ML22336A093

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U2 - Proposed Written Examination
ML22336A093
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/02/2022
From: Jeffrey Riley
Dominion Energy Nuclear Connecticut
To: Brian Fuller
NRC/RGN-I/DORS/OB
References
EPID L-2022-OLL-0007
Download: ML22336A093 (1)
v • d • e


Text

Page 1 of 100 Question #1 The plant is operating at 100% power.

  • The Reactor subsequently trips.

What is the Alternating Current (AC) electrical supply path?

A. RSST to 25A, 25B, 24C and 24D 24C to 24A and 24D to 24B B. A EDG to 24C and B EDG to 24D 24C to 24A and 24D to 24B C. RSST to 25A, 25B, 24C and 24D 24C to 22E and 24D to 22F D. A EDG to 24C and B EDG to 24D 24C to 22E and 24D to 22F

Page 2 of 100 Question #2 The plant is operating at 100% power when a Pressurizer Safety valve lifts and remains partially open.

  • Pressurizer level is 80% and rising.
1. Is Pressurizer level an accurate indication of RCS inventory?

AND

2. Why?

A. 1. No.

2. RCS voiding results in increasing Pressurizer level.

B. 1. Yes.

2. RCP flow will sweep any voids from the RCS to the Pressurizer steam space.

C. 1. No.

2. Steam bubble formation in the reference legs of the level instruments.

D. 1. Yes.

2. Voiding occurs in the Pressurizer due to the open Safety valve.

Page 3 of 100 Question #3 Given the following conditions:

  • The plant is at 100% power.
  • RCS pressure is 1950 psia and lowering.
  • Quench Tank pressure is 30 psig and rising.
1. What indication(s) is/are available to indicate a Pressurizer Safety Valve is open?

AND

2. At what pressure in the Quench Tank will it discharge to Containment?

A.

1. Tailpipe temperature only.
2. 50 psig.

B.

1. Tailpipe temperature and Acoustic Valve Monitor.
2. 50 psig.

C.

1. Tailpipe temperature only.
2. 100 psig.

D.

1. Tailpipe temperature and Acoustic Valve Monitor.
2. 100 psig.

Page 4 of 100 Question #4 A Loss of Coolant Accident (LOCA) has occurred inside Containment. The following are the current plant conditions:

  • Pressurizer pressure is 950 psia.
  • RCS Tc is 475 °F.
  • Containment pressure is 4.8 psig.

Given EOP 2541, Appendix 2, Figure 2 - RCP NPSH Curve.

1. How many RCPs must be secured?

AND

2. The RCP(s) must be secured within how many minutes?

A. 1. 2 RCPs.

2. 5 minutes.

B. 1. 2 RCPs.

2. 10 minutes.

C. 1. 4 RCPs.

2. 5 minutes.

D. 1. 4 RCPs.

2. 10 minutes.

Page 5 of 100 Question #5 The plant is at 90% power.

What condition requires tripping the Reactor and securing the affected Reactor Cooling Pumps?

A. RCP RBCCW outlet temperature increases to 130 F.

B. RCP Lower Seal temperature increases to 160 F.

C. RCP Lower Guide Bearing temperature increases to 180 F.

D. RCP Stator winding temperature increases to 250 F.

Page 6 of 100 Question #6 The plant is at 100% power.

Charging Pumps are aligned as follows:

  • CHG PP BACK-UP CNTL switch is in the P1&P2 position.
  • CHG PP OVERIDE switch is in the LEV1 position How will Pressurizer level respond to the A Charging Pump tripping?

Pressurizer level will stabilize

1.

because the

2.

A 1. at setpoint

2. Letdown Flow Controller (HIC-110) output will lower B 1. below setpoint
2. Letdown Flow Controller (HIC-110) output will lower C 1. at setpoint
2. B Charging Pump will start D 1. below setpoint
2. B Charging Pump will start.

Page 7 of 100 Question #7 A plant startup is in progress. A and B Reactor Coolant Pumps (RCPs) are running in concurrent operation with Shutdown Cooling (SDC).

An inadvertent Safety Injection Actuation Signal (SIAS) actuates on both facilities.

What temperature would RISE as a result of the SIAS signal?

A. SDC system return to the RCS.

B. A and B RCP seals.

C. Spent Fuel Pool Cooling Heat Exchanger outlet.

D. Containment atmosphere.

Page 8 of 100 Question #8 The plant is at 100% power.

  • Pressurizer Pressure Transmitter PT-100X is selected for control.
  • Pressurizer Pressure Transmitter PT-100Y is out-of-service.
  • Indicated pressure on PIC-100X begins rising.
  • Both Pressurizer Spray valves are opening.
  • Pressure is lowering on all Pressurizer Safety channels.

What action could be used to stabilize Pressurizer Pressure?

A. Place PIC-100X in MANUAL and raise its output as necessary.

B. Place PIC-100X in MANUAL and lower its output as necessary.

C. Turn the Pressurizer Proportional Heater control switches to ON.

D. Turn the Pressurizer Backup Heater control switches to ON.

Page 9 of 100 Question #9 An Anticipated Transient Without Scram (ATWS) occurred from 100% power.

What indicates the ATWS Mitigation Circuit Diverse SCRAM System (DSS) actuated?

A. All eight of the Trip Circuit Breakers (TCBs) are open.

B. Both of the MG Set 480 VAC supply breakers are open.

C. Both AFW pumps are running and both AFRVs are open.

D. The TCB indicating lights on C-04 are all de-energized

Page 10 of 100 Question #10 A Steam Generator Tube Rupture (SGTR) on the #1 Steam Generator (S/G) occurred with a subsequent Loss of Offsite Power.

Current plant conditions are:

  • RCS cooldown rate = 70 F/hr.
  • Loop 1 THOT = 462 F.
  • Loop 2 THOT = 450 F.
  • RCS pressure = 600 psia.
1. What action is required per EOP 2534, Steam Generator Tube Rupture?

AND

2. Why is this action required?

A. 1.

Raise the cooldown rate to between 80 F/hr and 100 F/hr.

2.

To ensure Shutdown Cooling is placed in service within the required time after the event.

B. 1.

Lower the RCS pressure to between 470 psia and 500 psia.

2.

To minimize the volume of water leaking from the Reactor Coolant System into the affected S/G.

C. 1.

Lower the cooldown rate to between 30 F/hr and 60 F/hr.

2.

To keep the loops coupled and ensure the isolated S/G is adequately cooled and depressurized.

D. 1.

Raise RCS pressure to between 850 psia and 900 psia.

2.

To eliminate voiding and ensure that natural circulation flow is adequate to continue the cooldown.

Page 11 of 100 Question #11 The plant is operating at 100% power.

An Excess Steam Demand Event (ESDE) occurs inside Containment.

