ML030070603
| ML030070603 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/10/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Gasser J Southern Nuclear Operating Co |
| References | |
| 50-424/02-301, 50-425/02-301 50-424/02-301, 50-425/02-301 | |
| Download: ML030070603 (46) | |
Text
QUESTIONS REPORT for srotest
- 1. 001AK1.05 001 The following conditions exist:
- Reactor power = 100%
- Control Bank D is at 137 steps withdrawn
- Rod control is in AUTO If PT-505 fails LOW, how will the rods in Control Bank D respond?
A. Move inward at 48 steps per minute.
B. Move inward at 72 steps per minute.
C. Move outward at 72 steps per minute.
D. Move outward at 48 steps per minute.
- 2. 001K1.05 001 Given the following:
- 75% power
- Channel N-41 - 74%
- Channel N-42 - 73%
- Channel N-43 - 75%
- Channel N-44 - 74%
- Rod control is in Automatic Which of the following describes Rod Control system response to channel N-41 failing low?
A. Control Rods drive in at a maximum rate until C-5 blocks rod motion or a reactor trip on low prz press occurs.
B. Control Rods drive in until the temperature mismatch equals the power mismatch and Tavg stablizes at a lower temperature.
C. Control Rods remain in present position until power mismatch causes a signal to move.
D. Control Rods drive out until the temperature mismatch equals the power mismatch and Tavg stablizes at a lower temperature.
Tuesday, January 07, 2003 02:20:02 PM 1
QUESTIONS REPORT for srotest 3.002K5.10 002 Given the following conditions:
- Tavg is on program
- Unit 1 is at 94% power and ramping up.
- Rods are in automatic with Bank D at 200 steps
- Turbine load set is raised to 1220 MWe using the increase pushbutton
- Turbine control valves are opening and megawatts are increasing Which ONE of the following describes Tavg behavior assuming no operator action?
A. Tavg and Tref will increase and continue to be matched until the turbine reaches set load.
B. Tref will increase until the turbine reaches set load, but Tavg will remain constant.
C. Tavg and Tref will remain constant and matched as the turbine load increases.
D. Tavg will decrease and Tref will increase until the turbine reaches set load.
- 4. 003A2.02S 002 Unit 1 Reactor power has been reduced to remove Loop 3 RCP due to excessive vibrations.
Which ONE of the following describes the plant response at the time the RCP is tripped and any follow-up action required?
A. Tave in loop 3 increases to Thot of the other 3 loops and MFW flow to loop 3 must be reduced.
B. Tave in loop 3 decreases below Tcold of the other 3 loops and MFW flow to loop 3 must be reduced.
C. Delta T in loop 3 increases above Delta T of the other 3 loops and MFW flow to the other 3 loops must be reduced.
D. Delta T in loop 3 decreases below Delta T of the other 3 loops and MFW flow to the other 3 loops must be increased.
Tuesday, January 07, 2003 02:20:02 PM 2
QUESTIONS REPORT for srotest
- 5. 003G2.4.49 002 At 11:00 you are notified that RCP #1 ACCW inlet line is leaking badly. Maintenance was notified and is in the process of determining what type of repairs are needed. At 11:05 via plant computer and other control room indications, you determine that the following conditions exist:
- Motor bearing temperature is 195 OF and rising at 1 OF / min
- Motor stator winding temperature is 315 OF and steady
- Seal water Inlet temperature is 190 OF and steady Based on the above conditions, what action(s) should be taken?
A. Immediately trip the RCP B. Trip the RCP if ACCW to the pump is not re-established by 11:16 with total #1 seal flow greater than 5 gpm C. Trip the RCP if ACCW flow is not re-established by 11:10 D. Trip the RCP, then the reactor if seal water temperature is not returned to 230 OF by 11:16
- 6. 004A2.12 001 Given the following:
- Unit 2 is at 100% power
- CCP "A" is in service, providing normal charging flow
- An inadvertent "B" train SI was generated by I&C
- SI "A" train is NOT present
- No operator action takes place Which of the following is correct?
A. Normal mini-flow paths for both CCPs are isolated, alternate flow-paths for both CCPs are available.
B.! Normal mini-flow paths for both CCPs are isolated, CCP "A" alternate minif low path is isolated, CCP "B" alternate mini-flow path is available.
C. CCP "A" normal mini-flow path is available, CCP "A" alternate miniflow path is isolated, CCP "B" alternate mini-flow path is available.
D. Normal mini-flow paths for both CCPs are isolated, alternate flow-paths for both CCPs are isolated.
Tuesday, January 07, 2003 02:20:02 PM 3
QUESTIONS REPORT for srotest
- 7. 004A4.07 001 Which of the following describes the proper reactor makeup control system valve positions after the Makeup Control Switch is placed to the START position with the Mode selector switch in DILUTE?
Af Boric Acid to Blender Valve (FV-01 1OA) - CLOSED Blender Outlet to Charging Pumps Suction Valve (FV-01 1OB)- CLOSED Blender Outlet toVCT Valve (FV-01 11 B)- OPEN RX MU WTR to BA Blender Valve (FV-01 11 A)- MODULATED B. Boric Acid to Blender Valve (FV-01 10A) - CLOSED Blender Outlet to Charging Pumps Suction Valve (FV-01 1OB)- OPEN Blender Outlet to VCT Valve (FV-01 11 B)- MODULATED RX MU WTR to BA Blender Valve (FV-01 11 A)- CLOSED C. Boric Acid to Blender Valve (FV-01 1OA) - OPEN Blender Outlet to Charging Pumps Suction Valve (FV-01 1OB)- OPEN Blender Outlet to VCT Valve (FV-01 11 B)- CLOSED RX MU WTR to BA Blender Valve (FV-01 11A)- MODULATED D. Boric Acid to Blender Valve (FV-01 10A) - MODULATED Blender Outlet to Charging Pumps Suction Valve (FV-01 1OB)- MODULATED Blender Outlet to VCT Valve (FV-01 11 B)- OPEN RX MU WTR to BA Blender Valve (FV-01 11A)- OPEN
- 8. 005AK3.02S 002 Given the following plant conditions:
- Reactor power is at 75%
- Control bank D is at 175 steps
- Control Bank D, rod M-12 is immovable and is 20 steps below the other rods in Bank D.
- The rod is mechanically bound
- Crew is performing 18003-C, "Rod Control System Malfunction" to correct the rod alignment condition while using turbine load to maintain Tavg matched with Tref.
Which ONE of the following describes how the control rods should be realigned and how rod insertion limit (RIL) will be affected?
A. Control Bank D will be realigned to the rod and RIL will remain the same.
B.' Control Bank D will be realigned to the rod and RIL will be lower.
C. The rod will be realigned to Control Bank D and RIL will be lower.
D. The rod will be realigned to Control Bank D and RIL will remain the same.
Tuesday, January 07, 2003 02:20:02 PM 4
QUESTIONS REPORT for srotest
- 9. 005K5.03S 001 Given the following plant conditions:
- The Unit 1 is in MODE 6, refueling activities in progress inside containment.
- "B" train RHR was just taken out of service and "A" train RHR was placed in service for core cooling and letdown to CVCS.
- Chemistry reports RCS boron concentration is 1711 ppm.
Which ONE of the following describes the correct actions and basis?
A. Isolate Refueling Cavity from the Spent Fuel Pit by closing the transfer tube wafer valve to prevent dilution of the Spent Fuel Pit.
B. Place train"B" RHR in service, remove "A" train to isolate dilution paths connected to "A" train RHR.
C0 Initiate boration using 13009-1, CVCS Reactor Makeup Control System, to increase boron concentration to minimum required limits.
D. Evacuate containment and verify contaiment integrity intact.
- 10. 006A1.11 002 Given the following plant conditions:
- 19031, "Post-SGTR Cooldown Using Backfill", is in progress.
- Ruptured SG level is 25% NR.
- Crew is cooling down using steam dumps to condenser.
- RCP #4 in service.
19031, "Post-SGTR Cooldown Using Backfill"
- Step 14 requires a return to step 3 if RCS temperature is greater than 2000 F.
- Step 3 requires the operator to ensure adequate shutdown margin.
Why is it necessary to re-verify shutdown margin at this point in the procedure?
A. The RCS temperature change during cooldown will cause significant boron concentration changes due to PZR outsurge.
B. Charging to maintain PZR level during cooldown will cause significant boron concentration changes.
C! The secondary fluid in the ruptured SG will cause a significant decrease in RCS boron concentration.
