HLC 20 Flashcards
Unit I is performing a startup with the following:
* Reactor power is 17%
* Main Generator output is 60 Mwe
The running DEH pump trips and the standby pump started when DEH header pressure indicated 900 psia.
Which ONE of the following states the expected plant indication?
A. Reactor power indicates 17%, Main Generator indicates 60 Mwe.
B. Core mimic CEA display amber lights are ALL illuminated.
C. Reactor power indicates 17% with SBCS controlling temperature. Main Generator indicates ‘0’ Mwe.
D. Trip Circuit Breaker (TCB) lights indicate ‘WHITE’
B. Core mimic CEA display amber lights are ALL illuminated.
Given the following conditions:
- Unit 1 is at 45% power and stable.
- A 5 gpm break from the upper instrument tap of Pressurizer (Pzr) Level transmitter, LT-1110X, occurs.
Assuming no operator action, which ONE of the following describes the response of LI-1110X?
Ll-1110X “ChanneiX Pzr Level” indication will begin to_(l)____ as a result of the P cell element between the reference and variable leg sensing a (2)
A.
1)lower
2) higher DP due to VARIABLE leg pressure lowering
B.
1)lower
2) lower DP due to REFERENCE leg pressure lowering
C.
1)increase
2) lower DP due to REFERENCE leg pressure lowering
D.
1) increase
2) higher DP due to VARIABLE leg pressure lowering
C.
1)increase
2) lower DP due to REFERENCE leg pressure lowering
Unit 1 has the following post trip indications:
* A Differential Current Bus Lockout has occurred on the 1B3 4.16kv bus
* Pressurizer level is 12% lowering
* Pressurizer pressure is 1780 psia lowering
* CET is 520° F stable
* Containment Pressure is 0.2 psig stable
* SG 1A and 1B are 930 psia and slowly lowering
* Safety I PORV tailpipe temperatures are 140-150°F
* SJAE readings indicate 3.2 E-07 pCi/cc.
Upon the trip the following annunciator came in:
B SAFEGUARDS PUMP ROOM SUMP LEVEL HIGH-HIGH LA-2
(NO operator actions have been taken)
Based on the above conditions, enter:
A. 1-EOP-04, SGTR
B. 1-EOP-09, LOOP
C. 1-EOP-03, LOCA
D. 1-EOP-05, ESDE
C. 1-EOP-03, LOCA
Unit I has tripped. On the trip, a loss of the 1A1 6.9 KV bus occurred. 1-EOP-02, ‘Reactor Trip Recovery’ was entered.
While in 1-EOP-02, ‘Reactor Trip Recovery’ the crew has lowered RCS pressure to between 1800 and 1850 psia.
Which ONE of the following states:
1.the basis for this RCS pressure LOWER limit.
2.the bases for the RCS pressure UPPER limit.
A.
1. The LOWER limit ensures Figure IA, ‘RCS pressure temperature curve’ stays within acceptable range
2. The UPPER limit is based on maintaining the lower RCP seal cavity below 300°F.
B.
1. The LOWER limit is based on providing a margin above SIAS actuation setpoint
2. The UPPER limit is based on maintaining the lower RCP seal cavity below 300°F.
C.
1. The LOWER limit is based on providing a margin above SIAS actuation setpoint
2. The UPPER limit ensures RCP controlled bleedoff flow meets minimum requirement.
D
1. The LOWER limit ensures Figure IA, ‘RCS pressure temperature curve’ stays within acceptable range
2. The UPPER limit ensures RCP controlled bleedoff flow meets minimum requirement.
B.
1. The LOWER limit is based on providing a margin above SIAS actuation setpoint
2. The UPPER limit is based on maintaining the lower RCP seal cavity below 300°F.
Unit 2 is in Mode 3. Due to Pressurizer level control problems, charging and letdown was secured at 2:15 pm. The following conditions are noted:
* RCS temperature is 532°F
* RCS pressure is 2250 psia
* RCP controlled bleedoff is 1.1 gpm per pump
* Pressurizer level is 33%
* Last RCS leak rate was 0.05 gpm.
Assuming no auto or Operator actions, which ONE of the following states the APPROXIMATE time that the Pressurizer will be at the minimum Tech. Spec. limit?
