ML12283A404
| ML12283A404 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/04/2012 |
| From: | NRC/RGN-II |
| To: | Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-338/12-301, 50-339/12-301 | |
| Download: ML12283A404 (78) | |
Text
___________
ES-401 Site-Specific RO Written Examination Form ES.-401.-7 Cover Sheet US. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: September 19, 2012 Facility/Unit: North Anna Units 1 & 2 Region: I El II Ill El IV El Reactor Type: W CE El BW El GE El Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent
- 1. Given the following conditions:
- Unit 1 is at 80% power
- Control bank D is at 190 steps with rods in AUTO
- Median-Hi Select Tave 1-RC-Tl-1408A fails LOW As a result of this malfunction reactor power will (1) and the OTAT setpoint will (2)
(Consider the initial plant response prior to any actions occurring to terminate the rod motion)
A. (1) increase (2) decrease B. (1) increase (2) increase C. (1) decrease (2) decrease D. (1)decrease (2) increase
- 2. Unit 1 was initially at 100% power.
Operators tripped the reactor due to decreasing Pressurizer pressure & level.
The crew is implementing 1-E-3, Steam Generator Tube Rupture, and is at Step 12a, Determine required core exit temperature based on SG pressure.
Plant conditions are as follows:
- RCS pressure is 1270 psig and stable
- RCS Hot Leg Temperatures are 546°F and stable
- RCS Cold Leg Temperatures are 545°F and stable
- Core Exit TCs are 556°F and stable
- A train ICCM Subcooling is 20°F and stable
- B train ICCM Subcooling is 30°F and stable Based on these plant conditions, the OATC should inform the US that train ICCM indication is INCORRECT and A. A leave RCPs running B. A stop all RCPs C. B leave RCPs running D. B stop all RCPs
- 3. Unit 1 is at 100% power.
The OATC receives annunciator C-G7, RCP lA-B-C Seal Leak Hi Flow, and determines that seal leak-off flow for 1-RC-P-1A is pegged high.
The crew enters 1-AP-33.1, Reactor Coolant Pump Seal Failure.
Which ONE of the following 1-RC-P-1A indications is used to validate this condition in accordance with 1-AP-33.1 and states a correct required action in accordance with 1-AP-33.1?
A. Seal Injection flow; begin an orderly shutdown and stop 1-RC-P-1A B. Seal Injection flow; trip the reactor and stop 1-RC-P-1A C. Thermal Barrier temperature; begin an orderly shutdown and stop 1-RC-P-1A D. Thermal Barrier temperature; trip the reactor and stop 1-RC-P-1A
- 4. Operators have just finished synchronizing Unit 1 to the grid following a scheduled refueling outage.
1-RC-P-1B, B Reactor Coolant Pump trips.
Which ONE of the following identifies how B SG level will initially respond to this transient, and also correctly states whether a manual reactor trip is required?
A. decrease; manual Reactor trip is NOT required B. decrease; manual Reactor trip is required C. increase; manual Reactor trip is NOT required D. increase; manual Reactor trip is required
- 5. Which ONE of the following identifies the sources of power to the A Boric Acid Storage Tank heaters and includes how the heaters respond in the event of a loss of offsite power?
A. 1H and 1J emergency Busses; automatically restored when the EDG energizes its associated Emergency Bus B. 1H and 1J emergency Busses; must be manually reset after the EDG energizes its associated Emergency Bus C. 2H and 1J emergency Busses ; automatically restored when the EDG energizes its associated Emergency Bus D. 2H and 1 J emergency Busses; must be manually reset after the EDG energizes its associated Emergency Bus
- 6. Both Units are at 100%.
Burnup on Unit 1 is 3,000 MWD/MTU Burnup on Unit 2 is 12,500 MWD/MTU Which one of the following correctly completes the following statement?
The moderator temperature coefficient is more negative on (1) , and if power is lowered to 90%
on both units by boration then (2i will require a larger boration than the other unit.
A. (1)Unitl (2) Unit 1 B. (1)Unitl (2) Unit 2 C. (1)Unit2 (2) Unit 1 D. (1)Unit2 (2) Unit2
- 7. Initial Conditions:
- Unit 1 is in Mode 6 following a refueling outage.
- All 157 fuel assemblies were replaced with new assemblies
- Reactor vessel level is 74 above centerline and head bolt tensioning is in progress.
- VCT float is in service.
The running RHR pump trips.
Which of the following choices (1) identifies the effect, if any, this malfunction will have on Reactor Vessel level and (2) whether or not pump venting is required in accordance with 1-AP-il, Loss of RHR prior to placing the standby RHR pump in service?
A. (1) reactor vessel level remains constant (2) RHR pump venting IS required prior to placing the standby RHR pump in service B. (1) reactor vessel level remains constant (2) RHR pump venting IS NOT required prior to placing the standby RHR pump in service C. (1) reactor vessel level increases (2) RHR pump venting IS required prior to placing the standby RHR pump in service D. (1) reactor vessel level increases (2) RHR pump venting IS NOT required prior to placing the standby RHR pump in service
- 8. Given the following conditions on Unit 1:
- The RCS is solid
- RCS pressure is stable at 350 psi 9
- RCS temperature is stable
- RHR is in service and supplying letdown
- Letdown orifice HCVs are closed
- Charging flow control valve 1-CH-FCV-1 122 is set at 30% demand in MANUAL
- RHR to letdown isolation valve 1-CH-HCV-1142 is set at 50% demand
- Letdown pressure control valve 1-CH-PCV-1145 is set at 50% demand in MANUAL Which of the choices below correctly completes the following statements?
If the air line separates from the 1-CH-HCV-1142 actuator, RCS pressure will (1)
AND If the air line separates from the 1-CH-FCV-1122 actuator, RCS pressure will (2)
(Consider each failure independently)
A. Increase; Increase B. Increase; Decrease C. Decrease; Increase D. Decrease; Decrease
- 9. Operators are responding to a large break LOCA.
RWST level is 40% and decreasing.
Which ONE of the following identifies the setpoint at which automatic swap-over to the Containment sump should occur, and describes how a failure of 1-SI-MOV-1885A, Low-Head SI Pump Recirc Valve, to reposition would effect the swapover?
