Week 4-5 Flashcards by Justin Selepec

The plant is at 100% power.
A gradual loss of instrument air occurs.

As instrument air pressure decreases, which of the following events occur first?

A. Condensate pump miniflow valves fail open.
B. Main feedwater pump speed decreases.
C. Feedwater economizer reg valves fail in current position.
D. Heater drain tank pump discharge valve fails open.

A. Condensate pump miniflow valves fail open.

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Unit 1 is operating at rated power.
A CREFAS is manually initiated with both trains of Control Room Essential AFUs running.
Window 7B01A “INST AIR SYSTEM TROUBLE” alarms.
Instrument Air header pressure is noticed to be lowering.

If the air problem continues to degrade, the Control Room Essential AFUs….

A. will trip.
B. will lose cooling water.
C. ventilation lineup will not change.
D. outside air dampers will fail open.

C. ventilation lineup will not change.

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Following a complete Loss of All Instrument Air (without IA system backup Nitrogen), which one of the following conditions describes the final status of the Steam Generator #1 Feedwater Economizer Isolation Valve (SGA-UV-174) with NO operator action?

A. Fails fully OPEN.
B. Fails fully SHUT.
C. Fails AS-IS.
D. Modulates on FWCS demand.

C. Fails AS-IS.

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A Loss of Instrument Air has occurred.
Nitrogen is supplying the Instrument Air Header.

In order to reduce the possibility of Nitrogen buildup in the Auxiliary Building, which of the following actions are taken?

A. Isolate Instrument Air to the Auxiliary Building.
B. Open all Auxiliary and Fuel Building Rollup Doors.
C. Start a Fuel Building Essential Exhaust Fan taking suction on the Fuel Building.
D. Start a Fuel Building Essential Exhaust Fan taking a suction on the Auxiliary Building.

D. Start a Fuel Building Essential Exhaust Fan taking a suction on the Auxiliary Building.

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Following a complete Loss of All Instrument Air (No Nitrogen backup), which one of the following conditions describes the final status of a Main Steam Isolation Valve with NO operator action?

A. Fails fully OPEN.
B. Fails fully CLOSED.
C. Fails AS-IS, and can only be slow closed.
D. Fails AS-IS, but can be fast closed.

D. Fails AS-IS, but can be fast closed.

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At less than 80 psig instrument air header pressure, the Heater Drain Pump discharge valves will:

A. Fail open
B. Fail closed
C. Fail as-is
D. Remain unaffected, since they are on nitrogen backup

B. Fail closed

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Instrument Air isolation valve IAA-UV-2 has inadvertently closed and will not reopen.
Service air backup is unavailable for containment.

Which one of the following describes the expected response of the Reactor Coolant Pump Seal Injection Supply Flow Control Valves (CHE-FV241, 242, 243 and 244) as containment IA header pressure drops below 26 psig?

A. Fail locked.
B. Fail fully closed.
C. Fail fully open.
D. No response, they are motor operated.

C. Fail fully open.

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In the installed Ingersoll-Rand Instrument Air Compressors, which of the following provides the motive force for the oil to circulate through system?

A. Separator Tank Pressure.
B. A DC driven oil pump.
C. An AC driven oil pump.
D. The delta P across the Coolant Filter.

A. Separator Tank Pressure.

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The reactor is at 100% power.
All instrument air compressors are running.
IA header pressure is 88 psig and gradually decreasing.

Which one of the following states when the reactor should be tripped and the Emergency Operation procedures implemented according to 40AO-9ZZ06,”LOSS OF INSTRUMENT AIR”?

A. If instrument air pressure decreases to 65 psig and the Front Standard Turbine Trip Air Relay Dump Valve actuates its low pressure switches.
B. If instrument air pressure can not be maintained above 73.5 psig.
C. If instrument air pressure cannot be maintained above 85 psig with the Nitrogen Backup Valve open.
D. If the CRS determines that a trip is needed due to reduced instrument air pressure.

D. If the CRS determines that a trip is needed due to reduced instrument air pressure.

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Instrument air header pressure is 65 psig.
The reactor has been manually tripped from 100% power due to plant instability.

Based on these conditions, what means of ADV operations are available?

A. normal for one closure only.
B. only local operation in the MSSS.
C. normal operation for > 13 hours.
D. only at the remote shutdown panel.

