LaSalle SRO Quiz - ILTandMe

#1. The reactor vessel water level Safety Limit (SL) ensures that adequate core coolingcapability is maintained during (1) of reactor operation. Establishment ofEmergency Core Cooling System (2) provides margin such that the SL willNOT be reached or exceeded.

a. (1) all MODES(2) divisional separation

b. (1) all MODES(2) instrumentation setpoints higher than the SL

c. (1) MODES 1; 2; and 3 (ONLY)(2) divisional separation

d. (1) MODES 1; 2; and 3 (ONLY)(2) instrumentation setpoints higher than the SL

#2. Unit-1 was at full power when it was determined that the Suppression Pool Wide Range levelinstruments for both divisions were improperly calibrated. The system engineer determined thatactual Suppression Pool level is 700 feet 2.5 inches.For this condition; the MOST limiting action according to the Technical Specifications can befound in …

a. 3.3.3.1 Post-Accident Monitoring Instrumentation.

b. 3.3.3.2 Remote Shutdown Monitoring Instrumentation.

c. 3.6.2.2 Containment Systems – Suppression Pool Water Level.

d. 3.6.2.3 Containment Systems – Suppression Pool Cooling

#3. Unit 2 is operating near full power when instrument maintenance technicians discovered that three turbine stop valve closure channels that input to RPS are inoperable. PROVIDE T.S. 3.3. 1. Which of the following actions is required?

a. Within one hour; verify sufficient channels remain operable or tripped to maintain trip capability in the Functional Unit.

b. Within one hour; initiate a reduction in reactor power to less than 25% thermal power within two hours.

c. Within six hours restore the inoperable channels or reduce power to less than 25% within the following 12 hours.

d. Within six hours place the remaining operable channel in the tripped condition.

#4. 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

#5. You are the Unit 1 Unit Supervisor. With Unit 1 operating at rated conditions; a manual scram was inserted due to a sudden drop in condenser vacuum. The Unit 1 NSO transferred the Mode Switch to SHUTDOWN and then reported the following: – Four rods remain FULL OUT. – RPV Level is – 15 inches and rising slowly – Suppression Pool temperature is 106 F and going up slowly Based on the indication below; reactor power is determined to be _(1) and you must provide direction to hold RPV level in the band of (2)__; in accordance with the governing LGA.

A. (1) unknown (2) 11 inches and 59.5 inches

B. (1) less than or equal to 3%. (2) -150 inches on Wide Range and 59.5 inches

C. (1) greater than 3% and less than 14% (2) -150 inches on Wide Range and – 60 inches

D. (1) greater than 14% (2) -150 inches and -120 inches on Wide Range

#6. Unit 1 has scrammed due to a Loss of Off-Site Power. Both Div 1 and 2 DGs failed to start. HPCS DG tripped 15 minutes into the event. RCIC is maintaining level at -75″.(1) What are the required actions to keep RCIC available for injection after4 hours?(2) What procedure will the Unit Supervisor direct after 4 hours?

A. (1) Transfer to local operation in the RCIC room.(2) Operate RCIC IAW LGA-Rl-101 U-1 ALTERNATE VESSEL INJECTION USING RCIC INClUDING DEFEAT OF RCIC ISOLATIONS.

B. (1) Transfer control to Remote operation at the remote shutdown panel1C91-P001.(2) Operate RCIC IAW LOP-RX-04 STARTUP AND OPERATION OF RCICFROM THE REMOTE SHUTDOWN PANEL.

C. (1) Transfer control to Remote operation at the remote shutdown panel1C91-P001.(2) Operate RCIC IAW LGA-Rl-103 U-1 RPV INJECTION USING RCIC WHEN ALOSS OF DC IS IMMINENT OR HAS OCCURRED.

D. (1) Transfer to local operation in the RCIC room.(2) Operate RCIC IAW LGA-Rl-103 U-1 RPV INJECTION USING RCIC WHEN ALOSS OF DC IS IMMINENT OR HAS OCCURRED.

#7. Unit 2 is experiencing an ATWS with the following conditions: Reactor water level is 10 inches and is being rapidly lowered. – The Reactor operator reports that APRMs are oscillating between two and sixteen percent. Which of the following actions should be taken?

a. Reduce the rate of level decrease.

b. Raise reactor water level until oscillations stop.

c. Maintain reactor water level at 10 inches.

d. Continue with the level decrease.