D. Using auxiliary spray will cause a significant decrease in RCS boron concentration changes.
Tuesday, January 07, 2003 02:20:02 PM 5
QUESTIONS REPORT for srotest
- 11. 006K1.07 002 Given the following sequence of events:
- The plant is operating at 100% power.
- Safety Injection actuated
- Reactor tripped due to the SI signal
- Controlling #1 SG level transmitter fails low after the trip
- #4 SG ARV opened momentarily and developed a large packing leak.
Which ONE of the following would cause the INITIAL main feedwater isolation during this transient?
A. The #1 SG level reached 86%.
B.! The safety injection actuation signal.
C. Tavg dropping to 564 0F following the reactor trip.
D. Main Steam Valve Room level had risen due to the ARV packing leak.
- 12. 007EA1.03 002 An RCS cooldown is in progress per 19002-C, "Natural Circulation Cooldown". The plant is being depressurized using auxiliary spray. As pressure drops through 1300 psig, a rapid rise in pressurizer level is observed. Charging and Letdown are in manual and are matched.
Which of the following describes the expected operator actions?
A. Isolate charging flow and raise the cooldown rate to 50 degrees F/hr.
B. Isolate charging flow and place additional letdown orfice(s) in service.
C. Isolate the ECCS Acculmulators, and place both SIPs in pull to lock.
D.' Isolate the auxiliary spray and energize pressurizer B/U heaters.
Tuesday, January 07, 2003 02:20:02 PM 6
QUESTIONS REPORT for srotest
- 13. 008AK1.01 001 Given the following:
- Unit 1 is stable at 100% power
- A pressurizer safety valve opens and fails to reseat, remaining 25% open and the Unit trips
- RCS pressure stabilizes at 1600 psig
- SI acuates Which of the following indications would the operator expect to see as a result of this event in the next 30 minutes?
A. Safety tailpipe temperature would increase to greater than 600 OF and then decrease to 450 OF.
B. Safety tailpipe temperature would increase to greater than 600 OF and then slowly increase.
Cf Safety tailpipe temperature would increase to between 220 and 340 OF and then decrease and stablize.
D. Safety tailpipe temperature would increase to between 220 and 340 OF and then slowly increase and stablize at 600 OF.
- 14. 009EA2.34S 002 Given the following conditions on Unit 1:
- A small break LOCA is in progress
- MSIVs have just closed due to containment pressure
- 19010-C "E-1, LOSS OF REACTOR OR SECONDARY COOLANT" is in progress with plant parameters as follows:
- RCS pressure is 1700 psig and stable
- CETCs indicate 570 F
- Total AFW flow is 700 gpm
- PZR level is 42% and rising Based on these known conditions, which one of the following actions should the operators take?
A. Verify all RCPs are stopped.
B. Check if containment spray should be stopped.
Cf Transition to 19011-C "ES-1.1, SI Termination".
D. Remain in 19010-C, "E-1, Loss of reactor or secondary coolant".
Tuesday, January 07, 2003 02:20:02 PM 7
QUESTIONS REPORT for srotest
- 15. 010K3.01 001 Given the following:
- Pressurizer pressure is 2230 psig and increasing.
- The proportional heaters are energized.
- The spray valves are closed.
- The Master Pressure Controller fails to a constant output equivilent to 2219 psig.
Which ONE of the following describes the response of the pressure control system if the operator takes no further action?
A. Pressure will rise until the spray valves open to control pressure.
B! Pressure will rise until PORV 456 opens to control pressure.
C. Pressure will rise until PORV 455 opens to control pressure.
D. Pressure will cycle on the variable heaters at a higher setpoint.
- 16. 011A3.03 001 Given the following:
- Unit is at 50% power.
- All automatic control systems are in their normal lineup.
- Pressurizer program level sticks at constant output for 50% power.
- Assume no operator action is taken.
Which of the following describes the effect on charging flow and PZR level as the plant load is increased to 100%?
A. Actual PZR level remains constant and charging flow increases.
B. Actual PZR level decreases and charging flow decreases.
C0 Actual PZR level increases and charging flow decreases.
D. Actual PZR level increases and charging flow remains constant.
Tuesday, January 07, 2003 02:20:02 PM 8
QUESTIONS REPORT for srotest
- 17. 01 EA1.04 002 Given the following plant conditions:
- Unit 1 tripped due to a Large Break LOCA.
- Containment pressure is 23.5 psig.
- RWST level is 14%.
- Containment Emergency Sump levels are 15 inches.
4 containment coolers running in low speed.
RHR Swapover to the Containment Sump could not be performed.
The operating crew has transitioned to 19111-C, "ECA - 1.1, Loss of Emergency Coolant Recirculation."
After completion of steps 5 & 6 of 19111-C which one of the following would be the correct configuration for the Containment Spray Pumps?
A. Both Containment Spray pumps running in the injection mode.
B. Both Containment Spray pumps aligned and running in the recirculation mode.
C. One Containment Spray pump aligned and running in the injection mode.
D. One Containment Spray pump aligned and running in the recirculation mode.
- 18. 011EK2.02 001 Given the following conditions:
- A large break LOCA occurred
- Operators have just completed 19013-C, "Transfer to Cold Leg Recirculation"
- A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?
A. Pull to lock SIPs and CCPs until the RHR pumps are started by the blackout sequencer aft( r the diesel generators start and load the 4160 vital buses.
B.Y Ensure the RHR pumps are manually started after the diesel generators start and load the 4160 vital buses, then manually start SIPs as needed.
C. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators start and load, then manually start CCPs and SIPs as needed D. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize 4160 vital buses.
Tuesday, January 07, 2003 02:20:02 PM 9
QUESTIONS REPORT for srotest
- 19. 012K6.10 001 Given the following conditions
- Unit shutdown in progress
- Power at 9%
- Permissive "P-7 LO POWER TRIPS BLOCKED" illuminates Which ONE of the following describes the effects on RPS?
A. The reactor will not trip on Pressurizer High Pressure.
B. The reactor will not trip on high positive rate.
C0 The reactor will not trip on Pressurizer Low Pressure.
D. The reactor will not trip on low steam generator level.
- 20. 013K2.01 002 Given the following:
- SIP1A&1BareinAuto
- Control power is lost to SIP 1A
- Safety injection (SI) occurs Which of the following describes the response of the SI pumps to the Safety Injection signal?
A. SIP 1B will start, but SIP 1A will not auto start or manually start from the QMCB handswitch.
B. SIP 1B will start, but SIP 1A will not auto start and must be started from OMCB handswitch.
C. Both SI pumps will auto start, but the SIP 1A can not be stopped from the QMCB.
D. Both SI pumps will auto start, but the SIP 1A can not be stopped except mechanically at the breaker.
Tuesday, January 07, 2003 02:20:02 PM 10
QUESTIONS REPORT for srotest
- 21. 014A4.01 002 Given the following:
- Operators are conducting a reactor startup
- ALL shutdown banks are withdrawn
- Control banks are being withdrawn in 50 step increments
- The SS notices that Control Bank A is at 200 steps and Control Bank B is at 0 steps Which of the following explains these indications?
A. Rod bank selector switch is in the manual position.
B! Rod bank selector switch is in the Control Bank A postion.
C. The rod control startup switch is stuck in the reset postion.
D. DRPI Data B failure has occurred.
- 22. 015K4.06 002 Given the following conditions:
- Reactor power is at 18% with a startup in progress
- N41 was placed in bypass (BTI) following a failed surveillance How does this affect the coincidence for a power range High Flux Reactor Trip?
A. 2 out of 4 power range channels at 25% reactor power will generate a reactor trip B. 2 out 3 power range channels at 25% reactor power will generate a reactor trip C! 2 out 3 power range channels at 109% reactor power will generate a reactor trip D. 2 out of 4 power range channels at 109% reactor power will generate a reactor trip Tuesday, January 07, 2003 02:20:03 PM 11
QUESTIONS REPORT for srotest
- 23. 015K5.04 001 Manual calibration of the NIS is being performed in accordance with procedure 14030-2, "Nuclear Instrument Calorimetric Calibration." Feedwater average temperature is incorrectly calculated to a value 17 degrees less than actual. For these conditions, which of the following is correct?
Calculated reactor thermal power will be ......
A. lower than actual and a gain adjustment of the NI channels using the calculated value would be non-conservative such that the indicated power is farther from the setpoints.
