HPT001.012

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NUCLEAR TRAINING

TRAINING MATERIALS COVERSHEET

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RADIOLOGICAL PROTECTION TECHNICIAN INITIAL TRAINING
PROGRAM
RADIOLOGICAL CONTROL HPT001
COURSE
personnel monitoring / COURSE NO.
HPT001.012
LESSON TITLE / LESSON PLAN NO.
INPO ACCREDITED / YES / X / NO
MULTIPLE SITES AFFECTED / YES / X / NO
PREPARED BY
Ralph G. Wallace/Brian K. Fike / ------
Signature / Date
PROCESS REVIEW
David L. Stewart / ------
Signature / Date
LEAD INSTRUCTOR/PROGRAM MGR. REVIEW
R. L. Coleman / ------
Signature / Date
PLANT CONCURRENCE / ------
Signature / Date
TVAN CONCURRENCE (If applicable) / ------
Signature / Date
BFN SQN WBN CORP
Receipt Inspection and Distribution:
Training Materials Coordinator / / Date
Standardized Training Material
Copies to:

TVA 40385 [NP 6-2003] Page 1 of 2

NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER / DESCRIPTION
OF CHANGES / DATE / PAGES
AFFECTED / REVIEWED BY
0 / Initial Issue. / ALL
1 / Program was inactive. / 03/12/90 / ALL
Reviewed and revised to reac- / 1 - 4, 14
tivate
2 / General revision to enable lesson / 01/01/94 / ALL / Amy E. Burzese
plan to be used as initial training
and continuing training and to
incorporate 10CFR20 changes.
3 / General revision to update materials during program / 2004 / ALL / Ralph G. Wallace/ Brian K. Fike
re-activation.

TVA 40385 [NP 6-2003] Page 2 of 2

I. PROGRAM: Radiological Protection Technician Initial Training

II.COURSE: Fundamentals Training

III.LESSON TITLE: Personnel Monitoring

IV.LENGTH OF LESSON/COURSE:8 Hours

V.TRAINING OBJECTIVES:

A.Terminal Objective

Upon completion of this course, the participants will demonstrate their knowledge and understanding of the information presented during RADCON Technician training by obtaining a score of greater than or equal to 80% on a written examination. The information presented in this lesson plan may be part of an overall exam or be the only information for which the student is examined.

B.Enabling Objectives

Standards and conditions apply to all enabling objectives. They include under the examination ground rules, without the use of training materials or outside assistance and utilizing information presented in this lesson plan. Upon completion of this each participant will be able to:

1.Identify and describe the significant terms applicable to personnel monitoring.

2.Know and be able to apply the regulatory and TVA administrative dose limits and describe the methods and equipment used in TVA to determine doses from various types of radiation.

3.Identify the types of radiation monitoring devices used in the monitoring for:

a.External radioactivity

b.Internal radioactivity

c.Contamination

And describe the conditions under which they are used.

4.Describe the principles of operation and characteristics of the types of dosimetry used at TVA, including:

a.TLDs

b.Electronic dosimeters

c.Pocket ion chambers

5.Explain TVA’s administrative controls over the issue, use and control of dosimeters.

6.Explain the requirements for the use of multiple and extremity dosimeters.

7.Describe the types of dosimetry required for various work situations.

8.Describe actions to be taken in the event of abnormal situations, such as:

a.Discrepancies in dosimetry readings

b.Lost dosimeters

c.Off-scale dosimeter readings

d.Exposures in excess of TVA administrative limits

e.Skin contamination.

9.Identify the basic concepts of internal dosimetry and internal dose calculations, including:

a.Exposure pathways;

b.Methods to reduce internal exposures; and

c.Processes for elimination of internal radioactivity.

10.Identify the primary radionuclides of concern for the assessment of internal exposures, including their sources and pathways.

11.Describe the biological effects and risks associated with exposure to ionizing radiation.

12.Identify the methods used to estimate doses from inhalation or ingestion of radioactive materials and explain and be able to apply or determine the following:

a.Annual Limit on Intake (ALI).

b.Committed Dose Equivalent (CDE).

c.Committed Effective Dose Equivalent (CEDE).

d.Total Effective Dose Equivalent (TEDE).

e.Total Organ Dose Equivalent.

f.Derived Air Concentration (DAC).

g.Derived Air Concentration-hours (DAC-hours)

h.Shallow (skin) Dose Equivalent (SDE)

IDeep Dose Equivalent (DDE)

13.Describe the means for assessing the uptake of radioactivity (bioassay) and the required frequency for performing bioassay.

