ML113640158
| ML113640158 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/30/2011 |
| From: | Operator Licensing and Human Performance Branch |
| To: | |
| References | |
| Download: ML113640158 (115) | |
Text
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 1. Given the following:
- A reactor trip occurs on Unit 1.
- ES-Ui, 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 SRO NRC License Exam 12/29/2011
- 2. Given the following:
- Unit 1 is 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 C2)
LIJ A. Rise >1.0 gpm B. Rise >logpm C. Lower >1.Ogpm D. Lower >logpm Page 2
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 3. Given the following:
- Unit 1 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 SRO NRC License Exam 12/29/2011
- 4. Given the following:
- Unit I 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 automatical[y start (2) ensure a suction path to the I B-B CCS pump Page 4
10-2011 Watts Bar SRO 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-PI-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-Pl-68-323 - 2220 psig 1-Pl-68-322 - 2230 psig
- Operators are performing AOI-18, 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 I -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 SRO NRC License Exam 12/29/2011
- 6. Given the following:
- Unit us at 45% power when the reactor fails to trip from a valid trip signal and cannot be tripped from the MCR handswitches.
- FR-S.1, 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 SRO NRC License Exam 12/29/2011
- 7. The following conditions exist on Unit 1:
- A SIG 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 SRO NRC License Exam 12/29/2011
- 8. Given the following:
- Unit us 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 Tavg/Tref 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 SRO 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) w 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 SRO 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 LCO 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 SRO NRC License Exam 12/29/2011
- 11. Which ONE of the following identifies the pump that will be sequenced on first following a blackout signal on a 6900v Shutdown board and a reason?
First Pump Reason A. COP 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 SRO 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 lii 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 BC-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 III 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 Jita! 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 SRO 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) w A. C drop B. A drop C. C remain constant D. A remain constant Page 13
10-2011 Watts Bar SRO NRC License Exam 12129/2011
- 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-i 0, 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)
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 SRO NRC license Exam 12/29/2011
- 15. Given the following:
- Unit 1 is operating at 100% power with the following conditions:
Megawatts 1210 MWe Megavars +20 Mvars GenVoltage 23.6Kv
- 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.
A. has lowering B. has raising C. has NOT lowering D. has NOT raising Page 15
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 16. Given the following:
- Unit I 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.
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 SRO 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 Ogpm 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 SRO NRC License Exam 12/29/2011
- 18. Given the following:
0900 - Areactortripoccurs.
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 I SIP and I CCP 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 SRO NRC License 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 OAC 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 Waifs Bar SRO 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 L)
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 SRO NRC License Exam 12/29/2011
- 21. Given the following:
- Unit 1 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 SG TARGET INCORE PRESSURE (PSIG) TEMP F) 1 100 491 F 1000 479T 900 466T 800 451F 700 434F 690 433F 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 SRO NRC License Exam 12/29/2011
- 22. Given the following:
- Main Turbine load is 660 MWe.
- Condenser vacuum is decreasing at 0.1 in-HgAlmin due to air in-leakage.
- The crew has entered AOl-il, Loss of Condenser Vacuum.
- Currently Condenser pressures are:
Zone A Zone B Zone C 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 Li)
A. has B B. has NOT B C. has C D. has NOT C Page 22
10-2011 Watts Bar SRO 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 AOI-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.
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 SRO 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 1 and 3 have no ERCW supply for the motor coolers.
- S/G Narrow Range levels are:
- 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 RCP5 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. RCPs1,2,and4ONLY Page 24
10-2011 Watts Bar SRO 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 (1)
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. (1) and stabilize at a lower value due to an increase in RCS temperature with lower ECCS injection flow (2) less B. (1) 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 SRO NRC License Exam 12/29/2011
- 26. Following a Small Break LOCA, the crew is performing the actions contained in FR-Ri, Pressurized Thermal Shock.
Which ONE of the following describes the reason for RCP restart in FR-P.i, 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 SRO 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 (21 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) atthe 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 SRO NRC License Exam 12/29/2011
- 28. Given the foflowing:
- Unit 1 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 SRO NRC License Exam 12/29/2011
- 29. Given the following:
- Unit I 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 A. filling #3 B. filling #2 C. draining #3 D. draining #2 Page 29
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 30. Given the following:
- Unit I 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. (1) rise overtime (2) place 1-HS-62-79A, LTDN HI TEMP DIVERT, to V.C. TK D. (1) rise overtime (2) initiate normal boration Page 30
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 31. Given the following:
- Unit I is operating at 100% power.
- Annunciator 110-D, LTDN TO DEMINS TEMP HI, alarms.
- The OAC determines the indication on 1-Tl-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 SRO 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)
A. decrease increase B. decrease decrease C. increase increase D. increase decrease Page 32
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 33. Given the following:
- Unit 1 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 SRO 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 PORVs are closed and placed in P-AUTO when (2) w 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°F in one hour Letdown flow exceeds charging flow D. 100°F in one hour PZR Liquid Temperature reaches 235° F Page 34
10-2011 Watts Bar SRO NRC license Exam 12/29/2011
- 35. Given the following:
- Unit us 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 IA (TBBP) is PULL A-P AUTO.
1-HS-70-130A, THRM BAR BSTR PMP IB(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.
Li) L?)
A. IA 20 B. lB 20 C. IA D. lB 35 Page 35
10-2011 Watts Bar SRO 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) w 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 SRO NRC License Exam 12/29/2011
- 37. Unit I is operating at 100% power when the following sequence of events occurs:
- Pressurizer Power Operated Relief Valve (PORV) I -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.Opsig rise atafasterrate Page 37
10-2011 Watts Bar SRO 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 125V DC Vital Battery Board I Power Boards II and IV B. 12OvAC Vital Instrument 125V DC Vital Battery Board II Power Boards II and IV C. 12OvAC 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 SRO NRC License Exam 12/29/2011
- 39. Given the following:
- Unit 1 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 SRO 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 SRO NRC License Exam 12/29/2011
- 41. Given the foHowing:
- Unit I 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 I -FCV-61-1 10, 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 SRO NRC License Exam 12/29/2011
- 42. Which ONE of the foflowing is required to automatically start the Containment Spray Pump IA-A room cooler?
