ML20141A962
| ML20141A962 | |
| Person / Time | |
|---|---|
| Issue date: | 06/14/1997 |
| From: | Lohaus P NRC OFFICE OF STATE PROGRAMS (OSP) |
| To: | GENERAL, OHIO, STATE OF, OKLAHOMA, STATE OF, PENNSYLVANIA, COMMONWEALTH OF |
| References | |
| SP-97-045, SP-97-45, NUDOCS 9706230226 | |
| Download: ML20141A962 (56) | |
Text
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ALL AGREEMENT STATES SUN'l41997 OHIO, OKLAHOMA, PENNSYLVANIA TRANSMITTAL OF STATE AGREEMENTS PROGRAM INFORMATION (SP-97049 Your attention is invited to the attached correspondence which contains:
INCIDENT AND EVENT INFORMATION.........
PROGRAM MANAGEMENT INFORMATION...
l TRAINING COURSE INFORMATION.............XX ACCEPTANCE TO THE INTRODUCTORY HEALTH PHYSICS COURSE (H-117)
TECH NIC AL INFORM ATION........................
OTHER.....................................................
Supplementary Information: Enclosure 1 is the list of students from the States selected to attend the July 14-18,1997, introductory Health Physics course (H-117). Please provide the list of students and the travel instructions (Enclosure 2) to each individual from your program that is on the list. Those traveling at State expense should be encouraged to follow the instructions and make the appropriate travel and lodging arrangements as soon as possible. Those traveling at NRC expense should follow the specific additional instructions in Enclosure 2. Please refer to the All Agreement States Letter (SP-95-006)
" Timeliness of Travel Orders" for further information on timing and travel arrangements for attendance at training courses.
If you have any questions regarding this correspondence, please contact me or the individual named below.
POINT OF CONTACT:
Dennis M. Sollenberger TELEPHONE:
(301) 415-2819 FAX:
(301) 415-3502 INTERNET:
DMS4@NRC. GOV Original signod Di:
PAUL H. LOHAUS I
Paul H. Lohaus, Deputy Director Office of State Prugrams 3.,
7
Enclosures:
j kg As stated Distribution:
DIR RF BUsilton D.CD (SPO3)
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GDayis
- PDR (YES v' 4 NO
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All Agreement State File TTC(JAN):
FAXED TO STATES: 6/16/97 DOCUMENT NAME:
G:\\SP97045.DMS, G:\\lNTROHP.DMS, Chapter 12 materialis not available cisctronically.
o To receive a copy of this document. Indicate in the box: h Col'y without attachment /enclosur,e1 "E* = Copy with attachment / enclosure "N" = No copy OFFICE OSPA$ l
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OSP:g(/ f.l l
l NAME DSollenberdsi:nb PHLyh4,0_s 1
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j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 l
June 14, 1997 ALL AGREEMENT STATES OHIO, OKLAHOMA, PENNSYLVANIA TRANSMITTAL OF STATE AGREEMENTS PROGRAM INFORMATION (SP-97-045 )
Your attention is invited to the attached correspondence which contains:
INCIDENT AND EVENT INFORMATION........
PROGRAM MANAGEMENT INFORMATION...
TRAINING COURSE INFORMATION.............XX ACCEPTANCE TO THE INTRODUCTORY HEALTH PHYSICS COURSE (H-117)
TECH NICAL IN FO RM ATIO N........................
OTHER...................................................
Supplementary Information: Enclosure 1 is the list of students from the States selected to attend the July 14-18,1997, introductory Health Physics course (H-117). Please provide the list of students and the travel instructions (Enclosure 2) to each individual from your program that is on the list. Those traveling at State expense should be encouraged to follow the instructions and make the appropriate travel and lodging arrangements as soon as possible. Those traveling at NRC expense should follow the specific additional instructions in Enclosure 2. Please refer to the All Agreement States Letter (SP-95-006)
" Timeliness of Travel Orders" for further information on timing and travel arrangements for attendance at training courses.
If you have any questions regarding this correspondence, please contact me or the individual named below.
POINT OF CONTACT:
Dennis M. Sollenberger TELEPHONE:
(301) 415-2819 FAX:
(301) 415-3502 INTERNET:
DMS4@ RC. GOV 3
1 hM l \\
l Paul H. Lohaus, ep ty Director Office of State Programs
Enclosures:
As stated l
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l
i AGREEMENT STATE STUDENT LIST FOR THE INTRODUCTORY HEALTH PHYSICS COURSE (H-117)
JULY 14-18,1997 MARYLAND P.L.. Eisgruber (Traveling at State Expense)
Maryland Department of the Environment Radiological Health Program 2500 Broening Highway Baltimore, MD 21224 Howerd Perry ill (Traveling at State Expense)
Maryland Department of the Environment Radiological Health Program 2500 Broening Highway Baltimore, MD 21224 OKLAHOMA Steven K. Fernandez (Traveling at State Expense)
Oklahoma Department of Environmental Quality Waste Management Division / Radiation Management j
1000 N.E.10th Street Oklahoma City, OK 73117-1212 Earlon Shirley (Traveling at State Expense)
Oklahoma Department of Environmental Quality Waste Management Division / Radiation Management 1000 N.E.10th Street Oklahoma City, OK 73117-1212 TEXAS - TNRCC George FitzGerald (Traveling at NRC Expense)
TX Natural Resource Conservation Commission UIC, Uranium and Radioactive Waste Section - MC 131 P.O. Box 13087 Austin, TX 78711-3087 l
Alice Hamilton Rogers (Traveling at NRC Expense)
TX Natural Resource Conservation Commission UIC, Uranium and Radioactive Waste Section - MC 131 P.O. Box 13087 Austin, TX 78711-3087 Kathleen Vail (Traveling at NRC Expense) l TX Natural Resource Conservation Commission UIC, Uranium and Radioactive Waste Section - MC 131 P.O. Box 13087 Austin, TX 78711-3087 ENCLOSURE 1
1 IN rp;c;.NS TO STUDENTS ACCEPTANCE: This is to advise you that those individuals in Enclosure 1 have been accepted for participation in the training course (H-117), " Introductory Health Physics."
This course is scheduled to be presented July 14-18,1997 at the Professional Training Center on the third floor of the Two White Flint North Building,11545 Rockville Pike, Rockville, MD. The NRC buildings are across the street from the White Flint Metro station.
COURSE: The course starts at 8:30 a.m. on Monday, July 14,1997, and will begin at 8:00 a.m. on all other days. The class will end at approximately 4:00 p.m. each day except for Friday, July 18,1997, which will end at approximately 12:00 noon. Attached are the course outline and Chapters 11 and 12 of the course manual that we recommend you read prior to coming to the course. The materialin Chapters 11 and 12 will not be covered specifically in the course but will enhance your understanding of the other material.
i LODGING AND TRAVEL: The following hotels are listed for your use. Participants must make their own lodging arrangements, individuals should request a State or government employee rate at the hotels. The Ramada or Doubletree are recommended based on their location near the Twinbrook Metro station. For those participants that fly to the area, taxi or metro service is available to take you to the hotel.
Ramada Inn at Congressional Park Doubletree Hotel 1775 Rockville Pike 1750 Rockville Pike Rockville, MD Rockville, MD j
(301)881-2300 (301) 230-6729 1-800 255-1775 1 -800-222-TREE TRAVEL AND EXPENSES FOR STUDENTS TRAVELING AT NRC EXPENSE:
l For those States that have requested that NRC continue funding their travel to training and have received notice in writing that NRC will continue to fund seasonable training and travel expenses for fiscal year 1997, they should follow the instructions below for Federal travel orders:
TRAVEL: If you travel by air, you must call Carlson Wagonlit Travel, (202) 554-1850, to l
make your flight reservations. You must use Carlson or you may not be reimbursed for your plane ticket. Your tickets will be mailed to you about a week before the course begins. If you travel by car, you will be reimbursed at a rate of $0.31 per mile, with the total payment not to exceed the minimum government airfare. For those participants that fly to the area, taxi or metro service is available to take you to the hotel.
The Nuclear Regulatory Commission has received approval from the General Services Administration to allow State employees who are able to obtain a special discount (i.e., a lower fare than is available from Carlson Wagonlit Travel) through their State travel agency to purchase airline tickets themselves and be reimbursed via their travel voucher. In order to use your own State travel agency, it must be confirmed that Carlson Wagonlit Travel is not able to obtain that same class ticket for the same price. Before purchasing your own ENCLOSURE 2 a
ticket, please contact Brenda Usilton at (301) 415-2348 in order to assure the proper
. procedures are followed.
l EXPENSES: State participants traveling on Federal orders will be reimbursed for expenses in accordance with Federal travel regulations. A voucher will be provided to you at the l
course. Receipts are necessary to claim any expenses of $75,00 or more. Telephone calls l
will not be reimbursed by NRC. The per diem rate for the Rockville, MD area is $124.00
)
for lodging and $42,00 for meals and miscellaneous expenses, not to exceed $166.00 per day.
l Any questions about, or changes in, travel should be directed to Ms. Brenda Usilton at l
(301) 415 2348. Any questions on the course should be made to Dennis Sollenberger at (301) 415-2819.
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ENCLOSURE 2
1 l
Please FAX the following information to Brenda Usilton at (301) 415-3502 by 5 pm (EDT) June 27,1997 Course or Workshop: Introductory Health Physics (H-117)
Dates:
July 14 - 18,1997 Travel:
July 13 - 18,1997 Location:
NRC Professional Training Center, Room T-38-39 Third Floor, Two White Flint North 11545 Rockville Pike Rockville, MD NAME:
BUSINESS ADDRESS:
l WORK PHONE NUMBER:
l SS#:
Departure City (airport):
1 Date of Departure (if not Jul 13):
Please provide reason:
Date of Return (if not Jul 18):
l Please provide reason:
l Cost of Airfare (from Carlson Travel):
If you are driving indicate roundtrip miles:
Lodging Arrangements Made: (Yes)
(No)
ENCLOSURE 2
i Introductory IIerith Physics TABLE OF CONTENTS CIIAPTER 1 INTRODUCTION
1.0 INTRODUCTION
1-1 CIIAPTER 2 FUNDAMENTAL llEALTII PilYSICS CONCEPTS 2.0 FUNDAMENTAL llEAITil PIIYSICS CONCEPTS..
2-1 2.1 The Atom 2-1 2.2 Radioactivity and Radioactive Decay 2-3 2.3 Alpha Emission....................
2-3 1
2.4 Beta Emission.....
2-4 2.5 Positron Emission 2-5 2.6 Orbital Electron Capture.
2-5 2.7 Gamma Rays 2-6 2.8 Internal Conversion
........... 2-6 2.9 Radioactive Decay Law 2-7 2.10 Serial Decay 2-8 Chapter 2 Study Questions..........
. 2-9 CIIAPTER 3 INTERACTION OF RADIATION WITII MATTER 3.0 INTERACTION OF RADIATION WITII MATTER 3-1 3.1 Charged Particle Interactions 3-1 3.2 Energy Loss Mechanisms.
3-1 3.3 Stopping Power...........
3-1 3.4 Specific Ionization..
3-2 3.5 Range of a Charged Particle 3-2 3.6 Linear Energy Transfer............................
3-3 3.7 Photon Interactions
.......................................3-3 3.7.1 Photoelectric Effect
...........3-3 3.7.2 Compton Scattering...
