ML113640154

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Initial Exam 2011-302 Final RO Written Exam with References
ML113640154
Person / Time
Site: Watts Bar  Tennessee Valley Authority icon.png
Issue date: 12/30/2011
From:
Operator Licensing and Human Performance Branch
To:
References
Download: ML113640154 (83)


Text

10-2011 Watts Bar RO NRC License Exam 12/29/2011

1. Given the following:

- A reactor trip occurs on Unit 1.

- ES-0.1, Reactor Trip Response, has been implemented.

- Shutdown Bank B rod G3 remains at 228 steps.

- Control Bank D rod M8 sticks at 16 steps while inserting.

- Tavg dropped to 549°F before stabilizing.

Which ONE of the following completes the statement below?

Conditions indicate Immediate Boration is to satisfy Shutdown Margin.

A. NOT required B. required due to the RCS temperature ONLY C. required due to the stuck control rods ONLY D. required due to the RCS temperature and the stuck control rods Page 1

10-2011 Watts Bar RO NRC License Exam 12/29/2011

2. Given the following:

- Unit us operating at 100% power with Pressurizer Heater Group C energized.

- Pressurizer PORV 68-340A leakage exceeds spray flow.

Which ONE of the following completes the statement below?

Assuming NO operator action, 1-Tl-68-318, PZR SURGE LINE TEMP, indication will (1) and the Tech Spec Operational Leakage limit would be exceeded when the leakage reached (2)

(IJ A. Rise >1.0 gpm B. Rise >logpm C. Lower >1.Ogpm D. Lower >logpm Page 2

10-2011 Watts Bar RO NRC License Exam 12/29/2011

3. Given the following:

- Unit I is operating at 18% power.

- RCP #2 motor winding temperatures have increased to 304°F.

Which ONE of the following identifies the action required and the reason for the sequence?

A. Trip the reactor and then stop RCP #2 because the unit will not be operated on 3 loop operation in Modes I or 2 due to conservative industry operating principles.

B. Trip the reactor and then stop RCP #2 because Tech Spec LCO 3.4.4 does not allow 3 loop operation with the Unit in Mode 1.

C. Stop RCP #2 and then trip the reactor because the challenge is to the pump and there is no challenge to DNB during 3-loop operation at the current reactor power level.

D. Stop RCP #2 and then trip the reactor because the challenge is to the pump and stopping the pump does not challenge the reactor trip system at the current reactor power level.

Page 3

10-2011 Watts Bar RO NRC License Exam 12/29/2011

4. Given the following:

- Unit 1 is operating at 100% power.

- The C-S CCS Pump trips while supplying the B Train CCS.

- Operators have not taken any action.

Which ONE of the following completes the statements below?

To restore flow, the 2B-B CCS pump (1)

If the I B-B CCS pump is used to supply B Train CCS, its suction valve must be re-aligned to (2)

A. (1) must be manually started (2) protect train separation within the CCS surge tank B. (1) must be manually started (2) ensure a suction path to the 1 B-B CCS pump C. (1) will automatically start (2) protect train separation within the CCS surge tank D. (1) will automatically start (2) ensure a suction path to the 1 B-B CCS pump Page 4

10-2011 Watts Bar RO NRC License Exam 12/29/2011

5. Given the following:

- Unit 1 is operating at 100% power.

- 1-XS-68-340D, PZR PRESS CONTROL CHANNEL SELECT, is selected to PT-68-340 & 334.

- 1-XS-68-340B, PZR PRESS RECORDER CHANNEL SELECT, is selected to PT-68-334.

- 1 -P1-68-334, PRESSURIZER PRESSURE, fails to the bottom of the scale due to transmitter failure.

- The other three pressurizer pressure instruments indicate:

1-Pl-68-340A - 2235 psig 1-PI-68-323 - 2220 psig 1-Pl-68-322 - 2230 psig

- Operators are performing AOl-i 8, Malfunction of Pressurizer pressure Control System, and have placed 1-XS-68-340D, PZR PRESS CONTROL CHANNEL SELECT, to PT-68-340 B322.

Which ONE of the following identifies how 1-XS-68-340B, PZR PRESS RECORDER CHANNEL SELECT, will be positioned and the reason why?

A. PT-68-323 because it is the channel with the lowest reading.

B. PT-68-322 because it is the channel replacing the control function of 1 -PT-68-334.

C. PT-68-323 or PT-68-322 because neither is the channel selected for control.

D. Any position other than PT-68-334 because each is an operable channel.

Page 5

10-2011 Watts Bar RO NRC License Exam 12/29/2011

6. Given the following:

- Unit 1 is at 45% power when the reactor fails to trip from a valid trip signal and cannot be tripped from the MCR handswitches.

- FR-SI, Nuclear Power Generation/ATWS, is entered and the immediate actions are in progress.

- RCS Tavg is 548° F and dropping.

Which ONE of the following completes the statement below?

Both MFPTs will be tripped by a Feedwater Isolation Signal is/are opened.

A. after the first reactor trip breaker B. after the first MG set output breaker C. only after both reactor trip breakers D. only after both MG set output breakers Page 6

10-2011 Watts Bar RD NRC License Exam 12/29/2011

7. The following conditions exist on Unit 1:

- A S/G tube rupture is in progress.

- The crew is backfilling at 125 gpm per ES-3.1, Post-SGTR Cooldown Using Backfill.

- A 75 gpm and the 45 gpm orifices are in service.

- The TSC has requested the crew to reduce the backfill rate from 125 gpm to 75 gpm.

Which ONE of the following actions would the crew take to reduce the backfill rate?

A. Lower RCS pressure B. Raise RCS pressure C. Lower ruptured SG pressure D. Raise ruptured SG pressure Page 7

10-2011 Watts Bar RO NRC License Exam 12/29/2011

8. Given the following:

- Unit I is operating at 75% power steady-state conditions.

- A steam line leak occurs on a steam header outside the north valve room.

Which ONE of the following completes the statement below?

(1) is the time in core life that results in the largest addition of positive reactivity and a manual reactor trip is required in accordance with AOl-38, Main Steam or Feedwater Leak, if (2)

A. BOL final reactor power rises to 79%

B. BOL TavglTref cannot be maintained within 4°F C. EOL final reactor power rises to 79%

D. EOL Tavg/Tref cannot be maintained within 4°F Page 8

10-2011 Watts Bar RO NRC License Exam 12/29/2011

9. Given the following:

- Unit I is operating at 100% power when an ATWS occurs.

Which ONE of the following completes the statement below?

To ensure long term reactor protection, the AFW pumps are assumed to be started within a maximum of (1) and the limiting ATWS accident which determines this maximum AFW start time is (2)

A. 30 seconds turbine trip B. 30 seconds loss of main feedwater C. 60 seconds turbine trip D. 60 seconds loss of main feedwater Page 9

10-2011 Watts Bar RD NRC License Exam 12/29/2011

10. Given the following:

- Unit 1 is in Mode 3 following a loss of offsite power 20 minutes ago.

- Both of the Unit 1 diesel generators failed to start.

- A fire on the lower level of the Control Building results in the loss of both 250v DC Station Batteries.

Which ONE of the following completes the statement below?

The MCR will be able to monitor Core Exit Thermocouples on (1) and to prevent entry into a REQUIRED ACTION in Tech Spec LCD 3.3.3, Post Accident Monitoring, a minimum of (2) operable thermocouples per train are required.

A. (1) Plasma displays on the control board or Integrated Computer System (ICS)

(2) 2 quadrants with at least 4 B. (1) Plasma displays on the control board or Integrated Computer System (ICS)

(2) 4 quadrants with at least 2 C. (1) Plasma Displays ONLY (2) 2 quadrants with at least 4 D. (1) Plasma Displays ONLY (2) 4 quadrants with at least 2 Page 10

10-2011 Watts Bar RO NRC License Exam 12/29/2011

11. Which ONE of the following identifies the pump that will be sequenced on t following a blackout signal on a 6900v Shutdown board and a reason?

First Pump Reason A. CCP Largest blackout load on the board.

B. CCP To restore Reactor Coolant Pump seal cooling.

C. ERCW pump Largest blackout load on the board.

D. ERCW pump To restore Diesel Generator engine cooling.

Page 11

10-2011 Watts Bar RO NRC License Exam 12/29/2011

12. Given the following:

- Unit 1 is operating at 100% power.