(1-SI-MOV-1885B, C and D repositioned as designed)
A. 16%; 1-Sl-MOV-1860A, Low-Head SI Pump Suction from Containment Sump WILL NOT automatically open B. 16% ; 1-SI-MOV-1860A, Low-Head SI Pump Suction from Containment Sump WILL automatically open C. 23%; 1-SI-MOV-1860A, Low-Head SI Pump Suction from Containment Sump WILL NOT automatically open D. 23% ; 1-Sl-MOV-1860A, Low-Head SI Pump Suction from Containment Sump WILL automatically open
- 10. Unit 1 tripped from 100% power due to a spurious Safety Injection signal.
The Crew is implementing 1-E-0, Reactor Trip or Safety Injection and the OATC has just taken the SI RESET switches to RESET.
Which ONE of the following identifies the effect that Train A Safety Injection failing to reset would have on subsequent recovery actions?
A. Placing 1-C H-P-lA in P-T-L will stop the pump; Train A of Phase A CANNOT be reset B. Placing 1-CH-P-1A in P-T-L will stop the pump ; Train A of Phase A CAN be reset C. Placing 1-CH-P-1A in P-T-L will NOT stop the pump; Train A of Phase A CAN be reset D. Placing 1-CH-P-1A in P-T-L will NOT stop the pump ; Train A of Phase A CANNOT be reset
- 11. Given the following:
Unit 1 was initially at 100% power.
Bistables for 1..RC-PT-1455, PRZR Pressure Protection Channel I, are in trip for the PT.
A loss of 1-Ill Vital AC Bus occurs.
The Crew has just completed the Immediate Actions of 1-E-0, Reactor Trip or Safety Injection.
Based on these plant conditions 1-CH-MOV-1 381, RCP Seal Return Isolation, remained open because of the loss of and RCP # 1 Seal Return is flowing to the A. power to the MDV PDTT B. power to the MDV; PRT C. power to Train B Safeguards slave relays; PDTT D. power to Train B Safeguards slave relays; PRT
- 12. Given the following conditions:
Operators tripped Unit 1 from 100% power due to a stuck open PRZR Safety Valve.
- The crew is performing the actions of 1-ES-i .2, Post LOCA Cooldown and Depressurization.
- Both LHSI pumps have been stopped.
- One charging pump has been stopped.
- Normal charging has been re-aligned.
- RCPs are OFF.
- The crew is on Step 21, Depressurize RCS to minimize break flow.
- The depressurization was stopped when subcooling reached 35°F The following conditions exist:
- RCS subcooling is 23°F and trending DOWN.
Based on these indications, what action will be taken in accordance with 1-ES-i .2?
A. Manually start charging pumps and align the BIT B. Start one RCP C. Manually actuate SI D. Increase RCS cooldown rate
- 13. Both Units are at 100%.
- 1-CC-P-lA is tagged and uncoupled for maintenance
- 2B CC Hx has been valved out for temperature control due to colder weather conditions The CC System is required by Tech Specs based on these plant conditions the LCO is A. to provide accident mitigation for a Steam the Generator Tube Rupture; MET B. to provide accident mitigation for a Steam the Generator Tube Rupture; NOT MET C. to cooldown one unit quickly while the other unit is operating should the need arise; MET D. to cooldown one unit quickly while the other unit is operating should the need arise; NOT MET
- 14. Unit 1 was initially at 100% power.
The OATC tripped the reactor due to decreasing PRZR Level and Pressure.
Offsite power was lost shortly after the trip.
The crew is currently preforming 1-ES-i .2, Post LOCA Cooldown and depressurization, Step 13, depressurize the RCS to refill the PRZR Plant conditions prior to starting depressurization were:
- PRZR Level 4% and stable
- RCS Subcooling 40°F and slowly increasing
- Core exit TCs 532°F and slowly decreasing While depressurizing, the OATC notes the following conditions:
- PRZR Level 40% and increasing rapidly
- RCS Subcooling -5°F and slowly decreasing
- Core exit TCs 530°F and slowly decreasing Given the current conditoins, which one of the choices below correctly answers the following questions?
(1) What is the method used for depressurization lAW 1-ES-i .2?
AND (2) Can depressurization continue lAW 1-ES-i .2?
A. (1) Auxilliary Spray (2) Depressurization can continue B. (1) Auxilliary Spray (2) Depressurization can NOT continue C. (i)PORV (2) Depressurization can continue D. (1)PORV (2) Depressurization can NOT continue
- 15. Unit 1 is at 100% power.
1-RC-PT-1456, PRZR Pressure Protection Channel II, failed high and 1-MOP-55.73, Pressurizer Pressure Protection Instrumentation, has been implemented, but bistables have NOT been placed in trip yet.
A loss of 1-I Vital 12OVAC Bus occurs.
Based on these plant conditions an automatic reactor trip occur and automatic Pressurizer Pressure Control is A. will not; available B. will not; NOT available C. will ; available D. will; NOT available
- 16. Given the following:
- Unit 1 is in Mode 3 following a scheduled refueling outage.
- 1-OP-1.4, Unit Startup from Mode 4 to Mode 3 is in progress
- RCS pressure is 700 psig
- RCS temperature is 375°F
- All letdown orifices isolation valves are open The following alarms are received:
- C-B3, REGEN HX LETDWN LINE HI TEMP
- C-B4, LO PRESS LETDWN LINE HI FLOW Which ONE of the following identifies the cause of these alarms and includes the corrective action the operator should take?
A. inadequate charging flow; place 1-CH-FCV-1122, Charging Flow Control Valve in MANUAL and increase charging B. inadequate charging flow; isolate Normal Letdown C. excessive letdown flow; place 1-CH-PCV-1145, Letdown Pressure Control Valve in MANUAL and fully close the valve D. excessive letdown flow; close one letdown orifice isolation valve
- 17. Unit 1 was operating at 100%.
A Large Break LOCA occurred at time 12:00.
The crew has completed 1-ES-i .3, Transfer to Cold Leg Recirc.
1-E-i, Loss of Reactor or Secondary Coolant, will direct the crew to go to i-ES-i .4, Transfer to Hot Leg Recirculation, after event initiation; the reason for this action is to A. 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />; preclude boron precipitation which could potentially hinder core cooling B. 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ; preclude accelerated localized corrosion of cladding in the upper regions of the core C. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />; preclude boron precipitation which could potentially hinder core cooling D. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />; preclude accelerated localized corrosion of cladding in the upper regions of the core
- 18. Unit 1 just cleared a Chemistry hold at 30% power and is ramping to 100% power following a scheduled refueling.
Which of the choices below completes the following statement?
