LaSalle 2012 NRC - ILTandMe

#1. Unit 2 is at 100% power when the scram air header pressure regulator fails CLOSED. Which of the following would be the FIRST response of the RPS system?

a. Scram on SDV High Level

b. Scram on Group 1 Isolation

c. Scram on APRM Thermal Hi Hi

d. Scram due to Reactor Water Level 8 Feedwater Pumps trip

#2. Unit-1 and Unit-2 are at rated power Which one of the following might you expect FIRST as a result of a lowering station air dryer outlet pressure?

a. Closure of the Feedwater Testable Check Valves.

b. Decreasing Feed Pump Suction Pressure.

c. Increasing TBCCW Expansion Tank level.

d. Closure of the Inboard MSIVs.

#3. Given the following conditions: Unit 2 is at rated conditions. Bus 236X-2 has lost power. Which one of the following sets of Average Power Range Monitors (APRMs) and LPRM Groups would indicate downscale?

a. APRM E and LPRM Group A.

b. APRM E and LPRM Group B.

c. APRM F and LPRM Group A.

d. APRM F and LPRM Group B.

#4. Given the following on Unit 1: Reactor is in Mode 5 with the shorting links equipment status tagged and REMOVED. Off-Gas Air Purge is in progress. Which of the following identifies the immediate impact a loss of 24VDC Bus 1B will have on Unit 1?

a. Half Scram and Off-gas isolation

b. Off-gas isolation ONLY

c. Full Scram ONLY

d. Half Scram ONLY

#5. Unit 2 was at rated conditions when the Unit 2 TSC UPS output failed to zero volts. Which of the following would be expected to occur?

a. Reactor scram on low reactor water level.

b. TDRFP Speed Control Trouble alarms.

c. TSC Diesel Generator auto start.

d. Process computer failure.

#6. While operating at 100% reactor power; the following alarms were received on Unit 1: Which one of the following is the component of MOST limiting concern?

a. Reactor Recirculation Pump Motor Windings

b. Fuel Pool Cooling Demineralizer Resin

c. RWCU Demineralizer Resin

d. CRD Pump Motor Windings

#7. Given the following: Paralleling of 141Y with the 0 DG is in progress 0 DG is at rated frequency and voltage ACB 2413; 0 DIESEL GEN TO BUS 241Y; indicates open Div 1 Synchroscope indicates at the 12 O Clock position The ACB 1413; 0 DIESEL GEN TO BUS 141Y; sync switch is in OFF. What happens if the ACB 1413; 0 DIESEL GEN TO BUS 141Y; control switch is taken to CLOSE and then NAC?

a. Breaker CLOSES and and trips OPEN after a time delay.

b. Breaker CLOSES and immediately trips OPEN.

c. Breaker CLOSES and remains CLOSED.

d. Breaker remains OPEN.

#8. The following manual actions were performed on the SBGT Train in the following sequence: (1) Inlet Damper OPENED (2) Cooling Fan STARTED (3) Outlet Damper OPENED (4) Primary Fan STARTED What is the earliest point in the sequence of events you would expect the Standby Gas Treatment Electric Heater to energize?

a. 1

b. 2

c. 3

d. 4

#9. The following conditions exist on Unit 1: Shutdown is in progress. Reactor Power is STEADY on IRM Range 4. Ten seconds after starting to insert the SRMs; from the fully withdrawn position; the RO notices the SRM Period Meter indicates as shown below. Is the SRM response EXPECTED or NOT EXPECTED and why? (Note: Assume the core flux is peaked in the CENTER of the core.)

a. This reading is NOT EXPECTED. The period meter should be indicating infinity because reactor power is steady.

b. This reading is EXPECTED. The period meter is responding to detector movement and is an accurate indication of period.

c. This reading is NOT EXPECTED. The period meter should indicate a positive period because the detectors are approaching the center of the core.

d. This reading is EXPECTED. The SRMs are bypassed under the current plant conditions.

#10. Unit 1 is operating at 100% of rated thermal power operating on the 100% Flow Control Line All nuclear instruments are operable The C Flow Unit fails to 0% Based on the above conditions; which of the following correctly states the effect on the unit?

a. A Full Scram.

b. A Rod Block ONLY.

c. A Rod Block and a Half Scram.

d. A Flow Comparator alarm ONLY.

#11. Given the following Unit 2 conditions: DBA LOCA occurs on Unit 2 Unit 2 Southeast Corner Room water level is 20 inches above floor level and rising 12 inches/minute Unit 2 RPV water level is at top-of-active fuel and steady Which of the following identifies ALL the ECCS systems that will be injecting into the Unit 2 reactor vessel 10 minutes later?

a. A RHR / LPCS; B/C RHR

b. A RHR / LPCS; HPCS

c. B/C RHR; HPCS

d. LPCS; HPCS

#12. The Division 1 and 2 batteries are sized to start and carry the normal DC loads; plus all DC loads required for Safe Shutdown; and perform the required switching operations for a minimum of _________ hour(s) following the loss of all AC sources.

a. one (1)

b. four (4)

c. eight (8)

d. twelve (12)

#13. The operator has just placed the A RPS MG SET into service IAW LOP-RP-01; Reactor Protection System Startup and Operation. Given the following: 2C71-BS001 2H13-P610 MG SETS TRANSFER SWITCH is in the NORM position. 2C71-S003A Electrical Protection Assembly (EPA) Breaker is CLOSED. 10 seconds later 2C71-S003A EPA Breaker indicates the following due to its high voltage setpoint drifting down: Which of the following indications would you expect to see on the local A RPS MG SET voltage meter?

a

b

c

d

#14. A normal Unit-1 Shutdown is in progress. The 1A loop of RHR has just been placed into Shutdown Cooling. The following conditions exist: Reactor water level is +45 inches and stable 1A RHR Pump flow is 5000 gpm 1A RR loop flow is 3000 gpm 1B RR loop flow is 3400 gpm RHR Service Water flow to the 1A RHR Heat Exchanger is 8400 gpm In order to raise the 1A RHR cooldown rate; the operator throttled open the 1E12-F053A; A RHR SHTDN CLS RETURN ISOL; until 1A RHR pump flow was 6200 gpm. Which one of the following statements is correct with regards to the above conditions? “

a. RHR Service Water flow is in the range allowed ONLY for emergency operations.

b. All parameters are within the range of normal Shutdown Cooling operations.

c. 1A RHR pump flow is above the point that will cause Jet Pump vibration.

d. The 1A Reactor Recirculation Pump may be dead headed.

#15. Given the following: 0 DG is running and is the only available power supply to the associated Unit 1 bus. CO2 Trouble Alarm (Zone 419) is received Operators have left the room and report NO Fire but CO2 has initiated (1) What impact would this have on the 0 DG? (2) What actions should be taken FIRST to control those conditions?

a. (1) 0 DG will trip. (2) ISOLATE CO2 to the 0 DG room.

b. (1) 0 DG will trip. (2) RESTART the 0 DG room ventilation fan.

c. (1) 0 DG will continue to operate. (2) ISOLATE CO2 to the 0 DG room.

d. (1) 0 DG will continue to operate. (2) RESTART the 0 DG room ventilation fan.

