses.

6)

Prepare emergency procedures in case of an accident involving ionizing radiation.

7)

Indoctrinate all new Teledyne Isotopes personnel who will be working with, or be exposed to sources of ionizing radiation (IWL-ilP-07).

l 8)

Perform quarterly calibrations of all radiation survey instruments (IWL-lip-08).

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9) Perform semiannual Icak tests of all licensed scaled sources owned l

by Teledyne Isotopes.

10) Assure compliance with all effective licenses and apply for amendments i

and renewals in a timely manner as approved by the Radiation Safety i

Committee.

11)

Formulate procedures for, revise, and maintain the Radiation Safety Code and Quality Control Manual.

12) Serves as Technical Advisor to llcalth and Safety Subcommittee of the Radiation Safety Committee.

Provides liaison with the Radiation Safety Committee and submits recommendations for approval.

13) Approve all users of radioactive materials (IWL-IIP-06).

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l WTELEDYNE I"10 ISOTOPES

14) The Company llealth Physicist has the authority to shut down operations if he feels the continuation of activities could pose a hazard to the health and well being of the employees or the general public. The Radiation Safety Officer will have this authority when the Company licalth Physicist is unavailabic.

15) The Radiation Safety Officer will review all survey and persor.ncl monitoring data and report to the Radiation Safety Committee, at periods not exceeding one year, his recommendations to reduce exposure with respect to ALARA.

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TTELEDYNE ISOTOPES I-11 i

I-3.3 Records Records are maintained by the llealth Physics Office on the following:

1)

Licenses and license applications.

2)

License inspection reports and responses.

3)

Radiation history, past and present, on all Telodyne Isotopes per:onnel.

4)

All requests for sources of ionizing radiation.

5) h*aste disposal.

6)

Surveys and recommendations.

7)

Calibration results.

8)

Surveys of all scaled sources.

1-3.4 Reference Material 1)

Maintains a current file of all domestic and foreign regulations pertinent to activities under the various licensed activities.

I

• 2)

Maintains a reference library of health physics, radiation protection and related measurement technology as required for support of licensed activities, license revisions, and expansion of business in related areas.

I-3.5

, Professional Association 8

1)

Maintains membership in appropriate local, state, national and i

international professional societics as required to remain current f

in development of radiation protection philosophy, regulation, and techniques, and to enhance Teledyne Isotope s professional reputation and explore opportunities for future business.

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WTELEDYNE I-12 ISOIOPES 1-4.0 PROCEDURE FOR REVISING RADIATION SAFETY CODE AND QUALITY CONTROL MANUAL To ensure that any procedure or form coinplies with all of the laws, rules, and regulations governing the safe handling of radioactive materials, a procedure, whereby a person directly involved in the manipulation of the materials may submit a procedure or form for approval by the Radiation Safety Committee and the Company llcalth Physicist must be followed. The following lists the steps to be followed to ensure such compliance.

1-4.1 Writing a Procedure or Producing a Form I

4.1.1 The person who writes the procedure will generally be the supervisor or manager of the area.

I 4.1.2 A general outline will be followed in the writing of a procedure as follows:

General Information I

- Conclusions (when necessary)

Detailed Procedures Forms Used (Documentation) 4.1.3 The numbering system will be as follows:

I 1.0 - General Information 1.1 1.1.1 1.1.2 8

1.1.2.1 1.2 8

1.2.1 1.3 1.3.1 5

1.3.2 1.3.2.1 etc...

Forms are numbered by INL (Isotopes Westwood La'aoratories), plus a two letter code designating the license area (e.g., RW-Radiological Waste) and a consecutive two digit serial number.

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TTELEDYNE ISOTOPES 1_13 I-4.2 Submission and Review 4.2.1 Once drafted, the procedure will be reviewed by the Department blanager with respect to general safety practices and fulfillment objectives.

4.2.2 Once reviewed by the Dept. blanager, he will submit it to the Company Radiation Safety Officer (R.S.O.) for review with I

respect to compliance with all the applicable laws, rules and regulations, f

4.2.3 The R.S.O. will make any changes deemed necessary and return the draft to the Dept. )!anager for review. This is done to ensure that any changes made will not appreciably alter the scope or purpose of the procedure.

4.2,4 The manager will then submit the draft to the Executive Sub-f Committee. The Executive Sub-Committee will make a determination on the draft and if acceptable, the chairman af the R.S.C. will approve the draft. He will endorse the procedere to verify acceptance.

4.2.5 If the procedure does not meet with approval by the Executive Sub-Committee, the changes will be made and resubmitted.

4.2.6 Upon final acceptance, the procedure and/or forms will be incorporated into the appropriate section of the Radiation Safety Code and Quality Control >!anual.

4.2.7 Review of Radiation Safety Lude and Quality Control 31anual The entire Radiation Safety Code and Quality Control h!anual will be reviewed and approved by the 1.S.C. at intervals not to ex-cced three years.

Upon complete review and revision all pre-f viously issued copics will be replaced.

Significant interim changes will be issued for insertion into issued copies as they occur.

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TTELEDYtlE ISOTOPES II 1

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RADIATION SAFETY PROCEDURES SECTION II - GENERAL PROCEDURES FOR CONTROLLING RADIOACTIVE MATERIALS AND RADIATION EXPOSURES This section deals with the general procedures for radiation protection t

which apply to the activities carried on under the several licenses cur-I rently in effect.

Specific procedures relating to activities under par-i ticular licenses are included as sub sections of Section III of this Manual.

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T TELEDYNE ISOTOPES II-2 11-1.0 INDOCTRINATION OF PERSONNEL EXPOSED TO IONIZING RADIATION II-1.1 Company Policy on Matters Involving Radiation Exposure i

Work perfomed under the various licensed activities treated in this manual require in some cases some degree of exposure to radiation by operating personnel.

It is necessary, therefore, to classify these indi-viduals in the population subgroup of occupational radiation workers.

For f

individuals classified in this group, radiation exposure must be recorded on the employce's radiation exposure history while in the employ of Teledyne Isotopes. All radiation protection guides which have been established for this group are adhered to by the company.

II-1.2 Indoctrination of Personnel All persons starting to work with any radiation sources at Tcledyne Isotopes are required to read this Radiation Safety Code and this is documented on Form IWL-lip-07.

In addition each employee is required to furnish as complete a history of their training in the principles and practices of radiation protection as possible. This is documented on Form IWL-ilP-06. A basic course is then presented to each employee. The f

outline of this course is given on Form INL-ilP-07 and this form is used as documentation of the presentation. These records are kept in the person's Ilealth Physics folder.

Periodically, Icetures and films on Radiation f

Safety are shown to keep all personnel appraised of the necessity for safe operating procedures.

f Form INL-ilP-06 is given to the supervisor of the employee who then fills in the section requesting authorization for the employce.

This form is then sent to the Radiation Safety Officer who will determine what additional training or monitoring is required for the employee to begin f

work utilizing radioactive materials.

Persons who through their work attitudes and habits show a disregard for safe operating procedures with radioactive material are recommended for transfer out of radiation work or if such alternative work is not available may be terminated from employment.

11-1.3 Rights and Responsibilities of Radiation Workers and the Company Regarding NRC Licensed Activities 1.3.1 Exposure Ilistory All personnel starting to work with radiation at Teledyne Isotopes f

are required to supply their supervisor and the licalth Physics Office as complete a radiation exposure history as availabic.

Pursuant to 10 CFR PART 19.13 (c), a worker may request his/her exposure history from a previous licensed employer.

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I TTELEDYNE ISOTOPES 11 3 Pursuant to 10 CFR PART 19.13 (b), a worker may request, I

and each licensee (company) shall furnish annually, the radiation ex-posure that the worker has received.

When the company (licensee) is required pursuant to I

10 CFR 20.405 or 10 CFR 20.408 to report to the NRC an exposure of an individual to radiation or radioactive material, the company (licensee) must : Iso report to the individual.

1.3.2 Notification of Violations During Inspections Pursuant to 10 CFR 19.14 (b) the NRC inspector may consult privately with workers concerning matters of occupational radiation erotection and other matters as deemed necessary by the in-

- I spector.

During the course of these consultations, any worker may bring privately to the attention of the inspector, either orally or in writing, any past or present condition which he has reason to be-lieve may have contributed to or caused any violation of the act, the regulations of PARTS 19, 20 and 21, or license condition, or any un-necessary exposure of an individual to radiation from licensed' radio-active material under the licensee's control.

1.3.3 Notice of Violations, Adverse Conditions, or Potential Violations or Conditions Prior to an Inspection Upon the notice of an employee of any condition which may cause a violation of 10 CFR PARTS 19, 20 or 21 or a license con-dition, or any unnecessary radiation exposure of an individual, the I

employee is responsible for the reporting of such a condition. The procedures for reporting can be found in Section II-1.3.4.

1.3.4 Procedure for Reporting Violations and/or Potential Violations Upon noticing a suspected item of non-compliance as de-tailed in Section II-1.3.3 the individual is required to report the incident or conditien according to the following procedures.

1.3.4.1 Supervisor Contact The first person to be notified is the supervisor of the area in question. This notification is to be in writing and as detailed as possible.

The supervisor is then to take the necessary steps te follow up the report.

If the problem is of sufficient severity, he will report it to the company Radiation Safety Officer.

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I TTELEDYNE J

ISOTOPES II-4 I

1.3.4.2 Radiation Safety Officer Contact The Radiation Safety Officer will be notified in writing by the individual if they feel the supervisor has not handled the situ-I ation in a prompt and efficient manner.

This report is to be in writ-ing ano as detailed as possible.

The Radiation Safety Officer is then to take the necessary I

steps to follow up the report.

If the problem is of sufficient severity, he will report it to the Radiation Safety Committee.

4

1. 3. 4. 3 Radiation Safety Committee Contact, The Radiation Safety Committee will be notified in writing by the individual if they feel the R.S.O. has not handled the situation in a prompt and efficient manner. This report is to be in writing and as detailed as possible.