As the Unit is ramped up the OATC should expect the (1) SETPOINT to change, and (2) is the input that has the largest impact on this setpoint over the course of the ramp.
A. (1)OPAT (2) axial flux B. (1)OPAT (2)Tave C. (1)OTAT (2)axial flux D. (1)OThT (2)Tave
- 19. Unit 1 is at 100% power.
Containment Pressure Protection Channel II (1-LM-P-100B) failed on the previous shift and all bistables have been positioned in accordance with 1-MO P-55.75, Containment Pressure Protection Instrument.
Which ONE of the following is true concerning a subsequent Containment Pressure Channel failure?
A. If 1-LM-P-100A, Containment Pressure Protection Channel I, fails high, CDA will actuate. Safety Injection and Main Steam Line Isolation will NOT actuate.
B. If 1-LM-P-1 CCC, Containment Pressure Protection Channel III, fails high, Safety Injection and Main Steam Line Isolation will actuate. CDA will NOT actuate.
C. If 1-LM-P-1 COD, Containment Pressure Protection Channel IV, fails high, CDA, Safety Injection and Main Steam Line Isolation will actuate.
D. A failure high of any one of the remaining Containment Pressure Protection Channels will NOT cause an ESF actuation.
- 20. A Reactor Startup is in progress on Unit 1.
Unit 1 is at 1.1 E-8 AMPs and stable.
The OATC has just completed recording critical data.
Annunciator A-G2, RPI Rod Bot Rod Drop, is received and the OATC observes that Rod Bottom Lights are ON for Rods D4 and M12, and the IRPIs for both indicate 0 steps.
Based on the above, select the choice that,
- 1) identifies the parameter that is the best to use to differentiate between an actual dropped rod condition versus an IRPI malfunction, and
- 2) includes the required operator action assuming the parameter has changed?
A. 1) RCS Tave
- 2) manually insert all control banks B. 1)RCSTave
- 2) trip the reactor C. 1) Intermediate Range SUR
- 2) manually insert all control banks D. 1) Intermediate Range SUR
- 2) trip the reactor
- 21. Select the choice that completes the following statement.
The instrumentation used to derive the Train A ICCM Subcooling display are RCS Wide Range Pressure and assuming all temperature instruments are reading 550°F, if a single temperature element in that train fails low the subcooling indication will A. core exit thermocouples ; decrease B. core exit thermocouples; NOT change C. RCS Wide Range Hot Leg RTDs ; decrease D. RCS Wide Range Hot Leg RTDs; NOT change
- 22. Unit 1 is at 50% power.
The crew is recovering from a failure of the selected Pressurizer Level Transmitter.
Operable PRZR level channels have been selected.
1-CH-FCV-1 122, Charging Flow Control Valve, is in manual.
Current conditions are:
- PRZR level is 50% and stable
- RCS Tave is 564° F and stable
- 1-RC-LC-1459G, Pressurizer Level Controller, is in manual with output at 10%
Based on the currect conditions, which one of the following describes the system status and the action required by 1-AP-3, Loss of Vital Instrumentation, to restore PRZR level control to automatic?
A. PRZR level is below program; increase charging to restore PRZR level to program, adjustment of 1-RC-LC-1459G is required prior to placing 1CH-FCV-1122 in automatic.
B. PRZR level is below program; increase charging to restore PRZR level to program, adjustment of 1-RC-LC-1459G is NOT required prior to placing 1-CH-FCV-1122 in automatic.
C. PRZR level is above program; decrease charging to restore PRZR level to program, adjustment of 1-RC-LC-1459G is required prior to placing 1-CH-FCV-1122 in automatic.
D. PRZR level is above program; decrease charging to restore PRZR level to program, adjustment of 1-RC-LC-1459G is NOT required prior to placing 1-CH-FCV-1122 in automatic.
- 23. Unit 1 is at 100% power.
The Mechanical Chiller has tripped and cannot be re-started.
As a result the crew should expect that over time the indicated partial pressure will (1) and the crew will restore a source of cooling water in accordance with 1-AP-35, Loss of Containment Air Recirculation Cooling, by aligning (2) to Containment Air Recirc Fans.
A. (1) increase (2) CC B. (1) increase (2) Service Water C. (1)decrease (2) CC D. (1)decrease (2) Service Water
- 24. Unit 1 is cooling down for a scheduled refueling.
The crew has just completed placing RHR in service.
1-RH-P-lB and 1-CC-P-lB are running.
1-RH-P-A and 1-CC-P-lA are in standby with the control switches in AUTO-AFTER-STOP.
A lightning strike results in a loss of the A RSST.
All remaining equipment functions as designed.
With no operator action, 1 minute after the loss of the A RSST the Unit 1 OATC should expect that there will be RHR pump(s) running and Unit 1 CC pump(s) running.
A. 0:1 B. 0;2 C. 1;1 D. 1;2
- 25. Select the choice that completes the following description of the Recirc Spray Sub-systems.
In the event of a Design Basis Loss of Coolant Accident, when RWST level reaches 60%,
the (1) Recirc Spray Pumps will start following a two minute time delay; NPSH to these pumps is increased by the operation of the (2) pumps.
A. (1) Inside (2) Casing Cooling B. (1) Inside (2) Quench Spray C. (1) Outside (2) Casing Cooling D. (1) Outside (2) Quench Spray
- 26. Unit 1 is at 100% power.
1-RC-PT-1444, PRZR Pressure Control Transmitter fails HIGH As a result of the failure, the demand on 1-RC-PC-1444J, Master Pressure Controller, will and in accordance with 1-AP-44, Loss of Reactor Coolant System Pressure, the OATC will place 1-RC-PC-1444J in MANUAL and depress the pushbutton.
A. increase; lower B. increase; raise C. decrease; raise D. decrease; lower
- 27. According to the System Design Basis Document, the Containment Iodine Filtration Fans are powered from (1) and are placed in operation to (2)
A. (1) Emergency Busses (2) reduce airborne radioactivity in Containment prior to opening Containment for a normal refueling outage.
B. (1) Emergency Busses (2) minimize release during a postulated fuel handling accident inside Containment.
C. (1) Station Service Busses (2) reduce airborne radioactivity in Containment prior to opening Containment for a normal refueling outage.
D. (1) Station Service Busses (2) minimize release during a postulated fuel handling accident inside Containment.
NAPS 2012 NRC RD Exam
- 28. Unit 1 was initially at 100% power A load rejection occurred causing a PRZR Safety to lift and stick open.
The reactor tripped and SI actuated.
