HPT001.010
Revision 4
Page 1 of 68
NUCLEAR TRAINING
TRAINING MATERIALS COVERSHEET
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RADIOLOGICAL PROTECTION TECHNICIAN INITIAL TRAININGPROGRAM
FUNDAMENTALS TRAINING HPT001
COURSE
RADIATION PROTECTION STANDARDS
AND GUIDELINES / COURSE NO.
HPT001.010
LESSON TITLE / LESSON PLAN NO.
INPO ACCREDITED / YES / X / NO
MULTIPLE SITES AFFECTED / YES / X / NO
PREPARED BY
Brian K. Fike and Ralph G. Wallace / ------
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 TRAININGREVISION/USAGE LOG
Rev. # / Description of Changes / Date / Pages Affected / Reviewed By
1
2
3
4 / Initial Issue
To reflect Corporate RadCon
Suggestions
To incorporate 10 CFR 20 Revision
And enable lesson plan to be used
As Initial (Basic Phase) and
Retraining (Continuing Training).
General revision to update materials
During program re-activation. / 06/24/88
10/06/94 / ALL
ALL
ALL
ALL / Brian K. Fike and
Ralph G. Wallace
TVA 40385 [NP 6-2003] Page 2 of 2
I. Program: Radiological Protection Technician Initial Training
II. Course: Fundamentals Training
III. Lesson Title: Radiation Protection Standards and Guidelines
IV. Length of Lesson: 16 hours
V. Training Objectives:
A. Terminal Objective:
Upon completion of this course the participant will demonstrate an understanding of the Radiation Protection Standards and Guidelines by successfully completing a written examination with a score of ≥ 80%.
B. Enabling Objectives: Basic Phase (B.P.).
Upon completion of this lesson, the participant will be able to answer test items on the following:
B.P.-1. Explain the historical development of radiological protection standards.
B.P.-2. Recognize the radiological protection regulatory and advisory organizations and describe the function of each.
B.P.-3. Select the purpose for the Nuclear Regulatory Commission’s Radiological Protection Standards and Regulatory Guides.
B.P.-4. State the philosophy/basis for the radiation protection limits.
B.P.-5. Identify where the scientific data is acquired by the Nuclear Regulatory Commission in order to set the radiation protection limits.
B.P.-6. Choose between stochastic effects and non-stochastic effects of radiation and list one example of each.
B.P.-7. State the reason for the administrative dose level at TVA.
B.P.-8. Identify the importance of an effective ALARA program as it relates to stochastic and non-stochastic effects of radiation.
B.P.-9. Define the following terms:
a. License Condition
b. NUREG
c. Recommendation
d. Regulation
e. Regulatory Guide
f. Technical Specification
B.P.-10. Identify the title/significant contents of 10 CFR 19, 10 CFR 20 per this lesson.
B.P.-11. Name the form mailed to employees for dose record reporting.
B.P.-12. List the Nuclear Regulatory Commission’s Federal 10 CFR 20 Occupational Adult Dose Limits.
B.P.-13. List TVA’s administrative Dose Levels per Nuclear Power Standard 5.1.
B.P.-14. State the three requirements for the implementation of a successful ALARA program.
B.P.-15. Identify the title/significant contents of 10 CFR 21, 10 CFR 50,
10 CFR 61, 10 CFR 71, 49 CFR Parts 100-199 per this lesson.
B.P.-16 Identify two requirements regarding information provided to the NRC.
B.P.-17. Identify the TVAN document which establishes the guidelines for managing the licensing interface between TVA and the NRC.
B.P.-18. Describe the organization and content of the Radiation Protection Plan (Corporate) and Plant RadCon (Health Physics) Manuals.
C. Enabling Objectives: Continuing Training (C.T.).
Upon completion of this lesson, the participant will be able to answer test items on the following:
C.T.-1. Summarize the historical development of radiological protection standards.
C.T.-2 Differentiate between the regulatory and advisory organizations and describe the function of each.