A. 3:01 pm
B. 3:31 pm
C. 3:37 pm
D. 3:46 pm
D. 3:46 pm
Unit 1 is on SDC in reduced inventory condition. The SDC system is aligned and operating in accordance with 1-NOP-01.04, ‘RCS Reduced Inventory And Mid-Loop Operation’.
lAW 1-NOP-Ol .04, ‘RCS Reduced Inventory And Mid-Loop Operation’, which ONE of the following states the LPSI pump that is in STANDBY and the reason for this standby lineup?
A. 1A LPSI pump. V3483, ‘1A LOOP SDC return to 1A LPSI pump relief” has the potential to lift at a higher pressure than 1 B LPSI pump.
B. 1A LPSI pump. Due to suction piping arrangement, LPSI Pump 18 will experience adverse suction conditions before LPSI Pump 1A.
C. I B LPSI pump. V3468, ‘18 LOOP SDC return to 1 B LPSI pump relief’ has the potential to lift at a higher pressure than 1A LPSI pump.
D. 18 LPSI pump. Due to suction piping arrangement, LPSI Pump 1A will experience adverse suction conditions before LPSI Pump 1 B.
D. 18 LPSI pump. Due to suction piping arrangement, LPSI Pump 1A will experience adverse suction conditions before LPSI Pump 1 B.
Given the following conditions on Unit 2:
* The COW system has developed a leak
* LA-lO, “COW SURGE TANK COMPARTMENT A LEVEL LOW,” is locked in
* LB-b, “CCW SURGE TANK LEVEL HIGH/COMPARTMENT B LEVEL LOW,” alarmed but subsequently clears.
1) What COW system loads are affected?
2) What actions need to be performed to restore CCW to that load?
A.
1) Fuel Pool Heat Exchanger
2) Place the “B” train “N” Header valve control switches to CLOSE then OPEN
B.
1) Fuel Pool Heat Exchanger
2) Place the “A” train “N” Header valve control switches to CLOSE then OPEN
C.
1) Letdown Heat Exchanger
2) Place the “A” train “N” Header valve control switches to CLOSE then OPEN
D.
1) Letdown Heat Exchanger
2) Place the “B” train “N” Header valve control switches to CLOSE then OPEN
D.
1) Letdown Heat Exchanger
2) Place the “B” train “N” Header valve control switches to CLOSE then OPEN
Given the following conditions on Unitl:
- The unit is operating at 100% power.
- PlC-li lOX, “Pressurizer (Pzr) pressure controller” is selected.
- Pzr pressure is being maintained at 2250 psia with Pzr Backup Heaters Bi, B2, and B5 ON with a 10% output to the Pzr Proportional Heaters.
The Output on PlC-I I lOX begins to slowly drift HIGH due to a malfunction of PT-il lOX.
Which ONE of the following describes the response of the OUTPUT on HIC1 100, “Main Spray controller “AND the effect on actual Pzr pressure?
(Assume no Operator actions)
HIC-ilOO output_(l)____
Actual Pzr pressure _(2)______
A.
l)rises
2) rises
B.
i)rises
2) lowers
C.
l)lowers
2) lowers
D.
i)lowers
2) rises
B.
i)rises
2) lowers
Unit I has a loss of feedwater event at 100% power. The unit DID NOT TRIP when trip conditions were met.
For the initial onset of the event, which ONE of the following will be the LARGEST contributor of negative reactivity insertion and why? (assuming no Operator actions)
The reactivity added by the increase in the:
A. fuel temperature. For the above event as the fuel temperature increases, this value becomes lower per °F.
B. fuel temperature. For the above event as the fuel temperature increases, this value becomes higher per °F.
C. moderator temperature. For the above event the core is ‘under moderated’ resulting in this value becoming higher per °F.
D. moderator temperature. For the above event the core is ‘over moderated’ resulting in this value becoming less per °F.
C. moderator temperature. For the above event the core is ‘under moderated’ resulting in this value becoming higher per °F.
Unit I was operating at 100% power when the Steam Jet Air Ejector radiation monitor was trending up but has not reached the alarm setpoint. The crew has entered 1-AOP-08.02, ‘Steam Generator Tube Leak’. No other radiation monitors have an increasing trend.
One minute later, the Reactor tripped.