3-3 3.7.3 Pair Production..........
3-4 3.8 Photon Attenuation and Absorption 3-4 3.9 Neutron Interactions.........
3-5 3.9.1 Slow Neutron Interactions
.........3-5 3.9.2 Fast Neutron Interactions 3-6 3.9.3 Neutron Cross Sections........
3-6 Chapter 3 Study Questions......
..... 3-7 CIIAPTER 4 RADIATION QUANTITIES AND UNITS 4.0 RADIATION QUANTITIES AND UNITS
... 4-1 4.1 Introduction
.. 4-1 4.2 Activity....
. 4-1 USNRC Technical Training Center i
Rev.0595
Introductory lierith Physics TABLE OF CONTENTS 4.3 Exposure
. 4-1 4.4 Specific Exposure Rate Constant 4-1 4.5 A bso r bed D o se.......................................... 4 -2 4.6 Dose Equivalent
. 4-2 4.7 Effective Dose Equivalent...........
4-2 4.8 Committed Dose Equivalent 4-3 4.9 Conversion Between Special Units and SI Units.................... 4-3 Chapter 4 Study Questions......
........... 4-4 CHAPTER 5 BIOLOGICAL EFFECTS OF RADIATION 5.0 BIOLOGICAL EFFECTS OF RADIATION..
. 5-1 5.1 Cell and System Biology Foundation
........ 5-1 5.1.1 Embryonic Development.
. 5-1 5.1.2 Body Systems.......................................... 5-2 5.2 Interactions and Effects
... 5-3 5.2.1 Indirect Effect....
......5-3 5.2.2 Direct Effect..
5 -4 5.3 Cell Radiosensitivity 5-5 5.4 Relative Biological Effectiveness (RBE)............
........5-5 5.5 Radiation Ilormesis..........
. 5-6 5.6 H igh Dose E ffec ts........................................ 5-6 5.7 Low Dose Effects
. 5-7 5.8 Radiation Risk 5-9 5.9 Radiation Injury Treatment.................................. 5-9 5.9.1 Initial Evaluation..........
5-9 5.9.2 External Contamination 5-10 5.9.3 Internal Contamination.
5-12 5.9.4 Penetrating External Exposure.
5-14 Chapter 5 Study Questions................................
5-17 CIIAPTER 6 SOURCES OF RADIATION EXPOSURE 6.0 SOURCES OF RADIATION EXPOSURE.........
6-1 6.1 Natural Radiation Sources..
6-1 6.1.1 Terrestrial Gamma Rays....................................
6-1 6.1.2 Cosmic Radiation 6-1 6.1.2.1 Introduction 6-1 6.1.2.2 Galactic Radiation.....
..................................6-3 6.1.2.3 Radiation Belts..............
... 6-4 6.1.2.4 Solar Particle Events 6-4 6.1.3' Radon and Its Decay Products.......
. 6-5 6.1.4 Ingested Radionuclides from Food............................ 6-5 l
6.1.5 Naturally Occurring Radioactive Materials.
6-5 6.2 Artificial Radiation Sources...........
6-6 USNRC Technical Training Center li Rev.0595
Introductory IIe:lth Physics TABLE OF CONTENTS 6.2.1 Fallout..........
.................... 6-6 6.2.2 Doses from Medical Radiation.....
. 6-7 6.2.3 Consumer Products and Industrial Devices
. 6-9 6.2.4 Nuclear Fuel Cycle Sources
. 6-9 6.2.4.1 Uranium Mining and Milling Operations..
6-10 6.2.4.2 Uranium Conversion Operations
. 6-11 6.2.4.3 Uranium Enrichment Operations 6-11 6.2.4.4 Fuel Fabrication Operations..
6-12 6.2.4.5 Power Production Operations................................
6-13 6.2.4.6 Waste Generation and Storage / Disposal Operations........
6-14 6.2.5 NARM..
6-14 Chapter 6 Study Questions........
6-16 CHAPTER 7 PRINCIPL.ES OF RADIATION DETECTION 7.0 PRINCIPLES OF RADIATION DETECTION 7-1 7.1 Methods of Radiation Detection 7-1 7.2 Gas-Filled Detectors..............
..................7-2 7.3 Solid State Radiation Detectors
.............. 7 -4 7.4 Commonly Used Portable Health Physics Instruments..
. 7-5 7.5 Guidelines for Instrument Selection.............
7-6 7.6 Exercise on Conducting Radiation / Contamination Surveys for Lost Radiation Sources / Contamination - Use of Different Instrumentation............
7-7 Chapter 7 Study Questions..................
7-8 CIIAPTER 8 PERSONNEL DOSIMETRY AND DOSE ASSESSMENI' 8.0 PERSONNEL DOSIMETRY AND DOSE ASSESSMENT..............
8-1 8.1 Introduction 8-1 8.2 External Dosimetry.........
8-1 8.2.1 Thermoluminescent Dosimeters.........................
8-2 8.2.2 Film Dosimeters
.........................8-3 8.2.3 Pocket Dosimeters....
8-3 8.2.4 Electronic Dosimeters...
8 -4 8.3 Internal Dosimetry....................
8-4 8.3.1 Scope and Responsibility
............................8-4 8.3.2 llazard Potential...
8-5 8.3.3 Bioassay 8-6 8.3.4 Measurement Equipment and Facilities........
8-9 8.3.5 Internal Dose Calculation Principles 8-12 8.4 Dosimetry Records.........
. 8-14 Chapter 8 Study Questions..
8-16 USNRC Technical Training Center lii Rev.0595 l
Introductory Hulth Physics TABLE OF CONTENTS CIIAPTER 9 ENVIRONMENTAL RADIOLOGICAL MONITORING 9.0 ENVIRONMENTAL RADIOLOGICAL MONITORING..
9-1 9.1 Reasons For A Program........
9-1 9.2 Environmental Pathways......
. 9-2 9.3 Environmental Transport Modeling
. 9-9 Chapter 9 Study Questions.
9-11 CIIAPTER 10 OPERATIONAL ASPECTS OF IIEALTil PIIYSICS 10.0 OPERATIONAL ASPECTS OF IIEALTil PHYSICS,..
10- 1 10.1 Philosophy, Meaning and Regulatory Bases of ALARA....
10-1 10.2 General ALARA Goals and Responsibilities 10-2 10.3 Dose Reduction Techniques.
10-3 10.3.1 Administrative Control Doses
. 10-3 10.3.2 Job Planning.....
10-4 10.3.3 Basic ALARA Principles for External Exposure...................
10-4 10.3.4 Contamination Control........
10-6 10.3.5 Training and Instruction...........
10-7 10.3.6 Facility and Equipment Design 10-7 10.3.7 Radiation Protection Program 10-9 Chapter 10 Study Questions.............
10-13 CHAPTER 11 RADIATION PROTECTION STANDARDS AND REGULATIONS 11.0 RADIATION PROTECTION STANDARDS AND REGULATIONS............. Il-1 l
11.1 History of Protective Standards..
11-1 11.2 Dose Liniits 11-3 11.2.1 Standards Based on Prevention of Stochastic Injury to Populations (the AEC and FRC years)..............
11-3 11.2.2 Standards Based on Assumed Risk-Benefit and ALARA Assessments (Adversary Era)......
11-5 11.3 Regulating Agencies...,
11-7 11.4 Agreement State 11-8 11.5 40 CFR Overview..........
11-8 11.6 Role of 0SHA - 29 CFR.
11-9 l
11.7 Summary of 10 CFR 20 11-9 l
Chapter 11 Study Questions 11-12 l
CHAPTER 12 RADIATION PROTECTION PLANS AND PROCEDURES 12.0 RADIATION PROTECTION PLANS AND PROCEDURES.......
12-1 l
12.1 Introduction 12-1 USNRC Technical Training Center iv Rev. 0595
Introductory II:cith Physics TABl.E OF CONTENTS 12.2 Administration 12-1 12.3 Occupational ALARA Programs 12-2 12.4 Operational Radiation Protection Procedures.
12-2 12.4.1 Radiation Protection Program Surveys and Monitoring 12-2 12.4.2 Posting and Labeling for Radiological Control..
12-3 12.4.3 Work Place Air Monitoring.................................
12-4 12.4.4 Instrument Calibration 12-4 12.4.5 Scaled Radioactive Source Control...
12-4 12.4.6 Management and Disposal of Radioactive Waste....
12-5 12.4.7 Emergency Response.............
12-6 12.5 Dosimetry Programs...
12-6 12.5.1 Internal Dosimetry Program................................
12-6 12.5.2 External Dosimetry Program..............
12-6 12.5.3 Radiation Dose to the Embryo / Fetus.......
12-7 12.6 Radiation Safety Training..................................
12-7 12.7 Occupational Radiation Protection Record-Keeping and Reporting......
12-8 12.8 Quality Assurance.................
12-8 12.9 Other Health and Safety Plans.....
12-8 12.10 S u m.m ary.........................
12-9 Chapter 12 Study Questions................................ 12-10 CHAPTER 13 COURSE
SUMMARY
13.0 COURSE
SUMMARY
13-1 13.1 Introduction...........................................
13-1 13.2 Radi oac ti vity...........................................
13-1 13.3 Interactions of Radiation with Matter..........................
13-1 13.4 Radiation Units.........................................
13-1 13.5 Biological Effects of Radiation..............................
13-2 13.6 Sources of Radiation Exposure..............................
13-2 13.7 Principles of Radiation Detection..
13-2 13.8 Personnel Dosimetry and Dose Assessment............
13-2 13.9 Environmental Radiological Monitoring 13-2 13.10 Operational Aspects of Health Physics 13-3 13.11 Radiation Protection Standards and Regulations..................
13-3 13.12 Radiation Protection Plans and Procedures.
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I USNRC Technical Training Center y
Rev.0595 i
l
Introductory lle:lth Physics TABLE OF CONTENTS LIST OF TABLES Table 2-1 Frequently Cited Radionuclides..
2-10 Table 3-1 Neutron Energies
. 3-8 Table 4-1 Radiation Quality Factors..
4-5 Table 4-2 Risk-Based Tissue Weighting Factors 4-6 Table 4-3 Special Units and SI Units 47 Table 5-1 Acute Effects of Radiation 5-18 Table 6-1 Ai erage Doses to Persons in the U.S.
. 6-18 Table 6-2 Additional Naturally Occurring Radioactive Substances...
6-19 Table 6-3 Typical Patient Doses From Nuclear Medicine Procedures..........
6-20 Table 6-4 Radiation Exposure From Consumer Products and Miscellaneous Sources 6-21 i
Table 6-5 Status of the Uranium Mills Licensed by the NRC as of May 1992......
6-23 Table 6-6 Listing of BWR Plants in the U.S.....
6-24 Table 6-7 Listing of PWR Plants in the U.S......
6-25 Table 7-1 Guide to Selecting Portable Radiation Detection Instrumentation........
7-9 Table 7-2 Commonly Used Portable Health Physics Instrumentation 7-10 Table 7-3 Portable Health Physics Instrumentation Selection Exercise 7-11 Table 8-1 Occupational Dose Equivalent Limits.....
8-17 Table 8-2 ICRP Stochastic Risks 8-18 Table 11-1 Non-Occupational Radiation Standards (NCRP) and Dose Limits (NRC, EPA) 11-13 Table 11-2 Weighing Factors for Stochastic Risk.............