B. higher than actual and a gain adjustment of the NI channels using the calculated value would be non-conservative such that the indicated power is farther from the setpoints.
C. lower than actual and a gain adjustment of the NI channels using the calculated value would be non-conservative such that the indicated power is closer to the setpoints.
D.W higher than actual and a gain adjustment of the NI channels using the calculated value would be conservative such that the indicated power is closer to the setpoints.
- 24. 017AK1.02 002 IF RCP #1 trips when the plant is at 10% power during a load increase to 100%, which one of the following statements is correct?
A. A reactor trip will occur and operators should implement 19000-C.
B.Y The affected pressurizer spray valve should be shut to prevent spray flow from bypassing the pressurizer.
C. The affected S/G blowdown rate may be isolated to facilitate level control.
D. Reactor trip breakers should be immediately opened to comply with the action statement for LCO 3.4.4, "RCS Loops-Modes 1 and 2".
Tuesday, January 07, 2003 02:20:03 PM 12
QUESTIONS REPORT for srotest
- 25. 017K3.01 002 Given the following conditions:
- All RCPs are tripped
- All core-exit thermocouples are inoperable
- 19001-C is in progress Which one of the following describes the indication that could be used to verify that natural circulation cooling is in progress A. RCS loop Tave's stable or lowering.
B. RCS loop loop Tave's increasing to full power values.
C.f Steam Generator Pressures Stable or lowering.
D. Steam Generator Levels Stable or lowering.
- 26. 022AG2.1.32 001 During water solid operations with letdown from RHR, procedure 13011-1, "Residual Heat Removal System" requires that 1-HV-0128, Letdown From RHR, be full open.
Which ONE of the following describes the basis for this precaution?
A. To ensure maximum letdown flow rate for purification.
B. To ensure VCT level can be maintained under all charging flow conditions.
C:f To ensure 1-PIC-0131, Low Pressure Letdown Controller can control pressure transients.
D. To ensure RCS to RHR Supply Line Relief Valves PSV-8708B and PSV-8708A are not challenged.
Tuesday, January 07, 2003 02:20:03 PM 13
QUESTIONS REPORT for srotest
- 27. 024AK2.01 002 Given the following conditions:
- 2 rods stick out on a reactor trip
- The RO initiates emergency boration using HV-8104
- Boric flow on FI-0183A is 23 gpm and charging flow is 42 gpm Which of the following is the correct response to this condition?
The RO can correct this condition by ......
A. Placing charging flow controller FIC-0121 in manual and increasing the set point to >42 gpm, ensuring charging flow increases and FI-0183A indicates >30 gpm.
B. Opening FV-110A, closing FV-110B, and ensuring FI-0183A indicates >30 gpm.
C' Opening HV-112D and HV-112E, then closing HV-112B and HV112C, ensuring charging flow is >87.5 gpm.
D. Opening HV-112B and HV-112C, then closing HV-112D and HV112E, ensuring charging flow is >87.5 gpm.
- 28. 025AK2.02 001 Given the following:
- RCS temperature is 118 OF
- Reactor Vessel head is removed
- Reactor Upper Internals are installed in the reactor vessel
- Refueling Level is 187.9 ft
- RCS draining is in process at 10 gpm
- RHR pump A is running with indicated flow of 3800 gpm
- RHR pump A is exhibiting indications of cavitation The cavitation and resulting loss of RHR is occurring due to .......
A. draining with the upper internals in place, which reduced the RHR suction pressure.
B. steam binding of the RHR pump, caused by low recirculation flow.
Cf air entrapment at the RHR suction inlet, caused by the high flow conditions.
D. draining with the upper internals in place, which reduced the RHR discharge pressure.
Tuesday, January 07, 2003 02:20:03 PM 14
QUESTIONS REPORT for srotest
- 29. 026A1.01 002 Given the following conditions on Unit 2:
- Following a LOCA, containment pressure is rising.
- Containment pressure has reached 20 psig on three channels and 22 psig on one channel.
Which one of the following are the MINIMUM actions that would result in containment spray actuation?
A. When 1 more containment pressure channel indicates 22 psig, or when 1 manual handswitch is actuated.
BY When 1 more containment pressure channel indicates 22 psig, or when 2 manual handswitches are actuated.
C. When 2 more containment pressure channels indicate 22 psig, or when 1 manual handswitch is actuated.
D. When 2 more containment pressure channels indicate 22 psig, or when 2 manual handswitches are actuated.
- 30. 026AK3.01 002 Given the following plant conditions:
- Unit 2 is in Mode 3
- ALB 04, window A2, "ACCW LO HDR PRESS" is illuminated
- ALB 07, window D3, "LTDN HX OUT HI TEMP" is illuminated Which one of the following events would cause both of these alarms?
A. Letdown Hx Tube Rupture BY ACCW Supply Header Rupture C. Loss of Seal Injection D. Loss of Charging Flow Tuesday, January 07, 2003 02:20:03 PM 15
QUESTIONS REPORT for srotest
- 31. 027AK3.03 002 Given the following conditions:
- Unit 1 is at 100% power.
- ALB12 E01 "PRZR RELIEF DISCH HI TEMP" illuminates
- Both PORVs indicate closed.
- PORV-455 tailpipe temperature is reading 220 degrees F.
- PORV-456 tailpipe temperature is reading 187 degrees F.
- Pressurizer pressure is lowering.
Which one of the following is the correct action in accordance to ARP 17012-1?
A. Close the associated block valve for PORV-456 because a vapor-space leak causes PZR level to increase.
B. Close both block valves because a vapor-space leak causes PZR level to increase.
C." Close the associated block valve for PORV-455 to stop leakage to the PRT.
D. Close both block valves to stop leakage to the PRT.
- 32. 028AA2.12 002 Given the following conditions:
- The Unit is at 100% power
- Pressurizer level is decreasing slowly
- Charging flow is decreasing
- Alarm ALBI 1 D01, Przr Lo Level Deviation, illuminates.
Which ONE of the following is the cause of the Pressurizer level decrease?
A. FCV-121, charging flow control valve, has developed a diaphram leak.
B. FIC-0121, Charging Flow Controller, is failing high.
Cf1 LIC-0459, PZR level master controller output, is failing low.
D. The Tave input to the PZR level control is failing high.
Tuesday, January 07, 2003 02:20:03 PM 16
QUESTIONS REPORT for srotest
- 33. 029EA1.13 001 Which ONE of the following is the NEXT action the operator is required to take if the main turbine does NOT trip automatically and CANNOT be tripped from the QMCB per 19211 -C, FR-S.1, "RESPONSE TO NUCLEAR POWER GENERATION/ATWT"?
A. Place both EHC pumps control switches in P-T-L.
B. Trip the turbine locally at the front standard.
Cf Manually Runback the turbine.
D. Shut the MSIV's.
- 34. 032AK1.01 002 Given the following conditions:
- Reactor Startup in progress
- Startup is on hold due to a problem with SR N-31
- SR N-32 indicates 1000 cps
- SR N-31 is in bypass Which ONE of the following will occur if the control power fuse for SR N-31 blows?
A. Lose indication for SR N-31 on Main Control Board and NIS cabinets.
B. Both SR drawers deenergize and the "non-operate" alarm acuates.
C! Reactor will trip.
D. Rod withdrawal is blocked.
- 35. 033G2.4.18S 002 A loss of SFPC has occured. The procedure instructs you to open the cask loading gates.
The basis for this action is to allow ........
A. a feed path from the RWST.
B! circulation between the pools.
C. a recirculation path to the RWST.
D. the water to bypass the spent fuel pool demineralizers.
Tuesday, January 07, 2003 02:20:03 PM 17
QUESTIONS REPORT for srotest
- 36. 034K4.01 001 Which one of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?
A. The Gripper is mechanically engaged and disengaged by a remote operating handle on tihe bridge and requires no power or air to operate.
Bf The gripper requires air to disengage, however, a mechanical latch prevents gripper release under load even if air is supplied.
C. The gripper will disengage upon loss of air, however, a mechanical latch prevents gripper release under load even if air is removed.
D. When the gripper is engaged, fuel handlers mechanically lock gripper in place with extension shaft which must be unlocked before the gripper can release.
- 37. 035K1.09 002 Given the following plant conditions:
- The reactor is operating at 50% power.
- Rod control is in MANUAL.
- Turbine control is at set load.
- #3 S/G ARV fails OPEN.
Which ONE of the following describes the resulting steady-state conditions?