1. A Main Steam Isolation (MSI) will occur at a Steam Generator (S/G) pressure of 1..

AND

2. Once the faulted S/G has blown dry, the intact S/G pressure will 2..

A. 1. 572 psia

2. rise B. 1. 572 psia
2. stabilize C. 1. 691 psia
2. rise D. 1. 691 psia
2. stabilize

Page 12 of 100 Question #12 The crew is aligning the Condensate pumps to feed the #1 Steam Generator (S/G) using EOP 2541, Appendix 16, LOAF Response.

Given the following plant conditions:

  • S/G #1 pressure is 650 psia and slowly lowering.
  • S/G #2 pressure is 420 psia and lowering.
  • S/G #1 level is 293 inches and slowly lowering.
  • S/G #2 level is 180 inches and lowering
  • Containment pressure is 7 psig and rising.
1. Which valves will be used to throttle feed flow?

AND

2. What is the CONTINGENCY ACTION if a valve does NOT open?

A. 1. Feedwater Regulating Valves.

2. PUSH DOWNCOMER RESET reset pushbuttons.

B. 1. Feedwater Regulating Valves.

2. PUSH MSI OVRD pushbutton.

C. 1. Feedwater Regulating Bypass Valves.

2. PUSH DOWNCOMER RESET pushbuttons.

D. 1. Feedwater Regulating Bypass Valves.

2. PUSH MSI OVRD pushbutton.

Page 13 of 100 Question #13 The plant has entered EOP 2530, Station Blackout.

1. When must DC Bus load stripping be completed?

AND

2. What loads are stripped?

A. 1. 45 minutes.

2. VA10 and VA20.

B. 1. 45 minutes.

2. VA30 and VA40.

C. 1. 75 minutes.

2. VA10 and VA20.

D. 1. 75 minutes.

2. VA30 and VA40.

Page 14 of 100 Question #14 The plant tripped due a Loss of Offsite Power.

Five (5) minutes post trip:

1. How will Reactor Coolant System (RCS) temperatures be responding?

AND

2. Why are they responding in this manner?

A. 1. THOT will be rising and TCOLD will be stable.

2. The plant is experiencing a RCS cooldown.

B. 1. THOT will be rising and TCOLD will be stable.

2. Natural circulation heat removal is building in.

C. 1. THOT will be stable and TCOLD will be lowering.

2. The plant is experiencing a RCS cooldown.

D. 1. THOT will be stable and TCOLD will be lowering.

2. Natural circulation heat removal is building in.

Page 15 of 100 Question #15 A loss of what two Vital AC Electrical Instrument buses will result in a Sump Recirculation Actuation?

A. VA10 and VA20.

B. VA20 and VA30.

C. VA20 and VA40.

D. VA30 and VA40.

Page 16 of 100 Question #16 The plant trips from 100% power.

  • Vital DC Bus DV20 is lost.
1. What component actuated due the AFAS signal?

AND

2. What component can be remotely operated?

A. 1. B AFRV.

2. TDAFW pump.

B. 1. B AFRV.

2. B AFW pump.

C. 1. A AFRV.

2. TDAFW pump.

D. 1. A AFRV.

2. B AFW pump.

Page 17 of 100 Question #17 The plant tripped from 100% power.

Which room will lose cooling as a result of the loss of Facility 1 Service Water?

A. East 480 VAC Switchgear room.

B. 25' 6" Cable Vault.

C. East DC Switchgear room.

D. Upper 4160 VAC Switchgear room.

Page 18 of 100 Question #18 The plant is operating at 100% power.

  • CONVEX requests maximum VARs output to support the grid.
  • Main generator output = 900 MWe
  • Main generator hydrogen pressure = 60 psig Given AOP 2580, Degraded Voltage, Attachment 1, Estimated Capability Curves
1. What is the VARs limit for the given conditions?

AND

2. How will you raise VARs?

A. 1. 360 MVARs.

2. ADJUST CS-70, MAN DC REG.

B. 1. 360 MVARs.

2. ADJUST CS-90, AUTO AC REG.

C. 1. 440 MVARs.

2. ADJUST CS-70, MAN DC REG.

D. 1. 440 MVARs.

2. ADJUST CS-90, AUTO AC REG.

Question #19 A reactor startup is in progress.

  • The CEA Control switch is released.
  • The CEDS OFF pushbutton is pushed and its light is lit.

The CEAs continue to withdraw.

What are your actions?

Page 19 of 100 A. Terminate the startup and insert all Regulating Group CEAs per OP 2302A.

B. Initiate Emergency Boration in accordance with AOP 2558, Emergency Boration.

C. Suspend the reactor startup and enter AOP 2556, CEA Malfunctions.

D. Trip the reactor and enter EOP 2525, Standard Post Trip Actions.

Page 20 of 100 Question #20 The plant was tripped.

  • Multiple CEAs have not inserted.
  • Reactor power is 10E-5 % and rising.
  • Charging is unavailable.
  • RCS pressure is 1950 psia.
  • 2540A, Functional Recovery of Reactivity Control, has been entered.
1. What actions will you perform to Emergency Borate?

AND

2. How will you initiate HPSI flow?

A. 1. Depressurize the RCS.

2. Manually start a HPSI pump and open a HPSI injection valve.

B. 1. Depressurize the RCS.

2. Allow SIAS to automatically initiate on lowering RCS pressure.

C. 1. Cooldown the RCS.

2. Manually start a HPSI pump and open a HPSI injection valve.

D. 1. Cooldown the RCS.

2. Allow SIAS to automatically initiate on lowering RCS pressure.

Page 21 of 100 Question #21 The crew is performing OP 2202, Reactor Startup ICCE.

What indicates a failed HIGH Wide Range Nuclear Instrument (WRNI) channel?

A. Associated Reactor Protection System (RPS) channel tripped.

B. Wide Range Nuclear Instrument (WRNI) Level 2 LED not lit.

C. All CEA motion is stopped from a CEA motion inhibit (CMI).

D. Local Power Density (LPD) and Loss of Load trips are enabled.

Page 22 of 100 Question #22 The plant was shut down due to a Steam Generator Tube Leak.

Conditions prior to the shutdown were:

  • Pressurizer pressure was 2250 psia.
  • Primary-to-secondary leakage = 20 gpm.

Post-shutdown conditions are as follows:

  • Pressurizer pressure is 1600 psia.

Approximate the post-shutdown primary-to-secondary leakage?

A. 10 gpm.

B. 14 gpm.

C. 20 gpm.

D. 28 gpm.

Page 23 of 100 Question #23 The plant is operating at 100% power. Containment radiation levels rise significantly.

1. What Radiation monitors will isolate the Hydrogen Purge valves (EB-91, 92, 99, and 100)?

AND

2. How are the vent paths configured to isolate?

A. 1. Containment Atmosphere Particulate and Gaseous radiation monitors.

2. One radiation monitor isolates only one vent path.

B. 1. Containment High Range radiation monitors.

2. One radiation monitor isolates only one vent path.

C. 1. Containment Atmosphere Particulate and Gaseous radiation monitors.

2. Either radiation monitor isolates both vent paths.

D. 1. Containment High Range radiation monitors.

2. Either radiation monitor isolates both vent paths.

Page 24 of 100 Question #24 The plant is at 100% power.