Current plant conditions are:
- Subcooling on Train A & Train B ICCMs is 50°F and decreasing
- The PRZR Safety is still stuck open
- PRT pressure is 80 psig and increasing Based on the current plant conditions, which of the following choices:
(1) identifies whether or not RCPs are required to be tripped lAW 1-E-0, Reactor Trip or Safety Injection, AND (2) how PRZR level will respond during the performance of 1-E-0.
A. (1) tripping all RCPs is NOT required (2) PRZR level will decrease B. (1) tripping all RCPs is NOT required (2) PRZR level will increase C. (1) tripping all RCP5 is required (2) PRZR level will decrease D. (1) tripping all RCPs is required (2) PRZR level will increase
- 29. Given that Containment Purge is in-service on Unit 1.
Which ONE of the following identifies the two items that can cause automatic isolation of the Containment Purge?
A. 1-RM-RMS-159, Containment Particulate Radiation Monitor Hi-Hi alarm.
Manual Actuation of Containment Isolation Phase A.
B. 1-RM-RMS-162, Manipulator Crane Radiation Monitor Hi-Hi alarm.
1-VG-RI-180-1, MGP Vent Stack B Rad monitor Hi alarm.
C. 1-RM-RMS-159, Containment Particulate Radiation Monitor Hi-Hi alarm.
1-RM-RMS-162, Manipulator Crane Radiation Monitor Hi-Hi alarm.
D. Manual Actuation of Containment Isolation Phase A.
1-VG-RI-180-1, MGP Vent Stack B Rad monitor Hi alarm.
- 30. Unit 1 was initially at 100% power when the following sequence of events occurred:
- A Main Steam Trip Valve drifted closed causing a Safety Injection
- The OATC notes that the Reactor Trip breakers failed to open and manually trips the reactor.
- All equipment functions as designed EXCEPT B Reactor Trip Breaker failed to open.
- The OATC momentarily places both SI reset switches in RESET per the applicable EOP Based on the above sequence of events, which of the following choices correctly states (1) the status of SI reset AND (2) the status of SI automatic initiation A. (1) ONLY the A train of SI is reset (2) ONLY the A train of SI automatic initiation is blocked B. (1) ONLY the A train of SI is reset (2) BOTH trains of SI automatic initiation are blocked C. (1) BOTH trains of SI are reset (2) ONLY the A train of SI automatic initiation is blocked D. (1) BOTH trains of SI are reset (2) BOTH trains of SI automatic initiation are blocked
- 31. Which ONE of the following identifies the correct differential pressure limit across the SG U-tubes?
A. 1600 psid primary-to-secondary B. 600 psid primary-to-secondary C. 670 psid secondary-to-primary D. 1085 psid secondary-to-primary
- 32. The following conditions exist:
- A SGTR has occurred on Unit 2
- The RCS cooldown is complete and the crew is preparing to depressurize the RCS in accordance with 2-E-3, Steam Generator Tube Rupture.
Which ONE of the following describes the reason for the RCS depressurization?
A. Increases SI flow to increase RCS inventory while decreasing the amount of leakage to the ruptured SG.
B. Allows backflow of the ruptured steam generator into the RCS minimizing contamination levels in the generator.
C. Prevent lifting a SG safety valve.
D. Ensures there will be no release of radioactivity through the ruptured SG PORV for the duration of the event.
- 33. Unit 1 was initially at 100% when a Loss of Coolant Accident (LOCA) occurred.
Subsequent to the LOCA a loss of offsite power occurred.
Unit 1 is now on Cold Leg Recirc and the crew is performing 1-E-1, Loss of Reactor or Secondary Coolant.
The crew is at 1-B-i, Step 24, Check if intact SGs should be depressurized to RCS pressure In accordance with 1-B-i and its background document, which one of the choices below correctly completes the following statement?
The depressurization will be performed using the (1)
AND the depressurization (2) performed to aid in further cooldown and depressurization of the RCS.
A. (1) condenser Steam Dumps (2) is B. (1) condenser Steam Dumps (2) is NOT C. (i)SGPORV5 (2) is D. (1)SGPORV5 (2) is NOT
- 34. Operators are performing 1-ECA-2.1, Uncontrolled Depressurization of ALL Steam Generators.
Containment pressure is 26 psia and slowly decreasing.
SG NR Levels are:
- SG A is 18%
- SG B is 19%
- SG C is 20%
Which of the choices below completes the following statements?
lAW the CAUTION prior to Step 2 of 1-ECA-2.1 and the current plant conditions. a MINIMUM AFW flow of 100 gpm (1) required to be supplied to each SG; the reason for this requirement is (2)
A. (1) is (2) preclude water hammer if feed flow is subsequently increased to control RCS temperature B. (1)is (2) minimize thermal stresses if feed flow is subsequently increased to control RCS temperature C. (1)isNOT (2) preclude water hammer if feed flow is subsequently increased to control RCS temperature D. (1)isNOT (2) minimize thermal stresses if feed flow is subsequently increased to control RCS temperature
- 35. Which ONE of the following identifies (1) how main steam header pressure responds as turbine load is raised from 25% to 65%, and (2) how Moderator Temperature Coefficient (MTC) will change as boron concentration is decreased during the ramp?
A. (1) Main steam header pressure rises.
(2) MTC becomes more negative.
B. (1) Main steam header pressure rises.
(2) MTC becomes less negative.
C. (1) Main steam header pressure lowers.
(2) MTC becomes more negative.
D. (1) Main steam header pressure lowers.
(2) MTC becomes less negative.
- 36. Unit 1 was initially at 100% power with Auxiliary Feedwater Pump 1-FW-P-3A tagged out.
A spurious Safety Injection occurred and all equipment functioned properly except:
- Auxiliary Feedwater Pump 1-FW-P-2 oversped and tripped when starting up
- Auxiliary Feedwater Pump 1-FW-P-3B shaft sheared when starting up Operators are implementing 1-F-a, Reactor Trip or Safety Injection, and are at step 7, Verify AFW Flow Current plant conditions are:
- C SG WR level 44%, slowly lowering Based on the current plant conditions, transition to 1-FR-Hi, Loss of Secondary Heat Sink, is and A. required ; bleed and feed criteria is NOT met B. required ; bleed and feed criteria is met C. NOT required ; Enter H.i ONLY after exiting E-0 D. NOT required ; Enter H.1 ONLY when directed by E-0
- 37. Given the following plant conditions:
- Unit 2 has experienced a Loss of All AC power.
