Week 1 Flashcards
- Nuclear Cooling water has been lost due to a pipe rupture
- Train ‘A’ EW has been cross-connected to NC
Which one of the following identifies a plant condition that will isolate Essential Cooling Water to the RCP’s?
A. Pressurizer pressure drops to 1900 psia.
B. Containment pressure rises to 4.0 psig.
C. Instrument Air header pressure drops to 60 psig.
D. Loss of power to the EW to NC cross connect valves
B. Containment pressure rises to 4.0 psig.
- Unit 1 is in Mode 1
- ‘A’ NCW Pump is under Permit
- ‘B’ NCW pump trips and is locked out
The Operating Crew directed to restore Nuclear Cooling Water flow within…..
A. 10 minutes or trip the reactor, stop all RCPs, and ensure controlled bleedoff isolated.
B. 3 minutes or commence a controlled shutdown.
C. 3 minutes or trip the reactor, stop all RCPs, and ensure controlled bleedoff isolated.
D. 10 minutes or commence a controlled shutdown.
A. 10 minutes or trip the reactor, stop all RCPs, and ensure controlled bleedoff isolated.
- Unit 1 is at 100% power.
- An RCS leak to the NC system is in progress.
Which of the following would be indicative of an RCS leak into the letdown heat exchanger?
A. backpressure control valve opening.
B. indicated letdown flow increasing.
C. NC flow from the heat exchanger decreases.
D. backpressure control valve closing.
D. backpressure control valve closing.
- Unit 1 is operating in Mode 1.
- Due to a loss of the NC pumps, EW ‘A” has been crosstied to NC.
Based on these conditions, EW ‘A’ is…
A. considered OPERABLE as long as it is NOT supplying Fuel Pool Cooling at the same time it is aligned to NC.
B. INOPERABLE.
C. considered OPERABLE since it was analyzed to support the plant during accident conditions while supplying the priority loads of NC.
D. considered OPERABLE since the crosstie valves have an automatic feature that will close them when EW is required to support its safety function.
B. INOPERABLE.
Essential Cooling Water (EW) will supply which of the following Nuclear Cooling Water (NC) loads when cross-tied to NC?
A. Letdown heat exchanger.
B. Containment Normal AHUs.
C. Normal Chillers.
D. Waste Gas Compressors.
C. Normal Chillers.
- Unit at 100% power.
- PWN-P01A has been removed from service for maintenance and is disassembled.
- PWN-P01B trips on ground fault.
Which one of the following Operator actions is required?
A. Trip the reactor and perform Standard Post Trip Actions.
B. Immediately cross tie EW to NC and SFP cooling.
C. Trip the turbine and stabilize RCS/PZR pressure <2383 psia.
D. Trip the turbine and maintain reactor power <40% using SBCS.
A. Trip the reactor and perform Standard Post Trip Actions.
- Unit 1 is operating at rated power.
- Seal Injection is isolated to the RCPs due to a leak in the Aux building.
Which of the following describes the effect (if any) that this has on the RCP temperatures?
A. Isolating Seal Injection should have NO impact on the seal temperatures.
B. HP Seal Cooler inlet temperature will rise to between 200°F and 220°F, all other seal temperatures should increase by about 70°F.
C. HP Seal Cooler inlet temperature should remain relatively constant, while all other seal temperatures should increase by about 70°F.
D. HP Seal Cooler inlet temperature will rise to between 200°F and 220°F while all other seal temperatures remain normal.
D. HP Seal Cooler inlet temperature will rise to between 200°F and 220°F while all other seal temperatures remain normal.
- Unit 1 is operating at 100% power.
- A Regulating Group 4 CEA drops to the bottom of the core.
Based on these conditions, the operating crew must:
A. begin a power reduction within 10 minutes.
B. have the CEA restored within 15 minutes.
C. be less than 80% power within 30 minutes.
D. begin efforts to restore the CEA in 10 minutes.
A. begin a power reduction within 10 minutes.
- Unit 1 is operating at rated power.