C. normal operation for > 13 hours.

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A gradual loss of Instrument Air is occurring.
The area operator reports a large differential pressure across the in service Instrument Air Dryer.

Which one of the following actions should be taken to assist in correcting this problem?

A. Shift Air Dryers
B. Bypass Air Dryers
C. Shutdown Air Dryers
D. Vent the Air Dryers

A. Shift Air Dryers

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The Reactor was tripped due to a degrading condenser vacuum.
Immediately after the trip, the Secondary Operator became involved with the B01 report. When this operator returned to B06, condenser backpressure was 9.0” HgA (highest shell).
Steam Generator levels are both 65% WR.

Assuming no other operator performed actions on B06, in what condition can this operator expect to find the secondary plant?

A. No feed with SBCS valves 1001 & 1004 maintaining SG pressure.
B. Main Feed Pumps feeding in RTO with SBCS valves 1007 & 1008 maintaining SG pressure.
C. Main Feed Pumps feeding in RTO with MSSVs maintaining SG pressure.
D. No feed with SBCS valves 1007 & 1008 maintaining SG pressure.

B. Main Feed Pumps feeding in RTO with SBCS valves 1007 & 1008 maintaining SG pressure.

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Describe how the SBCS Condenser Interlock is reset.

A. Depress the SBCS Condenser Interlock Reset button at the RRS test panel.
B. Place the Emergency Off Reset Switch to the EMERGENCY OFF position then to the RESET position.
C. Place the Emergency Off Reset Switch to the RESET position.
D. Place the SBCS Mater in MANUAL then back to AUTO

C. Place the Emergency Off Reset Switch to the RESET position.

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A down-power is in progress in accordance with 40AO-9ZZ07 due to an air inleakage problem on the Main Condenser.
The Main Generator is presently operating at 400 Mwe.
Backpressure is noted to increase to 5.2” HgA on the ‘C’ shell.

Based on these conditions, the operating crew:

A. must reduce backpressure to less than 4” HgA within one hour.
B. can continue operating indefinitely.
C. must immediately trip the Main Turbine and take actions iaw 40AO-9ZZ08.
D. must immediately trip the Reactor and perform SPTA’s.

D. must immediately trip the Reactor and perform SPTA’s.

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Unit 1 is operating at rated power when backpressure in the Main Condenser starts to rise.
Regulating Group 5 is at 135 inches.
Turbine load is being shifted to SBCS valve 1007 in an effort to stabilize backpressure.
CEDMCS is inadvertently left in AUTO SEQUENTIAL.
Assuming Steam Demand remains constant.

The Operating Crew should expect CEAs to…

A. start stepping in.
B. start stepping out.
C. remain in their present position due to AMI.
D. remain in their present position due to AWP.

A. start stepping in.

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• The unit is at rated power.
•All equipment is aligned normally/ in automatic.
•No evolutions are in progress.
•Condenser back pressure degrades rapidly from:
2.2, to (A) 8.0, (B) 2.3, (B) 8.0, (C) 2.5, (C) 8.3inches HGA.

With no operator action, what would the unit status be at this point in the event?

A. Main Turbine On Line, MFWPs Running, SBCS Normal/Auto.
B. Main Turbine On Line, MFWPs Tripped, SBCS Condenser Interlock in.
C. Main Turbine Tripped, MFWPs Tripped, SBCS Normal/Auto.
D. Main Turbine Tripped, MFWPs Running, SBCS Condenser Interlock in.

D. Main Turbine Tripped, MFWPs Running, SBCS Condenser Interlock in.

Which one of the following will a Non-Licensed Operator be expected to check after 40AO-9ZZ07, Loss of Condenser Vacuum, has been entered?

A. Main Feed Pump operation
B. SBCV 1007 & 1008 operation
C. Air Removal Pump operation
D. Seal Oil Vacuum Tank level

C. Air Removal Pump operation

The plant is operating at 100% power.
A large load reject occurs due to degraded vacuum in the condenser.
Hotwell level is 35 inches and holding steady.

Which one of the following actions will need to be performed?

A. Trip the Main Turbine.
B. Trip the Reactor.
C. Open at least one Main Feed Pump Mini-flow Valve.
D. Open the Hotwell Manual Makeup Isolation Valve(s).

D. Open the Hotwell Manual Makeup Isolation Valve(s).

The unit is in Mode 1.
The upper two sensors in the RVLMS Train ‘B’ have failed and are not functioning.
All other RVLMS sensors are functioning normally.