During performance of 1-EOP-01, ‘Standard Post Trip Actions’, the suspected SG tube leak escalated to a 400 gpm SG tube rupture.
While in 1-EOP-01, which ALARM would annunciate FIRST to indicate WHICH Steam Generator has a SG tube rupture?
A. Main Steam line radiation monitor.
B. Steam Jet Air Ejector radiation.
C. Steam Generator level high.
D. Steam Generator blowdown radiation.
D. Steam Generator blowdown radiation.
Unit 1 has experienced an Excess Steam Demand event on the lB SG and has entered 1-EOP-
05, ‘Excess Steam Demand’ with the following:
* 1A SG TOId is 500°F
* lB SG TOjd is 240°F
* I B SG indicates ‘0’ Wide Range
* IA ADV is currently in automatic
The US has directed you to stabilize RCS temperature. lAW Operations Department Policy,
OPS-539, ‘RCS Cooldown Guidance’ which ONE of the following states how RCS temperature is controlled and the basis for this manipulation?
A. Maintain IA ADV in auto and adjust setpoint to 25 psia steam pressure.
This will maximize Safety Injection flow to regain Pressurizer level to within the RCS Inventory control safety function criteria.
B. Maintain IA ADV in auto and adjust setpoint to 25 psia steam pressure.
This will limit the RCS heatup which could result in exceeding the RCS subcooling limit.
C. Place 1A ADV in manual, fully open, then adjust the auto setpoint to 25 psia steam pressure and place in automatic. This will maximize Safety Injection flow to regain Pressurizer level to within the RCS Inventory
control safety function criteria.
D. Place IA ADV in manual, fully open, then adjust the auto setpoint to 25 psia steam pressure and place in automatic. This will limit the RCS heatup which could result in exceeding the RCS subcooling limit.
D. Place IA ADV in manual, fully open, then adjust the auto setpoint to 25 psia steam pressure and place in automatic. This will limit the RCS heatup which could result in exceeding the RCS subcooling limit.
Unit 1 is at 45% power with the following conditions:
* IBAFW Pump is out of service.
* IA Main Feedwater pump is out of service.
The following alarm is received:
125V DC BUS lAB Uv A-60
Shortly after the alarm, the I B Main Feedwater pump trips and cannot be restarted.
Which ONE of the following actions are taken in I -EOP-O1, ‘Standard Post Trip Actions’ as a direct result of the above conditions?
A. Align the lAB DC bus to the IC or ID DC bus.
B. Align the lAB Battery Charger to the lAB DC bus.
C. Maintain current DC alignment with ALL RCP’s running.
D. Secure ONE RCP in EACH loop.
D. Secure ONE RCP in EACH loop.
Given the following conditions:
* Unit 2 is in 2-EOP-1 0, ‘Station Blackout’ receiving power via the Station Blackout Crosstie, to the 2AB 4.16KV bus to the 2A3 4.16KV bus from the 1A Emergency Diesel Generator WHICH IS THE ONLY RUNNING UNIT I DIESEL.
Which ONE of the following states when / if the 2A Intake Cooling Water Pump can be started?
The 2A Intake Cooling Water pump can:
A. be started if Unit 1 has determined sufficient load (KW) capacity is available on the 1A Diesel Generator.
B. be started if Unit 1 has determined sufficient amperage capacity is available on the station blackout crosstie breaker.
C. NOT be started due to the potential for exceeding the station blackout crosstie breaker amperage limits.
D. NOT be started due to the potential for exceeding the 1A Diesel loading (KW) limits.
D. NOT be started due to the potential for exceeding the 1A Diesel loading (KW) limits.
Unit 2 has the following Intake Cooling Water (ICW) system alignment at 100% power:
* 2A and 2B ICW pumps are running.
* 2AB 4.16KV bus is aligned to the 2B3 4.16KV Bus.
The 2C ICW pump was just started on the 2B ICW header for surveillance testing and the 2B ICW pump has yet to be stopped. A loss of offsite power occurs and both Diesel Generators start and load on the bus.
Which ONE of the following states the response of the 2C and 2B ICW pumps?
2B ICW Pump will:
A. automatically restart as the Diesel loads sequence on the bus.
2C ICW pump will NOT automatically restart and CANNOT be manually restarted.