A. Containment Spray Pump lA-A running ONLY.
B. Room temperature increases to 95°F ONLY.
C. Either Containment Spray Pump IA-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 SRO 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 SRO 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 psig (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 SRO 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 SRO 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 I-LCV-3-156A is SG 2 AUX FEED WA TER 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
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 47. Given the following:
- Unit I 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 SRO 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 AOl-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 SRO 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 125v DC Battery IV and the 125v DC Battery Board V is connected to the 125v DC Battery Board IV.
- 0-Sl-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 Baffery Board IV and the 120v AC Vital Inverter 2-IV?
REFERENCE PROVIDED 1 25v DC Battery Board IV Vital Inverter 2-IV A. Operable Inoperable B. Operable Operable C. Inoperable Inoperable D. Inoperable Operable Page 49
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 50. Given the fobwing
- Unit 1 was operating at 100% power when a safety injection occurred.
- Eighteen (18) seconds after Safety Injection, a loss of I 25v Vital DC Power Channel II occurs.
Which ONE of the following identifies the current status of RHR pump I B-B?
A. RHR pump 1 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 lB-B is running and can be stopped from the MCR handswitch.
D. RHR pump I B-B is running but can NOT be stopped from the MCR handswitch.
Page 50
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 51. Given the following:
- Unit 1 is operating at 100% power with DG IA-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 lA-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 SRO 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 SRO NRC License Exam 12/29/2011
- 53. Given the following:
- Unit I 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.
Li)
A. was same as B. was higher than C. was NOT same as D. was NOT higher than Page 53
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 54. Given the following:
- Unit I 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 SRO 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 Handhng Exhaust Fans and Annulus Vacuum Control Fans D. Fuel Handling Exhaust Fans and Containment Purge Exhaust Fans Page 55
10-2011 Watts Bar SRO 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 SRO NRC License Exam 12/29/2011
- 57. Given the following:
- Unit 1 is operating at 80% steady state power with all controls in automatic.
Which ONE of the choices below completes the following sentence?
Assuming no operator action, RCS temperature will INCREASE if the (1) fails (2) w A. N43 Power Range lower detector HIGH B. N43 Power Range upper detector LOW C. Rod control auctioneered high nuclear power signal HIGH D. Rod control auctioneered high nuclear power signal LOW Page 57
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 58. Given the following:
- Unit I is operating at 100% power with all controls in automatic.
- 1-XS-68-339E, PZR LEVEL CONTROL CHANNEL SELECT, is selected to the Ll-68-339/B320 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)
A. rising remain constant B. rising be dropping C. dropping remain constant D. dropping be dropping Page 58
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 59. Given the following:
- Unit I 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 SRO NRC License Exam 12/29/2011
- 60. Given the following:
- Unit 1 isatlOO%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 1A 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.
A. NOT allow ONLY 2B B. NOT allow IA and 2B C. allow ONLY 2B D. allow IA and 2B Page 60
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 61. Given the following:
- Unit I was operating at 100% power when a reactor trip occurred.
- A steam dump Tavg Hi bistable malfuncUon 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) pjjjy 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) jy after both switches Page 61
10-2011 Watts Bar SRO 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:
0-RE-90-1 18, Waste Gas Rad Monitor 0-RE 101, 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-90-1 01 will detect the release.
C. Only 1 -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 SRO NRC License Exam 12/29/2011
- 63. Given the following:
- Unit 1 is operating at 100% power.
- While performing a board walkdown, the incoming DAC determines annunciator 174-E, 1-RR-90-1 AREA MONITORS INSTR MALF, is LIT.
Which ONE of the following completes the statements below?
In accordance with ARI for window I 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 (2)
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 SRO NRC License Exam 12/29/2011
- 64. Given the foflowing:
- 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 I D has been removed from service.
- CCWPs 1A, 1B, and 1C are each running 235 amps.
- East side amertap system has been shutdown.
- Condenser Vacuum Pumps IA 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 SRO 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 over-pressurizing 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 SRO 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 Initation C. Reactor Critical D. Opening MSIVs Page 66
10-2011 Watts Bar SRO 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?
The AFD HIGH LIMIT is Li)
If 2) outside of the limit, TS LCO 3.2.3, Axial Flux Difference, action statement will be entered.
REFERENCE PROVIDED Li)
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 SRO NRC License Exam 12/29/2011
- 68. Given the following:
- The Unit is in Mode 6, with refueling operations in progress.
- The 3Qth. 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 y 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 SRO NRC License Exam 12/29/2011
- 69. Given the following:
- Unit i 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 IA-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 CRC 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 SRO 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 SRO NRC License Exam 12/29/2011
- 71. Given the following:
- The crew implemented AOI-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 AOI-33.
As a result of actions directed in AOl-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 SRO 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 SRO 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 IA.
- Projected dose rate in the pump room is 1.0 xl 5 mRlhr.
- 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 SRO NRC License Exam 12/29/2011
- 74. Given the following:
- Unit us operating at 50% power, with all systems aligned normally with Train A CCP and CCS pumps in service.
- A loss of lA-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)
(I-)
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 I B-B prior to isolating letdown.
D. unavailable Start CCP 1 B-B prior to isolating letdown.
Page 74
10-2011 Watts Bar SRO 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) w 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 SRO NRC License Exam 12/29/2011
- 76. Which ONE of the following completes the statements below?
(1) of the barriers in EPIP-1, Emergency Plan Classification Logic, Fission Product Barrier Matrix contain(s) a decision point based directly on a RVLIS threshold level.
The RVLIS threshold level that first requires a classification declaration to be made is (2) w A. Only 1 <44%
B. 2 <44%
C. Only 1 <33%
D. 2 <33%
Page 76
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 77. Given the following:
- Unit I was shutdown 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago for a refueling outage.
- RHR pump I B-B is tagged for maintenance.
- Current RCS temperature is 135°F and 80 psig.
- RHR pump IA-A trips and cannot be restarted.
- RCS temperature begins to rise.
- The crew is performing AOl-I 4, Loss of RHR Shutdown Cooling, and Section 3.9, RCS Alternate Cooling Method with RX Vessel Head Installed, has been initiated.
Which ONE of the following completes the statements below?
