CURRICULUM COMMITTEE NEW COURSE CHECKLIST

• Document Type: CREST
• Collection: General CIA Records
• Document Number (FOIA) /ESDN (CREST): CIA-RDP87-00956R000100030026-7
• Release Decision: RIPPUB
• Original Classification: K
• Document Page Count: 7
• Document Creation Date: December 22, 2016
• Document Release Date: November 16, 2010
• Sequence Number: 26
• Publication Date: December 4, 1984
• Content Type: MEMO

Sanitized Copy Approved for Release 2010/11/16: CIA-RDP87-00956R000100030026-7
4 December 1984
MEMORANDUM FOR: Members of the Office of Training and
Education Curriculum Committee
Chief, Topical issues Branch
SUBJECT: Curriculum Committee New Course Checklist
1. The Topical Issues Branch (TIB) is planning to conduct a
three-day course titled "Introduction to Nuclear Power and
Radiation" during the period of 15-17 January 1985, in the
Chamber of Commerce Building. The objective of this course is to
provide an understanding of the basic design and operation of
nuclear power plants. This course fits into a series of
scientific and technologically oriented courses and seminars
conducted by TIB primarily for DI and DS&T analysts.
2. Two months ago, OSWR asked TIB to consider conducting
this course. Since then, other offices in the DI, DO, and DS&T
have joined the list of customers.
3. Students will be professionals of all grades from
throughout the Intelligence Community ---NSA, DIA, DOE--- who,
because of their analytic and collection responsibilities require
an understanding of nuclear power plants and how they operate.
4. The purpose of this course is to provide the layperson
with an introduction to the terminology, process, and equipment
involved in generation of nuclear power. An outline of the
course is provided in Attachment A. The method of instruction
includes two and one half days of unclassified lecture and
discussion augmented by slides and viewgraphs of actual equipment
and facilities. The last half of the third day will include
classified discussions conducted by OSWR experts.
5. The course will be conducted by members of the Reactor
Training Staff of the Nuclear Regulatory Commission's (NRC)
Reactor Training Center. The course outline has been reviewed by
members of TIB, and in our judgment, the course provides a
comprehensive understanding of nuclear power plant design and
operation.
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SUBJECT: Curriculum Committee New Course Checklist
6. The course will be conducted by NRC instructors at no
cost to the Agency. The course administrat' nn will rpoll . rim an
estimated two man-weeks of TIB instructor - and
training assistant - - time. A room as been
reserved in the Cham er o ommerce uilding for the course. We
have not identified any opportunity costs associated with
conducting this course.
7. A considerable amount of informal marketing of the
course has already taken place through the Nuclear Energy
Division of OSWR. We will distribute an "0TE Special Training
Bulletin" to all Agency training officers --- and interested
parties elsewhere in the Intelligence Community.
8. We will ask each student to evaluate critical segments
of the course. If student responses indicate that this pilot
running of the course was useful, we will include the course in a
survey of needs for specific seminars and determine how often we
should run the course.
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INTRODUCTION TO NUCLEAR POWER AND RADIATION
COURSE OUTLINE
DAY 1 (Morning)
1. POWER GENERATION - OVERVIEW
a. Comparison of electrical generation from nuclear power
plants to that of fossil and hydroelectric plants.
Explanation of what makes a nuclear plant unique.
b. Explanation of BWR, PWR and HTGR power generation
systems.
c. Explanation of waste heat from fossil and nuclear plants.
d. Explanation of cooling towers and water vapor discharges.
e. Brief discussion of the layout of a typical nuclear power
plant.
2. FISSION PROCESS AND HEAT PRODUCTION
a. Review of atomic structure (elements, compounds), and
electrostatic forces.
b. Explanation of nuclear force, neutrons as part of atomic
structure, and isotopes of various elements.
c. Explanation of uranium isotopes, fission and heat
production.
d. Explanation of criticality, neutron behavior in the
reactor, neutron leakage, and moderator and fuel
properties that affect the fission process.
e. Description of the use of neutron poisons (control
rods, soluble boron) in controlling fission rate and
thus heat output of the reactor.
DAY 1 (Afternoon)
3. BWR PLANT SYSTEMS
a. Description of BWR components, coolant systems and
containments.
b. Description of BWR Steam, Condensate and Feedwater Systems.
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DAY 1 (Afternoon) Continued
4. PWR PLANT SYSTEMS
a. Description of PWR components, coolant systems and
containments.
b. Comparison of PWR Secondary System to BWR Steam,
Condensate and Feedwater Systems.
c. Description of a typical Chemical and Volume Control
System (PWR) (BWR).
d. Description of a typical Residual Heat Removal System
(PWR) (BWR).
e. Description of refueling operations at a PWR.
DAY 2 (Morning)
5. INTRODUCTION TO RADIATION TERMINOLOGY
DESCRIPTION OF:
a. Radioactivity
b. Radiation
Alpha
Beta
Gamma
X-Ray
Neutron
c. Half Life
d. Ionization
e. Dose
Roentgen
Rad
Rem
f. Dose Rate
g. Stay Time
h. Contamination (types & properties)
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DAY 2 (Morning) Continued
6. SOURCES OF RADIATION
a. Explanation and demonstration of natural and manmade
radiation and its sources:
Cosmic Medical
Terrestrial Electronic
Internal Weapons Testing
b. Explanation of sources and types of radiation at a
nuclear power plant.
Fuel decay
Fission process
Fission product decay
Activation products
Calibration sources
c. Introduction to fission product barriers at a nuclear
plant and their importance to public health and safety.
Fuel Pellet Construction
Fuel Cladding Integrity
Coolant System Integrity
Containment Integrity
7. BIOLOGICAL EFFECTS OF RADIATION
a. Explanation of effects of radiation exposure at the
cellular level.
b. Discussion of possible cellular processes after exposure.
c. Discussion of radiation effects as seen at the body level.
Acute Effects
Radiation Syndrome
Chronic Effects
Types of cancer related to radiation exposure.
d. Discussion of NRC dose limits.
Unrestricted Areas
Restricted Areas
ALARA Program
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DAY 2 (Morning) Continued
e. Discussion of Radiosensitivity and its determining
factors.
f. Discussion on Methods of Protection against Radiation
(with examples).
g. Discussion on Methods of Protection against Contamination.
DAY 2 (Afternoon)
8. RADIOACTIVE WASTE HANDLING SYSTEMS
a. _Liquid Radwaste System
b. Gaseous Radwaste System
c. Solid Radwaste System
9. REACTOR EMERGENCIES
a. Discussion of what constitutes a Reactor Emergency and
the difference between a Reactor Emergency and a
Radiological Emergency.
b. Description of Design Basis Accidents and possible
consequences.
Loss of Coolant
Steam Line Break
Rod Ejection
Steam Generator Tube Rupture
c. Discussion of systems designed to mitigate Reactor
Emergencies and protect the public.
d. Normal Core Cooling and Moderating Systems
Aux Feedwater System
Steam Relief Valves
Residual Heat Removal System
Service Water System
e. Emergency Core Coolant and Moderating Systems
Active Safety Injection Systems
Passive Safety Injection Systems
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DAY 3 (Morning)
f. Containment Systems
Structure/Construction
Depressurization and Air Cooling Systems
Purification Systems
Isolation Systems
Emergency Preparedness Systems
Licensee's Responsibility
Local Government Responsibility
State Government Responsibility
Federal Response/Assistance Agencies
h. The Three Mile Island Accident
Discussion of events at TMI utilizing information
presented in previous lectures.
10. Questions, comments, critique.
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