B. NOT automatically restart but CAN be manually started.
2C ICW pump will automatically restart as the Diesel loads sequence on the bus.
C. NOT automatically restart and CANNOT be manually restarted.
2C ICW pump will automatically restart as the Diesel loads sequence on the bus.
D. automatically restart as the Diesel loads sequence on the bus.
2C ICW pump will NOT automatically restart but CAN be manually started.
D. automatically restart as the Diesel loads sequence on the bus.
2C ICW pump will NOT automatically restart but CAN be manually started.
The 120 VDC input breaker spuriously opened.
- 20 Instrument bus Inverter trouble alarm annunciates
Which ONE of the following would be expected as a result of this malfunction?
The 2C Instrument bus:
A. remains energized from the 480 VAC alternate source through the maintenance bypass bus.
B. remains energized from the 120 VAC alternate source directly to the Instrument bus.
C. becomes de-energized. The Instrument bus should be re-energized by placing the 120 VAC manual bypass switch to the Bypass Source to Load’ position.
D. becomes de-energized. The Instrument bus should be re-energized by closing the 480 VAC MOO input breaker to the maintenance bypass bus.
C. becomes de-energized. The Instrument bus should be re-energized by placing the 120 VAC manual bypass switch to the Bypass Source to Load’ position.
Unit I is at 100% power with the 1C ICW pump out of service. The IA lOW pump trips and cannot be restored.
As Turbine Cooling Water temperature rises, which ONE of the following would require entry into 1-AOP-22.01, ‘Rapid Downpower’?
A. Main Generator COLD gas temperature indicates 49°C
B. Main Generator HOT gas temperature indicates 100°C
C. 1A Main Feedwater pump bearing temperature indicates 190°F
D. Turbine bearing oil temperature indicates 160°F
A. Main Generator COLD gas temperature indicates 49°C
Unit 1 is at 100% power when a large Instrument air leak occurs. The crew has implemented 1-AOP-1 8.01, ‘Instrument Air Malfunction’. If Instrument air continues to degrade, which ONE of the following states the HIGHEST pressure that requires the Unit to be manually tripped AND which procedure will be implemented AFTER 1-EOP01 ‘Standard Post Trip Actions’?
A. 74 psig, 1-EOP-02, ‘Reactor Trip Recovery’
B. 59 psig, 1-EOP-02, ‘Reactor Trip Recovery’
C. 74 psig, 1-EOP-09, ‘Loss of Offsite Power/Loss of Forced Circulation’
D. 59 psig, 1-EOP09, ‘Loss of Offsite Power/Loss of Forced Circulation’
D. 59 psig, 1-EOP09, ‘Loss of Offsite Power/Loss of Forced Circulation’
Given the following conditions on Unit 1:
* Reactor power is 100%.
* Unit 2 is off-line due to a Short Notice Outage.
* Switchyard Voltage has lowered from 242kV to 237kV due to a high load demand on the grid.
Based on the above noted conditions, the DRCO would observe Main Generator (1 )
If switchyard voltage continued to lower, the FIRST Main Generator OVER-EXCITATION protection action would be (2).
A.
1) MEGAWATTS and VARS RISING
2) automatically swapping to the DC Voltage Regulator which will maintain the field current at a preset limiting position.
B.
1) VARS RISING ONLY
2) the AC Voltage Regulator limiting maximum field current
C.
1) MEGAWATTS and VARS RISING
2) the AC Voltage Regulator limiting maximum field current
D.
1) VARS RISING ONLY
2) automatically swapping to the DC Voltage Regulator which will maintain the field current at a preset limiting position.
B.
1) VARS RISING ONLY
2) the AC Voltage Regulator limiting maximum field current
Given the following conditions on Unit 1:
* The reactor is at 3.0 E-4% power following a start up from a two week forced outage.
* Critical start up data is being recorded by the RO.
* CEA group 7 was at 108” withdrawn when they were withdrawn to 113”
(Assume no operator action)
Actual reactor power will rise _____________
A. and RCS Temperature will remain stable until reaching the POAH
B. and RCS Temperature will continually rise upon reaching the Power Range
C. until the reactor trips due to High SUR
D. until the reactor trips due to VHPT
A. and RCS Temperature will remain stable until reaching the POAH
Unit 2 is at 100% power. Pressurizer level Channel ‘X’ is selected.