(Assume no reactor trip, no operator action and turbine power remains constant)
A. Final Tavg < initial Tavg and final power > initial power.
B. Final Tavg < initial Tavg and final power = initial power.
C. Final Tavg = initial Tavg and final power > initial power.
D. Final Tavg = initial Tavg and final power = initial power.
Tuesday, January 07, 2003 02:20:03 PM 18
QUESTIONS REPORT for srotest
- 38. 037AK3.07 001 Given the following:
- A SG #3 has a 30 gpm leak.
- AOP 18009-C, Steam Generator Tube Leak is being implemented.
- S/G #3 is maintained greater than 10%.
Which ONE of the following is a bases for ensuring the affected SG level greater than 10%?
A. To ensure that the pressure and temperature limits of the SG shell are maintained.
BY To prevent RCS cooldown from causing depressurization of the affected SG.
C. To prevent SG overfill.
D. To prevent thermal shock to the tubes during RCS cooldown.
- 39. 038EA1.04 002 Given the following conditions:
- A SGTR with a small primary LOCA has occurred
- The crew is implementing 19131-C, "ECA-3.1, SGTR with Loss of Reactor Coolant, Subcooled Recovery Desired"
- RCS pressure is 1534 psig and temperature is 547 degrees F
- RCPs #1 & 3 have tripped due to a loss of power to 1NAA Which ONE of the following describes the actions required to minimize the primary to secondary break flow?
A. Cooldown by dumping steam from the intact SG's followed by depressurization of the RCS with both Pressurizer Spray valves.
B. Cooldown with RHR followed by depressurization of the RCS with Loop 1 Pressurizer Spray valve.
CY Cooldown by dumping steam from the intact SGs followed by depressurization of the RCS with loop 4 Pressurizer Spray valve.
D. Cooldown with RHR followed by depressurization of the RCS with Pressurizer PORV's.
Tuesday, January 07, 2003 02:20:03 PM 19
QUESTIONS REPORT for srotest
- 40. 039Ai.03 002 Given the following:
- Unit 2 is in mode 3 at NOPT for a post refueling start up
- MSIVs are shut and the main steamlines need to warmed
- SG ARVs are in manual, controlling loop Taves at 557 OF Which of the following correctly describes the method used and the indications observed while warming the main steamlines?
A. Slowly open MSIVs one at a time. RCS pressure will remain constant while temperature decreases.
B. Open steam dumps to 1% to 2% after placing both bypass switches in the bypass position.
RCS temperature and pressure will decrease.
Cf Open MSIV bypass valve(s) and maintain MSIVs shut. RCS temperature and pressure will decrease.
D. Open MSIV bypass valve(s) after placing both steam dump bypass switches in the bypass position. RCS temperature and pressure will decrease.
- 41. 040AG2.4.4 002 Given the following plant conditions:
- Unit was at 100% power
- A main steam line break occurred in the Turbine Building
- Operators were unable to close the MSIVs and transitioned to procedure 19121-C, ECA-2.1, "Uncontrolled Depressurization of All Steam Generators."
- SI termination steps of ECA-2.1 are in progress
- Loop 3 MSIV is closed locally
- The CRO observes the # 3 S/G pressure rising slowly Which of the following actions should be performed?
A. Immediately transition to E-2, "Faulted S/G Isolation" B. Immediately transition to ES-I.1, "SI Termination" C. Remain in ECA-2.1 until RHR is in service D. Remain in ECA-2.1 until SI is terminated Tuesday, January 07, 2003 02:20:03 PM 20
QUESTIONS REPORT for srotest
- 42. 041K3.04 001 Given the following conditions:
- Unit at 100% power, EOL conditions.
- Turbine operating at set point
- A steam dump valve inadvertently comes full open.
- All other control systems normal.
Which ONE of the following correctly describes the plant conditions, when the plant stabilizes, assuming NO reactor trip and NO operator action?
A. Megawatts electrical same as initial; reactor power increases.
B. Megawatts electrical same as initial; reactor power decreases.
Cf Megawatts electrical decreases; reactor power increases.
D. Megawatts electrical decreases; reactor power decreases.
- 43. 045A3.05 001 The following plant conditions exist:
- Unit 1 is at 90% power
- Main Turbine is in STANDBY to repair a failed speed sensor Which ONE of the following correctly describes the status of the Turbine Control System?
A. All overspeed protection has been defeated except for the Mechanical Trip and the Backup Overspeed Trip.
B. Overspeed protection from the speed control circuits and PLU has been defeated. IVFast Closure, Mechanical Trip, and Backup Overspeed Trip are still operable.
Cf The Power Load Unbalance circuit is still active and will allow fast closure of the Control Valves and the Intercept Valves if a sudden load rejection of more than 40% occurs.
D. The Power Load Unbalance circuit is defeated and the Backup Overspeed Trip setpoint is reduced to 105%.
Tuesday, January 07, 2003 02:20:03 PM 21
QUESTIONS REPORT for srotest
- 44. 051AA2.02S 002 The following plant conditions exist:
- Unit 1 is at 38% power.
- TURB CNDSR LO VAC annunciator lit.
- Condenser vacuum reads 20.5 inches Hg.
Which ONE of the following should have occurred?
A. Turbine run back, only.
Bf' Turbine trip, only.
C. Reactor trip initiating a turbine trip.
D. Turbine trip initiating a reactor trip.
- 45. 054EG2.4.48 002 Given the following:
- Unit 1 is at 100% power.
- Annunciator ALB13-DO1 STM GEN 1 HI/LO LVL DEVIATION alarm is illuminated
- Only S/G #1 level is rising
- Both MFPs speed are rising Which ONE of the follow describes the (1) cause, (2) required action and (3) direct consequence of an operator failing to take action?
A. (1) #1 S/G FRV is opening, (2) stabailize #1 S/G level at new level, (3) Turbine Runback Initiated B.! (1) #1 S/G FRV is opening, (2) return #1 S/G level to program, (3) Feedwater Isolation initiated C. (1) MFP master controller failing high, (2) control MFP speed using manual, (3) Auto Turbine Trip initiated D. (1) MFP master controller failing high, (2) manually trip turbine, (3) Feedwater Isolation initiated Tuesday, January 07, 2003 02:20:03 PM 22
QUESTIONS REPORT for srotest
- 46. 055EK3.02 002 Which ONE of the following is a purpose of depressurizing all intact SGs to 300 psig during the performance of 19100-C, "ECA-0.0, Loss of All AC Power"?
A. Reduces DP across SG U-tubes to minimize possibility of tube rupture.
Bf Reduces DP across RCP seals to minimize leakage and loss of RCS inventory.
C. Maximizes Natural Circulation flow before Reflux cooling begins as the RCS becomes saturated.
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM cooling fans are unavailable.
- 47. 056AK1.01S 002 Given the following plant conditions:
- The operating crew is performing a cooldown, in accordance with 19002-C ES-0.2, Natural Circulation Cooldown
- All CRDM fans trip
- RCS cold leg temperatures indicate a cooldown rate of 65 0 F/hour
- Subcooling has decreased to 74 0 F Which ONE of the following describes the appropriate action?
A. Continue the cooldown/depressurization of RCS since steam voiding in the RCS vessel will not occur unless subcooling is less than 74 0 F.
B. Transition to 19003-C, ES-0.3 Natural Circulation Cooldown with Void in Vessel (with RVLIS) and reduce coodown rate to 50 °F/hr because a void has probably formed.
Cf Continue the cooldown/depressurization of RCS, reduce cooldown rate to 50 °F/hr and increase subcooling to 125 OF.
D. Decrease the rate of depressurization by decreasing the cooldown rate to 50°F/hour, ensure subcooling is returned to 74 OF and then continue with the procedure.
Tuesday, January 07, 2003 02:20:03 PM 23
QUESTIONS REPORT for srotest
- 48. 056K1.03 002 Unit 1 is at 70% power. A limit switch problem causes MFP 1A turbine exhaust valve to close.
Which ONE of the following describes the effect on continued plant operation?
A. 1A MFP rolls to idle, the Standby condensate pump starts and Rx power can remain at 70%
B! 1A MFP trips, the standby condensate pump remains in standby, and Rx power can remain at 70%.
C. 1A MFP trips, the standby condensate pump starts and Rx power must be reduced to 56%.
D. 1A MFP rolls to idle, the standby condensate pump does not start and Rx power must be reduced to below 56%
- 49. 057AA2.19S 001 Unit 1 is shutting down due to a failure of 120 VAC Vital Instrument bus 1AYlA.