- A loss of 125V DC Vital Battery Board Ill occurs.

- Operators are performing AOl-21.03, Loss of 125V DC Vital Battery Board Ill, Appendix A, Transfer of 125v DC Buses.

Which ONE of the following completes the statements below?

The operator is directed to DEPRESS and HOLD the 6.9kV SD Bd 2A-A BO-RESET switch in logic Panel 2A-A when control power is being restored to Shutdown Board 2A-A to (1)

The switch to transfer the 6.9kV SD Bd 2A-A 125V DC NORMAL BUS power supply is located (2)

A. (1) prevent inadvertent equipment tripping (2) inside the 125V DC Vital Battery Board Ill room B. (1) prevent inadvertent equipment tripping (2) inside a compartment on 6.9kV Shutdown Board 2A-A C. (1) prevent unwanted starts of equipment (2) inside the 125V DC Vital Battery Board Ill room D. (1) prevent unwanted starts of equipment (2) inside a compartment on 6.9kV Shutdown Board 2A-A Page 12

10-2011 Watts Bar RO NRC License Exam 12/29/2011

13. Given the following:

- Unit 1 is operating at 100% power.

- All available Train A ERCW pumps are in service.

- ERCW pump B-A trips.

Which ONE of the following completes the statements below?

If needed to maintain CCS temperature on the Unit 1 Miscellaneous Equipment Header, the CCS heat exchanger (1) outlet flow control bypass valve will be adjusted. As the valve is adjusted, the ERCW flow rate on CCS Heat Exchanger B will (2)

(1)

A. C drop B. A drop C. C remain constant D. A remain constant Page 13

10-2011 Watts Bar RO NRC License Exam 12/29/2011

14. Given the following:

- Unit 1 is currently in Mode 3, with the reactor trip breakers open.

- A control air leak develops inside containment.

- 1-FCV-62-86, Alt Charging to Loop 4, is in service and 1-FCV-62-85, Norm Charging to Loop 1, begins drifting open.

- AOl-b, Loss of Control Air, is entered.

- The operating crew stops RCPs #1, #3, and #4 in accordance with AOl-b guidance.

Which ONE of the following completes the statement below?

The leak is on the (1) header and stopping the RCPs will (2)

Li)

A. Auxiliary Air Train B reduce the increase in the pressurizer level B. Auxiliary Air Train B stop uncontrolled pressurizer spray flow C. Non-essential Control Air reduce the increase in the pressurizer level D. Non-essential Control Air stop uncontrolled pressurizer spray flow Page 14

10-2011 Watts Bar RO NRC License Exam 12/29/2011

15. Given the following:

- Unit I is operating at 100% power with the following conditions:

Megawatts 1210 MWe Megavars +20 Mvars Gen Voltage 23.6 Ky

- A disturbance occurs on the Transmission Grid resulting in the following:

Megawatts 1210 MWe Megavars -180 Mvars Gen Voltage 23.6 Ky

- Annunciator 1-C, STATOR TEMP HI, alarms.

- The Stator Coil Outlet temperature is determined to be 177°F and rising at 2°F/minute.

Which ONE of the following completes the statements below?

Under the conditions, the timer to trip the turbine (1) been initiated.

The stator temperature can be reduced by (2) generator excitation current.

{i)

A. has lowering B. has raising C. has NOT lowering D. has NOT raising Page 15

10-2011 Watts Bar RO NRC License Exam 12/29/2011

16. Given the following:

- Unit 1 was operating at 100% power when a small break LOCA occurred.

- The crew has implemented ECA-1 .2, LOCA Outside Containment, due to alarm AUX BLDG HIGH ENERGY LINE BREAK being LIT.

- When the crew closes RHR Train A cold leg injection valve, 1-FCV-63-93, the RCS pressure begins to rise.

- RCS pressure is now 1520 psig and slowly rising.

Which ONE of the following completes the statement below?

The (1) are currently contributing the most ECCS flow to the core and ECA-1 .2 will require (2) to be stopped.

Li)

A. Safety Injection Pumps only RHR pump IA-A B. Safety Injection Pumps both RHR pumps C. Centrifugal Charging Pumps only RHR pump lA-A D. Centrifugal Charging Pumps both RHR pumps Page 16

10-2011 Watts Bar RO NRC License Exam 12/29/2011

17. Given the following:

- The crew has entered FR-H.1, Loss of Secondary Heat Sink, due to a loss of inventory in the S!Gs and failure of the AFW pumps to start.

SG Wide Range Levels (%) AFW Cnmt Time SG#1 SG#2 SG#3 SG#4 Flow Press 0800 41 39 38 37 0 gpm 1.70 psid 0810 37 32 34 33 0 gpm 2.40 psid 0820 30 28 27 26 0 gpm 2.70 psid 0830 27 25 22 24 0 gpm 2.50 psid Which ONE of the following is the earliest time, if any, that the initiation of Bleed and Feed is required?

A. Bleed and Feed NOT required.

B. 0810 C. 0820 D. 0830 Page 17

10-2011 Watts Bar RO NRC License Exam 12/29/2011

18. Given the following:

0900 - A reactor trip occurs.

0910 - A small break LOCA occurs.

0930 - The crew transitions to ECA-1 .1. Loss of RHR Sump Recirculation due to the failure of both RHR pumps.

0940 - Crew reduces ECCS flow to 1 SIP and I COP per ECA-1 .1.

0950 - Crew determines SI flow cannot be terminated due to lack of subcooling.

1000 - The crew is performing ECA-1 .1 Step 19 RNO to establish the minimum required ECCS flow to remove decay heat.

Which ONE of the following identifies the minimum flow rate that meets the intent of ECA-1 .1, Step 19 RNO, and the flow adjustment methodology for meeting this flow rate?

REFERENCE PROVIDED A. Establish 460 gpm ECCS flow.

Starting and stopping ECCS pumps.

B. Establish 460 gpm ECCS flow.

Throttling ECCS valves.

C. Establish 370 gpm ECCS flow.

Starting and stopping ECCS pumps.

D. Establish 370 gpm ECCS flow.

Throttling ECCS valves.

Page 18

10-2011 Watts Bar RD NRC Ucense Exam 12/29/2011

19. Given the following:

- Unit I is operating at 60% power when the Control Rods begin an uncontrolled withdrawal at 72 steps/rn mute.

- The QAC places 1-RBSS, ROD BANK SELECT to MAN stopping the rod movement.

- The operating crew determines a failure of the RCS temperature input to the Rod Control System resulted in the uncontrolled rod movement.

- The temperature input to the system has been repaired.

- Current conditions are:

- Tavg is 1.4°F above Tref.

- ROD SPEED indicates 48 Steps/mm.

- PASSIVE SUMMER ROD DEMAND indicates slightly over +1.0.

- Control Bank D rods are at 176 steps withdrawn.

If 1-RBSS, ROD BANK SELECT is returned to AUTO, which ONE of the following identifies how the control rods will respond?

Control Rod position will...

A. remain at 176 steps withdrawn.

B. decrease because of the Tavg-Tref error.

C. increase because the Rod Speed has not decayed to 0.

D. decrease because of the PASSIVE SUMMER ROD DEMAND.

Page 19

10-2011 Watts Bar RO NRC License Exam 12/29/2011

20. Given the following:

- During receipt of new fuel, a non-irradiated fuel assembly is dropped on the refueling floor.

- A plant announcement is made per AOl-29, Dropped or Damaged Fuel or Refueling Cavity Seal Failure, to evacuate the affected area.

In accordance with AOl-29, which ONE of the following completes the statements below?

The affected area is required to be evacuated to protect against the potential exposure to (1) radiation.

Non-fuel handling related work on the Refuel Floor can first be resumed when (2) w A. Alpha ONLY Radiation Protection grants approval to inspect the fuel assembly.

B. Alpha ONLY the damaged fuel assembly has been inspected and stored.

C. Alpha/Beta/Gamma Radiation Protection grants approval to inspect the fuel assembly.

D. Alpha/Beta/Gamma the damaged fuel assembly has been inspected and stored.

Page 20

10-2011 Watts Bar RO NRC License Exam 12/29/2011

21. Given the following:

- Unit I was operating at 100% when a steam generator tube leak occurred.

- The unit has been placed in Mode 3.

- The leaking steam generator pressure is 950 psig.

