Text

QA Program for Transportation of Radioactive Matls
	ML20153H020
Person / Time
Site:	07100583
Issue date:	02/11/1986
From:	; MINNESOTA VALLEY ENGINEERING
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ML20153H001	List: ML20153G997; ML20153H020;
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' APPENDIX H 1.0 Q. A. PROGRAM FOR TRANSPORTATION OF RADIOACTIVE MATERIALS 1.1.

INTRODUCTION i

1.1.1 This section identifies Minnesota Valley Engineering s Quality Assurance Program for the transportation of radioactive materials in accordance with 10 CFR Part 71.

MVE is licensed under 10 CFR Part 34 for the use of IR-192 for purposes of industrial radiography.

l 1.1.2 This section is applicable to any transportation package containing an IR-192 source in excess of 20 ci. delivered to a carrier.

1.1.3 MVE activities with respect to transportation packages includes; j

use, handling, inspection and maintenance.

Design, fabrication, I

i assembly and testing of transportation, packages is by others.

L However, responsibility for compliance with Part 71 requirements is with MVE for those transportation packages which it utilizes

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j-and delivers to a carrier.

1.2 Q.A. PROGRAM j

1.2.1 This Q.A. Program identifies the administrative controls to r

be followed to assure all requirements for transportation l

packages are being met.

Written procedures needed for implemen-tation of this program are identified in the Radiation Safety j

Manual. Control of this, including revision, will be as e.tated i

in Section 1.0 of the Radiat bn Safety Manual.

l 1.2.2 Attached to this section is a matrix identifying the require-i ments of the Q.A. Program with the sorresponding implementing procedures, and procurement of documentation and control of all NRC licensed equipment used by MVE. All certification and handling procedures will be on file with the Radiation Safety Office.

i 1.2.3 The company Safety Of ficer has over all administrative re-sponsibility for this program. The Radiation Safety Officer shall have specific implementing responsibility, including 1

training and certification of personnel, document control, and i

ensuring manufacturers design and Q. A. Program control.

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I 1.3 ORGANIZATION i

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1.3.1 The organizational structure of MVE's Radiation Safety Program

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te depicted in Figure 1.

The specific individuals are as follows.

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1.3.2 The President has overall responsibility and authority for the j

direction of MVE.

I 1.3.3 The Company Safety Officer reports to the President and has j

overall responsibility and authority for the adminstration of I

i the MVZ Safety Program.

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1.3.4 The Radiation Safety Officer has the authority and responsibility for the implementation of the Radiation Safety Program at MVE.

1.4 DOCUMENT CONTROL 1.4.1 Measures will be established to r3sure that documents relating to procurement, handling, stora,e, shipping, and inspection of transportation packages art controlled. Changes to documents will be performed in accordan;e with written procedures.

1.4.2 The Radiation Safety Officer shall assure that Q.A. functions are conducted in accordance with the latest approved requirements.

1.5 HANDLING, SHIPPING AND STORAGE 1.5.1 Measures shall be established to assure that handling, shipping, and storage requirements are completed and implemented in accor-dance with procedures prior to release of shipments.

1.5.2 Radiographers will implement the necessary activities.

1.6 INSPECTION 1.6.1 Measures shall be established to assure that appropriate inspections are completed and accepted prior to delivery of transportation packages to a carrier.

The appropriate records shall be completed to indicate the inspection acceptance.

1.6.2 Nonconforming items shall be positively identified by use of status tags to prevent inadvertant use.

1.6.3 Radiographers will perform all necessary inspections' directed by the Radiation Safety Officer.

1.7 RECORDS 1.7.1 A system shall be developed to assure appropriate records are maintained, identified, and nasily retrievable.

1.7.2 The Radiation Safety Of ficer shall be responsible for implementing the records system in accordance with written procedures. These

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procedures shall identify the types of records under this program including manufacturer's certificate of Compliance and reference drawing.

1.8 AUDITS 1.8.1 Measures shall be established to assure compliance to this program through audits utilizing written checklists.

1.8.2 Audits shall be conducted at least once a year and deficiencies evaluated and corrected. Auditors shall have no responsibility in the area audited.

1.8.3 Management shall be informed of audit results.

O Minnesota Valley Engineering Radiation Safety Manual O

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Control Ilumber

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Ph: 612 75M434 Tetx: 294571

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MINNESOTA VALLEY ENGINEERING, Inc.

[fMU 407 SEVENTH St. N.W., NEW PRAGUE, MINNESOTA 56071 September 14, 1984 POLICY STATEMENT ine procedures contained Perein are designed to provide the Radiographers and l

Radiographer's Assistants with the necessary instructions to assure that there is an adequate Radiation Safety Program for Radiographic Operations.

The Radiation Safety Officer has my support and the authority for implementing the requirements contained in this manual.

Failure to comply with the procedures and regulations set forth in this manual will be just cause to apply appropriate disciplinary action.

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ej Je y Flicek Company Safety Officer 1

TABLE OF CCNTENTS

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Section Number Rev.

Date

Title, Statement of Policy 1.0 0

Radiatica Catety Administration 2.0 0

Radiation Scfety Training 3.0 0

Reports and Records 4.0 0

Personnel Monitoring 5.0 0

Survey Meters 6.0 0

Posting, Security and Storage Requirements 7.0 0

Procedure for Exchange of Scaled Sources 8.0 0

Procedure for Operating Exposure Devices 9.0 0

Receipt Shipment, and Transportation of Radioactive Materials 10.0 0

Emergency Procedure 11.0 0

Inspection and Maintenance of Radiographic Equipment 12.0 0

Leak Testing 13.0 0

Radiation Safety Audits APPENDIXES A Responsible Individuals B NRC Licenses C Notice to Employees Form D 10CFR19 E 10CFR20 F 10CFR34 0 10CFR71 H QA Program for Transportation of Radioactive Materials 2

1.0 SCOPE 1.1 This procedure describes the administration of the Minnesota Valley Engineering Radiation Safety Program to comply with established federal, state, and local Radiation Safety Requirements.

2.0 ORGANIZATION 2.1 The organizational structure of MVE'S Radiation Safety Frogram (Figurs 1) cutlines the structure of the Radiation Safety Program with referenco to management, radiographers and radiographers' assictants.

2,2 The radiation safety officer is appointed by and reports to the company safety officer of MVE.

2.3 The radiation safety consultant is an outside agency who reports La l

the company safety officer and acts in an advisory capacity for the evaluation of the adequacy and effectiveness of the MVE l

Radjation Safety Program.

l 3.0 CUALIFICATIOMS l

i 31 The radiation cafety officer will be appointed by virtue of a l

resume submitted to the company safety officer of MVE. He should be thoroughly familiar with all phases of radiographic operations and applicable federal, state, and local regulations.

3.2 The radiatien safety consultant is an established radiation safety consultant who is experienced in the development and l

implementation of radiation safety operations.

4.0 RESPONSIBILITIES 4.1 The radiation safety officer has the authority and responsibility for the implementation of the M7E Radiation 3afety Program as i

required by federal, state, and local regulations. Caecific responsibilities include, but are not necessarily limited to :

4.1.1 Liason with the USNP,C en license matters.

4.1.2 Periodic review and updating the contents of this manual.

4.1 3 Maintaining control of procurement and disposal of licensed material.

4.1.4 Developing and maintaining up-to-date operating and emergency procedures.

4.1.5 Establishing and maintaining a personnel conitoring program.

4.1.6 Procuring and maintaining radiation survey instruments.

4.1.7 Establiching and conducting the training program for radiographers and radiographers' assistants.

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4.1.8 Examining and determinicg co.tpetence of radiographic personnel.

4.1.9 Establishing and maintaining storogo facilities.

4.1.10 Maintaining exposure devices, radiography facilities, and associated equipment.

4.1.11 Establishing and maintaining the leak-testing pregram.

4.1.12 Establishing and maintaining the internal inspectien system.

4.1.13 Performing source replacement and source tagging operations.

4.1.14 Conducting quarterly inventories and maintaining utilization lc68.

4.1.15 Establishing and conducting a survey ir.strument calt5raiton pregram.

4.1.16 Establichir.g ard Inintaining MVE'S record keeping system.

4.1.17 !!cviewing and ensuring maintenance of those reccrds kept by others.

k.1.18 Assuming control and. instituting corrective action in emergency

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situations.

4.1.19 Investigating the cause of incidents and detereining necessary preventative action.

4.2 The radiation safety officGr may delegato the performance of the foregoing duties to radiographers er radiogrsphors' assistants.

However, the responsitility for *.50 adequato perforcanco cannot be delegated.

43 The radicarapher is an individual uno porforms or supervisca radiographic operations. !!o reports to the Radiation Safety Officer and is responsible for ensuring that radiographie practioss tro in et,rpliance with this Radiatien Saroty Program.

4.4 The radiographer's assistant is an individual who assists the radiographer in carrying equipreent, setting up and providing sury.9111ance over radiation areas, placement of radiographic film, and processing of the film. The radiographor's assistant may operate the exposure devices and conduct survoys only while under the direct supervision of the radiographor.

Direct supervision meanst a.

Radiographer's personal prosonco.

b.

Radiographor's ability to give immediato assistanco f.f required.

Radiographer's observing the performanco of the radiographer's c.

assistant for compliance to the rules of this nanual.

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520 RADIATIO!1 SAFETY PROGRAM S.1 Content The MVC 3adistion Safety Program ia decerited in the WE Radiation Safety Manual and is cenpriced of administrative and operating procedures as well as the NRC rules and regulations applicable to radiation safety.

The radiation safety officer is responcible for the adminis-tration, approval, and distribution of the Padiation Safety Manual and the revisions thereto.

Distribution chtll be to the !!RC, the radiation safety officer, the radiation safety consultant, and designsted radiographers/

radiographers' assistants.

5.2 Fevision The acetion revision nu ber of the table of contents page indicate 1 the current revision of the Radiation Safety !!anual.

Each tecton chall airo be identified in the table of contents nth its individual revision number and revision dato. When a change is made to any secticn of the Radiation Safety Manual, the whole section shall be reissued in its entirety.

53 Review and Approval The radiatitn safety officer shall be responsible for review and the icplementatien of changes to the MVS R1diaticn Safety Progran.

The radiatien asfety officer c.ty use the servicen of the radiation safety consultant as needed.

6.0 FANI.CFMENT PEVIEW 6.1 The radiatien safety consultant and radiatica asfety officer shi.1 be responsible for roviawing the Radiation Safety Progre anr.ually.

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Nuclear Regulatory Commissin i

ISOTOPE 1.ICENSIhG DIVISION GENTLEMEN The radiation safety program detailed in this Radiation Safety Manual will be used at Minnesota Valley Engineering. The mailing address is i

407 - 7th St. N.W., New Prague, Minnesota 56071.

i The responsible administrative individual for this program ist l

Jerry Flicek Minnesota Valley Engineering l

407 7th St. N.W.

New Prague, Minnesota 56071 Business Phone (612) 758-4484 Home Phone (612)-758-2746 The radiation safety consultant for this program ist t

Robert Brostemn Sioux Hills Hutchinson, Minnesota 55350 Business Phener (612) 587-6785 Home Phone:

(612) 587-3636 The radiation safety officer for this program ist t

William J. McKnight R. 1 Box 202 l

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New Prague,612 -364-8915 Mn 56071 1

Home Phono l

Business Phone:

(612) 758-4484 I

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ORGANIZATION CHART FOR RADIATION SAFETY PROGRAtt President I

company Safety Of ficer

_ Radiation Safety Consultan l

l Radiation Safety Officer l

Radiographer Assistant Radiographor figure 1 0

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2c0 TRAINING AND QUALIFICATION OF PERSONNEL 2.1 SCOPE This procedure outlines the Radiation Safety Training Program used by A

Minnesota Valley Engineering. The radiation safety of' facer shall be responsible for the administration of the Radiation Safet Training Program.

2.2 RADIOGRAPHER TRAINING AND OUALIFICATIONS 2.2.1 Classroom Training a.

The classroom training shall be conducted in accordance with 10 CFR Part 34, Para. 34.31 (a).

A minimum of forty hours classroom training is required. The topics to be covered and the apprsximato hours shall be as shown in this procedure.

b.

The classroom training shall be conducted in one of the following methodst Conducted by MVE Corporation Radiation Saroty Officer, Radiation Saroty Consultant or their designated alternate utilizing the MVE Radiation'Cafety Manual and the applicsblo NRC regulations.

Conducted by an organization that has a Radiation Safety Training Program approved by the Nuclear Regulatory Commission, such as:

1) Gamma Industries 2255 Ted Dunham Avenue Baton Rouge, Louisiana 70821 2)

Tech / Ops Product Division 40 North Avenuo Burlington, Massachusotta 01803 3)

Hutchinson Area Vocational-Technical Institute 200 Century Avenue Hutchinson, MN 55350 NRC License No. 22-15554-01 When the above training programs are used, the radiation safoty officer chall require docu=ontation of satisfactory completion.

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2.2.2 Field Training a.

For new NDT personnel and requalification of personnel on-the-job training under the supervision of a qualified radiographer shall be required.

b.

A minimum of 3 months training in the topics as shown in this procedure shall be required.

2.2.3 Examination. Upon completion of the foregoing training, ar.d prior to assignment as a radiographer, each radiographer trainee shall sucessfully complete per 2.2.4 the following examinations:

a.

Specific: The specitic examination shall consist of mirimum twenty-five questions which shall be given upon successful completion of the classroom training.

This exam will cover the MVE Radiation Safety and Operating Procedures and the applicable NRC Regulations.

b.

General: The general examination shall consist of a minimum of forty questions which shall be given upon successful completion of the ficid training. This test covers radiography and radiation safety.

c.

Practical: A practical examination shall be given upon successful completion of the field training.

6 The examination shall demonstrate the individual's competency to conduct safe radiographic operation.

2.2.4 Grading of Examinations a.

To successfully complete cach examination at least 807, of the questions must be answered correctly.

b.

Examinations will be reviewed by the Radiation Safety Officer with the trainee so that any information that is not understood can be again covered so the indiv-idual does understand. Those who do not successfully complete any or all of the three examinations will require additional training as determined by the Radiation Safety Officer and re-examination.

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2.3 RADIOGRAPHER'S ASSISTANT 2.3.1 Classroom Training a.

The classroom training shall be conducted in accordance with 10CFR 34, Paragraph 34.31 (b).

A minimum of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of classroom training and a working knowledge of radiography is required. The required topics to be covered and the approximate hours shall be as shown in this procedure.

b.

MVE classroom training shall be conducted by the Radiation l

Safety Officer, Radiation Safety Consultant or their de-signated alternate utilizing the MVE Rad"ation Safety Manual and the applicable NRC Regulations.

2.3.2 Examination Specific The radiographer's assistant examination shall consist of a minimum of twenty-five questions approved by the Radiation Safety Officer and shall be given upon completion of'the classroom training. This exam will require a thorough knowledge of the MVE Radiation Safety Manual arid the applicable NRC Regulations.

1 Practical A field examination of knowledge will be to demonstrate an j

understanding of the classroom training.

2.3.3 Evaluation of Examination a.

To successfully coraplete each examination at least 80% of the questions must be answered correctly.

b.

Examinations will be reviewed by the Radiation Officer with the trainee so that any information that is not under-stood can be again covered so the individual does understand.

Those who do not successfully complete the examination will receive additional training as determined by the Radiation Safety Officer and re-examination.

2.4 PERIODIC TRAINING 2.4.1 Radiographers and Radiographer's Assistants shall be given periodic training in MVE Radiation Policy and Procedures, and NRC Bulletins regarding radiation safety. The Radiation Safety Officer will be responsible to assure that the personnel re-ceive the periodic training at least once a year.

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2.5 PREVIOUS TRAINING 4*

2.5.1 Uhen acceptable documentation is available to assure that previous training complies with 10 CFR 34, the Radiation Safety Officer may waive the initial training as described in Paragraph 2.2.1.

2.5.2 When the initial training is waived, the radiographer shall be given instruction in the MVE Radiation Safety Manual by the Radiation Safety Officer or Radiation Safety Consultant and successfully complete the examination as described in Paragraph 2.2.3.

2.6 RECORDS 2.6.1 A Radiation Safety Training Record (Form 2) shall be completed for each radiographer and radiographer's assistant and shall be retained in accordance with Section 3 of this manual.

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RADIOGRAPHERS TRAINING Ecurs of Ingeqgregn tru ti Tonic I.

Fundamentals of Radiation Safety 12 A. Characteristics of gamma radiation (1)

B. Units of radiation dose (mrem) and quantity of radioactivity (curie)

(2)

C. Hazards of exposure to radiation (1)

D. Levels of radiation from licensed material (2)

E. Methods of controlling radiation dose (6)

1. Working time

2. Working distances

3. Shielding II.

Radiation Detection Instrument To Be Used 7

A. Use of radiation survey instruments (4)

1. Operation

2. Calibration

3. Limitations

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'xl B. Survey techniques (2)

C. Use of personnel monitoring equipment (1)

III.

Radiographic Equipment To Be Used 7

9 A. Radiographic exposure devices (4)

B. Storage containers (2)

C. Remote handling equipment (1)

IV.

Explanation of MVE Radiation Safety Manual 4

V.

Practical Demonstration of Radiographic Inspection 4

a. Set-up of radiographic exposure devices

2. Surveys

3. Calculations of radiation area

4. Radiographic techniques

5. Disassembly and securing of exposure device after inspection VI.

Inspection of Maintenance Performed by the Radiographer 4

VII.

Case Histories of Radiography Accidents 2

TOTAL 40 Hours'

RADIOGRApHERS TRAINING Hours of tru ti Ingeq]regn Tonic I.

Fundamentals of Radiation Safety 12 A. Characteristics of gamma radiation (1)

B. Units of radiation dose (mrem) and quantity of radioactivity (curie)

(2)

C. Hazards of exposure to radiation (1)

D. Levels of radiation from licensed material (2)

E. Methods of controlling radiation dose (6)

1. Working time

2. Ylorking distances

3. Shielding II.

Radiation Detection Instrument To Be Used 7

A. Use of radiation survey instruments (4)

1. Operation

2. Calibration

3. Ilmitations Al B. Survey techniques (2)

C. Use of personnel monitoring equipment (1)

III.

Radiographic Equipment To Be Used 7

A. Radiographic exposure devices (4)

B. Storage containers (2)

C. Remote handling equipment (1)

IV.

Explanation of MVE Radiation Safety Manual 4

V.

Practical Demonstration of Radiographic Inspection 4

a. Set-up of radiographic exposure devices

2. Surveys

3. Calculations of radiation area

4. Radiographic techniquec

5. Dicassembly and securing of exposure device after inspection VI.

Inspection of Maintenance Performed by the Radiographer 4

VII.

Case Histories of Radiography Accidents 2

TOTAL 40 Hours' g

FIELD TRAINING PROGR.UI 1.

Instruction on radiation monitoring and detection equipment.

A.

Survey instruments B.

Pocket dosimeters C.

Film badges 2.

Instruction on the set-up aad operation of the radiographic exposure device and related equipment.

3.

Instruction on the establishment of restricted areas and performing survey.

4.

Instruction on the performance of preventive maintenance on radiographic equipment.

5.

Instruction on completing the Radiographer's Field Report and other required records.

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RADIOGRAPHERS ' ASSISTAT TRAINING Hours of Instruction Topic Required I.

M,y g.

' Corporation Administration Policy 1/2 II.

M.V.E.

Corporation Administrative and Operating Procedures for Radiographic Operations (Radiation Safety Manual)

A.

Radiation Safety Adr'nistration 1/4 B.

Radiation Safety Tra._ning Program 1/2 C.

Reports and Records 1/2 D.

Personnel Monitoring 1/2 E.

Survey Meters - What they are and how they are used 1/2 F.

Posting, Security and Storage ioquirements 1/2 G.

Operating Procedure for Exposure Devices 1/2 Minimum Each Device y

H.

Demonstration of the Operation of the Exposure Devices 1/2 Minimum Each Device I.

Procedure for Exchange of SesLa Sources 1/i J.

Transportation of E.posare Devices 1/4 K.

Emergenc-/ Procedures 1

L.

Inspection and Maintenance of Radiographic Exposure Devices 1/2 M.

Procedure for Leak Testing 1/4 N.

Radiation Safety Audits 1/4 0.

Nuclear Regulatory Cc= mission Rules and 'legulations 1/2

10CFR19 - Notices, instructions and Reports to I?orkers:

1/2 Instruction 10CFR20 - Standards for Protection Against Radiation 10CFR34 - Licenses for Radiography and Radiation Safety Requirements for Radiographic Operations 1/2 P.

Notice to Employees 1/4 Q.

Radiation Protection Time, Distance and Shielding 1 1/4 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months Minimum f*

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3.0 REPORTS AND RECORDS 3.1 SCOPE j

This procedure lists the reports and records used in the Minnesota Valley Engineering Radiation Safety Program.

3.2 REPORTS 3.2.1 The MVE Radiation Safety Officer shall-be responsible for the following reports or notification as required by the Nuclear Regulatory Co= mission in accordance with 10CFR20.

3.2.2 Records of surveys, radiation monitoring and disposal Reference 10CFR 20.401 3.2.3^. Reports of thef t or loss of licensed material Reference 10CFR 20.402 3.2.4 Notification of incidents Reference 10CFR 20.403 3.2.5 Reports of overexposur e Reference 10CFR 20.405 3.2.6 Personnel exposure and monitoring reports Reference 10CFR 20.407 3.2.7 Reports of personnel exposure on tennination of employment or work Reference 10FFR 20.408 3.2.8 Notification and reports to individuals Reference 10CFR 20.409 and 10CFR 19.13 3.3 RECORDS 3.3.1 A su= mary of the records required for the administration of the MVE Radiation Safety Program is listed below:

a.

Radiation Safety Training Record (Form 2) b.

Radiographers Field Report (Form 3)

Quarterly Inspection & Maintenance Report (Form 5) c, d.

Radioisotope Quarterly Inventory Report (Form 6) e.

Leak Test Report

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f.

Survey Instruemnt Calibration g.

Receipt / Transfer of Radioisotope, includes inspection of shipping container (Fom 7) h.

Film Badge Reports 1.

Occupational Exposure History (Fom 8)

j. Quarterly Radiographer's Audit Report (Fom 9) k.

Radiation Safety Program Audit Report (Fom 10) 3.4 RETENTION 3.4.1 The retention period for the records shall be as stated below:

- Radiation Safety Training Record and Examinations 3 years

- Rr agrapher's Field Report Pemanent

- Qu terly Inspection & Maintenance Report 2 years

- Rau. isotope Quarterly Inventory Report 2 years

- Leak fest Reports 6 months after next required test

^

- Survey Instrument Calibration 2 years

- Film Badge Reports Pemanent

- Receipt / Transfer of Radioisotopes Pemenent

- Occupational External Radiation Exposure History Pemanent

- Quarterly Radiographers Audit Report 2 years

- Radiation Safety Program Audit Report 2 years 18

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-The above named has successfully compicted the required training and s

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7ffU RADIOGRAPHERS FIELD REPORT FORM 3

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Date 8th BUILDING EXPOSURE BOOTH Tech / Ops 660 SN IR 192 Curies

'On SN Tech / Ops 660 SN IR-192 Curies On.

SN Victoreen 492 SN Due 692 SN Due Radiographic equipment inspected per checklist OK Repair Survey of storage area before removing exposure device mr/hr Survey of storage area after returning exposure device mr/hr Exposure device surveyed after removal from storage mr/hr at surface Exposure device surveyed after each exposure mr/hr at surface Exposure device surveyed prior to securing mr/hr at surface 10th BU!LDING EXPOSURE BOOTH Tech / Ops 660 SN IR-192 Curles On SN Tech / Ops 660 SN IR-192 Curies On SN Victoreen 492 SN Due 692 SN Due Radiographic equipment inspected per checklist OK Repair Survey of storage area before removing exposure device mr/hr Survey of storage area after retuming exposure device mr/hr Exposure device surveyed after removal from storage mr/hr at surface Exposure device surveyed after each exposure mr/hr at surface Exposure device surveyed prior to securing mr/hr at surface EXPOSURES OUTSIDE EXPOSURE BOOTHS l

Restricted area @

mr/hr @

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Area under visual control yes no Area roped off and signs posted yes no Tech / Ops 660 SN IR-192 Curies On SN Victoreen 492 SN Due 692 SN Due RADIOGRAPHIC CHECKLIST A.

Projector inspected for damage to fittings, lock, fasteners & labels.

B.

Control cable and guide tube inspected for cuts, breaks, broken or loose fittings. Crank inspected forlooseness.

C.

Operation of control checked to assure freedom of source movement.

D.

Collimator, if used, checked for secure attachment.

RADIOGRAPHER Dosimeter reading start mr end mr Total mr ASSISTANT Dosimeter reading start mr end mr Total mr

Booth #

ActualTime ExposursTime _

A B

C D

Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime ExposureTime A

B C

D Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime ExposureTime A

B C

D Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime Exposure Time A

B C

D Booth #

Actual Time ___ __ Exposure Time A

B C

D Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime Exposure Time __

A B

C D

Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime Exposure Time A

B C

D Booth #

ActualTime Exposure Time A

B C

D C

C 8th 10th Building Building g

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8th BUILDING EXPOSURE BOOTH Philips 300 KV DirectionalTube.

Panoramic Tube Victoreen 492SN Due 692SN Due 10th BUILDING EXPOSURE BOOTH Philips 300 KV DirectionalTube Panoramic Tube Victoreen492SN Due 692SN Due NUMBER oF LENGTH OF booth EXPOSURES EXPOSURES KV MA A

B C

D A, B, C, and D are to be filled in if the survey at the perimeterof the g

booth shows a W

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'I Tyo of Byproduct Material Location Strencth Date Rtc.

1)

\\

2) 3)

4) 5)_

6)-

\\

7) 8)

\\

9) 10) 11) i 12) 1 13) 14) 15)

Inventory Performed By:

Date_.

O 4.

22

RSCEIPT/ TRANSFER OF RADIOISOTOPES F0FJ! 7

-Reedo *.

Dats Time Location S~urce Removed from

_ Serial Number Activity r

hIR-92

~

curies QOther curies Shipping Container Model Number Serial Number CSourceChanger bErojector Survey,,

Maxi =um Actual Meter S/N Radiation level 3 feet from external surface 10 mr/hr or/hr Radiation' level at external surface 200 nr/hr mr/hr If radiation levels exceed the maximums abo e, contact Rad. Safety Officer Time Date

, diographer Source Exchance Serial Number Removed From Installed To bProjector

[ Projector CScurceChanger

[ Source Changer

[

~

Model J Model #

k S/N s/n Radiographer Date Outbound Shipment Source Serial Number Activity curies Radiation level at external surface ar/hr at 3 feet er/hr Shipment to via Preshiement Checklist 1.

S' hipping' container labels affixed.

2.

Proper shipping papers complete.

3.

Transport index entered.

Inspect the shipping container for any defects or damage prior to being released for shipment.

Radiographer Date s

23

QUARTERLY AUDIT REPORT OF RADIOGRAPHERS FORM 9 Date Minnesota Valley Engineerino NCR Region ill Radiographer Being Audited Assistant Radiographer Audit Conducted By

_t Exposure Device-Model S/N Source S/N bl COMMENTS g

g g

W EW s

1. Is the Radiation Area properly controlled and posted?

2. Is the High Radiation Area properly posted?

/

3.. Is the Radiographers Field Report-Equipment filled out indicating "p

N equipment check?

V

4. Are film badges being properly worn?

s

5. Are dosimeters re-zerced before use and properly worn?

6. Radiation Survey Heter in proper working order,: including calibration date and properly used ?

7. Source Storage container properly surveyed'7

8. Are surveys of the exposure device completed properly af ter each exposure?

~.

24

FORM 9 COMMENTS d

U W 5W

??

9. Is the controlled area monitored during exposures?

10. Is the equipment connected properly and handled carefully?

11. Is a copy of the Safety Manual at the work location?

12. Was shielding utilized to best extent, i.e., walls, collimater, etc.?

13. Was Radiographers Field Report filled our correctly?

Rrmarks

[

\\b/

.Y t/

\\_

A N

,'(>

\\

s

\\/

1 %

v dadiographer Auditor O

25

RADIATION SAFETY PROGRAM AUDIT REPORT FORM 10 4

Dintribution:

Company Safety Officer Radiation Safety Officer

"[,"

Quality Assurance Manager

\\.

Minnesota Valley Engineering NRC REGION:

- III b

RADIATION SAFETY OFFICER:

NAME:

SURVEY C010iENTS C01DIENTS y =y 4 Q 3 9 2

1) Are Dosi=eters in working order?

Is record of Dosimeter calibrations being kept?

2) Are radiation survey meters in work-

^

s ing order including calibration date and records or calibration?

3) Are fils' badges properly stored?

j 4)

Is a copy of Radiation Safety Manual available?

5) Is a copy of the NRC License posted?

6) Are the copies of the applicable NRC rules and regulations available?

i

~

f 7;)

Are copics of URC Form III properly posted?

8) Are copies of source transfers main-tained?

9) Are projectors posted to indicate contents?

10)

Is radioisotope storage. c,on ta ine r Properly posted to indicate radio-active material?

11) Are records of source utilization maintained?

e 26 e "'

.s m i v.u r u tta s u SURVEY C01DIENTS CO)0!ENTS k

w w<

\\

E

$E

12) Are rcccipt of sources properly documented?

53) Arc leak test reports m intained and conducted every six (6) months?

14) Arc records of personnci exposure maintained?

13) Arc quarterly maintenance check-lists completed and maintained?

16) Have personnci utilising equip-

)

ment, rcccived proper training?

/

17) Arc quarterly isotope inventories maintained?

18) Arc test results on file for each source design in use, gO meeting requirements of 49

\\'

'l CFR 173?

19) Are test results on file for

\\'

performance test on shipping containers used for radioactive material quantitics over 20 curies?

20) Has an NRC Certificate of Compliance been issued for those devices used to ship quantities over 20 curies and is MVE registered for use with the NRC?

21) Arc package inspections and shipment documentation main-tained and completc?

b 27

RADIATION SAFETY PROGR/JI AUDIT REPORT FOR1! lO Rec: arks or Rece:::nendation:

\\

)

sW fNN e

\\N

\\1

/

(/,'

/

b Licensed Safety Officer or Representative 28

luut 11 Sil!PPER'S CERT!r1CATICN FCRf'.sI0 ACTIVE MATERIALS

g

/

D0rlESTIC Sit!P!! S ONLY This shipment is within the limitations prescribed for: CANCO ONLY AIRCRAFT Two coelete glened en,ntes of this (c_rtification shall be handed to the carrier FACKACI: 1DICNrtrtCATION AND O WTfNTS TYPE cr SutrntNT AS INutCATED Radiographic placards required Source Empty Container Empty Container L.S.A.

Proper Shipping Name Radionuclide Transport Haterial Material Label Transport Package Croun Form Activity Catarory Inden Type S

Radioactive material Iridium 0

special form. n.o.s.

192 111 Special U

NRC ID INA9182 S/N Form R

Cargo only aircraf t USNRC CoC C

No.

E Radioactive device n.o.s.

1 NRC ID #UN2911 Depicted III toli EXDfPT DtPTY EXDtPT EXDfPT Hazard Classt Urainium t<*a E

Radioactive M

material Y

1.

Except fecm specification packaging, marking, and lab ( k d exempt f rom the provisions of 49CTR173.393 per 49CTR173.391c.

2.

Exempt from the requirements of 49CFR part 175 pc RI?5.10a6.

E Radioactive material

' M N

L. S. A, n.c. s.

Pj f

FRC ID l' N2912 Depicted fSolid J

Urainium III Metal N/A Cargo only aircraft USNRC CoC g

No.

5 A

' NAME AND ADDRESS OF Sil!PPER:

This is to certify that the above-named materials are Minnesota Valley Engineering properly classified described. packaged. marked and labcica. and are in proper condition for transportation EDRESS SHIPPED FROM:

according to the applicable regulations of the Desart-ment of Transportation.

I hereby certify that the contents of this consignment are fully and accurately described above by proper shippinr,r..mc and are classified, packed, marked and labeled, and ACORESS SHIPPED To:

in proper condition for carriage by air according to applicable national goves... ental regula-tions.

Radiation' safety 0111ccr Date 29

4.0 PERSONNEL MONITORING 4.1 SCOPE This procedure describes the requirements of personnel monitoring.

4.2 PERSONNRL MONTTORING DEVICES 4 2.1 The personnel monitoring devices used by Minnesota Valley Engineering are described below:

a. Pocket Dosimeters:

The dosimeters used are the direct reading type with a range from zero to at least 200 milliroentengens.

The dosimeter may be read at any time by the wearer to check the ace-umulated radiation dose received.

To charge the dosimeter,1.e., return the meter reading to zero, it is inserted in the charging receptacle of the dosimeter charger and depressed.

The voltage is adjusted by means of the control knob until the dosimeter is " Zeroed".

The dosimeter should then be checked by holding it up to the light and view-ing the scale.

Dosimeters are to be zerced at the beginning of each work day.

At the end of each day the exposure reading from the dosimeter will be recorded on the Radiographers Field Report.

The radiation safety officer shall ensure that dosimeters are checked at least once a year for correct response to radiation.

They shall be acceptable if capable of reading to 130% of the actual dose they are exposed to.

Records of these checks shall be maintained in the radiation safety files.

9

b. Film Badges:

MVE uses the G-1 film badge which is supplied by R.S. Landauer, Jr. & Company.

The G-1 film badge records whole body dosage of X and/

or gamma radiation within the range of 10 MR to 700 R.

Each radiographer and radiographer's assistant is assigned a permanent film badge imprinted with the radiographer's name, participant number, and the beginning date of the exposure period.

Film badges vill be changed monthly.

Exposed film badges are returned to the R.S Land-auer, Jr. & Company for processing and perparation of a monthly Radiation Dosimetery Report.

The Radiation Dosimetry specifics the following information:

Radiographer's Name

Participant Number

Social Security Number

Birthdate

Exposure to Badge

Cumalitive Totals

Permissible Accumulated Dose

Unused Part of Permissible Assumulated Dose

c.- R dietion Monitcra: In tddition to dosimeters and fiin badges, radiation monitors may be used which give an audible warning Wen in a gamma radiation field. The output is in " chirp

which-i begins at approximately 0.1 MR/HR, and increases in rate in.

i a manner that to roughly proportional to tho increasing field.

In high fields, individual chirps cease and a constant tone is emitted. The radiographers are requested to wear this additional protective device during' operations and as required in Section 7.

paragraph 7.2.2.

4.3 RESPONSIBILITIES 4.3.1 The radiographer and radiographer's assistant shall be respon' sible for wearing the personnel monitoring devices described in paragraph 4.2.1a and 4.2.1b prior to performing radio-graphy.

4 3.2 Radiography shall not be performed if any of the personnel monitoring devices are defective or the radiographer or radiographer's assistant does not have all the personnel monitoring devices described in paragraphs 4.2.1a and 4.2.1b r

p 4.3.3 The radiation safety officer sMll be responsible for assigning i

a film badge and pocket dosimeter fcr each radiographer and

]

radiographer's assistant.

4 3.4 The radiation safety officer shall be responsible to assure that t

each radiographer and radiographer's assistant prepare the Occupational External Radiation Exposure History Form (Form 8).

4.3.5 The radiographer shall be responsible for completing the i

Radiographer's Field Report (Form 3).

t 4 3.6 The radiation safety officer is responsible to forward, the first quarter of each calendar year, to the Nuclear

)

Regulatory Commission Director of Management and Program Analysis:

l a.

A report of the total number of individuals for whom personnel monitoring was provided the preceding year.

a b.

A statistical summary report of the personnel monitoring 1.

information for individuals in (a) above, indicating whole body exposure for previous year by exposure range.

This report is provided by the R.S. Landauer, Jr. &

Company to MVE.

4.3.7 The radiation safety officer is responsible to provide to terminated employees for whom personnel monitoring wao provided, l

a report of their total whole body exposure while under e=ployment to MVE.

A copy of this report will also be sent to the Nuclear Regulatory Commission, Director To Management and Program Analysis. Report will be furnished within 30 days of determination of exposure, or 90 days of termination, which ever is earlier.

t 31

v.g.f.,

n ;

s.-

5.0 SURVEY METERS M,k%$9Am-12i 5.1 scope

,ME@E%+

p g,y m This procedure describes the operation, staintenance Y">';Ii.Sd; ? -.

and calibration of survey meters.

s 3.2 TYPRS OF m mVRY METERS ifj$?/Md'3Ji.W.

5 2.1 The survey meters used by Minnesota Valley by%MA:

Engineering shall be capable of detect 2.ng radi-5f dm

'*N N'....

ation in a range of at least 2 mr/hr through 1,000 mr/hr, and are as follows:

;:a a.-->

a.

Victoreen Model 692 dMTF' Comparablo survey meters of other manufacturers

.j"a.

7E

may be used as approved by the radiation cafety

.l.

j'h:h.

officor.

l-.hE" 5.3 OPReaTInn di ikbe ~

. ;on WT:.Td..

5.3.1 Victoreen Model 692 z %:32.V -

'..~

% %"i-a.

Turn the selector switch to the "Batt J

position".

Meter indicator should be in hjIhh'6...

the area. designated " Bat-CHK" on the scale

.m..';

or over.

(c.., c,.V45n.

(/

=;

~-

b.

Zero meter.

c.

Turn the selector to the "MR/HR" position -

X1000, X 100, X 10 or X 1 as needed.

.7 l,,,. J.!

-N-1.

5.4 M A THTnir HCP AND C AUMATTON.

s...;

5.4.1 MVC has a maintenance and calibration program

j,.y.sg that is in compliance with 10CFR Part 34, a.p.

pc.ragraph 34.24 Calibration of survey meters

$,c7.;;v

~ -

will be performed with:

..r.e.

u m nufacturer /.

Mmufacturer &

mdal (b. of Mxk:1 No. of letope fa ~o Arsmbiien Expowre Device C siun 07 Tech / ops 773 To park voy meter calibration use the form shown

'he end of this section and perform th

. allowing:

a.

Instrument inspected for damage b.

Circuit board visually inspected c.

Mcchanical hardware inspected (and tightened as necessary) d.

Exterior surfaceo cleaned e.

Duttorica checked f.

Meter zarced prior to calibration

_ _ _. ~.

i i

'*. sf ':. p :;

l g.

After proper warm-up of the survey instrument, the. distance from the source at which the radiation intensit.y would be i

_800 mr/hr is-determined (9.6" for 150 millicuries Cesium 137).

1

. h,, 5z.g,Using the tape measure attached to the Model 773, the survey

)

i 4 ' meter is placed at the prescribed distance. With the survey i

,, n..,, meter switched on, the following steps are taken

.., y, j

c re uhg'idd,1. The source is exposed by raising the source rod. The survey l

e meter reading is noted and recorded and the source is 1

returned to the stored position. This reading is checked against the actual intensity.

If within I207., the next

{

i

... y step is taken. If not, adjust the instrument and recommence

. y:

1

.46

+.2-calibration.

3

' W ' N '3' 2.

Place the 0.25 attenuator in the beam; repaeat step 1; the actual intensity is 200 mr/hr.

i 3.

Remove the 0.25 attenuator from the t, cam and place a 0.10 attenuator in the beam. Repeat step 1; thea ceual i

IY r% ' =

intensity is 80 mr/hr.

1 4,

Place the 0.25 attenuator in the beam. Repeat step 1; i

the actual intensity is 20 mr/hr.

l

)

5.

Remove the 0.25 attenuator from the beam and place the 2

other 0.10 attenuator in the beam. Repeat step 1; the actual intensity is 8 mr/hr.

i 6.

Place the 0.25 attenuator in the beam. ' Repeat step 1; the L

j actual intensity is 2 mr/hr.

I h.

If unable to adjust the meter to within 1 207,the meter

{

shall be sent for repair to:

I c

t Victoreen l

i Authorized Repair Service i

4 I.' E

.a I-Wayne Corp.

t i

1 5213 West Lorance Ave.

Chicago, IL 60630 i

i. If the exposure rate is within 1 207. of the calculated rate, j.

a calibration chart containing the calibration factor, the i

j date of last calibration, and due date of next calibration will be affixed to the survey meter.

i t

i 5.5.

RESPONSIBILITIES OF THE RADIOGRAPHER i

5.5.1 The radiographer shall be responsible for having a calibrated survey meter at the work area. A spare survey meter will be available for the purpose of rotation for calibration or repair.

1 5

CERTIFICATE OF SURVEY INSTRUMENT CALIBRATION

~

Type Model Serial Number CALCULATED ACTUAL CHECKLIST SCALE READING READING Instrument inspected for XI 2 MR/HR damage Circuit board visually XI 8 MR/HR inspected Mechanical hardware inspected X10 20 MR/HR (and tightened as necessary)

Exterior surfaces cleaned X10 80 MR/HR Batteries checked X100 200 MR/HR Meter ze roed prior to X100

'800 MR/HR calibration Calibration Source Source Serial Number REMARKS:

I certify that this instrument was calibrated on the date shown and is accurate to within 20% on each scale.

Calibrated By Date Re calib ra tion Date t

6.0 POSTING. SECURTTY AND STORAGE 6.1 SCOPE This procedure describes the requirements for posting and security during radiographic operations, storage requirements for exposure devices and posting of source storage facility.

6.2 pOSTTNG OF NOTICES TO WORKERS 6.2.1 The Radiation Safety Officer shall conspicuously post the following documents in the offices where radiographic operations are centered:

a.

Form NRC Notice to Dsployees (in this section).

b.

Notice - (in this section).

6.2.2 Noticos of violation involving radiological work-ing conditions, proposed civil penalties, or Nuclear Regulatory Commission orders applicable to Minnesota Valley Engineering activities shall be posted immediately upon receipt by the Radiation Safety Of ficer.

6.2.3 Such notices shall be posted for a minimum of five (5) working days or until corrective actions

("i have been completed, as directed by the Radiation

's Safety Officer.

6.3 POSTING OF RESTRICTED AREAS FOD RADIOGRAPHIC OPERATIONS 6.3.1 Prior to performing radiography at temporary sites within the plant, a restricted area shall be established and conspicuously posted with the applicable signs as described in Paragraphs (a) through (c) below, a.

Restricted Area:

An area where personnel if continuously present could receive a dose in excess of 2 mr in any one hour or 100 mr in any seven consecutive days, b.

High Radiation Area:

Any area accessible to personnel where they may receive a dose in excess of 100 mr in one hour upon entry into that area.

" Caution, High Radiation Area" signs, as shown in this section shall be conspicuously posted.

c.

Radiation Area:

Any area accessible to personnel where they may receive a dose in excess of 5 mr in one hour or in any five (5) consecutive days, a dose in excess of 100 mr upon entry into the area.

" Caution, Radiation g

Area" signs, as shown in this section shall

be conspicuously posted at the boundary of the restricted area.

h'.

6.3.1.1 During the first radiographic exposure, a

\\

survey shall be made at the perimeter of the restricted area to assure thatthe radiation level meets the requirements of a restricted area.

The results of this survey shall be recorded on " Radiographer's Field Report" (Form 3).

6.3.2.

Radiography performed at the exposure booths in the 8th and 10th buildings.

The entrance to each exposure booth shall be equiped with both visible and audible warning cignals to warn of the presence of radiation.

The visible signal shall be actuated by radiation whenever the source is exposed.

The audible signal shall be actuated when an attempt is made to enter the installation while the source is exposed.

6.3.2.1

" Caution Radiation Area" signs will be posted on the outside of all walls.

A " Caution High Radiation" sign will be posted at the entrance of each exposure booth.

6.3.2.2 During the first radiographic exposure, a (l) survey shall be made at the perimeter of the exposure booth to assure that the radiation levels meets the requirements of a restricted area.

The results of this survey shall be recorded on " Radiographer's Field Report"

( Form 3).

6.3.2.3 The alarm system must be inspected for proper operation at intervals not to exceed 3 montLJ.

A check list as shown in this section shall be used for the inspection.

6.4 SECURTTY 6 4.1 For radiographic operations at temporary sites the radiographer will maintain direct surveillance over the restricted area to prevent unauthorized access.

6.4.2 All accesses to entrances to roof areas are posted and controlled in the following manner:

a.

post all access areas to the roof with

" Caution Radiation Area" signs.

b.

The following notice will also be posted at all access areas to the roof:

Approval from the Radiation Safety Officer or Radiographer on duty must

be obtained prior to going up on the roof.

Failure to follow this procedure will result in disiplinary action and/

or termination.

6 4.3 For radiographic operations in the exposure booths, the radiographer will maintain direct surveillance over the entrance to the exposure booth except when making surveys.

6.5 sOtmCE STORAGE AREA 6.5.1 The source storage container shall be con-structed in such a manner that when the exposure device is placed inside, the radiation level at the outside surface shall not exceed 2.0 mr/hr.

6.5.2 The storage container shall be locked at all times when not under surveillance by authorized personnel.

6.5.3 Source storage container shall be posted with " Caution, Radioactive Material" signs, as shown in this procedure, in this section

" Caution, Radioactive Materials": signs are not required on areas where radioactive materials are stored for less than eight (8) hours, provided the radioactive materials are constantly attended.

6.5 4 At the completion of radiographic activities the projector will be returned to the storage container and a curvey shall be performed and results shall be recorded of the

" Radiographer's Field Report" (Form 3).

6.6 CALCULATQJG RADTATTON POUNDARIES 6.6.1 Calculating the boundaries of the High Radiation i

Area, The Radiation Area, and The Restricted Area.

I 6.6.2 The follovit/ factors and terms are to be used in calen1Nii_? ; the radiation boundaries and the dose ' a ea r a given location.

6.6.3 The Inverse Square Law states that he intensity of radiation is inversely proportional to the square of the distance from the source.

Mathematically, this law is symbolized as:

Ri 2

D2 Where Rj = the known dose rate in Roentgen / hour.

l s(,

R2 D2 Dj = the distance from the source for the value R.

3

6'. 6. 3 Continued in R cntgen/ hour.

R2 = the desc rate at distance D2 D2 = distance from the source for the value R '

2 To determinc R 10 unknown:

2 R D R

=

t D t To determiric D if unknown:

2 R D 2 D

=

2 g

R2 6.6.4 The value for Iridium -192 in Rocntgens/ hour at one (1) foot per one (1) curic is 5.9 Rocntgenr/ hour (R/Ilr).