* Pzr Channel X Level Low-Low level alarmed at 27% indicated level (actual level is 63%)
Assuming NO Operator actions which ONE of the following states the number of Charging pumps running and the expected high level alarm?
A. Three Charging pumps running. Pressurizer high level alarm at 73%.
B. Two Charging pumps running. Pressurizer level alarm at 67%.
C. Three Charging pumps running. Pressurizer level alarm at 67%.
D. Two Charging pumps running. Pressurizer high level alarm at 73%.
B. Two Charging pumps running. Pressurizer level alarm at 67%.
Given the following conditions on Unit 1:
* Reactor power is 11% power
* The turbine is being rolled for a start up
* The condenser has developed a small vacuum leak
* Condenser back pressure is 2.7 inches of Hg. and slowly rising
* The crew has entered 1-AOP-12.O1, ‘Loss of Condenser Vacuum’
Which ONE of the following states:
The MINIMUM backpressure setpoint at which the SBCS becomes unavailable and the basis for this setpoint?
A. 8” of Hg. absolute, protect low pressure turbine blades from resonance cracking
B. 12” of Hg. absolute, protect low pressure turbine blades from resonance cracking
C. 8” of Hg. absolute, protect main condenser from overpressure
D. 12” of Hg. absolute, protect main condenser from overpressure
D. 12” of Hg. absolute, protect main condenser from overpressure
Unit I is performing a Liquid Release of the 1A Waste Monitor Tank when the following alarm is received:
LIQUID WASTE RAD HIGH N-37
Liquid release flow control valve, FCV-6627X indicates open and will not close from the RTGB.
lAW I-AOP-06.02, ‘Uncontrolled Release Of Radioactive Liquids’ which ONE of the following is a required SUBSEQUENT Operator action?
A. At the IA Waste Monitor Storage Tank, stop the IA Waste Monitor pump AND at the CCW platform lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
B. At the 1A Waste Monitor Storage Tank, close FCV-6627X AND at the CCW platform lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
C. From the Liquid Waste Control panel, close FCV-6627X AND at the Waste Monitor Storage Tanks, stop the Waste Monitor pump associated with the liquid release.
D. From the Liquid Waste Control panel, stop the IA Waste Monitor pump AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
A. At the IA Waste Monitor Storage Tank, stop the IA Waste Monitor pump AND at the CCW
platform lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation
valve.
The following conditions exist on Unit 1:
* The unit is in a refueling outage with a core offload in progress.
* The Spent Fuel Handling Machine (SFH) is transporting a spent fuel assembly, which has been used for 3 refueling cycles, from the fuel transfer canal to the Spent Fuel Pool (SFP).
* The spent fuel assembly came into contact with transfer gate wall * Gas bubbles are reported to be rising rapidly to the fuel transfer canal surface and bursting.
The FHB EFFLUENT Radiation monitor AND the Spent Fuel Pool Transfer Canal AREA RADIATION MONITOR indications are in ALARM due to the release of(1) . The FHB ventilation system (2).
A.
1) beta and gamma radiation
2) is in its NORMAL alignment
B.
1) gamma radiation ONLY
2) is in its NORMAL alignment
C.
1) beta and gamma radiation.
2) has re-aligned to the Shield Building Ventilation filter train
D.
1) gamma ONLY.
2) has re-aligned to the Shield Building Ventilation filter train.
A.
1) beta and gamma radiation
2) is in its NORMAL alignment
Unit 1 is implementing 1-EOP-15, ‘Functional Recovery’ with the following:
* A Loss of Offsite Power (LOOP) has occurred.
* 1A Steam Generator (SG) has experienced a Steam Generator Tube Rupture (SGTR).
* 1 B SG has an Excess Steam Demand outside the Containment upstream of the Main Steam Isolation valves.
* 1A SG pressure is 850 psia.
* I B SG pressure is 454 psia.
* Neither SG has been isolated.
Which ONE of the following states:
1) When the Containment Isolation Safety Function will be met?
2) Bases for meeting the Safety Function
A.
1) When 1-EOP-99 Appendix R, ‘Steam Generator Isolation’ is complete on the lB SG AND the 1A SG is capable of being steamed ONLY to the condenser.
2) Steaming to the condenser contains the radiological effluents.