- The operating crew is currently determining the target incore temperature for RCS cooldown, per the following table in AOl-33, Steam Generator Tube Leak.

LEAKING SQ TARGET INCORE PRESSURE (PSIG) TEMP °F) 1100 491F 1000 479F 900 466F 800 451F 700 690 43.3F Which ONE of the following identifies the steam pressure setpoint on the steam dump system that would maintain the target incore temperature?

A. 480 psig B. 495 psig C. 545 psig D. 560 psig Page 21

10-2011 Watts Bar RO NRC license Exam 12/29/2011

22. Given the following:

- Main Turbine load is 660 MWe.

- Condenser vacuum is decreasing at 0.1 in-HgAImin due to air in-leakage.

- The crew has entered AOl-Il, Loss of Condenser Vacuum.

- Currently Condenser pressures are:

ZoneA ZoneB ZoneC 3.75 in-HgA 4.93 in-HgA 6.06 in-HgA Which ONE of the following completes the statements below?

The turbine automatic low vacuum trip (1) failed.

Zone (2) is currently at a condenser pressure that requires a plant trip.

REFERENCE PROVIDED A. has B B. has NOT B C. has C D. has NOT C Page 22

10-2011 Watts Bar RO NRC License Exam 12/29/2011

23. Given the following:

- Unit I was operating at 100% power when a Main Control Room evacuation was performed in accordance with AOl-30.2, Fire Safe Shutdown, Series procedure C.69, Fire Safe Shutdown Control Building.

Which ONE of the following completes the statements below with respect to Aux Control Room indications?

Tcold is determined using (1) installed instrumentation.

Thot is determined using (2) installed instrumentation.

Li)

A. RCS temperature Incore Thermocouple B. RCS temperature RCS temperature C. SG pressure Incore Thermocouple D. SG pressure RCS temperature Page 23

10-2011 Watts Bar RO NRC License Exam 12/29/2011

24. Given the following:

- Following a LOCA the operating crew is performing FR-C.1, Inadequate Core Cooling.

- Containment pressure peaked at 5.2 psid.

- Depressurizing the S/Gs to atmospheric pressure is ineffective in reducing incore T/C temperatures.

- All RCP support systems are available for RCP5 2 and 4.

- RCP5 I and 3 have no ERCW supply for the motor coolers.

- S/G Narrow Range levels are:

  1. 1 #2 #3 #4 40% 41% 32% 52%

- Core exit thermocouples have exceeded 1200°F.

- RCPs are to be started one at a time in an attempt to reduce core exit thermocouples below 1200°F.

Which ONE of the following identifies the RCPs that would be started in an attempt to reduce core exit thermocouple temperatures?

A. RCP4ONLY B. ALL four of the RCPs C. RCP5 2 and 4 ONLY D. RCPs 1, 2, and 4 ONLY Page 24

10-2011 Watts Bar RO NRC License Exam 12/29/2011

25. Given the following:

- A small break LOCA occurred on Unit 1.

- ES-I .2, Post LOCA Cooldown and Depressurization, is in progress.

- RCS pressure is 1420 psig and one charging pump has been stopped.

- The crew is ready to stop the first SI pump.

Which ONE of the following completes the statements below?

When the SI pump is stopped, RCS subcooling will drop (I)

The minimum RCS subcooling value required to allow the second SI pump to be stopped is (2) than the value required for stopping the first pump.

A. (I) and stabilize at a lower value due to an increase in RCS temperature with lower ECCS injection flow (2) less B. (I) and stabilize at a lower value due to an increase in RCS temperature with lower ECCS injection flow (2) greater C. (1) due to reduced ECCS injection flow and stabilize at a lower value when break flow equals ECCS injection flow.

(2) less D. (1) due to reduced ECCS injection flow and stabilize at a lower value when break flow equals ECCS injection flow.

(2) greater Page 25

10-2011 Watts Bar RO NRC License Exam 12/29/2011

26. Following a Small Break LOCA, the crew is performing the actions contained in FR-P.1, Pressurized Thermal Shock.

Which ONE of the following describes the reason for RCP restart in FR-P.1, Pressurized Thermal Shock, if the SI termination criteria cannot be satisfied?

An RCP running...

A. raises the RCS temperature entering the vessel downcomer.

B. prevents vessel head voiding as the RCS pressure is dropped.

C. restores pressurizer spray flow for reducing RCS pressure.

D. reduces the minimum required subcooling to terminate SI.

Page 26

10-2011 Watts Bar RO NRC License Exam 12/29/2011

27. Given the following:

- A large break LOCA has occurred on Unit 1.

- The crew is performing E-1, Loss of Reactor or Secondary Coolant, with the ECCS aligned for cold leg recirculation.

- The operating crew determines the criteria for entering FR-Z.2, Containment Flooding, is met.

Which ONE of the following completes the statements below?

The implementation of FR-Z.2 is (1)

The procedure directs the sampling of the sump to (2)

A. (1) required (2) ensure shutdown margin is being maintained, since non-borated water has entered the containment sump B. (1) at the discretion of the crew.

(2) ensure shutdown margin is being maintained, since non-borated water has entered the containment sump C. (1) required (2) to allow the TSC to determine if excess sump water can be transferred to tanks outside of containment D. (1) at the discretion of the crew (2) to allow the TSC to determine if excess sump water can be transferred to tanks outside of containment Page 27

10-2011 Watts Bar RO NRC License Exam 12/29/2011

28. Given the following:

- Unit i is in Mode 5 preparing for an RCS heatup.

- RCP #2 is in service.

- RCP #4 has experienced the following start and run times as part of a maintenance PMT:

- 1615- started but stopped before it reached rated speed.

- 1655- started and then stopped after a 10 minute run.

- 1740 started and then stopped after a 10 minute run.

- The time is now 1800 and RCP #4 is ready to be placed in service.

Which ONE of the following identifies the earliest time the pump can be started and the breaker handswitch that will be used to start the RCP motor?

Time Handswitch A. 1820 1-HS-68-73AA, RCP 4 NORMAL BKR & LIFT PMP B. 1820 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR C. 1850 1-HS-68-73AA, RCP 4 NORMAL BKR & LIFT PMP D. 1850 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR Page 28

10-2011 Watts Bar RO NRC License Exam 12/29/2011

29. Given the following:

- Unit 1 is operating at 100% power.

- Annunciator 95-C, RCP 1 STANDPIPE LEVEL HI/LO, alarms.

Which ONE of the following completes the statement below?

The operating crew will first attempt to clear the alarm by (1) the standpipe and if this action clears the alarm, the condition indicates a possible problem with the (2) seal on the RCP.

w L)

A. filling #3 B. filling #2 C. draining #3 D. draining #2 Page 29

10-2011 Watts Bar RO NRC License Exam 12/29/2011

30. Given the following:

- Unft 1 is operating at 100% power after restart following a refueling outage.

- Rod Control in MANUAL.

- VCT level is currently at 32%.

- An AUO places an un-borated mixed bed demineralizer in service.

Which ONE of the following completes the statements below?

Assuming NO operator action is taken, the VCT level will (1)

In accordance with AOI-3, Malfunction of Reactor Makeup Control, the first corrective action the RO will take that will stop the event in progress is to (2)

A. (1) remain constant (2) place 1-HS-62-79A, LTDN HI TEMP DIVERT, to V.C. TK B. (1) remain constant (2) initiate normal boration C. (i)nseovertime (2) place 1-HS-62-79A, LTDN HI TEMP DIVERT, to V.C. TK D. (1) rise over time (2) initiate normal boration Page 30

10-2011 Watts Bar RO NRC License Exam 12/29/2011

31. Given the following:

- Unit I is operating at 100% power.

- Annunciator 11O-D, LTDN TO DEMINS TEMP HI, alarms.

- The OAC determines the indication on 1-T!-62-78, letdown temperature, has slowly increased from 120°F to 132°F and is stable.

Which ONE of the following completes the statements below?

The letdown temperature rise results in reactor power (1)

The action required by the OAC is to (2) in accordance with the ARI.

