ML100070306
| ML100070306 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 01/06/2010 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML100070306 (123) | |
Text
Watts Barr 2009-302 Initial Written Exam SRO Watts Barr 2009-302 Initial Written Exam SRO
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 1. Given the following conditions:
Unit 1 was operating at 100% power when Control Bank '0" started inserting with Rod Control in manual.
A manual Reactor Trip is initiated from handswitches on1-M-4 and1-M-6.
Reactor Trip Breaker "A" indicates green.
Reactor Trip Breaker "B" indicates red.
Reactor power indicates 3% and decreasing.
All CERPI indication is lost.
Pressurizer pressure is 1990 psig and slowly trending down.
All SG Narrow Range levels are off scale low.
The Unit Supervisor has entered E-O, "Reactor Trip or Safety Injection."
Which ONE of the following identifies the condition of the reactor and the appropriate action?
A. The Reactor has tripped.
Continue in E-O; Actuate Safety Injection.
B. The Reactor has tripped.
Continue in E-O; Do not actuate Safety Injection.
C. The Reactor has not tripped.
Transition to FR-S.1, "Response to Nuclear Power Generation/ATWS."
Actuate Safety Injection.
O. The Reactor has not tripped.
Transition to FR-S.1, "Response to Nuclear Power Generation/ATWS."
Manually trip the turbine and start AFW pumps.
Page 1 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 1. Given the following conditions:
Unit 1 was operating at 100% power when Control Bank '0" started inserting with Rod Control in manual.
A manual Reactor Trip is initiated from handswitches on1-M-4 and1-M-6.
Reactor Trip Breaker "A" indicates green.
Reactor Trip Breaker "B" indicates red.
Reactor power indicates 3% and decreasing.
All CERPI indication is lost.
Pressurizer pressure is 1990 psig and slowly trending down.
All SG Narrow Range levels are off scale low.
The Unit Supervisor has entered E-O, "Reactor Trip or Safety Injection."
Which ONE of the following identifies the condition of the reactor and the appropriate action?
A. The Reactor has tripped.
Continue in E-O; Actuate Safety Injection.
B. The Reactor has tripped.
Continue in E-O; Do not actuate Safety Injection.
C. The Reactor has not tripped.
Transition to FR-S.1, "Response to Nuclear Power Generation/ATWS."
Actuate Safety Injection.
O. The Reactor has not tripped.
Transition to FR-S.1, "Response to Nuclear Power Generation/ATWS."
Manually trip the turbine and start AFW pumps.
Page 1
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 2. Given the following:
Unit 1 is at 100% power.
Containment Purge Train A is in service to lower containment.
A small break LOCA occurs.
A Containment Vent Isolation occurs.
Four minutes later the crew initiates a manual Reactor Trip and Safety Injection.
Which ONE of the following identifies the position indicated for valves, 1-FCV-30-37 and 1-FCV-30-40, LWR CNTMT PURGE EXH PRESS RLF, on the supply line to the Containment Vent Air Cleanup Units during this period?
A. Green lights will be lit on the control switches during the entire period.
B. Green lights will be lit on the control switches only after the Safety Injection occurs.
C. Red lights will be lit on the control switches until the Phase A Containment Isolation occurs.
D. Red lights will be lit on the control switches unless a Phase B Containment Isolation occurs.
Page 2 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 2. Given the following:
Unit 1 is at 100% power.
Containment Purge Train A is in service to lower containment.
A small break LOCA occurs.
A Containment Vent Isolation occurs.
Four minutes later the crew initiates a manual Reactor Trip and Safety Injection.
Which ONE of the following identifies the position indicated for valves, 1-FCV-30-37 and 1-FCV-30-40, LWR CNTMT PURGE EXH PRESS RLF, on the supply line to the Containment Vent Air Cleanup Units during this period?
A. Green lights will be lit on the control switches during the entire period.
B. Green lights will be lit on the control switches only after the Safety Injection occurs.
C. Red lights will be lit on the control switches until the Phase A Containment Isolation occurs.
D. Red lights will be lit on the control switches unless a Phase B Containment Isolation occurs.
Page 2
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 3. During which ONE of the following events does reflux cooling become important?
A. Any Large break LOCA with the break on an RCS Cold Leg and RCS subcooling indicating O°F.
B. Only a Large break LOCA with the break on an RCS Cold Leg and RVLlS indicating less than 100%.
C. Any Small Break LOCA with reactor vessel level below the top of the hot legs and RCS subcooling indicating O°F.
D. Only a Small Break LOCA in the pressurizer vapor space and RVLlS indicating less than 100%.
Page 3 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 3. During which ONE of the following events does reflux cooling become important?
A. Any Large break LOCA with the break on an RCS Cold Leg and RCS subcooling indicating O°F.
B. Only a Large break LOCA with the break on an RCS Cold Leg and RVLlS indicating less than 100%.
C. Any Small Break LOCA with reactor vessel level below the top of the hot legs and RCS subcooling indicating O°F.
D. Only a Small Break LOCA in the pressurizer vapor space and RVLlS indicating less than 100%.
Page 3
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 4. Given the following:
Unit 1 is at 41 % power.
Reactor Coolant Pump (RCP) #4 trips.
Which ONE of the following identifies how steam generator #4 level indications will be initially affected by the RCP trip and the effect of the RCP trip on reactor status?
SG #4 Level Reactor Status A.
Decrease RCP trip generates an automatic reactor trip.
B.
Decrease Manual reactor trip is required due to RCP tripping.
C.
Increase RCP trip generates an automatic reactor trip.
D.
'Increase Manual reactor trip is required due to RCP tripping.
Page 4 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 4. Given the following:
Unit 1 is at 41 % power.
Reactor Coolant Pump (RCP) #4 trips.
Which ONE of the following identifies how steam generator #4 level indications will be initially affected by the RCP trip and the effect of the RCP trip on reactor status?
SG #4 Level Reactor Status A.
Decrease RCP trip generates an automatic reactor trip.
B.
Decrease Manual reactor trip is required due to RCP tripping.
C.
Increase RCP trip generates an automatic reactor trip.
D.lncrease Manual reactor trip is required due to RCP tripping.
Page 4
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 5. Given the following:
Unit 1. is at 100% reactor power.
Letdown flow is 75 gpm.
The CAC closes 1-FCV-62-90A, "Charging Line Isolation."
Which ONE of the following identifies...
(1) when Annunciator 108-A, "CHARGING FLOW HI/LO" would alarm as the charging flow drops, and (2) how the charging flow indication would be affected when the valve reached the full closed position?
A. (1 ) 47gpm (2) indicating 0 gpm flow B. (1 ) 47gpm (2) indicating - 32 gpm flow C. (1 ) 55 gpm (2) indicating 0 gpm flow D. (1 ) 55 gpm (2) indicating - 32 gpm flow Page.5 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 5. Given the following:
Unit 1 is at 100% reactor power.
Letdown flow is 75 gpm.
The OAC closes 1-FCV-62-90A, "Charging Line Isolation."
Which ONE of the following identifies...
(1) when Annunciator 108-A, "CHARGING FLOW HIILO" would alarm as the charging flow drops, and (2) how the charging flow indication would be affected when the valve reached the full closed position?
A. (1 ) 47 gpm (2) indicating 0 gpm flow B. (1 ) 47gpm (2) indicating - 32 gpm flow C. (1 ) 55 gpm (2) indicating 0 gpm flow D. (1 ) 55 gpm (2) indicating - 32 gpm flow Page 5
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 6. Given the following:
Unit 1 is at 100% power when a Reactor trip and Safety injection are initiated due to a LOCA.
RHR pump 1A-A is tagged with maintenance in progress.
RHR pump 1 B-B trips when it attempts to start.
The crew makes a transition from E-I, "Loss of Reactor or Secondary Coolant," to ECA-1.1, "Loss of RHR Sump Recirculation."
-. The conditions at the transition are:
RCS pressure is 480 psig.
RWST level is 73% and dropping.
Containment sump level is 17% and rising.
Containment pressure had peaked and is now stable at 3.2 psid.
STA reports an Orange path to FR-Z.1,"High Containment Pressure."
Assuming the plant conditions remain unchanged, which ONE of the following identifies...
(1) the procedure controlling the operation of the containment spray pumps, and (2) if one of the spray pumps is later required for restoring the level in the RWST, how it will be aligned from the containment sump to the RWST?
(1 )
Procedure A.
FR-Z.1 B.
FR-Z.1 C.
ECA-1.1 D.
ECA-1.1 (2)
Alignment Through the containment spray test line.
Through the containment spray pump mini flow line.
Through the containment spray test line.
Through the containment spray pump mini flow line.
Page 6 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 6. Given the following:
Unit 1 is at 100% power when a Reactor trip and Safety injection are initiated due to a LOCA.
RHR pump 1 A-A is tagged with maintenance in progress.
RHR pump 1 B-B trips when it attempts to start.
The crew makes a transition from E-I, "Loss of Reactor or Secondary Coolant," to ECA-1.1, "Loss of RHR Sump Recirculation."
The conditions at the transition are:
RCS pressure is 480 psig.
RWST level is 73% and dropping.
Containment sump level is 17% and rising.
Containment pressure had peaked and is now stable at 3.2 psid.
STA reports an Orange path to FR-Z.1,"High Containment Pressure."
Assuming the plant conditions remain unchanged, which ONE of the following identifies...
(1) the procedure controlling the operation of the containment spray pumps, and (2) if one of the spray pumps is later required for restoring the level in the RWST, how it will be aligned from the containment sump to the RWST?
(1 )
Procedure A.
FR-Z.1 B.
FR-Z.1 C.
ECA-1.1 D.
ECA-1.1 (2)
Alignment Through the containment spray test line.
Through the containment spray pump mini flow line.
Through the containment spray test line.
Through the containment spray pump mini flow line.
Page 6
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 7. Given the following:
Unit 1 is at 100% power when a LOCA occurs.
Which ONE of the following identifies an automatic signal that will cause an isolation of the CCS to the RCP thermal barrier cooling during an accident and the reason for the isolation?
A. Phase A Isolation B. Phase A Isolation C. Phase B Isolation D. Phase B Isolation To isolate a potential containment release path.
To protect the CCS system from steam formation.
To isolate a potential containment release path.
To protect the CCS system from steam formation.
Page 7 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 7. Given the following:
Unit 1 is at 100% power when a LOCA occurs.
Which ONE of the following identifies an automatic signal that will cause an isolation of the CCS to the RCP thermal barrier cooling during an accident and the reason for the isolation?
A. Phase A Isolation B. Phase A Isolation C. Phase B Isolation D. Phase B Isolation To isolate a potential containment release path.
To protect the CCS system from steam formation.
To isolate a potential containment release path.
To protect the CCS system from steam formation.
Page 7
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 8. Given the following plant conditions:
Unit 1 is operating at 100% power.
Pressurizer backup heater C is energized.
The pressurizer pressure controller, 1-PIC-68-340, fails to 100%.
Which ONE of the following describes the immediate response of the pressurizer pressure control system to this failure?
A. Spray valves go full closed, backup heater C remains energized.
. B. Spray valves go full open, backup heater C remains energized.
C. Spray valves go full closed, backup heater C de-energizes.
D. Spray valves go full open, backup heater C de-energizes.
Page.B 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 8. Given the following plant conditions:
Unit 1 is operating at 100% power.
Pressurizer backup heater C is energized.
The pressurizer pressure controller, 1-PIC-68-340, fails to 100%.
Which ONE of the following describes the immediate response of the pressurizer pressure control system to this failure?
A. Spray valves go full closed, backup heater C remains energized.
B. Spray valves go full open, backup heater C remains energized.
C. Spray valves go full closed, backup heater C de-energizes.
D. Spray valves go full open, backup heater C de-energizes.
Page 8
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 9. With the plant at full power, the following occurs:
A spurious turbine trip occurs which resulted in the crew performing FR-S.1, "Nuclear Power Generation 1 ATWS."
The crew is at Step 20 for checking the reactor subcritical.
Power range channels indicate 2%.
Intermediate range startup rate indicates slightly positive.
NO charging pumps are available.
Which ONE of the following describes:
A.
B.
C.
D.
(1) an action which will address the step for reactor subcriticality and (2) the time in core life when the action would have the greatest effect on reactivity?
(1 )
(2)
Required Action Time in Core Life Manually initiate SI to provide boration.
BOL Manually initiate SI to provide boration.
EOL Lower AFW flow to allow RCS to heatup.
BOL Lower AFW flow to allow RCS to heatup.
EOL Page 9 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 9. With the plant at full power, the following occurs:
A spurious turbine trip occurs which resulted in the crew performing FR-S.1, "Nuclear Power Generation 1 ATWS."
The crew is at Step 20 for checking the reactor subcritical.
Power range channels indicate 2%.
Intermediate range startup rate indicates slightly positive.
NO charging pumps are available.
Which ONE of the following describes:
A.
B.
C.
D.
(1) an action which will address the step for reactor subcriticality and (2) the time in core life when the action would have the greatest effect on reactivity?
(1 )
(2)
Required Action Time in Core Life Manually initiate SI to provide boration.
BOL Manually initiate SI to provide boration.
EOL Lower AFW flow to allow RCS to heatup.
BOL Lower AFW flow to allow RCS to heatup.
EOL Page 9
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 10. With the plant initially at 80% power, a single tube, completely ruptures on #3 SG. The crew has entered E-3, "Steam Generator Tube Rupture" and is at the step for identifying which SG is ruptured.
Which method will be used for determining which SG is ruptured and why?
A. RADCON surveys of the main steam lines, since the Main Steam Line Post Accident Monitors will not be effective due to lack of N16 response.
B.RADCON surveys of the main steam lines, since the ability to perform a Chemistry sample is no longer available.
C. Main Steam Line Radiation Monitors high range indication, since the low range has been disabled.
D. Main Steam Line Radiation Monitors high range indication, since they have a high level of sensitivity to N16.
Page 10 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 10. With the plant initially at 80% power, a single tube completely ruptures on #3 SG. The crew has entered E-3, "Steam Generator Tube Rupture" and is at the step for identifying which SG is ruptured.
Which method will be used for determining which SG is ruptured and why?
A. RADCON surveys of the main steam lines, since the Main Steam Line Post Accident Monitors will not be effective due to lack of N16 response.
B. RADCON surveys of the main steam lines, since the ability to perform a Chemistry sample is no longer available.
C. Main Steam Line Radiation Monitors high range indication, since the low range has been disabled.
D. Main Steam Line Radiation Monitors high range indication, since they have a high level of sensitivity to N16.
Page 10
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 11. With the plant initially at full power, a steam line break occurred. The crew is currently at Step 3 of E-2, "Faulted Steam Generator Isolation" and has determined that SGs 1 and 2 are intact. For SGs 3 and 4, the crew is evaluating the following parameters:
1-PI-1-20A (SG 3) indicates 470 psig and lowering.
1-PI-1"'-27A (SG 4) indicates 440 psig and lowering.
- 3 RCS Thot = 454°F.
- 4 RCS Thot = 456°F.
All Core Exit Thermocouples are 460°F.
- 3 RCS Tcold = 453°F.
- 4 RCS Tcold = 410°F.
All Reactor Coolant Pumps are in service.
Which ONE of the following describes the status of Steam Generators 3 and 4?
A.
B.
C.
D.
SG 3 Intact?
YES YES NO NO SG 4 Intact ?
NO YES NO YES Page 11 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 11. With the plant initially at full power, a steam line break occurred. The crew is currently at Step 3 of E-2, "Faulted Steam Generator Isolation" and has determined that SGs 1 and 2 are intact. For SGs 3 and 4, the crew is evaluating the following parameters:
1-PI-1-20A (SG 3) indicates 470 psig and lowering.
1-PI-1-27 A (SG 4) indicates 440 psig and lowering.
- 3 RCS Thot = 454°F.
- 4 RCS Thot = 456°F.
All Core Exit Thermocouples are 460°F.
- 3 RCS Tcold = 453°F.
- 4 RCS Tcold = 410°F.
All Reactor Coolant Pumps are in service.
Which ONE of the following describes the status of Steam Generators 3 and 4?
SG 3 Intact?
SG 4 Intact ?
A.
YES NO B.
YES YES C.
NO NO D.
NO YES Page 11
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 12. Due to the loss of the running Main Feedwater Pump Turbine, Unit 1 is operating at 12% power with the Standby Main Feedwater Pump in service.
The following occurs:
The Standby Main Feedwater Pump trips.
The crew implementsAOI-16, "Loss of Normal Feedwater," and initiates actions to stabilize the plant within AFW pump capability.
Steam Generator Narrow Range levels are trending to setpoint and are currently:
- 1 - 27%, #2 - 25%, #3 - 28%, #4 - 31 %.
In accordance with AOI-16, which ONE of the following sets of conditions would direct the operators to manually control AFW flow and the reason why?
Conditions Reason A. Tavg at 554°F and rising with To meet minimum heat sink AFW flow at 100 gpm to each SG.
requirements.
B. Tavg at 554°F and rising with To terminate the RCS heatup.
AFW flow at 120 gpm to each SG.
C. Tavg at 555°F and lowering with To meet minimum heat sink AFW flow at 100 gpm to each SG.
requirements.
D. Tavg at 555°F and lowering with To minimize the RCS cooldown.
AFW flow at 120 gpm to each SG.
Page 12 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 12. Due to the loss of the running Main Feedwater Pump Turbine, Unit 1 is operating at 12% power with the Standby Main Feedwater Pump in service.
The following occurs:
The Standby Main Feedwater Pump trips.
The crew implements AOI-16, "Loss of Normal Feedwater," and initiates actions to stabilize the plant within AFW pump capability.
Steam Generator Narrow Range levels are trending to setpoint and are currently:
- 1 - 27%, #2 - 25%, #3 - 28%, #4 - 31 %.
In accordance with AOI-16, which ONE of the following sets of conditions would direct the operators to manually control AFW flow and the reason why?
Conditions Reason A. Tavg at 554°F and rising with To meet minimum heat sink AFW flow at 100 gpm to each SG.
requirements.
B. Tavg at 554°F and rising with To terminate the RCS heatup.
AFW flow at 120 gpm to each SG.
C. Tavg at 555°F and lowering with To meet minimum heat sink AFW flow at 100 gpm to each SG.
requirements.
D. Tavg at 555°F and lowering with To minimize the RCS cooldown.
AFW flow at 120 gpm to each SG.
Page 12
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 13. Given the following:
A Station Blackout has occurred.
The crew is implementing AOI-40, "Station Blackout."
The decision has been made to backfeed from the 500kV switchyard.
The overcurrent relays on 6.9kV Unit Board 1 B actuated when the blackout occurred.
Which ONE of the following identifies which main bank transformers will be aligned to backfeed, and the action required to reset 6.9kV Unit Board 1 B overcurrent lockout?
Transformers A.
Unit 1 B.
Unit 1
- c.
Unit 2 D.
Unit 2 Lockout Relay Must be manually reset locally at the unit board.
Reset by placing the board's normal and alternate feeder control switches on 1-M-1 to TRIP.
Must be manually reset locally at the unit board.
Reset by placing the board's normal and alternate feeder control switches on 1-M-1 to TRIP.
Page 13 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 13. Given the following:
A Station Blackout has occurred.
The crew is implementing AOI-40, "Station Blackout."
The decision has been made to backfeed from the 500kV switchyard.
The overcurrent relays on 6.9kV Unit Board 1 B actuated when the blackout occurred.
Which ONE of the following identifies which main bank transformers will be aligned to backfeed, and the action required to reset 6.9kV Unit Board 1 B overcurrent lockout?
Transformers A.
Unit 1 B.
Unit 1 C.
Unit 2 D.
Unit 2 Lockout Relay Must be manually reset locally at the unit board.
Reset by placing the board's normal and alternate feeder control switches on 1-M-1 to TRIP.
Must be manually reset locally at the unit board.
Reset by placing the board's normal and alternate feeder control switches on 1-M-1 to TRIP.
Page 13
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 14. Given the following plant conditions:
Unit 1 is operating at 100% power.
A loss of 120V AC Vital Instrument Power Board 1-1 occurred.
The crew implements AOI-2S.01, "Loss of 120V AC Vital Instrument Power Boards 1-1 and 2-1."
Which ONE of the following identifies the Main Feedwater Reg Valve controller(s) that will not function in automatic control and why AFW pump 1A-A is placed in PULL-TO-LOCK during performance of the procedure?
Main Feed Reg.
Valve controller(s)
A.
Only#1 B.
Only #1 C.
Both #1 & #2 D.
Both #1 & #2 AFW pump 1 A-A is placed in PULL-TO-LOCK To prevent injection of cold water into SG #1 and # 2.
Because the Pressure Control Valve is failed closed.
To prevent injection of cold water into SG #1 and # 2.
Because Pressure Control Valve is failed closed.
Page 14 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 14. Given the following plant conditions:
Unit 1 is operating at 100% power.
A loss of 120V AC Vital Instrument Power Board 1-1 occurred.
The crew implements AOI-25.01, "Loss of 120V AC Vital Instrument Power Boards 1-1 and 2-1."
Which ONE of the following identifies the Main Feedwater Reg Valve controller(s) that will not function in automatic control and why AFW pump 1A-A is placed in PULL-TO-LOCK during performance of the procedure?
Main Feed Reg.
Valve controller(s)
A.
Only #1 B.
Only #1 C.
Both #1 & #2 D.
Both #1 & #2 AFW pump 1 A-A is placed in PULL-TO-LOCK To prevent injection of cold water into SG #1 and # 2.
Because the Pressure Control Valve is failed closed.
To prevent injection of cold water into SG #1 and # 2.
Because Pressure Control Valve is failed closed.
Page 14
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 15. Given the following plant conditions:
Unit 1 was at 80% power.
A loss of 125V DC Vital Battery Board III occurred.
AOI-21.03, "Loss of 125V DC Vital Battery Bd III," Appendix A, "Transfer of 125V DC Buses," is in progress.
Depressing and holding the BO-RESET switch while 6.9kV Shutdown Board 2A.. A 125V DC control bus is reenergized will prevent which ONE of the following?
A. Inadvertent start of ALL four Emergency Diesel Generators.
B. Inadvertent start of ONLY the Emergency Diesel Generator 2A-A.
C. Unwanted trip of components supplied by 6.9kV Shutdown Board 2A-A.
D. Unwanted start of components supplied by 6.9kV Shutdown Board 2A-A.
Page 15 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 15. Given the following plant conditions:
Unit 1 was at 80% power.
A loss of 125V DC Vital Battery Board III occurred.
AOI-21.03, "Loss of 125V DC Vital Battery Bd III," Appendix A, "Transfer of 125V DC Buses," is in progress.
Depressing and holding the BO-RESET switch while 6.9kV Shutdown Board 2A-A 125V DC control bus is reenergized will prevent which ONE of the following?
A. Inadvertent start of ALL four Emergency Diesel Generators.
B. Inadvertent start of ONLY the Emergency Diesel Generator 2A-A.
C. Unwanted trip of components supplied by 6.9kV Shutdown Board 2A-A.
D. Unwanted start of components supplied by 6.9kV Shutdown Board 2A-A.
Page 15
11/2009 Watts BarSRO NRC License Exam 12/17/2009
- 16. Which ONE of the following identifies...
(1) the reason for the backup nitrogen supply for the Turbine Driven AFW Pump LCVs, and (2) the action/condition required to align the backup supply?
A. (1) Allows the LCVs to be OPENED during a Station Blackout event.
(2) Is automatically supplied when air pressure drops below regulator setpoint.
B.. (1) Allows the LCVs to be OPENED during a Station Blackout event.
(2) Requires local manual alignment.
C. (1) To prevent overfeeding Steam Generators during a Station Blackout.
(2) Is automatically supplied when air pressure drops below regulator setpoint.
D. (1) To prevent overfeeding Steam Generators during a Station Blackout.
(2) Requires local manual alignment.
Page 16 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 16. Which ONE of the following identifies...
(1) the reason for the backup nitrogen supply for the Turbine Driven AFW Pump LCVs, and (2) the action/condition required to align the backup supply?
A. (1) Allows the LCVs to be OPENED during a Station Blackout event.
(2) Is automatically supplied when air pressure drops below regulator setpoint.
B. (1) Allows the LCVs to be OPENED during a Station Blackout event.
(2) Requires local manual alignment.
C. (1) To prevent overfeeding Steam Generators during a Station Blackout.
(2) Is automatically supplied when air pressure drops below regulator setpoint.
D. (1) To prevent overfeeding Steam Generators during a Station Blackout.
(2) Requires local manual alignment.
Page 16
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 17. Given the following plant conditions:
Unit 1 is at 100% power with all equipment aligned and functioning normally.
Generator reactive load indicates 70 MVAR OUT as indicated on 1-EI-57-8, MEGAVARS.
A grid disturbance occurs which results in a gradually lowering grid frequency.
As a result of the above conditions, how will the identified generator parameter indication be affected?
Generator Amps 1-EI-57-9, -10, -11 Exciter Amps 1-EI-57-7 A.
Rising Rising B.
Lowering Lowering C.
Rising Lowering D.
Lowering Rising Page 17 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 17. Given the following plant conditions:
Unit 1 is at 100% power with all equipment aligned and functioning normally.
Generator reactive load indicates 70 MVAR OUT as indicated on 1-EI-57-8, MEGAVARS.
A grid disturbance occurs which results in a gradually lowering grid frequency.
As a result of the above conditions, how will the identified generator parameter indication be affected?