14.Describe TVA’s exposure tracking and reporting system.

Note: Conditions and Standards for enabling objectives unless otherwise specified are implied. Conditions are “as presented in the lesson plans, with the use of reference material as directed by the instructor” and Standards are “as evaluated by written examination.”

VI.TRAINING AIDS:

  1. Dry marking board and pens
  1. Overhead projector and networked computer
  1. Thermoluminescent Dosimeter and Crystals
  1. Extremity TLD
  1. Pocket Chamber
  1. Electronic Dosimeter

VII.TRAINING MATERIALS:

  1. Appendices

1.Handouts:

a.HO-1 – Attachment 1, Transparencies

b.HO-2 - Enabling Objectives

c.HO-3 - Terms and Definitions

d.HO-4 - Administrative Dose Level Program

e.HO-5 - Dosimetry Investigating Report Guidelines

f.HO-6 - Representative Radionuclides of Concern

g.HO-7 - Radionuclides in Dry Compressed Waste

h.HO-8 - 10CFR20 Appendix B (Extract)

i.HO-9 - WBC MDA Critical Values

j.HO-10 - Guidelines for Conducting Follow-Up Bioassay Analyses

k.HO-11 - Organ Dose Weighting Factors

l.HO-12 - Attachment 2, NRC Form 4, Cumulative Occupational Dose History

o.HO-13 - Attachment 3, NRC Form 5, Occupational Dose Record for a Monitoring Period

  1. Attachments
  1. Transparencies: PowerPoint slide show stored at P/Training/Technical Programs and Services/Radcon/Initial Program/Lesson Plan Library/HPT001.012 Personnel Monitoring\HPT001.0112r3.ppt.
  1. TP-1 - Lesson Title
  2. TP-2 - Course Overview
  3. TP-3 - Enabling Objectives 1
  4. TP-4 - Enabling Objectives 2
  5. TP-5 - Units of Radiation Dose, Absorbed
  6. TP-6 - Units of Radiation Dose, Dose Equivalent
  7. TP-7 - Quality Factors
  8. TP-8 - Personnel Monitoring Required by 10CFR20.1501
  9. TP-9 - Purposes for Monitoring

j.TP-10 - Conditions Requiring External Monitoring

  1. TP-11 -Conditions Requiring Monitoring for Internal Exposures
  2. TP-12 -Exposure Limits and Guidelines
  3. TP-13 -Planned Special Exposures
  4. TP-14 -Emergency Dose Limits
  5. TP-15 -Exposure to Pregnant Women
  6. TP-16 -Modes of Exposure
  7. TP-17 -External Monitoring
  8. TP-18 -Thermoluminescence
  9. TP-19 -Electron Trapping
  10. TP-20 -TLDs
  11. TP-21 -Li2B4O7:Cu TLDs
  12. TP-22 -Lithium Borate Response Curves
  13. TP-23 -CaSO4:Tm TLDs
  14. TP-24 -Calcium Sulfate Response Curves
  15. TP-25 -Limitations of Both Types
  16. TP-26 -Panasonic TLDs
  17. TP-27 -Thermoluminescent Dosimeter
  18. TP-28 -TLD Badge Assembly
  19. TP-29 -TLD Badge
  20. TP-30 -Panasonic 802 TLD
  21. TP-31 -Measuring Neutrons with TLDs
  22. TP-32 -Panasonic 802 TLD
  23. TP-33 -Reading Panasonic TLDs
  24. TP-34 -System Calibration
  25. TP-35 -SystemQC & QA
  1. TP-36 -Badge Issue and Collection
  2. TP-37 -Special Pulls
  3. TP-38 -Wearing TLDs
  1. TP-39 -Photo – Proper Wearing of Dosimeters
  2. TP-40 -Multiple Badging
  3. TP-41 -Multi-Badging Placement
  4. TP-42 -Extremity Badges
  5. TP-43 -Photo – Extremity Badge
  6. TP-44 -Photo – Wearing Extremity Badges
  7. TP-45 -Secondary Dosimetry
  8. TP-46 -Electronic Dosimeter (ED)
  9. TP-47 -Electronic Dosimeter Display
  10. TP-48 -Pocket Chamber
  11. TP-49 -Pocket Chamber Diagram
  1. TP-50 -Dosimetry Requirements for Work Areas – 1
  1. TP-51 -Dosimetry Requirements for Work Areas – 2
  2. TP-52 -Dosimeter Discrepancies

