ML18045A123
| ML18045A123 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/14/2018 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-327/17-301, 50-328/17-301 50-327/OL-17, 50-328/OL-17 | |
| Download: ML18045A123 (104) | |
Text
- 1. Given the following:
- Unit 1 is operating at 100% power.
- 1-SI-IFT-099-90.8A, "Reactor Trip Instrumentation Monthly Functional Test (SSPS) Train A," is in progress.
- Reactor Trip Breaker A (RTA) is open.
Subsequently, conditions occur which meet an automatic reactor trip.
- The reactor fails to trip automatically.
- Operation of the manual reactor trip switch trips the reactor.
Which ONE of the following completes the statements below?
The manual trip switch inputs signals to the (1)
AND the (2) will open.
A. (1) shunt trip and UV coils (2) RTB and BYA breakers B. (1) shunt trip and UV coils (2) RTB only C. (1) shunt trip coil only (2) RTB and BYA breakers D. (1) shunt trip coil only (2) RTB only 1
- 2. Given the following:
- Unit 1 is at 100% power.
- The operating crew has entered AOP-R.05, RCS Leak and Leak Source Identification.
- Charging flow is maximized and pressurizer level is lowering.
- 1-TI-62-71, REGEN HX OUTLET TEMP - LETDOWN has lowered from its steady state value.
In accordance with AOP-R.05, which ONE of the following completes the statement below?
After letdown is manually isolated, operators (1) allowed to start an additional charging pump to stabilize pressurizer level and RCS leakage is from the charging line at point (2) of the drawing below.
A. (1) are (2) X B. (1) are (2) Y C. (1) are NOT (2) X D. (1) are NOT (2) Y 2
- 3. Given the following:
- A large break LOCA occurred.
- Operators have just completed transfer to containment sump.
- A loss of offsite power occurs.
In accordance with ES-1.3, "Transfer to RHR Containment Sump," which one of the following describes the operator actions required for this condition?
A. Place the SI pumps and CCPs in Pull-to-Lock until the RHR pumps have been restarted after the shutdown boards are reenergized.
B. Place the CCPs in Pull-to-Lock until the RHR pumps have been restarted after the shutdown boards are reenergized.
C. Ensure both RHR pumps are started by the blackout sequencers after the diesel generators reenergize the shutdown boards, then restart the SI pumps.
D. Ensure ALL ECCS pumps are started by the blackout sequencers when the diesel generators reenergize the shutdown boards.
3
- 4. Given the following:
- Unit 1 is in Mode 1 at 30% power
- All 4 RCPs are in service Subsequently, the following reator trip - SI status bistable lights illuminate:
Which ONE of the following completes the statement below?
In-Core average temperature will (1)
AND the above bistable indications (2) result in an AUTOMATIC reactor trip on loop low flow.
A. (1) lower (2) will B. (1) lower (2) will NOT C. (1) rise (2) will D. (1) rise (2) will NOT 4
- 5. Given the following:
- Unit 1 is in Mode 5 with the pressurizer solid.
- Train A RHR is operating in Shutdown Cooling.
- The following alarm is received:
"FCV-74-1/2 TROUBLE OR RHR PRESS HI (M6-C, E-7)"
- Operators are unable to reduce RCS pressure.
- The 1A-A RHR pump is stopped and RCS pressure continues to rise.
Which ONE of the following identifies ...
(1) the minimum RCS Pressure at which FCV-74-1 and 74-2 (RHR SUCTION FROM LOOP 4 HL) will be closed in accordance with AOP-R.03, "RHR System Malfunction" AND (2) the reason for this required action?
A. (1) 380 psig (2) Prevent RCS inventory loss B. (1) 380 psig (2) Prevent over-pressurization of the PRT C. (1) 450 psig (2) Prevent RCS inventory loss D. (1) 450 psig (2) Prevent over-pressurization of the PRT.
5
- 6. Which ONE of the following completes the statements below?
(1) #3 RCP Thermal Barrier Heat Exchanger will automatically isolate when the (1) setpoint is reached AND (2) the CCS flow through the #4 RCP Thermal Barrier Heat Exchanger will (2) ?
(1) (2)
A. Inlet flow > Outlet flow rise B. Inlet flow > Outlet flow isolate C. Outlet flow > Inlet flow rise D. Outlet flow > Inlet flow isolate 6
- 7. Given the following:
- Unit 1 is drawing a bubble in the Pressurizer
- PZR level cold cal is at 100%
- The OATC placed 1-PIC-68-340A, PZR PRESSURE CONTROL in MANUAL and the output failed to 25%
Which ONE of the following completes the statements below?
When the BACKUP HEATERS A and B heater control switches are placed in A-P AUTO from the OFF position they energize due to the (1) .
AND As the PZR liquid is heated for bubble formation letdown flow must be (2) to maintain a constant RCS pressure.
A. (1) pressure control malfunction (2) raised B. (1) pressure control malfunction (2) lowered C. (1) PZR level (2) raised D. (1) PZR level (2) lowered 7
- 8. Given the following:
- Unit 1 is at 98% power.
- A Steam Generator Tube Leak to the #1 SG is in progress.
- The crew has calculated a leak rate of 7 gpm.
- PZR level is stable.
- VCT level is at 12% and lowering.
- AUTO and MANUAL VCT make-up are NOT available.
Which ONE of the following completes the statement below?
In accordance with AOP-R.01, "Steam Generator Tube Leak", the reactor (1) required to be tripped AND Unit 1 (2) in compliance with the primary to secondary leakage specification of TS 3.4.13, "RCS Operational LEAKAGE".
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT 8
- 9. Given the following:
- A station blackout has occurred.
- ECA-0.0, "Loss of All AC Power," is in progress.
Which ONE of the following completes the statement below?
Prior to the restoration of AC power, the Pressurizer Power Operated Relief Valves (PORVs) (1) be able to be operated from the MCR AND the PORV Block Valves (2) be able to be operated from the MCR.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT 9
- 10. Given the following:
- Unit 1 has experienced a Loss of all AC.
- ECA-0.0, "Loss of All AC Power," is in progress.
In accordance with EA-250-1, "Load Shed of Vital Loads After Station Blackout",
(1) The maximum time for initial Load Shed actions to be completed is (1) and (2) the SSPS status lights (2) be available.
A. (1) 45 minutes (2) will B. (1) 45 minutes (2) will NOT C. (1) 90 minutes (2) will D. (1) 90 minutes (2) will NOT 10
- 11. Given the following:
- Unit 1 has experienced a Loss of all AC.
- ECA-0.0, "Loss of All AC Power," is in progress.
- EA-250-1, "Load Shed of Vital Loads after Station Blackout," is complete.
- Flex procedures are NOT implemented.
Which ONE of the following identifies the indications that operators will use in accordance with ECA-0.0 to determine the status of CST water supply to the TDAFW pump?
A. CST level on 1-M-2 B. CST level on 2-M-2 C. Condensate Transfer Pump Suction pressure D. TDAFW suction pressure 11
- 12. Given the following:
- Unit 1 & 2 are steady-state at 100% power.
- 125V DC Vital Battery Board IV is inadvertently deenergized.
- All 4 Diesel Generators start.
Which ONE of the following describes an effect this has on the diesel generators?
A. Diesel Generator 2B-B can be shutdown using the EMERGENCY STOP pushbutton on 0-M-26.
B. Diesel Generator 2B-B can be shutdown using the Local Panel EMERGENCY STOP pushbutton at the DG Building.
C. All engine trips except for overspeed on Diesel Generator 2B-B will be disabled and ALL generator trips will remain enabled.
D. All generator trips except for generator differential on Diesel Generator 2B-B will be disabled and ALL engine trips will remain enabled.
12
- 13. Given the following:
- The crew entered AOP-M.01, "Loss of Essential Raw Cooling Water," due to high flow on ERCW Supply Header 2A.
- The leak was isolated by closing 2-FCV-67-223, Hdr 2A to Hdr 1B Isol Valve.
Which one of the following describes the flow path of the ERCW Supply Header to the CCS heat exchangers after the leak is isolated?
[REFERENCE PROVIDED]
2A1/2A2 Hx OB1/OB2 Hx 1A1/1A2 Hx A. 2A ERCW Supply 2B ERCW Supply 1B ERCW Supply Header Header Header B. 2A ERCW Supply ERCW Isolated 1B ERCW Supply Header to Hx Header C. 2A ERCW Supply 2B ERCW Supply ERCW Isolated Header Header to Hx D. ERCW Isolated 2B ERCW Supply 1B ERCW Supply to Hx Header Header 13
- 14. Given the following:
- Unit 1 is in Mode 3 following a manual reactor trip due to a control air line break in the non-essential control air header.
- The crew has implemented AOP-M.02, "Loss of Control Air."
Which ONE of the following completes the statement below?
During the performance of AOP-M.02 local actions are required to control _________ due to the loss of non-essential control air.
A. RCS pressure B. RCS temperature C. SG levels D. PZR level 14
- 15. Which ONE of the following completes the statement below?