- The US has directed the SBO operator to energize 2H Emergency Bus Based on the above plant conditions, the SBO operator will energize and place the interlock defeat switch for the Feeder breaker to 2H Bus in SBO, in order to allow this Feeder breaker to be closed with breaker A. L 4160v Bus 05L1 closed B. L 4160v Bus; 15E1 open C. M 4160v Bus ; 05L1 closed D. M 4160v Bus; 15E1 open
- 38. Given the following conditions:
- Unit 1 is at 35% power ramping up following a scheduled refueling
- The Turbine Operator reports that one of the Condenser Air Ejector Loop Seal Drain lines feels hot to the touch
- The OATC notes that Condenser pressure is 3 in Hg abs and slowly degrading
- The crew has entered 1-AP-14, Loss of Condenser Vacuum, and commenced a ramp down at 2%/minute.
5 minutes after starting the 2%/minute ramp down the OATC reports the following:
- Condenser pressure is 4 in Hg abs and stable
- Tave is 557°F
- Tref is 556°F Based on the OATC report, which ONE of the following identifies the action required lAW 1-AP-14?
A. Trip the Turbine and go to 1 -AP-2. 1, Turbine Trip Without Reactor Trip.
B. Continue the ramp until condenser pressure is 3.5 in Hg abs or less.
C. Trip the Reactor and go to 1-E-O, Reactor Trip or Safety Injection.
D. Hold the ramp and place Rods in MANUAL.
- 39. Unit 1 tripped from 100% due to a loss of offsite power.
Plant conditions are as follows:
- PRZR Pressure is 2100 psig and slowly increasing
- PRZR level is 38% and slowly increasing
- RCS Tavg is 552°F and stable The immediate actions of 1-E-0, Reactor Trip or Safety Injection have been completed, but no other operator actions have been taken.
Which of the choices below; (1) identifies the current status of Group 1 and Group 4 PRZR Heaters AND (2) correctly states the required capacity of Pressurizer Heaters lAW LCO 3.4.9, Pressurizer.
A. (1) energized (2) Two groups of pressurizer heaters with the capacity of each group> 125 KW B. (1)energized (2) Two groups of pressurizer heaters with the capacity of each group> 250 KW C. (1) de-energized (2) Two groups of pressurizer heaters with the capacity of each group> 125 KW D. (1) de-energized (2) Two groups of pressurizer heaters with the capacity of each group > 250 KW
- 40. Unit 1 is at 12% power preparing to go on-line.
Several annunciators are received and the BOP reports a loss of Vital 12OVAC Bus 1-Ill.
Which ONE of the following identifies the immediate impact of the loss of Vital 12OVAC Bus 1-Ill?
A. Condenser steam dumps will close but can be opened by placing the controller in MANUAL; outward rod motion is possible B. Condenser steam dumps will close but can be opened by placing the controller in MANUAL; outward rod motion is NOT possible C. Condenser steam dumps will close and CANNOT be opened from the control room ; outward rod motion is possible D. Condenser steam dumps will close and CANNOT be opened from the control room ; outward rod motion is NOT possible
- 41. Given the following conditions:
- Unit 1 is at 100% power
- 125VDC bus 1-I is lost due to a grounded cable Which ONE of the following describes the effect of this malfunction on the 1 H EDG?
A. The EDG excitation circuit is unaffected; The EDG output breaker can be closed from the control room B. The EDG excitation circuit is unaffected; The EDG output breaker CANNOT be closed from the control room C. The EDG excitation circuit is de-energized; The EDG output breaker can be closed from the control room D. The EDG excitation circuit is de-energized; The EDG output breaker CANNOT be closed from the control room
- 42. Unit 1 is at 25% power.
Feed Control has been transfered to the Main FRVs and all 3 are in automatic.
Assuming NO operator action is taken, which ONE of the following malfunctions would result in AFW automatically starting PRIOR to the reactor automatically tripping?
A. A SG controlling level channel fails high B. A SG controlling steam pressure channel fails low C. Feed back arm falls off A Main FRV D. A Main FRV fails closed
- 43. Fuel movement is in progress in the Fuel Building and the fuel handlers report that an assembly has been dropped and appears to be damaged.
A Hi Alarm is received on 1-RM-RMS-153, Fuel Pit Bridge Radiation Monitor.
Which ONE of the following identifies the corrective action to be taken by the Control Room crew in accordance with O-AP-5.1, Common Unit Radiation Monitoring System, and includes the recorder that is used to monitor the effectiveness of that action?
A. isolate fuel building ventilation to stop or reduce release; 1-RM-RR-179, MGP Vent Stack A B. isolate fuel building ventilation to stop or reduce release; 1-RM-RR-180, MGP Vent Stack B C. place fuel building exhaust through the charcoal filters; 1-RM-RR-179, MGP Vent Stack A D. place fuel building exhaust through the charcoal filters; 1-RM-RR-180, MGP Vent Stack B
- 44. Unit 1 tripped spuriously from 100% power.
Operators have transitioned to 1-ES-0.1, Reactor Trip Response.
The crew has just completed throttling AFW per 1-ES-O.1.
If the pressure sensing line for 1-FW-PCV-159B were inadvertently severed, AFW flow to the A. B SG will decrease B. B SG will increase C. C SG will decrease D. C SG will increase
- 45. Unit 1 is in Mode 3.
Severe thunder storms are causing large swings in grid voltage and frequency.
Operators are responding to a spurious SI and have just completed Step 5 of 1-E-0, Reactor Trip or Safety Injection.
The 1J bus voltage has taken a step change from 4000 volts to 3700 volts.
The OATC should expect bus stripping to occur after the degraded voltage condition occurs and as a resuft A. 2 seconds; 1-CH-P-1 B breaker opens and then re-closes once the EDG restores power to the bus.
B. 2 seconds; 1-OH-P-lB breaker remains closed throughout the event.
C. 7.5 seconds; 1-OH-P-lB breaker opens and then re-closes once the EDG restores power to the bus.
D. 7.5 seconds 1-OH-P-lB breaker remains closed throughout the event.
- 46. Unit 1 is at 100% power.
The OATC receives FW < STM Flow alarms on all three SGs The OATC notes that both the red and green position indicator lights are OFF on all three MFRVs A possible cause of these indications is a breaker has tripped on the A. 1-Ill AC Bus B. 1-IVAC Bus C. 1-Ill DC Bus D. 1-JV DC Bus
- 47. Unit 1 is at 100% power.