The R.S.C. is then to take the necessary steps to follow up the report.

If in the estimation of the Radiation Safety Committee, the situation warrants it, they will notify the Nuclear Regulatory Commission. See 10 CFR 19.5 for whom to contact.

1.3.4.4 Nuclear Regulatory Commission Contact I

The Nuclear Regulatory Commission will be notified in writ-ing by the individual as detailed in 10 CFR 19.5 if he feels the Radiation Safety Committee has not handled the situation in a prompt and efficient I

The report shall include appropriate identifying data such as the manner.

name of the licensee, the name of the individual, and a detailed descrip-tion of the suspected violation.

I 1.3.4.5 Review of Reports on Violations I

In all cases where the report reaches the Radiation Safety Committee, the actions required, the actions taken, and the results ob-tained will be kept with the minutes of the Radiation Safety Committee.

If the report does not warrant the Radiation Safety Committee's review, it I

will be deemed of not sufficient importance and therefore no written accord shall be required.

1.3.5 Requirement for Posting NRC " Notice of Violations" If subsequent to an NRC inspection the licensee is given a

" Notice of Violations", such notice must be posted in a conspicuous place for 5 days or until compliance is achieved whichever period is longer.

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TTELEDYNE ISOTOPES 17_3 II-2.0 MEDICAL EXAMINATIONS AND EMERGENCIES II-2.1 Pre-Employn :nt Medical Examination New company personnel who will be exposed to, or potentially I

exposed to ionizing radiation may be required te submit to a medical examination at the discretion of the Company IIcalth Physicist. The results of this examination become a part of each person's pre-employment record and is kept on file in the Personnel Department.

II-2.2 Follow-up Medical Examination Routine medical examinations are not presently required for those persons who are working with ionizing radiation due to the low permissible limits and excellent detection methods now available for external and internal radiation protection. At present, physical methods of detection of radiation are much more sensitive than signs or symptoms of deleterious Siological effect identifiable in a routine medical examination. Ilowever,

if merson receives an exposure in any one quarter in excess of the radia-tion p e ction guide value but less than two times this value, then he may be required to take a medical examination at the discretion of the Company Radiation Safety Officer or C9mpany llealth Physicist.

If the exposure is in excess of two times the radiation protection guide value, a medical examination is mandatory.

II-2.3 Termination Medical Examination Persons who are leavir.g the employment of the Company may be required to submit to a medical examination as directed by the Company llealth Physicist or Radiation Safety Officer. A radiobioassay examination is required for all personnel having worked with icnizing radiation.

II-2.4 Accidents Involving Radiation Every incf dent involving exposure of Company personnel to radi-ation in excess of ae quarterly radiation protection guide value is classi-fied as an accident and a report of the accident must be made to the Radi-ation Safety Committee by the Radiation Safety Officer. An incident involv-ing exposure m Company personnel to two times the quarterly radiation pro-tection guide must be immediately reported to the Radiation Safety Committee and Company President at the earliest practical date on its findings.

Every incident involving contamination of equipment and requiring disposal or decontamination in excess of $100 or 1 man-day cican-up time must be investigated by the Radiation Safety Officer and a report made to I

the Radiation Safety Conmittee.

Incidents with equipment losses in excess of $1,000 or 5 man-days for decontamination must be investigated by an Investigating Sub-Commit:ce appointed by the Radiation Safety Committee.

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TTELEDYNE ISOTOPES II-6 Reports to Federal, State, County and City authorities as required by law are the responsibility of the Company Radiation Safety Officer.

II-2.5 Emergencies and Decontamination of Equipment The 11ealth Physics Office is equipped with the necessary tools and protective clothing to handle all forsceable incidents on Company property.

Specially trained teams are available to handle most antici-pated incidents involving Company personnel and property.

II-2.6 Fire Every precaution must be taken by all personnel to eliminate the possibility of fire on Company property. This involves personal habits in regard to smoking and housekeeping. All electrical connections and electrical equipment installation are made only with the approval of Company Maintenance Department.

The presence of radioisotopes can complicate the control of a fire once started. Therefore, sources must not be left unattended ex-cept for standard sources used in instrument calibration containing an insignificant amount of activity (less than one microcurie). Overnight, all sources except as noted must be locked in fireproof cabinets. Those sources under active preparation are excluded from this requirement as long as adequate safeguards are instituted and cicared with the IIcalth Physics Office.

In case of a fire near or involving radioactive material, the person (s) must immediately alert the Radiation Safety Officer or Company President who will call the local Fire Departsent and then notify Tele-dyne Isotopes personnel.

In the case of restricted labs, reentry will not be made unless accompanied by a flealth Physicist.

'E Fires at night in Company buildings will be controlled by the local Fire D(gart.nent but Company personne1 will be alerted by the Fire Department ana be present to direct them in fires involving radioactive material.

fl.c list of persons to call is included in Section II-3.4 and is posted in easily accessible locations at the front and rear entrances of the main building and radiological warehouse.

II-2.7 Security All radioactive material misplaced, lost or stolen must be immediately reported to the llealth Physics OffRe.

An immediate investi-gation is made by this office to locate the radioactive material.

If it is not immediately found, steps must be taken to alert other persons in the company to this fact as well as fedcral, state, county and city officials as required by law.

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WTELEDYNE ISOTOPES 11 7 a

II

~,.0 LABORATORY PRACTICES IN TIIE SAFE IIANDLING OF RADIOACTIVE MATERIALS II-3.1 Personnel Directives 3.3.1 Wear laboratory coats or other protective clothing at all times in areas where loose radioactive materials are used.

3.1.2 Wear disposabic gloves at all times while handling loose radioactive materials.

3.1.3 Do not cat, drink, smoke, or apply cosmetics in any area where radioactive materials are stored or use.

3.1.4 Wear a TLD badge at all times if you have been assigned one.

If you are entering an area where the suspected radiation B

IcVels are in excess of.5 mR/hr., contact the llealth Physics Office for a temporary TLD badge.

3.1.5 Confine radioactive materials in covered containers plainly identified and labeled with an identification number and if

<pplicable, a " radioactive material" label bearing the radio-nuclide, activity, date, and radiation level.

3.1.6 Always transport radioactive material in shielded containers if required by character of radiation and strength of source.

3.1.7 Dispose of radioactive wastes only in specifically designated receptacles.

Radioactive contents of waste drums must be recorded on a Radioactive Waste Disposal Card attached to each drum. See Section 11-8.0 for packaging and disposal procedures.

3.1.8 Remove your lab coat when you leave an area where loose radio-I active materials were used.

3.1.9 Never pick up an unshielded radioactive container with your hands. Even short tongs may make a significant difference in exposure.

3.1.10 Remember the inverse square law: DoseRate=hwhered= distance.

II-3.2 Minor Spills I

3.2.1 Notify persons in the area that a spill has occured.

3.2.2 Cover the spill with absorbant material.

3.2.3 Use disposabic gloves and remote handling tongs.

Carefully fold the absorbant paper and pad.

Insert into a plastic bag and dispose of in the radioactive waste container.

Also insert into the plastic bag all other contaminated materials such as disposabic gloves.

3.2.4 Report the incident to the Radiation Safety Officer.

04 81

T TELEDYNE ISOTOPES II-8 3

11-3.3 Major Spills 3.3.1 Notify all persons not involved in the spill to vacate the room.

3.3.2 Cover the spill with absorbant material, but do not attempt to clean it up.

Confine the movement of all personnel potentially contaminated to prevent the spread.

lf 3.3.3 If possibic, the spill should be shicided, but only if it can be done without further contamination or

.without significantly increasing your radiation exposure.

3.3.4 Leave the room and lock the door (s) to prevent entry.

3.3.5 Notify the Radiation Safety Officer immediately, 3.3.6 Contaminated clothing should be removed and stored for f

further evaluation by the Radiation Safety Officer.

If the spill is on the skin, flush thoroughly and then wash with mild soap and lukewarm water.

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I WTELEDYNE ISOTOPES II-9 II-3.4 LIST OF PERSONS TO CALL IN RADIATION EMERGENCY 1.

Person who is in charge of laboratory or area where I

emergency has occurred.

This person's name will be on the radiation hazard sign for the laboratory area.

2.

Radiation Safety Officer S. A. Black Office: (201) 664-7070 X228 Home:

(201) 489-4127 3.

Alternate Radiation Safety Officer J. Pasinosky Office: (201) 664-7070 X257 Ilome:

(201) 391-2378 4.

Alternate Radiation Safety Officer D. Eag1cson Office: (201) 664-7070 X257 i

5.

Maintenance Engineer R. Pavese Office: (201) 664-7070 X205 I

llome:

(?01) 262-4270 6.

President, Chairman Radiation Safety D. Schut:

I Committee Office: (201) 664-7070 X213 llome:

(201) 391-2790 I

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I 04 81

WTELEDYNE ISOTOPES II-10 II-3.5 Contamination Control I

3.5.1 Never consider the outside surface of the inner container of radioactive material to be free of contamination.

I 3.5.2 Always survey the inner container surface for contamination by taking a smear and checking it with the proper instrument.

3.5.3 Always use gloves and radiochemical hood when working with unsealed radioactive materials.

3.5.4 Never open a container unnecessarily without a definite purpose.

3.5.5 In transferring any liquids, the following steps must be taken:

a)

Prepare a shallow tray by lining it with plastic-backed absorbant material.

b) Put t',e radioisotope container, the properly labeled receptacic I

and accessary tools into the tray.

c) Evaluate by calculation or measurement the extremity and whole body dose expected during the operation.

d) Consider that the radioisotope container top and the neck of the container is highly contaminated.

c) Perform the transfer operation in a hood wearing gloves and lab coat.

f)

Remove and dispose of the absorbant liner, survey and dispose of or decontaminate any contaminated items.

g) Decontaminate the original container unless it is to be dispesed of, seal it in a plastic bag and return it to storage.

