LaSalle RO Quiz - ILTandMe

#1. Unit 2 had been operating at full power for an extended period of time when a Group 1 Isolationoccurred due to a steam leak in the Turbine Building. All components/systems were operableprior to the Group 1 Isolation. After the reactor scram; reactor power remained between 5-10% of rated due to failure of all control rods to insert. Operators have placed RHR A and B insuppression pool cooling. No other actions have been completed.Based on the above conditions; suppression pool temperature SHALL be determined using . . .

a. SPDS.

b. 2TI-CM037; on the Remote Shutdown Panel 2C61-P001.

c. Bulk Average Temperature from either NUMAC 2UY-CM037 OR 2UY-CM038.

d. an average of the divisional Average Suppression Pool Temperature readings from 2TR-CM037A AND 2TR-CM038A.

#2. A 20% RTP ATWS occurs on Unit 1 and SBLC is manually initiated.Which of the following is confirmation that the 1C41-F004A, Standby Liquid Control Squib Valve, is open AND SBLC is injecting into the RPV?

A. Reactor Water Cleanup is isolated

B. Discharge Pressure of the SBLC pump is 985 psig

C. Discharge Pressure of the SBLC pump is 1340 psig

D. SBLC INJ SQUIB VLV 1C41-F004A Continuity Light Lit

#3. To reduce containment pressure; operators are venting primary containment using standby gas treatment system (SBGT) post-accident in accordance with LGA-VQ-01; “Containment Vent.” Reactor plant conditions are stable. Other plant conditions are as follows: -Unit 1 SBGT train is in operation -Unit 2 SBGT train is in standby -Radiation levels in primary containment are elevated -Primary containment pressure is 1.5 psig; decreasing -Primary containment temperature is 145 deg F; decreasing If the discharge rate through the Unit 1 SBGT radiation monitor causes annunciator 1PM07J-A304; “SBGT WIDE RANGE GAS MONITOR TROUBLE” to alarm due to a high radiation release condition; the operator would be required to…

A. continue venting; no radiation release limits are imposed.

B. secure venting to prevent exceeding offsite release.

C. continue venting until General Emergency radiation limits are reached.

D. verify automatic shutdown of the Unit 1 SBGT.

#4. Unit 1 is at rated condition. Which of the following describe the listed valve’s position if BOTH Unit 1 OG Post Treatment PRMs go downscale? Off Gas Air Off Gas Ejector Suction Valves Discharge Valve (1 N62-F300A and B) (1 N62-F057)

a. Open Open

b. Closed Open

c. Open Closed

d. Closed Closed

#5. During performance of the shiftly surveillance; MFLCPR is discovered to have increased from a value of 0.980 to 1.003. Based on this information you can conclude that the number of fuel clad failures will &

A. increase significantly and reactor power must be reduced per LGP-3-1; Power Changes.

B. increase significantly and reactor power must be reduced per LGP-3-2; Reactor Scram.

C. remain relatively stable but reactor power must be reduced per LGP-3-1; Power Changes.

D. remain relatively stable but reactor power must be reduced per LGP-3-2; Reactor Scram.

#6. Unit 2 is shutdown for a refuel outage. The reactor head is removed and core reload is inprogress (Mode 5). The following additional plant conditions exist: – A” RHR is in shutdown cooling mode at 6000 gpm – ” B” RHR is in standbyThe NSO inadvertently positions 2E12-F006B to open. The refuel floor supervisor observeslevel dropping in the refueling cavity. The NSO observes Suppression Pool level is increasingand identifies that both the 2E12-F004B; “”RHR Pump Suction Valve;”” and 2E12-F006B; “”RHRShutdown Cooling Suction Valve;”” are open.Actions prescribed by Abnormal Procedures must be taken to mitigate…”

a. high radiation levels on the refuel floor by closing the 2E12-F004B valve.

b. exceeding heat capacity temperature limit by closing the 2E12-F006B valve.

c. inadequate NPSH for RHR pump operation by closing either the 2E12-F004B or the 2E12-F006B valve.

d. excessive temperature stratification within the reactor vessel by closing either the 2E12-F004B or the 2E12-F006B valve.