When Rx power is approximately 10%, the unit trips.
Which ONE of the following decribes the reason for the trip?
A. SR High Flux Trip B. IR High Flux Trip C. Low Setpoint of PR High Flux Trip D. High Setpoint of PR High Flux Trip
- 50. 059A4.11 001 After which one of the following events can feedwater isolation be reset by operating the feedwater isolation reset handswitches without performing any other actions?
A. A spray valve fails open causing pressurizer pressure to drop to 1725 psig. The spray valve is closed and pressure returns to 2235.
B! At 75% Rx power, the operator overfeeds a single steam generator to the High-High Level setpoint and clears the High-High Level.
C. Turbine high vibrations causes a turbine trip from 65% Rx power. Steam dumps open to control Tavg at 557 0 F.
D. A high steam line flow causes a low Tavg and an SI. Main Steam isolation terminates high flow condition and allows Tavg to return to 557 0F.
Tuesday, January 07, 2003 02:20:04 PM 24
QUESTIONS REPORT for srotest
- 51. 059AA1.01 001 Given the following plant conditions:
- Plant is operating a 100% power.
- Plant systems aligned for normal at power operations.
- RE-1950, Auxiliary Component Cooling Water radiation monitor, is in alarm Which ONE of the following lists the type and process flows that are sensed by the alarming radiation monitor?
A. Gamma; Thermal Barrier leakage.
B. Beta; Excess Letdown Hx leakage C. Gamma; RHR Hx leakage D. Beta; RCP Motor Cooler leakage
- 52. 059K6.09 001 Given the following:
- Unit 1 is at 60% power with both MFPs operating in AUTO.
- PT-507, Steam Header Pressure, output begins to slowly drift low.
Which ONE of the following describes the initial effect on the Main Feed Water System, assuming no operator action?
A. Both MFP's discharge pressure begins to increase and all Feed Water Reg valves begin eI to close.
begin to B. Both MFP's discharge pressure begins to increase and all Feed Water Reg valves e open.
C.f Both MFP's discharge pressure begins to decrease and all Feed Water Reg valves begin to open.
begin D. Both MFP's discharge pressure begins to decrease and all Feed Water Reg valves to close.
Tuesday, January 07, 2003 02:20:04 PM 25
QUESTIONS REPORT for srotest
- 53. 060AA2.04 001 Given the following plant condtions:
- Gas Decay Tank release in progress
- A leak occurs on the waste gas compressor which results in a gas release to the Auxiliary building
- RE-12442C, Plant Vent Radiation Monitor, is in High alarm Which of the following indicates the effect this leak will have on the plant?
A. Gas Decay Tank release will be terminated; Auxiliary Building Exhaust Units trip B. Gas Decay Tank release will be terminated; Auxiliary Building Exhaust Units continue to run C. Gas Decay Tank release will continue; Auxiliary Building Exhaust Units trip D. Gas Decay Tank release will continue; Auxiliary Building Exhaust Units continue to run 002
- 54. 06 1A 1.04 002 061A1.04
- 54. Given the following plant conditions:
- The Unit 1 is at 100% power
- A loss of both RATs occurs due to a switchyard fault
- The unit is manually tripped
- 1AA02 and 1BA03 are energized by their D/Gs Which of the following correctly describes the effect this will have on CST level and the actions that will be necessary?
CST #1 level will:
A. continuously lower requiring manual swap to CST #2.
B. be maintained by automatic makeup.
C. continuously lower and automatically swaps to CST #2.
D. remain full until CST #2 level reaches 66%.
Tuesday, January 07, 2003 02:20:04 PM 26
QUESTIONS REPORT for srotest
- 55. 062A3.05 002 Given the following sequence:
- A small break LOCA occurred resulting in a reactor trip and SI.
- The SI signal was reset during the performance of 19010-C, "E-1, Loss of Reactor or Secondary Coolant."
- A loss of offsite power occurred and the diesel generators loaded as designed.
Assuming no operator actions, which ONE of the following would be the status of the loads on the 416OVac 1E buses?
A. All equipment powered from the 416OVac 1E buses with the control board switch in automatic will be restarted.
B. No 416OVac 1E bus loads are automatically restarted.
Cf Equipment normally started during a LOSP will be automatically restarted; SI and RHR pumps remain OFF.
D. All equipment that was operating prior to the LOSP will be automatically restarted; All running ESF equipment will be reenergized.
- 56. 062AG2.4.24 002 The crew is in 19100-C, "Reactor Trip or Safety Injection". Prior to the step that the crew places equipment in PTL, the procedure cautions that 2 NSCW pumps should be available to load on each AC Emergency Bus.
These pumps are required to provide cooling for the .........
A. SI pump B. MDAFW pump C. ACCW pump DW EDG Tuesday, January 07, 2003 02:20:04 PM 27
QUESTIONS REPORT for srotest
- 57. 063K3.02 001 Given the following:
- Unit 1 was at 100% power
- DG1A was running paralled to the 416OVac 1E bus for a surveillance.
- Unit 1 trips
- The following annunciators are lit:
- ALB34 D01 "125V DC SWGR lADI TROUBLE"
- AL834 E03 "120V AC PANELS 1AY1A 1AY2A TROUBLE"
- ALB34 D03 "125 DC PNL 1AD12 TROUBLE"
- ALB34 F02 "125V DC PNL lAD11 TROUBLE" Which ONE of the following describes the response to this event by DGIA?
A. DG1A trips and its output breaker opens B. DG1A continues to run and it's output breaker opens C. DG1A trips and its output breaker remains closed D.' DG1A continues to run and its output breaker remains closed
- 58. 064K2.03 002 Unit 2 is at 100% power All Diesel Generators are currently operable Annunciator ALB38-809, "DG2B ENGINE CNTL POWER B FAILURE" just illuminated Which ONE of the following describes the status of the Diesel Generator 2B with this annunciator in alarm?
A. DG2B still has capability to start and load once and is operable.
B. If DG2B was running when this occurred it will continue to operate and can be shutdown from the control room. DG2B must be declared inoperable.
C. DG2B can be started and loaded manually but is inoperable.
D. If DG2B was running it will continue to operate and can only be shutdown from the front standard. DG2B must be declared inoperable.
Tuesday, January 07, 2003 02:20:04 PM 28
QUESTIONS REPORT for srotest
- 59. 065AA1.03 002 Unit 1 just experienced a loss of air and entered AOP 18028-C, "Loss of Instrument Air" The header pressure is 63 psig. Given the current conditions, what action, per procedure, should be taken by the operator to prevent inadvertent operation of equipment repositioned due to the loss of air?
Aý Verify the cask loading pit gate seal assemblies are supplied with bottled nitrogen > 50 psig.
B. Ensure 1PV-9385 "Service Air Isolation Valve" is open.
C. If MSIVs closed due to low air pressure, place the MSIV hand switches to closed.
D. If normal letdown had not isolated due to low pressure, place the normal letdown isolation switches in open.
- 60. 067AK1.02 001 There is a fire in the generator hydrogen cooling system. Fire fighting efforts have caused the fire main header pressure to lower.
Which one of the following is the design pressure that will cause the FIRST diesel driven fire pump to start automatically?
A fire header pressure of .......
A. 85 psig.
B? 95 psig.
C. 105 psig.
D. 110 psig.
- 61. 068AK3.18 001 Evacuation of the Control Room is required due to a Control Room fire.
The actions of AOP 18038-1, "Operation From Remote Shutdown Panels," prior to evacuating the control room, include which of the following?
Aý Trip both main feedwater pumps.
B. Ensure S/G pressure control in AUTO C. Place the PZR pressure control in AUTO D. Trip all RCPs Tuesday, January 07, 2003 02:20:04 PM 29
QUESTIONS REPORT for srotest
- 62. 068K1.07 002 Which one of the following describes how the incore instrumentation seal table leakage enters the Liquid Rad Waste system?
A" Drains to Reactor Cavity Sump, and then is pumped to the Floor Drain Tank.
B. Drains to the floor drain, overflows into the Reactor Cavity Sump, and then is pumped to the Waste Monitor Tank C. Drains to the floor drain, overflows into the Reactor Cavity Sump, and then is pumped to the Floor Drain Tank D. Drains to Reactor Cavity Sump, and then is pumped to the Waste Monitor Tank.