C.T.-3 Explain the purpose for the Nuclear Regulatory Commission’s Radiological Protection Standards and Regulatory Guides.
C.T.-4 Restate the philosophy/basis for the radiation protection limits.
C.T.-5 Identify where the Nuclear Regulatory Commission obtains scientific data for setting radiation protection limits.
C.T.-6 Distinguish between stochastic effects and non-stochastic effects of radiation and list one example of each.
C.T.-7 Contrast NRC limits and the administrative dose levels at TVA.
C.T.-8 Relate the importance of an effective ALARA program to stochastic and non-stochastic effects of radiation.
C.T.-9 Define the following terms:
a. License Condition
b. NUREG
c. Recommendation
d. Regulation
e. Regulatory Guide
f. Technical Specification
C.T.-10. Identify the title/significant contents of 10 CFR 19, 10 CFR 20 per this lesson.
C.T.-11. Identify the form mailed to employees for dose record reporting.
C.T.-12. List the Nuclear Regulatory Commission’s Federal 10 CFR 20 Occupational Adult Dose Limits.
C.T.-13. List TVA’s administrative Dose Levels per Nuclear Power Standard 5.1
C.T.-14. State the three requirements for the implementation of a successful ALARA program.
C.T.-15. Identify the title/significant contents of 10 CFR 21, 10 CFR 50, 10 CFR 61, 10 CFR 71, 49 CFR Parts 100-199 per this lesson.
C.T.-16. Describe two requirements regarding information provided to the NRC.
C.T.-17. Identify the TVAN document which establishes the guidelines for managing the licensing interface between TVA and the NRC.
C.T.-18. Describe the organization and content of Radiation Protection Plan (Corporate) and Plant RadCon (Health Physics) Manuals.
VI. Training Aids:
A. Marker board.
B. Portable compact disc player using music disc of instructor’s choice.
VII. Training Material:
A. Appendices
1. Handouts
a. HO-1, Enabling Objectives
b. HO-10, Radiological Protection Standards and Guidelines Crossword
Puzzle
Note: Handout 1A is to be used for Basic Phase (B.P.) training and Handout 1B is to be used for Continuing Training (C.T.).
B. Attachments
1. Power Point Transparencies, Slide show located at P\Training\Technical Programs and Services\Radcon\Initial Program\Lesson Plan Library \Library\HPT001.010 Radiation Protection Standards and Guidelines \HPT001.010.ppt.
2. (HO-2) Attachment 2 – NRC Form 3.
3. (HO-3) Attachment 3 – NRC Form 5 Equivalent.
4. Attachment 4 – U.S. Nuclear Regulatory Commission Regulatory Guide 8.7, Revision 1, “Instructions for Recordkeeping and Reporting Occupational Radiation Exposure Data,” June 1992.
5. (HO-4) Attachment 5, OE16645, “Improper Posting of an Area Due to the Inability of a Technician to Locate a Small Beam of Radiation,” Catawba 3, June 24, 2003.
file://C:\WINDOWS\Temp\InpoReader119302.htm.
6. (HO-5) Attachment 6 – U.S. Nuclear Regulatory Commission Regulatory Guide 8.8, Revision 3, “Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations will be As Low As Reasonably Achievable,” June 1978.
7. (HO-6) Attachment 7 – U.S. Nuclear Regulatory Commission Regulatory Guide 8.10, Revision 1-R, “Operating Philosophy For Maintaining Occupational Radiation Exposures As Low As Reasonably Achievable,” May 1977.
8. Attachment 8 – U.S. Nuclear Regulatory Commission Regulatory Guide 8.13, Revision 3, “Instructions Concerning Prenatal Radiation Exposure,” June 1999.
9. Attachment 9 – U.S. Nuclear Regulatory Commission Regulatory Guide 8.15, Revision 1, “Acceptable Programs for Respiratory Protection,” October 1999.