  • SP 2605A, Verifying Containment Integrity, is being performed.
  • A manual valve is found not in its required position.
1. What action will be taken per OP-AA-1500, Operational Configuration Control?

AND

2. What method will be used to verify valve position?

A. 1. Notify on-shift SRO and when directed, close the valve.

2. Independent verification.

B. 1. Notify on-shift SRO and when directed, close the valve.

2. Concurrent verification.

C. 1. Close valve then notify on-shift SRO.

2. Independent verification.

D. 1. Close valve then notify on-shift SRO.

2. Concurrent verification.

Page 25 of 100 Question #25 The Chemistry department has recommended raising Charging and Letdown flow to the maximum limit to clean up high fission product activity in the RCS.

What describes a required action and why that action must be taken when Charging and Letdown flow is raised?

A. The second Letdown Flow Control valve must be placed in service in order to raise Letdown flow to maximum.

B. Health Physics department must be notified of changes in Letdown flow because this will change radiation levels.

C. Chemistry department must verify RCS boron concentration within six hours due to a potential change in boron from raising Letdown.

D. A second Ion Exchanger must be placed in service during maximum Letdown flow to limit the Ion Exchanger delta-pressure.

Page 26 of 100 Question #26 The plant has entered EOP 2540, Functional Recovery.

  • Containment conditions are normal.

What parameter prevents you from placing Shutdown Cooling in service and exiting from the Functional Recovery procedures?

A. Pressurizer level = 25%.

B. RCS subcooling = 0 F.

C. RCS pressure = 250 psia.

D. RCS THOT = 275 F.

Page 27 of 100 Question #27 The plant is at 100% power.

  • Bus 24E is aligned to Bus 24D.
  • B RBCCW Heat Exchanger is not in service.
1. Which Reactor Coolant Pumps (RCPs) are affected by the loss of the A RBCCW pump?

AND

2. What action is procedurally directed to mitigate the consequences of this malfunction?

A. 1. A and C RCPs.

2. Align and start the B RBCCW pump.

B. 1. A and C RCPs.

2. Trip the reactor and secure A and C RCPs.

C. 1. B and D RCPs.

2. Align and start the B RBCCW pump.

D. 1. B and D RCPs.

2. Trip the reactor and secure B and D RCPs.

Page 28 of 100 Question #28 The plant is operating at 100 % power.

  • Auxiliary Steam is secured.

If either the (-) 5 or (-) 25 Auxiliary Building temperature drops below 1., your actions would be to 2..

A. 1. 35 °F

2. REMOVE Radwaste Ventilation from service B. 1. 35 °F
2. ENSURE Boric Acid Heat Tracing is energized C. 1. 65 °F
2. REMOVE Radwaste Ventilation from service D. 1. 65 °F
2. ENSURE Boric Acid Heat Tracing is energized

Page 29 of 100 Question #29 The plant experienced a Large Break LOCA 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.

  • Bus 24C is de-energized.
  • EOP 2541, Appendix 18 Simultaneous Hot and Cold Leg Injection is entered.
1. What flowpath will be aligned for Simultaneous Hot and Cold Leg Injection?

AND

2. What procedural action is required to achieve a Hot Leg flowpath?

A. 1. Primary Flowpath (Shutdown Cooling/LPSI).

2. Align SI-651, SDC Isolation, power to Facility 2.

B. 1. Primary Flowpath (Shutdown Cooling/LPSI).

2. Align LPSI injection valves so one valve is open to each loop.

C. 1. Alternate Flowpath (Pressurizer/HPSI).

2. Align SI-651, SDC Isolation, power to Facility 2.

D. 1. Alternate Flowpath (Pressurizer/HPSI).

2. Align LPSI injection valves so one valve is open to each loop.

Page 30 of 100 Question #30 The plant is operating at 100% power.

Select the proper electrical alignment/indication for SYS ISOL, SI-651 (C-01).

Breaker Disconnect Green light A.

Open Open NOT lit B.

Open Closed NOT lit C.

Closed Open Lit D.

Closed Closed Lit

Page 31 of 100 Question #31 The plant has experienced a LOCA and is performing the actions of EOP 2532, Loss of Coolant Accident.

  • SRAS has initiated and all supplemental actions performed.

EOP 2532, identifies which of the following as a cause of Containment Spray Pump motor amps becoming erratic?

A. LPSI pumps are robbing CS flow.

B. HPSI pumps are robbing CS flow.

C. Containment Sump Screens are becoming blocked.

D. Containment Spray Nozzles are becoming blocked.

Page 32 of 100 Question #32 The plant is operating at 100% power.

Describe how a SIAS signal will affect the HPSI injection valves.

A. The valves will open to their full open position.

B. The valves will open to their throttled position.

C. The valves will not move due to their opening limit switch being met.

D. The valves will not move due to their opening coils being removed.

Page 33 of 100 Question #33 The plant is operating at 100% power.

  • A Pressurizer Code Safety Valve opens.
  • Pressurizer pressure is lowering.
1. How would the Pressurizer Quench Tank pressure respond?

AND

2. What actions will you take to mitigate this event?

A. 1. Rise and stabilize at a higher pressure.

2. Perform Immediate Operator Actions then enter AOP 2585.

B. 1. Rise and stabilize at a higher pressure.

2. Trip the plant then enter EOP 2525, Standard Post Trip Actions.

C. 1. Rise and then lower to below its peak pressure.

2. Perform Immediate Operator Actions then enter AOP 2585.

D. 1. Rise and then lower to below its peak pressure.

2. Trip the plant then enter EOP 2525, Standard Post Trip Actions.

Page 34 of 100 Question #34 Limiting RBCCW flow to 4800 gpm through the Shutdown Cooling Heat Exchanger prevents A. erosion of the heat exchangers shell.

B. erosion of the heat exchangers tubes.

C. run-out of the RBCCW pump.

D. robbing other RBCCW loads of cooling water.

Page 35 of 100 Question #35 Instrument Air is lost to 2-SW-8.1A, A RBCCW HX TEMPERATURE CONTROL VALVE.

Describe the actions taken to control RBCCW temperature.

A. Take Local Manual control and throttle of 2-SW-8.1A.

B. Align Back-Up air bottles to 2-SW-8.1A.

C. Throttle 2-SW-9A, A RBCCW HX SW OUTLET STOP.

D. Throttle 2-SW-8A, A RBCCW HX SW INLET STOP VALVE.

Page 36 of 100 Question #36 The plant is operating at 100% power when a plant transient results in the following:

  • Pressurizer level = 69.6%.
  • RCS pressure = 2315 psia.

How will the Pressurizer Pressure Control System respond?

Spray Valves Backup Heaters A.

Closed De-energized B.

Closed Energized C.

Partially Open De-energized D.

Partially Open Energized

Page 37 of 100 Question #37 The plant is operating at 100% power.

  • RPS Channel A High Power trip is bypassed
  • RPS Channel B Linear Range Nuclear Instrumentation power supply fails.