In accordance with AOP-P.07, Degraded Grid or Abnormal Voltage Conditions, the latest the transmission operator must be notified is within (1) of (2) .
(1) (2)
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> generator frequency of less than 59.5 Hz B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> loss of the automatic generator voltage regulator C. 30 minutes generator frequency of less than 59.5 Hz D. 30 minutes loss of the automatic generator voltage regulator 15
- 16. Given the following:
- Unit 1 was operating at 100% power.
- A Loss Of Coolant Accident (LOCA) outside containment results in RCS Subcooling of 0 oF and pressurizer level at 9%.
- The operating crew is performing ECA-1.2, "LOCA Outside Containment."
Which ONE of the following completes the statements below?
The first component expected to be manipulated in ECA-1.2 is (1) .
Confirmation the LOCA has been isolated would be a rising (2) .
(1) (2)
A. RHR suction from RCS Pressurizer level B. RHR suction from RCS RCS pressure C. RHR Cold Leg Injection Pressurizer level D. RHR Cold Leg Injection RCS pressure 16
- 17. Given the following:
- FR-H.1, "Response to a Loss of Secondary Heat Sink," is in progress.
- All SGs are completely dry and depressurized.
- RCS bleed and feed has been initiated.
- Containment pressure is 2.9 psig and stable.
Subsequently,
- Auxiliary Feedwater (AFW) capability is restored.
- All CETs are LOWERING.
Which ONE of the following completes the statements below?
With AFW restored the crew will feed one SG at (1)
AND Secondary heat sink is considered to be restored at (2) narrow range level.
A. (1) the maximum available rate (2) 10%
B. (1) the maximum available rate (2) 25%
C. (1) 50 - 100 gpm (2) 10%
D. (1) 50 - 100 gpm (2) 25%
17
- 18. Given the following:
- Unit 1 is in Mode 1 with 1A-A RHR pump tagged out.
Subsequently,
- A LOCA occurs and 1B-B RHR pump trips due to a locked rotor.
- The crew transitions to ECA-1.1, "Loss of ECCS Sump Recirculation."
- The conditions at the transition are:
- RCS pressure is 160 psig
- Containment pressure is 9.7 psid
- RWST level is 58%
- Containment sump level is 17%
When ALL ECA-1.1 steps to address Containment Spray Pump operation are completed, which ONE of the following identifies the number of Containment Spray Pump(s) that will be running and their suction source?
Number of Pumps Running Suction Source A. 1 RWST B. 1 Containment sump C. 2 RWST D. 2 Containment sump 18
- 19. Given the following:
- Unit 1 is at 80% power and stable.
- Rod control is in Automatic.
- CBD group 1 rods ONLY begin to withdraw continuously with the Urgent Failure Alarm not responding properly to stop movement.
- Operators place rod control in manual and rod withdrawal stops.
- CBD group 1 rods are now 14 steps greater than group 2.
Which ONE of the following completes the statement below?
In accordance with Tech Spec 3.1.4, "Rod Group Alignment Limits," Shutdown Margin is required to be verified __________.
A. immediately B. within a maximum of 15 minutes C. within a maximum of 30 minutes D. within a maximum of 60 minutes 19
- 20. Given the following:
- Unit 1 is at 75% power and stable.
- Pressurizer Level Control Selector Switch (XS-68-339E) is in the 339/335 position, and level control is in automatic.
- Subsequently,
- Temperature input to the PZR level control system fails to 530°F.
Which ONE of the following describes the effect this condition would have on the PZR level control system? (Assume NO operator action)
A. Charging initially rises to 120 gpm then returns to normal and PZR level stabilizes at a higher value.
B. Charging initially lowers to minimum flow and indicated PZR level lowers to 25%
where it stabilizes.
C. Charging lowers to minimum and indicated PZR level lowers until Letdown isolates, then level rises until the reactor trips.
D. Charging rises to 120 gpm and the PZR level rises until the reactor trips.
20
- 21. Given the following:
- Unit 1 is in Mode 6.
- An irradiated assembly is in the manipulator crane and is being transferred from an incore location to the upender.
- The Refueling SRO determines a leak has developed in the Reactor Cavity Seal.
- No assemblies are in the RCCA change fixture.
In accordance with AOP-M.04, "Refueling Malfunctions," which ONE of the following identifies the required action to be taken with the fuel assembly?
A. Place the fuel assembly in the upender and transport to the SFP.
B. Place the fuel assembly in the upender and lower the upender.
C. Place the fuel assembly in the RCCA change fixture.
D. Place the fuel assembly in any core location.
21
- 22. Given the following:
-Unit 1 is operating at 100%
Subsequently, a rise in secondary plant radiation levels with stable charging flow and pressurizer level require the crew to enter AOP-R.01, Steam Generator Tube Leak.
Which one of the following completes the statement below?
In accordance with AOP-R.01, the preferred indication for leak rate monitoring is the (1) radiation monitor AND IF the leak rate stabilizes at an acceptable level the secondary radiation monitor setpoints are raised to (2) .
Note:
Steam Generator Blowdown (SGBD) Radiation Monitor (1-RM-90-120 and 1-RM-90-121)
Condenser Vacuum Exhaust (CVE) Radiation Monitor (1-RM-90-99 and 1-RM-90-119)
A. (1) SGBD (2) provide prompt indication of a rise in leakage B. (1) SGBD (2) allow SGBD release to Con DI C. (1) CVE (2) provide prompt indication of a rise in leakage D. (1) CVE (2) allow SGBD release to Con DI 22
- 23. Given the following:
- Unit 1 turbine load is at 65% power.
- Condenser pressure is 1.8 psia and rising.
- Operators have entered AOP-S.02, "Loss of Condenser Vacuum."
Subsequently, the following indications are observed:
Time Condenser Pressure 0900 2.7 psia 0903 2.9 psia 0905 3.4 psia 0907 3.6 psia Based on the conditions listed above what is the earliest time a Reactor Trip is required in accordance with AOP-S.02?
A. 0900 B. 0903 C. 0905 D. 0907 23
- 24. Given the following:
- Unit 1 is at 100%
- Waste Gas Decay Tank (WGDT) A is in service
- WGDT B is in standby
- WGDT H is on HUT cover gas
- WGDT 'J' is being released Following increased radiation levels in the Auxiliary Building (AB), a pipe leak into the AB is discovered downstream of 0-77-751A, Isolation valve to cover gas header.
Which ONE of the following list the valves that must be repositioned to stop the leak?
NOTE: Assume system lineup is as shown on reference.
[REFERENCE PROVIDED]
A. 0-77-740A, Gas inlet header isolation valve and 0-77-742A, Gas Decay Tank Isol Valve.
B. 0-77-748J, "Isol Valve to Gas Release Header" and 0-77-749, "Gas Tank Discharge Isolation Valve Before HEPA Filter".
C. 0-77-751H, Isolation valve to cover gas header and 0-77-752, Header ISOL to Holdup Tanks.
D. 0-77-740A, Gas inlet header isolation valve, 0-77-739A, "Waste gas Compressor Discharge Valve" and 0-77-739B, "Waste gas Compressor Discharge Valve".
24
- 25. Given the following:
- The Main Control Room has been abandoned.
- The transfer switches per AOP-C.04, "Shutdown from the Auxiliary Control Room," have been placed in the AUX position.
- Aux Control Room alarm "PS-68-336AC RCS PRZR PRESS HI" has just been received .
Which ONE of the following identifies the lowest RCS pressure when the alarm is received and where the PZR Backup heaters will be operated?
RCS Pressure Location A. 2310 psig 6.9 Kv Shutdown Boards 1A-A & 1B-B B. 2310 psig 1-L-10, Auxiliary Control Room C. 2335 psig 6.9 Kv Shutdown Boards 1A-A & 1B-B D. 2335 psig 1-L-10, Auxiliary Control Room 25
- 26. Given the following:
- Unit 1 is operating at 100% power at BOL.
Subsequently, a reactor trip occurs.
- Shutdown Bank 'B' rod G3 remains at 228 steps.
- Control Bank 'D' rod M8 indicates 10 steps.
- Tavg dropped to 529°F and stable.
Which ONE of the following completes the statement below?
In accordance with ES-0.1, "Reactor Trip Response," Emergency Boration is ______ .
A. NOT required B. required due to the RCS temperature ONLY C. required due to the stuck control rods ONLY D. required due to BOTH the RCS temperature and the stuck control rods 26
- 27. Given the following:
- Unit 1 has experienced a reactor trip with a loss of offsite power.
- The operating crew has entered ES-0.2, "Natural Circulation Cooldown."
Which ONE of the following identifies the maximum allowed RCS cooldown rate and the method for dumping steam for the RCS cooldown?
Rate RCS Cooldown Method A. 50°F / hour Atmospheric Relief Valves B. 50°F / hour Steam Dumps C. 100°F / hour Atmospheric Relief Valves D. 100°F / hour Steam Dumps 27
- 28. Given the following:
- Unit 1 is in Mode 3 with the reactor trip breakers open and the RCS at normal operating temperature and pressure.