Il-14 Table 13-1 Useful Equations 13-5 l
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USNRC Technical Training Center vi Rev.0595 l
Introductory IIc lth Physics TABLE OF CONTENTS LIST OF FIGURES Figure 2-1 Basic Structure of the Atom 2-11 Figure 2-2 Three isotopes of Hydrogen 2-12 Figure 2-3 Three Isotopes of flelium..
2-13 Figure 2-4 Nuclear Line of Stability 2-14 Figure 2-5 Upper Portion of the "Am Alpha Spectrum as Recorded by a High-2 Resolution Surface Barrier Detector
. 2-15 Figure 2-6 Beta Spectrum...
2-16 22 Figure 2-7 Na Decay Scheme.
2-17 Figure 2-8a
'"Cs Decay Scheme 2-18 Figure 2-8b
'"'"Ba Decay Scheme 2-19 Figure 2-9 Attainment of Secular Eauilibrium 2-20 Figure 2-10 Attainment of Transient Equilibrium.
2-21 Figure 2-11 No Equilibrium Possible.
2-22 Figure 3-1 Charged Particle Energy Loss Mechanisms 3-9 Figure 3-2 Ranges of Alpha Particles in Various Materials...
3-10 Figure 3-3 Relative Probability Curve 3-11 Figure 3-4 Primary and Secondary Buildup...
3-12 Figure 3-5 Skyshine 3-13 Figure 3-6 One Example of a Slow Neutron Interaction: Charged Particle Emission..
3-14 Figure 3-7 Elastic and Inelastic Collisions 3-15 Figure 5-1 Simplified Model of a Cell................
5-19 Figure 5-2 Mitosis - The Process of Cell Reproduction 5-20 Figure 5-3 Normal Human Chromosomes..
5-21 Figure 5-4 Damaged Human Chromosomes.
5-22 Figure 5-5 Dose Response Curves 5-23 Figure 6-1 Average Effective Dose Equivalent to U.S. Population From Radiation Sources 6-28 Figure 6-2 Deflection of Charged Particles by the Earth's Magnetic Field..
6-29 Figure 6-3 Primary Cosmic Photon Interacting with a Nitrogen Nucleus in the Earth's Atmosphere 6-30 Figure 6-4 Cosmic Radiation Dose Rate in the U.S. Versus Altitude.....
6-31 Figure 6-5 Principal Decay Scheme of the Uranium Series 6-32 Figure 6-6 Principal Decay Scheme of the Actinium Series 6-33 Figure 6-7 Principal Decay Scheme of the Thorium Series 6-34 Figure 6-8 Stages of the Uranium Fuel Cycle Without Reprocessing.
6-35 Figure 6-9 Uranium Resources in the Western United States 6-36 Figure 6-10 Generalized Underground Mine Showing Modified Room and Pillar Method of Mining..
6-37 Figure 6-11 Artist's Conception of Open-Pit Mining Operation and Support Facilities.. 6-38 Figure 6-12 Plot Plan of a Generic Mill 6-39 Figure 6-13 Flow Diagram for the / id Leach Process.
6-40 USNRC Technical Training Center vii Rev.0595 l
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Introductory Herith Physics TABLE OF CONTENTS Figure 6-14 Schematic for Wet Uranium Conversion Process..................
6-41 Figure 6-15 Schematic for Dry Uranium Conversion Process................... 6-42 Figure 6-16 Simplified Flow Diagram of Fuel Fabrication by the ADU Process 6-4 3 i
Figure 6-17 Pressurized Water Reactor Fuel Assembly......................
6-44 i
Figure 6-18 Boiling Water Reactor Fuel Assembly................
6-4 5 Figure 6-19 Boiling Water Reactor Steam Cycle
...........................6-46 Figure 6-20 Pressurized Water Reactor Plant.
6-47 Figure 6-21 Low-Level Radioactive Waste Compact Status (02/93)..............
6-4 8 Figure 6-22 Schematic Diagram of the Accelerating Tube of a Linear Accelerator....
6-49 Figure 6-23 Schematic Diagram of Cyclotron Operation 6-50 i
Figure 6-24 Contour Map of the Magnetic Field of the UCLA Sector-Focused Cyclotron 6-51 Figure 6-25 Schematic Diagram of the Cross-Section Through the Central Region o f a B e ta tro n...........................................
6-5 2 Figure 6-26 Schematic Diagram of the Magnet of an Alternating-Gradient Synchrotron. 6-53 i
Figure 7-1 Pulse Size as a Function of Voltage in a Gas-Filled, Two-Electrode Chamber 7-12 Figure 8-1 Thermoluniescent Dosimeter 8-19 Figure 8-2 Direct Reading Pocket Dosimeter....
. 8-20 Figurc 8-3 Marinelli Container for Counting Bioassay Samples................
8-21 Fig ne 8-4 Lung and Whole-Bviy Counter.......
8-22 Figure 8-5 Lung and Whole-Bodj Counter Geometry......................
8-23 Figuie 8-6 Germanium Scanning Whele-Body Counter......................
8-24 Figure 8-7 Multiple Uses of Scanning Whole-Body Counters..................
8-25 i
Figure 8-8 A Shadow-Shield Type Whole-Body Counter.....................
8-26 Figure 9-1 Simplified Conceptual Model of Pathways from Sources to Man.......
9-11 Figure 9-2 Pressurized Ionization Chamber.............................
9-12 Figure 9-3 Marinelli Container for Counting Bioassay Samples...........
9-13 USNRC Technical Training Center viii Rev. 0595
Introductog IIcIlth Physics TABLE OF CONTENTS INTRODUCTORY HEALTH PHYSICS CHAPTER 11 RADIATION PROTECTION STANDARDS AND REGULATIONS l
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This chapter provides the course participants with an overview of:
The history of protective standards for ionizing radiation.
The historical dose limits and their bases.
The regulating agencies in relation to NRC licensees.
The role of agreement states, EPA, and OSHA in relation to licensee regulation.
The fundamental components of 10 CFR Part 20.
LEARNING OBJECTIVES
-l Upon completion of this chapter, the student should be able to successfully:
Describe the historical origins of radiation protection standards:
Early observations of radiation injury Standards based on prevention of clinicalinjury to radiation workers Standards based on prevention of stochastic injury to populations Standards based on assumed risk-benefit and ALARA assessment.
a identify the regulatory agencies that regulate NRC licensees.
a Describe the roles of EPA and OSHA in regulating NRC licensees.
Describe and define the regulatory dose equivalent limits.
Describe the fundamental components of 10 CFR Part 20.
USNRC Technical Training Center ix Rev.0595
Introduct:ry He:lth Phy:Ic3 Chapt:r 11: Rzdiation Protection Strndrrds end Regulations 11.0 RADIATION PROTECTION still lagged because oflack of knowledge of STANDARDS AND REGULATIONS the many complex factors which enter into radiation effects.
11.1 IIistory of Protective Standards The following summarizes the keystone t
i With the discovery x-rays in 1895 by developments in radiation protection.
Roentgen, mankind started using radiation for beneficial purposes. However, there was soon Evolution of Radiation Protection to be discovered a Pandora's Box that was associated with this new wonder. In 1896, The history of radiation protection is traced injuries caused from exposure to Roentgen from the discovery of x-rays by Roentgen in rays (x-rays) were being reported. Scientists 1895 up to the present time. The began to study the reported injuries and other chronological summary of the development of effects on animals when exposed to x-rays.
radiation protection standards and of the By 1915, the users of x-ray machines in promulgating organizations up to 1971 is taken Britain (i.e., the British Roentgen Society) largely from Taylor's book, Radiation were urging the adoption of rules for the Protection Standards, published by the CRC operators of x-ray equipment.
Press,1971.
Early efforts at control were hampered by a Early Observations of Radiation Iniury lack of quantitative methods. There were no (Pre-WW I) units by which one could assess the amount of radiation. As a result of the use of radiation In 1896, the earliest x-ray injury on record by doctors in treating patients, a unit called the appears to have been observed in January of erythema dose came into use. This was a 1896 by Grubb6. In March 1896, Edison highly qualitative unit; defined in terms of the reported severe smarting of the eyes after amount of radiation which would produce a several exposures to a " discharge tube". Skin well-defmed reddening of the skin. It soon dermatitis was reported by several observers became apparent that this dose unit was not at before the end of 1896.
all satisfactory. It varied not only with the type of radiation and the dose rate, but also In 1901, hollins reported that x-rays could with the response of different parts of the cause injury at depth within the bodies of body. Thus, two people could receive the animals as well as to the skin.
same supposed fraction of an erythema dose, yet one might show skin effects and the other In 1902, Rollins proposed a radiation tolerance none. This lack of a certain value for this unit dose based on lack of fogging of a made protection work more or less of a trial-photographic plate after 7 minutes of exposure, and-error process.
In 1915, a resolution was introduced at a Around 1914, radiation began to be used in meeting of the British Roentgen Society urging industry. The radium dial-painting process the universal adoption of stringent rules for the came into being, and x-rays were found useful protection of operators conducting Roentgen for showing up flaws in materials. Larger ray examination. The resolution was l
numbers of people were then being expossd.
unanimously adopted, but due to the No longer could the vague notion of erythema interruption caused by World War I no l
does serve the purpose of a protection significant action was taken prior to 1920.
standard. Yet progress toward better standards r
USNRC Technical Training Center Rev.0595
intr: duct ry Hxlth Physica Chapter 11: Radiation Protection Standards and Regulations Standards Hased on Prevention of Clinical In 1928, the !nternational X-ray and Radium Iniury to Radiation Workers (WW I - WW Protection Committee [ forerunner of the 11)
International Commission on Radiological Protection (ICRP)] was established by the In 1920, the first standing radiation protection second International Congress of Radiology.
committee was formed by the American The committee held its initial meeting in 1928 Roentgen Ray Society.
and adopted interim regulations based upon :he 1921 recommendations of the British X-ray In 1921, the first general set of radiation and Radium Protection Committee. These protection recommendations were published in protection standards were directed primarily to the Journal of Roentgen Society.
the shielding of x-ray tubes operated at various voltages and for radium sources. The By the end of 1922, many countries had committee also adopted the defmition of the adopted standards for radiation protection.
roentgen (1 electron spin unit /cm' air at standard temperature and pressure).
The year 1925 was one of the landmark years in the evolution of radiation protection. The in 1929, the Advisory Committee on X-ray first International Congress of Radiology was and Radium Protection [ forerunner of the held in London and formed an Ad Hoc group National Committee on Radiation Protection to study the problem of radiation units; this and Measurements (NCRP)] was organized in was the forerunner of the International the United States. The work of this body was Commission on Radiological Units and coordinated by the National Bureau of Measurements (ICRU). Efforts to establish a Standards. The early recommendations of the
" tolerance dose" were being made Committee appeared in the National Bureau of independently in several countries.
Standarh Handbooks. The NCRP Mutscheller recommended a tolerance dose of recommendations as outlined in Handbooks 20 1/100 of a threshold erythema dose (TED, also and 23, which have been superseded by later called the skin erythema dose [ SED]) per reports, served as the basis for protection month or approximately 1/10 TED per year.
practices during the days of the project Sievert arrived independently at the same developing the atomic bomb during the value, i.e.,1/10 of the threshold erythema dose Manhattan project. Many members of the per year. Although there began to be some NCRP were engaged in this program and were general acceptance of Mutscheller's method of helpful in seeing that protection standards defining the tolerance dose, the actual value of prevailed.
the TED was not well established.