One Rocntgen = 1000 millirocutgens (mR).

6.6.5 A half value layer (llVL) is that amount of material that will reduce a radiation level to one-half of its original intensity'. The following IIVL may be used in making calculations:

For iridium -192 The IIVL for steci is 's" The llVL for lead is 's" The llVL for concretc is 1.9" 6.6.6 Reduction factors arc marked on cach of the different collimators to be used in our radiographic operations. The reduction factor in-dicates the amount the collimator reduces the source strength.

Divide the source value by the reduction factor to obtain the source.

strength outside the collimator.

Exampic 1 A 100 curic, Iridium -192 source is used to radiograph a !s" thick steel vessel.

Ilow far f rom the source wi.ll the liigh Radiation Arca and Restricted Arca boundaries he located?

1) A 100 curies source of Iridium -192 yicids:

590 R/llr of one (1) feot f rca the source (100 curics)

(5.9 R/lfr)

=

Curic

2) The Is" steci vessel is onc(1) liVL for Ir-192.

/

3) 590 R/llr x!5 = 295 R/llr at one (1) foot from the sourec.

36

6.6.6 Example Continued A

4) To convert R/Ilr to mR/llr 295 R/Iir x WOO mR/Iir R/Ilr 295000 mn/Iir

=

5) To determine (D ) t th !!igh Rndlation Arca boundary (where R2 = 100 mR/llr) 2 using the Inverse Squarc Law:

D R D

=

y R2 295000 mR/llr x (1 ft.)

\\

100 mR/llr 2

2950 ft.

f 4-D2 = 54.3 ft. = the distance from the source to the High Radiation Arca boundry.

6) To determine (D ) t th Rcstricted Arca boundary:

2 2

D2=

R D t

g R2 295000 mR/Ilr x (1 ft) 2 mR/llr 2

\\ 147500 ft D = 384 ft = th distance from the source to The Restricted Area beundary.

37

Exampic 2

.A 60 Curies, Iridium-192 source is used with a collimator having a 40:1 reduction factor for Iridium. What is the distance to the Restricted Area boundary from the collimated source, using Condition A?

1) A 60 Curies, Iridium-192 source yicids:

(60 Curics) (5.9 R/Hr) 354 R/11r at one (1) foot

=

Curie from the source.

2) 354 R/11e divided by the 40:1 reduction factor equals,:

354 = 8.85 R/Ilr at one (1) foot 40

3) To convert R/llr to mR/llr:

8.85 R/Itr x 1000 mR/lir 8850 mR/IIr

=

R/llr e

8850 mR/llr is R at one (1) foot from the source (Distance D ).

g 1

4) To determine the distance (D ) t the Restricted Arc.a boundary (where 2

R2 = 2 mR/llr) usir.,; the Inverse Square Law.

R D2

=R D

y y 2 2 oR (8850 mR/llr) (1 foot)2 '= (2 mR/IIr) (x feet)2 (x feet)2 = (8850 mR/llr)

(1 foot) 2 mR/IIr S

(x fect)2 = 4425 x feet =

N 4425 - 66.52 feet to the Restricted Arca boundary from the l

co111 mated source.

9 38

Exampic 3 A 100 Curic' Iridium-192 is used to radiograph 1" thick steel. The arca is shicided by 2

" of concrete. Itow far from the source will the lligh Radiation Arca"and Restricted Arca boundaries be located?

1) 100 Curies of 1.idium-192 yicids:

(100 Curies) (5.9 R/ltr) 590 R/llr at one (1) foot from the source.

=

Curic

2) The 1" of stcci is two (2) IIVL of stccl.

2 IIVL = !s x !s = !c 3)

(590 R/llr) (!s) = 147.5 R/llr at onc(1) foot from the sourec.

4) The 2

" of concretc is 1 IIVL of concrete.

5)

(147.5 R/Hr) (h) = 74 R/llr at one (1) foot from the source.

6) To convert R/Ilr to mR/llr (74R/llr) (1000 mR/llr) 74,000 mR/Ilr

=

R/I!r

7) To determine the distance (D ) to the IIigh Radiation Arca boundary where 2

(R ) = 100 mR/IIr, using the Inverse Squarc Law:

2 2

D2=

Ry (D )

1 R2 2

74,000 mR/Ilr (1 ft )

\\ 100 mR/ilr 2

740 ft D2 = 27 feet to the Ifigh Radiation Arca boundary.

39

\\

1 i

p Exampic 3 Continued

8) To determine the distance (D ) to the Restricted Radiation Area boundary 2

where (R ).= 2 mR/11r using the Inverse Squarc Law.

2 D2=

R (D )

g 1

E2 74;000 mR/llr (1 f t)

-) 2 mR/Ilr 2

37,000 ft.

D2 = 192 feet to the Restricted Radiation Arca boundary.

l

)

l 40

9 6.6.7 Radiation exposure reduction factors:

When preparing to make radiographic exposurcs, the Radiographer

determines what part of each hour the source will actually be ex- ~

posed. The Radiographer can use the ratio of the actual ex-posure time in one (1) hour to one (1) hour as a reduction factor.

Reduction Factor =

Actual Exposure Time One !!our Exampic 4 A 100 curic Iridium-192 source is used to radiograph piping. A 20 times reduction collimator is used to reduce the radicactive area and it is determined that the radiographer will make (4) four - (5) five minute exposures per hoar. What is the distance from the source to the restricted boundary?

1) To calculate the reduction by the collimator:

100 curies x 1/20 = 5 curies

2) To calculate the reduction by the exposure reduction factor:

Exposure time per hour = 4 cxposures x 5 minutes 20 minutes

=

Reduction factor = 20 minutes = 1/3 60 minutes 5 curies x 1/3 = 1.66 curies

3) To change curies to milliroentgens:

Rt = 1.66 curies x 5.9 R/llr x 1000 mR/Hr Curic R/llr Rt = 9,794 mR/Ilr

4) To determine the distance D 2 from the source to the Restricted Area boundry using The Inverse Squarc Law:

R1

IU )

D I

2

\\R2 9,794 mR/lfr (1 f t) 2 2 mR/llr D2 = 69 feet to the boundary of the Restricted Area.

NOTE: The following tabic has precalculated boundary values.

S 41

RADIATION LEUFI,/DISTMCC CHART h Iridium-192 (unchicided) 5 curies 10 curies 15 curies 20 curies feet mR/hr feet mR/hr feet mR/hr feet mR/hr

- i 1.0 29500 1.0 59000 1.0 88500 1.0 118000 16.0 100 24.3 100 29.7 100 34.4 100

35.0 24.1

35.0 48.2

35.0 72.2

35.0 96.3 "76.8 5

103.6 5

133.0 5

153.6 5

121.5 2'

171.6

-2 210.4 2

242.9 2

25 curies 30 curies 35 curies 40 curies feet mR/hr feet mR/hr feet mR/hr feet mR/hr 1.0 147500 1.0 17700 1.0 206500 1.0 236000

35.0 120.4

35.0 144.5

35.0 168.6

35.0 192.6 38.4 100 38.4 100 45.4 i100 48.6 100 171.7 5

188.1 5

203.2 5

217.2 5

271.6 2

297.5 2

321.3 2

343.5 2

45 curies 50 curies 55 euries 60 curies feet mR/hr feet m7/hr feet mR/hr feet mR/hr 1.0 265500 1.0 295000 1.0 324500 1.0 354000

35.0 216.7

35.0 240.8

35.0 264.7

35.0 289.0 51.5 100 54.3 100 57.0 t100 59.5 100 230.4 5

242.8 5

254.7 5

266.1 5

364.3 2

384.0 2

402.8 2

420.7 2

65 curies 70 curies 75 curies 80 curies feet mR/hr feet mR/hr feet mR/hr feet mR/hr 1.0 383500 1.0 413000 1.0 442500 1.0 472000

35.0 313.1

35.0 337.1

35.0 361.2

35.0 385.3 61.9 100 64.3 100 66.5 100 68.7 100 276.9 5

287.4 5

297.5 5

307.2 5

437.9 2

454.4 2

470.4 2

485.8 2

85 curien 90 curies 95 curies 100 curies feet mR/hr feet mR/hr feet mR/hr feet mR/hr 1.0 501500 1.0 531000 L.0 560500 1.0 590000

35.0 409.4

35.0 433.5

35.0 457.5

35.0 481.6 70.8 100 72.8 100 74.9 100 76.8 100 316.7 5

325.9 5

334.8 5

343.5 5

500.7.

2 515.3 2

529.4 2

543.1 2

105 curies 110 curies 115 curies 120 curies feet mR/hr feet mR/hr feet mR/hr feet mR/hr 1.0 619500 1.0 649000 1.0 678500 1.0 708000

35.0 505.7

35.0 529.8

35.0 553.9

35.0 557.9 78.7 100 80.6 100 82.4 100 84.1 100 352.0 5

360.3 5

368.4 5

376.3 5

556.5 2

569.6 2

582.4 2

595.0 2

Average cranking distance (coi.:rol box to f ree end of guide tube) 42

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NOTICE COPIES OF THE FOLLOWING DOCU>ENTS ARE AVAILiBLE FOR REVIEW AT MINNESOTA VALLEY ENGINEERING.

1.

NRC RULES & REGULATIONS A.

10CFR-19 NOTICES, INSTRUCTIONS AND REPORTS TO WORKERS:

INSPECTIONS B.

10CFR-20 STANDARDS FOR PROTECTION AGAINSI RADIATION 2.

MINNESOTA VALLEY ENGINEERING STANDARD OPERATING PROCEDURE (RADIATION SAFETY MANUAL)

A.

OPERATING & EMERGENCY PROCEDURES B.

NRC LICENSE PERSONS WHO WISH TO REVIEW THE ABOVE DOCDENTS SHOULD CONTACT THE RADIATION SAFETY OFFICER.

/

BUILDING 10 CONCRETE SHIELDED EXPOSURE BOOTH g

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ALL WALLS ARE 24 INCHES THICK TWO ROWS OF CONCRETE BLOCK FILLED WITH CONCRETE m

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BUILDING 8 CONCRETE AND SAND SHIELDED EXPOSURE BOOTH ALL WALLS ARE 2f+ INCHES THICK TWO ROWS OF CONCRETE BLOCK FILLED WITH SAND

(

)N This wall is i

This wall is 8 feet high This wall is 10 feet high This wall is 8 feet high 10 feet high and has an add-itional i inch of steel shield-ing This wall is 8 feet high This wall is This wall is 10 feet high 8 feet high DC SCALE:

3/16 inch equals 1 foot

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Radioactive Material Storrgo Contain:r This contein:r is bolted to the floor in the 10th building shooting booth.

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with a 1/2" Icad lining.

The container is made of 1/8" steel 85".

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AIJRt SYSTDI OECK 'ID BE DCNE EVERY 3 MON 11tS

1) Press alam test button on control panel nd observe both visual and audible alams to check for preper operation.

2) With a source of radiation in the booth observe that the visual alam is working and next place smething over the infra red eye to r:nke sure that the audible alarm is working.

]

Alam system checked by Date Date to be re checked 9

sd "#*g U~1TED STATES CUCLf AJ LULATO^.Y C MMiSSION

+*o

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Washington. D.C. 20%5

.i NOTICE TO EMPLOYEES

~

6TANDARDS FOR PROTECTION AGAINST R ADIATtON qPART 201. NOTICES. INSTROCTIONS ANO

ee.'

REPORTS 10 WORKERS. INSPECTtONS (PART 19L EMPLOYE E PROTECTDON WHAT 23 THE NUCLEAR WHAT IS MV RESPONSIBILITYF MAY l GE T A RECORD OF

=e 6 *e coaa*aa. vou a ev *ewest sa WHAT FORMS OF DISCRIMINA WHAT CAN THE LABOR REGULATORY COMIWS$40N?

My RADIATION EXPOSURE?

- =hea

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correctea veteeeru.a-oaomg f no40tirr I UNITED STATES NUCLEAR HEGULATOM COMMIESION RtGiONAL OFFICE LOCATIONS A-

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REGaO88 ADOAf $$

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V,.,,' e' = u.aoi=a n*s sei.cear me e., c esi 8 312 790 5500 MAmeAs ce vinGss i$ G.e. E.seewom ass. Me as 42 eye, :L 60137 ye g e.9 .om..a..r. ear e s, u s os. aee.neear, Co au e .v S1 F 860 a100 .a.e o ~ i e e g Wm. u e , g g,C,,, u s hussear ameneser, C.ewamma n een, ei5 943 3700 9.u sulere La.e si..ee 210 OsflC Fones 3

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r p*****o,, s vaWTfo Staffs h.'f ". ** ) NUCLE AR REGUL ATORY COMMISSION ?* 01:4TED staff 5 asucLama nsoutAronv coasasesssom I { ~'.,0.' s ~<. waswessioes. o C Emes j namenes o e som f c m7.f TS.se SEP 17 804 TO: NRC Licensees. Femittees, and Applicarts Please find enclosed a revised NRC Fors 3.

Notice to Est oyees". which l

is required by 10 CFR 19.ll(c) and 10 CFR 30.7. 40.7. 50.7 and 70.7 to be pested by each hRC licensee, pemittee. and applicant. NRC licensees, permittees and applicants must haec the 4RC f orm 3 posted in those areas ut'Itzed by their tvricyees and contractors and subc ytractors. The revised Form 3 should be promptly posted at locations sufficient to permit eccioyMS to observe a copy on the way to or f rom their place of work. Fom 3 m st remain posted while the application for a pemit or u license is pending during the tem of the permit or license, and for ~ 30 days after termination of the license. Revised Form 3 is written in the form of simple questions and answers which paraphrase relevant statutes and regulations. The purpose of this change in format is to male the form more readable and understandable. The various protections and prohibitions are described in a straightforward, ganeral way. The hRC believes that the revised For, 3 wi11 help employees of its licensees. permittees. applicants, and of their contractors, subcontractors, and vendors, to clearly understand their resporsibilities and rights. and those of the NRC and the Department of Labor, on matters related to pbblic health and safety and employee protection from discrtatnation. Pursuant to 10 CFR 19.ll(c), each Itcensee and applicant shall post the current revision of Form 3. You should tale steps to ensure that the current reviston of Forv. 3 is posted by Jawary 1.1985. / ) ~ Ruhard C. C y ng. Di ctor Office of Im L tion and Enforcement

Enclosure:

As stated L

7.0 PROCEDLrRE FOR EXCHANGE OF SEALED SOURCES 7.1 scope This procedure governs the methods of exchanging sealed sources. Manufacturer and Manufacturer and Manuf. and Model No. of Model No. of Model No. of Source Assemblies Source Changer Exposure Device Technical Operations Technical Operations Tech / Ops l A-424-9 650 660 Gamma Industries Gamma Industries Tech /Dps T-3-T C-10 660 Industrial Nuclear Industrial Nuclear Tech /dps 7 IR-50 660 l 7.2 GENERAL l 7.2.1 All the precautions used when making radiographic exposures, as described in Section 6.0 of this l Manual shall be followed during the exchange of a scaled source. 'q 7.2.2 The Radiographer performing the source change x] shall also wear an audible radiation monitor in s addition to film badge and dosimeter. 7.3 pRncEnn9E 7.3.1 Locate source changer and projector in ene of the exposure booths. A survey of the source changer and projector shall be performed. NOTE: Place units to minimize any bend radius in the source guide tube and control cabling. 7 3.2 Remove plug from exposure device and connect source control cable to the exposure device. Extend the control cable so that the operator is in a safe position. 7.3.3 Remove plug for cource guide tube to the exposure device outlet tube. 7 3.4 Remove round plug from source changer (empty chamber). 7.3 5 Connect the short source guide tube to the exposure device outlet and source changer empty chamber. Unlock the exposure device and changer. l 7.3 6 Crank decayed source into source changer. I

7.3.7 At this point a survey meter shall be employed to insure that the source has been safely located in the shielded position in the source chang /hr at er. The radiation level shall not exceed 200 mr the surface of the changer. Lock the source changer side containing the decayed source. 7.3.8 Disconnect the short sourco guide tube from source changer and disengage disconnects. 7.3.9 Replace plug in source changer outlet. 7.3.10 Remove plug from source changer new source chamber. 7.3.11 Connect the control cable and new source pigtail. 7.3.12 Connect short source guide to source changer outlet. 7.3.13 Unlock the side of the source changer containing the "new" isotope and pull the new source into the exposure device by turning the control cable handle counter clockwise. 7.3 14 Survey the exposure device with a curvey meter to make sure the radioactive cource is in the " safe" position in the exposure device. Verify that radia-tion levels not exceed 200 mr/hr at the surface of either the exposure device or changer. Lock the 9 device and changer, then remove chort cource tube from exposure device and cource changer. 7.3.15 Replace plug in empty chamber of cource changer. 7.3.16 Receal outlets on cource changer with lead seals provided. 7.3.17 Remove old cource number plate from plate holder on exposure device and replace with new source number plate located incide source changer. Place old cource number plate in source changer. 7.3.18 Return chart source tube to cource changer case and coal. Two (2) lead s6al wires have boon furnished with the new cource. One is to be used for reccaling the cource hanger cap plugs and one for coaling the locking device on changer shipping container. 7.3.19 Affix proper shipping labela and return to the cource supplier in accordance with Section 9.0.

8.0 PROCEDURE FOR OPERATING EXPOSURE DEVICES 8.1 g-This nrocedure describes the used bp Minnesota Valley Engineering. method of operating exposure devicca 8.2 PROCEDURE 8.2.1 Prior to perfor=ing radiographic operations, the Radiographer shall perform the following: Perfom the dakly inspection and maintenance required and a. record the results on the Radiographer's Field Report (Fom 3). Operation characteristics may be checked during the first exposure of the shift. b. Perfom all necessary set up on parts to be radiographed. Establish a restricted area as described'in Section 6.0 of c. their Manual. d. Survey exposure device at outlet plug and record the. meter reading on the Radiographer's Field Report (Form 3).- 8.3 _ OPERATION OF EXPOSURE DEVICES 8.3.1 Operation of Tech / Ops Model 660 Always have an operating survey meter on hand during radio-t a. graphic operations and use it. y y'. b. Unlock the projector with the key provided and turn the connector seicetor ring from the lock position to the connect position. When the ring is in the connect position, the storage cover vill disengage fron the projector. See Figure #1. . f, Slide the control cable ecliar back and open the jaws of the c. *2 control,cabic connector. ' 4., y,,,, the svivel connector as.shown.This exposes the cale position of 1 .g See Figure #2., ,g, i. d. Engage the male portions of the swivel connector as shown by .I' deprescing the spring-loaded locking pin toward the projector with the thu=bnail. the connection has been properly made.Reicase the locking pin and See Figure #3. Close jaws of the control cable connector over suivel-type e. r,. connector. See Figures #4 and #5. Slide control cable collar over connector jaws. f. lloid the control cable collar flush against the projector connector and rotate the selector ring from the connect position to the lock position. Keep projector in the lock o position until actual operation is ready to start.

g. Remov] sar;ty plug from protruding nippio loc;t;d cpproximat:ly 1" from bottom of unit. h. Connect source tube. W

i. Place free end of source tube in desired position.

Check to assure that no kinks exist in the source tube, J. Stretch control cable away from projector in as straight a line as possible. k. Unicek the projector connector and rotate the selector ring to the cperate position. The source is now free to move. 1. Crank source out as smooth as possible. When you feel that source is approaching end of tube, slow the turning speed so that pigtail does not strike the end of the source tube with undue force. e. Survey the restricted area to see that radiation levels are within limits. n. Upon ccmpletion of the exposure, retract the source into the exposure device. o. Survey carafully to insure that source has returned to safe positien. The entire circunference of the exposure device shall be sur*/eved. Also survev the entire length of the gu id e t'J b e. p. Lock the exposure device while still watching the survey meter for any large deflections. q. Disconnect the source tube form exposure device, Screw the source tube safety plug into place, r. s. Disconnect the control cable. 4 t. Replace the storage cover. u. Survey exposure device prior to storage to insure that the sealed cource is locked into its safe storage position. 0 54

8.4 PERFORMING EXPOSURES IN THE PLANT FABRICATION SHOP 8.4.1 The surface of the Radioactive Materials storage container is surveyed and should be less than 2 MR/HR. 8.4.2 The exposure device is removed from the storage centainer and and surveyed at the surface. The radiation level is recorded. If this radiation level exceeds 50.iillirem per hour at 6" from ther surface, the radiation safety officer shall be notified immediately. 8.4.3 When the exposure device is removed from either the storage container or its shipping container, the exposure device is surveyed at the surface and at six inches from the surface of the device. 8.4.4 Whenever possible, exposures will be made in the exposure booths of the fabrication shop where access by unauthorized personnel can be best controlled. 8.4.5 Lead, tungsen, or spent uranium collimators will be used on all exposures where possible to reduce the radiation area. 8.4.6 Whenever possible, exposures will be cade behind shielding concrete barricades, both stationary and portable. 8.4.7 During exposure, surveys will be made at the periceter of the restricted area to assure that the radiation area is properly restricted so that the total quantity of radiation in any 1 hour does not exceed 2 MR. 55

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9.0 RECEIPT, SHIPMENT, AND TRANSPORTATION OF RADIOACTIVE MATERIALS ~ 9.1 SCOPE 9.1.1 This procedure describes the requirements for receivin;;, shipping, and transporting radioactive material by Minnesota Valley Engineering. ~~ 9.1.2 The Quality Assurance Program is applicable for transportation of radioactive material (IR-192) over 20 curies. 9.2 CENERAL 9.2.1 This procedure meets the requirements of the Nuclear Regulatory Commission and the Department of Transportation regulations. 9.2.2 Prior to release of any packages over 20 curies to a carrier, the l Radiation Safety Officer shall assure appropriate certificates and/or test results are on file for the source and shipping container. 1 9.3 PROCURD1ENT AND RECEIPT OF RADIOACTIVE MATERIAL l 9.3.1 All radioactive material will be ordered by Purchase Order. The Purchase Order shall be reviewed by the Radiation Safety Officer, i 9.3.2 Prior to approval of the Purchase Order, the Radiation Safety l Officer shall assure he has on file appropriate certifications and/or test results for the source, camera and shipping container. 9.3.3 The following procedure shall be followed when receiving radio-active material, Uhen delivery is by common carrier, the Radiation Safety a. Officer or Radiographer shall receive the radioactive material when delivered, b. When the radioactive material is to be picked up at the carrier's terminal, the Radiation Safety Officer shall make arrangements for the carrier to notify him upon arrival. When notified by the carrier, the Radiation Safety Officer or Radiographer shall pick up the radioactive material expeditiously. The package of radioactive material shall be monitored as soon c. as possible, but no later than three (3) hours after receipt Radiation levels shall not exceed.200 mr/hr at the external surface or 10 mr/hr at three (3) feet from the external surface of the package. The Receipt of Radioactive Material Form (Form 7) shall be completed upon receipt of radioactive material.

d. The package shall be inspected for any evidence of physical damage. Evidence of physical damage shall be re-ported to the Radiation Safety Officer. The results of the inspection shall be documented.

9.3.4 When the radiation level at the external surface of the package exceeds the limits stated in paragraph 9.3.3c a Restricted Area shall be established around the package and the Radiation Safety Officer notified. 9.3.3 Packages of radioactive material shall be stored as described in Section 6.0 of this manual. e e

9.4 PACKAGING 9.4.1 Projectors and source changers shall be packaged as described below: PACKAGING REQUIRE >ENTS - MAXIMUM NUFBER OF EXPOSURE DEVICE OR SOURCE CURIES ALLOWED TO BE MINIMUM TYPE OF CHANGER MODEL NUFBER SHIPPED AND SOURCE TYPE OVERPACK REQUIRED Exposure Device Tech Ops 660 100 Curies (IR-192) Wooden Crate Source Changers Tech Ops 650 100 Curies (IR-192) None Required Industrial Nuclear 100 Curies (IR-192) None Required Model IR-50 9.4.2 When shipping an exposure device / source changer containing a source, assure that the source is in the stored position. 9.4.3 The exposure device or source changer shall be prepared for ship-ment as described below, Assure that the shipping plug is secured in place and sealed a. and the projector locked. h. If an overpack is used, verify seals are in place and that the outer packaging is strong enough to withstand the normal conditions of transportation. 61 l

9.5 MARKING The package shall be marked with the proper shipping name and 9.5.1 identification number as described below: Package Containing Proper Shipoing Name Projector / Source Chancer A. Containing Source Radioactive Material Special Form, N.O.S. ID #NA9182 B. Empty but requiring Radioactive Material Yellow II or III label L.S.A., N.O.S. ID #UN2912 C. Empty Radioactive Device N.O.S. ID #UN2911 9.5.2 The package shall have the name and address of MVE affixed to the package. 9.6 LABELING 9.6.1 A survey of the package shall be made to determine the appropriate shipping label as described below: MAXIMUM RADIATION AT SURFACE OF THREE FEET FROM SHIPPING CONTAINER LABEL Not exceeding 0.5 MR/HR Radioactive White I at surface (Figure 1) More than 0.5 MR/HR, but 8 Radioactive Yellow II not more that 50 MR/HR,at (Figure 2) surface and not exceeding 1.0 MR/HR at three feet More than 50 MR/HR at surface

Radioactive Yellow III but not exceeding 200 MR/HR, (Figure 3) exceeds 1 MR/HR, but not greater than 10 MR/HR at 3 feet 9.6.2 Complete two labels indicating the contents, Iridium 192 and the number of curies. For Radioactive Yellow II or III labels, insert the transport index in the box.

(See note following.) The label shall be attached to opposite sides of the package, near the shipping name. 62

(NOTE Th3 tran1 port index is defined as the highest radiation dose rate in millirem per hour at three feet from any accessible external surface of the package. This number shall be rounded up to the next highest tenth and written in the transport index box on Radioactive Yellow II and III labels. 9.6.3 Empty projectors or source changers do not require labeling if' the following conditions exist: a. The radiation level at the surface is less than.5 MR/HR. b. There is no measureable radiation at three feet from the sur-face. c. If the above conditions exist, the package shall be marked with the following stitement: " EXEMPT FROM SPECIFICATION PACKAGING MARKING AND LABELING AND EXEMPT FROM THE PROVISIONS OF 49 CFR 173.393 PER 49 CFR 173.391." 9.6.3.1 If the surface radiation level exceeds.5 MR/HR, determine proper label per 9.6.1. 9.7 SHIPPING PAPERS 9.7.1 A Shippers Certification for Radioactive Materials (Form 11) shall be completed for each package of radioactive material. Complete the information in the appropriate section titled " source, empty, empty LSA", as applicable. 9.8 SHIPMENT BY COMPANY VEHICLES 9.8.1 In addition to the requirements of Paragraphs 9.2 thru 9.7, the following shall apply for the transportation of radioactive material by company vehicle. a. The package shall be suitably secured, b. A calibrated and operable survey meter shall be located next to the driver while in transit. The driver shall also wear a film badge and dosimeter. c. The radiatier, level at the driver and the outside of the vehicle shall be a 2 MR/HR or less. The radiation level shall be determined by a physical radiation survey. 63

d. During transit of rzdionctiva mat: rial a NOTICE sign as shown in this procedure shall be conspicuously displayed inside the vehicle. C e. If the vehicle becomes disabled on the road, do not leave the vehicle unguarded when going for help. A message for help may be sent by a. passing motorist or the police be enlisted to guard the vehicle. f. Should any kind of accident occur, make an immediate radiation survey to see where, if at all, the radiation levels are higher than normal. If any abnormal radiation areas exist, restrict and post the area at the 2MR/HR level. Get police assistance, if necessary to keep all persons at a safe distance. Do not leave the area if possible, but send the police or other persons to call the radiation safety officer to give your location and situation. g. Collect information pertinent to the accident, such as names'of witnesses, names of people involved, names of police, license numbers, circumstances of the accident. Inform the radiation safety officer promptly upon arrival, giving him as much infor-mation as possible about the condition of the radioactive source. h. If a source should escape from its container, the vehicle operator should made no attempt to restore the source by him-self, but he should wait for assistance from the radiation ~ safety officer. W 9.9 SHIPMENT BY CARGO AIRCRAFT 9.9.1 In addition to the requirements of paragraphs 9.2 through 9.6, the following additional requirements shall apply for the shipping of radioactive material by cargo aircraft. a. The package shall have a " Cargo Aircraft Only" label, as shown in Figure 4 of this procedure affixed to the package near the proper shipping name. b. The Shipper's Certification (Form 11) shall indicate cargo aircraft only. 9.10 SHIPMENT BY MOTOR FREIGHT 9.10.1 In addition to the requirements of paragraphs 9.2 through 9.5, the following additional requirements shal' app]y for shipments of radioactive material by motor freight. a. Four placards bearing the words " Radioactive" shall be sup-plied to the driver if radioactive Yellow III materials are transported. Also, the Shipper's Certification shall have the statement " Radioactive Placards" required (Figure 5). 64

NOTE: Prior to releasing any radioactive materials for shipment as stated in 7.0, 8.0, and 9.0, the package shall be inspected for any conditions which may cause shipping container failure in transit. Performance of this inspection shall be signified by signature of the appropriate space on Form 7. b 65

NOTICE IN CASE OF AN ACCIDENT INVOLVING THIS 7EHICLE IMMEDIATELY NOTIFY: WILLIAM MCKNIGHT Route 1 Box 2G2 New. Prague, MI 560.71 Home Phone 612-364-8915 BUISNESS PHONE: (612) 758-4484 JERRY FLICEK MINNESOTA VALLEY ENGINEERING 407 7th ST. N.W. NEW PRAGUE, 201 56071 BUSINESS PHONE: (612) 758-4484 HCIE PHONE: (612) 758-2746 ROBERT BROSTROM SIOUX HILLS HUTCHINSON, MN 55350 BUSINESS PHONE: (612) 587-3636 HOME PHONE: (612) 587-6785 e e t 66

6 Figure 1 a HANDLE CAREFULLY RADIDAC"IVE Figure 2 CONTENT 5... NO. OF CU. 5:.. ) ,s,__ _. _ w __ Ru! %u! hj HANDLE CAREFULLY J:=;i" antra \\ =- CQNTENTS-. ~ ~- ~.:'"~"~***""** .ho,of Cutili -[ - -.r:4.;.- .i ";;i:1 _,d h - o m x__ l l 1" ] f '" HANDLE CAREFULLY d. hJ l" J::::;'.;'i.n..:. A CON f(NIS:....... p '... p.. '9.. NO. OF Cutif'1, .f-k _. e "*ag,"lf "::. ;a i s sLT 67

G DANGER! DO NOT LOAD ON PASSENGER AIRCRAFT l wn4Wy; d, a .Y Fh D b A \\ a. " it if l[- i % m m ma1 cs m macw wrvum:gaayL Figure 4 l b0

6 VEHICLE PLACARD 7:.*N x s' $l \\ -(RAD 10ACTI\\'E,' x \\ / / g s / s/ Figure 5 69

10.0 EMERGENCY PROCEDURE 10.1 SCOPE 10.1.1 This procedure describes the method of handling malfunction of equipment, over-exposure to per-sonnel and other unusual incidents. 10.1.2 The Radiation Safety Officer has the responsibility for direction and resolution of any emergency situation involving source material. The respon-sibility includes source retrivals. 10.1.3 Emergency phone numbers: Radiation Safety Officer Radiation. Safety Consultant William J. McKnight Robert Brostrom Rt. 1 Box 202 Sioux Hills New Prague, MN 56071 Hutchinson, MN 55350 Phone: Work'612-758-4484 Phone: Work 612-587-3636 Home 612-364-8915 Home 612-587-6785 10.2 RXAMPLRS OF EOUTPMENT MALFUNCTION 10.2.1 Run off. Symptoms Source exposed. Control crank turns very freely and quietly. Source can-gg not be retracted. Cause Failure to connect sourco guide tube or snout switch. End of cable has passed beyond hobbed drive wheel. Remedial Undo the bottom nut (3/4" wrench) of control cable housing fitting at the crank unit. End of cable will be exposed. Pull cable out of housing about 1 foot. Insert cable in crank unit and engage hobbed wheel. Refasten nut. Retract source in normal way. If much resistance is encountered, don' t force c udt. Work handle back and forth. Cable may, because of bends, be catching at opening. After retracting source, inspect the source guide tube. If source and cable were ejected onto the ground or floor, it has very likely become fouled with dirt and grit, and the machine should be cleaned before returning to service. There may be cases where the end of the cable is too far inside the housing to be () withdrawn. In this case, it is necessary '%;( to undo the fitting of the housing at the projector itself, withdraw the cable from the shield, and push it into the housing.

In this case you will be in a radiation area. The operation can be done in less than one minute if uncomplicated by an awkward location. Observe the precautions that will minimize your dose. 10.2.2 Disconnect. Symptoms Source is exposed. Turning crank moves the cable, but no change in radiation level is observed. Crank may not turn if male portion of connector is caught in STORED-OPEN switch mechanism. Cause Connector damaged, dirty or not conected. Remedial Crank out cable and attempt to make Action connection by repeated probing. If this fails you will have to undo the source guide tube and spill the source assembly out on the floor so that it may be picked up and placed in a container or projector. To do this you will need some means of manipulation and some shielding. Shield the source by either moving the guide tube to shielding existing or move in shielding material so that you can uncouple the source guide tube. After uncoupling the guide _ tube lift it with some manipulator and pour the source assembly out on the floor. A piece of paper on the floor will keep the source clean. Next pick up the source assembly with your manipulator and insert it in the projector, connector first. Then with the shipping plug held in the manipulator push the source assembly into the projector. The radia-tion levels should now be back to normal. Fasten the shipping plug in place. The machine is now in a safe condition. If further repair is desirable remove the STORED-OPEN switch assembly. The connector is now exposed for examination. If proper operation of the connector has been prevented by dirt, clean it with any solvent such as lighter or cleaning fluid. If the connector spring has been bent or destroyed there is no way to repair it effectively in the field. The projector may be reassembled and the entire unit shipped to the factory for repair or the source may be ejected in-to a source changer, even if the connector will not hold. Follow the source changer manual for technique. We can fit a new connector to the source assembly and

usually return it the day.it is received. 10.2.3 Crushed Control Housing. Symptoms Damage usually obvious. Cranking difficult or impossible. Cause Rough handling or accident. Remedial If cranking is. impossible and source is Action exposed, remove lower fitting of control housing at crank unit. Pull the cable to retract housing. A rag will assist you in holding the cable. Don' t kink the cable and don't use pliers to pull it. If it is impossible to retract the source by this method remove the hous-ing fitting at the machine and retract the source by pulling the cable. Move back as you pull the cable to keep the maximum source distance. If you must work at the machine, observe the rules for minimizing your dose. After the source is retracted the shipping plug should be installed. The cable may now be withdrawn from the damaged housing. If not, remove the 7-) STORED-OPEN switch actuator, disconnect (g the source, replace the switch actuator, and replace both housing and cable. Use caution when you remove the switch actuator housing as you can withdraw the source from 1.ts shield. 10.2 4 Crushed Source Guide Tube. Symptom Exposed source cannot be moved or can only be moved back to, but not by, crushed portion. Cause Falling object. Remedial Move source with control to position Action furthest from crushed portion. Shield source so you can work at point where tube is damaged. Attempt to open up crushed portion by hammering tube back to a more'round shape. If unsuccessful, the crushed potion must be cut away. Cut i vinyl cover and peel away from damaged j part. Hold tube in a vise to board so i that one side of the crushed part can be filed, ground or sawn thru. With two pairs of pliers the spiral wrap of the tube can be twisted out. Take care that you do not damage the cable within the tube. l f

Next, align.and secure the severed ends of the tube. They~need not be in contact. The source may now be retracted. 7,() ( 10.2 5 Dirt Fouled Projector. Symptom Cranking difficult or impossible. Operation crunchy. Cause Cable fouled with dirt and grit. Use of graphite -in source tube. Remedial Retract source. If impossible to crank, Action open lower fitting at crank and pull back by hand. If this fails, open fit-ting on rear of shield and pull back by hand. Install shipping plug. Remove control cable housings by undoing fit-tings and stripping out cable. Inspect ' cable for damage. Kinks may be straightened out by bending by hand. Don' t use pliers or hammer on cable. Coil cable and wash in solvent. Kerosene, gasoline or clean-ing fluid may be used. Do not use caustics, Oakite or similar degreasers. l Wash housings and guide tubes by syring-ing solvent through them, followed 1rith a gentle air blast. Hang housings and ~ guide tubes so that they can drain. The vinyl cover on the tubes can be ruined by soaking in solvent. Disassemble crank unit and wash in sol-vent. Brush out teeth of hobbed drive wheel. Reassemble with touch of grease on bearin63 Observe the precautions on the container of solvent. Avoid prolonged exp,osure to solvent vapors, and use care with flam-mable liquids. Grease cable with grease conforming to mil. spec. No. G23827A and reassemble projector. Handle cable to avoid re-introduction of dirt. Most projector repair and servicing is greatly facilitated by having a source changer available. By all means use one is possible. If none is available a second projector, even if loaded, can be used for temporary source storage. g Eject the source from one projector l l

through the source guide tube into the exit of the second projector. The source guide tube must be aligned with the exit of the second projec+.or and secured. Orank carefully and abserve the survey meter to be sure the source has entered the second projector. The radiation level at the second projector may be quite high, but low enough to permit you to accomplish your repair. If you uncouple the source assembly in the second projector use care, and be very sure the source is not accidentally withdrawn. 10.2.6 Recommended Tools and Supplies for Emergency Service. Survey meter-two if available. Dosimeters and charger. Adjustable wrenches, opening to 3/4". Set Allen keys up to t". Screw driver. Pliers. File-10" mill. Roll of tape. 6 Foot tongs. Cord. Grease. (mil spcu. No. G23827A) Solvent-1 gallon. Round cake pan. Dummy source assembly. Spare parts. 10.3 pROCIRDURE 10.3.1 Each Radiographer shall be responsible for assuring that the following steps are taken in.the event of an emergency situation. a. Restrict and post the radiation or suspected radiation area to ~a.2 mr/hr level. This can be done with a radiation survey instrument or by calculations. b. Assess the incident to determine the possible cause. c. If there is high exposure to individuals attempt to determine the actual exposure, by calculation. d. Call the Minnesota Valley Engineering Radiation Safety Officer and report the details of the incident. 10.3.2 The Radiation Safety Officer shall ensure that the fih badres of nersonnel whose dosimeter has gone o f f scale shall be sent immediately to

R. S. Landauer, Jr. & Company for processing. He shall call the R. S. Landauer, Jr. & Company telling him that the badges have to be sent and require immediate processing and reporting of results. R. S. Landauer, Jr. & Company Glenwood Science Park Glenwood, IL 60425 Phone: (312) 755-7000 10 4 OFF-SCALE POCKET DOSIMETER READINGS 10.4.1 In the event that the dosimeter reads off scale indicating an over-exposure to personnel, the following steps shall be taken. a. Stop work immediately and place the source in the safe storage position in the exposure device. b. Notify Radiation Safety Officer. 10.5 VEHICULAR ACCIDENT INVOLVING RADIOACTIVE MATERTAL 10 5.1 Survey the projector to determine if the source is still in the shielded condition. If the source is exposed, restrict and post the area at the ,r~s 2 mr/hr level. If possible, post guards at the ( ) perimeter of this area. 10.5.2 Notify the Radiation Safety Officer. 10.6 ACTTON IN CASE OF OVER-EXPOSURE 10.6.1 If is is apparent that the Radiographer, Radio-grapher's Assistant or any other individual received or is in danger of receiving 25 rems or more because of an incident, the Radiation Safety Officer will immediately inform the Chicago Operations Office of the Nuclear Regulatory Commission. Their address and phone number is: United States Nuclear Regulatory Commission Division of Compliance - Region III 799 Roosevelt Glen Ellyn, IL 60137 Phone: (312) 932-2500 (daytime or night-time) 10.6.2 If an exposure was received of more than 5 rems, but less than 25 rems, the Radiation Safety Officer will notify the Nuclear Regulatory Commission within 24 hours. I

10.6.3 The Radiation Safety Officer shall review the film badge service report and prior exposure history to determine whether or not the individual may continue working with radioactive sources. Individuals having suspected over-exposure shall not perform work with radioactive sources until the foregoing review i.s completed and a determination is made that an over-exposure did not occur. 10.6.4 If the source is lost or stolen and causes any person to receive 5 rems or more of radiation, the Nuclear Regulatory Commission shall be notified immediately by the Radiation Safety Officer at the address and phone number on the precceding page. 10.6.5 If the Radiographer or Radiographer's Assistant should receive core radiation in any calendar quarter (13 weeks) than set forth in Part 20 of Federal Regulations, that is 3000 millirems per quarter, the individual shall make a written report explaining the circumstances under which the exposure took place and submit this report the the Radiation Safety Officer. 4 4 72

11.0 INSPECTION AND MAINTENANCE OF RADIOGRAPHIC EQUIPMENT 11.1 SCOPE This procedure governs the method and responsibilities for the inspec-tion and maintenance of radiographic equipment. 11.2 DAILY MAINTENANCE AND INSPECTION 11.2.1 Prior to perfoming radiography, the Radiographer shall perform a daily inspection of the equipment. The Radiographer shall be responsible for completion of " Radiographer's Field Report" (Form 3), which serves as a combination checklist and record that the inspection was perfomed. 11.2.2 During use, this form shall be completed during use of the exposure device. All completed records will be filed by the Radiation Safety Officer or his designee. 11.3 OUARTEP1Y MAINTENA';CE AND INSPECTION -T 11.3.1 The Quarterly Maintenance and Inspection Program shall be in accordance with the radiographic equipment manufacturer's reco=mendations. 11.3.2 The inspection and maintenance shall be performed at least once every three (3) months by the Radiation Safety Officer, Radiographer, or Radiation Safety Consultant. 11.3.3 The p,rocedure for quarterly maintenance and inspection shall be as described on Radiographic Equipment Report (Fom 5) which serves as a combination checklist and record that the operations were perfomed. 11.3.4 The individual performing the operations shall complete the Radiographic Equipment Report (Fom 5) and return to the Radiat. ion Safety Officer for review. Copies of this record shall be maintained on file. 11.4 OUARTERLY INVENTORY 11.4.1 Once each quarter the Radiation Safety Officer shall conduct a phy-sical inventory of all isotopes received and possessed under this license. The inventory shall include isotope type, quantity, loca-tion and the date conducted. Results of the inventory shall be documented on Fom 6. 73 m

12.0 LEAK TESTING 12.1 SCOPE This procedure describes the method for leak testing sealed sources. Leak testing of sealed sources shall be conducted a minimum of every six months. 12.2 PROCEDURE Tech / Ops 660 12.2.1 Leak tests shall be performed by the Radiation Safety Officer, Radiographer, or the Radiation Safety Consultant. 12.2.2 The leak tests will be performed using ICN or Model 1000 Leak Test Kits and after the tests are performed, the Test Kits are sent to: ICN Model 1000 ICN - Isotope & Nuclear Division 2727 Campus Drive David S. Gooden P.H.D. 6161 S. Vale Avenue Irvine, CA 92664 Tulsa, OK 74177 Phone: (714) 833-2500 Phone: (918) 494-1444 (918) 496-3232 12.2.3 Be sure to survey all smears taken before sending them. If the radiation level from the snears is in excess of 0.4 MR/HR, notify the Radiation Safety Officer. These smears must not be sent throuch the mail. The leak test facility should be notified for 7 shipping instructions. 12.2.4 Leak test the sealed source in the Exposure device. Dissolve the Alconox powder supplied with the kit in 20 ml a. of water, b. Remove one wooden stick with a cotton swab from the kit and moisten swab with the Alconox solution. Survey exposure device and remove safety plug at the outlet c. of the exposure device. d. Insert the moist swab into the "S" tube of the exposure device and wipe the surface of the "S" tube. Return moist swab to plastic envelope in kit, e. secure with staple, f. Remove second dry swab from kit and dry the moistened surfaces of the "S" tube of the exposure device. Return second swab to the plastic envelope in the kit and g. secure with a staple. / 74

h. Return the safety plug to outlet of exposure device. Survey exposure device and return device to storage. i. Survey leak test kit with smears to insure that there is no radiation in excess of 0.4 MR/HP.. J. If the smears show no detectable radiation, fill in the information required on the kit and forward per paragraph 12.2.2. k. If the smears show detectable radiation in excess of 0.4, contact the Radiation Safety Officer. 12.3 PROCEDURE Tech / Ops Model 773 Instrument Calibration Device 12.3.1 Leak test shall be performed by the Radiation Safety Of ficer or Radiographer. 12.3.2 The leak test will be performed using Tech / Ops Model 518 leak Test Kit. After the tests are performed, the Test Kits are sent to: Tech / Ops - RPD 40 North Burlington Avenue Burlington, Mass 01803 617-272-2000 ![f r~~ 12.3.3 Locace Model 773 Instrument Calibration Device in the exoosure booth in the 10th Building, a. Remove lock and rotate handle from top of source rod and remove shipping cover. b. Moisten the leak test swab with EDTA solution and blot off excess. Wipe around top of source rod. Standing away from beam port, raise the source rod to the open position and wipe exposed source rod thoroughly, c. Place the leak test swab in plastic envelope. Set survey meter on it's most sensitive range and place the meter in a low background area. Move the swab in its plastic envelope to the meter, not the meter to the swab. If the meter indication is less than 0.2 mr/hr. above background place the plastic envleope with the swab into the mailing box and mail to Tech / Ops. Be sure to fill out return identification sheet. d. If the swab shows more than 0.2 mr/hr. do not mail, contact Tech / Ops for specific instructions.