3.5.6 Notify Health Physics whenever work is to be done with finely divided powders or especially hazardous substances.

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WTELEDYNE ISOTOPES 11-11 I

II-4.0 ORDER, TRANSFER, RECEIPT AND SilIPh!ENT OF RADIOACTIVE h!ATERIAL 11-4.1 Order All purchase requests for radioisotopes must be forwarded to the flealth Physics Office on a standard Teledyne Isotopes Purchase Requisition I

form and Form IliL-ilP-04.

II-4.2 Transfer No radioisotope can be transferred from the user (s) as recorded on Form INL-IIP-04 for the specific radioisotope or radiation source unless another Form IlVL-ilP-04 is submitted and approved indicating the new user (s),

I use, and location of the radioisotope.

11-4.3 Receipt All incoming radioactive material must be checked and recorded by the liealth Physics Officer or designated representative on Form IWL-ilP-05.

Prior to delivery of radioisotopes from Teledyme Isotopes to a user, the shipment must be checked by the 11ealth Physics Office.

11-4.4 Shipment Shipment of all radioactive material is under the supervision of the IIcalth Physics Office.

Each shipment must be checked and approved by the I

llealth Physics Office on Form IliL-ilP-05. Shipment procedures are dealt with in detail in subsections on Radiological Waste Disposal License (NRC Lic.

1. 29-00055-14), State of New Jersey License (Li'c. #10123), TeleTrace License (NRC Lic. #29-00055-02), Source h!aterial License (NRC Lic. #SUB-1235), and Special Nuclear histerial License (NRC Lic. #SNhl107).

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04 81 1

II-12 WTELEDYNE ISOTOPES II-5.0 PERSONNEL MONITORING 11-5.1 External Dosimetry Every employee of, and visitor to, Teledyne Isotopes laboratories and plants must wear personnel monitoring devices such as TLD badges and/or I

pocket dosimeters if their work or tour involves entry to radiologically controlled areas containing sources of penetrating radiation.

Radiologically controlled areas are defined as specified by Part 20 of Title 10 of the Code of Federal Regulations and consists of the following areas:

I Environmental Analysis Provisions of NRC Lic. No. 29-00055-06 Standard Solution Storage Room Laboratory Room 88 Provisions of NRC Lic. No. SNM-107 Metals Processing and Provisions of NRC Lic. No. 29-00055-15, Nuclear Fuels Laboratory SUB-1235, and SNM-107 Source Room Provisions of NRC Lic. Nos. 29-00055-02 and 29-00055-06 Warehouse Provisions of NRC Lic. No. 29-00055-14 I

and New Jersey License No. 10123 A list of those persons monitored by TLD badges is maintained by the !!calth Physics Office. The TLD badges are read out by Toled>me Isotopes Badge Service Department.

Quality Control of TLD dosimetry is set forth in the TLD Personnel Badge Service Quality Control Manual (IWL-0342-416) and TLD Badge Service Quality Assurance Manual (IWL-0792-442).

11-5.2 Internal Dosimetry Some radioisotopes do not emit radiation capable of penetrating I

1 millimeter of tissue but are extremely toxic if taken internally.

In this case, the standard monitoring technique is to analyze urine, feces, breath, or blood of the person exposed to the particular radioisotope.

This analysis is called bioassay and approximate equations permit an estimate of the internal body burden and whole body dose.

Bioassay samples are collected from all Telodyne Isotopes personnel working with alpha emitters, I

carbon-14, hydrogen-3 (tritium) and such other radioisotopes as indicated by the llcalth Physics Office on a quarterly basis.

Whole or partial body counts can also be used to estimate the body burden.

Direct thyroid counting is done on employees using quantities in excess of 0.1 mci of any of the iodine isotopes.

I Bioassays for company perronnel are carried out under the same procedures and controls employed for commercial service under Clinical Laboratory License No. 29-1012 by the U.S. Department of !!calth, Education and Welfare,

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l TTELEDYNE 11-13 ISOTOPES I

Procedures are set forth in the Environmental Analysis Analytical Procedures llandbook (INL-0032-419) with Quality Assurance as set forth in Section IV of IWL-0052-420, Radiocarbon Age Determination Quality Control Procedures.

Bioassays are also performed in the llcalth Physics Department I

under the llealth Physics Analytical Procedures llandbook (Ih'L-0312-452) with Quality Assurance according to Section IV of the Radiation Safety Code and Qu11ity Control Manual (IWL-0312-451).

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I WTELEDYNE ISOTOPES 11-14 II-6.0 SURVEYS All areas where Tcledyne Isotopes personnel work with ionizing radiation are surveyed by the licalth Physics Office on a routine basis.

Depending on the nature of the radiation emitted and the level of radio-I activity, the area is checked for external radiation as well as airborne and surface contamination.

II-6.1 Area Surveys Areas are checked with the properly calibrated instrument for intensity of external radiation.

In addition, smears are taken on all accessibic surfaces to check for transferable radioactivity.

Particulate air and gas samples are collected with the appropriate sampling device to check for airborne contamination. The operation of all safety devices incorporated in laboratories and work areas for safe work with ionizing radiation, such as interlocks, hoods and area radiation alarms are period-ically checked as well. The results of these surveys are sent to the per-I sons in charge of these areas on Forms INL-ilP-01, 02, and 03 or other similar forms. These reports include recommendations to correct any defi-ciencies which may have been detected. A copy of the IIcalth Physics Survey is kept in the flealth Physics Office for future references. Non-compliance I

with these recommendations is cause for removal from work with sources of ionizing radiation in Teled>me Isotopes facilities.

11-6.2 Decontamination Periodically areas will become contaminated with radioactive material. The above mentioned periodic surveys attempt to control this contamination hazard but will not eliminate it.

Therefore, the llealth Physics Office is equipped with decon clothing, face masks, tools, and c1 caning solutions to assist in the decontamination of equipment and buildings in case I

the need arises.

In most cases, the IIcalth Physics Office will merely super-vise the decontamination operation because of the educational value of decontamination experience by personnel responsible for the contamination.

I Request for permission to deviate from this rule must be made to the !!calth Physics Office.

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04 81

W TELEDYNE II-15 ISOTOPES l

l II-7.0 INSTRUMENT CALIBRATICN II-7.1 General On each company instrument a label must be placed indicating date of calibration, instrument serial number, and persons doing the calibration.

Instrument calibration records traceable to NBS standardized sources are maintained by the llealth Physics Office.

(Form IWL-lip-08).

Each scale of the instruments is calibrated using two points. One point is in each half of the scale and they are separated by at least 35% of I

the full scale.

Log scale instruments are calibrated with one point near the mid-point of each scale. All instruments used must read within 10'6 of the calculated or known calibration point.

If the reading cannot be adjusted within 10% but is within i 20%, the instrument will not be used unless a graph is attached.

If the reading is off by more than 20"6, the instrument will be declared out of service and repaired.

A reference check source with a specific geometry shall be utilized after calibration, before use, after use, after maintenance and after a battery change.

If the reading dit'fers by more than the 20% of the reading measured after calibration, the instrument will be recalibrated.

II-7.2 Gamn.a Calibration All gamma sensitive radiation survey instruments are calibrated quarterly utilizing standard sources traceable to NBS. The sources are approximate point sources.

II-7.3 Beta Calibration All instruments used to measure beta radiation during radiation surveys are calibrated quarterly with sources traceable to NBP.

II-7.4 Alpha Calibration All instruments usei to measure alpha radiation during radiation surveys are calibrated quarterly with sources traceabic to NBS.

I

TTELEDYNE ISO 11)P10S II-16 1

11-8.0 RADIOACTIVE WASTE PACKAGING AND DISPOSAL Radioactive waste materials are disposed of by the Radiological Services Department in accordance with all international, federal, state and local regulations. The generators of the waste are trained in the proper method of packaging the waste and then tested on their knowledge to ensure compliance. The materials will be packaged using the "Classifi-cation of Radioactive Waste to be Packaged for Shipmes,t" as a guide, and in conformance with the " Packaging Procedure for Radioactive Waste".

II-8.1 Training and Retraining of Personnel Involved with the Safe Packaging of Radioactive Material Any person engaged in the preparation of waste for disposal must be properly trained in all the DOT, NRC and burial site requirements for proper packaging. The training program is as follows.

8.1.1 Each person is given a copy of the current Radiation Safety Code and Quality Control Manual. He is to study these procedures (II-8.2 and 11-8.3) and then be tested on his knowledge of the material using form IWL-RW-23;, " Packaging of Radioactive Waste Examination".

8.1.2 Subsequent to the examination, each person will be physically supervised in the proper classification and packaging of waste in their area.

Using form IWL-RW-206, the supervisor will document such on-the-job training.

8.1.3 When the supervisor is satisfied the person has demonstrated a complete understanding of the procedures he will notify the Radiation Safety Officer, who will authorize the individual to perform these pro-cedures unsupervised and will document this on form IWL-RW-206.

8.1.4 Retraining of the individual in the most current DOT, NRC and burial site packaging requirements is tr )e perforned at a maximum 6 months interval unless significant cb ges require immediate review.

Retraining and review will be documented using Form IWL-RW-206.

l 04 80

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TABLE S.2 II-17 san 10AcTlyr Mut alat t'artactur. nitor_

CONTAINER LARCL SrcutITY 3rAL INTrt.4AL PACKACINC mR/hr LIMITS 8 CONTACT C045NT5 alAL Otscaltfl0N RI@laLD stquiars atquisto YTrA (DW) 0-200.0 I est soLIO mitalAL ikspecified tosctive Katerlat, thspecified Radioective-LSA no i

l

. e.e.s.

