EO 1 Block 3 Aux Feedwater Flashcards
Which ONE of the following is a purpose of the Auxiliary Feedwater system?
A. Provide feedwater to BOTH steam generators during plant startups.
B. Promote natural circulation in the RCS during a large break LOCA.
C. Remove decay heat via the Steam Generators when in Mode 5.
D. Provide feedwater to BOTH steam generators on a loss of off site AC power.
D
The following plant conditions exist:
MU/HPI cooling is in progress due to a loss of all feedwater.
Which one of the following methods should be used to restore feedwater to the steam generators?
A. MDFP in the Main Feedwater mode at less than 800 gpm
B. MDFP in the Auxiliary Feedwater mode with 1200 gpm to the SGs
C. Main Feed Pump at 1.0 mpph
D. Auxiliary Feed Pump at less than 225 gpm
A
The Auxiliary Feed Water Pumps can take suction from EITHER the (approved sources):
A. Condensate Storage Tanks or the Dearators
B. Condensate Storage Tanks or the Service Water system.
C. Borated Water Storage Tanks or the Service Water System
D. Borated Water Storage Tanks or the Dearators
B
What system provides an AUTOMATIC backup source of water to the Auxiliary Feed Pumps?
A. Fire Water System
B. Service Water System
C. Deaerator Storage Tanks
D. Condensate Storage Tank
B
Which one of the following identifies where the Motor Driven Feed Pump taps into Auxiliary Feedwater Train 1?
A. Between AF 608 and the Containment penetration.
B. Between the AFW FLOW ELEMENT AND AF 608.
C. Between AF 3870 and THE AFW FLOW ELEMENT.
D. Between the Auxiliary Feedwater Pump Target Rock valve and AF 3870.
C
Which ONE of the following describes the supply source(s) for the Auxiliary Feedwater System?
A. Condensate pumps provide net positive suction head for the Auxiliary Feedwater pumps.
B. Suction for Auxiliary Feedwater pumps shifts to the Service Water System AUTOMATICALLY
on LOW Condensate Storage Tank level alarm.
C. Condensate Storage Tank suction valves (FW-786/790) to Auxiliary Feedwater pumps
AUTOMATICALLY OPEN when an Auxiliary Feedwater pump starts.
D. The Condensate Storage Tanks reserve a MINIMUM of 250,000 gallons for Auxiliary
Feedwater usage.
D
Which ONE of the following is NOT correct regarding the Auxiliary Feedwater System flowpath?
A. Check valves are the ONLY isolation between the CSTs and the OTSGs with AFW in its
NORMAL lineup.
B. MS Line 2 to AFW 1 Isolation Valve (MS 106) and MS Line 1 to AFW 21solation Valve (MS
107 A) are normally OPEN in MODES 1, 2 and 3.
C. AFW 1 to SG 1 Stop Valve (AF 3870) and AFW 2 to SG 2 Stop Valve (AF 3872) are normally
OPEN in MODES 1, 2, 3.
D. Closing AFW 1 SG Level Control Valve (AF 6452) OR AFW 2 SG Level Control Valve (AF
6451) isolates ALL AFW flow from that AFW pump to the OTSGs.
D
The following plant conditions exist:
A loss of off-site power has occurred
Steam Generator pressures are both 900 psig
RCS Pressure is 1500 psig and lowering slowly
Select the Auxiliary Feedwater response and Once Through Steam Generator level response.
A. BOTH Auxiliary Feedwater Pumps start and maintain Steam Generator levels at 49 inches
B. BOTH Auxiliary Feedwater Pumps start and maintain Steam Generator levels at 124 inches
C. ONE Auxiliary Feedwater Pump starts and maintains Steam Generator levels at 55 inches
D. ONE Auxiliary Feedwater Pump starts and maintains Steam Generator levels at 130 inches
B
Which ONE of the following statements is correct concerning the Auxiliary Feedwater System?
A. The Auxiliary Feedwater Pump Turbines receive steam from the 235# Auxiliary Steam Header
when aligned for normal 100% power by Operations
B. The Auxiliary Feedwater Steam Generator nozzles are located high in the Steam Generator to
promote natural circulation.
C. The Auxiliary Feedwater Pump Turbine exhaust is routed to containment in the event of a
steam generator tube rupture.
D. Steam Generator level is NORMALLY maintained by controlling Auxiliary Feedwater Pump
Turbine speed.
B
The following plant conditions exist:
* A reactor trip from 100% has occurred due to the trip of all four RCPs.
* Natural circulation cooldown using AFW is in progress.
* The decision is made to feed the SGs with MFW so that AFW can be secured.
Which one of the choices below accurately describes the initial effect of the AFW to MFW transition
on core Differential Temperature (T-hot minus T-cold)? Note: Assume SG levels do not change.