The crew is performing 1-PT-82H, 1H EDG Slow-Start Test and are slowly raising load on the EDG.
Current conditions are:
- EDG load is 800 KW.
- Reactive load is 0 KVAR.
A loss of off-site power (LOOP) occurs.
Once all automatic actions have taken place, the EDG operator should expect to see that real load has and reactive load has (Assume no actions are taken by the EDG operator in response to the transient)
A. increased; remained the same B. increased; increased C. decreased; remained the same D. decreased ; increased
- 48. In accordance with Technical Specifications, for a Loss of Offsite Power the EDG shall energize its associated Emergency Bus in less than or equal to and all automatic trips are bypassed EXCEPT for A. 10 seconds; Overspeed ONLY B. 10 seconds; Overspeed AND Generator Differential C. 12 seconds; Overspeed ONLY D. 12 seconds; Overspeed AND Generator Differential
- 49. Given both Units at 100% power.
A fire has been confirmed in the Unit 1 Cable Vault and the crew is implementing 1-FCA-3, Cable Vault and Tunnel Fire.
1-FCA-3, will direct the crew to AND the type of fire protection system in the cable vault is A. Shutdown the Unit using 1-AP-2.2, Fast Load Reduction; Halon B. Shutdown the Unit using 1-AP-2.2, Fast Load Reduction: C02 C. Manually trip the Unit: Halon D. Manually trip the Unit: C02
- 50. Consider the following EDG start signals:
- 1) Manual Start (Control Room)
- 2) Automatic Start (Bus Under Voltage Signal)
- 3) Automatic Start (Safety Injection Signal)
Select the choice that completes the following:
Placing the Control Room Emergency (CRE) switch for an EDG in the EMERG position will PREVENT EDG start from__________________________________
A. 1&2ONLY B. 2&3ONLY C. 3 ONLY D. 1 ONLY
NAPS 2012 NRC RO Exam 51 Which ONE of the choices below correctly; (1) states whether the CLOSE pushbuttons for 1-DA-TV-100A & 1-DA-TV-100B, containment sump pump discharge trip valves, must be pushed after resetting phase A isolation in order to restore sump pumping capability AND (2) states the tanks to which the containment sump pumps normally discharge?
A. (1) Close pushbuttons are required to be pushed after phase A reset (2) Low Level Liquid Waste Tanks (LLLW Tanks)
B. (1) Close pushbuttons are required to be pushed after phase A reset (2) High Level Liquid Waste Tanks (HLLW Tanks)
C. (1) Close pushbuttons are NOT required to be pushed after phase A reset (2) Low Level Liquid Waste Tanks (LLLW Tanks)
D. (1) Close pushbuttons are NOT required to be pushed after phase A reset (2) High Level Liquid Waste Tanks (HLLW Tanks)
- 52. Annunciators K-D2, RAD MONITOR SYSTEM HI RAD LEVEL, and K-D4, RAD MONITOR SYST HI-HI RAD LEVEL, were received due to 1-RM-LW-1 11, Clarifier Outlet, failing high.
lAW O-AP-5.1, Common Unit Radiation Monitoring System, the operator verifies all of the following actions have occurred EXCEPT ?
A. Contaminated Drain Tank pumps tripped B. 1-LW-PCV-1 15 (Liquid Waste Tunnel Isol Control) closed C. Low-Capacity Steam Generator Blowdown pumps tripped D. 1-LW-FCV-100 (Holdup Tank Influent Valve) closed
- 53. Given the following conditions:
- A WGDT release is in progress.
- 1-GW-RM-178-1, Process Vents Rad Monitor, indication is trending up.
As 1-GW-RM-178-1 continues to increase, 1-GW-FCV-1O1, WGDT to Process Vents, will remain open until the alarm is received. Assuming the indication begins trending down at that point and returns to normal, 1-GW-FCV-1O1 A. Hi ; will automatically re-open B. Hi ; will NOT automatically re-open C. Alert will automatically re-open D. Alert ; will NOT automatically re-open
- 54. Both Units are at 100% power.
1-SW-P-lA was tagged out yesterday for scheduled maintenance 2-SW-P-i B trips and the crew enters 0-AP-i 2, Loss of Service Water Based on these plant conditions, will lose Service Water flow, and lAW 0-AP-12, the crew will perform A. Unit 1 CC HXs ; Attachment 6, Aligning One SW Pump per Supply Header when NO Pumps are Running on One Header B. Unit 1 CC HXs Attachment 10, Operation of Auxiliary Service Water Pumps C. Unit 2 CC HXs : Attachment 6, Aligning One SW Pump per Supply Header when NO Pumps are Running on One Header D. Unit 2 CC HXs Attachment 10, Operation of Auxiliary Service Water Pumps
- 55. Given the following:
12:00 Unit 1, 100% power 12:20 Unit 1, 82% power and stable following a fast ramp due to secondary issues Which of the choices below correctly completes the following statements?
(1) TS 3.4.16, RCS Specific Activity, requires sampling and analysis of the RCS (1)
AND (2) Sampling is performed to verify reactor coolant Dose Equivalent (2) specific activity is less than the limit.
A. (1) anytime within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of initiating the power change (2)1-131 B. (1) anytime within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of initiating the power change (2) Xe-i 33 C. (1) between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the power change (2)1-131 D. (1) between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the power change (2) Xe-i 33
- 56. Both Units are at 100% power.
1-SW-P-lB and 2-SW-P-lB are running.
1-SW-P-lA and 2-SW-P-lA are in standby with the control switches in AUTO-AFTER-STOP.
A spurious Train A SI occurs on Unit 2.
Prior to any operator actions, there will be SW pumps running and SW flow to Unit 2 CC HXs has A. 3 ; decreased B. 3; increased C. 4; decreased D. 4; increased
- 57. Unit 1 is at 100% power and Unit 2 is in refueling.
A Grid disturbance results in a 10 kV decrease in switchyard voltage.
The System Operator requests that you raise voltage back to the pre-event value.
Current conditions are:
- Switchyard Voltage 514 KV
- Generator MVARS -100 MVARS Based on the current conditions, the Offsite Power Source is (1) and assuming the OATC is using the adjust and wait method of raising Switchyard Voltage, after making the first adjustment he should expect Generator MVARS to be (2)
A. (1) Inoperable (2) more negative B. (1) Inoperable (2) less negative C. (1)Operabie (2) more negative D. (1) Operable (2) less negative
- 58. Select the choice that completes the description of how instrument air is provided for B Main Steam Trip Valve, 2-MS-TV-201 B.
