LaSalle SRO Quiz - ILTandMe

#1. Operators trying to exit the reactor building reported that only one door at the DG corridorairlock can be opened and annunciator “RB 3 DOOR AIRLOCK F21 UNDERVOLTAGE”alarmed. The Unit Supervisor dispatched operators to the reactor building to complete requiredactions.In accordance with LOA-AP-101 Attachment L; since power is lost to ___(1)_; the UnitSupervisor should direct the operators to _(2)___.

a. (1) both doors at the DG corridor airlock; (2) close the door to reset the interlock; then open the next door

b. (1) both doors at the DG corridor airlock; (2) bypass the interlock with jumpers located in the DG corridor to simultaneously open both doors

c. (1) an interlock relay; (2) open breakers to de-energize the interlock relays to simultaneously open both doors

d. (1) an interlock relay; (2) reset the undervoltage relay logic for the airlock doors in the control room to open both doors

#2. A Unit 2 Startup is in progress; with reactor power at approximately 45 percent. ReactorRecirculation Pumps are in fast speed. The TDRFP A is providing feedwater flow in AUTO;TDRFP B is operating on minimum flow with it’s M/A station in MANUAL. As the UnitSupervisor you have directed the unit assist NSO to perform LOS-FW-SR1; Turbine FeedwaterPump Surveillance on TDRFP B.During performance of the Low Pressure Stop Valve test; the valve continued to stroke to theClosed position when the Test pushbutton was released. Which of the following describes:(1) the status of TDRFP B; and(2) the direction you should give to the unit assist Reactor Operator?

a. (1) Coasting down toward 0 RPM (2) Depress the TURB RESET pushbutton and verify that the Low Pressure Stop Valve reopens.

b. (1) Coasting down toward 138 RPM (2) Shutdown TDRFP B in accordance with LOP-FW-05.

c. (1) Operating at the set speed (2) Depress the TURB RESET pushbutton and verify that the Low Pressure Stop Valve reopens.

d. (1) Operating at the set speed (2) Shutdown TDRFP B in accordance with LOP-FW-05.

#3. Unit 2 is shutdown with the following conditions: – A Group I isolation occurred due to personnel error. – Reactor pressure is being controlled from 900-1000 psig by RCIC in the pressure control mode. – RB North HCU radiation level has increased to 20 mr/hr. – RCIC pipe route temperature has increased to 175F. Which of the following describes the required actions? PROVIDE LGA-002 (with entry conditions blanked out)

a. Enter LGA-002 immediately BUT leave RCIC running.

b. Enter LGA-002 immediately AND isolate RCIC steam lines.

c. Delay LGA-002 entry until pipe route temperature increased by 50F AND THEN RCIC could be left running.

d. Delay LGA-002 entry until pipe route temperature increased by 50F AND THEN RCIC isolation would be required.

#4. 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.

#5. Unit 2 was at 93% reactor power when the following event took place: A HIGH STEAMLINE FLOW signal has resulted in a Group 1 isolation. There was a report from the field that steam was coming from the Div 3 switchgear room. Control rods DID NOT fully insert. SBLC has been initiated. RPV water level is currently-145″ and being intentionally lowered. Low-Low Set SRVs are controlling RPV pressure.Would it be required for the US to direct installation of LGA-MS-01; “MSIV ANDMSL DRAIN RX LO-LO-LO LEVEL ISOLATION DEFEAT” and why or why not?

A. NOT REQUIRED; There are indications of a Steam Line break.

B. NOT REQUIRED; LGA-MS-01 CANNOT be performed after the MSIVs haveclosed.

C. REQUIRED; The main condenser is available and reopening of the MSIVs/MSLDrains will help stabilize RPV pressure.

D. REQUIRED; The main condenser is available and reopening of the MSIVs/MSLDrains will reduce the challenge to Primary Containment.

#6. If an irradiated fuel bundle is damaged in the fuel pool during refueling operations; the PRIMARY concern is a higher level of (1) ; and this condition will be made worse if (2) .

