EPRI EXAM 2 QUESTIONS WITH
CORRECT ANSWERS!!
Defined as hypothesized events that affect one or more of the radioactive material
barriers and that are not expected during plant operations
Accidents
What are two accident types that are considered?
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
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?
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
True
- It is the specification to which a plant is designed
Primary safety concern for nuclear power plant operation is....
the protection of the public from the release of fission products
First line of defense is....
, keeping the core covered, cooled, and properly reactive
The systems of the plant are designed with several layers of protection including....
automatic controls, alarms, and automatic protective systems.
The focus of accident mitigation is....
protecting the reactor core
is a quantitative assessment of the risk associated with plant operation and maintenance
Probabilistic Risk Assessment (PRA)
Also known as Probabilistic Safety Assessment (PSA)
What is the original goal of PRA?
To analyze and understand sever accident behavior, and then identify and fix the plant
vulnerabilities
What are the attributes of a PRA
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
Several conservative (worst-case) assumptions are used to set the bounds for the design...
- Worst case single failure of equipment
- Non-safety equipment not available during an accident
- Equipment providing no capability if not fully operable
Baseline for plant configuration to mitigate the various design basis events.
Technical Specification's Limiting Condition for Operation (LCO)
CORRECT ANSWERS!!
Defined as hypothesized events that affect one or more of the radioactive material
barriers and that are not expected during plant operations
Accidents
What are two accident types that are considered?
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
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?
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
True
- It is the specification to which a plant is designed
Primary safety concern for nuclear power plant operation is....
the protection of the public from the release of fission products
First line of defense is....
, keeping the core covered, cooled, and properly reactive
The systems of the plant are designed with several layers of protection including....
automatic controls, alarms, and automatic protective systems.
The focus of accident mitigation is....
protecting the reactor core
is a quantitative assessment of the risk associated with plant operation and maintenance
Probabilistic Risk Assessment (PRA)
Also known as Probabilistic Safety Assessment (PSA)
What is the original goal of PRA?
To analyze and understand sever accident behavior, and then identify and fix the plant
vulnerabilities
What are the attributes of a PRA
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
Several conservative (worst-case) assumptions are used to set the bounds for the design...
- Worst case single failure of equipment
- Non-safety equipment not available during an accident
- Equipment providing no capability if not fully operable
Baseline for plant configuration to mitigate the various design basis events.
Technical Specification's Limiting Condition for Operation (LCO)