The cooling method that is directed to be attempted fjrt after AOl-I 4 Section 3.9 is implemented is (1)
A condition that will result in a REP declaration being required is (2)
A. (1) RCS feed and bleed using a CCP and a pressurizer PORV (2) the RCS incore temperature > 200°F B. (1) Natural circulation in the RCS using the steam generators (2) the RCS incore temperature > 200° F C. (1) RCS feed and bleed using a CCP and a pressurizer PORV (2) a failure to establish RHR within 15 minutes D. (1) Natural circulation in the RCS using the steam generators (2) a failure to establish RHR within 15 minutes Page 77
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 78. Given the following:
- Unit 1 is operating at 100% power with the following components out of service and tagged for maintenance:
- CCP lB-B
- CCSpumplB-B
- Component Cooling Water pump lA-A trips due to motor failure.
- AOl-i 5, Loss of Component Cooling Water (CCS), is implemented.
Which ONE of the following correctly completes the statements below?
In accordance with AOl-i 5, (1) minutes is the maximum time the Reactor Coolant Pumps are allowed to remain in service.
Implementation of (2) is required.
Note:
Attachment I - Alignment of ERCW to CCP IA-A Lube Oil Coolers Attachment 2 - Alignment of CCS Train B to SFP HX B Li) L?)
A. 10 only Attachment 1 B. 10 both Attachments C. 12 only Attachment I D. 12 both Attachments Page 78
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 79. Given the following:
- Unit 1 was operating at 100% power when a Safety Injection occurred due to a tube rupture in SG #2.
- The crew determined a Target Incore Temperature of 466°F and has initiated a rapid RCS cooldown in accordance with E-3, Steam Generator Tube Rupture.
- Before reaching the Target Incore Temperature, SG #2 pressure begins dropping in a uncontrolled manner.
Which ONE of the following completes the statements below?
The basis for cooling the RCS to a Target lncore Temperature of 466°F is to (1)
Based on current plant conditions, the SRO will transition to ECA-3.1, SGTR and LOCA Subcooled Recovery, (2)
A. (1) ensure adequate RCS subcooling is maintained after the subsequent RCS depressurization (2) immediately B. (1) ensure adequate RCS subcooling is maintained after the subsequent RCS depressurization (2) after the Target Incore Temperature is reached C. (1) provide the maximum amount of RCS temperature reduction without exceeding Pressurized Thermal Shock limits (2) immediately D. (1) provide the maximum amount of RCS temperature reduction without exceeding Pressurized Thermal Shock limits (2) after the Target Incore Temperature is reached Page 79
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 80. Given the following:
- Unit I is operating at 100% power with I -FCV-68-332, BLOCK VALVE FOR PORV 334, closed as required by Tech Specs due to PZR PORV 334 being inoperable but capable of being cycled.
- The following sequence of events occur:
1300 - Both 161 kV Offsite power supplies are lost.
1400 - Annunciator 91-A, PZR PORV/SAFETY OPEN, alarms due to PORV 340A opening and the PORV sticks open in mid-position during a pressure transient.
1401 - The QAC reports:
1-TI-68-331, PORV 340A & 334 TAILPIPE TEMP, rising, PORV 340A GREEN and RED indicating lights DARK, and 1 -FCV-68-333A, BLOCK VALVE FOR PORV 340A has been closed.
1500 - Both offsite power supplies are restored.
Which ONE of the following completes the statements below?
The indicating lights on 1-HS-68-340A, PZR PORV 340AA, were DARK at 1401 due to the (1)
Tech Specs, (2) allow continued operation in Mode I for an unlimited period of time with the current status of the pressurizer PORVs.
A. (1) loss of offsite power (2) will B. (1) loss of offsite power (2) will NOT C. (1) valve being at mid-position (2) will D. (1) valve being at mid-position (2) will NOT Page 80
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 81. Given the following:
- During performance of ECA-1 .2, LOCA Outside Containment, the crew determines RCS pressure is rising after RHR Train B cold leg injection valve 1-FCV-63-94 is closed.
- The crew then stops and locks out RHR pump I B-B and closes its suction valve.
Which ONE of the following identifies the required procedure transition?
A. ES-i .1, SI Termination B. E-1, Loss of Reactor or Secondary Coolant C. ECA-1 .1, Loss of Emergency Coolant Recirculation D. ES-i .2, Post LOCA Cooldown and Depressurization Page 81
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 82. Given the following:
- Unit I power was reduced to recover a dropped control rod in Control Bank D, Group 2.
- Following recovery of the dropped rod, the lift coils for the appropriate rods are reconnected.
- Annunciator 86-A, CONTROL ROD URGENT FAILURE, has NOT been reset.
- Rod Control is placed to MANUAL using 1-RBSS, ROD BANK SELECT.
Which ONE of the following completes the statements below?
When the OAC places the IN-HOLD-OUT switch lever to the IN position, (1)
The basis for the reactor power reduction required by Tech Spec 3.1.5, Group Rod Alignment Limits is to ensure (2)
A. (1) no rod motion will occur (2) AFD remains within limits B. (1) ONLY Bank D Group 2 rods will step IN (2) Core design limits for local LHR are not exceeded C. (1) no rod motion will occur (2) Core design limits for local LHR are not exceeded D. (1) ONLY Bank D Group 2 rods will step IN (2) AFD remains within limits Page 82
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 83. Given the following:
- Unit 1 was operating at 100% power with 1-RBSS, ROD BANK SELECT, in MAN.
- 1-XS-68-339E, PZR LEVEL CONTROL CHANNEL SELECT, is selected to LI-68-339 & 335.
- Performance of 1-Sl-68-33, Measurement Of Reactor Coolant Pump Seal Injection Flow, Section 6.2, Determination of Seal Leakage, is in progress.
- The CR0 has adjusted 1-HIC-62-89A, CHRG HDR-RCP SEAL FLOW CONTROL, as required and is now ready to record the seal injection flow rates for each of the RCPs.
- The Auctioneered High Tavg signal fails LOW.
Which ONE of the following completes the statements below?
Due to the Auctioneered High Tavg signal failure, the RCP seal injection flow indication will (1)
The Bases for Tech Spec LCO 3.5.5 requiring performance of this test is to ensure (2)
A. (1) remain the same (2) sufficient CCP flow to the RCS through ECCS injection lines during an accident B. (1) remain the same (2) CCP flow to the RCP seals remains within 8-13 gpm after an actuation of the ECCS during an accident C. (1) decrease (2) sufficient CCP flow to the RCS through ECCS injection lines during an accident D. (1) decrease (2) CCP flow to the RCP seals remains within 8-13 gpm after an actuation of the ECCS during an accident Page 83
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 84. Given the following:
0915 - The crew establishes control in the Auxiliary Control Room.