Describe the effect on the plant.

A. RPS will trip the unit.

B. RPS is in a 1 out of 2 logic.

C. RPS is in a 2 out of 3 logic.

D. RPS processes a partial trip.

Page 38 of 100 Question #38 The plant is operating at 100% power.

A transient occurs with the following conditions indicated (C-04):

  • MG-A Green light - LIT
  • MG-A Red light - NOT LIT These indications show the A Motor Generator set 1. is 2. ?

A. 1. Bus 22E Feeder Breaker.

2. Open.

B. 1. Bus 22E Feeder Breaker.

2. Closed.

C. 1. Output Contactor.

2. Open.

D. 1. Output Contactor.

2. Closed.

Page 39 of 100 Question #39 The plant is at 100% power.

  • D CAR fan is in Standby.
  • 2-RB-28.3D, EMERG OUTLET, is closed.
  • Intake temperature is 60 F.

An inadvertent SIAS occurs on Facility 2.

Containment temperature will 1. and Facility 2 RBCCW temperature will 2..

A. 1. rise

2. rise B. 1. lower
2. lower C. 1. rise
2. lower D. 1. lower
2. rise

Page 40 of 100 Question #40 The plant is operating at 100% power.

  • An Excess Steam Demand (ESD) occurs inside Containment.
  • RCS pressure = 1700 psia and lowering.
  • Facility 1 SIAS does NOT actuate.
1. The SIAS pushbutton 1. need to be pushed to actuate Facility 1 SIAS.

AND

2. The CSAS pushbutton 2. need to be pushed to actuate Facility 1 CSAS.

A. 1. does

2. does B. 1. does
2. does not C. 1. does not
2. does D. 1. does not
2. does not

Page 41 of 100 Question #41 What could cause runout conditions of a Containment Spray pump?

A. Clogged spray nozzles.

B. Closed suction valve.

C. Discharge line rupture.

D. Suction line rupture.

Page 42 of 100 Question #42 The purpose of the Tri-Sodium Phosphate (TSP) baskets is to 1. the pH of the Containment Sump water to minimize the amounts of 2. in the Containment atmosphere.

A. 1. raise

2. hydrogen B. 1. raise
2. iodine C. 1. lower
2. hydrogen D. 1. lower
2. iodine

Page 43 of 100 Question #43 The plant tripped from 100% power.

  • ALL Condenser Steam Dumps are open.
  • BOTH Atmospheric Dump Valves are closed.

What parameter is being used to control RCS temperature?

A. T-COLD B. T-AVERAGE C. S/G Pressure D. Main Steam Line Pressure

Page 44 of 100 Question #44 The plant is operating at 100%.

  • Steam Flow transmitter F4243A is reading normal.
  • Feed Flow transmitter F5268A is reading higher than normal.
  • Level transmitter L5271 is reading 3% higher than normal
  • Level transmitter L5272 is reading 3% lower than normal What can you determine from these indications?

A. Feed Flow transmitter F5268A is failing high B. Feed Flow transmitter F5268B is failing low C. Level transmitter L5271 is failing high D. Level transmitter L5272 is failing low

Page 45 of 100 Question #45

1. State the minimum allowed operating speed for the Turbine Driven AFW pump.

AND

2. What is the basis for this limit?

A. 1. 1400 rpm.

2. To avoid running the governor into the low speed stop.

B. 1. 1400 rpm.

2. To avoid running the pump in its resonance vibration region.

C. 1. 2000 rpm.

2. To avoid running the governor into the low speed stop.

D. 1. 2000 rpm.

2. To avoid running the pump in its resonance vibration region.

Page 46 of 100 Question #46 The plant is operating at 100%.

Static Switch VS-1s MANUAL BYPASS SWITCH is in the BYPASS TO LOAD position.

What condition would challenge the Containment design pressure if a Design Basis Accident were to occur?

A. Loss of Battery Bus 201A B. Loss of Battery Bus 201B C. Loss of Battery Bus 201D D. Loss of Bus VR-11

Page 47 of 100 Question #47 The plant is operating at 100% power.

The crew has entered AOP 2580, Degraded Voltage.

The procedure directs to trip the unit when the 4.16 kV buses reach 1. in order to prevent safety-related pumps and motors from 2..

A. 1. 2,912 V (70% nominal voltage)

2. tripping on under-voltage B. 1. 2,912 V (70% nominal voltage)
2. over-heating the windings C. 1. 3700 V (88% nominal voltage)
2. tripping on under-voltage D. 1. 3700 V (88% nominal voltage)
2. over-heating the windings

Page 48 of 100 Question #48 The plant tripped from 100% power.

The following alarms are locked in:

  • RSST LOCKOUT CHANNEL 1 (C-08, A-3).
  • DIESEL GEN 13U BKR DIFFERENTIAL LOCKOUT (C-08, D-36).

Compared to an uncomplicated trip,

1. Battery 201A discharge rate is 1. for this trip.

AND

2. Battery 201B discharge rate is 2. for this trip.

A. 1. the same

2. the same B. 1. the same
2. higher C. 1. higher
2. the same D. 1. higher
2. higher

Page 49 of 100 Question #49 F-38A/B, Emergency Diesel Generator Room Supply Fan, starts when the associated 1. and stops when the 2..

A. 1. EDG speed reaches 250 rpm

2. fans STOP button is pushed B. 1. EDG speed reaches 250 rpm
2. EDG room temperature reaches 65 F C. 1. EDG room temperature reaches 105 F
2. fans STOP button is pushed D. 1. EDG room temperature reaches 105 F
2. EDG room temperature reaches 65 F

Page 50 of 100 Question #50 RM-5099, SJAE Radiation Monitor, has its alarm setpoint adjusted weekly.

1. How is the new setpoint determined?

AND

2. Where is the setpoint adjustment required to be performed?

A. 1. Chemistry will calculate and provide the new setpoint.

2. Radiation Monitor panel RC-14 only.

B. 1. Chemistry will calculate and provide the new setpoint.

2. Radiation Monitor panel RC-14 and the Plant Process Computer.

C. 1. Operations will use OP 2383C to calculate the new setpoint.

2. Radiation Monitor panel RC-14 only.

D. 1. Operators will use OP 2383C to calculate the new setpoint.

2. Radiation Monitor panel RC-14 and the Plant Process Computer.

Page 51 of 100 Question #51 The plant is operating at 100% power.

What would indicate a Service Water Heat Exchanger tube rupture?

A. Alarm, AUX BLDG SUMP LEVEL HI (C-06/7, AA-21), annunciates.

B. Elevated air temperature in the East 480 Volt Switchgear Room.

C. Elevated air temperature in the West 480 Volt Switchgear Room.

D. Elevated air temperature in the DC Switchgear Rooms.

Page 52 of 100 Question #52 The plant is operating at 100%. A CIAS signal is generated (both facilities).

What is the status of Instrument Air and Station Air alignment to Containment?

Instrument Air Station Air A.