Generator Amps 1-EI-57-9, -10, -11 Exciter Amps 1-EI-57-7 A.
Rising Rising B.
Lowering Lowering C.
Rising Lowering D.
Lowering Rising Page 17
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 18. Given the following:
The crew has entered ECA-1.2, "LOCA Outside Containment" from E-O, "Reactor Trip or Safety Injection" based upon high radiation levels in the Auxiliary Building.
After closing 1-FCV-74-33, "RHR Crosstie Valve," and 1-FCV-63-93, "RHR Train A Cold Leg Injection Valve," the following conditions exist:
RWST level continues to drop.
RCS pressure is slowly increasing.
Which ONE of the following indicates the status of the LOCA and the subsequent action that would be taken?
A. The LOCA is isolated; Stop RHR 1A-A pump and close 1-FCV-74-3, "RHR Pump 1A-A Suction Valve."
B. The LOCA is isolated; Leave RHR 1A-A pump running and injecting through the RHR crosstie valves, 1-FCV-74-33 and 1-FCV-74-35.
C. The LOCA is NOT isolated; Re-open 1-FCV-63-93, and close 1-FCV-63-94, "RHR Train B Cold Leg Injection Valve."
D. The LOCA is NOT isolated; Leave 1-FCV-63-93 closed and close 1-FCV-63-94, "RHR Train B Cold Leg Injection Valve."
Page 18 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 18. Given the following:
The crew has entered ECA-1.2, "LOCA Outside Containment" from E-O, "Reactor Trip or Safety Injection" based upon high radiation levels in the Auxiliary Building.
After closing 1-FCV-74-33, "RHR Crosstie Valve," and 1-FCV-63-93, "RHR Train A Cold Leg Injection Valve," the following conditions exist:
RWST level continues to drop.
RCS pressure is slowly increasing.
Which ONE of the following indicates the status of the LOCA and the subsequent action that would be taken?
A. The LOCA is isolated; Stop RHR 1A-A pump and close 1-FCV-74-3, "RHR Pump 1A-A Suction Valve."
B. The LOCA is isolated; Leave RHR 1A-A pump running and injecting through the RHR crosstie valves, 1-FCV-74-33 and 1-FCV-74-35.
C. The LOCA is NOT isolated; Re-open 1-FCV-63-93, and close 1-FCV-63-94, "RHR Train B Cold Leg Injection Valve."
D. The LOCA is NOT isolated; Leave 1-FCV-63-93 closed and close 1-FCV-63-94, "RHR Train B Cold Leg Injection Valve."
Page 18
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 19. Given the following:
Following a turbine runback, AOI-34, "Immediate Boration" is entered to restore control rods above the LO-LO insertion limit.
Normal boration is unavailable due to 1-HS-62-140A, "VCT Makeup Control," being broken.
1-FCV-62-138, "Emergency Borate" could not be opened from the MCR or locally.
Which ONE of the following identifies the next boric acid flow path that AOI-34 directs to be established and additional valve alignment(s) required when using the flow path?
Flow Path Valve alignment A. Open 1-ISV-62-929, Open 1'-FCV-62-140, Manual Borate Valve.
VCT Makeup Control.
B.
Open 1-ISV-62-929, Close 1-FCV-62-128, Manual Borate Valve.
Makeup to the VCT Inlet.
C. Open 1-FCV-62-135 & 136 Open 1-FCV-62-132 &1 33 CCP suction from RWST.
D. Open 1-FCV-62-135 & 136, Close 1-FCV-62-132 & 133 CCP suction from RWST.
Page 19 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 19. Given the following:
Following a turbine runback, AOI-34, "Immediate Boration" is entered to restore control rods above the LO-LO insertion limit.
Normal boration is unavailable due to 1-HS-62-140A, "VCT Makeup Control," being broken.
1-FCV-62-138, "Emergency Borate" could not be opened from the MCR or locally.
Which ONE of the following identifies the next boric acid flow path that AOI-34 directs to be established and additional valve alignment(s) required when using the flow path?
Flow Path Valve alignment A. Open 1-ISV-62-929, Open 1-FCV-62-140, Manual Borate Valve.
VCT Makeup Control.
B. Open 1-ISV-62-929, Close 1-FCV-62-128, Manual Borate Valve.
Makeup to the VCT Inlet.
C. Open 1-FCV-62-135 & 136 Open 1-FCV-62-132 &1 33 CCP suction from RWST.
D. Open 1-FCV-62-135 & 136, Close 1-FCV-62-132 & 133 CCP suction from RWST.
Page 19
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 20. Given the following plant conditions:
Unit 1 is at 100% power.
The Pressurizer Level Master Controller setpoint is failed at the current value.
Pressurizer Level Control is selected to LI-68-339.
A load reduction to 60% is initiated to remove a Main Feedwater Pump from service.
Which ONE of the following describes the action that will be taken in accordance with AOI-20, "Malfunction of Pressurizer Level Control System," and the reason for those actions?
A. Change the pressurizer level channel input to the pressurizer level master controller and restore Letdown because the backup level channel response to actual level will cause a letdown isolation.
B. Place the charging flow Control Valve in MANUAL and reduce charging flow because actual pressurizer level will be higher than program level for the actual power level as load is decreased.
C. Place the charging flow Control Valve in MANUAL and raise Charging flow because actual pressurizer level will be lower than program level for the actual power level as load is decreased.
D. Change the pressurizer level channel input to the pressurizer level master controller and restore Letdown because the controlling level channel failure will cause a letdown isolation.
Page 20 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 20. Given the following plant conditions:
Unit 1 is at 100% power.
The Pressurizer Level Master Controller setpoint is failed at the current value.
Pressurizer Level Control is selected to U-68-339.
A load reduction to 60% is initiated to remove a Main Feedwater Pump from service.
Which ONE of the following describes the action that will be taken in accordance with AOI-20, "Malfunction of Pressurizer Level Control System," and the reason for those actions?
A. Change the pressurizer level channel input to the pressurizer level master controller and restore Letdown because the backup level channel response to actual level will cause a letdown isolation.
B. Place the charging flow Control Valve in MANUAL and reduce charging flow because actual pressurizer level will be higher than program level for the actual power level as load is decreased.
C. Place the charging flow Control Valve in MANUAL and raise Charging flow because actual pressurizer level will be lower than program level for the actual power level as load is decreased.
D. Change the pressurizer level channel input to the pressurizer level master controller and restore Letdown because the controlling level channel failure will cause a letdown isolation.
Page 20
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 21. Given the following:
Unit 1 is in Mode 6.
1-HS-90-410-A [back of 1-R-73] and 1-HS-90-415-B [back of 1-R-78] are in the REFUEL position.
Compare the following two events:
(1) An assembly is dropped in the Spent Fuel Pit resulting in radiation monitors 1-RM-90-102 and -103 High Radiation relay actuation.
(2) An assembly is dropped inside containment resulting in radiation monitors 1-RM-90-130 and -131 High Radiation relay actuation.
Which ONE of the following identifies the automatic initiation of Containment Vent Isolation (CVI) and the isolation of the Auxiliary Building for the two events?
A. Dropping either assembly results in initiation of CVI and isolation of the Auxiliary Building.
B. Dropping the assembly inside containment results in an isolation of the Auxiliary Building but dropping the assembly in the Spent Fuel Pit does NOT result in a CVI.
C. Dropping the assembly in the Spent Fuel Pit results in a CVI but dropping the assembly inside containment does NOT result in isolation of the Auxiliary Building.
D. Dropping the assembly inside containment does NOT result in an isolation of the Auxiliary Building NOR does dropping the assembly in the Spent Fuel Pit result in a CVI.
Page 21 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 21. Given the following:
Unit 1 is in Mode 6.
1-HS-90-410-A [back of 1-R-73] and 1-HS-90-415-B [back of 1-R-78] are in the REFUEL position.
Compare the following two events:
(1) An assembly is dropped in the Spent Fuel Pit resulting in radiation monitors 1-RM-90-102 and -103 High Radiation relay actuation.
(2) An assembly is dropped inside containment resulting in radiation monitors 1-RM-90-130 and -131 High Radiation relay actuation.
Which ONE of the following identifies the automatic initiation of Containment Vent Isolation (CVI) and the isolation of the Auxiliary Building for the two events?
A. Dropping either assembly results in initiation of CVI and isolation of the Auxiliary Building.
B. Dropping the assembly inside containment results in an isolation of the Auxiliary Building but dropping the assembly in the Spent Fuel Pit does NOT result in a CVI.
C. Dropping the assembly in the Spent Fuel Pit results in a CVI but dropping the assembly inside containment does NOT result in isolation of the Auxiliary Building.
D. Dropping the assembly inside containment does NOT result in an isolation of the Auxiliary Building NOR does dropping the assembly in the Spent Fuel Pit result in a CVI.
Page 21
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 22. Unit 1 is at full power with the following conditions:
162-F, "RIVER FLOW LO DISCHARGE TERMINATED" lit.
1-HS-15-44,"SG BLOWDOWN DISCH TO CTBD," is in the OPEN position.
Which ONE of the following identifies how the SGBD effluent is affected if a malfunction on the in-service SGBD radiation monitor causes output of the monitor to fail high and the reason why?
A. SGBD flow will automatically divert from CTBD to the Condensate Demin to prevent an unmonitored release.
B. SGBD flow must be manually diverted from CTBD to the Condensate Demin because of low CTBD flow.
C. SGBD flow will be isolated automatically to prevent an unmonitored release.
D. SGBD flow must be manually isolated because of low CTBD flow.
Page 22 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 22. Unit 1 is at full power with the following conditions:
162-F, "RIVER FLOW LO DISCHARGE TERMINATED" lit.
1-HS-15-44,"SG BLOWDOWN DISCH TO CTBD," is in the OPEN position.
Which ONE of the following identifies how the SGBD effluent is affected if a malfunction on the in-service SGBD radiation monitor causes output of the monitor to fail high and the reason why?
A. SGBD flow will automatically divert from CTBD to the Condensate Demin to prevent an unmonitored release.
- 8. SGBD flow must be manually diverted from CTBD to the Condensate Demin because of low CTBD flow.
C. SGBD flow will be isolated automatically to prevent an unmonitored release.
D. SGBD flow must be manually isolated because of low CTBD flow.
Page 22
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 23. For a fire in the charcoal filter unit of the CREVS system, which ONE of the following describes the classification of the fire and what type of extinguishing agent is used to put out the fire?
Fire Classification Extinguishing Agent A.
A Water B.
D Foam C.
A Foam D.
D Water Page 23 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 23. For a fire in the charcoal filter unit of the CREVS system, which ONE of the following describes the classification of the fire and what type of extinguishing agent is used to put out the fire?
Fire Classification Extinguishing Agent A.
A Water B.
o Foam C.
A Foam D.
o Water Page 23
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 24. Given the following:
A Steam Line break occurs on Unit 1.
Containment pressure is 3.7 psig.
Control Air pressure is 97 psig.
During the performance of E-O, "Reactor Trip or Safety Injection" the Unit Supervisor directs the CRO to perform E-O Appendices A and B to evaluate the support systems.
Containment Isolation Status PaneI1-XX-55-6E window 13 "FCV-32-11 0" indicates RED.
Which ONE of the following identifies the correct CRO response to the window indication?
A. The valve is in the correct position for the current conditions; continue with the support system evaluation.
B. Verify the penetration is isolated by verifying the Train B valve is closed in the flow path.
C. If the FCV can NOT be closed, direct an AUO to close manual isolation valve in the penetration flow path.
D. If the FCV can NOT be closed, direct an AUO to stop all Control & Station Air Compressors.
Page 24 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 24. Given the following:
A Steam Line break occurs on Unit 1.
Containment pressure is 3.7 psig.
Control Air pressure is 97 psig.
During the performance of E-O, "Reactor Trip or Safety Injection" the Unit Supervisor directs the CRO to perform E-O Appendices A and B to evaluate the support systems.
Containment Isolation Status Panel 1-XX-55-6E window 13 "FCV-32-11 0" indicates RED.
Which ONE of the following identifies the correct CRO response to the window indication?
A. The valve is in the correct position for the current conditions; continue with the support system evaluation.
B. Verify the penetration is isolated by verifying the Train B valve is closed in the flow path.
C. If the FCV can NOT be closed, direct an AUO to close manual isolation valve in the penetration flow path.
D. If the FCV can NOT be closed, direct an AUO to stop all Control & Station Air Compressors.
Page 24
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 25. Given the following:
Unit 1 experienced a Safety Injection.
The operating crew entered E-O, " Reactor Trip or Safety Injection" and has reached the step for checking if SI termination criteria are met.
The crew is contemplating use of ES-O.O, "Rediagnosis."
Current conditions are:
Levels AFW flow RCS Subcooling RCS Pressure Pressurizer Level SG#1 34%NR 40gpm 66°F SG#2 22% NR 260 gpm 1630 psig and rising 11 % and rising Which ONE of the following identifies...
SG#3 29%NR 130 gpm SG#4 38%NR o gpm (1) if current conditions allow the termination of safety injection, and (2) if use of ES-O.O is allowed at this time for the current conditions?
A. (1) SI Termination criteria are currently met.
(2) Allowed.
B. (1) SI Termination criteria are currently met.
(2) NOT allowed.
C. (1) SI Termination criteria are NOT currently met.
(2) Allowed.
0.(1) SI Termination criteria are NOT currently met.
(2) NOT allowed.
Page 25 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 25. Given the following:
Unit 1 experienced a Safety Injection.
The operating crew entered E-O, " Reactor Trip or Safety Injection" and has reached the step for checking if SI termination criteria are met.
The crew is contemplating use of ES-O.O, "Rediagnosis."
Current conditions are:
Levels AFW flow RCS Subcooling RCS Pressure Pressurizer Level SG#1 34%NR 40gpm 66°F SG#2 22% NR 260 gpm 1630 psig and rising 11 % and rising Which ONE of the following identifies...
SG#3 29%NR 130 gpm SG#4 38%NR o gpm (1) if current conditions allow the termination of safety injection, and (2) if use of ES-O.O is allowed at this time for the current conditions?
A. (1) SI Termination criteria are currently met.
(2) Allowed.
B. (1) SI Termination criteria are currently met.
(2) NOT allowed.
C. (1) SI Termination criteria are NOT currently met.
(2) Allowed.
D. (1) SI Termination criteria are NOT currently met.
(2) NOT allowed.
Page 25
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 26. Following an ATWS event that resulted in the MSIVs being closed, the following conditions exist:
The crew has performed the applicable Emergency Instructions and has now implemented ES-O.1, "Reactor Trip Response."
The crew determines the following conditions exist:
Reactor trip breakers are open.
Tavg has dropped from a high of 591°F to 566°F.
All SG levels are between 39% and 41 % NR.
1-HS-3-45, MFW Mode Switch, is in the 'LONG CYCLE RECIRC' position.
PORVs on S/G # 1, # 2 and # 4 maintaining SG pressure approximately 1025 psig.
SG #3 pressure is 1223 psig.
PORV on S/G #3 is closed and cannot be opened.
The crew transitions to FR-H.2 "Steam Generator Overpressure."
Which ONE of the following identifies the expected status of the Feedwater Isolation valves and a procedurally directed action to lower SG #3 pressure in accordance with FR-H.2?
FW Isolation Valves A.
Open B.
Closed C.
Open D.
Closed Action to lower SG #3 pressure Cooldown RCS using INTACT S/Gs.
Cooldown RCS using INTACT S/Gs.
Supply AFW to S/G #3.
Supply AFW to S/G #3.
Page 26 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 26. Following an ATWS event that resulted in the MSIVs being closed, the following conditions exist:
The crew has performed the applicable Emergency Instructions and has now implemented ES-O.1, "Reactor Trip Response."
The crew determines the following conditions exist:
Reactor trip breakers are open.
Tavg has dropped from a high of 591°F to 566°F.
All SG levels are between 39% and 41 % NR.
1-HS-3-45, MFW Mode Switch, is in the 'LONG CYCLE RECIRC' position.
PORVs on S/G # 1, # 2 and # 4 maintaining SG pressure approximately 1025 psig.
SG #3 pressure is 1223 psig.
PORV on S/G #3 is closed and cannot be opened.
The crew transitions to FR-H.2 "Steam Generator Overpressure."
Which ONE of the following identifies the expected status of the Feedwater Isolation valves and a procedurally directed action to lower SG #3 pressure in accordance with FR-H.2?
FW Isolation Valves A.
Open B.
Closed C.
Open D.
Closed Action to lower SG #3 pressure Cooldown RCS using INTACT S/Gs.
Cooldown RCS using INTACT S/Gs.
Supply AFW to S/G #3.
Supply AFW to S/G #3.
Page 26
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 27. After a design basis accident on Unit 1, the following conditions exist:
Containment Sump level increased to 83% and is rising.
RWST level reached sump swapover setpoint.
Which ONE of the following identifies...
(1) an unexpected source of water entering containment, in addition to the analyzed sources, that could result in the containment sump level and trend, and (2) how many trains of RHR will be aligned to the containment sump and in service in accordance with ES-1.3, "Transfer to Containment Sump?"
A. (1) High Pressure Fire Protection.
(2) ONLY one RHR train..
B. (1) High Pressure Fire Protection.
(2) BOTH RHR trains.
C. (1) Condensate Storage Tank.
(2) ONLY one RHR train.
D. (1) Condensate Storage Tank.
(2) BOTH RHR trains.
Page 27 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 27. After a design basis accident on Unit 1, the following conditions exist:
Containment Sump level increased to 83% and is rising.
RWST level reached sump swapover setpoint.
Which ONE of the following identifies...
(1) an unexpected source of water entering containment, in addition to the analyzed sources, that could result in the containment sump level and trend, and (2) how many trains of RHR will be aligned to the containment sump and in service in accordance with ES-1.3, "Transfer to Containment Sump?"
A. (1) High Pressure Fire Protection.
(2) ONLY one RHR train.*
B. (1) High Pressure Fire Protection.
(2) BOTH RHR trains.
C. (1) Condensate Storage Tank.
(2) ONLY one RHR train.
D. (1) Condensate Storage Tank.
(2) BOTH RHR trains.
Page 27
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 28. Given the following plant conditions:
Unit 1 is in Mode 5.
A heatup is in progress.
RCS pressure is 320 psig.
RCS temperature is 190°F.
As the pressurizer pressure is raised to 400 psig, which ONE of the following correctly describes...
(1) the response of #1 seal leakoff flow from the RCPs, and (2) how the pressure indicated on the #1 seal differential pressure indicators on 1-M-5 will respond to the change in pressurizer pressure?
(Assume seal injection flow, VCT temp., and VCT press. remain constant.)
- 1 seal leakoff flow Indicated #1 Seal Differential Pressure A.
rises rises B.
rises remains the same C.
drops rises D.
drops remains the same Page 28 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 28. Given the following plant conditions:
Unit 1 is in Mode 5.
A heatup is in progress.
RCS pressure is 320 psig.
RCS temperature is 190°F.
As the pressurizer pressure is raised to 400 psig, which ONE of the following correctly describes...
(1) the response of #1 sealleakoff flow from the RCPs, and (2) how the pressure indicated on the #1 seal differential pressure indicators on 1-M-5 will respond to the change in pressurizer pressure?
(Assume seal injection flow, VCT temp., and VCT press. remain constant.)
- 1 seal leakoff flow Indicated #1 Seal Differential Pressure A.
rises rises B.
rises remains the same C.
drops rises D.
drops remains the same Page 28
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 29. Given the following conditions:
- Unit 1 is at 100% power. TE-62-78A, Letdown Heat Exchanger Temperature, fails HIGH.
Which. ONE of the following describes...
(1) the impact of the failure on the plant and (2) what effect placing 1-M-6 controller 1-HIC-62-78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, to manual and adjusting in the closed direction would have on letdown temperature?
(1 )
(2)
Impact on the plant Letdown Temperature response A. Negative reacfivityaddition Letdown temperature would rise.
B. Positive reactivity addition Letdown temperature would rise.
C. Negative reactivity addition Letdown temperature will NOT change.
D. Positive reactivity addition Letdown temperature will NOT change.
Page 29 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 29. Given the following conditions:
- Unit 1 is at 100% power. TE-62-78A, Letdown Heat Exchanger Temperature, fails HIGH.
Which ONE of the following describes...
(1) the impact of the failure on the plant and (2) what effect placing 1-M-6 controller 1-HIC-62-78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL, to manual and adjusting in the closed direction would have on letdown temperature?
(1 )
(2)
Impact on the plant Letdown Temperature response A. Negative reactivity addition Letdown temperature would rise.
B. Positive reactivity addition Letdown temperature would rise.
C. Negative reactivity addition Letdown temperature will NOT change.
D. Positive reactivity addition Letdown temperature will NOT change.
Page 29
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 30. Which ONE of the following procedure alignments, when performed, results in an RHR system alignment with both RHR Crosstie Valves, 1-FCV-74-33 and 1-FCV-74-35 aligned in the open position?
A. RHR Spray alignment in accordance with FR-Z.1, "High Containment Pressure."
B. ECCS Cold Leg Injection alignment in accordance with SOI-74.01, "Residual Heat Removal System."
C. ECCS Cold Leg Recirculation alignment in accordance with ES-1.3, "Transfer to Containment Sump."
D. Hot Leg Recirculation alignment in accordance with E-1, "Loss of Reactor or Secondary Coolant."
Page 30 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 30. Which ONE of the following procedure alignments, when performed, results in an RHR system alignment with both RHR Crosstie Valves, 1-FCV-74-33 and 1-FCV-74-35 aligned in the open position?
A. RHR Spray alignment in accordance with FR-Z.1, "High Containment Pressure."
B. ECCS Cold Leg Injection alignment in accordance with SOI-74.01, "Residual Heat Removal System."
C. ECCS Cold Leg Recirculation alignment in accordance with ES-1.3, "Transfer to Containment Sump."
D. Hot Leg Recirculation alignment in accordance with E-1, "Loss of Reactor or Secondary Coolant."
Page 30
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 31. Plant conditions are as follows:
Unit 1 is in Mode 4.
RHR Train 'A' is in service per SOI-74.01, "Residuai Heat Removal System."
RCS temperature is stable at the current RHR flow rate.
Which ONE of the following malfunctions will result in a reduction in flow through the RHR Heat Exchanger 1A?
A loss of...
A. 480V Shutdown Board 1 A 1-A.
B. 120V AC Vital Instrument Power Board 1-11.
C. air to 1-FCV-74-32, RHR HTX Bypass.
D. air to 1-FCV-74-16, RHR HTX 'A' Outlet.
Page 31 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 31. Plant conditions are as follows:
Unit 1 is in Mode 4.
RHR Train 'A' is in service per SOI-74.01, "Residual Heat Removal System."
RCS temperature is stable at the current RHR flow rate.
Which ONE of the following malfunctions will result in a reduction in flow through the RHR Heat Exchanger 1 A?
A loss of...
A. 480V Shutdown Board 1 A 1-A.
B. 120V AC Vital Instrument Power Board 1-11.
C. air to 1-FCV-74-32, RHR HTX Bypass.
D. air to 1-FCV-74-16, RHR HTX 'A' Outlet.
Page 31
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 32. Given the following A small break LOCA has occurred and RCS pressure has stabilized at 985 psig.
The crew is performing ES-1.2, "Post-LOCA Cooldown and Depressurization. "
The crew is ready to stop the first Centrifugal Charging Pump (CCP) as part of SI reduction.
RCS temperature is 462°F.
Subcooling is 82°F.
After stopping the CCP, the following conditions exist:
RCS pressure is 947 psig.
RCS temperature is 455°F.
Which ONE of the following identifies...
(1) how the relationship between ECCS flow and break flow will be initially affected, and (2) based on the above conditions, how the RCS subcooling margin has changed?
Relationship between Change in ECCS Flow to Break Flow Subcooling Margin A.
Break flow and ECCS flow Subcooling rises.
remain equal.
B.
Break flow and ECCS flow Subcooling drops.
remain equal.
C:
Break flow exceeds ECCS flow.
Subcooling rises.
D.
Break flow exceeds ECCS flow.
Subcooling drops.
Page 32 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 32. Given the following A small break LOCA has occurred and RCS pressure has stabilized at 985 psig.
The crew is performing ES-1.2, "Post-LOCA Cooldown and Depressurization."
The crew is ready to stop the first Centrifugal Charging Pump (CCP) as part of SI reduction.
RCS temperature is 462°F.
Subcooling is 82°F.
After stopping the CCP, the following conditions exist:
RCS pressure is 947 psig.
RCS temperature is 455°F.
Which ONE of the following identifies...
(1) how the relationship between ECCS flow and break flow will be initially affected, and (2) based on the above conditions, how the RCS subcooling margin has changed?
Relationship between Change in ECCS Flow to Break Flow Subcooling Margin A.
Break flow and ECCS flow Subcooling rises.
remain equal.
- 8.
Break flow and ECCS flow Subcooling drops.
remain equal.
C.
Break flow exceeds ECCS flow.
Subcooling rises.
D.
Break flow exceeds ECCS flow.
Subcooling drops.
Page 32
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 33. Given the following:
Unit 1 is at 100% power.
AnnunCiator 88-D "PRT TEMP Hl"alarms.
Which ONE of the following identifies the actions required to establish and monitor Pressurizer Relief Tank (PRT) cooling?
A. Open 1-FCV-68-303, PRI WATER TO PRT, from the Main Control Room but monitor the PRT temperature on 0-L-2, Rad Waste Panel.