B.
1) When 1-EOP-99 Appendix R, ‘Steam Generator Isolation’ is complete on thel B SG AND the 1A SG is capable of being steamed to the condenser OR the atmosphere.
2) The IA SG is the least affected SG and has the capability to remove heat by steaming to atmosphere or condenser.
C.
1) When 1-EOP-99 Appendix R, ‘Steam Generator Isolation’ is complete on BOTH SG’s AND Once Through Cooling is initiated.
2) Both SG’s are considered faulted and should be isolated.
D.
1) When 1-EOP-99 Appendix R, ‘Steam Generator Isolation’ is complete on the 1A SG AND the I B SG has blown dry.
2) Until 1 B SG blows dry, RCS cooldown CANNOT be controlled.
B.
1) When 1-EOP-99 Appendix R, ‘Steam Generator Isolation’ is complete on thel B SG AND the 1A SG is capable of being steamed to the condenser OR the atmosphere.
2) The IA SG is the least affected SG and has the capability to remove heat by steaming to atmosphere or condenser.
Given the following conditions on Unit 2:
* The Unit has experienced a LOCA with multiple ECCS failures.
* Safety injection flow does NOT meet Figure 2
* The crew is performing actions contained in 2-EOP-1 5, Functional Recovery’ Plant conditions are now:
* REP CET indicate 539° F and constant.
* RCS TH 0ttemperatures are 51 9°F and constant.
* RCST0ld temperatures are 51 2°F and constant.
* RCS pressure indication is 870 psia.
Which ONE of the following states the status of RCS subcooling and Natural Circulation?
A. RCS is 9°F subcooled, Single phase Natural Circulation is NOT met.
B. RCS is 11°F superheat, Two phase Natural Circulation IS met.
C. RCS is 9°F subcooled, Single phase Natural Circulation IS met.
D. RCS is 11°F superheat, Two phase Natural Circulation is NOT met.
D. RCS is 11°F superheat, Two phase Natural Circulation is NOT met.
Unit I is performing a natural circulation cooldown in accordance with 1-EOP-03 using the
ADV’s with the following conditions: * RCS pressure is 140 psia and lowering.
* Rep CET temperature is 335°F and constant.
* Hot leg temperature is 325°F and constant.
* Cold leg temperature is 320°F and lowering.
* Reactor Vessel Head temperature is 353°F and constant.
* Aux. spray valve SE-02-03 is open and Aux. spray valve SE-02-04 is closed.
Which ONE of the following states the required actions?
Throttle:
A. open the ADV’s further and close SE-0203.
B. open the ADV’s further and open SE-02-04.
C. close the ADV’s and close SE-02-03.
D. close the ADV’s and open SE-02-04.
A. open the ADV’s further and close SE-0203.
Unit 2 was tripped from 100% power due to LOOP.
The following conditions exist during 2-EOP-01, ‘Standard Post Trip Actions”:
* ADV’s are in service in AUTO/AUTO set to 900 psia
* RCS TaveI5 530°F and stable
* Auxiliary Feedwater was throttled after AFAS actuation
* SG Pressures are 880 psia and stable
Then a SIAS occurred due to lowering pressurizer pressure
Following SIAS actuation, which ONE of the following states the Operator actions that is performed to ensure RCS Heat Removal is maintained within limits?
A. Throttle closed AFW header valves to both SG’s.
B. Place ADV’s in AUTO / MANUAL.
C. Reduce ECCS flow by throttling HPSI valves.
D. Close the MSIV’s.
A. Throttle closed AFW header valves to both SG’s.
Given the following conditions on Unit 1:
* Reactor power is 100%.
* The Containment Instrument Air Compressors are out of service.
* MV-I 8-1, Instrument Air Containment isolation valve closes and cannot be re-opened.
Which ONE of the following Reactor Coolant Pump motor indications would be expected?
A. Increasing RCP Controlled Bleedoff Temp
B. Increasing motor stator temperatures.
C. Decreasing CCW flow to motor oil coolers.
D. Decreasing Upper I Lower oil reservoir levels.
D. Decreasing Upper I Lower oil reservoir levels.
Unit 1 is in Mode 5. RCS level is 30 feet 6 inches with RCP seal injection in service. Two Charging pumps are in service with the 1A LPSI pump filling the RCS.