0915 - Tech Spec 3.0.3 is entered.
1030 - The crew initiates a natural circulation cooldown and the following SIG pressure trends are observed:
Time S/G Pressures 1030 1040 psig 1050 825 psig 1110 55opsig 1130 470 psig 1150 385 psig Which ONE of the following completes the statements below?
In accordance with Tech Specs, the crew (1) violated the limit for RCS cooldown rate.
The unit must be placed in Mode 5 no later than (2)
A. (1) has (2) 1515 the next day B. (1) has (2) 2215 the next day C. (1) has NOT (2) 1515 the next day D. (1) has NOT (2) 2215 the next day Page 84
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 85. Given the following:
- The Unit I operating crew is performing ES-0.3, Natural Circulation Cooldown with Steam Void In Vessel (With RVLIS).
- The Chem Lab reports increasing radiation level in Steam Generator #3.
Which ONE of the following completes the statements below?
Based on the current plant conditions, the operating crew will (1)
In accordance with EPIP-1, Emergency Plan Classification Logic, the minimum amount of tube leakage that, if exceeded, would exceed the System Degradation EAL criteria is (2)
(Assume the tube leakage is the only RCS leakage present.)
A. (1) transition to E-3, Steam Generator Tube Rupture (2) 10 gpm B. (1) transition to E-3, Steam Generator Tube Rupture (2) 25 gpm C. (1) implement AOI-33, Steam Generator Tube Leak, in parallel with the performance of ES-0.3 (2) logpm D. (1) implement AOI-33, Steam Generator Tube Leak, in parallel with the performance of ES-0.3 (2) 25gpm Page 85
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 86. Given the following:
- All Shutdown Bank Rods are withdrawn to the full out position.
Which ONE of the following identifies the minimum required status of the Reactor Coolant Pumps and the bases for the requirement per Tech Spec 3.4.5 RCS Loops MODE 3?
A. at least one in operation to ensure adequate decay heat removal capability.
B. at least one in operation due to the postulation of a power excursion because of an inadvertent control rod withdrawal.
C. both in operation to ensure adequate decay heat removal capability.
D. both in operation due to the postulation of a power excursion because of an inadvertent control rod withdrawal.
Page 86
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 87. Given the foNowing:
- The crew is currently performing ECA-3.1, SGTR and LOCA Subcooled Recovery, with safety injection termination in progress.
- Maximum containment pressure reached during the event is 2.3 psid.
- After stopping the first charging pump, RCS subcooling drops and stabilizes at 64°F.
Which ONE of the following completes the statement below?
Based on the current plant conditions, the SRO will direct the crew to (1) and then (2)
A. (1) restart the charging pump (2) continue with ECA-3.1 B. (1) leave the charging pump off (2) continue with ECA-3.1 C. (1) restart the charging pump (2) transition to ECA-3.2, SGTR and LOCA Saturated Recovery D. (1) leave the charging pump off (2) transition to ECA-3.2, SGTR and LOCA Saturated Recovery Page 87
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 88. Given the following:
- Unit I is operating at 100% power.
- Control Heater Bank D is out of service and its breaker is tagged.
- The following annunciators alarm:
90-B - PZR PRESS LO-DEVIN BACKUP HTRS ON 14-E - M-1 THRU M-6 MOTOR TRIPOUT
- Backup Heater Bank C 6.9kv breaker is determined to be tripped.
Which ONE of the following completes the statement below?
Assuming no operator action is taken, the heater failure will cause pressurizerpressuretobe (1)
The bases of the Tech Spec LCO required to be entered is (2)
A. (1) controlled less than 2235 psig (2) to maintain RCS subcooling following a loss of offsite power for an extended period of time B. (1) controlled less than 2235 psig.
(2) to ensure the core operates within the limits assumed in the safety analyses C. (1) returned to and controlled at 2235 psig.
(2) to maintain RCS subcooling following a loss of offsite power for an extended period of time D. (1) returned to and controlled at 2235 psig.
(2) to ensure the core operates within the limits assumed in the safety analyses Page 88
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 89. Given the following:
- Unit 1 is in Mode 3 preparing for a reactor startup when Tech Spec LCO 3.6.12, Ice Condenser Doors, is entered due to the following:
0600 Annunciator window 144-A, ICE COND INLET DOOR OPEN, alarms.
0620 An AUO reports one lower inlet door is cracked just off the closed position, is free to open, but will not close completely.
1010 - Maximum ice bed temperature verified to be 24.6°F.
1345 - Maximum ice bed temperature verified to be 24.8°F.
1850 - Maximum ice bed temperature verified to be 25.2°F.
2050 Inlet door is repaired, closed, and testing completed.
Which ONE of the following completes the statement below?
The purpose of the Ice Condenser lower inlet doors flow proportioning springs is to (1)
The earliest of the listed times a Tech Spec violation has occurred was at (2)
REFERENCE PROVIDED A. (1) limit the radiation at the inlet door to 5 rad/hr during normal operation (2) 1010 B. (1) limit the radiation at the inlet door to 5 rad/hr during normal operation (2) 1850 C. (1) ensures flow proportioning through the ice beds during an accident (2) 1010 D. (1) ensure a balanced flow through the ice beds during an accident (2) 1850 Page 89
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 90. Given the following:
- Unit I RCS temperature is 325°F with a heatup in progress following a refueling outage.
- During a board walkdown both indicating lights on 1-HS-72-40, RHR SPRAY HDR A. are discovered to be DARK.
- The AUO sent to investigate reports back:
- the valve is closed.
- the 480v breaker for the valve is tripped and cannot be reset.
Which ONE of the following completes the statements below?
Based on current plant conditions, LCO 3.6.6 Containment Spray System (1) met.
The next Mode change as the heatup continues (2) be made using the provisions of LCO 3.0.4.b.
A. (1) is NOT (2) may B. (1) is NOT (2) may NOT C. (1) is (2) may D. (1) is (2) may NOT Page 90
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 91. Given the following:
- Unit us defueled with fuel shuffles in progress in the spent fuel pool.
- Personnel report that a leak has developed and level is dropping in the spent fuel pool.
- The irradiated fuel assembly on the hoist is dropped from the Spent fuel Handling Tool while restoring it to a cell location in the storage rack.
- Gas bubbles are reported to be rising in the Spent Fuel Pool.
- Fuel Pool Rad Monitors 0-RM-90-102 and 0-RM-90-103 both increase to the alarm setpoint.