13.0 RADIATION SAFETY AUDITS 13.1 SCOPE This procedure describes the teethod of conducting Radiation Safety Audits. 13.2 PROCEDURE AND RESPONSIBILITIES 13.2.1 Radiation Safety Audits are conducted in two (2) phases as follows: a. Radiographer's Audits The radiation safety officer or a qualified radiographer designated by the radiation safety officer shall audit each radiographer and radiographer's assistant at least once every three (3) months. The elements to be audited shall be based upon the requirements of the Nuclear Regulatory Commission Regulations, license conditions and the Minnesota Valley Engineering operating and emergency procedures. b. Program Audit At least yearly, the company safety officer shall arrange to have the Radiation Safety Program audited by the radiation safety consultant or other qualified individual not having responsibility for radiation safety at the particular project being audited. The results of the audit shall be reported /g on the Radiation Safety Program Audit Report (Form 10). 13.2.2 The radiation safety officer shall be responsible for providing corrective action for deficiencies noted in the foregoing audits. A copy of the audit reports, and corrective action shall be provided to the company safety officer. 76

Nuclear Regulatory Commissin ISOTOPE LICENSING DIVISION I GENTLEMEN The radiation safety program detailed in this Radiation Safety Manual will be used at Minnesota Valley Enginaering. The mailing address is 407 - 7th St. N.W., New Prague, Minnesota 56071. The responsible administrative individual for this program is: Jerry Flicek Minnesota Valley Engineering 407 7th St. N.W. New Prague, Minnesota 56071 Business Phone: (612) 758-4484 Home Phone: (612)-758-2746 The radiation safety consultant for this program is: Robert Brostrom Sioux Hills Hutchinson, Minnesota 55350 Business Phone: (612) 587-6785 Home Phone: (612) 587-3636 The radiation safety officer for this program is: William J. McKnight R. 1 Box 202 New Prague, Mn 56071 Home Phone 612 -364-8915 Business Phone: (612) 758-4484 s 77

) UNITED STATES NUCLEAR RESULATCRY C2MMISSIEN RULES and REGULATIONS m TITLE 10. CHAPTER 1. CODE OF FEDERAL REGULATIONS-ENERGY ) PART PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL 71 2 ~ Subpart A-General Provtatoesa ser. 71 4 Purpose and 3 cope. 71 1 Connuruca cona. 71 59 SpcMc standards for a Essile Class Appendit A-Determiration of A and Aa. M2 Intqntation' 11 package - Authority Secs 53.57.62 63 81.161 181 18). 71 3 Requirement for license-Ti et Specific standards for a Leslie Class 64 Stat MO. 932. 931935 948 953 954. as III shipment amended (42 l' S C 20*3. 20??. 2092. n. p ial n un enH ut nu 3H.

2. 2n3) Secs 201. as 71 a por t on oflicensed material-p 71.6 Information collection reqwrements:

shipments amended. 302 208. Se Stat 1242. as 71 65 Add.tional requiremerits amended. 1244.1246 (42 U.S C. Sa41. Subpart F-Package and Speclei Form 5442.5646). Subpart B-Esempt6ana Teste Section n r also innd under sec. 301. ec hb L 96-295. 94 Stat faF9a ?1.71 Normalconddions of transport 2 For the pu* poses of sec 223. es Stat e64. aa H p 'hefical accident cond.fiona 71.7 Specific esemptions' 17 3 71 75 Quahfication of special form amended (42 U.S C. 2273). Il 71.3. n 43. 71 8 Esemption of physiciana rei acuse matenal 7145. 7155. 7183 (al and (b). 7183. 7185. E 71.77 Tests for special form rad:oacnve n 87.n 89. and 7197 are issued under sec., 71.10 Esemption for low-level mate 71.11 [ Reserved] 88'm8I Selb. Se Stat 948 as amended (42 U.S C. fs 2201(b)). and Il 71 $(b). 7181. 7193. 71.95. s Subpart C-General Licenses-Subpart G-Operating Controle and and 71101(a) are issued urider sec telo. Se Procedurve 7112 Ceneral ucense'NRC appoved Stat 950. as amended (42 U.S C 2201(o)) 71.81 Appbcabiht) of operating controls and package-procedures Subpart A--General Provisicme 7113 Prenous!y approved Type B package. 71 53 Assumptions as to unknown 71 14 Genera! Ucense. DOT specificauon conta m. proprues O7tO P##'**and* " 71 85 Prehminary determmations. 71.16 Gene s! Ucense. Use of foreign 71 87 Routine dete mmations (a) This part establishes:(1) approsed package. 71 88 Aar transport of plutorum .. requirements for packaging preparation 71.18 Ceneral Ucense. Type A. Essile Cl*" 71 a9 Opening instruct 4oria. 3 for shiprnent and transportation of U pack ag*- 71 91 Records

licensed material, and (2) procedures 71 20 General Ucense Restncted.Osalle 71 93 Inspection and tests and standards for NRC approval of Class H package.

g 71 95 Reports n 22 n, a], g packaging and shippmg procedures for e s

P 8

97 Adiance n tification f shipment of a y,, h me fissile matenal and for a quantity of a n 24 Ceneralucense Restricted.nse0s n gg k,*[ l other licensed materialin excess of a Cia as !!! shipment. L. Type A quantity. Subpar 1 D-Apptcation for Package

D Approval n tot 4ahty asscence mqusremente (b) De packaging and transport of 71103 Qaht) assurance organ;zation.

licensed matenal are also subject to 105 Quaht) asseance pmgtam-33 acka e d senp o other parts of this chapter (e g. Parts 20.

C 88'
8"
71 35 Packa&e evaluation.

21. 30. 40. 70. and 73) and to the n 37 Quaht) assurance D#

'"" *'"'. pr o? """' ' " chons cedures. mod regulations of other agencies (e g. the 73.39 Requirement for additional s inf0"" 8 0"- dra US M Mate n 113 Document control. (DOT) and the U.S. Postal Semce $wbpar1 E-Package Approvst Standarde 71 115 Corfrol of purchased ma'snal, $ o(USPS) ') having jurisdiction over me 71 41 Demonstration of compliance. equipment. and sernces f transport The requtternents of this 7143 General standards for all packages. 71117 Id<nticanon and control of f, part are in addation to, and not in Ft.45 Uffir3 and tie-down standards for all mater ats parts. and components. 7 packages. 71119 Control of special processes. [ substitution for, other requirements. Sec n 121 Intemal nspection. (c) De regulations in this part apply 714? Entemal radration standards for all 71 123 Test control. ., to any licensee authorized by specific packases 71125 Control of measuring and sent I cense issued by the Commission to 71 51 Ad1tional requirements for Type B equipment. receive, possess. use or transfer packages 71127 Hand:mg storage.and shipping licensed materialif the licensee delivers p 71 52 Exemption for low specific actmry control that material to a carner for transport or (LSA) packages 71 129 Inspection test and operating status. transports the material outside the 71 53 Ossde matenaf esemptions n 131 Nonconform ng ma'enets parts.or confines of the licensee's facility, plant. 71 55 Generai requirements for all fisode components. matenal packages 71 133 Correctise action , g,g g

g_4, 71 5? Specific stendards for a Ossile Class I 71 135 Qualit) assurance records.

g 3 g,g package M 137 Audits, p m OsN 71 1 May 31,1984

PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL cr other authorized place of use. No form radioactive material. permitted in a to provide nuclear criticality safety prsvision of this part authortnes Type A package.These values are either during transportation. Certain possission oflicensed maternal listed in Appendix A of this part. Table esclusions are provided in i 71.53. (d) Exemptions from the requirement A-1.or may be derived in accordance low specific activity materio/ means f:r hesnse in i 713 are specifie with the procedure prescribed in any of the,ollowing-f Appendix A of this part. (1) Uran um or thorium ores and l 7110. Generallicenses for wh no ph sical or chemical concentrates of. 3 Carrier means a person engaged in NRC package approvalis requi are issuid in i t 71.14-71.24. De ge the transportation of passengers or those cres, license in i 7112 requires that C property by land or water as a common. III,Unirradiated natural or depleted c rtificate of compliance or oth contract. or private carrier, or by civil uramum or unitradiated natural thorium; aircraft. (3) Tritium oside in aqueous solutions package approval be issued for provided the concentration does not pickage to be used under the general Close reficction by water means g esceed 5.0 millicuries er milliliter: license. Appl. cation for package immediate contact by water of sufficient g (4) Materialin whic the radioactivity approvat must be completed in thickness for masimum reflection og is essentially uniform! distributed and accordance with Subpart D of this part, neutrons. z* in which the estimate aserage. demonstrating that tha design of the Containment system means the package to be used satisf es the package components of the packaging intended

concentration per gram of contents does tppros al standards contained in to retain the radioactive matenal durms not exceed.

(i) 0.0001 millicurie of radionuclides Sul art E of this part as related to the transport. tests of Subpart F of this part.De Conveyance means any vehicle, for which the A quantityin Appendix A trent, ort of licensed material or aircraft, vessel fre:ght contamer, or of this part is not more than 0.05 curie; ddi..ry of licensed material to a carrier hold, compartment. or defined deck area (ii) o 005 millicurie of radionuclidts for for transport is subject to the operating of an inland wsterway craft or seagoing which the As quantity in Appendix A of usul b pan b mm than nos curk, but not controfs and procedures requirements of Esclusive use (also refernd to in more than 1 curie; or Subpart G of this part.to the quality assur:nce requirements of Subpart H of other regulations as " sole uu" or " full w{ili) 0.3 millicune of radionuclides for ch the A quantity in Appendix A of this part and to the general provisions load") means the sole use of a of Subpart A of this part. including DOT conveyance by a single consignor and - is part la mm than 1 cuna. regulataona referenced in i nA.

kol, (5) Objects of nonradioactive material a

a e a I 7'.1 Communecomens. out in accordance with the direction of extamany contaminated with All communications concerning the the consignor or consignee. radioactive material.,provided that the regul:tions in this part should be Assi/c c/cssification means ihe radioactive material is not readily addressed to the Director. Office of categonzation of fissile matenal

dispersible and the surface s Nuc!est Material Safety and Safeguards, g psekages into one of the following three
contamination, when averaged over an area of1 square meter. does not exceed f IJ S Nuclear Regulatory Commission.

$ c!ssses accordmg to the cont-ola needed m o 0001 millieurie (220.000 disintegratione ~ Washington.DC 20555. or may be to provide nuclear cnticahty safety a z duneg transportation: ' per m'nute) per square cantimeter of 2 2 dnivered in person at the Comrruulon NW' (1) Fissile Class I. A package which

radionuclides for whhh the As quantity

~ cflices at 1717 H Street'ofnces at 7 Tis Wa shmaton. DC. or its

may be transported in urdunited in Appendix A of Part 711s not more I

Eastern Avenue. Silver Spnng, nurnbers and in any arrangement. and than 0 05 curie, or 0.001 millicurie M ryland. which requires no nuclear cntacality (2.200.000 disintegrations per minute) safety controls during transportation. A per square centuneter for other

Integretations.

transport index is not assigned for _ radionuclides. j wntten interpretations of the purposes of nuclear cnticality safety but cions in this part by the may be required because of external Maximum normoloperatinspressure

mssion's General Counsel are radiation levels.

means the maximum gauge pressure that cmg upon the Commission. (2) Fissile Class II: A packrge which would develop in the containment may be transported together with other system in a period of cne year under the 1 71,3 Requirement for scenas. packages in any arrangement but, for beat tut specified In I n.71(c)(1). in the A licensee subject to the regulaticas enticahty control,in numbers which do absence of venting. extemal coolms by in this part may not (a) deliver any not exceed an aggregate transport index en anci!!ary system, or operational fiernsed matenal to a carrier for of 50. These shipments require no other controle dunna transport. trcnsport or (b) transport licensed nuclear criticahry safety control during Naturalthorium means thorium with material except as authorized in a transpo f ation. Indmdual packages may the naturally occurring distnbution of grnzrallicense or a speafic heense have a transport inden not less than 0.1 thorium isotopes (essentially 100 weight issued by the Commission, or as and not more than 10. 8 percent thonum-232). enempted in this part. (3) Fissite Clase 111. A shipment of j Normo / form indeocctive material packages which is controlled in means radioactive material which has t 71.4 Denmana. transportation by specific arrangements

not been demonstrated to qualify as Ths following terrns are se defined between the shipper and the carrier to

, "special form radioactive material." here for the purpose of this part. provide nuclear criticahty safety. Optimum interspersedbydrogenous Throughout this part, the standards are fissile materialand fissile moderation means the presence of espressed in metric units; the radionuclides:" Fissile ereterial" means bydrogenous material between packas approximate Er,glish equivalenq any materi,al consisting of or containing to such an extent that the maxirnum presinted in parentheses are foi one or more fissile radionuclides. Fissile nuclear reactivity resulta. information only. radionuclides are plutonium-238. Package means the packaging A, means the maximum activ i of plutonium 239. plutonium.241. uranium. together with its radioactive contents as speci:1 form radioactive matenal 233. and uranium-235. Neither natural presented for transport. p:rmitted in a Type A package. A, nor depleted uranium is finile material. (1) Fissile materio/pocAoge means a miens the ma ximum activity of Fissile materials are classified in this fissile material packaging together with raio:ctive material. other than special section awcording to the controis needed its fissile contenta. gust 31,1983 71 2

PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL (2) 7)pe SpacAage means a Type B Virgin talande. Cuam. American Samoa. (iv) Monitoring-49 CE Part 172. package together with its radioactive the trust Territory of the Pecific Istanda. Subpart C. (q contente On approval. e Type B and the Commonwealth of the Northem (v) Accident reporting--49 CFR Part ~ I package design is designated by NRC se Mariana Islanda. 171.15 and 171.16. B(U)unless the package has a maximum Transportindes means the (vi) Shipping papere-49 CFR Part 172. normal operating pressure of more than dimens;onfese number (rounded up to Subpart C. 700 kilopeseal (2001b/in') gauge or a the first decimal place) placed on the (2) The licensee shall also note DOT pressure relief device which would label of a package to designate the regulations pertaining to the fo!!ewmg allow the release of radioactive material degree of control to be exercised by the modes 5f transportation-90 the enviro.a.inent under the teste carrier during transportation. De (i) Rall-49 CG Part I?4. Subparta A-heilled in i 71.73 (h)pothetical transport inden le determined as D and K. ccident conditions). in which case it fo!!ows: (ii) Atr-49 CHt Part 178. Subparts A. !! receive a des!gnation B[M). B(U) (1) The namber expressms the D and M. fers to the need for unilateral approval maximum radiation level m milbrem per (iii) Vessel-49 Cm Part 176. Subparte ' of international shipments. B(M) refers hour at 1 meter from the external A-D and M. to the need for multilateral approval. eeface of the package. or (iv) Pubhc Highway-49 Cm Part 177. Here la no distinction made in how (2) For Fissile Cla ss il packages. the (b)If DOT regulations are not packages with these designations may number expressmg the maximum applicable to a shipment of hcensed De used m domestic transportation.To radiation levelin milhrem per hour at 1 matenal by rail, highwey. or water determine their disunction fo, meter from the external surface of the because the shipment or the international transportation. ese DCTT package or the number obtained by transportation of the shipment is not in regulations in 46 CR Part 173 A Type B dividmg 50 by the allowable number of interstate or foreign commerce. or to a package approved prior to September e, the packages which may be transported shipment of!icereed matenal by air 19s3. was designated ordy as Type 8. together as determined under i 71.59. because the shipment is not transported limitehona on its use are specified in whachever number le larger. in civil aircraft, the licensee shall l 71.13. Type A quantity means a quantity of conform to the standards and Pbdosing means the auembly of radioactive matenal. the aggregate requiremen's of the DOT specified in componente necenary to ensur, radioactivity of which does not exceed paragraph fe? -f this section to the same compliance with the packagmg As for special form radioactive matenal extent se if the shipment or requirements of this part. It may consist or Aa for normal form radioactive transportatior. were m mterstate or of one or more receptacles, absorbent material. where Ai and As are given in foreign commerce or in civil aircraft. A matenals. spacing structures. thermal Appendix A of this part or may be request for modification. waiver. or insulation. radiation shieldmg. and determmed by procedures described in exemption from thcee requiremente, and e e S devices for cooling or absorbmg S Appendix A of this part. h any notification referred to m those O

4 mechanical shocks ne vehicle. tie-4 T)pe B quantity means a quantity of 4 requiremente,must be filed with or e down system and auxiliary equipment radioactive material greater than a Type, made to the Director. Office of Nuclear e

me) be destgnated as part of the

A quantity.

Matenal Safety ar.d Safeguards. U.S. g packagmg Urenium-naturo!depletedenriched . Nuclear Regulatory Ccmmtesson. a i Specialform radioactive matenci . (1)Naturo1 uranium means uramum Washmston. DC 20555. means radioactive material which with the naturally occurnng dietnbution L satisfies the followmg condat2one. of uraniurn isotopes (approximately (1)It is either a omgle solid piece or la 0 711 weight percent uranium.235, and contained in a sealed capsule that can the remamder essentia!!y uranium.238). be opened only by destroytng the (2) Depleted uronium means uranium p g 75.s in,armatwn oosectwn

capsule, containing less uranium-235 than the reqWruments:0ess appreat (2) ne piece or capsule has at least naturally occurrma distnbution of one d:mension not fees than 5 uranium isotopes-(a) De Nuclear RegWatc,ry millirneters (0197 inch). and (3Mntiched uranium means uranium Commiss;on has submitted the (3)lt satisfies the test requiremente of containmg more uranium.235 than the information collection requiremente 6 71.75.

naturally occurnns distnbution of contained in this part to the O*fice of A special form encapsulation designed uranium isotopes. Management and Budget (OMB) for approval as required by the Paperwork m in accordance with the requirements of $ 71.5 Transportation of Rcensed matartel. 2 Reduction Act of19a0(44 U.SC 3501 et i 714(o) of this part in effect oo lune 30. (a) Each licensee who transporte ! seq ). OMB has approved the 1983 and constructed prior lo july 1. licensed material outside of the confines [ information collection requittiner.te ] 1985 may continue to be used A specsal ofits plant or other pIace of use, or who $ contained in this part under con'rol I form encapsulation either designed or dehvers licensed material to a carrier number 31ma i constructed after June 30.1945 must for transport. shall comp!) with the (b) The approved mformation meet requirements of this paragraph applicable requirements of the collection requiremente conta:ned in this applicable at the time of its dee.gn of regulations appropriate to the mode of part appear in il M.S. 71.12. 71.31. 71.33. ,ponstruction-transport of DOT in 49 CFR Parts 170 E 37, nes, ns?. n at n A e Specific activity of a redionuclide through 180

93. 71.95. n97. M.101. M 103, 71.105.

ano the radioactivity of the dionuchde per unit mass of that (1) The licensee shall particularly note 71.107. 71.100. 71.111. 71 113. 71.115. uclide He specific activity of a DOT regulations in the following areas. n117.411E ntn nu nm (i) pack aging-49 CFR Part 173. M.12t 7t.1MI. 71.131. n.133. 71.135. and "imatertalin which the radionuclide le Subparts A and B and il 173.401-II 137' # I essentially uniformly distributed is the 173 47s. i radioactivity per unit mass of the material. (ii) Marking and labeling-49 CFR f* O Part 172. Subpart D and il 172.400-l State means the several States of the 172.40t 172 436-172.440. Union, the District of Columbia, the Commonweahh of Puerto Rico, the (iii) Placarding-49 CFR Part 172.500-172 519.172.556 and Appendices B and C. j d 2 1 71 3 May 31,1984 toest Dage et rl.3a)

PART 71 O I KAOING AND TRANSPORTATION OF RADIOACTIVE MATERIAL Subpart B-EsempWens

p

$7t.7 speemsese 's On application of any interested person or on its own initiative, the Commissen may grant any exemption from the requirements of the regulations in this part that it determines is authorized by law and will not endanger life or property or the common defense and security. e 17t2 (Reserved) o

i 71.9 fsemption of physiciana, Any physicianlicensed by a State of a

i the United States to disper.se drugs in " the practice of medicine is exempt from I 71.5 with respect to transport by the physician oflicensed material for use la the practice of medicine. However, tny physictsn operating under this exereption must be licensed under 10 CFR Part 35. $ 71.10 Esereption for low levet materials. (a) A ficensee is exempt from all requirements of this part with respect to shipreent or carriage of a package containing radioactise materialhaving a specific activity not greater than 0.002 O I 71-3a Mey 31,1984 (resetf t

PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERfAL 1 mkrocorie/g-em. 3-(e} For p.eviously approved T3pa 3 C end H cf this part. (b) A bcensee is exernpt fro:n eB 3 padages which are not destgrated as (d) T1Js generallicense is s4fect to requirements cf this part, chr ha X either B(U) or S(M} iti the NFC the Lmitation that the specification. i s14 erd I n.88. with respect to z Certifi a'e of Coreplianc e. this general centainer may not be used foe e shipment or carriage of the following ' license is subject to the addnior.a! ahipment to a locarian outside the packages 7 restrictiorts of i 7113 Umted States after August 31,1986. (1) A package can'amir [ no mor,

- cept under specfal arrar.geraents than a Type A quactety od radioactive l 71.u Previovely approved Type s

$y material af the package et ttoine no pecupe. Assile matenal orif tbs fd nie matenal Ie) A Type a packare previately 6 7t* Geawu8 Ucorne uw et exemption standarda of t 153 ar'

- U*E'd 8' approsed t:3 the NEC but not asp oms poonesa.

des gasted as 8(U)cr E(M)in the NRC (e) A generalIcense is luned ts (2) A padage trensported betwee locationa withm the Uni'ed States whkh C,.tficate of Cornpl ance. may be used licensee of the Comrrission to tra under the generallicense of $ 71.12 with or to deber to. carr'er for trent cor.taina only americia. t.t plutonium te the fotowirg editiotal limitations; g hcersed metensiin a package tne special form with an aggr gate (1) Febecat.on of the packogmg wes design of whi:A has been appreved ir, a rsdgactivi'y not to exceed 20 cunes. L' sansfactonly comp'eted before August forep natictic! competent sathority g thepathage centains no fissile etsterial 31.1986 as demcnstrated by apphcatmn certincate wluch has been avvaldsted or u tne fissile materis! exemption ofits model number in accordance with ; by DOT as meetir+4 the oppucable standards of i 71.13 are nadafied. $ 7185fc), and requirements of 40 CMt 171.12. I H " @"***83 (2)The packsge may not be used for a (b) nie generall2cerse a shqmant to a location outside the sh4menta made to or frcm [v!ies on!y to ocatiosa "#I United States af ter Atgue 31.19e6. outade the U t:ted States. except under spec.ial ar angement (c) This general bcense opplies cdy to p$71.12 Gerwraf huonee.sf#capsmeg e.oprcsed by DOTi:i.secordance with 4g a licensee who-k- ectape CFR 1?3 471. (1) Has a copy of the applicabse (s) A generallicense is hereby issued (b) The NRC will approve certificate, the eevahdatior ar.d the to any beansee of the Commission to modications to the design and drawings and c6er documents transport, or 1o deliver to a carriet for authorized centents of a Type B package referenced in the cartificate relating to transpcrt. brensed materfelin a package preneus!) approeed by the NRC. but the use and memtenance of the for which a liceres, certdicate of ect des.g<.ated as B(U) or B;M)is the packaging and to the actions to be taken comphance, or cier app oval has been PGC Cert 4cate of Co:rpliance, g issued by the NRC. presided ' prior to shipment, and ~ N The moddications are not (2) Complies with the terma and ? (b) This geners! bcense applies cnly to y si nificant with respect to the design, ,, cor.ditiona of the certMeste and 6 a heensee who has a gus!Py anuranca cpe. sting charactenstica, or nfe g rnahdation end with the applicable program apprened by the Cocmismic'c g as sat:sf>ing the pesisicna cf SubpartH,f perferrnance cf the con:ainment e) stem A requirementa of Subparts A.C and H of . of this part. wher, the package is adjected to the , th;s part. With terpect to the quality

tests specded n 117171 end 71.73 and w assure ce provisions of Subpart H of (c) 71us sentralheecse appDes only to (2) The modificatton to the package

. this part. the licer.see is enerept from a bcensee who, satisnes the requirements of this part. I dnign. construction, and fabncation s (1) Has e cepy of the specific license. (c) The NRC =il! reWse the pecaege Lconsideratior.o. certificate of comphance, cr other identScation namber to designate approsal of the peekage and hae the previously approsed Type Bpchage g yg,3g g,n.,,, g,,n,, y,, g, pi,,g, ~ y d awir.gs and o'.her docwnenta designs as BlU) or BiM) after recent of ciees a p.eetage, teferenced in the approval relatfrq to an atpScat;cn derr.orst<atirs that the (a) A geners!!icense la lesved to any the use and tr.eintenance of the des:gn eneets the requirements of this licensee of the Comminion to transport packer:ng and to the actions to be fd en p*"- fissi)e ma'etial.or to deliver fleeile prior to shipment: $7tMe Generaf ucense poispeerr,caton caterial to a carrier for transport. (2) Comp?ies with the terms and conininar, withont comptying with the package conditiene cf the !!cer.se cert &cate, or (e) A genera!I; cense is tssued to any standards of Sdparts E and F of this ether opprovel, as applicable. and the licensee of tte Comrriss;en to transport part if the materialie shipped as a appbcab!eicqdrements of Sebparts A. ce to deliver to a carrier for transport Fi G. and H of this prt; and hcensed tr.ateria!in e specification ! stile Class U package-(b)nie general beacse opplies only (3) Submiu in writing to the Direc: tor, centair.er for fin:le rnater;al or for a $ when a package centains no more than Office of Nuefeat Meterial Safety sad Type B quanti *y of redicectise mater:al e a Type A quantity of radioactive Safer.ards. U S. Nudear Regulatory as specief in the regdations of DOT in ' material.anclud ng on! one of the f Comrniuion. Washirg'on. DC 20555. 49 CFR Par's 173 and 178. 3 foIfowmg. price to the ficenne's first use of the (b) Th's geecral hcense applies or.ly to pack ege, the hcensee,e name and lic.ense a I censee whc has a quahiy assuranca (1) Up to 40 grams of uraniuri-234; oc currher a.d the path a.ge ide<itification program ap; roved by the Comtnission gp g ,gg p nurnter specWedin the package as satn.fying the provis.sce of Supart H W Up m 23 grams 5f thdsaGa -

approval, of this st.

radionn! ides of pftatonium, except (d) This geteral licer.s e applies only (c) > is generat hcense app!ies only to for encapsu!sted piutonium-bery!); when the pact age approvelauthorizes " l'8"'" who: neutron sources in sWah na 4 ) use of the package under t)(s general (1) Has a copy of the specification: gr. entity of p!utoalura may be presset: or !icecas, and j (4) A combination of Eu0e (2) Ccmptes witt the terme and isdionuclides in which the sus of the con 6tions of the specification end the ution sithe amount of each applicabte requ.sements cf Sdparts A. radienaclide to the corresponding August 21,1983 73 4 l

PART71 o PACKACING AND TRANSPORTATION OF RADIOACTIVE MATERIAL maximum enounts in p., _i (b)(1), peckaging) the maximum enouest of -l71Jt Generalscense; Type A pochese, (2), s':d (3) of this sect 6on dose not uranium-235 per package may not Roene cases si eNpment, exceed the value given in Table D of this (a) A generallicense le leeued to any % exceed unity, , part and. licensee of the Comminion to transport a L l (7)The transport index of each Assile material, or to dehver fissile (c)his generallicense applies only W package beoed on criticality meterial to a carrier for transport, Ewhen.except as specified below lor consideretions is taken as 10 times the without complying with the packege a y escapsulated plutonium-beryllium number of grams of uranium 235 in the standards of Subparts E and F of tbs k 3I sources, a package containing more than y package divided by the maximum part iflimited material is shipped as a 18 Fems of Assue radionuclides le allowable number of greme per package Fissile Class m shipment labeled with a transport index mot less in accordance with Table I or Table B of (b)His general beense appSes on!> h p than the number given by the foBowies _,this part as applicable. when a package contains ne rnore than equation, where the package contains x a Type A quantity of re&c,s:m yeme of uranium-238. y peas of material and no more than 400 p a ts total of the fissile radionuchden of arenlum 233 and a greme of the SeeDe radionuclides of plutonium: p!utonium encapsu!ateo ae ph:tomum-Minimum Transport ledex = (0.40s + 0 67y + )(1 ,,"F,, beryllium neutron aources in speual ). form-(c) This generallicense apphe, only ~For a package in which the only fleelle when the fissile re&onuchdes in the materialis in the form of encapsulated Fissile Class III shipmot exceeds none plutonium beryllium neutron sources in of the following: j special form, the transport index ba sed l en criticality considerations may be (1) 500 grams of urani ac.235. or taken as 0.026 times the number of (2) 300 greme total of uramam 233. grams of the fissile radionuclides of and the fissile re&onuchdes of plutonium in exceu of 15 grams In all plutonium; or l cases, the transport index must be (3) A total quantity of uranium 233. rounded up to one decimalpiece, and uranium-235, and the fissile may not exceed 10A radionuclides of plutonium such that the 57120 Generet scense: Restrteted, Pleste ~TAeLa t.-Pseemstets Mass ce Umuusivu 235 sum of the retics of the quantity of each CIses N package, paa Feen.E class N PAcnAos AppucAeta radionuclide to the quantit) speci$ed in (e) A general!! cense is issued to any fog? W M paragra# (cW and (cM o% 'h'

,#'g gng, licensee of the Commission to trenoport l**'***" *=8ma=3 J

7 l fissile material, or to deliver fissile 3 radionuclides of plutonium encapsulated w -,, meterial to e carrier for transport, g ewu ,, _ W,,e',,, " es without complying with the package g g, plutonium beryhium neutror sources eg,; go,,, standards of Subparts E and F of this o' [ This generallic*nse applies only i rt if the materialis shi gseue Class ilpackage.pped as a "a ' when shipment of ther packagee is l made under procedures spe:ifi: ally n This generallicense applies only 13 y authorized by DOT in eccordance with i i e na 49 CHL Part 173 of its regulations to u (1)De Peckage contains no more as es prevent loading. transport or storage of then a Type A quantity of radioactive !s these packages with other Fissile Class a a ! meterial;and ? !! packages or F ssile Clan m (2) Neither bery!!!um nor hydrogenoes I f E shipments. 3 materf al enriched in deuterium is 3 as se present and e es (3) The total mass of graphite present f f E Utta knw scenuAutr,cted,muHe does not exceed 150 times the total mass as as mu m shW of uranium-235 plus plutonium; and I e a (4) Substances having a higher p (a) A generallicense is issued to any = licensee of the Commisnon to transport hydrogen density than water.e.g., is m certain hydrocarbon oils, are not "o no fissile material. or to deh er fissue present, except that polyethylene may b un"o material to a carrier for transport. 8 with ut complyirg with tte rockage be used for packing or wrapping: and (5) Uranium-233 is not present, and standards of Subparts E and F of this the amount of plutonium does not TARE u Ptanosseta Mass or Ummuu. part iflimited materialis shred as a exceed 1% of the amount of utent.m-235; 235 pan Fisssts class u PAcnAos AppucA-Fissile Class !!! shipment and e6a to 9 71Jo@McMu) (b)This general hcense appbs only when-(6) The amount of uranium 235 is t**'= *=' ham'4 hmited as foUows: (1) No packese contains rvre than a y u be maximum g t I ed sh e d..a e cecing 5 te the laT I of as e na sun in thickness. tungsten sNelding or this part ce (ii)If the flesile radionuclides are a f g aren!um shielding: and (3) Neither berythum nor h> drogenous distributed uniformly (i.e., cannot form a "sms s'e"s material enriched in deutenum is lattice arrangement within the present and l 71 5 Agust 31,1983

PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL (4) The total mese of graphite present ' Tasta ut -Psaurssa.a Mass or usiAmuw (b) Except as provided in 171.13 an does not exceed 130 times the total mass 235 Pen Fissu.a CLAsa fit Swerweirr Apri.F-application for modification of a of uranium.235 and plutonium: and cAad to I 71.2a(bH6Xi) package design, whether for (5) Substances having a hisber tw.w modification of the packaging ae hydrogen density than water, ag, authorized contents, must include certain hydrocarbon oils, aec not j,% Q y _ y g** sufficient information to demontrate present. except that polyetylene may that the proposed design satisfies the ne== - be used for packing or wrapping and package standards in effect at the time (6) For fissile contents cghtsining no g g the application la filed. uranium-233 and less thanf total si eso i2 plutordum. g I 71.33 Peekage descripeast 4 (1)If the fissile radionuc!! des are not e en The application must include a uniformly distributed, the maximum 8,s description of the proposed package he ano amount of uranium-235 per consignment sufficient detail to identify the package u rso does not exceed the value given in Table ? Foo accurately and provide a sufficient basis III of this part ce y f evaluation of the package.The (ii)If the fissile radionuclides are u sao description must include: distnbuted uniformly and cannot form a 4 (a) With respect to the packaging: u lattke arrangement within the a uno S (1) Classification as Type B(U). Type packaging, the maximum amount of 8,8 g A B(M) or fissile materialpackagmg-uranium-235 per shipment does not I u i son 2 (2) Cross weight exceed the value gfven in Table IV of a toeo (3) Model number; this part and ,',s, g

(4) Identification of the containment l

(7) For fissile contents containing i uoo system: 1, utenlum 233 or more than 14 plutonium. (5) Specific materials of construction, j the total mass of fissite materialper weights, dimensions. and fabrication

shipment is limited so that the sum of Tas6.a N.-Pf auiss.a6.E Mass or UnaNiuM-methods of; the number of grams of uranium-235 235 Ptn Fissrts CLAsa ni S,uputwT Arru-(i) Receptacles

$ divided by 400, the nuznber of grama of casa to I 71.2a(bH6Xs) (ii) Materials specifically used as , plutonium divided by 225. and the tw e nonfissile neutron absorbers or i ' number of grams of uranium-233 divided moderators; by 250 does not exceed unity as expressed in the formula T"[w,T,,4 T_yg= (iii) Internal and external structures

==<==am ar=r.we supporting or protecting receptacles: (iv) Valves, sampling porta, lifting a y devices, and tie <fown devicts: E m va*v= 225. t= = W oww=. i.so (v) Structural and mechanical means " 8'""

- - 8"**

y g for the transfer and dissipation of heat u uso _a nc' swes uranium 2ss, us iO ooo p 250 ersms 3 to (8) The transport must be direct to the (6) Identification and volumes of any consignee without any mtermediate 2 receptacles containing coolant. w transit storage; and = (9) Shipment of these packages is I-I made under procedures specifically ~Subpart D-Application for Package authorized by DOT in accordance with Approval (b) With respect to the contents of the ~ 49 CFR Part 173 ofits regulations to package: present loadirg. transport or storage of (1) Identification and maximum these packages with other Fissile Class e I#' 8' C*""te of appncanon-radioactivity of radioactive constituenta; 11 packages or Fissile Class 111 $ (a) An application for en approval (2) Identification and maximum shipmenta.

under this part must include, for each quantities of fissile constituents:

g prepesed packaging design, the (3) Chemical and physical fortn: fo!!owing information: (4) Extent of reflection, the amount I (1) A package description as required and identity of nordissile materials used by I 71.33; as neutron absorbers or moderators, and (2) A package esaluation as required the atomic ratio of moderator to fissile _by I 71.35; $ constituents: g 4 (5) Maximum normal operating [ e pressure: (6) Maximum weight: w (3) A quality assurance program I ""I7) Maximum amount of decay beati l d description as required by I 71.37; 2 (8) Identification and volumes of amh coolanta. I j S 71.35 Package evefwattorL The application must include ~ (4)In the case of fissile material, an (a) A demonstration that the package identification of the proposed fissile satisfies the standards specified in cla ss. Subparts E and F of this part: August 31,1983 71 6

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL (b) For a Fissile Class Il package, the iM.43 Gewalstandardaseeas (1)If there la a eystem of tie.down Packages

devices which is a structrual part of the allowable number of packsges which may be transported in the same vehicle (a)Re smallest overall dimension of paclage, the system mul be capable of O

in accordance with 5 71.59; and a package must not be less than 10 aos withstanding. without generating stress (c) For a Fissile Class III shipment. (four in.). In any material of the package in excess any proposed special controls and (b) he outside of a package must ofits yield strength, a static force precautions for transport. loading. Incorporate a featum. such as a seal. 3 applied to the center of gravity of the unloading. and handling, and any which le not readily bmakable, and g package having a vertical component of proposed special controle in the event of which. while intact, would be evidonos a two times the weight of the package accident or delay. that the packege ha6 not been opened a with its contents, a horizontal l by unauthorized persona.

component along the direction in which 971J7 Ovatity ass.iranas, (c) Each package must include a

the vehicle travels of to times the we!ght (a)he cpplicant sha!! describe the quality assurance program (see Subpart cont *!nment systern ucaly closed by of the package withits contents,and a.

a p sitive fastening device which cannot hcrizontal component in the transverse H of this part) for the design, be opened unintentionally. direction of five timu the weight of the fabrication, assembly, testing. (d) A package roust be of materials package with its contents. j maintenance repair, modification.and and construction which assure that we of the proposed package. there will be no significant chemical. p (2) Any other structural part of the (b)he applicant aballidentniy any galvanic. r ther maction among the

package which could be used to tie established codes and standards packa8 na e mponents or between the down the package must be capable of i

proposed for un in package desism p.ekaging components and the package " bhing rendered inoperable for tying fabrication. assembly, testas. f down the Package during transport. or ^8 " ' "* C " NSultin8 T m 18188f88' I**1'TI and use In the absence of maintenance'd standards, the applicant I th* must be designed with strength 4 any codes an ma mum cM "tu 3 equivalut to eat mquimd fw hwn shall describe the basis and rationale (e) A package valve or other device. (devic,s. used to formulate the Pachase 9vality the failure of which would allow Nohallidentify any g[ns u$M " (3) Each tie.down device which is a (c ap pr t te specific provisions of the quality operation and, except for a pressure structuralpart of a package must be issurance program which are applicable relief device, must be provided with an designed so that failure of the device under excessive load would not impair to the particular package design under enclosure to retain any leakage. consideration. including a description of (f) A package must be designed, the ability of the chage to meet other the leak tuting proceduma. constructed. and prepared for shipment mquimmuts of s part. I 71.se Requirement for ampuanas so that under the teste specified in 37M7 Entwned rasseen standarea ter as g uformonen. i n.71 (Normal Conditions of pace 6 ages. y C De Commission may at any time 3 Transport) there would be no lose or A packs e must be des ed and " mquire additionalinformationin order a djspersal of radioactive contents no prepared f r shipment so at the g to enable it to determine whether a sigmficant increa se in external radiation radiation level does not exceed 200 e-levels, and no substantial reduction in millirem per hour at any point on the , licerwe. certificate of compliance,or the effectiveness of the packaging. external surface of the package and the , other approval should be granted. g denied. modified. suspended, or (g) A package must be designed, transport index does not exceed to (See revoked. constructed, and prepared for transport g 734 Definitions"). For a package so that in still air at 38*C (100*F) and in transported as exclusive use by rail. Subpart E-Package Approval the shade, no accessible surface of a 8 highway, or water. rediationlevels Standard

package would have a temperature external to the package may exceed m

ut must not neeed any M I " **"'**P"****- e clus e u e hipme t or C (180*F) "g (a)De effects on a package of the in an exclusive use shipment. '. (a) 200 millimm/ hour on the tests specified in i n 71(Normal Conditions of Transport) and the tests fehre h beINede to al Package unless the following conditions specified in i n.73 (Hypothetical cutinuous vnting during transpon. are met. in which case the limit le 1000 Accident Conditions) must be evaluated millirem per hour-by subjecting a sample package or scale i 71.45 Lifting and tiewsown stendards for model to test or by other method of as pachgoes (1)De shipment is made in a closed demonstration acceptable to the (a) Any lifting attachment that is a transport vehlde: Commission, as apprcpriate for the structural part of a package must be (2) Prcvisions are made to secure the particular feature being considered. designed with a minimum safety factor package so that its position within the (b) Taking into account the type of of three against yielding when used to vehicle remains fixed during vehicle, the method of securing or lift the package in the intended manner, transponstion; arm attaching the package, and the controls and must be designed so that failure of (3)Here are no loading or unloading to be exercised by the shipper.the any lifting device under excessive load operations between the beginning and Commission may permit the shipment to would not impair the ability of the end of the transportation; be evaluated together with the package to meet other requirements of (b) 200 millirem / hour at any point on transporting vehide. this sut,part. Any other structural part of the outer surface of the vehicle. (c) Environmental and test conditions the package which could be used to lift including the upper and lower surfaces, different from those specified in i n.n the package must be capable of being or. in the case of an open vehicle, at any and i M.n may be approved oy the rendered inoperable for lifting the point on the vertical planes projected Commission if the controle proposed to package during transport or must be from the outer edges of the vehicle, on be exercised by the shipper are designed with strength equivalent to the upper surface of the load, and on the Iower external surface of the vehicle: O demonstrated to be adequate to assure that required for lifting attachments. the safety of the shipment. (b) Tie-down devices: (c]10 millirem / hour at any point two 9 71-7 August 31,1983 i

PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE M ATERIAL meters from the vertical planes hydrogenous solutions or mixtures (1) The most reactive credible represented by the outer lateral surfaces whers: configuration consistent with the cf the schicle, or,in the case of an open (1) The minimum ratio of the number chemical and ph sical form of the 3 vehicle, at any point two meters frorn of hydrogen atoms to the number of material; the vertical planes projected from the atoms of fissile radionuchdes(H/X)la (2) Moderation by water to the most outer edges of the conveyance; and $200: reactive cred:ble extent; and (d) Two mi!!irem/ hour la any (2) ne ma ximum concentration of , Z Close reflection by water on all normally occupied position' of the fissile radionuclides is five grams /litar. sidea. s vehicle. except that this prairision does and (c)He Commission may approve not apply to private motor carriers when (3) ne maximum mass of fissile exceptions to the requirements of u persons occupying these pcisitions are radionuclides in the packese is 800 paragraph (b) of this section if the / prosided with special health grams. except for a mixture where the package incorporates special design ". supervision, personnel radiation total mass of plutonium and uranium-233 features that ensure that no single 4 exposure monituring devices, and exceeds one percent of the mass of packaging error would permit leakasei training in accordance with l Ig.12 of uranium-235 the hmit is 500 grams. If the and if appropriate measures are taken Cis chapter. material is transported in bulk. the before each shipment to ensure the quantity hmitations apply to the vehicle, containment system does not leak. I 71.5 t usmonal requirements for Type a packag m to a hold or compartment of an inland (d) A package used for the shipment waterway craft, or to a hold, of fissile material must be so designed (s) A Type B package. In addition to compartment, or defined deck area of a and constructed and its contenta so satisfying the requirements of Il 71.41-seagoing vessel; or limited that under the testa specified in 71.47 must be designed. constructed, and (d) A package containing uranium 471.71 (Normal Conditions of prepared for shipment so that under the enriched in uranium-235 to a reeximum Transport): tests specified in: of one percent by weight, and with a (1) The contents would be subcritical; (1) Section M.n (Normal Conditions total plutonium and uranium-233 content (2) The geometric form of the package of Transport), there would be no loss or of up to one percent of the mass of contents would not be substantially dispersa! of radioactive contents, as uranium 235. if the fissile radionuclides alters & demonstrated to a sensitivity of10' A. are distnbuted homogeneously (3) There would be no leakage of per hour, no signific. ant increase in throughout the package centents and do water into the containment system cxternal radiation levels, and no not form a lattice arrangement within unless. in the evaluation of undamaged substantial reduction in the the package; or packages under ll71.57(a). M.59(b)(1), effectiveness of the packaging: and (e) A package containing any fissile and n.61(a). it has been assumed that (2) Section 71.n (Hypothetacal materialifit does not contain more then moderation is present to such an extent Accident Cond tions), there would be no five grams of fissile radionuclides in any as to cause maximum reactivity u escape of kryption-45 exceeding 10.000 10-liter volurne, and if the materialis consistent with the chemical and e 3 curies in one week.no escape of other 3 packaged so as to maintain this limit of 3 physical form of the material; and o 2 radioactive material exceedmg a total A fissile radionuclide concentration during 4 (4) nere will be no substantial e amount A. in one week. and no external e normal transport;or reduction in the effectiveness of the e ' radiation dose rate exceeding one tem (f) A package containing not more packaging,includm' g-w g per hour at one meter from the external i than one kilogram of plutonium of which (i) No more than five percent surface of the package. not more than 20% by mass may consist reduction in the total effective volume of (b) Compliance with the permitted of plutonium 239 plutonium-241. or any the packaging en which nuclear safety la i I retivity release limits of paragraph (a) of combination of those radionuclides; or assessed this section must not depend upon filters (8) A package containingliquid (ii) No more than five percent or upon a mechanical cooling system. solutions of uranyl nitrate enriched in reduction in the effective spacing uranium-235 to a maximum of two between the fissile contents and the 17t.52 Esemption for low specmc acMy M P****8" percent by weight. with total plutonium outer surface of the packaging: and and uranium 233 not trore than one. (iii) No occurrence of an aperture in A package need not satisfy the tenth percent of the mass of uranium. the outer surface of the packaging large requirementa of I 71.51 if it contains 235. only low specific activity material and is enough to permit the entry of a 10 cm (four in.) cube. transported as exclusive use. but la 171.55 Cenerairequirements for as naase subject to ll 7141-71.47 of this part. materlat packages, (e) A paczage used for the shipment of fissile material must be 80 designed and includmg i n.43(f). (a) A package used for the shipment constructed and its contents so limited of fissile material must be designed and that under the tests specified in i 71.73 ( l71.53 Flasile matertal esemptions. constructed in accordance with (Hypothetical Accident Conditions). the ne fo!!owing packages are exempt il 71.41-71.47. When required by the package would be subcritical. For this from fissile material classification and total amount of radioactive material, a determination. It must be assumed that: from the fissile materiel standards of package used for the shipment of fissile (1)ne fissile materialis in the most il 71.5Mt.81, but are subject to all material must also be designed and reactive credible configuration sther requirements of this part: constructed in accordance with 171.51. consistent with the damaged condition (a) A package containing not more (b) Except as provided in paragraph of the package and the chemical and than 15 grams of fissile radionuclides. If (c) of this section, a package used for the physical form of the contents; I materialis transported in bulk. the shipment ofi ssile material must be so (2) Water moderation occurs to the ' quantity limitation applies to the designed and constructed and its most reactive credible extent consistakt conveyance; or contents so limited that it would be with the damaged condition of the 2 (b) A package containing feradiated suberiticalif water were to leak into the package and the chemical and physical n:tural or depleted uranium lncluding containment system or liquid contente form of the contents; and l the products ofirradiation if the were to leak out of the containment (3) nere is reflection by water on all irradiation has taken place only in a system so that, under the following sides, as close as is consistent with the thirmal reactor: or conditions. maximum reactivity of the damaged condition of the package. (c) A package containing homogenous fissile material would be attained: August 31,1983 71 8