#16. Given the following: Unit 2 is at rated conditions. Main Steam Line Flows are matched at 3.7 Mlb/hr. 2A TDRFP speed control fails such that speed is 5800 rpm. (1) Predict the response of Reactor Water Level Control (RWLC) and (2) Select the procedurally required action to mitigate the event.

a. (1) Reduces demand signal to 2B TDRFP (2) TRIP 2A TDRFP

b. (1) Transfers 2A TDRFP to DEMAND Substitution (2) Place RWLC in Single Element

c. (1) Reduces demand signal to 2B TDRFP (2) Place RWLC in Single Element

d. (1) Transfers 2A TDRFP to DEMAND Substitution (2) TRIP 2A TDRFP

#17. Given the following conditions: Unit 2 was at rated conditions. Group 1 isolation on Low Condenser Vacuum occurred. RCIC and HPCS are injecting. LPCS is in a normal standby lineup. Reactor Pressure is 1050 psig (highest pressure was 1100 psig). Immediately following the highest pressure reading you are directed to record SRV Tailpipe Temperatures from the 2H13-P614 panel. Which SRV Tailpipe temperatures are reading significantly higher than before the transient?

a. ALL SRVs

b. SRVs U and S ONLY

c. SRVs S; C; U; R; V; E and D ONLY

d. SRVs D; E; S; K; C; U; P and F ONLY

#18. Unit 1 is operating at 75% power. A Low Pressure Core Spray (LPCS) pump surveillance is in progress with the system maintaining rated flow. The 1E21-F001 Thermal Overload Bypass Switch is in TEST. Which of the following indications will be observed FIRST if the LPCS system receives a high drywell pressure signal with a simultaneous Sudden Pressure signal in the Unit 1 Unit Auxiliary Transformer (UAT)?

a. LPCS pump trips.

b. Injection valve starts to open.

c. Minimum Flow valve starts to open.

d. Full Flow Test valve starts to close.

#19. Given the following conditions on Unit 1: Reactor water level: -60 inches and STABLE Which of the following Primary Containment Isolation Valve indications is EXPECTED?

a.

b.

c.

d.

#20. LOCA conditions exist in the Drywell: Reactor Pressure is 475 psig and dropping slowly Reactor Water Level is -140 inches and STABLE Drywell Pressure is 0.5 psig and STABLE (Max value reached 2.0 psig) ADS has automatically initiated and 7 valves are OPEN Based solely on the above conditions; what effect would depressing both divisional LOW LEVEL RESET pushbuttons have on the ADS logic?

a. All ADS valves would CLOSE and stay CLOSED.

b. The logic is not affected; all ADS valves would remain OPEN.

c. All ADS valves would CLOSE; then time delay Re-OPEN in less than 2 minutes.

d. All ADS valves would CLOSE; then Re-OPEN immediately as both pushbuttons are released.

#21. Given the following conditions: Unit 1 is in MODE 3. The 1A Emergency Diesel Generator is declared INOPERABLE following surveillance testing. Which of the following actions are required to be taken within one (1) hour of determining the Emergency Diesel Generator is INOPERABLE?

a. Perform LOS-VC-M1; Control Room Emergency Makeup Unit Operability Test.

b. Perform LOS-DG-SR3; 1A and 2A Diesel Generator Action Statement Operability Test.

c. Perform LOS-AA-W1 Attachment 1D and 2D; Unit One and Unit Two Tech Spec Weekly Offsite Power Lineup Verification.

d. Perform LOS-VQ-SR2; Primary Containment Vent And Purge HEPA Filter And Charcoal Filter Leak Test.

#22. While operating at 100% power you receive the following annunciators ONLY: Predict the impact on HPCS. HPCS will …

a. START and inject at 1650 gpm.

b. START and inject at 6250 gpm.

c. START and run on Minimum Flow.

d. remain in STANDBY.

#23. A manufacturing defect resulted in a flow path between the outer tube of the SBLC injection line and the bottom head area. Which of the following describes the consequences of this failure?

a. HPCS Line Break Detection would be unreliable.

b. CRD Drive Water Flow indication would fail to zero.

c. SBLC solution will not inject into the proper vessel area.

d. RWCU Bottom Head Drain Flow indication would fail to zero.

#24. Given the following indication while shutting down Unit 1: (1) What is the indication for SRM B as compared to the other 3 SRMs? (2) What action must the Reactor Operator take per procedure?

a. (1) Reads Higher (2) Stop ALL rod motion and bypass SRM B

b. (1) Reads Lower (2) Stop ALL Rod Motion and bypass SRM B

c. (1) Reads Higher (2) Continue rod motion and place SRM B function switch to STANDBY

d. (1) Reads Lower (2) Continue rod motion and place SRM B function switch to STANDBY

#25. Per LSCS UFSAR RCIC is designed …

a. as an ECCS system to assure adequate core cooling during a loss of feedwater.

b. as an ECCS system to assure adequate core cooling during a loss of main turbine bypass valves.

c. to assure adequate core cooling during a loss of feedwater; but NOT as an ECCS system.

d. to assure adequate core cooling during a loss of main turbine bypass valves; but NOT as an ECCS system.

#26. Unit 1 is starting up IAW LGP 1-1; NORMAL UNIT STARTUP REACTOR MODE SWITCH is in STARTUP. Select the one statement that describes a condition in which the Intermediate Range Monitor (IRM) detector(s) is(are) functioning properly.

a. IRM A and IRM G detectors both fail upscale and a reactor scram occurs.

b. IRM B indicates 111/125 of scale on range 7 and NO rod block signal occurs.

c. IRM B indicates 124/125 of scale on range 6; a rod block and a half-scram occurs.

d. IRM C detector drawer mode switch is placed in STANDBY and ONLY a rod block occurs.

#27. The plant is at 93% thermal power. Using the drawing provided; identify how the SIGNAL VALUES at the points marked A and B would change if one Safety Relief Valve were to FAIL OPEN in this situation.

a. A. Signal Value A Higher Signal Value B Higher

b. B. Signal Value A Higher Signal Value B Lower

c. C. Signal Value A Lower Signal Value B Higher

d. D. Signal Value A Lower Signal Value B Lower

I cannot find the drawing that was provided with this question

#28. Given the following conditions: 1A and 1B FC pumps are running for Fuel Pool Cooling 1B RHR is running in Fuel Pool Cooling Assist Which of the following power supplies; if LOST; would have the greatest impact on Fuel Pool Cooling?

a. 141Y

b. 142Y

c. 141X

d. 142X

#29. The Unit 1 NSO is withdrawing control rod 18-43 from position 00 to position 08 for a sequence exchange. The control rod settles at position 12. Which ONE of the following best describes the effects of the control rod movement? The control rod will have the MOST significant effect on (1) ; and will be indicated PRIMARILY on (2) .

a. (1) Radial Power distribution (2) APRMs

b. (1) Radial Power distribution (2) All 16 LPRMs for the selected rod

c. (1) Axial Flux shape (2) All 16 LPRMs for the selected rod

d. (1) Axial Flux shape (2) APRMs

#30. Given the following conditions: The Unit-1 Standby Gas Treatment System (SBGT) is in operation to support an ongoing surveillance. An event occurs on the refuel floor that causes 0D21-K604A Refuel Floor High Range ARM to exceed its respective trip setpoint. The following events then occur: 12:00 – The U1 Standby Gas Treatment fan breaker trips 12:05 – A low flow condition exist on Unit 1 SBGT train 12:10 – A second refuel floor ARM exceeds its trip setpoint 12:15 – Reactor Building Ventilation (VR) exhaust PRMs reach their trip setpoint Based on these conditions; what is the earliest time that the Unit-2 SBGT would automatically start?

a. 12:00

b. 12:05

c. 12:10

d. 12:15

#31. If elevated drywell temperatures were to cause the reference leg of the Wide Range Level instrument to flash to steam; and actual level was 10 inches; what would you expect the Wide Range Level instrument to indicate in the Control Room?