#7. Unit 2 has scrammed from rated conditions. – There is a small leak in the DRYWELL. – DRYWELL pressure indication is unavailable – There is no indication of a bypass path in the containment. – SUPPRESSION CHAMBER pressure is 1.2 psig Based on the above information; DRYWELL pressure is approximately ___(1)_ AND Stand-by Gas Treatment _(2)___ have auto-started.

A. (1) 1.2 psig (2) should

B. (1) 6.2 psig (2) should

C. (1) 1.2 psig (2) should NOT

D. (1) 6.2 psig (2) should NOT

#8. 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.

#9. Unit 1 is at 100% RTP with LIS-NB-105A, UNIT 1 REACTOR HIGH PRESSURE SCRAM CHANNELS AAND C CALIBRATION, in progress.IMD has discovered the High Pressure Scram Channel 1B21-N023AA will not trip.1) What effect will this condition have on RPS if RPV pressure reaches a RPS scram setpoint?2) What is the status of LCO 3.3.1.1 RPS Instrumentation?

A. 1) RPS Channels A2 and (B1 or B2) will actuate, causing a FULL reactor scram.2) LCO 3.3.1.1 is met

B. 1) RPS Channels A2 and (B1 or B2) will actuate, causing a FULL reactor scram.2) LCO 3.3.1.1 is NOT met.

C. 1) TheA RPS trip system will NOT actuate, preventing a scram from high pressure.2) LCO 3.3.1.1 is NOT met.

D. 1) TheA RPS trip system will NOT actuate, preventing a scram from high pressure.2) LCO 3.3.1.1 is NOT applicable.

#10. Given the following plant conditions: After a scram; 12 control rods are at notch position 48 – ARI was initiated 15 minutes ago – BOTH CRD pumps are tripped and will NOT restart – RPS sub-channels are de-energized and CANNOT be reset – A fire has destroyed both RPS power supply cabinets – RPV pressure is 920 psig 1) What action is directed to be taken for the given conditions to insert the 12 control rods currently at notch position 48? 2) What is the operational effect resulting from the action taken?

A. 1) PLACE the individual CRD SRI-TEST-NORM switches to TEST. 2) OPENS the individual CRD s scram valves.

B. 1) VENT and REMOVE the CRD HCU Air Supply Filter 2) DEPRESSURIZES the Scram Air Header to OPEN all scram valves.

C. 1) RESET ARI; and then INSERT individual control rods using RMCS. 2) CLOSES all scram valves; allowing RMCS to INSERT individual control rods.

D. 1) Manually VENT the individual CRD withdrawal lines. 2) VENTS the individual CRD s overpiston area.

#11. A loss of ALL 125 vde Battery Chargers has occurred on Unit-1.Assume equal loads of 25 amperes are being supplied by each battery; which one of thefollowing lists the expected relationship between the Unit-1 battery voltages after 2 hours?

A. Division 1; 2 and 3 battery voltages approximately equal.

B. Division 2 and 3 battery voltage approximately equal and greater than Division 1.

C. Division 1 and 2 battery voltage approximately equal and greater than Division 3.

D. Division 1 and 3 battery voltage approximately equal and greater than Division 2. 2003-01 ILT NRC Exam; Version: 5

#12. Unit 1 is operating at rated conditions; and Unit 2 is shutdown for a refueling outage. 1A Service Water pump and 0A Service Water Jockey pump are in operation. All other Service Water pumps are unavailable to support Unit 1. Service Water Header pressure is stable. Unit 1 Service Water Strainer dP is 6 psid. Annunciator and WS system indication is as shown below: Given the above conditions; the Unit 1 Service Water Strainer (1) be automatically backwashing and a (2) is required in response to the alarm.