0-0.5 sA/hr limits 8 aclystve-use)

Unspecified contact 0-2.0 if

6. Badtractive MaterLal, Unspecified Radioactive no shipped eactusive-r.se 1:ited quantity, n.o.s.

thspecified 0-2.0 df esctive Device, Unspecified Radiosctive ao araced 0-0.5 tequire velght

.c.s.

d. Radtractive Material, Def 7A-Type A sadioactive yes printed on out-Srsced 0.5 50.0

, ['c, f (Inf) nhlte I

.t.s.

RaJioactive yes of 110 lbs.

I'II'" II Radioactive yes traced 50.0-200.0 Yellow 111 l

Sraced 0-0.5 Require weight I

Radioective Material, DOT 7A-Type A Radioactive yes printed on out-spe1111 fore, n.o.s.

(17H) thite I Braced 0.5-50.0 side of package Radioactive yes when in excess Teltow 11 50.0-200.0 of 110 lbs.

Braced i

Radioactive yes Yellow 111 (SYL) 5MA.LL VOLINE LIQUIDS

• See Instructions 0-200.0 DGT 17H Radioactive-LSA no 1Badtwcthe Material, i

LSA. a.o.s.

(;xclusive-use) i -

b. kad!1 active Katerials,

• See Instructions 0-0.5 Require weight

• DOT 7A Type A Radioactive yes printed on out-c.c.s.

thite !

• See 'nstructions 0.5-50.0 side of package i

Radioactive yes th*n la *=ces8 Yellow II

• See Instructions 50.0-200.0 Radioactive yes Yellow III Scintillation Vials amt fluids eust be pac 6 aged seostatelv from all other smalt volume liquids.

ECIAL NOTE CH SMALL VOLtN. LIQUIDS:

l (DwtVL)

CE VOLANE LiqUlt'S

• See Instructions 0-200.0 l

Rad 11 active Material, DOT 17H Radioactive-LSA no 1

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LSA, n.o.s.

(inclusive-use)

'See instructions 0-0.5 Require weight b, Radirective Material.

DOT 7A Type A Badioactive yes ptinted on out.

(17H) thite I side of package

• See Instructions 0.5-50.0 Ic.c.s.

when in excess Radioactive yes I

y,ggo, g g of 110 lbs.

l

• See Instructions

?n.0-200.0 Radioactive yes I

(DWAC)

LE EALLIO ANIMAL CAACAssis

'See Instructions 0 200.0

s. Rad 1* active;Matertal, 2-DOT IMI Radioactive-L5A no l

LSA, n.o.s.

l (1sclustse-use)

• See Instructions 0-0.5 pequire selght l

. RaJ1sactive Material 00T 7A-Type A RsJ1oactive yes -

printed on out-e.e.s.

(2 ths) hhtte I SlJe of P"b88'

• 5ee Instructions 0.5-50.0 then in encess RaJteactive yes I

of110lbe.

l y,gge,33

• 5ee Instructions 50.0 200.0 i

As.lloactive yes i

Yellow III luL-0172 45l Et s.o.s. o. cans: "not otherwise specifieJ.

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TTELEDYNE i

lNS II-18 RADIOACTIVE WASTE II-8.2 Classification of Radioactive Waste to be Packaged for Shipment 8.2.1 Characteristics of blaterial to be Packaged Isotope Activity (mci)

Physical state (solid, liquid (bulk or vials), animal carcasses biological matter or gaseous)

Concentration (mci / gram)

Transport Group (I through VII)

Form (Normal or Special) 8.2.2 Type of blaterial (Proper Shipping Names)

' Radioactive Device, n.o.s.

Radioact! ce blaterial, Limited Quantity, n.o.s.

I

' Radioactive blaterial, Low Specific Activity or LSA, n.o.s.

Radioactive biaterial, n.o.s.

Radioactive b!aterial, Special Form, n.o.s.

I Radioactive b!aterial, fissile, n.o.s.

Note: All LSA material is shipped " Exclusive Use".

8.2.3 Determination of Shipment Specification What Specification container is required.

What labels are required.

Whether a security seal is needed or not.

mR/hr limits O contact.

Additional requirements.

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I TTELEDYNE II-19 l

11-8.3 Packaging Procedures for Radioactive Waste 8.3.1 General 8.3.1.1 Six (6) categories:

Dry Solid 5faterial Small Volume Liquids (SVL) Scintillation vials ONLY.

Small Volume Liquids (SVL) Other than scintillation vials.

Large Volume Liquids (DWLVL) 50ml or greater Animal carcasses (DWAC) or Biological waste.

Liquid Special Nuclear blaterial (SN51)

P.3.1.2 Items in different categories cannot be mixed.

8.3.1.3 The inckaging procedure that is used should be marked on the drum (e.g. DS51-3/80).

8.3.1.4 Transuranic waste in excess of 10 nanocuries per gram is not acceptable.

g 8.3.1.5 Gaseous tritium waste must meet certain provisions.

g Please see the burial site's license for details or call the Radiological Services Department office.

8. 3.1. 6 Special Nuclear h!aterial (SNbt) requires specific approval and will be accepted only upon special request to the Radiological Services Department office.

8. 3.1. 7 Liquid Special Nuclear F!aterial (SNB1) additionally requires that the material be solidified.

See SNh1 Liquid Packaging Procedures.

8.3.1. 3 For shipments of alpha emitting isotopes and tritium (11-3) customer is expected to supply data on the removable I

contamination on the outside of the container.

Limits are: 2200 dpm/100 cm2 - alpha and 22,000 dpm/100 cm2 beta-gamma.

For natural or depleted uranium and natural thorium use the beta-gamma limits for alpha analysis.

8. 3.1. 9 Special Note:

The chemical composition of the materials disposed must be compatible with the procedures which follow. Any additional ba ards of the material must be evaluated to determine if additional treatment or packaging is required.

8.3.1.10 As a new (empty) drum is received a blank Radioactive Waste Disposal Record card will be attached tc the drum.

As the drum is filled, the individual will fill in the isotope, amount and date.

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I TTELEDYNE ISOTOPES II-20 8.3.2 Dry Solid h!aterial (DS$1-3/80)_

8.3.2.1 Select a 5, 30, or 55-gallon drum.

8.3.2.2 Fill to capacity with only dry-solid materials.

Do not exceed the following weights:

100, 280, or 400 lbs.

respectively for 5, 30, or 55-gallon drums.

I 8.3.2.3 Secure drum cover.

8.3.2.4 Label drum DShi (3/80), to designate that the drum has been packaged according to these directions.

8.3.3 Small Volume Liquid Waste (SVL 3/80), Scintillation Vials or Other SVL's Liquid should not be absorbed directly onto the absorption media (c.i. do not open vials). Any tool or device which contains any amount of liquid (e.g. syringes or test tubes) must be considered small volume liquid waste.

8.3. 3.1 Select only a 30 or 55-gallon drum, 5-gallon pails are not allowed.

8.3. 3. 2 Line the drum with 4-m1 thick poly liner.

(See special notes following this section.)

8.3. 3. 3 Using an approved absorbant, alternate 1-ycrs of absorbant with layers of waste.

(See special notes following this section.)

8.3. 3. 4 Twist and seal liner.

8. 3. 3. 5 Secure drum cover.

8. 3. 3. 6 Label drum SVL-3/80, to designate that the drum has been packaged according to these instructions.

8. 3. 3. 7 Special Notes:

Two 2-m1 liners may be used in place of the single 4-wl liner.

Instead of lining the whole drum, individual 4-m1 (or double 2-ml) bags may be substituted, provided each bag is layered as above.

I 08* 80

TTELEDYNE ISOTOPES II-21 Approved absorbants:

Vermiculite - Grade 4 Agricultural ONLY.

Microccl-E.

la Diatomaccus Earth Pel-E-Cel - Note:

Pel-E-Cel may not be suitabic for some solvents and/or scintillation fluids. Tests should be performed to determine effectiveness.

When layering, tk absorbant must be the first layer on the bottom and the last layer on the top.

Proper volume ratios must be determined by generator to be used for the different absorbants.

The amount of abscvbant must be capabic of absorbing twice the amount of liquid present.

8.3.4 Large Volume Liquid Waste (DWLVL-3/83 All items containing 50-m1 or more of liquid may not be disposed in an SVL drum. The liquid must be packaged as follows, while the container itself must be either 1) dried and placed in a DSM drum or 2) placed in an SVL drum once the bulk of the liquid is removed.

8.3.4.1 Celect only the 55-gallon double-walled container for liquid waste.

8. 3. 4. 2 Remove the 55-gallon drum cover.

8. 3.4. 3 Loosen and remove the bung from the 30-gallon drum.

I

8. 3. 4.4 Pour up to 10 gallons of liquid (pH-6.0 - 9.0) into the 30-gallori drum.

8. 3. 4. 5 Replace bung ar;d tighten.

8. 3.4.6 Twist and seal poly liner.

i

, em

8. 3. 4. 7 Secure cover of 55-gallon drum.

g

8. 3.4. S Label drum DWLVL-3/80 to designate that the drum has been I

packaged according to these instructions.

8. 3. 5 Animal Carcasses or Biological Waste (DWAC-3/80)

Animal carcasses or biological waste must be disposed using a double-walled container.

Be sure when ordering to specify a 55-gallon double-walled container for animal carcasses.

I O ta 80

I TTELEDYNE ISOTOPES II-22 8.3.5.1 Select only a 55-gallon double-walled drum.

8.3.5.2 Remove inner 30-gallon container and absorbant.

8.3.5.3 Line 30-gallon drum with 4-m1 poly liner. See Section 8.2.3.7.

8.3.5.4 Package waste into liner using at 1 cast one part slaked lime for every 10 parts of absorbant. See approved absorbant list in Section 8.2.3.7.

Fill completely.

8.3. 5. 5 Twist and seal liner.

• 3.5.6 Seal 30-gallon drum 8.3. 5. 7 Place 30-gallon drum into 55-gallon drum.

8.3. 5. 8 Place absorbant around and covering 30-gallon drum.

8. 3.5. 9 Secure 55-gallon drum cover.