A. Core Differential Temperature will remain the same because changing to MFW has no effect
on natural circulation flow.
B. Core Differential Temperature will INCREASE because changing to MFW INCREASES
natural circulation flow.
C. Core Differential Temperature will DECREASE because changing to MFW DECREASES
natural circulation flow.
D. Core Differential Temperature will INCREASE because changing to MFW DECREASES
natural circulation flow.
D
The following plant conditions exist:
* The plant is operating at 75% power.
* All equipment is operating normally.
The following event occurs:
* An SFRCS actuation occurred due to SG 2 low steam pressure.
* LT SP 983, SG 1 Startup Level Transmitter, slowly drifts high.
* RCS pressure is 1950 psig and steady.
* RCS temperature is 540 °F and steady.
* Containment pressure is 14.7 psia and steady.
Assuming NO operator action, SG 1 will _____ _
A. boil dry
B. be maintained at 49 inches
C. be maintained at 55 inches
D. be maintained at 124 inches
C
Sequence of events:
* Reactor power is 100%
* ICS in full automatic
The following events occur:
* Turbine trip causes a reactor trip
* RCPs 1-1 and 1-2 trip.
Based on these conditions, identify the ONE statement below that describes automatic response of
the (1) Main Feedwater system and (2) AFW system.
A. (1) Main Feedwater controls both SG levels at 40 inches.
(2) AFW remains secured.
B. (1) Main Feedwater controls SG #1 level at 40 inches and SG #2 level at 49 inches.
(2) AFW remains secured.
C. (1) Main Feedwater controls SG #2 at 40 inches.
(2) AFW actuates and controls SG #1 at 49 inches.
D. (1) Main Feedwater remains available to control both SG levels at 40 inches.
(2) AFW actuates, and controls both SG levels at 49 inches.
A
The plant is operating at 100% power.
The following indications are observed:
* AFP 1 TRBL annunciator.
* MS106, MS Line 1 to AFPT 1 Isolation Valve, indicates closed.
* MS106A, MS Line 2 to AFPT 1 Isolation Valve, indicate closed.
* There are no indications of a steam leak.
Procedure DB-OP-02010, Feedwater Alarm Panel 10, NOTE 3.2.4.a., says to open MS106A slowly
using the manual handwheel.
The reason for this NOTE is to ______ _
A. reset the AFP 1 LOW STEAM PRESSURE TRIP
B. lower the differential pressure across the MS106A while opening
C. prevent water hammer
D. to ensure MS 726, MS Line 1 to AFPT 1 Check Valve, seats
C
Which ONE of the following describes the Service Water system interlock for supplying a BACKUP
suction source to the Auxiliary Feedwater Pumps?
A. Service Water AUTOMATICALLY aligns to Auxiliary Feedwater if Auxiliary Feedwater Pump
suction pressure is below 2 psig for 10 seconds.
B. Service Water AUTOMATICALLY aligns to Auxiliary Feedwater if Auxiliary Feedwater Pump
suction pressure is below 10 psig for 5 seconds.
C. Service Water may be MANUALLY aligned to Auxiliary Feedwater when Auxiliary Feedwater
Pump suction pressure has been below 2 psig for 10 seconds.
D. Service Water may be MANUALLY aligned to Auxiliary Feedwater when Auxiliary Feedwater
Pump suction pressure has been below 10 psig for 5 seconds.
A
While at 50% power, Main Steam Line 1 ruptures in Containment.
The following conditions are observed:
* Steam Generator 1 pressure -12 psig (stable)
* Containment pressure -26 psia (stable)
* Reactor Coolant System temperature -511 °F (decreasing)
* Reactor Coolant System pressure -1600 psig (decreasing)
Which one of the following describes the response of the Auxiliary Feedwater System?
A. BOTH Auxiliary Feedwater Pumps will be aligned to Steam Generator 2 and level will be
controlled at 55 inches.
B. EACH Auxiliary Feedwater Pump will be aligned to its own Steam Generator and level will be
controlled at 49 inches.
C. BOTH Auxiliary Feedwater Pumps will be aligned to Steam Generator 2 and level will be
controlled at 130 inches.
D. EACH Auxiliary Feedwater Pump will be aligned to its own Steam Generator and level will be
controlled at 124 inches.
C
Which of the following valves receives a Steam Feed Rupture Control System signal?
1 . MS 107 A- MS Line #1 to AFPT #2
2 . ICS 38D-Trip throttle Valve (TTV) for #2 AFPT
3. MS 5889B-#2 AFPT Steam Admission Valve
4 . AF 6451-#2 AFP Level Control Valve
5 . AF 3872-#2 AFP to SG#2 Stop Valve
6. AF 599 -AFW to SG#2 Discharge Isolation Valve
A. 1, 3, 5
B. 1, 4, 5
C. 2,3,5
D. 2,4,6
A
Plant conditions are as follows:
* An Steam Feed Rupture Control System Isolation TRIP has occurred following a loss of
BOTH Main Feedwater pumps.