- The spent fuel pool level stabilized one foot above the siphon breaker.
Which ONE of the following identifies the event declaration to be made and the external notification having the shortest allowed time?
REFERENCE PROVIDED Declaration Notification A. NOUE NRC B. NOUE TEMA C. ALERT NRC D. ALERT TEMA Page 91
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 92. Given the following:
- Unit 1 operating at 100% power.
- An internal electrical failure causes the output of 0-RM-90-103, Spent Fuel Pit Area Radiation Monitor, to fail above the HI RAD setpoint.
- The operating crew is performing SOI-30.05, Auxiliary Bldg HVAC Systems, Section 8.8, Recovery from Aux Bldg Isolation (ABI), to restore the system.
Which ONE of the following completes the statements below?
During performance of SOI-30.05 to recover from the ABI, a section of (1) will be required to be implemented.
The ABI actuation (2) required to be reported to the NRC as an Immediate Notification.
A. (1) SOI-30.06, Auxiliary Building Gas Treatment System (2) is B. (1) SOl-31 .02, Post Accident Sampling Facility Ventilation System (2) is C. (1) SOI-30.06, Auxiliary Building Gas Treatment System (2) is NOT D. (1) S0I-31.02, Post Accident Sampling Facility Ventilation System (2) is NOT Page 92
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 93. Given the following:
- Unit 1 is at 4% power after being restarted from a refueling outage.
- An Appendix R valve is determined to be out of its required Fire Safe Shutdown (FSSD) condition.
Which ONE of the following completes the statements below?
A maximum time of (1) is allowed by OR 14.10 to restore the valve to the proper FSSD condition before additional action is required.
The planned entry into Mode I is (2) w A. 14 days NOT restricted by the action statement B. 14 days prohibited until the action statement is cleared C. 30 days NOT restricted by the action statement D. 30 days prohibited until the action statement is cleared Page 93
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 94. Given the following:
- Unit 1 is in Mode 3 following a reactor trip on the previous shift.
- Auxiliary Air Compressor B is tagged for maintenance.
- A failed temperature switch results in an Auxiliary Building Isolation (ABI).
- ABGTS fan A-A trips due to motor failure when it attempts to start.
Which ONE of the following completes the statements below?
The OPDP-8, Limiting Conditions for Operation Tracking, LCO Tracking Log entry for the ABGTS Train A failure will be designated as an (1)
The Loss of Safety Function evaluation will identify that a loss of safety function (2)
L)
A. Active LCO has occurred B. Information Only LCO has occurred C. Active LCO has NOT occurred D. Information Only LCO has NOT occurred Page 94
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 95. Given the following:
- UnitlisinModel.
- To facilitate on-going work, Status Control was relaxed on a section of safety related piping inside an existing clearance boundary.
- While the operators are re-establishing Status Control following release of the clearance, a valve that is required to be open by the valve checklist is found to be closed and documented in an open work order.
Which ONE of the following completes the statements below?
The (1) is the lowest position in the Operations Organization that can authorize the relaxing of Status Control inside the clearnace boundary.
With the valve in the closed position, the valve checklist to re-establish status control (2)
A. Shift Manager or designee must remain open until the valve can be restored to the required position B. Shift Manager or designee can be documented as complete and closed C. Operations Superintendent must remain open until the valve can be restored to the required position D. Operations Superintendent can be documented as complete and closed Page 95
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 96. Which ONE of the following completes the statements below?
To be in compliance with Tech Spec LCO 3.1.5 Rod Group Alignment Limits, the performance of 1-SI-85-10, Rod Drop Time Measurement Using CERPI Rod Drop Test Computer, is required prior to a reactor criticality following (1)
The performance of 1-Sl-85-10 requires a minimum of (2) Reactor Coolant Pumps to be in service.
w A. a Mode 5 entry 4 B. a Mode 5 entry 3 C. reactor head removal 4 D. reactor head removal 3 Page 96
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 97. Given the following:
- Unit I reactor is critical below the Point of Adding Heat in accordance with GO-2, Reactor Startup, during startup following a refueling outage.
- Physics Testing has been declared, and PET-201, Initial Criticality and Low Power Physics Testing, is in progress.
- The Plant Manager designates the Site Engineering Director to exercise continuous responsibility for the oversight of PET-201.
Which ONE of the following completes the statements below?
The (1) the responsibility for control of PET-201.
The (2) is responsible for covering the items contained on the CIPTE PRE-TEST BRIEFING CHECKLIST for the test.
A. (1) Shift Manager retains (2) Test Director B. (1) Shift Manager retains (2) Site Engineering Director C. (1) Site Engineering Director assumes (2) Test Director D. (1) Site Engineering Director assumes (2) Site Engineering Director Page 97
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 98. Given the following:
- Unit 1 is in Mode 3 with RCS at normal operating temperature and pressure awaiting secondary plant equipment repair to continue the startup.
- RCS Activity was determined to be 0.28 microcuries/gram DOSE EQUIVALENT 1-131 and Technical Specification LCD 3.4.16, RCS Specific Activity, is entered.
- The DOSE EQUIVALENT 1-131 was unable to be restored to within the LCD limit in the required action time.
Which ONE of the following completes the statement below?
Technical Specification LCO 3.4.16 states the RCS Tavg must be reduced to less than 500° F within a maximum of (1) hours and the bases is to limit doses at the site boundary in the event of a (2)
A. 8 LOCA in conjunction with the La value of 0.25%/day leakage from containment.
B. 6 LOCA in conjunction with the La value of 0.25%/day leakage from containment.
C. 8 Main Steam Line Break in conjunction with an existing SG tube leakage of 150 gpd.
D. 6 Main Steam Line Break in conjunction with an existing SG tube leakage of 150 gpd.
Page 98
10-2011 Watts Bar SRO NRC License Exam 12/29/2011
- 99. Given the following:
- Unit 1 was operating at 100% power when a fire occurred outside of the 125v Vital Battery I and II rooms.
- AOl-30.2, Fire Safe Shutdown, has been entered.
- Using AOl-30.2, Appendix B, Fire Safe Shutdown Elevation Diagrams, the determination is made that the fire involves both of the following rooms:
- 480v Rx MOV Bd Rm I B (East)
- 480v Rx MOV Bd Rm 1 B (West)
- While the fire is in progress, a Safety Injection signal is generated.