In 1931, the first x-ray protection rules In 1927, Kustner conducted an elaborate producej by the NCRP were published as survey to determine the value of the TED.
Burem.: of Standards Handbook 15. (It should Reported values ranged from 400 to 650 be noted that up until this time, protection roentgens, with an average value of 550 standards were expressed in terms of working roentgens. (It should be noted that during this hours, x-ray shielding, electrical precautions, time, the concept of the roentgen as a unit of radium shielding, etc. and not in terms of air exposure was being developed, but that it exposure or dose limits).
was not quantitatively defined nor adopted by any official committee until 1928).
In 1934 and 1935, ICRP adopted a permissible dose limit of 0.2 R/ day (72 R/ year). NCRP adopted an exposure limit of 0.1 R/ day (36 USNRC Technical Training Center Rev.0595
introduct:ry Halth Phy;lc3 Chapter 11: Rrdiation Protection Standards and Regulations IUyear). Both of these limits were based on Because of the rapid expansion of the use of the earlier recommendations related to the radiation by industrial organizations, the TED (i.e.,0.1 TED per year, or approximately American Standards Association organized 55120 IUyear). The NCRP was more Committee Z-54 to develop radiation cautious in establishing a dose limit because of protection standards for use in industry. Also, growing suspicions that radiation might induce the rapid increase in shipments of radioactive more subtle and delayed injuries. The materials prompted the Interstate Commerce possibility of genetic effect was also under Commission (ICC) to develop special tariffs consideration during this time period.
pertaining to radioactive materials. This tariff was actually developed by the Bureau of In 1941, the Advisory Committee on X-ray Explosives of the Association of American and Radium Protection recommended a Railroads, but was adopted and enforced by permissible body burden for radium of 0.1 the ICC. The development of operational Ci. This standard was based on an intensive standards by associations of commercial or study of radium patients and dial painters.
industrial organizations based on the recommendations of scientific committees is a The Manhattan District (WW II) pattern that has been continued in the field of radiation protection.
In the 1940's, the intensive wartime effort to deve!op fission reactors and nuclear weapons The three organizations, ICRU, ICRP, and introduced radiation protection problems on a NCRP, have figured prominently in the scale never before anticipated. For example, development of present day radiation the entire world supply of radioactive materials protection practices. Although these bodies act prior to 1940 consisted of approximately I kg as advisory boards only, much of the radiation (1000 Ci) Ra-226; in contrast, millions of protection philosophy which has evolved and curies of a wide variety of radionuclides were which has been adopted by various regulatory produced in the first reactors of the Manhattan agencies throughout the world, had its origins District and in the early detonations of nuclear in the recommendations of these organizations.
weapons. Also, prior to 1940, the most intense sources of external radiation were x-ray 11.2 Dose Limits machines, cyclotrons, or other high-voltage accelerators; the external radiation intensities The changes in acceptable dose limits followed from a nuclear reactor core are orders of and continues to follow the growth of magnitude larger.
scientific data and recommendations by the ICRU, ICRP, and NCRP. The following Large scale animal experiments on the summarizes the changes in dose limits that biological effects of radiation, both internal took place between 1948 and 1977.
and external, were initiated at the National Cancer Institute, the University of Chicago, the 11.2.1 Standards Based on Prevention of University of Rochester, and at Oak Ridge.
Stochastic Iniury to Populations (the The radiobiology programs started during AEC and FRC vears)
World War 11 have since been greatly expanded and collectively represent the largest In 1948 and 1949, the NCRP lowered the single source of radiation effects data in the maximum permissible dose for radiation world.
workers to 0.3 R/ week (15 R/ year); this standard was still based primarily on the absence of detectable injury to individuals.
USNRC Technical Training Center Rev.0595
Introduct:ry H alth Phy:Ic2 Chapter 11: R diation Protection Strndards and Regulations The NCRP also introduced the risk-benefit data that are used in support of radiation I
philosophy and considered population and standards.
genetic effects of radiation (NBS Handbook 59).
In 1957, the NCRP formulated the age prorated occupational dose limit and also In 1950, the ICRU and ICRP were reorganized adopted the population dose concept of ICRP and adopted the same standards as the NCRP (0.5 rem /yr to any individual or 0.17 rem /yr to for external radiation. The ICRU expanded a population at large).
the definition of the curie to include all radioactive materials, not just radium.
In 1959, the ICRP recommended a genetically significant dose limit of 5 rems in 30 years for in 1952, the ICRP and ICRU held the first the general population. The Federal Radiation Conference on Genetic Effects and reached Council (FRC) was formed in 1959 (Public conclusions essentially as subsequently Law 86-373) to " advise the president with recommended in 1956.
respect to radiation matters directly or indirectly affecting health including guidance In 1953, the NCRP listed maximum for all federal agencies in the formulation of permissible concentrations and maximum radiation standards and in the establishment permissible body burdens for 100 isotopes.
and execution of programs of cooperation with (NBS Handbook 52) The ICRP adopted these states..."
- NCRP recommendations and also recommended for members of the general In 1960, the FRC issued its first report public a dose limit 1/10 of that for radiation
" Background Material for the Development of workers. The ICRU introduced the concept of Radiation Protection Standards" The report absorbed dose and adopted the rad as its unit.
introduced the terms radiation protection guide (RPG) and radioactivity concentration guide In 1956, the ICRP introduced the concept of (RCG) to replace the terms maximum cumulative dose for both occupational and permissible dose and maximum permissible population exposures and recommended a dose concentration as used by the NCRP and ICRP.
limit of 5 rem /yr for radiation workers. The These recommendations were made in the ICRU introduced the concepts of relative recognition of the linear non-threshold biological effectiveness (RBE) and the RBE assumptions of the dose-effect relationship.
dose and adopted the rem as the unit of dose equivalent. The National Academy of In 1964, the FRC introduced the concept of Sciences published the first of a series of protective action guides (FRC Report No. 5).
reports on the biological effects of atomic radiation (BEAR Committee, forerunner of the In 1967, the increasing concern over the Biological Effects of Ionizing Radiation excessive lung cancer deaths among uranium
[BEIR] Committee). The United Nations miners lead to Congressional Hearings (JCAE Scientific Committee on the Effects of Atomic 1967) and to the last report issued by the FRC Radiation (UNSCEAR) held its first two (FRC 1967).
meetings and submitted a yearly progress report to the General Assembly of the United In 1968, the Radiation Control for Health and Nations at its 11* Session. The Committee Safety Act (PL 90-603) was passed. This act has subsequently become a most valuable gave the federal government, for the first time, source of radiation exposure and protection the authority to regulate electronic product radiations. This category includes ionizing and USNRC Technical Training Center Rev.0595
s Intr duct 2ry Hulth Physics Chapter 11: Radiation Protaction Standards and Regulations j
non-ionizing electromagnetic or particulate The National Hnvironmental Policy Act (PL radiation, and sonic, infrasonic or ultrasonic 91-190) was rassed in 1969 also.
waves emitted from electronic products. Prior to this act, regulation of such devices was a In 1970, the U.S. Environmental Protection 4
state responsibility. The act directed the Agency (EPA) was fonned by Reorganization Secretary of the Department of Health, Plan No. 3 of 1970. The FRC was abolished Education and Welfare (DHEW) to establish and its responsibilities for providing guidance performance standards for electronic products to all federal agencies on matters of radiation and to regulate the manufacturing and protection were given to the EPA.
distribution of such products, but only to
" study" the control of uses and users.
In 1972, the BEIR Committee released its report, The Effects on Populations of The research supported by the AEC, and the Exposures to Low Levels of lonizing coordination provided by the FRC, motivated Radiation. The UNSCEAR report, Ionizing i
much of the development effort on standards Radiation: Levels and Effects, was published.
l during the 1950's and 1960's, even though Both committees used the same database and AEC regulations remained relatively static arrived at comparable estimates of somatic and during that time.
genetic effects from radiation exposures of l
large populations. UNSCEAR did not 11.2.2 Standards Based on Assumed Risk-extrapolate to individual risk from low doses, i
Benefit and ALARA Assessments as did BEIR.
l (Adversary Era) in 1974, the Energy Reorganization Act (PL Three events occurred in rapid succession,93-438) split the AEC and also abolished the producing a significant change in public Joint Committee on Atomic Energy. The attitudes toward radiation standards and in the regulatory functions of the AEC were given to standards-setting process, if not in the the U.S. Nuclear Regulatory Commission numerical values of the standards themselves.
(NRC) and the development and promotional These events were all instigated by a public functions of the AEC were given to the mood of the late 1960's; this mood could best Energy Research and Development be described as anti-establishment and Administration (ERDA),
distrustful political leaders.
Several noteworthy events took place in 1975 In 1969, Drs. John W. Gofman and Arthur R.
and 1977:
Tamplin presented a paper before the Institute for Electrical and Electronic Engineers (. San 1975 The NRC issued Appendix I to 10 CFR Francisco, October 29), challenging the 50, Numerical Guides for Design
- Atomic Energy Commission (AEC) and FRC Objectives and Limiting Conditions for standards and demanding an immediate Operation to Meet the Criterion "As reduction of the dose limit for members of the Low as Practicable" for Radioactive general public by at least one ouier of Material in Light-Water-Cooled Nuclear magnitude. In response to Gofman and Power Reactor Effluents (40 FR 19439, Tamplin, the FRC requested a review of May 5,1975).
radiation standards by the National Academy of Sciences. The BEIR Committee held its first meeting on March 25,1970.
USNRC Technical Training Center Rev.0595
Introduct:ry Hxith Phy:lca Chapter 11: Radiation Protection Strndards and Regulations The EPA published its proposed standards no single tissue should receive more than the (40 CFR Part 190), Environmental dose limit to prevent nonstochastic damage.
Radiation Protection for Nuclear Power Operations (40 FR 23420, May 29,1975).
The ICRP recommendations are intended to limit somatic effects in the individual, The NCRP reaffirmed its existing standards, hereditary effects in the individual's immediate i.e., individual dose limits, but strongly offspring, and somatic and hereditary effects in reiterated its emphasis on the ALARA the population as a whole. For any organ, the principle. A summary of NCRP standards dose limitation refers to the sum of the annual and NRC and EPA dose limits for members dose equivalents from external sources and the of the general public are shown in Table committed dose equivalents from internal 11-1.
sources during that year.
1977 UNSCEAR released a comprehensive The NRC's occupational dose limits have been report on Sources and Effects of adjusted to agree with ICRP 26. Currently, Ionizing Radiation (UN Publ. No. E. 77.
the NRC believes that nonstochastic effects IX.1). This report is an expansion and will be prevented by applying a dose update of the 1972 report.
equivalent limit of 0.5 Sv (50 rem) in a year to all tissues except the lera of the eye, for The BEIR Committee issued a report on which the recommendation is 0.15 Sv (15 rem)
Considerations of Health Benefit-Cost in a year. In addition, the limits apply Analysis for Activities Involving Ionizing whether the tissues are exposed singly or in Radiation Exposure and Alternatives (EPA combination with other organs.
