Sro Drpi, Esfas, Esw, Pzr Level Ctrl, Sw, Sis Wk6

Front 1

Which one of the following describes the actual position of a rod whose indicated DRPI position is 100 steps with a Data 'A' failure present? A. 96-104 stepsB. 96-110 stepsC. 90-104 stepsD. 90-110 steps

Back 1

B

Front 2

During normal plant conditions with no equipment out-of-service or malfunctioning, DRPI indicates Control bank D at 204 steps. The actual position of Control Bank D Control Rod D4 according to DRPI is: A. Between 205 and 203 stepsB. Between 208 and 194 stepsC. Between 208 and 200 stepsD. Between 214 and 200 steps

Back 2

C

Front 3

Data cabinet A's power supply has just failed causing the "DATA A FAILURE" lights on the DRPI display bezel to illuminate. How will this affect the DRPI System? A. This will generate a "DPRI URGENT FAILURE" annunciatorB. The "NON-URGENT FAILURE" light will illuminate on the DPRI bezelC. The accuracy of the system will be diminished to +4/-10 stepsD. The accuracy of the system will be diminished to +10/-4 steps

Back 3

D

Front 4

In the DRPI System, HALF ACCURACY means that an error has developed in: A. one train, decreasing accuracy +/-8 stepsB. both trains, decreasing accuracy to +/- 8 stepsC. one train, decreasing accuracy to +/-10 stepsD. one train, decreasing accuracy to +10/-4 steps if the error is in Train A or +4/-10 steps if the error is in Train B

Back 4

D

Front 5

At 0800, while in Mode 1, the Moveable Incore Detector System is discovered to be inoperable.At 1300 on the same day, Rod H-8 on DRPI indicates a General Warning flashing light with Data "A" and Data "B" failure lights.If no repairs can be made, what action is required? A. Restore the rod to operable status in 72 hours.B. Reduce thermal power to < 75% within four hours.C. Restore the moveable Incore system within 24 hours.D. Reduce thermal power to < 50% within eight hours.

Back 5

D

Front 6

At 0800 on 10/10 an automatic control rod withdrawal resulted in one rod in Control Bank D to drop. The unit is at 100% RTP and the rod bottom light is lit on the Digital Rod Position Indication (DRPI) display. The rod cannot be restored to within alignment limits, so a Shutdown Margin (SDM) verification was completed at 0850.When is the next SDM verification required to be completed, (including any extensions permitted), without requiring entry into the LCO ACTION to proceed to Mode 3? A. 2300B. 2050C. 2400D. 2250

Back 6

B

Front 7

The unit is in Mode 1 at 100% RTP. - At 1000 a Digital Rod Position Indicator (DRPI) is found inoperable in Control Bank C. - At 1400 another Digital Control Rod Position Indicator (DRPI) is found inoperable in Control Bank D.- No control rod movement has occurred in the previous 12 hours.What are required TS ACTIONS? A. The position of the affected rods in both Control Banks must be verified using incore detectors by 1800.B. Both inoperable DRPIs must be restored to OPERABLE status by 1400 on the following day.C. Thermal Power must be less than or equal to 50% RTP by 2000.D. The position of the affected rod in Control Bank C must be verified by 1800 and in Control Bank D must be verified using incore detectors by 2200.

Back 7

D

Front 8

Which one of the following will cause a main control board "RPI or PR Tilt" alarm? A. One of the DRPI rod positions has a computer quality less than "good".B. A control bank overlap sequence error.C. There is a 12 step difference between any two control rod banks.D. A DRPI "General Warning" alarm exists.

Back 8

B

Front 9

The Bank Demand Position Indication system counts the pulses produced by the Rod Control System as it generates the orders to move a group.Which of the following correctly describes this operation? A. Each indication is driven by two solenoids, one for an up step, and one for a down step.B. Each indication is driven by four solenoids, two for an up step, one for a down step, and one for resetting the indication to zero.C. The indication is reset to zero during recovery of dropped rod in accordance with OFN SF-011.D. Each indicator is driven by three solenoids, one for an up step, one for a down step, and one for resetting the indication to zero.

Back 9

D

Front 10

The Rod Insertion Limit (RIL) monitor uses auctioneered high reactor coolant system loop __________ to calculate the rod height _______________ which all control rods must be maintained. A. DT; aboveB. Tavg; aboveC. DT; belowD. Tavg; below

Back 10

A

Front 11

The following events occur:* Reactor Power @ 90%* All control systems in automatic* Control bank D @ 215 steps* The rod position P-A converter has failed as is* The plant experiences a loss of a main feedwater pump* A turbine runback occurs and turbine load stabilizes at 600 MWeWhich ONE of the following describes the response of the ROD BANK LO-LO LIMIT annunciator? A. Does not annunciate throughout the transientB. Does not annunciate until rods are 10 steps above the insertion limitC. Does not annunciate until Control bank C begins to moveD. Does not annunciate until rods are at the insertion limit

Back 11

A

Front 12

One control rod indicates 10 steps farther out than its bank.What would confirm the actual misalignment of the rod versus an indication failure? A. A Quadrant Power Tilt Ratio (QPTR) of 1.03 for the core quadrant opposite the one containing the suspected rod. B. A Quadrant Power Tilt Ratio (QPTR) of 1.03 for the core quadrant containing the suspected rod.C. A more positive Axial Flux Difference (AFD) for the power range detector opposite the quadrant (180?) containing the suspected rod.D. A more negative Axial Flux Difference (AFD) for the power range detector in the immediate vicinity of the suspected rod.

Back 12

B

Front 13

When the plant is in Mode 1, how is sufficient negative reactivity verified available in the event of a steam line break? A. RCS Cold Leg temperature greater than 551?F.B. Axial Flux Difference alarm is operable.C. Accumulator boron concentration greater than 2300 ppm.D. Rods are above the Rod Insertion Limit.

Back 13

D

Front 14

What parameter does the Rod Insertion Limit Computer use as an indication of reactor power? A. Highest Power Range Nuclear Instrument Indication.B. Highest T-avg.C. Highest RCS loop deltaT.D. Median RCS Loop deltaT.

Back 14

C

Front 15

Which ONE of the following is NOT a consideration in establishing Control Rod insertion limits? A. Ensuring minimum shutdown margin availableB. Maintaining allowable power distributionC. Maintaining post accident boron solubility within limitD. Minimizing the effects of an ejected rod

Back 15

C

Front 16

Maintaining the control rods above the Rod Insertion Limit (RIL) is necessary to be assured that other important core parameters are maintained within limits.All but one of the following parameters relies on control rods being maintained above the RIL.What parameter does NOT rely on rods above RIL? A. Axial OffsetB. Peak to local power densityC. Shutdown marginD. Departure from Nucleate Boiling Ratio

Back 16

A

Front 17

The plant has returned to 100% power and a large xenon oscillation is in progress because the crew did not use Direct Axial Offset Control to control it.What action should the reactor operator take to force ?I to target? A. With delta I negative and going positive, withdraw control rods.B. With delta I positive and going negative, withdraw control rods.C. Just prior to a positive peak, insert the control rods and dilute.D. Just prior to a negative peak, insert control rods and dilute.

Back 17

C

Front 18

The ESFAS actuation signals originate in the ___________, the ________________ or the ____________________ cabinets. A. LSP; CRVIS; SISB. ESFAS; MSFIS; SISC. SSPS; ESFAS; MSFISD. SIS; SSPS; FWIS

Back 18

C

Front 19

An inadvertent safety injection occurred. Operators are performing EMG ES-03, SI TERMINATION, and preparing to reset the SI.What is the indication if only one SI train resets? A. SI actuate light on SB069 would blink and automatic SI would re-initiate after 60 seconds.B. SI actuate light would not extinguish since either switch will reset the SI actuate light.C. SI actuate light on SB069 would blink since reset switches are train specific.D. SI actuate light would not extinguish and automatic SI would re-initiate after 60 seconds.

Back 19

C

Front 20

IF the following plant conditions exist:* 75% power and increasing* All steam generator pressures decreasing slowly* Containment temperature, pressure and humidity increasing* Tave decreasingWhat actuation is designed to prevent the containment from exceeding its design pressure limit? A. CISAB. MSLISC. CISBD. SIS

Back 20

B

Front 21

Why is a Feedwater Isolation Signal generated when the Reactor Protection System senses a P-4 coincident with Low TAVE (564?F)? A. Prevent Main Feedpump discharge pressure causing Aux Feed pumps to run at shut-off head.B. Limit RCS cooldown which minimizes positive reactivity and maintains shutdown margin.C. Limit the mass addition to the containment following a Steam Generator Tube Rupture.D. Limit Steam Generator cooling causing thermal stresses in the downcomer region.

Back 21

B

Front 22

What effect does a Containment Isolation Signal Phase "A" (CISA) have on the Reactor Coolant Drain Tank Subsystem? A. Opens isolation valves on drain lines to RCDT and closes RCDT discharge line isolation valves.B. Closes inside/outside RCDT vent isolation valve (HB HV-7126/7150) and closes RCDT discharge line isolation valves (HB HV-7136/7176).C. Closes isolation valves on drain lines to RCDT and closes RCDT discharge isolation valves to outside containment.D. Closes isolation valves on drain lines to RCDT and opens RCDT discharge isolation valves to outside containment.

Back 22

B

Front 23

Which one of the following uses P-4 as an input to actuate Engineered Safety Features Actuation (ESFAS)? A. Auxiliary Feedwater ActuationB. Containment Spray ActuationC. Steamline IsolationD. Feedwater Isolation

Back 23

D

Front 24

What is the coincidence and value, which results in a Main Steam Line Isolation? (All control switches are aligned for 100% power operation) A. "A" Steamline pressure equal to 575 psig on 2/3 detectors.B. Containment pressure equal to 5.0 on 2/3 detectors.C. Steamline rate of 110 psig/50 seconds on 2/3 detectors on "B" S/G.D. Pressurizer pressure equal to 1825 psig on 3/4 detectors.

Back 24

A

Front 25

What is NOT a plant response to a Main Steam Line Isolation actuation? A. Turbine Driven Auxiliary Feedwater Pump supply close.B. Main Steam Isolation Valves close.C. Main Steam Line Bypass Valves close.D. Upstream Steam Line Drain Traps close.

Back 25

A

Front 26

What single condition causes both a safety injection and main steamline isolation? A. Low PZR pressure.B. High steamline pressure rate (100#/50sec).C. Low steam line pressure (rate sensitive 615#).D. High containment pressure (Hi-1).

Back 26

C

Front 27

If an inadvertent SI occurs with a Train "B" LOCA Sequencer failure, what action must be taken to prevent equipment damage? A. Secure CCP "B".B. Secure RCPs.C. Start ESW Pump "B".D. Close cross connect valves the "B" Train ESW.

Back 27

C

Front 28

What actuation signal will NOT cause an AFAS-T? A. Both MFPs tripped and not blocked.B. All S/G NR levels < 5% with turbine power > 35% for 30 seconds.C. Undervoltage on bus NB01 only.D. All S/G levels < 23.5% with turbine power > 40%.

Back 28

A

Front 29

What signal(s) automatically close LF HV-105 CTRL/AUX BUILDING SUMP PUMPS DISCHARGE VALVE? A. Radiation monitor HIHIB. SISC. CISAD. Radiation monitor HI

Back 29

B

Front 30

What set of conditions BOTH prevent a reset of AFAS-M? A. Trip of both MFPs and Safety Injection Signal.B. S/G water level Lo-Lo and trip of both MFPs.C. Safety Injection Signal and NB Bus Undervoltage.D. NB Bus Undervoltage and S/G water level Lo-Lo.

