LaSalle SRO Quiz - ILTandMe

#1. In order to move fuel; the fuel handling SRO must be . . .

a. within phone contact

b. on the refuel bridge

c. at the refuel floor managers desk

d. within 10 minutes of the refuel floor

#2. You have been performing the duties of the Field Supervisor for the first 4 hours of the shift. A casualty occurs; and you have been directed to relieve the Unit Supervisor on the affected unit. Which of the following are required to be performed prior to assuming command and control of the main control room 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.

A. 1 and 2 ONLY

B. 1 and 3 ONLY

C. 2 and 3 ONLY

D. 1; 2; and 3

#3. Unit 1 and Unit 2 are both in Mode 5; Refuel The following Non Licensed Operators are assigned to the on coming shift: Chad Johnson Tom Smith Randy Jefferson Bill Washington Frank Jones Paul White Mike Black Mark Franklin Paul White called in sick and will not be coming in for his shift. Jeff Martin and Pat Hardy are available for call-out if needed. With the remaining crew compliment; staffing requirements in accordance with OP-LA-101-111-1001; On-Shift Staffing Requirements (1) met and a callout of (2) is required. (Reference material provided for this question)

A. (1) ARE (2) NO One

B. 1) ARE NOT (2) Jeff Martin or Pat Hardy

C. (1) ARE NOT (2) Jeff Martin ONLY

D. (1) ARE NOT (2) Pat Hardy ONLY

#4. 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.

#5. Unit 1 is operating at rated conditions; with the 1B CW pump OOS. Bus 141X experiences an overcurrent trip. The crew responds to the event per:o LOA-AP-101; Unit 1 AC Power System Abnormal ando LOA-CW-101; Unit 1 Circulating Water System Abnormal.Which of the following technical specification actions must be taken for the givenconditions?Perform a functional test of each within the next 12 hours.

a. Safety Relief Valve

b. Main Steam Isolation Valve

c. Main Turbine Bypass Valve

d. Suppression Chamber to Drywell Vacuum Breaker

#6. Unit 2 is operating at rated power with the following conditions: – Primary Containment Vent Fan 2VP02CB is OOS. Primary Containment Vent Fan 2VP02CA trips. Which of the following describe the expected crew response to this event? Enter LGA-003…

a. immediately and start hydrogen and oxygen monitors.

b. immediately and start containment venting lAW LGA-VQ-02.

c. if Drywell temperature exceeds 135F on 2TR-CM037A or B. Then start hydrogen and oxygen monitors.

d. if Drywell temperature exceeds 135F on 2TR-CM037A or B. Then start containment venting lAW LGA-VQ-02.

#7. Unit 1 was operating at 100% power when a Generator Load Reject event resultedin a turbine trip and reactor scram. The following were noted: RPV water level dropped to a low of -60″; and is now being raised using HPCSand Feedwater for injection. ONE control rod failed to fully insert; ALL other control rods are full in. Bypass valves failed to operate as designed. One Turbine control valve remained Open.Reactor pressure peaked at 1155 psig; and pressure is 1000 psig and loweringslowly; with one SRV currently open as a result of the event. Drywell pressure is 1.5 psig and stable.Which of the following identifies the issue that will be addressed first and. theprocedure that must be directed?The crew will address the …

A. failure of the TCVs to Close; enter LOA-EH-101 EHC ABNORMAL.

B. operation of the Open SRV; enter LOA-SRV-101 STUCK OPEN SAFETYRELIEF VALVE

C. control rod that did NOT fully insert; enter LOA-RD-101 CONTROL ROD DRIVEABNORMAL.

D. loss of core circulation; enter LOA-RR-101 REACTOR RECIRCULATIONABNORMAL.

#8. 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.

#9. Unit 1 is at rated conditions with NO LCO action statements in effect. Electrical maintenance has requested permission to de-energize the LPCS minimum flow valve in the closed position while they perform a required breaker inspection. Which of the following describes the shortest time clock that would be entered if you allowed the maintenance to start?Provide Tech Specs 3.5.1 ;3.6.1.1; and 3.6.3.

a. 1 hour

b. 4 hours

c. 12 hours

d. 7 days

#10. A small primary system leak that CANNOT be isolated developed on Unit 1 in the vicinity of theReactor Sample Station. Reactor Building Ventilation (VR) exhaust radiation levels were 40mrem/hr and constant prior to VR isolating. Radiation levels in the vicinity of the ReactorSample Station are 1100 mrem/hr and rising slowly.The corrective actions to be taken and bases for those actions include:

a. starting VR per LGA-VR-01 because VR will do a better job of maintaining area temperatures and differential pressure than VG.

b. shutting down the reactor per LGP-2-1 to reduce decay heat levels and energy discharged to containment without introducing an unnecessary transient on plant systems.

c. scramming the reactor and entering LGA-001 to reduce energy that the RPV may be discharging to the Secondary Containment because adequate core cooling; containment integrity; and/or the continued operability of equipment necessary to perform a safe shutdown may not be assured.

d. scramming the reactor and entering LGA-001; followed by LGA-004; “RPV Blowdown;” to preclude further temperature increases by rejecting the heat to the SP instead of outside the Primary Containment because the problem is widespread.

#11. 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.

#12. A reactor startup is in progress on Unit 1: Reactor Mode Switch is in RUN. Annunciator 1H13-P603-A107; IRM HI; is in alarm Annunciator 1H13-P603-B304; Channel A IRM HI-HI/INOP; is in alarm It is determined that the A’ IRM is NOT fully withdrawn; and the detector is STUCK. (1) What is the expected IRM system response; if any? (2) What action(s) is/are required; if any?