Instrument air is supplied to B Main Steam Trip Valve, 2-MS-TV-201 B, via solenoid operated valves (SOVs), any one of the SOVs will close 2-MS-TV-201 B.
A. 2 ; energizing B. 2; de-energizing C. 6 ; energizing
- 0. 6; de-energizing
- 59. While at 100% power, which ONE of the following conditions represents a loss of containment integrity lAW Technical Specifications?
A. An operator discovers steam emitting from a pipe-to-body weld on the upstream side of 1-CH-TV-1204B, Reactor Coolant Letdown Line Isolation Valve.
B. An electrician opens the outer containment airlock door to perform maintenance activities without prior approval.
C. While performing an operability test of two normally open redundant containment isolation valves, one of the valves fails to close.
D. The LMC drain line upstream of the containment hogger isolation valve is discovered with the pipe cap missing and the drain valve closed.
NAPS 2012 NRC RD Exam
- 60. Unit 1 is at 100% power.
Tags are being cleared on 1-SD-P-lA, A High Pressure Heater Drain Pump.
lAW OP-AA-200, Equipment Clearance, which of the choices below correctly completes the following statements?
The (1) pressure side of the pump shall be unisolated first AND (2) verification shall be used to clear the electrical tags.
A. (1) high (2) Independent B. (1) high (2) Concurrent C. (1)10w (2) Independent D. (1)10w (2) Concurrent
- 61. Preparations for core off-load are in progress lAW 1-OP-4.1, Controlling Procedure for Refueling.
Which ONE of the following conditions DOES NOT meet the requirements of 1-OP-4.1, Attachment 2, Core Alterations Checklist?
A. Refueling Cavity Level is 290 feet B. A Containment Air Recirc Fan (CARF) running, B and C CARFs tagged out C. N-31 is operable and N-32 is tagged out D. Personnel Air Lock Emergency Escape doors are closed with the operating handles CAUTION tagged
- 62. Unit 1 is at 95% power and stable.
The reactor operator is calculating core thermal power lAW 1-PT-24, Hand Calorimetric, but does not include the effects of reactor coolant pump heat or steam generator blowdown flow.
Which of the choices below correctly completes the following statements concerning the calculated core thermal power?
Not including reactor coolant pump heat will cause the calculated value to be (1) than actual power.
AND Not including steam generator blowdown flow will cause the calculated value to be (2) than actual power.
A. (1) lower (2) lower B. (1) lower (2) higher C. (1) higher (2) higher D. (1) higher (2) lower
- 63. Unit 1 is at 100% power.
Operators have performed 1-MOP-31.6, Subsection 5.1, Removing 1-FW-P-1A, Main Feedwater Pump, from Service and Tagging the Pump for Maintenance, and have pulled the patch cords for the associated annunciators in accordance with the procedure.
The associated annunciators are to be added to the Disabled Annunciator List and are to be entered into the Temporary Modifications Log.
A. required; NOT required B. required ; required C. NOT required; NOT required D. NOT required ; required
- 64. Unit 1 core off-load is in progress.
SFP level and Reactor Cavity level begin decreasing.
lAW O-AP-27, Malfunction of Spent Fuel Pit System, the Fuel Building is required to be evacuated A. if a high alarm is recieved on 1-RMS-RM-153, SFP Bridge Crane rad monitor B. as soon as all fuel assemblies are in a safe location C. if radiation levels in the Fuel Building reach 1 R/HR D. if level decreases more than 4 feet 2 inches below the 0 reference mark
- 65. Isolation of Service Water blowdown (close 1-SW-i 5, Service Water Supply Header #1 to Liquid Waste System Isolation Valve) is listed in O-GOP-17, Time Critical Operations Actions.
Which ONE of the following identifies the upper time limit for closing this valve, and includes the reason for this upper time limit?
A. 29 minutes; auxiliary building flooding B. 29 minutes; auxiliary building radiation levels C. 59 minutes ; auxiliary building flooding D. 59 minutes ; auxiliary building radiation levels
- 66. lAW VPAP-2 101, Radiation Protection Program, which of the choices below correctly completes the following statements?
A radiation worker can receive _(1)_ Rem TEDE prior to exceeding the annual radiation worker administrative dose limit for their home site.
AND A radiation worker can receive (2) Rem TEDE prior to exceeding the annual radiation worker 10CFR2O Federal dose limit.
A. (1)2 (2) 3 B. (1)2 (2) 5 C. (1)1.7 (2) 3 D. (1) 1.7 (2) 5
- 67. Given the following:
- A Large break LOCA occurred on Unit 1.
- The crew has transitioned to 1-ES-i .3, Transfer to Cold Leg Recirculation, and are in the process of verifying proper Service Water System Operation lAW Step 3 of 1-ES-i.3.
The STA reports Critical Safety Function Status Trees (CSFSTs) are as follows:
Subcriticality Green Core Cooling Orange Heat Sink Red-RCS Integrity Red-Containment Yellow Inventory Yellow Which ONE of the following correctly identifies the crew response?
A. Immediately transition to i-FR-P.i, Response to Imminent Pressurized Thermal Shock Condition B. Immediately transition to i-FR-Cl, Response to Inadequate Core Cooling C. Immediately transition to i-FR-Hi, Response to Loss of Secondary Heat Sink D. Continue with ES-i .3, Transfer to Cold Leg Recirculation
- 68. Assume the EPIPs are entered and a Notification of Unusual Event is declared at 12:00.
lAW the applicable Emergency Plan procedures, the State must be notified no later than and activation of the TSC is A. 12:15: Required B. 12:15 NOT Required C. 13:00 ; Required D. 13:00 ; NOT Required
- 69. Assume the initial notification of state and local governments of an ALERT Classification has been made.
Select the choice that correctly completes the following:
lAW EPIP-2.O1, Notification of State and Local Governments, a follow-up report (update) should be provided to state and local governments approximately every (1) (unless otherwise agreed upon with the State); changing the Emergency Classification to Notification of Unusual Event (2) one of the update criteria of EPIP-2.O1.
A. 60 minutes; is NOT B. 60 minutes ; is C. 30 minutes; is NOT D. 30 minutes ; is
- 70. Unit 1 is at 100% power with all equipment in a normal configuration.
A LOCA occurs and the crew enters 1-E-O, Reactor Trip or Safety Injection.