B. Open 1-FCV-68-303, PRI WATER TO PRT, from 0-L-2, Rad Waste Panel but monitor PRT temperature from the Main Control Room.
C. Open 1-FCV-68-303, PRI WATER TO PRT, and monitor the PRT temperature from the Main Control Room.
D. Open 1-FCV-68-303, PRI WATER TO PRT, and monitor the PRT temperature from 0-L-2, Rad Waste Panel.
Page 33 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 33. Given the following:
Unit 1 is at 100% power.
Annunciator 88-0 "PRT TEMP HI" alarms.
Which ONE of the following identifies the actions required to establish and monitor Pressurizer Relief Tank (PRT) cooling?
A. Open 1-FCV-68-303, PRI WATER TO PRT, from the Main Control Room but monitor the PRT temperature on 0-L-2, Rad Waste Panel.
B. Open 1-FCV-68-303, PRI WATER TO PRT, from 0-L-2, Rad Waste Panel but monitor PRT temperature from the Main Control Room.
C. Open 1-FCV-68-303, PRI WATER TO PRT, and monitor the PRT temperature from the Main Control Room.
O. Open 1-FCV-68-303, PRI WATER TO PRT, and monitor the PRT temperature from 0-L-2, Rad Waste Panel.
Page 33
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 34. Given the following:
Unit 1 has been shutdown for refueling and is in Mode 5.
The operating crew is performing the initial drain down of the pressurizer to 25% in accordance with GO-1 0, "Reactor Coolant System Drain and Fill Operations. "
During the drain down, which ONE of the following identifies how the PRT level will be maintained and the tank level that would be rising?
PRT level will be maintained...
A. at zero (0%) or less and Holdup Tank (HUT) level would be rising.
B. at zero (0%) or less and Refueling Water Storage Tank (RWST) level would be rising.
C. above the low level alarm and Holdup Tank (HUT) level would be rising.
D. above the low level alarm and Refueling Water Storage Tank (RWST) level would be rising.
Page 34 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 34. Given the following:
Unit 1 has been shutdown for refueling and is in Mode 5.
The operating crew is performing the initial drain down of the pressurizer to 25% in accordance with GO-10, "Reactor Coolant System Drain and Fill Operations."
During the drain down, which ONE of the following identifies how the PRT level will be maintained and the tank level that would be rising?
PRT level will be maintained...
A.
at zero (0%) or less and Holdup Tank (HUT) level would be rising.
B. at zero (0%) or less and Refueling Water Storage Tank (RWST) level would be rising.
C. above the low level alarm and Holdup Tank (HUT) level would be rising.
D. above the low level alarm and Refueling Water Storage Tank (RWST) level would be rising.
Page 34
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 35. Given the following:
Unit 1 Component Cooling Water System (CCS) Surge Tank level is decreasing due to a leak in the system.
Which ONE of the choices correctly completes the following statement?
The make-up from the Demineralized Water System would __
..l.(..:...1 )f--__
and if the emergency make-up was needed, it would be supplied from the (2) ill A. require manual alignment Primary Water System B. require manual alignment Essential Raw Cooling Water System C. auto open on low level in Surge Tank Primary Water System D. auto open on low level in Surge Tank Essential Raw Cooling Water System Page 35 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 35. Given the following:
Unit 1 Component Cooling Water System (CCS) Surge Tank level is decreasing due to a leak in the system.
Which ONE of the choices correctly completes the following statement?
The make-up from the Demineralized Water System would __
---'-(....;,..1 )1--__
and if the emergency make-up was needed, it would be supplied from the (2) ill m
A. require manual alignment Primary Water System B. require manual alignment Essential Raw Cooling Water System C. auto open on low level in Surge Tank Primary Water System D. auto open on low level in Surge Tank Essential Raw Cooling Water System Page 35
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 36. Given the following:
Unit 1 is operating at 100% power when a pressurizer PORV fails and sticks open approximately 15%.
The OAC closes the PORV block valve to isolate the PORV.
Which ONE of the following identifies the indicating light status on...
(1) the failed PORV and (2) the PORV Block valve while the Block valve is travelling from open to close?
A. (1) Both the RED and GREEN lights LIT.
(2) Only the RED light UT.
B. (1) Neither the RED nor GREEN light LIT.
(2) Only the RED light LIT.
C. (1) Both the RED and GREEN lights LIT.
(2) Both the RED and GREEN lights LIT.
D. (1) Neither the RED nor GREEN light LIT.
(2) Both the RED and GREEN lights LIT.
Page 36 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 36. Given the following:
Unit 1 is operating at 100% power when a pressurizer PORV fails and sticks open approximately 15%.
The OAC closes the PORV block valve to isolate the PORV.
Which ONE of the following identifies the indicating light status on...
(1) the failed PORV and (2) the PORV Block valve while the Block valve is travelling from open to close?
A. (1) Both the RED and GREEN lights LIT.
(2) Only the RED light LIT.
B. (1) Neither the RED nor GREEN light LIT.
(2) Only the RED light LIT.
C. (1) Both the RED and GREEN lights LIT.
(2) Both the RED and GREEN lights LIT.
D. (1) Neither the RED nor GREEN light LIT.
(2) Both the RED and GREEN lights LIT.
Page 36
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 37. Given the following conditions:
Unit 1 was at 100% power.
The 120V Vital Instrument Power Board 1-11 feed to the Train B Solid State Protection System (SSPS) is de-energized.
Which ONE of the following identifies the status of the Solid State Protection System (SSPS) logic cabinet 48v DC and 15v DC power?
A. Both the 48v and 15v power would be available.
. B. Only the 48v power would be available.
C. Only the 15v power would be available.
D. Neither the 48v nor 15v power would be available.
Page 37 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 37. Given the following conditions:
Unit 1 was at 100% power.
The 120V Vital Instrument Power Board 1-11 feed to the Train B Solid State Protection System (SSPS) is de-energized.
Which ONE of the following identifies the status of the Solid State Protection System (SSPS) logic cabinet 48v DC and 15v DC power?
A. Both the 48v and 15v power would be available.
B. Only the 48v power would be available.
C. Only the 15v power would be available.
D. Neither the 48v nor 15v power would be available.
Page 37
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 38. Given the following:
Annunciator 114-A "SSPS-A GEN WARNING" alarms.
Which ONE of the following identifies...
(1) a condition thatwould cause the alarm, and (2) where the card with the board-edge LEDs identifying the probable cause of the alarm is located?
A. (1) Permissive Switch placed in the OFF position.
(2) in the SSPS Logic cabinet.
B. (1) Permissive Switch placed in the OFF position.
(2) in the RONAN annunciator cabinets.
C. (1) Input Error Inhibit switch being placed in the INHIBIT position.
(2) in the SSPS Logic cabinet.
D. (1 ) Input Error Inhibit switch being placed in the INHIBIT position.
(2) in the RONAN annunciator cabinets.
Page 38 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 38. Given the following:
Annunciator 114-A "SSPS-A GEN WARNING" alarms.
Which ONE of the following identifies...
(1) a condition that would cause the alarm, and (2) where the card with the board-edge LEOs identifying the probable cause of the alarm is located?
A. (1) Permissive Switch placed in the OFF position.
(2) in the SSPS Logic cabinet.
B. (1) Permissive Switch placed in the OFF position.
(2) in the RONAN annunciator cabinets.
C. (1) Input Error Inhibit switch being placed in the INHIBIT position.
(2) in the SSPS Logic cabinet.
O. (1) Input Error Inhibit switch being placed in the INHIBIT position.
(2) in the RONAN annunciator cabinets.
Page 38
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 39. Given the following:
The plant is at 100% power.
All control systems are in their normal alignments.
Pressurizer Pressure Transmitter 1-PT-68-323 has failed LOW.
All actions have been taken to remove the transmitter from. service in accordance with the appropriate plant procedures.
Which ONE of the following describes the logic required from the remaining operable pressurizer pressure channels to initiate...
(1) a Low Pressurizer Pressure Reactor Trip, and (2) a Low Pressurizer Pressure Safety Injection actuation?
A. (1) 1 out of 2 (2) 1 out of 3 B. (1) 1 out of 3 (2) 1 out of 2 C. (1) 1 out of 2 (2) 1 out of 2 D. (1) 1 out of 3 (2) 1 out of 3 Page 39 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 39. Given the following:
The plant is at 100% power.
All control systems are in their normal alignments.
Pressurizer Pressure Transmitter 1-PT 323 has failed LOW.
All actions have been taken to remove the transmitter from. service in accordance with the appropriate plant procedures.
Which ONE of the following describes the logic required from the remaining operable pressurizer pressure channels to initiate...
(1) a Low Pressurizer Pressure Reactor Trip, and (2) a Low Pressurizer Pressure Safety Injection actuation?
A. (1) 1 out of 2 (2) 1 out of 3 B. (1) 1 out of 3 (2) 1 out of 2 C. (1) 1 out of 2 (2) 1 out of 2 D. (1) 1 out of 3 (2) 1 out of 3 Page 39
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 40. Which ONE of the following identifies the electrical board where the power supply breaker for the Incore Instrument Room Chiller 1A is located?
A. 6.9kv Common Board A B. 6.9kv Shutdown Board 1A-A C. 480V Reactor MOV Board 1 A 1-A D. 480V Aux Bldg Com MCC Board A Page 40 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 40. Which ONE of the following identifies the electrical board where the power supply breaker for the Incore Instrument Room Chiller 1A is located?
A. 6.9kv Common Board A B. 6.9kv Shutdown Board 1A-A C. 480V Reactor MOV Board 1 A 1-A D. 480V Aux Bldg Com MCC Board A Page 40
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 41. Given the following:
A large break LOCA has occurred on Unit 1.
Which ONE of the following identifies a valve that is interlocked such that it could NOT be opened from the MCR control switch until after the automatic swapover to the containment sump occurred?
A. 1-FCV-72-40, RHR Spray Header A.
B. 1-FCV-63-172, RHR Hot Leg injection.
C. 1-FCV-63-156, SIP Hot Leg Injection.
D. 1-FCV-72-45, CSP B Suction from Containment Sump.
Page 41 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 41. Given the following:
A large break LOCA has occurred on Unit 1.
Which ONE of the following identifies a valve that is interlocked such that it could NOT be opened from the MCR control switch until after the automatic swapover to the containment sump occurred?
A. 1-FCV-72-40, RHR Spray Header A.
B. 1-FCV-63-172, RHR Hot Leg injection.
C. 1-FCV-63-156, SIP Hot Leg Injection.
D. 1-FCV-72-45, CSP B Suction from Containment Sump.
Page 41
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 42. Given the following:
A plant shutdown and cooldown is in progress on Unit 1.
The cooldown is stopped with RCS pressure at 1850 psig and Tavg at 500°F.
Steam Dumps are returned to automatic with 3 valves throttling open.
SIG #1 PORV (atmospheric relief valve) fails open.
Which ONE of the following identifies the parameter that will cause the steam dump valves to start closing and the condition that will result in the automatic closure of the MSIVs?
Steam Dumps MSIVs A.
RCS Tavg Low Steam Line Pressure B.
RCS Tavg Steam Line negative rate function C. Steam pressure Low Steam Line Pressure D. Steam pressure Steam Line negative rate function Page 42 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 42. Given the following:
A plant shutdown and cooldown is in progress on Unit 1.
The cooldown is stopped with RCS pressure at 1850 psig and Tavg at 500°F.
Steam Dumps are returned to automatic with 3 valves throttling open.
SIG #1 PORV (atmospheric relief valve) fails open.
Which ONE of the following identifies the parameter that will cause the steam dump valves to start closing and the condition that will result in the automatic closure of the MSIVs?
Steam Dumps MSIVs A.
RCS Tavg Low Steam Line Pressure B.
RCS Tavg Steam Line negative rate function C. Steam pressure Low Steam Line Pressure D. Steam pressure Steam Line negative rate function Page 42
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 43. Given the following:
Unit 1 is at 100% power following a refueling outage.
A significant feedwater heater level transient results in HI-HI levels in Feedwater Heaters A 1 and B 1.
Which ONE of the following identifies the initial effect on...
(1 ) indicated RCS T cold,
and (2) reactor power?
A.
(1 ) RCS T cold will decrease.
(2) Reactor power decreases.
B.
(1 ) RCS T cold will decrease.
(2) Reactor power increases.
C.
(1 ) RCS T cold will increase.
(2) Reactor power decreases.
D.
(1 ) RCS T cold will increase.
(2) Reactor power increases.
Page 43 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 43. Given the following:
Unit 1 is at 100% power following a refueling outage.
A significant feedwater heater level transient results in HI-HI levels in Feedwater Heaters A 1 and B 1.
Which ONE of the following identifies the initial effect on...
(1 ) indicated RCS T cold,
and (2) reactor power?
A.
(1 ) RCS T cold will decrease.
(2) Reactor power decreases.
B.
(1 ) RCS T cold will decrease.
(2) Reactor power increases.
C.
(1 ) RCS T cold will increase.
(2) Reactor power decreases.
D.
(1 ) RCS T cold will increase.
(2) Reactor power increases.
Page 43
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 44. Which ONE of the following describes:
(1) when the main feed pump turbine trip runback circuit is enabled, and (2) how far will the load be automatically reduced to if a main feedwater pump trips?
ill ill A. Load greater than 67%.
Less than or equal to 800 MWe.
B. Load greater than 85%.
Less than or equal to 800 MWe.
C. Load greater than 67%.
Less than or equal to 1000 MWe.
D. Load greater than 85%.
. Less than or equal to 1000 MWe.
Page 44 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 44. Which ONE of the following describes:
(1) when the main feed pump turbine trip runback circuit is enabled, and (2) how far will the load be automatically reduced to if a main feedwater pump trips?
ill ill A. Load greater than 67%.
Less than or equal to 800 MWe.
B. Load greater than 85%.
Less than or equal to 800 MWe.
C. Load greater than 67%.
Less than or equal to 1000 MWe.
D. Load greater than 85%.
Less than or equal to 1000 MWe.
Page 44
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 45. Given the following:
Unit 1 was operating at 100% power when a reactor trip occurred.
The operating crew entered the emergency procedures and have transitioned to ES-O.1, "Reactor Trip Response."
CRO notes the following conditions:
- 1
- 2
- 3
- 4 Steam Generator levels:
36%NR 31 %NR 33%NR 39%NR AFW flows are:
100 gpm 320 gpm 280 gpm 0 gpm All AFW LCVs controllers are in automatic.
Considering Conditions A and B below, (1) which ONE would cause the larger change in the AFW flow rate to SG #2, and (2) which ONE would require that local action be taken to isolate feed flow to the affected SG in order to stabilize the SG level in accordance with ES-0.1?
Condition A The control air line breaks off the SG #1 Motor Driven AFW supply valve, 1-LCV-3-164.
Condition B The control air line breaks off the SG #4 Turbine Driven AFW supply valve, 1-LCV-3-175.
Largest Change Require Local Actions A.
Condition A Condition A B.
Condition A Condition B C.
Condition B Condition A D.
Condition B Condition B Page 45 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 45. Given the following:
Unit 1 was operating at 100% power when a reactor trip occurred.
The operating crew entered the emergency procedures and have transitioned to ES-O.1, "Reactor Trip Response."
CRO notes the following conditions:
- 1
- 2
- 3
- 4 Steam Generator levels:
36%NR 31 %NR 33%NR 39%NR AFW flows are:
100 gpm 320 gpm 280 gpm 0 gpm All AFW LCVs controllers are in automatic.
Considering Conditions A and B below, (1) which ONE would cause the larger change in the AFW flow rate to SG #2, and (2) which ONE would require that local action be taken to isolate feed flow to the affected SG in order to stabilize the SG level in accordance with ES-0.1?
Condition A The control air line breaks off the SG #1 Motor Driven AFW supply valve, 1-LCV-3-164.
Condition B The control air line breaks off the SG #4 Turbine Driven AFW supply valve, 1-LCV-3-175.
Largest Change Require Local Actions A.
Condition A Condition A B.
Condition A Condition B C.
Condition B Condition A D.
Condition B Condition B Page 45
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 46. The plant is at 40% and raising power when the following occurs:
An internal transformer problem resulted in a sudden pressure condition on CSST A.
503-A, "CSST A Failure" alarms.
What is another expected alarm, and what action is directed by procedures as a result of the condition?
Alarm A. 505-A, "Sprinkler Initiated" B. 505-A, "Sprinkler Initiated" C. 75-C, "Electrical Trouble" D. 75-C, "Electrical Trouble" Action Verify shutdown of South TB bldg air intake fans.
Notify Appendix R AUOs to report to U-2 side control room.
Verify shutdown of South TB bldg air intake fans.
Notify Appendix R AUOs to report to U-2 side control room.
Page 46 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 46. The plant is at 40% and raising power when the following occurs:
An internal transformer problem resulted in a sudden pressure condition on CSST A.
503-A, "CSST A Failure" alarms.
What is another expected alarm, and what action is directed by procedures as a result of the condition?
Alarm A. 505-A, "Sprinkler Initiated" B. 505-A, "Sprinkler Initiated" C. 75-C, "Electrical Trouble" D. 75-C, "Electrical Trouble" Action Verify shutdown of South TB bldg air intake fans.
Notify Appendix R AUOs to report to U-2 side control room.
Verify shutdown of South TB bldg air intake fans.
Notify Appendix R AUOs to report to U-2 side control room.
Page 46
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 47. Given the following:
Unit 1 at 100% power.
Control and Station Air Compressors A, B, & C running and loaded.
Control and Station Air Compressor D out of service.
All electrical boards in a normal alignment.
ERCW system in a normal alignment with 1 pump running on each shutdown board.
2B-B Shutdown Board automatically transferred to the Diesel Generator.
Which ONE of the following is an action required while restoring the plant back to normal in accordance with SOI-211.04, "6.9KV Shutdown Board 2B-B?"
A. Manually start Control and Station Air Compressor B.
B. Manually stop an Essential Raw Cooling Water pump.
C. Transfer 480v Auxiliary Building Common Board back to normal.
D. Restore CCS Heat Exchanger 'C' Outlet, 0-FCV-67-152, to close.
Page 47 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 47. Given the following:
Unit 1 at 100% power.
Control and Station Air Compressors A, B, & C running and loaded.
Control and Station Air Compressor D out of service.
All electrical boards in a normal alignment.
ERCW system in a normal alignment with 1 pump running on each shutdown board.
2B-B Shutdown Board automatically transferred to the Diesel Generator.
Which ONE of the following is an action required while restoring the plant back to normal in accordance with SOI-211.04, "6.9KV Shutdown Board 2B-B?"
A. Manually start Control and Station Air Compressor B.
B. Manually stop an Essential Raw Cooling Water pump.
C. Transfer 480v Auxiliary Building Common Board back to normal.
D. Restore CCS Heat Exchanger 'C' Outlet, 0-FCV-67-152, to close.
Page 47
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 48. The unit is operating at 100%.
Which ONE of the following correctly describes the effect of a loss of 125 V DC Vital Battery Board I on the DG(s), assuming no operator action?
A. ONLY DG 1 A-A starts. Power is available to the DG 1A-A local control panel relays.
B. ONLY DG 1 A-A starts. Power is NOT available to DG 1A-A local control panel relays.
C. ALL four DGs start. Power is available to DG 1 A-A local control panel relays.
D. ALL four DGs start. Power is NOT available to DG 1A-A local control panel relays.
Page 48 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 48. The unit is operating at 100%.
Which ONE of the following correctly describes the effect of a loss of 125 V DC Vital Battery Board I on the DG(s), assuming no operator action?
A. ONLY DG 1 A-A starts. Power is available to the DG 1A-A local control panel relays.
B. ONLY DG 1 A-A starts. Power is NOT available to DG 1A-A local control panel relays.
C. ALL four DGs start. Power is available to DG 1A-A local control panel relays.
D. ALL four DGs start. Power is NOT available to DG 1A-A local control panel relays.
Page 48
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 49. Which ONE of the following identifies a condition that would result in the 250 V DC Turbine Building Distribution Board 1 automatically transferring to its alternate supply, and, if the condition was cleared, how the transfer back to normal would occur?
Condition Transfer Back A. Normal feeder current Automatically exceeds 800 amps.
B. Normal feeder current Manually exceeds 800 amps.
C. Board voltage Automatically drops to 188vfor 4 seconds.
D. Board voltage Manually drops to 188v for 4 seconds.
Page 49 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 49. Which ONE of the following identifies a condition that would result in the 250 V DC Turbine Building Distribution Board 1 automatically transferring to its alternate supply, and, if the condition was cleared, how the transfer back to normal would occur?
Condition Transfer Back A. Normal feeder current Automatically exceeds 800 amps.
B. Normal feeder current Manually exceeds 800 amps.
C. Board voltage Automatically drops to 188v for 4 seconds.
D. Board voltage Manually drops to 188v for 4 seconds.
Page 49
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 50. The operating crew has performed a manual start of Diesel Generator (DG)1A-A using 1-HS-82-14, START-STOP, on O-M-26, when the following alarm is received:
196-D, "CRANKCASE PRESS HI" Which ONE of the following:
(1) Is the LOWEST crankcase pressure which would result in the above
- alarm, and (2) how the crankcase pressure will affect DG operation?
ill
(~
A. 1"H2O DG will NOT automatically trip.
S. 1"H2O DG will automatically trip.
C. 7"H2O DG will NOT automatically trip.
D. 7"H2O DG will automatically trip.
Page 50 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 50. The operating crew has performed a manual start of Diesel Generator (DG)1A-A using 1-HS-82-14, START-STOP, on O-M-26, when the following alarm is received:
196-D, "CRANKCASE PRESS HI" Which ONE of the following:
(1) Is the LOWEST crankcase pressure which would result in the above
- alarm, and (2) how the crankcase pressure will affect DG operation?
ill
(£)
DG will NOT automatically trip.
B. 1"H20 DG will automatically trip.
DG will NOT automatically trip.
DG will automatically trip.
Page 50
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 51. Given the following:
DIG 1 A-A is running for a surveillance test.
The Fuel Oil Transfer Pump on Engine 1A1 is automatically started due to low level in the Day Tank.
As the tank level rises the Day Tank "Hi Level" switch fails to stop the pump.
Which ONE of the following identifies...
(1) the result of the "Hi Level" switch failure, and (2) how Engine 1A2 Day Tank is affected by the fuel oil transfer pump running on Engine 1A1?
A. (1) The Day Tank will overflow back to the 7-day Tank.
(2) 1A2 Day Tank will receive fuel oil while the pump is running.
B. (1) The Day Tank will overflow back to the 7-day Tank.
(2) 1A2 Day Tank level will lower until the Fuel Oil Transfer Pump on its engine is started.
C. (1) The pump will be stopped by a "HI-HI Level" switch actuation.
(2) 1A2 Day Tank will receive fuel oil while the pump is running.
D. (1) The pump will be stopped by a "HI-HI Level" switch actuation.
(2) 1A2 Day Tank level will lower until the Fuel Oil Transfer Pump on its engine is started.
Page 51 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 51. Given the following:
DIG 1A-A is running for a surveillance test.
The Fuel Oil Transfer Pump on Engine 1 A 1 is automatically started due to low level in the Day Tank.
As the tank level rises the Day Tank "Hi Level" switch fails to stop the pump.
Which ONE of the following identifies...
(1) the result of the "Hi Level" switch failure, and (2) how Engine 1A2 Day Tank is affected by the fuel oil transfer pump running on Engine 1A1?
A. (1) The Day Tank will overflow back to the 7-day Tank.
(2) 1A2 Day Tank will receive fuel oil while the pump is running.
B. (1) The Day Tank will overflow back to the 7-day Tank.
(2) 1A2 Day Tank level will lower until the Fuel Oil Transfer Pump on its engine is started.
C. (1) The pump will be stopped by a "HI-HI Level" switch actuation.
(2) 1A2 Day Tank will receive fuel oil while the pump is running.
D. (1) The pump will be stopped by a "HI-HI Level" switch actuation.
(2) 1A2 Day Tank level will lower until the Fuel Oil Transfer Pump on its engine is started.
Page 51
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
-52. Given the following plant conditions:
Waste Gas Decay Tank 'D' planned release is in progress.
184-C, "WGDT REL LINE O-RM-118INSTR MALF," actuates due to a momentary power failure.
The instrument malfunction has been reset by the crew.
Which ONE of the following identifies the effect of the above conditions on the Plant Vent Flow Control Valve, 0-FCV-77-119?
A. 0-FCV-77-119 will close and cannot be opened until after local action is taken to reduce the controller output to ZERO.
B. 0-FCV-77-119 will remain open unless the radiation monitor spikes to the HI RADsetpoint when the power is restored.
C. 0-FCV-77-119 will close but reopen when the power is restored.
D. 0-FCV-77-119 will close but reopen when the instrument malfunction is reset.
Page 52 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 52. Given the following plant conditions:
Waste Gas Decay Tank '0' planned release is in progress.
184-C, "WGDT REL LINE O-RM-118 INSTR MALF," actuates due to a momentary power failure.
The instrument malfunction has been reset by the crew.
Which ONE of the following identifies the effect of the above conditions on the Plant Vent Flow Control Valve, 0-FCV-77-119?
A. 0-FCV-77-119 will close and cannot be opened until after local action is taken to reduce the controller output to ZERO.
B. 0-FCV-77-119 will remain open unless the radiation monitor spikes to the HI RAD setpoint when the power is restored.
C. 0-FCV-77-119 will close but reopen when the power is restored.
D. 0-FCV-77-119 will close but reopen when the instrument malfunction is reset.
Page 52
11/2009 Watts 8ar SRO NRC License Exam 12/17/2009
- 53. Given the following:
ERCW pump F-8 is running and is the pump selected to start by the load sequencing relays if off-site power was lost.