Back 30

B

Front 31

What initiating condition MUST be cleared before FWIVs can be re-opened? A. AMSAC Trouble.B. S/G Lo-Lo Level Reactor Trip.C. Trip of both Main Feed Pumps.D. P-4 and Low T-ave.

Back 31

B

Front 32

What signal/condition would NOT cause a Feedwater Isolation Signal (FWIS) actuation? A. Reactor Trip (P-4) with a Low T-aveB. Steam Generator Lo-Lo LevelC. Safety Injection Signal (SIS)D. Trip of Both Main Feed Pumps

Back 32

D

Front 33

If a Safety Injection Signal is actuated and reset, what ESFAS conditions exist? A. Resetting a manual SIS signal will block an automatic SIS actuation.B. When the automatic SIS is reset the Reactor Trip breakers can be closed even though the initiating SIS condition still exists.C. The manual reset for both SIS trains must be depressed before either SIS train will reset.D. After an automatic SIS is reset, a manual SIS will cause the "Auto SI Block" status light to go out.

Back 33

A

Front 34

A 600 gpm tube rupture occurred in 'A' S/G during Mode 1 operation. During recovery phase, the BOP notices condenser air removal vacuum pumps have tripped and discharge dampers are closed.What caused the condenser air removal system to secure? A. CISBB. SISC. SGBSISD. CISA

Back 34

B

Front 35

A Fuel Building Isolation Signal (FBIS) has been manually actuated. Minutes later a Safety Injection Signal (SIS) is actuated.The Auxiliary/Fuel Building Emergency Exhaust System responds by ______________________ the suction dampers to the Fuel Building and ________________________ the suction dampers to the Auxiliary Building. A. closing; openingB. closing; closingC. opening; closingD. opening; opening

Back 35

A

Front 36

The unit is in Mode 2 when an operator inadvertently opens the normal feeder breaker to NB01. All equipment operates per design.What is the correct actuation for the auxiliary feedwater system? A. TD AFP starts immediately, 'A' MD AFP starts at time 30 seconds on the S/D sequencer.B. Only TD AFP starts at time 20 seconds on the S/D sequencer.C. Only 'A' MD AFP starts at time 30 seconds on the S/D sequencer.D. Both TD AFP and 'A' MD AFP start at time 20 seconds on the S/D sequencer.

Back 36

A

Front 37

What condition will cause the auto start of both motor driven auxiliary feedwater pumps but NOT start the turbine driven aux feed pump? A. Undervoltage on NB02B. AMSACC. Trip of both MFW pumpsD. Lo-Lo level in two S/G's

Back 37

C

Front 38

At 5% power 'B' steam generator level decreased to 10% level causing a Feedwater Isolation Signal.What action must be performed to open the Bypass Feed Reg. valves? A. Depress SB HS-17 and 18, FWIS reset pushbuttons.B. Restore all steam generators to normal band.C. Restore all steam generators to normal band and close reactor trip breakers.D. Restore all steam generators to normal band and depress SB HS-17 and 18, FWIS reset pushbuttons.

Back 38

D

Front 39

The following plant conditions exist:* Plant tripped 45 minutes ago from full power.* A pressurizer safety valve is partially open.* Pressurizer pressure is 1900 psia.* Pressurizer level is 34% and stable.* PRT rupture disk has ruptured.* Containment pressure is 2.0 psig.What is the expected temperature in the tailpipe downstream of the safety valve and ECCS equipment actuation status? A. 220?F, SI actuated.B. 300?F, SI NOT actuated.C. 220?F, SI NOT actuated.D. 300?F, SI actuated.

Back 39

C

Front 40

A plant startup is in progress per GEN 00-003.The reactor is at 9% power with a Main Feedwater Pump in service.While rolling the Main Turbine, S/G level control malfunctions result in actual NR level in "A" S/G exceeding 78%.Which automatic actions would occur? A. All AFW pumps will immediately start.B. Both motor driven AFW pumps will immediately start.C. Both motor driven AFW pumps will start following a time delay.D. All AFW pumps will start following a time delay.

Back 40

B

Front 41

Which ONE signal/condition given will actuate a Feedwater Isolation (FWIS) AND Auxiliary Feedwater Actuation - Motor (AFAS-M)? A. Reactor trip (P4) and RCS Tavg (566oF) B. One of four Steam Generators level (<23.5%)C. High Steam Pressure negative rate (100psig/1sec)D. Pressurizer pressure low (1820psig)

Back 41

B

Front 42

The Unit is operating with the following Main Control Board indications:* Reactor tripped* PZR level 10%* PZR Pressure 1750psig* Steam line pressures 870psig* CTMT Pressure 3.5psigWhich of the following Engineered Safety Features Systems would NOT have received an ESF actuation signal based on the above plant conditions? A. Containment Purge Isolation System (CPIS)B. Feedwater Isolation (FWIS)C. Control Room Emergency VentilationD. Main Steam Line Isolation (MSLIS)

Back 42

D

Front 43

During a transient event an SI is caused by a Main Steam Line Isolation signal (MSLIS). Operators observe containment conditions as normal and determine a fault must have occurred somewhere in the plant.Which of the below safety systems would NOT have received an actuation signal as a DIRECT result of the MSLIS signal? A. Emergency Diesel GeneratorsB. Feedwater IsolationC. Control Room Emergency VentilationD. Containment Fan Coolers

Back 43

C

Front 44

Manual Containment Spray Actuation will NOT cause: A. actuation of Containment Isolation - Phase BB. Safety Injection actuation.C. initiation of spray flow to ContainmentD. actuation of the Loca sequencer.

Back 44

B

Front 45

Main Steam Line Isolation will occur if: A. 2/3 High Containment pressures > 3.5 psigB. 2/3 pressure rates > setpoint in 1/4 main steam lines if low steam line pressure isolation has been blocked below P-11C. 1/3 pressure rates > setpoint in 2/4 main steam lines if low steam line pressure isolation has been blocked below P-11D. 1/3 pressures < 615 psig in 2/4 main steam lines

Back 45

B

Front 46

Unit 1 is operating at 100% power with all control systems in auto. A Reactor Operator trainee inadvertently places one Containment Spray/Phase "B" control switch to "actuate".Which of the following describes the resulting ESF actuations? A. Only one train of Containment Spray will actuate, but Containment Isolation Phase "B" and CTMT Purge Isolation will fully actuate.B. Containment Spray, Containment isolation Phase "B", and CTMT Purge Isolation will fully actuate.C. No ESF actuations occur.D. Containment Spray will not actuate, but Containment isolation Phase "B" and CTMT Purge Isolation will fully actuate.

Back 46

C

Front 47

Which of the following describes an expected response of the Engineered Safety Features (ESF) System due to the given operator action? A. Depressing Train A and Train B SI reset switches will allow automatic reinitiation of SI if the initiating condition returnsB. Manually initiating Spray actuation and Containment Isolation Phase B will also initiate Phase AC. Inadvertently energizing two Hi-2 containment pressure bistables during testing will actuate SID. Closing the reactor trip breakers will re-initiate SI following reset and termination if the initiating condition returns

Back 47

D

Front 48

Wolf Creek was operating at 90% RTP when a faulted steam line caused operators to manually trip the unit. A Safety Injection Signal (SIS) subsequently resulted caused by low steam line pressure. Operators discovered that the Train B reactor trip breaker did not open. Which of the following statements is true under these conditions? A. Only Train "A" ECCS equipment automatically started and Train "B" equipment must be manually actuated by the operators.B. Neither train of ECCS equipment can be secured because the SIS cannot be reset with the failed reactor trip breaker.C. SIS can be reset but if another SIS setpoint is exceeded another SIS will occur and start any equipment stopped.D. Only Train "A" SIS can be reset but all SIS setpoints exceeded in the future will not cause Train "A" equipment to actuate.

Back 48

D

Front 49

Determine the condition the plant should be in given the following condition (Assume NO operator action taken):* RCS pressure 2235 psig* Tave 557oF* Loop 1 Main Steam line pressure 600psig* Loop 2-4 Main Steam line pressure 1092psig* Containment pressure 2.5 psig A. Reactor tripped, SI not actuated, MSIV's closed, Containment Isolation Phase "A" actuatedB. Reactor tripped, SI actuated, only Loop 1 MSIV closed, Containment Isolation Phase "A" actuatedC. Reactor tripped, SI actuated, MSIV's open, Containment Isolation Phase "A" actuatedD. Reactor tripped, SI actuated, MSIV's closed, Containment Isolation Phase "A" actuated

Back 49

D

Front 50

A normal plant shutdown is in progress with the following conditions:* Pressurizer Pressure is 2000 psig* Steam Line pressure is 800 psig* All other conditions are normalA large steam line break occurs upstream of 'B' MSIV resulting in a complete depressurization of 'B' Steam Generator (S/G) in 1 minute. No manual operator action occurs.What describes the expected response of the Engineered Safety Features Actuation System (ESFAS) to this event? A. MSLIS due to high rate of 'B' Steam Line pressure decrease. No SIS occurs.B. SIS due to high rate of 'B' Steam Line pressure decrease. MSLIS due to Low 'B' steam line pressure.C. SIS due to low 'B' steam line pressure. No MSLIS occurs.D. SIS and MSLIS due to Low 'B' Steam Line pressure.

Back 50

D

Front 51

The plant is shutdown in Mode 3 cooling down to Mode 5. The following conditions exist:* RCS Temperature 488 degrees F* RCS Pressure 1890 psig* Ctmt Pressure 0.4 psig* PZR Level 35%* S/G Pressures A) 595 psig B) 592 psig C) 597 psig D) 595 psig* MSIVs OPEN60 seconds later the conditions are:* RCS Temperature 472 degrees F* RCS Pressure 1830 psig* Ctmt Pressure 4 psig* PZR Level 17%* S/G Pressures A) 510 psig B) 515 psig C) 461 psig D) 512 psigWhat is the current status of the MSIVs and why? A. MSIVs - OPEN, no Main Steam Line Isolation signal present.B. MSIVs - CLOSED, due to low RCS pressure.C. MSIVs - CLOSED, due to high steam pressure rate.D. MSIVs - OPEN, no Safety Injection signal is present.

Back 51

C

Front 52

The unit has experienced a transient with a reactor trip, the following conditions exist.* PZR Level 2%* PZR Pressure 1770 psig* Steam Line Pressure 870 psig* Ctmt Pressure 1.2 psig* Reactor Trip Bkr "A" indicates closedWhich of the following list ESF actuations that should have occurred based on the above conditions? A. FBIS and FWISB. CRVIS and MSLISC. CIS-A and FWISD. CIS-A and FBIS

Back 52

C

Front 53

What ESFAS actuation can be reset any time following initiation? A. CSASB. MSLISC. AFAS-MD. CPIS

Back 53

A

Front 54

A large steam line break in containment has caused "C" steam generator to dry out with containment pressure exceeding 27 psig.Which one of the following Engineered Safety Features (ESF) does NOT require the initiating event to clear before it may be reset? A. Control room ventilation isolation signal.B. Containment Spray Actuation signal.C. Fuel Building Isolation Signal.D. Auxiliary feedwater actuation signal.