Note: 1-HIC-62-78A Letdown Heat Exch Outlet Temp Control A. (1) increasing (2) ensure CVCS demineralizers bypassed and adjust 1-HIC-62-78A B. (1) decreasing (2) ensure CVCS demineralizers bypassed and adjust 1-HIC-62-78A C. (1) increasing (2) adjust 1-HIC-62-78A ONLY D. (1) decreasing (2) adjust 1-HIC-62-78A ONLY Page 31

10-2011 Watts Bar RD NRC License Exam 12/29/2011

32. Given the following:

- Unit 1 is in Mode 5, midloop operation.

- RHR Train A in service at a flow rate of 2100 gpm.

- The RCS temperature is stable at 126°F.

- The operator throttles open 1-FCV-74-32, RHR HXS BYPASS.

Which ONE of the following completes the statement below?

As 1-FCV-74-32, RHR HXS BYPASS is throttled open, the RCS temperature will (1) and the RHR flow rate indicated on 1-M-6 will (2) w A. decrease increase B. decrease decrease C. increase increase D. increase decrease Page 32

10-2011 Watts Bar RO NRC License Exam 12/29/2011

33. Given the following:

- Unit I was operating at 100% power when a reactor trip and SI with loss of offsite power occurred 20 minutes ago.

- Pressurizer pressure dropped to 1750 psig, then recovered five minutes later to 2235 psig.

Current conditions:

- Offsite power has been restored.

- Pressurizer level is currently at 68% and stable.

- RCS cold leg temperatures are 561°F and stable.

- RCS hot leg temperature is 590°F and slowly decreasing.

- RVLIS indicates 96%.

- All SGs are at 1125 psig and controlled by the SG PORVs.

- ES 1.1, SI Termination, is being performed and is at the step for determining RCP status.

Which ONE of the following identifies the impact of the above conditions on RCP restart?

A. RCP restart is NOT allowed; The resulting injection of cold water could result in reactor restart.

B. RCP restart is NOT allowed; The resulting heat transfer from the steam generators could result in a pressure surge in the RCS.

C. RCP restart is allowed only after an engineering analysis of the boration from ECCS injection during natural circulation operation.

D. RCP restart is allowed; Natural circulation flow has been established and has removed the cold ECCS water from the cold legs.

Page 33

10-2011 Watts Bar RD NRC License Exam 12/29/2011

34. The pressurizer (PZR) cold cal level is at 40% with a nitrogen blanket present.

Which ONE of the following choices completes the statement below?

When establishing a steam bubble, in accordance with GO-i, Unit Startup From Cold Shutdown To Hot Standby, the pressurizer administrative maximum heat-up rate limit is (1) and the POR\/s are closed and placed in P-AUTO when (2)

A. 75°F in one hour Letdown flow exceeds charging flow B. 75°F in one hour PZR Liquid Temperature reaches 235°F C. 100°Finonehour Letdown flow exceeds charging flow D. 100°F in one hour PZR Liquid Temperature reaches 235°F Page 34

10-2011 Watts Bar RD NRC License Exam 12/29/2011

35. Given the following:

- Unit 1 is at 100% power with Thermal Barrier Booster Pump (TBBP) lB running.

- TBBP handswitches on 0-M-27 are aligned with:

1-HS-70-131A, THRM BAR BSTR PMP 1A (TBBP) is PULL A-P AUTO.

1-HS-70-130A, THRM BAR BSTR PMP lB (TBBP) is IN A AUTO.

- Loss of Offsite Power occurs.

Which ONE of the following completes the statement below?

During the blackout relay sequencing to restore equipment, only the (1)

TBBP will start after a (2) second time delay.

A. 1A 20 B. lB 20 C. IA 35 D. lB 35 Page 35

10-2011 Watts Bar RO NRC License Exam 12/29/2011

36. Given the following:

- Unit I is operating at 100% power.

- Abnormal RCS leakage has been detected.

- One of the pressurizer PORVs is suspected to have seat leakage.

Which ONE of the following completes the statements below?

Without any additional operator action, the operator could use the MCR indication for (1) to identify which PORV was leaking.

If the PORV is declared inoperable, the crew is required close the PORV Block valve within (2) c)

A. TAILPIPE TEMPS on 1-M-4 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. TAILPIPE TEMPS on 1-M-4 30 minutes C. PZR VALVES ACOUSTIC MONITOR on 0-M-25 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. PZR VALVES ACOUSTIC MONITOR on 0-M-25 30 minutes Page 36

10-2011 Watts Bar RO NRC License Exam 12/29/2011

37. Unit 1 is operating at 100% power when the following sequence of events occurs:

- Pressurizer Power Operated Relief Valve (PORV) 1-PCV-68-334 opens and fails to reseat when closed.

- Pressurizer PORV Block valve, 1-FCV-68-332, for PORV 334 cannot be closed.

- Pressurizer Relief Tank (PRT) pressure begins to slowly rise.

- The PRT pressure continues to rise until the PRT ruptures.

Which ONE of the following completes the statements below?

1-PCV-68-301, PRT VENT TO WDS VENT HDR, will automatically close when the PRT pressure reaches (1) psig.

When the PRT ruptures, the PORV tailpipe temperature will (2) w A. 6.5psig begintodrop B. 6.5 psig rise at a faster rate C. 8.0 psig begin to drop D. 8.0 psig rise at a faster rate Page 37

10-2011 Watts Bar RO NRC License Exam 12/29/2011

38. Which ONE of the following identifies the plant electrical boards that supply power to the listed components on Unit 1?

SSPS Train B Reactor Reactor Trip Bypass Breaker A Trip Breaker 48v UV coil (BYA) Control Power Circuit A. 120v AC Vital Instrument 125! DC Vital Battery Board I Power Boards II and IV B. 120v AC Vital Instrument 125V DC Vital Battery Board II Power Boards II and IV C. 120v AC Vital Instrument 125V DC Vital Battery Board I Power Board II ONLY D. 120v AC Vital Instrument 125V DC Vital Battery Board II Power Board II ONLY Page 38

10-2011 Watts Bar RO NRC License Exam 12/29/2011

39. Given the following:

- Unit I has been shutdown for a refueling outage.

- GO-6, Unit Shutdown from Hot Standby to Cold Shutdown, is in progress.

- The lowest RCS Tcold temperature and pressure trend is:

Time Temp Pressure 0500 349°F 395 psig 0530 337°F 380 psig 0600 324°F 345 psig 0630 302°F 340 psig 0700 280°F 340 psig 0730 257°F 340 psig 0800 235°F 340 psig 0830 214°F 340 psig 0900 199°F 330 psig 0930 185°F 330 psig Which ONE of the following is the earliest of the identified times that one of the Centrifugal Charging Pumps is required to be tagged with its breaker racked down and the reason for the requirement?

Time Reason A. 0600 to be in compliance with TR 3.1.3 Charging Pump, Shutdown.

B. 0600 to be in compliance with LCO 3.4.12 Cold-Overpressure Mitigation System.

C. 0900 to be in compliance with TR 3.1.3 - Charging Pump, Shutdown.

D. 0900 to be in compliance with LCO 3.4.12 Cold-Overpressure Mitigation System.

Page 39

10-2011 Watts Bar RO NRC License Exam 12/29/2011

40. Given the following:

- Unit 1 was operating at 100% power when a design basis LOCA occurred.

Which ONE of the following identifies system(s) directly providing Containment Cooling during the first minute following the Phase B containment isolation?

A. Containment Spray only B. Air Return Fans and Ice Condenser C. Containment Ventilation System and Ice Condenser D. Air Return Fans and Containment Spray Page 40

10-2011 Watts Bar RO NRC License Exam 12/29/2011

41. Given the following:

- Unit 1 is operating at 100% power when a LOCA occurs.

- A Safety Injection has been actuated.

- Containment pressure is 1.1 psig and slowly rising.

Which ONE of the following identifies the expected position of 1 -FCV-61 -110, GLYCOL COOLED FLOOR RETURN HEADER ISOL?

A. CLOSED due to a containment isolation signal.

B. CLOSED due to an Auxiliary Building isolation signal.

C. OPEN unless the containment pressure rises to Hi-Hi setpoint.

D. OPEN unless Glycol Storage Tank level reaches Lo-Lo setpoint.

Page 41

10-2011 Watts Bar RO NRC License Exam 12/29/2011

42. Which ONE of the following is reciuired to automatically start the Containment Spray Pump lA-A room cooler?

A. Containment Spray Pump lA-A running ONLY.

B. Room temperature increases to 95°F ONLY.

C. Either Containment Spray Pump lA-A running OR room temperature increases to 95°F.

D. Room temperature increases to 95°F ONLY if the Containment Spray pump running.

Page 42

10-2011 Watts Bar RO NRC License Exam 12/29/2011

43. Given the following:

- Containment spray pumps are running after automatically starting during a LOCA.