a. (1) should(2) SCRAM

b. (1) should(2) reduction in auxiliary Service Water loads

c. (1) should NOT(2) SCRAM

d. (1) should NOT(2) reduction in auxiliary Service Water loads

#13. Unit 1 is scrammed with the following conditions: – Feedwater flow has been lost. – Drywell pressure is 2.5 psig. – Reactor water level is stable. – Wide Range Level instruments are indicating -120 inches. – Fuel Zone Level instruments are indicating -194 inches. – Reactor pressure is 510 psig and decreasing at 220 psig/hr. – ‘A’ and ‘B’ RHR are aligned for containment cooling. When possible; ‘A’ and ‘B’ RHR should be…

a. aligned for LPCI injection because adequate core cooling is NOT assured.

b. aligned for LPCI injection because initiation conditions have been met.

c. left in containment cooling because adequate core cooling is assured.

d. left in containment cooling because initiation conditions have NOT been met.

#14. 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.

#15. A reactor startup was in progress with operators rejecting RWCU flow to the condenser. Control room operators then detected the following conditions: – Primary containment pressure at 10 psig and increasing – Primary containment temperature 140F and increasing – Reactor pressure vessel level drops to -60 inchesAssuming no operator intervention; ONLY RWCU valve(s) __________ CLOSE(S).

a. G33-F033; “RWCU Blowdown Header Control Valve”

b. G33-F001 AND G33-F004; “RWCU Inboard and Outboard Isolation Valves”

c. G33-F004; “RWCU Outboard Isolation Valve”

d. G33-F001; “RWCU Inboard Isolation Valve”

#16. The following conditions exist on Unit 2 following a transient: Reactor power is stable at 18% following a reactor scram. Reactor water level is -30 inches and lowering. MSIVs are open and reactor pressure is stable. The Motor Driven Feedwater Pump is NOT available. LGA-010; Failure to Scram requires the crew to bypass MSIV isolations per LGA-MS-01; Using Main Condenser as Heat Sink. Which of the following describes the reason this action must be taken?

A. Avoid adding heat to the Suppression Pool.

B. Maintain Feedwater as a preferred ATWS injection system.

C. Avoid the LGA-010 requirement for Standby Liquid Control (SBLC) injection.

D. Maintain Turbine Bypass Valves available for depressurization when Cold Shutdown Boron has been injected.

#17. Which one of the following would explain an increase in HCU pressure with noaccumulator trouble alarm?

A. The nitrogen side of the accumulator is leaking through the fill connection.

B. CRD Pressure Control Valve was throttled closed.

C. Charging water leaked past the accumulator seals.

D. Reactor Building Area temperatures are approaching Max Normal.

#18. You have been directed to transfer RHR from Suppression Pool ool Cooling toShutdown Cooling at the Remote Shutdown Panel (RSP).While performing the above task; there are NO interlocks that would prevent you from opening .1E12-F006B; Shutdown Cooling Suction if is already OPEN.|

A. 1E12-F016B; 1B RHR Upstream Drywell Spray Isolation

B. 1E12-F004B; 1B RHR Suppression Pool Suction

C. 1E12-F024B; 1B RHR Full Flow Test

D. 1E12-F027B; 1B RHR Suppression Chamber Spray

#19. Unit 1 was operating at 100% reactor power when a LOCA occurred resulting in the following: – The reactor has scrammed – RPV pressure is 480 psig – RPV level is -140 inches – HPCS and RCIC are injecting to the RPV Based on these conditions; the LPCS pump is (1) and the LPCS injection line check valve is (2)

a. (1) not running (2) closed

b. (1) not running (2) open

c. (1) running (2) closed

d. (1) running (2) open

#20. LOS-DG-M2; 1A/2A DIESEL GENERATOR OPERABILITY TEST is in progressfor the 1A Diesel Generator.While performing this surveillance; you must NOT go below (1 ) _ load inorder to (2) __

A. (1) 200 kW(2) prevent excessive wear to turbocharger gear drive

B. (1)400kW(2) prevent excessive wear to turbocharger gear drive

C. (1)200kW(2) prevent the Diesel Generator from tripping on reverse power due to large loadchanges on the grid

D. (1) 400 kW(2) prevent the Diesel Generator from tripping on reverse power due to large loadchanges on the grid

Results