Aligned Aligned B.

Aligned Isolated C.

Isolated Aligned D.

Isolated Isolated

Page 53 of 100 Question #53 The plant is operating at 100% power. A low pressure weather system is moving across Connecticut.

1. Containment pressure will 1. as the system moves closer to the site.

AND

2. What actions will you take if Containment pressure limits are challenged?

A.

1. increase
2. Lower pressure using Hydrogen Purge and EBFS systems.

B.

1. increase
2. Lower pressure using only the Hydrogen Purge system.

C.

1. decrease
2. Raise pressure using Hydrogen Purge and EBFS systems.

D.

1. decrease
2. Raise pressure using only the Hydrogen Purge system.

Page 54 of 100 Question #54 The plant trips from 100% power.

  • EOP 2525, Standard Post Trip Actions is in progress.

What will cause TCOLD to be low out of program band?

A. Loop 2 THOT control channel temperature failing to 515 °F.

B. Main Condenser vacuum at 10 Hg back pressure.

C. Failure of electrical buses to transfer to the RSST.

D. TIC-4165, Steam Dump TAVE Controller, in manual and closed.

Page 55 of 100 Question #55 What Reactor Protection System trip prevents a Departure from Nucleate Boiling?

A. Power Level - High B. Reactor Coolant Flow - Low C. Steam Generator Water Level - Low D. Local Power Density - High

Page 56 of 100 Question #56 The plant is at 70%, raising power to 100%.

  • Alarm RX POWER T CH DEVIATION (C-04, AA-8), annunciates This alarm annunciated due to the NI instruments reading 1. than the T power indications.

Increasing 2. causes the NIs to de-calibrate.

A. 1. higher

2. RCS temperature B. 1. higher
2. neutron flux C. 1. lower
2. RCS temperature D. 1. lower
2. neutron flux

Page 57 of 100 Question #57 The plant is operating at 100% power.

  • TAVERAGE = 569 °F.
  • THOT = 593 °F.
  • TCOLD = 545 °F.
  • Subsequently, Loop 2 THOT fails to 533 °F.
1. What TAVERAGE will be indicated on C-04?

AND

2. What is the impact of the instrument failure?

A. 1. 554 °F.

2. On a plant trip, the Condenser Steam Dumps will maintain a higher temperature.

B. 1. 554 °F.

2. Letdown will go to maximum and any running B/U charging pumps will stop.

C. 1. 569 °F.

2. Foxboro IA will substitute a Loop 2 value of 593 °F with no system response.

D. 1. 569 °F.

2. A Foxboro system alarm will sound due to Loop 2 THOT being deselected.

Page 58 of 100 Question #58

1. Where are Inadequate Core Cooling (ICC) system temperatures sensed?

AND

2. What combination of RCS pressure and temperature is used to determine Subcooling Margin?

A. 1. Above fuel assemblies.

2. Highest pressure and lowest temperature.

B. 1. Above fuel assemblies.

2. Lowest pressure and highest temperature.

C. 1. Inside fuel assemblies.

2. Highest pressure and lowest temperature.

D. 1. Inside fuel assemblies.

2. Lowest pressure and highest temperature.

Page 59 of 100 Question #59 A plant power ascension is in progress. Nuclear and Delta-T power are BOTH at 50%.

What is the expected value for Pressurizer Level?

A. 47 - 48%

B. 50 - 51%

C. 53 - 54%

D. 56 - 57%

Page 60 of 100 Question #60 Which of the following is a refueling equipment design feature or interlock?

A. An interlock prevents the Cask Crane Monorail Hoist from colliding with the SFP Platform Crane.

B. An interlock on the SFP Platform Crane prevents manually placing a new fuel assembly in a Region 3 location.

C. Control circuit design ensures lifting forces will not exceed Refuel Machine design maximum load capacity.

D. Control circuit design ensures the Refuel Machine will not operate unless the bridge-mounted source range speaker is energized.

Page 61 of 100 Question #61 The plant is operating at 100% power.

Instrument Air is lost to (fail closed) CN-218, Condensate Minimum Flow Recirculation Control Valve.

How will the plant respond?

A. The plant will trip due to Low S/G Level B. S/G levels will fluctuate and stabilize at a lower level C. S/G levels will fluctuate and stabilize at a higher level D. There will be no noticeable effect on the plant.

Page 62 of 100 Question #62 Annunciator CH C CTMT AIR GASEOUS RADIATION HI (C-01, C-28), is alarming.

ESAS responds by sending a CLOSE signal to what valves?

A. The outboard CTMT Purge Valves only.

B. The inboard CTMT Purge Valves only.

C. All CTMT Purge Valves.

D. No CTMT Purge Valves.

Page 63 of 100 Question #63 The following conditions are noted at FLP-6, West DC Switchgear Room Fire Panel:

  • Strobe lights and horn are pulsating quickly.

What is the status of the West DC Switchgear Room Fire system?

A.

ONE smoke detector (photoelectric OR ion) has activated.

B.

TWO smoke detectors (photoelectric AND ion) have activated.

C.

The Halon system is discharging into the room.

D.

The Halon system has completed discharging into the room.

Page 64 of 100 Question #64 The plant is operating at 100% power.

What prevents -SI-652 from opening if keyswitch SDC SYS SUCT CTMT ISOL SI-652 (C-01) was taken to OPEN?

A.

Disconnect Switch, NS652 for SI-652 is OPEN.

B.

The closing coils are removed for SI-652.

C.

The control power fuses are removed for SI-652.

D.

Breaker 6119 for SI-652, is OFF.

Page 65 of 100 Question #65 The plant is in MODE 4, on Shutdown Cooling with Concurrent RCP Operations.

Which temperature instrument is used for determining Heatup/Cooldown rates?

A. T-115, Loop 1 TCOLD wide range temperature.

B. T-111X, Loop 1 THOT narrow range temperature.

C. T-351X, RCS to SDC temperature.

D. T-351Y, SDC to RCS temperature.

Page 66 of 100 Question #66 A Technical Specification Quarterly (92 days) surveillance was last performed 95 days ago.

1. What is the status of the equipment?

AND

2. The equipment will remain in its current status.

A. 1. OPERABLE.

2. as long as the surveillance is completed within an additional 25% of the 92 days.

B. 1. OPERABLE.

2. as long as the surveillance is completed at anytime within the next three months.

C. 1. NOT OPERABLE.

2. until the missed surveillance and a risk evaluation are performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. 1. NOT OPERABLE.

2. until the missed surveillance is completed.

Page 67 of 100 Question #67 Which practice fulfills the requirements for Tags Plus?

A.

A clam shell is tye wrapped over the valve handwheel.

B.

The tagged device is located within a Contaminated Area.

C.

A sign is hung from the tagged device reading Do Not Touch.

D.

Perform Live-Dead-Live testing prior to performing work.

Page 68 of 100 Question #68 The plant is operating at 100% power.