aaa.TP-53 -Internal Exposure Pathways

bbb.TP-54 -Reducing Internal Exposures

  1. TP-55 -Elimination of Internal Radioactivity

ddd.TP-56 -Potential Health Effects and Risks

eee.TP-57 -Naturally Occurring Radioactive Materials

fff.TP-58 -Potential Health Effects

ggg.TP-59 -Other Influences

hhh.TP-60 -Internal Exposure Terms – 1

iii.TP-61 -Internal Exposure Terms – 2

jjj.TP-62 -Sample Problem # 1

kkk.TP-63 -Internal Exposure Terms – 3

lll.TP-64 -Relationship Between DAC and ALI

mmm.TP-65 -Internal Exposure Terms # 4

nnn.TP-66 -Sample Problem # 2

ooo.TP-67 -Sample Problem # 3

ppp.TP-68 -Relationship of DAC-h and ALI

qqq.TP-69 -Sample Problem # 4

rrr.TP-70 -Sample Problem # 4, Knowns

sss.TP-71 -Sample Problem # 4, Solution with Respirator

ttt.TP-72 -Sample Problem # 4, Solution with No Respirator

uuu.TP-73 -Sample Problem # 4, Conclusion

vvv.TP-74 -Measuring Internal Radioactivity (Bioassay)

-Compliance

  1. TP-76 -Internal Dose Monitoring

yyy.TP-77 -Bioassay Requirements

zzz.TP-78 -Whole Body Counting (In-Vivo Bioassay)

aaaa.TP-79 -Photo – Chair WBC

bbbb.TP-80 -Photo – Booth WBC

cccc.TP-81 -Multi-Channel Analyzer

dddd.TP-82 -WBC Measurement Quality Assurance

eeee.TP-83 -Actions Taken for Positive Results – 1

ffff.TP-84 -Actions Taken for Positive Results – 2

gggg.TP-85 -In-Vitro Bioassay

hhhh.TP-86 -In-Vitro Bioassay Results

iiii.TP-87 -Required Actions: Results >/= 0.01 ALI or
20 DAC-h

jjjj.TP-88 -Dose Terms and Calculations

kkkk.TP-89 -CEDE From CDE

llll.TP-90 -CEDE From Nuclide Intake and ALI

  1. TP-91 - CEDE From Airborne Concentration and DAC

nnnn.TP-92 -CEDE From Nuclide Intake and Dose Conversion Coefficient (RADCON computer system methodology)

oooo.TP-93 -Committed Dose Equivalent (CDE)

pppp.TP-94 -Federal Guidance Report # 11

qqqq.TP-95 -CDE From Intake and ALI

rrrr.TP-96 -CDE From Airborne Concentration and DAC

ssss.TP-97 -CDE From Intake and Dose Conversion Coefficient (RADCON computer system methodology)

tttt.TP-98 -Dose to Embryo/Fetus – 1

uuuu.TP-99 -Dose to Embryo/Fetus – 2

vvvv.TP-100 -Doses From Contamination

w -Contamination Dose Calculations Required for:

xxxx.TP-102 -Activity-Hour Concentration

yyyy.TP-103 -Shallow (Skin) Dose Equivalent (SDE)

zzzz.TP-104 -Deep Dose Equivalent (DDE)

aaaaa.TP-105 -Doses From Hot Particles

bbbbb.TP-106 -Total Organ Dose Equivalent (TODE)

ccccc.TP-107 -Total Effective Dose Equivalent (TEDE)

ddddd.TP-108 -Dose Tracking and Reports

eeeee.TP-109 -Summary – 1

fffff.TP-110 -Summary – 2

ggggg.TP-111 -Summary – 3

2.NRC Form 4, Cumulative Occupational Dose History

3.NRC Form 5, Occupational Dose Record for a Monitoring Period

VIII.REFERENCES:

  1. Basic Radiation Protection Technology, 2nd Edition, Daniel A. Gollnick, Pacific Radiation Corporation, Altadena, CA, 1988.