- Containment pressure has dropped and the procedure directs the pumps be stopped.

Which ONE of the following identifies the minimum signals required to be reset to allow the Containment Spray pumps to remain off when their control switches are returned to A AUTO after the pumps are stopped?

A. Containment Spray, only B. Phase B and Containment Spray, only C. Safety Injection and Containment Spray, only D. Safety Injection, Phase B and Containment Spray Page 43

10-2011 Watts Bar RO NRC License Exam 12/29/2011

44. Given the following:

- At EOL, a reactor startup is in progress following a 6-day outage.

- The Reactor Engineer has provided an ECP which predicts the reactor going critical at 120 steps on Control Bank D.

Which ONE of the following completes the statements below?

(1) will result in the critical rod height being HIGHER than the value predicted by the ECP.

(2) is the maximum allowed tolerence between the ECP and the actual critical position before the insertion of all control banks is required.

A. (1)An inadvertent drop in steam pressure of 50 psi 9 (2)1000 pcm B. (1) A closure of all MSIVs (2)1000 pcm C. (1) An inadvertent drop in steam pressure of 50 psig (2) 750 pcm D. (1) A closure of all MSIVs (2) 750 pcm Page 44

10-2011 Watts Bar RD NRC License Exam 12/29/2011

45. Given the following:

- Unit 1 is operating at 550 MWe.

- Operators have placed the second main feed pump in service.

- Annunciator 49-E, MN/STBY FWP SUCTION NPSH LO, alarms.

- The operating crew determines Main Feed Pump Suction pressure to be 120 psig.

Which ONE of the following identifies the action required by the Annunciator Response Instruction?

A. If suction pressure cannot be restored to greater than 250 psig, a turbine trip is required.

B. Suction pressure is low and needs to be raised but currently is above the minimum required.

C. Unless suction pressure is restored to greater than 250 psig, a trip of one MFP is required.

D. Unless suction pressure is restored to greater than annunciator 49-E setpoint, a trip of both MFPs is required.

Page 45

10-2011 Watts Bar RO NRC License Exam 12/29/2011

46. Given the following:

- Unit 1 was at 100% power with the TD AFW pump unavailable.

- S/G #2 experiences a steam line break inside containment.

- S/G #2 conditions are as follows:

- Level is currently 12% WR.

- Pressure is 80 psig and decreasing.

- No operator action has been taken on the AFW system.

Which ONE of the following completes the statement below?

(1) will have been automatically closed to prevent (2)

Note: 1-LCV-3-156 is MD AFW PUMP IA-A SG 2 LEVEL CONTROL l-LCV-3-156A is SG2AUX FEED WATER I-LCV-3-156 BYPASS A. (1) 1-LCV-3-156 ONLY (2) Cavitation damage to the valve B. (1) 1-LCV-3-156 ONLY (2) AFW pump runout C. (1) Both 1-LCV-3-156 and 1-LCV-3-156A (2) Cavitation damage to the valves D. (1) Both 1-LCV-3-156 and 1-LCV-3-156A (2) AFW pump runout Page 46

1 0-2011 Watts Bar RO NRC License Exam 12/29/2011

47. Given the following:

- Unit 1 is operating at 4% power.

- Main Feed Pump B is in service.

- Main Feed Pump A is NOT reset.

- All Steam Generator levels are at 38% NR.

Which ONE of the following identifies the status of the AFW Pumps immediately after Main Feedwater Pump B trips?

A. Only the TDAFW pump has automatically started.

B. Only the MDAFW pumps have automatically started.

C. Both the MDAFW pumps and TDAFW Pump have automatically started.

D. Neither the MDAFW pumps nor TDAFW Pump have automatically started.

Page 47

10-2011 Watts Bar RO NRC License Exam 12/29/2011

48. Given the following:

- Unit 1 is operating at 60% power.

- 480V Shutdown Board 1A2-A de-energizes due to an internal fault.

- The crew enters AOl-43.01, Loss of Unit 1 Train A Shutdown Boards.

Which ONE of the following completes the statement below?

The loss of the board results in (1) and the condition can be mitigated by (2) in accordance with AOI-43.01.

A. (1) increasing Main Turbine Oil temperature (2) placing 1-TIC-24-69, MTOT TEMP TEMP CONTROL, in MAN and opening the TCV B. (1) the loss of most radiation monitor rate meters in the MCR (2) transferring Instrument Power Rack A to ALTERNATE C. (1) a turbine trip due to Stator Cooling Water temperature increasing (2) transferring Instrument Power Rack A to ALTERNATE D. (1) increasing Generator Hydrogen temperature (2) placing 1-TIC-24-48, GENERATOR H2 TEMP CONTROL, in MAN and opening the TCV Page 48

10-2011 Watts Bar RO NRC License Exam 12/29/2011

49. Given the following:

- Unit I is operating at 100% power.

- A battery discharge test is in progress on I 25v DC Battery IV and the 125v DC Battery Board V is connected to the 125v DC Battery Board IV.

- 0-SI-0-3, Weekly Log, is being performed.

Using 0-Sl-0-3, Appendix A, which ONE of the following identifies the status of the 125v DC Battery Board IV and the 120v AC Vital Inverter 2-IV?

REFERENCE PROVIDED 125v DC Battery Board IV Vital lnverter 2-IV A. Operable Inoperable B. Operable Operable C. Inoperable Inoperable D. Inoperable Operable Page 49

10-2011 Watts Bar RO NRC License Exam 12/29/2011

50. Given the following

- Unit I was operating at 100% power when a safety injection occurred.

- Eighteen (18) seconds after Safety Injection, a loss of 125v Vital DC Power Channel II occurs.

Which ONE of the following identifies the current status of RHR pump I B-B?

A. RHR pump I B-B is NOT running but can be started from the MCR handswitch.

B. RHR pump lB-B is NOT running and can NOT be started from the MCR handswitch.

C. RHR pump I B-B is running and can be stopped from the MCR handswitch.

D. RHR pump lB-B is running but can NOT be stopped from the MCR handswitch.

Page 50

10-2011 Watts Bar RO NRC License Exam 12/29/2011

51. Given the following:

- Unit I is operating at 100% power with DG lA-A connected to the shutdown board during performance of the monthly surveillance instruction.

- CCP lA-A is in service.

- I phase of the 50 overcurrent relay acutates on Shutdown Board IA-A Emergency Feeder Breaker 1912.

- I second later Offsite power is lost.

Which ONE of the following identifies how the RHR pump lA-A and CCP lA-A are affected?

A. The CCP will continue to run and the RHR pump will not be started.

B. The CCP will be tripped and neither pump will sequenced on by blackout relays.

C. Both the CCP and the RHR pump will be sequenced on by blackout relays.

D. Only the CCP will be sequenced on by blackout relays.

Page 51

10-2011 Watts Bar RO NRC License Exam 12/29/2011

52. Given the following:

- Annunciator 186A, MCR INTAKE 0-RM-90-1 25/1 26 RAD HI, alarms.

- Both 0-RM-90-125, MCR INTAKE and 0-RM-90-126, MCR INTAKE have the RED light LIT on 0-M-12.

Which ONE of the following completes the statement below?

The MCR is maintained at a positive pressure by the (1) and if 0-RM-90-206A, MCR EMERG INTAKE, subsequently detects high radiation, the outside air supply will (2) to the alternate source.

A. (1) Main Control Room Air Handling Units (2) automatically realign B. (1) Main Control Room Air Handling Units (2) require manual action to realign C. (1) Control Building Emergency Air Pressurization Fans (2) automatically be realigned D. (1) Control Building Emergency Air Pressurization Fans (2) require manual action to realign Page 52

10-2011 Watts Bar RO NRC License Exam 12/29/2011

53. Given the following:

- Unit 1 is operating at 100% power.

- ERCW pump handswitch status:

- A-A is in P-T-L

- B-A is in A-AUTO and pump stopped.

- C-A is in A-AUTO and pump running.

- D-A is in A-AUTO and pump stopped.

- Emergency Power Selector Switches are positioned to B-A and C-A, respectively.