Which of the choices below correctly completes the following:
(1) is an indication of RCS leakage into the Safeguards building AND (2) will have to be closed by the operator to isolate the leak lAW 1 -ECA-1 .2, LOCA Outside Containment.
A. (1) High alarm on 1-VG-RI-180-1, (MGP) Vent Stack B Noble Gas Normal Range (2) 1-SI-MOV-1890C & 1890D, Low Head SI Pumps Cold Leg Injection Valves B. (1) High alarm on 1-VG-RI-180-1, (MGP) Vent Stack B Noble Gas Normal Range (2) 1-SI-MOV-1890A & 1890B, Low Head SI Pumps Hot Leg Injection Valves C. (1) High alarm on 1-VG-Rl-179-1, (MGP) Vent StackA Noble Gas Normal Range (2) 1-Sl-MOV-1890C & 1890D, Low Head SI Pumps Cold Leg Injection Valves D. (1) High alarm on 1-VG-Rl-179-1, (MGP) Vent Stack A Noble Gas Normal Range (2) 1-Sl-MOV-1890A & 1890B, Low Head SI Pumps Hot Leg Injection Valves
NAPS 2012 NRC RD Exam
- 71. Unit 1 was tripped from 100% power due a Condensate System header rupture.
Subsequently a Tornado struck damaging the Unit 1 ECST.
Current status is:
- The Shift Manager directed securing Unit 1 AFW pumps to prevent them from operating without a suction source
- Operators have transitioned to 1-FR-Hi, Response to Loss of Secondary Heat Sink.
- Wide Range SG levels are approximatley 50% and slowly decreasing.
Which of the following choices identifies (1) the action required by 1-FR-H.1 with respect to the RCPs and (2) the preferred source of alternate makeup water for the AFW pumps?
A. (1) Stop ALL RCPs (2) Fire Main Water from the lake B. (1) Stop ALL RCPs (2) Service Water C. (1) Stop ALL but ONE RCP (2) Fire Main Water from the lake D. (1) Stop ALL but ONE RCP (2) Service Water
- 72. Given the following:
- A Large steam break occurred outside CNTMT on the A Main Steamline
- Offsite power was subsequently lost
- The crew has transitioned to 1-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition
- SI has been terminated
- Letdown is NOT in-service
- The crew is at step 17 Depressurize RCS to Decrease RCS Subcooling Based on the above, the OATC will depressurize using and stop the depressurization at 69% PRZR LEVEL in order to A. ONE PRZR PORV; ensure the PRZR has a substantial steam bubble for pressure control B. ONE PRZR PORV; limit reactor vessel head voiding for core cooling C. Auxiliary spray; ensure the PRZR has a substantial steam bubble for pressure control D. Auxiliary spray; limit reactor vessel head voiding for core cooling
- 73. Given the following:
- The reactor was tripped 45 minutes ago.
- All RCPs were tripped.
- The plant cooldown is being performed in accordance with 1-ES-O.3, Natural Circulation Cooldown With Steam Void in Vessel (With RVLIS).
- The crew is preparing to start a RCP Current plant conditions are:
- RVLIS Upper Range indication is 80% and stable.
- PRZR level 30% and stable
- RCS Subcooling based on core exit TCs 60°F and stable Which ONE of the following describes the relationship of the current plant conditions to those required by 1-ES-0.3 for starting the RCP?
A. Current plant conditions are acceptable for RCP start B. PRZR level is acceptable for RCP start; RCS Subcooling is NOT acceptable for RCP start C. PRZR level is NOT acceptable for RCP start; RCS Subcooling is acceptable for RCP start D. PRZR level is NOT acceptable for RCP start; RCS Subcooling is NOT acceptable for RCP start
- 74. Given the following:
- A LOCA has occurred.
- NO LHSI pumps could be started and the crew has transitioned from 1-E-1 Loss of Reactor or Secondary Coolant, to 1-ECA-1.1, Loss of Emergency Coolant Recirculation
- Containment pressure has been slowly increasing throughout the event and is 21 psia and still slowly increasing.
- RWST level is 86% and lowering.
- The Recirc Spray sump level is 2 feet.
- The crew is at step 8, Determine Containment Spray Requirements.
lAW 1-ECA-1.1, which of the choices below identifies:
(1) how many Recirc Spray pumps are required to be operating AND (2) how many Quench Spray pumps are required to be operating?
(Reference Provided)
A. (1) 0 recirc spray pumps are required (2) 2 quench spray pumps are required B. (1) 0 recirc spray pumps are required (2) 0 quench spray pumps are required C. (1) 2 recirc spray pumps are required (2) 2 quench spray pumps are required D. (1) 2 recirc spray pumps are required (2) 0 quench spray pumps are required
- 75. Unit 1 is on Cold Leg Recirculation following a LOCA and Loss of Offsite Power.
The following Containment conditions exist:
- CNTMT Pressure 22 psia and slowly increasing
- CNTMT Sump Level 12 feet and slowly increasing Based on the Containment conditions the crew is required to implement in order to mitigate the potential for_______________________________________
A. 1-FR-Z.1, Response to High Containment Pressure; accident doses to exceed acceptable limits B. 1-FR-Z.1, Response to High Containment Pressure; equipment qualification limits to be exceeded C. 1-FR-Z.2, Response to High Containment Sump Level; plant components/indications to be damaged by flooding D. 1-FR-Z.2, Response to High Containment Sump Level; excessive depletion of Service Water Reservoir inventory
REFERENCE PROVIDED TO APPLICANT 1-ECA-1.1 Page 8 of 36, Rev 17 GFE EQUATIONS AND CONVERSIONS SHEET
NAPS 2012 NRC EXAM ANSWER KEY I A 51 B 2 D 52 A 3 D 53 B 4 B 54 A 5 B 55 C 6 D 56 D 7 D 57 D 8 A 58 C 9 B 59 A 10 C 60 D 11 D 61 C 12 A 62 C 13 C 63 A 14 D 64 C 15 C 65 B 16 D 66 B 17 A 67 0 18 D 68 B 19 B 69 B 20 D 70 A 21 B 71 A 22 C 72 A 23 D 73 C 24 B 74 A 25 B 75 C 26 B 27 C 28 B 29 C 30 C 31 A 32 A 33 C 34 B 35 C 36 A 37 B 38 C 39 C 40 D 41 B 42 C 43 D 44 C 45 D 46 C 47 B 48 B 49 D 50 D