The Charging Loop isolation valves are as follows:
* SE-02-01, ‘1B1 Loop Charging lsol’ is OPEN
* SE-02-02, ‘1A2 Loop Charging lsol’ is CLOSED
A short circuit causes SE-02-01, ‘1B1 Loop Charging Isol’ to fail closed.
Which ONE of the following states the effect of SE-02-01 closing on the RCP seals?
Seal injection flow has:
A. decreased which could cause contaminants to enter the seal cartridge as the
RCS level is raised.
B. decreased which could result in the seal cavity not filling completely.
C. increased which could result in excessive vapor seal leakoff flow.
D. increased which could result in extreme seal damage.
D. increased which could result in extreme seal damage.
Unit 1 is on SDC. The Pressurizer is being cooled and has just gone solid. RCS pressure is 75 psia.
In accordance with 1-GOP-305, Reactor Plant Cooldown - Hot Standby To Cold Shutdown, which ONE of the following describes:
1. How the Letdown valve controller PIC-2201 will be configured for solid plant operations:
PIC-2201, Ltdn Pressure controller will be in:
AND
2. If HCV-3657, SDC Temp Control, were throttled closed, what response would need to occur
to maintain pressure constant?
A.
1)AUTO.
2) Letdown pressure control valves PCV-2201P and PCV-2201Q will OPEN.
B.
1)AUTO.
2) Letdown pressure control valves PCV-2201P and PCV-2201Q will CLOSE.
C.
1) MANUAL.
2) Manually OPEN Letdown pressure control valves PCV-2201 P and PCV 2201Q.
D.
1)MANUAL.
2) Manually CLOSE Letdown pressure control valves PCV-2201 P and PCV 2201Q.
A.
1) AUTO.
2) Letdown pressure control valves PCV-2201P and PCV-2201Q will OPEN.
Unit 1 has just placed 1A LPSI pump on SDC with the following:
* RCS temperature is 320°F
* RCS pressure is 262 psia
* HCV-3657 SDC TEMP CONTROL is open 100%
* FCV-3306 SDC RETURN FLOW is open 25%
Instrument air to the RAB is lost due to a ruptured air header line.
Which ONE of the following states the expected response?
LPSI amps will:
A. increase, RCS temperature will decrease.
B. decrease, RCS temperature will increase.
C. increase, RCS temperature will increase.
D. decrease, RCS temperature will decrease.
B. decrease, RCS temperature will increase.
Unit 1 is experiencing a Large Break LOCA and is implementing 1-EOP-15, ‘Functional Recovery’ with the following:
* RWTlevelis8feet.
* All ECCS pumps are available
Due to equipment problems, RAS preparation steps are unable to be performed.
Which ONE of the following states the possible effects of not being able to perform the RAS preparation steps?
A. Containment cooling may be jeopardized.
B. Containment sump pH limit may be jeopardized.
C. HPSI Pumps NPSH may be jeopardized.
D. LPSI Pumps may not stop on RAS.
C. HPSI Pumps NPSH may be jeopardized.
Unit 2 has tripped from 100% power due to a Main Generator Lockout. Shortly after the trip, the
ROD noticed:
* Quench Tank pressure is 58 psig and rising
* Pressurizer level is 41% and rising
* Pressurizer pressure is 1720 psia and lowering rapidly
* ROS temperature is 530°F
* V1201 has 5 “led” lights lit
Which ONE of the following contingency actions would the crew take while in EOP-01, “Standard Post Trip Actions”?
A. Trip one RCP in each loop.
B. Stop the running Oharging pumps.
C. Close PORV block valves.
D. Reset AND energize Pressurizer heaters.
A. Trip one RCP in each loop.
Unit 1 is at 100% power. The IA Component Cooling water (CCW) pump is to be removed from
service. The 1C CCW is to be aligned to replace the 1A COW pump.
Which ONE of the following states the MINIMUM electrical lineup required to meet the Technical
Specification requirements for the 1C CCW pump?
A. ONLY the lAB 4.16 KV bus aligned to the 1A3 4.16KV bus.
B. The lAB 4.16 KV bus aligned to the 1A3 4.16KV bus and the lAB 480V bus aligned to the 1A2 480V bus.
C. The lAB 4.16 KV bus aligned to the 1A3 4.16KV bus, lAB 480V bus aligned to the 1A2 480V bus and the lAB DC bus aligned to the 1A DC bus.