- A loss of offsite power occurs.

Which ONE of the following completes the statements below?

Prior to the loss of the offsite power, Tech Spec LCO 3.7.8 Essential Raw Cooling Water (ERCW) System (1) met.

After the blackout sequence relays complete restoration of loads on the Shutdown Boards, 0-Pl-67-18A, A ERCW SUP HDR PRESS, will indicate (2) before the loss of offsite power.

w A. was same as B. was higher than C. was NOT same as D. was NOT higher than Page 53

10-2011 Watts Bar RO NRC License Exam 12/29/2011

54. Given the following:

- Unit 1 is in Mode 3 following a reactor trip when a loss of off-site power occurs.

- All Diesel Generators start and restore the shutdown boards.

Which ONE of the following completes the statements below?

As control air pressure drops, Control and Station Air Compressor A (1) as needed automatically.

The compressor is supplied from (2)

A. (1) will start and load (2) 480V SD Bd 1A2-A B. (1) will start and load (2) 480V SD Bd 2A2-A C. (1) must be manually started but will load (2) 480V SD Bd 1A2-A D. (1) must be manually started but will load (2) 480V SD Bd 2A2-A Page 54

10-2011 Watts Bar RO NRC License Exam 12/29/2011

55. Which ONE of the following identifies ventilation systems that exhaust out a Shield Building Exhaust Vent?

A. EGTS Cleanup Fans and Annulus Vacuum Control Fans B. EGTS Cleanup Fans and Containment Purge Exhaust Fans C. Fuel Handling Exhaust Fans and Annulus Vacuum Control Fans D. Fuel Handling Exhaust Fans and Containment Purge Exhaust Fans Page 55

10-2011 Watts Bar RO NRC License Exam 12/29/2011

56. Given the following:

- 480v Emergency Common Transformer is out of service.

Which ONE of the following describes the effect on the Control Rod Drive MG Sets if 6900v Unit Board IC is de-energized by relay operation?

A. Both MG sets lose power to the motor.

B. Neither MG set loses power to the motor.

C. Only A MG set loses power to the motor.

D. Only B MG set loses power to the motor.

Page 56

10-2011 Watts Bar RO NRC License Exam 12/29/2011

57. Given the following:

- Unit us operating at 80% steady state power with all controls in automafic.

Which ONE of the choices below completes the following sentence?

Assuming no operator action, RCS temperature will INCREASE if the (1) fails (2)

A. N43 Power Range lower detector HIGH B. N43 Power Range upper detector LOW C. Rod control auctioneeréd high nuclear power signal HIGH D. Rod control auctioneered high nuclear power signal LOW Page 57

10-2011 Watts Bar RO NRC License Exam 12/29/2011

58. Given the following:

- Unit 1 is operating at 100% power with all controls in automatic.

- 1-XS-68-339E, PZR LEVEL CONTROL CHANNEL SELECT, is selected to the Ll-68-3391B320 position.

- A small leak develops on the upper tap fitting for Pressurizer level transmitter 1 -LT-68-339.

Which ONE of the following completes the statement below?

1-Ll-68-339 indication will start (1) and the actual pressurizer level will (2) w A. rising remain constant B. rising be dropping C. dropping remain constant D. dropping be dropping Page 58

10-2011 Watts Bar RO NRC License Exam 12/29/2011

59. Given the following:

- Unit 1 was operating at 100% power when a small break LOCA resulted in a reactor trip and safety injection.

- The crew is now performing E-1, Loss of Reactor or Secondary Coolant, and is determining if the Hydrogen Recombiners are to be placed in service.

- Containment Hydrogen analyzers 1-H21-43-200 and 1-H21-43-210 indicate 0.5%.

Assuming conditions do not change, which ONE of the following identifies the hydrogen mitigation systems that will be in service when E-1 is completed?

A. ONLY the hydrogen igniters B. ONLY the hydrogen recombiners C. BOTH the hydrogen igniters and the hydrogen recombiners D. NEITHER the hydrogen igniters nor the hydrogen recombiners Page 59

10-2011 Watts Bar RO NRC License Exam 12/29/2011

60. Given the following:

- Unit 1 isatl00%RTP.

- Fuel Assembly shuffles are being made in the Spent Fuel Pit.

- 0-RM-90-102, Spent Fuel Pit Radiation Monitor, has been declared INOPERABLE and removed from service due to an instrument malfunction.

- Auxiliary Building Supply fans IA and 2B are running.

Which ONE of the following completes the statements below?

Technical Specifications would (1) continued movement of fuel assemblies in the Spent Fuel Pit.

If 0-RM-90-1 03, Spent Fuel Pit Radiation Monitor, subsequently detected Hi Radiation, (2) Auxiliary Building General Supply fan(s) would trip.

Li)

A. NOTallow ONLY2B B. NOT allow 1A and 2B C. allow ONLY 2B D. allow IA and 2B Page 60

10-2011 Watts Bar RO NRC License Exam 12/29/2011

61. Given the following:

- Unit 1 was operating at 100% power when a reactor trip occurred.

- A steam dump Tavg Hi bistable malfunction resulted in 6 Steam Dump valves remaining full open as Tavg dropped following the reactor trip.

Which ONE of the following completes the statements below?

Tavg dropping to 550° F will result in (1)

If the operators had placed the handswitches listed below to OFF prior to Tavg reaching 550°F, the steam dump valves would have closed (2) was/were placed to OFF.

Note:

1-HS-1-103A, STEAM DUMP FSV A 1-HS-1-103B, STEAM DUMP FSV B A. (1) all 6 of the steam dump valves closing (2) after either switch B. (1) all 6 of the steam dump valves closing (2) g.pjy after both switches C. (1) only the 3 cooldown valves remaining open (2) after either switch D. (1) only the 3 cooldown valves remaining open (2) ppjy after both switches Page 61

10-2011 Watts Bar RO NRC License Exam 12/29/2011

62. Given the following:

- Unit 1 is operating at 100% power.

- Waste Gas Decay Tank J relief valve develops a flange leak and the tank contains high activity gas.

Which ONE of the following identifies how the radiation monitors listed below will respond to the gas release?

Note:

O-RE 118, Waste Gas Rad Monitor O-RE-90-1O1, Auxiliary Building Ventilation Monitor 1-RE-90-400, Unit 1 Shield Building Vent Monitor A. Both 0-RE-90-1 18 and 1 -RE-90-400 will detect the release.

B. Only 0-RE-90-101 will detect the release.

C. Only I -RE-90-400 will detect the release.

D. Both 0-RE-90-1 18 and 0-RE-90-1 01 will detect the release.

Page 62

10-2011 Watts Bar RO NRC License Exam 12/29/2011

63. Given the following:

- Unit I is operating at 100% power.

- While performing a board walkdown, the incoming OAC determines annunciator 174-E, 1-RR-90-I AREA MONITORS INSTR MALE, is LIT.

Which ONE of the following completes the statements below?

In accordance with ARI for window 1 74-E, the operator would determine which Area Radiation Monitor was the cause of the annunciator being LIT by the (1) on the associated rate meter.

A condition that would cause the alarm is the L2)

A. (1) GREEN light being DARK (2) rate meter function switch in ALARM ADJ B. (1) GREEN light being DARK (2) sample flow less than setpoint C. (1) RED, AMBER and GREEN lights all being LIT (2) rate meter function switch in ALARM ADJ D. (1) RED, AMBER and GREEN lights all being LIT (2) sample flow less than setpoint Page 63

10-2011 Watts Bar RD NRC License Exam 12/29/2011

64. Given the following:

- Unit 1 has reduced power due to a condenser tube leak that has been identified in the East Side tubes.

- The unit is currently at 34% power.

- CCWP 1 D has been removed from service.

- CCWPs 1A, 1B, and IC are each running 235 amps.

- East side amertap system has been shutdown.

- Condenser Vacuum Pumps 1A and lB are in service.

Which ONE of the following identifies an additional operating condition that MUST be established when removing the East Side Waterboxes from service in accordance with SOl-27.01, Condenser Circulating Water System?

A. Turbine load MUST be reduced.

B. An additional CCWP is required to be stopped.

C. Stop one of the Condenser Vacuum Pumps.

D. Discharge valves on running CCWPs must be throttled.

Page 64

10-2011 Watts Bar RD NRC License Exam 12/29/2011

65. Which ONE of the following identifies why 0-SW-026-0320, RAW SERVICE WATER ISOLATION VALVE 0-FCV-26-320, located in the Makeup Water Treatment Plant Control Room, would be placed to OFF?