a. +180 inches

b. +60 inches

c. 0 inches

d. -150 inches

#32. Unit 2 is shutting down. The RR pumps LFMG Set Drive Motor Breakers 1A and 1B have been closed in preparation for downshifting both pumps. The NSO takes Reactor Recirc Motor Breakers 3A and 3B to Transfer MG position. When the Reactor Recirc Motor Breakers 3A and 3B are taken to Transfer MG the LFMG Set Drive Motor Breaker 1A also trips OPEN. What will be the status of the RR pumps sixty (60) seconds later? 2A RR Pump 2B RR Pump

a. Off Off

b. Fast Fast

c. Fast Slow

d. Off Slow

#33. Given the following: Unit 1 is running at rated conditions 1A Primary Containment Cooling (VP) Chiller running 1A Primary Containment Cooling (VP) Chill Water pump trips The operator immediately starts 1B Primary Containment Cooling (VP) Chill Water pump and the 1B Drywell Cooler Supply Fan. (1) What is the maximum expected cooling provided by the Primary Containment Cooling? (2) What is the expected Primary Containment pressure response?

a. (1) 10 minutes of residual cooling is provided (2) remains stable for 5 minutes; then starts to increase

b. (1) 20 minutes of residual cooling is provided (2) start increasing within the first 10 minutes

c. (1) 10 minutes of residual cooling is provided (2) start increasing within the first 5 minutes

d. (1) 20 minutes of residual cooling is provided (2) remains stable for 10 minutes; then starts to increase

#34. Unit 1 is at rated power with the 1A CRD Pump online and the following indications: The required action is to……

a. swap to FCV; 1C11-F002B.

b. swap to standby stabilizer valve.

c. swap to the standby drive water filter.

d. throttle CRD drive pressure control valve; 1C11-F003; closed.

#35. Unit 1 is at rated power when the operator observes the following: Which of the following is the cause of these indication for the four control rods in the red box?

a. Data Faults

b. Rods are at the overtravel position

c. Probe MUX Card not responding

d. No position switches are CLOSED

#36. Unit 1 is at rated power. The following indications are observed: An Equipment Operator reports that the breaker for the 1B21-F418A; MS TO AS LOADS SUPPLY ISOL VLV; is tripped and will NOT reset. Which of the following is the impact of the valve being de-energized?

a. Loss of steam to Main Steam Bypass valves

b. Loss of steam to the Steam Seal Evaporator (SSE)

c. Loss of HP steam to the 1A TDRFP

d. Loss of a MSIV Leakage Control Boundary valve

#37. Both Units are operating at rated conditions. FP is in a normal lineup. Fire system checks are being performed at the Lake Screen House. POINT 1 POINT 2 TIME PRESSURE PRESSURE 10:05 195 psig 175 psig 10:10 lowers to 140 psig lowers to 110 psig 10:15 lowers to 115 psig lowers to 85 psig 10:20 raises to 150 psig raises to 120 psig 10:25 raises to 195 psig raises to 175 psig Predict the automatic start and stop times of the Fire Protection Intermediate Jockey Pump. START STOP

a. A. 10:15 10:20

b. B. 10:15 10:25

c. C. 10:10 10:20

d. D. 10:10 10:25

#38. During performance of the shiftly surveillance on Unit 2; MCPR is discovered to have decreased from a value of 1.21 to 1.09. (1) Based on this information you can conclude that the number of fuel clad failures will … (2) What is the maximum time you have to complete the required Tech Spec actions?

a. (1) increase significantly and reactor power must be reduced. (2) 2 hours

b. (1) remain relatively stable but reactor power must be reduced. (2) 2 hours

c. (1) increase significantly and reactor power must be reduced. (2) 1 hour

d. (1) remain relatively stable but reactor power must be reduced. (2) 1 hour

#39. What are the operational implications of RPS having a built in time delay of 10 seconds before allowing a SCRAM to be manually reset?

a. To ensure all the control rods fully insert.

b. To allow the Scram Air header to repressurize.

c. To allow Rod Worth Minimizer to determine shutdown status.

d. To ensure the Scram Discharge Volume vent and drain valves fully closed.

#40. Given the following Unit 2 conditions: – Reactor is in Hot Shutdown – All electrical power being supplied from the System Auxiliary Transformer (SAT) -The SAT trips for unknown reasons. – There were no bus fault alarms activated Assuming NO OPERATOR ACTIONs are taken; predict the status of the following buses 30 seconds after a trip of the SAT. Bus 236X | Bus 237Y

a. Energized | Energized

b. Energized | De-energized

c. De-energized | Energized

d. De-energized | De-energized

#41. Unit 1 is at rated conditions Safety Relief Valve; 1B21-F013K; has inadvertently opened due to a failed ‘B’ solenoid during normal full power operation. Which of the following identifies the expected indications available to the operator when this event occurs? 1B21-R614A; Tail Pipe 1H13-P601 Valve Temperature Recorder Position Indication

a. 525 to 540°F RED light ON ONLY

b. 525 to 540°F GREEN light ON ONLY

c. 310 to 335°F GREEN light ON ONLY

d. 310 to 335°F RED light ON ONLY

#42. Given the following indications: AND TRACOR Point 3; 1A COOLER RETURN; indicates 135°F TRACOR Point 4; 1B COOLER RETURN; indicates 115°F Which of the following High Drywell temperature alarms; if any; are in? (1) 1PM13J-A503; SUP CHBR AIR PRESS HI/DW AIR TEMP HI (2) 1PM13J-B503; SUP CHBR AIR PRESS HI/DW AIR TEMP HI

a. 1 ONLY

b. 2 ONLY

c. 1 and 2

d. NO alarms

#43. Given the following: 2A RHR is in Shutdown Cooling with a flow of 6200 gpm. 2E12-F047A; ‘A’ RHR HX INLET VLV; is OPEN. 2E12-F003A; ‘A’ RHR HX OUTLET VLV; is OPEN. 2E12-F048A; ‘A’ RHR HX BYPASS VLV; is OPEN Reactor water level is +45 inches on the Shutdown Range. No RR pumps are running. 2B33-F023A; RR PMP SUCT VLV; is OPEN. 2B33-F067A; RR PMP DSCH VLV; is CLOSED. Which of the following by itself would result in a loss of Shutdown Cooling due to inadequate reactor recirculation flow?

a. lowering Reactor water level by 7 inches

b. closing 2E12-F048A; ‘A’ RHR HX BYPASS VLV

c. closing 2E12-F003A; ‘A’ RHR HX OUTLET VLV

d. opening 2B33-F067A; RR PMP DSCH VLV

#44. Using the attached REFERENCE: Unit ONE was operating at 65% power and 67 Mlb/hr core flow. A transient occurred; resulting in the following: 1A Reactor Recirc Pump shaft sheared. APRMs indicate Reactor Power at 45%. Core Flow indicates 37 Mlb/hr. 1H13-P603-A408 OPRM TRIP ENABLE did NOT alarm AND 1H13-P603-A109 OPRM HI is in SOLID. What are the required operator actions?

a. Immediately SCRAM the reactor – Exit to LGP-3-2.

b. Insert CRAM rods ONLY to a power less than 35%.

c. Monitor APRM/LPRM noise levels two times normal while shutting down the ‘A’ Reactor Recirc Pump.

d. Lower Recirc Core Flow with the ‘B’ Flow Control Valve AND insert CRAMS to exit both region 1 and 2.