,f PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL g 71.37 specmc standards for a PlesAs exceed 10 and must be rounded up to Subpad FCT a.d Special Form Class Ipeekage. the first decimal place. Testa' ' - O, A Fissile Class I package must be so I?ut enormaieendmene et wennom designed and constructed and its p ol EvduHin d M $y"num g g 7tsi speems standares ser e Finnes packay design under normal cond2tions packages would be subcri ' inany cues m empment. of wanspy must include a I a eHec arrangement and with optimum A packese for Fissile Class !!! ""g"a interopersed hydrogenous moderation shipment must be so designed and ed M uc Sepamw unless there is ter amount of constructed and its contents so hmited. opecimens may be esed for the tree drop lateropersed tion in the and the number of packages in a Fissile test, the compression test. and the packaging.in which case the ter Class 111 shipment must be so hmited, penetration test if each specimen is amount may be assumed for that-subjected to the water sprey test before dekraination; and (a) Twice this number of undamaged being subjected to any of the other tests (b)Two hundred fifty (250) packman, packsges would be subcriticalif stecked (b) /nitic/ conditions. With respect to lleach package were subjected to the together in any arrangement, assuming the initial conditions for the tests in this tests specified in i 71.73 (Hypothetical close reflection on all sides of the stack section. the demonstration of Accident Conditions), would be by water: and compliance with the requirements of this subcriticalif stacked together in any (b)This number of packages would be Part must be based on the ambient arrangement, closely renected on all sides of the stack by water, and with subenticalif stacked together in any temperature precedmg and following the opumum intmpmed hdmgenous arrangement, closely reflected on all tests remaining constant at that value sides of the stack by water, and with between -25*C (-20*F) and + 38*C optimum interspersed hydrogenous (1erF) which is most unfavorable for etum du consid e on The 9 71.se specmc standards for a Please moderation. Except as permitted under I'g Clees Il peekage. g 71.41. each package must be containment system must be considered (a) A Fassile Class H package must be considered to have been subjected to to be the maximum normal operating controlled by the carrier during the tuts specified in i 71.73 pmm unlm a Iown inkrnal transport. To provide this control, the (Hypothetical Accident Conditions). pressure consistent with the ambient designer of a Fissile Class D package must deternune the allowable number of g ytes g,,egimquimm.ni,ser temperature considered to precede and peuterwum anspmente, follow the tests is more unfavorable. packages of that design which can be (c) Conditions and tests. (1) Nect. An safely transported in a vehicle under the (e) Plutonium in excess of 20 curies ambient temperature of 38'C (100*F)in conditions specified in this section.This per package must be shipped as a solid. j still air, and insolation according to the y g allowable number of packages 3 (b) Plutonium in exceu of 20 curies e following table: i i i ; determines the minimum transport index 4 per packese must be packaged in a hesotanodata which the shipper of the packese marks separate inner container placed within a " on the package label when the package outer packaging that meets the . le shipped. By limiting to 50 the total

requirements of Subparts E and F for e,,,,,,,e,,,,,,,,,

w

u~

' number of transport indexes in a vehicle packaging of matenalin normal form. If t er storage area, the carrier provides the entire packese is subjected to the i I adequate criticality control. tests specified in i 71.71 (Normal

",",',',"8"""'r j

(b) A Fissile Class H package must be Conditions of Transport). the separete -cr. oc ene designed and constructed and its inner container must not release

""" * **s reamer - suo

~ contents solimited and the alloweble plutonium, as demonstrated to a 1 number of these packages in a Fissile sensitivity of10-' A. per hour. If the l Class U shipment so determined, that: entire package is subjected to the tests (2) Cold. An ambient temperature of (1) Five times the elloweblet number of specified in i 71.73 (Hypothetical -40*C (-40 F)in still air and shade. undamaged packages would be Accident Conditions). the separate inner N ""#'*#""#I ## * * ^^ exim a mum of 24 5 kuopescal(3.5 subcriticalif atacked togetherin any container must restrict the loss of ps oo arrangement and closely reflected on all plutonium to not more than A,in one

4) ncrw se externolpressure An sides of the stack by water: and week. Solid plutonium in the following external ressure of140 kilepascal(20 (2)Twice the allow.able number of forms is exempt from the requirements pM) obso uu.

packages. if each package were of this paragraph: (5) Vibration. Vibration normally subjected to the tests specified in i 71.73 (1) Reactor fuel elements; incident to transport. (Hypothetical Accident Conditions). (2) Metal or metal alloy: and (6) Water sproy. A water spray that Ir atefy r e n (t oi per hour th te[r s on d e i es should Pp de of c ae optimum, interspersed fydrogenous be exempt ficm the requirements of this r at s (7)F e drop. Be een 1% and 2% moderation. section. hours after the conclusion of the water (c) The transport index with respect to l7t65 Additional requirementa. spray test. a free drop through the criticality control for each Fissile Class E packese must be calculated by The Commission may, by rule, distance specified below onto e flat. essentiall yielding. horizontal dividing the number 50 by the allowable regulation. or order, impose surface. the surface in a positior number of Fissile Class H packages requirements upon any licensee in, ,xp,c,ed For Fissile Class 5 packages. fee which miaximum alemage le which may be transported together as addition to those established in this part determined under the limitations of as it deems necessary or appropriate to his free drop must be preceded by a paragraph (b)of this section.The prctect health or to minimize danger'to transport index so determined must not life or property. N seen.re corneined us s@en r. 73,9 August 31,1983 4 _.,.,nn . ~ -, .--,--..,.n, .. - +, ~, -, ,,,m., ,_--,.---n

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL Gree dmp droe a height of 0.3 m (ane ft.) unfavorable for the feature under (a) Evaluation of the contents of a en each comer oe. in the case of a consideration ne initialinternal single package for qualification as cyffndrical Pinue Clus D ekage,seco pressure within the containmeht system special form must include a nach of the quarters of en rias. must be the maximum normal operstm, g determination of the effect ce a pressure unless a lower intemal , specimen of those contents of the teste OuTsmna eca Fass Dnor TasT (wesawr/ pressure consistent with the ambient 3 specified in i 71.77. Osvassus temperature assumed to precede and 2 (1) Specimens (solid radioactive fo!!aw the tests is more unfavorable. material or capsules) to be tested must i ***u8' (c) Tests. Tests for hypothetical - E be as norma *ly prepared for loading in a l assy e en samme

==

accident conditions must be conducted . single package, with the redloactive i as follows:

material dupbcated as closely as E @,,7, Q,,,,,

y 2 (1) Free Drop. A free drop of the practicable. wase e a sse-as aso m maest as e specimen through a distance of nine m (2) A different specimen may be need ". = issmo. om m as 89 (30 ft) onto a flat, essentially unyielding. ~for each of the testa. horizontal surface. striking the surface in a position for which maximum 7 (a) Cornardv A frw drop onto each damage is expected. cornar of the package in succession. oc (2) Puncture. A free drop of the g (b)ne specimen must not break or in the case of a cylindrical package onto specimen through a distance of one m , shatter when subjected to the impact. each quarter of each rim. from a height (40 in)in a position for which maximum a percussion.or bending testa. of OL3 m (one fL) onto a flat essentially damage is expected, onto the upper end unyielding. borizontal surface. His test of a solid, vertical, cylindrical, mild steel { applies only to fiberboard or wood bar mounted on an essentially rectangular packages not exceeding so unyielding. horizontal surface. ne bar f kg (110 pounds) and fiberboard or wood must be 15 cm (six in) in diameter, with 3 cylindrical packages not exceeding 100 the top horizontal and its edge rounded kg (220 pounds). to a radius of not more than six mm (% edij} e k'n u' s o me (9) Compression. For packages in) and of a length as to cause maximum p te w weighing up to 5000 kg. the package damage to the package, but not less than must be subjected. for a period of 24 20 cm (eight in) long. De long axis of L hours, to a compressive load applied the bar must be vertical. un!formly to the top and bottom of the (3) Thermal Exposure of the whole (d) After each test. leak tightness or package in the position in which the specimen for not less than ;so minutes to indispersibility of.he specimes must be package would normally be transported. a heat flux not less tuan that of a determined by e method no 16.a J De compressive load must be the 8 radiation environment of 800*C(14759 sensitive the, the fallowing leaching

with an emissivity coefficient of at least assessment proct:1ere. For a capsule g greater of the following-g 0.9. For purposes of calculation. the W resistant to corrosion by water, and f we(1)De equivalent of five times the? surface absorptivity must be either that a which has an internal void volume ight of the package: or value which the package may be

" 3reater than 0.1 milliliters, an alternative (ii) De equivalent of 12.75 kilopascal ,,-- expected to possess if exposed to a fire f to the teaching assessment is a " (1.851b/in') multiplied by the vertically projected area of the package. or 0.8. whichever is greater. In addition., demonstration ofleak. tightness of10-* (10) Penetfetion. Impact of the when sigmficant, convective heat input

torr.1/s (1.3x 10-* stm cm8/s) (based on hemispherical end of a vertical steel must be included on the basis of still-air at 25'C and one atmosphere cylinder of 3.2 cm (1% in) diameter and ambient air at 800*C (1475'F). Artificial differential pressure) for solid six kg (13 lb) mass dropped from a cooling must not be applied after radioactive contert. or 10 torr.1/s height of one m (40 in) onto the exposed cessation of external heat mput and any (3.3 x to-e tm cm'/s) for liquid or a

surface of the package whichis combustion of materials of construction expected to be most vulnerable to must be alle.wed to proceed untilit

gaseous radioactive content.

puncture. ne long axis of the cylinder terminates naturally.ne effects of solar (1) De specimen must be immersed must be perpendicular to the package radiation may be neglected prior to, for seven days in water at ambient surface. during and fo!!owing the test. temperature. De water must have a pH (4)Immmion-fissile material. For of 6-8 and a maximum conductivity of $ 71.73 Ptypothetical eccklent conditions, fissile nateriel,in those cases where 10 pmho/cm at 20*C (88'F). (a) Testprocedures. Evaluation for. wsten n!eakage has not been assumed Encapsulated material is not subject to bypothetical accident conditions is to be for criticality analysis, the specimen the seven. day requirement, based on sequential application of the must be immersed under a head of (2) ne water with specimen must tests specified in this section. in the water of at least 0.9 m (three It) for a g then be heated to a temperature of order indicated, to determine their period of not less than eight bours and - 3 50*tS*C (122*19'F) and maintained at cumulative effect on a package or array in the attitude for which maximum " this temperature for four hours. of packages. An undarcaged specimen leakage is expected. (3)De activity of the water must be m must be used for the water immersion (5) Immersion-cl/pacAages. A ' determined at that time. test specified in paragraph (c)(5) of this separate, undamaged specimen must be (4)De specimen must then be stored section. subjected to water pressure equivalent for at least seven days in still air of (b) Test conditions. With respect to to immersion under a head of water of humittity not less than 90% and a the initial conditions for the tests, at least 15 m (50 ft) for a period of not temperature not less than 30*C (88*F). except for the water immersion testa, to less than eight hours. For test purposes. (5) ne specimen must then be demonstrate compilance with the an external pressure of water of147 f.mmeysed in water having a pH of 6-4 requirements of this part during testing. kilopucal (21 psi) ga uge is considered and a maximum conductivity of to the ambient air temperature before and to meet these conditions. pmho/cm at 20*C and the water with after the teste must remain constant at specimen heated to 50* 5*C (122* 29*F) that value between -29'C (-207) and i M.78 OncMeason of special fenn and maintained at this temperature for + 38'C (100*F) which is most #'**"rn mamist. four hours. l August 31,1983 71 10 l l

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL le)ne activity of the water meet be qunhty assurance requirements of i (3) For Sosite material, any moderator deteresined at that time. Subpart H of this part, and with the I or neutron absorber. if required. le (7)The activities determined la general provisions of Subpart A of this 8 present and in proper condition; paragraphs (c)(3) and (c)(e) of this part. 3 (h) Any structural part of the package " which could be used to lift or tie down section must not exceed 0.05 pCL i 71.83 Asawmptione as to unknown ' the package during transport is rendend a 9 71.FF Tests for apeelal term radeessse P'#P8'888-

inoperable for that purpose unlesa it

[ satisfies the design requirements of snesortal. When the isotopic abundance, mass. (a)Impoet test he speciesen must concentration. degree of irradiation. $ MR ~ fall onto a flat, horisontal, essentially degree of moderstion, or other pertinent unyielding surface from a height of not property of fissile materialin any (t)(1)The level of non fixed less than nine n (30 ft). package is not known, the licensee shall (removable) radioactive contamination (b) Percussion test he specimen package the fissile material as if the on the exte nal surfaces of each package g must be placed on a sheet oflead which unknown properties have credible offered for shipmentis as low as

le supported by a smooth solid surface salues that will ceuse the maximum reasonably achievable. De level of non-and struck by the flat face of a steel nuclear reactivity.

fixed radioactive contamination may be E billet so as to produce en impact determined by wiping an area of 300 I square centimeters of the surface . equivalent to that resulting from a free ' fall of 1.4 kg (three Ib.) through one m (40 Prior to the first use of any packaging concerned with an absorbent material, in.).ne flat face of the billet must be 2s for the shipment oflicensed matenal: usin; moderate pressure. and measuring am (one in.) in diameter with the edges (a) The licensee shall ascertain that the activity on the wiping material. rounded to a radius of three mm (032 there are no cracks, pinholes. . Sufficient measurements must be taken in.)20.3 mm (0.012 in.) ne lead, of uncontrolled voids. or other defects

in the most appropriate locations to hardness number 3.5 to 4.5 on the which could significantly reduce the

yield a representative assessment of the Vickers scale and not more than 25 mm effectiveness of the packaging-ncn fixed contamination levels. Except a

(one in.) thick.must cover an area (b) Where the maximum normal a as provided under paragraph (1)(2) of greater than that covered by the operating pressure will exceed 34.3 . this section, the amount of radioactivity specimen. A fresh surface oflead must kilopascal (5 psi) gauge. the licensee measured on any single wiping meteelal be used for each impact.ne billet must shall test the containment system at en when averaged over the surface wiped. strike the specimen so as to cause internal pressure at least 50% higher must not exceed the limits given in _ maximum damage. than tne maxirr.urrgnormal operating Table V of this part at any time during pressure to verify the capability of that transport. Other methods of assessment 4 (c) Bending test. De test is applicable system to maintain its structural of equel or greeter efficiency may be only to long. elender sources with both a integrity at that pressure. used. When other methods are used. the minimum length of to cm (four in.) and a (c) ne licensee shall conspicuously detection efficiency of the method used length to minimum width ratio not less 3 and durably mark the packsging with its must be taken into account and in no i O than 10 ne specimen must be rigidly 2 model number, gross weight. and a case may the non-fixed cotitsmination clamped in a horizontal position so that a package identification number assigned on the external surfaces of the package exceed ten times the limits listed in one. half ofits length protrudes from the '. by the Nuclear Regulatory Commission. _ Table V. face of the clamp.ne orientation of the Prior to applying the model nsmber, the j specimen must be such that the

licensee shall determine that the specimen will suffer maximum damage packagit:g has been fabricated in Taoi.a V.-Aswovaat. Extement when its free end is struck by the flat accordance with the design approved by g

RADCAcwt CoNrAW6ArCN Wre tJh5TS l face of a steelbillet.ne billet must the Corr. mission. a strike the specimen so as to produce an Impact equivalent to that resulting from I 71.47 Routina determinations. ,,,,g, a free vertical fall of1.4 kg (three Ib.) Prio' to each shipment oflicensed " "* *a * "'* *: through one m (40 in.). ne flat face of rnaterial, the licensee shall ensure that i the billet must be 25 mm (one in.)in the package with its contents satisfies aw. e sma s diameter with the edges rounded off to a the applicable requirements of this part C***", *,,";,j"Z g radius of three mm (0.12 in.)10.3 mm and of the license.The licensee shall .* ewe.werss. (0.012 in.). determine that: 8,L W Z ("8 (a) The package is prcper for the er ea w c wess. 10 at r o (d)Reat test ne specimen must be e ntents to be shipped; 3 " *** *'*e C s 2.2 8 heated to a temperature of not less than (b)The package is in unirnpaired 2 800'C (14757)in an atmosphere which physical con 6 tion except for superficial (2)ln the case of packages g is essentially air, and held at that defects such as marks or dents: w transported as exclusive use shipments by rail or highway only, the non f!xed temperature for a period of10 minutes (c) Each closure dnice of the and must then be allowed to cool packaging including any required

radioactive contamination at any time 8

gasket. is properly installed and secured dur ng transport must not exceed ten g Subpart G-Operat!ng Controls and and free of defects: times the levels prescribed in paragraph Procedures (d) Any system for containing liquid is (i)(1.) of this section.De levels at the a adequately sealed and has adequate begmning of transport must not exceed 8 i I A cabmty of operating controle space or other specified provision foc the levels prescribed in paragraph (t)(1) expans*on of the liquid'. of this section: A licensee subject to th.is part, who (j) External radiation levels around under a general or specific license (,) Any pressure reg; 7gvg the ficable, will not exceed the limitsackage a transports licensed material or delivers perable and set In accordance with ,pp n 4 at any time during ee as been loaded and transport shal ce ply w e closed in acco ence with written requ ements of this Subpart G with the procedures; (k) Accessible packay surface 71 11 August 31,1983 4

PART73 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL. temperatures wil! not exceed the limita material not exempt under I 71.10, chapter at least 45 dayi prior to specified in i 71.43(3) at any time during showing. where apphcable: febrication of a package to be usr.d for trensportation. (1)Identdication of the packaging by the shipment uf licansed meterial having model number: a decay heat load in excess of Sve I n.se Ak transport et pueda (2) Verification that there are no kilowatta or with a msmimum normal (a) Notwithstanding the provisions of significant defects in the packaging. as operating pressure in excess of 103 any generallicenses and shipped; kilopascal (15 psi) gauge. notwithstanding any exemptions stated (3) Volume and identification of directly in this part or included coolant: 57188 hPorte-indkectly by citation of 40 C'1 Chapter (4) Type and quantity oflicensed The licensee shall report to the r

1. as may be applicable. the licensee materialin each package and the total Director. Office of Nuclear Material shall assure that plutonium in any form.

quantity of each shipment: Safety and Safeguards. U.S. Nuclose whether for import. export, or domestic (5) For each item of irradiated fissile Regulatory Commission. Washington. shipment. is not transported by air oc material: DC 20555, within 30 days: dehvered to a carrier for air transport (i) Identification by model number (a) Any instance in which there is unlan; and/or serial numberi significant reduction in the effectiveness (ii) Irradiation and deca history to of any authorized packaging during use; (1) ne plutonium is contained in a de extent appropriate to emonstute and medical device designed for individual that its naclear and thermal (b) Details ot any defects with safety human appbcation; or amc C8 C y cen8e 8

nce e padagsg & W (2) The plutonium !s contained in a conditions, and use, with the means employed to repair ma ag ch spe vity is (iii) Any abnormal or unusual the defects and prevent their recurrence.

g P' condition relevant to radiation safety. gram of material and in which the (8) Date of the shipment; I H.97 Abance nom M aNpment radioactivity la essennally uniformly (7) For Fissile Class III and for Type B distributed: or packages. any special controls (a) Except as specified in paragraph (3)The plutonium is shipped in a exercised; (b) of this section. prior to the transport single package containing no more than (6) Name and address of the or delivery to a carrier for transpo=t of an A, quantity of plutonium in any transferee; licensed material outside the confines of isotope or form and is shipped in (9) Address to which the shipment the licensee's plant or other place of use actordance with I 71.5 of this part; or was made; and or storage, each licensee shaU provide (4) The plutonium is shipped in a (10) Results of the determinations advance notification to the governor of a package specificaUy authcrized for the required by 5 71.87. state. or the governor's designee. of the shipment of plutonium by air in the (b) The licensee shall make ava!!able shipment to. through, or actos. the Certificate of Compliance for that to the Commission for inspection, upon boundry of the state. e 5 paekage issued by the Commission. 8 reasonable notice, all records required j (b) Advence notificationis required A (b) Nothi in paragraph (a) of this by this part. 3 only when-

section is to interpreted as removing (c) The licensee shall maintain. dudng (1) The licensed materialis required a

- or dunin:shirg the requirements of $ the life of the packaging to which they g by this part to be in Type B packaging

l 73 24 of this chapter.

. pertain. sufficient quality assurar'ce for transportation; " records to furnish documentary (2) The licensed meterial other than (c) There has e been two orders lesued by the NRC restncting the air shipment evidence of the quality of packaging irradiate 1 fuelis being transported to, of piatonium in accordance with Pub. L cpmp nems w have, safey h4 or acron state kudadu u a significance and of services affecting disposal site or to a collectica point for M-79 The f:rst order. issued on August quality. The records to be maintained transport to a disposal sitet .15.19~5 m as superseded by the second include results of the determinations (3) The quantity r.1 licensed material order dated September 1.19"a. which required by 5 71.85. of monitoring. in a single package exceeda: has remained in effect since that time inspection, and auditing of work ]i) 5.000 curies of special form As of the effec.tive date of this rule. the ,..onuclides; performance duries the design. outstanding order dated September 1. fabrication. assembly, testing. (f.) 5.000 curies of uncornpressed gese: 1978 is revoked ~ modification, maintenance, and repair of of Argon-41. Krypton-45m. Krypton-47, the packaging. Xenon-131m. or Xenon-135; (iii) 50.000 curies of Argon-37, or of uncompressed gases of Krypton-85 or I 71.89 Operseg Instructiona. I 71.93 Inspection and testa. Xenon-133 or of Hydrogen-3 as a gas. Prior to delivery of a package to a ga)g gicenne shan pumit de as luminous paint or adsorbed on solid mmission at a!! reasonable times to material; carrier for transport, the licensee shau ensure that any specialinstructions inspect the licensed material. packaging. (iv) 20 curies of other non special form needed to safety open the package have [remises, and facilities in which the radionuclides for which As is less than. been sent to or otherwise made censed material or psckaging is used, or equal to four curies: or availab!e to the consignee for the produced. tested. stored, or shipped. (v) 200 curies of other non.special (b) The licensee shall perform, and form radionuclides for whleh As la consignee's use in accordance with permit the Commission to perform testa greater than four curies; and i 20 205 of this chapter. as the Commission deems necessary or less than t$uantity of irradiated fuelle (4)The appropriate for the administration of the at subject to advance 17181 R* cords-c) el$cen e nEtify se tification requirements of to CF1L Part l (a) Each licensee shall maintain for a Director of the appropriate Nuclear (c) Procedures for submitting advance period of two years after shipment a Regulatory Commission Regional Office notification. (1) The notification must be record of each shipment oflicensed listed in Appendix A of Part 73 of this August 31,1983 71 12 l i

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL I made in writing to se eRios of each the governor's oepignee and inform that assurance actions related to esatrol of appropriate er govermore individual of the extent of the delay _ the physical characteristics and quality O designee to the Director of the beyond the schedule originally reported. of the material or componest to appropriate Nuclear tory The licensee shall maintain a record of predeterudned requir==mana Ceaunission Regional listedin the name of the individual contacted for (b)EstehtiaAment ofprugram Each Appendix A of port 73 of this chapter. ene year. licensee shall establish, maintain, and (3) A motincation delivered by maa (f) Concellation motice. (1) Each execute a quality assurance preyan i' must be postmarked at least seven doye licensee who cancels a nuclear waste estisfyi sech of the applicable criteria before the besmning of the seven-day shipment for which advance notification of this ou tt. and estisfytqs any period during which departure of the has been sent, shall send a cancellation specific previsions which are a cable i shipmentis estimated to sauer. notice to the governor of each state or to the licensee's activities 1 (3) A notification delivered by the novernor's duisnee previously procurement of packaging. De boonsee messenger must reach the office of the notified and to the f>irector of the shall apply the applicable criteria in a povernor or of &e governor's designee at appropriate Nuclear Regulatory graded approach. and to an extent that 4 most four days before the beginning of Commission Regional Office listed in is consistent with their importance to A pendix A of Part 73 of this chapter. safety. ihe seven day period during which P departure of the shipment is estimated (2)De licensee shall state in the (c) Approvolofpragmm. prior to the to occur. notice that it is a cancellation and shall use of any package for the shipment of l (1) Alist of the names and mailing identify the advance notification which licensed material subject to this subpart, addreme of the governors' desisness is being cancelled The licensee shall each licensee shall obtain thi* i receiving advance notification of retain a copy of the notice as a record approval ofits quality assurance transportation of nuclear weste wee for cne year. ~ program Each licensee shall Sie a desenption ofits quality assurance .d hublished in the yederal Register onIIt '88'"*' program, including a discussion of e so. Iges (48 FR 30321) An injunction or other court order - which requirements of this subpart are (ii) De list will be published annuall may be obtained prohibiting any applicable and how they will be la the Federal Register on or about june violation of any provision of the Atomic satisfied. with the Directee. Office of 30 to reflect any che s in infonaation. Energy Act of1954. as amended.(the Nuclear Material Safety and Safeguards, (iii) A list of the na es and mailing Act) w Me 11 of ee Energy M Nuclear Regulatory hw addresses of the governors' designees is Reorganization Act of1974, as amended. Washington.DC 30665. 1 available ukce of State programa.UA. or any regulation or order issued under (d)Esisting se designs.He n request frca the Director. O 4 se Acts. A court order may be obtemed provisions of a paragraph deal with Nuclear Regulatory Commission, t fe the paywnt of a civ!! penalty packages which have been approved for i Washington. DC 30588* Imposed under section 234 of the Act for use is accordance with this part to ~ j 4)De licensee shall retain a copy sf violation of sections 53. 57. 82. 83. St. 82. .'anuary 1.197s, and which have ?bd 101.103.104.107. or 100 of the Act, or c'esigned in accoedanae with the l 3 3 )' roam notificols.on of shipment. Each Act of 1974. an amend or any rule. A time of application for pack d 8 O g*,dvance notificat'on of shipment of . section 200 of the Ene Reorganization. provisions of this part in *ffect at tha ,a ngulation, or order issued under the , approval. Dose packages w be " f,f,*g,"88h' ", a"ddress, and telephone

- "'*I" 8' accepted as having been designedin Acts, or any term. condition, or S

6 g, pecordance with a quality assurance = limitation of any license issued under = i (1)De name the Acts. or for any violation for which a program which satisfies the provisions number of the ship r. carrier. and license may be revoked under section of{e)ragraph(b)of thissection. a receiver of the nu er waste shipment les of the Act. Any person who willfully Esistisqrpockages.De provisions (2) A duen tion of the nuclear weste violates any provision of the Act or any of this parebaph deal with packages contained in e shi ment, as required regulation or order issued under the which have n approved for use in by the egulations o DOTin to CFR Acts may be guilty of a crime end. upon accordance with this part prior to 172.202 and 172.303(d): conviction. rr.ay be pt.nished by fine or January 1.1979, have been atleast j (3) he point of origin of the shipment imprisonment or both, as provided by partially fabricated prior to that date. and the seven-day period during which gew' and for which the fabrication is in departure of the shipment is estimated accordance with the provisions of this to occur: Subpart H-Ouality Assurance part in effect at the time of application (4) ne seven. day period during which for approval of rekage design.Deee j arrivalof the shipment at state 9 71.101 cuanty sesurance requiremanea, neckages w 11 be accepted as having l boundaries is estimated to occur: (a) Purpose his subpart describes been fabricated and assembled in j (5) De destination of the shipmer.i. quality assurance requirements applying accordance with a quality assurance and the seven. day period during which to desip, purchase, fabrication. program which satisfies the provisions i l arrival of the shipment is estimated to handlink shipping. storing. cleaning. of paragraph (b) of this section. t occur: and assembly, inspection, testing. operation. (f)Piev/ovs/yapprovedprogroms. A l (8) A point of contact with a telephone maintenance. repair. and modification of Commission. approved quality assurance number for current shipment components of packsging which are program wh!ch satisfies the applicable i j information. Important to safety. As used in this criteria of Appendix B of part 30 of this l (e) Revision notice. Alicensee wbe subpart." quality assurance" comprises chapter and which is estoblished. finds that schedul. infonnation s'l those planned and syste;natic actions mainteined, and executed with rege'rd to previously furnished to a governor er necessary to provide adequate trarnsport packages will be accepted as ' ntisfying the requirements of paragraph ' governor's designee in accordance with confidence that a system or corhponent a a l mis section will not be met. shall will perform satisfactorily in service. (b) of this section. Prior to first use, the telephone a rasponsible individualin the Quality assurance includes quality licensee shall riotify the Director. Office office of the governor of the state or of control. which comprises those quality of Nuclear Material Safety and i O a 4 1 71 13 August 31,1983 b 4

1 PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL Safeguards. UA Nuclear Regulatory authonty and organizational freedom. (4) ne degree to which functional Commisson. Wuhington. DC 30655, of Irrespective of the organizational compliance can be demonstrated by its intent to apply its previously structure. the individual [s) assigned the inspection or test; and approved Appendix B program to responsibility for e souring effective (5) The quality history and degree of transportation activities. De licenese execution of any portion of the quahty standardization of theitem. shallidentify the program by date of assurance program at any location (d)De licensee sha!! provide for submittel to the Commission. Docket where activities subject to this section indoctrination and training of personnel Number and date of Comelsalon are being performed must have direct performing activites affecting quality as access to the lesels of management necessary to assure that suitable roval. s necessary to perform this f zetaon. proficiency la achieved and maints' l 71.103 Queaty assurance organtasman, The licensee shall review the status I 71.105 Ouality assurance progen-adequacy of the quali assurance ( > ra ite

ti ' du h ' th-pre 8r - ' i su>h fi=' r i - A thet,M"t"'2L':res" fora earliest practicable time consistent with Management of other organizations quality assurance program. ne licenew the schedule for accomplishing the participatmg in the quality assurance may delegate to others, such as activities. a quality assurance program program shall regularly review the contractors. agents. or consultants. the which complies with the requirements of status and adequacy of that part of the work of estabhshing and executing the this section. The bcensee shall quality assurance program which they quality assurance program. or any part document the quality assurance program are executing.

of the quality assurance program but by wntten procedures or instructions 8 shall retsin responsibility for th* and shall carry out the program in g 57W M*9e *a8en W program.ne licensee shall clearly accordance with those procedures (a) ne licensee shall establish a establish and delineate in writing the throughout the period daring which z measures to assure that applicable authority and duties of persons and packag:rg is used The licensee shall ' regulatory requirements and the organizations performing activities identify the material and components to P ck88 d i n 8 specifiedin the 8 affecting the safety related functions of be covered by the quality assurance license for those materials and structures. systems and componenta-program. the major organizations components to which this section nese activities include performing the participating in the pro ram, and the applies, are correctly translated into a functions associated with attaining designated functions of these specifications, drawings. procedures, quality objectives and the quality organizations. and instructions. nese measures must assurance functions ne quality (b) The licensee, through its quality include provisions to assure that b assurance functions are (a) assuring that g assurance program. shall provide appropriate quality standards are j en appropriate quality assurance 1 control over activities affecting the specified and included in design a program is established and effectively

quality of the identified materiale and documents and that deviations from z executed and (b) ve-ifying, by z components to an extent consistent with standards are controlled. Measures must procedures such as checking. auditing.

' their importance to safety. and as be established for the selection and

and inspection. that activities effecting i necessary to assure conformance to the review for suitability of application of the safety-related functions have been approved design of each Individual materists, parts, equipment, and correctly performed He persons and package used for the shipment of processes that are essential to the organizations performing quality radicactive material The licensee shall safety related functions of the materials, assurance functions must have sufficient assure that activities affecting quality parts, and components of the packaging.

authority and organizational freedom to are accornp!ished under suitably [ Identify quality problems; to initiate. controlled conditions Controlled (b) ne licensee shall establish recommend, or provide solutions, and to conditions include the use of measures for the identif; cation and verify irnplementation of solutions. ne appropriate equipment; suitable control of design interfaces and for persons and organizations performing ensironmental conditions for coordination among participating design quality assurance functions shall report accomplishing the activity, such as organizations.nese measures must to a snan gement lesel which assures adequate cleanliness: and assurance include the establishment of written that the required authority and that all prerequisites for the given procedures among participating design organizational freedom. including activity hase been satisfied ne organizations for the review, approval. sufficient independence from cost and licensee shall take into account the need release, distribution, and revision of schedule when opposed to safety for special controls processes. test documents involving design interfaces. consideratior's are provided Because of equipment, tools and skil?s to attain the , The design control measures must the rnany vanables involved. such as the required quality, and the need for I provide for verifying or checking the number of personnel, the type of activity serification of quality by inspection and "! adequacy of design, by methods such as being performed. and the location or test. 2 design reviews, alternate or simphfied locations where activities are (c) ne licensee shall base the - calculstional methods, or by a suitable performed. the organizational structure requirements and procedures ofits

testing program. For the venfying or for executing the quality asrurance quality assurance program on the checking process, the licensee shall program rnay take sarious forma following considerations concerning the designate individuals or groups other provided that the persons and complexity and proposed use of the than those who were responsible for the crganizations assigned the quality package and its components

original design, but who may be fman assurance functions have the required (1) The impact of malfunction or the same organization. Where a test' failure of the item to safety; program is used to verify the adequac mw th. iem -1.ceu.9. =4 in o (2) The des;gn ind fabrication of a specific design feature in lieu o( y %'[,* Q 7 7 '"J',

(,

comp!exity or uniqueness of the' Item:- other verifying or checking processas or e, p.cn.s. i..ccomptinsed wen e..p.c,i.. (3) The need for special controls and the licensee shallinclude suitable p.cn.s. pnor vo rhe virne. p cn.ee.pp,...! e. surveillance oser processes and qualification testing of a prototype or ww 4 equipment; sample unit under the most ads erse design conditions.The licensee shall O August 31,1983 M I l

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL ,,,3y ,,g,,,,,,,3,,,,,,,, a gesmo measures must include provisions, as assure quality. If direct inspection of g g each se he feDowing celucahty r%ysica.

PProPriate. for source evaluation and proc,essed material er products is not l/ sdknon shieWms.Mress termal, selection, objective evidence of quality carned out. ladirect osotrol g hydrdic. and accWent analyses.

fumished by the contractor or monitoring _--- - me simpatibiuty dederhis asemes&Ety subcontractor. inspection at the equipment and perso,nnel must be a a contractor or subcontractor source, and provided. Both lespection and pressee ' fee havice byecean, malateasace. and mPe13.feMures w facBek examination of products upon delivery monitorlag must be psevided when P g,,, aminahm and dehassuem of (b) The licensee shall have available quality osotrol is inodoquete without

ocep,ance,gg,g g,,

,- 7; go,is, documentary evidence that meterial and both. If mandatory loopection held equipment conform to the pws.; r.t points, which require witasseing er specificatione prior to installation or use inspecting by the beensee's des ted _ (c) He licensee shall subject design of the material and equipment.ne mpresentative and beyond work shanges,includmg field changes, to licensee shall retain or have seallable should not proceed without the consent ' design control measures commensurete this documentary evidence for the life of ofits ted tative, are with those applied to the original design. the package to which it applies.%e mquimd. hold pointe must Qanges in me conditions specified in hcensee shall assare that the evidence is be indicated in appropriate docussents. the package approval require NitC sufficient to identify the specific gFuss Temesent approval. requirements met by the purchased g gg I I"" '**"'***"'8'*""*'d**' e I ce e o designee shall prog am to,assum est aH toonne De licensee shall establish measures essess the effectiveness of the control of mquimd k demonstmW &at to to assure adequate quality is requimd in quality by contractors and Packaging canponents wi one causfacMiy la service is ufled a ad the documents for procurement of subcontractors at intervals consistent material, minipment. and services, with the importance, complexity, and perknned in accenlance wl& wduen W Pmcedes which lacorporow to whether purchased by the licensee or by quntity of the product or services.. reguimmuta of this part and the its contractors or subcontractors. To the extent necessary, the licensee shall l 71.117 identtfication and sentrol of requirements and acceptance limits require contractors or subcontractors to motetals, parta, and componensa, contained in the package a al.De provide a quality assurance program The licensee shall utablish measures test procedures must inc! provimiens consistent with the applicable for the identificatJon and control of for assuring that all prerequisites for the provisions of this part. materials, parts, and cornponents Dese given test am met, that adequate test o instrumentation is available and used. l Fun inetmenene,pocasures,and ! measures must assure that identification j and that the test is performed under of the item is mamteined by heat suitable environmental conditions. De J N number, part number, or other a t

De licensee shall prucribe activities a appropfiate means. either on the item or a licensee shall document and evaluate effecting quality by documented

' on records traceable to the itect as ' the test resulta to aneure that test a 3 required throughout fabrication. 3 f*1uirements have been entiefled. O 'z instructions. procedures, or drewings of a type a propriate to the circumstanas installation. and use of the item. These 1 71.125 centrol et mesewing and test

and e a I require that these instructions, identification and control measures agulpmesa, procedures, and drawings be followed.

must be designed to prevent the use of De licenen shah ntabush menern The instructions, procedures. and incorrect or defective materials. parts, I assum that tools, gages. instrumets, drawings must include appropriate and components-and other measur'ng and testmg devices quantitative or qualitative acceptance criteria for determining that important i71.1to Controlof spectat processee. used in activities arrecting quality are activities have bun satisfactorily ne licensee shall establish measurn properly controlled, calibrated. and accomplished. to assure that special processes. adjusted at a fled times to maintain including welding. heat treating. and accuracy wi necesary limits. ifu13 Documentconwet nondestructive testing. are controlled gfu 7 standung, egrege,and asuppeng 4 ne licensee shall establish measures and accoraplished by qualified eeners 1 to control the issuance of documente personnel using quahfied procedures in De licensee shall establish measures such as instructions, procedures, and accordance with applicable codes. to control. in accordance evith drawings, including changes. which standards. spcifica tions. criteria, and instructions, the handling. storage, prescribe all activities affecting quality. other specia. requirements. shipping. cleaning. and preservation of j ( These measures must assure that resterials and equipment to be poed la l documents. including changes, are 3 71.121 Intemet inspecuen packaging to prevent damage ce reviewed for adequacy, approved for ne licensee shall establish and deterioration.When necessary fee release by authorized personnel, and execute a program for inspection of particular products special protective distributed and used at the location activities affecting quality by or for the environments,such as inert gas where the prescribed activity is organization performing the activity to atmosphere, and specific moisture performed. nese measures must assure verify confurmance with the content and temperature levels must be that changes to documents are reviewed documented instructions. procedures. specified and provided. j and opproved. and drawings for accomplishing the activity %e inspection must be 1 71.139 spepection leet.and operoling l71.115 Centrolof purchased mate tal, performed by individuals other than esseum. % ment, and wMees' those who performed the activity being (a)De licensee shall establish (e)De licensee shall estoblish inspected. Examination, measurements, musures to indicate,by the use of measures Io assure that purchased or tests of material or products ma'rki,ngs such as stamps, tags. labels, + material, equipment, and services, processed must be performed fdr each touting cards, or other suitable means, whether purchased directly or thro work operation where necessary to the status ofinspections and tests contractors and subcontractors, to orm i to the procurement documents. Rose i 1 71 15 August 31,1933

~ PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL performed upon individualitema of the retained for thelife of the package to whm r is the gamme. ray constant, packaging. Heae measures muag which they apply. Records pertaming to cormspondmg to the dose in R/h at 1 a per n se number e neulta hm se datos di provide for the identification of items the use of the package for shipment of which have satisfactorily passed radioactive material must be retained 'bivale'Ia's d se required inspections and tests wher, for a period of two years after the giij re, x. rey emit era. A. la detemined by necessary to preclude inadvertent by, shipment. the atomic number of b nuchde: paesing of the inspections and testa. (b) De licensee shall establish a for Z < 55-A.=1000 Q (b)he licensee shall eedlieb records retention program which is for Z > 55-A.= 200 Q measures to identify the ting status consistent with the applicable whm Z is the atomic number of h n of components of the pa aging. such as regulations. designating factors such as (lu) For beta emitters. A. is determined tagging valves and switches, to prevent duration. location. and assigned febeA

h. advertent operation.

responsibihty. (ivl For alpha emittes. A. la determinadtry l 71.131 leoneonforming motettate. parts. 8 9 71.137 Ausste. se eupmssion: A.= 000 A. er eenpenenas. $ He licensee shall ca out e He licensee shall estab!!ah measuree [ comprehensive system planned and 3 ia"th more n ^ etive o penodic audits to verify compliance following two valuu. to control materials. parta, oc a with all aspects of the quality assurance (i)De correspond r3Ag and components which do not conform to the licensee *a requirements in order to

program and to determine the (ii) De value A. obtained from Table A-3 prevent their inadvertent use or effectiveness of the program.De audits (3) For any single rsionudide whose installation.Dese measures mt st must be performed in accordance with identity is unknown, the value of A. la taken include, sa appropriale. procedures for written procedures or checklists by to be two O and the wafue of A.to taken to be 0 002 Q. However, if the atomic number of identi$ cation. documentation, appropriately trained personnel not the rae nuchde is known to be less than a2.

segregation. disposition. and notification having dinct responsibilities in the to affected organizations. areas being audited. Audited resulta ,j,$*h'g ;,,*,$,'fj"d"M U ""d ** 0 dA Nonconforming itema must be reviewed must be documented and reviewed by and accepted. rejected. repaired. or management having responsibility in the IL MIntures of radioocutides,includlag roworked in accordance with area audited. Fo!!ow up action. '*dioacth* d8F thain*- documented procedures, including re. audit of deficient areas, (1) For mised fission products the following must be taken where indicated. 8 activity limits may be assumed if a detailed o "J $ 71.133 Corrective action. $ anal)sie of the mixture is not carried out: APP'" i" ^ '"*AS* " * ^' **d A*

A.= to o ne licensee shall establish measures f to assure that conditions adverse to

,_L Engle radioeudidae. [ A.=H Q [2] A sing e ndiosctive decay chain la uality, such as deficiencies, deviations. . e naidered to be a siegte radionudide when efectne material and equipment, and . nonconformances, are promptly identif;ed and corrected. In the case of a { (1) For a single radionuchde of known ["[* 8j',' , ', ' "( significant condition adverse to quality. g 6dentity. the values of A. and A are taken than 10 days or longer than that of the parent fr m Table A-1 if hsted there. De values A* nuchde. no activtt to be taku into account i the measures must assure that the cause ' a opp ble f" of the condition is determined and

(do amj f app,the A. or A.va ue from Table A-1 to be and ci e co ied am those correspon&ng to the parent correcthe action taken to preclude repetition. The identification of the J neum sourcu' nuchde of that chain When calculating A.or significant condition adverse to quality.

L- ^* values, ra&ation emitted by daughters must be considered However,in the case of the cause of the condition, and the rs&oacttve decay chains in which any correctgwe act;on tagen must be (2) For any single r6&cnuchde whose daughter nuchde has a half.hfe either longer documented and reported to appropriate identity is known but which 6e not listed in than to days or greater than that of the levels of management. Table A-1.the values of A. and A.are parent nuchde. the parent and daughter determined accordmg to the following nuclides are considered to be mixtures of f 71.135 Oua!!ty assurance recorda, procedure: different nuchdee. (a) ne licensee shall maintain (a)If the radionuclide emits only one type (3)In the case of a mixture of different aufDcient written records to furnfah of re&ation. A. 68 determined accor&ng to re&onuchdes where the idennty and activity the rufes in paragraphs (i). (ii). (iii) and (iv) of of each rs&onuchde are known. the cvidence of actidtles affectinfolioN ~ quality' this parag aph For radionuchdes emitting rmissible activt of each re&onuchde R., The. records must include the d f'erent k nds of re&ation. A. le the most ...R.lasuch at F. + Fe +.. F 6e not desi n :ecords. records of use and the o restriciive value of thou determtned for each smeter them unity. where resu ta of reviews. Inspections. testa. 3 kind of red;ation However,in both cases. A. audits. rr.onitoring of work performance, f, is restncted to a maumur af 2000 C. If a and materials anal ses. The recorda parent nuchde decays into a shorter hved must include close related data such E daughter with a half Lfe not greater than to T***! *ctar a' 8L I'

ce qualifications of personnel.

dans. A. ls calculated for both the parent and ggg,, procedures. and equipment. Inspection

th* daughter. and the mon hmiting of the two and test records must, at a minimum, values ta assigned to the parent nudade.

Identify the inspector or data recorder. 0] For gamma eminen. A. la detennined by the type of obsets ation, the results, the ccceptability, and the action taken in Teist acovity of 3. connection with any deficiencies noted-e

- 3 Records must be identifiable and A.

oww. f I retrics able. Records pertaining to the fabrication of the package must be Tetet acevtey of B. MR.) August 31.1983 71 16

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL AlR., A.R.)le the value of A.se As se appropriate for the nuchde R., A.R / (4) When the identity of each redsonuchde (d le known but the indmdual activitsee of some 0 of the radionuchdee are not known, the $ formule given in peregraph (3)le oppbed to a estabbeh the velves of A, or A.as a appropriate. All the radionuchdeo whose ' indsvidual activities are not known (their total actnity wt!!. however be known) are e' eleased in a single group and the moet sestrictive value of A. and A. epplicable to any one of them is used es the value of A.se % tn the denominator of the fraction. I 15 Where the identity of each radionuchde $ le kn)own but the individual activity of none of the radionuchdee is known, the moet p restrictive value of A. or A. applicable to any a one of the radionuchdes present is adopted

es the appbce'le value.

rmu(chdes is known,the value of A is taken to

6) When the identity of none of the I be two Q and the value of A.ie taken to be 00c2 O However ff e!phe emitters are g known to be absent,the value of A.to taken (to be 0 4 CL TABLE A-1.-Aa AND Ao VAWEs Fom RADioNUCUDES (See footnotes at and of telde)

Symte of rechonuchde Element and storme nurneer A.(Cl) A.C) ,,ime, fg3 227 Actnsum (89) 1000 C.003 7J x10 228 10 4 2.2 x 10' 105 S4ver (47) 40 40 3.1 x 10' 110m.. 7 7 4.7 x 10e (h 111 100 20 1.8 x 10' / 241 Amencium (95) 4 0.008 3.2 243. 8 0.008 1.9 x 10-'

37. (compressed or uncompressed)*

Argon (18) 1000 1000 1.0 x 10' $ 41. (uncompressed)* 20 20 4.3 x 10'

41. (compressed)*

1 1 4.3 x 10' " 73.. Arsenic (33) 1000 400 2.4 x 108 s 74.