A. Prevent exceeding maximum flow rating of the water treatment system following the start of any fire pump.

B. Prevent overpressurizing the water treatment system following the start of any fire pump.

C. Prevent the automatic closure of 0-FCV-26-320 due to a diesel fire pump start.

D. Prevent automatic closure of 0-FCV-26-320 when an electric fire pump start signal is generated.

Page 65

10-2011 Watts Bar RD NRC License Exam 12/29/2011

66. Given the following:

- Unit 1 is being returned to service following a refueling outage.

Which ONE of the following is NOT identified in the GO procedures as requiring a Public Address (PA) announcement be made?

A. Entering Mode 4 B. Reactor Startup lnitation C. Reactor Critical D. Opening MSIVs Page 66

10-2011 Watts Bar RD NRC License Exam 12/29/2011

67. Using the attached ICS AFD TARGET DISPLAY screen printout, which ONE of the following choices completes the following statements?

TheAFDHIGHLIMITis (1)

If (2) outside of the limit, TS LCD 3.2.3, Axial Flux Difference, action statement will be entered.

REFERENCE PROVIDED w

A. -5 any NIS channel is B. -5 at least 2 NIS channels are C. +7 any NIS channel is D. +7 at least 2 NIS channels are Page 67

10-2011 Watts Bar RD NRC License Exam 12/29/2011

68. Given the following:

- The Unit is in Mode 6, with refueling operations in progress.

- The 30th. fuel assembly is being loaded into the core.

Which ONE of the foliwing conditions, in accordance with FHI-7, Fuel Handling and Movement, will require fuel handling activities be stopped immediately?

A. An unanticipated rise in count rate by a factor of two occurs on responding nuclear channel during any single loading step.

B. Communications is lost between Containment and the Control Room.

C. Water in the Spent Fuel Pit in not clear enough to view the Fuel top Nozzles without supplemental lighting.

D. Boron concentration drops by 18 ppm as determined by two successive samples of Reactor Coolant.

Page 68

10-2011 Watts Bar RO NRC License Exam 12/29/2011

69. Given the following:

- Unit 1 is operating at 100% power.

- Maintenance is to be performed on AFW Pump lB-B.

- Protected Equipment portable sign stands have been placed locally at AFW Pump lA-A.

- An engineer request permission from the CR0 to enter the area protected.

Which ONE of the following completes the statements below in accordance with ODM-4.0, Protected Equipment?

(1) is the organization responsible for the placement of the Protected Equipment portable sign stands.

The CR0 would direct the engineer to contact the (2) to get approval to enter the area being protected.

A. Operations Shift Manager B. Operations Work Control SRO C. Maintenance Shift Manager D. Maintenance Work Control SRO Page 69

10-2011 Watts Bar RO NRC License Exam 12/29/2011

70. During shutdown for a Refueling Outage, which ONE of the following identifies the highest level of risk that can be voluntarily entered and who must approve entering the risk in accordance with NPG-SPP-07.2.1 1, Shutdown Risk Management.

A. ORANGE Plant Manager B. ORANGE Outage Manager C. RED Plant Manager D. RED Outage Manager Page 70

10-2011 Watts Bar RO NRC License Exam 12/29/2011

71. Given the following:

- The crew implemented AOl-33, Steam Generator Tube Leak, due to a tube leak in SG #1 and has placed the unit in Mode 3.

- ES-0.1, Reactor Trip Response, has been completed and the crew has resumed performance of AC 1-33.

As a result of actions directed in AOI-33, which ONE of the following will require an entry into a Technical Specification Action statement?

A. Closing the SG #1 Main Steam Isolation Valve.

B. Adjusting the SG #1 PORV controller setpoint to 90%.

C. Isolating the TD AFW pump steam supply valve from SG #1.

D. Blocking Low Steamline pressure and Low PZR pressure SI actuation.

Page 71

10-2011 Watts Bar RO NRC License Exam 12/29/2011

72. Given the following:

- Unit us operating at 100% power.

- Annunciator 183-C, AB VENT 0-RM-101 RAD HI, alarms.

- Operators have been unsuccessful in identifying the source of the release.

Which ONE of the following completes the statement below?

If the alarm source is NOT known, the ARI directs the operators to within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the alarm receipt.

A. stop and lock out the Fuel Handling Area Exhaust fans B. close LWR CNTMT PURGE EXH PRESS RLF, 1-FCV-30-40 & 1-FCV-30-37 C. manually initiate an Auxiliary Building Isolation signal D. notify RADCON to restrict nonessential entry into the Auxiliary Building Page 72

10-2011 Watts Bar RO NRC License Exam 12/29/2011

73. Given the following:

- A LOCA has occurred and a SAE has been declared.

- The TSC and OSC have been activated.

- To prevent damage to equipment needed for protection of the public, it is recommended that an individual make an entry into the lA-A Safety Injection Pump Room 1A.

- Projected dose rate in the pump room is 1.0 xl 0 mR/hr.

- Duration of the exposure is expected to be 6 minutes.

Which ONE of the following individuals must authorize this exposure?

A. Radcon Manager ONLY B. Site Emergency Director C. Plant Manager D. Radcon Manager OR Site Vice President Page 73

10-2011 Watts Bar RO NRC License Exam 12/29/2011

74. Given the following:

- Unit 1 is operating at 50% power, with all systems aligned normally with Train A CCP and CCS pumps in service.

- A loss of IA-A 6.9KV Shutdown Board due a differential relay operation occurs.

- The OAC observes RCP Seal Water Injection flow to all RCPs to be 0.

- The Control Building AUO reports extensive damage to the lA-A 6.9 KV Shutdown Board bus bars.

- The crew implements AOl-43.01, Loss of Unit I Train A Shutdown Boards.

Under these conditions, RCP seal cooling is (1) and in accordance with AOl-43.01, the crew will (2) w A. available Isolate letdown prior to starting CCP 1 B-B.

B. unavailable Isolate letdown prior to starting CCP 1 B-B.

C. available Start CCP 1 B-B prior to isolating letdown.

D. unavailable Start CCP I B-B prior to isolating letdown.

Page 74

10-2011 Watts Bar RO NRC License Exam 12/29/2011

75. Given the following:

- The plant is operating at 100% power.

- Annunciator 114-A, SSPS-A GENERAL WARNING is LIT.

Which ONE of the following completes the statement below?

(1) will cause the alarm and the probable source of the alarm can be determined locally by (2)

A. Racking in Reactor Trip Semi-Automatic Tester Board edge Bypass Breaker A LED lights B. A blown Ground Return Fuse Semi-Automatic Tester Board edge LED lights C. Racking in Reactor Trip Status Lights on the outside of the Bypass Breaker A SSPS Panels D. A blown Ground Return Fuse Status Lights on the outside of the SSPS Panels Page 75

10-2011 Watts Bar RO NRC License Exam 1212912011 REFERENCE PACKAGE

1. Steam Tables
2. AOl-i 1, Appendix A, Condenser Vacuum ICS Graph, (1 page)
3. O-SI-O-3, Weekly Log, Appendix A, (2 pages)
4. ICS AFD TARGET DISPLAY, (1 page)
5. ECA-1-1, Loss of RHR Sump Recirculation, (2 pages)

LU o A & B and C CONDENSER VACUUM LO-LO AND LO ALARMS cm o

1 zr tJ (I) 0-i 1

Li) Ui 0

C, 0 0 0

Q (U) I (1)

CI)

(0 (DO (1) (DZ w o (DW (0

O C0

-f (1)

(0 0 (I) C LU C)

3-,

OD) 0.

LU 133 13)

(0:3 Q)

(DCL Z LII (DZT

-- c 0

z C) 0 CD 3

0 Li CD CL 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 LOAD (MWe)

WBN I Weeky Log j Unit 0 Rev. 0045

[ Page 20 of 43 Appendix A (Page 9 of 24)

SR 3.8.4.3 SR 3 8 5 1 SR 3.8.7.1 480V SD SD 2B2-B L8OV SD SD 2A1-A SR 3.8.8.1 SR 3.8.9.1 NC(IQA) NO(1OA)

SR 3.8.10.1 K- LiOI NC NO 4SSVACVITAL I TRANSFER swrrc iv A

I- UOPER.OELE S-PNL-236-4 4 80V AC V ITA.