#45. Unit 1 was operating at rated conditions when a grid disturbance resulted in lowering frequency on the Main Generator. Plant conditions stabilize and the following conditions exist: LOR-0PM12J-B407; 345 KV SYSTEM FREQUENCY LO; is in alarm. Generator frequency is steady at 58.3 Hz The Unit 1 CRS directs operators to Manually Scram and verify Main Turbine Trips. This direction is&

a. REQUIRED; the generator brushes will become overloaded.

b. REQUIRED; an automatic generator trip should have occurred.

c. REQUIRED; operation at this frequency will cause turbine blade damage.

d. NOT REQUIRED; the generator can operate indefinitely at this frequency.

#46. LGA-005; RPV Flooding; specifies actions that use steam cooling method of heat transfer to (1) that the reactor core remains adequately cooled under conditions when (2) source of ECCS injection into the RPV is permitted.

a. (1) maximize the time (2) a single

b. (1) indefinitely ensure (2) a single

c. (1) maximize the time (2) NO

d. (1) indefinitely ensure (2) NO

#47. When fighting a fire on site with a failure of both Diesel Fire Pumps: LOA-FP-101; Unit-1 Fire Protection System Abnormal; directs you to SHUTDOWN or SCRAM the reactor if a minimum fire header pressure; indicated on 1PM10J; of at least (1) CANNOT be maintained; because Service Water may have to be diverted to the fire protection header in order to ensure minimum required pressure is available for fighting fires (2) .

a. (1) 125 psig; (2) in multiple locations at the same time

b. (1) 125 psig; (2) on the Refuel Floor

c. (1) 175 psig; (2) on the Refuel Floor

d. (1) 175 psig; (2) in multiple locations at the same time

#48. Which of the following is directed to be monitored per LOA-WR-101; Loss of Reactor Building Closed Cooling Water RBCCW during reduced cooling capacity conditions in the RBCCW system?

a. RR Pump seal cavity outlet temperature

b. Offgas Refrigeration Machine glycol outlet temperature

c. IN Compressor intercooler discharge temperature

d. RWCU Pump Motor Cooler outlet temperature

This question was deleted following exam review

#49. With the reactor operating at 50% power; the Main Turbine Trips due to low EHC pressure. Which one of the following describes the initial expected Reactor Recirculation (RR) pump response to this event?

a. Trips to OFF due to ATWS-RPT signal

b. Downshifts to SLOW speed due to EOC-RPT signal

c. Remains in SLOW speed with FCVs full OPEN

d. Trips to OFF due to Low Reactor Water Level

#50. The following conditions exist 15 minutes following a loss of offsite power. Reactor Pressure is at 750 psig LOWERING Reactor Level is -125 in. and STABLE Suppression Pool Level is -9 ft. STABLE Drywell pressure is 3 psig RISING Suppression Chamber pressure is 0 psig RISING Division 3 EDG is tripped. RCIC ____(1)_ because _(2)____

a. 1. must be immediately TRIPPED 2. operation may cause pump/piping damage due to LOW Suppression Pool Level.

b. 1. is allowed to inject 2. ALL trips are bypassed.

c. 1. must be immediately TRIPPED 2. the steam exhaust discharging into the Suppression Pool will cause Pressure Suppression Pressure(PSP) to be exceeded.

d. 1. is allowed to inject 2. the steam exhaust discharging into the Suppression Pool will NOT cause Pressure Suppression Pressure(PSP) to be exceeded.

#51. A TRIP of which of the following breakers would eventually result in a loss of DC control power to Unit 1 RCIC?

a. BUS 131A & 131B FEED ACB

b. BUS 133A & 133B FEED ACB

c. BUS 135X & 135Y FEED ACB

d. BUS 137X & 137Y FEED ACB

#52. While operating at 100% power on both Units you receive the following annunciators: Instrument air header pressure reads 50 psig. Which one of the following describes the expected position of the listed Unit 1 valves? (without operator action)

a. Inboard Main Steam Isolation Valves – CLOSED.

b. CRD HCU Scram Inlet Valves – OPEN.

c. TDRFP Min Flow Valves – CLOSED.

d. DW Vacuum Breakers – OPEN.

#53. Which one of the following meets the criteria of a fuel handling accident?

a. Fuel misplaced in the reactor vessel

b. Fuel misplaced in the spent fuel pool

c. Dropped fuel bundle in the cattle chute

d. Dropped double blade guide in the cattle chute

#54. Given the following indications: Unit 1 has an ATWS. SPDS Reactor Power Bar indicates CYAN/BLUE. Based on the SPDS indication alone Reactor power is ..

a. unknown.

b. below low power setpoint.

c. above low power alarm point.

d. between low power alarm point and low power setpoint.

#55. Unit 1 is at 100% power. The Off Gas 1N62-F042 (Charcoal Adsorber Train Inlet) is CLOSED and the Adsorber Train Inlet Valve Switch is in BYPASS due to Off Gas Reheater temperature approaching adsorber temperature. The following are observed: 1N62-P600-B207 OFF GAS POST-TRMNT RAD HI OG POST TRTMT Monitor; 1D18-R601; indicates 104cps and rising at 103cps/minute Which one of the following is expected to occur NEXT?

a. Off-Gas Post Treat Rad Hi-Hi will alarm ONLY

b. Off Gas Discharge Valve 1N62-F057 will CLOSE.

c. Off Gas Charcoal Adsorber Inlet Valve 1N62-F042 will OPEN

d. Off Gas Charcoal Adsorber Bypass Valve 1N62-F043 will CLOSE.

#56. Which one of the following statements regarding the interlocks and automatic functions for 1B Residual Heat Removal (RHR) is true when the Remote Shutdown Transfer Switches are placed in EMERGENCY?

a. ALL 1B Residual Heat Removal (RHR) valve interlocks are disabled.

b. The 1B Minimum Flow Valve is interlocked closed on 1B Residual Heat Removal (RHR).

c. The Shutdown Cooling Suction valve cannot be opened unless the Full Flow Test valve is closed.

d. The automatic Low Pressure Coolant Injection (LPCI) mode of 1B Residual Heat Removal (RHR) remains functional.

#57. Unit 1 has scrammed and the crew has entered LGA-003 on High Drywell pressure. The Unit Supervisor has directed you to perform LGA-VQ-02; Emergency Containment Vent. The purpose of this action is to maintain containment pressure below the…..

a. Primary Containment Pressure Limit (PCPL)

b. Pressure Suppression Pressure (PSP).

c. Drywell Spray Initiation Limit (DWSIL).

d. SRV Tail Pipe Level Limit.

#58. Given the following conditions: Suppression Pool temperature is 100°F and rising. Suppression Pool water level of -4 ft. and stable. Which of the following would provide accurate Suppression Pool temperature to determine LGA-003; PRIMARY CONTAINMENT CONTROL; re-entry requirements? (1) Average Suppression Pool Temperature recorders TR-CM037A/38A. (2) PPC computer points L122 and L123 SUPP POOL WATER TEMP NE/SW. (3) PPC computer points A944 and A918 SP WTR BULK TEMP DIV 1/2. (4) Bulk Average Temperature as read from the NUMAC UY-CM037/38.

a. 1

b. 2

c. 3

d. 4

#59. Given the following conditions: Fuel Pool moves are in progress in preparation for Unit 2 outage. 2PM01J-B304; DIV 2 125V DC 212X/Y BUS FEED BKR AUTO TRIP is in alarm. R0989; 125VDC Pnl 212Y Mn Fd Bkr Trip is up on SER. A loss of the Unit 2 SAT due to a lightning strike has occurred. As the Unit 1 RO you report that: 1H13-P601-F205 DIV 1 FUEL POOL RAD HI-HI is in alarm. 1H13-P601-E205 DIV 2 FUEL POOL RAD HI-HI is in alarm. No Operator actions have been taken. Which of the following lists the SBGT response and release monitoring ability fifteen minutes later?

a. Unit 1 SBGT train is running and the Radioactive release can NOT be monitored by SBGT WRGM.

b. Unit 2 SBGT train is running and the Radioactive release can NOT be monitored by SBGT WRGM.

c. Unit 1 SBGT train is running and the Radioactive release CAN be monitored by SBGT WRGM.

d. Unit 2 SBGT train is running and the Radioactive release CAN be monitored by SBGT WRGM.