8. 3.5.10 Label drum Dh'AC-3/80 to designate that drum has been

. packaged according to these instructions.

8. 3. 6 Liquid Srecial Nuclear Material 8.3.6.1 Select a 30 gallon or 55-gallon DOT 17H container.

I 8.3.6.2 Line the drum with a 4-m1 poly liner.

8.3.6.3 Solidify the liquid using any of the following medias:

Dow media Cement Asphalt Delaware custom media Other solidification media and processes which have l

l been received and approved by the NRC and/or the state of Nevada.

8.3.6.4 Place solidified waste into the container.

8. 3. 6. 5 Do not exceed the following weights:

30-gallon container......... 280 lbs.

55-gallon container......... 400 lbs.

Revised:

fu Approved:

3

~

1PTELEDYNE ISOTOPES 8.3.6.6 Secure drum covet, f

i 8.3.6.7 Label drum: SNM-DSM-4/80, to designate the the drum has been packaged according to these instructions.

j l

'I I

J t

i I

I Revised: '//9/

Cd-Approved:

4

T TELEDYNE ISOTOPES II-24 I

II-9. 0 INTERSTATE OPERATIONS From time to time Teledyne Isotopes will engage in activities involving the use of radioisotopes in Agreement States.

A list of such states is included in Table 9.0 for reference so that appropriate regulations can be consulted regarding interstate operations.

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l O te 80

11-25 TABLE II - 9.0 I

LICENSING OFFICIALS IN AGREE 5fENT STATES ALABAMA (205-832-5990)

GEORGIA (404-894-5795)

HR. AUBREY GODWIN, DIRECTOR MR. CilARLES F. TEDFORD, DIRECTOR DIVISION OF RADIOLOGICAL llEALTil RADIOLOGICAL llEALTli UNIT STATE DEPARTMENT OF PUBLIC llEALTil DEPARTMENT OF IIUMAN RESOURCES STATE OFFICE BUILDING STATE OFFICE BUILDING MONTGOMERY, ALABAMA 36104 47 TRINITY AVENUE ARIZONA (602-271-4845)

IDA110 (208-384-3335)

I MR. DONALD C. GILBERT, EXEC. DIR.

ARIZONA ATOMIC ENERGY C03NISSION MR. ROBERT FUNDERBURG, SUPERVISOR 2929 W. INDIAN SC1100L ROAD RADIATION CONTROL SECTION I

P110ENIZ, ARIZONA 85017 IDAi!O DEPARTMENT OF llEALTil 6 WELFARE STATE 110USE ARKACAS (501-661-2307)

BOISE, IDA110 83702 MR. DAVID S. SNELLING, DIRECTOR KANSAS (913-862-9360 EXT. 284)

DIVISION OF RADIOLOGICAL llEALTli DEPART 11ENT OF llEALTli MR. GERALD W. ALLEN, DIRECTOR 4815 WEST MARKliA>l STREET BUREAU OF RADIATION CONTROL LI'ITLE ROCK, ARKANSA'S 72201 DEPARTMENT OF IIEALTil 6 ENVIRONMENT FORBES FIELD, BUILDING 740 CALIFORNIA (916-322-2073)

TOPEKA, KANSAS 66620 MR. JOSEPil 0. WARD, CiiIEF KENTUCKY (502-564-3700)

I RADIOLOGIC llEALTil SECTION STATE DEPARTMENT OF PUBLIC llEALTil MR. CllARLES M. IIARDIN, MANAGER 714 P STREET, BUILDING #8 RADIATION CONTROL BRANCil SACRAMENTO, CALIFORNIA 95814 DEPARTMENT OF llUMAN RESOURCES CAPITOL ANNEX COLORADO (303-388-6111)

FRANKFORT, KENTUCKY 406'J1 I

MR. A.J. IIAZLE, DIRECTOR LOUISIANA (504-925-4518)

RADIATION AND liAZARDOUS WASTE CONTROL DIVISION MR. RONNY WASCOM DEPARTMENT OF llEALTil DEPARTMENT OF NATURAL RESOURCES 4210 EAST 11Til AVENUE OFFICE OF ENVIRONMENTAL AFFAIRS DENVER, COLORADO S0220 NUCLEAR ENERGY DIVISION P.O. B0X 14690 I

FLORIDA (904-487-2437)

BATON ROUGE, LOUISIANA 70898 MR. BERNilARDT C. WARREN MARYLAND (301-383-2744)

PUBLIC llEALTil PilYSICIST STATE OF FLORIDA MR. ROBERT E. CORCORAN, CilIEF DEPT. OF llEALTil 6 REllABILITATIVE DIVISION OF RADIATION CONTROL SERVICES DEPARTMENT OF llEALTil 6 MENTAL llYGIENE RADIOLOGICAL I!EALTil PROGRAM O'CONNOR OFFICE BUILDING 1323 WINEWOOD BOULEVARD 201 WEST PRESTON STREET TALLAllASSEE, FLORIDA 23201 BALTIMORE, MARYLAND 21201 04 81

II-26 MISSISSIPPI (601-354-6657)

NEW YORK (518-457-6600)

MR. EDDIE S. FUEN"E, DIRECTOR MR. T!!OMAS J. CAS13 TAN, DIRECTOR DIVISION OF RAIM0 LOGICAL llEALTil BUREAU OF RADIATION STATE BnARD OF llEALTil N.Y. STATE DEPARTMENT OF FELIX J. UNDERK00D ENVIRONMENT /.L CONSERVATION STATF. 40ARD OF !!EALTil BUILDING 50 WOLF ROAD P.O. 40X 1700 ALBANY, NEW YORK 12233 JACK 30N, MISSISSIPPI 39205 LEONARD SOLON, Pil.D., DIRECTOR (212-566-7750)

NEBRASKA _,

(402-471-2168)

BUREAU OF RADIATION CONTROL NEW YORK CITY DEPARTMENT OF llEALTil I

MR.11. LLLIS SIMMONS, DIRECTOR 325 BROADWAY DIVISION OF RADIOLOGICAL llEALTil NEW YORK, NEW YORK 10007 DEPARTMENT OF llEALTil 201 r".fENNIAL MALL, SOUTil NORTil CAROLINA (919-733-4283)

P.O. LJX 95007 LINCOLN, NEBRASKA 68509 MR. DAYNE 11. BROWN, DIRECTOR RADIATION PROTECTION BRANCil NEVADA (702-885-4750)

DEPARTMENT OF llUMAN RESOURCES P.O. BOX 12200 MR. WILLIAM C. Il0RTON, SUPERMSOR RALEIGil, NORTil CAROLINA 27605 RADIOLOGICAL llEALTil STATE DEPARTMENT OF llUMAN RESOURCES NORTil DAKOTA (701-224-2374) 505 KING STREET CARSON CITY, NEVADA 89701 MR. GENE CllRISTIANSON, DIRECTOR DIVISION OF ENVIRONMENTAL ENGINEERING NEW !!AMPSilIRE (603-271-2281)

NORTil DAKOTA STATE DEPARTMENT OF llEALTil MISSOURI 0FFICE BUILDING MR. J0l!N R. STANTON, DIRECTOR 1200 MISSOURI AVENUE STATE RADIATION CONTROL AGENCY BISMARCK, NORTil DAKOTA 58505 STATE LAB 0P.ATORY BUILDING llAZEN D M S, P.O. BOX 148 OREGON (503-229-S797)

CONCORD, NEW llAMPSilIRE 03301 MARSHALL W. PARROTT, D.SC., MANAGER NEW MEXICO (505-827-5271)

RADIATION CONTROL SECTION

.I STATE llEALTil DIVISION MR. BENITO GARCIA P.O. BOX 231 ENVIRONMENTAL SCIENTIST PORTLAND, OREGON 97207 RADIATION BUREAU P.O. E0X 968 SOUTil CAROLINA (803-758-5548)

SANTA FE, NEW MEXICO 87503 MR. IlEYWOOD G. SilEALY, CIIIEF NEW YORK (518-474-2846)

BUREAU OF RADIOLOGICAL llEALTil S.C. DEPARTMENT OF llEALTil 6 MR. SilERWOOD DAVIES, DIRECTOR ENVIRONMENTAL CONTROL BUREAU OF RADIOLOGICAL llEALTl!

137 J. MARION SIMS BUILDING STATE DEPARTMENT OF llEALTil COLUMBIA, SOUT!! CAROLINA 29201 EMPIRE STATE PLAZA TOWER BUILDING ALBANY, NEW YORK 12237

ei-27 I

TENNESSEE (615-741-7812)

MR. J. A. BILL GRAllAM, DIRECTOR DIVISION OF RADIOLOGICAL llEALTil DEPARTMENT OF PUBLIC llEALTl!

344 CORDELL llULL BUILDING NAS!!VILLE, TENNESSEE 37219 TEXAS (512-458-7341)

MR. J0llN !!AYG00D ISOTOPE PROGRA51, COMPLIANCE 6 INSPECTION RADIATION CONTROL BIL\\NCil DIVISION OF OCCUPATIONAL llEALTil 6 RADIATION CONTROL TEXAS DEPARTMENT OF IIEALTil 1100 WEST 49Til STREET AUSTIN, TEXAS 78756 WASilINGTON (206-753-3459)

MR. ROBERT C. WILL, SUPERVISOR RADIATION CONTROL PROGRAM DEPARTMENT OF SOCIAL AND llEALTil SERVICE MS OB-44J OLYMP", WASilINGTON 98504 I

I 04 81

1PTELEDYNE 11-28 ISOTOPES 11-10.0 FOIBIS All forms referenced in Section I and II follow.

Forms referenced in Sections III-1.0 through 111-11.0 can be found at the end of each individual part.

I I.