520/4-77-003). This report, also called the BEIR-II report, represents an attempt to For stochastic effects, the annual dose develop benefit-cost analysis methods and equivalent limit for uniform irradiation of the apply them to specific applications, i.e.,
whole body is 50 mSv (5 rem). If the energy production and medical diagnosis.
irradiation is non-uniform, the system is based upon the premise that the risk should not The ICRP published a newly revised exceed that for uniform whole body version of its recommendations (ICRP Publ.
irradiation. This obtains if:
26). Although the terminology and wording are substantially different from Hwy 2,>E w Hr (11-1) r1 previous ICRP publications, the underlying i
concepts and philosophy of radiation where protection are consistent with all earlier ICRP recommendations.
t fw31 is the annual whole body limit (50 mSv)
The ICRP believes that, for stochastic effects, Hr is the annual dose equivalent in a given the dose equivalent limit may be based on the tissue T, and total risk of all irradiated tissues. So, the system sets a single limit for uniform w is a weighing factor.
r irradiation of the whole body and a weighing system to ensure that the total risk from partial This weighing factor expresses the ratio of the body irradiation does not exceed the risk from stochastic risk in tissue T to that in the Mtal uniform whole body irradiation. In addition, body. Values of w are given in Table 11-2.
r The sununation on the right side of equation USNRC Technical Training Conter Rev.0595
i introductory Hxith Phy:ica Chapter 11: Radiation Protection Standards and Regulations 11-1 is called the effective dose equivalent, for these rules are: to protect the public health He.
and safety, and provide for national defense and security. Under this mandate, the AEC The weighing factor w, is 0.06 for each of the was concerned with the development of r
five organs of the remainder receiving the regulatory safety standards.
highest dose equivalents, and the remaining tissues can be neglected.
The Energy Reorganization Act of 1974 abolished the AEC and established two The NRC does not intend that the hands and agencies to perform the functions of the AEC.
forearms, the feet and ankles, the skin and the The U.S. Nuclear Regulatory Commission lens of the eye be included in the (NRC) has taken over the licensing and determination of the remainder in Table 11-2.
regulatory functions. Licensed material under l
the control of the NRC includes source The NRC dose limit in 10 CFR Part 20 for material (uranium and thorium or ores members of the public is 0.1 rem (100 mrem) containing.05% of these materials), special per year total effective dose equivalent. This nuclear material (plutonium, U-233, U is a stochastic limit. There are no non-enriched in U-233 or U-235), and by-product stochastic limits for members of the public material (radioactive material resulting from since it is assumed that non-stochastic effects producing or utilizing special nuclear material).
will not occur at dose levels at or below the The regulations of the NRC are set forth in the stochastic limit for the public.
Code of Federal Regulations, Title 10. Part 20, Standards for Protection Against Radiation, Although the ICRP functions only as an deals specifically with the regulations for advisory body, their recommendations have control of radiation hazards by the licensee.
generally been adopted and applied as the Other parts of Title 10 deal with licensing and basis for the radiation protection standards in regulatory requirements associated with the use use throughout the world. The NCRP has also of source, special nuclear material and by-endorsed these recommendations.
product material.
11.3 Reculatine Acencies As part of its duties, the NRC is charged with the task of seeing that these measums prevail.
So far, our attention has been directed to those This aspect requires inspection and review in groups which supply recommendations for order to assure this. This functbn is carried exposure levels and safe practices and to the out by NRC personnel (inspectcrs) at regular dose limits. The rest of this section will be intervals. Their job is to make the inspections concerned with the organizations which are and report their fmdings. In the event that a charged with developing regulations. Of prime failure te comply is noted, the licensee is interest are those groups which regulate required to correct this.
radiation matters in this country.
Mmy of the states have taken up the task of Under the Atomic Energy Act of 1954, the setting up their own safety standards. The United States Atomic Energy Commission NRC has been directed to assist the states to (AEC) was given the responsibility of assure that the state and Commission programs regulating the atomic-energy industry. The are compatible. These states are referred to as Act authorized the AEC to set up a licensing Agreement States.
program to be augmented by whatever rules or regulations are deemed appropriate The bases USNRC Technical Training Center Rev.0595
introduct:ry Hnith Physic 3 Chapter 11: Radiation Protection St:ndirds end Regulations An Agreement State is any state using private agencies and to the general public.
legislation known as the Radiation Control Act IIearings are held, if necessary, to discuss to provide regulation of radioactive materials amending the proposals. Subsequently, the and radiation producing machines and whose amended proposals are published in the purpose is to protect the health and safety of Federal Register. If no adverse action is taken, the public. The governor of an Agreement the changes or additions become part of the State signs an agreement with the NRC or its Code of Federal Regulations and have the predecessor, the Atomic Energy Commission.
effect of law. Other agencies of the Federal As part of this agreement, the State maintains Government having an interest in the a radioactive materials regulatory program that regulations for the shipment of radioactive is sufIicient to protect the health and safety of substances are: Interstate Commerce the public and that meets or exceeds that of Commission, Coast Guard, Federal Aviation the NRC.
Agency, Postal Service, DOE and the NRC.
The Department of Transportation has made an The U.S. Department of Energy (DOE) has effort to make its labeling system conform taken over the remaining functions of the with the regulations of the International AEC. These activities related to energy Atomic Energy Agency.
research and development and involved activities carried out by the Commission or by This concludes the brief outline of the main its contractors. The DOE has issued groups whose function is to regulate. From regulations which pertain to its own activities the dynamic nature of the field of atomic as well as to those of its contractors, not energy, one can expect that many new subject to licensing. These regulations appear problems will arise. for this reason, no in the DOE Orders, which replaced the Manual attempt has been made to discuss any of the Chapters of the AEC. The standards which present regulations in detail. As new problems apply specifically to radiation protection are arise, new rules must be worked out. Thus, as contained in DOE Order 5480.11. These in the case of exposure limits, changes will standards are based upon the recommendations occur. To keep up on current changes, it is of the ICRP, NCRP, and the guidance of the necessary to periodically review the Federal EPA. Similar to the NRC, the DOE is Register.
charged with the inspection ofits contractors to see that they are in compliance with the 11.4 Aercement State DOE Orders.
An Agreement State is any state using Safety in the shipment of radioactive legislation known as the Radiation Control Act substances is principally the responsibility of to provide regulation of radioactive materials the U.S. Department of Transportation (DOT).
and radiation producing machines and whose Title 49-Transportation, of the Code of Federal purpose is to protect the health and safety of Regulations, deals with hazardous shipments the public. The governor of an Agreement including radioactive materials. See Section State has signed an agreement with the NRC 16.K for a discussion of these regulations.
or its predecessor, the Atomic Energy Commission. As part of this agreement, the From time-to-time, changes are made in State maintains a radioactive materials various regulations. The Code of Federal regulatory program that is sufficient to protect Regulations is revised through submission of the health and safety of the public and that changes proposed by an agency and the meets or exceeds that of the NRC.
Federal Government to other governmental and USNRC Technical Training Center Rev.0595
.=
.~._.-
Introductory HIalth Physics Chapter 11: Radiation Protection Standards and Regulations 11.5 40 CFR Overview regulations it is not required that the NRC Inspectors become proficient with the Section 40 of the Code of Federal Regulations regulations, but only that they report situations primarily sets limits on the activities and that appear to be unsafe, or known violations i
effects of radioactive materials dispelled based on the Inspector's knowledge.
beyond the boundaries of the facility. A brief outline of some specific parts are listed below:
11.7 Summary of 10 CFR 20 l
40CFR 61 air pollutant limits The new 10 CFR Part 20, Standards for including radon and Protection Against Radiation, represents the other radionuclides most significant change in radiation protection 40CFR 141 public drinking water regulations in over 35 years. The new rule limits including Ra-226 became effective on June 20,1991 and j
and Ra-228 compliance was mandatory for all NRC 40CFR 190 nuclear power plant licensees on January 1,1994. The new Part operation and uranium 20 is a risk-based system of radiation i
fuel cycle operation protection which implements the limits recommendations of the ICRP (1977) and the 40CFR 191 release limits for NCRP (1977) and Presidential Guidance to disposal of spent nuclear Federal Agencies issued in 1987. The new q
fuel, high-level, and regulation updates dose / risk models and j
transuranic wastes parameters, particularly with regard to 40CFR 192 standards for remedial internally deposited radioactivity. The format j
actions at inactive of the new regulations has also been changed j
uranium processing sites to consolidate certain portions and improve its 40CFR 220-229 ocean / marine dumping
. organization.
limits 40CFR 440 effluent limits from ore Major changes to Part 20 include: new dose 3
mining.
limits for workers and members of the public; introduction of the concept of effective dose 11.6 Role of OSIIA - 29 CFR equivalent; summation of external and internal dose; use of Annual Limit on Intake (ALI) and The Occupational Safety and Health Derived Air Concentration (DAC); dose Administration is charged with improvement limitation to the embryo / fetus of a declared i
of safety to workers in the United States.
pregnant woman; planned special exposure Their rules are codified in 29 CFR 1910 (PSE); the new respirator rule requiring total
" Occupational Safety and Health Standards" effective dose equivalent to be maintained and 1926 " Construction" for operational ALARA; changes in dose recordkeeping and facilities and construction respectively. These reporting (NRC Forms 4 and 5); and new i
rules cover most aspects of worker safety and effluent concentration limits for releases of 4
are applicable to any company that has more radioactivity to air and water.
I than ten employees. The Commission has a memorandum of understanding with the OSHA A series of regulatory guides have been issued
{
which allows NRC Inspectors to report / review to provide additional guidance on the new Part safety compliance status by a licensee, thus
- 20. Also, an extensive series (seven sets to becoming additional OSHA " eyes." However, date) of questions and answers (Q & A's) have due to the complexity of the OSHA been issued to reflect NRC staff decisions and USNRC Technical Training Center Rev.0595
Introduct:ry Hxith Physics Chapter 11: Radiation Protection Standards and Regulations technical opinions on specific aspects of new Subpart H provides the requirements for Part 20 regulatory requirements.
respiratory protection and controls to restrict internal exposure in restricted areas.
A summary of the subparts of 10 CFR 20 is presented below:
Subpart I provides the requirements for the storage and control oflicensed material.
Subpart A discusses the general provisions of the regulations including purpose, scope, Subpart J provides the requirements for definitions, and units of dose and radioactivity.
precautionary procedures including posting of Further it defines the proper mechanism for areas and materials, and the receiving and interpretations of these regulations, and lists opening of packages.
the proper directions for communication and provides implementation guidance.
Subpart K provides the requirements for radioactive waste disposal.
Subpart B states the requirements for licensees to develop, document, and implement a Subpart L provides the requirements for 1
radiation protection program, records generated in support the radiation protection program. These records consist of Subpart C provides the requirements for such things as survey and monitoring reports, occupational dose limits. This subpart dose reports, planned special exposure i
includes requirements for summing internal documents, member of the public dose, and and external dose, determining dose due to waste disposal.
internal exposure, the use of planned special exposure, and dose limits for ~ minors and an Subpart M provides the requirements for embryo / fetus.
reports to the Comrnission and include such things as theft or loss oflicensed material, Subpart D provides the requirements for c'ose incidents, events where radiation levels, limits for members of the public and incluhs exposures, or concentrations of radioactive compliance with 40 CFR 190.
materials exceed limits, planned special exposures, and individual dose monitoring.
Subpart E is reserved.