10. (HO-7) Attachment 10 – OE15307, :Sources Obtained Under a General License Were Not Being Leak Tested in Accordance with the Provisions of 10 CFR 31.5,” Fort Calhoun Station, November 4, 2002.
file://C:\WINDOWS\Temp\InpoReader766896.htm.
11. (HO-8) Attachment 11 – NRC Information Notice (IN) 2002-36: Incomplete or Inaccurate Information Provided to the Licensee and/or NRC By Any Contractor or Subcontractor Employee, December 27, 2002.
http://www.nrc.gov/reading-rm/doc-collections/gen-comm/info-notices/2002/in200236.pdf
12. (HO-9) Attachment 12, OE11952, “Radioactive Sources Improperly Controlled during Transport from the Environmental Lab to TMI,” Three Mile Island Unit 1, January 8, 2001.
file://C:\WINDOWS\Temp\InpoReader745198.htm.
VIII. References:
A. Gollnick, Daniel A. (Ed.) Basic Radiation Protection Technology, 2nd Edition, Pacific Radiation Corporation, CA, 1988.
B. HPT099.100 Revision 2, Attachment 3 – Tennessee Valley Authority Health Physics (RadCon) Technician/Specialist Training Knowledge’s and Skills Task to Training Matrix (RCT Task Number 014.200).
C. Hogerton, John F. (Ed.) The Atomic Energy Desk book, Reinhold Publishing Corporation, New York, 1963.
D. INPO 91-014, Guidelines for Radiological Protection at Nuclear Power Stations, December 1991.
E. INPO 93-008, Guidelines for Training and Qualifications of Radiological Protection Technicians, August 1993.
F. Radiation Protection Plan, Nuclear Power Standard (STD-5.1), January 01, 1994.
G. Title 10, Code of Federal Regulation, Part 19, “Notices, Instructions, and Reports to Workers,” April 30, 1992.
H. Title 10, Code of Federal Regulation, Part 20, “Standards for Protection Against Radiation; Final Rule,” June 20, 1991.
I. Title 10, Code of Federal Regulation, Part 21, “Reporting of Defects and Noncompliance,” April 30, 1992.
J. Title 10, Code of Federal Regulation, Part 34, “Licenses for Radiography and Radiation Safety Requirement for Radiographic Operations,” April 30, 1992.
K. Title 10, Code of Federal Regulation, Part 50, “Domestic Licensing of Production and Utilization Facilities,” April 30, 1992.
L. Title 10, Code of Federal Regulation, Part 61, “Licensing Requirements for Land Disposal of Radioactive Waste,” April 30, 1992.
M. Title 10, Code of Federal Regulation, Part 71, “Packaging and Transportation of Radioactive Materials,” April 30, 1992.
N. Title 49, Code of Federal Regulation, Parts 100-199, “Transportation Regulations for Radioactive Materials.”
O. TVAN Business Practice 213 (BP-213), “Managing TVA’s Interface With NRC,” Revision 21, March 8, 2004.
P. TVAN SPP-3.0, “Nuclear Assurance and Licensing,” Revision 2, August 29, 2003.
Q. TVAN SPP-3.3, “NRC Commitment Management,” Revision 6, March 19, 2001.
R. U.S. Environmental Protection Agency (EPA), “Manual of Protective Action Guides and Protective Actions for Nuclear Incidents,” October 15, 1991.
S. U.S. Nuclear Regulatory Commission Regulatory Guide 8.7, Revision 1, “Instructions for Recordkeeping and Reporting Occupational Radiation Exposure Data,” June 1992.
T. U.S. Nuclear Regulatory Commission Regulatory Guide 8.8, Revision 3, “Information Relevant To Ensuring That Occupational Radiation Exposures At Nuclear Power Stations Will Be As Low As Reasonably Achievable,” June 1978.
U. U.S. Nuclear Regulatory Commission Regulatory Guide 8.10, Revision 1-R, “Operating Philosophy For Maintaining Occupational Radiation Exposures As Low As Reasonably Achievable,” May 1977.