Which ONE of the following completes the statements below?
In accordance with AOI-30.2, Appendix B, Fire Safe Shutdown Elevation Diagrams, the minimum required action by the operating crew is the performance of (I)
AOl-30.2 actions (2) precedence over the Emergency Operating Procedures.
REFERENCE PROVIDED A. (1) both AOI-30.2 C.3 and C.4 (2) take B. (1) both AOI-30.2 C.3 and C.4 (2) doNOTtake C. (1) either AOI-30.2 C.3 or C.4 (2) take D. (1) eitherAOl-30.2C.3orC.4 (2) do NOT take Page 99
10-2011 Watts Bar SRO NRC License Exam 12/29/2011 100. Given the following:
0825 - Shift Manager/SED declares a Site Area Emergerency and initiates the Emergency Paging System to staff the TSC and OSC.
0830 - The Assembly and Accountability process is initiated.
Which ONE of the following completes the statements below in accordance with the Radiological Emergency Plan?
A report from Security on the results of accountability will be provided to the Shift Manager/SED no later than (1)
The Shift Manager will be relieved of the SED status and the Technical Support Center activated no later than (2) w ()
A. 0900 0925 B. 0900 0955 C. 0915 0925 D. 0915 0955 Page 100
10-2011 Watts Bar SRO NRC License Exam 1212912011 REFERENCE PACKAGE
- 1. Steam Tables
- 2. AOl-i 1, Appendix A, Condenser Vacuum ICS Graph, (1 page)
- 3. 0-SI-O-3, Weekly Log, Appendix A, (2 pages)
- 4. ICS AFD TARGET DISPLAY, (1 page)
- 6. Tech Spec 3.6.12, Ice Condenser Doors (5 pages)
- 7. EPIP-1, Emergency Plan Classification Logic, (1 page)
- 8. AOI-30.2 APP B, Fire Safe Shutdown Elevation Diagrams 2.0 AB EL 772.0, 776.0 &
763.5 ELEVATION DIAGRAM (1 page)
A & B and C CONDENSER VACUUM LO-LO AND LO ALARMS W zrN o
cm o j 1
tJ Cl)
Cl) 3 0
(p 3 o U) 0 0
- :3 Z3 0 U) 0 m5
-U (p Cl) DJO (Q (DO U)
CT) (DZ w (p o (D(D o (0= (p
- (I)
(() 0 Iii C) 0(1) LL Cl) 3 0
)
LU (p COD Z
LII (T)ZT
- 30 2 1
- 0. 0 0
o cv CD 3
0 ci Eu CD 1
0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 LOAD (MWe)
WBN Weeky Log 0-S-0-3 UnftO Rev. 0045 L Page 20 of 43 Appendix A (Page 9 of 24)
SR 3.8.-L3 SR 3 8.5 1 SR 3.8.7.1 SR 3. 8. 8. 1 SR 3.8.9.1 NO (IDA)
SR 3.8.10.1 S- CLOSED ly A- AVAUSELE I- 00088RABLE S-PNL-2S64 4808 ACYIrAL DISCONNECT PNL CHANNSI IV S.5W43SO4SIVI FROM 015 O-XSW236-79002-S, OUTPUT 2 I 20820 TRANSFER SWITCH l25V VITAL SELECT CHARSERS 7-SIN-S BAUIV ROlE 2 O-SW-364SW5 820)
NC) Il-IDi 2-BISOl-Z3-4CB1 U-SI0-23V-4)C2II
)NCJ 082 810) 1-XSW-235-4 120 VAC vrrAL 21T I 2-XOW-235-4 120 SAC VITAL 1808.1 NOTE POWER 8101 SO 1-IV (510) NOTE POWER W.A3-ISVER WANStER 1-981-230-4 125 VRC VITAL 2-SW-SOS-I 125 VITHL NC asTR ROWER SD i-R OSIC ISO 150W POWER 3D 2-IVDISC 1-30210-4120 Sac VITAL 2-SD 215-4 123 Vat VITAL PlOW SOWER BOARD 1-TI O4STR POvvER BOARD 2-SO NOTE (I) In Modes 5&6 only one train of ac/dc PWR is reouired, ii this train is nol required this nace rosy be N/A.
(2) When 7-S or 8-S charQer is connected to Bait Sd Th rify aesoc. train Transf Switches are closed and.SJt bkrs are open.
NITIALS OF DATA COLLECTOR: J1i DATE REMARKS: //
WBN Weekly Log 0-Sl-0-3 Unit 0 Rev. 0045 Page 21 of 43 Appendix A (Page 10 of 24)
Ir SR 3.8.9.1 NC I 480V Aux Bldg Corn MCCC SR 3.8.10.1 I I 0-BKR236-5 I
- I cot NCI 125V VITAL V I 125VViICItgrV BAIT V C02 I L.
(NC 125V VITAL NC See ncle2 BAiT 01] V (102) 125V DC 01ST PNL 5A 125V DC 01ST PNL 5B I
- 1I I I Ji(301) 2) I (401> NO I (402) I I I I I I I I I I NO NO NOi (2/0)i I (4/0)i I I I I O-DPL230-l 0-DPL-2364 0-OPL-236-2 0-DPL-238-4 NO 125V VITAL 125V VITAL 125V VITAL 125V VITAL ,
BAiT 00 I BAIT BO 18 BATT oti BATT BD IV CLOSED S..)
1 NOTE 1: Only one baltery board may be teed from the 5th battery board et erty one lime. () AVAILABLE NOTE 2: 0-BKR-238-5002 must be OPEN when 5th battery is inservice for battery bd I, II, II, cc IV 0 INOPERABLE INITIALS OF DATA COLLECTOR: DATE REMARKS: K
Main Jarm Grphi Trorid Pnint oin/Layer Print Hep 0-iL-2O1i 07:44t: 10
- .i Vi KE (R POWER LEVEL 4) { Lj.
P .L1J 2 \,
CTRL BANK D (STEPS ) (_ &_ I 7
AF[) NIS CHAN hEL 41 r AED iIS CHANNEL .1 AED HIS CHA.i\DEL .43 -7 7 AF[) NJ S CHANNEL 44 s.