DISCONNECTPNLCHAANEL IV (1) FRDSI O.OW-26-4SW3

( SXSW20679002-S, OUTPUT 2 I 2SF DC TRANSFER SWITCH SELECT CHARGERS 7.5)9.5 NOTE 2 125V VITAL BATT BD IV iNC) r_i V-1iISL-23V-4C3(I1 I 2-5130231--805301 I 1-5101-IUS(CE301 I I lOUD) NC)

IRe) 1 I I c) I 2-EIR-ZUF-4CBI 1-EER-ZW..ILT,I (10-5b01.235--C51 (NC)

I CR01 I

I ---

I52.W I I I 2.E1D021).1CB2 V.P.ISi..T04 cEO (OWl

() (NC) i-Y.SW-235-4 2-KS W-235.4 120 VAC VITAL I Air:

84320 POWER SD l-IV NOR 125 VAC VITAL POTP POWER 1

r ITWI A IN TRANS PER TRANSFER 1-SW-2054 120 VAC VITAL 2-SW-230.4 120 Vao VITAL NC INSTR POWEF: ED 1-IV DISC NC INEW POWER SD 2-IVDISC 1-SD 205-4 120 OW VITAL 2-SD 205-4 120 Vac VITAl.

NOW POWER BDARD I-IV INSW POWER BOARD 2-IV NOTE (1) In Modes 5&6 only one train of ac/do PWR is reooired, if this train is not reauired this aoe may be N/A.

(2) When 7-S or .S charger is connected to Bed Sd t n rify assoc. train Transfer Switches are closed and Jt bkrs are open.

INITIALS OF DATA COLLECTOR: DATE REMARKS: 7 V

WBN Weekly Log 0-Sl-0-3 Unit 0 Rev, 0045 Page 21 of 43 Appendix A (Page 10 of 24)

SR 3.8.9.1 NCI480VAwrBId C

9 omMCCC SR 3.8.10J I 0-BIcR-236-5 NCI 125V VITAL V I r 9 V 125VV1ICh BAIT V C82 125V VITAL NC Sennote2 (10l) BATTBDV (102)

NO No(4 (201) (202) 125V DC 01ST PNL OA 125V DC 01ST PNL 5B ANO NO (301) (302) i I (

1 I I I

--1 I I I I I

INO I I NO I

z I I

NOI O)i 2

( 1 I

I TNoI I (4/0)

I__..__I 0-DPL-236-1 0-DPL-236-3 0-DPL-236-2 0-DPL-236-4 125V VITAL 125V VITAL 125V VITAL 125V VITAL BATT SD I BAiT SD III BATT BUll BATT 00 IV CLOSED Uc)

NOTE I Only one batlery board may he feed Irom the 5th battery board at any one lime. () AVAILABLE NOTE 2: 0-BKR-238-5/102 must be OPEN when 51h ballery is Inservice for batlery Sd I, II, III, or IV INOPERABLE INITIALS OF DATA COLLECTOR: DATE REMARKS: F

Vain JJarm Gr3phic:c Trends Points oorn/Layers Print Help 06-JUL 2011 07:46:16 EiLiJi iHLL. (4 11H 1) l.{)[)E [}0{H0US[ II IL U 4I POWER LEVEL CTRL BANK [) (STEPS) w AFD N I S CHA.[L 41 7 E AF[i NI S flANNEL ti /

AED N I S CHANNEL 1 3 - I J

1 AED MIS CHANNEL 44 / I

\, \.

66- 7O/

NIS ACTUAL AFD / 3 o L HIS TARGET AR) 7 1

1 AF[) LOW L IN IT AE[) HIGH LIMIT

(;c} NTR) L LOW [ IN CO HTO L HIGH [IN Ji TFjTTrfrrnJThrpJTq-TfTT[ 1rrrrrinn o 2 21) 1 10 14) 1 20 AX IAL FLUX D I FFERENCE  % TINE OUT OF BAN[) ACCUM (HIM) j:

TT1)9 Vi1K A 4)I I)US SEC LV L i PFI[I [ACK CPU I H0[}E j

WN Loss of RHR Sump Recircuaton ECA-1.1 Unftl Rev. 0012 Step Lti07Expted Response Response Not Obtained

19. CHECK SI termination criteria:
a. RVLIS greater than 60% a. iF RVLIS is less than or equal to with NO RCP running, setpoint, THEN OR **

GO TO Step 25.

RVLIS greater than 63%

with ANY RCP running.

b. RCS subcooling greater than b. ESTABLISH minimum ECCS flow required from table: for decay heat removal:
1) REFER TO Figure 1, Minimum SI Flow For Decay Heat Versus Time After Trip.
2) GO TO Step 25.

RCS PRESS BETWEEN REQUIRED SUBCOOLING 285 AND 585 psig 115°F [1 35°F ADV]

585 AND 1085 psig 102°F [1 23°F ADV) 1O85AND 1885 psig 97°F[117°FADV]

Greater than 1885 psig 94°F [1 14°F ADVJ

20. RESET Phase A and Phase B.

Page 12 of 35

WBN Loss of RHR Sump Redrcu[ation ECA-1.1

[ Ut1 Rev. 0G12 Figure I (Page 1 off)

Mtimum S Fo*w for Decay Heat vs. Time After Thp 700.0 600.0 500.0 C) 400.0 0

300.0 LL 200.0 100.0 0.0 1D 100 1000 10000 Time After Trip (Minutes)

Page 29 of 35

KEYID 1SCOR1NG & kEsci DiULP;INSWER SCORING NCS Test Sheet 0000 PRINTING ( O CORRECT ANSWER 0 MARK X 0 TOTAL ONL 1001W L OPTIONS:

L MARK ONLY ONE Form No. 95677 TF TF 100*00 51 00 © 50 TF 26*000 7600 © 00 Reorder Phone Number 2000*0 52000*0 1-800.367.6627 2700S©© 700000 3*0000 530S000

28000*0 7800000 00*00 29*0000 00000

5 000*0 ss0*000 ANSWER PERFORMANCE 3000*00 8000000 KEY INFO. ASSESSMENT 6*0000 560S000 #OF KEYS  % OF owrs 31000*0 8100000 ITEM EARNED 7 0* 000 57000*0 COUNT 00 = 100%

32 00 *0 8200000 8 00*00 58 0* © 0 E 33000 83 00 © 00 Q 0 0 9 000*0 59

  • 0000 OcDaO L aD 34 0*000 8400000 000 P cc 0 10 oo©.o 60 000*0 00 T 0 0 35 S 00 8500000 00 0 GD ii o.©©© 61 *000 00 V cc A

0 3600*00 8600000 00 L cc 0 U

12 000 5 0 620*000 00 C 0 0 3700*00 8700000 cc 0 13 0*000 63*0000 cc 0 38*0000 8800000 1400*00 640*000 Copyright © 1994 National Computer Systems, Inc.

390*000 8900000 A!! rights reserved. Printed in U.S.A.

15 000*0 65000*0 40 9000000 1600*00 66 000*0 41 *0000 91 00000 17000*0 67000*0 42 00* 9200000 18 00*00 68 0*

43*0000 19 *0000 69*0000 44000*0 9400000 20 0*000 70*0000 450*000 9500000 21 *0000 7100*00 46*0000 9600000 22 0*000 720*000 4700* 00 9700000 23 00 © *0 730*000 48 0*000 9800000 24 00 © *0 @0 49 00*00 9900000 25 000*0 75 0*© ©© 50000*0 100 00000 COMBINED NUMBER POINTS CORRECT EARNED COMBINED L

PERCENT PERCENT CORRECT CORRECT 100 3, ITEM ROSTER LETTER NUMBER GRADE SCORE SCORE STUDENT ID NUMBER RESCORE RESCORE MARKING 00 () 000(Q) 0 (.2)0 INSTRUCTIONS 0000000000 0 0 0 00 0 0 0 CD 0 h

NAME Use a No. 2 Pencil 0000000000 0* © @0 0000000000 SUBJECT Fill oval completely O 0000000 () 0

,PERIOD Mark Reflex by NCf H

!lIt pliPer 00000 Erase cleanly 0000000000 0000000000 O 000000000