V. U.S. Nuclear Regulatory Commission Regulatory Guide 8.13, Revision 2, “Instructions Concerning Prenatal Radiation Exposure,” November 1975.
W. U.S. Nuclear Regulatory Commission Regulatory Guide 8.15, Revision 1, “Acceptable Programs For Respiratory Protection,” October 1976.
X. U.S. Nuclear Regulatory Commission Regulatory Guide 8.35, Revision 1, “Planned Special Exposures,” June 1992.
IX. Introduction:
The discovery of X-rays by Wilhelm Conrad Roentgen in December of 1895 was looked upon as the beginning of a new era in diagnosis and treatment for many medical problems. For the first time a doctor could look inside a person. This phenomenon rapidly spread and by February of 1896 most major cities had at least one X-ray facility. By October of 1896, people began to realize that there was more to radiation than was first suspected. Severe burns and loss of limbs caused by too high exposures to radiation, especially to the users, raised concern about the use of X-rays. It took many years of experimentation and use by the medical profession before enough data has been gathered to be able to quantitatively and qualitatively measure exposure to radiation. It wasn’t until the 1920’s that the first quantitative unit of exposure, the Roentgen, was defined. As more knowledge and understanding of radiation was gained, meaningful guidelines and standards could be established. There are now several international organizations and every major country has a national organization dedicated to radiation protection. From all of these have come the standards we now use. The purpose of this lesson is to explain the standards and limits that govern the nuclear industry and the organizations that regulate these limits.
Note that for the purposes of this lesson plan, the historical unit of exposure as measured in R/hr and subunits, thereof, is equivalent to dose (RAD) and dose equivalent (REM). Based on the American National Standards Institute (ANSI) standard N13.11 development and terminology, any dose greater than 10 REM is generally denoted in units of RAD, since that level is considered as the accident range of personnel exposure. Any dose less than that level is considered the protective range of personnel exposure.
X. Terms and Definitions (Additional definitions are found throughout the lesson plan. In particular, those for 10 CFR 20 begin on page 23.)
A. Agreement State – A state that enters into an agreement with the NRC over control of reactor by-products. The state must show that it’s regulations are at least as stringent as the NRC’s and that they have the ability to enforce them.
B. ALAP – As Low As Practical.
C. ANSI – American National Standards Institute.
D. CFR (Code of Federal Regulations) – A legal statement written into a government code.
E. DOE – Department of Energy.
F. DOT – Department of Transportation.
G. ERDA – Energy Research and Development Administration.
H. ESD (Erythema Skin Dose) – The amount of radiation required to redden the skin. Depends on the energy of the radiation, e.g., An acute exposure of 300R of low energy X-rays or an exposure of 800R from 700KeV gamma’s will produce reddening of the skin.
I. FRC – Federal Radiation Council.
J. IAEA – International Atomic Energy Agency.
K. ICRP – International Council on Radiation Protection and Measurements.
L. ICRU – International Commission on Radiation Units and Measurements.
M. NCRP – National Council on Radiation Protection and Measurements.
HPT001.010
Revision 4
Page 36 of 68
XI. Lesson Body
/Instructor Notes
A. The historical development of radiation protection standards.
/HO-1
B.P.-1 TP-1
C.T.-11. X-rays were discovered in December 1895 by Wilhelm Conrad Roentgen.
/TP-2
2. Roentgen’s discovery of radiation protection standards.
/3. X-rays and subsequent injury to X-ray patients led to the development of radiation protection standards.
/4. The first known therapeutic use of X-rays was in February 1896.
/a. An hour or more of X-ray exposure was not uncommon.
/b. Patients and doctors suffered from lack of exposure control.
/5. By October 1896, doctors realized that X-rays could have harmful effects.
/TP-3
a. Skin burns were observed at relatively low doses.
/b. Severe burns and loss of limbs occurred at significantly higher doses.
/6. Even with the above effects, by 1897 every major U.S. city had an X-ray machine and the demand for X-ray therapy was worldwide.