* The operator has depressed the LOW level select pushbuttons for the Auxiliary Feedwater
System located on the Safety Features Actuation System panel.
Which ONE of the following describes the Steam Generator levels maintained by Auxiliary
Feedwater if a Safety Features Actuation System Level 2 actuation subsequently occurs?
A. Steam Generator #1 at 49 inches, Steam Generator #2 at 49 inches
B. Steam Generator #1 at 49 inches, Steam Generator #2 at 55 inches
C. Steam Generator #1 at 124 inches, Steam Generator #2 at 124 inches
D. Steam Generator #1 at 124 inches, Steam Generator #2 at 130 inches
C
The following plant conditions exist:
* Emergency Diesel Generator 1 is inoperable due to routine maintenance.
* While operating at 100% power, all Off-Site power is lost.
* Emergency Diesel Generator 2 fails to energize D1 Bus.
* Reactor Coolant System pressure is 1735 psig and Reactor Coolant System Temperature is
555 °F. Steam Generator levels will be controlled at ____ inches on the Startup Range.
A. 55
B. 49
C. 124
D. 40
B
The following plant condition exist:
* Safety Features Actuation System has actuated on low Reactor Coolant System pressure.
* All Reactor Coolant Pumps have been tripped.
* No other control panel manipulations have been made.
The Steam Generator 2 Auxiliary Feedwater HIGH/LOW level control select switch on the Safety
Features Actuation System panel is BLOCKED and the LOW pushbutton is pressed.
Which one of the following describes the SG level control setpoints under these conditions?
Steam Generator 1 controls at __ inches; Steam Generator 2 controls at __ inches.
A. 40; 40
B. 49; 49
C. 124; 49
D. 124; 124
C
The following plant conditions exist:
* Seismic event
* Loss of offsite power
* The condensate storage tanks common outlet line is RUPTURED
* Service Water Pump 1 FAILED to start
Which ONE of the following represents the Auxiliary Feedwater System status after 15 minutes?
(NO OPERATOR ACTIONS ARE TAKEN.)
Auxiliary Feedwater Pump 1 is ____ . Auxiliary Feedwater Pump 2 is ___ _
A. running; running
B. stopped; running
C. running; stopped
D. stopped; stopped
B
While at 50% power, Main Steam Line 1 ruptures in Containment.
The following conditions are observed:
* Steam Generator 1 pressure - 11 psig
* Containment pressure - 26 psia
* Reactor Coolant System Temperature - 511 “F
* Reactor Coolant System Pressure - 1580 psig
Which of the following describes the response of the Auxiliary Feedwater System? (Assume all
safety systems function as designed.)
A. Both Auxiliary Feedwater Pumps will be aligned to Steam Generator 2, and Auxiliary
Feedwater will control level at 55”.
B. Each Auxiliary Feedwater Pump will be aligned to its own Steam Generator, and Auxiliary
Feedwater will control level at 49”.
C. Both Auxiliary Feedwater Pumps will be aligned to Steam Generator 2, and Auxiliary
Feedwater will control level at 130”.
D. Each Auxiliary Feedwater Pump will be aligned to its own Steam Generator, and Auxiliary
Feedwater will control level at 124”
C
Plant conditions are as follows:
* An Steam Feed Rupture Control System Isolation TRIP has occurred following a loss of
BOTH Main Feedwater pumps
* The operator has depressed the LOW level select pushbuttons for the AUxiliary Feedwater
System located on the Safety Features Actuation System panel
Which ONE of the following describes the Steam Generator levels maintained by Auxiliary
Feedwater System if a Safety Features Actuation System Level 2 actuation subsequently occurs?
A. Steam Generator #1 at 49 inches, Steam Generator #2 at 49 inches
B. Steam Generator #1 at 49 inches, Steam Generator #2 at 55 inches
C. Steam Generator #1 at 124 inches, Steam Generator #2 at 124 inches
D. Steam Generator #1 at 124 inches, Steam Generator #2 at 130 inches
C
Steam Generator 1 pressure is less than the Steam Feed Rupture Control System LOW PRESSURE trip setpoint.
From the following list, select the response that describes the effect on Steam Feed Rupture Control System components if Steam Generator 2 pressure also drops below the Steam Feed Rupture Control System low pressure trip setpoint without being blocked.
A. Steam Feed Rupture Control System will isolate Steam Generator 2, realigning Auxiliary
Feedwater to feed Steam Generator 1 .