Subpart N provides exemptions to these Subpart F provides the requirements for the regulations as well as other additional making of surveys and monitoring of requirements.
personnel for external and internal occupational dose.
Subpart O provides the requirements for enforcement of these regulations.
Subpart G provides the requirements for the control of exposure from external sources in Appendix A provides the allowed protection restricted areas and includes access to high and factors for respirators.
very high iadiation areas for both normal licensees and irradiators.
Appendix B provides radionuclide specific values for the annual limits on intake and derived air concentrations for occupational exposure, effluent concentrations, and sewerage releases.
USNRC Technical Training Center Rev.0595
. - _.. _ _. _... - _. _ - - - ~ _
Intrrduct:ry H:alth Phy2ics Chapter 11: Radiation Protection Standards and Regulations Appendix C provides radionuclide specific l
values for quantities oflicensed material that requires labeling.
Appendix D lists the addresses and phone numbers for each of the four NRC Regions
}
and the California Field Office.
Appendix E is reserved.
J l
Appendix F lists the requirements for low-level-waste transfer for disposal at land disposal facilities and manifests.
4 i
?
'l i
i USNRC Technical Training Center Rev.0595 w
,v.
y--.,
Introductsry Hrlth Phy les Chapter 11: Radirtion Protection Standards and Regulations Chapter 11 Study Questions
- 1. What are four of the subparts of 10 CFR Part 20?
- 2. What gives agreement states jurisdiction / power to regulate NRC licensees?
- 3. What gives the EPA jurisdiction / power to regulate NRC licensees?
- 4. What gives the DOT jurisdiction / power to regulate NRC licensees?
- 5. What gives the OSHA jurisdiction / power to regulate NRC licensees?
- 6. What are the radiation dose equivalent limits specified by the NRC for licensee workers and members of the public? Where can these limits be found?
- 7. Prior to the adoption of dose limits, how did the early radiation workers limit their exposure to ionizing radiation?
- 8. What agencies have guided the evolution of dose limits the most?
USNRC Technical Training Center Rev.0595
Introductery Hrlth Phy:lca Chapter 11: Radiation Protection Stand:rds and Regulations Table 11-1. Non-Occupational Radiation Standards (NCRP) and Dose Limits (NRC, EPA)
NCRP (Reports 39,1971 and 40,1975)
To individual members of the public:
50 mrem /vr i
Average to populat on groups:
170 mrendyr i
NRC (10 CFR 50, Appendix I), LWR Design Criteria From liquid effluents:
.All pathways - Total body:
3 mrem /yr
- Individual organs:
10 mrem /yr From airborne effluents.
Air dose - gamma radiation:
10 mrad / r
- beta radiation:
20 mra r
External dose to individual:
Total body:
5 mrem /yr 1
Skin:
15 mrem /hr Internal dose to any organ:
15 mrem /yr NRC (10 CFR 20) Radiation Protection Regulations From all pathways, total effective dose equivalent to 100 mrem /yr member of the public:
EPA (40 CFR 61) Clean Air Regulations (except nuclear power plants From all air pathways, effective dose equivalent to member 10 mrem /yr of the public:
From airborne radiciodine:
<3 mrem /yr EPA (40 CFR 190), Nuclear Fuel Cycle From all sources except radon and short-lived progeny:
To any individual - Total body:
25 mrem /yr
- Thyroid:
75 mrem /
- Other organs 25 mrem /yr yr Release limits for total fuel cycle (effective 1983):
Per gigawatt-year of power production:
- krypton-85:
50 kCi
- iodme-129:
5 mci
- transuranics:
0.5 mci USNRC Technical Training Center Rev.0595
Introduct:ry Hrlth "hyIIca Chapter 11: Radi: tion Protection Standards and Regulations Table 11-1. Non-Occupational Radiation Standards (NCRP) and Dose Limits (NRC, EPA)
(Continued)
EPA (40 CFR 141), Safe Drinking Water Act Regulations From man-made radionuclides in drinking water 4 mrem /yr USNRC Technical Training Center Rev.0595
introduct:ry H sith Phy:Ica Chapter 11: Radiation Protection Standards and Regulations Table 11-2. Weighing Factors for Stochastic Risk Tissue wt Gonads 0.25 Breast 0.15 Red bone marrow 0.12 Lung 0.12 Thyroid 0.03 Bone surfaces 0.03 Remainder 0.30 USNRC Technical Training Center Rev.0595
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RO-12-1997 15:00 TTD CHATT4 00GA 423 855 6546 P.03 unruuuctory ricann t'nyacs Chrpter 12: R:diathn Pr:tection Pirns and Prrcedures 12.0 RADIATION PROTECTION PLANS the RPP. One topic that is general to all areas
- f')
AND PROCEDURES of an RPP is documentation and records j
V retention. Every area to be discussed requires 12.1 Introduction that sufficient documentation be retained to show that the program is being operated i
A Radiation Protection Plan (RPP) is one part correctly and that worker doses are ALARA l
of every NRC license for radioactive materials and within regulatory limits. Some records or special nuclear materials. This requirement are to be maintained until the license is serves the purpose of directing activities of the termmated while others need to be retained for licensee such that exposures to the licensee's 75 years. Therefore it is important that a l
employees and the public are kept as low as licensee have a good document control system i
reasonably achievable. A RPP is a to support the RPP.
multifaceted program which entails all aspects of radiation protection, ranging from 12.2 Administration administration, to facility assessment, to training, to dose evaluation and control. Each Within the arena of administration lies the of the many components of the RPP supports requirement for an ALARA commitment from the philosophy of ALARA.
the upper level facility managemeut down to the mid-level managers. Without this There is no specified outline for an RPP commitment there cannot be an active and because facilities have various designs, progressive radiation protection program. The functions, and needs. However, the dominant admuustration must support the health physics concepts include:
programs with the resources (personnel, 7(O equipment, space, etc.) needed to fulfill the l
e Admuustration task of radiation protection of the work force
- Occupational ALARA programs and the public. Failure to support health
- Radiation protection program surveys physics will ultimately lead to facility and monitoring conditions that are not conducive to the
- Posting and labeling for radiological principals of ALARA.
control
- Workplace air monitoring More close to home is the need to have a well e Instrument calibration for fixed and trained Health Physics administmtor to ensure portable instn1ments all aspects'of a good health physics prognm
- Internal dosimetry program are instituted at a level commensurate with the
- External dosimetry program potential for exposure to radiation and
- Evaluation and control of fetal exposure radioactive materials in the workplace and the
- Radiation safety training environment. Levels of administration that
- Sealed radioactive source accountability report to the Health Physics administrator will and control be dependant on the complexity of the
- Occupational radiation protection program. For instance a nuclear power record-keeping and reporting generating station will have a far more
- Quality assurance, and complex (both in terms of personnel and
- Emergency response.
resources) program than might be found at a i
facility that has a sealed source only license.
Emphasis may differ among facilities and
(,)
some facilities may include additional concepts, but this list comprises the core of USNRC Technical Training Center 12-1 Rev.0595
JUH-12-1997 15:o2 TTD CHATTAt400GA 423 855 6546 P.04 intr:ductrry H:alth Physics ChIpt:r 12: Radhtiin Pr:tecthn Plans cnd Pr:cedures 12.3 Occuoational ALARA Programs e implementing a strong contamination control program h
Occupational ALARA programs vary widely a posting and identification of radiation dependant on the potential for exposure to areas and radioactive materials radiation and radioactive materials. The basic
- use of administrative dose limits for tenant to which these programs operate is that personnel.
there should be a net benefit to justify the exposure to radiation or radioactive materials.
The last part of the ALARA program is the The size of the facility and the types of tasks use of protective clothing to mmimize worker performed at the facility will affect the size of exposure to direct radiation (e.g., alpha the ALARA program. In the most basic of radiation), contammation and airborne programs should be a review of the current radioactive materials. Clothing can range program to identify opportunities for reducing from simple lab coats and gloves to full total man-rem expended in performing the anticontamination attire, including respiratory facilities task.
protection. What type of clothing is used and how much is required is dependant on the ALARA programs should first target potential for exposure to radioactive materials.
engineered controls, then administrative controls, and lastly personal protective 12.4 Operational Radiation Protection equipment. Engineered controls consist of Procedures modification of new and existing facility design that reduces the exposure of personnel 12.4.1 Radiation Protection Procram to radiation and radioactive materials.
Surveys and Monitorine Examples of engineered systems are:
h Every radiation protection program, from very
- use of heavy shield walls and labyrinths simple to complex, requires that surveys and
- use of remote handling, use of robotics monitoring be performed in a facility to e use of local ventilation exhaust establish the exposure to radiation and
- use of local shielding and facility layout radioactive materials on surfaces and in the to ensure radiation sources are remote air. A good program will utilize survey from office areas and other locations frequencies that are commensurate with the where personnel tend to congregate.
potential for radiation fields to change and for radioactive materials to be found in the Admimstrative controls are " soft fixes" that workplace. For example in areas where little result in programs for the reduction of worker to no radioactive matenals are allowed and exposure. Examples of administrative radiation fields are near background there is controls are:
little need to spend valuable personnel and instrument resources in monitoring activities.
4
- locking access to high radiation areas In this situation monthly surveys may be
- implementing ALARA review boards sufficient. However, in facility areas where for all scheduled maintenance contamination probability is high and known
- pre-job mockup maintenance trainmg loose contamination levels are routinely
- setting of ALARA man-rem goals elevated, there is good reason to implement
- purchasing control systems that ensure monitoring programs that require frequent air materials brought into the facility are samples, and loose contamination surveys. In g compatible with the system components facilities where radiation fields change daily it W is important to perform radiation surveys USNRC Technical Training Center 12-2 Rev.0595
m.12-te/97 15:03 TTD Cm TTAHOOGA 423 855 6546 P.05 intrecuctrry Herith Physics Chapter 12: Ridittian Prr.tection Plans rnd Pracadures daily. Types of surveys and monitoring CAUTION, HIGH RADIATION AREA techniques must be tailored for the radionuclides of concern at the facility.
High radiation area is an area, accessible to individuals, in which radiation levels could Although the primary focus of most survey result in an individual receiving a dose and monitoring programs deals with the equivalent in excess of 0.1 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at facilities it is imponant to not overlook the 30 cm from the radiation source or from any need to survey personnel and equipment as surface that the radiation penetrates.
they come out of radiologically controlled areas, especially from areas containing loose GRAVE DANGER, VERY HIGH or fixed radioactive contammation. All RADIATION AREA personnel leaving these type of areas should perform a frisk to detect the presence of A very high radiation area is an area, contamination on their person or personal accessible to individuals receiving an absorbed articles they may be carrying out of the area.
dose in excess of 500 rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 The extent of the frisk, whole or partial body, meter from the radiation source or from any should be driven by the potential for exposure.
surface that the radiation penetrates.
l This is true also for equipment leaving the area. However, all equipment should be CAUTION, AIRBORNE l
monitored by a health physics technician or a RADIOACTIVITY AREA fixed monitoring device to ensure ccatamination control is affected.