Back 54

B

Front 55

Which one of the following signals resets only by depressing the FWIS RESET switch? A. AFASB. Low-Low steam generator levelC. P-14, High-High steam generator levelD. Low Tavg with P-4

Back 55

D

Front 56

Which pumps do both the LOCA and Shutdown Sequencer start? A. Safety InjectionB. Residual heat removalC. Normal chargingD. Centrifugal charging

Back 56

D

Front 57

What is the MINIMUM number of manual switches required to actuate yellow train CISA, CRVIS, and CPIS and why? A. Two - because CRVIS actuates CPIS.B. Three - because signals are independent.C. Two - because CPIS actuates CRVIS.D. One - because CISA actuates CRVIS & CPIS.

Back 57

D

Front 58

Preparations are being made to establish charging flow in EMG ES-03, SI TERMINATION, when offsite power is lost. The Emergency Diesel Generators start and power both safety buses. Fifteen seconds later the SS/STA observes SI Pumps are NOT running. SI Pumps were running before loss of offsite power.Should SI Pumps restart automatically by this point in time? A. Yes, the Shutdown Sequencer should have started the SI Pumps 10 seconds ago.B. No, the LOCA Sequencer did not actuate because the SI signal has been reset.C. Yes, the LOCA Sequencers should have started the SI Pumps 10 seconds ago.D. No, the LOCA Sequencers will not start the SI Pumps for another 10 seconds.

Back 58

B

Front 59

Assume S/G level has been restored to 50% narrow range with Auxiliary Feed Water flow. What manipulations would be required to reopen the FWIVs following a P-14 turbine/reactor trip? A. Close reactor trip breakers.B. Reset SI.C. Recharge hydraulic accumulators.D. At both MSFIS Cabinets reset each FWIV (using Operate Switches).

Back 59

D

Front 60

What is the normal condition for SI reset? A. The reset pushbuttons for both SI trains must be depressed before either SI train will reset.B. After an auto SI is reset, a manual SI actuation will cause the "AUTO SI BLOCK" status lights to extinguish.C. When auto SI is reset, a manual SI is inhibited until P-4 is reset.D. An SI signal, when reset, will block an auto SI actuation until the reactor trip breakers are reclosed.

Back 60

D

Front 61

During a plant heatup after a refueling, the Shift Manager is requested to establish the following conditions for a special test:Tavg 4500FRCS Pressure 2000 psigRCPs All runningWhat is the proper response to the request? A. The test can be performed because it is not an unreviewed safety question.B. The test cannot be performed because of the differential temperature between the spray line and the pressurizer.C. The test cannot be performed because it would cause a Safety Injection.D. The test can be performed provided a Special Test Procedure is approved.

Back 61

C

Front 62

Based on Criterion 21, WCGS is designed such that no _______________________ results in loss of protective function. A. double failureB. 120VAC failureC. single failureD. battery charger failure

Back 62

C

Front 63

The following Technical Specifications, related to ESFAS, include actions required to be completed in less than or equal to what amount of time?* 3.3.2, Engineered Safety Features Actuation System Instrumentation* 3.3.6, Containment Purge Isolation Instrumentation* 3.3.7, Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation* 3.3.8, Emergency Exhaust System (EES) Actuation Instrumentation A. one hourB. 3.5 hoursC. 6 hoursD. 29 hours

Back 63

A

Front 64

The plant is in Mode 3. An I & C Technician reports to the Shift Manager that STS IC 211A, ACTUATION LOGIC TEST TRAIN A SOLID STATE PROTECTION SYSTEM, found an actuation relay for Main Steam Isolation did not operate.What action should be taken? A. Be in Mode 4 within the next six hours.B. Repair the actuation relay within six hours or be in Mode 4 within the next 12 hours.C. Repair the actuation relay within 48 hours or be in Mode 4 within the next six hours.D. Repair the actuation relay within six hours or be in Mode 4 within the next six hours and Mode 5 within the next 24 hours.

Back 64

B

Front 65

Following an ESFAS Actuation, what condition results in an unlit indication on the engineered safeguard feature status panel, SA066X, Y, & Z? A. 74 Status Relay FailureB. In safeguards positionC. Loss of powerD. Not in safeguards position

Back 65

D

Front 66

Which describes when a system level red light is manually actuated on the engineered safeguard feature status panels, SA066X, Y, & Z? A. The last component in the system is let red and the component handswitch is in normal after run.B. A component/system has no component level window and cannot perform its safeguard functionC. A system that should have actuated its system level red light, but did not.D. A system that is known to be in its safeguard alignment, but the components do not show proper alignment.

Back 66

B

Front 67

The plant is at 100% power all systems in normal alignment when a LOCA occurs.What will happen as RCS pressure decreases? A. At 1830 psig on 1/2 instruments, a trip signal in one protection train opens one reactor trip breaker.B. At 1940 psig on 2/4 instruments, a trip signal in both protection trains opens both reactor trip breakers.C. At 1940 psig on 2/4 instruments, a trip signal in one protection train opens one reactor trip breaker.D. At 1830 psig on 1/2 instruments, a trip signal in both protection trains opens both reactor trip breakers.

Back 67

B

Front 68

Which one of the following is NOT a Condition I event, as classified by ANS? A. Operation with steam generator leaks.B. Small Break LOCA.C. Ramp load change of 3%/minute.D. A Plant Startup.

Back 68

B

Front 69

What Blowdown (BM) valves are closed by a SGBSIS? A. HV-54; PV-16; TV-40; PV-39AB. HV-1; HV-19; HV-35; HV-65C. HV-2; HV-19; PV-39; PV-16D. HV-4; HV-68; PV-39A; HV-37

Back 69

B

Front 70

A turbine/reactor trip has occurred due to High-High Steam Generator level; S/G levels have been restored to 50% using Auxiliary Feedwater System.What action is required to clear the signal that is keeping the Feedwater Isolation Valves closed? A. Close/cycle reactor trip breakersB. Allow sufficient time for the hydraulic accumulators to rechargeC. Depress FWIS RESET TRN A and B pushbuttonsD. Reset Safety Injection Signal

Back 70

C

Front 71

A Feedwater Isolation Signal (FWIS) is generated from a manual reactor trip at 75% power. Safety Injection does not actuate. S/G levels are stable at 35% NR using Auxiliary Feedwater.What (if any) condition must be clear before using the FWIS Reset pushbuttons on the Main Control Board? A. P-11(>1970 psig) reset.B. Close reactor trip breakers.C. No condition.D. Raise Tavg greater than 564?F.

Back 71

C

Front 72

The plant is at 100% power when a Hi-Hi radiation alarm is received on Condenser Air Discharge Monitor (GE-RE-92).What action is necessary to open valves BM HV-5, 6, 7 and 8? A. Reset AFAS M, then open the valves.B. Open the valves. No reset required.C. Reset SGBSIS, then open the valves.D. Reset BSPIS, then open the valves.

Back 72

B

Front 73

A loss of Coolant outside containment is in progress, and a Safety Injection has been actuated.When the RWST level reaches 36% on 2/4 level instruments, the Containment Recirculation Sump will _________________________________________________. A. remain dry since the RWST suction to the RHR pumps close before the Containment Recirculation Sump suction valves open.B. be filled with RCS inventory flowing back from the RCS through the RHR System to the sump.C. fill with RWST water due to gravity draining while the Containment Recirculation Sump and RWST RHR valves are repositioning.D. remain dry since check valves prevent flow from the RWST to the Containment Recirculation Sump through the suction of the Residual Heat Removal pumps.

Back 73

C

Front 74

The American Nuclear Society (ANS) classification of plant conditions divides plant conditions into four categories. Which condition is considered the most severe? A. Condition IIIB. Condition IIC. Condition IVD. Condition I

Back 74

C

Front 75

What event/fault is the most severe plant failure according to the American Nuclear Society Classifications (ANS) system? A. Reactor Coolant Pump shaft seizureB. Loss of normal feedwater flowC. Complete loss of forced Reactor Coolant flowD. Inadvertant opening of PRZR Safety or Relief Valve

Back 75

A

Front 76

According to American Nuclear Society Classifications (ANS), which events/fault are considered to be the most drastic plant failures? A. Design Basis Fuel Handling accidentB. Radioactive gas waste system leak or failureC. Spent fuel cask drop accidentD. Uncontrolled rod cluster control assembly bank withdrawal

Back 76

A

Front 77

A Fuel Handling Accident is defined, for accident analysis purposes, as dropping of a Spent Fuel Assembly on to the fuel storage area floor , or refueling pool, resulting in what percentage of cladding rupture in the fuel rods of an assembly? A. 25%B. 100%C. 80%D. 50%

Back 77

B

Front 78

Why is a Main Steamline Break more severe at End of Life (EOL) and Hot Zero Power (HZP) than at any other time? A. Will cause melting at the Fuel Centerline of the most limiting rod. B. The large amount of Decay Heat available slows the cooldown.C. Loss of Offsite Power will cause increased heat removal.D. Moderator Temperature Coefficient (MTC) is the most negative.

Back 78

D

Front 79

There are four phases of a large break Loss of Coolant Accident (LOCA).Which of the following shows the correct order in which these phases occur? A. Refill Phase, Reflood Phase, Long Term Recirculation, Reflux PhaseB. Refill Phase, Blowdown Phase, Reflood Phase, Reflux PhaseC. Blowdown Phase, Refill Phase, Reflood Phase, Long Term RecirculationD. Blowdown Phase, Reflood Phase, Refill Phase, Long Term Recirculation

Back 79

C

Front 80

What is a Condition II fault? A. Propagates to cause a more serious fault.B. Results in a reactor trip with the plant capable of returning to power.C. Expected to occur only once during the lifetime of the plant.D. Results in the failure of a small fraction of fuel.

Back 80

B

Front 81

What plant parameters are inputs to the Safety Injection Signal? A. RCS Pressure, Containment Pressure, RCS TemperatureB. RCS Pressure, Pressurizer Level, Steam Line PressureC. Pressurizer Pressure, Containment Pressure, Steam Line PressureD. Pressurizer Pressure, Pressurizer Level, RCS Temperature

Back 81

C

Front 82

What is the coincidence and value, which results in a Main Steam Line Isolation? (All control switches are aligned for 100% power operation) A. Containment pressure equal to 5.0 on 2/3 detectors.B. Steamline rate of 110 psig/50 seconds on 2/3 detectors on "B" S/G.C. Pressurizer pressure equal to 1825 psig on 3/4 detectors.D. "A" Steamline pressure equal to 575 psig on 2/3 detectors.

Back 82

D

Front 83

What is NOT a plant response to a Main Steam Line Isolation actuation? A. Turbine Driven Auxiliary Feedwater Pump supply close.B. Main Steam Line Bypass Valves close.C. Upstream Steam Line Drain Traps close.D. Main Steam Isolation Valves close.

Back 83

A

Front 84

What ESFAS actuation can be reset any time following initiation? A. CPISB. CSASC. MSLISD. AFAS-M

Back 84

B

Front 85

During a plant heatup after a refueling, the Shift Manager is requested to establish the following conditions for a special test:Tavg 4500FRCS Pressure 2000 psigRCPs All runningWhat is the proper response to the request? A. The test cannot be performed because of the differential temperature between the spray line and the pressurizer.B. The test can be performed provided a Special Test Procedure is approved.C. The test cannot be performed because it would result in an unreviewed safety question.D. The test cannot be performed because it would cause a Safety Injection.

Back 85

D

Front 86

What, if any, interlock exists to prevent RHR Pumps from taking a suction on a dry Containment Sump? A. Low Containment Sump level prevents the switchover.B. There is no interlock to prevent this.C. The RHR Pumps trip on low Containment Sump level.D. Low Containment Sump level keeps the RWST Suction valve open.