- The following annunciators alarm:
1-XA-55-5B, B REAC COOL PMPS SEAL LEAKOFF HIGH FLOW 1-XA-55-5B, E REAC COOL PMPS SEAL WATER TEMP HI
- MCR indications for Loop 3 RCP seal parameters are:
Supply 9.6 gpm and stable Leakoff 8.4 gpm and stable Outlet Temperature 178°F and rising slowly
- 1-XA-55-5B, C REAC COOL PMP 3 STANDPIPE LVL HIGH-LOW, is DARK.
- The operating crew enters AOP-R.04, "RCP Malfunctions" and removes the pump from service.
Which ONE of the following identifies...
(1) the RCP seal that has failed, AND (2) how the seal return valve will be positioned following the RCP coastdown?
Seal Failed #1 Seal return valve A. #1 Seal closed B. #1 Seal remain open C. #2 Seal closed D. #2 Seal remain open 28
- 29. Given the following:
- Unit 1 is at 100% power.
- 1-FCV-62-93, Charging Flow Control Valve is in Manual.
- 1-FCV-62-89, Charging Seal Water Flow Control Valve, is operating at 60%
open.
- Due to a positioner failure, 1-FCV-62-89 throttles close, and sticks at the 30% open position.
What effect will this malfunction have on charging pump discharge pressure and RCP seal injection flow?
Charging Pump RCP Seal Discharge Press Injection Flow A. Lowers Rises B. Rises Lowers C. Rises Rises D. Lowers Lowers 29
- 30. Given the following:
- Auto Makeup occurred due to VCT level Subsequently, LT-62-130A, VCT Level (ICS computer point L0112A) failed low to 0%
- The following indications are observed:
Which ONE of the following completes the statements below?
Makeup flow indications for the given controller setpoints (1) as expected and the AUTO Makeup (2) stop automatically.
A. 1) are
- 2) will B. 1) are
- 2) will NOT C. 1) are NOT
- 2) will D. 1) are NOT
- 2) will NOT 30
- 31. Given the following:
- Unit 1 is in Mode 4 cooling down for a refueling outage.
- RHR is in shutdown cooling mode.
Subsequently,
- A LOCA occurs with RCS temperature at 234°F.
- The operating crew is responding in accordance with AOP-R.02, "Shutdown LOCA," and the following parameters exist:
- RCS temperature (CETs) is 234°F and lowering.
- RCS pressure is 50 psig and lowering.
- The crew is on step 18:
Based on the conditions above which ONE of the following completes the statements below?
Currently, RHR injection (1) required.
AND If RHR injection is required, the time to cool RHR and realign the RHR pump for ECCS (2) a time critical action?
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT 31
- 32. Given the following:
- Unit 2 is in Mode 4 cooling down.
- RCS temperature is at 340 °F and slowly lowering.
- RCS pressure is at 340 psig and slowly lowering.
- LTOP is armed.
SI-OPS-068-001.0, "Low Temperature Overpressure Protection," is complete.
Subsequently,
- A Safety Injection occurs on high containment pressure due to a LOCA.
Which ONE of the following completes the statements below?
The RHR pumps (1) auto start.
The SI pumps (2) inject into the RCS.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT 32
- 33. Given the following:
- Unit 1 is at 90% power.
- Due to a leaking PORV, 1-FCV-68-332, BLOCK VLV FOR PORV 334, was closed.
- The following indications are observed:
Which ONE of the following identifies the parameter(s) above, if any, that are procedurally required to be adjusted?
A. PRT pressure ONLY B. PRT temperature ONLY C. BOTH PRT pressure and temperature D. Neither parameter requires adjustment.
33
- 34. Given the following:
- Unit 1 is being cooled down and has been placed in shutdown cooling with 'A' Train RHR in service.
- Annunciator "RHR HX A OUTLET TEMPERATURE HIGH" alarms on 0-XA-55-27B-A, E-6 "Component Cooling."
- Temperature on 1-TI-70-157, "RHR Heat Exchanger 1A Outlet Temperature," reads 120°F and stable.
In accordance with the Annunciator Response Procedure, which ONE of the following completes the statement below?
It is (1) to operate with the CCS temperature leaving the heat exchanger above the alarm setpoint and (2) could be used to lower the CCS temperature.
(1) (2)
A. acceptable lowering RHR heat exchanger bypass flow B. acceptable raising RHR heat exchanger bypass flow C. NOT acceptable lowering RHR heat exchanger bypass flow D. NOT acceptable raising RHR heat exchanger bypass flow 34
- 35. Which ONE of the following identifies the Normal and Alternate power supplies to the C-S CCS Pump?
Normal Alternate A. 6.9 KV Shutdown Board 2B-B 6.9 KV Shutdown Board 1A-A B. 6.9 KV Shutdown Board 1A-A 6.9 KV Shutdown Board 2B-B C. 480V Shutdown Board 2B2-B 480V Shutdown Board 1A2-A D. 480V Shutdown Board 1A2-A 480V Shutdown Board 2B2-B 35
- 36. Given the following:
- Unit 1 is operating at 100% power.
- Pressure Control Channel Selector Switch, 1-XS-68-340D is selected to PT-68-340 & 334 position.
Subsequently, PT-68-334, Pressurizer Pressure Transmitter, fails LOW.
- The operating crew enters AOP-I.04, "Pressurizer Instrument and Control Malfunctions."
Which ONE of the following completes the statements below?
Before any operator actions occur, the failure (1) result in the pressurizer back-up heaters being energized.
When AOP-I.04 performance is completed (2) of the PORVs will be able to automatically open if pressurizer pressure begins rising.
(1) (2)
A. will both B. will only one C. will NOT both D. will NOT only one 36
- 37. Given the following:
- Unit 2 is in Mode 3 with a cooldown in progress in accordance with 0-GO-7, "Unit Shutdown from Hot Standby to Cold Shutdown."
- The loop spray valve controllers (2-PCV-340B and 340D) have been placed in MANUAL to support maintenance.
Which ONE of the following completes the statements below?
To provide adequate spray flow through the Loop 2 Spray Valve, the minimum RCP alignment is (1) running.
The PZR heater groups C and D (2) required for Technical Specification compliance.
A. (1) #2 RCP and one other (2) are B. (1) #2 RCP and one other (2) are NOT C. (1) #2 RCP ONLY (2) are D. (1) #2 RCP ONLY (2) are NOT 37
- 38. Given the following:
- Unit 1 shutdown is in progress.
- Reactor power is 14% and lowering.
- Intermediate Range NI-36 fails HIGH.
Which ONE of the following identifies how the failure of NI-36 will affect the reactor trip system and the effect the failure will have on the Source Range NIs?
Reactor Trip System Effect on Source Range NIs A. Reactor trip will occur at Source Range NIs will the time of failure. AUTOMATICALLY reinstate.
B. Reactor trip will occur at Source Range NIs will have the time of failure. to be MANUALLY reinstated.
C. Reactor trip will occur if Source Range NIs will the power reduction is AUTOMATICALLY reinstate.
continued.
D. Reactor trip will occur if Source Range NIs will have the power reduction is to be MANUALLY reinstated.
continued.
38
- 39. Given the following:
- Unit 1 is operating in Mode 1.
- Bypass Breaker BYA is closed in preparation for Train-A SSPS testing.
Subsequently,
- Bypass Breaker BYB is inadvertently racked in and closed.
Which ONE of the following identifies the response of the plant?
A. No Reactor Trip or alarm.
B. Reactor will Trip.
C. "Protection System Train-B Trouble" alarm, no Reactor Trip.
D. Bypass Breaker BYB will trip open, no Reactor Trip.
39
- 40. Given the following:
- The operating crew is responding to a loss of 120V AC Vital Instrument Power Board I-I.
- PZR pressure transmitter 1-PT-68-334 (Channel II) fails LOW.
Which ONE of the following describes the plant response?
A. Both trains of SSPS SI master relays would actuate AND both trains of ECCS equipment auto start.
B. Both trains of SSPS SI master relays would actuate BUT only "B" train ECCS equipment auto starts.
C. Only the "B" train SSPS SI master relays would actuate BUT both trains of ECCS equipment auto start.
D. Only the "B" train SSPS SI master relays would actuate AND only "B" train ECCS equipment auto starts.
40
- 41. Given the following:
- Reactor Trip & Safety Injection occurred due to Large Break LOCA on Unit 1.
- Containment Phase B Isolation has occurred.
Which ONE of the following describes the response of the Lower Compartment Coolers?
Running Fans Cooler ERCW Isolation Valves A. Remain on Remain open B. Remain on Will close C. Auto Stop Remain open D. Auto Stop Will close 41
- 42. Which ONE of the following Ice Condenser temperatures is within the optimum range to minimize sublimation, frost buildup, and ice condenser door binding problems?
o A. 18 F B. 21oF C. 24oF D. 27oF 42
- 43. Given the following:
- A large break LOCA occurs on Unit 1.
- 1A-A Containment Spray (CS) Pump is out of service.
- ES-1.3, "Transfer To RHR Containment Sump," has been completed.
- 60 minutes later, the following conditions exist:
- Containment pressure is 10 psig and steady.