I h

I I

I 04 81

11-29 ll SMEAR RESULTS ggs7Q"C0YNE LIQUID SCINTILLATION I

ISOTOPES COUNTING umim ag;aggta wai-y,;,"gg.r g

I I

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I-I I

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IKL-llP-01 Rev. 04 El

u.so DIAGRAM OF SURVEYED AREA SPTELEDYNE I

ISOTOPES LOCATION J.

PRINCIPLE OCCUPANTS gangujen, Ave..Westw I

ISOTOPE USAGE I

I I

I I

I I

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m.im.o2

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11-31 TPTELEDYNE ISOTOPES I

ilEALTil PilYSICS SURVEY To:

Date:

5 f

On a health physics survey was conducted in your laboratory, located at The area was checked for external radiation by an appropriate survey instrument and removabic surface contamination by smearing (swiping) sur-face with Whatman filter paper.

Recommendations:

If further information is desired on this survey, please contact the llealth Physics Office.

"s Rev.

Ole E1

l I

"RTELEDYNE t

ISOTOPES l "-32 g

APPLICATION FOR RADIATION SOURCE (S) l I

Name oate building Position I

Isotope (s)

Telephone Number Quantity (ies)

Chemical Form Present Inventory Physical form Location of Use (Bldg. & Rm.)

Location of Storage Proposed use (activity levels, special hazards, method of disposal of wastes, safety measures). Attach supplementary sheet if necessary.

Applicant's training and experience (relevant to use of radioisotopes):

Radiatio.1 detection instruments, facilities, and equipment that will be used:

l The applicant agrees to abide by the letter and spirit of all applicable i

regulations as recorded in Teledyne Isotopes Radiation Safety Code.

l l

Applicant's signature l

FOR USE OF HEALTli PHYSICS OFFICE ONLY Comments of Ilealth Physics Office Decision:

Date:

Signature Please complete and return with Purchase Request -to:

llealth Physics Office l

l Form IWI.-lil'-04 I

O r, ao

"/PTELEDYNE i

ISOTOPES II-3s SHIPPING / RECEIVING SURVEY RECORD A.

Shipment Data Date Shipped Date Received From To Via Owner of Transport Type of Package Approximate dize B.

DOT Label Information Class I, II, III (circIc)

Radioactive Concents l-Activity of Contents Transport Index (Radiation dose rate 0 3 ft. from package) Maximum 10 mR/hr.

~

I C.

Ilealth Physics Office Survey Data Reading at Contact Reading at 3 ft.

Instrument Smear Survey DOT Label Attached Yes No Surveyed by Date Form Ih'L-ilP-05 I

08, 80

"vPTELEDYNE E

ISOTOPES USER REQUEST FORM 11-34 Social Security No.

Name Birth Date Training:

B Highest level of education completed

's':

b Type of Training hhere Trained Duration of On the Fornal I

Training Job Course D

E A. Principles and practices Yes No Yes No M

of radiation protection.

h

b. Radioactive measurement standardi:stion and I

o U

conttoring techniques Yes No Yes No d

and instruments...

E

c. Hathematics and calcula-f tions basic to the use g

r,nd measurement of Yes No Yes No radioactivity....

8

d. Biological effects of Yes No Yes No radiation......

EXPERIENCE W1nt RADIATION (Actual use of radioisotopes or equivlant experience)

ISOTOI'E HAXI:RDI AMOUNT h11ERE EXPERIENCE WAS DURATION P TYPE OF GAINED EXPERIENCE USE l

l Radiation work for which authorization is sought i

g Isotopes:

Physical and Chemical Form yy Activity Supervisor Requesting Authorization l

E' E c~

Date:

E@

EE i

llealth Physics Cornents f.s=

TLD Badge Required Yes No og "3 y Bioassay Required Yes No f

{E Type Analysis Frequency 5

Authori:stion Date By Radiation Safety Officer 8E Copies of this form are te be distributed as follows:

llealth Physics TLD Badge Service (If checked above)

Orf. ginal form to be returned to Personnel Department fpip }WI..llP-06

WTELEDYNE ISOTOPES II-35 I

BASIC'llEALTil PIIYSICS TRAINING RECORD Name Length of Course Presented by Test I

Course Outline I.

Ionizing Radiation Alpha Beta Gamma II.

Radiation Units and Measurement A.

Curie, millicurie, microcurie, nonocurie, picoeurie B.

Roentgen, Rad, Rem, cR, etc.

C.

Dose and Dose rate III.

Radiation Protection A.

Radiation vs Contamination B.

Time, distance and shiciding C.

Personnel Monitoring

1) TLD Badges 2)

Bioassay 3)

Portable Survey Meters t

l D.

Exposure Limits - References E.

Biological Effects F.

Occupational Exposure G.

Prenatal Exposure IV.

Company 11calth Physics Program A.

Radiation Safety Code and Quality Control Manual B.

Ilealth Physicist, Radiation Safety Officer l

l C.

Ilealth Physics signs, labels, tags, etc.

D.

IIcalth Physics Department Responsibilities I have received the training outline above, read the Radiation Safety Manual and l

Regulatory Guide 8.13 " Instruction Concerning Prenatal Radiation Exposure", and l

understand its implications.

Any questions I may have had were answered to my i

sati s faction.

Date l

Enployee's Signature l

Remarks:

RWL-ilP Rev. 04 81

II-36 CERTIFICATE D.: CALIBRATION

,7 g

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\\

ISO OPES 50 Van Buren Ave..V'estwood. N.J.07675 (201)664 7070 Telex: 134-474 Instrurcnt Serial No.

Type of Source RANGE CAI.IBRATION POINT READING I

l I

l l

l Dose rates were determined with a Victorcen condenser R-Meter with calibration traceabic to the National Bureau of Standards.

I Measurements were determined on electroplated disk sources with certification traceabic to the National Bureau of Standards.

I Date Calibrated by Approved by l

l IWL-llP-0S Rev. 01 81

11-37 l

TTELEDYNE ISOTOPES 60 VAN '4UREN AVENUE WESTWOOD. NEW JERSEY 07675 (201)664 7070 TELEX 134474 TDYlSOT WTWO SUFB!ARY REPORT OF RADIATION EXPOSURE DOSE I

TO:

?

In accordance with the provisions of 10 CFR Part 20

" Standards for Protection Against Radiation" the following information concerning the radiation exposure history of I

, Social Security Number is given.

Our records show that the person identified above was with Tcledyne Isotopes during the period to and received a whole body radiation exposure I

during this period of rem. To our knowledge, there were no everexposures to the (1) whole body; (2) skin of the whole body; or (3) hands and forearms; or (4) feet and ankles during this period.

Significant bio assay data (if any) is summarized by an attached report.

I I certify that the exposure history above is correct and complete to the best of my knowledge and belief.

I Radiation Safety Officer INL-llP-11 Rev. 04 81 I

4 I

,o.. Anc-.

r.ri. cc,r..a.

11-38 (Ms)

Deresi st Budset N* ss-unat.t.

U.S. ATOMIC ENERGY COMMIS510N OCCUPATIONAL EXTERNAL RADIATION EXPOSURE HISTORY See Instructions on the Back soanverscation

i. =A.a (Pacer-ust.ress..o miomas a sam ucusari.0.

8. DaTE & IWRTM {IIOhfM. Daf. TEAR 3

& AGE IN REA TEAN$ (N)

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(str m)

(841ENT 04)

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n. AccumuuirD cccwariout ooz-voral I

I have received an occupational dose of rem during the current calendar quarter.

et catcLtarions-namissaad cosa

u. cartincariani eaarrytiAtt Ea:Pcsuete='570' ListtD in cotues=s s.s. Asia r es ccasiscr A%D ComMITE T3 THE IEsf W ut amow'JDGE ago utEF.

anar socv (A) assurssaz AcctwJLATED D05E = S(E-16)==

atu twPLOSEIS 54%ATURE Da ft (g) 10 fat EXPO %Att 10 Daft (paces Iftu 11) e arm i haut w tacanus (c) LPuuMD FART W e

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Plam4Wa6E acCLAsWTED COM 4 A-8)

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.3 g

g TTELEDYNE ISOTOPCS RADIATION DETECTION INSTRtD'ENTATION g

T-i The following instruments are currently available for field use or laboratory counting as Radiation Protection devices:

~s cc NO.

TYPE RADIAa10N MAWFACTURER'S NAVE DESCRIPTION MODEL NO.

AVA11ABLE DETECTABLE RANGE WINDOW THICKNESS 11SE Eberline Lin-Log Gas PAC-4G 3

alpha 0-500,000 cpm Aluminized M lar Surveying Proportional FM-4G beta 0.85 mg/cm Floor durveying Alpha Counter Eberline Liu-Log Cas PAC-4G-3 1

tritium 0-500,000 cpm Aluminized Hylar Surveying 2

beta 0.85 mg/cm Proportional Alpha Counter alpha Eberline Beta-Gamma E-120 4

alpha 0-50 mR/hr Mica 1.4 to Surveying 2

beta 2 mg/cm Survey Meter gamma Eberline Gamma Radiographi:

E-1201 1

gamma 0-1000 mR/hr none Surveying Survev Meter Eberline Camas Radiographic E-130G 3

gamma 0 1000 mR/hr none Surveying Survey Meter Eberline Beta-Gamma E-530 1

alpha 0-200 mR/hr Mica 1.4 to surveying beta 2.0 mg/cm2 Survey Meter gamma Eberline Beta-Gamma E-140 2

alpha 0-50 mR/hr Mica 1.4 to Surveying 2

beta 2.0 mg/cm Survey Meter gamma Victorcen Ion Chamber V-440 /V-440RF 2

alpha 0-300 mR/hr Mylar 1/4 mil Surveying beta Survey Meter gamma x-ray Victorcen Ion Chamber V-471 1

alpha 0-300 R/hr Mylar 1.1 Surveying 2

beta mg/cm Survey Meter gamma x-ray Intertechnique Liquid SL-30,

1, low energy beta 0-1,000,000 none Laboratory

[

Counting i

Scintillation total counts to Eberline Mini Scaler MS-2 g

alpha, beta, gamma 0 500,000 Mylar Laboratory 2

total counts (0.9 mg/cm )

Counting SAC-4 1

sipha 0-1,000,000 none Laboratory Eberline Alpha Counter total counts Counting

l11-40 g'

m Retraining of Personnel Regarding Processing of Generated Waste DATE:

/ /

INSTRUCTOR:

l ATTENDEES:

SUBJECT OUTLINE:

i i

i

. I i

Form IWL-RW-206 issued:

3/80 b1h DD

Q E

TTELEENNE i

ISOTOPES 11 43 Packaging of Radioactive Waste Examination i

I.