D. lAB 4.16 KV bus aligned to the 1A3 4.16KV bus, lAB 480V bus aligned to the 1A2 480V bus, lAB DC bus aligned to the 1A DC bus. IA Emergency Diesel Generator operable.
C. The lAB 4.16 KV bus aligned to the 1A3 4.16KV bus, lAB 480V bus aligned to the 1A2
480V bus and the lAB DC bus aligned to the 1A DC bus.
Unit I is operating at 50% power. The Pressurizer was placed on recirculation lAW 1-GOP-101, ‘Reactor Operating Guidelines During Steady State and Scheduled Load Changes’.
PlC-i bOX is selected for Pressure control. PT-i iOOX fails HIGH.
Assuming NO Operator action, which ONE of the following states the response of the
Proportional and Backup heaters?
Proportional heaters are:
A. at MINIMUM output. Backup heaters are de-energized.
B. de-energized. Backup heaters are de-energized.
C. at MINIMUM output. Backup heaters stay at the position prior to the failure.
D. de-energized. Backup heaters stay at the position prior to the failure.
C. at MINIMUM output. Backup heaters stay at the position prior to the failure.
Given the following indications on Unit I during an up power.
* Channel ‘D’ Variable High Power (VHP) reset pushbutton has just been depressed.
* Channel ‘D’ tkT Power indicate 57%
* Channel ‘D’ Nuclear Power indicates 55%
Assuming no Operator actions, which ONE of the following states the power level at which Channel ‘D’ will trip?
A. 66.61%
B. 64.61%
C. 61%
D. 59%
A. 66.61%
Unit I is performing a startup with the following:
* Reactor power is 10%
* Turbine is latched
* SBCS is in service
* RPS Channel ‘A’ Startup rate has failed high and is yet to be bypassed.
* Both SC pressures are 900 psia
Which ONE of the following will result in the crew entering 1-EOP-01, ‘Standard Post Trip Actions’?
A. Startup rate spikes to 1.6 DPM on the ‘B’ channel.
B. DEH pump trips and the backup will not start.
C. HCV-08-IA, ‘A’ MISV fails closed. ‘A’ SC pressure increases to 950 psia.
D. MB Instrument bus becomes de-energized.
D. MB Instrument bus becomes de-energized.
Unit I is experiencing a Loss of Coolant Accident (LOCA) and has entered 1-EOP-03, ‘LOCA’ with the following conditions:
* Pressurizer pressure is 1580 psia and lowering
* Containment pressure is 5.5 psig and rising
* Containment radiation is 8 RIhr and rising
* ONLY SIAS has actuated
Which ONE of the following states response of the Engineered Safety Feature Actuation System (ESFAS) and the expected Operator actions lAW 1-EOP-03, ‘LOCA’?
A. The ESFAS system is responding as expected. Verify proper operation of pumps and valves.
B. The ESFAS system is responding as expected. Manually actuate CIAS AND CSAS in anticipation of imminent automatic actuation.
C. CIAS should have actuated automatically. Manually actuate CIAS.
D. CIAS and CSAS should have actuated automatically. Manually actuate CIAS and CSAS.
C. CIAS should have actuated automatically. Manually actuate CIAS.
Unit I is in 1-EOP-03, ‘LOCA’, with the following:
* Pressurizer pressure is 980 psia
* 1A HPSI did not start and cannot be started
* IA and 1 B LPSI pumps are operating
* All Charging pumps are operating
Which ONE of the following states the expected Safety Injection flow?
References provided
A. 530 gpm
B. 400 gpm
C. 330 gpm
D. 220 gpm
D. 220 gpm
Unit 2 has experienced a LOCA. RCS pressure is 1580 psia and the crew has entered 2-EOP-03, ‘LOCA’.
On the trip, feeder breakers to MCC 2B9 tripped.
Which ONE of the following states the RUNNING Containment Fan Coolers?
A. C and D Containment Fan Coolers.
B. A and C Containment Fan Coolers.
C. A and B Containment Fan Coolers.
D. B and D Containment Fan Coolers.
C. A and B Containment Fan Coolers.