With the above alignment, which ONE of the following identifies...
(1) the 6.9kV Shutdown 80ard that supplies power to ERCW pump F-8 and (2) an additional ERCW pump that can be selected to start on the opposite Unit Shutdown 8oard?
Pump F-8 Power Supply
. Additional Pump Selected A.
18-8 ERCW pump E-8
- 8.
18-8 ERCW pump H-8 C.
28-8 ERCW pump E-8 D.
28-8 ERCW pump H-8 Page 53 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 53. Given the following:
ERCW pump F-B is running and is the pump selected to start by the load sequencing relays if off-site power was lost.
With the above alignment, which ONE of the following identifies...
(1) the 6.9kV Shutdown Board that supplies power to ERCW pump F-B and (2) an additional ERCW pump that can be selected to start on the opposite Unit Shutdown Board?
Pump F-B Power Supply Additional Pump Selected A.
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 54. Given the following:
A leak in the Control Air System has caused the air pressure to decrease to 82 psig.
Which ONE of the following identifies the status of the Auxiliary Air Compressors and 0-PCV-33-4, Service Air Isolation Valve?
Auxiliary Air Compressors A. Not running but will start if pressure drops lower.
B. Not running but will start if pressure drops lower.
C. Would have automatically started.
D. Would have automatically started.
0-PCV-33-4 OPEN CLOSED OPEN CLOSED Page 54 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 54. Given the following:
A leak in the Control Air System has caused the air pressure to decrease to 82 psig.
Which ONE of the following identifies the status of the Auxiliary Air Compressors and 0-PCV-33-4, Service Air Isolation Valve?
Auxiliary Air Compressors A. Not running but will start if pressure drops lower.
B. Not running but will start if pressure drops lower.
C. Would have automatically started.
D. Would have automatically started.
0-PCV-33-4 OPEN CLOSED OPEN CLOSED Page 54
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 55. Given the following:
Unit 1 is in Mode 3 following a forced shutdown.
The operating crew is performing the procedure to place Train A Containment Purge in service to lower containment.
Both Containment Purge Radiation Monitors1-RM-90-130 and 1-RM-90-131 are operable.
Which ONE of the choices below completes the following statement?
When placing only Containment Purge Train A in service (1) of the Containment Purge Radiation Monitors will be aligned for service and maintenance would be notified to (2)
(1 )
A.
both B.
both C.
only one D.
only one (2)
Block lower ice doors to prevent inadvertent opening.
Recalibrate 1-RM-90-106, Containment Radiation Monitor, alarm setpoint.
Block lower ice doors to prevent inadvertent opening.
Recalibrate 1-RM-90-1 06, Containment Radiation Monitor, alarm setpoint.
Page 55 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 55. Given the following:
Unit 1 is in Mode 3 following a forced shutdown.
The operating crew is performing the procedure to place Train A Containment Purge in service to lower containment.
Both Containment Purge Radiation Monitors 1-RM-90-130 and 1-RM-90-131 are operable.
Which ONE of the choices below completes the following statement?
When placing only Containment Purge Train A in service (1) of the Containment Purge Radiation Monitors will be aligned for service and maintenance would be notified to (2)
(1 )
A.
both B.
both C.
only one D.
only one (2)
Block lower ice doors to prevent inadvertent opening.
Recalibrate 1-RM-90-1 06, Containment Radiation Monitor, alarm setpoint.
Block lower ice doors to prevent inadvertent opening.
Recalibrate 1-RM-90-1 06, Containment Radiation Monitor, alarm setpoint.
Page 55
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 56. Given the following:
Unit 1 reactor startup is in progress.
Control Bank C is withdrawn 48 steps.
ECP predicts criticality at 97 steps on Control Bank C.
OAC is withdrawing Control Rods when an AFW flow perturbation occurs.
Control Rod withdrawal is stopped with Control Bank C at 72 steps.
Tavgdrops to 554°F and the reactor is determined to be critical.
Power is stabilized below P-6.
Which ONE of the following choices completes the following statement?
The Control Rod Insertion Limit was (1) and Tavg (2) the Surveillance Requirement for the minimum temperature for criticality.
REFERENCE PROVIDED ill ill A. Violated lowered below B. Violated remained above C. NOT Violated lowered below D. NOT Violated remained above Page 56 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 56. Given the following:
Unit 1 reactor startup is in progress.
Control Bank C is withdrawn 48 steps.
ECP predicts criticality at 97 steps on Control Bank C.
OAC is withdrawing Control Rods when an AFW flow perturbation occurs.
Control Rod withdrawal is stopped with Control Bank C at 72 steps.
Tavg drops to 554°F and the reactor is determined to be critical.
Power is stabilized below P-6.
Which ONE of the following choices completes the following statement?
The Control Rod Insertion Limit was (1) and Tavg (2) the Surveillance Requirement for the minimum temperature for criticality.
REFERENCE PROVIDED ill
{£}
A. Violated lowered below B. Violated remained above C. NOT Violated lowered below D. NOT Violated remained above Page 56
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 57. Given the following plant conditions:
A Reactor Cavity seal failure occurred during refueling operations.
Reactor Cavity water level lowered to EI 746'.
The crew enters AOI-29, "Dropped or Damaged Fuel or Refueling Cavity Seal Failure."
The decision has been made to makeup to the cavity using the CVCS system.
When the alignment of the CVCS is complete in accordance with AOI-29, the CCP will be taking suction from the _(1L-,- and discharging to the RCS through the (2) flow path.
(1.)
A.
VCT normal charging B.
VCT BIT C.
RWST normal charging D.
RWST BIT Page 57 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 57. Given the following plant conditions:
A Reactor Cavity seal failure occurred during refueling operations.
Reactor Cavity water level lowered to EI 746'.
The crew enters AOI-29, "Dropped or Damaged Fuel or Refueling Cavity Seal Failure."
The decision has been made to makeup to the cavity using the CVCS system.
When the alignment of the CVCS is complete in accordance with AOI-29, the CCP will be taking suction from the _(~
and discharging to the RCS through the (2) flow path.
(11 A.
VCT normal charging B.
VCT BIT C.
RWST normal charging D.
RWST BIT Page 57
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 58. Consider Unit 1 operating in the following 2 conditions with the Main Control Room Radiation Monitm, O-RM-90-125, out of service.
Condition 1 - Mode 5 with no fuel movement in progress in the Spent Fuel Pit.
Condition 2 - NO Mode with spent fuel shuffles being conducted in the Spent Fuel Pit.
Which ONE of the following correctly identifies the status of Technical Specification 3.3.7, "CREVS Actuation Instrumentation" for each of the conditions?
The LCO is...
A. required to be entered with the Unit in Condition 1 only.
B. required to be entered with the Unit in Condition 2 only.
C. required to be entered with the Unit in either Condition.
D. NOT required to be entered with the Unit in either Condition.
Page 58 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 58. Consider Unit 1 operating in the following 2 conditions with the Main Control Room Radiation Monitor, O-RM-90-125, outof service.
Condition 1 - Mode 5 with no fuel movement in progress in the Spent Fuel Pit.
Condition 2 -
NO Mode with spent fuel shuffles being conducted in the Spent Fuel Pit.
Which ONE of the following correctly identifies the status of Technical Specification 3.3.7, "CREVS Actuation Instrumentation" for each of the conditions?
The LCO is...
A. required to be entered with the Unit in Condition 1 only.
B. required to be entered with the Unit in Condition 2 only.
C. required to be entered with the Unit in either Condition.
D. NOT required to be entered with the Unit in either Condition.
Page 58
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 59. Given the following:
A LOCA has occurred on Unit 1.
One train of EGTS has been removed from service in accordance with E-1, "Loss of Reactor or Secondary Coolant."
Which ONE of the following identifies...
(1) the purpose of the charcoal filter on the suction side of the EGTS cleanup
- fan, and (2) why flow is maintained through the EGTS Filter removed from service?
A. (1) To remove iodine and other halogen gases.
(2) To remove the heat generated in the charcoal bed.
B. (1) To remove iodine and other halogen gases.
(2) To prevent corrosive carbolic acid build-up in the charcoal bed.
C. (1) To remove Cesium and other particulates.
(2) To remove the heat generated in the charcoal bed.
D. (1) To remove Cesium and other particulates.
. (2) To prevent corrosive carbolic acid build-up in the charcoal bed.
Page 59 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 59. Given the following:
A LOCA has occurred on Unit 1.
One train of EGTS has been removed from service in accordance with E-1, "Loss of Reactor or Secondary Coolant."
Which ONE of the following identifies...
(1) the purpose of the charcoal filter on the suction side of the EGTS cleanup
- fan, and (2) why flow is maintained through the EGTS Filter removed from service?
A. (1) To remove iodine and other halogen gases.
(2) To remove the heat generated in the charcoal bed.
B. (1) To remove iodine and other halogen gases.
(2) To prevent corrosive carbolic acid build-up in the charcoal bed.
C. (1) To remove Cesium and other particulates.
(2) To remove the heat generated in the charcoal bed.
D. (1) To remove Cesium and other particulates.
(2) To prevent corrosive carbolic acid build-up in the charcoal bed.
Page 59
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 60. Given the following plant conditions:
The plant is in Mode 6.
The Reactor Cavity has been filled from the RWST.
Reactor Cavity and Spent Fuel Pool (SFP) levels are equalized.
A purification of the Transfer Canal has just been commenced.
A rupture ofthe Transfer Canal drain line then occurs.
Reactor Cavity and SFP levels are at 747' and lowering.
Which ONE of the following identifies...
(1) if no operator action is taken, at what level above the fuel assemblies would the Spent Fuel Pool level stabilize, and (2) if the operators respond by isolating the leak and immediately establishing.
makeup to the SFP makeup per SOI-78.01, "Spent Fuel Pool Cooling and Cleaning System," the source of makeup to the SFP that will be used?
A. (1 )
13 feet (2)
Demineralized water B. (1 )
13 feet (2)
RWST C. (1 )
25 feet, 10 inches (2)
Demineralized water D. (1 )
25 feet, 10 inches (2)
RWST Page 60 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 60. Given the following plant conditions:
The plant is in Mode 6.
The Reactor Cavity has been filled from the RWST.
Reactor Cavity and Spent Fuel Pool (SFP) levels are equalized.
A purification of the Transfer Canal has just been commenced.
A rupture of the Transfer Canal drain line then occurs.
Reactor Cavity and SFP levels are at 747' and lowering.
Which ONE of the following identifies...
(1) if no operator action is taken, at what level above the fuel assemblies would the Spent Fuel Pool level stabilize, and (2) if the operators respond by isolating the leak and immediately establishing makeup to the SFP makeup per SOI-78.01, "Spent Fuel Pool Cooling and Cleaning System," the source of makeup to the SFP that will be used?
A. (1 )
13 feet (2)
Demineralized water B. (1 )
13 feet (2)
RWST C. (1 )
25 feet, 10 inches (2)
Demineralized water D. (1 )
25 feet, 10 inches (2)
RWST Page 60
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 61. Given the following conditions:
Unit 1 is at 21 % power with all systems in normal alignment.
The Main Generator is synchronized to the grid.
SG #1 Main Steam Isolation Valve closes due to a spurious signal.
Assuming the reactor does NOT trip, which ONE of the following describes how RCS
~T and Steam Generator pressure wililNITIALL Y respond in the affected loop?
In the affected Loop, RCS ~T...
A. rises and SG steam pressure rises.
B. rises and SG steam pressure lowers.
C. lowers and SG steam pressure rises.
D. lowers and SG steam pressure lowers.
Page 61 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 61. Given the following conditions:
Unit 1 is at 21 % power with all systems in normal alignment.
The Main Generator is synchronized to the grid.
SG #1 Main Steam Isolation Valve closes due to a spurious signal.
Assuming the reactor does NOT trip, which ONE of the following describes how RCS
~T and Steam Generator pressure wililNITIALL Y respond in the affected loop?
In the affected Loop, RCS ~T...
A. rises and SG steam pressure rises.
B. rises and SG steam pressure lowers.
C. lowers and SG steam pressure rises.
D. lowers and SG steam pressure lowers.
Page 61
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 62. Given the following conditions:
The plant is at 40% power and 1-TRI-47-1, "Main Turbine Oil Trip Devices Quarterly Test" is in progress for the mechanical overspeed trip device.
Operator #1 places the TO TEST - NORMAL lever to the TO TEST position.
Operator #2 fullyopens the 1-TV-47-27, Overspeed Trip Test valve.
If the TO TEST - NORMAL lever were to slip from Operator #1's grasp, which ONE of the following will occur?
A. Neither the turbine nor the reactor will trip, but indicated auto stop oil pressure will drop to approximately 70 psig and stabilize.
B. Neither the turbine nor the reactor will trip, but indicated auto stop oil pressure will drop to 0 psig.
C. ONLY the turbine will trip. The reactor will remain operating.
D. BOTH the reactor and the turbine will trip.
Page 62 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 62. Given the following conditions:
The plant is at 40% power and 1-TRI-47-1, "Main Turbine Oil Trip Devices Quarterly Test" is in progress for the mechanical overspeed trip device.
Operator #1 places the TO TEST - NORMAL lever to the TO TEST position.
Operator #2 fully opens the 1-TV-47-27, Overspeed Trip Test valve.
If the TO TEST - NORMAL lever were to slip from Operator #1's grasp, which ONE of the following will occur?
A. Neither the turbine nor the reactor will trip, but indicated auto stop oil pressure will drop to approximately 70 psig and stabilize.
B. Neither the turbine nor the reactor will trip, but indicated auto stop oil pressure will drop to 0 psig.
C. ONLY the turbine will trip. The reactor will remain operating.
D. BOTH the reactor and the turbine will trip.
Page 62
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 63. Given the following conditions:
Reactor power is steady-state at 80%.
Condenser Vacuum Pumps (CVP) 1A and 1 B are running.
Condenser Vacuum Pump 1 C pump is out of service for maintenance.
Which ONE of the following conditions would result if NO operator action is taken in response to a leak which completely drains the seal water tank?
A. CVP 1 B would trip when seal water pressure drops to 12 psig, and condensate temperature leaving the hotwell would rise.
B. CVP 1 B would trip when seal water pressure drops to 20 psig, and condensate temperature leaving the hotwell would drop.
C. Both the Generator electrical output and condensate temperature leaving the hotwell would drop.
D. The Generator electrical output would drop and condensate temperature leaving the hotwell would rise.
Page 63 11/2009 Watts 8arSRONRC License Exam 12/17/2009
- 63. Given the following conditions:
Reactor power is steady-state at 80%.
Condenser Vacuum Pumps (CVP) 1 A and 18 are running.
Condenser Vacuum Pump 1 C pump is out of service for maintenance.
Which ONE of the following conditions would result if NO operator action is taken in response to a leak which completely drains the seal water tank?
A. CVP 18 would trip when seal water pressure drops to 12 psig, and condensate temperature leaving the hotwell would rise.
B. CVP 18 would trip when seal water pressure drops to 20 psig, and condensate temperature leaving the hotwell would drop.
C. 80th the Generator electrical output and condensate temperature leaving the hotwell would drop.
D. The Generator electrical output would drop and condensate temperature leaving the hotwell would rise.
Page 63
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 64. Given the following:
A release of the Waste Gas Tank "G" is being performed.
Which ONE of the following identifies...
(1) the ABGTS alignment required during the release, and (2) how the running ABGTS fan will be affected if the release is automatically terminated due to an instrument malfunction of 0-RM-90-118, Waste Gas Release Radiation Monitor?
ABGTS alignment A. Either ABGTS Train can be in service.
B. Either ABGTS Train can be in service.
C. ABGTS Train A is required to be in service.
D. ABGTS Train A is required to be in service.
Running ABGTS fan will...
automatically shutdown.
have to be manually shutdown usingthe SOL automatically shutdown.
have to be manually shutdown using the SOL Page 64 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 64. Given the following:
A release of the Waste Gas Tank "c" is being performed.
Which ONE of the following identifies...
(1) the ABGTS alignment required during the release, and (2) how the running ABGTS fan will be affected if the release is automatically terminated due to an instrument malfunction of O-RM-90-118, Waste Gas Release Radiation Monitor?
ABGTS alignment Running ABGTS fan wilL..
A. Either ABGTS Train automatically shutdown.
can be in service.
B. Either ABGTS Train have to be manually shutdown using the can be in service.
SOL C. ABGTS Train A is automatically shutdown.
required to be in service.
D. ABGTS Train A is have to be manually shutdown using the required to be in service.
SOL Page 64
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 65. Which ONE of the following describes a personnel hazard associated with the fire extinguishing agent used in the Lube Oil Dispensing Room, and the method used to warn personnel that the extinguishing agent has been discharged?
Hazard A.
asphyx~ation from C02 B.
asphyxiation from C02 C.
toxic fumes from aqueous foam D.
toxic fumes from aqueous foam Method of Protecting Personnel wintergreen odor AND audible alarm audible alarm ONLY wintergreen odor AND audible alarm audible alarm ONLY Page 65 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 65. Which ONE of the following describes a personnel hazard associated with the fire extinguishing agent used in the Lube Oil Dispensing Room, and the method used to warn personnel that the extinguishing agent has been discharged?
Hazard A.
asphyxiation from C02 B.
asphyxiation from C02 C.
toxic fumes from aqueous foam D.
toxic fumes from aqueous foam Method of Protecting Personnel wintergreen odor AND audible alarm audible alarm ONLY wintergreen odor AND audible alarm audible alarm ONLY Page 65
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 66. Which ONE of the following describes an acceptable method for verifying the position of a LOCKED and THROTTLED valve in a safety related flowpath?
A. Independent verification is conducted by two individuals at different times, where the first positions and locks the valve. The second then verifies the locking mechanism installed.
B. Independent verification is conducted by two individuals, one who physically positions and locks the valve and the second who verifies valve closure using alternate indications.
C. Concurrent verification is conducted by two individuals at the same time where one initially positions and locks the valve while the second party observes.
D. Concurrent verification is conducted by two individuals at the same time where the valve is positioned and locked, then a third person is required to verify the locking mechanism is in place.
Page 66 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 66. Which ONE of the following describes an acceptable method for verifying the position of a LOCKED and THROTTLED valve in a safety related flowpath?
A. Independent verification is conducted by two individuals at different times, where the first positions and locks the valve. The second then verifies the locking mechanism installed.
B. Independent verification is conducted by two individuals, one who physically positions and locks the valve and the second who verifies valve closure using alternate indications.
C. Concurrent verification is conducted by two individuals at the same time where one initially positions and locks the valve while the second party observes.
D. Concurrent verification is conducted by two individuals at the same time where the valve is positioned and locked, then a third person is required to verify the locking mechanism is in place.
Page 66
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 67. Which ONE of the following identifies two (2) components that can be directly controlled from the Auxiliary Control Room 1-L-10 Panel?
A. TO AFW pump.
B. TO AFW pump.
Main Steam Isolation Valve 1-FCV-1-4.
M-O AFW Pump 1 B-B Pressure Control Valve.
O. Main Steam Isolation Valve 1-FCV-1-4.
M-O AFW Pump 1 B-B Pressure Control Valve.
Page 67 11/2009 Watts 8ar SRO NRC License Exam 12/17/2009
- 67. Which ONE of the following identifies two (2) components that can be directly controlled from the Auxiliary Control Room 1-L-10 Panel?
A. TO AFW pump.
- 8. TO AFW pump.
Main Steam Isolation Valve 1-FCV-1-4.
M-O AFW Pump 18-8 Pressure Control Valve.
O. Main Steam Isolation Valve 1-FCV-1-4.
M-O AFW Pump 18-8 Pressure Control Valve.
Page 67
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 68. Given the following:
Unit 1 is at 100% power.
The Shift Manager and the Shift Technical Advisor (who has an active SRO license) are in the Control Room discussing an upcoming evolution.
The Unit 1 Unit Supervisor is on a plant walkdown when the following events occur:
Unit 1 experienced a spurious turbine trip.
The Unit 1 reactor did NOT trip automatically and could not be tripped manually from the Control Room.
In accordance with TI-12.04, "User's Guide for Abnormal and Emergency Operating Instructions," which ONE of the following identifies who can be the initial EOP 'Procedure Reader,' and also identifies the required frequency of
'Status Tree' monitoring while performing FR-S.1, "Nuclear Power Generation/ATWS?"
Procedure Reader Status Tree Monitoring A. Shift Manager Continuously.
B. Shift Technical Advisor Continuously C. Shift Manager Every 10-20 minutes D. Shift Technical Advisor Every 10-20 minutes Page 68 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 68. Given the following:
Unit 1 is at 100% power.
The Shift Manager and the Shift Technical Advisor (who has an active SRO license) are in the Control Room discussing an upcoming evolution.
The Unit 1 Unit Supervisor is on a plant walkdown when the following events occur:
Unit 1 experienced a spurious turbine trip.
The Unit 1 reactor did NOT trip automatically and could not be tripped
. manually from the Control Room.
In accordance with TI-12.04, "User's Guide for Abnormal and Emergency Operating Instructions," which ONE of the following identifies who can be the initial EOP 'Procedure Reader,' and also identifies the required frequency of
'Status Tree' monitoring while performing FR-S.1, "Nuclear Power Generationl ATWS?"
Procedure Reader Status Tree Monitoring A. Shift Manager Continuously B. Shift Technical Advisor Continuously C. Shift Manager Every 10-20 minutes D. Shift Technical Advisor Every 10-20 minutes Page 68
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 69. Given the following:
An operator is retrieving an electrical system schematic drawing from the
. Business Support Library (BSL) to verify system status.
The computer screen displays 2 active versions of the print.
The "Drawing Type" column identifies one as "AC" and the other as "CC."
Which ONE of the following identifies...
(1) which of the prints is the correct print to retrieve from BSL, and (2) how markings on a MCR primary drawing would reflect a recent change that added something to the print?
ill A.
AC with Green lines B.
AC with Red lines C.
CC with Green lines D.
CC with Red lines Page 69 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 69. Given the following:
An operator is retrieving an electrical system schematic drawing from the Business Support Library (BSL) to verify system status.
The computer screen displays 2 active versions of the print.
The "Drawing Type" column identifies one as "AC" and the other as "CC."
Which ONE of the following identifies...
(1) which of the prints is the correct print to retrieve from BSL, and (2) how markings on a MCR primary drawing would reflect a recent change that added something to the print?
ill A.
AC with Green lines B.
AC with Red lines C.
CC with Green lines D.
CC with Red lines Page 69
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 70. Given the following conditions; Unit 1 is in Mode 3 with a reactor startup in progress.
During Control Rod withdrawal, the OAC notes the following:
Control Bank A Group 1 demand position indication is 107 steps.
All of the Group 1 control rod RPls indicate from a low of 94 steps to a high of 111 steps.
Control Bank A Group 2 demand position indication is 104 steps.
All of the Group 2 Control rod RPls indicate from a low of 97 steps to a high of 108 steps.
Control Bank B step counters and all RPls indicate zero (0).
Which ONE of the following actions is required?
A. Immediately open the Reactor Trip breakers.
B. Restore rod to within alignment limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
C. Stop rod withdrawal until RPI indications are verified.
D. Manually insert all Bank A Control Rods to zero steps.
Page 70 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 70. Given the following conditions; Unit 1 is in Mode 3 with a reactor startup in progress.
During Control Rod withdrawal, the OAC notes the following:
Control Bank A Group 1 demand position indication is 107 steps.
All of the Group 1 control rod RPls indicate from a low of 94 steps to a high of 111 steps.
Control Bank A Group 2 demand position indication is 104 steps.
All of the Group 2 Control rod RPls indicate from a low of 97 steps to a high of 108 steps.
Control Bank B step counters and all RPls indicate zero (0).
Which ONE of the following actions is required?
A. Immediately open the Reactor Trip breakers.
B. Restore rod to within alignment limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
C. Stop rod withdrawal until RPI indications are verified.
D. Manually insert all Bank A Control Rods to zero steps.
Page 70
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 71. Given the following:
The operating crew is performing AOI-31, "Abnormal Release of Radioactive Material," due to radiation being detected in the Turbine Building.
Turbine Building Station Sump is determined to have high radiation.
Station Sump pumps are realigned tothe unlined pond.
Efforts to determine the point of release and terminate are underway.
In accordance with AOI-31, which ONE of the following describes...
(1) why the station sumps will be operated locally, and (2) the position of the station sump pump handswitches if Radiological Protection determines the area must be evacuated?
A. (1) To prevent overflowing sump into the condenser waterbox area.
(2) Placed in off.
B. (1) To prevent overflowing sump into the condenser waterbox area.
(2) Placed in automatic.
C. (1) To prevent overflowing the Unlined Pond.
(2) Placed in off.
D. (1) To prevent overflowing the Unlined Pond.
(2) Placed in automatic.
Page 71 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 71. Given the following:
The operating crew is performing AOI-31, "Abnormal Release of Radioactive Material," due to radiation being detected in the Turbine Building.
Turbine Building Station Sump is determined to have high radiation.
Station Sump pumps are realigned to the unlined pond.
Efforts to determine the point of release and terminate are underway.
In accordance with AOI-31, which ONE of the following describes...
(1) why the station sumps will be operated locally, and (2) the position of the station sump pump handswitches if Radiological Protection determines the area must be evacuated?