NI ACTUAL AFD -75 %
L *\
HIS TARGET AFD - 7J E
4i -
AF[} LOW [BITT AED HIGH LIMIT CONTROL BAND LOW [TM CONTROL BAND H IGH L TM ri- l1--l I I II FF[TTLTpT1Tffl 111111 I
-.) -2 -.20 -10 - 0 10 i 20 2 AXIAL FLUX DIFFERENCE TIHE OUT OE BAND ACGUFI (HIM ) U jijjj 1Ji9 i1: A i)US SEC LV L= i PFIF[/ EACK CF- I IJDF 1
WRN Loss of RHR Sump Recircuation ECA-1.1 LJrit I Rev. 0012
[Step j [Action/Expeed Response Response Not Obtained
- 19. CHECK SI termination criteria:
- a. RVLIS greater than 60% a. F RVLIS is less than or equal to vith 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) **GOTOStep25 RCS PRESS BETWEEN REQUIRED SUSCOOLING 285 AND 585 psig 1 15°F [135°F ADV]
585 AND 1085 psig 102°F [1 23°F ADV]
1085 AND 1885 psig 97°F [1 17°F ADV)
Greater than 1885 psig 94°F [1 14°F ADV]
- 20. RESET Phase A and Phase B.
Page 12 of 35
WBN Loss of RHR Sump Redrcu[atoF1 ECA-i.1 L Unft I Rev. 0Q12 Figure I (Page 1 ofl)
Mhirnurn S Fcw for Decay Heat vs. Tme After Thp 700.0 600.0 500.0 2
400.0 300.0 200.0 100.0 0.0 10 100 1000 10000 Time After Trip (Minutes)
Page 29 of 35
Ice Condenser Doors
- 3. 6.12 3.6 CONTAINMENT SYSTEMS 3.6.12 Ice Condenser Doors LCO 3.6.12 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be OPERABLE and closed.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS NOTE Separate Condition entry is allowed for each ice condenser door.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more ice A.1 Restore inlet door to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> condenser inlet OPERABLE status.
doors inoperable due to being physically restrained from opening.
B. One or more ice B.1 Verify maximum ice bed Once per condenser doors temperature is 27°F. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable for reasons other than AND Condition A or not closed. B.2 Restore ice condenser 14 days door to OPERABLE status and closed positions.
(continued)
Watts EarUnit 1 3 . 631
Ice Condenser Doors 3.6.12 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Restore ice condenser 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> associated door to OPEPABLE status Completion Time of and closed positions.
Condition B not met.
D. Required Action and D.l Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of AND Condition A or C not met. D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.12.1 Verify all inlet doors indicate closed by 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> the Inlet Door Position Monitoring System.
SR 3.6.12.2 Verify, by visual inspection, each 7 days intermediate deck door is closed and not impaired by ice, frost, or debris.
(continued)
Natts BarUnit 1 3.632 Amendment 3
Ice Condenser Doors
- 3. 6. 12 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.12.3 Verify, by visual inspection, each irilet----NOTE door is not impaired by ice, frost, or The 3 month debris, performance due September 9, 1996 (per SR 3.0.2) may be extended until October 21, 1996.
3 months during first year after receipt of license AND 18 months SR 3.6.12.4 Verify torque required to cause each NOTE inlet door to begin to open is The 3 month 675 inlb. performance due September 9, 1996 (per SR 3.0.2) may be extended until October 21, 1996.
3 months during first year after receipt of license AND 18 months (continued)
Watts EarUnit 1 3.633 Amendment 3
Ice Condenser Doors
- 3. 6.12 SURVEILLANCE_REQUIREMENTS__(Continued)
SURVEILLANCE FREQUENCY SR 3.6.12.5 Perform a torque test on a sampling of NOTE
> 50% of the inlet doors. The 3 month performance due September 9, 1996 (per SR 3.0.2) may be extended until October 21, 1996.
3 months during first year after receipt of license AND 18 months SR 3.6.12.6 Verify for each intermediate deck door: 3 months during first
- a. No visual evidence of structural year after deterioration; receipt of license
- b. Free movement of the vent assemblies; and AND
- c. Free movement of the door. 18 months (continued)
Watts Bar-Unit 1 3.634 Amendment 3
Ice Condenser Doors
- 3. 6.12 SURVEILLANCE REQUIREMENTS (Continued)
SURVEILLANCE FREQUENCY SR 3.6.12.7 Verify, by visual inspection, each top 92 days deck door:
- a. IS in place;
- b. Free movement of top deck vent assembly; and
- c. Has no condensation, frost, or ice formed on the door that would restrict its opening.
Watts BarUnit 1 3.634a Amendment 3
WBN Emergency Pan Classification Logic EPIP-1 Unit 0 Rev. 0035 Page 49 of 51 Attachment 7 (Page 6 of 7) 1TI:fliTtlm Mode Ir Mode InitiatinglCondition Refer to Fission Product Barrier Matrix or Refer to Gaseous Effluents (7. 1)
Gaseous Effluents (7.1)
Refer to Fission Product Barrier Matrix or Refer to Gaseous Effluents (7.1)
Gaseous Effluents (7.1)
UNPLANNED increases in Radiation levels All Major damage to Irradiated Fuel, i: Loss of within the Facility that impedes Safe water level that has or will uncover Irradiated Operations or establishment or maintenance Fuel outside the Reactor Vessel of Cold Shutdown (1 and2)
(1 cr2)
- 1. VALID alarm on 0-RE-90-l 01 B
- 1. VALID, area Radiation Monitor readings g 0-RE-90-l 02 survey results exceed 15 mrem/hr in the Control Room or CAS 0-RE-90-103 or l-RE-90-130/131 or
- 1 -RE-90-1 12 1 -RE-90-400
- 2. (a and b) 2-RE-90-400
- a. VALID area radiation monitor readings 2. (aorb) exceed values listed in Table 7-2
- a. Plant personnel report damage of
- b. Access restrictions impede operation of Irradiated Fuel sufficient to rupture Fuel systems necessary for Safe Operation Rods the ability to establish Cold Shutdown b. Plant personnel report water level drop has or will exceed makeup capacity See UNUSUAL EVENT Note Below such that Irradiated Fuel will be uncovered UNPLANNED increase in Radiation levels All UNPLANNED loss of water level in Spent Fuel within the Facility Pool Reactor Cavity Transfer Canal with fuel remaining covered (1 and 2 and 3)
- 1. VALID area Radiation Monitor readings increase by a factor 1000 over normal levels 1. Plant personnel report water level drop in Spent Fuel Pool, or Reactor Cavity, Note: In Either the UE 0rALERT EAL, the SED Transfer Canal must determine the cause of Increase in Radiation Levels and Review Other 2. VALID alarm on 0-RE-90-1 02 or INITIATING/CONDITIONS forApplicability (e.g., D-RE-90-103 1-RE-90-59 1-RE-90-60 a dose rate of 15 mrem/hr in the Control Room could be caused by a release associated with a 3. Fuel remains covered with water.