Based on these conditions, Technical Specification LCO 3.3.10 is…

A. not met, enter Condition A, Action A.1.
B. not met, enter Condition C, Action C.1.
C. met.
D. not applicable.

C. met.

You are investigating a trip of FBEVAS at the BOP ESFAS cabinets. The following lights are illuminated on the Train “A” FBEVAS module:
•ACTUATE
•MAN
•RST

Based upon these indication, which one of the following has caused this trip?

A. Manual actuation from B05.
B. Cross train trip signal
C. Manual actuation from BOP ESFAS Cabinet.
D. High radiation signal from RU-31 (Fuel Pool Monitor).

A. Manual actuation from B05.

Unit at 50% power.
PNC-D27, 120 VAC distribution panel, loses power.
All systems operate as designed.

WHICH ONE of the following describes the expected response of the Reactor Protection and BOP-ESFAS Systems?

A. Reactor trip and all ESFAS and BOP-ESFAS actuations.
B. Initiation relays deenergize on PPS Channel’s A & C and no BOP ESFAS actuations.
C. CREFAS, CPIAS, and FBEVAS Train actuations and initiation relays deenergize on Channels A and C.
D. CREFAS, CPIAS, and FBEVAS Train actuations and initiation relays deenergize on Channels C and D.

B. Initiation relays deenergize on PPS Channel’s A & C and no BOP ESFAS actuations.

Unit 1 is operating at 80% power.
Engineering informs the operating crew that there is a problem with Reactor Trip Circuit breakers (RTCB) #1 and #3.
This problem will impact their ability to open.

Based on these conditions, the operating crew is required to open…

A. RTCBs #1 and #3 within 1 hour.
B. either RTCBs #1 or #3 immediately.
C. RTCBs #1 and #3 immediately.
D. either RTCBs #1 or #3 within 1 hour.

C. RTCBs #1 and #3 immediately.

A plant cooldown is in progress.
RCS temperature is currently 362°F.
The secondary operator reports RCS cooldown rate for the last hour has been 120°F.

The operator is required to restore the cooldown rate to within limits in:

A. immediately.
B. 15 minutes.
C. 30 minutes.
D. 60 minutes.

C. 30 minutes.

Unit 1 is at 60% power
VOPT Channel A fails due to a bad input.
The operator carries out actions in accordance with Technical Specifications and I & C is notified.
Subsequently, 1 hour and 10 minutes later, the Shift Manager determines due to troubleshooting the channel that it was never bypassed or trip.

The Crew should …

A. Enter 3.0.3 and commence a plant shutdown
B. Invoke 25% completion time extension time and place VOPT in trip or bypass
C. Invoke a completion time extension of 1 hour and place channel in trip or bypass
D. Enter LCO 3.3.1 condition E and be in Mode 3 in 6 hours.

D. Enter LCO 3.3.1 condition E and be in Mode 3 in 6 hours

* The plant is at 100%. * Pressurizer pressure channel "A" (narrow range) fails HIGH. Within 1 hour the operator must bypass or trip Channel "A"... ``` A. Variable Overpower (VOPT) Local Power Density - HIGH (RPS) DNBR - LOW (RPS) B. Variable Overpower (VOPT) Local Power Density - HIGH (RPS) RCS Flow - LOW C. Pressurizer Pressure - HIGH (RPS) Local Power Density - HIGH (RPS) DNBR - LOW (RPS) D. Pressurizer Pressure - LOW (RPS) Local Power Density - HIGH (RPS) DNBR - LOW (RPS ```

C. Pressurizer Pressure - HIGH (RPS) Local Power Density - HIGH (RPS) DNBR - LOW (RPS)

* The plant is at 100% power. * Steam Generator Level #1 (wide range) Channel "A" fails LOW. Within 1 hour, the operator must bypass or trip Channel "A": ``` A. Steam Generator #1 Level Low (RPS) Steam Generator #1 Level Low (ESF) Steam Generator #2 Level Low (RPS) B. Steam Generator #1 Level Low (RPS) Steam Generator #1 Level Low (ESF) Steam Generator #2 Level Low (ESF) C. Steam Generator #1 Level Low (RPS) Steam Generator #1 Pressure Low (ESF) Steam Generator #2 Level Low (RPS) D. Steam Generator #1 Level Low (RPS) Steam Generator #2 Pressure Low (ESF) Steam Generator #2 Level Low (RPS) ```