A. (1) To prevent overflowing sump into the condenser waterbox area.
(2) Placed in off.
B. (1) To prevent overflowing sump into the condenser waterbox area.
(2) Placed in automatic.
C. (1) To prevent overflowing the Unlined Pond.
(2) Placed in off.
D. (1) To prevent overflowing the Unlined Pond.
(2) Placed in automatic.
Page 71
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 72. During accident conditions, which ONE of the following identifies the maximum dose an individual is allowed to receive to prevent damage to equipment needed for protection of the public?
A. 5 Rem B.
10 Rem C. 25 Rad D. 75 Rad Page 72 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 72. During accident conditions, which ONE of the following identifies the maximum dose an individual is allowed to receive to prevent damage to equipment needed for protection of the public?
A.
5 Rem B.
10 Rem C. 25 Rad D.
75 Rad Page 72
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 73. Given the following:
The operating crew is performing E-1, "Loss of Primary or Secondary Coolant."
The "Procedure Reader" directs the OAC to perform an action contained in a step of the procedure.
Which ONE of the following correctly describes the crew's "Peer Checking" and "Place Keeping" responsibilities related to performance of the step in accordance with OPDP-1, "Conduct of Operations?"
Peer Checking Place Keeping A. Required Initial the step when completed.
B. Required Use the "circle/slash" method.
C. Desired but Initial the step when completed.
not required D. Desired but Use the "circle/slash" method.
not required Page 73 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 73. Given the following:
The operating crew is performing E-1, "Loss of Primary or Secondary Coolant."
The "Procedure Reader" directs the OAC to perform an action contained in a step of the procedure.
Which ONE of the following correctly describes the crew's "Peer Checking" and "Place Keeping" responsibilities related to performance of the step in accordance with OPDP-1, "Conduct of Operations?"
Peer Checking Place Keeping A. Required Initial the step when completed.
B. Required Use the "circle/slash" method.
C. Desired but Initial the step when completed.
not required D. Desired but Use the "circle/slash" method.
not required Page 73
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 74. Given the following:
Unit 1 is responding to a LOCA.
The operators are performing E-1, "Loss of Reactor or Secondary Coolant,"
when the STA reports the following Critical Safety Functions (CSFs) status indications:
- 1. INVENTORY
- 2. CORE COOLING
- 3. CONTAINMENT
- 4. PRESSURIZED THERMAL SHOCK
- 5. HEAT SINK
- 6. SUBCRITICALITY Status Yellow Red Green Green Red Yellow Which ONE of the following is the correct order in which these CSFs shall be prioritized in regard to the challenge presented?
A.
5, 2, 6, 4, 3, 1 B. 2,5,6,1,4,3 C. 5,2,6,1,4,3 D. 2,5,6,4,3,1 Page 74 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 74. Given the following:
Unit 1 is responding to a LOCA.
The operators are performing E-1, "Loss of Reactor or Secondary Coolant,"
when the STA reports the following Critical Safety Functions (CSFs) status indications:
- 1. INVENTORY
- 2. CORE COOLING
- 3. CONTAINMENT
- 4. PRESSURIZED THERMAL SHOCK
- 5. HEAT SINK
- 6. SUBCRITICALITY Status Yellow Red Green Green Red Yellow Which ONE of the following is the correct order in which these CSFs shall be prioritized in regard to the challenge presented?
A. 5,2,6,4, 3, 1 B. 2,5,6,1,4,3 C. 5,2,6,1,4,3 D. 2,5,6,4,3,1 Page 74
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 75. Given the following:
A LOCA has occurred on Unit 1.
The operating crew is responding in accordance with the Emergency Procedures.
All Emergency Centers are staffed and operational.
The SED has just initiated Assembly and Accountability.
Which ONE of the following correctly identifies both...
(1) the Operator at the Controls' (OAC) responsibility when Assembly and Accountability is sounded, and (2) if someone calls x3911 to report a medical emergency after the OSC is staffed and operational, who will answer the phone?
A. (1) The OAC's badge must be swiped for Assembly and Accountability.
(2) x3911 calls will continue to be answered by the MCR staff.
B. (1) The OAC's badge must be swiped for Assembly and Accountability.
(2) x3911 calls will be directed to and answered by the OSC staff.
C. (1) The OAC will already be carded in for Assembly and Accountability due to being in the MCR.
(2) x3911 calls will continue to be answered by the MCR staff.
D. (1) The OAC will already be carded in for Assembly and Accountability due to being in the MCR.
(2) x3911 calls will be directed to and answered by the OSC staff.
Page 75 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 75. Given the following:
A LOCA has occurred on Unit 1.
The operating crew is responding in accordance with the Emergency Procedures.
All Emergency Centers are staffed and operational.
The SED has just initiated Assembly and Accountability.
Which ONE of the following correctly identifies both...
(1) the Operator at the Controls' (OAC) responsibility when Assembly and Accountability is sounded, and (2) if someone calls x3911 to report a medical emergency after the OSC is staffed and operational, who will answer the phone?
A. (1) The OAG's badge must be swiped for Assembly and Accountability.
(2) x3911 calls will continue to be answered by the MCR staff.
B. (1) The OAG's badge must be swiped for Assembly and Accountability.
(2) x3911 calls will be directed to and answered by the OSC staff.
C. (1) The OAC will already be carded in for Assembly and Accountability due to being in the MCR.
(2) x3911 calls will continue to be answered by the MCR staff.
D. (1) The OAC will already be carded in for Assembly and Accountability due to being in the MCR.
(2) x3911 calls will be directed to and answered by the OSC staff.
Page 75
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 76. Given the following:
Unit 1 at 100% power, steady state conditions.
MCR Controller for 1-HIC-62-89A, CHRG-HDR-RCP SEALS FLOW CONTROL, fails to "0" output.
Pressurizer level is increasing.
Which ONE of the following identifies how RCP seal injection flow will be.
affected and which AOI should receive priority for implementation?
RCP Seal Injection Flow A. Increase Procedure Implementation AOI-24, "RCP Malfunctions During Pump Operation" B. Increase AOI-20, "Malfunctions of the Pressurizer Level Control System" C. Decrease D. Decrease AOI-24, "RCP Malfunctions During Pump Operation" AOI-20, "Malfunctions of the Pressurizer Level Control System" Page 76 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 76. Given the following:
Unit 1 at 100% power, steady state conditions.
MCR Controller for 1-HIC-62-89A, CHRG-HDR-RCP SEALS FLOW CONTROL, fails to "0" output.
Pressurizer level is increasing.
Which ONE of the following identifies how RCP seal injection flow will be affected and which AOI should receive priority for implementation?
RCP Seal Injection Flow A. Increase Procedure Implementation AOI-24, "RCP Malfunctions During Pump Operation" B. Increase AOI-20, "Malfunctions of the Pressurizer Level Control System" C. Decrease D. Decrease AOI-24, "RCP Malfunctions During Pump Operation" AOI-20, "Malfunctions of the Pressurizer Level Control System" Page 76
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 77. Given the following:
Time 0500 -
Unit 1 was operating at 100% power when a turbine trip occurred.
The reactor did not trip automatically or manually.
0501 -
FR-S.1, "Nuclear Power Generation / ATWS," was entered.
0503 -
RCS pressure increased to 2715 psig.
0505 -
AUO opened both Reactor Trip Breakers and all rods fully inserted.
0506 -
RCS pressure stabilized at 2235 psig.
0509 -
Shift Manager (SM) determined the EAL had been met for a Site Area Emergency.
Which ONE of the following identifies...
(1) the action the SM will take in accordance with the REP, and (2) if the RCS Pressure Safety Limit was exceeded during the event?
(1 )
Condition A. Declare the Site Area Emergency.
B. Declare the Site Area Emergency.
C. Report that Site Area Emergency conditions had existed, but do NOT declare a Site Area Emergency.
D. Report that Site Area Emergency conditions had existed, but do NOT declare a Site Area Emergency.
(2)
Safety Limit Exceeded NOT exceeded Exceeded NOT exceeded Page 77 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 77. Given the following:
Time 0500 -
Unit 1 was operating at 100% power when a turbine trip occurred.
The reactor did not trip automatically or manually.
0501 -
FR-S.1, "Nuclear Power Generation / ATWS," was entered.
0503 -
RCS pressure increased to 2715 psig.
0505 -
AUO opened both Reactor Trip Breakers and all rods fully inserted.
0506 -
RCS pressure stabilized at 2235 psig.
0509 -
Shift Manager (SM) determined the EAL had been met for a Site Area Emergency.
Which ONE of the following identifies...
(1) the action the SM will take in accordance with the REP, and (2) if the RCS Pressure Safety Limit was exceeded during the event?
(1 )
Condition A. Declare the Site Area Emergency.
B. Declare the Site Area Emergency.
C. Report that Site Area Emergency conditions had existed, but do NOT declare a Site Area Emergency.
D. Report that Site Area Emergency conditions had existed, but do NOT declare a Site Area Emergency.
(2)
Safety Limit Exceeded NOT exceeded Exceeded NOT exceeded Page 77
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 78. Given the following plant conditions:
A tube rupture occurred on Unit 1 in Steam Generator #2.
The operating crew is performing E-3, "Steam Generator Tube Rupture."
After terminating safety injection, the operating crew observes the following conditions:
RCS pressure is lowering.
Pressurizer level is at 12% and continuing to lower.
Charging flow is at maximum.
Containment pressure, temperature, and radiation are rising.
The correct action for the Unit Supervisor is to direct the operating crew to:
A. Manually initiate Safety Injection and go to ES-O.O, Re-diagnosis.
B. Manually initiate Safety Injection and return to E-O, "Reactor Trip or Safety Injection."
C. Manually start ECCS pumps as necessary and transition to E-1, "Loss of Reactor or Secondary Coolant."
D. Manually start ECCS pumps as necessary and transition to ECA-3.1, "SGTR and LOCA - Subcooled Recovery."
Page 78 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 78. Given the following plant conditions:
A tube rupture occurred on Unit 1 in Steam Generator #2.
The operating crew is performing E-3, "Steam Generator Tube Rupture."
After terminating safety injection, the operating crew observes the following conditions:
RCS pressure is lowering.
Pressurizer level is at 12% and continuing to lower.
Charging flow is at maximum.
Containment pressure, temperature, and radiation are rising.
The correct action for the Unit Supervisor is to direct the operating crew to:
A. Manually initiate Safety Injection and go to ES-O.O, "Re-diagnosis."
B. Manually initiate Safety Injection and return to E-O, "Reactor Trip or Safety Injection."
C. Manually start ECCS pumps as necessary and transition to E-1, "Loss of Reactor or Secondary Coolant."
D. Manually start ECCS pumps as necessary and transition to ECA-3.1, "SGTR and LOCA - Subcooled Recovery."
Page 78
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 79. Given the following plant conditions:
Unit 1 is at 100% power.
Window 18-A, 125 DC VITAL CHGRIBATT I! ABNORMAL is LIT.
Battery Board I! Voltage indicates 130V DC and lowering.
Battery Charger I! DC Output Breaker is tripped open.
In accordance with Technical Specifications BASES, and based on the given plant conditions, which ONE of the following identifies...
(1) why the 125V DC Vital Battery Channell! is inoperable, and (2) how long the battery is designed to be able to maintain greater than the minimum terminal voltage for the current plant conditions?
A. (1) Battery voltage is less than required; (2) 30 minutes.
B. (1) Battery voltage is less than required; (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
C. (1) The battery board is not connected to a charger; (2) 30 minutes.
D. (1) The battery board is not connected to a charger; (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Page 79 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 79. Given the following plant conditions:
Unit 1 is at 100% power.
Window 18-A, 125 DC VITAL CHGRIBATT "ABNORMAL is LIT.
Battery Board" Voltage indicates 130V DC and lowering.
Battery Charger" DC Output Breaker is tripped open.
In accordance with Technical Specifications BASES, and based on the given plant conditions, which ONE of the following identifies...
(1) why the 125V DC Vital Battery Channel" is inoperable, and (2) how long the battery is designed to be able to maintain greater than the minimum terminal voltage for the current plant conditions?
A. (1) Battery voltage is less than required; (2) 30 minutes.
B. (1) Battery voltage is less than required; (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
C. (1) The battery board is not connected to a charger; (2) 30 minutes.
D. (1) The battery board is not connected to a charger; (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Page 79
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 80. Given the following plant conditions:
. Unit 1 is at 100% power.
Diesel Generator 1 B-B is operating and paralleled to the grid for a surveillance..
A switching error at the Hydro Unit causes a Loss of Offsite Power to '0' CSST.
The resulting grid disturbance causes the 6.9kV Shutdown Board 1 B-B Emergency Feeder Breaker 1914 to trip due to operation of its overcurrent (50) relay.
Which ONE of the following describes...
(1) the expected status of CCP 1 B-B and RHR pump 1 B-B 30 seconds after the
. event, and (2) the required Tech Spec completion time for restoring the offsite power supply?
(1 )
(2)
Pump Status Required Action Completion Time A. Only the CCP pump running 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. Both CCP and RHR pump running 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. Only the CCP pump running 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D. Both CCP and RHR pump running 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Page 80 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 80. Given the following plant conditions:
Unit 1 is at 100% power.
Diesel Generator 1 B-B is operating and paralleled to the grid for a surveillance.
A switching error at the Hydro Unit causes a Loss of Offsite Power to '0' CSST.
The resulting grid disturbance causes the 6.9kV Shutdown Board 1 B-B Emergency Feeder Breaker 1914 to trip due to operation of its overcurrent (50) relay.
Which ONE of the following describes...
(1) the expected status of CCP 1 B-B and RHR pump 1 B-B 30 seconds after the
- event, and (2) the required Tech Spec completion time for restoring the offsite power supply?
(1 )
(2)
Pump Status Required Action Completion Time A. Only the CCP pump running 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. Both CCP and RHR pump running 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. Only the CCP pump running 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D. Both CCP and RHR pump running 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Page 80
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 81. Given the following:
Unit 1 initially at 100% power.
A Reactor Trip/Safety Injection occurs.
The crew was performing E-1, "Loss of Reactor or Secondary Coolant,"
when a transition to FR-H.1, "Loss of Secondary Heat Sink" was required due to complications with AFW.
Upon entry into FR-H.1 the following conditions exist:
RCS pressure 950 psig and trending down All 4 SG pressures 1040 psig and trending down Containment Pressure 4.4 psid and stable All 4 SG WR levels 53% and trending down Max attainable AFW flow 360 gpm Reactor Coolant Pumps Stopped Which ONE of the following identifies...
(1) the Post Accident qualified instrumentation in the Main Control Room, and (2) the actions required by FR-H.1?
A. (1) Instrument will have a Black Label.
(2) Transition back to E-1.
B. (1) Instrument will have a Black Label.
(2) Continue FR-H.1 actions to restore feedwater.
C. (1) Instrument will have a White Label (2) Transition back to E-1.
D. (1) Instrument will have a White Label (2) Continue FR-H.1 actions to restore feedwater.
Page 81 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 81. Given the following:
Unit 1 initially at 100% power.
A Reactor Trip/Safety Injection occurs.
The crew was performing E-1, "Loss of Reactor or Secondary Coolant,"
when a transition to FR-H.1, "Loss of Secondary Heat Sink" was required due to complications with AFW.
Upon entry into FR-H.1 the following conditions exist:
RCS pressure 950 psig and trending down All 4 SG pressures 1040 psig and trending down Containment Pressure 4.4 psid and stable All 4 SG WR levels 53% and trending down Max attainable AFW flow 360 gpm Reactor Coolant Pumps Stopped Which ONE of the following identifies...
(1) the Post Accident qualified instrumentation in the Main Control Room, and (2) the actions required by FR-H.1?
A. (1) Instrument will have a Black Label.
(2) Transition back to E-1.
B. (1) Instrument will have a Black Label.
(2) Continue FR-H.1 actions to restore feedwater.
C. (1) Instrument will have a White Label (2) Transition back to E-1.
D. (1) Instrument will have a White Label (2) Continue FR-H.1 actions to restore feedwater.
Page 81
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 82. Given the following:
Unit 1 is at 3% reactor power being returned to service following a refueling outage.
Intermediate Range Monitor, NI-35, fails low.
Which ONE of the following is correct regarding:
(1) the actions required to comply with Tech Spec LCO 3.3.1 "RTS Instrumentation, "
and (2) the reason why?
A. (1) Reduce power to less than P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 can NOT be entered.
- 8. (1) Raise power to greater than 10% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 CAN be entered.
C. (1) Place NI-35 HIGH LEVEL TRIP bistable in the trip position and reduce power to less than P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 can NOT be entered.
D. (1) Place NI-35 HIGH LEVEL TRIP bistable in the trip position and raise power to greater than 10% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 CAN be entered.
Page 82 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 82. Given the following:
Unit 1 is at 3% reactor power being returned to service following a refueling outage.
Intermediate Range Monitor, NI-35, fails low.
Which ONE of the following is correct regarding:
(1) the actions required to comply with Tech Spec LCO 3.3.1 "RTS Instrumentation,"
and (2) the reason why?
A. (1) Reduce power to less than P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 can NOT be entered.
B. (1) Raise power to greater than 10% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 CAN be entered.
C. (1) Place NI-35 HIGH LEVEL TRIP bistable in the trip position and reduce power to less than P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 can NOT be entered.
D. (1) Place NI-35 HIGH LEVEL TRIP bistable in the trip position and raise power to greater than 10% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(2) Because Mode 1 CAN be entered.
Page 82
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 83. Given the following:
Unit 1 was operating at 100% power.
A fire developed in the EI 713' pipe chase near the BIT.
The electrical cables for BIT outlet valves 1-FCV 63-25 and 1-FCV-63-26 have been severely damaged.
The Shift Manager declared an Appendix R fire and the crew entered AOI-30.2, "Fire Safe Shutdown."
The operating crew determined the fire area to be A28 and are now performing AOI-30.2 C.59, "Fire Safe Shutdown Room 676-A1, 676-A16, 692-A8, 713-A28."
Which ONE of the following identifies..
(1) the action required forthe unit, and (2) the operational consequence of the BIT outlet valves being damaged due to the fire?
A. (1) Trip the reactor and continue in AOI-30.2 C.59.
(2) Requires reopening the charging flow isolation valves to establish high pressure injection if safety injection was actuated.
B. (1) Trip the reactor and continue in AOI-30.2 C.59.
(2) No consequence because the BIT outlet valves are required to remain closed during an Appendix R fire.
C. (1) Trip the reactor and go to E-O, "Reactor Trip or Safety Injection."
(2) Requires reopening the charging flow isolation valves to establish high pressure injection if safety injection was actuated.
D. (1) Trip the reactor and go to E-O, "Reactor Trip or Safety Injection."
(2) No consequence because the BIT outlet valves are required to remain closed during an Appendix R fire.
Page 83 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 83. Given the following:
Unit 1 was operating at 100% power.
A fire developed in the EI 713' pipe chase near the BIT.
The electrical cables for BIT outlet valves 1-FCV 63-25 and 1-FCV-63-26 have been severely damaged.
The Shift Manager declared an Appendix R fire and the crew entered AOI-30.2, "Fire Safe Shutdown."
The operating crew determined the fire area to be A28 and are now performing AOI-30.2 C.59, "Fire Safe Shutdown Room 676-A 1, 676-A 16, 692-A8, 713-A28."
Which ONE of the following identifies..
(1) the action required for the unit, and (2) the operational consequence of the BIT outlet valves being damaged due to the fire?
A. (1) Trip the reactor and continue in AOI-30.2 C.59.
(2) Requires reopening the charging flow isolation valves to establish high pressure injection if safety injection was actuated.
B. (1) Trip the reactor and continue in AOI-30.2 C.59.
(2) No consequence because the BIT outlet valves are required to remain closed during an Appendix R fire.
C. (1) Trip the reactor and go to E-O, "Reactor Trip or Safety Injection."
(2) Requires reopening the charging flow isolation valves to establish high pressure injection if safety injection was actuated.
D. (1) Trip the reactor and go to E-O, "Reactor Trip or Safety Injection."
(2) No consequence because the BIT outlet valves are required to remain closed during an Appendix R fire.
Page 83
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 84. Given the following conditions:
A LOCA is in progress with all RCPs stopped.
The crew is performing E-1, "Loss of Reactor or Secondary Coolant."
The STA reports the following:
Core exit TCs:
734°F RCS Pressure:
1385 psig RVLlS:
50%
Which ONE of the following describes the procedure required to be entered and the restrictions on starting the RCPs during the performance of the procedure?
Procedure RCP start restrictions A. FR-C.2, "Response to Even with support equipment available Degraded Core Cooling" an RCP would NOT be started.
B. FR-C.2, "Response to RCP would be started without all Degraded Core Cooling" normal support conditions available.
C. FR-C.1 "Response to RCP would NOT be started without Inadequate Core Cooling" support equipment available.
D. FR-C.1 "Response to RCP would be started without all support Inadequate Core Cooling" conditions available.
Page 84 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 84. Given the following conditions:
A LOCA is in progress with all RCPs stopped.
The crew is performing E-1, "Loss of Reactor or Secondary Coolant."
The STA reports the following:
Core exit TCs:
734°F RCS Pressure:
1385 psig RVLlS:
50%
Which ONE of the following describes the procedure required to be entered and the restrictions on starting the RCPs during the performance of the procedure?
Procedure RCP start restrictions A. FR-C.2, "Response to Even with support equipment available Degraded Core Cooling" an RCP would NOT be started.
B. FR-C.2, "Response to RCP would be started without all Degraded Core Cooling" normal support conditions available.
C. FR-C.1 "Response to RCP would NOT be started without Inadequate Core Cooling" support equipment available.
D. FR-C.1 "Response to RCP would be started without all support Inadequate Core Cooling" conditions available.
Page 84
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 85. Given th~ following plant conditions:
A reactor trip occurred on Unit 1.
The crew was performing ES-0.1, "Reactor Trip Response," when a loss of off-site power occurred.
A transition is made to ES-0.2, "Natural Circulation Cooldown," to cool down the plant.
Which ONE of the following identifies...
(1) a reason the crew would transition to ES-0.3, " Natural Circulation Cooldown with Steam Void In Vessel (with RVLlS)."
and (2) why RVLlS is maintained greater than 69% during performance of ES-0.3?
A. (1) RCS subcooling drops to less than 65°F.
(2) To prevent loss of natural circulation due to steam voiding in the SG tubes.
B. (1) RCS subcooling drops to less than 65°F.
(2) To ensure pressurizer level is adequate to accommodate void collapse.
C. (1) Plant conditions require a cooldown rate faster than allowed by ES-0.2.
(2) To prevent loss of natural circulation due to steam voiding in the SG tubes.
D. (1) Plant conditions require a cooldown rate faster than allowed by ES-0.2.
(2) To ensure pressurizer level is adequate to accommodate void collapse.
Page 85 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 85. Given the following plant conditions:
A reactor trip occurred on Unit 1.
The crew was performing ES-0.1, "Reactor Trip Response," when a loss of off-site power occurred.
A transition is made to ES-0.2, "Natural Circulation Cooldown," to cool down the plant.
Which ONE of the following identifies...
(1) a reason the crew would transition to ES-0.3, " Natural Circulation Cooldown with Steam Void In Vessel (with RVLlS)."
and (2) why RVLlS is maintained greater than 69% during performance of ES-0.3?
A. (1) RCS subcooling drops to less than 65°F.
(2) To prevent loss of natural circulation due to steam voiding in the SG tubes.
B. (1) RCS subcooling drops to less than 65°F.
(2) To ensure pressurizer level is adequate to accommodate void collapse.
C. (1) Plant conditions require a cooldown rate faster than allowed by ES-0.2.
(2) To prevent loss of natural circulation due to steam voiding in the SG tubes.
D. (1) Plant conditions require a cooldown rate faster than allowed by ES-0.2.
(2) To ensure pressurizer level is adequate to accommodate void collapse.
Page 85
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 86. Given the following plant conditions:
Unit 1 is being cooled down for a refueling outage.
All RCPs were required to be removed from service.
All 4 SG levels are at 38% NR.
The RCS is 220°F with RHR Train A in service.
Component Cooling Water (CCS) pump 1 A-A trips due to motor failure.
The crew is performing actions of AOI-15, "Loss of Component Cooling Water."
Based on the current plant conditions, which ONE of the following identifies the applicability of the listed LCOs and the reason, as identified in the Technical Specification Bases...
(1) LCO 3.7.7, "Component Cooling System" (2) LCO 3.4.6, "RCS Loops - Mode 4?"
A. (1) LCO 3.7.7 is required to be entered until Mode 5 is reached.
(2) LCO 3.4.6 entry NOT required due to the loss of a support system as provided for by LCO 3.0.6.
B. (1) LCO 3.7.7 is required to be entered until Mode 5 is reached.
(2) LCO 3.4.6 is required to be entered due to the loss of a support system and the provisions of LCO 3.0.6 can NOT be used.
C. (1) LCO 3.7.7 entry NOT required because the plant is in Mode 4.
(2) LCO 3.4.6 entry NOT required due to the loss of a support system as provided for by LCO 3.0.6.
D. (1) LCO 3.7.7 entry NOT required because the plant is in Mode 4.
(2) LCO 3.4.6 is required to be entered due to the loss of a support system and the provisions of LCO 3.0.6 can NOT be used.
Page 86 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 86. Given the following plant conditions:
Unit 1 is being cooled down for a refueling outage.
All RCPs were required to be removed from service.
All 4 SG levels are at 38% NR.