#60. With Unit 2 at rated power; a large LOCA occurred in which fuel became temporarily uncovered. LGA-001 and LGA-003 have been entered. 20 Minutes after operators started the Post-LOCA H2/O2 monitoring system; the following readings are taken: Drywell O2 concentration is 0.5% by volume and stable. Drywell H2 concentration is 1% by volume and rising slowly. 1) Would these Post-LOCA H2/O2 monitoring system readings be RELIABLE or would they still NEED MORE TIME to warm up and stabilize? 2) Based souley on the H2/O2 content; for these post-LOCA conditions; would operation of the H2 Recombiners per LGA-HG-101 be DESIRABLE or NOT DESIRABLE?

a. 1) RELIABLE 2) NOT DESIRABLE

b. 1) RELIABLE 2) DESIRABLE

c. 1) NEED MORE TIME 2) DESIRABLE

d. 1) NEED MORE TIME 2) NOT DESIRABLE

#61. With Unit-1 in Shutdown Cooling on 1A RHR; the following valves close and 1A RHR pump trips: 1E12-F053A; 1A RHR Shutdown Cooling Return Isolation 1E12-F008; RHR Shutdown Cooling Suction Header Outboard Isolation 1E12-F009; RHR Shutdown Cooling Suction Header Inboard Isolation Determine which one of the following caused the above conditions to occur and why?

a. RHR Pump suction flow at 5700 gpm to prevent lifting blade guides.

b. Reactor Vessel pressure at 135 psig to protect suction piping from overpressurization.

c. Reactor water level at +55 inches to prevent flooding Main Steam Lines.

d. Breaker 1412 trips on overcurrent leaving 141Y a dead bus to prevent damage to 0 DG.

#62. Given the following plant conditions: After a scram one Control Rod is at position 48 ARI was initiated 10 minutes ago One CRD pump is running All scram valves indicate open The RPS EPMAs have tripped and will NOT reset Reactor pressure is greater than 920 psig Based on the above conditions; the operator assigned to complete the scram actions should NEXT attempt to insert the remaining control rod using which one of the following?

a. Removing the air supply filter and venting the scram air header.

b. Scramming the rod in using the SRI test switches at its HCU.

c. Venting the CRD withdraw line of this rod.

d. Manually driving the rod in with RCMS.

#63. Given the following conditions on Unit 1: At 1500: Scram occurred and all rods are in. Group 2 isolation occurred. WS Header pressure reads 50 psig. The following annunciators occur at the TIME specified: 1600 1H13-P601-B401; RBCCW RAD HI; is in alarm 1605 1H13-P601-B301; SERV WTR EFFLUENT RAD HI; is in alarm Based on the above conditions; which of the following components is the source of the HI RAD alarms?

a. 1A RHR Heat Exchanger

b. 1A RR Pump Seal Heat Exchanger

c. 1A Fuel Pool Cooling Heat Exchanger

d. 1A RWCU Non-Regenerative Heat Exchanger

#64. Using the attached reference and given the following: Unit 1 VR Radiation Monitors are reading 15 mr/hr. LGA-VQ-02; EMERGENCY CONTAINMENT VENT; is in progress on Unit 1 to allow for Low Pressure injection. Unit 1 VG is running. Unit 2 VG has been shutdown to ensure isokinetic flow. The operator notices that Reactor Building d/p indication is reading 0 WC. In accordance with procedures; the operator should use which of the following to make Reactor Building d/p more negative?

a. Unit 2 VG system

b. Unit 1 VQ system

c. Unit 2 VQ system

d. VR system

#65. LGA-003; Primary Containment Control; requires drywell sprays to be terminated if suppression pool water level exceeds 722 feet. What is the impact of continued operation of drywell sprays with suppression pool water level in excess of 722 feet?

a. Drywell sprays would be operated outside the drywell spray initiation limit curve.

b. Drywell spray would be rendered ineffective due to the lower ring of drywell spray nozzles being submerged.

c. Post-spray drywell vacuum relief cannot be assured due to the submergence of the vacuum breakers.

d. The static head resulting from the level of water in the suppression pool would cause the drywell spray nozzle flow to exceed design capacity.

#66. Unit-1 and Unit-2 are both operating in Mode 1 with no equipment out of service. A valving error caused Fire Protection Header Pressure to drop to 116 psig for 30 seconds. Based on the above event; the control room NSOs should verify proper operation of the Diesel Fire Pumps (DFPs) by observing on …

a. 1PM09J that both 0A and 0B DFP red lights are lit.

b. 1PM09J that 0A DFP red light is lit and 0B DFP green light is lit.

c. 1PM09J that 0A DFP red light is lit and 2PM09J that 0B DFP red light is lit.

d. 1PM09J that 0A DFP red light is lit and 2PM09J that 0B DFP green light is lit.

#67. A Unit startup is in progress with the following conditions: The reactor is critical; below the point of adding heat The reactor is on an infinite period Reactor power is on the Intermediate Range Monitors (IRMs) Range 2 The unit NSO withdraws several control rods per the sequence package and takes the following readings to determine reactor period: Initial power 20 on IRM Range 2 Final power 40 on IRM Range 2 Time to change from initial to final power was 30 seconds. Based on the above information and calculated reactor period; the SRM SHORT PERIOD annunciator _(1) be alarming; and the unit NSO _(2)___.

a. (1) should NOT; (2) is required to insert control rods using RCMS.

b. (1) should NOT; (2) is allowed to withdraw additional control rods using RCMS.

c. (1) should; (2) is required to insert control rods using RCMS.

d. (1) should; (2) is required to scram the reactor using RPS scram pushbuttons.

#68. Which of the following switch modifications on Unit 1 does NOT exist on Unit 2?

a. 1A RHR SP SPRAY ISOL (1E12-F027A)

b. Div. 1 INJ OVERRIDE ATWS/NORM/NON-ATWS (1E12-S24A)

c. 1A RHR DW SPRAY UPSTREAM ISOL (1E12-F016A)

d. 1A/B RHR HX BLOWDOWN UPSTRM ISOL (1E12-F049A/B)

#69. The Unit is at 4% power during a startup. Rod 26-35 is stuck at notch position 08. The rod can NOT be driven in or out despite multiple attempts. What is the NEXT required Technical Specification action?

a. Vent the control rod.

b. Disarm the control rod.

c. Verify control rod separation criteria.

d. Use SRI test switches to scram the control rod.

#70. An Equipment Operator is to perform a clearance that requires independent verification. Which ONE of the following components could be eligible for an independent verification waiver? A Danger tag to be hung on the…

a. 1CO01T CO2 compressor disconnect switch.

b. breaker for 1WS002A at Lake Screenhouse MCC 1A.

c. 1G33-F043A; RT Pump A suction isolation valve; handwheel.

d. 1CP-MV1A condensate polisher A inlet valve control switch at 1PL03J; TB 710.