#8. Given the following Conditions: Reactor Mode Switch is in Shutdown. Average Reactor Coolant Temperature is 205 F. Reactor Vessel Head Closure bolt tensioning will be complete in 2 hours.The Unit is currently in (1) and the (2) __ must be completed prior to the completion of Reactor Vessel Head closure bolt tensioning.

A. (1)MODE5(2) MODE 4 Checklist

B. (1) MODE 5(2) MODE 3 Checklist

C. (1) MODE 4(2) MODE 3 Checklist

D. (1) MODE 4(2) cooldown to less than or equal to 200 degrees F.

#9. An unisolable RWCU system leak to the Reactor Building is in progress with the following: – A failure to scram has occurred. – Reactor power is 15%. – RPV water level is being intentionally lowered. – Both RHR pump room water levels are 2 feet. – Only 2 SRVs can be opened and are open. – Reactor pressure is 1080 and slowly rising. – Suppression chamber pressure is 2 psig and steady.(1) Which of the following identifies the MSIV isolations that should be defeated and(2) what is the required pressure control band?

a. (1) All isolations (2) less than 33 psig

b. (1) Lo-Lo RPV water level ONLY (2) 800 – 1000 psig

c. (1) Lo-Lo RPV water level ONLY (2) less than 33 psig

d. (1) All isolations (2) 800 – 1000 psig.

#10. 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

#11. You are reviewing the shift manning schedule and identify that two of the fourReactor Operators (RO) scheduled for the next shift have No-solo Operationrestrictions on their license.What action; if any; is required to be taken regarding shift staffing for the next shift?

a. No action is required to be taken.

b. Assign the ROs with No-solo Operation restrictions to the Unit 1 andUnit 2 Assist RO positions.

c. Replace one of the ROs with the No-solo Operation restriction with anRO that does NOT have the restriction.

d. Separate the ROs No-solo Operation restrictions such that only one ROwith a No-Solo Operation restriction is assigned to each unit.

#12. Several hours after an automatic initiation during a LOCA; and with the initiationsignal still present; the Unit-1 Standby Gas Treatment Primary Fan trips.After the trip; the Unit-1 Assist NSO observed the following at panel 1PM07J:- SBGT Primary Fan – OFF- SBGT Cooling Fan – OFF- SBGT Heater – OFF- SBGT Flow – 0 scfm- 1VG001; SBGT Inlet Isolation damper – CLOSED- 1¥VG003; SBGT Outlet Isolation damper – OPENThe SBGT train (1) to the Primary Fan trip and the Unit Supervisor shoulddirect the operator to (2) .

A. (1) responded as expected;(2) SHUTDOWN the SBGT train per LOP-VG-02; Shutdown of the SBGT System

B. (1) responded as expected;(2) START the standby SBGT per LGA-VG-101; Secondary Containment PressureControl

C. (1) did NOT respond correctly;(2) manually START the Cooling Fan per LOR-1PM07J-A502; SBGT Pri Fan AutoTrip

D. (1) did NOT respond correctly; /(2) CLOSE the Outlet Isolation damper per LOR-1PM07J-A502; SBGT Pri Fan AutoTrip

#13. The Technical Specification bases for the Main Steam Line Pressure-Low Primary ContainmentIsolation is . . .

a. protection from RPV cooldown greater than 100F/hour.

b. ensuring that offsite dose limits of 10CFR 100 are not exceeded.

c. providing diversity to the high steam line flow isolation.

d. providing detection and prevention of a leak in any Main Steam Line.