Fill in the blanks (3 pts cach) 1.

List 5 characteristics of the material needed in order to detennine the " proper shipping names":

2.

List 5 " proper shipping names":

3.

The radiation limit at contact with the container cannot exceed mR/hr for a package of LSA material.

4.

Label mR/hr limits 9 contact Radioactive White I to Radioactive Yellow II to Radioactive Yellow III to 5.

The marking (label) needed on a package of LSA material (exclusive-use) should read 6.

The marking (label) on a package of Radioactive devices should read 7.

The weight is required to be printed on a container when it is in excess of lbs., and it is a DOT-7A TYPE A container.

8.

List the 6 categories of radioactive waste:

I 9.

Items in different categories be mixed.

10.

ALL SVL drums must be lined with a

,I 11.

'Ihe amount of absorbant added to any SVL drum must be capabic of absorbing the volume of liquid in the drum.

Form INL-RN-225 1

l T TELE M)IE 11-42 ISOTOPES 12.

Liquid Special Nucicar Material has to be before disposal.

II.

True_oz False (1 pt. cach) 1.

All drums which have a Radioactive I, II or III label require security seals.

2.

400 lbs. is the maximum weight allowed in a 55-gallon container.

3.

,11 gallons of liquids are allowed in a DWLVL container.

4.

Two 2-mil liners is an acceptable substitute for a 4-mil liner.

5.

The pil range for liquids in a DWLVL container is 5.0-10.0.

6.

The animal carcass is to be completely surrounded with rock salt and absorbant.

7.

Cement is an acceptable solidification media.

8.

11-3 gas is acceptable at the Washington burial site under certain conditions.

9.

Packaging regulations are under the direct control of the NRC only.

10.

The burial site's requirements are of paramount consideration when determining how to package a given material.

I u

I FORM IWL-RW-225 04 P0

WTELEDYNE ISOTOPES III-l I

III-3.0 SPECIAL PROCEDURES FOR NRC CENSE NO. SNM-107 LICENSED ACTIVITIES III-3.1 Introduction This section includes items specific for the Nuclear Fuels.. Mass Spectrometry laboratory which performs uranium isotopic and concentration measure-ments of urani9m compounds such as U 0 e, UO, UF, alloys and solutions.

3 2

6 I

h'ith the exception of government owned naval grade uranium which is quantitatively recovered and returned to the owner facility, all other SNM is recovered and subject to radioactive disposal through our Radiological Services Department.

111-3.2 Training and Retraining All employees working under this license are required to attend the Basic Radiation Safety Course as outlined in Section II-1.2 " Indoctrination of Personnel". Only employees working with greater than 50 milligram quantities are I

mandatorily required to have additional training. This additional training consists of more than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of superviscel on-the-job training. All specific procedures and health and safety factors are to be learned to the supervisor's satisfaction.

The items of health and safety are listed in Section III-3.7.

A refresher course will be given at one year intervals. This will be documented on f'rm IWL-ilP-06, User Request Form, as an update.

The employees are require d to read this section of the Radiation Safety Code and Quality Control Manual, and will be tested on their knowledge using form IWL-IIP-30, "SNM-107 Licensed Activities Exam".

III-3.3 Radiation Survey Program The radiation safety program is similar to that found in Sections II-5.0, 11-6.0 and II-7.0.

The following is a further description of the procedures to be performed.

I 3.3.1 Weekly Surveys flealth physics surveys of the Uranium llexafluoride Laboratory, the Uranium-Plutonium Laboratory, the Low Level Uranium Preparation Laboratory, the Buffer Zone, and the Mass Spectrometry area are performed weekly.

Surveys include monitoring for surface contamination on all labora-tory bench tops, chairs, tables, sinks, floors, exposed portions of hoods and glove boxes, s'd general laboratory equipment. An Eberline Instrument PAC-4G or PE-4G3 gas proportional survey instrument is used to measure direc. surface contamination. General radiation levels I-in the rooms are measured with an Eberline Instrument E-120 GM counter with end window probe or comparabic instrument. Smear surveys for

{

04 81

WTELEDYNE I

ISOTOPES III-2 I

removabic surface contamination are taken of areas designated to be representative of contamination on floors, benches, and equipment.

Smear surveys are assayed using an Eberline Instrument Model MS-2 Mini Scaler Single Channel Analyzer with Model FC-1 Proportional Flow Counter or comparable instrument.

All survey results are reviewed by the Radiation Safety Officer or, in his absence, the Alternate R.S.O.

Results are evaluated according to the action limits designated in this document.

Items found to be in excess of 25% of these limits will be reported to the laboratory manager.

Items in excess of 50% will be decontaminated as soon as practicable.

The Uranium Hexafluoride Laboratory and the Uranium-Plutonium Laboratory are facilities with access restricted to authori:cd personnel only.

I Entrance to these areas may only be obtained through use of a magnetic card key.

Laboratory coats and laboratory equipment are of the disposable type whenever possible, and must be removed prior to leaving the area.

h'orkers must monitor hands and feet before leaving the area with Radiation Monitors equipped with alpha and beta-gamma probes.

Gloves in glove boxes are inspected routinely during surveys. Gloves I

are changed immediately if deterioration or rupture is noticed.

If deterioration is not noticed, gloves will be changed at least annually.

Common laboratory equipment is monitored routinely during the weekly survey. Any equipment which may contain radioactive contamination is reported to the Itboratory workers and department managers for appropriate remedial action.

A general survey of the entire Teledyne Isotopes facility, including lunchroom areas, entrances, and exits, halls, offices and lavatories, is performed monthly.

3.3.2 The following limits for radioactive material contamination will not i

be exceeded on lab surfaces or equipment outside of hoods or glove boxes:

3.3.2.1 Alpha Contamination 2

Fixed -

1,000 dpm/100 cm average 2 maximum 3,000 dpm/100 cm 2 maximum Removable -

200 dpm/100 cm I

I 04 81 l

l WTELEDYNE ISOTOPES III-3 I

3.3.2.2 Beta Contamination 2

Fixed -

5,000 dpm/100 cm average 2 maximum 15,000 dpm/100 cm 2 maximum Removable -

1,000 dpm/100 cm 3.3.3 Air Monitoring 3.3.3.1 A manifold air sampling system is set up in the buffer zone I

to sample both ambient and effluent air for each hood and glove box contained in the Uranium Hexafluoride and the Uranium-Plutonium Laboratories. Millipore filter air samples are used. Sampling locations are situated at breathing zone heights at or near glove boxes and hood faces to provide sampling points representative of the exposure that workers may receive. Sampling is performed continuous.ly for a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week. An Eberline Instrument Alpha-1 air monitor with built-in single channcI analyzer and audibic alarm is also available and may supplement the stationary air monitoring system for projects where the possibility of airborne con-tamination could contribute to significant internal exposure.

Air sampics are assayed using an Eberline Instrument Model MS-2 Mini Scaler Single Channel Analyzer with Model FC-1 I

Proportional Flow Counter or other comparabic instrument.

3 Air samples are assayed for the particular isotopes used g

during the preceding time interval.

In the case where a mixture of nuclides was used, air samples are evaluated using the isotope with the most stringent maximum permissible con-I centration allowed.

If significant airborne concentrations are detected, additional bioassavs will be required. Calculation of internal deposition and expos..re will be performed by the Ilealth Physics Section using the most current assumptions and I

models available.

In such a situation, the action points available in Regulatory Guide 8.11 " Applications of Bioassay for Uranium", will be referred to for the appropriate recourse.

[

3.3.3.2 Effluent air monitoring of all stacks emanating from the Uranium licxafluoride and Uranium-Plutonium Laboratories is contained in the manifold air sampling system located in the buffer zone. All stacks are monitored continously unless activity was known not to exist during the preceding time I

interval.

Isokinetic sampling is deemed unnecessary because of the efficiency of the filtration system employed on air released to the environment.

(Effluent air is filtered using I

a roughing prefilter and absolute filter rated 99.9716 efficient against D.O.P. smoke to 0.3 micron diameter.)

I 04 81

WTELEDYNE ISOTOPES yir_4 3.3.3.3 Sampic points for effluent monitoring are located two-thirds of the distance between the filter unit and the first bend in the ductwork. Sampling points employ fittings which curve in the direction of air mover it to a point which is representative of air flow. Air flow cht acteristics are measured on a I

monthly basis at hood faces and glove box openings using an Alnor Velometer.

In the case of an emergency release or filter rupture, calculations for effluent release will be made using air sampling data and estimating the magnitude of particulate release that may have bypassed the sampling tube.

3.3.3.4 hhen the pressure drop across the llEPA filter (s) exceeds three I

and one-half inches of water, the filter (s) will be scheduled for change. This change of filters will take place prior to the change in pressure exceeding four inches of water.

3.3.4 Effluent llold-up and Release Normally, all radioactive waste materials are discarded in radioactive waste receptacles contained in each individual lab and ultimately dis-posed through Teledyne Isotopcs Radiological Services Department.

Ilowever, there is *. possibility that some radioactive material may be drained from sinks in the processes of washing laboratory glassware or other routine laboratory procedures.

For this reason, the Chem. Prep.

area and Uranium-Plutonium Laboratory are equipped with special sinks whose effluent is stored in a holding tank located in the Utility Room.