#71. You are an extra NSO directed to verify a single Reactor Water Clean-up (RT) valve’s position. Your Electronic Dosimeter (ED) alarms on dose rate immediately after entering the RT Pump room. The Electronic Dosimeter indicated dose rate is LESS than that stated on the applicable RWP. You are required to…

a. obtain new dosimetry at the Work Execution Center (WEC) and then verify the valve position.

b. call Radiation Protection (RP) and then wait in the area for an RP technician to arrive and verify area dose rates.

c. immediately verify the valve’s position and then write a Condition Report (CR) based on the errant alarm.

d. immediately leave the radiologically controlled area and report to Radiation Protection (RP) department.

#72. During an annunciator test on 1PM13J the annunciators FAIL to test. Per LOA-AN-101; LOSS OF ANNUNCIATORS; annunciators at which of the following panels should be checked NEXT?

a. 1H13-P603

b. 1H13-P602

c. 1PM03J

d. 1PM02J

#73. Assuming a primary system is discharging into the reactor building and all rods are fully inserted; which of the following conditions above Maximum Safe Values would require an RPV Blowdown?

a. RCIC Equipment Area temperature; and RCIC Room Sump water level.

b. RWCU Pump Area Room temperature; and Refuel Floor temperature.

c. HPCS Pump Room radiation level; and HPCS Room water level.

d. RT Phase Separator Room radiation level; and HPCS Pump Room radiation level.

#74. Unit 1 is at rated conditions with TIP traces in progress. TIP area is posted and verified clear. B’ TIP has just completed a trace and has been returned to the shield. ‘A’ TIP is at position 0001. The 1H13-P601-B211; RB TIP ROOM RAD HI/DOWNSCALE; has come in and is verified to be HI. Which of the following is the NEXT expected action(s) for the operator running the TIP trace?

a. close the ‘A’ TIP ball valve ONLY

b. continue with the next TIP trace

c. close the ‘A’ TIP ball valve and shutdown the TIP machine

d. withdraw the ‘A’ TIP to the in-shield position and then close the ‘A’ TIP ball valve

This question was deleted following exam review

#75. Unit 1 scrammed from rated conditions: APRM Downscale lights are NOT illuminated 27 Control Rods remain out past notch 02 RPV water level is 38 inches Which of the following actions can the Reactor Operator perform without Unit Supervisor direction? 1. INITIATE ARI 2. INITIATE SBLC 3. DRIVE IN control rods 4. TRIP RR Pumps

a. 1 and 2 ONLY

b. 1 and 3 ONLY

c. 1; 2; and 3 ONLY

d. 1; 2; 3; and 4

#76. LGA-001 and LGA-003 were entered due to a steam leak inside Primary Containment. The following conditions exist: Suppression Chamber Sprays are in service Drywell pressure is 5 psig and rising slowly Drywell temperature is 290oF and rising slowly Suppression Chamber pressure is 4 psig and rising slowly Suppression Pool level is 720 ft and steady Which of the following identifies the use of Drywell sprays and why? Drywell Sprays&

a. shall be initiated to prevent excessive temperatures inside the primary containment.

b. shall be initiated to prevent chugging in the downcomers which could cause Primary Containment damage.

c. shall NOT be initiated because this could result in Drywell Pressure negative enough to challenge the Primary Containment.

d. shall NOT be initiated because this could cause chugging in the downcomers which could cause Primary Containment damage.

#77. Given the following: A transient occurred on Unit 2. At time =00; the following conditions exist: Stack WRGM 12.0E8 uCi/sec and rising at 5E6 uCi/sec per second Standby Gas treatment WRGM 7.5E8 uCi/sec and stable; What is the LONGEST time allowed before LGA-004; RPV Blowdown; must be entered?

a. 20 minutes

b. 22 minutes

c. 24 minutes

d. 26 minutes

#78. Using the attached reference and given the following: Unit 1 is at rated conditions Fire alarm #223; DG CORR SPRINKLER ACTUATED; is in an alarming state Rounds Operator reports that there is no fire in the area As the CRS which of the following is the minimum group of actions that will meet the TRM requirements? 1. Establish an hourly fire watch patrol 2. Establish a continuous fire watch of the affected area 3. Restore the system to OPERABLE status 4. Prepare a corrective action report

a. 1; 2; and 4 ONLY

b. 2 and 3 ONLY

c. 2 and 4 ONLY

d. 1 and 3 ONLY

#79. Given the following: Unit 1 is in an ATWS Reactor Power is 15% EHC Pressure is 1300 psig Unit 1 Main Condenser reads 9.0 HG Backpressure The 1PM02J indicates: Is 1PM02J-B308 indication VALID/INVALID and what should the SRO direct the operator to enter?

a. INVALID and enter LOA-EH-101; UNIT 1 EHC ABNORMAL

b. VALID and enter LGA-MS-01; USING MAIN CONDENSER AS HEAT SINK IN ATWS

c. INVALID and enter LOA-TG-101; UNIT 1 TURBINE GENERATOR

d. VALID and enter LGA-SC-102; UNIT 1 ALTERNATE VESSEL INJECTION USING STANDBY LIQUID CONTROL

#80. The following conditions exist: A refueling accident has occurred on Unit 1 A General Emergency has been declared A release is in progress Which one of the following events requires an additional state notification?

a. Unit 1 HPCS becomes INOP.

b. Refueling Supervisor becomes contaminated.

c. The wind shifts from 60 degrees to 120 degrees.

d. Non-essential personnel are evacuated from site.

#81. Using the attached reference(s) and given the following: An event on Unit 1 has occurred. RPV level is -40 inches and stable. You are informed by IMD that the following level instruments are inoperable. Unit 1 Fuel Zone Range Level Recorder 1B21-R610 Unit 1 Upset Range Level Recorder 1C34-R608 Which of the following identifies the (1) Technical Specification; which must be entered for these inoperable instruments and the (2) basis?

a. (1) 3.3.6.1 Primary Containment Isolation Instrumentation. (2) In combination with other systems to limit fission product release during and following a DBA.

b. (1) 3.3.6.1 Primary Containment Isolation Instrumentation. (2) Ensures that there is sufficient information available on selected plant parameters to monitor and assess plant status.

c. (1) 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation. (2) In combination with other systems to limit fission product release during and following a DBA.

d. (1) 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation. (2) Ensures that there is sufficient information available on selected plant parameters to monitor and assess plant status.

#82. The reactor was at rated power when a LOCA occurred. Present plant conditions include the following: All control rods inserted RPV pressure is 100 psig and lowering slowly RPV water level is 60 (inches) and rising slowly 1 Condensate Pump is injecting B and C LPCI are injecting Suppression Pool Level is 690 ft on 1LR-CM027 (Wide/Narrow Range SP LVL) and slowly rising Suppression Chamber pressure is 5 psig and slowly rising Suppression Pool temperature is 210F Suppression Chamber and Drywell Sprays are running. Which of the following shall the SRO direct next?

a. Initiate an ADS in accordance with LGA-004; RPV Blowdown.

b. Align A RHR to shutdown cooling per LOP-RH-07; Shutdown Cooling System Startup Operation and Transfer.

c. Secure A and B RHR pumps and LPCI injection lineup using LOP-RH-12; Shutdown of LPCI After Automatic Initiation.

d. Stop all drywell sprays and raise suppression pool level using LOP-RH-16; Raising and Lowering Suppression Pool Level.