- 1B-B CS Pump discharge flow is 4000 gpm.
Which ONE of the following completes the statement below?
Containment spray flow is (1)
AND RHR spray (2) be placed in service.
(1) (2)
A. NORMAL should B. NORMAL should NOT C. LOWER than normal should D. LOWER than normal should NOT 43
- 44. Given the following:
- The #3 SG MSIV failed to close manually when operated during the performance of E-0, "Reactor Trip or Safety Injection."
- EA-1-1, "Closing MSIVs Locally" is complete and all 125v control power fuses for #3 MSIV have been removed.
Which ONE of the following completes the statement below?
The #3 SG MSIV valve position is ____.
A. available at 6K Monitor Lights panel (1-XX-55-6K) ONLY B. available at #3 MSIV Handswitch (1-HS-1-22A) on 1-M-4 ONLY C. NOT available from 6K Monitor Lights panel or #3 MSIV Handswitch D. available from BOTH 6K Monitor Lights panel and #3 MSIV Handswitch 44
- 45. Given the following:
- Unit 1 is stable at 100% power.
- A plant transient has occurred that has affected the SG level control system.
- Ten seconds after the transient began, the following indications are noted on associated loop 1 indications (all other loops are reading the same as loop 1):
Which ONE of the following identifies the Main Feed Reg Valve response at this time and the indication, if any, generating the signal(s) demanding that response? (Assume NO operator action)
A. MFRVs will continue to maintain their current position.
B. MFRVs will modulate open based on SG level indications ONLY.
C. MFRVs will modulate open based on the feed flow / steam flow indications ONLY.
D. MFRVs will modulate open based on BOTH feed flow / steam flow indications AND SG level indications.
45
- 46. Which ONE of the following is the Normal power supply for the Unit 2 TDAFW pump Trip and Throttle valve, 2-FCV-1-51A-S?
A. 125V DC Vital Board I B. 125V DC Vital Board II C. 125V DC Vital Board III D. 125V DC Vital Board IV 46
- 47. Given the following:
- Unit 1 & 2 are operating steady-state at 100%.
- 1B-B 6900V Shutdown Board voltage lowers to 6450V.
- The following alarms are received:
XA-55-26B window C-7, "6900V SD BD 1B-B FAILURE OR BUS UNDERVOLTAGE."
XA-55-1B, window B-6, "6900V SD BD 1B-B FAILURE OR BUS UNDERVOLTAGE/OVERVOLTAGE."
If the voltage remains unchanged, which ONE of the following identifies when the 1B-B 6.9 kV Shutdown Board Normal Feeder Breaker would open?
A. 1.25 seconds B. 9.5 seconds C. 30 seconds D. 300 seconds 47
- 48. Given the following:
- Loss of off site power occurred on Unit 1 resulting in a Reactor Trip and Safety Injection.
- The Emergency Diesel Generators (EDGs) started and EDG 1A-A loaded to 4.6 MWs.
In accordance with AOP-P.01, "Loss of Offsite Power", which ONE of the following describes the operation of EDG 1A-A under this load condition?
A. May operate indefinitely.
B. Must be immediately tripped.
C. May operate for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before excess EDG load must be reduced.
D. May operate for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before excess EDG load must be reduced.
48
- 49. Given the following:
Which ONE of the following identifies ...
- 1) the failure that caused these indications AND
- 2) the required operator action in accordance with the alarm response procedure?
A. 1) Vital Charger I has tripped
- 2) Place Spare Charger 1-S in service to Vital Battery Board I B. 1) Vital Charger I has tripped
- 2) Place Spare Charger 2-S in service to Vital Battery Board I C. 1) A ground on Vital Battery Board I
- 2) Locally adjust red flag set point to clear the control room alarm.
D. 1) A ground on Vital Battery Board I
- 2) Open breakers one at a time on Vital Battery Board I until the ground clears.
49
- 50. Given the following:
- Unit 1 is at 100% power.
Subsequently,
- A loss of offsite power occurs
- Fifteen (15) seconds after 1A-A 6.9kv Shutdown Board was energized by the 1A-A D/G, the following plant conditions are observed:
- 1A-A AFW pump is NOT running What are the required operator actions to restore the CCP and the AFW pump?
1A-A CCP 1A-A AFW Pump A. Monitor for Automatic Start Monitor for Automatic Start B. Manually Start Manually Start C. Manually Start Monitor for Automatic Start D. Monitor for Automatic Start Manually Start 50
- 51. Given the following:
- Annunciator 0-XA-55-26A, LS-18-3 Main Fuel Oil STG Tank 1 or 2 Low Level, has alarmed.
- The dispatched AUO reports that the No. 2 Fuel Oil Storage Tank (FOST) level is 4.0 feet and lowering and fuel oil is leaking into the FOST moat.
- All other diesel parameters are normal.
Which ONE of the following completes the statement below?
Unit 1 (1) in compliance with LCO 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, and the affected diesels (2) have at least 7 days of fuel left.
A. (1) is (2) do B. (1) is (2) do NOT C. (1) is NOT (2) do D. (1) is NOT (2) do NOT 51
- 52. Given the following:
- A release of the Neutralization Tank is in progress from the Condensate DI
- FCV-14-187, Neutralization Tank Outlet Isolation Valve, automatically closes Which ONE of the following conditions could cause the automatic closure of FCV-14-187?
A. Low level in the Neutralization Tank.
B. 0-RM-90-212, Turbine Building Sump Rad Monitor.
C. Hi Rad Signal from 0-RM-90-225, Cond DI Waste Effluent Monitor.
D. 0-FT-27-175, Cooling Tower Blowdown Flow, transmitter fails downscale.
52
- 53. In accordance with AOP-M.01, "Loss of Essential Raw Cooling Water", which ONE of the following completes the statement below?
If running, (1) pumps may experience bearing failure (2) minutes after a loss of ERCW cooling.
A. 1) Containment Spray
- 2) 10 minutes C. 1) Containment Spray
- 2) 15 minutes 53
- 54. Given the following:
- Unit 1 is in Mode 3, preparing for reactor startup.
- An air leak on the non-essential air header inside Unit 1 containment has developed.
- 1-FCV-32-110, Nonessential Air to Rx Bldg U-1 Isol, automatically closes.
Which ONE of the following completes the statement below?
As pressure on the header drops to 0 psig, CVCS Letdown Orifice isolation valves will (1) and ERCW TCVs for the Lower Containment Fan Coolers will (2) .
(1) (2)
A. be unaffected fail as is B. be unaffected fail open C. fail closed fail as is D. fail closed fail open 54
- 55. Which ONE of the following completes the statement below regarding Phase B Containment Isolation?
The coincidence for an Automatic Phase B Containment Isolation is (1) bistables AND to initiate a Manual Phase B Containment Isolation, the operator will place a minimum of (2) of the Phase B handswitches on panel 2-M-6 to ACTUATE.
A. (1) 2 of 3 (2) one B. (1) 2 of 3 (2) two C. (1) 2 of 4 (2) one D. (1) 2 of 4 (2) two 55
- 56. Given the following:
- A Small Break LOCA has occurred on Unit 1.
- RCS Subcooling is less than 40oF.
- RCPs are NOT in service.
o o
- All Core Exit T/Cs are between 710 F to 720 F and slowly rising.
- RVLIS Dynamic Range indications (1-LI-68-367 & 370) are 17% and stable.
- RVLIS Lower Range indications (1-LI-68-368 & 371) are 38% and slowly lowering.
Which ONE of the following completes the statements below?
(1) will be used to determine the state of core cooling AND FR-C.1, "Inadequate Core Cooling," (2) be entered.
A. (1) RVLIS Lower Range (2) will B. (1) RVLIS Lower Range (2) will NOT C. (1) RVLIS Dynamic Range (2) will D. (1) RVLIS Dynamic Range (2) will NOT 56
- 57. Given the following:
- Unit 1 is at 100% power.
- Pressurizer Level Control Selector Switch, 1-XS-339E, is selected to the LT-68-339/320 position.
Which ONE of the following failures would result in a reactor trip in the shortest time assuming all systems respond as designed and there is NO operator action?
(Consider each failure to occur independently)
A. 1-LT-68-339 fails LOW B. 1-LT-68-339 fails HIGH C. 1-LT-68-320 fails LOW D. 1-LT-68-320 fails HIGH 57
- 58. Given the following:
- Unit 1 is at 100% power.
- CBD group demand counters read 220 steps.
- CBD Rod D-4 is the highest indicated individual rod position at 218 steps.
- All other Rods in CBD indicate 216 steps.
Subsequently,
- RPI indication for CBD rod H-12 fails to 207 steps.
Which ONE of the following completes the statement below?
Annunciator 1-XA-55-4B D-4, COMPUTER ALARM ROD DEV & SEQ NIS PWR RANGE TILTS is ____________.
A. NOT in alarm B. in alarm due to the Rod to Bank Demand deviation ONLY C. in alarm due to the Rod to Rod deviation ONLY D. in alarm due to BOTH the Rod to Bank Demand and Rod to Rod deviation 58
- 59. Given the following:
- Both Units are in Mode 1
- An alarm is received on 0-M-29, Fire Detection System.