76 I

.20 20 1.0 x 10' 10 10 1.8 x 10'

77 I

300 20 1.1 x "' 211 3 Astatine (85) 200 7 2.1 x 10' 193 I Gold (79). 200 200 9.3 x 10' 196 30 30 1.2 x 10' 190 40 20 2.5 x 108 199 200 25 2.1 x 108 131a. Benum (56) 40 40 S.7 x 10'

133e, 40 10 4.0 x 108 140s.

7e. 10 20 7.3 x 10' Berythum (4) 3C 1 300 3.Sx10'

206e, Bismutn (83) 0 5

9.9 x 10' 207e.. If 25 2.2 x 10' 210s,is, 100 4 1.2 x 10'

212e, S

6 1.5 x 10' 249e. Berkehum (97) 1000 1 1.8 x 10' 77,. Bromine (35) - 70 I 25 7.1 x 108 \\ 71 17 August 31,1983

i i PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MAT TABLE A-1.-Ai AND A. VALUES FoR RADioNUCUDES-Cofitir1ued 1 e, (See footnotes at end of tab 6e) l Element and atome number A.(C) A.(G) yq ) Sysc,. of radenuct oe 6 8 1.1 x 10' 82,,. 20 20 8.4 x108 ' Carnon (6) ite 1000 80 4.6 k 1000 25 1.9 x to' 14e ' Caloum (20) 45c. 20 20 5.9 x 10' 47e. 1000 70 2.6 x108 g Cadmum (48) 109u.- 30 30 2.6 x 10* 115m. L 80 20 5.1 x 1 '1' c 115a 1G0 100 6.5 x 10' > Cenum (58) 139c. 300 25 2.8 x 10* 1:1c. - 80 20 6.6 x 10' 143c. 10 7 3.2 x 108 144c. 2 0.002 3.1

CaWomum (96) 249a.-

7 0.007 1.3 x to' 250c,. 2 0.009 6.5 x 108 300 10 3.2 x t0-8 25 % [ CNonne (17). 10 10 1.3 x108 34.. 3a p 200 0.2 3.3 x 10s a > Cem (96) 'c2c. i 9 0.000 4.2 x 10 s43c... 10 0.01 8.2 x 10 244 6 0 006 1.0 x 10 L c 6 0.006 3.6 x 10*

2:Sc.

-[ 246a. 5, 5 3.0 x 10* 56e.

Cocelt (27) 90 90 8.5 x 10s j

l. 57c. 1000 1000 5.9 x 10* ^ Som. 20 20 3.1 x 10* e 58c. 7 7 1.1 x 108 Sco. 800 000 9.2 x 10* Chromum (24) Sta. 40 40 7.6 x 108 @ 129 Ceemm (55). 1000 1000 1.0 x108

7. 131 1000 10 7.4 x 10'

" 134m I 10 10 - 1.2 x 108 m 8 134.. I 1000 25 8.8 x 10*

c 135m-7 7

7.4 x 10* 3 138o 30 10 9 8 x 10 137o-80 25 3.8 x 10* 6% Copper (29) 200 25 7.9 x 108 100 20 8.2 x 108 67c. IDyspresum (66) 3 1000 200 2.3 x 108 165, as,, h 1000 25 8.2 x 10* Ertnum (68). 69, b 50 20 2.4 x 108 171er 30 30 2.2 x 108 152m. Eurocnum (63) e 20 10 1.9 x 108 152s. 10 5 15 x 108 154 400 00 1.4 x 10s 3 Fluonne (9). 20 20 9 3 x 10' 155s. 5 5 7.1 x 10' 18, Iron (26).. 52,. - 1000 1000 2.2 x 10' 5b p 10 10 4 9 x 10' SA 100 100 6 0 x 10' ( salhum (31) 20 20 4 0 x 10' 67e. 7 7 3.1 x 10' 68c.. [Gadohrwum (64) 200 100 3.6 x 108 72c. -I 300 20 1.1 x 10' 153o.. 20 to 7.0 x 10' 159ae ' Germarwum (32).- 68c. 1000 1000 1.6 x 10' 71ee 3. Hydrogen (1) see T.Trmuni 30 25 1.6 x 10' 18 lay Hafnum (72) 200 200 6.6 x 108 197m. Mercury (80).. m 200 200 2.5 x 10' 197m. 80 25 1.4 x 10* 203me 30 30 6 9 x108 166m.. Holmom (67). 50 50 1.9 x 10

123:

IWne (53) t000 70 1.7 x 10 *

125, 40 10 7.8 x 10 *

126, 1000 2

1.6 x 10"* 129: - - 40 10 1.2 x to

131:

7 7 1.1 x 10 ' 13?r. g 71 18 August 31,1983

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL TAsLE A-1.-A AND As VALUES FOR RAoioNUCUDES-Continued (See footnotes at end cf tab 6e) Symooi of reconuchoe Coment and atome number f A,(CQ 08'ChC,g, A (Ci) 133.. 1 134..~ 30 10 1.1 x 10 8 8 8 2.7 x 10 ' 13 5,.......... .-.I 10 10 3.5 x 10 *

111, Indium 149).

I 30 25 i 4.2 x 10

113m..

i 8 80 80 { 1.6 x t o ' 114m.. I i 30 20 2.3 x 10

115m I'

w..-._- 190 -- I 100-20 61 x to

Indium (77).

I 10 ' 10 l 6.2 x 10

102,.

20 to I 194 9.1 x 10 s a

42...

10 10 8.5x10* 43.. Potassium (19) 10 l 10 6.0 x 10

85m, funcomo>essec)*

20 10 j 3.3 x 10

Krypton (36) 100' 100 8 4 x 10
a 85m,(como'essec)*

9 a 85a, tuncomo*essec1' 3 3 8.4 x 10 4 85a, (compressece 1000 1000 4.0 x 10 8 87, funcomo essec)* 5 5 4 0x to 8 a 67, (comoressec)* 20. 20 2.8 x 10 ' a 0.6 : 0.6 2.8 x 10 ' 140a. Lante. anum (57). 30. 30 5.6 x 10

u.

177w... Low soecrhc actmty matenawsoe i 71.4 Lutetwm (71) ...-.... -. Woc fisson products 300 25 1.1 x 10

m.

10 i 04 28.... Magnesium (12).. 6 i 6 5.2 x 10

52...

... Mangamese (25)... 5: 5 4.4 x to

5A....

20 20 8.3 x 10 s

56....

99.. 5' 5 2.2 x 10 ' ll 13... Molybdenum (42).- .) 100.' 20 4.7 x 10

Nitrogen (7)

!" 22. Sodium (11) 20, 10 1.5 x 10

2 24....

8, 8 6.3 x 10 s A ; 93m% I 5l 5 8.7x 10

Nceium (41).

1000 200 1.1 x 10 8 t 95.. - )

97 20,

20 3.9 x to

b/

20 20 2.6 x 10 ' 147 ' Neocymium (60). 100l 20 8.0 x 10

14 9...

5 9... 30 ; 20 1.1 x 10 ' 63., - Nicket (28).. 1000+ 900 8.1 x 10'8 65.,. 1000' 100 4 6 x 10 23 7......-... 10 - 10 1.9 x 10 ' Neptuntum (93).. I $l 0.005 6 9 x 10*

239...

200l 25 2.3 x 10' I 185o. Osmium (76). 191... 20 ' 20 7.3 x 10' a 19 t m.. I 600: 200 4.6 x 10* ) o I 193o... 200' 200 1.2 x 10* I 100t 20 5.3 x 10'

32...

- Pnosphorus (15) 30 < 30 2.9 x 10* 230,... Protact.nsum (91).. 20 ! 0.8 3.2 x 10' 231,.. 2! 0.002

4.5 x 10**

233,... I 100I 100 2.1 x 10* 201n..

Lead (82)..

210m-20 ! 20 1.7 x 10' 100-0.2 8.8 x 10 212m.....-... 61 5 1.4 x 10' 103,... _....... Danacium (46).. 1000i 700 7.5 x 10' 109,... 100 20 2.1 x 10' 147 149 Prometneum (61) 1000: 25 9 4 x 10' .y,,,,,,,.... 100. 20 4.2 x 10' 210,.._ ! Poloneum (84). 200 ! 0.2 4.5 x 108 142n.. -.l Praseodymium (59) 10 10 1.2 x to' 143r.. 300 20 6.6 x 10' 191m Platinum (78).. 100 100 2.3 x 10' 193r% - 197m - 2tM 200 2.0 x 10' n _ i.. 197.- 300 20 1.2 x 10' n 238 r. 303 20 8 8 x 10' _ Ptutonium (94). 3 0 003 1.7 x 10 239,.... _ f. 2 0 002 6.2 x 10** 240,... 2 0 002 2.3 x 10** 241,.. 1003 0.1 1.1 x 10' O 24 2,... I'..... 3 0 003 3 9 w 10** 223a.. t Radium (88).. 53 0.2 5 0 x 10' 71 19 November 30.1983 (reset)

i PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL i TABLE A-1,-As AND A VALUES FoA RADIONUCUDES-Contnued (See footrvates at end of table) O' Symood of raconuchde Element and stanc number A.(C;) A.(Ci) m jg; 6 0.5 1.6 x 10' 224 226 4 10 0.05 1.0 228.,. T 10 0.05 2.3 ); 10' 81 .I. Aue oum (37) 30 25 8.2 x,10' 86.. 30 30 8.1 10' 87 Unkmeted. Unbrruted. 8.6 0' Unhmrtet Unkmrted, 1.8 0** . (natura0... 186u. . Ahenium (75) 100 20 1.9 x 10' 3.8 x 10** 187., Unkmrted. junkmeted. 10 : 10 1.0 x 10' 188 ,, (naturan....._.. Unkmeted. 'Unkmrted. 2.4 x 10' 103m Ahoeum (45). 1000 f 1000 3.2 x 10' n. 105 200j 25 8.2 x 10' 22l... Aadon (86). 10 - 2 1.5 x 10' 91., Authensum (44). 80 80 5.5 x 10' 30 25 3.2 x 10* 103a* r-105.... L 20 20 8.8 x 108 t 10 7 3.4 x 10' 106.-

35...

Sutonur (16). 1000; 80 4 3 x 10* 122 . Anamony (51).. 30 30 3.9 x 10' 5 5 1.8 x 10' 124,. I 40 25 1.4 x 108 125... 46., ' Scanoum (21) 8 8 3.4 x 10' I 200 20 8.2 x 10' 4 7., L 48., 5 5 1.5 x 10' 75. Sesenum (34) 40 40 1.4 x 10' S 3i. ., Sebcon (14) 100 lUnkmrted. 20 3.9 x 10' %147,. l Samanum (62) Unkmrted. 2.0 x 10*

15 t e.

L 1000 90 2.8 x 10 i 300 20 4.4 x 108 g 153. 113

Tin (50) 60 80 1.0 x 10*

119m. l. 100 100 4 4 x 108 10 to 1.1 x 10' 125 85m.

Stronnum (38).-

80 80 3.2 x 10' 85.. 30 30 2 4 x 10' 87m.- l 50 50 1.2 x 10' 89..- 100 10 2.9 x 10' 00 10 04 1.5 x 10' 91. 10 10 3.8 x 10' 92.. L 10 10 1.3 x 10' , (uncompressed)* ! Tntum (1). 1000 1000 9.7 x 10' 1000 1000 9.7 x 108 , (compressed)* 1000 1000 9.7 x 108 , (actrvsted lum. nous paint). , (acsorted on sohd camer).- 1000 1000 9.7 x 108 ,(tntrated water) - L 1000 1000 9.7 x 10 , (other forms).- . (... 20 20 9.7 x 10' 182,,. t Tantalum (73) 20 20 8 2 x 108 I Terteum (65). 20 10 1.1 x 10* 18Cn. 96m, ! Technetium (43) 1000; 1000 3 8 x 10' e f 6 8 3 2 x 10' 96,, 97m. L-- 1000 200 1.5 x 10* e 9 7,.... 1000 400 1.4 x 10*

I 100 1(M S 2 x 10' 99m..

r 99,,.. 1000 25 1.7 x 10*

125m,, _

Teilunum (52)- 1000 100 1.8 x 10* 127W. 300 20 4 0 x 10' 127,,. 300 20 2.8 x 10' 129 W. 30 10 2.5 x 10' 129,. 100 20 10 x 10' 131m. 10 10 8.0 x 108 e 132,, 7 7 3.1 x 108 227n. Thonum (90) 200 02 32 x 10' 226n 8 0 008 8.3 x 108 230r. 3 0 003 19 x 10-

1000 25 1.3 x 10' 231n.-

Unhmted Unkmrted. 1.1 x 10* ' ) 232,. 234n. -. 10 10 2 3 x 10' n (natwal).. Unbr,wted. Unkreuted. 2.2 x 10-' l 71 20 August 31,1983 l l l

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL TAsLE A-1.-A AND A. VALUES Fon RADIONUCUDES-Continued i ( (See footnotes at and of table) l g'**hg) Symbos of reconuchoe Element and atome number A.(C) A (C.) 8 ( e,.dr-200n Theihum (81) 20 20 5 8 x 10' 201n 1 200 200 2.2 x 10' 202n. 40 40 5.4 x 10* 20an 300 to 4.3 x to' 170m ' Thuhum (69) 300 to a 6.0 x 10' 171 % 1000 100 i 1.1 x 10'

230s, i Urarwm (92) 100 '

O.1 l 2.7 x 10* 232c 30 0.03 2.1 x to 233 100 0.1 0.5 x 10*

t 234 t.

100' O.1 0.2 x 10*

235.

100 - 02 2.1 x 10" t 236. 200 0.2 6.3 x 10*

t 238s.

Uremated. 'Unhmated. 3.3 x 10" c (naturall Unkmrted Unhmrted ISEE TABLE A-Unkmeted. lUnkmrted l 4)

I*""*"" < 20 % -

i ISEE TABLE A- [ 4) 20% or greater. 100 ' O.1 ISEE TABLE A-l , (depeeted). Uremrted. Uniemsted. [SEE TA8LE A-l 4) . (neestedP" a8v.....-... IVanadium (23). 6' 6 1.7 x 10' " 181 Tungsten (74) 200 1 100 5.0 x 10' a 185.. 1000 25 0.7 x 10* ' 187._ 40 l 20 7.0 x 10' 127. (uncompressedP iXenon 7 127s. (compressed)* L - (54) 70 l 70 2.8 x 10' 3 5' 5 2.8 x 10' O. t31mu (compressed)* [ 10 l 10 1.0 x 10' 131mu (uncomptessedP 100 100 1.0 x 10

133u funcompressedP I

1000 : 1000 1.9 x 10

133u (compressedP.

} 5 1.9 x 10

135u (uncompressedP 135u (compressedP.

y 70 ; 70 2.5 x to

e 2i 2

2.5 x 10 8 8 7,. - ' Yttnum (39) 20 i 20 4.5 x 10 90,.. I 10 10 2.5 x 10

S i m,.

L 30 ' 30 4.1 x t o ' 01,.

l..

30 ' 30 2.5 x 10

92,.

I' 10 ' 10 9.5 x 10 e 93, 10 10 3.2 x to * [Yttertwm (70) 169 80 00 2.3 x 10

n 175v.-

5 400 25 1.8 x 10

65u Inc (30) 30 30 8.0 x 10 8 80mu 40 20 3.3 x to
1 46u 300,

20 5.3 x 10 ' 93, Ircorwum (40)

1000, 200 3.5 x 10* '

3 1 95, 20 1 20 21 x 10

3 97,

20 1 20 2.0 x 10

3
For the purpose of Table A-1 compressed gas means a gas at 4, pressure which exceeds the ame.ent atmosphenc pressure at the locanon where the containment system was closed.

" The vases of A, and A. must be calculated e accordance with the procedure speerned e Appe% A. paragraph 11(3), tatung mto account the actmfy of the fiss.on products and of the uranium-233 m adoton to that of the thonum. "* The values of A, and A m st be calculated e accordance wdh the procedu e spec #.ed m Appends A. paragrapn 11(3). tasung cto account u r the actmty of the fiss.on products and plutornum isotopes e adeten to that of the urarwm. O 71 21 August 31,1983

PART 71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL TABLE A-2 RELATIONSHIP BETWEEN A AND E,, FOR SETA EMITTERS y E,,(Mev) A (Cf) J j ( 0.5 1000 \\ E 0.5 - ( 1.0 300 1.0 - ( 1.5 100 1.5 - < 2.0 30 > 2.0 10 TABLE A-3 O RELATIONSHIP BEikEEN A AND THE ATOMIC NUMBER 3 OF THE RADIONUCLIDE A3 3 Atomic Half-life less Half-11fe 1000 days Half-life greater E Nuncer than 1000-days to 108 years than los years 1 to 81 5 C1 .05 C1 3 C1 82 and above .002 Cf .002 C1 3 Ci l \\ August 31,1983 71 22 1

PART71 o PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL TAsLE A-4.-ACTIVITY Mass RELATIONSHIPS FOR URANIJM/ THORIUM O Thonum enJ ure.*snn M acwly ennchment ' wt % "y present of, ,jg 0.45.. 5.0x10-' 2.0u10' O.72 (nonsel) : 7.08 10*' 1.42x10' 1.0 7.S 10-' 1.310' 1.5 1.0x10-' 1.0x10' 2 5.0 2.7m10-' 3.7x10' E 10.0 48:10-' 2.1x10' a 20.0. 1.0u10-* 1.0m10' , 35 0 2.0u10-' 5.0u10' 50.0 2.5a10-' 4.0x10' 90.0. 5.8x10-' 1.7x10' I 93.0 7.0m10-' 1.4x10' 95 0 9.1x10** 1.1x10' Natural Thanurn 2.2x10-' 4.ta10' s The Agures for uranun eclude representatnre values for the acwty of the uranium.234 wach = concentrated aunne me ennchmere process The acwty for Thonum mcdudes me ognenum nor anersten of Thonwn.239 O 1 I J 71 23 August 31,1983 1 I

w.3-- ~ ~ UNITED STATES NUCLEAR CECULATCRY C7MMISSION RULES and REGULATIONS I TITLE 10. CH APTER 1. CODE OF FEDERAL REGUt.ATIONS-ENERGY d 919.1 g 19.12 PART NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS; 19 iNSeecriONS b ec. 19.1 Purpose.

$ 19.3 Definitions.

k number 3150 0044. 19.2 Scope. As used in this part: $ (b)'lhe approved infoi.uation i 19.3 Defintilons' tal "Act" means the Atomic Energy a collect!on requiremente contained in this I",'[' $I$ $ Act of 1954 (68 Stat. 919) includtlig any y part appearin i19.13. g 19 s n ma t n collection requirements: n" means the 1/nited States m 19.11 Postans of notices to wormers.

m. Nuclear Reguistory Commassaan;

[ 19.11 Poeting of notw, es to worker 19.12 Instructions to workers. R (c) " Worker" means an individual (a) Each Ilcensee shall post current 19.13 Notthcauona and reporta to individ. engaged in acuvities licensed by the Coma copies of the following documents: (1) mission and controlled by a licensee' "F* The regulations in this part and in Part uals. but does notinclude the heensee. 19.14 Presence of representatives of licens. g 20 of this chapter; (2) thelicense.lleense a ees and workers during inspecuona. 19.15 Consultation with workers durtng in. " (d)" License" means a license issued e conditions, or documents incorporated spections. under the regulations in Parts 30 through

into a license by reference, and amend-19.18 Requests by workers for inspections. 35.40.60.61.7o or 12 of this charter.

N ments theretol (3) the operating proCe-19.17 Inspections not warranted, informaa 3 including licenses to operate a dures applicable to licensed activiues: til any notice of violauon involving 19.30 Vloisuona. O production or utilization facility radiological woriting conditions, proposed 19.31 Application for esemptions. E pursuant to Part 50 of this chapter and impostuon of civil penalty, or order 1s. 19.32 Discrimination prohibited.

- licenses to possess power reactor spent sued pursuant to Subpart B of Part 2 of Authenty: Sem.53.63.81.103.104.181.186. O fuelin an independent spent fuel atorage this chapter, and any response from the as Stat.1DO. 933. 935. 936. 93r. 944,955. es instellation (ISFSI) pursuant to Part 72 Itcensee.

amended. sec. 234. 83 Stal 444. as amended of this chapter." Licensee"means the (b) If posting of a document specified (42 U.S C 20?3. 2003 rit t. 213J. 2134. 2201, 2236,22a2). eec. 201, as Stat 1242 es holder of such a license. In paragraph (a) (1). (2) or (3) of this section la not practicable. the licensee amended by Pub. L 96-rs. 89 Stal 413 (42 may post a nouce which desertbes the ~ U.S C 5441 k I4b. L 95-401. sec.10. 92 8 tat, O te) Restricted area means any ares document and states where it may be 2s51 (42 U'S.C 5a51). access to which is controlled by the 11* examined. L/ For the P"# Poses of sec. 223. 68 Saat 958, as censee for purposes of protection of in- = emended (42 U.S C 22?3): 1i 1911(a]. (c). (d), dividuals from exposure to radiation and $h'f' [,',12 c) Each licenace and applicant shall radioactive matenals. " Restricted area". E po(st Form NRC-3. (Revision 6-42 o ~ ,m ed( than not include any areas used as rest and li te.13 aod 19.14{a) are tsoued under "I","j,1 g"o,nual bu di e later)" Notice to Employees." as 8h 'P eec. talo, es StsL eso. as amended (42 U.S C o, 22n[o]F N may be set apart as a restricted area.

required by Parts 30,40.50.00.70,72.

land 150 of this chapter. 5 19.1 l'urpam E g 19.s iniceprei.ii.n The regulations in this part establish R Except as specifically authorized by the Nort: Copies of Form NRC.3 may be ob-requirements for notices. Instructions, Commission in writing, no interpretation tained by wnting to the Director of the ap-and reports by licensees to individuals of the meaning of the regulations in this propriate U.S. Nuclear Regulatory Commis. w participating in licensed activities, and part by any omeer or employee of the slon Inspection and Enforcement Regional E opuons available to such individuals in Commission other than a wTitten in-Office listed in Appendix "D" Part 20 of terpretation by the General Counsel will this chapter, or the Director. Office of In. [ connection with Commission inspections i" of licensees to ascertam compliance with be recognized to be binding upon the spection and Enforcement. U.S. Nuclest o the provtsions of the Atomic Energy Act Commission. Regulatory Commission. Washington, D.C. ' of 1954, as amended. Title II of the En [(33-ergy Reorganization Act of 1974.and reg. ulations, orders, and licenses thereunder I 39*3 d) Documents, notices, or forms regarding radiological working condl. Except where otherwise specified in posted pursuant to this section shall ap. this part, all communtentions and reports pear in a sumelent number of places to J1ons. s g concerning the regulations in this part permit individuals engaged in licensed ""{ 19.2 Scope. g should oe addressed to the Director. Of. activities to observe them on the way to flee of Inspection and Enforcement. U.S. or from any partleular licensed activity The regulations in this part appy to all m Nuclear Regulatory Commission. Wash, location to which the document appliss. g persons who receive, passess. use, or S ington, D C. 20555. Communications, re, shall be conspicuous, and shall be re-transfer materiallicensed by the ports, and applications may be delivered placed if defaced or altered. j . Nuclear Regulatory Commission in person at the Commission's omces at dei commission documents posted

pursuant to the regulatione in Parts 30 1717 H Street. NW., Washington D.C.:

pursuant to paragraph (a)(4) of this or at 7920 Norfolk Avenue. Bethesda, n secuon shall be posted within 2 working throu8h at.40.60.el.tO or 72 of ihas 6 days after receipt of the documenta f rom a Maryland

a chapter. including persons licensed to M the Commission: the Itcensee's response.

= e if any, sha!! be posted within 2 working , operate a production or utilization ]g days after dispatch by the licensee. Such facility pursuant to Part 50 of this eosse w E documents shall remain posted for a o chapter and persons licensed to possess (a) Nuctur Regulatory mirumum of 5 working days or untti ac.., power reactor spent fuel in en independent spent fuel storage n Commisalon Las submitted tl.e tion correcung the violauon has been

" * * 'U"" H"

"'"I'

I" '#'

I ^ '"*"d in this part to the Office of v insf allalion (ISFSij pursuant to Part 72

contetna 8 19.12 In.iruciion e.

orker.. of this chapter' . Managernent and Iludget (OMB) for Allindividuals working in or frequent- '= g approval se required by the Peperwork ing any poruon of a restricted area shall Reduction Act of tes0 (44 U.S.C. 3501 et be kept informed of the storase, trans-seg 1. OMB has approved the fer, or use of radioactive materials or of trdormation collection requirements radiation in such portions of the re-stricted area; shall be instructed in the contained in this part under control health protection problems asacciated i 19-3 January 31,1985 (reset)

g 19.13 Q 19.16(b) PART 19 e NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS: INSPECTIONS (di When a licensee is required pur. sions of this section. Commission inspec. suant to i 20.405 or 120.408 of this chap. tors are authorized to refuse to permit a with exposure to such radioactive mate, ter to report to the Commission any ex. ]ompan e any individual sh rials or radiation. In precautions or pro. posure of an individual to radiation or cedures to minimize exposure, and in the radioactive material the 11censee sha!! orderly inspection. With regard to areas purposes and functions of protective de. also provide the individual a report on containing information classified by an vices employed; shall be instructed in, his exposure data In-f uded therein. Such agency of the US. Government in the and instructed to observe, to the exteng report shall be transmitted at a time interest of national security, an individ. within the worker's control, the applica, not later than the transmittal to the ual who accompanies an inspector may have access to such information only if ble provisions of Commission regulations SOD"nission, authortzed to do so. With regard to any and licenses for the protection of per. <== (c) At the request of g worker who is sonnel from exposures to radiation or area containing proprietary information, radioactive materials occurring in such terminating emplo)1rient in a given the workers' representative for that area shall be an indJvidual previously author. areas: shall be instructed of their re. calendar quarter with the licensee in tzed by the licensee to enter that area. sponsibility to report promptly to the 11 work involving radiation dose. or of a censee any condition which may lead to worker who, while employed by another $ 19.15 Cun.uheilon wo, h workers due. I"8 I"#*"'* or cause a violation of Commission regu. person. is terminahng assignment to 1ations and beenses or unnecessary ex. work insolving radiation dose in th, tal Commission inspectors may con. posure to rr.diation or to radioactive ma.. iscense s fac:ht) en that calendar sult pnvately with workus concuning terial; shall be in.tructed in the appro.

matters of occupational radlauon protec.

cuarter. each hcensee shau pede to prtate respon e to warnings made in the tion and other matters related to ap. event of any unusual occurrence or maj. y each such worker. of to the worku 8 plicable provisions of Commission regu. function that may involve exposure to

designee, at termination a written lations and licenses to the extent the in.

w radiation or radioactive material: and ' report regarding the radiation dose spectors deem necessary for the conduct recen ed by that w orker from operations of an effective and thorough inspection. sha!! be advised as to the radiation ex. of the licensee dunng that specifically ib) During the course of an inspection posure reports which workers may re* identified calendar quarter or fraction any worker inay bring privately to the quest pursuant to 11913. The extent of thereof* or provide a wntten estimate of attention of the inspectors. either orally or in wnung, any past or msent condl. these instructions shall be commensur. ate with potential radiological health that d se if the Imsh. determined Lion which he has reason to believe may protection problems in the restricted personnel monitanng results are not have contributed to or caused any tio.

area, available at that time. Estimated doses lauon of the act, the regulations in this sha!! be clearly mdicated as such.

$ 19.13 Notincations and reports to in. chapter, or license condition, or any un. necessary exposure of an individual to ~ $ 19.14 Presence of repeesentatises of radiation from licensed radioactive ma. ta) Radiation exposure data for an licensees and workers during in pec. terial under the licensee's control. Any ind;vidual, and the resulta of any meas. . tlons. such notice in writing shall comply with o t e mat rial de it d or r, % (a) Each licensee shall aford to the g the requirements of l 19.16(a), ~ N tanned in the body of an individual. shall N Commission at all reasonable times op. g of this section shall not be interp (c) 'Ihe provisions of paragraph (b) C be reported to the individual as specified e portunity to inspect materials, activities, e

in this section. The informattort reported "" facilities, premises, and records pursu. u authorization to disregard instructions N shall include data and resulta obtained N ant to the regulations in this chapter. F I

pursuant to Cornmission regulations, or. I ta.6 Requests by workees foe inspec. (b) During an inspection, Commission ders or license condition,s, as shown in ons. records maintained by the licensee pur. Inspectors may consult privately with suant to Commission regulations. Each workers as specined in I 19.15. The !!. notification and report shall: be in writ. censee or licenseea representative may workers who believes that a violation of ing; indude appropriate identifying data accompany Ccmmission inspectors dur. the Act, the regulauons tri this chapter such as the name of the licensee, the ing other phases of an inspection. or license conditions exists or has oc. name of the Individual, the individual's (c) If, at the time of inspection, an Curred in license activttles with regard to social security number; include the indl. individual has been authortzed by the radiological working conditions in which vidual's exposure information; and con. workers to represent them during Com. the worker is engaged, may request an tain the following statement: mission inspections, the licensee shall inspection by giving notice of the alleged ThM report is turnnhed to you under the pruwp notify the inspectors of such authoriza. ""I"" 8" 'h' D"tur UI Inspection anJ E n-nuns ur the Nudear Regulatory commmuon resu-tion and shall give the workers' repre. forcement. to the Director of the appro-ution to O R ISri 19. You wouu preprve uns report fut further reference. sentative an opportunity to accompany priate Commisalon Regional OfBee, or' to (b) At the request of any worker,each the inspectors during the inspection of Commission inspectors. Any such notice licensee shall advise such worker annu. physical working conditions, shall be in writing, shall set forth the (d) Each workers' representative shall spectAc grounds for the notice, and shall ally of the worker's exposure to radiation or radioactive material as shown in rec

be routinely engaged in licensed activt.

be signed, by the worker or representa. ties under control of the licensee and live of workers. A copy shall be provided ords maintained by the licensee pursu. ant to i 20A0!tal and (c)* shall have received instructions as spec, the Inensed by the Director of Inspesteun and 1Aed in i 19.12 t nfurcement. Regonal OfAe Director, (c) At the request of a worker former* te) Dt!!ererIt representatives of !!. or the inspector no later than at the time ly engaged in licensed activities con

trolled by the licensee, each licensee sr. alt censees and workers may accompany the of inspection except that, upon the re.

furnish to the worker a report of the inspectors during different phases of an quest of the worker giving such notice, worker s exposure to radiation or radto* inspection if there is no resulting inter. his name and the name of individuals sLctive material. Such report shall be fut* ference with the conduct of the inspec. refuted to therein shall not appear in nished wittun 30 days from the time the tion, llowever, only one workers' repre. such copy or on any record published, request is made, or within 30 days after sentative at a time may accompany the released, or made available by the Com. inspectors. misalon, except for good cause shown, the exposure of the individual has been (f) With the approval of the licensee eb) If, upon receipt of such notice, the determined by the licensee, whichever is later; shall cover, within the period of and the workers' representative an in. Ditessur of Inspession and Enfutsemens ut Me-time specified in the request, each calen* dividual who la not routinely engaged Monal Offne Deressur determines that In licensed activities under control of the complaint meets the requirements set dar quarter in which the worker a ac* tivities involved exposure to radiation the license, for example, a consultant forth in paragraph (a) of this section, from radioacuve materials 'icensed by to the licensee or to the workers' repre. and that there are reasonable grounds to the Commission; and shall include the sentauve, shall be afforded the oppor. believe that the alleged violation exista tunity to accompany Commission inspec. or has occurred, he shall cause an in. dates and locations of licensed activittes In uhtch the worker part.ctpated during tors during the Inspecuon of physical spection to be made as soon as pracuca. working conditions, ble, to deter mine Lf such alleged violation this pnM f gl Notwithstanding the other provl. entsts or has occurred. li spections pur. January 31,1985 (reset) 19-2

l 3 919.32 I 19.17 PART 19 e NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS: INSPECTIONS D)

s"/

suant to this secuan need not he limited r g 19.30 Violation I to matters referred to in the complaint. E An injunction or other court order may $ 19.17 Inspections not warrented t in. g be obtained prohibiting any violation of { &ny pronssion of the Act or Title II of f inspection and inforce. the Energy Reorganization Act of 1974 tal lithe r or ment or of the appropnate Regiunal

or any ngulauon or oder MM h-o Office determines, with respect to a com. e plaint under i 19.16. that an inspection kunder, A court b

is not warranted because there are r.o reasonable grounds to believe that a vio* order may be obtained for the payment a lation exists or has occurred. he shall no. of a civil penalty imposed pursuant to tify the complainant in writing of such section234 of the Act for violation of sec. determination. The complainant may tion $3. 67, 62, 63. St. 82,101,103,104, obtain review of such determination by 107,or 109 of the Act or any rule.regula. submitting a written statement of post. tion, or order issued thereunder, or any f. tun with the Esecutne Director for O rat uns. term, condition or limitation of any 11-U.5 Nuclear Retulatory Osmminion. ashing-cense issued thereunder, or for any 910 tun. D.C. 20553. who will provide the bcensee lation for s hlch a license may be revoked j with a copy of such statement by certi. under section les of the Act. Any person i fled mall excluCng, at the request of the who willfully violates any proviston of n complainant, the name of the complain-E the Act or any regulation or order issued thereunder may be guilty of a crime and, ant. The licensee may submit an oppos-rw tw ing written statement of position withthe Esecutne Drector for Ortations who will f upon conviction, may be punished provide the complainant with a cupy of such g or imprisonment or both, as provided by statement by certified mail. L' pun the request

law, of the complainant. the IAccutne Drector for

$ 19.3I APP cat. ion for esemptions. li Operations or has deugner may hold an informal conference in which The Commtssion may, upon applica-the complainant and the heensee may tion by any licensee or upon its own in-orally present their views. An informal itiative, grant such' exemptions from the conference may also be held at the re. requirements of the regulations in this g quest of the beensee, but disclosure of the part as it determines are authorized by twN identity of the complainant will be made law and will not result in undue hazard i only following receipt of wntten author-i g l

- isation from the complainant. Af ter con.

.to life or property. R sidering all written and ora.1 views pre. "l sented, the hecutive Director for Operations $ 19.32 Discriniination proliiliitral. I shall affirm. nndify.or reverse the determina-No person shall on the ground of Sex tion of the Drector of Inspection and 1 nforce-be excluded from participation in, be de-nied the benefits of, or be subjected to coIpla ant and O e d fu sh disernmination under any program or ac-the licensee a written notification of his tivity licensed by the Nuclear Regulatory decision and the reason therefor. Commission. This provision will be en-Ibn if the Drector of intpection snJ Enforce. % forced through agency provisions and ment or of the appropnate Regional Othee determines that an inspectJon is Q rules similar to those already established, 4 not warranted because the requirementa m with lespect to racial and other discrim. Anation, under title VI of the Civl! Illshts of I 19.16(at have not been met, he shall *E Act of 1964 This remedy la not exclu-notify the complainant in writing of such determination. Such determination site, houeter, and will not prejudice or shall be without prejudice to the filing of cut off any other legal remedies avall. a new complaint meettng the requite. able to a discriminatee. l ,ments of i 19168 m). I e suo Empeer preses.n. Employment discrimination by a i e licensee or a contractor or subcontractor I l of a hcensee against an employee for se engaging in protected activities under l "* this part or Parte 30,40.50.80.70.72,or {150 of this chapter is prohibited. l O u 19-3 January 31,1985 (resst)

1 UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS n I e V TITLE 19. CHAPTEA 1. CODE OF FEDERAL.IIEGULATIONS-ENERGY IW g 20.3(a) P STANDARDS FOR PROTECTION AGAINST RADIATION should, in addition to complying with Enronement the requirements set forth in this PART 20-$7ANDAEDS FOR part, make every reasonable effort to PROTECTION AGAINST RADIATION 20 sol violations. ma a a M os m s. W M-Arrrmatz A-Protection f actors for Respirators leases of radioactive materials in el-Orwen at Paovtstons Arranc x B-ConcExtaAttons In Ala AND sec. watra Asovt NatenAt BaCKC9oCnD fluents to unrestricted areas, as low as 20.1 Purpost Arrannix C is reasonably achteimble. The term as 20.2 Scope. Arresnix D-Untite Starts NecLEAR Rtco-low as is reasonably achievable" means Lat av Comssiongunawrness as low as is reasonably achievable n f ramation dose. taking into account the state of tech-20.3 Uruts of radionettvity. 20 6 Interpretauona. Ausbeskyt See, as, es, es, et 10% 104 tel. nology, and the economics of imptove-20.'t commurucations. se Stat ma es3 sea, eso, Mr. set es ments in relation to benefits to the 2 o. 8 Information collection requirements: amended,(42 USC sors, ages,2006,21:n-public health and safety, and other so-OM 8 appraval. 213s, 2134, Sant) esca. 301, se ameedd act' eletal and socioeconomic consider-Prmuissi La Dosts.Levrts AND 30s hb, L es-43% se Stat.1342,134a 13e% RUons, and in rdadon 2 Une uh CometataAttons hb. t., e6-rs, se Stat 413 (as USC sost. hMahkMUMWWW W 20.101 Radaatton done standards for inda. seta, teest terest. viduals in restrteted areas. Poe the pwposee of ese. 333, as Stat est se 20.102 Determination of prtor dose, amended. (42 USC 12rs), il ao 101. satot. I 20.2 Rope. 20.103 Exposure of Individuals to concen. atto3(a) (bl, and (fk aatos (el and (bL trations of radioactive materials in air in satos(bL salon (s),30 act, ac aostek aasas, The regulations in this part apply to restricted areaa. som so act aasas,30 304 and so see m all persons who receive, possess use. 20 104 Exposure of minors-seeued under sec, totb. es Stat see, as or transfer material licensed pursuant 20.105 Permissible levels of radiation in un-amended. (42 US C tact (bik and il aatos, to the regulations in Parts 30 through restricted areas. 30103(ek so oot-an cor. 20 ece(b) and 30 40s I 3 s,e o.60.61.10 er 72 of this chapter. in-20.106 Radioseurity in effluents to untrs-m teoued under eer.1ste, se Stat ena se 3cluding persons licensed to operate a amen d(4 US tapt(o)) et production or utilization facility pur. V 20.107 Medical'diaenosts ano therapy. 'suar.t to Part 50 of this chapter and 20.104 Orders requirtns fumishing of bio. Ocstaat. Paortstows

persons licensed to possess power reae-assay serv 6ces.

3 ;0.1 Purpose. tot spent fuel in an independent spent Pascarrionaev Psoctments fuel storage installation (ISTSD puru-(a The regulations in this part es* sant to Part 72 of this chapter. e to 201 Surveys. g tabhsh standards for protection 20 202 Personnel monitortna. to 203 Caution signs labels, signals and se against radiation hazards arising out E of activities under licenses issued by controts. 20 204 Same: exceptions. the Nuclear Regulatory Commission 20 203 Procedures for picking up, recelstns, and are issued pursuant to the Atomic $ 20.3 ar.d epening packases. Energy Act of 1954. as amended, and 20 206 Instruction of personnel. the Energy Reorganization Act of 8 20.3 Definitions. 20.201 Storage and control of licensed ma.

1974, (a) As used in this part:

tenals in unrestrteted areas. wasts Disposas, '" 40) The use of radioactive material (1) "Act" means the Atomic Energy Act of 1954 (68 Stat. 919) including or other sources of radiation not II. 30 301 General requirement _ 20.302 Method for obtaining approval of censed by the Commission is not sub. any amendments thereto. 4 (2) Airborne radioactive ma proposed d.sposal procedures. Jeet to the regulations in this part.g means any' radioactive material dis-Homeser. It is the purpose of the regu. se 20.303 Disposal by release into sanitary 2 !ations in this part to control the pos. e persed in the air in the form of dusta. senersse systems. E session, use. and transfer of licensed " fumes, mists, vapors. or gas,es; 20.305 Treatment or disposal br inemer. E material by any lleensee in such a S (3)

Byproduct material means any atton.

radioactise rnaterial (except special 20 304 Disposalef specific mastes. $ manner that the total dose to an indl. nuclear material) yielded in or made 20.381 Teansfer for d sposal and manifests. ? tidual (including exposures to licensed a exp r ra Rsecans. Ratonts. aan Nottricatso, ano unlicensed radioactive material g, g y y g pr " I0 uct g or utilizing special nuclear ma-20.4 1 Records f sys, radiation mont-on. het ln e lo o to 402 Reporte of theft or loss of licensed the licensee or any other person, but

matertal, not including exposures to radiation - W " Calendar quarter" means not from natural background sources or less than 12 consecutive weeks nor sec.

20 403 Nottf acations of incidents. medical diagnosis and therapy) does more than 14 consecutive weeks. The 20 404 (Resert ed) not exceed the standards of radiation first calendar quarter of each year $c f,7ts7n ec'n'ce'n't o$s protection prescribed in the regula* shall twin in January and subsequent s anJ e e .tlons in this part.

calendar quarteis shall be such that 20 4t<6 (Reseried) no day is included in more than one

(#} to 407 Personnel monitoring reports. l (C) In accordance t.ith recommenda. calendar quarter or omitted from in. 20638 Reports of personriel morutorant en e= tions of the Federal Radiation Coun. a cil, approved by the President, persons f clusion within a calendar quarter. No termination of emplorment or scrs. engaged in activities under licenses I licensee shall chanse the method ob-20.409 Notificatwns and reports to indmd. served by him of determining calendar

uals,

. issued by the Nuclear Regulatory quarters except at the beginning of a Enestisons as Aantrionu Rzectasumts g Commission pursuant to the Atomic

lend
20 Sol Ancheations for exemptions-Energy Act of 1954, as amended and 20 502 Add.uonal requirements the Energy Reorganization Act of'1974 2qg January 31,1MS (reset)

PART 20 o CTANDARDS FOR PR3TECTITN A"AINST RADIATITN (5)" Commission" means the Nuclear (13) " Radioactive material" inclu E at 1237, 42 U.S.C. 5814) and retrans-Regulatory Commission or its duly su. any such material whether or su thorized representatives; ject to licensing control by tbe C m. E ferred to the Secretary of Energy 7, mission; suant to section 301(a) of the Dep

(6)" Government agency" means any 7

[ ment of Energy Organizatic,n xecutive department, commission in. (14) " Restricted area,, means any,,, (Pub. L. 95-91, 91 Stat. 565 at 577-5h., bependent establishment, corporation, area access to which is controlled by (,42 U.S.C.1151). cholly or partly t,wned by the United, the licensee for purposes of protection States of America which is an instru. " of indhiduals from exposure to radi-g3g),, Termination" means the end mentality of the United States, or any atton and radioactive materials. Re g~ of employment with the licensee or,in ( board, bureau, division, service, office, e stricted area' shall not include any :: the case of individuals not employed f tificer, authority, administration, or

areas used as residental quarters, al E signme by the licensee, the end of a work as-2 (branch of the Government;ther estab!!shrnent in the executive N hough a separate room or rooms in a t

residential building may be set apart -- areas in a given calendar quarter, g (1) "IndMdual" means any human ,,,,as a restricted area; without expectation or specific sched-being; uling of reentry into the licensee's re. * (8) " Licensed material" means stricted areas during the remamder of source material, special nuclear mate- .,, that calendar quarter. rial, or by. product material received, possessed, used, or transferred under a (b) Definitions of certain other general or specific license issued by words and phrases as used in this part the Commission pursuant to the regu-are set forth in other sections, includ- _litions in this chapter; (15) " Source material" means: (1) ing: Uranium or thorium, or any combina-(1) " Airborne radioactivity area" de-g tion thereof, in any physical or chemi-fined in i 20.203; $ cal form; or (11) cres which contain by e weight one twentieth of one percent (2) "Raciation area" and "high radi-

(9) " License" means a license issued a7 (0.05%) or more of (c) uranium, (b) atton tres" defined in i 20.202; (3) " Personnel monitoring equip-

under the regulatfor,s in Parts 30 thorium or (c) any combination there-of. Source material does not include ment" defined in i 20.202; y through ss,40,60,61,70 er 72 of this a chrpter. " Licensee" means the holder special nuciene material.

(4) " Survey" defined in l 20.201;

cisuch license.

