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EPRI Core Protection Nantel Exam Questions and Answers
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EPRI Core Protection Nantel Exam Questions and Answers
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EPRI Core Protection Nantel ExamQuestions and Answers
What is the primary safety concern for nuclear power plant operations? - Answers -
Preventing significant radiation exposure to the public during routine and accident
conditions.
How is the primary safety concern for nuclear power plant operations achieved? -
Answers -Employing fission product barriers and engineered safety features.
Identify ways a core can fail - Answers -Any loss of core geometry, particularly into a
configuration where cooling becomes impractical, is considered a core failure
List three ways that the core has an inability to fully remove the heat created by the fuel
- Answers -1. A failure of the heat removal systems
2. An increase of heat created beyond the ability of the heat removal systems
3. The inability to transfer heat from the fuel
What are the three fission product barriers? - Answers -1. fuel pellet and cladding
2. Reactor Coolant System (RCS) pressure boundary
3. Containment
Prevents the escape of fission products from cladding - Answers -Fuel pellet and
cladding (first fission product barrier)
Contains the radionuclides that escaped the cladding or were produced outside the
cladding - Answers -RCS pressure boundary (second fission product barrier)
Holds radionuclides that have escaped from the RCS - Answers -Containment (third
fission product barrier)
The defense-in-depth policy states that a utility should: - Answers -1. Design to prevent
the occurrence of nuclear accidents
2. Assume that accidents will occur
3. Provide proven capability to meet the range of worst-case accidents
Defined as hypothesized events that affect one or more of the radioactive material
barriers and that are not expected during plant operations - Answers -Accidents
, What are two accident types that are considered? - Answers -1. Mechanical failure of a
single component leading to the release of radioactive material from one or more
barriers
2. Arbitrary rupture of any single pipe up to and including complete severance of the
largest pipe in the nuclear system process barrier
By definition, what is typically a worst-case accident of interest - Answers -Design Basis
Accident (DBA)
When designing a plant, the philosophy documented in the FSAR contains several
layers. Which of the following assumptions are used to ensure core protection? -
Answers -a. The plant is operating in a given band via proper control
b. The plant is assumed to be in steady state prior to the transient
c. The plant is being operated within Technical Specifications
A design basis accident is typically a worst-case accident of interest.... T/F - Answers -
True
- It is the specification to which a plant is designed
Primary safety concern for nuclear power plant operation is.... - Answers -the protection
of the public from the release of fission products
First line of defense is.... - Answers -keeping the core covered, cooled, and properly
reactive
The systems of the plant are designed with several layers of protection including.... -
Answers -automatic controls, alarms, and automatic protective systems.
The focus of accident mitigation is.... - Answers -protecting the reactor core
is a quantitative assessment of the risk associated with plant operation and
maintenance - Answers -Probabilistic Risk Assessment (PRA)
Also known as Probabilistic Safety Assessment (PSA)
What is the original goal of PRA? - Answers -To analyze and understand sever accident
behavior, and then identify and fix the plant vulnerabilities
What are the attributes of a PRA - Answers -1. It realistically models plant design, plant
procedures, and human performance
2. It is a best estimate
3. It is not a safety-related tool
4. It is a mathematical model of all important plant systems using plant - specific data for
critical components
5. It models the plant response for various initiating events using calculated systems
reliabilities
6. It takes into account realistically usable mitigating equipment
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