- The CRO determines the alarm to be Cross Zone alarms from Zones 522 and Zone 523, both in Unit 2 Aux Building Supply Duct.
Which ONE of the following identifies ...
(1) how the Aux Bldg Fans are affected AND (2) the requirements for dispatching the Fire Brigade?
A. (1) Only the Aux Bldg Supply fans trip (2) Immediately dispatch the Fire Brigade.
B. (1) Only the Aux Bldg Supply fans trip (2) Confirm the alarms are valid prior to dispatching the Fire Brigade.
C. (1) All Aux Bldg Supply, Exhaust and Fuel Handling Exhaust fans trip (2) Immediately dispatch the Fire Brigade.
D. (1) All Aux Bldg Supply, Exhaust and Fuel Handling Exhaust fans trip (2) Confirm the alarms are valid prior to dispatching the Fire Brigade.
59
- 60. Which ONE of the following is the power supply to the Emergency Gas Treatment System (EGTS) Fan B?
A. Reactor Vent Board 1B-B B. Reactor Vent Board 2B-B C. C & A Vent Board 1B1-B D. C & A Vent Board 2B1-B 60
- 61. Given the following:
- Unit 1 is in Mode 1
- A lower containment purge is in progress RM-90-106 and 1-RM-90-131 indications are rising due to an RCS leak.
Note: 1-RM-90-106, Lower Containment Radiation Monitor 1-RM-90-131, Containment Purge Radiation Monitor Which ONE of the following completes the statement below?
When the High Radiation Setpoint is reached for the (1) Radiation Monitor a Containment Vent Isolation signal will be initiated AND After the Containment Vent Isolation, the 1-RM-90-106 control board reading (2) a valid indication.
A. (1) 1-RM-90-106 (2) is B. (1) 1-RM-90-106 (2) is NOT C. (1) 1-RM-90-131 (2) is D. (1) 1-RM-90-131 (2) is NOT 61
- 62. Given the following:
- Annunciator AR-M12-B, B-5, "0-RA-90-103A FUEL POOL RAD MONITOR HI RAD", alarms.
Which ONE of the following completes the statement below?
In accordance with the annunciator response for AR-M12-B, B-5, an operator will have to manually actuate (1) ABI AND the purpose of the ABI actuation is to (2) .
A. (1) Train A (2) limit dose rates at the site boundary to less than federal limits.
B. (1) Train A (2) ensure any ABSCE boundary release is monitored by a PAM qualified radiation monitor.
C. (1) Train B (2) limit dose rates at the site boundary to less than federal limits.
D. (1) Train B (2) ensure any ABSCE boundary release is monitored by a PAM qualified radiation monitor.
62
- 63. Given the following:
- Unit 1 is at 100% power.
- A reactor trip is initiated by operator action.
- Reactor Trip Breaker A (RTA) does NOT open.
Which ONE of the following identifies the response of the steam dump system?
The steam dumps will maintain the RCS Tavg at (1) with the (2) controller.
A. (1) 549°F (2) reactor trip B. (1) 549°F (2) load rejection C. (1) 552°F (2) reactor trip D. (1) 552°F (2) load rejection 63
- 64. Which ONE of the following completes the statement below?
Before a liquid radwaste release can occur, the tank to be released must be recirculated for a minimum of (1) to prevent (2) .
A. 1) 30 minutes
- 2) obtaining a sample that is not representative of the tank contents B. 1) 30 minutes
- 2) the need for the process rad monitor(s) to be flushed prior to the release C. 1) 60 minutes
- 2) obtaining a sample that is not representative of the tank contents D. 1) 60 minutes
- 2) the need for the process rad monitor(s) to be flushed prior to the release 64
- 65. Given the following:
- Both units are operating at 100% power.
- Control air system pressure begins to drop.
Which ONE of the following identifies...
(1) the pressure setpoint that the 0-PCV-33-4, "Service Air isolation from Control Air", will close AND (2) the expected position of 0-FCV-32-82, "Train A Control Air Supply Valve," if the air pressure is stabilized at 73 psig?
0-PCV-33-4 0-FCV-32-82 A. 88 psig Open B. 88 psig Closed C. 77 psig Open D. 77 psig Closed 65
- 66. Given the following:
- Unit 1 at 100% power with Boric Acid Tank (BAT) A aligned.
- RWST Boric Acid concentration is 2550 ppm.
Which ONE of the following identifies BAT A Volume and Boric Acid Concentration that will meet Functionality requirements for TR 8.1.1, Borating Systems - Operating?
[REFERENCE PROVIDED]
A. 9600 gallons at 6500 ppm B. 9400 gallons at 6575 ppm C. 9250 gallons at 6775 ppm D. 9750 gallons at 6375 ppm 66
- 67. Given the following:
- A Unit 2 automatic Safety Injection occurred 1 minute ago.
Which ONE of the following completes the statement below?
The indicated valve position for 0-FCV-67-152 (1) as expected AND the indicated valve position for 2-FCV-67-146 (2) as expected.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT 67
- 68. Which ONE of the following completes the statement below?
Spent Fuel Pool temperature alarms __________.
A. on Unit 1 ONLY B. on Unit 2 ONLY C. on BOTH Units D. locally ONLY 68
- 69. Given the following:
- "PNL 1-M-7 Trouble" annunciator on 1-XA-55-1C is lit due to a blown fuse on 1-M-7 Preferred Power Rack .
- This is the first time the fuse has blown.
- A 'like-for-like' replacement fuse matching the installed fuse is available.
In accordance with OPDP-7, "Fuse Control" which ONE of the following completes the statements below?
A WO to 'troubleshoot the circuit' (1) required prior to the fuse replacement.
The Control Room Operator (CRO) (2) allowed to perform the fuse replacement.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT 69
- 70. While performing a cooldown on Unit 1 from Mode 3 to Mode 4 the following parameters were logged:
Time RCS Temp PZR LIQ Space Temp 0200 553°F 650°F 0230 527°F 606°F 0300 505°F 560°F 0330 447°F 494°F 0400 402°F 440°F Which ONE of the following completes the statement below?
RCS cooldown limits (1) exceeded AND PZR cooldown limits (2) exceeded.
A. (1) were (2) were B. (1) were (2) were NOT C. (1) were NOT (2) were D. (1) were NOT (2) were NOT 70
- 71. In accordance with EPIP-15, "Emergency Exposure Guidelines," which ONE of the following individuals must authorize emergency exposure limits in excess 10CFR20 limits?
A. RP Manager B. Plant Manager C. Site Vice President D. Site Emergency Director 71
- 72. Given the following:
- Unit 1 is in Mode 6, with core reload in progress.
- The Shutdown Monitor was last reset when the count rate was 6 cps.
- As the 20th fuel assembly is being set in the core, both source range monitor count rates begin rising.
Which ONE of the following listed 'count rates' is the lowest that would result in 1-X-55-4B, B-1, SOURCE RANGE HI FLUX AT SHUTDOWN being in alarm AND where the SOURCE RANGE HI FLUX AT SHUTDOWN alarm can be reset once counts have dropped below the alarm setpoint?
A. (1) 13 cps (2) 1-M-4 B. (1) 13 cps (2) 1-M-13 C. (1) 19 cps (2) 1-M-4 D. (1) 19 cps (2) 1-M-13 72
- 73. Given the following:
- Reactor power is 100%.
- A reactor trip setpoint has been exceeded.
- Both the reactor and turbine will not trip via their respective control room trip switches.
Which ONE of the following identifies the immediate operator actions that the OATC and the CRO will perform per FR-S.1 "Nuclear Power Generation / ATWS?"
OATC CRO A. Maintain auto or manual rod Close main turbine governor insertion at max achievable rate. valves using the VPL or, if they cannot be closed, close MSIVs and MSIV bypass valves.
B. Maintain auto or manual rod Reduce turbine load using insertion at max achievable rate. turbine load controls at 200% per minute or, if controls do not respond, close MSIVs and MSIV bypass valves.
C. Initiate emergency boration from Close main turbine governor either the BAT or RWST. valves using the VPL, or if they cannot be closed, close MSIVs and MSIV bypass valves.
D. Initiate emergency boration from Reduce turbine load using either the BAT or RWST. turbine load controls at 200% per minute or, if controls do not respond, close MSIVs and MSIV bypass valves.
73
- 74. Given the following:
Which ONE of the following completes the statements below?
In accordance with EPM-4, "User's Guide," 1-PR-1-2 "SG PRESSURE" (1) a Post Accident Monitoring (PAM) indication and 1-PI-1-2A "SG-1 PRESSURE" (2) a PAM indicator.
A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT 74
- 75. Given the following:
- Unit 1 was operating at 100% power when a LOCA occurs.
- Safety Injection automatically initiated but the reactor failed to trip and the operating crew was unable to trip the reactor from the MCR handswitches.
- FR-S.1, "Nuclear Power Generation/ATWS," has been entered.