The radioactive contents of this tank are monitored to insure that all water effluents are below the maximum permissible concentration for each specified nuclide before any re.'. case to the environment. The tank may not be released until form IWL-hP-C9 has been properly executed by the Radiation Safety Officer or his alternate.

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1 04 81

W TELEDYNE ISOTOPES 111 3 III-3.4 Shipments Incoming and outgoing shipments of samples are controlled by the Manager, Mass Spectrometry Services. The drums are surveyed for compliance with all applicable laws, rules and regulations prior to opening.

III-3.5 Records Management The data received from all surveys, inventories, personnel dosimetry, and documentation pertaining to the receipt, use and disposal of radioactive materials are evaluated and retained by the llcalth Physics Office or the Office of the Manager, Mass Spectrometry Services of Teledyne Isotopes.

It is the primary responsibility of the Health Physics Office to obtain information on the exposure of each individual, location, or procedure employing radioactive material. The llealth Physics Office is also responsibic for observing trends or changes in the working habits of a single individual or department, and thus to measure the effectiveness of the radiation safety program.

Qualified members of the IIcalth Physics Office responsible for these functions include the Alternate Radiation Safety Officer and the Radiation Safety Officer.

III-3.6 Material Control Provisions "Ihe procurement, receipt, use and disposal of all special nuclear materials is maintained and controlled through strict administrative procedures by the llcalth Physics Section. All records and documents pertaining to these functions reside I

in appropriate files and are the responsibility of the Manager of the Mass Spectrometry Services Department.

The total inventory system for special nuclear material contained on the premises is primarily based on book value. Only material contained in the Uranium llexafluoride Laboratory is subject to physical inventory. The balance of material 3

is contained in samples which are prepared for analysis in the Low Level Uranium 3

Preparation Laboratory.

Because of the nature of the analytical process, the special nuclear material is consumed and disposed of following the analysis. There is only one exception in the case of U-235 when some material may be returned to the customer at his request.

The responsibility for maintenance of the special nuclear material in-ventory system resides with the Manager of the Mass Spectrometry Services Department.

III-3.7 General Safety Rules 3.7.1 General safety rules for work with special nuclear material are listed i

below.

General safety instructions for glove box use may be found in i

Section 3.7.2.

3.7.1.1 The doors to the laboratory and between individual labs should remain closed to prevent improper air flow.

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WTELEDYNE ISOTOPES III-6 3.7.1.2 The blowers in all hoods and glove boxes should be runninF continuously.

3.7.1.3 h'ork involving plutonium in excess of 10 micrograms must be performed in a glove box.

3.7.1.4 floods should not be opened to a point beyond the 100 Ifm mark which is posted.

3.7.1.5 All work should be performed at least seven inches from the front of the hood.

3.7.1.6 Large objects placed into the hood will affect airflow. Contact the llealth Physics Office for a re-evaluation.

3.7.1.7 Never place yot:- head in the hood.

3.7.1.8 Do not rapidly rush op to or away from the hood as it may affect the airflow significantly.

3.7.1.9 Do not use explosive substances in any hood.

3.7.1.10 Upon noticing any def.ation or deficiency in items 3.7.1.1 through 3.7.1.9, ple-se contact the Manager of Mass Spectrometry Services or the liealth Physics Office.

3.7.2 General Safety Instructions for Glove Box Use 3.7.2.1 h'ork involving plutonium in excess of 10 micrograms must be performed in the glove box unless written approval to the contrary is obtained from the ficalth Physics Section.

3.7.2.2 All material to be used in the glove box must be bagged in and agged out.

3.7.2.3 Any time glove box containment is to be broken (i.e., a glove removed or a door opened without bagging). a IIcalth Physics representative must be present.

3.7.2.4 Explosive or flammabic material must not be taken into glove box.

3.7.2.5 An open flame cannot be used in the glove box without prior

!!calth Physics approval.

3.7.2.6 Material which could produce fumes which could d- 'ge the glove box filter or containment seals must not be taken into the glove box.

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WTELEDYNE ISOTOPES III_7 3.7.2.7 Disposable gloves must be worn when inserting hands into the glove box gloves and when performing bagging operations.

Gloved hands must be checked with the alpha contamination monitor (or beta gamma monitor where appropriate) whenever removed from the glove box gloves.

1 3.7.2.8 Upon loss of a glove, or containment in any manner, or upon detecting contamination, notify the llea'.th Physics Section immedia ely.

I I

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04 81

!l TPTELEDYNE ISOTOPES 333,3 2 I 111-3.8 FORMS SPECIFIC FOR SNM-107 LICENSED ACTIVITIES F.

P t

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{

llI t

!I r

i A

i i I

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WTELEDYNE ISOTOPES III-9 ALPilA LAB !*0LDING TANK ANAI.YSIS AND RELEASE AUTil0RIZATION FOP 31 Date:

Date of Last Release:

Isotopes Used During Interval:

I Analyses Required:

Recommended By:

II.P. Authorization:

DATA:

SEE ATTACHED SilEETS Isotope MPC (uC/ml)

Positive Results

% MPC I

I Gross Alpha 3 X 10-8 Gross Beta 3 X 10-8 Review of Data:

Authorization to Release:

RSO Assist. RSO Dept.

Ilead IIKI.-IIP 0904 81

14'TELEDYNE ISOTOPES 111_10 "SNM-107 LICENSED ACTIVITIES EXAM" Name Date I

Section 1 Fill in the blanks.

Each blank worth 4 points.

1.

The Uranium IIcxafluoride Laboratory and the Uranium-Plutonium Laboratory are areas.

2.

Weekly surveys are performed to measure radiation IcVels and contamination.

F 3.

All survey results are reviewed by 4.

Items found in excess of

% will be decontaminated as soon as practicabic.

5.

Laboratory coats must be prior to 1 caving a restricted area.

6.

Workers must monitor and prior to 1 caving a restricted area.

7.

A general survey of the entire Teledyne Isotopes facility is performed 8.

The limits for radioactive contamination are:

Alpha:

2 Fixed:

dpm/100 cm average 2

dpm/100 cm maximum 2 maximum Removabic:

dpm/100 cm Beta:

2 Fixed:

dpm/100 cm average 2 maximum dpm/100 cm 2

Removable:

dpm/100 cm maximum IWL-h6-01 04 81

1 WTELEDYNE ISOTOPES III-ll "SNM-107 LICENSED ACTIVITIES EXAM" (page 2) 9.

Air sample locations are located at heights at or near glove boxes and hood faces to provide sampling representative of the exposure that the worker may receive.

10.

Between the hood and the exit there are two filters which are:

and 11.

The filters are scheduled to be changed when the pressure drop exceeds inches of water.

12.

The holding tank contents cannot be released prior to and the evaluation form is filled out by the 13.

Shipments must be prior to opening and receiving of contents.

14.

The doors to the laboratory must be kept closed to prevent improper 15.

Work involving plutonium in excess of micrograms must be performed in a glove box.

16.

Iloods should not be opened past the Ifm mark.

17.

Do not use substances in any hood.

I IWL-MS-01 04 81

i WTELEDYNE ISOTOPES III-12 I

i ANSWERS TO "SNM-107 LICENSED ACTIVITIES EXAM" i

1.

restricted 2.

direct removable 3.

Radiation Safety Officer 4.

50%

5.

removed 6.

hands and feet 7.

monthly 8.

1,000 3,000 200 5,000 15,000 l

1,000 l

9.

breathing zone 10.

IIEPA filters and roughing 11.

3!s 12.

sampling, radiation safety officer 13.

surveyed 14.

air flow 15.

10 16.

100 17.

explosive

! I i

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I m.ms.02 e4 e,

~

~

TTELEDYNE III-6.1 ISOTOPES I

SECTION III SPECIAL PROCEDURES APPLICABLE TO ACTIVITIES UNDER SPECIFIC LICENSES Tcledync Isotopes carries out activities involving radioactive material under ten different licenses from state, national, and foreign government authorities.

In adoition to continuing licenses, other activities are carried out under temporary permits or reciprocal recognition of exist-ing licenses with a variety of special requirements.

Because the Radiation Safety Code and Quality Control Manual may be required to support the applica-tion for or operation under a given license, it is designed in such a way that only the general provisions of the code and the provisions particularly applicabic to a given license are included in copies presented to a given agency.

This copy includes the sections relevant to the licensed activi-ties checked below.

111-1.0 USAEC BYPRODUCT MATERIAL LICENSE (No. 29-00055-06)

~--

C SPECIFIC LICENSE OF BROAD SCOPE III-2.0 USNRC MATERIALS LICENSE (No. 29-00055-14)

~

(RADIOACTIVE WASTE DISPOSAL)

III-3.0 USNRC SPECIAL NUCLEAR MATERIALS LICENSE (No. SNM-107)

III-4.0 USSRC MATERIALS LICENSE (No. 29-00055-151

~

(METAL DECONTAMINATION)

III-5.0 USNRC DEPLETED URANIUM SOURCE MATERIAL LICENSE (No. SUB-1235)

III-6.0 USNRC BYPRODUCT MATERIAL LICENSE (No. 29-00055-02)

~

(TELETRACE)

III-7.0 COLOMBIA, SOUT11 AMERICA LICENSE FOR IMPORTATION OR USE OF RADIONUCLIDES (No 320) (LICENCIA PARA IMPORTACION O MANEJO DE RADIONUCLIDOS No.320)

(TELETRACE)

III-8.0 STATE OF NEW JERSEY, DEPT. ENVIRONMENTAL PROTECTION, l

RADIOACTIVE MATERIAL LICENSE (No. 10123)

III-9.0 US DEPT. II.E.W. CLINICAL LABORATORY LICENSE (No. 29-1012)

~

(RADIO-BI0 ASSAY)

III-10.0 RADIATION SURVEYS III-11.0 ATOMIC ENERGY CONTROL BOARD OF CANADA RADIOISOTOPE LICENSE i

i l

it1988 l

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