  • Alarm VENT STACK RADMONITOR HI/FAIL (C-06/7, A-12) annunciates.
  • STACK GAS EFFLUENT, RIC 8168 EQUIP FAIL light is lit and cannot be cleared.
1. Are the RM-8132B, Unit 2 Gaseous Stack Radiation Monitor, readings considered reliable in this condition?

AND

2. Your response would be to ensure that RM-8132B purge is 2..

A. 1. Yes.

2. started B. 1. Yes.
2. secured C. 1. No.
2. started D. 1. No.
2. secured

Page 69 of 100 Question #69 The plant is operating at 75% power. What requires a plant trip?

A.

A Main Steam Isolation (MSI) actuation on Facility 1.

B.

Breaker A304, 24A/24C TIE BKR, trips open.

C.

A Containment Isolation Actuation Signal (CIAS) on Facility 1 and 2.

D.

Safety Channels LT-1113A (#1 SG) and LT-1123A (#2 SG) fail low.

Page 70 of 100 Question #70 The plant is operating at 100% power.

The #1 Atmospheric Dump Valve (ADV) fails open.

The ADV opening causes the number of neutrons present in the core to be 1. the number of neutrons in the previous generation AND Keff is 2. one (1).

A. 1. less than

2. less than B. 1. less than
2. greater than C. 1. greater than
2. less than D. 1. greater than
2. greater than

Page 71 of 100 Question #71 Millstone Unit 2 is at 100% power and has been operating at this power level for 100 days.

1. State the primary production mechanism of xenon-135.
2. State the secondary production mechanism of xenon-135.

A. 1. Fission

2. Iodine decay B. 1. Fission
2. Promethium decay C. 1. Iodine decay
2. Fission D. 1. Promethium decay
2. Fission

Page 72 of 100 Question #72 CEA insertion limits (PDIL, PPDIL) ensure that CEAs will become more withdrawn as reactor power is 1. to compensate for the change in 2..

A. 1. raised

2. Xe effects of reactivity B. 1. raised
2. power defect C. 1. lowered
2. Xe effects of reactivity D. 1. lowered
2. power defect

Page 73 of 100 Question #73 The plant is operating steady-state at 80% power with all CEAs fully withdrawn.

Compare inserting Group 7 CEAs twenty (20) steps against inserting an individual CEA (#69) twenty (20) steps.

(Assume reactor power returns to 80%)

Inserting Group 7 CEAs will cause a 1. effect on the Axial Shape Index and a 2. effect on the Radial Peaking Factor compared to inserting only CEA # 69.

A. 1. smaller

2. smaller B. 1. smaller
2. larger C. 1. larger
2. smaller D. 1. larger
2. larger

Page 74 of 100 Question #74 The unit is shutdown with 2-AR-17, Condenser Vacuum Breaker, OPEN.

What is the pressure in the Condenser?

A. 0.0 mm Hg absolute.

B. 14.7 psig.

C. 14.7 psia.

D. 30.0 H2O absolute.

Page 75 of 100 Question #75 The plant tripped from 100% power when offsite power was lost. Natural Circulation has developed and verified by the crew.

What will enhance Natural Circulation flow in the Reactor Coolant System?

A.

Raising Pressurizer level.

B.

Lowering Steam Generator Level.

C.

Raising Pressurizer pressure.

D.

Lowering Steam Generator pressure.

Page 76 of 100 Question #76 The plant tripped from 25% power.

1. What chemistry sample is required by Technical Specifications?

AND

2. The basis for this sample is to minimize dose consequences for what event?

A. 1. RCS Specific Activity.

2. SGTR.

B. 1. Containment Atmosphere grab sample.

2. SGTR.

C. 1. RCS Specific Activity.

2. LOCA.

D. 1. Containment Atmosphere grab sample.

2. LOCA.

Page 77 of 100 Question #77 An Alert has been declared due to a LOCA.

1. A RMT #1 brief is required for actions taken in 1..

AND

2. 2. will coordinate activities outside the Control Room after SERO is fully activated.

A. 1. all areas

2. The Manager, Operational Support Center B. 1. all areas
2. The Manager, Control Room Operations C. 1. the RCA only
2. The Manager, Operational Support Center D. 1. the RCA only
2. The Manager, Control Room Operations

Page 78 of 100 Question #78 The plant experienced a SBLOCA. The crew is performing EOP 2532, Loss of Coolant Accident.

The following conditions currently exist:

  • Two CEAs are not fully inserted.
  • THOT = 520 °F.
  • CET temperatures = 522 °F.
  • Pressurizer Pressure = 1325 psia.
  • Pressurizer Level = 33% and rising.
  • RVLMS = 100%.
  • S/G levels = 65%.
1. Is HPSI Throttle Criteria MET?

AND

2. Can Charging be secured?

A. 1. No.

2. No.

B. 1. No.

2. Yes.

C. 1. Yes.

2. No.

D. 1. Yes.

2. Yes.

Page 79 of 100 Question #79 The plant is in Reduced Inventory with the following plant conditions:

  • Pressurizer vent port is removed.

A PEO reports abnormal knocking and banging noises emanating from the A LPSI pump.

  • A LPSI pump current = 15 amps and oscillating +/- 2 amps.

Describe your actions.

A.

Enter OP 2310, Shutdown Cooling and throttle the LPSI injection valves.

B.

Enter OP 2310, Shutdown Cooling and SECURE the A LPSI pump.

C.

Enter AOP 2572, Loss of Shutdown Cooling and throttle the LPSI injection valves.

D.

Enter AOP 2572, Loss of Shutdown Cooling and SECURE the A LPSI pump.

Page 80 of 100 Question #80 Annunciator, INVERTER INV-1 TROUBLE (C-08, A-25) is determined to be malfunctioning.

1. What process will remove the annunciator from service?

AND

2. How will the out of service annunciator be tracked?

A. 1. WM-AA-100, Work Management.

2. Tagging, OP-AA-200, Equipment Clearance.

B. 1. WM-AA-100, Work Management.

2. Shift Turnover Report.

C. 1. OP 2387A, Annunciator System Operation and Control.

2. Tagging, OP-AA-200, Equipment Clearance.

D. 1. OP 2387A, Annunciator System Operation and Control.

2. Shift Turnover Report.

Page 81 of 100 Question #81 The plant is performing a power ascension in accordance with OP 2204, Load Changes.

  • CTMT AIR RCVR PRES LO (C-06/7, CB-2) annunciates.
  • CTMT ISOL IA IA-27.1 green light is lit.

Given these conditions RCS pressure will 1. due to 2..

To address this condition, you will enter procedure 3..

A. 1. increase

2. MSIVs closing
3. EOP 2525, Standard Post Trip Actions B. 1. increase
2. Spray valves closing
3. AOP 2573, Loss of Instrument Air C. 1. decrease
2. MSIVs NOT closing
3. EOP 2525, Standard Post Trip Actions D. 1. decrease
2. Spray valves opening
3. AOP 2585, Immediate Operator Actions

Page 82 of 100 Question #82 C RPS Channels ZERO-POWER-MODE switch is in BYPASS

  • The power supply to Channel C Wide Range Nuclear Instrumentation fails.
1. The RPS C Channel LO FLOW, LO RCP SPD, and TM/LO PRES bistables are 1..

