1 of 73
Term
When designing a plant, the philosophy documented in the FSAR
contains several layers. Which of the following assumptions are used to
ensure core protection?
Give this one a try later!
, False. Any plant modification can have an effect on plant's CDF. For instance, adding
an additional power source to mitigate the loss of off-site power can greatly reduce
the chance that a core damage event will occur at the power plant.
- Worst case single failure of equipment
- Non-safety equipment not available during an accident
- Equipment providing no capability if not fully operable
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
Action Statement
Don't know?
2 of 73
Term
typically worst-case accident of interest used to design plant
components
Give this one a try later!
Safety injection (si) Design Basis Accident (DBA)
, Radiolytic Decomposition of Water Limiting conditions of operation (lcos)
Don't know?
3 of 73
Term
-Used in licensing
-Estimated the likelihood of the YES/NO answer
-Uses realistic techniques
-Considers the Probability of a Failure
- Considers Multiple Failures
-Credits all potentially available equipment. Any possible plant
configuration may be included
-Adverse consequences defined as Core Damage that is generally
taken as loss of structural integrity of the fuel
-Functional
Give this one a try later!
Low Pressure Coolant Injection (LPCI) Safety Limits
Probabilistic Analyses Deterministic Analyses
Don't know?
, 4 of 73
Term
The defense-in-depth policy states that a utility should:
Give this one a try later!
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
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
-Rapid rise in dry well (primary containment) pressure
-Decrease in reactor water level
-All ECCS pumps start
-Reactor empty and depressurized (inventory to suppression pool)
1. A heat source (the reactor core)
2. A heat sink to which the secondary fluid transfers its heat (the steam generators)
3. The heat sink (steam generators) must be at a higher elevation than the heat
source (reactor core)
4. A continuous, unobstructed flowpath (the reactor coolant system piping)
Don't know?
Term
When designing a plant, the philosophy documented in the FSAR
contains several layers. Which of the following assumptions are used to
ensure core protection?
Give this one a try later!
, False. Any plant modification can have an effect on plant's CDF. For instance, adding
an additional power source to mitigate the loss of off-site power can greatly reduce
the chance that a core damage event will occur at the power plant.
- Worst case single failure of equipment
- Non-safety equipment not available during an accident
- Equipment providing no capability if not fully operable
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
Action Statement
Don't know?
2 of 73
Term
typically worst-case accident of interest used to design plant
components
Give this one a try later!
Safety injection (si) Design Basis Accident (DBA)
, Radiolytic Decomposition of Water Limiting conditions of operation (lcos)
Don't know?
3 of 73
Term
-Used in licensing
-Estimated the likelihood of the YES/NO answer
-Uses realistic techniques
-Considers the Probability of a Failure
- Considers Multiple Failures
-Credits all potentially available equipment. Any possible plant
configuration may be included
-Adverse consequences defined as Core Damage that is generally
taken as loss of structural integrity of the fuel
-Functional
Give this one a try later!
Low Pressure Coolant Injection (LPCI) Safety Limits
Probabilistic Analyses Deterministic Analyses
Don't know?
, 4 of 73
Term
The defense-in-depth policy states that a utility should:
Give this one a try later!
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
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
-Rapid rise in dry well (primary containment) pressure
-Decrease in reactor water level
-All ECCS pumps start
-Reactor empty and depressurized (inventory to suppression pool)
1. A heat source (the reactor core)
2. A heat sink to which the secondary fluid transfers its heat (the steam generators)
3. The heat sink (steam generators) must be at a higher elevation than the heat
source (reactor core)
4. A continuous, unobstructed flowpath (the reactor coolant system piping)
Don't know?