- 63. 069AK2.03 002 Given the following conditions:
- The unit 1 RCS is at 190 OF and 350 psig
- The Aux Bldg. SO reported that both containment airlock doors are open Which one of the following is the correct action?
A. Close the outer door within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or reduce RCS temperature to 140 OF within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> BW Close the outer door prior to RCS heatup above 200 OF C. Close the outer door prior to RCS heatup above 350 OF D. Close the outer door within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and lock the outer door within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 64. 071K3.05 001 Chemistry has taken a grab sample of the release in progress from the gaseous radwaste system. The results indicate that the release is above the release permit setpoints.
Which one of the following caused this?
A" Waste Gas effluent monitor, RE-14, failed low.
B. Waste Gas effluent monitor, RE-14, failed high.
C. A loss of 125 vDC power to radiation trip valve, RV-001 4.
D. A loss of instrument air to radiation trip valve, RV-0014 Tuesday, January 07, 2003 02:20:04 PM 30
QUESTIONS REPORT for srotest
- 65. 072A1.01 002 ARE-2532A and ARE-2533A are indicating increasing levels of radiation.
If this trend continues which of the following should occur?
A. Only the Train A FHB isolation dampers close, the supply unit trips but the post-accident filter unit does not start.
B. The AREs will alarm locally and in the control room, initiating an isolation and a direct trip of the normal FHB HVAC units.
C. Only the Train A supply and exhaust dampers isolate, supply and exhaust units continue to run and the post-accident filter units start.
D." Train A and B supply and exhaust dampers isolate, the supply and exhaust units trip on low flow, and the post-accident filter units start.
- 66. 072G2.1.28 001 RE-0019, 0020 and 0021 are in alarm. Waste Water Retention Basin RV-0021 and FV-1 150 have just closed.
Which equipment caused the closure?
A. RE-0019 Only B. RE-0020 Only C! RE-0021 Only D. The Combination of both RE-0019 and RE-0020
- 67. 073A2.01S 001 Given the following:
- The Unit is in Mode 5
- The containment vent effluent radiation monitor's (RE-2565) power supply failed.
Which ONE of the following would be required to correct the automatic actions caused by this failure?
A. Reestablish flow from containment drains system to the waste water retention basin.
B. Secure the control room ventilation from safety grade filtration train.
C! Open containment purge supply and exhaust ducts.
D. Place the control room ventilation in safety grade filtration mode Tuesday, January 07, 2003 02:20:04 PM 31
QUESTIONS REPORT for srotest
- 68. 075A4.01 001 An operator making rounds reports that l-TI-1712, which measures the NSCW temperature at the outlet of the CCW Hx is reading 204 degrees F.
Which one of the following describes how this can be verified in the control room?
A. Use D/G jacket water inlet temperature since this is essentially the same temperature as the CCW Hx outlet temperature.
B. ACCW Hx outlet temperature can be used, a table is available to convert the indicated temperature.
C! Use the IPC since redundant information is available on the IPC.
D. CCW Hx and ACCW Hx flow can be used since a nomograph is available to convert the indicated temperature.
- 69. 076AA2.02 002 Given the following plant conditions:
- Unit is at 100%
- RCS Dose Equivalent Iodine-131 sample taken 0730 on 11/04/02 is 6.30 pCi/gram.
- RCS Dose Equivalent Iodine-131 sample taken 0730 on 11/06/02 is now 2.5 pCi/gram.
Based on these conditions which ONE of the following is the required action(s)?
A. Place all CVCS demins in service at maximum flow rate and continue power operations.
BY Place the Unit in Mode 3 at less than 500 degrees F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C. Continue to monitor dose equivalent Iodine 131 to ensure it remains within acceptable region once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
D. Complete a load reduction to less than 50% within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and monitor RCS Dose Equivalent lodine-131 every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 70. 076K2.08 001 Which one of the following describes the power supply for containment coolers 7 & 8 NSCW Supply Valve (HV-1 809)?
A. 480 Vac switchgear 1AB1 6 B. 480 Vac switchgear 1NB21 C! 480 Vac MCC 1BBD D. 480 Vac MCC 1NBM 32 Tuesday, January 07, Tuesday, January 02:20:04 PM 2003 02:20:04 07, 2003 PM 32
QUESTIONS REPORT for srotest
- 71. 079K4.01 002 If Station Instrument and Service Air System air pressure is dropping, the Service Air System is designed to automatically isolate from the Instrument Air System when pressure drops below which ONE of the following?
A. 70 psig.
B. 78 psig.
C. 80 psig.
D. 100 psig.
- 72. 086G2.4.25 002 During the response to a fire in the turbine building, an injured person must be transported off site. The only safe way to transport this person is via the Turbine Building elevator. The elevator is locked out. According to procedure 92005-C, which one of the following persons can authorize the use of the elevator during the fire?
A. Fire Team Captain, only B. The Unit Shift Supervisor of the affected unit, only C. Any Fire alarm response Team Member D. The Burke County Emergency Management Agency
- 73. 103A2.03S 002 Following a LOCA, containment pressure has reached 45 psig. Hydrogen concentration is 8%
and the Emergency Director instructed you to implement SOP-13130 "Diluting Containment Hydrogen Concentration Using the Service Air System".
Which one of the following is the required action to open the "Service Air to CNMT Header Isolation Valve", 1-HV-9385?
A. Only Train A CIA signal must be reset to open 1-HV-9385, then place 1-HS-9385A to OPEN, hold 1HS-9385B in OPEN until 1-HV-9385 is fully open.
B. Both Train A and B SI signals must be reset, then place 1-HS-9385B to OPEN, hold 1HS-9385A in OPEN until 1-HV-9385 is fully open.
Cf Both Train A and B CIA signals must be reset, then place 1-HS-9385A to OPEN, hold 1HS-9385B in OPEN until 1-HV-9385 is fully open.
D. Only Train A CIA signal must be reset to open 1-HV-9385, then place 1-HS-9385B to OPEN, hold 1HS-9385A in OPEN until 1-HV-9385 is fully open.
Tuesday, January 07, 2003 02:20:04 PM 33
QUESTIONS REPORT for srotest
- 74. G2.1.14 002 Given the following Conditions/events:
- Unit 1 is at 100% power
- Steam Generator Tube Rupture has occurred
- Reactor is manually tripped and SI is actuated
- Emergency Director declares an ALERT Which ONE of the following is the correct notification required for plant personnel according to Procedure 00004-C, "Plant Communications"?
A. A warble tone would be sounded for 15 seconds, then make page announcement warning personnel of the tube rupture and its location.
B. A siren tone would be sounded for 15 seconds, then make page announcement warning personnel of the tube rupture and its location C. Page announcement warning personnel of the tube rupture and its location there is no alarm required.
D. Page announcement warning personnel of the tube rupture and its location, then sound warble tone for 15 seconds.
- 75. G2.1.2 002 Given the following indications on Unit 1:
- 19030-C, SGTR is being implemented
- Both CCPs and both SIPs are running
- RCS pressure 1350 psig and falling slowly
- Level in S/G 1 is 80% NR rising slowly
- Level in other S/Gs is 5% NR rising slowly
- MSIVs are open
- RCS temperature is 558 degrees F and rising slowly Which ONE of the following describes the action to be taken and the basis for that action?
A. Dump steam at the maximum rate to cooldown the RCS.
B. Isolate SG#1 to minimize RCS cooldown.
C.f Stop all RCPs because RCP trip Criteria have been met prior to initiation of RCS cooldown.
D. Stabilize the level in intact S/Gs to preserve a heat sink for cooldown.
Tuesday, January 07, 2003 02:20:04 PM 34
QUESTIONS REPORT for srotest
- 76. G2.1.3 002 A procedure writer with an active RO license is in the control room to review a procedure revision. The RO is called for a random drug test. The RO requests that the procedure writer relieve him for about 15 minutes for the drug test.
Which one of the following describe the shift relief requirements for this situation?
The procedure writer may relieve the RO provided...
A ... the procedure writer reviews the narrative logs, rounds sheets, and checklists for his station. The review shall include narrative logs since the last shift worked or the preceding 3 days, which ever is longer.
B ... the procedure writer and the on-shift RO independently walk-down their assigned control boards to verify checklists items and discuss equipment status.
C ... the relief is 45 minutes or less and a) the relieving operator is knowledgeable of plant conditions, b) they perform a joint walkdown of applicable control panels, and c) the Unit Shift Supervisor acknowledges the relief.