- During performance of FR-S.1 Step 3, Check AFW status, the following conditions exist:
- Containment pressure is 3.0 psig and rising.
- RCS pressure is 1230 psig and dropping.
- Reactor power is 9% and dropping.
Which ONE of the following completes the statement below?
The RCPs (1) be tripped because (2) .
(1) (2)
A. are required to of the small break LOCA design basis requirements B. are required to the normal running support systems are not satisfied C. should NOT Immediate Operator Actions have not been completed D. should NOT reduced RCS heat removal could challenge fuel integrity 75
- 76. Given the following:
- Unit 1 at 100% power when a pressurizer safety valve failed open.
- The operator manually tripped the reactor and initiated a safety injection.
- While performing the step to determine if the RHR pumps should be stopped in accordance with E-1, "Loss of Reactor or Secondary Coolant", the crew determines the following:
- The safety closed when pressurizer pressure dropped to 1280 psig.
- Containment pressure rose to 2.6 psig, and began trending down.
- Pressurizer level is 100%.
- RCS subcooling is 43oF.
- All four SG levels at 33% narrow range.
Which ONE of the following identifies the correct procedure implementation and operation of the RCPs for the above conditions?
Note:
ES-1.1, "SI Termination" ES-1.2, "Post LOCA Cooldown" A. Transition from E-1 to ES-1.1; The RCPs will have remained running throughout the event.
B. Transition from E-1 to ES-1.1; The RCPs would have been secured but will be restarted in ES-1.1.
C. Continue E-1 to terminate SI until a transition is directed to ES-1.2; The RCPs will have remained running throughout the event.
D. Continue E-1 to terminate SI until a transition is directed to ES-1.2; The RCPs would have been shutdown but will be restarted in ES-1.2.
76
- 77. Given the following:
- Unit 1 is in Mode 5 at 190°F
- 1A-A RHR pump flow = 3000 gpm
- 1A-A RHR pump amps = 20 amps
- 1A-A RHR discharge pressure = 140 psig
- RCS pressure = 60 psig Subsequently, a malfunction occurs which results in the following 1A-A RHR pump parameters:
- Pump flow = 0 gpm
- Pump amps = 3 amps
- Discharge pressure = 60 psig Which ONE of the following completes the statement below?
The 1A-A RHR pump indications were caused by (1)
AND in accordance with Tech Spec 3.4.7, "RCS Loops-Mode 5 Loops Filled," the bases for maintaining one RHR loop in operation is (2) .
A. (1) a 1A-A RHR pump shaft shear (2) for decay heat removal and proper boron mixing B. (1) a 1A-A RHR pump shaft shear (2) to maintain ability to continue plant cooldown C. (1) FCV-63-93, RHR Cold leg injection to Loops 2 & 3, failing closed (2) for decay heat removal and proper boron mixing D. (1) FCV-63-93, RHR Cold leg injection to Loops 2 & 3, failing closed (2) to maintain ability to continue plant cooldown 77
- 78. Given the following:
- Unit 1 has entered E-1, "Loss of Reactor or Secondary Coolant."
- Both SI pumps are running.
Subsequently, the following indications are observed:
- RCS pressure is 1000 psig and lowering.
- Containment pressure is 2.3 psig and rising.
Which ONE of the following completes the statement below?
When directed by the foldout page in E-1, the RCPs must be secured within (1)
AND the basis for securing RCPs is to (2) .
(1) (2)
A. 5 minutes prevent excessive depletion of RCS inventory through the break B. 5 minutes prevent damage to RCPs due to loss of support conditions C. 10 minutes prevent excessive depletion of RCS inventory through the break D. 10 minutes prevent damage to RCPs due to loss of support conditions 78
- 79. Given the following:
- Both Units were at 100% power when a Loss of Offsite Power occurs due to physical damage to the switchyard.
- Both Unit 2 DGs are supplying their respective Unit 2 shutdown board.
- The Unit 1 crew is performing ECA-0.0, "Loss of All AC Power."
- The crew was NOT able to start 1A-A or 1B-B Diesel Generator.
- RCS subcooling is 8°F.
- PZR level is 4% and lowering slowly.
Which ONE of the following identifies...
(1) the procedure that will be evaluated by the TSC for restoring power to 1A-A or 1B-B Shutdown Boards AND (2) the subsequent recovery procedure that will be performed by Unit 1 upon transition from ECA-0.0?
A. (1) AOP-P.01, "Loss of Offsite Power,"
(2) ECA-0.1, "Recovery From Loss of All AC Power Without SI Required."
B. (1) AOP-P.01, "Loss of Offsite Power,"
(2) ECA-0.2, "Recovery From Loss of All AC Power With SI Required."
C. (1) EA-202-4, "Emergency Use of 6900V Shutdown Utility Bus,"
(2) ECA-0.1, "Recovery From Loss of All AC Power Without SI Required."
D. (1) EA-202-4, "Emergency Use of 6900V Shutdown Utility Bus,"
(2) ECA-0.2, "Recovery From Loss of All AC Power With SI Required."
79
- 80. Given the following:
- Unit 1 is in Mode 4 with 'A' RHR aligned for shutdown cooling.
- Unit 2 is in Mode 1 at 100% power.
- 2B-B CCS pump is tagged out for maintenance.
Subsequently, the following occurs:
0900 - The C-S CCS pump trips. Both units enter AOP-M.03, "Loss of Component Cooling Water," and T.S. 3.7.7, Component Cooling Water System (CCS.)
0945 - All applicable sections of AOP-M.03 are complete.
1100 - The 1A CCS pump trips. Unit 1 enters AOP-M.03.
Which ONE of the following completes the statement below?
At 0945, Unit 2 (1) exit TS 3.7.7, Component Cooling Water System (CCS),
AND due to the failure at 1100, AOP-M.03 (2) require Unit 1 to perform AOP-R.03, "RHR System Malfunction."
A. 1) will
- 2) will B. 1) will
- 2) will NOT C. 1) will NOT
- 2) will D. 1) will NOT
- 2) will NOT 80
- 81. Given the following:
- Unit 1 is operating at 100% power when both Main Feedwater Pumps trip and the reactor fails to trip automatically and manually.
- All AFW pumps failed to start and cannot be started manually.
- SG LO-LO levels are reached.
- FR-S.1, "Nuclear Power Generation / ATWS," is currently being performed.
- Reactor Power has just been verified to be 4%, with a negative start up rate.
Which ONE of the following identifies proper procedure usage by the SRO?
Note:
FR-H.1, "Loss of Secondary Heat Sink" E-0, "Reactor Trip or Safety Injection" A. Immediately make the transition from FR-S.1 to FR-H.1.
B. Return to E-0 and transition to FR-H.1 when directed by E-0.
C. Continue in FR-S.1, transition to FR-H.1 when FR-S.1 required actions complete.
D. Return to E-0, complete immediate operator actions and then transition to FR-H.1.
81
- 82. Given the following:
- Unit 1 is defueled with fuel shuffles in progress in the Spent Fuel Pool.
- Personnel report that a leak has developed and level is dropping in the Spent Fuel Pool.
- The irradiated fuel assembly on the hoist is dropped from the Spent Fuel Handling Tool while restoring it to a cell location in the storage rack.
- Gas bubbles are reported to be rising in the Spent Fuel Pool.
- Spent Fuel Pool Rad Monitors 0-RM-90-102 and 0-RM-90-103 both rise to the alarm setpoint.
- The Spent Fuel Pool level stabilized one foot above the siphon breaker.
Which ONE of the following identifies the event declaration to be made and the external notification having the SHORTEST allowed time?
[REFERENCE PROVIDED]
Declaration Notification A. NOUE NRC B. NOUE State of Tennessee C. ALERT NRC D. ALERT State of Tennessee 82
- 83. Given the following:
- A Unit 1 reactor startup in accordance with GO-2, "Reactor Startup," is in progress with the reactor critical at 2.0 X10-3% power.
- The following window alarms on NIS/ROD CONTROL 1-XA-55-4B
- The operating crew determines Source Range CH I, 1-XX-92-5001, drawer has a blown Instrument Power fuse.
- The operating crew enters AOP-I.01, "Nuclear Instrumentation Malfunction."
Which ONE of the following completes the statements below?
Placing the drawer LEVEL TRIP switch to BYPASS in accordance with AOP-I.01, (1) prevent a reactor trip signal from being generated if power is reduced.
AND In accordance with TS 3.3.1, "Reactor Trip System Instrumentation" bases the Source Range Trip function provides protection (2) .
A. (1) will (2) against violating the DNBR limit B. (1) will (2) for an uncontrolled rod withdrawal C. (1) will NOT (2) against violating the DNBR limit D. (1) will NOT (2) for an uncontrolled rod withdrawal 83
- 84. Given the following:
- An event occurred 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> ago and the following area radiation monitors have been steadily rising over that period from a background level of < 1.00 E-1.
Which ONE of the following identifies the HIGHEST Emergency Plan Classification and the area radiation monitor that meets that threshold, if any?