Back 86

B

Front 87

Power is removed from EM HV-8835, SI PUMPS to COLD LEG INJ, during normal operations to prevent inadvertently shutting it.Why is this necessary? A. To ensure SI Pumps discharge to only two loops.B. To ensure Hot Leg Injection from the SI pumps.C. To prevent SI Pumps running at Shut-Off Head on a Safety Injection.D. To ensure Cold Leg Injection from the SI pumps.

Back 87

D

Front 88

Following a large break LOCA during the cold leg recirculation mode, core decay heat is being removed.What is the heat transfer path? A. Injection of cooled water from the recirculation sump and removal of steam/water out the break.B. RCS to the S/Gs from natural circulation.C. Cold water Injection from the RWST and removal of steam/water out the break.D. RCS to the S/Gs from reflux boiling.

Back 88

A

Front 89

Which ONE parameter will enable the crew to distinguish between an RCS LOCA and a steam line break? A. Pressurizer level decreases in an uncontrolled manner only during a LOCA.B. RCS pressure decreases rapidly only during a LOCA.C. AFAS-T is actuated only during a steam line break.D. S/G pressure decreases in an uncontrolled manner only during a steam line break.

Back 89

D

Front 90

What actuation signal will NOT cause an AFAS-T? A. Both MFPs tripped and not blocked.B. Undervoltage on bus NB01 only.C. All S/G levels < 23.5% with turbine power > 40%.D. All S/G NR levels < 5% with turbine power > 35% for 30 seconds.

Back 90

A

Front 91

A loss of coolant inside containment is in progress, and a Safety Injection has been actuated.What occurs or must occur when the RWST level reaches 36% on 2/4 level instruments? A. Nothing. The operator manually transfers RHR suction from the RWST to the Containment Recirculation Sump at 6% RWST level.B. Nothing. The automatic transfer of RHR suction from the RWST to the Containment Recirculation Sump occurs at 6% RWST level.C. The RHR suction is automatically transferred from the RWST to the Containment Recirculation Sump.D. The RHR suction is manually transferred from the RWST to the Containment Recirculation Sump.

Back 91

C

Front 92

When a Safety Injection Signal is actuated, how do the Centrifugal Charging Pump Mini-Flow valves (BG HV-8110 and 8111) operate? A. Close until SI is reset and will open/close on low/high flow.B. Close on high flow and open on low flow through the BIT.C. Remain open unless BIT flow is low, then they will close.D. Not affected by SIS.

Back 92

B

Front 93

What signal(s) automatically close LF HV-105 CTRL/AUX BUILDING SUMP PUMPS DISCHARGE VALVE? A. Radiation monitor HIHIB. SISC. CISAD. Radiation monitor HI

Back 93

B

Front 94

What set of conditions BOTH prevent a reset of AFAS-M? A. Safety Injection Signal and NB Bus Undervoltage.B. Trip of both MFPs and Safety Injection Signal.C. NB Bus Undervoltage and S/G water level Lo-Lo.D. S/G water level Lo-Lo and trip of both MFPs.

Back 94

D

Front 95

What initiating condition MUST be cleared before FWIVs can be re-opened? A. Trip of both Main Feed Pumps.B. AMSAC Trouble.C. S/G Lo-Lo Level Reactor Trip.D. P-4 and Low T-ave.

Back 95

C

Front 96

What signal/condition would NOT cause a Feedwater Isolation Signal (FWIS) actuation? A. Steam Generator Lo-Lo LevelB. Safety Injection Signal (SIS)C. Trip of Both Main Feed PumpsD. Reactor Trip (P-4) with a Low T-ave

Back 96

C

Front 97

What is the MINIMUM number of manual switches required to actuate yellow train CISA, CRVIS, and CPIS and why? A. Two - because CRVIS actuates CPIS.B. Three - because signals are independent.C. One - because CISA actuates CRVIS & CPIS.D. Two - because CPIS actuates CRVIS.

Back 97

C

Front 98

Which ONE signal/condition given will actuate a Feedwater Isolation (FWIS) AND trip the Main Feed Pumps? A. Pressurizer pressure low (1820psig)B. Reactor trip (P4) and RCS Tavg (566oF) C. Low Steam Generator level (25% NR)D. High Steam Pressure negative rate (100psig/1sec)

Back 98

A

Front 99

The Unit is operating with the following Main Control Board indications:* Reactor tripped* PZR level 10%* PZR Pressure 1750psig* Steam line pressures 870psig* CTMT Pressure 3.5psigWhich of the following Engineered Safety Features Systems would NOT have received an ESF actuation signal based on the above plant conditions? A. Feedwater Isolation (FWIS)B. Control Room Emergency VentilationC. Containment Purge Isolation System (CPIS)D. Main Steam Line Isolation (MSLIS)

Back 99

D

Front 100

During a transient event an SI is caused by a Main Steam Line Isolation signal (MSLIS). Operators observe containment conditions as normal and determine a fault must have occurred somewhere in the plant.Which of the below safety systems would NOT have received an actuation signal as a DIRECT result of the MSLIS signal? A. Feedwater IsolationB. Emergency Diesel GeneratorsC. Containment Fan CoolersD. Control Room Emergency Ventilation

Back 100

D

Front 101

Which ONE of the following will NOT correctly complete the following statement regarding ESFAS actuation?Manual Containment Spray Actuation..: A. will actuate the load sequencer B. will actuate Safety InjectionC. will actuate Containment Isolation - Phase BD. will initiate spray flow to Containment

Back 101

B

Front 102

Unit 1 is operating at 100% power with all control systems in auto. A Reactor Operator trainee inadvertently places one Containment Spray/Phase "B" control switch to "actuate".Which of the following describes the resulting ESF actuations? A. Only one train of Containment Spray will actuate, but Containment Isolation Phase "B" and CTMT Purge Isolation will fully actuate.B. Containment Spray, Containment isolation Phase "B", and CTMT Purge Isolation will fully actuate.C. Containment Spray will not actuate, but Containment isolation Phase "B" and CTMT Purge Isolation will fully actuate.D. No ESF actuations occur.

Back 102

D

Front 103

Which of the following describes an expected response of the Engineered Safety Features (ESF) System due to the given operator action? A. Manually initiating Spray actuation and Containment Isolation Phase B will also initiate Phase AB. Inadvertently energizing two Hi-2 containment pressure bistables during testing will actuate SIC. Closing the reactor trip breakers will re-initiate SI following reset and termination if the initiating condition returnsD. Depressing Train A and Train B SI reset switches will allow automatic reinitiation of SI if the initiating condition returns

Back 103

C

Front 104

Wolf Creek was operating at 90% RTP when a faulted steam line caused operators to manually trip the unit. A Safety Injection Signal (SIS) subsequently resulted caused by low steam line pressure. Operators discovered that the Train B reactor trip breaker did not open. Which of the following statements is true under these conditions? A. Neither train of ECCS equipment can be secured because the SIS cannot be reset with the failed reactor trip breaker.B. Only Train "A" ECCS equipment automatically started and Train "B" equipment must be manually actuated by the operators.C. SIS can be reset but if another SIS setpoint is exceeded another SIS will occur and start any equipment stopped.D. Only Train "A" SIS can be reset but all SIS setpoints exceeded in the future will not cause Train "A" equipment to actuate.

Back 104

D

Front 105

Determine the condition the plant should be in given the following condition (Assume NO operator action taken):* RCS pressure 2235psig* Tave 557oF* Loop 1 Main Steam line pressure 600psig* Loop 2-4 Main Steam line pressure 1092psig* Containment pressure 2.5 psig A. Reactor tripped, SI actuated, only Loop 1 MSIV closed, Containment Isolation Phase "A" actuatedB. Reactor tripped, SI actuated, MSIV's open, Containment Isolation Phase "A" actuatedC. Reactor tripped, SI actuated, MSIV's closed, Containment Isolation Phase "A" actuatedD. Reactor tripped, SI not actuated, MSIV's closed, Containment Isolation Phase "A" actuated

Back 105

C

Front 106

A normal plant shutdown is in progress with the following conditions:* Pressurizer Pressure is 2000 psig* Steam Line pressure is 800 psig* All other conditions are normalA large steam line break occurs upstream of 'B' MSIV resulting in a complete depressurization of 'B' Steam Generator (S/G) in 1 minute. No manual operator action occurs.What describes the expected response of the Engineered Safety Features Actuation System (ESFAS) to this event? A. SIS due to high rate of 'B' Steam Line pressure decrease. MSLIS due to Low 'B' steam line pressure.B. SIS and MSLIS due to Low 'B' Steam Line pressure.C. SIS due to low 'B' steam line pressure. No MSLIS occurs.D. MSLIS due to high rate of 'B' Steam Line pressure decrease. No SIS occurs.

Back 106

B

Front 107

The plant is shutdown in Mode 3 cooling down to Mode 5. The following conditions exist:* RCS Temperature 488 degrees F* RCS Pressure 1890 psig* Ctmt Pressure 0.4 psig* PZR Level 35%* S/G Pressures A) 595 psig B) 592 psig C) 597 psig D) 595 psig* MSIVs OPEN60 seconds later the conditions are:* RCS Temperature 472 degrees F* RCS Pressure 1830 psig* Ctmt Pressure 4 psig* PZR Level 17%* S/G Pressures A) 510 psig B) 515 psig C) 461 psig D) 512 psigWhat is the current status of the MSIVs and why? A. MSIVs - CLOSED, due to low RCS pressure.B. MSIVs - CLOSED, due to high steam pressure rate.C. MSIVs - OPEN, no Safety Injection signal is present.D. MSIVs - OPEN, no Main Steam Line Isolation signal present.

Back 107

B

Front 108

What ESFAS actuation can be reset any time following initiation? A. CPISB. CSASC. MSLISD. AFAS-M

Back 108

B

Front 109

The following conditions exist:A plant startup is in progress, the RCS is currently at 4500F and 1800 psig. The reactor operator raises Reactor Coolant System (RCS) pressure to 2235 psig to perform post-maintenance testing on a Pressurizer Power Operated relief valve.Which one of the following explains the response of the Engineered Safety Features (ESF) for this event? A. SIS and MSLIS actuate on low pressurizer pressure when P-11 energizes.B. SIS actuates on low pressurizer pressure and MSLIS will not actuate.C. SIS will not actuate, but MSLIS actuates on low steam line pressure.D. SIS and MSLIS actuate on low steam line pressure when P-11 de-energizes.

Back 109

D

Front 110

A large steam line break in containment has caused "C" steam generator to dry out with containment pressure exceeding 27 psig.Which one of the following Engineered Safety Features (ESF) does NOT require the initiating event to clear before it may be reset? A. Control room ventilation isolation signal.B. Fuel Building Isolation Signal.C. Auxiliary feedwater actuation signal.D. Containment Spray Actuation signal.

Back 110

D

Front 111

Which one of the following signals resets only by depressing the FWIS RESET switch? A. Low Tavg with P-4B. AFASC. Low-Low steam generator levelD. P-14, High-High steam generator level

Back 111

A

Front 112

Which one of the following uses P-4 as an input to actuate Engineered Safety Features Actuation (ESFAS)? A. Feedwater IsolationB. Steamline IsolationC. Containment Spray ActuationD. Auxiliary Feedwater Actuation

Back 112

A

Front 113

If a Safety Injection Signal is actuated and reset, what ESFAS conditions exist? A. The manual reset for both SIS trains must be depressed before either SIS train will reset.B. Resetting a manual SIS signal will block an automatic SIS actuation.C. When the automatic SIS is reset the Reactor Trip breakers can be closed even though the initiating SIS condition still exists.D. After an automatic SIS is reset, a manual SIS will cause the "Auto SI Block" status light to go out.