B. Steam Feed Rupture Control System will isolate Auxiliary Feedwater flow to Steam Generator
2, but will NOT realign to feed Steam Generator 1.
C. Steam Feed Rupture Control System will maintain the current Auxiliary Feedwater System
alignment.
D. Steam Feed Rupture Control System will realign Auxiliary Feedwater 1 to Steam Generator 1
and Auxiliary Feedwater 2 to Steam Generator 2.
C
The following plant conditions exist:
* All Reactor Coolant Pumps are tripped.
* Safety Features Actuation System Actuation Channel 2 has failed to actuate.
* A small break Loss of Coolant Accident has caused a loss of adequate subcooling margin.
Determine what operator action is required to allow Steam Generator 2 to be automatically
controlled at the proper setpoint.
A. Manually select the high setpoint using HIS 6454, AFW Train 2 Hi/Lo Level Setpoint.
B. Depress the SEL button on UC 6451, AFW 2 Level Control Valve until Over Ride Setpoint is
displayed.
C. Manually raise Steam Generator level to set point then place UC 6451, AFW 2 Level Control
Valve, into automatic
D. Depress HIS 6403 and HIS 6404 to initiate an Steam Feed Rupture Control System Initiation
and Isolation trip.
A
The plant is operating at 100% power.
* A total loss of ALL on-site and off-site AC power occurs.
If no operator action is taken, Auxiliary Feedwater Pump 2 will receive steam from Steam
Generator __ and supply feedwater to Steam Generator __ .
A. 1. 1
B. 2; 1
C. 1; 2
D. 2; 2
C
The plant was operating at 100% power.
A rupture occurred on Main Feedwater Line 2 downstream of SP6A, Main Feedwater Control Valve
and upstream of FW 156, FW Loop 2 Check Valve. Auxiliary Feedwater Pump #1 feeds Steam Generator # __ . Auxiliary Feedwater Pump #2 feeds Steam Generator# __
A. 1; 2
B. 2; 2
C. 1;
D.
A
The following plant conditions exist:
1 . Reactor power was steady state at 7 5%.
2. Both main feedwater pumps tripped.
Which ONE of the following describes the auxiliary feedwater response and Steam Generator level
response?
A. Both auxiliary feedwater pumps start and maintain Steam Generator levels at 49 inches.
B. Both auxiliary feedwater pumps start and maintain Steam Generator levels at 124 inches.
C. One auxiliary feedwater pump starts and maintains Steam Generator levels at 55 inches.
D. One auxiliary feedwater pump starts and maintains Steam Generator levels at 130 inches.
A
The following plant conditions exist:
1. An Safety Features Actuation System Level 2 actuation has occurred in conjunction with an
Steam Feed Rupture Control System trip.
2. Steam Generator 1 is being fed by Auxiliary Pump 2.
3. No other actions were taken.
Steam Generator 1 level will be maintained at which ONE of the following levels?
A. 49inches
8. 55inches
C. 124inches
D. 130inches
D
Which ONE of the following correctly describes the response of the Auxiliary Feedwater System to
an Steam Feed Rupture Control System actuation? (Assume no SFAS, unless stated.)
A. Low Main Steam pressure signal on Steam Generator 2 will result in Auxiliary Feedwater
Pump 2 turbine maintaining Steam Generator 1 at 55 inches while Auxiliary Feedwater Pump
Turbine 1 level control valve (AF 6451) will be closed.
8. Low Steam Generator level signal on Steam Generator 1 will result in Auxiliary Feedwater
Pump 1 and Auxiliary Feedwater Pump 2 turbines both feeding Steam Generator 1 to maintain
its level at 49 inches.
C. Safety Features Actuation System Level 2 actuation signal with a valid high Steam Generator
level Steam Feed Rupture Control System trip signal will result in each Auxiliary Feedwater
Pump turbine feeding its own Steam Generator, maintaining level at 130 inches.
D. With the Auxiliary Feedwater Pump turbine discharge valves cross-connected, a Steam Feed
Rupture Control System signal on low Steam Generator level on Steam Generator 1 will result
in Auxiliary Feedwater Pump 2 turbine controlling Steam Generator 2 level at 55 inches if AF
3870 (AFP 1 to SG 1) comes off its open seat.
A
If a Steam Feed Rupture Control System actuation was to occur due to loss of both main feed
pumps, at what level would the Auxiliary Feedwater System control the Steam Generators?
A. Steam Generator - 49 inches; Steam Generator - 55 inches.
B. Steam Generator 1 - 55 inches; Steam Generator 2 - 49 inches.
C. Steam Generator 1 - 49 inches; Steam Generator - 49 inches.
D. Steam Generator 1 - 124 inches; Steam Generator 2 - 124 inches.
C