Week 7: Simulator Morning Questions Flashcards
There are 3 transitions in the first 4 steps of E-0. What are they and where do they occur?
Transition to Failure to Trip, Step 1
Transition to Loss of All AC Power, Step 3
Transition to Trip Recovery with no SI, Step 4
What are the 5 actions on the foldout page of E-0?
RCP Trip Criteria
Cold Leg Recirculation Criteria
Ruptured SG Criteria
Faulted SG Criteria
AFW Switchover Criteria
Which of the 3 major events (LOCA, HELB, SGTR) is checked for first in E-0? Why?
HELB, Fairly unique indicators of this event, so it can be quickly determined if this is the event in question
List the 6 critical safety functions in order of priority.
Subcriticality (S)
Core Cooling (C)
Heat Sink (H)
Integrity (P)
Containment (Z)
Inventory (I)
Why do we trip RCPs at 1375 psig on LOCA?
If we don’t, the potential exists for the RCPs to pump more water out of the break (and out of the core) than assumed by the safety analysis.
List the symptoms of a LOCA.
PZR level drops
PZR pressure drops
High containment pressure
Sump level increasing
Differentiate between a leak, small LOCA, and a large LOCA.
Leak: 1 charging pump can maintain PZR level
LBLOCA: decay heat completely removed through break
SBLOCA: requires SG as heat sink
How is energy removed from the RCS on a LOCA?
Out the break for LBLOCA
SGs first on SBLOCA
What are the SI termination criteria?
At least 4% level in the PZR
RCS pressure stable or increasing
Either 260 MPPH or 4% level in at least 1 SG
Greater than 30 degrees of subcooling
What are the T.S. allowable leak rates?
No pressure boundary leakage
1 gpm unidentified leakage
10 gpm identified leakage
150 gpd P-S leakage through any 1 SG
Plant is at 100%. Loop 2 Thot fails high. Describe the plant response.
Rod control uses the auctioneered high Tavg signal, so the failed loop 2 Tavg indicates that the RCS is too hot. Rod control drives in rods in response.
List the immediate actions of E-0, including the RNOs.
Verify Rx trip (DRPI at bottom, trip breakers open, IR current decreasing) - RNO manually trip reactor
Verify Turbine trip (Main stop valves closed) - RNO manually trip turbine, pull to lock EHS pumps
Verify power to NB busses - RNO start diesel generators
Verify SI actuation - RNO verify SI not required, if it is, manually initiate both trains
List the 6 preempive actions.
Reduce AFW to SGs to limit cooldown
Isolate faulted SG
Mitigate Tavg heatup from SG dryout
Isolate ruptured SG
Switch steam dumps to pressure mode when RCPs tripped
Trip RCPs associated with stuck open PZR spray valves
What is ES-0.0? When can you use it?
Re-diagnostic procedure, use when Rx is tripped with SI actuated or SI required
What is the plant response to a failed high PZR level channel with no operator action?
CCP flow reduces, actual PZR level reduces, eventually PZR level reaches LTDN isolation setpoint, PZR level begins to rise through seal injection, PZR level rises to Rx trip setpoint