Back 113

B

Front 114

What initiating condition MUST be cleared before FWIVs can be re-opened? A. Trip of both Main Feed Pumps.B. AMSAC Trouble.C. S/G Lo-Lo Level Reactor Trip.D. P-4 and Low T-ave.

Back 114

C

Front 115

Which ONE of the following will NOT correctly complete the following statement regarding ESFAS actuation?Manual Containment Spray Actuation..: A. will actuate the load sequencer B. will actuate Safety InjectionC. will actuate Containment Isolation - Phase BD. will initiate spray flow to Containment

Back 115

B

Front 116

A normal plant shutdown is in progress with the following conditions:* Pressurizer Pressure is 2000 psig* Steam Line pressure is 800 psig* All other conditions are normalA large steam line break occurs upstream of 'B' MSIV resulting in a complete depressurization of 'B' Steam Generator (S/G) in 1 minute. No manual operator action occurs.What describes the expected response of the Engineered Safety Features Actuation System (ESFAS) to this event? A. SIS due to high rate of 'B' Steam Line pressure decrease. MSLIS due to Low 'B' steam line pressure.B. SIS and MSLIS due to Low 'B' Steam Line pressure.C. SIS due to low 'B' steam line pressure. No MSLIS occurs.D. MSLIS due to high rate of 'B' Steam Line pressure decrease. No SIS occurs.

Back 116

B

Front 117

Which one of the following signals resets only by depressing the FWIS RESET switch? A. Low Tavg with P-4B. AFASC. Low-Low steam generator levelD. P-14, High-High steam generator level

Back 117

A

Front 118

Which one of the following uses P-4 as an input to actuate Engineered Safety Features Actuation (ESFAS)? A. Feedwater IsolationB. Steamline IsolationC. Containment Spray ActuationD. Auxiliary Feedwater Actuation

Back 118

A

Front 119

A turbine/reactor trip has occurred due to High-High Steam Generator level; S/G levels have been restored to 50% using Auxiliary Feedwater System.What action is required to clear the signal that is keeping the Feedwater Isolation Valves closed? A. Close/cycle reactor trip breakersB. Allow sufficient time for the hydraulic accumulators to rechargeC. Depress FWIS RESET TRN A and B pushbuttonsD. Reset Safety Injection Signal

Back 119

C

Front 120

A Feedwater Isolation Signal (FWIS) is generated from a manual reactor trip at 75% power. Safety Injection does not actuate. S/G levels are stable at 35% NR using Auxiliary Feedwater.What (if any) condition must be clear before using the FWIS Reset pushbuttons on the Main Control Board? A. P-11(>1970 psig) reset.B. Close reactor trip breakers.C. No condition.D. Raise Tavg greater than 564?F.

Back 120

C

Front 121

A large steam line break in containment has caused "C" steam generator to dry out with containment pressure exceeding 27 psig.Which one of the following Engineered Safety Features (ESF) does NOT require the initiating event to clear before it may be reset? A. Control room ventilation isolation signal.B. Fuel Building Isolation Signal.C. Auxiliary feedwater actuation signal.D. Containment Spray Actuation signal.

Back 121

D

Front 122

Which of the following lists the correct power supply for the given equipment? A. Traveling Screen B - NG06E; Self Cleaning Strainer A - NG06E; ESW Pump A - NB01B. ESW Pump B -NB02; Traveling Screen B - NG06E; Self Cleaning Strainer A - NG05EC. Traveling Screen A - NG06E; Self Cleaning Strainer B - NG05E; ESW Pump A - NB01D. ESW Pump B - NB02; Traveling Screen A - NG06E; Self Cleaning Strainer B - NG05E

Back 122

B

Front 123

ESW Pumps A and B respectively receive their power from ____________________________________. A. NG02A and NG02BB. NB01 and NB02C. NG05E and NG06ED. NG01A and NG01B

Back 123

B

Front 124

What two conditions will cause all of the cross-tie valves between Service Water and Essential Service Water Systems to close? A. Loss of Offsite Power; SISB. Loss of ESW pressure; SISC. Loss of ESW pressure; trip of all Service Water PumpsD. Loss of Offsite Power; trip of all Service Water Pumps

Back 124

A

Front 125

Which of the following will NOT cause an automatic isolation of the Essential Service Water System from the Service Water System? A. Loss of Site PowerB. Safety Injection SignalC. Low Suction Pressure with AFAS-T presentD. Emergency Diesel Generator Manual Start

Back 125

D

Front 126

In addition to Loss of Off-site Power, which signals will close the Essential Service Water System supply and return valves to the Service Water System? A. Safety Injection Signal (SIS)B. Low Suction Pressure (LSP)C. Feedwater Isolation Signal (FWIS)D. Containment Isolation Signal Phase "A" (CIS-A)

Back 126

A

Front 127

An undervoltage condition has occurred on NB02 Bus.If all components operate as required, how would plant systems respond? A. All Service Water to ESW supply and return valves would close, isolating Service Water to both trains.B. Flow to "A" Train components would be lost when the Service Water isolated.C. Service Water supply to "B" Train ESW would isolate, but return would remain cross-connected.D. Flow to "B" Train Components would be lost when the Service Water isolated.

Back 127

B

Front 128

Which signals will automatically start the Essential Service Water Pumps? A. Safety Injection Signal; Loss of Off-Site Power; Low Suction Pressure (with AFAS)B. Safety Injection Signal; Loss of Off-Site Power; Reactor tripC. Reactor Trip; Containment Spray Actuation Signal; Low Suction Pressure (with AFAS)D. Safety Injection Signal; Containment Spray Actuation Signal; Low Suction Pressure (with AFAS)

Back 128

A

Front 129

> A. All Service Water and ESW supply and return valves close isolating all flow to both trains.B. All flow to "A" Train components is lost when the Service Water supply valves close.C. Service Water supply valve to "B" Train ESW closes but the Service Water return valve remains open.D. ESW flow to "B" Train components is lost when the Service Water supply valves close.

Back 129

B

Front 130

A localized severe windstorm has resulted in the complete destruction of the CST and an inadvertent opening of the main generator breaker at 100% power. The reactor has tripped, but no Safety Injection Signal has been actuated. No other damage is apparent onsite.How will the Service Water and ESW Systems respond? A. AFW suction automatically aligns to either SW or ESW depending on which system maintains normal discharge pressure and survives the event.B. The Main Feedwater pump suctions align to ESW, the ESW pumps start, and SW supply valves can be aligned from the Main Control Board.C. ESW pumps start, but the AFW pumps trip when the SW supply valves shut.D. AFW pumps suctions align to ESW, the ESW pumps start, and Service Water supply valves close automatically.

Back 130

D

Front 131

Essential Service Water to Auxiliary Feedwater Auto Swap Pressure Transmitter AL PT-38 was found failed to 20 psig. A new transmitter will not arrive on site for 72 hours. The next ACOT on AL PT-38 is scheduled in three weeks.What decision is appropriate for this situation? A. Trip the channel within one hour.B. Trip the channel within six hours.C. Bypass the channel within six hours.D. Bypass the channel within one hour.

Back 131

A

Front 132

If the red train NB bus had an Under Voltage and the "A" Emergency Diesel Generator is now supplying NB01, why is the yellow train ESW system started and aligned to the UHS? A. To provide ESW cooling water to the running yellow train Emergency Diesel.B. Because the CCW service loop has been (or will be) swapped to the yellow train CCW system.C. Because the red train Shutdown Sequencer isolated Service Water to the yellow train ESW system.D. Because of single failure criteria considerations.

Back 132

C

Front 133

Following a Safety Injection Signal (SIS), what describes the position of the Service Water and Essential Service Water systems supply and return cross-connect valves (EF HV-23, 24, 25, 26 and EF HV-39, 40, 41, 42)? A. All supply valves remain open, return valves close.B. These valves are not affected by a SIS.C. All supply and return valves close.D. All supply valves close, return valves remain open.

Back 133

C

Front 134

Which of the following describes the result of an Aux Feed Pump Low Suction Pressure signal coincident with an Auxiliary Feedwater Actuation Signal (AFAS)? A. Service Water to ESW supply and return valves close, and the UHS return valves open.B. An open signal is sent to the AFW Pump Suction valves from the CST.C. A Component Cooling Water Pump in each train starts.D. Service Water to Essential Service Water (ESW) supply valves close.

Back 134

D

Front 135

The "A" ESW pump has started as a result of the "A" Train Shutdown Sequencer. Approximately 5 minutes later, the Control Room requests you to check out a possible problem with the "B" Instrument Air Compressor.What is the most probable cause of the problem? A. "B" ESW pump is not running and must be started to supply "B" Train components.B. The "B" ESW pump is running but flow is bypassed on most "B" Train components until the cross-tie isolation is closed.C. The inlet cooling flow control valve to the "B" air compressor is actually powered from the "A" Train bus and must be reset manually and reopened.D. The "B" ESW pump has started and tripped due to an overload of the NB02 Bus.

Back 135

A

Front 136

A loss of offsite power occurred and both Emergency Diesel Generators (EDGs) are supplying NB buses. ESW Pump 'B' will not start.What action should be performed on EDG 'B' as a result of this failure? A. Unload it within 3 minutes.B. Stop it within the next hour.C. Unload it within the next hour.D. Stop it as soon as possible.

Back 136

A

Front 137

If an inadvertent SI occurs with a Train "B" LOCA Sequencer failure, what action must be taken to prevent equipment damage? A. Close cross connect valves the "B" Train ESW.B. Secure CCP "B".C. Secure RCPs.D. Start ESW Pump "B".

Back 137

D

Front 138

If the yellow train NB bus lost power, what actions, if any, would be performed on the red train? A. The red train Emergency Diesel would be manually started.B. The red train would require no actions to be performed.C. The red train Containment Coolers would be manually started in SLOW.D. The red train ESW system would be started and aligned to the UHS.

Back 138

D

Front 139

Which of the following statements is correct, regarding the cooling water supply to the Instrument/Service Air Compressors? A. ESW train "B" supplies compressor CKA01BB. Central Chilled water supplies compressor CKA01BC. Central Chilled water supplies compressor CKA01AD. ESW train "B" supplies compressor CKA01C

Back 139

A

Front 140

Which of the following does NOT supply a start signal to the ESW supply fan "B"? A. Local HandswitchB. ESW pump "A" startC. Handswitch on RP-068 (Main Control Room)D. ESW Pump "B" start

Back 140

B

Front 141

Which of the following components receive cooling water from the ESW System? A. Boron Thermal Regeneration System ChillerB. Fuel Pool Cooling Heat ExchangerC. Safety Injection Pump "A", Room CoolerD. "C" Instrument Air Compressor

Back 141

C

Front 142

The Essential Service Water System supplies cooling water to Instrument Air Compressors "A" and "B" through air-operated isolation valves.These air operated valves automatically __________ on a sensed ________ differential pressure to conserve system inventory. A. close / lowB. open / highC. open / lowD. close / high

Back 142

D

Front 143

Which of the following does ESW provide an emergency water source to? A. Auxiliary Feedwater SystemB. Main Feedwater SystemC. Component Cooling Water SystemD. Service Water System

Back 143

A

Front 144

Which of the following describes a system to which ESW could provide emergency makeup water if necessary? A. Closed Cooling Water SystemB. Spent Fuel PoolC. Condensate Storage TankD. Refueling Water Storage Tank

Back 144

B

Front 145

Which system, other than the Spent Fuel Pool, is the Essential Service Water a source of emergency makeup? A. Component Cooling Water SystemB. Refueling Water Storage TankC. Condensate Storage TankD. Closed Cooling Water System.