B. Steam Generator #1 Level Low (RPS) Steam Generator #1 Level Low (ESF) Steam Generator #2 Level Low (ESF)

* The reactor is tripped following a Steam Generator Tube Rupture. * RCS pressure is 895 psia. * RCS subcooling is 55°F. * Steam Generator #1 pressure is 890 psia. * RU-4 in high alarm. * Steam generator #1 is isolated. * Steam generator #1 level is 78% NR and rising slowly. * Steam generator #2 level is 50% NR and steady. WHICH ONE of the following is the preferred method to control level in the isolated steam generator? A. Steam the #1 steam generator to atmosphere via the ADVs. B. Line-up high rate blowdown to the condenser from #1 steam generator. C. Bypass the MSIV and steam the #1 steam generator to the condenser. D. Lower RCS pressure below #1 steam generator pressure and allow backflow to the RCS.

D. Lower RCS pressure below #1 steam generator pressure and allow backflow to the RCS.

* A SGTR has occurred on SG 2. * RCS pressure is 1600 psia. * SIAS has actuated, providing adequate flow. * Thot is 565°F. * Tcold is 562°F. * RCPs in operation * SBCS is controlling SG pressure at 1150 psia. * Level is rising in SG 2. * The CRS directs depressurizing the RCS. Based on current conditions and applying the SGTR strategy, determine the RCS pressure to use as the initial target. A. 1450 psia B. 1135 psia C. 1200 psia D. 1300 psia

A. 1450 psia

Which one of the following is the basis for waiting until Hot leg temperature is less than 540°F when isolating a S/G with a SGTR? A. Affected Steam Generator pressure is low enough to prevent lifting of the Steam Generator safety valves. B. Differential pressure between the RCS and the affected Steam Generator can be minimized while still maintaining subcooling. C. Affected Steam Generator pressure is less than the shutoff head of the High Pressure Safety Injection pumps in case the tube leak propagates. D. Steam Generator pressure is sufficiently high to minimize the possible RCS boron dilution to an acceptable level during the RCS cooldown.

A. Affected Steam Generator pressure is low enough to prevent lifting of the Steam Generator safety valves.

SG # 1 has been isolated following a SGTR, and the following conditions exist: •1A and 2A RCPs are operating. •Th 490°F. •SG 1 level 65% NR and slowly trending up. •SG 1 pressure 950 psia and slowly trending up. •Pressurizer pressure 1200 psia. Per the SGTR ORP and the CE mitigation strategy, the RCS should be depressurized to between: A. 800 and 900 psia B. 900 and 1000 psia C. 1000 and 1100 psia D. 1100 and 1200 psia

B. 900 and 1000 psia | Note: within 50 of SG1

* Unit 1 experienced a SGTR from 100% power * CRS is implementing the SGTR ORP * RCS depressurization has been initiated Which one of the following is a potential impact of lowering RCS pressure below the existing pressure in the ruptured SG? A. Taking the RCS water solid. B. Excessive cooldown of the RCS. C. Causing a dilution of the RCS. D. Loss of SG heat removal capability.

C. Causing a dilution of the RCS.

Which one of the following would increase the probability of drawing a reactor vessel head bubble during a SGTR. (Assume all equipment functions as designed unless stipulated below.) A. Energizing pressurizer heaters. B. Loss of offsite power. C. Isolating the affected generator. D. Reducing the rate of RCS depressurization.

B. Loss of offsite power.

``` Following a SGTR 6 hours ago on SG #2, conditions are as follows: •RCS Thot is 325 degrees •RCS Pressure is 700 psia •SG #1 Pressure is 95 psia •SG #2 Pressure is 700 psia •RCPs 1A and 2A are running ``` What should be performed at this time? A. Secure RCPs 1A and 2A B. Place SDC into service C. Commence a cooldown of SG #2 D. Lower Pressurizer pressure to less than 400 psia

C. Commence a cooldown of SG #2

The SGTR ORP may be entered whenever indications of a SGTR are exhibited: A. from Mode 3 only if LTOPs are not in service . B. from Mode 4 only if LTOPs are in service. C. from Mode 5 only if LTOPs are in service. D. only immediately following completion of SPTAs.

A. from Mode 3 only if LTOPs are not in service .