The RCS is 220°F with RHR Train A in service.
Component Cooling Water (CCS) pump 1 A-A trips due to motor failure.
The crew is performing actions of AOI-15, "Loss of Component Cooling Water."
Based on the current plant conditions, which ONE of the following identifies the applicability of the listed LCOs and the reason, as identified in the Technical Specification Bases...
(1) LCD 3.7.7, "Component Cooling System" (2) LCD 3.4.6, "RCS Loops - Mode 4?"
A. (1) LCD 3.7.7 is required to be entered until Mode 5 is reached.
(2) LCD 3.4.6 entry NOT required due to the loss of a support system as provided for by LCD 3.0.6.
B. (1) LCD 3.7.7 is required to be entered until Mode 5 is reached.
(2) LCD 3.4.6 is required to be entered due to the loss of a support system and the provisions of LCD 3.0.6 can NOT be used.
C. (1) LCD 3.7.7 entry NOT required because the plant is in Mode 4.
(2) LCD 3.4.6 entry NOT required due to the loss of a support system as provided for by LCD 3.0.6.
D. (1) LCD 3.7.7 entry NOT required because the plant is in Mode 4.
(2) LCD 3.4.6 is required to be entered due to the loss of a support system and the provisions of LCD 3.0.6 can NOT be used.
Page 86
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 87. Given the following:
Unit 1 in Mode 3 with the RCS at normal operating temperature and pressure with the following conditions:
Loop #2 Pressurizer spray valve unable to be opened.
RCP #4 out of service.
A Safety injection occurs due to a Steam Generator #3 tube rupture.
The operating crew is ready to initiate RCS depressurization following the Rapid cooldown in accordance with E-3, "Steam Generator Tube Rupture."
Which ONE of the following identifies...
(1) a condition that would result in the pressurizer sprays being ineffective in depressurizing the RCS, and (2) the action required to accomplish the RCS depressurization as a result of the normal spray valves being ineffective?
(1 )
Condition A. Trip of the RCP #2 B. Trip of the RCP #2 C. Loss of 120v Vital Instrument Power Board 1-1 D. Loss of 120v Vital Instrument Power Board 1-1 (2)
Action required to depressurize the RCS Use a pressurizer PORV in accordance with E-3.
Transition to ECA-3.3, "SGTR without PZR Pressure Control" to allow use of auxiliary sprays.
Use a pressurizer PORV in accordance with E-3.
Transition to ECA-3.3, "SGTR without PZR Pressure Control" to allow use of auxiliary sprays.
Page 87 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 87. Given the following:
Unit 1 in Mode 3 with the RCS at normal operating temperature and pressure with the following conditions:
Loop #2 Pressurizer spray valve unable to be opened.
RCP #4 out of service.
A Safety injection occurs due to a Steam Generator #3 tube rupture.
The operating crew is ready to initiate RCS depressurization following the Rapid cooldown in accordance with E-3, "Steam Generator Tube Rupture."
Which ONE of the following identifies...
(1) a condition that would result in the pressurizer sprays being ineffective in depressurizing the RCS, and (2) the action required to accomplish the RCS depressurization as a result of the normal spray valves being ineffective?
(1 )
Condition A. Trip of the RCP #2 B. Trip of the RCP #2 C. Loss of 120v Vital Instrument Power Board 1-1 D. Loss of 120v Vital Instrument Power Board 1-1 (2)
Action required to depressurize the RCS Use a pressurizer PORV in accordance with E-3.
Transition to ECA-3.3, "SGTR without PZR Pressure Control" to allow use of auxiliary sprays.
Use a pressurizer PORV in accordance with E-3.
Transition to ECA-3.3, "SGTR without PZR Pressure Control" to allow use of auxiliary sprays.
Page 87
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 88. Given the following:
Unit 1 at 100% power.
Containment Pressure Transmitter "1-PDT-30-43" (Channel III) failed and is out of service with the channel bistables positioned as required by Technical Specifications.
The Surveillance Instruction for "1-PDT-30-44" (Channel II) is now due.
Which ONE of the following describes the required action for performing the Surveillance Instruction on "1-PDT-30-44," and what is the impact on Containment Spray actuation?
A. "1-PDT-30-43" is required to be placed in the TRIPPED position; subsequent testing of "1-PDT-30-44" will still allow a valid automatic Containment Spray actuation to occur.
B. "1-PDT-30-43" is required to be placed in the TRIPPED position; subsequent testing of "1-PDT-30-44" will prevent a valid automatic Containment Spray actuation from occurring.
C. "1-PDT-30-43" is required to be placed in the BYPASS position; subsequent testing of "1-PDT-30-44" will still allow a valid automatic Containment Spray actuation to occur.
D. "1-PDT-30-43" is required to be placed in the BYPASS position; subsequent testing of "1-PDT-30-44" will prevent a valid automatic Containment Spray actuation from occurring.
Page 88 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 88. Given the following:
Unit 1 at 100% power.
Containment Pressure Transmitter "1-PDT-30-43" (Channel III) failed and is out of service with the channel bistables positioned as required by Technical Specifications.
The Surveillance Instruction for "1-PDT-30-44" (Channel II) is now due.
Which ONE of the following describes the required action for performing the Surveillance Instruction on "1-PDT-30-44," and what is the impact on Containment Spray actuation?
A. "1-PDT-30-43" is required to be placed in the TRIPPED position; subsequent testing of "1-PDT-30-44" will still allow a valid automatic Containment Spray actuation to occur.
B. "1-PDT-30-43" is required to be placed in the TRIPPED position; subsequent testing of "1-PDT-30-44" will prevent a valid automatic Containment Spray actuation from occurring.
C. "1-PDT-30-43" is required to be placed in the BYPASS position; subsequent testing of "1-PDT-30-44" will still allow a valid automatic Containment Spray actuation to occur.
D. "1-PDT-30-43" is required to be placed in the BYPASS position; subsequent testing of "1-PDT-30-44" will prevent a valid automatic Containment Spray actuation from occurring.
Page 88
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 89. Given the following plant conditions:
A loss of power has occurred to 125V DC Vital Battery Bd I.
Operators are in the process of stopping 1 8-B, 2A-A and 28-B DGs and placing in standby.
The SRO has dispatched the AUOs to perform the applicable portion of SOI-82 for each DG.
All 43TL switches have been placed in the "TEST" position in accordance with the SOls.
Power to 125V DC Vital Battery Bd I has NOT been restored.
Which ONE of the following describes the direction the SRO will give the AUO with regard to the position of each logic panel 43TL switch?
A. Place ALL 43TL switches in "NORMAL" when directed by the SOL B. Place 43TL switches for 1 B-B, 2A-A and 2B-B in "NORMAL" and leave the 1 A-A 43TL switch in "TEST" until the board is reenergized.
C. Leave ALL 43TL switches in "TEST" until the board is reenergized.
D. Leave 43TL switches for 1 B-8, 2A-A and 2B-8 in "TEST" until the board is reenergized and then place the 1 A-A 43TL switch in "NORMAL."
Page 89 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 89. Given the following plant conditions:
A loss of power has occurred to 125V DC Vital Battery Bd I.
Operators are in the process of stopping 1 8-B, 2A-A and 2B-B DGs and placing in standby.
The SRO has dispatched the AUOs to perform the applicable portion of SOI-82 for each DG.
All 43TL switches have been placed in the "TEST" position in accordance with the SOls.
Power to 125V DC Vital Battery Bd I has NOT been restored.
Which ONE of the following describes the direction the SRO will give the AUO with regard to the position of each logic panel 43TL switch?
A. Place ALL 43TL switches in "NORMAL" when directed by the SOL B. Place 43TL switches for 1 8-B, 2A-A and 2B-B in "NORMAL" and leave the 1 A-A 43TL switch in "TEST" until the board is reenergized.
C. Leave ALL 43TL switches in "TEST" until the board is reenergized.
D. Leave 43TL switches for 1 B-8, 2A-A and 2B-B in "TEST" until the board is reenergized and then place the 1 A-A 43TL switch in "NORMAL."
Page 89
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 90. Given the following:
Unit 1 is at 100% power.
An inadvertant Phase A Isolation occurs and cannot immediately be reset.
Which ONE of the following procedures would first be used to mitigate the consequences for the above conditions?
A. AOI-20, "Loss of Pressurizer Level Control."
B. E-O, "Reactor Trip and Safety Injection."
C. AOI-24, "RCP Malfunctions During Pump Operation."
D. AOI-18, "Loss of Pressurizer Pressure Control."
Page 90 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 90. Given the following:
Unit 1 is at 100% power.
An inadvertant Phase A Isolation occurs and cannot immediately be reset.
Which ONE of the following procedures would first be used to mitigate the consequences for the above conditions?
A. AOI-20, "Loss of Pressurizer Level Control."
B. E-O, "Reactor Trip and Safety Injection."
C. AOI-24, "RCP Malfunctions During Pump Operation."
D. AOI-18, "Loss of Pressurizer Pressure Control."
Page 90
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 91. Unit 1 is at 100% power with the following conditions:
Auxiliary Building Gas Treatment System (ABGTS) Train A is unavailable.
Hydrogen Recombiner A is unavailable.
1-FCV-68-332, Block valve for PORV 334, is closed due to the PORV leaking through.
A LOCA occurs and the operating crew is in the process of placing Hydrogen Recombiner B in service.
Containment pressure is 4.5 psig.
Which ONE of the following identifies...
(1) the Large Early Release Frequency (LERF) radiological risk level that existed before the LOCA occurred, in accordance with TI-124, "Equipment To Plant Risk Matrix,"
and (2) the required power level that would be established on Hydrogen Recombiner B when it is placed in service?
REFERENCE PROVIDED LERF risk Recombiner Power Level A.
Yellow 63kW B.
Yellow 72 kW C.
Orange 72 kW D.
Orange 63 kW Page 91 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 91. Unit 1 is at 100% power with the following conditions:
Auxiliary Building Gas Treatment System (ABGTS) Train A is unavailable.
Hydrogen Recombiner A is unavailable.
1-FCV-68-332, Block valve for PORV 334, is closed due to the PORV leaking through.
A LOCA occurs and the operating crew is in the process of placing Hydrogen Recombiner B in service.
Containment pressure is 4.5 psig.
Which ONE of the following identifies...
(1) the Large Early Release Frequency (LERF) radiological risk level that existed before the LOCA occurred, in accordance with TI-124, "Equipment To Plant Risk Matrix,"
and (2) the required power level that would be established on Hydrogen Recombiner B when it is placed in service?
REFERENCE PROVIDED LERF risk Recombiner Power Level A.
Yellow 63 kW B.
Yellow 72 kW C.
Orange 72 kW D.
Orange 63 kW Page 91
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 92. Given the following plant conditions:
A planned release of the Monitor Tank is in progress.
181-A, "WDS RELEASE LINE O-RM-122 LlQ RAD HI" alarms (valid).
0-RCV-77-43, "CT BLDN LN RAD RELEASE CNTL," remains OPEN.
Which ONE of the following identifies...
(1) how the Liquid Radwaste System will respond if there was no operator
- action, and (2) if the operators did respond by closing 0-RCV-77-43, can the same release package be used to continue the release following repair of the valve?
A. (1) The entire contents ofthe Monitor Tank will be released.
(2) No, a new release package would be required.
B. (1) The entire contents of the Monitor Tank will be released.
(2) Yes, the same release package is still applicable.
C. (1) Release will continue until the Monitor Tank level lowers to approximately 10%.
(2) No, a new release package would be required.
D. (1) Release will continue until the Monitor Tank level lowers to approximately 10%.
(2) Yes, the same release package is still applicable.
Page 92 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 92. Given the following plant conditions:
A planned release of the Monitor Tank is in progress.
181-A, "WDS RELEASE LINE O-RM-122 LlQ RAD HI" alarms (valid).
0-RCV-77-43, "CT BLDN LN RAD RELEASE CNTL," remains OPEN.
Which ONE of the following identifies...
(1) how the Liquid Radwaste System will respond if there was no operator
- action, and (2) if the operators did respond by closing 0-RCV-77-43, can the same release package be used to continue the release following repair of the valve?
A. (1) The entire contents of the Monitor Tank will be released.
(2) No, a new release package would be required.
B. (1) The entire contents of the Monitor Tank will be released.
(2) Yes, the same release package is still applicable.
C. (1) Release will continue until the Monitor Tank level lowers to approximately 10%.
(2) No, a new release package would be required.
D. (1) Release will continue until the Monitor Tank level lowers to approximately 10%.
(2) Yes, the same release package is still applicable.
Page 92
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 93. Given the following Unit 1 at 100% power.
A release of the Waste Gas Decay Tank 'c' in progress.
The following conditions occur:
RCS pressure and Pressurizer level dropping.
167-0, TURB/AUXlRX BLDG FLOODED alarms.
113-B, RHR 1 CVCS HI TEMP PIPE BREAK alarms.
0-RM-90-1 01, Auxiliary Building Stack, alarms on Hi Rad.
1-RM-90-400, Shield Building Stack, alarms on Hi Rad.
Area monitor recorder 1-RR-90-1 indicates radiation increasing in the Auxiliary Building.
0-RM-90-118, Waste Gas Rad Monitor, is steady.
The operating crew manually trips the reactor, initiates Safety Injection, and enters E-O, "Reactor Trip or Safety Injection."
Which ONE of the following identifies...
(1) the status of the Waste Gas release and (2) the procedure, when implemented, will check the status of the Waste Gas release?
A. (1) The release has automatically terminated.
(2) ECA-1.2, "LOCA Outside Containment," ensures that the release has terminated.
B. (1) The release has automatically terminated.
(2) AOI-31, "Abnormal Release of Radioactivity," ensures that the release has terminated.
C. (1) The release continues until manually terminated.
(2) ECA-1.2, "LOCA Outside Containment," contains actions directing release termination.
D. (1) The release continues until manually terminated.
- 2) AOI-31, "Abnormal Release of Radioactivity," contains actions directing release termination.
Page 93 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 93. Given the following Unit 1 at 100% power.
A release of the Waste Gas Decay Tank 'c' in progress.
The following conditions occur:
RCS pressure and Pressurizer level dropping.
167-0, TURB/AUXlRX BLDG FLOODED alarms.
113-B, RHR 1 CVCS HI TEMP PIPE BREAK alarms.
0-RM-90-1 01, Auxiliary Building Stack, alarms on Hi Rad.
1-RM-90-400, Shield Building Stack, alarms on Hi Rad.
Area monitor recorder 1-RR-90-1 indicates radiation increasing in the Auxiliary Building.
0-RM-90-118, Waste Gas Rad Monitor, is steady.
The operating crew manually trips the reactor, initiates Safety Injection, and enters E-O, "Reactor Trip or Safety Injection."
Which ONE of the following identifies...
(1) the status of the Waste Gas release and (2) the procedure, when implemented, will check the status of the Waste Gas release?
A. (1) The release has automatically terminated.
(2) ECA-1.2, "LOCA Outside Containment," ensures that the release has terminated.
B. (1) The release has automatically terminated.
(2) AOI-31, "Abnormal Release of Radioactivity," ensures that the release has terminated.
C. (1) The release continues until manually terminated.
(2) ECA-1.2, "LOCA Outside Containment," contains actions directing release termination.
D. (1) The release continues until manually terminated.
- 2) AOI-31, "Abnormal Release of Radioactivity," contains actions directing release termination.
Page 93
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 94. Given the following plant conditions:
Unit is in Mode 6.
The Containment Equipment Hatch is held closed by 4 bolts.
Upper Containment Air Lock inner and outer doors are open.
50 fuel assemblies have been reloaded.
RHR Train A is in service with RCS temperature at 103°F.
RHR Train A loop boron concentration: 2950 ppm.
Source Range N-131 indicates 10 cps.
Source Range N-132 indicates 8 cps.
In accordance with FHI-7, "Fuel Handling and Movement," which ONE of the following conditions would require fuel movement to be stopped?
A. Source Range N-131 and N-132 rise to 22 cps and 14 cps, respectively.
B. Updated log reading on RHR Train A inlet temperature indicates 111°F.
C. Auxiliary Building Gas Treatment (ABGTS) Train A is declared inoperable.
D. Updated RHR Train A boron concentrations on two consecutive samples indicate 2935 ppm.
Page 94 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 94. Given the following plant conditions:
Unit is in Mode 6.
The Containment Equipment Hatch is held closed by 4 bolts.
Upper Containment Air Lock inner and outer doors are open.
50 fuel assemblies have been reloaded.
RHR Train A is in service with RCS temperature at 103°F.
RHR Train A loop boron concentration: 2950 ppm.
Source Range N-131 indicates 10 cps.
Source Range N-132 indicates 8 cps.
In accordance with FHI-7, "Fuel Handling and Movement," which ONE of the following conditions would require fuel movement to be stopped?
A. Source Range N-131 and N-132 rise to 22 cps and 14 cps, respectively.
B. Updated log reading on RHR Train A inlet temperature indicates 111°F.
C. Auxiliary Building Gas Treatment (ABGTS) Train A is declared inoperable.
D. Updated RHR Train A boron concentrations on two consecutive samples indicate 2935 ppm.
Page 94
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 95. Unit 1 is at 100% power when the following occurs:
Monday at 0700 - RHR pump 1 B-B is tagged for a scheduled 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> component outage.
Tuesdayat 0300 - CCP 1 A-A tripped and is damaged.
CCP 1 B-B is started and the plant stabilized.
Tuesday at 1900 - RHR pump 1 B-B is restored to service.
Which ONE of the following identifies the latest time the plant is required to be in Mode 3 in accordance with Technical Specifications requirements?
A. Tuesday at 0900.
B. Tuesday at 1000.
C. Friday at 0900.
D. Friday at 1300.
Page 95 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 95. Unit 1 is at 100% power when the following occurs:
Monday at 0700 - RHR pump 1 B-B is tagged for a scheduled 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> component outage.
Tuesdayat 0300 - CCP 1 A-A tripped and is damaged.
CCP 1 B-B is started and the plant stabilized.
Tuesday at 1900 - RHR pump 1 B-B is restored to service.
Which ONE of the following identifies the latest time the plant is required to be in Mode 3 in accordance with Technical Specifications requirements?
A. Tuesday at 0900.
B. Tuesday at 1000.
C. Friday at 0900.
D. Friday at 1300.
Page 95
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 96. Given the following plant conditions; Unit 1 is at 100% power.
131-A, "CL ACCUM 1 LEVEL HI/LO" alarms.
The following unexpected changes have occurred on CLA #1 since the last shift:
Level increased from 7880 gallons to 7975 gallons.
Pressure increased from 645 psig to 650 psig.
Which ONE of the following identifies...
(1) the Technical Specification (TS) requirement for verifying the Cold Leg Accumulator boron concentration is within limits, and (2) how many CLAs are required for adequate core injection in accordance with 10 CFR 50.46 acceptance criteria during the blowdown phase of a LOCA?
TS Boron Requirement CLAs Required to meet 1 OCFR 50.46 A. Verify within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2 CLAs B. Verify within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
3 CLAs C. Verify within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
2CLAs D. Verify within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3 CLAs Page 96 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 96. Given the following plant conditions; Unit 1 is at 100% power.
131-A, "CL ACCUM 1 LEVEL HI/LO" alarms.
The following unexpected changes have occurred on CLA #1 since the last shift:
Level increased from 7880 gallons to 7975 gallons.
Pressure increased from 645 psig to 650 psig.
Which ONE of the following identifies...
(1) the Technical Specification (TS) requirement for verifying the Cold Leg Accumulator boron concentration is within limits, and (2) how many CLAs are required for adequate core injection in accordance with 10 CFR 50.46 acceptance criteria during the blowdown phase of a LOCA?
TS Boron Requirement CLAs Required to meet 1 OCFR 50.46 A. Verify within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2 CLAs B. Verify within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
3CLAs C. Verify within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
2 CLAs D. Verify within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3CLAs Page 96
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 97. Given the following:
Unit 1 is at 100% power.
The Monitor Tank is to be released.
Which ONE of the following identifies...
(1) how O-RM-90-122, "Liquid Radwaste Effluent Line," being inoperable would affect the planned release, and (2) the permit requirements to restart the release if it isolated due to low Cooling Tower Blowdown (CTBD) flow?
0-RM-90-122 inoperable A. 2 independent samples required.
B. 2 independent samples required.
C. ONLY 1 sample required.
D. ONLY 1 sample required.
Low CTBD flow Release can not be restarted until a new release permit generated after it is isolated due to low CTBD flow.
Release can be continued if restarted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with existing release permit.
Release can not be restarted until a new release permit generated after it is isolated due to low CTBD flow.
Release can be continued if restarted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with existing release permit.
Page 97 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 97. Given the following:
Unit 1 is at 100% power.
The Monitor Tank is to be released.
Which ONE of the following identifies...
(1) how 0-RM-90-122, "Liquid Radwaste Effluent Line," being inoperable would affect the planned release, and (2) the permit requirements to restart the release if it isolated due to low Cooling Tower Blowdown (CTBD) flow?
0-RM-90-122 inoperable A. 2 independent samples required.
B. 2 independent samples required.
C. ONLY 1 sample required.
D. ONLY 1 sample required.
Low CTBD flow Release can not be restarted until a new release permit generated after it is isolated due to low CTBD flow.
Release can be continued if restarted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with existing release permit.
Release can not be restarted until a new release permit generated after it is isolated due to low CTBD flow.
Helease can be continued if restarted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with existing release permit.
Page 97
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 98. Given the following plant conditions:
The plant is in a refueling outage.
Irradiated fuel and control rod movements are in progress in the Spent Fuel Pit.
An inspection requiring a diving operation in the Spent Fuel Pit is planned to commence later in the shift.
Due to the potential for high radiation dose, the Radiation Work Permit (RWP) has been written as an entry into a Very High Radiation Area (VHRA).
Which ONE of the following describes:
(1) who, in addition to the Radiation Protection Manager, must authorize the RWP for the dive, and (2) what restriction applies to irradiated fuel and control rod movements in the Spent Fuel Pit, in accordance with RCI-100, "Control of Radiological Work," and RCI-153, "Radiation Work Permits?"
RWP Authorization A. Shift Manager AND Plant Manager
- 8. Shift Manager ONLY C. Shift Manager AND Plant Manager D. Shift Manager ONLY SFP Fuel and "Fuel Insert" Movement Irradiated fuel and "fuel insert" movement stopped no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive.
Irradiated fuel and "fuel insert" movement stopped no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive.
Fuel movements must STOP no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive. "Fuel insert" movement may continue up to the time of the dive.
Fuel movements must STOP no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive. "Fuel insert" movement may continue up to the time of the dive.
Page 98 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 98. Given the following plant conditions:
The plant is in a refueling outage.
Irradiated fuel and control rod movements are in progress in the Spent Fuel Pit.
An inspection requiring a diving operation in the Spent Fuel Pit is planned to commence later in the shift.
Due to the potential for high radiation dose, the Radiation Work Permit (RWP) has been written as an entry into a Very High Radiation Area (VHRA).
Which ONE of the following describes:
(1) who, in addition to the Radiation Protection Manager, must authorize the RWP for the dive, and (2) what restriction applies to irradiated fuel and control rod movements in the Spent Fuel Pit, in accordance with RCI-100, "Control of Radiological Work," and RCI-153, "Radiation Work Permits?"
RWP Authorization A. Shift Manager AND Plant Manager B. Shift Manager ONLY C. Shift Manager AND Plant Manager D. Shift Manager ONLY SFP Fuel and "Fuel Insert" Movement Irradiated fuel and "fuel insert" movement stopped no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive.
Irradiated fuel and "fuel insert" movement stopped no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive.
Fuel movements must STOP no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive. "Fuel insert" movement may continue up to the time of the dive.
Fuel movements must STOP no later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the dive. "Fuel insert" movement may continue up to the time of the dive.
Page 98
11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 99. Given the following Unit 1 plant conditions:
ECA-O.O, "Loss of All AC Power" is in effect.
Depressurization of ALL intact SGs at the "maximum rate" is in progress.
Which ONE of the following identifies...
(1) the parameter used to limit the "maximum rate" of depressurization and its bases and (2) a parameter used to determine which recovery procedure will be implemented upon exiting ECA-O.O?
A. (1) Maintain pressurizer level above 15% to prevent reactor vessel head voiding.
(2) RCS pressure trend.
B. (1) Maintain pressurizer level above 15% to prevent reactor vessel head voiding.
(2) RCS Subcooling value.
C. (1) Maintain at least one SG narrow range level above 29% to prevent loss of sufficient heat transfer capability from the RCS.
(2) RCS pressure trend.
D. (1) Maintain at least one SG narrow range level above 29% to prevent loss of sufficient heat transfer capability from the RCS.
(2) RCS Subcooling value.
Page 99 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
- 99. Given the following Unit 1 plant conditions:
ECA-O.O, "Loss of All AC Power" is in effect.
Depressurization of ALL intact SGs at the "maximum rate" is in progress.
Which ONE of the following identifies...
(1) the parameter used to limit the "maximum rate" of depressurization and its bases and (2) a parameter used to determine which recovery procedure will be implemented upon exiting ECA-O.O?
A. (1) Maintain pressurizer level above 15% to prevent reactor vessel head voiding.
(2) RCS pressure trend.
B. (1) Maintain pressurizer level above 15% to prevent reactor vessel head voiding.
(2) RCS Subcooling value.
C. (1) Maintain at least one SG narrow range level above 29% to prevent loss of sufficient heat transfer capability from the RCS.