DBA).
WBN Fre Safe Shutdown Eevatbn AO-3O.2 APP B Unft 0 Diagrams Rev. 0000 Page5ofl6 2.0 AB EL 772.0, 776.0 & 763.5 ELEVATION DIAGRAM Auxiliary Building El 772.0, 776.0 & 73.5 Diagram ROOM ROOM NAME PROCEDURE ROOM ROOM NAME PROCEDURE 772.0Al 480V Rx MDV 3d Rm ADl30.2 0.2 772.0AlO Mech Equip Rm ADI-30.2 0.11 1A 772.0A2E 480V Rx MDV AD30.2 C.3 772.0All 480V Xfmer Rm 2B AOl-30.2 0.12 3d Rm lB (East) 772.0A2W 480V Rx MDV Bd Rm A0l-3D.2 C.4 772.0A12 480V Xfmer Rm 2A AOl-30.2 0.13 I B (West) 772.0A3 l25V Vital Batt Rm II AOl-30.2 0.5 772.0A13 125V Vital Batt Rm IV ADl-30.2 0.14 772.0A4 125V Vital Batt Rrn I AOI30.2 0.6 772.0Al4 125V Vital Batt Rm ill AOl-30.2 C.l5 772.0A5 480V Xfmer Rm lB ADl-30.2 0.7 772.0A15E 480V Rx MDV Bd Rm ADI-30.2 0.16 2B (East) 772.0A6 480V Xfmer Rm IA AOI-30.2 0.8 772.0A15W 480V Rx MDV Bd Rm ADl-30.2 0.17 23 (West) 772.0A7 Mech Equip Rm ADl-30.2 0.9 772.0A16 480V Rx MDV Bd Rm AOl-30.2 0.18 2A 72.0A8 5th Vit Batt & Bd Rm AOl-30.2 010 776.0Al Elev Mach Rrn ADI-30.2 0.60 p 772.0A9 HEPA Filter Plenum Rm AOl-30.2 0,44 763.5Al Ice Equip Rm A0l-30.2 0.45 757.0A13 (Next Page)
KEY IDfl 1SCORING & 0 1 RLS(01 0/tn IIJIH/ 4 NS WER SCORING NCS Test Sheet
L__ PRINTING IOPTIONS. ( 0cgj?i?lçv5weR 0 MARK X 0 TOTAL ONLY, 1001W MARK ONLY ON YE TF Form No. 95677 i *© YE si CD © a TF 26
- Ci) © Ci) CD 76 (A) Ci) ©
- Ci) Reorder Phone Number 2 i© 52 CD © a 1-800-367.6627
27 CD*© 77 CD* © CD 3
- CD © CD 53 CD. © CD
28 CA) CD ©* © 78 S © © © 4 *CD©ci 54(A) (1) * © (I) 29
- CD © CD 79 CD* © CD CD
5 CD CD ©
- 55 CD. © © CD (ANSWER PERFORMANCE 30 CD* CD 80 CD © CD KEY iNFO. ASSESSMENT 6 CD©©CD 56 CDQ © CD (I) #OF KEYS %OF POIATS 31 CD CD ©a (A) 81 a©©© ITEM TOTAL EARNED 7 CA) * © Ci) CD 57 CD©CD COUNT SCORE 00- 100%
32 CD CD* Ci) CD 82 CD CA)* © CD 8 CA) CA) * © CD 58 CDS © © CD E CD CD ©a () 83 a © © © 0 CD CD (AD 9 CD (I) © a CD © © CD DDDCD L GD CD GD (A) a © © 84 CD © a P CD CD CAD 10 CDCD©QCD 60 CD Ci) CD
- CD T CD cAD 35 CD CD* © CD 85 CD © a CD 0 CD GD 11 ©©D 61 ©©CD CD V CD CD (A) (1) © a A
36 CD Ci)S Ci) CD 86 CD L (AD 1
CAD 12 K©*© 62 CA) © © CD ccv E CD CD CD©CD 87 © © CD CD CD (AD 13 CD. © © CD 63
- CD © CD CD CD CD 38SCD © © CD 88 (A) * © CD 14 CD©CD 64 CD* © CD (A) Copyright © 1994 National Computer Systems, Inc.
39 (A) a © CD 89 CDCD © CD All rights reserved. Printed in U.S.A.
15 CD © * () 65 CD © a Ci) 40
- CD CD © CD 90 a © © 16 CD*©CD 66 CD © CD 41
- CD © CD 91 CD © a © 17 CD©CD 67 CD © S © 42 CA) CD* © CD 92 CD* CD CD 18 CDCD* CD 68 CD. © CD 43 a © © © CI) CD a © © 19 Q©ci)CD 69 CD © CD Ci) 44 (A) CD © a © 94 a © CD 20 CD*©CDcD 70 *©©(A) 45 CD. © © CD 95 (A) S © © CD 21 *©©Ci) 71 CD © CD 46 CD © © 96 CDS © (A) 22 CA) * © CD CA) 72 CD. © © (A)
CD © CD CD a © CD © 23 CD © CD 73 CD. © © © 48 CD © CD Ci) 98 CD ©* (A) 24 CDCD© 74 a CA) © © CD CD
- CD Ci) CD a © Ci) 25 CD (I) ©* CD 75 CD * © © CD 50 CD ci) © CD 100 a©©© COMBINED NUMBER POINTS CORRECT EARNED
COMBINED L
PERCENT PERCENT CQRRECT CORRECT 100 ITEM
ROSTER LETTER tTh NUMBER GRADE
SCORE SCORE STUDENT ID NUMBER RESCORE RESCORE
MARKiNG INSTRUCTIONS
, N CA) CD NAME Use a No. 2 Pencil
© CD CD CD CD SUBJECT Fill oval completely CD (A) (A) CD (A.) (A) Cl) ()) CD PER1OD DATE CD©CDCD CD Cl) (A) CD (A) CD (A)
Erase cleanly 0 Mark Reflex by NCS MM95677: 3029 Printed on recyclable paper