[REFERENCE PROVIDED]
A. NOUE on 1-RM-90-10 CVCS BD AREA RADMON B. ALERT on 1-RM-90-10 CVCS BD AREA RADMON C. ALERT on 0-RM-90-135 MCR AREA AREA RADMON D. No Emergency Plan Classification thresholds are met.
84
- 85. Given the following:
- Unit 1 is at 100% power.
- When 1-HS-43-22, RCS Hot Leg inboard containment isolation sample valve, is placed in the closed position the valve indicates both RED and GREEN lights LIT.
- All indicators for 1-FSV-43-22 are showing the valve in an intermediate position.
- RCS Hot Leg outboard containment isolation sample valve, 1-FCV-43-23, is indicating closed.
Which ONE of the following completes the statements below?
In accordance with TS 3.6.3, "Containment Isolation Valves," removing control power from 1-FCV-43-23 (1) meet the Required Action Statement of the LCO.
AND TS 3.6.3, "Containment Isolation Valves" (2) allow unisolating the penetration under administrative controls if a dedicated operator is stationed to close the valve.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT 85
- 86. Given the following:
- Unit 1 at 100% power.
- An Eagle 21 malfunction has occurred that caused several annunciators to alarm and unexpected reactor trip bi-stables to be LIT.
- AOP-I.11, "Eagle 21 Malfunction," has been entered.
- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the event, MIG is prepared to initiate work on the failure.
Which ONE of the following completes the statements below?
The Unit Supervisor will direct performance of AOP-I.11, Section (1) to address the failure.
AOP-I.11 directs that the preferred action is to (2) .
A. (1) 2.1, "Test Sequence Processor (TSP) Subsystem Failure "
(2) hard trip bistables before attempting a system reset B. (1) 2.1, "Test Sequence Processor (TSP) Subsystem Failure" (2) attempt a system reset before hard tripping bistables C. (1) 2.2, "Loop Control Processor (LCP) Failure" (2) hard trip bistables before attempting a system reset D. (1) 2.2, "Loop Control Processor (LCP) Failure" (2) attempt a system reset before hard tripping bistables 86
- 87. Given the following:
- Unit 1 is operating at 100% power when the following annunciator alarms on 1-M-30:
"1-RA-421A MN STM LN HI RAD" The CRO reports the following Steam Line Radiation monitor readings:
Loop 1 Loop 2 Loop 3 Loop 4 mr/hr 9.35 E-4 9.95 E-3 1.12 E-3 8.93 E-4
- Pressurizer level is dropping rapidly.
- RCS activity is normal for a core with no fuel leaks.
- The SRO directs a reactor trip and safety injection to be initiated.
- When ready to isolate the affected steam generator, all 4 MSIVs fail to close and subsequent actions are unsuccessful in closing MSIVs.
- RWST level is 81% and slowly lowering.
Which ONE of the following identifies...
(1) the ruptured steam generator AND (2) the procedure transition required due to the failure of the MSIVs to close?
Steam Generator Procedure A. Loop 2 ECA-3.1, "SGTR and LOCA - Subcooled Recovery" B. Loop 2 ECA-3.2, "SGTR and LOCA - Saturated Recovery" C. Loop 3 ECA-3.1, "SGTR and LOCA - Subcooled Recovery" D. Loop 3 ECA-3.2, "SGTR and LOCA - Saturated Recovery" 87
- 88. Given the following:
- Unit 1 is performing a plant shutdown in accordance with 0-GO-7, "Unit Shutdown From Hot Standby To Cold Shutdown."
- When the 1B-B RHR pump was started for boron sampling, it experienced excessive vibration and is tagged out of service.
- Current plant conditions are:
- RCS temperature = 260°F
- RCS pressure = 325 psig
- SG conditions:
- 1 #2 #3 #4 5% Narrow Range 30% Narrow Range 9% Narrow Range 25% Narrow Range RCP Tagged RCP Running RCP available RCP available
- During post work review, I&C technicians report to the WCC SRO that the flow transmitter for 1-FCV-74-12A, RHR Pump 1A Mini-flow valve, has failed high.
Which ONE of the following completes the statements below?
Prior to taking any operator action the 1A-A RHR pump is (1)
AND in accordance with TS 3.4.6, "Reactor Coolant System - RCS Loops - MODE 4" bases, the LCO requirements for this specification (2) met.
A. (1) OPERABLE (2) are B. (1) OPERABLE (2) are NOT C. (1) INOPERABLE (2) are D. (1) INOPERABLE (2) are NOT 88
- 89. Given the following:
- Unit 1 is being cooled down following a shutdown for a refueling outage.
- With the RCS at 340°F a LOCA occurred resulting in a Safety Injection due to the containment pressure increase.
Subsequently, 125V DC Vital Battery Board I de-energized.
- While performing AOP-R.02, "Shutdown LOCA," the operating crew is unable to get either of the RHR containment sump valves, 1-FCV-63-72 or 1- FCV-63-73, to OPEN from the MCR.
- Subsequently, the following annunciator window alarms on 1-M-6E:
- LS-63-50B RWST LVL LO-LO Which ONE of the following completes the statements below?
The failure of the sump valves to open requires the crew to go to (1) .
'A' train pumps taking suction from the RWST that are required to be stopped (2) be operated from the Main Control Room.
(1) (2)
A. ECA-1.1, "Loss of RHR Sump Recirculation" can B. ECA-1.1, "Loss of RHR Sump Recirculation" can NOT C. AOP-R.03, "RHR System Malfunction" can D. AOP-R.03, "RHR System Malfunction" can NOT 89
- 90. Given the following:
- Unit 1 is at 100% power.
Time Event May 12 0815 The inner door of the lower containment airlock failed to meet acceptance criteria of 1-SI-SLT-088-259.2, Airlock Resilient Seal Leak Rate Test." The outer door is closed.
May 12 0900 The outer door of the lower containment airlock failed to meet acceptance criteria of 1-SI-SLT-088-259.2.
May 12 0945 Engineering reports Unit 1 overall containment leakage rate (La) is currently 0.05 La.
May 12 1045 Maintenance reports it will take at least 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to repair either airlock door.
What is the date and time Unit 1 is required to be in Mode 3 to complete the most restrictive applicable Technical Specification required action?
[REFERENCE PROVIDED]
A. May 12 1515 B. May 12 1600 C. May 13 1400 D. May 13 1500 90
- 91. Given the following:
- A transient involving control rod insertion has reduced power from 60%
to 50% power.
- The failure that caused the transient rendered the rod insertion limit computer inoperable.
- The following rod positions are observed on CBC and CBD (all other banks are full out):
Which ONE of the following completes the statements below?
Control rods are (1) the TS required limit.
In accordance with TS 3.1.6, "Control Bank Insertion Limits" bases, the control rod bank insertion limits ensure that (2) is met.
[REFERENCE PROVIDED]
A. (1) above (2) Shutdown margin B. (1) below (2) Shutdown margin C. (1) above (2) Departure from Nucleate Boiling ratio (DNBR)
D. (1) below (2) Departure from Nucleate Boiling ratio (DNBR) 91
- 92. Given the following:
- Unit 1 is at 99% power.
- In response to alarms and control board indications, the crew has determined that Quadrant Power Tilt Ratio is 1.03.
Which ONE of the following correctly states the REQUIRED power reduction per T.S 3.2.4, Quadrant Power Tilt Ratio?
[REFERENCE PROVIDED]
A. Power must be reduced to less than or equal to 97%.
B. Power must be reduced to less than or equal to 96%.
C. Power must be reduced to less than or equal to 91%.
D. Power must be reduced to less than or equal to 90%.
92
- 93. Given the following:
- A release of Waste Gas Tank "B" is in progress to the Unit 2 stack with 2-RM-90-400, "Unit 2 Shield Building Rad Monitor", and 0-RM-90-118, "Waste Gas Effluent Rad Monitor", both FUNCTIONAL.
Subsequently,
- Power is lost to 0-RM-90-118.
Which ONE of the following completes the statements below?
Operator action (1) be required to terminate the release.
The "Offsite Dose Calculation Manual (ODCM)" (2) procedurally allow the release to resume with 0-RM-90-118 non-Functional.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT 93
- 94. Given the following:
- Both units are at 100% power.
- Maintenance personnel need to perform work with an aerial lift in the switchyard.
Which ONE of the following completes the statement below in accordance with OPDP-2, "Switchyard Access and Switching Order Execution?"
At a minimum, approval of the activity is required by the (1) or designee AND a ground escort (2) required when the aerial lift is moving.
A. (1) Shift Manager (2) is B. (1) Shift Manager (2) is NOT C. (1) Security Shift Manager (2) is D. (1) Security Shift Manager (2) is NOT 94
- 95. Given the following:
- Unit 1 is at 100% power.
- One main steam safety valve has been determined to be inoperable due to relieving 100 psig below its setpoint.
Which ONE of the following completes the statement below in accordance with TS 3.7.1, "Main Steam Safety Valves (MSSVs)," and associated bases?
Reactor power will be limited to a maximum of (1) to ensure that secondary system pressure does not exceed a maximum of (2) of the steam generator design pressure.