#14. Unit 1 is in Run with recirculation loop flow mismatch of 3000 gpm. Which of the following is the MAXIMUM percentage of core flow that is allowed to exist WITHOUT entering a Technical Specification Action statement?

a. 64%

b. 69%

c. 74%

d. 79%

#15. In order to maintain an active Senior Reactor Operator (SRO) License, quarterly, the MINIMUM the License Holder must stand is…

A. five (5) twelve (12) hour shifts as the Unit Supervisor or Shift Manager.

B. four (4) twelve (12) hour shifts as the Unit Supervisor or Shift Manager.

C. five (5) twelve (12) hour shifts as Work Execution Control (WEC) Supervisor.

D. four (4) twelve (12) hour shifts as the Field Supervisor fulfilling the role of Shift Technical Advisor (STA).

#16. Unit-1 is in Mode 4 with reactor coolant temperature at 190F. The |operating loop of Shutdown Cooling trips and can NOT be restarted. Both Reactor |Recirculation pumps are out of service and Reactor Water Cleanup (RWCU) is isolated. |It has been determined that it will take 2 hours to align and start the standby Shutdown |||Cooling loop.As the Shift Manager you should …

A. authorize raising RPV level to between 50 and 60 inches in order to provide the extra NetPositive Suction Head (NPSH) needed to start the standby Shutdown Cooling pump whencoolant temperature is above 180F.

B. authorize raising RPV level to between 220 and 260 inches in order to more accuratelydetermine vessel metal temperatures and demonstrate that stratification is NOT occurring. |

C. authorize raising RPV level to between 220 and 260 inches in order to increase the watervolume available for removal of decay heat which increases heat transfer rate to thecontainment atmosphere.

D. direct maintaining RPV level between 30 and 40 inches in order to increase the Time to Boil |allowing extra time to start the standby Shutdown Cooling loop. |

#17. Unit 1 was operating at full power when a loss of feed occurred. All RPV Level 3 and Level 2actuations and isolations functioned as designed except the Standby Gas Treatment systemfailed to start. RCIC subsequently isolated due to a high RCIC room temperature; however;RCIC room temperature is now trending downward. Operators have determined that NO otheractuation or isolations signals currently exist.Select the statement below that correctly describes action(s) required to be directed by the UnitSupervisor in accordance with LGA-002; Secondary Containment Control:

a. Restart the Reactor Building Ventilation system.

b. Close the MSIVs and start MSIV Leakage Control.

c. Start the Primary Containment Purge system (aligned for Secondary Containment pressure control).

d. Rapidly depressurize the RPV; using the Main Turbine Bypass Valves; in anticipation of RPV Emergency Depressurization.

#18. 165 F.The Unit is currently in (1) and the (2) must be completed prior to Reactor Vessel Head closure bolt detensioning.

A. (1) Mode 3(2) Mode Change Checklist From Mode 3 To Mode 4A.

B. (1) Mode 4(2) Mode Change Checklist From Mode 4 To Mode 5

C. (1) Mode 4(2) Mode Change Checklist FromAt All Times To Mode 5

D. (1) Mode 5(2) Mode Change Checklist From Mode S To Mode 4

#19. Unit 2 is in Mode 5. You are the Unit 2 Control Room Supervisor Fuel movements are scheduled to begin; for the first time in the outage; later thisshift. Non-Spiral off-loading is being utilized. 24/48VDC Bus A is de-energized. The Fuel Handling Supervisor has called you to request permission tocommence fuel movements. The only item remaining to be checked is the operability of required nuclearinstrumentation.Based on the given conditions; fuel movements (1) as (2) .NOTE: Technical Specification 3.3.1.2 SRM Instrumentation provided.

a. (1) can begin(2) the required number of SRMs and their locations meet LCOrequirements.

b. (1) can NOT begin(2) the required number of SRMs will NOT meet LCO requirements(ONLY).

c. (1) can NOT begin(2) the location of operable SRMs will NOT meet LCO requirements(ONLY).

d. (1) can NOT begin(2) the required number AND location of operable SRMs will NOTmeet LCO requirements.

#20. Unit 2 is at rated power with the following conditions: – HD tank level increasing. – HD Pump Minimum Flow Valves opening. – HD Pump Forward Valves closing. – LP Heater Emergency Spills Valve opening. Which of the following is responsible for all of the conditions AND which procedure(s) should be implemented?

a. LP Heater 23 Level transmitter failing high; enter LOA-HD-201.

b. HD Pump Flow Transmitter failing low; enter LOA-HD-201.

c. Loss of Misc. Auto Control System; enter LOA-HD-201 and LOA-GC-201.

d. Loss of Instrument Air; enter LOA-HD-201 and LOA-IA-201.

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