#83. Given the following: Station Blackout 1B Emergency Diesel Generator failed to start All Narrow Range meters on 1H13-P603 are reading downscale (1) What instrument can be utilized to determine RPV water level? (2) Which procedure should the U1 Unit Supervisor direct the Unit 1 NSO to perform?

a. (1) 1B21-R610; Rx Level Fuel Zone Range; on the 1H13-P601 (2) LOA-AP-101; Unit 1; AC Power System Abnormal

b. (1) 1C61-R010; VSL Level; on the 1C61-P001 Remote Shutdown Panel (2) LOA-AP-101; Unit 1; AC Power System Abnormal

c. (1) 1B21-R604; Wide Range Rx Water Level; on the 1H13-P603 (2) LOA-NB-101; Reactor Vessel Instrumentation Abnormal

d. (1) 1C61-R010; VSL Level; on the 1C61-P001 Remote Shutdown Panel (2) LOA-NB-101; Reactor Vessel Instrumentation Abnormal

#84. Given the following conditions: Unit-1 was at 100% power. ‘A’ IN Compressor is cross-tied to ‘B’ Dryer. Group 1 and Group 10 isolations were caused by an instrument failure. The Unit 1 Supervisor directs the LOCAL Operators to (1) IAW (2) .

a. (1) CHECK; 1IN22M; Rupture Disk is NORMAL to verify the IN Dryer did not over pressurize the purge line (2) LOA-IN-101; Loss of Drywell Pneumatic Air Supply

b. (1) CHECK; 1IN22M; Rupture Disk is NORMAL to verify the IN Dryer did not over pressurize the purge line (2) LOP-IN-03; Drywell Pneumatic System Transfer to Station Instrument Air System

c. (1) ISOLATE 1IN09MA; South Side Bottle Bank Gas Manifold System in order to preserve bank pressure (2) LOP-IN-03; Drywell Pneumatic System Transfer to Station Instrument Air System

d. (1) ISOLATE 1IN09MA; South Side Bottle Bank Gas Manifold System in order to preserve bank pressure (2) LOA-IN-101; Loss of Drywell Pneumatic Air Supply

#85. Per Tech Spec Bases; which of the following is the LOWEST reactor pressure and the LOWEST CRD Accumulator pressure at which CRD pump availability is NOT needed to ensure control rod scram insertion times? Reactor Accumulator Pressure Pressure

a. 800 psig 800 psig

b. 800 psig 940 psig

c. 940 psig 800 psig

d. 940 psig 940 psig

#86. The following conditions exist: A small LOCA is in progress A RHR and LPCS are injecting RPV water level is -55 inches and lowering Drywell Pressure is at 4 psig and slowly lowering Drywell Temperature is at 152F and slowly lowering Drywell and Suppression Chamber Sprays are running on 1B RHR LOR-1H13-P601-B112; 1A RHR SERV WTR RAD HI; has just alarmed at 165 cpm and rising rapidly. What actions must be directed next?

a. SHUTDOWN the A RHR Service Water Loop ONLY per LOP-RH-05; Operation of RHR Service Water System.

b. SHUTDOWN the A RHR System per LOP-RH-13; Suppression Pool Cooling Operation; AND SHUTDOWN the A RHR Service Water Loop per LOP-RH-05; Operation of RHR Service Water System.

c. OPEN 1E12-F048A; A RHR HX Bypass Valve; and ISOLATE the A RHR Heat Exchanger per LOP-RH-03; Draining the RHR and RHR Service Water Systems; ONLY.

d. OPEN 1E12-F048A; A RHR HX Bypass Valve; and ISOLATE the A RHR Heat Exchanger per LOP-RH-03; Draining the RHR and RHR Service Water Systems; AND SHUTDOWN the A RHR Service Water Loop per LOP-RH-05; Operation of RHR Service Water System.

#87. In response to an event on Unit 1; the crew scrammed and initiated ADS IAW LGA-004; RPV Blowdown. Reactor pressure is 42 psig and lowering. Drywell pressure is 0.2 psig and stable. 111Y is deenergized. Then the following occurred: Northside Unregulated Header Relief Valve; downstream of the regulator; fails OPEN. Annunciator 1H13-P601-F102; ADS VALVE ACCUMULATOR PRESSURE LO; alarms. SRV Accumulator pressures supplied by Northside Unregulated header are 100 psig and lowering. SRV Accumulator pressures supplied by Southside Unregulated header are 150 psig and stable. Given the above conditions: (1) What is the status of the ADS valves? (2) What action should the SRO direct to mitigate the consequences of these events?

a. (1) ADS valves supplied by the Northside Unregulated header are CLOSED and ADS valves supplied by the Southside Unregulated header are OPEN. (2) IAW LGA-004; RPV Blowdown; maintain RPV pressure less than 38 psid above Suppression Chamber pressure.

b. (1) ALL ADS valves are OPEN but those supplied by the Northside Unregulated header will eventually close as accumulators depressurize. (2) IAW LGA-004; RPV Blowdown; maintain RPV pressure less than 38 psid above Suppression Chamber pressure.

c. (1) ADS valves supplied by the Northside Unregulated header are CLOSED and ADS valves supplied by the Southside Unregulated header are OPEN. (2) IAW LOA-IN-101; Loss of Drywell Pneumatic Air Supply; direct that ADS Bottle Banks be re-pressurized via Emergency Pressurization Station.

d. (1) ALL ADS valves are OPEN but those supplied by the Northside Unregulated header will eventually close as accumulators depressurize. (2) IAW LOA-IN-101; Loss of Drywell Pneumatic Air Supply; direct that ADS Bottle Banks be re-pressurized via Emergency Pressurization Station.

#88. Unit 1 has been operating at rated conditions for an extended period of time. A Loss of Offsite Power results in a Group 1 isolation. RCIC is being used to maintain Reactor water level. Based on the stated conditions; what is the LOWER value of the Reactor Water level band that the CRS should direct the NSO to maintain?

a. 11 inches

b. 0 inches

c. -30 inches

d. -150 inches

#89. Given the following: 0 DG was started to conduct LOS-DG-M1; 0 Diesel Generator Operability Test. While operating fully loaded in parallel with the Unit-1 SAT in accordance with LOS-DG- M1; a lockout of the Unit-1 SAT occurred. The EO informs you that 0DG03J-2-1; High Water Temperature; is alarming. 0 DG temperature is 200F and rising 1 degree every 5 minutes. (1) The SRO must direct the NSO to: (2) In 10 minutes; with NO Operator Action; what will be the status of the 0 DG?

a. (1) VERIFY proper operation of 0 DG Cooling Water System per LOP-DG-04; Diesel Generator Special Operations. (2) The DG will remain running as the only source connected to bus 141Y.

b. (1) SHUTDOWN the 0 DG per LOS-DG-M1; 0 Diesel Generator Operability Test. (2) The DG will trip on High Temperature and de-energize bus 141Y.

c. (1) VERIFY proper operation of 0 DG Cooling Water System per LOP-DG-04; Diesel Generator Special Operations. (2) The DG will trip on High Temperature and de-energize bus 141Y.

d. (1) SET the governor Speed Droop to 50 percent; AND return bus voltage and frequency to nominal values per LOP-DG-02; Diesel Generator Startup and Operation. (2) The DG will remain running as the only source connected to bus 141Y.