(5) Units of measurement of dose trad. rem) defined in i 20.4; ~ (6) Units of measurement of radioac. tivity defined in i 20.5. '" (10) " Occupational dose" includes exposure of an individual to radiation 5 20.4 11 nits of radiation dose. (1) in a restricted area; or (11) in the (16) "Special nuclear material,, gg),, Dose," as used in this part ,, c::urse of employment in which the in-means: (1) Plutonium, uranium 233, the quantity of radiation absorbed, ' e. g dividual's duties involve exposure to uranium enriched in the isotope 233 or

unit of mass, by the body or by any radiation, provided, that " occupational y m the isotope 235, and any other ma 6 portion of the body When the regula-2 dose" shall not be deemed to include 5 terfal *hich the cornmisslon, pursuant.e tions,in,thi,s part speelf,y a dose during N any exposure of an individual to radi-e to the provisions of section 51 of the g,otal quantity o

,,,,, tim,, 13,,,,,,,,, 13, cti:n for the purpose of medical ding.

act, determines to be special nuc! car t

nosis or medical therapy of such indi. R material, but does not include source per unit of mass, by the body or by ,,.yldual. material; or (11) any material artificial. any portion of the body during such ly enriched by any of the foregoing period of time. Several different units (11) " Person" means: (1) Any individ-but does not include source matulat of dose are in current use. Definitions ual, corporation, partnership, firm, as. of units as used in this part are set soclition, trust, estate, public or prf-(17) " Unrestricted area" rneans any forth in paragraphs (b) and (c) of this v:.te institution, group. Government e{by the licensee for purposes section. area access to which is not controlled (b) The rad, as used in this part, is a AUncy other than the Commission or M., the Department (except that the De e tion of individuals from exposure to measure of the dose of any fonizing ra-radiation and radioactive materials, diation to body tissues in terms of the partment shall be considered a person *R and any area used for residential quar cithin the meaning of the regulations energy absorbed per unit mass of the I ltles and activities are subject to the 11. { ters. tissue. One rad is the dose correspond-in this part to the extent that its fac1]. U ing to the absorption of 100 ergs per 2 censing and related regulatory author. gram of tissue. (One millirad F lty if the Commission pursuant to see-(18),' Department,' means the De* (mrad)= 0.001 rad.) tt:n 202 of the Energy Reorganization partment of Energy established by the (c) The rem, as used in this part, is a Act tf 1974 (88 Stat.1244)), any State. Department of Energy Organization measure of,the dose of any lonizing ra. any foreign government or nation or Act (Pub. L. 95-91, 91 Stat. 565, 42 diation to body tissues in terms of its any political subdivision of any such U.S.C.1101 ci seq.) to the extent that estimated biological effect relative to a 1 givernment or nation, or other entity; the Department, or its duly authorized dose of one roentgen (r) of X rays. (One millitem (mrem)= 0.001 rem.) and (11) any legal successor, repre. representatives, exercises functions sentative, agent, or agepey of the fore- ; formerly vested in the U.S. Atomic The relation of the tem to other dose i units depends upon the biological %,3g,

Energy Commission, its Chairman,

- members, officers and components and effect under consideration and upon l ~ (12)" Radiation" means any or all of f transferred to the U.S. Energy Re-the conditions of irradiation. For the th) f;11owin } gamma rays,g; alpha rays, beta rays, ; search and Development Administra-purpose of the regulations in this part, X. rays, neutrons, high. 9 speed electrons, high. speed protons, tion and to the Administrator thereof any of the following is considered ts et and ?ther atomic particles; but not pursuant to sections 104 (b), (c) and be equivalent to a dose of one rem: (1) A dose of 1 r due to X-or 1 (d) of the Energy Reorganization Act { sound or radio waves, or visible, in-of 1974 (Pub. L. 93-438. 88 Stat 1233 gamma radiation; frared, or ultraviolet light; (2) A dose of I rad due to X. gamma, or beta radiation; December 30,1982 20-2

PART 20

STANDARDS F2R PROTECTICN ACAINST RADIATIEN (3) A dose of 0.1 rad due to neutrons I 20.4 Interpretat one, f use any

~ , tg,ece e i y pedo ! ne (N or high energy protons. Except as specifically authorized by 3 calendar quarter from radioactive ma-4 \\ es j the Commission in mTiting, no inter " terial and other sources cf radiation a hes'l t an p otor s with fi a of ~ pretation of the meaning of the regu

m. total occupational dose in excess of ye I t more conv le t go E lations in tais part by any officer or g the standards specified in the follow-ure the neutron flux, or equivalent, lQ employee of the Commission other Ling table:

than to determine the neutron dose in than a written interpretation by the rads, as provided in paragraph (c)(3) General Counsel will be recognized to Haus na CattwoAn Quanita of this section, one tem of neutron ra _be binding upon the Commission. distion may, for purposes of the regu-s ' g g Z",,7p*7 7 lations in this part, be assumed to be = ,a..wa,.. - e *w e,s.~.. - ia*. equivalent to 14 million neutrons per IC 3 sw os.w noe aquare centimeter incident upon the 5 20.7 Communications. I.,_ N body; or, if there exists sufficient in-Except where otherwise specified in A formation to estimate with reasonable this part, all communications and re. (b) A licensee may permit an individ/c accuracy the approximate distribution ports concerning the regulations in in energy of the neutrons, the incident ;! this part should be addressed to the :. ual in a restricted area to recene a 4 total occusa*.lonal dose to the whole number of neutrons per square centi ; Executive Director for Operations, body greater than that permitted meter equivalent to one tem may be a U.S. Nuclear Regulatory Commission, a under paragraph (a) of this section, estimated from the following table:

Washington, D.C. 20555. Communica I provided:

I NeuTaow Flux Dost EcurvaLENTS tions, reports, and applications may be ' (1) During any calendar quarter the delivered in person at the Commis-total occupational dose to the whole = l M7., g Washington, D.C.: or at 7920 Norfolk -body shall not exceed 3 rems; and sion's offices at 1717 H Street NVI., y,,y,

agg
Avenue, Bethesda. Maryland.

- (2) The dose to the whole body, g '"***8* '.w.m,o e, ews when added to the accumulated occu- " g '*, *

7 ' k,.

pational dose to the whole body, shall ee gseA basermemenesessmen not exceed b (N-18) rems there "N" r reaperesnente: Oess approveL equals the individual's age in years at M (a)De Nuclear Regulat his last birthday; and o oes ~ ]M sa.io*! s7o f%==laalon has submitted (3) The licensee has determined the i o ca laformation co!!ection requirements g individual's accumulated occupational soc. ic a ' no N. ~ -]

'9' contained in thle part to the Office of

, dose to the whole body on Form NRC-4 or on a clear and legible record con. ! a,nning a!! the information required in r e Management and Budget (OMB) for t as n. io * ' no ePproval as mquimd h the Peperwd g that form; and has otherwise complied O, s o _.

n.. io

Reduction Act of tse0 (44 U.S.C. 3801 st is a. io. '

it is _ re. 'e

it seq.). OMB has approved the with the requirements of $ 20.102. As i,o used in paragraph (b), " Dose to the information collection requirements whole body" shall be deemed to in, contained in this part under control clude any dose to.the whole body.

(d) For determining exposures to X number 3190-0014. gonads, active blood. forming organs, or gamma rays up to 3 Mev, the dose (b) De approved information head and trunk, or lens of eye, limits specified in il 20.101 to 20.104, 4 collection requirements contained in thle inclusive, may be assumed to be equiv E part appear in il 20.10L 20.103,20.106, alent to the " air dose" For the pur* " atL108,20.203, atL206,20.302, atL811. I 20.102 Determination of prior dose. pose of this part " air dose" means that E 20.401,20.402,20.403, 20.406,20.407, (a) Each licensee shall require any the dose is measured by a properly

calibrated appropriate instrument in

' 20.408. and 20.40s. Individual, prior to first entry of the (c)This part contalas information individual into the licensee's restricted air at or near the body surface in the collection requirements in addition to area during each employrnent or work , region of highest dosage rate. those approved under the control assignment under such circumstances number specified in paragraph (a) of this that the individual will receive or is section. Theee information collection likely to recette in any period of one I 20.5 l' nits of radioactivity, requirements and the control numbers (a aqa an o eu ona ose (a) Radioactivity is commonly, and under which they are approved are as for purposes of the regulations in this ICIIOW8-ble standards speelfled in i 20.101ta) part shall be. measured in terms of dis. (1)In $120.101 and 2tL102. Form and i 20.104(a), to disclose in a sTit. X integrations per unit time or in curies. NRC-4 is approved under control ,, ten, signed statement, either: (1) That

the individual had no prior occupa-N I II" I '

y'0F8 NRC41s

ti nal dose during the current calen-

One curie = 3.7 x 10 disintegrations h' per second (dps)= 2.2 x 10'8 disintegra.

approved under'controt number 3130-I amount of any occupational dose a dar quarter, or (2) the nature and tions per minute (dpm). Commonly used submultiples of the curie are the 0006. thich the individual may have re-millicurie and the microcurle: ceived during that specifically identi. l = (1) One millicurie (mCl) 8- 0.001 Prmurssistr Dosts, Lrvrt.s AND fled Current Calendar quarter from j curie (Cl) '- 3.7 x 10' dps. C6cawtoNa a urces of radiation possessed or con. (2) One microcurie 4Cl) '=0.000001 trolled by other persons. Each heensee , curie = 3.7 x 10 ' dps. g 120.101 Radiation dow standards for in. s au maWa m ords d a d s h 2 ments until the Conunisse aho dividuals in restricted areas. ises their disposition. a (a In accordance with the provisforu (b) Before permitting. pursuant to M LDeleted 40 FR $0704'I of I 20.102(a), and except as provided i 20.101(b), any indiddual in a restrict. a \\ te) ipeseted it FR 21990 1 in paragraph (b) of this section, no 11 ed area to receive an occupational ra. ) censee shall possess, use, or transfer 11 diation dose in excess of the standards i censed material in such a manner as to specified in i 20.101(a), each licensee 1 a shall 20 3 May 31,1984 i m, _. _. ~..

PACT 20

STANDARDS FOR PROTECTION AGAINST RADIATION (1) Obtain a certificate on Form O

NRC-4. or on a clear and legible record containing all the informatic7 { required in that form. signed by thw Individual shoains each period of te.

after the individual attained the age of 18 in which the individual receive 1 as occupauonal dose of radlauon: arv.

l co(rdance with the instructions appear.

2) Calculate on Form NRC-4 in ac.

f Ang therein. or on a clear and legible g record containing all the inforznation required in that form the previously Accu 2Bulated occupational dote re-ceived b.v the individual and the addl. tional dose allosed for that individual under i 20.101(u,. (ex1) In the pseparation of Form NRC-4. or a clear and legible record containing all the informadon re. quired in that form, the licensee shall make a reasonable effort to obtain re-ports of the lodjvfdual's prestously ac-cuinulated occupational dose. For each period for which the licermee obtains 1 I l ) i l 1 O V l l l 1 20 3e Mey 31,1944

i PART 20 o STANDARDS FC] PCTECT12N ACAINST RADIATi^N such reports the Idensee shall use the trancer as to permit any induloualin would result ficm Inhalation of such dose snom'n in the report in greparing a restricted ared to ir. hale a quantity material for 40 hours at the uniform the form _ In any case where a licensee of such material in excess of the ' concentrations spectfled in Appendix is unable to obtain reports of the it.di-in*ake hmits spee!!!ed to Appendix B. E,

Table 1. Column 1 as is rea.sonably vidual's occupationaJ dose for a previ, Table !. Colurnn 3 of thJs part. If such.achleycle. Whenever f.he intake of ra-ous cornplete calendar quarter, Jt shall soluble utarJLam ts of a form such that dioactive staterial by any individual be assumed that the 13alvidual ha.s re-abscrption through the skin is IJkely, O exceeds thts 40. hour control escasure, s.tived the occupational dose specified it.dandt.at esposures to such material r the Ucensee shall make such evalua-in Chichever of the foljoring columns shall oe controHed so that the uptake tjons and take such actior.s as ue nec.

apply; of such snaterial br any organ ficm

enary to a,uure against recurrence.

either inhalation or absorption or The liceruce shall. maintain records of cm u Ca *8-both routes of intake

does not eacted such occurrences, evalcations, and ac.

eU?C',, that which would result from inhaling tior.s taken in a clear and readily iden-

E*

such tr. sternal at the Emits specified in tdjaMe fom sWtaWe for s-ny e g JQ C Appendix B. Table I. Column 1 and e revlew and evaluatioo.

Pwe e factncte 4 thereto, l. e i. i%7 (3) For purposes of determining a

compliance with the requirements of (c) Wa rnptntyy protsch.n one. l E we see this secticn the licensee shall uAe suit. '945'at ***d "I'8ut th* iaM*uen '"" *'ame able measurements of concentrations or strborne rednecthe as terial % U ~" "~~ anraphM of tMs of radioactive materials in air for de.~ pimant t]e canon sha2 Lee supW n,- tecting and evaluating airborne radio secus th acurity in restricted areas and to addi-that is cerufied at had carnestson tion, as appro;riate, shall tase meas g extended by theNationalicsuiate for [ (2) The lleensee shaU retain and pre. t;tements of radioactivity in the body, O Occuperionsl Esfety and Huhk/he measurements of radfoactivity excret. Esfety and Health Admi.njettstoon

serse records used in preparing Tcfm ed from the body, or any combination (NIOSH/1,GHA). The licenses may NRC-4 until the Ccmmluton author-1ses their d;sposition.

of such measurerrents as may be nec. make allownce for this un of ensary for timely detection and assess-f88H'*'CfY Protective eq.cptnent la esmaatire exposvres of kedwid.als to grcent of Individual intakes of rasjcac, ,,titity by exposed individuals. It is as-this e stertal psovided tr.at;

cmed that an individual inhales ra.

If cClculation of the individual's accu-E;dioacthe resterial at the airborne con- ,8 e n sp n f trs inulated occupatienal dose for au peri- ; centration in shich he is present gja', j e{ra ods prior to January 1,1961 yields a unless he uses respiratory prt,Lective

g. result higher than the applictble accu-son absorsuon and intk;avon. the total eq1.ipment pursuarnt to parngraph Ic) intske perrr.itted as twice that which sou!d 2 mul:ted dose valate for the individual of this section. When asseument of a

res.nlt from Inhafation elone at the concen.

g as if that date. as specified in para-particular indwidual's it,take of radio-2 trauco spec 1hed for H 3 $ m 4cpenda B. l graph !b) of I 20.101. the excess may acme matmal is necessary. Makes ; Taoe !. Column a W H M.rs per week for be disregarded. less than those thich would result = 13 *eess. from inhajaticn for 2 hours in arty ont ; 'For radon 222 the lunatme Guantity is ~ day or for 10 hours in any cne week at th.at inhaled in a perico af one calendar 8 20.103 Esposure of individuals to con. uniform concentrations sp*cJ)ed in Ij*[b-tb $ sin 8g t$the t centrations of redsonctive materials an Appendix D. Table I. Column 1 need the concentrauon tatue specified as pased cir in restricted areu not be included in such assessment, protided thr.t for any assessment in upon nposare to the matertal as an uter. (3x1) No lleensee sha!! possess. use* cr transfer heensed matereal in such a eacess of these amounts the entire nal radisuu sarce.1r.dnwuai nposwn to arr. unt is included-these enaterials may be accour;ted for as manner as to permit any indn. dual ttt cart of the limitat,on on nr.dn1 dust dose in 0 restricted area to inhale a quantJty ib)f!) The licenser shall, as a precau' l 20101, These nucides sna!! he suNert to tionary procedure, use process or tr.e precauuonary procedures required by cf radioactive matettal in any period (f Cne calendar quarter gTeater than other engineering controls, to the 8 20 :03/bx1 A extent practicable to lirnit concentra- 'Mulus.ly the ccr.ty ntrauort va'ues spect-the et.ar.tity shich sould result from tior.s of rad.oactive materials in air to fi d 18 APPendJa B. Table I, Column 1 by inhilation for 40 hours per seek for 5.'3 = to'rr.1 t6 obtain the guarter;r uvantity levels below those which dellinit an 13 teeks at uniform concentrations of radioactive material in air specified in airborne radioactivity area as defined M W.uoly *h ronemrauon salue spa-M in spam B. Taw f, cola.mn 1. ty in 120 203(dH1Hil)'precticable to apply A,9endix B, Table I. Colurnn 1. 'is }f (2) When it is im I tfor r 222 the radjoactive material is of such process or other engineering contrais '64rruf cant antaae ty insesuon or injee. firm that intake by absorption to limit conctntrations of radioactive uen is presarned to occur orJy u a restilt of through the skin is 12kely, individaal material in air belos those deftned in esreumstances such as accident. Inads er. c posures to radioactive material shall i 20.203(dH1Xill, other precautionary tence poor pricedure, or stir.nar avecial be controlled so that the uptake of rg. procedures such as incretard survell-cond.tlons. Such tr:tases must be evaluated [ dioactive material by any organ from lance, limitation of working tirnes, or ',d or by ques roe g Cither inhalation or abacrption or provision of respiratory protective stancu of the occurrence-E.sposuru ao ar both routes of tritake " it' any calen, egulpment, shall be used to maintain evaluated staatJ be included in uterminins dar quarter does not exceed that intake of radioactive material by any shether the tunitation oc and.od aJ expo-U Chich would result from inhaling such (ndhidual within any period of seven sures an I sol 03(aMID riu been escreed radioactive matertal for 40 hours per consecutive days as f ar below that

Jtegulatory svidance on saaeurnent of (n.

seek for 13 weeks at untform concen-intake of radioactive material which dmdua) totates of radicaruve materiat ;e tiven in Regulatory O.ide a 9. ' Acceptable trations specified in Appendis D. Concepts. Models. Equations and Assump. TF 5!e I. Colurr.n 1. nons for a s,oa.anay Program," sussle copies (2) llo Ik.nsee shall possen

r. or of *Neh are siaalable from tr'e office of transfer traxtures of U 234. U-235. and standards pe,elopment. US. Nuetest Retu.

U 238 % soluble form in such a L*torF Conane'm. Wuhmston. D C. 20363, upon written reput. S 41 ember 1, l982 2M i

~ w + ~ PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION r(

(t)ne licetsee selecterespiretrey $oes spoo6ed la Appendia A et be fc) Tbe provisions of i$ 20103(b)(2) I past locEng and asles feepir*terY and 20.103(c) sha!! apply to exposures 's prot F tr protecto, equipment. e Conselsetoa k subject to paragraph (b) of this sec. may authoMae.e hoeases to see hifter g Hon except that the references in protection facam se q d an i120.103(b)(2) and 20.103(d) to Appen-a r oet v me aa e ne siluotice wtrWr.g arw are espected to exceed h epPlueden(1)= _. forhieber ,d!E B. Table I. Colurnn 1 shan be for which e seed smote , deemed to be references to Appendia valees specified in Appenda B. Tame L o Ca'uan 1 of fale part.%e equipment es ' pegectfoo factore, and D) deeMmetrohg B. Table !! Colurt.n 1. l eclected shall be used to that the that the raspiratwy potecove

WIPa**Heill rovide 6ese W P

oversge concestrasce of rahtive amatertal to the aft tast is inhaled darmg pickectos facts lader de propeeed I any period of kr.inferry ted use in as 3 ocoMoss of nee. 120103 l'armissinle leeela of radiation le; ,, airberas raduettivity area en any day. 1 (e)Where e@Pavet e a r@ 3 by anyIrd vioaalut the equipment. " type has not been Inted 4A*C ,,,,,g,g,3,g,,,,,, (a) There may be included in any ap-y{n t e e ame a 8 Toole L Col 1f e NIO eve le so p g e p p p g p . part For the purpous of tus peregraph. , en!stsr.g schedule for test els of sacation in unrastricted

Ine concentration of reloar.tive 2 owghges of corsa5n egulpesent, the mas yesulttr.g trotn the appucanta matettal.In @.e att that la Lesled when licoee shd not spake allewanos for this epipsest wttbeat specific posseaston or use of radiosctive Inste.

ruptretcre are woen may be ut.sieted by dividirg the siebiar.t concentration is f authoruagon by the Coeuninion. An rfal and other sources of radiation. e air I,y the protectica factst encified La " applicaten for this oathertsation meet Such appucations should include in-Append.s A of tnie part.If the equure inclade e descne'sden by teettag,or !ormation as to antic 44tetl at erage"n. le Leter fesad to be greeter than octhe beeis of edeble testlafwasah (Jatir.n levels and antfcipeted occupan. wiimated, the cortseted va!ss shall be met the meterial and performaace cy times for esch unrestricted area in-esed, if the esposure to later Nnd to be sharecem9ses.of b equiposet see volved. The Cocunlaston wal aDprose less than estineted, the corrected value cepble ofproeldiedthe proposed W prwd Unius !! the apphnt may be used-doyee of potecuos under esticipated dmonstrato N W proposed urnits (2) ne licate, e A.eintains ami esod;dcas of use. are not hkely to cause any individtaal impleman's e respirotory protectica m "ut most bt has been to rmhe a dose to W whole body m program that in:!udn. as a trJrAn* spectfl cornfed er had sem8 cation ""# #*f6 5 . air eaetpling Wticleat ta identily the emtended esorgency see by NIOSif/ g 3 pt authortred by the o used se amuseen !Coruusalon cursuant to paragraph tal on an e e teea o e. servrye and basassafe es appropriets to },, gg, werwee statt nottry. in writ. ,of this sectjon. no licensee shall pos. evaluate actua! empoemres, wrinan set the Dtreece of trie oppropriate Nu.

- sess, use or tracsfer Ucerned tasterial l

proceda es regarhs selectaan, fitting. clear Let.nlaurr communen Inspection ICin such a Ir. ant.et as to create in any and me;rttenance of respiratore, and ar.d Er.rorternere netterial Ortee luted ut. restricted area frofn radjoactJve ma. testag af reeptretore farspersbkry in amno D at lent H 'e terial and other sources of ratation in as t r u e es 7,rus secuenly M pmessu lammedsetely p.ior to each use; wntten , th,,,,,gg,,,, W Rsdiaucn lete.'s Wch If an in6 peacedures regardmg upervision ar.d vidual were continuously present in trabhs os pereorsseland luuance records; and deteeminettee by a the area, could result in his rece. ting a phpician prior to initial use of dose in excm of two mLWms in any ruprotore. and ot tee nt every 12 te ssihe one heur.or 6ereafter, that the irdvklaal user le (2) Radiation levels rhlch. If an indi-, 6 20.t44 Espoem oNnors. physicMiy able to use the mqstatory v! dual were continuoasly present tc prslecuve equipenent. f a) No licensee sha;l possess. use cr the ares, could rtsult in his receiving a DJ A ornites po!!cy staternert on transfer licer. sed thaterial in auch a dore in excera of 100 mi'tiretas in any reeptretar usese abeil be Lesued coverir,5 mannet as to cause a y indivi al seven cor.secutive days. 4

tthin a tertricted area who ja under euch thines es. nee of prac a e IB years of age, to retelve in any (c)ln addition to other reguirements esynnnr4 coctr s Lnetu roepJretors: roar.ne scaroutlpe, period of one calendar Guarter frtm 3 of this part, heeruees er.gased in ura.

u8e ef resp' Jews. ang radioactive material and other sourtes 2 nium fuel cycle operaticns subject to caertenyroepitette noe mad @sf fnes .of radiation in the latensee's posses.

the provisfor.s of 43 CFR Part 150 e

penods e galon a dose in escets of 10 percent of j the hmits specifieti in the table in."Er.visonmental Radiathn Protectior$ reepfsetor use. The heer.see shMI adesee

Standa.rcs for Nuclear Power Oper.

esca respirator aaer that the near mer paragraph,(a)cf H0.101. logggogg,

sha.1 comply with that part g

les vs the eroe et any ama fet rekel frees tb) No heenste shall posseas. u4e cr ) reeptreur use la the ennt of etpipment 1C transfer licertsed material in such a ) malfunctiaa. pbrotc4t orpeytholog' cal mantier sa (o cause any v.duldual s 20.106 Jtedicactivil; la effluems te un. destress. procedural or commulcation al',hin a restricted artt. who 18 under restrkted areas. fallare olysihcaat deteriorettet e! 18 years of age to be esposed to air. (s) A licettsee shall not tsosess. use. opererbis condabons. or eoy other borne ra.daoactise rnattrial poueued of transfer heer. sed materta! 10 as to sendiuon that mushisopire such rebel by the IJeer.see in an sterage ccncen. I release to an unrestricted ares radicac. l N) ne tscensee uses equayment tration in excess of the tunits specifled 3 va sr.aterial in concentratbns which tt arlihin bmitstionsfor type and une of in Arpendiz B. Table IJ cf thM pt.rt. j excee:S the lismta speckhed in Appen-4 see end provides proper vie 6el For purposes of this paragraph con

a diz.B, Table !! of this part, except as corcentncetion, and other speciel cetttrattorasinay be averased over part.
author 3rd pursuar.t 8.o l 26.M2 or 1

cepebthtles (s.sch as adequate enin . id.s not greater than a seeL E paragraph ib) of this section. T'or pur. J b protecuor) whett needed. pcses of thas sectlen concentrations 4 ( (d) LJalen othwwtae esbr(sed by msy be averased over a petlod not i * . b Gamiselon. ee 1&osease aball tot treater than one year. l naelan protect &oo f 6ctCes la essees of 204 Septerrber L 1982 1

4 PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION A"[DU centrations of radlonuclides.

PaccAUTroMany Psoctavar.s 9 may ine ud pro e limits higher than those specified in A ducrip i n of e waste treat. = paragraph (a) of this section. The ment facilities and procedures used to 8 20.201 Surveys. g reduce the concentration of radlonu. Commission will approve the prop > sed clides in effluents prior to their re. (a) As used in the regulations in this 11 mats if the app!! cant demonstratts-lease. s.*the radiation hazards incident to theart. "s Z - (1) That the app!! cant has made a (d) For the ptArposes of this section reasonable effort to minimite the ra. the concentration limita in Appendix Eproduction, use, release, disposal

O' i

dioactivity contained in effluents to B. Table II of this part shall apply at gpece d rahaethe maWials or 7 7 unrestricted areas; and the boundary of the restricted area. ther sources of radiation under a spe. _) aa (2) That it is not likely that radioac. The concentration of radioactive ma. "cific set of conditions. When appropri. tive material discharged in the efflu. terial discharged through a stack. pipe ate, such evaluation includes a physt. 3 ent would result in the exposure of an or similar conduit may be determined cal survey of the location of materials individual to concentrations of radio. With respect to the point where the and equipment, and measurements of _4-active material in air or water exceed. materialleaves the condult. If the con-levels of radiation or concentrations of ing the limits specified in Appendia B. dult discharges a1 thin the restricted radioactive matertal cresent. Table 11 of this part. A trea, the concentration at the bound-(c) An application for higher limit.s 4 ary may be determined by applying pursuant to paragraph (b) of this sec. ; persion, or decay between the point of appropriate factors for dilution. dis. tion shall include information demon. m f(b) Each licensee shall make strating that the applicant has made a g discharge and the boundary. -cause to be made such surveys as (1) reasonable effort to minimb the ra. (e)In addition to limiting concentra. ;am,y g necessary for the licensee to dioacthity discharged in effluents to tions in einuent streams, the Commis. ;compIy alth the regulations in this unrestricted areas. and shall include, sion may limit quantitles of radioac. hpart, and (2) are reasonable under the as pertinent: Live materials released in air or water preumstances to evaluate the extent (1) Information as to flow rates, during a specif!ed period of time if it of radiktion hazards that may be pres-total volume of effluent, peak concen. appears that tha daily intake of radio-ent. tration of each radwnuclide in the ef. active material from air, water, or food fluent, and concentration of each radi. by a suitable sample of an exposed if0.202 Personnel n'onitoring. onuclide in the effluent averaged over population group, averaged over a a period of one year at t! e point period not exceeding one year, would (a) Each licensee shall supply appro. where the effluent leaves a stack, otherwise exceed the daily intake re, priate personnel monitoring equip-tube. ptpe. or similar condult; sulting from continuous exposure to ment to, and shall require the use of y (2) A description of the properties of alr or water containing one third the such equipnient by:

the effluents including:

concentration of radioactive materials (1) Each indhidus! who enters a re-ll (1) Chemical composition; specified in Appendix B. Table II of stricted area under such circumstances ~ (11) Physical characteristics, includ. this part. = that he receives, or is likely to receive. ) m.ing suspended solids content in UQuid a dose in any calendar quarter in

effluents, and nature of gas or aerosol excess of 25 percent of the applicable

!cr air eifluent ; ~ (f) The provisions of paragraphs (a) value specified in paragraph (a) of ( 111 ) The hydrogen ton concentra. through (e) of inis section do not i 20.101. tions (p") of liquid effluents; and apply to disposal of radioacilve materi. (2) Each individual under 18 years of (iv) The size range of particulates in ; al into sanitary sewerage systems, age who enters a restricted area under = effluents released into air.

which is governed by 1 20.303.

such circumstances that he receives. (3) A description of the anticipated - (g) In addklon to other tequire. or is likely to receive, a dose in any cal-human occupancy in the unrestricted g ments of this part, licensees er. gaged endar quarter in excess of 5 percent of area there the highest concentration. in umnium fuel cycle operations sub. Ithe applicable value specified in para-of radioactive material from the efflu.

ject to the provisions of 40 CFR Part Erraph tal of i 20.101.

e ent is expected, and. In the case of a 190. " Environmental Radiation Protec- ~ a (3) Each individual who enters a 5 river or stream, a description of water tlon Standard for Nuclear Power Op- ' high radiation area. uses downstream from the point of re. erstions." # hall comply with that part. R (b) As used in this part. lease of the effluent. = (1) " Personnel monitoring equip. (4) Information as to the highest concentration of each radionuchde in 6 20.107 Sledical diagnosis and therapy. ment" means devices designed to be an unrestricted area. Including antici-pated concentrations averaged over a Nothing in the regulations in this worn or carried by an individual for the purpose of rocasuring the dose re. period of one year" part shall be interpreted as limiting ceived (e.g., film badges, pocket cham-E (D in air at any point of human oc. the intentional exposure of patients to bers pocket dosimeters. film rings. radiation for the purpose of medical cupancy; or ege,3; diagnosis or medical therapy. (11) In water at points of use down-(2) " Radiation area" means any 2 stream from the point of release of 8 20.108 Orders requiring furnishing of area, accessible to personnel, in which the effluent. bio assay sersites. there exius ndfatim orighting in whole or in part within licensed mate-(5) The background coricentration of Where necessary or desirable in radionuclides in the receiving river or g order to aid in determining the extent rial, at such levels that a major por-tion of the body could receive in any stream prior to the relesse of liquid ef. f of an indhidual's exposure to concen. one hour a dose in excess of 5 mil-fluent. trations of radioactive materal, the litem or in any 5 consecutive days a, i'1 g (6) A description of the environmen. Commission may incorporate appro-dose in excess of 100 millirems; tal monitormg equipment. including priate provisions in any license, direct. sensitivity of the system, and proce. ing the licensee to make available to (3)"High radiation area" means any area. accessible to personnel. in which 4 dures and calculations to determine the individual appropriate bio-aasay there exists radiation originating in concentrations of radlonuclides in the services and to furnish a copy of the shole or in part sithin licensed mate-n unrestricted area and possible recon. reports of such services to the Com. mission. rial at such levels that a major portion d of the body could receive in any one j hour a dose in excess of 100 millirem. m September 1,1982 20-6

PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION

" (11) Be equipped with silditional con

I i

(2) Each entrance or access point ta trol devices such that upon failure of r l a high radiation area shall be: the entry control devices to function (D 'Aquipped with a control device as required by paragraph (cX6xil of 1 which shall cause the level of radi-this section the radiation level within ~ ation to be reduced below that at the area, from the sealed source, shall 0 30 303 Caution signs, labels, signale and which an individual might receive a be reduced below that at which it

- - *3**

dose of 100 millitems in 1 hour upon would be possible for an individual to y ea entry into the area: or (a) Generst (1) Except as otherwise hc r* an e udib l authorised by the Commission, sym. (11) Equipped with a control device alarm signals shall be generated to bols prescribed by this section shall which shall energise a conspicuous make an individual attempting to 1 use the conventional radiation caution visible or audible alarm signal in such enter the area aware of the hasard l colors (magenta or purple on yellow a manner that the individual entering and the licensee or at least one other j background). The symbol prescribed the high radiation area and the licens-individual, who is familiar with the ac-by this section.is tile conventional ee or a supervisor of the activity are ? tivity and prepared to render or three bladed design: made aware of the entry; or g summon assistance, aware of such fall. (111) Maintained locked except during ure of the entry control devices. Rastation snssob periods when access to the area is re f (111) Be equipped with control devices quired, with positive control over each y such that upon failure or removal of

1. Cross hatched area is to be masenta or l

purple, individual entry.

l physical radiation barriers other than the source's shielded storage container

2. sacarround is to be yellos.

(3) The controls required by para-the radiation level from the source graph (cM2) of this section shall be es-shall be reduced below that at which it 8 Stablished in such a way that no indi-

- "3d D' '***3"I' "' "" A"d*d"*I **

'{ [ 60 h Evidual will be prevented from leaving a receive a done in excess of 100 mrem in ghtsh radiation area. one hour; and visible and audible I g (4) In the case of a high radiation alarm signals shall be generated to I area established for a period of 30 make potentially affected individuals g8 days or less. direct surveillance to pre

aware of the hasard and the licensee t

t { vent unauthorised entry may be sub-or at least one other individual, who is atituted for the controls required by familiar with the activity and pre-J paragraph (cM2) of this section. pared to render or summon assistance. (5) Any licensee, or applicant for a 11 Aware of the failure or remtwal of the ,l cer e. may apply to the Commission physical barrier. When the shield for I ( we e for apl:roval of methods not included the stored source is a liquid, means shall be provided to monitor the intes. %l in paragraphs (cM2) and (4) of this sec-rity of the shleld and to signal. auto i i tion for controlling access to high ra, matically, loss of adequate shielding i g I diation areas. The Commission will ap-l Physical radiation barriers that com 1 m g l prove the proposed alternatives if the j licensee, or spfcant demonstrates { 'p.,,,e A g that the alternanthe methods of con. g A 4.s *

trol will prevent unauthorized entry y

into a high radiation area, and that 'This parasrsph (exs> does not apply to the requirement of paragraph (cM3) of radioacthe sources that are used in tele- ,p jhls section is met. therapy in radiography, or in completely self shielded irradiators in thich the source (2) In addition to the contents of _ is both stored and operated atthin the same signs and labels prescribed in this sec 2 (6) Each area in which there may sheldans radiation barrier and, in the de. sasned configuration of the arradiator, is tion, licensees may provide on or near{ exist radiation levels in excess of 500 alseys physically inaccessible to any indi-such signs and labels any additionalinformation which may be appropriate f rems in one hour at one meter fro No" 'in an area thatY ' 'n'1 sealed radio-act!ve source 8 that is used in aiding individuals to minimize expo-daidual. This paragraph Nnot' sure to radiation or to radioactive ma* (to irradiate materials shall.e apply to sources from shich the sadlauon is terial. "" (1) Have each entrance or access incidental to some other use nor to nuclear (b) Radfoffon eress. Each radiation point equipped with entry control de-reactor senerated radiation other than rade area shall be conspicuously posted vices which shall function automati. ation from byproduet. source, or special nu-clear matenals that are used in sealed with a sign or signs bearing the radi-ca!!y to prevent any indivlelual from n I h ided rrgtog $ ation caution symb61 and the words: inadtertently entering the area when 8',u ce n such radiation levels exist; permit de* 1978. Each person heensed to conduct activi Cauttow '

liberate entry into the area only after ues to thich this parastaph scMG) applies

+

a ccntrol device is actuated that shall and a ho is not in compliance tith the provt.

RAD 1aTIow Ansa g cause the radiation level within the alons of this paragraph on Mar.14.197s. area, from the sealed source, to be re-shall file eith the Director. Office of Nucle. A (c) Nigh radiation areas. (1) Each at Material safety and safeguards, U.s. Nu. high radiation area shall be conspicu ? duced below that at which it would bepossible for an individual to re clear nesulatory commission, washinston, 4 ously posted with a sign or signs bear-dose in excess of 100 mrem in one D.C. sossa, on or before June 14.1sts, in-fonnation describing in detail the acuens ing the radiation caution symbol and hour; and prevent operation of the the words: source if the source would produce ra- $" tuts I4.N8. an$ O h by distion Imls in the area that could may conunue acus 1 ties in conformance tith CacTsow. result in a dose to an individual in present license conditions and the provt. excess of 100 mrem in one hour. The esons of the pret1ously effective s 30.3o14 EIGN Raatarios Ansa entry control devices required by this until such complannee is achseved. For sus d paragraph (cM6) shall be established persons compharme must te achieved not ' Or "Danser" in such a way that no individual will later than Dec. 14.1973. be prevented from leavine the area. September 1.1982 p

PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION f Aprise permenent structural compo-(7) Licensees with, or applicants for, CavisoM

Vnints, such as walls, that have no licenses for radiation sources that are credible probabitty of failure or re-within the purview of paragraph (cX6)

A MAums) moval in ordinary circumstances need of this section, and that n.ust be used : (2) Each arcatr room in which natu- , not meet the requirements of this in a variety of positions or in peculiar g ral uranium or thorium is used or -paragraph (cX5X11D. locations, such as open fields or for. - stored in any amount exceeding one j (iv) Be equipped with devices that ests, that make it impracticabae to " hundred times the quantity specified cill automatically generate visible and comply with certain requirements of. in Appendix C of this part sha'l be n* Cudible alarm signals to alert person-paragraph (cM6) of this section, such conspicuously posted with a sign or a Unel in the area before the source can as those for the automatic control of signs bearing the radiation caution be put into operation and in sufficient symbol and the tords: time for any individual in the area to

radiation levels, may apply to the Di.

rector. Offlee of Nuclear Material cperate a clearly identified control 2 device which shall be installed in the," Safety and Safeguards, U.S. Nuclear trea and which can prevent the source. Regulatory Commission, Washington, D.C. 20555, for approval, prior to use pom being put into coeration.

of safety measures that are alternative CAtmoM 8

~ to those specified in paragraph (cX6) of this section, and that will provide at RADloACr!VE MArERIAL(s) ~ (v) Be controlled by use of such ad-least an equivalent degree of person-(f) Containers, il) Except as pro-ministrative procedure and such de-nel protection in the use of such % vices as are necessary to assure that sources. At least one of the alternative vided in paragraph (fX3) of this sec-each container of licensed mate-tion' hall bear a durable, clearly visible

the area is cleared of personnel prior measures must include an entry pre-rial s a to each use of the source preceding venting interlock control based on a

% chich use it might have been possible physical measurement of radiation label identifying the radioactive con.

fir an tndnidual to have entered the that assures the absence of high radt-

~ (2) A label required pursuant to e n. ation levels before an individual can paragraph (fX1) of this section shall gain access to an area where such bear the radiation caution symbol and '(vD Be checked by a physical radi. sources are used. the words " CAUTION, RADIOAC-ttion measurement to assure that TIVE MATERIAL" or " DANGER, prior to the first individual's entry RADIOACTIVE MATERIAL". It shall into the area after any use of the (d) Airborne redfocciftdty crea.s. (1) also provide sufficient information 8 to source, the radiation level from the As used in the regulations in this part permit individuals handling or using source in the area is below that at " airborne radioactivity area" means (1) the containers, or t orking in the vicin-Chich it would be possible for an indl* any room, enclosure, or operating area ity thereof, to take precautions to ' J,vidual to receive a dose in excess of in which airborne radioactive materi, avoid or minimize exposures. 3 100 mrem in one hour. als composed wholly or partly of 13 (3) Notwithstanding the provisions (viD Have entry control devkes re-censed material, exist in concentra. ; of paragraph (fM1) of this section la-( quired in paragraph (cM6Xi) of this tions in excess cf the amounts spect. "that is not required: fled in Appendix B. Table I Column 1 [tain licensed materials in quantitles

section which have been tested for (1) For containers that do not con-Q proper functioning prior to initial op-of this part; or (1D any room enclo e n - ation with such source of radiation rare, or operating area in wnich air. O greater than the applicable quantitles any day that operations are not un' borne radioactive Insterial composed alisted in Appendix C of this part.

2 ' Lterruptedly continued from the pre-wholly or partly of licensed snaterial un For containers containing only vlous day or before resuming oper-exists in concentrations which aver. natural uranium or thorium in quanti-Etions after any unintended interrup-aged over the number of hours'in any ties no greater than 10 times the appil-titn. and for uhich records are kept of Iweek during which indhiduals are in cable quantities listed in Appendix C the dates, times, and results of such the area, exceed 25 percent of the of this part. tests of function. No operations other, amounts specified in Appendix B (111) For containers that do not con-than those necessary to place the ' Table 1. Column 1 of this part. tain licensed materiais in concentra-source in safe condition or to effect re 2 (2) Each airborne radioactMty area tions greater than the applicable con-paris on controls shall be conducted cith such source unless control de-shall be conspicuously posted with a centradons listed in Appendu B, sign or signs bearirG the radiation cau. Table I. Column 2. of this part. vices are functioning properly. The 11-tion symbol and the words~. (iv) For containers when they are at-censee shall submit an acceptable tended by an indhidual who takes the schedule for more complete periodic 'Catmon i precautions necessary to prevent the tests of the entry control and warning exposure of any individual to radiation systems to be established and adhered MasoaNE RADIoAcTrVITY ARIA or radioactive materials in excess of bxit por-(e) Addiffona! WrernentA (1) the limits estabhshed by the regala ( 11 ) e ose ertt tals that are used in transporting mm. Each area or room in which Ilcensed .tions in this part. terials to and from the irradiation material is used or stored and which ~ (v) For containers when they are in area, and that art not intended for use contains any radioactive material transport and packaged and labeled in by 8rldividuals, controlled by such de. (other than natural uranium or thor. ~ accordance with regulations of the De-Vicef and administrative procedures as lum)in an amount exceeding 10 times a partment of Transportation. the quantity of such material specified ,.7* (vi) For containers which are accessi-are necessary to physically protect and in Appendix C of this part shall be w:In against inadvertent entry by any individual through such portals. Exit conspicuously posted with a algn or ble 8 only to individuals authorized to portals for processed materials shall signs beartng the radiation caution handle or use them, or to work in the be equipped to detect and signal the symbol and the words: 3 vicinity thereof, provided that the con-presence of loose radiation sources E tents are identified to such indMduals

T T"^8 ~*

I"y ;[ by a rcadily available written record, bJ, hat are carried toward such an exit , DjQP"*h' ""g" ", and to automatically prevent such (viD For manufacturing or process loose sources from being carried out of timate of me*lvity. date for shich acurity is [s equipment, such as nucl e the area. estimated. mass ennehment, etc. reactor components, piping, and tanks. i September 1,1982 20-8 l

l i PART 20 0 STANDARDS FOR PROTECTION AGAINST RADIATION f (4) Each licensee shall, price to dis- ' S 20.205 Procedures for P tking #F. 'l'- TAats or Ensnart ano Tres A Ovantmss i

posal of an empty unconna'atane e lag. and opealag pechases.

l

container to unrestricted areas.

(aX1) Each licensee who expects to .Ml7 ,J.T', " E remove or deface the radioactive mate-receive a package containing quanti-e s.-m m ma=a m rial label or otherwise clearly lad 6cate ties of radioactive material in excess of O that the container no longer contains the Type A quantities specified in L 8' l [radioacuve materials. paragraph (b) of this section shall: 'l ) 3 (1) If the package is to be delivered u i ao to the licensee's facility by the caarler. y e a make arrangements to receive the vi jeso package when it is offered for delivery v. a j S 20.264 Samm emptions. by the carrier or a,

Notwithstanding the provisions of (11) If the package is to be picked up

.t i y.e ans essmes e.=- g 20.203 by the licensee at the carrier's termi-sus=='**

t h * * *'* ***'"

l (a) A room or area is not required to nat make anangements to Mceive p he posted with a caution sign because tification from the carrier of the arriv* > lFomnote i removed 49 FR 19623) E of the presence of a sealed source pro, al of the package, at the time of arriv-R

2) Each Ilcensee who picks up a (ex1) Each licensee, upon receipt of the of e

con, tainer or housing does not exceed five package of radioactive material froan a a package containing quantities of ra.

anulim m pu h N. carrier's terminal shall pick up the dioactive material in excess of the g ackage expeditiously upon receipt of Type A quantities specified in para-p g notification from the carrier of its ar* graph (b) of this section, other than I - rival. those transported by exclusive use ve-(b) Rooms or other areas in hospl- ! (bx1) Each licensee upon receipt of f hicle. shall monitor the radaation t tals are not required to be posted with g a package of radioactive material. I levels external to the package. The caution signs, and control of entrance l shall monitor the external surfaces of. or access thereto pursuant to ' the package for radioactive contami-package shall be monitored as soon as 120.203(c) is not required, because of nation caused by leakage of the radio-practicable after receipt. but no later pthe presence of patients containing by. active contents. except: than three hours after the package is gproduct material provided that there (1) Packages containing no more received at the licensee's facility if re-i gire personnel in attendance who 3111 than the exempt quantity specified in ceived during the licensee's normal a take the precautions necessary to pre-the table in this paragraph., working hours, or 18 hours !! received ] d vent the exposure of any individual to after normal working hours. (H) Packages containing no snore (2) If radiation levels are found on radiation or radioactive amaterial in than 10 millicuries of radioactive ma-the external surface of the package in excess of the limits established in the ngulations in this part. terial consisting solely of tritium, excess of 200 millirem per hour, or at i carbon 14. sulfur-35. or iodine 125; three feet from the external surface of (til) Packages containing only radio-the package in excess of 10 millirem l. ' (c) Caution signs are not required to

- D.

"*"*I *

- 8*'" " "

be posted at areas or rooms containing form ~ the tacensee shallimmediate-radioactive materials for periods of (iv) Packages containing only radio s ly notify by telephone and telegraph less than eight hours provided that (1) active material in other than liquid mailgram, or facsimile the director of the materials are constantly attended form (including Mo49/Tc49m gmr* the appropriate NRC Regional Office during such periods by an indhidual stors) and not exceding the Type Am, listed in Appendix D. and the final de- ~ who shall take the precautions neces. quantity limit specified in the table in; livering carrier. E sary to prevent the exposure of any in-this paragraph; and &= i f dividual to radiation or radioactive (v) Packages containing only radion-materials in excess of the limits estab-uclides with halflives of less than 30 (d) Each licensee shall establish and hshed in the regulations in this part days and a total quantity of no more maintain procedures for safely open-and: (2) such area or room is subject to than 100 millicuries. R ing packages in which licensed materi-the licensee's control. .i g g,f,,,g,,R, al is received, and shall assure that j soon as practicable after receipt, but! such procedures are followed and that than due consideration is given to special j (d) A room or other area is not re- ,'g, 's a g instructions for the type of package ce t c quired to be posted with a caution sign. and control is not required for cility if received during the Uwnsu's[ beknowned. each entrance or access poirt to a b or S teen room or other area which is a high ra. hours if received after normal working p f diation area solely because of the pres . hours. I 20.206 Instruction of personnel. gg ence of radioactive materials prepared Instructions required for individuals for trantysrt an3 pmaged and la-(2)If removable radioactive contami-working in or frequenting any portion beled in accordance with regulations nation in excess of 0.01 microcuriesf of a restricted area are specified in of the Department of Transportation. (22,000 disintegrations per minute) perg i 19.12 of this chapter. 100 square centimeters of package sur-L face is found on the external surfaces $ of the package. the licensee shall im. 1 28.207 Storase and control of licensed ," mediately notify the final delivering materials in unrestricted areas. carrier and, by telephone and tele g (a) Licensed materials stored in an j w

graph. maugram or facalmile, the ap-R unrestricted area shall be secured

Ftr example. containers in locations such propriate Nuclear Regulatory Com s from unauthorized removal from the mission Inspection and Enforcement *I place of storage.

"gater fined

=t

storase vauns. or het as of this part., Regional Office shown in Appendix Dl (b) Licer. sed materials in an unres. tricted area and not in storage shall be i + 304 May 31,1984 i l

PART 20o STANDARDS FOR PRSTECTISN A"?AINST RADIATION f (b)The Commission will not approve (a) 0.05 microcuries or less of hydro-tended under the constant survell-any application for a license for dis-gen 3 or carbon-Id. per gram of lance and immediate control of the 11- : posal of licensed material at sea unless medium, used for liquid scintillation censee. a the applicant shows that sea disposal counting, and f offers less harm to man or the en 1-(b) 0.05 microcuries or less of hydro-I - ronment than other practical alterna-gen 3 or carbon-14. per gram of animal Wasrs Dtarosat {tive methods of disposal-tissue averaged over the weight of the 5 20.301 General requirement, entire animal: provided however, No licensee shall dispose of licensed tissue may not be disposed of under this section in a manner that would pumi a use en u as d for [ aB er to an authorized re-cipient as provided in the regulations 3 20.303 Disposal by release into sanitary a humans or as animal feed.

in Parts 30. 40.60, es. 70 or 72 of this een erage systems.