Back 145

A

Front 146

The Plant has undergone a design basis earthquake:* RCS loop 3 cold leg is severed* Contents of RWST, BAST, RMWST has been used to cool the core.* Presently, the RHR is on cold leg recirculation from the Containment Sump* Spent Fuel Pool level has started to decrease and cannot be stopped.* Fuel uncovery is imminent* The SIS signal has not been reset.The preferred source of makeup to the Fuel Pool is from the: A. Demineralized Water SystemB. Fire Protection SystemC. Essential Service WaterD. Service Water System

Back 146

C

Front 147

Which of the following describes the design purpose of the ESW System pre-lube storage tanks? A. Provides strainer backwash water upon strainer high dPB. Provides water to the pump bearings and stuffing box during a pump start.C. Provides a water seal on the casing vent.D. Provides water to the pump motor air cooler on extended pump operation.

Back 147

B

Front 148

When will the ESW traveling screens automatically start? A. When the associated ESW pump starts and the screenwash water valve opens.B. When the SW/ESW cross-connect valves receive a close signal.C. When a high level differential develops between the fore-bay and after-bay.D. When the screen speed selector is placed in "fast wash".

Back 148

A

Front 149

Where is the actual location where the ESW trains can be manually cross-connected? A. ESW side of any of the components cooled by ESW.B. On the ESW pump suctions, inside the ESW Pumphouse.C. On the ESW pump discharge, but before the strainers.D. Just downstream of the strainers in the ESW Pumphouse.

Back 149

D

Front 150

Which of the following describes the result of an Aux Feed Pump Low Suction Pressure signal coincident with an Auxiliary Feedwater Actuation Signal (AFAS)? A. Service Water to Essential Service Water (ESW) supply valves close.B. An open signal is sent to the AFW Pump Suction valves from the CST.C. Service Water to ESW supply and return valves close, and the UHS return valves open.D. A Component Cooling Water Pump in each train starts.

Back 150

A

Front 151

When lake temperature is 32 degrees fahrenheit and air temperature is < 20 degrees fahrenheit, what conditions are most favorable to form Frazil ice? A. 2 mph gusting to 5 mph, heavy overcast, limited ice cover.B. 15 mph gusting to 25 mph, light overcast, majority of lake ice covered.C. 2 mph gusting to 5 mph, light overcast, majority of lake ice covered.D. 15 mph gusting to 25 mph, heavy overcast, limited ice cover.

Back 151

D

Front 152

The plant is at 100% power. B ESW Pump is tagged out to change motor oil. What actions, if any, are required? A. Perform STS NB-005 within one hour, verify the operability of the A Train equipment and the TD AFP.B. Since this is preventable maintenance, no action is required.C. Perform STS NB-005 within one hour, verify the operability of the A Train equipment and the TD AFP and start the A DG within 24 hours.D. Restore the B ESW Pump within 72 hours and be in Mode 5 within 36 hours.

Back 152

A

Front 153

You have been directed to close the throttled ESW valve from the B CCW heat exchanger by one-quarter turn to reduce the ESW flow through the CCW heat exchanger.Does this action render the B ESW System inoperable? A. No; the operability of the ESW system and associated components is not dependent on flow, but on whether the valves can perform their safety related function and the ESW pumps can start.B. No; reducing flow to a component cooled by ESW does not degrade the flow to the other components, thus that train of ESW is still operable.C. Yes; the reduced flow in the CCW heat exchanger will cause that CCW train to be inoperable, and since the inoperability is due to ESW flow, the ESW train must be declared inoperable.D. Yes; any change to the flows in the ESW system will render that train of ESW inoperable since it must have that amount of flow, as determined by flow balance measures, to be operable.

Back 153

B

Front 154

The unit is at 100% RTP.At 1800 on 9/6, EF-HV038, "B" Train ESW Return to Ultimate Heat Sink Isolation Valve will NOT automatically open because of a failure in the valve control circuit.What is required by Technical Specifications? A. Restore "B" ESW train to OPERABLE by 1800 on 9/7.B. Be in Mode 3 by 2400 on 9/6.C. Declare "B" RHR train INOPERABLE at 1800 on 9/6.D. Declare "B" EDG INOPERABLE at 1800 on 9/6.

Back 154

D

Front 155

An automatic reactor trip and safety injection occurred when RCS pressure began decreasing in an uncontrolled manner.Operators noted the following conditions:* Pressurizer pressure decreasing following SI* RCS average temperature stable prior to SI* Pressurizer level increasing prior to SI and increasing following SI* Reactor power stable prior to SI What condition could cause these indications? A. Small break LOCA on cold leg.B. Main steamline break.C. Guillotine shear of hot leg.D. Stuck open PZR safety.

Back 155

D

Front 156

While at full power, the selected pressurizer channel fails. Assuming no operator action, what channel failure will cause a Safety Injection Actuation? A. PZR pressure channel 455 fails low.B. PZR level channel 459 fails high.C. PZR pressure channel 455 fails high.D. PZR level channel 459 fails low.

Back 156

C

Front 157

How would the PZR Block Valves respond if pressure decreased to 2180 psig then quickly recovered to 2235 psig? A. Close fully then immediately reopen.B. Close fully then open after a 2 second time delay.C. Closed and remain closed unless re-opened by the Operator.D. Start closing but reverse when pressure recovers > 2185 psig.

Back 157

B

Front 158

Block valve BB HV-8000B is isolated due to seat leakage. A transient causes pressure to drop to 2150 psig.What would be the response of BB HV-8000A to pressure increasing to 2190 psig then quickly decreasing to 2180 psig? A. Fully open and remain open unless re-closed by the Operator.B. Fully open, then immediately start closing.C. Start opening, but reverse as soon as pressure decreases less than 2185 psig.D. Fully open, then start closing after a 2 - 4 second time delay.

Back 158

D

Front 159

What input(s) are used to determine pressurizer level setpoint? A. Turbine 1st Stage Impulse PressureB. Actual Pressurizer Level and No Load TavgC. PZR pressure and selected PZR levelD. Auctioneered high Tave

Back 159

D

Front 160

The pressurizer level setpoint is calculated as a function of which one of the following? A. Turbine first stage pressureB. Reactor powerC. RCS delta TD. RCS T-avg

Back 160

D

Front 161

While performing STS CR-001 shift logs for Modes 1, 2 and 3 with the unit at 100% RTP, the following Pressurizer Pressure readings are taken:Channels PressureBB PI-458 2235BB PI-457 2190BB PI-456 2235BB PI-455A 2245What action is required? A. Place the channel in the tripped condition within six hours.B. Place the channel in the tripped condition within one hour.C. Bypass the channel and declare the channel inoperable.D. Verify the minimum number of channels operable and continue operation.

Back 161

A

Front 162

The following plant conditions exist:* 100% RTP* PZR level control LS-459D is selected for BB LT-459/461* PZR level channel BB LT-459 has just failed low.Which one of the following describes the plant response to the pressurizer level channel failure? (Assume NO operator action taken) A. Letdown isolation occurs, VCT level increases, charging flow decreases, and actual PZR level decreases.B. Charging flow remains the same, letdown isolation does not occur, backup heaters turn on.C. Letdown isolation occurs, charging flow increases, actual PZR level increases, and reactor trips on high PZR level.D. Charging flow decreases, letdown isolation occurs, heaters ed-energize, and reactor trips on low pressurizer pressure.

Back 162

C

Front 163

During operation at 95% power and pressurizer level at 48%, the Tavg input to the pressurizer level controller fails low. What indications does the operator have that the Tavg input failed low? A. Backup heaters are energized, charging flow control valve slowly closes, high level deviation alarm actuates.B. Backup heaters are energized, charging flow control valve slowly opens, low level deviation alarm actuates.C. Backup heaters are de-energized, charging flow control valve slowly closes, high level deviation alarm actuates.D. Backup heaters are de-energized, charging flow control valve slowly opens, low level deviation alarm actuates.

Back 163

A

Front 164

Wolf Creek is entering Mode 4 from Mode 3 with the following conditions:* RCS pressure is being controlled at 600 psig.* All wide range cold leg temperatures are 3500F.* Cold overpressure protection is in "ARMED".* Loop 1 wide range cold leg temperature sensor, TE-413B fails low.Which one of the following describes the plant response to this failure? A. Only PORV 456A will open.B. Both PORV 455A and 456A will open.C. Neither PORV 455A or 456A will open.D. Only PORV 455A will open.

Back 164

A

Front 165

Plant conditions are as follows:* Mode 1* 100% Reactor Power* Tavg 586.5 F* Normal Charging Pump (NCP) running with FCV-462 in Auto* Pressurizer level controller, BB LK-459 in AUTO* BB LT-459 is the selected channelBB LT-459 fails HIGHWith NO operator action, which one of the following will occur? A. The reactor will trip on PZR High level after a period of time.B. The reactor will immediately trip on PZR High level.C. The reactor will trip on PZR low level after a period of time.D. The reactor does not trip due to PZR level for this condition.

Back 165

D

Front 166

The pressure control system is designed to handle which of the following transients without actuating a reactor trip? A. 25% step load reduction without auto rod control and auto steam dump operation.B. 50% step load reduction with auto steam dump and auto rod control operation.C. 10% per minute load ramp without auto rod control.D. 15% step load change with auto rod control.

Back 166

B

Front 167

The plant is operating at steady-state 100% power. The pressurizer master controller setpoint is then inadvertently changed from 2235 psig to 2370 psig. (Assume a step change in setpoint with PZR pressure controller remaining in automatic.What will be the immediate automatic response of the pressurizer pressure control system? A. Pressurizer PORVs PCV-455A and PCV-456A open, pressurizer spray valves full open, and pressurizer heaters energize.B. PORV PCV-455A opens, spray valves full open and the PZR heaters de-energize.C. PZR spray valves full open and pressurizer heaters energize.D. Pressurizer spray valves close, if open, and pressurizer heaters energize.

Back 167

D

Front 168

Which of the following will energize the pressurizer backup heaters? A. Pressurizer pressure deviation (+/- 25 psid) from normal setpoint of 2235 psig.B. PZR level deviation (+5%)C. Pressurizer level deviation (-5%)D. Pressurizer pressure 2220 psig.

Back 168

B

Front 169

A plant cooldown is in progress when the pressurizer level unexpectedly decreases to 17%. Which of the following is the correct description of the plant response to this occurrence? A. Pressurizer backup heater energize at 15% below program level to prevent a large pressure drop.B. RWST suction valves to the charging pumps automatically open and the VCT is isolated to prevent loss of RCP seal backpressure.C. Letdown isolation occurs, closing orifice isolation valves, and letdown isolation valves to conserve pressurizer inventory.D. Centrifugal charging pump speed increases to inject more water into the pressurizer.

Back 169

C

Front 170

The following parameters exist after a small transient has occurred.* Reactor power 100%* PZR level 60%* PZR pressure 2219 psig* Tavg 5800F* Centrifugal charging pump "B" supplying normal chargingThe reactor operator should expect the PZR pressure and level control system to respond by: A. energizing the backup heaters.B. opening normal pressurizer spray valves.C. modulating BG FCV-121 open to increase level to 61.5%.D. modulating the variable heaters to a minimum current value.