#90. Using the attached reference(s) and given the following: Unit-1 is shutdown Reactor recirculation temperature is 205F Instrument maintenance has completed LIS-LP-108; LPCS PUMP HIGH/LOW DISCHARGE PRESSURE ALARM CALIBRATION. The instrument technician informs the unit supervisor that the 1E21-N005B; LPCS System Discharge Pressure Low Switch; does NOT meet calibration requirements. 1H13-P601-C308; LPCS System Discharge Pressure Low Annunciator; did NOT reset. An operator was dispatched and identified that there was water at the high point vent and local pressure indicated 55 psig. What is the impact on Tech Spec 3.5.1 and 3.5.2?

a. entry into TS 3.5.1 Required Action A.1 is required; 3.5.2 is NOT applicable

b. entry into TS 3.5.2; Required Action A.1 is required; 3.5.1 is NOT applicable

c. LCO requirements of Tech Spec 3.5.1 are met; 3.5.2 is NOT applicable

d. LCO requirements of Tech Spec 3.5.2 are met; 3.5.1 is NOT applicable

#91. Given the following on Unit 1: LOCA on Unit 1 1A RHR is in Suppression Pool Cooling and Suppression Chamber Spray modes 1B RHR is running in Drywell Spray mode Suppression Pool Temperature is 200°F Based on the above information: (1) Which spray temp will rise the most? (2) Which of the following actions must the SRO direct first?

a. (1) Suppression Chamber Spray temperature will rise. (2) Throttle service water flow to prevent runout of running service water pump per LOP-RH-05; Operation of the RHR Service Water System.

b. (1) Drywell Spray temperature will rise. (2) Lower RHR system flow as required to accommodate for the lower RHR Service Water cooling flow to maintain operating band per LGA-RH-103; Unit 1 A/B RHR Operations in the LGAS/LSAMGS.

c. (1) Suppression Chamber Spray temperature will rise. (2) Lower RHR system flow as required to accommodate for the lower RHR Service Water cooling flow to maintain operating band per LOP-RH-13; Suppression Pool Cooling Operation.

d. (1) Drywell Spray temperature will rise. (2) Throttle service water flow to prevent runout of running service water pump per LOP-RH-05; Operation of the RHR Service Water System.

#92. Given the following plant conditions: Unit-1 is shutting down RCMS shows INSERT and WITHDRAW blocks RCMS shows Power Below LPSP and LPAP box 1H13-P603-A308; Rod Out Block is LIT What is the Technical Specification Basis for the CURRENT Rod Out Block? To prevent exceeding …..

a. 1% plastic strain during a control rod drop accident.

b. 280 cal/gram during a control rod drop accident.

c. 280 cal/gram during a control rod withdrawal accident.

d. 1% plastic strain during a control rod withdrawal accident.

#93. Given the following conditions: Unit 1 was ascending in power after a startup. The reactor scrammed due to high pressure in the Drywell. Several control rods did NOT fully insert. The following LGA-010 actions have been taken: ARI has been initiated. ADS has been inhibited. ECCS injection has been prevented. Reactor power is low enough that SBLC initiation is NOT required. RPV water level is at +30 inches and stable. Prior to inserting control rods per LGA-NB-01; the Recirculation System status must be addressed. Which LGA-010 direction(s); if any; is/are necessary concerning the Recirculation Pumps and Recirc Flow Control Valves (FCVs)?

a. Trip the Recirc Pumps ONLY.

b. No direction(s) is/are necessary.

c. Verify/runback Recirc FCVs to minimum ONLY.

d. Verify/runback Recirc FCVs to minimum AND then trip the Recirc Pumps.

#94. Given the following: Power is at 100% At 1200 on 2/16; it was determined that part of a T.S. required surveillance was NOT performed. The incomplete surveillance was performed on 2/13 The last complete satisfactory surveillance was completed at 1200 on 1/15. The surveillance is required to be performed at least once per 31 days At 1600 on 2/16; the surveillance is performed and is determined to be UNSAT. Which of the following is required first?

a. Be in Hot Shutdown by NO later than 0400 on 2/17.

b. Be in Cold Shutdown by NO later than 1600 on 2/17.

c. Be in Hot Shutdown by NO later than 0400 on 2/20.

d. Be in Cold Shutdown by NO later than 1600 on 2/20.

#95. Given the following information: Unit 1 is at rated conditions IMD is installing a jumper in 1PM13J to troubleshoot the 1CM022A; A POST LOCA H2/O2 CNMT MONITOR PANEL DW SAMPLE ISOL VALVE; that failed to open during LOS-AA-W1 The work order package does NOT have a 50.59 review What is the MAXIMUM time this jumper may remain installed without having a 10CFR50.59 screening?

a. 30 days

b. 60 days

c. 90 days

d. 120 days

#96. What is the relationship between the Station Emergency Director and the performance of an emergency containment vent per LGA-VQ-02; Emergency Containment Vent? The Station Emergency Director in the TSC _____ the primary containment.

a. must direct the emergency venting of

b. must be informed prior to emergency venting

c. has NO responsibilities related to emergency venting

d. must approve the release permit for emergency venting

#97. Using the reference(s) attached and the following: Unit 2 was operating at 96% power when the following occurred: 1900; the Unit 2 SAT trips and locks out; DGs 0; 2A; and 2B auto start 1901; a manual reactor scram is inserted; RPS A fails to trip; no rod motion 1902; manual ARI initiation is attempted; ARI fails to initiate 1904; SBLC is initiated; SBLC Pump 2A fails to start; SBLC Pump 2B starts 1907; RPS trip system A is tripped using Method 1 per LGA-NB-01; all rods insert 1908; the turbine trips; DG 2A closes in on to 242Y; DG 2B trips and locks out It is now 1910 and you are reviewing the Emergency Action Levels per EP-AA-1005. Which ONE of the following describes the event classification and notifications required to be made to off-site agencies?

a. Declare an Alert and notify off-site agencies of this classification ONLY.

b. Declare a Site Area Emergency and notify off-site agencies of this classification ONLY.

c. Declare an Unusual Event and notify off-site agencies that the EAL for an Alert was briefly exceeded; but no longer exists.

d. Declare an Alert and notify off-site agencies that the EAL for a Site Area Emergency was briefly exceeded; but no longer exists.

#98. This question intentionally withheld.

a.

b.

c.

d.

#99. You have been performing the duties of the Field Supervisor for the first 4-hours of the shift when a casualty occurs and it is necessary for you to relieve the Unit Supervisor on the affected Unit. Which one of the following are REQUIRED to be performed prior to assuming command and control of the affected Unit during the casualty situation? 1. Review appropriate abnormal conditions and initiating events. 2. Review the current status of the EOP flowcharts. 3. Receive permission from the Shift Manager. 4. Turnover to another qualified Field Supervisor.

a. 1; 2; and 3 ONLY

b. 1; 2 and 4 ONLY

c. 1 and 3 ONLY

d. 2 and 3 ONLY

#100. Using the attached ODCM calculation and given the following: LOP-VQ-04; Startup and Shutdown and Operations of the Primary Containment Vent and Purge System; requires an Offsite Dose Calculation for Drywell Purge. Floor drain sumps are running every 2 (two) days Radiation monitors are 100 cpm and stable Time now is 1200 10/22/12; what actions are required?

a. Continue the purge even if the 30 hours will be exceeded.

b. Stop the purge between 1800 and 1900 on 10/22/12.

c. Stop the purge between 1200 and 1300 on 10/22/12.

d. Stop the purge and perform a new Offsite Dose Calculation prior to 1900 10/22/12 before restarting the purge.

Results