- A failure of CHB-UV-515, letdown to regen heat exchanger, caused a loss of letdown.
- PZR level is 55%.
- The operating crew has stopped all charging pumps to establish conditions to support extended operations with letdown isolated.
- A loss of nuclear cooling water occurs.
To avoid tripping the reactor and securing all RCPs, the operating crew must restore:
A. seal injection within 10 minutes.
B. both seal injection and NC within 3 minutes.
C. NC within 3 minutes.
D. both seal injection and NC within 10 minutes.
C. NC within 3 minutes.
- Unit 1 is operating at rated power with all rods 150 inches withdrawn.
- A Regulating Group 3 CEA slips to 135 inches withdrawn.
- Shortly after this, a Regulating Group 5 CEA drops to the bottom of the core.
Based on these conditions, the operating crew must:
A. monitor CPC ASI and trip the reactor if it approaches +0.5.
B. reduce turbine load to maintain Tavg and Tref within 3°F of each other.
C. immediately trip the reactor.
D. monitor CPC DNBR and LPD margins to trip and trip the reactor if either one approaches its trip setpoint.
C. immediately trip the reactor.
When a CEA drops, the downpower that satisfies the requirements of 40AO-9ZZ11 (CEA Malfunction) is said to commence…
A. when the boration has been started.
B. as soon as the CEA dropped.
C. the crew notices the effect of the boron on temperature.
D. when load is taken off the turbine.
D. when load is taken off the turbine.
The plant is at 100% power when suddenly the following alarms and indications are observed in the Control Room:
•Reactor power decrease.
•Tavg/Tref Hi-Lo Alarm Window 4A08B on B04 with RCS temperatures decreasing.
•One four-fingered CEA bottom light on the core mimic and LEL lit.
•Pressurizer level and pressure decrease.
•COLSS, CPC, & PDIL alarms.
•Expected CVCS actions due to decreasing pressurizer level.
Which ONE of the following conditions would MOST likely be observed in the next five minutes, if NO operator actions were taken?
A. Reactor power would stabilize at ~ 100% with a higher than full power Tavg.
B. Reactor power would stabilize at ~ 100% power with a lower than full power Tavg.
C. Reactor power would stabilize at 50% with a lower than full power Tavg.
D. The reactor would have tripped due to low pressurizer pressure.
B. Reactor power would stabilize at ~ 100% power with a lower than full power Tavg.
Following a Reactor Power Cutback, how should the operating crew comply with Technical Specification 3.1.7, Regulating Control Element Assembly (CEA) Insertion Limits?
A. Enter the appropriate action, but add 2 hours to the completion time.
B. Enter the appropriate action, but add 4 hours to the completion time.
C. Do not apply the limiting condition for operation for up to 2 hours following the RPCB.
D. Do not apply the limiting condition for operation for up to 4 hours following the RPCB.
C. Do not apply the limiting condition for operation for up to 2 hours following the RPCB.
Which one of the following RRS failures would result in an AMI (Automatic Motion Inhibit) and an AWP (Automatic Withdrawal Prohibit)? Assume all switches are in AVERAGE.
A. Tcold fails high
B. Tcold fails low
C. TLI fails high
D. UIC #1 fails low
A. Tcold fails high
- Unit 1 is at 100% power.
- 40ST - 9SF01, CEA Exercising, is in progress.
- CEA #14 is being exercised and CEDMCS Trouble annunciator alarms.
- The AO reports that the CEA breaker on the Power Switch assembly for CEA # 14 is tripped open.
- CEA 14 is indicating within 2.5” of its group.
Which of the following action(s) is(are) necessary:
A. Trip the reactor and enter SPTAs.
B. Continue with the Surveillance Test after realigning the other CEAs to within 1.5” of CEA # 14.
C. Perform CEAC inoperable procedure, 72AO - 9RJ04.
D. Enter Tech Spec 3.1.5 for an inoperable CEA.
D. Enter Tech Spec 3.1.5 for an inoperable CEA.