A. (1) There are NO IRM generated trips. (2) Continue with the startup. No additional action is required.

B. (1) An IRM UPSCALE rod block and a ½ scram. (2) Bypass IRM A per 1H13-P603-B304; Channel A IRM HI-HI/INOP; and continue with the startup. No additional action is required.

C. (1) There are NO IRM generated trips. (2) Momentarily STOP the startup; bypass IRM A and troubleshoot the stuck IRM detector per LOA-NR-101; Neutron Monitoring Trouble.

D. (1) An IRM UPSCALE rod block and a ½ scram. (2) Momentarily STOP the startup; bypass IRM A per 1H13-P603-B304; Channel A IRM HI-HI/INOP; and troubleshoot the stuck IRM detector per LOA-NR-101; Neutron Monitoring Trouble.

#13. Unit-2 was operating at 100% power: A rupture in the 2C RHR suction line has flooded the Reactor Building Raceway. Manual scram was inserted due to low Suppression Pool level. 14 Control Rods are at position 04. The MDRFP is maintaining level per the LGAs. All ECCS Pumps are in PTL. The Turbine Bypass Valves are maintaining reactor pressure at 920 psig. Suppression Pool Level has rapidly dropped to -20 feet. What is the correct operator action?

A. Initiate ADS per LGA-006; ATWS Blowdown

B. Depressurize using Other Blowdown Systems per LGA-004; RPV Blowdown

C. Depressurize using Other Blowdown Systems per LGA-006; ATWS Blowdown

D. Depressurize using Alternate Pressure Control Systems per LGA-010; Failure to Scram

#14. LOP-WF-20; Radwaste Discharge Tank Discharge to the Lake Blowdown Line; requires the _______________ to sign for FINAL AUTHORIZATION of the Radwaste Discharge.

A. Plant Manager

B. Shift Manager

C. Chemistry Manager

D. NPDES Coordinator

#15. Unit 1 was at 20% power when the Main Turbine tripped. The Main Condenser is at 4 inches of backpressure Hg. At 1300 RPM; annunciator 1PM02J-A401; TURB GEN VIBR HI is in alarm; and PPC Bearing High Vibration alarms. All main turbine bearings are between 5 and 6 mils except bearings 9 and 10 which are indicating 11mils by the PPC indications.The alarms are (1) with the bearing indications. The Unit Supervisor will direct the operators to (2)

A. (1) CONSISTENT (2) THROTTLE OPEN 1TE111; CONDENSER VACUUM BREAKER; per LOA-TG-101; Unit 1 Turbine Generator

B. (1) CONSISTENT (2) VERIFY 1TE111; CONDENSER VACUUM BREAKER; CLOSED per LGP-3-2; Reactor Scram Procedure

C. (1) NOT CONSISTENT (2) VERIFY 1TE111; CONDENSER VACUUM BREAKER;CLOSED per LOA-TG-101; Unit 1 Turbine Generator

D. (1) NOT CONSISTENT (2) THROTTLE OPEN 1TE111; CONDENSER VACUUM BREAKER; per LGP-3-2; Reactor Scram Procedure

#16. 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.

#17. IAW LFP-100-1 MASTER REFUEL PROCEDURE; in order to move fuel within theRPV; at a minimum; a Licensed Fuel Handling Supervisor (SROL) or SeniorReactor Operator (SRO) must be an active license holder …

A. directly supervising core alterations from the refuel floor.

B. directly supervising core alterations from the refuel bridge.

C. within 10 minutes of the refuel floor AND knowledgeable of the status of refuelfloor activities.

D. supervising core alterations in constant communication from the 1H13-P603while observing SRMs.

#18. With the plant at rated power; Control Rod Accumulator Trouble alarms are received for two fully-withdrawn Control Rods within one minute. Investigation revealed that the alarms are both due to low accumulator pressures. The operators must

a. declare BOTH control rods inoperable AND immediately verify one CRD pump is operating OR place the mode switch in SHUTDOWN due to the indication of a systemic problem with the drive mechanisms.

b. declare BOTH control rods inoperable AND immediately verify one CRD pump is operating OR place the mode switch in SHUTDOWN to insure sufficient negative reactivity insertion on a scram.

c. insert and electrically disarm one control rod within one hour OR be in at least HOT SHUTDOWN within 12 hours due to the indication of a systemic problem with the drive mechanisms.

d. insert and electrically disarm one control rod within one hour OR be in at least HOT SHUTDOWN within 12 hours to insure sufficient negative reactivity insertion on a scram.

#19. 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.

#20. Refer To Plant Process Computer PPC Turbine DisplayU-1 was at 100% power when the Unit scrammed with the following conditions. Condenser vacuum is at 3 inches backpressure Hg and stable.What are the required actions to be directed by the Unit Supervisor?

A. Enter LOA-T0-101 Turbine Oil Abnormal; RAISE TLO temp to reduce vibrations.

B. Enter LOA-T0-101 Turbine Oil Abnormal; LOWER TLO temp to reducevibrations.

C. Enter LOA-TG-101 Turbine Generator Abnormal; FULLY Open the 1TE111;Condenser Vacuum Breaker; to Stop the Main Turbine.

D. Enter LOA-TG-101 Turbine Generator Abnormal; THROTTLE Open the 1TE111;Condenser Vacuum Breaker; to Slow down the Main Turbine.

Results