Back 170

A

Front 171

Given the following conditions:* The plant is at 50% power.* A single Tavg channel fails high* Pressurizer level control is in automaticWhat is the expected effect on the pressurizer level control system? A. PZR level increases to 92% and causes reactor tripB. PZR level decreases to 27% and stabilizesC. PZR level increases to 57% and stabilizesD. PZR level remains stable at present value

Back 171

C

Front 172

Following a plant transient, the plant is now stable with the following conditions:* Reactor Power = 100%* Tavg = 5800F* Pressurizer level = 56%Which of the following main control board alarms would be in alarm? A. None, the pressurizer level is on program.B. PZR LO LEV DEVC. PZR HI DEV HTS OND. PZR LEV HI

Back 172

C

Front 173

Which one of the following conditions will send a signal to open the pressurizer PORV block valves? A. Low Temperature Overpressure Protection Armed (LTOP)B. Low Pressurizer pressure block on P-11C. Low Pressurizer pressure SID. High Pressurizer pressure

Back 173

A

Front 174

Which one of the following is an input to the Low Temperature Over Pressure Protection circuitry for PZR PORV BB PCV-456? A. Narrow range pressurizer instrument, BB PT-456B. Auctioneered high wide range cold leg temperatureC. Wide range pressure instrument, BB PT-403D. Auctioneered high Tavg

Back 174

C

Front 175

Loss of PA02 bus will have what effect on the pressurizer pressure control system? A. De-energize the heater group "A"B. De-energize the heater group "B" & "C"C. De-energize the heater group "B"D. De-energize the heater group "C" (variable heater)

Back 175

D

Front 176

PZR level transmitter, BB LT-459 is selected for control.What will be the instrument and plant response when BB LT-459 develops a slow leak on the reference leg? A. PZR LVL indication decreasing; VCT level increasingB. PZR LVL indication decreasing; VCT level decreasingC. PZR LVL indication increasing; VCT level IncreasingD. PZR LVL indication increasing; VCT level decreasing

Back 176

C

Front 177

The plant is operating at 100% power. The controlling pressurizer level channel LT-459 fails low (indicated 0%). A. Both backup heaters de-energize and the variable heaters modulate to minimum current.B. The reactor would trip on pressurizer high level.C. BG FCV-121 would modulate open if the NCP was operating.D. Letdown isolation valves (BG HV-459 & 460) would close.

Back 177

B

Front 178

The plant was at NOT/NOP when the following occurred.Annunciator alarms activated:* PRZR PORV OUT TEMP HI* PRZR PRESS DEV HIPlant conditions:* Mode 1* P455/P456 is selected for PRZR pressure control* PRZR Control Heater Group "C" --OFF* BB PCV-455B, PRZR Spray Valve -- OpenWhat has occurred and what is the expected position of PRZR PORV BB-PCV-456? (not all alarms/indications given, and only one component has failed) A. BB PI-456, PRZR PRESS CHAN II failed at 2235 psig, BB PCV-456 is shut.B. BB PI-455A, PRZR PRESS CHAN I failed high, BB PCV-456 is shut.C. BB PI-455A, PRZR PRESS CHAN I failed high, BB PCV-456 is open.D. BB PI-456, PRZR PRESS CHAN II failed at 2235 psig, BB PCV-456 is open

Back 178

B

Front 179

The controlling channel for the pressurizer level control system has failed high.With no operator action, what is the expected system response? A. Charging flow increases and VCT level decreases until AUTO swapover to the RWST occurs.B. Charging flow will decrease and VCT level increase due to the failure of the pressurizer level input to the AUTO makeup circuitry.C. Charging flow will increase and actual pressurizer level will increase due to buildup on the integral controller.D. Charging flow will decrease and actual pressurizer level will decrease.

Back 179

D

Front 180

How would the PZR Block Valves respond if pressure decreased to 2180 psig then quickly recovered to 2235 psig? A. Close fully then open after a 2 second time delay.B. Close fully then immediately reopen.C. Closed and remain closed unless re-opened by the Operator.D. Start closing but reverse when pressure recovers > 2185 psig.

Back 180

A

Front 181

A PZR vapor space LOCA has caused SI to actuate. Core Exit TCs stabilize at 5500F. RCS pressure stabilizes at 1400 psig. PZR level is 20% and increasing. SI cold leg injection flow is 400 gpm. (Assume RCS temperature remains constant)With no operator action, how will PZR level, RCS pressure, and ECCS flow respond? A. PZR level will stabilize, RCS pressure will increase, and ECCS flow will decrease.B. PZR level will stabilize, RCS pressure will decrease, and ECCS flow will increase.C. PZR level will increase, RCS pressure and ECCS flow will remain constant.D. PZR level will increase, RCS pressure will increase, and ECCS flow will decrease.

Back 181

D

Front 182

Offsite power was lost and cannot be regained. BG HV-8160, Letdown Containment Isolation Valve, closed and cannot be re-opened.What component should be used to control RCS pressure? A. Auxiliary SprayB. Condenser Steam DumpsC. Pressurizer PORVsD. Normal PZR Spray

Back 182

C

Front 183

The plant is at 100% power. Power Range Channel N41 has failed high and all required actions of OFN SB-008 are complete when PZR Pressure Channel PT-456 fails low.What reactor trip logic is satisfied as a result? A. OPdeltaT Reactor TripB. PZR High Pressure Reactor TripC. OTdeltaT Reactor TripD. PZR Low Pressure Reactor Trip

Back 183

C

Front 184

At 60% power what is the normal (no alarms) PZR Level band? A. 17% to 60%B. 45% to 55%C. 40% to 50%D. 55% to 65%

Back 184

C

Front 185

Charging, letdown, and the PZR Level Control System are in automatic, and CCP "A" is in service.The following plant conditions exist: Letdown heat exchanger outlet flow (BG FI-132) 118 gpm Charging header flow (BG FI-121A) 130 gpm Total seal injection flow to RCPs (BG FI-215A/B) 32 gpmThe controlling PZR level channel fails high to 100%.What affect does this failure have on seal injection flow? (Assume NO operator action) A. Increase to approximately 75 gpm.B. Decrease to approximately 12 gpm.C. Decrease to approximately 0 gpm.D. Increase to approximately 45 gpm.

Back 185

C

Front 186

At 100% power, PZR Pressure Master Controller (BB PK-455A) is placed in MANUAL and both PZR B/U Heaters are ON in manual.How would PZR PORVs operate as RCS pressure increases toward 2400 psig? A. PORVs won't open automatically.B. PORV BB-PCV-456A opens.C. PORV BB-PCV-455A opens.D. Both PORVs open.

Back 186

B

Front 187

PZR Heater Backup Group "A" is energized by the control switch at the Auxiliary Shutdown Panel (in CLOSED position).What would automatically trip PZR heater breaker (PG2101) in this condition? A. SISB. Lockout on NB0106C. NB02 UndervoltageD. Pressurizer Low Level

Back 187

B

Front 188

The breaker for PZR Heater Group "C" is CLOSED.What three conditions will open the breaker? A. PA0207 Lockout, PZR High Pressure, PZR Low Level.B. PZR Low Level, BB HIS-50 in P-T-L, PA0207 Lockout.C. BB HIS-50 in P-T-L, PA0207 Lockout, PZR High Pressure.D. PZR High Pressure, PZR Low Level, BB HIS-50 in P-T-L.

Back 188

B

Front 189

What is the response when PZR PORV Block Valves (BB HV-8000 A & B) remote switches are placed in "ISO/CLOSE" and the valves are open? A. Valves remain open, position indication lost at MCB.B. Valves close, position indication available at MCB.C. Valves remain open, position indication available at MCB.D. Valves close, position indication lost at MCB.

Back 189

D

Front 190

The following plant conditions exist: Reactor Power 83% RCS T-avg 579.50F Pressurizer Level 53%What is "PROGRAM" PZR Level? A. 54%B. 49.5%C. 42.5%D. 52%

Back 190

B

Front 191

At 100% power, BB PT-455 (PZR Pressure Master controller) controlling channel failed HIGH.What component is FIRST to automatically respond to this failure? A. PZR heaters turn on.B. PZR PORV BB-PCV-455A opens.C. PZR Block Valve BB-HV-8000A opens.D. PZR spray valves shut.

Back 191

B

Front 192

What potentiometer setting on the PZR Pressure Master Controller would maintain RCS pressure at 2000 psig in automatic? A. 6.25B. 8.33C. 3.75D. 8.0

Back 192

C

Front 193

What protective function is NOT common between PZR Pressure Channels PT-455 and PT-458? A. P-11B. OTdeltaTC. Low pressure reactor tripD. High pressure reactor trip

Back 193

A

Front 194

Which of the following transients is within the design limits of the pressurizer pressure and level control systems without a reactor trip? A. A 10% per minute ramp load decrease with rod control in automatic.B. A 7% per minute ramp load increase with automatic rod control.C. A 100% load rejection using steam dumps and rod control in manual.D. A 10% step load decrease with automatic rod control and steam dumps.

Back 194

D

Front 195

The plant is operating at 75% steady-state power when reactor coolant pressure rapidly increases due to a transient. Assume all controllers are in automatic with "B" B/U heaters on.What accurately describes pressurizer PORV response? A. BB PCV-455A will open first due to the controller integral function.B. BB PCV-456A will open first due to the relative setpoint compared to BB PCV-455A.C. BB PCV-456A will open first due to the lagging feature on the controller for BB PCV-455A.D. BB PCV-455A will open first due to the controller derivative (rate) function.

Back 195

A

Front 196

The pressurizer pressure control system is in automatic with BB-PT455 controlling and BB-PT458 selected as backup channel.What is the immediate effect of BB-PT458 failing to 2500?psig? A. PZR backup heaters de-energize.B. PZR PORV BB-PCV456 opens.C. PZR variable heaters go to zero (0) voltage.D. PZR PORV BB-PCV455 opens.

Back 196

B

Front 197

Given the following conditions:* Reactor power is at 99%* Pressurizer level is at 58%* 120 gpm letdown flow* NCP in serviceCharging line containment outside isolation valve (BG HV-8105) has failed CLOSED.With NO operator action, what describes the plant response to this failure? A. Decreasing pressurizer level to 17%, letdown isolates and heaters turn off leading to low pressure trip.B. Slightly lower pressurizer level due to isolation of letdown upon loss of cooling flow and steam flashing in letdown line.C. Slightly higher pressurizer level due to isolation of letdown with continued seal injection flow to recover level.D. Decreasing pressurizer level to 17%, letdown isolates and pressurizer level slowly increases back to program value.

Back 197

D

Front 198

The method used at WCGS to control level in the Pressurizer is to vary the: A. spray flow into the PressurizerB. position of LCV-112CC. speed of the Centrifugal Charging PumpD. position of FCV-121 or FCV-462

Back 198

D

Front 199

The plant was operating at 50% power at BOL with all control systems in AUTOMATIC when a 10% step load DECREASE occurred. If no operator actions are taken, ACTUAL pressurizer level will: A. increase throughout the transientB. decrease throughout the transientC. increase initially, then decreaseD. decrease initially, then increase

Back 199

C

Front 200

The Reactor Coolant System (RCS) is at 1000 psig, with a plant cooldown in progress.What action will occur when the operator arms Low Temperature Over Pressure Protection and RCS temperature is 4000F? A. Pressurizer heaters are blocked.B. Pressurizer PORVs open.C. Residual Heat Removal pump hot leg suction valves open.D. Pressurizer PORV block valves open.