B. Radiation Protection, Jacob Shapiro, HarvardUniversity Press; Massachusetts, 1981.

C. Radiological Health Handbook, U.S. Department of Health, Education, and Welfare, Public Health Service, Rockville, MD, 1970.

D. The Health Physics and Radiological Health Handbook, Nucleon Lectern Associates, 1984.

E. The Health Physics and Radiological Health Handbook, Bernard Shleien, Editor, Scinta, Inc., Silver Spring, MD, 1992.

F. Environmental Radiation, 2nd Edition, Merril Eisenbud, Academic Press, New York, 1973.

G. NUREG/CR-3332, ORNL-5968, Radiological Assessment, John E. Till and H. Robert Meyer, Editors, U.S. Nuclear Regulatory Commission, Washington, 1983.

H. ICRP Publication 2, Report of Committee II on Permissible Dose for Internal Radiation, Pergamon Press, New York, 1959.

I. NCRP Report No. 39, Basic Radiation Protection Criteria, National Council on Radiation Protection and Measurements, Washington, DC, 1971.

J. NCRP Report No. 94, Exposure of the Population in the United States and Canada from Natural Background Radiation, National Council on Radiation Protection and Measurements, Bethesda, MD, 1987

K. ICRP Publication 10, Evaluation of Radiation Doses to Body Tissues from Internal Contamination due to Occupational Exposure, Pergamon Press, New York, 1967.

L. Code of Federal Regulations, Title 10, Part 20,U.S. Government Printing Office, Washington, 2003.

M.
dosimeter.htm.

N. wwwrses.anu.edu.au/environment/eePages/eeDating/Dating_Page.html.

O.

P.

Q.

R.

S.

T. INPO ACAD 93-008, Guidelines for Training and Qualification of Radiological Protection Technicians, August 1993.

U. Fundamentals of Radiation Protection, General Physics Corp. U.S., 1979.

V. OE13726, Contamination Found on New Employee During In-Coming Whole Body Count, Vermont Yankee Nuclear Power, April 24, 2002.

W. OE14697, DMC-2000 EPD Dose Rate Alarm Caused by Induced Oscillation from New RCA Turnstile System, Palo Verde Unit 1, September 10, 2002.

X. OE15549, Missing TLD Posphor Insert Events, Ginna, January 15, 2003.

Y. OE15663, Individual Fails to Immediately Exit Area When Dose Rate Alarm Received, Perry Nuclear Power Plant, January 24, 2003.

Z. OE15709, Wrench With Fixed Radioactive Contamination Found in a Non-Radiologically Controlled Area, LaSalle Units 1 & 2, January 23, 2003.

AA. Web sites of potential interest.

1.


IX.INTRODUCTION:
The development and application of effective monitoring methods are of basic importance to any radiation protection program. Decisions are required on the need for monitoring the individual and for surveying the methods to be used. The frequency of monitoring and the methods adopted depend on many factors. The most important of these are the type of radiation, the mode of radiation exposure, the level of radiation exposure relative to applicable permissible limits, and the extent to which reliance is placed on physical or procedural controls in achieving protection. / TP-1
Lesson Title
TP-2
Course Overview
Handout #-1
Enabling Objectives
TP-3
Objectives 1
TP-4
Objectives 2
X. TERMS AND DEFINITIONS: / INSTRUCTOR NOTES
Handout # 2
Terms & Definitions
Objective # 1
  1. Absorbed dose – The energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the rad and the gray (Gy).

  1. Anneal – The process in which the TLD phosphor is heated to a high temperature (usually 400° C or 750°F) to release all of the trapped electrons from the trap sites and return them to the low energy valence band. After proper annealing, the phosphor has the same sensitivity as previously and the TLD can be reused.

  1. Annual limit on intake (ALI) – The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a committed effective dose equivalent (stochastic) of 5 rems (0.05 Sv) or a committed dose equivalent (nonstochastic) of 50 rems (0.5 Sv) to any individual organ or tissue.

  1. Bioassay (radiobioassay) – The determination of kinds, quantities or concentrations, and in some cases, the locations of radioactive material in the human body, whether by direct measurement (in vivo counting) or by analysis and evaluation of materials excreted or removed from the human body.