D. ..... a full turnover is conducted as described in procedure 10004-C, Shift Relief.
- 77. G2.1.32 001 Which ONE of the following describes the normal configuration of the Component Cooling Water system and the reason, respectively?
A. 2 pumps running, one pump in pull-to-lock, to prevent CCW Hx tube vibration damage from excessive flow rates.
B. 2 pumps running, one pump in pull-to-lock, to avoid system pressure exceeding relief setpoints Cf 2 pumps running, one pump on standby, to avoid system pressure exceeding relief setpoints D. 2 pumps running, one pump on standby, to prevent CCW Hx tube vibration damage from excessive flow rates.
Tuesday, January 07, 2003 02:20:04 PM 35
QUESTIONS REPORT for srotest
- 78. G2.2.12 002 Unit 1 is at 100%
Surveillance 14905-1, RCS Leakage Calculation (Inventory Balance) is in progress Which ONE of the following would invalidate the leak rate calculation?
A. RCS diluted 50 gallons to raise RCS temperature back to program.
B. Main turbine load reduced 5 MWe to prevent exceeding allowed power limits.
C. Control rods inserted 5 steps for AFD control.
D. ECCS accumulator filled with an SI pump due to a slow leak.
- 79. G2.2.22 001 Which one of the following sets of conditions represents a violation of a technical specification safety limit and required action?
A. Power = 10%, Pressure = 2400 psig, Tavg = 655 0F, restore to within limits OR be in Mode 3 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> BY Power = 80%, Pressure = 2250 psig, Tavg = 640 0F, restore to within limits AND be in Mode 3 in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Power = 10%, Pressure = 2400 psig, Tavg = 655 0F, restore to within limits in 2 hrs or be in Mode 3 in 6 hrs D. Power = 80%, Pressure = 2250 psig, Tavg = 640 0 F, restore to within limits in 2 hrs or be in Mode 3 in 2 hrs
- 80. G2.2.29 001 The refueling SRO is directing refueling activities when he is notified that one source range channel failed its surveillance.
Which ONE of the following is the required action?
A. Suspend core alterations until the failed source range channel is operable B. Continue fuel reload as one channel is operable C. Continue fuel reload for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period until two source range channels operable.
D. Suspend core alterations until boron sampling has been completed Tuesday, January 07, 2003 02:20:05 PM 36
QUESTIONS REPORT for srotest 8 1. G2.2.3 002 Which one of the following decribes the Plant Integrated Computer (IPC) terminals?
They are in mirror image locations. The IPC terminals are identical except that .....
A. the common radiation monitors go to Unit 2 only and weather data goes to Unit 1.
B. the common radiation monitors go to Unit 1 only and weather data goes to Unit 2.
C. both the common radiation monitors and weather data go to Unit 1 only.
D. both the common radiation monitors and weather data go to Unit 2 only.
- 82. G2.2.8 001 Changes to which ONE of the following will require a 10CFR50.59 review?
A. Change to the Physical Security Plan that requires moving a section of the perimeter fence.
B. Revision to the Radiological Emergency Plan that changes the designated assembly areas for accountability.
C. System modification that adds a full flow recirculation test line to the discharge of the Safety Injection pumps.
D. Changes to the Nuclear Quality Assurance Plan.
- 83. G2.3.1 001 Which one of the following dose components are combined in a Radiation Worker's Occupational Dose?
A. Total Effective Dose Equivalent and Planned Special Exposures.
B. Planned Special Exposures and Committed Effective Dose Equivalent.
C. Total Effective Dose Equivalent and Committed Effective Dose Equivalent D. Deep Dose Equivalent and Committed Effective Dose Equivalent.
Tuesday, January 07, 2003 02:20:05 PM 37
QUESTIONS REPORT for srotest
- 84. G2.3.4 002 Given the following plant conditions:
- A LOCA occurred and a Site Area Emergency was declared.
- The TSC and OSC have been activated.
- It is recommended that entry be made into the Safety Injection Pump Room 1A to determine why the pump will not start.
- Projected dose rate in the pump room is 1.16x10 5 mr/hr.
- Duration of the exposure is expected to be 3 minutes.
Which ONE of the following may authorize this exposure?
A. EOF Manager B. Operations Support Center Manager C. Health Physics Supervisor D. Emergency Director
- 85. G2.3.8 002 A release of Waste Gas Decay Tank #1 is in progress. Which one of the following would require that the release be terminated?
A. RE-001 3, Waste Gas process monitor fails low and is declared inoperable by the USS B!' Waste Gas Decay Tank #2 pressure is lowering in conjunction with Gas Decay Tank #1 C. The inlet Oxygen analyzer on the recombiner panel is declared inoperable D. Auxiliary Building Continuous Exhaust Unit #1 trips on low flow Tuesday, January 07, 2003 02:20:05 PM 38
QUESTIONS REPORT for srotest
- 86. G2.3.9 001 Given the following conditions:
- Unit 1 is in Mode 2 following a refueling outage
- Containment Mini-Purge System was placed in operation in preparation for maintenance personnel to make a containment entry.
- Maintenance has requested the Mini-purge system be shutdown to reduce noise levels while they perform their activities.
Which ONE of the following should be considered prior to securing Containment Purge?
A. Outside air temperature and pressure B. Containment humidity Cf ALARA conditions D. Containment Purge HEPA and Charcoal filter DP
- 87. G2.4.1 002 Given the following events:
- Unit 1 reactor trip
- Operators observe the following conditons:
- 1AA02 is deenergized due to a bus fault
- 1B-DG supplying 1BA03
- 1BB06 feeder breaker trips during load sequencing Which of the following would describe the correct actions to take?
A. Remain in 19000-C on step 3 until power is restored to 1BB06 B. Transition to 19100-C, "ECA-0.0, Loss of All AC Power" C. Transition to 18031-C, "Loss of Class 1E Electrical Systems" Dý Continue in 19000-C while trying to restore power to 1AA02 and 1BB06 Tuesday, January 07, 2003 02:20:05 PM 39
QUESTIONS REPORT for srotest
- 88. G2.4.11 002 Given the following conditions:
- Unit 1 has been operating at 100% power with a 32 GPD tube leak for the last 3 months on S/G #2
- RE-724 &RE-810 became inoperable 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago, chemistry is investigating
- Chemisty sampling 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago indicated the leak rate was 37 GPD
- Chemisty sampling indicates the leak rate is currently 48 GPD Which ONE of the following should be performed per procedure 18009-C?
Aý Be in Mode 3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Reduce load to hot standby within 2 hrs, then cooldown and depressurize the RCS.
C. Trip the reactor; enter E-0, then transition to E-3.
D. Convene PRB to evaluate continued operation.
- 89. G2.4.16 001 While in the Emergency Response procedures the team is directed to "Go To" another procedure, which one of the following is the correct implementation of this action?
A. The "GO TO" implies the procedure in use is not applicable, and therefore any tasks in progress need not be completed.
B. The original procedure remains applicable because tasks still in progress must be completed prior to the transition directed by the "GO TO" step.
C:' The "GO TO" implies the procedure in use is no longer applicable, transition to the new procedure but any tasks in progress should be completed.
D. Tasks still in progress need not be completed prior to the transition directed by the "GO TO" step, unless preceded by a note stating otherwise.
Tuesday, January 07, 2003 02:20:05 PM 40
QUESTIONS REPORT for srotest
- 90. G2.4.8 002 Unit 1 has the following symptoms:
- Reactor is tripped
- core exit TC temperatures greater than 1200 F
- RVLIS full range indication is 25%
Which ONE of the following are your required actions?
Enter 19221-C FR-C.1, Response to Inadequate Core Cooling, from ....
A. Orange path on Core Cooling, and
- 1) Reinitiate high pressure safety injection
- 2) Rapidly depressurize the steam generators
- 1) Reinitiate high pressure safety injection
- 2) Slowly depressurize the steam generators
- 1) Reinitiate high pressure safety injection
- 2) Rapidly depressurize the steam generators
- 1) Reinitiate high pressure safety injection
- 2) Slowly depressurize the steam generators
QUESTIONS REPORT for srotest
- 91. WE02EK1.2S 002 Given the following conditions:
- Small LOCA is in progress
- SI termination criteria was met and the crew is currently terminating the SI per 19011-C "ES-1.1, SI Termination."
- Normal charging flow has been established
- RO raises charging flow to maximum with both CCPs running Which ONE of the following combinations of parameters would require reinitiation of safety injection per the foldout page of 19011 -C?