AND

2. The RPS C Channel Zero Power Mode automatic bypass is 2..

A. 1. tripped

2. OPERABLE.

B. 1. tripped

2. NOT OPERABLE C. 1. NOT tripped
2. OPERABLE.

D. 1. NOT tripped

2. NOT OPERABLE

Page 83 of 100 Question #83 The plant is operating at 100% power.

  • Fire Panel, C-26, ZONE 37, CONTAINMENT FIRE PANEL FLP-3, alarms
  • FLP-3, ZONE 2, CTMT B RCP HEAT, is in alarm.

The crew enters AOP 2559, Fire.

What components will you direct to be isolated?

A.

  1. 1 & #2 MSIVs, 2-MS-64A and 2-MS-64B.

B.

PORVs 2-RC-402 and 2-RC-404.

C.

  1. 1 & #2 S/G BLDN ISOL VLVs 2-MS-220A and 2-MS-220B.

D.

Ch. 1 & 2 ADV QUICK OPEN PERMISSIVE signals.

Page 84 of 100 Question #84 The plant is in MODE 3.

AOP 2568, Reactor Coolant System Leak is entered.

Plant conditions are as follows:

  • Pressurizer pressure is 2250 psia and stable
  • Pressurizer level is 36% and stable
  • RCS temperature Tc is 532 °F and stable.
  • Two (2) Charging pumps are operating.
  • Letdown is 28 gpm.

Pressurizer level and Pressurizer pressure begin lowering.

1. What indicates that the leak has gotten worse?

AND

2. What actions will the Unit Supervisor direct?

A. 1. Lowering RCS temperature.

2. Go to EOP 2532, Loss of Coolant Accident.

B. 1. RCS temperature remains stable.

2. Go to EOP 2532, Loss of Coolant Accident.

C. 1. Lowering RCS temperature.

2. Perform AOP 2568 Attachment A, Manual SIAS Initiation While Shutdown.

D. 1. RCS temperature remains stable.

2. Perform AOP 2568 Attachment A, Manual SIAS Initiation While Shutdown.

Page 85 of 100 Question #85 The plant has experience a Loss of Offsite Power (LOOP)

Conditions are as follows:

  • THOT = 521 °F and stable
  • TCOLD = 500 °F and stable
  • TCET = 535 °F and stable
  • PRCS = 2250 psia and stable
  • PZR Level = 40 % and stable You would direct steps to 1. because 2..

A. 1. ensure Single Phase Natural Circulation

2. low RCS heat removal is causing a bubble to form in the head B. 1. eliminate Voids
2. voids forming in the fuel channels are restricting natural circulation flow C. 1. ensure Single Phase Natural Circulation
2. low RCS heat removal is restricting natural circulation flow D. 1. eliminate Voids
2. voids forming in the fuel channels is causing reverse natural circulation flow

Page 86 of 100 Question #86 The plant is operating at 100% power.

The following events occur sequentially:

a) RCP A UPPER SEAL PRES HI annunciator alarms.

b) RCP A BLEED-OFF FLOW HI annunciator alarms.

c) RCP A BLEED-OFF FLOW HI annunciator clears.

d) RCP A BLEED-OFF FLOW LO annunciator alarms and remains lit

1. This sequence of annunciators was the result of the AND
2. What action must be directed?

A. 1. Controlled Bleed Off relief valve failing open.

2. Trip the reactor and turbine, secure the A RCP and go to EOP 2525, Standard Post Trip Actions.

B. 1. Controlled Bleed Off relief valve failing open.

2. Enter AOP 2575, Rapid Downpower, reduce power, remove the unit from service, and secure the A RCP.

C. 1. Controlled Bleed Off excess flow check valve seating.

2. Enter AOP 2575, Rapid Downpower, reduce power, remove the unit from service, and secure the A RCP.

D. 1. Controlled Bleed Off excess flow check valve seating.

2. Trip the reactor and turbine, secure the A RCP and go to EOP 2525, Standard Post Trip Actions.

Page 87 of 100 Question #87 The plant is operating at 100% power.

Calorimetric power = 2699.8 MWTH and rising.

1. This condition could be caused by 1. RBCCW flow through Letdown heat exchanger.

AND

2. Procedure 2. will be used to reduce turbine load.

A. 1. increased

2. OP 2204, Load Changes.

B. 1. decreased

2. OP 2204, Load Changes.

C. 1. increased

2. AOP 2585, Immediate Operator Actions.

D. 1. decreased

2. AOP 2585, Immediate Operator Actions.

Page 88 of 100 Question #88

1. The Condensate Storage Tank (CST) is considered OPERABLE with a minimum contained volume of 1. gallons.

AND

2. The basis is to provide sufficient water volume to cool down the RCS to 2. in the event of a Loss of Off-Site Power.

A. 1. 225,000 (90% indicated level)

2. MODE 5.

B. 1. 225,000 (90% indicated level)

2. MODE 4.

C. 1. 165,000 (66% indicated level)

2. MODE 5.

D. 1. 165,000 (66% indicated level)

2. MODE 4.

Page 89 of 100 Question #89 The plant has experienced a Station Blackout (SBO). The Turbine Driven Auxiliary Feedwater pump is operating feeding both Steam Generators at 300 gpm each.

1. Millstone Unit 2 is analyzed to cope with a Station Blackout (SBO) for 1..

AND

2. A 2. pump must be started, within one hour, to ensure the core will remain covered for the duration of the coping time.

A. 1. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

2. HPSI B. 1. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
2. Charging C. 1. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />
2. HPSI D. 1. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />
2. Charging

Page 90 of 100 Question #90 The plant was at 100% power when the Reactor was manually tripped.

Given the following plant parameters:

Containment pressure is 8 psig and rising Pressurizer pressure is 1180 psia and lowering Pressurizer level is at 0%

RVLMS at 80%

RCS Hot Leg temperature 450 °F and lowering

1. How will the Pressurizer Pressure Control System (PPCS) respond?

AND

2. What Emergency Operating Procedure (EOP) will you enter?

A. 1. The PPCS will turn Pressurizer heaters OFF.

2. EOP 2532, Loss of Coolant Accident.

B. 1. The PPCS will turn Pressurizer heaters OFF.

2. EOP 2536, Excess Steam Demand Event.

C. 1. The PPCS will turn Pressurizer heaters ON.

2. EOP 2532, Loss of Coolant Accident.

D. 1. The PPCS will turn Pressurizer heaters ON.

2. EOP 2536, Excess Steam Demand Event.

Page 91 of 100 Question #91 The plant is in MODE 6.

  • A full core offload is in progress.
  • The Upender is in the VERTICAL position in the Refuel Pool.
  • An irradiated fuel assembly is in the Refuel Machine.
  • The Refuel Machine is near the Upender.