  1. Bioassay area – Any airborne radioactivity area and any other area where unencapsulated radioactive material is present in a form and quantity such that the area has significant potential for becoming an airborne radioactivity area. Entry into bioassay areas is covered by Radiation Work Permits (RWPs).

  1. Collective dose – The sum of the individual doses received in a given period of time by a specified population from exposure to a specified source of radiation.

  1. Committed dose equivalent (CDE or HT,50) – The dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the 50-year period following the intake. The dose is assigned in the year in which it was received.

  1. Committed effective dose equivalent (CEDE or HE,50) – The sum of the products of the weighting factors (WT) applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues (HE,50 = ∑ WT * HT,50).

  1. Deep dose equivalent (DDE or Hd) – The dose equivalent, which applies to the external whole body exposure, at a tissue depth of 1 cm (1000 mg/cm2).

  1. Derived air concentration (DAC) – The concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2,000 hours under conditions of light work (inhalation rate of 1.2 cubic meters of air per hour), results in an intake of one ALI.

  1. Derived air concentration-hour (DAC-hour) – The product of the concentration of radioactive material in air (expressed as a fraction or multiple of the derived air concentration for each radionuclide) and the time of exposure to that radionuclide, in hours (f-DAC * number of hours). A licensee may take 2,000 DAC-hours to represent one ALI, equivalent to a committed effective dose equivalent of 5 rems (0.05 Sv).

  1. Direct reading dosimeter (DRD) or secondary dosimeter – Refers to an electronic dosimeter and/or a pocket chamber (PC) dosimeter.

  1. Dose or radiation dose – A generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, or total effective dose equivalent, as defined in this section.

  1. Dose equivalent (HT) – The product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The units of dose equivalent are the rem and sievert (Sv).

  1. Effective dose equivalent (EDE or HE) – The sum of the products of the dose equivalent to the organ or tissue (HT) and the weighting factors (WT) applicable to each of the body organs or tissues that are irradiated (HE = ∑ WT times HT).

  1. External dose – That portion of the dose received from radiation sources outside the body.

  1. Extremity – The portions of the human body farthest from the trunk of the body, including the hand, elbow, arm below the elbow, foot, knee, or leg below the knee.

  1. Fading – The loss of recorded information with the passage of time, as it applies to TLDs.

  1. Half-life, Biological - The time required for a biological system, such as that of a human, to eliminate by natural processes half the amount of a substance (such as a radioactive material) that has entered it.

  1. Half-life, Radiological – The time taken for the activity of a radionuclide to lose half of its value by radioactive decay.

  1. Half-life, Effective (Te) – The time required for the amount of a radioactive element deposited in a living organism to be diminished 50 percent as a result of the combined action of radioactive decay and biological elimination.
Te = (Tr)(Tb)
Tr+ Tb
Where Tr is the radiological half life for the radionuclide, and Tbis the biological half life.
  1. High radiation area – An area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 0.1 rem (1 mSv), but less than 1 rem (10 mSv), in 1 hour at 30 centimeters from the radiation source or 30 centimeters from any surface that the radiation penetrates.

  1. Individual monitoring devices – Devices designed to be worn by a single individual for the assessment of dose equivalent. Such devices include film badges, Thermoluminescence dosimeters, (TLDs), pocket ionization chambers, electronic dosimeters, and personal (“lapel”) air sampling devices.

  1. Internal dose – That portion of the dose equivalent received from radioactive material taken into the body.

  1. Lens dose equivalent (LDE) –The LDE applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm2).

  1. Nonstochastic effects – Health effects, the severity of which varies with the dose and for which a threshold is believed to exist. Radiation-induced cataract formation is an example of a nonstochastic effect (also called a deterministic effect). The threshold for radiation-induced cataract formation is approximately 600 rads.

  1. NVLAP - The National Institute of Standards and Technology (NIST, formerly National Bureau of Standards) administers the National Voluntary Laboratory Accreditation Program (NVLAP). NVLAP is comprised of a series of laboratory accreditation programs (LAPs) which are established on the basis of requests and demonstrated need and provides third-party accreditation to testing and calibration laboratories. Each LAP includes specific calibration and/or test standards and related methods and protocols assembled to satisfy the unique needs for accreditation in a field of testing or calibration. TVA’s Tennessee Valley Authority External Dosimetry Services (TEDS) Laboratory is accredited in the field of Ionizing Radiation Dosimetry.