CNTMT RCS RCS PZR Press Subcooling Pressure Level A. 4 psig 65°F dropping 39%
B. 2 psig 48°F dropping 14%
C. 3 psig 35 0F stable 34%
D. 4 psig 55°F stable 24%
- 92. WE03EK2.2 002 Given the following plant conditions:
- A small break LOCA has occurred.
- RCPs have been tripped.
- Appropriate actions in accordance with 19010-C, E-1, Loss of Reactor or Secondary Coolant have been completed.
- RCS pressure is stable at 1525 psig.
- ECCS is operating in cold leg injection mode.
Which ONE of the following statements describes the primary method of decay heat removal at this time?
A.' Heat transfer between the RCS and the S/Gs due to natural circulation flow.
B. Heat transfer between the RCS and CCW via the RHR Heat Exchangers.
C. Heat transfer from the injection of water from the RWST and the removal of steam/water out of the break.
D. Heat transfer from Reflux boiling in the S/Gs.
Tuesday, January 07, 2003 02:20:05 PM 42
QUESTIONS REPORT for srotest
- 93. WE04EA2.1 002 Given the following sequence of events:
- Reactor trip and safety injection actuated due to a LOCA outside CNMT
- They enter 19111-C "Loss of Emergency Coolant Recirculation," since they were unable to isolate the leak.
Which of the following choices describes the correct actions to take in 19111-C under these conditions?
A. Initiate RCS cooldown, minimize ECCS flow to keep RVLIS full range >62% and start makeup to the RWST.
B. Initiate RCS cooldown, verify containment cooling units running in low speed, maximize the number of containment spray pumps running.
C. Shift containment cooling units to fast speed, stop all containment spray pumps, and minimize ECCS flow to maintain at least 24 deg F subcooling.
D. Initiate RCS cooldown, maximize ECCS flow to maintain subcooling > 74 deg F, and start makeup to the RWST.
- 94. WE05EA1.3 002 Given the following plant conditions:
- Operators implement 19231-C, "FR-H.1, Response to Loss of Secondary Heat Sink".
- RCS feed and bleed criteria were met.
- Manual Safety Injection was initiated and when the operator attempted to open the pressurizer PORVs, PORV 455 failed to open.
Which ONE of the following describes the correct operator mitigation strategy to respond to this problem?
A. Stop one Centrifugal Charging Pump to reduce loss of inventory through PORVs.
B. Close any open Pzr PORV to conserve RCS inventory and return to the steps to re-establish Main Feedwater.
C. Open the reactor head vents to reduce RCS pressure since one pressurizer PORV may not provide sufficient heat removal capacity.
D. Verify PORV 456 and its block valve open to reduce RCS pressure since 1 Pzr PORV provides adequate heat removal capacity for a loss of heat sink.
Tuesday, January 07, 2003 02:20:05 PM 43
QUESTIONS REPORT for srotest
- 95. WE07A2.01S 002 19221-C, "FR - C.1 Response To Inadequate Core Cooling" has been implemented. The following conditions exist:
- ECCS flow could not be established by any means
- The secondary depressurization was performed at the maximum rate per 19221-C
- Hot Leg temperatures are stable at 370 degrees F
- All S/G pressures are at 190 psig
- Core exit thermocouples temperatures are approximately 900 degrees F The crew should .......
A. Exit 19221-C and enter 19222-C, FR-C.2, Response to Degraded Core Cooling B. Ensure reactor coolant pumps running regardless of support conditions C. Continue S/G depressurization to atmospheric pressure, isolating the accumulators at RCS pressure < 150 psig D." Stop S/G depressurization, isolate accumulators, then depressurize S/Gs to atmospheric pressure
- 96. WE08EA2.IS 002 Given the following plant conditions:
- Crew is responding to a large-break LOCA
- RCS Integrity CSFST is Orange
- 19241-C, "FR-P.1, Response to Imminent Pressurized Thermal Shock Condition" is being performed
- Containment CSFST is now Orange Which of the following is the correct crew response if the PTS status tree turns Yellow prior to the completion of 19241-C?
A. The crew should stop performance of all Function Restoration Procedures, then evaluate all Critical Safety Functions to determine the appropriate procedure to implement.
B. Crew must complete 19241-C, since it is equivalent to the PTS Red path Function Restoration Procedure, unless it is superceded by a higher priority red path.
C.f Crew should continue with 19241-C, until transitioned out or the procedure is completed.
Status Trees will be evaluated at that time to determine the appropriate procedure.
D. Crew should stop performing 19241-C, and implement the Containment Orange path Function Restoration procedure since it now has the highest priority.
Tuesday, January 07, 2003 02:20:05 PM 44
QUESTIONS REPORT for srotest
- 97. WEIOEA2.2 002 Given the following plant conditions:
- Shutdown is in progress to comply with Tech Specs
- The unit must be in mode 4 within 60 minutes
- Reactor trip occurred with subsequent loss of RCPs.
- Operators have implemented 19002, "ES-0.2, Natural Circulation Cooldown".
- A cooldown rate of 50 0F/hour has been established.
- Current RCS temperature is 450°F
- Operators are monitoring PZR level and RVLIS for void formation.
Which ONE of the following describes the appropriate procedural actions.
A. STOP the cooldown and remain in 19002, "ES-0.2, Natural Circulation Cooldown".
B. RAISE the cooldown rate and remain in 19002, "ES-0.2, Natural Circulation Cooldown".
C. Transition to 19003-C, "ES-0.3, Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS)" and LOWER the cooldown rate.
D.' Transition to 19003-C, "ES-0.3, Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS)" and RAISE the cooldown rate.
- 98. WEI lEA1.3 002 Given the following plant conditions:
- Reactor trip and SI occurred on Unit 1 due to a LOCA.
- Crew is performing 19111-C "ECA-1.1, Loss of Emergency Coolant Recirculation", due to the failure of both RHR sump suction valves to open.
- Crew has reduced ECCS flow to one train per step 11 of 19111-C
- Crew is performing Step 19 of 19111-C to check ECCS flow adequate and observes the following indications:
- No RCP running
- RVLIS Full Range = 60% and slowly dropping Which one of the following lists the correct operator action for this condition?
A. Maintain the current ECCS alignment.
B! Raise ECCS flow to increase RVLIS indication.
C. Place RHR shutdown cooling in service.
D. Isolate the ECCS accumulators.
Tuesday, January 07, 2003 02:20:06 PM 45
QUESTIONS REPORT for srotest
- 99. WE13EK3.2S 002 The Unit 1 operating crew is currently executing 19010-C, "E-1, Loss of Reactor or Secondary Coolant". Plant conditions are as follows:
- Containment pressure is 4.5 psig and slowly decreasing.
- RCS temperature is 570°F.
- S/G Pressures: S/G #1 = 1200 psig; S/G #2 = 1190 psig; S/G #3 = 1250 psig; S/G #4 = 1205 psig.
- SG NR Levels: S/G #1 = 25%; S/G #2 = 30%; S/G #3 = 95%; S/G #4 = 35%.
- 19232-C, "FR-H.2, Response To Steam Generator Overpressure", has been entered.
For the existing plant conditions, the Unit Supervisor should:
A. Direct the operators to NOT release steam from S/G #3 and transition to 19233-C, "FR-H.3, Response to Steam Generator High Level" to control and lower S/G #3's level.
B. Direct the operators to NOT release steam from S/G #3 and continue with 19232-C to reduce S/G pressure.
C. Direct the operator to open the ARV on S/G #3 to drop pressure below 1220 psig then transition to 19233-C, "FR-H.3, Response to Steam Generator High Level" to control and lower S/G #3's level.
D. Direct the operator to open the ARV on S/G #3 to drop pressure below 1220 psig and continue with 19232-C to reduce S/G pressure.
100. WE16G2.3.10 002 Given the following:
- A Small Break LOCA occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.
- Containment pressure is 4.7 psig.
- Containment temperature is 227 OF.
- CNMT low range radition montors (RE-002/003) are in high alarm reading 12 R/hr
- 19253-C, "FR-Z.3, High Containment Radiation Level", is entered.
Which ONE of the following actions is required in accordance with 19253-C?
A. Peform a manual CIA to isolate CNMT air from outside air.
B.f Ensure CVI actuated and verify damper alignment is correct.
C. Place all CNMT lower level air circulators in service to lower radiation levels.
D. Ensure that all CNMT coolers are in service on high speed to increase flow through the HEPA filters Tuesday, January 07, 2003 02:20:06 PM 46