An airborne radioactivity area is a room, enclosure, or area in which airborne 12.4.2 Postine and Labeline for radioactive materials, composed wholly or Radiological Control partly oflicensed material, exist in concentrations: (1)in excess of the derived A facility possessing radioactive materials is air concentrations (DACs) specified in required to identify the locations of such Appendix B of 10 CFR 20, or (2) to such a materials and the resultant dose rate or effect degree that an individual present in the area on contamination levels due to the radioactive without respiratory protective equipment could i
i materials. All postings must bear the exceed, during the hours an individualis internationally accepted symbol of present in a week, an intake of 0.6 percent of radioactivity, the trefoil in the appropriate the annual limit on intake (ALI) or 12 DAC-colors of magenta, purple, or black on yellow hours.
background. Types of signs and their associated definitions, as defined in 10 CFR CAUTION, RADIOACTIVE MATERIAL 20, are listed below:
A radioactive materials area is an area where CAUTION, RADIATION AREA amounts of stored material are p 10 times Appendix C values in 10 CFR 20.
j A radiation area is an area, accessible to l
individuals, in which radiation levels could CAUTION, RADIOACTIVE MATERIALS l
result in an individual receiving a dose h
equivalent in excess of 0.005 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at A radioactive materials area is an area where
!CJ surface that the rullation penetrates.
Licensing control by the NRC is located.
i USNRC Technical Training Center-
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jut F12-1997 15:o4 TTD CHATTANOOGA 123 855 6546 P.o6 IntrIduct:ry H:cith Physics Chrpt:r 12: R dictl:n Prat:cti n Plans and PrIc: durn 4
Although these postings cover most situations Radiciodine can either be a particulate or take for exposure control from direct radiation many chemical forms such as organic, I, or h
2 i
there is still the possibility of encountering HOI. Therefore sampling should be loose contammation in a facility. Although conducted by pulling air through a particulate not defined in 10 CFR Part 20, other filter followed by a charcoal cartridge. This appropriate postings may be as foUows:
combination of filters helps to assure that a representative sample will be collected.
CAUTION, CONTAMINATION AREA In the category of "other" lies all of the odd A contamination area is an area where ball radionuclides such as tritium and C-14 contamination > l time but _100 times Reg.
Also included in this category may be Guide 1.86 Table 1 values.
specialty radionuclides in specific chemical forms that have specific uses by a licensee.
DANGER, HIGH CONTAMINATION Types of sample collection devices must be AREA tailored to the nuclide and chemical form.
For example tritium can be found as hydrogen A high contamination area is an area where gas, water vapor, or organic vapors. Each contamination > 100 times Reg. Guide 1.86 form will require a different technique to Table 1 values.
adequately collect a representative air sample.
12.4.3 Work Place Air Monitorine 12.4.4 Instmment Calibration Monitoring of internal dose to workers is Instruments used for the detection of i
required by 10 CFR Part 20 where the contamination and radiation vary widely h
potential exists for a worker to exceed 10% of within the nuclear industry. However, there an ALI during the course of a year. To meet is one thing that doesn't vary and that is the this requirement, most licensees perform air need to properly maintain and calibrate the monitoring either continuously or on an instruments to assure proper operation.
intermittent schedule. Due to the large variety Normauy instruments are calibrated every six of contaminants that are handled by licensees months to one year depending on the license in the United States there is no one way to requirements. At these times the instrument obtain air samples. Typically air sampling should also be checked for damage and can be subdivided into four categories:
repaired if needed. Every instrument should particulate, noble gas, radiciodines, and other.
be returned into the workplace with a sticker attached that gives the date of calibration or Particulate radioactivity is normally associated next due date, and any specific information with small dust particles that are made up of, required by the licensee such as efficiency or have attached to them, radioactive material, factors, initials of calibrator, serial number of These materials are solid and can be collected meter and probe if two separate units.
as air is passed through a filter material.
Prior to each use the tag should be reviewed Noble gases are kryptons and xenons, fission to ensure the instrument is still within products that are inert and therefore do not calibration. The instrument should be attach to filters or quantitatively collect on inspected and the response checked with a absorbers. The normal method for sampling source. Any instrument that is not in is the use of grab samples, where container calibration or does not pass inspection should,
volumes are liters or larger.
USNRC Technical Training Center 12-4 Rev.o595
JUH-t2-1997 IS*06 TTD CHAT tat COG ^4 423 855 6546 P.07 Intr: duct ry H:dth Physics Chipter 12: R:di;tiin Prrt:ction Plans and Prrc7.duris be tagged out-of-service and sent for disposal should be addressed in the facility (a,)
calibration and/or repair, radiation protection plan because failure to do so results in increased radiation exposure to 12.4.5 Scaled Radioactive Source Control workers and potentially even to the public.
Proper control of and accountability for scaled The point of waste generation affords the best radioactive sources used in a facility or by a opportunity to control radiation exposures licensee in field or mobile equipment is very from radioactive waste. The best way to important, and must be addressed within an reduce exposures from radioactive waste is to RPP. There have been many instances where avoid generating the waste in the first place.
sources have been lost and later found by The RPP should include a mechanism for members of the public which resulted in death health physics review and oversight of all of individuals, severe radiation injury of operations that generate radioactive waste so individuals, and extensive contammation of that means to reduce the quantities of waste cities and the environs.
can be evaluated. For example, raw materials that become contaminated might be recycled Sources are used by licensees for many through a process operation (e.g. water, purposes such as instrument calibration, residual or scrap intermediate product),
reactor startup, thickness gauges, level processing operations might be consolidated gauges, well logging, weld mspections, tumor spatially to limit the area requiring irradiation, food irradiation, and many other decontamination, processes might be modified ways. Sources used by licensees can range to involve fewer personnel and pieces of from small sources on the order of micro equipment that handle radioactive materials.
(qj curies to very high activity sources having thousands of curies. The smaller sources Simple measures can be taken to establish represent significantly less hazard to an procedures for handling, storage, and disposal individual than the high activity sources, but of radioactive waste that minimize doses, their control is still important.
providing for greater worker protection and reduced doses to the public. Dose control A well functioning source control program measures can include double lining radioactive will allow for total accountability and control trash disposal bins to reduce the potential for of all sou ces. Documentation of use and breakage and contammation, short-to medium custody of sources is required to ensure term storage of radioactive wastes conmining sources do not end up in the hands of a short-lived radionuclides, automation of waste member of the public. It is easier to handling operations and use of remote accomplish this at a fixed facility than with handling tools and equipment for higher dose sources that are being used in the field for rate wastes if personnel must be involved.
well logging, weld inspection, and other Radioactive wastes must always be kept remote site uses, containerized to avoid potential releases of radioactive material and consideration should 12.4.6 Manacement and Disuosal of be given to waste storage location and the Radioactive Wagg need for shielding to keep doses under control. Radioactive waste disposal should be l
Operations at licensee facilities generate performed in a timely manner to eliminate l
p radioactive wastes that must be handled and sources of radiation exposure, unless waste is
()
ultimately disposed. All aspects of waste being stored for decay of short-lived generation, handling, storage, and waste radionuclides.
USNRC Technical Training Center 12-5 Rev.0595 l
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JUN-12-1997 15:07 TTD CHATTANOOGA 423 855 6546 P.03 Intr: duct:ry Hedth Physics Ch pt:r 12: Ridittiin Pratsetirn Pt:ns cnd Pr:c:dures l
12.4.7 Emernency Resnonse deposited radionuclides in that body of g
workers; in-vivo body counts and sample W
As with several other portions of the RPP, bicassay. In-vivo counting involves the emergency response varies with the needs of detection of gamma-ray emitting radionuclides the facility. The appropriate responses for the using detectors that are positioned over the following incidents or emergencies as they body or specific organ. These detectors are pertain to the safe use of radioactive material described more fully in Chapter 8.
are described in the facility emergency plan:
Bioassay sampling involves the collection of
- Electrical power failures urine, feces, blood, saliva, etc. from a worker
- Minor spills (liquid or dry) to identify the presence of a radionuclide and
- Accidents involving radioactive dusts, quantify the rate of excretion from the affected l
mists, fumes, vapors, or gases individual. More information on detection
- Injuries to personnel involving and sampling methods is presented in Chapter radioactive contamination 8.
- Fires or other emergencies.
l The internal dosimetry program must rely on l
In addition, radiological incidents may include the analytical results to estimate the dose to an l
lost or damaged TLDs or accidental organ and the effective dose equivalent to the overexposures. Such a loss or overexposure whole body that a worker is committed to must be reported to the proper authority, receive. This involves having the staff and usually the RSO. The emergency response computational software to perform these section provides methods for those responding calculations.
to other radiological emergencies.
12.5.2 External Dosimetry Proemrn A second side of emergency response involves handling of emergencies that result in off site Any radiation protection program requims the release of effluents (gaseous or liquids) that assessment of dose to workers from external l
potentially will impact members of the public, sources of radiation in the workplace. This l
Response to these type of emergencies program requires that all affected workers be requires a different and more complex monitored both on a routine basis, and in program than that used for on site certain instances on a special basis, to ensure emergencies. It may be prudent to not handle dose limits are not exceeded. Depending on l
these emergencies within an RPP but handle the size of the work force this program may within a separate group.
be very extensive. At a nuclear power reactor this program represents a total organizational 12.5 Dostmetry Programs structure to ensure that dosimetry is properly issued, collected, read, and results recorded 12.5.1 Internal Dosimetry Program and doses assigned. Typically the dosimetry program involves the use of monthly issue of It is important to maintain the capability to dosimetry. During outages daily orjob task monitor workers for the presence of intemally badges may be issued to ensure proper deposited radionuclides where there is the accounting of worker dose.
possibility for internal deposition. Internal dosimetry programs are as varied as NRC Not only does a dosimetry program rely on g licensees. However, there are two main ways dosimeters such as TLDs or film badges, but for quantifying the amount of internally self reading dosimeters are frequently used.
l -
USNRC Technical Training Center 12-6 Rev.0505 l
JUN-12-1997 15:08 TTD CHATTAtOOGA 423 855 6546 P.09 Intr: duct:ry H:alth Physics Chrpter 12: Ridt: tion Pret:cti:n Plans cnd Prrndur:s l
These dosimeters allow the worker to asses occupational dose limits and ALARA apply as g) their dose on a real-time basis as they are for any other worker.
('
performing their work. Typically the workers are allowed to work in an area until the self Dose records for the embryo / fetus should be reading dosimeter is at some fraction of the kept with those of the declared pregnant task allowed dose. For instance if the worker woman, who is still classified as a worker is authonzed a dose of 200 mrem for receiving occupational exposure. The dose disassembly of a contammated pump, he may records for the embryo / fetus are submitted to have to stop work and leave the area when the the NRC only in the case of an overexposure self reading dosimeter reads 175 mrem. The of the embryo / fetus.
cushion used depends on the experience the health physics department has with the self All workers should receive trauung on NRC reading dosimeters giving dependable dose Regulatory Guide 8.13, " Instructions measurements.
Concerning Prenatal Radiation Exposure".
12.5.3 Rndiation Dose to the 12.6 Radiation Safety Trainin_g l
Embryo / Fetus All personnel who are going to either work 10 CFR Part 20.1208 requires that each with or work in areas contauung radioactive licensee ensure that the dose to an materials or radiation fields must be trained in embryo / fetus during the entire pregnancy, radiation protection. The amount of trainmg from occupational exposure of a declared required depends largely on the potential for l
pregnant woman, does not exceed 0.5 rem.
exposure and the types oJ matenal of concern.
g(')
The licensee is also required to make efforts Two levels of training that may be applicable l
to avoid substantial variation above a uniform are casual workers and radiation workers.
monthly exposure rate to a declared pregnant woman that would satisfy the 0.5 rem limit.