(2) RCS pressure trend.
D. (1) Maintain at least one SG narrow range level above 29% to prevent loss of sufficient heat transfer capability from the RCS.
(2) RCS Subcooling value.
Page 99
11/2009 Watts Bar SRO NRC License Exam 12/17/2009 100. For the listed instrumentation, which one of the following describes whether it is:
(1) required by LCO 3.3.3, "PAM Instrumentation,"
and (2) included in EPIP-1, "Emergency Plan Classification Flowchart," as an indication for determining EALs?
Instrumentation LeO 3.3.3 A. Aux. Bldg. Passive Sump Level YES (0-LS-40-21 B)
B. Aux. Bldg. Passive Sump Level NO (0-LS-40-21 B)
C. Condenser Vacuum Pp.
YES Exhaust Vent (Noble Gas)
(1-RE-90-404A1B)
D. Condenser Vacuum Pp.
NO Exhaust Vent (Noble Gas)
(1-RE-90-404A1B)
EPIP-1 YES NO NO YES Page 100 11/2009 Watts Bar SRO NRC License Exam 12/17/2009 100. For the listed instrumentation, which one of the following describes whether it is:
(1) required by LCO 3.3.3, "PAM Instrumentation,"
and (2) included in EPIP-1, "Emergency Plan Classification Flowchart," as an indication for determining EALs?
Instrumentation LeO 3.3.3 A. Aux. Bldg. Passive Sump Level YES (0-LS-40-21 B)
B. Aux. Bldg. Passive Sump Level NO (0-LS-40-21 B)
C. Condenser Vacuum Pp.
YES Exhaust Vent (Noble Gas)
(1-RE-90-404A1B)
D. Condenser Vacuum Pp.
NO Exhaust Vent (Noble Gas)
(1-RE-90-404A1B)
EPIP-1 YES NO NO YES Page 100
1112009 SRO NRC Exam Reference Package
- 1. Steam Tables
- 2. Control Bank: Insertion Limits Versus Thermal Power Four Loop Operation, COLRpage 6
- 3. TI-124, Equipment to Plant Risk Matrix, page 21-23
- 4. TI-83.01, Hydrogen Recombiner Required Power-vs-Containment Pressure Curves 14 pages 1112009 SRO NRC Exam Reference Package
- 1. Steam Tables
- 2. Control Bank Insertion Limits Versus Thermal Power Four Loop Operation, COLRpage 6
- 3. TI-124, Equipment to Plant Risk Matrix, page 21-23
- 4. TI-83.01, Hydrogen Recombiner Required Power-vs-Containment Pressure Curves 14 pages
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Unit 1 WATTS BAR Page 6 of 10 Cycle 10 Revision 3 z
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Unit 1 WATTS BAR Page 6 of 10 Cycle 10 Revision 3
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT Technical Instruction TI-83.01 HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES Units 1 Revision 1 QUALITY RELATED PREPARED BY:
Ernest T. Haston SPONSORING ORGANIZATION: ___ -=D=EM:..:.:-.. __
APPROVED BY:
Charles R. Allen EFFECTIVE DATE:
05/22/2006 LEVEL OF USE: INFORMATION TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT Technical Instruction TI-83.01 HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES Units 1 Revision 1 QUALITY RELATED PREPARED BY:
Ernest T. Haston SPONSORING ORGANIZATION: _--=D..:::E.!.!.;M~ __
APPROVED BY:
Charles R. Allen EFFECTIVE DATE:
05/22/2006 LEVEL OF USE: INFORMATION
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 2 of 14 REVISION LOG REVISION OR AFFECTED CHANGE EFFECTIVE PAGE NUMBER DATE NUMBERS DESCRIPTION OF REVISION/CHANGE Rev 0 All Initial Issue. A 10CFRSO.S9 Screening Review has been prepared for this procedure (Engineering Tracking # WBP-LMN-OS-019-0).
Rev 1 OS/22/06 1,2,6,7,8,9, Recombiner 1:-RCB-83-1-A curve is being 10, ii, 13 revised since the power has changed from 48 kW to 44 kW which is outside the range of +/- 2 kW. Section S.1 and 6.1 was updated, Section 6.3 was revised to clarify the equations, Table 6.3 updated, and Attachment 1 was revised to change psig to psia.
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 2 of 14 REVISION LOG REVISION OR AFFECTED CHANGE EFFECTIVE PAGE NUMBER DATE NUMBERS DESCRIPTION OF REVISION/CHANGE Rev 0 All Initial Issue. A 1 OCFR50.59 Screening Review has been prepared for this procedure (Engineering Tracking # WBP-LMN-05-019-0).
Rev 1 OS/22/06 1,2,6,7,8,9, Recombiner 1:-RCB-83-1-A curve is being 10,11,13 revised since the power has changed from 48 kW to 44 kW which is outside the range of +/- 2 kW. Section 5.1 and 6.1 was updated, Section 6.3 was revised to clarify the equations, Table 6.3 updated, and Attachment 1 was revised to change psig to psia.
WBN 1
Section 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 4.0 5.0 5.1 5.2 6.0 6.1 6.2 6.3
. 7.0 8.0 HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES TABLE OF CONTENTS Title Revision Log Table of Contents INTRODUCTION Purpose Scope Frequency and Conditions
Background
REFERENCES Performance References Developmental References PRECAUTIONS AND LIMITATIONS PREREQUISITE ACTIONS ACCEPTANCE CRITERIA Acceptance Criteria for Hydrogen Recombiner A Acceptance Criteria for Hydrogen Recombiner B PERFORMANCE Hydrogen Recombiner A Hydrogen Recombiner B TI-83.01 Revision 1 Page 3 of 14 Required Power-vs-Containment Pressure Setting After a LOCA POST PERFORMANCE ACTIVITY RECORDS Page 2
3 4
4 4
4 4
4 4
5 5
6 6
6 7
7 7
8 9
10 10 ATTACHMENT 1 Recombiner Calibration Factor Curve 11 ATTACHMENT 2 Recombiner Power Correction Factor Curve 12 ATTACH MENT 3 Required Power-vs-Containment Pressure Curve 13 for Hydrogen Recombiner A ATTACHMENT 4 Required Power-vs-Containment Pressure Curve 14 for Hydrogen Recombiner B WBN 1
Section 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 4.0 5.0 5.1 5.2 6.0 6.1 6.2 6.3
. 7.0 8.0 HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES TABLE OF CONTENTS Title Revision Log Table of Contents INTRODUCTION Purpose Scope Frequency and Conditions
Background
REFERENCES Performance References Developmental References PRECAUTIONS AND LIMITATIONS PREREQUISITE ACTIONS ACCEPTANCE CRITERIA Acceptance Criteria for Hydrogen Recombiner A Acceptance Criteria for Hydrogen Recombiner B PERFORMANCE Hydrogen Recombiner A Hydrogen Recombiner B TI-83.01 Revision 1 Page 3 of 14 Required Power-vs-Containment Pressure Setting After a LOCA POST PERFORMANCE ACTIVITY RECORDS Page 2
3 4
4 4
4 4
4 4
5 5
6 6
6 7
7 7
8 9
10 10 ATTACHMENT 1 Recombiner Calibration Factor Curve 11 ATTACHMENT 2 Recombiner Power Correction Factor Curve 12 ATTACH MENT 3 Required Power-vs-Containment Pressure Curve 13 for Hydrogen Recombiner A ATTACHMENT 4 Required Power-vs-Containment Pressure Curve 14 for Hydrogen Recombiner B
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 4 of 14
1.0 INTRODUCTION
1.1 Purpose This Technical Instruction (TI) provides guidelines for development and revision of Hydrogen Recombiner "Required Power vs. Containment Pressure Curve" following.a Design Basis Event (DBE). These curves provide the operator with an initial setting for the recombiners, assist operations in assessing the heatup test results and reduce operator action during a DBE.
1.2 Scope A.. Operation Test Instruction OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test."
B.
Operation Test Instruction OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test."
C.
Post Performance Activity D.
System Operating Instruction SOI-83~01, "Containment Hydrogen Recombiners."
1.3 Frequency and Conditions A.
This instruction is to be used with the performance of OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" and OTI-83.02, "Hydrogen Recombiner B *18 Month Heatup Test."
B.
This instruction may be used in any Mode
1.4 Background
WBN has generated the "Required Power vs. Containment Pressure" curves for use in determining the Hydrogen Recombiner post-LOCA power setting. The curves were generated by multiplying the Cp value determined from Figure 4-5 in the Vendor Technical Manual by the power setting determined from the Operation Test Instruction OTI-83.01 and OTI-83.02.
2.0 REFERENCES
2.1 Performance References A.
None WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 4 of 14
1.0 INTRODUCTION
1.1 Purpose This Technical Instruction (TI) provides guidelines for development and revision of Hydrogen Recombiner "Required Power vs. Containment Pressure Curve" following a Design Basis Event (DBE). These curves provide the operator with an initial setting for the recombiners, assist operations in assessing the heatup test results and reduce operator action during a DBE.
1.2 Scope A.
Operation Test Instruction OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test."
B.
Operation Test Instruction OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test."
C.
Post Performance Activity D.
System Operating Instruction SOI-83.01, "Containment Hydrogen Recombiners."
1.3 Frequency and Conditions A.
This instruction is to be used with the performance of OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" and OTI-83.02, "Hydrogen Recombiner B18 Month Heatup Test."
B.
This instruction may be used in any Mode
1.4 Background
WBN has generated the "Required Power vs. Containment Pressure" curves for use in determining the Hydrogen Recombiner post-LOCA power setting. The curves were generated by multiplying the Cp value determined from Figure 4-5 in the Vendor Technical Manual by the power setting determined from the Operation Test Instruction OTI-83.01 and OTI-83.02.
2.0 REFERENCES
2.1 Performance References A.
None
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 5 of 14 2.2 Developmental References A.
System Oescription Manual N3-83-4001, "Combustible Gas Control System" B.
Tech Specs 3.6.5, Containment Air Temperature C.
Tech Specs 3.6.7, Hydrogen Recombiners D.
TVA Drawings 45W755-1 and -3 E.
WBN-VTM-W120-2298, Vendor Technical Manual for Westinghouse Electric Hydrogen Recombiner System F.
Westinghouse Energy System letter, WTO-O-9913 (RIMS # T33 950114 806), dated 01/13/95 and entitled "Tennessee Valley Authority Watts Bar Nuclear Plant Units 1 & 2 Hydrogen Recombiner Required Power Vs Containment Pressure Curve" G.
Westinghouse Energy System letter, WTD-O-9946 (RIMS # T33 950217 801), dated 02/17/95 and entitled "Tennessee Valley Authority Watts Bar Nuclear Plant Units 1& 2 Hydrogen Recombiner Required Power Vs Containment Pressure Curve" H.
Westinghouse Energy System letter, WTD-O-9964 (RIMS # T33 950309 812), dated 03/08/95 and entitled "Tennessee Valley Authority Watts Bar Nuclear Plant Units 1 & 2 Hydrogen Recombiner Required Power" 3.0 PRECAUTIONS AND LIMITATIONS None WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 5 of 14 2.2 Developmental References A.
System Description Manual N3-83-4001, "Combustible Gas Control System" B.
Tech Specs 3.6.5, Containment Air Temperature C.
Tech Specs 3.6.7, Hydrogen Recombiners D.
TVA Drawings 45W755-1 and -3 E.
WBN-VTM-W120-2298, Vendor Technical Manual for Westinghouse Electric Hydrogen Recombiner System F.
Westinghouse Energy System letter, WTD-D-9913 (RIMS # T33 950114 806), dated 01/13/95 and entitled "Tennessee Valley Authority Watts Bar Nuclear Plant Units 1 & 2 Hydrogen Recombiner Required Power Vs Containment Pressure Curve" G.
Westinghouse Energy System letter, WTD-D-9946 (RIMS # T33 950217 801), dated 02/17/95 and entitled "Tennessee Valley Authority Watts Bar Nuclear Plant Units 1 & 2 Hydrogen Recombiner Required Power Vs Containment Pressure Curve" H.
Westinghouse Energy System letter, WTD-D-9964 (RIMS # T33 950309 812), dated 03/08/95 and entitled "Tennessee Valley Authority Watts Bar Nuclear Plant Units 1 & 2 Hydrogen Recombiner Required Power" 3.0 PRECAUTIONS AND LIMITATIONS None
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 6 of 14 4.0 PREREQUISITE ACTIONS 4.1 PRELIMINARY ACTIONS Performance of the following procedures:
A.
OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" B.
OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" 4.2 SPECIAL TOOLS AND SUPPLIES None 4.3 FIELD PREPARATIONS None 4.4 APPROVALS AND NOTIFICATIONS None 5.0 ACCEPTANCE CRITERIA 5.1 ACCEPTANCE CRITERIA FOR HYDROGEN RECOMBINER A A.
IF the POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is 42 to 46 kW and the REFERENCE POWER recorded is 50.263 to 54.263 kW, THEN a revision' to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is not required..
B.
IF the POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is less than 42 or greater than 46 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is required and new acceptance criteria established (+/- 2 kW of new POWER OUT).
C.
IF the REFERENCE POWER kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is less than 50.263 or greater than 54.263 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is required and a new acceptance criteria established (+/- 2 kW of new REFERENCE POWER).
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES
. Page 6 of 14 4.0 PREREQUISITE ACTIONS 4.1 PRELIMINARY ACTIONS Performance of the following procedures:
A.
OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" B.
OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" 4.2 SPECIAL TOOLS AND SUPPLIES None 4.3 FIELD PREPARATIONS None 4.4 APPROVALS AND NOTIFICATIONS None 5.0 ACCEPTANCE CRITERIA 5.1 ACCEPTANCE CRITERIA FOR HYDROGEN RECOMBINER A A.
IF the POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is 42 to 46 kW and the REFERENCE POWER recorded is 50.263 to 54.263 kW, THEN a revision*to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is not required..
B.
IF the POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is less than 42 or greater than 46 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is required and new acceptance criteria established (+/- 2 kW of new POWER OUT).
C.
IF the REFERENCE POWER kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is less than 50.263 or greater than 54.263 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is required and a new acceptance criteria established (+/- 2 kW of new REFERENCE POWER).
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 7 of 14 5.2 ACCEPTANCE CRITERIA FOR HYDROGEN RECOMBINER B A.
IF the POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is 46 to 50 kW and the REFERENCE POWER recorded is 43.936 to 47.936 kW,THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is not required.
B.
IF the POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is less than 46 or greater than 50 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is required and new acceptance criteria established (+/- 2 kW of new POWER OUT).
C.
IF the REFERENCE POWER kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is less than 43.936 or greater than 47.936 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is required and new acceptance criteria established (+/- 2 kW of new REFERENCE POWER).
6.0 PERFORMANCE 6.1 HYDROGEN RECOMBINER A
[1]
DETERMINE Calibration Factor (Cc) from Attachment 1 using Containment Dry Bulb Temperature and Absolute Pressure (psia) recorded on OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test"
[2]
RECORD the determined Calibration Factor (Cc)
[3]
RECORD the POWER OUT wattmeter kW reading recorded on OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test"
[4]
CALCULATE REFERENCE POWER (PR), by multiplying the POWER OUT wattmeter kW reading by the Calibration Factor (Cc)
[5]
IF POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is 42 t046 kW OR WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 7 of 14 5.2 ACCEPTANCE CRITERIA FOR HYDROGEN RECOMBINER B A.
IF the POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is 46 to 50 kW and the REFERENCE POWER recorded is 43.936 to 47.936 kW,THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is not required.
B.
IF the POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is less than 46 or greater than 50 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is required and new acceptance criteria established (+/- 2 kW of new POWER OUT).
C.
IF the REFERENCE POWER kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is less than 43.936 or greater than 47.936 kW, THEN a revision to the "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is required and new acceptance criteria established (+/- 2 kW of new REFERENCE POWER).
6.0 PERFORMANCE 6.1 HYDROGEN RECOMBINER A
[1]
DETERMINE Calibration Factor (Cd from Attachment 1 using Containment Dry Bulb Temperature and Absolute Pressure (psia) recorded on OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test"
[2]
RECORD the determined Calibration Factor (Cc)
[3]
RECORD the POWER OUT wattmeter kW reading recorded on OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test"
[4]
CALCULATE REFERENCE POWER (PR), by multiplying the POWER OUT wattmeter kW reading by the Calibration Factor (Cd
[5]
IF POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is 42 to 46 kW OR
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 8 of 14 the REFERENCE POWER recorded is 50.263 to 54.263 kW, THEN a revision to "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is NOT required.
[6]
IF POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is less than 42 kW or greater than 46 kW OR the REFERENCE POWER recorded is less than 50.263 kW or greater than 54.263 kW, THEN a revision to Attachment 3 "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" for Hydrogen Recombiner A is required. The new curve for Hydrogen Recombiner A is generated as shown in Section 6.3.
6.2 HYDROGEN RECOMBINER B
[1]
DETERMINE Calibration Factor (Cd from Attachment 1 using Containment Dry Bulb Temperature and Absolute Pressure (psia) recorded on OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test"
[2]
RECORD the determined Calibration Factor (Cd
[3]
RECORD the POWER OUT wattmeter kW reading recorded on OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test"
[4]
CALCULATE REFERENCE POWER (PR), by multiplying the POWER OUT wattmeter kW reading by the Calibration Factor (Cc)
[5]
IF POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is 46 to 50 kW OR the REFERENCE POWER recorded is 43.936 to 47.936 kW, THEN a revision to "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is NOT required.
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 8 of 14 the REFERENCE POWER recorded is 50.263 to 54.263 kW, THEN a revision to "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" is NOT required.
[6]
IF POWER OUT kW rating recorded in OTI-83.01, "Hydrogen Recombiner A 18 Month Heatup Test" is less than 42 kW or greater than 46 kW OR the REFERENCE POWER recorded is less than 50.263 kW or greater than 54.263 kW, THEN a revision to Attachment 3 "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner A" for Hydrogen Recombiner A is required. The new curve for Hydrogen Recombiner A is generated as shown in Section 6.3.
6.2 HYDROGEN RECOMBINER B
[1]
DETERMINE Calibration Factor (Cc) from Attachment 1 using Containment Dry Bulb Temperature and Absolute Pressure (psia) recorded on OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test"
[2]
RECORD the determined Calibration Factor (Cc)
[3]
RECORD the POWER OUT wattmeter kW reading recorded on OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test"
[4]
CALCULATE REFERENCE POWER (PR), by multiplying the POWER OUT wattmeter kW reading by the Calibration Factor (Cc)
[5]
IF POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is 46 to 50 kW OR the REFERENCE POWER recorded is 43.936 to 47.936 kW, THEN a revision to "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is NOT required.
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 9 of 14
[6]
IF POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is less than 46 kW or greater than 50 kW OR the REFERENCE POWER recorded is less than 43.936kW or greater than 47.936 kW, THEN a revision to Attachment 4 "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is required. The new curve for Hydrogen Recombiner B is generated as shown in Section 6.3.
6.3 REQUIRED POWER-VS-CONTAINMENT PRESSURE SETTING AFTER A LOCA Required Power vs. Containment Pressure" curves for use in determining the Hydrogen Recombiner post-LOCA power setting curves were generated by multiplying the Cp value determined from Attachment 2 (Figure 4-5 in the Vendor Technical Manual) by the REFERENCE POWER (PR) determined from OTI-83.01 and OTI-83.02. Curves may need to be revised based on results of the applicable OTI performance.
Post-accident Required Power (PAl For example, the new Post-accident Required Power (PA) is calculated (Ref.
2.2.E) as follows:
Power Out during calibration = 48 kW Temperature in Containment during calibration = 75° F Pressure in Containment during calibration = 14.0 psia Reference Power (P R) = (Calibration Factor (Cc)) * (Power Out during calibration)
Cc = 0.92 (See Attachment 1)
PR = 0.92
- PR Pc = Pressure in containment after a Design Basis Event From Plant Operating Records, assume Pre-LOCA Containment Pressure 14.7 psia and Pre-LOCA Containment Temperature 110 0 F.
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 9 of 14
[6]
IF POWER OUT kW rating recorded in OTI-83.02, "Hydrogen Recombiner B 18 Month Heatup Test" is less than 46 kW or greater than 50 kW OR the REFERENCE POWER recorded is less than 43.936 kW or greater than 47.936 kW, THEN a revision to Attachment 4 "Required Power-vs-Containment Pressure Curve for Hydrogen Recombiner B" is required. The new curve for Hydrogen Recombiner B is generated as shown in Section 6.3.
6.3 REQUIRED POWER-VS-CONTAINMENT PRESSURE SETTING AFTER A LOCA Required Power vs. Containment Pressure" curves for use in determining the Hydrogen Recombiner post-LOCA power setting curves were generated by multiplying the Cp value determined from Attachment 2 (Figure 4-5 in the Vendor Technical Manual) by the REFERENCE POWER (PR) determined from OTI-83.01 and OTI-83.02. Curves may need to be revised based on results of the applicable OTI performance.
Post-accident Required Power (PAl For example, the new Post-accident Required Power (PA) is calculated (Ref.
2.2.E) as follows:
Power Out during calibration = 48 kW Temperature in Containment during calibration = 75° F Pressure in Containment during calibration = 14.0 psia Reference Power (P R) = (Calibration Factor (Cc)) * (Power Out during calibration)
Cc = 0.92 (See Attachment 1)
PR = 0.92
- PR Pc = Pressure in containment after a Design Basis Event From Plant Operating Records, assume Pre-LOCA Containment Pressure 14.7 psia and Pre-LOCA Containment Temperature 110 0 F.
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 10 of 14 Cp = Pressure Factor determined using Attachment 2 (Figure 4-5 in the WBN-VTM-W120-2298 (Ref 2.2.E)) and WAT-D-9913 (Ref. 2.2.F) that stated Cp =
1.52 @ 24.7 psia.
PA = 1.52
- 44.2 = 67.18 kW Post-accident Required Power (P £J for Recombiner A and B Post-accident Required Power (P A) setting for containment pressures 14.7 thru 24.7 psia are calculated and tabulated in Table 6.3 for Hydrogen Recombiners A
& B. This table uses the calibration data from performance of OTI-83.01 (Recombiners A) and OTI-83.02 (Recombiners B).
Table 6.3 Hydrogen Hydrogen Pc Cp Recombiner A Recombiner B.
Psia Psig PA PA 14.7 0.0 1.2 62.715 55.123 16.9 2.2 1.31 68.464 60.176 18.7 4.0 1.37 71.600 62.932 20.7 6.0 1.43 74.736 65.688 22.7 8.0 1.48 77.349 67.985 24.7 10.0 1.52 79.439 69.823 The "Required Power-vs-Containment Pressure" curves for Hydrogen Recombiner A and B are developed and included in Attachment 3 & 4 respectively.
7.0 POST PERFORMANCE ACTIVITIES None 8.0 RECORDS WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 10 of 14 Cp = Pressure Factor determined using Attachment 2 (Figure 4-5 in the WBN-VTM-W120-2298 (Ref 2.2.E)) and WAT-D-9913 (Ref. 2.2.F) that stated Cp =
1.52 @ 24.7 psia.
PA = 1.52
- 44.2 = 67.18 kW Post-accident Required Power (P 6) for Recombiner A and B Post-accident Required Power (PA ) setting for containment pressures 14.7 thru 24.7 psia are calculated and tabulated in Table 6.3 for Hydrogen Recombiners A
& B. This table uses the calibration data from performance of OTI-83.01 (Recombiners A) and OTI-83.02 (Recombiners B).
Table 6.3 Hydrogen Hydrogen Pc Cp Recombiner A Recombiner B.
Psia Psig PA PA 14.7 0.0 1.2 62.715 55.123 16.9 2.2 1.31 68.464 60.176 18.7 4.0 1.37 71.600 62.932 20.7 6.0 1.43 74.736 65.688 22.7 8.0 1.48 77.349 67.985 24.7 10.0 1.52 79.439 69.823 The "Required Power-vs-Containment Pressure" curves for Hydrogen Recombiner A and B are developed and included in Attachment 3 & 4 respectively.