(c) Nothing in this section, however. 6 j apter, whichever may be applicable: No licensee shall discharge licensed r s - g e et f a material into a sanitary sewerage and disposal of such byproduct materi-I hapter; 3 (a t re fly soluble or dispersible and ( )' e antity of any licensed or (d) Nothing in this section relieves (b) As authorized under i 20J02 or other radioactive material released e om pl wi Part el of this chapter; or into the system by the licensee in any one day does not exceed the larger of local regulations governing any other paragraphs (b)(1) or (2) of this section. toxic or hazardous property of these (1) The quantity which. If diluted by materials. l~ (c) As provided in i 20.303, applica. ? the average daily quantity of sewage._ A bl2 to the disposal of licensed material g released into the sewer by the licensee. by release into sanitary sewerage sys-a wn! result in an amage conemtrauon Im TewwW

- tems, or in i 20.306 for disposal of spe m equal to the limits specified in Appen-

mmNeats, f cific wastes, or in i 20.106 (Radioactiv, g dix B. Table I Column 2 of this part:

(a) Purpose.h requirements of this

tty in effluents to unrestricted areas).

or section are designed to control transfers ( (2) Ten times the quantity of such of redloactive waste intended for material specified in Appendix C of disposal at a land disposal facility and this part; and establish a manifest tracking system and 5 20.302 Method for obtaining opproval of (c) The quantity of any licensed or supplement existing requirements proposed disposal procedures. other radioactive material released in (4) Any licensee or applicant for a 11-any ne mnth, if diluted by the am* conceming transfers and scordkupg for such wastes.h reporting and cense may apply to the Commktion "I' ND mcordkeeping requirements contained f:r approval of proposed procedures to Y ' ' in this section have been approved by a e c nc x dispose of licensed material in a manner not otherwtse authorized in the limits specified in Appendix B' the Office of Management and Budget; I th* regulations in this chapter. Each Table I. Column 2 of this part; and OMB approval No.3150-0014. (b)Each shipment of radioact!ve application should include a descrip-waste 10 a licensed land disposal facility

tiin of the licensed material and any must be accompanied by a shipment 1

CthIt radioactive material involved. in-(d) The gross cuantity of licensed manifest that contains the name.

cluding the quantities and Itinds of and other radioactive material, exclud-address and telephone number of the

& such material and the levels of radio. ing hydrogen 3 and carbon 14. released ; person g,enerating the waste.h g activity involved, and the proposed manner and conditions of disposal, into t? e sewerage system oy the licens manifut shall also include the name, The appIlcation should also melude an ce does not exceed one curie per year.= ddmumd ephm&oc h a The quantitles of hydrogen.3 and' name and EPA hazardous waste analysis and evaluation of pertirient carbon 14 released into the sanitary; ldentification numberof the persen

~

h 1g dispo cility. e e talso I m teor g , an dr IIgical characteristics; usage of ground from individuals undergoing medical indicate as completely as practicable: a and surface waters in the general area; diagnosis or therapy with radioactive physical desalption of the weste; the the nature and location of other po-tentially affected facilities; and proce

3 material shall be exempt from any volume: rmdionuclide identity and limitations contained in this section, quantim the total radioschly and the dur::s to be observed to minimize the principal chemicalfoem.he a

risk of unexpected or hazardous expo ' solidification agent must be specified. sures. Waste conta more than 0,15 s 20. 5 Treatment or disposal by inciner. chelating agen weight must be identified and the weight percentage of No licensee shall treat or dispose of the chelating agenf estimated. Wastes licensed material by incineration clustfled as Clue A. Clan B. or Clam except for materials listed under Cin i e1.5s of this chapter must be i 20.306 or as specifically approved by clearlyidentified as such in the the Commfulon pursuant to manifest.h totalquantity of the ii 20.106(b) and 20.302. radionuclides M-3 C-14.To-go and I-5 20J04 Disposal of specific wastes. 129 must be abownD manMest required by this paragraph may be Any licensee may dispose of the iol-ahlpping papers used to meet lowing Ilcensed material without Department of Transportation er regard to its radioactivity: I / l February 28,1983(reset) 2040 l (mi om u ao.:on f

1 PART 20

STANDARDS FOR PROTECTIDN A'IAINST RADIATlDN Environmentalprotection Agamey (1) Pim.i t meelpt of the waste equivalent documentation by the regulations orrequiremente of the fross the generator within one week of co!!ector, sensiver.provided all the requhed mceipt by sturny a signed copy of the (7)loclude the new manifest with the informationis lacluded. Copies of manifest or equivasent documentation:

shipment: maalleets utrod by this section smay (1) prepare a new manifest to aflect (e) Retain copies of original manifesta i l he legible ospies erlegible consolidated shipments: the new and new manifests and documentauon of acknowled cment of receipt as the manifat shall serve as a listing or ladox 6 (c) Each manifest mostlaclude a for the detailed generator manifats. mcord of transfer oflicensed matuist mquired by arts 30. E and 70 of this p i eartincation by the waste generator that Copies of the generator manifats shan the trans materials are psoperly be a part of b new asanifat.ne waste chapter. and described, packaged, marked, collector may prepare a new manifest (e) For any shiprnent or part of a and labeled and are la osadition without atta the generator shipment tw which acknowledgemet is t for transportados to the manihta, provi b new manifat not received within the times set forth in tWe wcuen. conduct en inmugaum in applicable regulations of contains for each package the Department of Dansportation and the information specined in paragraph (b) of accordance with pemgraph (h) d &is 3-r'a==laaiaa An enthorised this section.no couector licensee shau secu m. h land &sposal facuuy opmeW representative of the waste ter certify that nothing has been done to the sh{a abau sign and date the est. waste which would invalidate the D) Acknowldge aceipt d se waste (d) Any generatinglicensee who generator's certincation: within one week of receipt by sturning transfers radioactive waste to a land (3) Forward a copy of the new ,l die facility or a heenard wasta manifest to the land disposal facility a signed copy of the manifest or equivalent documntadon 2 ee i or shan comply with the operetot at the time of shipment: shipper.De shipper to be acti8ed is the requirements la paragraphs (d)(1) (4) Include the new manifest with b UC***" *#**t Pmussed es waste 4 through (e) of this section. Any shipment to the disposal site: and tremferred the waste to the

j generating licensee who transfere waste (5) Retain a copy of the manifest and opera

.h stumd cm d se to a Scensed waste processor who treats documentation of acknowledgement of manifest or equivalent documentation er repackages weste shaB comply with receipt as the record of transfer of the sirements of paragraphs (d)(4) licened material as required by parts shau in&cate an(&acapan&ehoud on &e manife betwun matwie

30. 40 and 70 of this chapter, and retals 5 ** (4) of this section. A lica====

3 ia-men %e-a--nae-5 -a),=n':g:st,ac.m,ie,d E ** 'Pm mW We

manifests or equivalent documentadon

[ wa(1) prepare aH westes so that the a ' Co w1 atu ee Commiselon auswisse esir sk is classtAM accor&ng to l SIM [6] For an shipments or any part of a

and meets the waste characteristice

shipment for which acknowledgement of ; depoemon; and Mon y e*IpPM(IA.ee O

mquirements la l St.56 of thle chapter. receipt is not received within the times gem. *e COUeckt. # prmHM i (2) tabel each package of waste to

- t forth in thi* "*ti"' conduct **

identify whether it is Class A waste

n m used a accadance wie a.nd the Director of the nearest g...i..ron R ional Office listed in Class B weste, or Clau C wate,in paragmA N d &is secdon.

Appendix D of a part when any l accordance with I e1.55 of this chapter;

- $t]p O shipment or part of a shipment has not I

(3) Conduct a quality control program g,f, ,Y, p to assure compliance with Il 01.55 and (1) Acknowledge receipt of the waste manMut was meeMd. 81.56 of this chapter, the program must from the generator within one week,of (b) Any shipment or part of a belude management evaluation of mceipt by re a signed copy o. the shipment for which acknowledgement le ,,gg. not received within the tima set forth in (4) PNpare shipping manifests to meet 2 par a s ow a to ran monts ail E311(b) and (c) the requirements of paragraphs (b) and (1) Be in e tfgated by the shipper if. gg (c) this action.paparation of the the shipper has not mceived notification (5) Forward a copy of the manifest to new man ut whcts eat se pmcuse of receipt within 20 days after transfer: the intended recipient. at the time of hj'#** shipment: or, dehver to a coHector at the p,, allw te at the U oo d.ob weste is classi ed accordmg to I 61.55 (2)Se traced and reported he g s and meets the wate characteristics investigation ehen laclude tradng the of a rigned copy of the manifest or mquimrnente in I sim M eis chapter; ehipant and Rhns a mport wie the equivalent niacu==atation from the (4) Label each pa'* nearn idenur.,w. hee n i. CLof waste to held t Commission Regional OfE.ce. ,g,,,,., A wa. . - Cia,e C wem..ie. e. D d &is,ar a w ,,),,,,,,,,,,,,,,,m,,,,,, Ci.se hosaaes wi,o.ceauc,, a,,,ce ,,,,,,,a" ; (,3,e,ain ,, &e man,e,, sa g*g-e**sinmaa - a e,ew..o. a nis a writte. se,.rt s m,* t"c.Tii.,Z:7

- * --sa C-aswe ne.i-ai docume... a.anowi*2*,meni,

to'LC u = = ***=-e* < --s**- d -,i - * - a - a ,e com,u

*~u a.

.he-d m.i-i as m *w by >-t, .t a &is.e,te,. inciae...... no aw 7 a eis.e,ier. aw. evaiusoon i.i r- -y.w,me.. any,a,t a s au&ts: shipment for which acknowledgement of (e) Forward a copy of the new receipt has not been received within the manifest to the disposal site operator or times set forth la this section. conduct waste collector at the time of shipment. en investigation in accordance with or deliver to a collector at the time the paragraph (b) of this section. waste le collected, obtaining O: (e) Any waste collector hceasse who acknowledgement of receipt in the fons handles only propeckaged waste shall: of a signed copy of the manifest or i l 20-10e December 30,1982 inent peseisrs led) - - -, ~ _ -- -

1 PART 20 o STANDARDS FOR PR3TECT12N AOAINST RADIATI2N l 8 20.401 Records of surveys, radiation l monitoring, and disposal (a) Each licensee shall maintain re-t cords shosing the radiation exposures 8 of all indhiduals for whom personnel monitoring is required under i 20,202 f of the regulations in this part. Such records shall be kept on Form NRC-5, ~ in accordance with the instructicns m. g contained in that form or on clear and legible records containing all the in-formation required by Form NRC-5. The doses entered on the forms or re-cords shall be for periods of time not exceeding one calendar quarter. (b) Each licensee sha!! maintain . records in the same units used in this

part, showing the results of surveys required by i 20.201(b). monitoring

[ required by Ii 20.205(b) and 20.205(c). ~ and disposals made under il 2(L302,

30.303, removed i 20.304,8 and Part 81 of this chapter.

(c)(1) Records of individual exposure to radiation and to radioactive materi-al which must be maintained pursuant to the provisions of paragraph (a) of this section and records of bloassays, including results of whole body count-ing examinations, made pursuant to g Commission authorizes disposition. i 20.108, shall be preserved until the (2) Records of the results of sitrveys ! and monitoring which must be main-tained pursuant to paragraph (b) of ' this section shall be preserved for two years after completion of the survey except tuat the following iecords shall be maintained until the Commission authorizes their disposition: (1) Re. cords of the results of surveys to de-termine compliance with I 20.103(a); (ii) indhe absence of personnel moni-tory! g data, records of the results of sutTeys to determine external radt-ation dose; and (!!!) records of the re-sults of surveys used to evaluate the. release of radioactive effluents to the environment. 1 l i December 30,1982 20-10b j (next pese is n 11)

i l PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION exposures occurred, and the extent of [Each Dcensee shal I uals, circumstances under which the (b) 1kenty.fourhour notificotion. (3) Records of shaposal oflinessed

materials made persuant to $$ Eag i

l;; 30.303. semoved 8 M304.8 and Part 81 el possible hazard to persons in unres 2 discovery of the event, report any event tricted areas; a involving licensed material n-- M a ghis chapter are le be maintained untG the N==i==6= authorises their orIll tNe e ma e$.. by the licensee that may have caused or to r ver i disposidea. al; and {thmatens to cause (6) Procedures or measures which - (1) Exposure of the whole body of '4) Records which must be main-Lah.*d pursuant to this part may be a.have been or wn! be adopted to pre-any individual to 5 rems or more of ra- + a vent a recurrence of the loss or theft of h h M h the odtinal or a reproduced copy or microforO if s ch reproduced copy or NII" g,) S bseo e to' filing the written whole body of any individual to 30 microform is duly authenticated by report the licensee shall also report , nms or mon of ramauon; or exposum of the feet, ankles, hands, or forearms authorised personnel and the h any substantive addiuonal informa. , form is capable of producing a clear tion on the loss or theft which be g to 75 res or mm of radiation; or 3 and legible copy after storage for the comes available to the licensee, within a. (2) The release of radioactive materi-period specified by Comminaion regu-30 days after he learns of such infor 1; alin concentrations which.lf averaged a lations. mation. over a period of 24 hours, would (511f there is a conflict between the td) Any report filed with the Com-exceed 500 umes the limits specified = Comminaion's regulations in this part. mission pursuant to this section shall for such materials in Appendix B. license condition. or technical specif1-be so prepared that names of individ. Table II of this part; or cation. or other written Commission uals who may have received exposure (3) A loss of one day or more of the approval or authorisation pertaining to radiation are stated in a separate operadon of any faciliues affected; or to the retention period for the same

part of the report.

type of record, the retention period .r" specified in the regulauons in this (e) For holdere of an operating license g (4) Damage to property in excess of part for such records shall apply for a nuclear power plant, the events , 82.M. unless the Commission pursuant to included in paragraph (b) of this section g I 20.501. has granted a specific exemp-must be reported in accordance with the Uon from the record retention requirc-procedures described in 550.73 (b). (c). 1. ments specified in the regulations in (d;. (e), and (gl of this chapter and must f (c) Any report filed with the Com- .this part. include the information required in $: mission pursuant to this section shall "Isados neporte et meet er lose et paragraph (b) of this section. Events 3 be prepared so that names of individ-sceness maternet, reported in accordance with 550.73 of a uals who have' received exposure to ra-O (a)(1) Each licensee shall report to b this chapter need not be reported by a " diation will be stated in a separate Comminton, by telephone,immediately g duplicate report under paragraph (b) of { part of the report. 4 We section. i after it determines that a loss or theft of 2 (d) Reports made by licensees in I licensed material has occurred in such a iso.4os gesensemenesesneesenes, response to the requirements of this 9"*" secuon must be made as follwe: (a)Immediate notification. Each = that it appears to the licensee that a licenm shad immediately report any (1) Ucensees that have an lastalled e 'u tan may Nou to penons events involving byproduct source, or Emergency Notification System shau special nuclear material'-- by . make the reports required by paragraphs g g,unra amas. g ((2) Reports must be made as follows: h y 6 caused or 2 (a) and (b) of % section to the NRC i) Ucenms having an instaUed a ' threatens to cause. 2 Operetions Centerin accordanca with I"*I

- ""I***

(1) Exposure of the whole body of a $ 30.72 0f this chapter. e make the mports to the NRC Operations any individual to 25 rems or more of '. (2) All other licensees shall make the Center in acedence wie 65a72 of We radiation; exposure of the skin of the ' reports reruired b _ paragraphs (e) and chapter. whole body of any individual of 150 (b) of h section y telephone and by (11) AH other H-aa== shah make rems or more or radiation; or exposure telegram, mailgram, or facsimila to the reports to Ibe Administrator of the of the feet, ankles, hands or forearms Administrator of the appropriate NRC appropriate NRC Regional Office listed of any individual to 315 rems or more Resinnel Office listed in Appendix D of in Appendix D of this part. of radiauon; or h part. (b) Each hcensee who makes a report E (2) The release of radioactive materi. ~ under paragraph (a) of this section shall. 3 al in co*:centrations which, af averaged l g 20.404 IReserved) within 30 days afterloaming of the loss over a period of 24 hours, would or theft, make a in writing to the exreed 5.000 times the limits specified i 30.485 Reporte et everesqueouros and U.S. Nuclear tory Comedesion, for such materials in Appendix B. esemessve tovels end eenseneremons. Document Control Desk. Washington. Table II of this part; or (a)(1)In addidon to any nonfication D.C. 20655. with a copy to the (3) A loss of one working week or required by 6 20.40 of this part, each appropriate NRC Regional Of!Los listed more of the operation of any facilities licensee shall make a report in writing in Appendax D of this part.The report . affected; or R concoming any one of the following ,,ehall include the following inforination: g-g types of incidents within 30 days of its e occurrence { (1) A description of the licensed ma* 4 (1) Each exposure of an individual to a "y%a*cn. *!"#"Ji r,U""" e a=(4) Damage to property in excess of f =-

maa-in-me of

ape ma.

d u e-(2) A description of the circum g hihits in il 3 alm or M104(a) of We. O '8 stances under which the loss or theft (ii) Each exposure of an ladividual to part. or the ticense; occurred; I (3) A statement of disposition or radioactive materialin excess of the probable disposition of the licensed applicable limits in il 20.103(a)(1). material uwolved; 30.103(a)(2), or 30.106(b) of this part, or t4) Radiation exposures to individ-in the larenan. May 31,1984 (reset)

9 20.405(b) 0 20.408(a) PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION O (iii) levels of radiation or with the procedures described in year was in each of the following esti-h concentrations of radioactive mateL 1 in paragraphs 50.73 (b). (c), (d). (e) and (g) mated exposdie ranges: 7 a restricted ares in excess of any other of this chapter and must also include the applicable limit in the license: g information required by paragraphs (a) %,,,,,,,,,g,,,,,,,,,, s.omo e (iv) Any incident for which = and(c)of this section. Incidents vem ' 'O*l*?,," notification is required by 120.403 of

reported in accordance with i 50.73 of this part: or

! this chapter need not be reported by a >=== wen. e.oewe i._____ (v) Levels of radiation or . duplicate rep t under paragraphs (a) or

- - - - '4 concentrations of radioactive material

' fc) of this section-7,*','*,"1.. 7Z1. __.j ers,e3 (whether or not involving excessive (e) A ? otherlicensees who make o s = o is.. .l ,,8,*'- l exposure of any individual)in an reports under paragraphs (a) or (c) of f R unrestricted area in excess of ten times this section shall, within 30 days after

2=3.: 1. _ - ~~ ~

A any applicable limit set fonh in this part teaming of the overexposure or ea=a- " or in the license. excessive level or concentration, make a ','"' -_ -.. _ _._ __. - ^ --- E (2) Each report required under report in writing to the U.S. Nuclear " s = r ' ' ~ ~ 71 _ .Z.'.~" [ ~ ~ ~."~1

paragraph (a)(1) of this section must Regulatory Commission. Document r=s _

p-desenbe the extent of exposure of Control Desk. Washington, D.C.*20555.

", ' ~

individuals to radiation or to radioactive with a copy to the appropriate NRC ,o m i, material, including: Regional Office hated in Appendix D of si is is (i) Estimates of each individual's _this part- '2 - exposure as required by parsgraph (b) h as a w=== eo.e = = ew eoerewe of this section: a

- - - - "*'**"'***""8***

(ii) Levels of radiation and { E 2W NM The low exposure range data are re-concentrations of radioactive material E quired in order to obtain better infor-involved; L mation about the exposures actually (iii) ne cause of the exposure. levels recorded. This section does not require or concentrations; and i 2o.407 personnet monMortg reports. improved measurements. (iv) Corrective steps taken or planned Each person desenbed in i 20.408 of 3 20.408 Reports of personnel monitonng ,to prevent a recurrence. n this part shall, within the first quarter of on termination of employment or (o) Any report filed with the Com 3; each calendar year, submit to the ,,, g % Director. Office of Nuclear Regulatory mission pursuant to paragraph (a) of (a) This section applies to each , this section shall include for each indi a Research U.S. Nuclear Regulatory person licensed by the Commission to: 6

vidual exposed the name, social secu- ; Commission. Washington, DC 20555.the: rity number, and date of birth, and an reports specified in paragraphs (a) and (1) Operate a nuclear reactor de.

signed to produce electrical or heat a estimate of the individual's exposure. (b)of this section. covering e

The report shall be prepared so that preceding ca en at year.

g - this information is stated in a separate cility as defined in i 50.2(r) of this {part of the report. chapter (a) A report of either (1) the total (c)(1) In addition to any notification number of individuals for whom per-(2) Possess or use byproduct materi-monito al for purposes of radiography pursu-required by 120.403 of this part, each jo , ! 4 3I( of h h pt ant to Parts 30 and 34 of this chapter; 8 durmg the calendar year; or (2) the " (3) Possess or use at any one time, leve ofr la on or rel es o total number of individuals for whom for purposes of fuel processing, fabri-redioac ve c t I n excess of h..mnd personnel monitoring was provided cating or reprocessing, special nuclear speci y art 190, during the calendar year: Provided. - material in a quaatity exceeding 5 000 Environmental Radiation Protection Standards for Nuclear Power hotceter, That such total includes at ; grams of contained uranium-235, tira-Operations, orin excess oflicense least the number of ind viduals re ".: nium 233. or plutonium or any combi. ^ quired to be reported under paragraph a conditions related to compliance with 40 (ax1) of this section. The report shall

nation thereof pursuant to Part 70 of CFR Part 190.

Indicate whether it is submitted in ac I this chaE (4) P levd MMM (2) Each report submitted under - cordance with paragraph (ax1) or

paragraph (c)(!) of this section must I (ax2) of this section. If personnel waste at a geologic repository oper-2 desenbe

E monitoring was not required to be pro-ations area pursuant to Part 60 of this (f)The exttnt of exposure of

vided to any individual by the licensee

-chapter. or E incividuala to radiation or to radioactive under il 20.202(a) or 34.33(a) of this - (5) Possess spent fuel in an inde-a material; chapter during ue calendar year, the pendent spent fuei storage installation (ii) Levels of radiation and lit ensee shall submit a negative report (ISFSI) pursuant to Part 72 of this concantrations of radioactive material indicating that such personnel moni chapter;or involved; toring was not required. 0 (6) Possess or use at any one time. (b) A statistical summary report of E (iii)The cause of the exposure, levels

the personnel monitoring information ' for processing or manufacturing for or concentrations: and distribution pursuant to Parts 30, 32, I

(iv) Corrective steps taken or planned o ne\\ on or 33 of this Chapter, byproduct mate-ual or om pe to assure against a recurrence, including was either required or provided, as de- { rial in quantities exceeding any one of - the schedule for achieving conformance scribed in portgraph (a) of this sec-the following quantities: with 40 CFR Port 190 and with tion indicating the number of indsvid. associated license conditions. uals those total whole body exposure (d) For holders of an operating license recorded during the previous calendar for a nuclear power plant. the inciden's ir c!uded in paragraphs (a) or (c) of tha ' A inanees whose lgense empires or tennmates section must be reported in accordance Pnor to er on fbe last day of the calendar year. shall sebmit n ports at the emperation or term natan of the hcense. covenna that pa-t of the year der.r,g whwh the IKense was m effect January 31,1985 (reset) 2042 l

i 6 20.408(b) g 20.601 PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION

$ 20.409 Notifications and reports to indi-viduals. (a) Requirements for notifications Z and reports to individuals of exposure 3 cY$*' 3 to radiation or radioactive material are 3 e eies too a specified in i 19.13 of this chapter. J s

- - +1D

'S (b) When a licensee is required pur- ,$

suant to il 20.405 or 20.408 to report p

.ur in to the Commission any exposure of an T-*** tmo individual to radiation or radioactive material the licensee shall also notify n, ..c.m ,,,,,,.. t so m the individual. Such notice shall be .r,,, ,,,,,,,e s. a e eer wa==== ** =cesa = =. macers aos ** r= transmitted at a time not later than "M***""*****"'*"****'****** the transmittal to the Comm!ssion. and shall comply with the provistoris 3 of i 19.13(a) of this chapter. Excsrrious aun AnnITIow&L Rseurazaamers (7) Receive radioactive waste from , 2, other persons foe disposal under Part St 8 20.501 Applications for exemptions. { of this choter. The Commission may, upon applica. tion by any licensee or upon its own ( . Initiative, grant such exemptions from

the requirements of the regulations in

?. this part as it determines are acthor. E'. ised by law and will not result in (b) When an individual terminates undue hazard to life or property, emplognent with a licensee described in paragraph (a) of this section, or an 8 20.502 Additional requirementa. Individual assigned to work in such a The Commission may, by rule, regu. Os licensee's facihty, but not employed by lation, or order, impose upon any 11-the licensee, completes the work censee such requirements, in addition assignment in the licensee's facility, the to those established in the regulations licensee shall furnish to the Director. In this part, as it deems appropriate or g Office of Nuclear Regulatory Research. necessary to protect health or to mini-

U.S. Nuclear Regulatory Commission.

mize danger to life or property.

Washington, DC 20555 a report of the E radioactive material. incurred during the EuronesurxT a individual's exposures to radiation rad et period of employment or work 4 20.601 Violations, assignment in the licensee e facility, containing information recorded by the An injunction or other court order licensee pursuant to Ii 20.401(a) and may be obtained prohibiting any violi-20.106. Such report shall be furnished uon of any proMon of the Atornic within 30 days after the exposure of the Energy Act of 1954, as amended, or individual has been determined by the me H of the Energy Reorganizadon Ac o 19 r any reguladon or order licensee or 90 days after the date of termination of employment or worl' issued thereunder. A court order may assignment, whichever is earlier.

. be obtained for the payment cf a civil penalty imposed pursuant to section " 234 of the Act for violatien of section 53.57.62.63.81.82.101.103.104.107

or 109 of the Act, or section 206 of the Energy Reorganization Act of 1974, or any rule, re'gulation, or order tasued thereunder or any term, condition, or limitation of any licenst lasued there-under or for any violation for which a license may be revoked under section 186 of the Act. Any person who will-fully violates any provision of the Act or any regulation or order issued thereunder may be guilty of a crime and, upon conviction, may be punished O

by fine or imprisonment or both, as prrivided by law. [ Note removed 49 FR 19623] 20 13 January 31,1986 (reset)

1 1 PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION j

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. an.s Neem L.-Protecnon 1.cture f.r sempirators. as may be appro.ed t,y abe U1 B of bene./Nonomal in.ut.te los Osa.penanal Selaty and Heahb (MOSH) accord 6ag to appl. cable approvals for roepirators ser type and mode of use to protect agetast etrtiorna r=dwe=.itdea. swy t,e used to the est.nt Ibst they de med exceed the prot.cnon factor, based to tie, setne.The pr tecen.e facters hated am t.e takie may nos b. approp. tate to r.r ^ .bers ch cal er saber r.epirstery basards aaAst in additnen to redsological basarua De selecton and use of roepirstors for these circumstances abould taka into acco.nt oppheable approw.l. of Ane UA sarees of hemas/rpOSH. M.am h8a*aa ve contaalasse for erkich the om.m.atrainoa.alue, la Table 1. sol.ma 1. ndia B of this part are based en laternal d.e to inhalance may,la addanoa. present external es urs basarde i at high.r enac.etreuen.6 U these circumstances.16sutauens so ar.=t==.y.my be.e to be gover.ed by external does haats. O 20-14 December 30.1982(reset)

PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION me c.% ts n es eas.8 as ae.1 3.u.i -) ci c3 c c3 m w, n t (u i/mi)(uci/mi)(pci/mi)(pci/mi) c 4 m )..........

a. nF 3xi.-=

. xi." .s xi.e-= 3 x i.~- 3xi.-- , x i.4 xi

3 x i -.

i. . xi.4 3 x i.-> 3 xi, 33. . x i.. 3 xi.4 3 x i.- > xi-- xi > 4 m)......... A. mi xi.-= i = w. 4xi-= 3 xi 4 xi. .i xi.-- 3 x i -. e xi.~

a. us.

xw= i x i.~ 3 xwa ,. x w. 3xi.-- 3 x i.-- i x i,- x i.-. xi.-

a. us 4 xi.4 4 x i.-.

e xw. 4 x w. Exw' i x w. . xi.,

4. uS xi.-=

i x w. 3 xwa 4 x w. exi.-- e xi.~ 4 xwa 3 x w. i.

a. m.

4 x w. i xw. i xw, e x i.-. 3 x i.-. i x i.-- .e x iG-> s xi.4 , (m....... min s Exi -- e xi.-- x i.4 3 x w. i x i -, e xw. s xi.4 3 xw. I m iu 3 xw, F xi s xw. 3 x i.-. F xi.G-. 3 x w. ~ F xw-3 xw. 4 m in i s xw, 3 xw. .E xiO4 i xw. en)......... i,> 3 x w. 3xwe xw= i x w. 4 37 s. x w. i x w. A di S.es 3 x ?.0** 3 x1 4 x101 As ans (33)....... AsF3 I xi.*8 F x 10-' 3 x l." 1 4 xl A*F 1 xl0** I x10-s 3 x gg, Ae F4 8 3 x10*F 3 xW8 l x 10** S x1.0-8 3 x1 I l x1 *' 3 xle-8 4 x l.," -s As F4 5 1xW' 4 x1g-. 4 xgg g xgg-. I i xI.** . x 1.** 3 x10" 3 x10-8 As FF S 8 x1.*F 3 x te*8 3 x te-* 8 xle*8 8 f6 x t ** 3 xi.s-s 3 xi.e-e l xt g xyg-s A sa (88)....... As311 3 7 x 10-' S x.**8 3 x10-8 1 3x194 Bat

I x10-'

F xig-s S.G (8 3.......... B. l3t 5 i x i -* ' S X..*8 8 x1 4 x304 3 xi.-* I 4 x I.** 0-s i x 1 "' 3 x10*. i xI.O*P 3 x1.e's 3 144 8 S x l.** 4 x te-' 3 xt x 3 ** F xiO*. I x10-'

s i

4 x I.** " h f 7)......... Oh 34. 3 xifa4 3 xto-H e x te-. I Ixie*F 6 x 0*8 4 x I.O*. 3.11 4 x10-' E SS. S I x1.** 6 x1.0-s 4 x 1 "' S x1 3 x 1 ~. 1 I x 1.** 1 3 x 1.-* 9.ryG e (4)..........

8. F 4 x1 9 8 x1.0-s 8 x1 3 x1.*'

3 x 1.*8 4 I I x l **

8 4 x te-*

3 x1.-* St sh (83).......... Se see S 3xl.*P i xi.-s 4 x gg-. 4 xgg-s 8 1xl.** 9 xl.*8 4 x I.0-' 3 x1 4 x10-. 313.F 5 3 xit*F 2 x1.0-8 4xi

8 3 X1 6 xi 1

-s 3 xwe g xgg-s I i X. OI St. 8 l ki." 3x1.** 4 x1.-s I e x t -' I kiO*8 3x1.** 4 x1.*8 31 SIS S ixi *P i x 1

8 3 x1.**

4 x i ** 4 xl I 3x1.*P i xi *' F xse-' e e h 2045 D. comber 30,1982(r.wtl l _, -. ~ -,

PART 20 o STANDARDS F3R PROTECTION AGAINST RADIATl2N O l e mS mx 0 e- - an Ak and wesw Abese leesweg %.ru (See seees ei one as assemel Te6te I feba. 0 Oi

e. se i.e.e,s.

C4 i C e3 C.ie i C.is.e 3 Ah Weser Ab tresse t (pci/ml)(uct/ml)(u i/mip(u t/ml) c c % (ni 0 03 S i mie-a O xie 8 e xiG

S mie-*

I 3 xic-> sxe. ixi e xie-' 4 m:0 s Cod s4.) Ce to, S S iO-. 0 -> s xiG-. 3 x30 * + I F mig a 3 m:0- s 3 mIO-' 3 x 10

C4 llSe S

4 xte a1 y a lg-* I xle"? 3 mig s 1 4 xl0 8 F x t e '* S ale-* 3 x10 s Cd 115 5 3 xle

I XIS-s 0 x10-'

3 x10-e 1 3 x10-8 9 xle-s 4 xic ' 4 x 10- a Celstom (30) Ce 45 5 3 x 101 3 x10

I x 10
9 ule
I I xle '

S x10-a 4 mie ' 3 xte'* Ce 47 5 3 x 10 I xle 8 e x80 3 ute 8 1 3 xle ' 8 x10 a e m IO-' 3 mig a Caspermese (90) O 349 5 3 xIO*'s g xag

3 s 80. 4 x IO
I l ate-# : F ale
3 x ig-es 3 xte'8 0 330 S

S x t0 '88 4 xle-* 3xte'* l x le '8 h i 1x10** F ale-* 3 x 108 3 xl0 s E O 231 5 3 x 80-'8 9 x10

4 x 10-88 4 x IO
g i

l x 10**8 - 0 x 10 '* 3 x10-is 3 x10-s O 333 45 6 x IU '8

3 xle'*

3 x te-'8 F x10

g

1 J x 80'" e 3 x 10-*

I x10-es - F xIO

O 333 8

0 x 10-'3 4 x10-s 3 x10-'8 9 xto

l 1

0x10 " 4 x10 8 3 m le-" l x 10

O 354 5

3 xIO '8 I 4 x 10-* 3 x 10-88 Ix10-8 1 5 x 10-'8 ' 4 x 10-* 3 x 10-sa I x 10 ~ ' Cerber(e) C 14 S 4 xte-* 3 x10-8 9x10-8 0 mie * (Cor) Set 3 x80-s I x 101 Cerese (SS).. Ce 141 5 4 x10*F s 3 xt0*8 3 x 80-e 9 x te-a 1 3 x10-' s 3 x10'8 8 x10-' 9 x 10-e Ce843 8 3xt0-' 8 x10 s 9 zie" f 4 x10 s 1 3 xt0-' ' I x 10-s F x 10-'. 4 xle-s e mIO-' l 3 xle-* Ce led C 1 x lo-' 3 x 10** 3 x tt-m. I x10-s I 3 x 10-* - I Elo s + Caelee (58). Cetal S I x10-s. F x10-8 4 x10-F 3 x101 6 3 x 80-e 3 m80-8 I x30-8 9 x 10 8 Ca 184m 8 4 x 10-8 3 x 10-' I x 10-* e x10-s 5 6 x te-*. 3 xle-8 3 x le-', 9 xle-8 Ce SM S 4 x to-* a 3 x10-* I xt0" 9 x le-* I I xle-' f I x10-8 4 xta-#, 4 x t0-s Ca ISS S Sx10-8 3 xte-o 3 x IO-e, 3 xgg-e 1 9 x101 F x10-s S ale" 3 x 10 ** Ce lse S 3 xiG-'.' .l x10,-* t .9 x,ta-8 4 x 10*' 3 x le-8 i E xiO4 xit x 0-. Cs 937 8 e x t0-8 s 4 x10-8 3 x t99 : 3 x to-s 1 I x t0-* I x te8 3xt0-* 4 ute a Chietse (17) O 34 5 4 xIO*' 3 xle-8 l xig-e 8 0 x 10*8 1 3 x ta-* e 3 x t0-a exta-# e x te'8 a 30 5 3 x le-* E x10-8 9 xt0-* ! 4 x ie-* a 3 x te-* I l x te" r x t01 4 xle-* case au (34).... C,al 5 9 x te-8 s xle-8 4 x10-' 3 x10-8 3 x10-* s xle-* O xiO4 3 x le-s O D000mber 30,1982(reset) 20-16

~ PART 20

STANDARDS FOR PROTECTION AGAINST RADIAT13N i

~ umea e c mus I. Air o.s iuser A4=v. it.n.e. e --C sl.a is n =..i.nd as ess.n : 9

t..

i. wen e.=

s s. cas i ' cas col i 8 ce e 3 i a i a t (pci/al)(pci/ml)(pci/al)(u t/al) c c rs...

c. sr i

= w.

exw* .i m m.-- s. i.-. i e x w-> i x w. mi * . x w. 1

c. u.

s e x w-. .a xw. exw'l exw. e x w-> e x w. .x=4 i e xi.4 x w-. e x w '. ixw~ e xwn

c. n

.s sxw4 e xw. exw e xw-. c. e xwe e xw. i xi.4 s x w. e xw-. i xw-. e x w-o e xw. .i xi.-. . r xw. e x i.-- c w,

c. =

s = i.* xw. . x v. i n w. i i x w. cm mi..

c. us i xw=

i x w. xwa e x w. a xw. r=w, x w-= i nw.

c. us s

exwa i xw. e xwa exw* 1 i i nw-e xi., exw= a xw. e xwa r xi.*

c. =

s e xw= .e x w. .e x w. .w. e xi.-= i i x w. .exi.-a =w*

c. us s.

s x w= i xw. g i i x w. e xw-. xma e x w. .e x wa4 x w.

c. u.

s sni.-a i xw-. ,t .e x w. xi.-- i i nw-e xi.-. .i nn, .i n w= x i.4 c ur i exi.-- xw. xa-a .e x w. e i xw= =we c u. s e x w= i n w. .e x wa

4. x w.

xw= i x., I. i n wa xw. . x w. e x w-. c u. i nw. i x w. . x w. . x w,. e xw. e xi inw. e xw. xw. w en ., iu s ixi 4. i n i.-. r ni.. . x i. -. i e xw. i x w. xw4 xw. ., in .s s xw, i x i.4 rxw4 . x i.-.

e. us i

e xw. r x w. e xwa e xw. .xw = r xie. i =wa.

==w. 3x.i .s x w. l s.nu. e xw. .s exi.=l exw.- xw. x i.. .. = e xi.-. xi. = l 3 xw. inw.

e. nu s

. xi. xi i x w= xw= i xw. e .i .exi. = i xi. = i

a. in e x w.

=w-e x w. ini. = e x i.. exw. e xi..

,i.. ! e xi..

a mi e, in .=w-exw.; i x i.. + e xw. e xwe axw. e x i.. i i x i.. e, iri .s xwe e xw. e x i..,.i n w. e wi us s xw e a xw. i x w. xw. n/s...a n i s e xwe e xi.. .i x i.. -

e. x i..

.xw = ! us inw4 a e x i.. nw. ots. is, .e xw. i.e x w.. xw. e xi.. .w.!

e. iu xw4 i nw =. i x i..

3xw = 1 e xw. i r xw. ...i

s. in s

exi. ...I exi... e xi.. e x w. i r xi. x i.-. i e xi., I j I 2047 D mb.r 30,1982(r t)

~.. PART 20 o STANDARD 3 FOR PRCTECTIEN A'*AINST RADIATISN 4 O ) ("3 APfles0m 0

i. a we.e, u e x.e. were 4_c (See notes as and af appones) i l

Toble I .'able II i i i Gae.e= (m. mas beri s e,ea csI ce4 3 cea s c.a. 3 Air traser l Ak I Weser t (pci/mi)(uci/mi)(a i/ml)(u t/mi) c c exw.i ,e, (iOS, ,. u. s 4 xw8 i F xiO4. 4 ws. 3=w+. o w* 3 x w' u w* exw.! ixwsI4xw=e xiG-= l 3 mic-s

e. 3s3 s

3 xwe l x t0-s e a nw. ,e 384 8 3 xle-' ! 3 xws 3x30-4 9 x10-8 b or e (,). 3, x w-*. i 8 x10 I 3 x 10-s. 6*10*" 9 x 10-' , it S 3 xw8 3 m ie-' 0 w* 8 3 ul0-* ! 1 x10 8 9 x 101 5 x10-8 Gedeu.a.e (64). Gd 183 5 3 x10 l 4 x10-s 0 x10-' j 2 xle

I 9 x101 g e x10-s [ 3 x 10-' s 3 x 10-*

64 189 8 x10-P 3 xle-8 3 x 80-8 0 x 10 -8 0 4 x10'8 0 3 xte-s I g ult-'.' e xt0-s Gem.e (3 8) Se F3 5 3 x 10 ' I i x10-s 0 x 10-' l 4 x10-s I 3 xlg-P l x10-s 0 x 331 4 4 x10-8 ar Geme.a.e (33). So Fl 1 x10-8 3 5 xw.' .S 10-8xw.i4 xle-' i 3 x10-8 i 3 m' 3 xle, Seed (79)..... ' As 194 S I al0

8 xl0-s 4 x101 '

3 x le-* [ 4 x 30-8 3 g g g-e i g xgg

8 e ul0*F i

A. 190 8 3 xlO*8 3 xle-8 1 x101 3 x10 8 8 l 3 x10-' ' I x10-s

0 x10-'

S x10-s As 199 5 t I u to-* 8 xte-8 g 4 x t e 3 x10-* 8 0 80-8 i 4 x te-8 S u lo-* 3 xte * !' S al0 a l9 xIO-* l S ul0 08ef.a.m (F2) 180 tel 8 4 u l0-e l x 10 -' F ul0-s l I F ul0-8 3 x10-e F u gg-s 8e s.a.m (eF) 818e lee 5 3 x to -' F x 10-' 3 x10-s l 1 2 r10-' 9 x 10

4 x10-' l 3 mIO-8 88verocea (1) 843 3 x10-*

I x 40" 3 x10-8 3 3 x10-s I a x te-* t 3 x t01 3 x10'8 l 3 ule-s S.b 3 =le a 4 x30-8 *, hads.e (49). . l.I13e S , F x le-*

4 ule-8 2 x10-8 8 xle-s e u te
e 4 x10-e i ; x10-8 9 x10-8 1

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I ISS S

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I xle * -

8 ' 3 xlO P ' I miO a F xl01 4 v10-s I e is4 s ; s <10-' - 4 xie-* i e ult-4. 3.ie-s 9-DecembeF 30,1962(r000t) 28 m.-

. ~ PART 20 o STANDARDS FOR PROTECTION AGAINST RADIATION ? m.i a. C m n -C is a.a is.sw.8 rue.) T e. i T i.. S e (.a.mi. m r) p.. C.A.m. i C.I.e. : C.I.ma i C.A.ma Air Wr A. W.s.r t (a i/mi)(pci/mi)(u t/mi)(u i/mi) c c c e xi.-. 1 r xi.~ l i xi.-- e xi.-. - i m......... isu a e xi, iu i ni -> i m i.-. . xi, a 4 xi.-- .a xi.4 .i xi.4 r mi.,-. xi.4 x i.-. crri....... .m i mi, . x i.~ a 4 xi.-- . x i.-. i mi.4 xi 3 x i -- e xi i xi. n i.4 4 x i.-. .m i i mi

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mi --

. x i -. xi -= 3 x i.-. i e xi 4 x i -- m i.-. n iin s .e x i.-. s x i.-. rxi.-- e x i.-. - cris.. um a x i -- a xi -. . xi 4 i n i.,~ xi =i xi 4 i xi. i m cm.. =n s xi.-- i ni.4 s.x.i 4 r mi e xi 4 .i ni.-- 4 e i., . ni.-. x i.-. mu i..~ . x i.-. .. i.4 ixi 4 m i mi i i.~ i =i.-- e xi -. mu a 4 i x i. -. i

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a. m a

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a. m s xi.-.

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~ e i xi -. l M i 0 M8 D mb.c 30,1982(rmt)

PART 20 o STANDARDS F3FI PROTECTION ASAINST RADIATIUN am.mx 0 c a4 ,a _ c4 (8 i l v. 1.= 0 1 0, - - i 8 ci c.4 3 c i.c 3 a w l 4x -I w I t (pci/ml)(uct/mi)(u t/mif(u t/mi) c c 4 xie-= 1' 9xw I.i xie-is I (,3) l,nF S 3 xie-* 3xw.l 3xw8 i inie-- 9 x w' mie-a 0 xw' 4 xw8 , u, .S i n wa 3xw., i xiO' F xw' . xiG-s 4 u.,(n) .0 3, 5 s xw' xw. S a w. E xie ' 8 0 x10-8 4 x10-8 3 x10-* 3 x to-s 80 63 5 4 x101 0 x10'* 3 x10-*, 3x10'8 0 3 x te 3 x10-8 l x10 8 F xte' 00 63 5 9 x10 4 x10 8 3 xte' 8 l a te' i 8x10 3 x10-s S ale e 4 xl0 m l Den 93.s S Ixte 8 mio a 4 xiG e 4 x 10 * (C.A.eM.e) (4 3 L 8 3 x10-' - I x t0*8 8 x10 4 x10' 80n 95 5 8 xte l 3 xle-a 3 x10-s ' 5 x10** 1 x10** I kl0*' l I 3 u l0** 3 x10-* 9ein 97 3 5

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l xie a O t l December 30,1982(reset) 20-20 l l I

~ PART 20 o STANDARDS FOR PROTECTICN A'2AINST RADIATION a e Aff90DlX e

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1 PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION AM GERS l

1

. in Ab.m. Wo.u, A4.,e sim m,e. Seeh.,een.-C suem.o. (See asens an en.af a sen.n] Tehee i I f.has. _ I I gense.m. lese.eas as er:, onesspe. C le.e i l C.eu.m a Catessa i l C.co.a 1 I l Aa, i

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= w.

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= w.

w.

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s, u a

= w-i x w.