Spent Fuel Pool level begins to lower at approximately 1 inch per minute.

The Refuel SRO, in accordance with AOP 2578, Loss of Refuel Pool and Spent Fuel Pool Level, will direct which one of the following?

A. Lower the fuel assembly into an open core location, ensure the Upender is VERTICAL in the refuel pool, then close the Transfer Tube Isolation Valve..

B. Lower the fuel assembly into the south saddle and place the Upender in HORIZONTAL, do NOT close the Transfer Tube Isolation Valve.

C. Place the fuel assembly in the Upender and place Upender in HORIZONTAL, do NOT close the Transfer Tube Isolation Valve..

D. Place the fuel assembly in the Upender and transfer fuel assembly to the spent fuel pool, then close the Transfer Tube Isolation Valve.

Page 92 of 100 Question #92 The plant is operating at 100% power when Vital DC bus DV-10 is lost.

Plant conditions are as follows:

Pressurizer pressure = 2030 psia and lowering Pressurizer level = 35% and lowering Steam Generator pressure = 905 psia and lowering Annunciator STM GEN NO. 1 SAFETY RELIEF VALVE OPEN (C-05, DA-17) is lit

1. What action will you direct?

AND

2. In what procedure would you direct this action?

A. 1. Lower the Turbine Bypass valve setpoint to 840 psig.

2. EOP 2525, Millstone Unit 2 Standard Post Trip Actions.

B. 1. Lower the Atmospheric Dump Valve setpoint to 880 psia.

2. EOP 2525, Millstone Unit 2 Standard Post Trip Actions.

C. 1. Lower the Turbine Bypass valve setpoint to 840 psig.

2. EOP 2541, Appendix 4, Millstone Unit 2 Followup Actions.

D. 1. Lower the Atmospheric Dump Valve setpoint to 880 psia.

2. EOP 2541, Appendix 4, Millstone Unit 2 Followup Actions.

Page 93 of 100 Question #93 The plant is in MODE 6; with fuel movement is in progress.

  • Containment Purge is in service.
  • Containment Atmosphere Radiation Monitors, RM-8123/8262 are out of service.

A 1. operator is assigned to close the Containment Purge Valves (AC-4, 5, 6, and 7) to meet the requirements of 2. ?

A. 1. Dedicated (sole responsibility)

2. 3.6.3.2, CONTAINMENT VENTILATION SYSTEM B. 1. Dedicated (sole responsibility)
2. 3.9.4, CONTAIMENT PENETRATIONS C. 1. Designated (has concurrent duties)
2. 3.6.3.2, CONTAINMENT VENTILATION SYSTEM D. 1. Designated (has concurrent duties)
2. 3.9.4, CONTAIMENT PENETRATIONS

Page 94 of 100 Question #94 A Large Break Loss of Coolant Accident occurred 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> ago.

The following are the current plant conditions:

  • RWST level = 8% and stable.
  • RCS Pressure = 35 psia and lowering very slowly.
  • Containment Pressure = 20 psig and lowering very slowly.
  • Safety Injection flow on the PPC and Main Control Boards = 360 gpm.
  • VR-11 is de-energized.

Given EOP 2541, Appendix 2, Figures 3, 4, and 5, determine whether Safety Injection flow is acceptable and the appropriate procedure to address the conditions.

1. Safety Injection flow 1. for the existing conditions.

AND

2. Procedure 2. will address the conditions.

A. 1. is NOT met

2. EOP 2532, Loss of Coolant Accident B. 1. is NOT met
2. EOP 2540, Functional Recovery C. 1. is met
2. EOP 2532, Loss of Coolant Accident D. 1. is met
2. EOP 2540, Functional Recovery

Page 95 of 100 Question #95 Why must the Reactor be subcritical for a minimum of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to moving irradiated fuel?

A. To allow sufficient radioactive decay of short-lived fission products.

B. To allow sufficient time for the radioactivity decay of N-16.

C. To ensure decay heat will not exceed the cooling capacity of the SFPC system.

D. To ensure that off-loading the core to the SFP will not result in criticality.

Page 96 of 100 Question #96 Annunciator HEATER DRAIN PUMP TROUBLE has become a nuisance alarm and will be removed from service.

1. Approval is required from the 1. to remove this annunciator from service.

AND

2. A 10CFR50.59 Applicability Review 2. required for this activity.

A. 1. Shift Manager

2. IS B. 1. Shift Manager
2. IS NOT C. 1. Engineering Manager
2. IS D. 1. Engineering Manager
2. IS NOT

Page 97 of 100 Question #97 The plant is operating at 100% power.

A troubleshooting plan was written that requires filling the #1 SIT. The SIT will remain OPERABLE during the performance of the troubleshooting plan.

Given MA-AA-103, Conduct of Troubleshooting, Attachment 1, Risk and Rigor Determination Matrix, what level of risk would be assigned to the plan?

A. No risk.

B. Low.

C. Medium.

D. High.

Page 98 of 100 Question #98 The plant has entered AOP 2569, Steam Generator Tube Leak. Conditions are as follows:

  • N-16 ALERT (C-06/7, CB-19) is alarming.
  • A S/G has a 10 gpd tube leak.

The plant is to remain on line.

1. Why would you align blowdown to affected S/G?

AND

2. What flowpath would you align blowdown to?

A. 1. To reduce secondary chemical concentrations in the S/G.

2. Blowdown Tank draining to the Seal Well.

B. 1. To minimize the concentration of activity in the S/G.

2. Blowdown Tank draining to the Seal Well.

C. 1. To reduce secondary chemical concentrations in the S/G.

2. Blowdown Quench Tank draining to Clean Liquid Rad Waste.

D. 1. To minimize the concentration of activity in the S/G.

2. Blowdown Quench Tank draining to Clean Liquid Rad Waste.

Page 99 of 100 Question #99 The plant has declared an ALERT.

  • The Emergency Operating Facility (EOF) has been activated.
  • The EOF Director of Station Emergency Operations (DSEO) has assumed control.
  • The Shift Manager has entered MP-26-EPI-FAP01-002, Manager of Control Room Operations (MCRO).

Given the conditions above, what is the Shift Manager responsible for?

A. Declaring and making notifications of EAL Classifications changes.

B. Developing PARs that result from changes in plant and notifying State DEEP.

C. Authorizing exposure upgrades, up to 25 Rem, for on-shift Operations personal.

D. Coordinating with the ADTS to establish minimum equipment isolation.

Page 100 of 100 Question #100 The plant has experienced a Station Blackout. EOP 2530, Station Blackout, is in progress.

  • CET temperatures are 1300 °F and increasing.

Describe your actions.

A. Use the Diagnostic Flowchart to re-diagnose the event and implement Once-Through-Cooling.

B. Transition directly to the Functional Recovery Procedures and implement Once-Through-Cooling.

C. Stay in EOP 2530, Station Blackout and continue restoration of power.

D. Go To SAMG 25 SAG-01, Main Control Room SAMG Initial Response.

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