7.0 POST PERFORMANCE ACTIVITIES None 8.0 RECORDS
WBN 1
NOTE HYDROGEN RECOMBINER REQUIRED TI-83.01 POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 11 of 14 ATTACHMENT 1 RECOMBINER CALIBRATION FACTOR CURVE Page 1 of 1 1.8-,-----r-----r-----,r----..----~-____,
1.6-t----+~---t----I1----+---+_--_I 1.4-t----+----t----I1--::::.---='I---+_---I Containment pressure during calibration 9.7 psia 1.2-t------t---\\---1----i---+---=,..j-12.2 psia 1.0 -t----+/-:.,......-=--t----II----t---;----:=ooi_ 14.7 psi a
~-.- 17.2 psia 0:8-+----+----+--~1--"",,;..-.;:::::~-+----I
[==t==+_-+--i~-1--l-19.2 psia 0.6-+----+----+-----1----i---+----I 60 70 80 90 100 110 120 CONTAINMENT TEMPERATURE (OF)
Figure 4-1 (Reference 2.2E)
A straight edge and numerical interpolation should be used if the containment pressure falls between the constant pressure lines. For example: If containment pressure is 14.00 psia and containment temperature is 75° F:
Therefore, Cc @ 14.70 psia =.87 and Cc @12.20 psi a = 1.05 Cc @ 14.00 psi a =.87 + [(1.05 -.87) X (14.70 -14.00)] = 0.92 (14.70 -12.20)
I WBN 1
NOTE HYDROGEN RECOMBINER REQUIRED TI-83.01 POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 11 of 14 ATTACHMENT 1 RECOMBINER CALIBRATION FACTOR CURVE Page 1 of 1 1.8-r---~---"----~----r------r-----'
1.6-t----t---t----f----t-----t----j 1.4-t-----t---t----f-=:::::o-=t-----t----j Containment pressure during calibration 9.7 psia 1.2-+----r---+-----+----+-----+--=---+- 12.2 psia 1.0 -I----t:==--.....::::::..-t----f----t-----t--== 14.7 psia
___ -.-17.2 psia 0.8-1----+---+----+--=-""""""=---+----j t==t==+~-_t---~--r--T 19.2 psia 0.6 -I----t---t----f----t----t----j 60 70 80 90 100 110 120 CONTAINMENT TEMPERATURE (OF)
Figure 4-1 (Reference 2.2E)
A straight edge and numerical interpolation should be used if the containment pressure falls betvveen the constant pressure lines. For example: If containment pressure is 14.00 psia and containment temperature is 75° F:
Therefore, Cc @ 14.70 psi a =.87 and Cc @ 12.20 psi a = 1.05 Cc @ 14.00 psia =.87 + [(1.05 -.87) X (14.70 - 14.00)] = 0.92 (14.70 - 12.20)
I
WBN 1
0-w IX 0 t-w c(
u..
w IX
- )
V)
Vl W
c:r:
0-HYDROGEN RECOMBINER REQUIRED TI-83.01 POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 12 of 14 ATTACHMENT 2 RECOMBINER POWER CORRECTION FACTOR CURVE Page 1 of 1 1.7 1.6 1.5 1.4 1.3 1.2 1.1 1.0 14.7 Pre-Loca Containment Temp.
110 0 in Lower Compartment and 75°F in Upper Compart-ment
./
V V
./
V V
16.7 18.7 20.7 22.7 24.7 26.7 28.7 POST-lOCA CONTAINMENT PRESSURE (PSIA)
Figure 4*5 Ice Condenser Containment Recombiner Power Correction Factor Versus Containment Pressure, 14.7 PSIA Initial Pressure I
WBN 1
0-W HYDROGEN RECOMBINER REQUIRED TI-83.01 POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 12 of 14 ATTACHMENT 2 RECOMBINER POWER CORRECTION FACTOR CURVE Page 1 of 1 1.7 Pre-Loca Containment Temp.
110 0 in Lower Compartment and 75°F in Upper Compart-1.6 ment
.,/'
V V
/
V V
1.5 1.4 1.3 1.2 1.1
- 1. 0 14.7 16.7 18.7 20.7 22.7 24.7 26.7 28.7 POST-lOCA CONTAINMENT PRESSURE (PSIA)
Figure 4-5 Ice Condenser Containment Recombiner Power Correction Factor Versus Containment Pressure, 14.7 PSIA Initial Pressure I
~
2:. Yi WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 13 of 14 ATTACHMENT 3 REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVE FOR HYDROGEN RECOMBINER A Page 1 of 1 so so.-----------------------~------------------~------~
70 ------~--------=_~------------------~------~------------------------I 65 ----/"----,----------------------------------'-----------'--------------'------------------------/
60/-------~-----c---------------:------'----------------~---~-----------------/
~-
- 7
~
55
:------------~--------,-------,-------,-------t-----~------------------/
501-----~---L-------;-----------------,------~---------~-----------------/
451------------'-------,'-------"--------'--------,-------~-----------------------------I 40 40L---------------------~--~--~--------------------~
o 2
4 6
10 11 12 o
X; 12 Containment Pressure (psig)
Note: Curve based on a calculated Reference Power (PH) of 52.263 kW which is obtained from the eighteen month performance of OTI-83.01. This curve may need to be revised based on results of the OTI-83.01 performance.
I
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 13 of 14 ATTACHMENT 3 REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVE FOR HYDROGEN RECOMBINER A Page 1 of 1 80 80 75 ---------
70
-~---------------~--------------------------------'-~~~-----------~--
65--~-~-~--------'--------------"-------~----~------~~~--~~-
60
]-
J 501-----~---L-------'------~--------,-------~~--~~~~---------1 45
~--.----
40 40~--------------------------------------------~
o 4
6 10 II 12 o
X; 12 Containment Pressure (psig)
Note: Curve based on a calculated Reference Power (PR) of 52.263 kW which is obtained from the eighteen month performance of OTI-83.01. This curve may need to be revised based on results of the OTI-83.01 performance.
I
~
~
t
~
i:.
"0
.~
<J 0:::
WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
80 75 70 65 55 50 45 POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page 14 of 14 ATTACHMENT 4 REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVE FOR HYDROGEN RECOMBINER B 2
Page 1 of 1 3
4 5
6
- 7 8
9 Containment Pressure (psig)
Required Power-vs-Containment Pressure For Hydrogen Recombiner B 10 11 12 Note: Curve based on a calculated Reference Power (PR) of 45.936 kW which is obtained from the eighteen month performance of OTI-83.02. This curve may need to be revised based on results of the OTI-83.02 performance.
I WBN HYDROGEN RECOMBINER REQUIRED TI-83.01 1
POWER-VS-CONTAINMENT PRESSURE Revision 1 CURVES Page14of14 ATTACHMENT 4 REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVE FOR HYDROGEN RECOMBINER B Page 1 of 1 80~-------------------------------------------------'
75 ------------
70------------------~-
65
---~------------,-----------c~~--~-
60 55r-----~---------~-----~----------~----'-------~----~------------
50 ___________________________ c ____________________
45 --------,------------ ----------------------------------------------------------,------ --------------
40L-------------------~----------------------------~
o 2
3 4
5 67 8
9 10 11 12 C ontainmeJ1t Pressure (psig)
Required Power-vs-Containment Pressure For Hydrogen Recombiner B Note: Curve based on a calculated Reference Power (PR) of 45.936 kW which is obtained from the eighteen month periormance of OTI-83.02. This curve may need to be revised based on results of the OTI-83.02 performance.
I
WBN Equipment to Plant Risk Matrix TI-124 Unit 1 Rev. 0017 Page 21 of 46 6.2.2 Large Early Release Frequency The following systems are important to reducing the "beyond design basis" radiological risk to public/personnel but are not significant contributors to the risk of core damage. These systems impact the radiological release profiles for WBN.
For those activities modeled in the site PSA that could impact the probability of radiological releases the Large Early Release Frequency (LERF) should be considered. The following thresholds are established:
RED Incremental Large Early Release probability (ILERP) greater than 1 E-06 should not be entered voluntarily. If such conditions are entered it should be for very short periods of time and only with a clear detailed understanding of events that caused the risk level.
ORANGE ILERP greater than SE-07 but less than 1 E-06, assess non quantifiable factors, establish risk management actions.
YELLOW ILERP greater than 1 E-07 but less than SE-07, assess non quantifiable factors, establish risk management actions.
GREEN ILERP less than 1 E-07, no separate risk management plans or approval are required.
Only use the category/group for which the top system is unavailable. These risk levels are based upon deterministic evaluation; unavailability is bounded by Tech Spec allowable out of service time. SSCs that are modeled in the PSA are identified by an asterisk. Otherwise, the functions are not modeled in the PSA. Obtain risk evaluations from Corporate PRA analysts per SPP-9.11-2 PRA Evaluation Request to validate the risk configuration based upon actual unavailability.
A single train for anyone systems unavailable in a given category should be considered as GREEN.
A single train for any two systems unavailable in a given category should be considered as YELLOW.
A single train of any three or more in a category should be considered as ORANGE.
Example:
For Group 268; if A Train Hydrogen Analyzer (Permanent Hydrogen Mitigation System) is unavailable With B Train Hydrogen Recornbiner unavailable the likelihood of increased post accident fission product release would be YELLOW or one incremental color change. If either train of Air Return Fans was also unavailable, the likelihood would be increased to ORANGE or 2 incremental color changes.
WBN Equipment to Plant Risk Matrix TI-124 Unit 1 Rev. 0017 Page 21 of 46 6.2.2 Large Early Release Frequency The following systems are important to reducing the "beyond design basis" radiological risk to public/personnel but are not significant contributors to the risk of core damage. These systems impact the radiological release profiles for WBN.
For those activities modeled in the site PSA that could impact the probability of radiological releases the Large Early Release Frequency (LERF) should be considered. The following thresholds are established:
RED Incremental Large Early Release probability (lLERP) greater than 1 E-06 should not be entered voluntarily. If such conditions are entered it should be for very short periods of time and only with a clear detailed understanding of events that caused the risk level.
ORANGE ILERP greater than 5E-07 but less than 1 E-06, assess non quantifiable factors, establish risk management actions.
YELLOW ILERP greater than 1 E-07 but less than 5E-07, assess non quantifiable factors, establish risk management actions.
GREEN ILERP less than 1 E-07, no separate risk management plans or approval are required.
Only use the category/group for which the top system is unavailable. These risk levels are based upon deterministic evaluation; unavailability is bounded by Tech Spec allowable out of service time. SSCs that are modeled in the PSA are identified by an asterisk. Otherwise, the functions are not modeled in the PSA. Obtain risk evaluations from Corporate PRA analysts per SPP-9.11-2 PRA Evaluation Request to validate the risk configuration based upon actual unavailability.
A single train for anyone systems unavailable in a given category should be considered as GREEN.
A single train for any two systems unavailable in a given category should be considered as YELLOW.
A single train of any three or more in a category should be considered as ORANGE.
Example:
For Group 268; if A Train Hydrogen Analyzer (Permanent Hydrogen Mitigation System) is unavailable With B Train Hydrogen Recombiner unavailable the likelihood of increased post accident fission product release would be YELLOW or one incremental color change. If either train of Air Return Fans was also unavailable, the likelihood would be increased to ORANGE or 2 incremental color changes.
WBN Equipment to Plant Risk Matrix Unit 1 6.2.2 Large Early Release Frequency (continued) 030 Auxiliary Building Gas Treatment Sys Emergency Gas Treatment System Auxiliary Bldg Sec Cont Envelope Annulus Vacuum Control System Control Room Emer Ventilation Sys Auxiliary Control Air System*
030 Air Return Fan System*
Hydrogen Recombiner TI-124 Rev. 0017 Page 22 of 46 Permanent Hydrogen Mitigation System (Igniters*, Analyzers)
Ice Condenser System*
,030 Control Room Emer Ventilation Sys Emergency Gas Treatment System Auxiliary Building Gas Treatment Sys Annulus Vacuum Control System Auxiliary Control Air System*
065 Annulus Vacuum Control System*
Emergency Gas Treatment System Auxiliary Building Gas Treatment Sys Control Room Emer Ventilation Sys Auxiliary Control Air System*
065 Emergency Gas Treatment System Auxiliary Building Gas Treatment Sys Containment Isolation System*
Annulus Vacuum Control System Auxiliary Control Air System*
074 Containment Spray System including recirc path*
Lower Compartment Coolers Air Return Fan System*
Containment Isolation System*
RHR System (containment cooling via CS Hx)/RHR Spray)*
Safety Injection (CS to empty RWST for Charging Bleed & Feed)*
WBN Equipment to Plant Risk Matrix Unit 1 6.2.2 Large Early Release Frequency (continued) 030 Auxiliary Building Gas Treatment Sys Emergency Gas Treatment System Auxiliary Bldg Sec Cont Envelope Annulus Vacuum Control System Control Room Emer Ventilation Sys Auxiliary Control Air System*
030 Air Return Fan System*
Hydrogen Recombiner TI-124 Rev. 0017 Page 22 of 46 Permanent Hydrogen Mitigation System (Igniters*, Analyzers)
Ice Condenser System*
030 Control Room Emer Ventilation Sys Emergency Gas Treatment System Auxiliary Building Gas Treatment Sys Annulus Vacuum Control System Auxiliary Control Air System*
065 Annulus Vacuum Control System*
Emergency Gas Treatment System Auxiliary Building Gas Treatment Sys Control Room Emer Ventilation Sys Auxiliary Control Air System*
065 Emergency Gas Treatment System Auxiliary Building Gas Treatment Sys Containment Isolation System*
Annulus Vacuum Control System Auxiliary Control Air System*
074 Containment Spray System including recirc path*
Lower Compartment Coolers Air Return Fan System*
Containment Isolation System*
RHR System (containment cooling via CS Hx)/RHR Spray)*
Safety Injection (CS to empty RWST for Charging Bleed & Feed)*
WBN Equipment to Plant Risk Matrix Unit 1 6.2.2 Large Early Release Frequency (continued) 083 Hydrogen Recombiner System Pressurizer PORVS*
Reactor Head Vent System Air Return Fan System*
TI-124 Rev. 0017 Page 23 of 46 Permanent Hydrogen Mitigation Sys (Igniters*, Analyzers) 268 Perm H2 Mitigation Sys (lgniters)*
Hydrogen Recombiners Reactor Head Vent System Air Return Fan System*
Hydrogen Analyzers Pressurizer PORVS*
268 Perm H2 Mitigation Sys (Analyzers)
PHMS (Igniters)*
Reactor Head Vent System Air Return Fan System*
Hydrogen Recombiners Pressurizer PORVS*
061 Ice Condenser System*
Containment Spray System including recirc path*
Air Return Fans System*
Containment Isolation*
Residual Heat Removal (Spray and containment cooling)*
6.2.3 DRAM-SENTINEL WBN uses the ORAM-Sentinel computer program as one of the tools to assess the risk of core damage or radioactive releases to the environment for work on risk significant equipment. The ORAM-Sentinel model is a WBN Unit 1 model. The WBN Sentinel model originated from the WBN PRA, and the WBN Technical Specifications.
WBN Equipment to Plant Risk Matrix Unit 1 6.2.2 Large Early Release Frequency (continued) 083 Hydrogen Recombiner System Pressurizer PORVS*
Reactor Head Vent System Air Return Fan System*
TI-124 Rev. 0017 Page 23 of 46 Permanent Hydrogen Mitigation Sys (Igniters*, Analyzers) 268 Perm H2 Mitigation Sys (Igniters)*
Hydrogen Recombiners Reactor Head Vent System Air Return Fan System*
Hydrogen Analyzers Pressurizer PORVS*
268 Perm H2 Mitigation Sys (Analyzers)
PHMS (Igniters)*
Reactor Head Vent System Air Return Fan System*
Hydrogen Recombiners Pressurizer PORVS*
061 Ice Condenser System*
Containment Spray System including recirc path*
Air Return Fans System*
Containment Isolation*
Residual Heat Removal (Spray and containment cooling)*
6.2.3 DRAM-SENTINEL WBN uses the ORAM-Sentinel computer program as one of the tools to assess the risk of core damage or radioactive releases to the environment for work on risk significant equipment. The ~RAM-Sentinel model is a WBN Unit 1 model. The WBN Sentinel model originated from the WBN PRA, and the WBN Technical Specifications.
- ~, *..** : ID 1
007 EG2.4.21 1 2
009 EA2.20 2 3
011 EK1.01 3 4
015 AK1.02 4 5
022 AA1.02 5 6
025 AK2.056 7
026 AK3.02 7 8
027 AK2.03 8 9
029 EK1.05 9 10 038EA2.11 10 11 040 AA1.23 11 12 054 AK3.03 12 1:3 055 EA2.06 13 14 057 AG2.1.23 14 15 058 AG2.3.34 15 16 065 AK3.04 16 17 077 AK2.03 17 18 W/E04 EA1.3 18 19 024 AA2.02 19 20 028 AK3.05 20 21 036 AG2.4.2 21 22 059AK3.0122 23 067 AK1.01 23 24 069 AA1.01 24 25 W/E01 EA1.3 25 26 W/E13 EG2.1.31 26 27 W/E15 EK2.2 27 28 003 A1.09 28 29 004 K5.36 29 30 005 G2.1.23 30 31 005K6.0331 32 006 K5.09 32 33
. 007 A4.01 33 34 007 A4.09 34 35 008 K1.05 35 36 010 A4.03 36 37 012 A3.03 37 38 012 G 2.1.30 38 39 013 K6.01 39 40 022 K2.02 40 41 026 K4.08 41 42 039 K1.02 42 43 059 K3.04 43 44 059 K4.02 44 45 061 A2.08 45 11/2009 Watts Bar SRO NRC License Exam 12/17/2009
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1.00 MCS C
1.00 MCS C
1.00 MCS B
1.00 MCS D
1.00 MCS A
1.00 MCS A
1.00 MCS D
1.00 MCS C
1.00 MCS B
1.00 MCS D
1.00 MCS B
1.00 MCS A
1.00 MCS A
1.00 MCS A
1.00 MCS B
1.00 MCS A
1.00 MCS A
1.00 MCS A
1.00 MCS C
1.00 MCS D
1.00 MCS B
1.00 MCS B
1.00 MCS A
1.00 MCS B
1.00 MCS B
1.00 MCS C
1.00 MCS C
1.00 MCS C
1.00 MCS A
1.00 MCS D
1.00 MCS D
1.00 MCS A
1.00 MCS C
1.00 MCS B
1.00 MCS C
1.00 MCS A
1.00 MCS D
1.00 MCS B
1.00 MCS D
1.00 MCS A
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ID 1
007 EG2.4.21 1 2
009 EA2.20 2 3
011 EK1.01 3 4
015 AK1.02 4 5
022 AA1.02 5 6
025 AK2.05 6 7
026 AK3.02 7 8
027 AK2.03 8 9
029 EK1.05 9 10 038EA2.11 10 11 040 AA1.23 11 12 054 AK3.03 12 13 055 EA2.06 13 14 057 AG2.1.23 14 15 058 AG2.3.34 15 16 065 AK3.04 16 17 077 AK2.03 17 18 W IE04 EA1.3 18 19 024 AA2.02 19 20 028 AK3.05 20 21 036 AG2.4.2 21 22 059AK3.01 22 23 067 AK1.0 1 23 24 069 AA1.01 24 25 W/E01 EA1.3 25 26 W/E13 EG2.1.31 26 27 W/E15 EK2.2 27 28 003 A1.09 28 29 004 K5.36 29 30 005 G2.1.23 30 31 005 K6.03 31 32 006 K5.09 32 33 007 A4.01 33 34 007 A4.09 34 35 008 K1.05 35 36 010 A4.03 36 37 012 A3.03 37 38 012 G 2.1.30 38 39 013 K6.01 39 40 022 K2.02 40 41 026 K4.08 41 42 039 K1.02 42 43 059 K3.04 43 44 059 K4.02 44 45 061 A2.08 45 11/2009 Watts Bar SRO NRC License Exam 12/17/2009 Points Type 1.00 MCS B
1.00 MCS A
1.00 MCS C
1.00 MCS B
1.00 MCS D
1.00 MCS C
1.00 MCS C
1.00 MCS B
1.00 MCS D
1.00 MCS A
1.00 MCS A
1.00 MCS D
1.00 MCS C
1.00 MCS B
1.00 MCS D
1.00 MCS B
1.00 MCS A
1.00 MCS A
1.00 MCS A
1.00 MCS B
1.00 MCS A
1.00 MCS A
1.00 MCS A
1.00 MCS C
1.00 MCS D
1.00 MCS B
1.00 MCS B
1.00 MCS A
1.00 MCS B
1.00 MCS B
1.00 MCS C
1.00 MCS C
1.00 MCS C
1.00 MCS A
1.00 MCS D
1.00 MCS D
1.00 MCS A
1.00 MCS C
1.00 MCS B
1.00 MCS C
1.00 MCS A
1.00 MCS D
1.00 MCS B
1.00 MCS D
1.00 MCS A
Answers
46 062 A2.09 46 47 062 A2.1047 48 063 K3.oI 48 49 063 K4.0149 50 064 A1.04 50 51 064 K1.03 51 52 073 K3.0l 52 53 076 K2.01 53 54 078 A3.0154 55 103 G2.4.30 55 56 001 ALB 56 57 002 A4.05 57 58 016 G 2.2.3858 59 027 K5.01 59 60 033 A2.03 60 61 035 K6.01 61 62 045 K4.46 62 63 055 K3.0l 63 64 071 A2.02 64 65 086 K5.04 65 66 G 2.1.2966 67 G 2.1.3067 68 G 2.1668 69 G 2.2.4169 70 G 2.2.42 70 71 G 2.3.13 71 72 G 2.3.4 72 73 G 2.4.12 73 74 G 2.4.21 74 75 G 2.4.3975 SECTION 1 ( 75 items) 11/2009 Watts Bar SRO NRC License Exam 12/17/2009 1.00 MCS A
1.00 MCS D
1.00 MCS C
1.00 MCS D
1.00 MCS B
1.00 MCS A
1.00 MCS A
1.00 MCS B
LOO MCS C
1.00 MCS B
1.00 MCS C
1.00 MCS C
1.00 MCS C
1.00 MCS A
1.00 MCS B
1.00 MCS C
1.00 MCS C
1.00 MCS D
1.00 MCS D
1.00 MCS A
1.00 MCS C
1.00 MCS C
1.DO MCS B
1.00 MCS D
1.00 MCS A
1.00 MCS B
1.00 MCS B
1.00 MCS D
1.00 MCS B
1.0D MCS A
75.00 ID 46 062 A2.09 46 47 062 A2.10 47 48 063 K3.01 48 49 063 K4.01 49 50 064 A1.04 50 51 064 K1.03 51 52 073 K3.01 52 53 076 K2.01 53 54 078 A3.01 54 55 103 G2.4.30 55 56 001 A1.13 56 57 002 A4.05 57 58 016 G 2.2.3858 59 027 K5.01 59 60 033 A2.03 60 61 035 K6.01 61 62 045 K4.46 62 63 055 K3.01 63 64 071 A2.02 64 65 086 K5.04 65 66 G 2.1.2966 67 G 2.1.3067 68 G 2.1668 69 G 2.2.4169 70 G 2.2.4270 71 G 2.3.1371 72 G 2.3.4 72 73 G 2.4.1273 74 G 2.4.21 74 75 G 2.4.3975 SECTION 1 ( 75 items) 11/2009 Watts Bar SRO NRC License Exam 12/17/2009 Points Type 1.00 MCS A
1.00 MCS D
1.00 MCS C
1.00 MCS D
1.00 MCS B
1.00 MCS A
1.00 MCS A
1.00 MCS B
1.00 MCS C
1.00 MCS B
1.00 MCS C
1.00 MCS C
1.00 MCS C
1.00 MCS A
1.00 MCS B
1.00 MCS C
1.00 MCS C
1.00 MCS D
1.00 MCS D
1.00 MCS A
1.00 MCS C
1.00 MCS C
1.00 MCS B
1.00 MCS D
1.00 MCS A
1.00 MCS B
1.00 MCS B
1.00 MCS D
1.00 MCS B
1.00 MCS A
75.00 Answers
022 AA2.03 76 029 G 2.2.22 77 038 G 2.2.4478 058 AA2.02 79 077 AA2.07 80 W/E05 G 2.4.3 81 033 AG2.2.40 82 067 AA2.12 83 WE06 EG2.1.23 84 WE09 EA2.1 85 008 G2.2.25 86 010 A2.02 87 026 A2.03 88 063 G 2.4.20 89 103 A2.03 90 028 A2.01 91 068 A2.04 92 071 G 2.4.8 93 G 2.1.4194 G 2.2.22 95 G 2.2.37 96 G 2.3.6 97 G2.3.798 G 2.4.1899 G2.4.3 100 SECTION 1 ( 25 items) 11/2009 Watts Bar SRO NRC License Exam 12/17/2009 1.00 MCS D
1.00 MCS B
1.00 MCS b
1.00 MCS D
1.00 MCS C
1.00 MCS A
1.00 MCS B
1.00 MCS B
1.00 MCS A
1.00 MCS C
1.00 MCS B
1.00 MCS A
1.00 MCS C
1.00 MCS*
B 1.00 MCS A
1.00 MCS A
1.00 MCS C
1.00 MCS D
1.00 MCS C
1.00 MCS C
1.00 MCS B
1.00 MCS B
1.00 MCS A
1.00 MCS D
1.00 MCS D
25.00 ill 022 AA2.03 76 029 G 2.2.22 77 038 G 2.2.44 78 058 AA2.02 79 077 AA2.07 80 W/E05 G 2.4.381 033 AG2.2.40 82 067 AA2.12 83 WE06 EG2.1.23 84 WE09 EA2.1 85 008 02.2.25 86 010 A2.02 87 026 A2.03 88 063 G 2.4.20 89 103 A2.03 90 028 A2.01 91 068 A2.04 92 071 G 2.4.8 93 G 2.1.4194 G 2.2.22 95 G 2.2.37 96 G 2.3.6 97 G2.3.798 G 2.4.1899 G2.4.3 100 SECTION 1 ( 25 items) 11/2009 Watts Bar SRO NRC License Exam 12/17/2009 Points Type 1.00 MCS D
1.00 MCS B
1.00 MCS b
1.00 MCS D
1.00 MCS C
1.00 MCS A
1.00 MCS B
1.00 MCS B
1.00 MCS A
1.00 MCS C
1.00 MCS B
1.00 MCS A
1.00 MCS C
1.00 MCS B
1.00 MCS A
1.00 MCS A
1.00 MCS C
1.00 MCS D
1.00 MCS C
1.00 MCS C
1.00 MCS B
1.00 MCS B
1.00 MCS A
1.00 MCS D
1.00 MCS D
25.00 Answers