Casual workers may be personnel who are not This corresponds to roughly 50 mrem per routinely exposed or do not routinely work month. This is to prevent all of the 0.5 rem with radioactive material. Their level of dose being given at a time when the traming may be directed to a general embryo / fetus is at a particularly radiosensitive understanding of radioactivity and the methods stage of development.
used at their facility to control exposure to radioactive matenals and rndation. This The woman must declare her pregnancy in would include information on postings, writing but medical confirmation of pregnancy radiation alarms, reporting, and personal is not required nor can it be required. If at frisking. Certamly the information taught can the time of declaration, the embryo / fetus has be less than that required for a radiation already received 0.5 rem or more, the worker.
embryo / fetus is allowed to receive another 50 l
mrem for operational flexibility. The ALARA A radiation worker requires more knowledge principle is to be applied in the case of a about the types of radiations and the methods declared pregnant woman. The declared used to protect them from these rudlations l
pregnant woman can withdraw her declaration than a casual worker. The course outline for at any time, a radiation worker could include such things n
as:
()
If a woman is pregnant but chooses not to declare her pregnancy, the routine l
USNRC Technical Training Canter 12-7 Rev.0595 l
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JLN-12-1997 15:1o TTD CHATTMOOGA 423 855 6546 P.lo intrrduct ry H:alth Physics Chiptsr 12: Ridiati:n Pret:ctirn Pfins cnd PreredurIs l
- defining radioactivity and contamination 12.8 Ouality Assurance
- understanding the affects of time, h
distance, and shielding on worker dose This vital section of the RPP describes all
- cxplainmg postings and worker aspects of the quality assurance program and responsibility for compliance with how they are implemented in connection with postings the facility. Some aspects of this program a types of and use of respiratory may be the type and location of traming t
protection records for all authorized users, frequency and e understanding the use and proper types of audits, and/or frequency of review donning and doffing of. protective for safety procedures. This part of the clothing program should rely on both internal reviews e understar. ding and proper use of and external audits to assure staff and program personnel dosimetry compliance with the RPP requirements.
t
- forms used to document job tasks Quality assurance activities should be involving radiation or radioactivity and conducted by staff that is independent of any workers performing the tasks, etc.
of the licensee's operational organizations in order to be effective.
l The traming should be performance based using an exam to test worker understanding of 12.9 Other Health and Safety Plans l
concepts. Each training course should involve l
a donning and doffing and mock work There are three other areas of safety concern exercise to verify that the worker understands at every licensee's facility that do not deal i
the proper methods for the use of protective with radiation safety. These are industrial clothing and proper techniques for keeping safety, fire safety, and hazardous material h
dose ALARA.
worker right to know.
12.7 Occupational Radiation Protection Rules governing industrial safety within an Record-Keenine and Renortinn operatmg facility are found within 29 CFR 1910. These rules are broad in scope The regulations are replete with requirements covering virtually all aspects of work place for record keeping and reporting. These safety. There are specific training and safety requirements are applicable for all areas plan requirements within 29 CFR 1910 covered by an RPP. Ensuring that records are depending on the physical and chemical maintained and reports are generated and hazards that exist within the work place.
transmitted on time requires a dedicated staff Personnel at a facility who deal with the and space. The number and variety of report industrial operational aspects are either forms used to document activities covered industrial hygienists and/or industrial safety under the RPP can easily outpace the ability professionals. These individuals have been of a small staff to sort, catalog, copy, and trained in the recognition of hazards and l
file. Not to mention retrieving data to support hazard abatement. Depending on the size of the generation of reports. In addition the data the facility and its complexity the safety retention requirements within the regulations department may consist of one person or further exacerbate the situation involving many. These safety professionals implement records.
procedures, perform work place evaluations, and inform workers of good safety practices.
USNRC Technical Training Center 12-8 Rev.0595
l JUN-12-1977 15:11 TTD CHATTfd OJGA 423 855 6546 P.11 Introruct:ry Hrlth Physisc Chapt:r 12: Rsdiati:n Prrticti:n Pl:ns and PricIdures l
l Fire protection at a facility is guided by 29 and temporary storage areas. Implementation I
CFR 1910 Subpart L and by industry code of these requirements drives a facility to have setting organizations such as the National Fire program plans and to train all employees to Protection Association. These standards guide the plan.
design aspects for a facility as well as establish specific requirements for operations.
If the licensee's site contains outside areas that Facilities are to have fire protection systems have been contaminated by hazardous designed into them so that automatic systems materials the site cleanup may be driven by will initiate if a fire occurs. Sufficient exits the requirements of 29 CFR 1910.120. These and emergency lighting is to be in place to requirements address specific training and l
facilitate worker evacuation. Fire health and safety plan requirements that must l
extinguishers are placed strategically within a be complied with for personnel working at the j
facility to allow easy access by workers to cleanup site.
l fight small local fires. Fire evacuation signals are to be used at large facilities to alert 12.10 Summar_y_
workers to the need to evacuate buildings.
Training is to be provided to all workers so The Radiation Protection Program is designed that they understand what their actions are to to ensure that all operations at a facility using be in case of a fire. If the facility allows radioactive material and radiation-producing personnel to use fire extinguishers then there equipment are conducted within the scope of are specific training requirements. By the Radioactive Matenal License and implementing a comprehensive fire protection equipment registrations and in accordance with program at a facility, workers have little risk company policy, and local, state, and federal associated with fire.
regulations. The program is also designed to ensure that exposures to personnel and the Within the area of hazardous matenals there environment are maintained below the are two components. First is what is applicable standards and to a point that is as generally called the " worker right to know" low as reasonably achievable (ALARA).
requirements found in 29 CFR 1910.1200.
These regulations require that all personnel be informed about the chemical hazards that exist at a facility. Within these regulations are the requirements for having material safety data sheets (MSDSs) on any hazardous material or chemical that is used on site, and for the MSDSs to be kept on file and readily accessible to the work force. There are requirements for labeling of chemicals and other hazardous substances.
The second component for hazardous materials are the regulations governing the storage and disposal of hazardous waste materials within a facility. These regulations are found in 40 l
CFR 264 and 265. These requirements are
(
very specific and contain holdir.g times for i
wastes in either satellite accumulat on areas i
l USNRC Technical Training Center 12-9 Rev.0595
l-JUti-12-1997 15:12 TTD CHATTAtOOGA 423 855 6546 P,12 l
Intrzductrry H=lth Phy ics Chyptir 12: R:diati:n Prst:ction Plans and Proccdures Chapter 12 Study Questions
- 1. What are the basic components of a radiation protection plan?
- 2. Define the criteria that require each of the following posting labels:
- RADIATION AREA
- AIRBORNE RADIOACTIVITY AREA
- CONTAMINATION AREA
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1 1
9 USNRC Technical Training Center 12-10 Rev.0595 TOTAL P,12
< TRANSACTION REPORT >
06-17-1997(TUE) 13:14 C
TRANSMIT 3
NO.
DATE TIME DESTINATION STATION PO.
DURATION MODE RESULT l
32763 6-17 12:49 405 271 8425 g j g,y_,,
41 O*24'59' NORM.E OK i
41 O'24'59" i
l Y
Alld h 44%
4.J Lag J - 6.HtDiupuk'gu aw s h -
l b dx /?/.S' Oil, 02 PR.
4/ts/77 w
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< TRANSACTION REPORT >
12:16 06-17-1997(TUE) 1
[
SROADCAST 3
NO.
DATE TIME DESTINATION STATION PG.
DURATION MODE RESULT 32742 6-17 04:17 919 571 4148 41 O*24'53" NORM.E OK 32743 04:42 701 328 5200 41 O*24'49" NORM.E OK 32744 05:08 503 731 4081 41 O*24'49' NORM.E OK 32745 05:33 401 277 2456 41 O*47'17" NORM.E OK 32746 06:20 8037377412 19 O*15'21' NORM.E UO10 32747 06:36 615 532 7938 41 O*24'54*
NORM.E OK 32748 07:01 5128346708/ ( 4.)
41 O'26*52*
NORM.E OK 32749 07:28 801 533 4097 18 O*12'33*
NORM.E UO10 32750 07:41 360 753 1496 41 O*24'S1" NORM.E OK 3275t 08:06 518 457 2225 41 O* 24 ' C,5
- NORM.E OK 32752 08:32 518 457 5545 13 O*06*36' NORM.E UOiO 32753 08:39 NEW YORK CITY 41 O*25'11" NORr1.E OK 32754 09:04 502 227 7862 4i O'26*05" NORMAL OK 32755 09:31 AEC8 (613) 995-5086 41 O*25'42' NORMAL OK 32756 09:57 WASHINGTON OC 41 O*24'48" NORM.E OK 32757 10:22 7996726 41 O*25'21" NORM.E OK 32758 10:48 217 782 1328 41 O*28'07" NORM.E OK 32759 11:16 512 239 6362 41 O*25'00" NORM.E OK 32760 11:42 4024714840 41 O*29'50' NORMAL OK 32761 12:12 912 262 3143 4
O*03'47" NORMAL U008 ERROR PAGE:04 710 7*52'05*
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< TRANSACTION REPORT >
06-17-1997(TUE) 04:16 3
C BROAOCAST 3
NO.
DATE TIME DESTINATION STATION PO.
DURATION MOOE RESULT 32717 6-16 18: 15 610 337 5324 41 O*25'07" NORM.E OK 32718 18:40 404 562 4955 41 O*24'57' NORM.E OK 32719 19:05 7085151096 26 O'32*25" NORM.E UO10 32720 19:38 817 860 8122 14 O*O9*13" NORM.E UO10 32721 19:48 5109750381 41 O*25'08" NORM.E OK 32722 20:13 334 613 5387 18 O*20'45' NORt1.E UO10 1
32723 20:34 6024370705 41 O*30'35" NORMAL OK 32724 21:05 5016612468 41 O'26'45" NORt1. E OK 32725 21:32 0111916 3243610 41 O*24'52" NORM.E OK 32726 21:57 303 343 3697 27 O*17'29' NORM.E UO10 32727 22:15 904 487 0435 41 O*26'02" NORt1.E OK l
32728 22:42 404 362 2653 31 O*19'27' NORM.E UO10 32729 23:01 217 524 4724 41 O*24'54" NORt1.E OK 32730 23:27 515 242 6284 41 O*25'09*
NORt1. E OK 32731 23:52 913 296 0984 4i O*26*21" NORM.E OK 32732 6-17 00:19 502 564 6533 41 O*24'53" NORM.E OK 32733 00:44 LOU!S!ANA 13 O*06'54*
NORti.E UO10 32734 00:51 MAINE 41 O*29'48" NORMAL OK 32735 01:21 410 631 3198 wts., /
41 O*25'43" NORMAL OK 32736 01:47 601+354+6167 4i O*31'02*
NORMAL OK 4
32737 02:19 402 471 9449 41 O*24'49" NORt1.E OK 32738 02:44 7026875751 12 O'07*44" NORt1AL UOO8 ERROR PAGE:12 32739 02:52 603 225 2325 38 O*25'23" NORM.E UO10 32740 03:18 5058271544 41 O*29'47" NORt1AL CK 32741 03:48 518 458 6434 41 O*28'38" NORti. E OK 876 9'53'49" j
-