A. (1) 45%
(2) 102%
B. (1) 45%
(2) 110%
C. (1) 62%
(2) 102%
D. (1) 62%
(2) 110%
95
- 96. Given the following:
- Unit 1 is in Mode 5
- An emergent maintenance activity is being planned that, given the current equipment availability, will result in both the Shutdown EOOS and Defense-in-Depth Assessment being RED In accordance with NPG-SPP-07.2.11, "Shutdown Risk Management," which ONE of the following completes the statement below?
The Defense-in-Depth checklist must be performed each (1)
AND the planned activity above is (2) .
A. (1) shift (2) allowed with authorization from the Plant Manager B. (1) shift (2) NOT allowed to occur under these plant conditions C. (1) day (2) allowed with authorization from the Plant Manager D. (1) day (2) NOT allowed to occur under these plant conditions 96
- 97. Given the following:
- Unit 2 is in MODE 1.
SI-OPS-063-129.A, 2A-A SI Pump Casing and Discharge Piping Vent, is being performed and is expected to be completed on the current shift.
- The following Technical Specifications will be entered during the performance of the surveillance:
- TS 3.5.2, ECCS - Operating Condition A
- TS 3.6.3, Containment Isolation Valves Conditions A and C Which of the following completes the statements below in accordance with OPDP-8, Operability Determination Process and Limiting Conditions for Operation Tracking?"
The TS entries (1) required to be entered in the LCO Tracking log.
AND The TS entries in the Unit Narrative log (2) required to be peer checked by a second SRO.
A. (1) are (2) are B. (1) are (2) are NOT C. (1) are NOT (2) are D. (1) are NOT (2) are NOT 97
- 98. Given the following:
- Rad Waste water inventory is approaching storage capacity.
- A release of the Monitor Tank is planned.
- Sample results indicate non gaseous activity in the tank is slightly higher than the 7.0 E-6 ci/ml value listed in 0-SI-CEM-077-400.1, "Liquid Waste Effluent Batch Release," for opening a Batch Release Permit.
- The source check on 0-RM-90-122, "Liquid Radwaste Release Monitor,"
has failed and the monitor has been declared Non Functional.
Which ONE of the following completes the statement below?
In accordance with 0-SI-CEM-077-400.1, the Monitor Tank release is permitted A. after the Shift Manager obtains Operations Superintendent and Chemistry Manager approval B. after the US/SRO grants approval, without any additional required signatures/approvals needed C. ONLY after the Monitor Tank contents are reprocessed to lower activity D. ONLY after 0-RM-90-122 has been returned to FUNCTIONAL status 98
- 99. Given the following plant conditions:
- Unit 1 reactor has tripped with a Safety Injection.
- The operating crew is at step 6 of E-0,"Reactor Trip or Safety Injection."
- A fire occurs in the main control room causing it to quickly become uninhabitable.
Which ONE of the following identifies the correct transition, if any, that the Unit Supervisor is required to complete?
A. Perform E-0, "Reactor Trip or Safety Injection," ONLY B. Perform AOP-C.04, "Shutdown From Auxiliary Control Room," ONLY C. Perform AOP-C.04, "Shutdown From Auxiliary Control Room," AND E-0, "Reactor Trip or Safety Injection," in parallel.
D. Complete performance of E-0, "Reactor Trip or Safety injection," first and then perform AOP-C.04, "Shutdown From Auxiliary Control Room."
99
SQN ILT 1712 NRC Exam 100. Given the following:
- 0830 A plant equipment malfunction leads to an Alert Emergency declaration.
- 1045 Plant conditions have degraded leading to declaration of a Site Area Emergency.
Which ONE of the following completes the statement below?
The Site Area Emergency will be declared from the (1)
AND Protective Action Recommendations (PARs) (2) required.
A. (1) Technical Support Center (TSC)
(2) are B. (1) Technical Support Center (TSC)
(2) are NOT C. (1) Central Emergency Control Center (CECC)
(2) are D. (1) Central Emergency Control Center (CECC)
(2) are NOT 100
References for 1712 NRC SRO Exam
- 1. Steam Tables
- 2. Mollier Diagram
- 4. 1, 2 - 47W830-4, Mechanical Flow Diagram Waste Disposal
- 5. TRM Figure 8.1.1-1, Boric Acid Tank Limits Based on RWST Boron Concentration
- 6. EPIP-1, Emergency Plan Classification Matrix, pages 44, 46 and 49
- 7. TS 3.6.2, Containment Air Locks
- 8. COLR Figure 1, Rod Bank Insertion Limits Versus Thermal Power, Four Loop Operation
Answers
- ID Points 0 1 007 EK2.02 1 1.00 A 2 009 EA2.02 602 1.00 C 3 011 EK2.02 3 1.00 B 4 015AK1.05 204 1.00 D 5 025 AK3.02 105 1.00 C 6 026 AA1.06 6 1.00 D 7 027 AK1.02 207 1.00 C 8 038 EG2.2.42 208 1.00 B 9 055 EA2.04 9 1.00 B 10 056 AG2.4.34 210 1.00 B 11 057 AA1.05 111 1.00 D 12 058 AK3.01 12 1.00 B 13 062 EA2.03 113 1.00 C 14 065 AK3.08 114 1.00 D 15 077AG2.4.20 415 1.00 D 16 W/E04 EK2.1 216 1.00 D 17 W/E05 EK1.2 317 1.00 D 18 W/E11 EA1.3 118 1.00 A 19 001 AG2.2.39 19 1.00 D 20 028 AK2.02 20 1.00 B 21 036 AK2.01 21 1.00 D 22 037AK3.05 222 1.00 C 23 051 AA2.02 223 1.00 C 24 060AA2.0.3 24 1.00 C 25 068 AA1.12 125 1.00 A 26 024 AK3.01 26 1.00 B 27 W/E09 EK1.2 327 1.00 A 28 003A2.02 28 1.00 A 29 003 K6.02 29 1.00 C 30 004 A3.09 230 1.00 B 31 005K5.02 131 1.00 C 32 006 G2.4.9 332 1.00 B 33 007 A1.03 133 1.00 B 34 008 A1.02 134 1.00 B 35 008 K2.02 135 1.00 C 36 010 K6.01 36 1.00 C 37 010G2.1.23 337 1.00 D 38 012A4.04 38 1.00 D 39 012K4.08 139 1.00 B 40 013 A4.01 40 1.00 B 41 022 A4.04 141 1.00 D 42 025 K5.02 42 1.00 A 43 026 K3.02 143 1.00 C 44 039G2.2.44 844 1.00 A 45 059 K4.08 345 1.00 C 46 061 K2.01 46 1.00 A 47 062 A3.05 47 1.00 D 48 062 K1.02 48 1.00 C
Answers
- ID Points 0 49 063 A2.01 149 1.00 C 50 064 A3.07 50 1.00 C 51 064 K6.08 151 1.00 A 52 073K4.01 52 1.00 C 53 076 K1.19 53 1.00 B 54 078K3.02 154 1.00 D 55 103 K1.02 155 1.00 D 56 002K1.07 556 1.00 A 57 011K5.13 57 1.00 A 58 014K3.02 158 1.00 B 59 086 K4.03 59 1.00 C 60 027 K2.01 60 1.00 C 61 029 A3.01 161 1.00 D 62 033A1.02 162 1.00 A 63 041K6.03 163 1.00 C 64 068 A2.02 64 1.00 C 65 079 A4.01 65 1.00 A 66 G2.1.25 66 1.00 C 67 G2.1.31 367 1.00 C 68 G2.2.4 168 1.00 A 69 G2.2.20 469 1.00 C 70 G2.2.38 270 1.00 B 71 G2.3.4 71 1.00 D 72 G2.3.13 172 1.00 D 73 G2.4.1 173 1.00 A 74 G2.4.17 474 1.00 A 75 G2.4.20 75 1.00 D SECTION 1 ( 75 items) 75.00
Answers
- ID Points 0 1 008 AG2.4.2 176 1.00 A 2 025 AA2.01 177 1.00 A 3 009EG2.2.44 178 1.00 A 4 055 EA2.03 79 1.00 D 5 026 AG2.1.23 380 1.00 C 6 W/E05 EA2.1 81 1.00 C 7 036AA2.02 82 1.00 D 8 032 AG2.1.20 283 1.00 B 9 061 AA2.01 584 1.00 A 10 069 AG2.2.44 185 1.00 A 11 012 A2.05 86 1.00 D 12 039 A2.03 187 1.00 A 13 005A2.01 88 1.00 C 14 063 G2.4.9 89 1.00 B 15 103 G2.2.37 390 1.00 D 16 001 G2.1.25 391 1.00 B 17 015 G2.2.40 192 1.00 A 18 071 A2.06 93 1.00 C 19 G2.1.13 94 1.00 A 20 G 2.1.32 95 1.00 D 21 G2.2.18 196 1.00 B 22 G2.2.23 297 1.00 C 23 G2.3.6 98 1.00 A 24 G2.4.5 99 1.00 B 25 G2.4.42 REV1 100 1.00 B SECTION 1 ( 25 items) 25.00