Back 200

D

Front 201

The plant is in Mode 3 at normal operating pressure and temperature, train "A" Low Temperature Over Pressure Protection System (LTOP) has inadvertently been left ARMED for cold overpressure protection.The selected pressurizer pressure channel BB PT-455 fails high.With no operator action, what is the expected plant response? A. PORV PCV-455 stays closed, but will function as required for COPS.B. PORV PCV-455 opens and stays open.C. PORV PCV-455 opens and PORV block valve 8000A closes when actual PZR pressure decreases to <2185 psig.D. PORV 455 opens, then closes when actual PZR pressure decreases to <1976 psig.

Back 201

B

Front 202

How are the RCS and pressurizer boron concentrations maintained to prevent unwanted reactivity changes? A. Letdown flow is periodically increased to dilute the pressurizer boron concentration.B. Bypass flow around the spray valves will provide all the chemical mixing necessary.C. Charging flow is periodically increased to flush the pressurizer.D. Normal spray flow is continually in service to provide mixing.

Back 202

B

Front 203

The crew is increasing power from 30% to 100% power at 10%/hr.Why are pressurizer backup heaters placed in manual for this evolution? A. Allow for an increased ramp rate for the power increase.B. Ensure positive pressure control is established prior to starting the power increase.C. Maintain PZR pressure within the normal operating band for the expected PZR insurge as power is increased.D. Equalize the reactor coolant system and PZR boron concentration.

Back 203

D

Front 204

Technical Specification Limiting Condition for Operation 3.4.9, requires the pressurizer to be OPERABLE.What is a description for this required condition for OPERABILITY? A. One group of variable heaters and one group of backup heaters, each having a capacity of at least 150KW and a water level of less than or equal to 92%.B. Two groups of backup heaters, each having a capacity of at least 150KW and a water level of less than or equal to 92%.C. Two groups of backup heaters, each having a capacity of at least 150 KW and a water level of less than or equal to 70%.D. One group of backup heaters having a capacity of 150KW and a water level of less than or equal to 70%.

Back 204

B

Front 205

The plant is at 100% power with all equipment operating properly when breaker PG-2104 (fdr. Bkr to Heater Banks 33, 61, 62) trips and will not close.What is the status of the Pressurizer? A. Inoperable, and the plant needs to be in at least HOT STANDBY with Reactor Trip Breakers open in 6 hours.B. Inoperable, not required to be restored in 72 hours.C. Operable, but at reduced heater capacity.D. Operable and at full heater capacity.

Back 205

C

Front 206

The unit is in Mode 1. One required group of backup pressurizer heaters is found to be inoperable from supply breaker problems at 0800 on 8/1.What are the required TS Actions? A. Restore to OPERABLE status by 0800 on 8/4.B. Restore to OPERABLE status by 0815 on 8/1.C. Insert all rods with the Rod Control System incapable of rod withdrawal by 1400 on 8/1.D. Be in Mode 3 by 1400 on 8/1.

Back 206

A

Front 207

The following conditions exist:Reactor and Turbine power are at 40%.Rod control is in manual.Pressurizer level is at 39%.Loop Tave A - 568.8 B - 569.4 C - 569.0 D - 568.7All other systems are normally aligned in AUTOMATIC.If a Loop B T-hot RTD were to fail LOW, assuming NO operator action, pressurizer level will: A. decrease to 17%.B. decrease to 27%.C. remain at 39%.D. increase to 57%.

Back 207

C

Front 208

The following conditions exist:Reactor and Turbine power are at 40%.Rod control is in manual.Pressurizer level is at 39%.All other systems are normally aligned in AUTOMATIC.If a T-hot RTD were to fail HIGH, assuming NO operator action, pressurizer level will: A. decrease to 17%.B. remains at 39%.C. increase to 47%.D. increase to 57%.

Back 208

C

Front 209

Assume a Main Steam Line Break occurred inside containment. How does this affect INDICATED PZR level for LT-459? A. Fails off-scale low.B. Same as actual level.C. Lower than actual level.D. Higher than actual level.

Back 209

D

Front 210

A large loss of coolant has occurred inside containment and has raised containment pressure to 8 psig. Describe the effects containment pressure will have on indicated pressurizer level. A. Actual level will go down due to reference leg density decreasing.B. Indicated level will go up due to reference leg density decreasing.C. Actual level will not be affected by the non-adverse containment conditions.D. Indicated level will not be affected since reference legs are insulated.

Back 210

B

Front 211

The plant is in Mode 1 when breaker PG2101 trips open and CANNOT be closed.What impact, if any, on plant operations would result? A. Restore heaters to operable within 72 hours or be in Hot Standby within six hours.B. Restore heaters to operable within 72 hours or be in Hot Standby within four hours.C. Be in Hot Standby within six hours and Hot Shutdown within an additional six hours.D. If Pressurizer backup heaters with at least 300 KW capacity are operable, there is no impact.

Back 211

A

Front 212

The plant is at 85% power when it is determined that PORV BB-PCV-456A has excessive seat leakage. All other equipment is operable.What action must be performed? A. Within one hour shut its block valve.B. Restore the PORV within 72 hours.C. Restore the PORV within one hour.D. Within one hour, shut its block valve and remove block valve power.

Back 212

A

Front 213

The plant is at 50% power when a small steam space leak begins contacting the reference leg of BB LT-459, a controlling pressurizer level channel. All systems are in automatic.How does this event affect the plant? A. LT-459 will indicate higher than actual level, PZR B/U heaters may energize.B. LT-459 will indicate lower than actual level, CVCS charging flow will increase.C. LT-459 will indicate higher than actual level, CVCS will not be affected.D. LT-459 will indicate lower than actual level, PZR B/U heaters may trip.

Back 213

A

Front 214

The plant is at 2% power when the Pressurizer Level channel 459 fails low.What impact does this failure have on plant startup? A. The instrument must be repaired before entering Mode 1.B. The channel must be tripped before entering Mode 1.C. The channel must be tripped within six hours after increasing power above 10%.D. The instrument must be repaired within six hours or the plant must be in Hot Standby within the next six hours.

Back 214

C

Front 215

Charging, letdown, and the Pressurizer Level Control System are in automatic, and Centrifugal Charging Pump A is in service.The following plant conditions exist:* Letdown heat exchanger out flow (BG FI-132) = 118 gpm* Charging header flow (BG FI-121) = 130 gpm* Total seal injection flow RCPs (BG FI-215) = 32 gpmThe controlling Pressurizer level control channel fails high to an indicated 100%.What will seal injection flow do? A. increase to approximately forty-five (45) gpm.B. increase to approximately seventy-five (75) gpm.C. decrease to approximately twelve (12) gpm.D. decrease to approximately zero (0) gpm.

Back 215

D

Front 216

The plant is in MODE 5 solid plant operations. What indication is the best predictor of pressurizer pressure trend? A. VCT level.B. RHR discharge temperature.C. RHR flow.D. RCS temperature.

Back 216

A

Front 217

When necessary to run more than one Service Water Pump, care should be taken to select pumps powered from separate buses.Why is this a precaution? A. To even out the flowrate in the suction bays.B. To evenly distribute the heat load on power block pump room Heating, Ventilation, and Air Conditioning.C. To evenly distribute gland water pressure to the Circulating Water Pumps.D. To minimize the effect on the Service Water System due to a loss of power on one of the buses.

Back 217

D

Front 218

Which of the following is a Power Block system load supplied by the Service Water during normal operation? A. Auxiliary FeedwaterB. Essential Service WaterC. Domestic WaterD. Circulating Water

Back 218

B

Front 219

What two conditions will cause all of the cross-tie valves between Service Water and Essential Service Water Systems to close? A. Loss of Offsite Power; SISB. Loss of ESW pressure; SISC. Loss of ESW pressure; trip of all Service Water PumpsD. Loss of Offsite Power; trip of all Service Water Pumps

Back 219

A

Front 220

Which of the following describes the location of the controls for stopping/starting the Service Water Pumps? A. Main Control Board, CWSH Standby Panel, and locally at the pump motor switchgear.B. CWSH Standby Panel, Auxiliary Shutdown Panel, and PA01/PA02 bus switchgear.C. CWSH Standby Panel, locally at the CWSH Service Water Pump switchgear and PA01/PA02 Bus Switchgear.D. Main Control Board, CWSH Standby Panel, and Auxiliary Shutdown Panel.

Back 220

A

Front 221

While operating at 100% a loss of power occurs to C Circulating Water and A Service Water Pumps.Which bus has lost power? A. SL-1B. SL-2C. SL-3D. SL-4

Back 221

D

Front 222

Which of the following is a system considered to be a site auxiliary load of the Service Water System? A. Radwaste DischargeB. Domestic WaterC. Fire ProtectionD. Emergency Eyewash

Back 222

C

Front 223

Which of the following will NOT cause an automatic isolation of the Essential Service Water System from the Service Water System? A. Loss of Site PowerB. Emergency Diesel Generator Manual StartC. Safety Injection SignalD. Low Suction Pressure with AFAS-T present

Back 223

B

Front 224

The Service Water System Strainer backwash operations initiate once every _____ hours. The automatic function should initiate at a differential pressure of _____ psid. A. 8; 8B. 4; 8C. 8; 4D. 4; 4

Back 224

C

Front 225

The purpose of the CWSH standby control panel 1PL14J is to: A. provide additional controls and indication for CWSH equipment that is not available in the Main Control Room.B. prevent inadvertent operation of CWSH equipment during Main Control Board maintenance.C. allow local control of the Circulating Water Pumps and the Service Water Pumps.D. limit the amount of controls and indications that must be processed by the master panel.

Back 225

C

Front 226

Which of the following is a condition that will cause a trip of a Service Water Pump? A. Neutral ground overcurrentB. Low suction pressureC. Low inlet bay levelD. High discharge pressure

Back 226

A

Front 227

Following an ESFAS Actuation, what condition results in an unlit indication on the engineered safeguard feature status panel, SA066X, Y, & Z? A. 74 Status Relay FailureB. In safeguards positionC. Loss of powerD. Not in safeguards position

Back 227

D

Front 228

Which describes when a system level red light is manually actuated on the engineered safeguard feature status panels, SA066X, Y, & Z? A. The last component in the system is let red and the component handswitch is in normal after run.B. A component/system has no component level window and cannot perform its safeguard functionC. A system that should have actuated its system level red light, but did not.D. A system that is known to be in its safeguard alignment, but the components do not show proper alignment.

Back 228

B

Front 229

The plant experienced a refueling outage and is ready to return to service. The P-8 permissive has been satisfied.Which one of the following would be the expected color of the window seen on the reactor partial trip status permissive/block indicating panel for the permissive? A. GreenB. WhiteC. YellowD. Red

Back 229

A

Front 230

At 100% power a leak develops in the Circulating Water header to the condenser. Vacuum is decreasing.What indication would panel SC-066W show for this condition? A. Red lights extinguishing.B. Red lights illuminating.C. White lights extinguishing.D. Blue lights extinguishing.

Back 230

D

Front 231

An inadvertent safety injection occurred. Operators are performing EMG ES-03, SI TERMINATION, and preparing to reset the SI.What is the indication if only one SI train resets? A. SI actuate light on SB069 would blink and automatic SI would re-initiate after 60 seconds.B. SI actuate light would not extinguish since either switch will reset the SI actuate light.C. SI actuate light on SB069 would blink since reset switches are train specific.D. SI actuate light would not extinguish and automatic SI would re-initiate after 60 seconds.

Back 231

C