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w.

i4 xi e xi.,

i, n .s .e x w. a n w. a, . w. . w. i x i.4 w. 3, = s e xi.4 i n w. l e x i.~.

w, j

e anw4 i n w. e x w. .. w. i,.i 4 xw-e x w-. =w4 r=w. e i 3,we i n w.. enn4 e xw. i, n xi.-> 3xw.t exa* .r i.-. 8 exwe, 3 w. inw4 .w. l:u

1 exi.--

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w.

l v. w: r crs 4 x w. i x w. inu4 4 x w-. i a xi.4 i n w. i x w= 4 xw. O p enber 30.1es2(r t) 20 22

PART 20 o STANDARDS FOR PRSTECTION A2AINST RADIATIDN me ae .w m n sw_c w w.: ma. i w.s a ,3 m. ci c. c iis n m a w t (u i/miXpci/miXpci/alj(pci/ol) c .w3.. s e xwe 4 xw'. e x w. i xw e i a xi.-- a xi.- i xi.. . x i.-. ,. = s e xwe e xwe e xwe e xw. .s xi.. e s xwe e xi. e e xw. w w. s

===

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s. x i.*

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3 x w.

i x w, .e x w-. xw. .i x w. u isi. s . x i.-, e xw. x w. 4 x w-. .e x w-> i s xwe xw. r xw. e xw. ins s e xwe i x we e xi.* .xu* a x i.-. e........ mi i xwe exw* axw* 4 xwe 4 xw. .e xw* i e xi.* i x ws xwa 4 x w. n.m a n.......... a see a xi.* ixw* i exw* r me .. w. 3. i.. e xws ,.w. 3, w. .e x w* n mi xwe

= w.

3, w. 3 w. n on i exwe .. w-= .s, w. e e xwe e xw. r.w. ns s exwe e xw. 3. i.. .i.w. s w. s xw. ,, w. .w. .i exwn e x i.-. ixi.-" s= we w . n on uw e x w. e x w" an we i. s.x w " ex w. ex w" 1x w. n ou i ex w " 4x u* sx w " in w* n n. sx w" ex w' e x w" sx w* in a-ex u* a x w" ex ws ix w." saw' ex w. sxu i a . n ai e a e x w-. s x w' 4x we ex u .i sx w" exw ix w " .e x w. n on a exi.-" xws e x w" i.x w .i exi. " .x w. l e x w"i s m w

e xw n,,

a n w"l a x w* e x w". t D mber 30,1982(m st) 20 23 1

~ PART 20 o STANDARDS FOR PRT.,TECT13N ACAINST RADIATICN O> APP 9800tX S Came asseems en At one theer Abeee fesswel See6 pose 4_Cessessed lSee neess et end at appews) febee i febao E l Steeness (eseets asamber)' eessere8 Cetwee l Ceemme 3 Caesee I Cotome 3 i Ah Weses Ah Weser I t,(u i/al)(uci/mi)(u t/alj(u i/mi) c c c .s e xiG-. l e xie 4 e xie. S kie-* S mie-8 we,,,,

= 334 Themen (49) to 870 8

4 xle-o g mig-s, I xit. S m it. 3 mie. g g age e 3 msg s e 3 = 101 l x gg a t ul01 8 ulo 8 Te 173 I x te I x te 8 4 x le-' 8 mie' s p 3 x t0-F I x te-8 0 mt01 3xte* l Tim (30) Se 313 8 4 xte*8 3 mit 8 I x10 e g x go-s a 1 8 ul01 3 xl01 S ul01 G ale 8 I e its 8 I I XIO S xle' s 4 x 10"* 3 x10-s S t 8 0 xle'* { S x10M 3 x te-* 3 x l.Y* Temessee (Weake )(74) ; W 801 3 3 x 10** l ate 8 0 xte-a ; 4 xgg. l 8 l xt0 8 l ul01 4 xl49 s 3 x10 ' g W ISS S 0 x l9*'. 4 x10-s i g x ge-o, 3 xte t a ge,' a t ul0*8 3 xle-s 4 xgg-e 4 xte* F 3 xte-a l W IBF g s 3 xir, p 3 xir ! 3 xgg-e .F xte s 3.e om (9e .. 3m 3 xiG-. i nie-i mie-. mie-s i niem, i e xis, a i nie ! l xie, ! 4 xie-,. 3 miO4 = W 333 8 9xte-" 0utr' 3 ale-*. 3 x10-8 O x 10-* [ h 8 3 x te-"

9 x 10*# - 3 xtg-s l

U 333 8 8 xl0** l 9 x te-* 3 ule-" '. 3 xte*8 i m ir, mir. e x iG- - Smir. ) 1 8 ee U 334 6 ute**. 9 x10-8 3 xte* [ 3 x10-8 g 0 9 x10** e 9 x10** 4 xt0-4 3 xle-8 8 9e W 338 3 3x10-8 0 x 80** 3xle-" 3 x10-8 l 8 8 x10** 8 0 m IS** 4 x 10** ' 3 x10*8 9 336 8 e x te-* ' I u ge-o 3xiG-H g x gg-s 8 IXIG-# $ Mig-s 4 xgg-w 3 ggg s .e v Sm FxiG-a Inir. 3xis-= 4xir. l I 1x10-* I M IS-s 8x80-# 4 xle-8 U 340 5 3 x 30 I x10-8 0 x10-* 3 x 10-8 4 3 x10-8 l x te-s 4 x109 3 x te 8 De h 9xle-" l MIG *' S u lt*# 3 M iG-' s i IxIO-* I xIg-e g, gg-es 3 x gg-e Vesm4 seas (33) V 43 3 3 xte F e x ta-a e xig-* 3 x10-s 8 4 x te 8 xig-a 3 x l0* 3 IS-8 Eesse (54) Xe 131m Set 3 xIg-s 4 xle-8 Ne 133 Sob I xle 8 3 x10-' ; 3 x t e-' ' Be 533m Sob Ix10-8 3e ISS Set 4 x te-* I xle-8 Tuerquise (FG) Th 873 8 F x10 8 3 xIS-'.. 3 x101 , 1 xIG *.. I ext 0*8 3 x te-8 3 xte-o 3 m ggw TIh4em (39) T 90 3xgg-P 4 xlg-. 4 g gg-, g xgg-s I lxte 6 x10-8 3 x te*' 3 x10-8 T 9tm S Sugg s g xgg-s g xgg-r g x gg-s 8 3 x10-8 9 xte-8 e x t t 3 x 10-8 Y 99 3 4 mig-e g a ge-a g x gg* 3 mig e i 3 x 10-' 8 x te** I x te 3 xIO-s T 93 5 4 x10-8 3 x 10-8 9 x101 e x 10-8 8 3 x IO*' 3 x 10-s 3 xle-* 4 x 50-8 T 93 B ut0*F 0 x 10*a e xt0* S u gg-a 8 I n te 0 x tt-* S ule" S ale-o O O December 30,1982(r000t) 20-24

PART 20 o STANDARDS FOR PRC,TECT13N ASAINST RADIATISN - mmma e c .=e.d m w. w I l 3 mi mn ,c ilc

lc ilc l

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ir.

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ire ir.

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= ir.e-m, s,.

i nire

ire

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= i.4

.=ir. i exir. = ire .i n i.4 xir. e xir. .i nir.e = 3,.r smir. =ir s x i.. s mie-. exir. R a., e 1 i.4 amir. d , m.d. e .r eh l ed.h. er f . -ea l .a h NID. t s h.es. a., d.

xi.*

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i..

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t = C

Ame.ded 3, em FWF enhshi. mister af 5-M., U..se4
- Ame.ded 3. F R 233,..

y n m. ey easiereen e a U-t M 2 399.; font.ute re. katada,36 an ear sham. inal tenently may h se.e. am.f. asten. sim s. gester.If th pare desas t.d & M 5 1... l.a. tar of eer,t se _.e iceams r.es.h.m.e.nti e.t W M.S is. e e.m 8 ..* Ame.ded 6 R 5 1... th rtm he.a.. ... m.u,,r

A-*ww >e > = >ui a.

e.tn ee eee. fo.r pr.es.taen p.a. s.d.a.MS e smas.a. $ Ame.ded J9 iM 25. 3; redenis led .. per may eartsham.at m w-i ...e,... ,e ..-,-.e .emee i. r, .., in a. s, e.i . r *.r x -m,- - e .s..h.at.e,s. n,,e,n.ama.mmes, e m. .I.ss.d reden. ::.et g e mr. -..m see, passes.m.ni.e. , es.,,,,,,,.al s.e.r.s, ta.s. n, e, av m m. n.,,.,.m. ..m e m w. ,,,,,,,,.,,,,.m S et 30. 3..?,X i.4 supine per grass W. Th. speed. ' parteet. emes.r ) The T. eat. E one eron.: er a.m.y to and U-ses, e a. nases, seem to: estarier Sur other meat.ses et M W.MS sceneses e m. naves.-Tm.r .enarsi.e n an sesmene.ames en r. .ans - esens may e. mass. en en en-sa.i..nas s+.es fe, ysose)seaItY* en.e xsea em J" ** ss. e in p.seestsee my.sesnt as W. ass. empses se as parenes. 20-25 D mber 30,1982(r e.t)

PART 20 o STANDARDS FCR PR3TECT10N ACAINST RADIATION NOTE TO AP?FNDIX B " 8. If any of the enadnsone spectaed below Nema la any enee e1here there e a misture to mar e, m met, ao corresposatag enlues spectaed erecs er mere than ene redenucase sne lemnine to u,, below may be used la latu of those speciaed ter pu.rpsees of L&As appeadas should be etermined as ta paragraph 3 shoes.

== e. me u.. seenut, of ena recomuwd. is a e.i,'i,",m tt.e ',:T.u,:d.,e";::".?,,,"."e.t.. L'"::" ad

==iure = ma.f as remonucude. la me .-a mut ao -==uan . eu he e.,, e m.u rm a r.. of me or== '8 present a the m t re a d th asseuchde ae the mastere. tme ensso hn e ere rne quenen s. misture le act known, the concentrauca is u n e bmit othere ber cunh immed is Appendas B hr the spenAc redenschde a hem tima for the antature le the limit epoc18ed la Appendia "B" for the radsomuclide la the noe the masture r Rei 4 tie " MANtm haetag Me lowest eenceah> M " mans -). limit; or in -..a I.f redisauc.todes A E sse rt u m Ca. C.aw cc.a.and C ar.e.liremen,t g h. If tPe,e a aity of each radicauclide la 3. tdent 1 d d she p hmei ne maru tmao.a. nut a a hao.a MPC's. are %d Pfa, sad MPCs. and %f PCc Mate lateh. thee the eenestrattens shaN be haded w thei that certata radicauclides specined la Ap= ste Mnee nns atmeenes essas-pendia "S* are act present to the emitture. the ocasentrauca 3amit for the misture le fa fe Ce the lowest ooseentration tamat sParinad la W W W WF M Appendia -s for may reasommetsde wasch as not known to be annent Dom the misture; 5'~ "ser.a.h,,., in. n,re eny w *w wn,etro's *f tar It e er ,,,,u,,,. i,o.~a ,s.ue6.a me g ,e,a,e s s m i~ .r.o. im,,

a. For purposes of nble L Cs4.1-4 x 10-as

[

36. For purposes of Table 1. Col. 9-4 x 10-'

g

e. For purposes of Table D. Col 3-3 x 10.as

d. For purposes of hbie 32. col 2-8 x 104 Table I TehteII a E;mnant (eksels ammber) and has pe Cefama l Cohama 3 Cahma 3 Celmaa 3 Aar geCutal) a uer Aga t,Ca/aal) waser

(, Cunni) (eC.inD It a es known that Sr 80, f 131. I E3% 1 US. I Lat. G &ak saune la emipi. Pm 3 a Po al& At 214, BLa r21, sa 2.e, Re 22a. as m, ILe ZIL Th ak Pa ras. Tm 484 Th. mai. Cm sea. Ca 3:4. sue D an as are a presens...... 9Xnte 8X3te If a e sneen Lane Er m. I 12L I i e. 8 &Js. ta tan 813A tates la sely). PD 21& re 2iA Ra 723. Ra 22s, he ta Po 231. Th.aan. Cm ans. C1 ates and Fe aae are mes 8" N'J'",n';;; iig;;;gyig irig iigyyI"s ane are c sir enari re ria6 a rse, n ran Can ama, nr.e R ut".T::'Jhrcars s m uis m. is are u sw exiee u a e i n..n pr e.e nt.................................. ma Aem. a.n i eFemru ng.m.a se es I in. Pn ai mm za. . ad ma ae nre mi sa'"i.E*ai.esiLY Wei;&dA"a'as Eile".iU"..#f ~~ a am. aa Pu sei e,e.ai mas................. exw* 1xie = u a in enere sees aie==.m-s and As 327 are ses presena............................................. 8xle* 3Xat-e Il ti m k newe that Ae 227. Th 330. Ps 31. Fu 318. Pu ass. Fu tea Pu Js2. Fu 344. Ca 3et Ca De and Cf att are en pr--a 4XIe

1XIe e

~ h ara. If a alsture of radionuclides cosasete sf d ntum and its daughtere La are dust prten g to chamacal esparataos of the uranium freen m. .r.. ne esium.p.cised meio me, no [ tamed for uranium and its daughters through l S.-.radaum 338,taeteed of those from paragrapaa 4.s or s.amete. e

a. Per purposes of hble 2. Cat.1-1xte-se act/ent gross alpha acuelty; er s x te a Ct/

mal astural tarsalum; er 'IS anacrograans per emble anster of air astural treatuat i C m, ptar purposes of hble II, col 3-3 x ge o l act/en! gross alpha actiettT: er 3 x10 isact/ l R ma astural urnasuan; er 8 maerograans poe I '(emble meter of mar astural urnasua. I S. ptir purposes et this isote. a reale. ~ [ sustado enay be seasidered as not present la i e anasture 11 (a) the raue of the eencontra. teos of that recoauclide la the anasture ,i (C ) to the concentrauan tasant for that k'; radienuctide spectaed in Tanie n of Ap. pendas a (3rPC.) does not seemed tu Le.hght and (t) the stem et such 2 a(ntane fur au me r~ emmesdared e. e act pressel in the masture does met seemed c, ce (i.e, NMs + ~RRs + * * * *

SMI' 20-26 December 30,1962(reset)

[

PART 20 o STANDARDS FOR PROTECTIDN AGAINST RADIATION Amy alpha sumistaeg radleswetode Aeressen C meal hurweet met tieted aheve er malstume et i Onetumn.198ma*. 389 alpha amattare et sa.tnews amen. Noterset Mitretarice M Onetu m.191 See e pomataea...................... .es 4mersetum.34 3................ .e5 Ommlum. ISO See g Any realeauclide other than alpha A Attmony.132 300 palladiu m.las.. o _ _.. ISO 'h eenittias redteaushees, est lasted Antimen).IN De Palladium.149............. le0 g above et mustums et beta emat. g A ntimon y. I SS............ De Phamphorue.SS.......... Se (, tars et vatmown sempanttime... .I A rse n 6c.73................... le0 Flatinum.393 See Aree me.74 le Pisua um.100m.. ......... les Ay y 18................ ... y pistin um.lse............... les ma.a.. #er purpeees of I samal, erhere I'***""*'.I".*.**.*.**.**.*.**.*.*.*.**..*.* b le invoked a MW &'P" m to Platinum lD7 leS = Pluientum-s et

known amounts the Isail for the enmbinetion se.rmm 3.i).

hi p.3 iom.33,se................ e I y should be dortved as lenewat Determine. for / se n u m-l oo.............. av a l sm u th.210.................... I Potaass u m -43.................... le g each leolope la the sembinatiest the retio aromine e3 le Franeodymsum 1as.......... 300 e, between the quantity present in Iba Ca d minai-10s................. 30 Franeadysuum.1es ............ sec ** wnhUen aad the W ehw {mem 1 Ism y promettu um.1 e7........... le esteblished for the specirc leonope when not Ill................ Promethiums.840.... le Ca lci um.a s.................... le la combinetiee. The sue of such retioe for en Raetu m.sse...........-.. .el Ca>cl um-4 7................... le Rheneum.Ies.. .....m 300 the isotopes in the combination meF not Ca rme n.14................****

100 Rheniusa.100 m-..m..--..

See e steed l* (l.a. *smjty") Ce rium.le t See Rhodaum.lete....... 300 = Cersum.343 300 Rhodium.106 mmm. 800 Cert um.l e4...................... I H Ru,bi,dN m.48 m.. m. Cassum 131.................. 1.000 g,,,,,,g9,,,,,,,,,,,,,,,,,,,, gg Centum.134m 100 Cesi um.134.................. 1 " MS R uthe nium.97......... Ruthe alum.108......... 34 Cesaum.134 30 Ruthansum.108 -~~o--- H Cess u m. l H...................... 30 R uthalum.3 00...m---. 1 Cens um-13 7.................... 30 Samarium-l83....... H Chlori ne.34.................... 30 Samartum.163. See Chlor tne.3e.................. 10 Scandium.44... le Chrsmlum.53 1.000 Scandium.47. See Cobalt Sern................... le Scandium.44....... le Cobe l t 54..................... le Selentum.70... le Cub a l t - 00..................... 1 Salaeon.31......... . 800 Cep pe r.e4.................... 100 311ser.106........... Se Desprosa un.164 30 Silver.Il0m...... I Dysp rosmm l ee................. 300 Bilv er. I l l... ISD Ertba uen.n et 100 Soa mm.34.............. le Erbium. 3 73 300 strontium.88............ Se b, Europt.im.162 9 3 m.............. b3 300 3 6ronti um.m.............. 3 E ery:pm. l S 3 13 yr.............. I Strontium.00 G.1 3 wurmm m. i u................... 1 & Stron u um-e n................ So g E urops om l ES................... 30 g s t ron ti u m.92................ le a6 F luor nee. l e..................

1. 000 m,

sulp.iur.35........... See g o.selmium.i 53................. 10 g T.nt.ium.is: 30 1 Om uolm iu m. l SS................. 100 Tec hne ta um.>f............... 10 Os ll: n m.72...................... 10 Tec hnett um.9 7m............... 800 Ge r ma m u m.71................ 100 Technetium 97................ 500 G ul d I "8....................... SOC Tec t. ne u um.D9m................ 300 G uk. l PD....................... 300 T ec hne u um.De.................. 10 H a in.a am. I 8 3.................... IO Tell ut! um.125 m................. 30 H ol me tm. l as................... 100 Tauert um.3 37m............. 30 H i d rut e ru 3....................

1. 000 Telluri um.127..............

100 I n d n am. I 13 m................. SOC Tellurtum.12 le Teiiun um.i3.9m............... i luam m.ilem.................... 30 500 l is.ds um.1 I S ra.................... 100 Tell urtu er.. l a i m................. 80 l uo m m. l l a..................... 30 Tellarrt um. 3 33................... 10 ) IMl;ne 12% 1 Ter bmm.100.................. 30 luesne.126 I TNIlium 300................. 100 ledme429

9. I Thala e u m. 30 I................ ISO luime.3 31 I

Thalta u m. 302................ Sto Icelue.132 30 The na t um.304.................... 10 loome.333 I

*norium (natural)a....... 303 Iceme.134 le Thu tt u m. l ?0..................

le todme.IS8 30 Tn u ll um.17 3.................... 30 t r iemm. 3 92................. le Tm.lla....................... 30 t r uimm l H..................... 100 Tan.12$......................... 30 Brun.SS......................... 300

I u ng st en. I 8 8....................

10 I rc h. 59...................... Is Tmmten-ISS 30 Mr>pton.SS 100 Tunesten lB7 100 M.rl pt on.87 30 Ursalum (natorst)*...... .... See I.a m ha n u m. I 40............... t0 0 r a at u m.213.................... .91 Lutetsum.l?7 100 L'r.ntum.234 Uranium.338...... .03 11a9f a nese.S3................... le Vs tac i um.44.................... 10 S t e n g anene. H................... le 3*nau.333m................... 3.000 &la n g a nese. 34................... 30 Xe ness. l 33..................... 800 18erc urt. 5 67an................... 300 Kenon.154 Sto 11ereurt.I07................... Iso Tlterhtum.ITS ISO Sterc ur) 303..................... le Y t t n um.H...................... 30 Stali bde num. 99................. ISO Y t t riu m 9 3...................... 10 M ead e mi u m.14 7................. Igo T t u u m.9 2...................... ISO M ee nn u ni-l es................. 100 T. tri u m -93..................... ISO ,,,g y,, g g,g,g,g,,gg,, p %ckel H........................ 300 Eme.45......................... le N ic k e l.C 3........................ le E nc.or m...- ISO Th.333, h.330 mod their daughter Pfaduels. e Based es alphs distategration role of i . oc el.85........................ 800 lb ......................... 30 W.334. U.234. mad U.388. i N anba um.9 3 m.................... le E n trom u m.9 3.................... {"j]3 4,8 g-B i Maamum.WS le Za rcon t u m.93.................... le

- *c ha u m.91 10 Earcont um.9 7..................

30 o.m m m.I n.................... le 20 27 December 30,1982(reiet)

App.D App,9 PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION O APPfluOtX D -lftstTED $TATES NCLEAR REcutAfony Couw$$ov REGios.At OrreCEs l Assesses Teesmeae 04hent AmpW* 9 CornerelaA Deanet Duette et Cens'ee Weae Lf5NoC, 839 M AertA Esg of EF991337 9 @ toeveg asaaeamin hem awaerwe he. Jrsey ses.. Passe PA toept IF'$r ass-toop Q vn W st eas emet. rus tm eems Gespa am, weneso, n w l usW 901 +4 shepa,. e e s o hewis Sreef ern, Geositr atos $ Ce owe Nome mee M Ceews Tenrewee wepw $,,ee 2000. Assu GA 30323 FT56 242-4303 W g P tam are wen! vey es Repra has %. esseL w terwassak theen USN41 Fee Roossee Reed, Gam Oth % Moo k Orac ag mgaren Eam IL Wi37 FTS, 38s.6t00 o 0 SePF Fir Amaw Cowese tasse. ta=ess Lansees & US*e4C. 61 Man PataCNee.Sune 6117 eso4100 4 ing % a mas.co. anym Onnot Obe'w e la.ta tocc. Am Ta 7ecit. FTsa 72e-4100 Dears to as viaa are wyw'wg Re9er fir Fee O'ese Usas tC. m psn W ure%e meaney, CM23s 236-?232 s Femur ONe 73o $m's Soest. FT$a 234-F232 P O toe 253M W CO N225 n,, ..A., C m e. % oom usNo:. tese maai Lo o s.mo rio. eatsiso 3roo Ps:ph:1mme tygy g g.a stasy new Creen. CA 9dH6 FT5s 463-3M ~ O l I l l l I i 9 e l Deceminer 31,1984 20-28 1 l l w

i UNITED STATES NUCLEAR CECULATORY COMMISSl;N RULES and REGULATIONS TITI.E 10. CHAPTER 1. CODE OF pfDERAL AEGULATIONS-ENERGY U PART UCENSES FOR RADIOGRAPHY AND RADIATION SAFETY M REQUIREMENTS FOR RADIOGRAPHIC OPERATIONS Sec. g34.1 Furpose and scope. position for purposes of making a radio- ~ ,y 8 N # #*E '"#*3 M3 Applications for specific hcenses. Tlus part prescribes requirements for (e), Scaled source means any by-o 34.s nnformanon cosecnon requirements: the issuance of licenses for the use of i Out approval.

product mslerial that is encased in a Sabrert A-SpecificLkmassagRequhements scaled sources containing byproduct ma.3 capsule designed to prevent leakage or M.i t issuance of spectric Licennes for une of terial and radiatton safety requirement:8 escape of the byproduct material; mented sources in radiosraphy-for pertons using such sealed sources inj (f) " Storage contames" means a de-s sabpart B-Radastae: Safety Rageirements radiography. The provtsions and require' vice in which sealed sources are trans-ments of this part are in addition to, and in estitution h, oh rm

_ ported or stored. EQUIPM EN T CONTROL u not H.2 Laan as le.eis of redsstion for resio, ments of this chapter. In particular, the Sousa chager'* means a device sraphic esposure devices and stor. ese containers. Frovisions of Part 30 of this chapter designed and used for replacement of M.22 Locking of rodnesraphic esposure de. apply to applications and licentes subject sealed 60urces in radiographic exposure ricos and storase costanners. to this gart. Nothing in this part shall* devices. including those alao used for MN apply to uses of byproduct material forj transportmg and storage of sealed I u sur trunwa ts. ces H.2s Laak te*tias repaar, tassms. opes.ms. medical diagnosis or inerapy. g60 O 7Njc*,,** $34.2 Definitions.

installation" means e shielded installation or structure designed or

" sed 6 twat intsaded for radiography and in which i 2 mar a ses (a), Radiography means the exam >, radiography is regularly performed. M.2s inspection and mantennace of radm. sraphic esposure devices and stor." nation of the structure of materials by j nondestructive methods, utili2ing sealed 34,3 p ter speems seenees. age containers. M.29 Permanen t naiographic installations.. sources of byproduct snaterials; A person may file an application for I PERSONAL RADIATION SAFETY RE * (b) Radiographer" means any indi-{ specificlicense for use of sealed sources QUIREMENTS FOR R ADIOGR APHER $ vidual who perforins or who, in atten a in radiogr'apyin duplicate on NRC AND RADIOGRAPHERS' ASSISTANT dance at the site where the sealed sourceI, Form 313." Application for Material M.3 : Tuartas. cr sources are being used, persona!!y

Ucense."in accordance with the M.3 2 Operatins and eraersency procedures-supervises radiographic operations and Provisions of 9 30.32 of thle chapter.

M.3 3 P m m lanonnoeins who is responsible to the licenree for I PRECAUTIONARY PROCEDURES IN RADI. assuring compliance with the require-888 0 # "I # E** * "8 ments of the Commission's regulations H 88 8***'"Y - and the conditens of the license: (a)ne Nuclear Regulatory M 42 Postins. (c).. Radiographer s assistaat,, means g.harton has submitted m i M.43 Radiatbn survers and survey records. ""7 I*dindual who. under the pctsonal hformation milectios ta saperweios otratiosrataers'naenstants 34.44 superviaton of a radiographer, uses radio-a contained isitinis part to Omce of graphic exposure devices, sealed scurcesy u.n.g-.at and Budget (O.iB) for EmPTtONS approval es required by the Paperwork 1 or related handling tools, or r.fiation"f Reduction Act of1980(44 U.S.C. 3801 et M.s1 Appucetiums foe eseamptions. survey instruments in Jadiographyj ^PP**d'* ^- (d) " Radiographic exposure devic"""; esq4 NB hae W b information collection requirements 1 Asesentry: Esos. St.1st 1st 185. es S**t. ses, sea, sea, set to ammedet sa UE sitt means any instrument sontaining a sealed Waimd in this part under control n 3RRL 3M5. Per the perpeese of sec. 3es, source fastened or contained therein, in member 315).65*. i es mas.ses,as asended, et UM asPt. which the sealed source or sh.ieldmf (b)The oppsowed inf6rinatien I I 8', thereof may be moved, or ttherwise collection requiroasents contained la this i ss 4eicl assmed under ses, sese, se Sant. seeL changed, from a wielded to unshielded part appear la ll 34.11. M 34. M.25. as anseded, es U.S.C. Beattel, emissa 34.35, ME. 34.3L 3 LE M.31. M.33 '-' 8" O A & 31,1984 m i l

M PART 34 o UCENSES FOR RAD 15C2APHY AND RADIATISN CAFETY-(c) This part contains infermation (c) The applicant submits a descrip. (b) Each sealed source storage container end source chat:ger aball have collection requirementa in addition to tion of its over-all organizational strue, a lock or outer locked container those approved under the concol ture pertaining to the radiography pro-designed to prevent utwthorized or g cumber specified in peregraph ta) of this gram, includmg specified delegations of accidental removal of the sealed source g section. These infortr.ation collectica authont) and resporssibdity for operation from its shielded pcaitiort Stor86e

requirementa and the control cicbers under which they an approved m as of the program; and containers and source changers shall be (f) The apphcant who desires to con-kept locked wben contairwng sealed

fonows:

0)In 134.3 Form NRC-313R is duct his own leak tests has established sources except when under the direct a pproved under control number 3194-adequate procedures to be followed in surveillance of a radiog+apher or a leak testing sealed soarces, for possible ; radiographer's assistant. E3. 2 Jeakage and contammation and abmits : 6 34.23 Storage precautions. Subpart A-Specific Licensing to the Commission a description of such ! Locked radiographic exposure devices Requirements procedures includmg- .asto storage containers shall be physically (1) Instrumentati n to be used, secured to present tamperms er removal 34.11 issuance of specific bcenses (2) Method of performing test, e.g., by unauthorized personnel. for use of sesled sources in radiog-p ets on eq@ ment to be smead ad 34.24 Radiation wrvey instruments. raphy. method of taking smear, and An application for a specific license (3) Pertment experience of the person The licensee shall maintam sufficient for use of scaled scurces in radiography who wdl perform the test. cahbrated and operable radiation survey instruments to make physical radiation wdl be approved if. Subpart B-Radiation Safety surveys as required by this part and Part (a) The applicant satisfies the general Re@mts requirements specified ca 30.33 of this : 20 of this chapter. EQUIPMENT CONTROL chapter; tb) The apphcant will have an ade-E j 34.21 Limits on levels of radiation Each radiation survey instrument shau quate program for training raMgraphers for ra&ographic exposure devices and be cahbrated at iritervals not to exceed c. and radiograp!;ers' assistants and submits storage containers. ". three months and after each instrumert Radiographic exposure devices measur. $ serviews and a record shallt>e maintained to the Commission a schedule or de-scription of such program which spenfies ing less than four M) inches from the i of the results of each icstrument calibra-

tion and date thereof for two years after 2

scaled source storage position to any the date of cahbratiort [o fc r" "n. exterior surface of the device shalf have ( sio radiation level in excess of 50 mdli-(3) On-the-fob training; toentgens per hour at six (6) inches from (4) Means to be used by the bcensee any exterior surface of the device. Radio-to determme the radiographer's knowl, graphic exposure devices measuring a tion shall have a range such that two edge and understanding of and abdity to minimam of four (4) inches from the milhioentgens per houe through one comply with Commission regutations sea ed source storage position to any and licensing requ:rements, and the ger-exterior surface of the device, and all roentgen per hour can be measured. ating and emergency procedures of the storage containers for scaled sources or applicant; and for ra6ographic exposure devices, shall

15) Means to be used by the licensee have no radiation level in excess of 200

$ 34.25 Leak testing, repair, tessmg, opening. modification and replace-to determme the radiographer's assistant *s mdhroentgens per hour at any exterior knowledge and understandmg of and abil. ment of sealed sources. storlace, and ten (10) milliroentgens per ity to comply with the operatmg and hour at one meter trom any extenor (a) The replacement of any sealed emergency procedures of the applicant, surface. The ramation 1q1s specified are source futened to or contained in a (c) The applicant has estabhshed and with the saaled source in the shielded 3 radiographic exposure device and leak submits to the Commission satisfactory fiw "off' i o sition-E testing, repair, taggms, opening or any written operating and emergency proce-2 other modification of any sealed source dures as described in $34.32; 9 34E I.oeting et raeograpNe esposure shall be performed onh iby persons spe- " N '.N'

- N '"d **"'"

cifically authorized by the Cc-mmission to enenewa d '** (d) The applicant will have an internal inspection system adequate to assure t.) Each radiographic exposure device (b) Each sealed source shall be tested that Commission regulations, shat! have a lock or outer locked for leakage at intervals not to encred 6 C;mmission license provisions and the contamer designed ta prevent F

epplicant's operating and emergency g unauthorized or accidental removal of months. In the absence of a certificate; procedures are followed by; the sealed source frem its shielded from o transferor that a test has b'een
r: dngraphers and radiographers'
position.The expoore device or its made within the 6 months prior to the i

container shall be kept locked when not transfer, the scaled source shall soit be casistants; the inspection system shall S

include the performance of internal under the direct surveillacce of a put into use until tested.

inspections at intervals not to exceed radiographer or a radiographer s three months and the retention of assistant or as otherwise may be records of such inspections for two authorized in i 34.41. In addition. du-ing radiographic operations the sealed yzars: source assembly shall be secured in the shielded position each time tne source is returned to that position. May 31,1984 34 2

PART 34 o UCEN3ES FOR ftADIOGRAPHY AND RADtATIQ SAFETY-(e) ne took test aban be espawe or i 24.26 e.ortesy hee.iory, source is e= posed we eudele viin.: abam actueM wbn an anew detecting the presence of 0.005 micro-Each licenece sha2 corduca e qu6rtetty %) curie of reseovaMe contaminas6on on the phpical inventory to account for hD e

eseled source. An acceptabis 3sak test for sealed sources necerved and possessed (c]De alarm eyeiem she I be i.ewd g emaled sources in the posesseica c f a ender bie bcsaac, ne records of the at hiservela not to enceed shrea t: enths g radsography thas would be to tad at inventories shall be masteined for two or prior to the ftet wee therseSer d the e the nearest accessible point to the sealed years from the date of the inventory for ocurwin the troellet:om beords of the I source storage position, or other appro-d haspecti.on by the Commsenen, and shall testa shaNyt f9e two yeus priate measuring po6t, by a poordare to : include the quinthies ard kinds of by-PERSONAL A ADIAT3ONiaJETY 1

be approved pursuant to $34.11(f). jproduct meterial, location of sealed REQUIREMENTS FOR m sous es, and the date of the inveMory. RADIOGRAFHEKS AND 3 $ 34.U Utilhetion legs. RADNXGAPHEIS' ASSISTANTS l Each licensee shall cdntain current gwas ?remes Records of leak test results shad be loss, which shall be kept available for two (a) The beneee shallret peneJt any i

kept in units of microcurass and raain, years from the Aate of the recorded individual to act se a radiographer until t tai::ed for inspection by the Comssaseson event, for snspection by the Commission, such indMdeel:
for six months efter the next required at the addytss specifwd in the facense.

N Hes ken tnetmcwd in the suMeets - leaA test is performed or unt2 the Jealed showing fer each sealed source the fol-

- 08O D"b A 2 a s

source is transferred or disposed of. kwtag faformation: et on centemed in this port e:W ut the opplicable y' (a) A destription (or make and model sections of parte tg and ta et this sn.; ster) of the adaographat enosure chapter. NRC liceno61s) nnder which the 2, device or storage container in which the re hographer wi2 perform radiography, (d) Any test conducted pursa. ant to - and the beensee's operatang and paragra;;hs (b) and (c) e,f this :eection

teoled soarce islocated, (b) The Mentity of the radiographer emerFacy proudums; which reecaIs the pasence of 0.00$ Ttowhern as4ned;ord (3) Hee demaristrefed ca.mpetence to l

minocurse or note of removable radio. (c) T&s plant or site where used and '}see e e 3 r c emposure g, a-tive raaterul shad be considerei evi- ,dstes of #se. i dsoce that the sea:ed source as leaking. } handling tools.and survey iriatruments end ne licensee shan irtmediately wathdraw w," % j (4) Has demonsareted arsderstamding the equipment tavolved from use and amnesseere, one eeuree ehengers. g of the instructions in the paragraph (al 4 shat! cause it to be decontemhuted and (a) Re kensan sheff check for < by successful coupletion of o wntten sepaired or to be disposed of, in accor- . obvivos defects.irt radiographe

: eat and a fie xamination om the

@ts em. dance with Comrnisson regulatio.ns A e1powe devices, stosage con'.alwe. report sha!! be f3ed, within 5 days of the and source che.ngets prior to see each (b)%e licensee the5 not permit say day b e ipment is asied indMdual to ecs as e radiographer"e test, with the D: rector of Nuc]c,ar Mate-(b) The cansee sha!! coeduct a assistant until each indMdual: rial Safety an( Safeguards, U.S. Naclear program for inopution and metatsmace 1 (1) Hee received copjes of and Regulatory Coremission, Washington, : of radiographic exposare devices. instruction in the license (e opereting $ D.C. 20135, describing the equipssent storage meteinare,and source sianger, and emersecy procedures; e invoked, the test results, ar.d the corec 7et intervele not to enceed three meaths f2)Has demonstrated cornpetence to = or prior to the Aret use there efler to use. medenha personal evpervision of A g tive action taken. A copy of such report., neeere properIsact4nus of coepsnects he radiographer, the rediopephic shan be sent to the Directc; of the 1 important tosafety.Rece;deof thcee espoeere devics e, sealed sources. appsopriate N aclear Regulatory Commis. ' inspections and meintenance akin be I reisted hendhns l pols.and radia tion tion's Inspectaco and En.fortement R,. I keys for two yisie. say instmswnts that the assistant g>onal Office I;ated in Appud.x D of Peyt p p.,,,,,,,,

{

20 of this chaptrer "Standords for Protec-hiemmenene. of the inwruebone in this paragraph (b) tion Asamst Radietion. (a) Pernmenent radiographic by successfully completmg a written or (e) A analed source which is not foto. hastellations having high radiatica area oral test and a f; ele enorr.ination on the d tened to or contaxned in a radiographic avreece conds of the types deeMbed subjecto covered exposure device shal have permanently 2 8 AcH2W2Xii4 or N shall (c) Recorde sf the above training. 6 e ***t b I& wing ePeci*l incJuding copwe of written tests and attached to ft a duraMe tag at laset one (1) inch square bearing the p.teocribed trance thatis used for mine[ e$11bea ntained for radastion caution symbolin conventional personesi eccese to the high radiation duse m colors, sea, gents or purple on a ye!.ow ame is a permanent rad 6ographic background, and at least the instructione: instarlatien so which this section opplies "Desser-Radioactive tfeterial-Do Not shellhave both visible.end sudsbje Handie-Notify Ovil Authorities if warnme abale to worn of the presence Founi of es&ation. He visihIe signal shell be actmeted by radiat;oe whenever the I 1 1 a l

l l g 34.32 Operating and emergenc> pro-and worn by only one indmdual. I 34 44 SuP*' vision of radiogesphers' cedrres. (b) Pocket dosimeters shall be read and exposures recorded daily. Wheneser a radiographer's assistant i (c) Pocket dosimeters shall be uses radiographic esposure devices. l The hcensee's operating and emer-gency procedures shal. include instruc-checked at penods not to exceed one uses sealed sources or related source tions in at least the following: year for correct response to radiation. handling tools, or conducts radiation l C) The handhng and use of licensed, Acceptable dosimeters shall read within surveya required by i 34 43(b) to j sealed sources and radiographic caposure

plus or mmus 30 percent of the true

, determme that the sealed source has ( radiation exposure. returned to the shielded position after d; vices to be employed such that no (d)If an individual's pocket dosimeter a en exposure, he shall be under the a person is likely to be exposed to radiation ' is discharged beyond its range, his film ! personal supervision of a radiographer, doses in entess of the hmits estabhshed in ; badge or TLD shall be immediately sent The personal supervision shallinclude ) Part 20 of this chapter " Standards for Qor processing (a) the radiographer's personal presence l Protection Agamst Radiation"; at the site where the sealed sources are ( j (b) Methods and occasions for con-(e) Reports receive'd from the film being used.(b) the abihty of the radiographer to give immediate duct.ng radiation surveys.

badge or RD processor shall be kept for assistance if required. and (c) the 3

(c) Methods for controlhng access to inspection until the Commission radiographer's watching the assistant : ~ radiographic areas; a authorizes their disposal Records of ~ I (d) Methods and occasions forlocking j daily pocket dosimeter readings shall be "",*",ce Ife operations referred

tnd securms radgaphic exposure de.
kept for two years.

v.ces, storage contamers and scaled EXEMPTIONS s PRECAUTION ARY FROCEDURES IN sources. (e) Personnel monitonns and the use R ADIOGR APHIC OPER ATIONS i 34.51 Applications for exemptions. of personnel monitonns equipment; $ 34.41 Security. 2 The Commmion may, upon appbca-(f) Transportmg sealed sources to ition by any bcensee or upon its own I ** II* E #* ~ the radiographer or radiographer,'s assis-mitiative, grant such exemptions from the fhlJ locations. includirg packing of rade ographic esposure deuces and storage requirements of the regulations in this tant shal! maintain a direct surveillance of g art as it determines are authorized by containers m the s chicles, postmg of p

the operation to protect against unau-law and will not result m undue harard to schicles and control of the sealed sources thonzed entry into a high radiation area'

-dunng transportat t i, W or propen E as defmed in Part 20 of t' sis chapter, [ (gl Mmimizmg esposure of persons m ; except (a) where the high radtation area is 3

the esent of an accident, equipped with a control device or an (h) The procedure for nottfying alarm system as described in I rundamentals of Rodiotica safety g
proper persons in the event ot an acci-

{ 20.203(c)(2) of tius chapter, or (b) A Charactenstics of gamma radiation 8 I dent,ard where the high radiation area is locked to g', 'diIa t c (i) Maintenance of records. protect against unauthonzed or acci-C. Hazards of esposure to radiat on. de ntal entry. D teels of radiation from hcensed (j) The inspection and maintenance of matenal. radiographic esposure devices and storage $ 34 42 Post 188-E. Methods of controlhng radiation dose. E containers. Notwithstandmg any provisions in 1 W 'k *8 ** { $ 20.204(c) of this chapter, areas in f ed a which radiography is being performed = (k) Steps tr.ct must be taken shall be conspicuously posted as requtred !#[,Ro tion hrion Inmnwntorion To y, l immediately by radiography personnel by Q 20.203(b) and (c)(1) of this chapter. a A. Use of radiation surve) instruments j e m the nent a pocket dosimeter is found lL 6 t Operation l ' ta be off-scale j 34.43 Radiation surveys. I h (a) Atleast one cabbrated and 2 tion operable radiation survey instrument % (1)1he procedure (sl kr identifying B Survey techruques. shall be available at the location of ". cnd r?portmg defects and C Use of personnel monitonna equipment. radiographic operations whenever t Film badges and thermolummescent noncimphance, as required by Part 21 of 8 % this chapter. . radiographic operations are bein8 dosimetern ITts e1 l performed.

2. Adei dosimeters (b) A survey with a radiation survey

= i j sa 33 personnes mo<utonne. instrument shall be rnade after each III Rode gwhic Eqwpment To be Used (t) The beensee shall not permit any radiographic exposure to determine that A. Remote handhng equipment. mdividual to act as a radiographer or a

the sealed source has been retuined to B Radiographic exposure devices.

, rrdiographer's assistant unless. at all sta shielded position. The entire C S'0'ase contamer. I

tim:n durms radiographic operations, circumference of the radiographic IV Inspection ond Maintenance Performed

erch such indnidual wears a direct exposure device shall be surveyed. If the by the Radiog ophers 2

radiographic exposure device has a , rzidmg pocket dosimeter and either a

v. Case Histories o/ Radiography Accidents

, film btdge or a thermolummescent notree guide tube, the survey shall - dosimiter (TLDI Pocket dosimeters include the guide tube. shsil have a range from aero to et least (c) A racord of the survey required in 200 milbroentgens and shall be paragraph (b) shall be maintained for richtrged at the start of each shift Each two years when the survey is the last KNote removed 49 i R 196231 film bidge and TLD shall be assigned to survey prior to locking the radiographic exposure device and ending direct surveillance of the operation. May 31,1984 344

1 APPENDIX H 1.0 Q.A. PROGRAM FOR TRANSPORTATION OF RADIOACTIVE MATERIALS ()h 1.1. INTRODUCTION q 1.1.1 This section identifies Minnesota Valley Engineering's Quality Assurance Program for the transportation of radioactive materials in accordance with 10 CFR Part 71. MVE is licensed under 10 CFR Part 34 for the use of IR-192 for purposes of industrial radiography. 1.1.2 This section is applicable to any transportation package containing an IR-192 source in excess of 20 ci. delivered to a carrier. 1.1.3 MVE activities with respect to transportation packages includes; use, handling, inspection and maintenance. Design, fabrication, assembly and testing of transportation, packages is by others. However, responsibility for compliance with Part 71 requirements is with MVE for those transportation packages which it utilizes I and delivers to a carrier. 1.2 Q. A. PROGRAM 1.2.1 This Q.A. Program identifies the administrative controls to be followed to assure all requirements for transportation packages are being met. Written procedures needed for implemen-tation of this program are identified in the Radiation Safety () Manual. Control of this, including revision, will be as stated in Section 1.0 of the Radiation Safety Manual. t 1.2.2 Attached to this section is a matrix identifying the require-ments of the Q.A. Program with the corresponding implementing procedures, and procurement of documentation and control of all NRC licensed equipment used by MVE. All certification and handling procedures will be on file with the Radiation Safety Office. 1.2.3 The company Safety Officer has over all administrative re-sponsibility for this program. The Radiation Safety Officer shall have specific implementing responsibility, including training and certification of personnel, document control, and ensuring manufacturers design and Q. A. Program control. 1.3 ORGANIZATION 1.3.1 The organizational structure of MVE's Radiation Safety Program is depicted in Figure 1. The specific individuals are as follows. 1.3.2 The President has overall responsibility and authority for the direction of MVE. 1.3.3 The Company Safety Officer reports to the President and has (~'\\ overall responsibility and authority for the adminstration of ^% l the MVE Safety Program.

1.3.4 The Radiation Safety Officer has the authcrity and responsibility for the implementation of the Radiation Safety Program at MVE. 1.4 DOCUMENT CONTROL 1.4.1 Measures will be established to assure that documents relating to procurement, handling, storage, shipping, and inspection of transportation packages are controlled. Changes to documents will be performed in accordance with written procedures. 1.4.2 The Radiation Safety Officer shall assure that Q.A. functions. are conducted in accordance with the latest approved requirements. 1.5 HANDLING, SHIPPING AND STORACE 1.5.1 Measures shall be established to assure that handling, shipping, and storage requirements are completed and implemented in accor-dance with procedures prior to release of shipments. 1.5.2 Radiographers will implement the necessary activities. 1.6 INSPECTION 1.6.1 Measures shall be established to assure that appropriate inspections are completed and accepted prior to delivery of transportation O_ packages to a carrier. The appropriate records shall be completed to indicate the inspection acccptance. 1.6.2 Nonconforming items shall be positively identified by use of status tags to prevent inadvertant use. 1.6.3 Radiographers will perform all necessary inspections directed by the Radiation Safety Officer. 1.7 RECORDS 1.7.1 A system shall be developed to assure appropriate records are maintained, identified, and easily retrievable. 1.7.2 The Radiation Safety Officer shall be responsible for implementing the records system in accordance with written procedures. These procedures shall identify the types of records.under this program including manufacturer's Certificate of Compliance and reference drawing. 1.8 AUDITS 1.8.1 Measures shall be established to assure compliance to this program through audits utilizing written checklists. C'} 1.8.2 Audits shall be conducted at least once a year and deficiencies evaluated and corrected. Auditors shall have no responsibility in the area audited. 1.8.3 Management shall be informed of audit results. i

l l l 4~ 1 ORGAN!ZATION CHART FOR RADIATION SAFETY PROGRAM ) President Company Safety Officer Radiation Safety Consulta Radiation Safety Officer Radiographer r~ ~ Assistant Radiographer Figure 1 / esU l 1 141}}

ML20153H020

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