A. (1) External radiation exposure (2) Fuel pool temperature is at the LOWER limit

B. (1) External radiation exposure (2) Fuel pool temperature is at the UPPER limit

C. (1) Exposure to gaseous fission products (2) Fuel pool level is at the LOWER limit

D. (1) Exposure to gaseous fission products (2) Fuel pool level is at the UPPER limit

#7. 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.

#8. 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

#9. Both Units were at 100% power when a fire in the main control room required its evacuation. The crew has entered LOA-FX-101(201); Unit 1(2) Safe Shutdown with a Fire in the Control Room OR AEER. The initial actions in the control room for the Unit NSOs were completed prior to evacuation. It has been 20 minutes since the evacuation and RPV pressure control has yet to be fully established. The fire has just been reported extinguished. (1) Which of the following is the correct method of RPV pressure control? (2) What is the HIGHEST emergency action level that has been met?

A. (1) Operators will manually cycle the Relief Valves to establish a cooldown. (2) A Site Area Emergency must be declared.

B. (1) Operators will manually initiate a cooldown using DEHC. (2) A Site Area Emergency must be declared.

C. (1) Operators will manually initiate a cooldown using DEHC. (2) An Alert must be declared.

D. (1) Operators will manually cycle the Relief Valves to establish a cooldown. (2) An Alert must be declared.

#10. Unit 2 is operating at rated power with the following conditions: Instrument Maintenance is performing calibration checks of the ‘C’ Narrow Range Level instrument and reports that the trip setpoint is currently 55.7 inches and cannot be adjusted lower at this time. Which one of the following describes the applicable requirements? Provide T.S. pg. 3-86 to 3-89

a. ‘C’ Narrow Range instrument is still OPERABLE; no action is required.

b. Declare the channel INOP immediately and verify sufficient channels remain OPERABLE or tripped to maintain trip capability.

c. Within two hours; declare the channel INOP and verify sufficient channels remain OPERABLE or tripped to maintain trip capability.

d. Restore ‘C’ Narrow Range within seven days or place it in the tripped condition.

#11. Unit 1 was operating at 100% power when: All running Circulating Water Pumps have tripped. A manual reactor scram is inserted. 3 control rods remain at position 48. LGA-010; Failure to Scram; directs the Unit Supervisor to stabilize RPV pressure below 1059 psig using main turbine bypass valves. What order will the Unit Supervisor give concerning pressure control?

A. Control reactor pressure 800 1000 psig with SRVs.

B. Control reactor pressure 800 1000 psig with bypass valves.

C. Commence a cooldown not to exceed 100 p F per hour with SRVs.

D. Commence a cooldown not to exceed 100 p F per hour with bypass valves.

#12. Reactor Pressure is 1002 psig Turbine Generator is 1193 MWeMoments later the following changes were noted… Average Power Range Monitors (APRM’s) indicate 98.3% and are stableN cv 100 W IU2 100 W V’ Q0 #2. 1 100 % 2. %Bypass Valves1 2 3 4KL L IIWLLIF FrTPI OieB ResetD at erimsLackThe Unit Supervisor should direct the crew to enter…

A. LOA-EH-101 (Unit 1 EHC Abnormal) to reduce reactor power to less than 85% to maintain within the COLR assumptions

B. LOA-PWR-101 (Unit 1 Unplanned Reactivity Addition) to reduce Reactor power using Control Rods

C. LOA-EH-101 (Unit 1 EHC Abnormal) to check Reactor Pressure consistent with EHC Active Pressure Setpoint

D. LOA-PWR-101 (Unit 1 Unplanned Reactivity Addition) to reduce Reactor power using RR FCVs

#13. The unit has suffered a casualty. Both loops of RHR are unavailable. Suppression Pool temperature is 190F. MSIVs are closed. Which of the following sets of conditions would require a reactor blowdown? Reactor Suppression Pressure Pool Level

A. 400 psig -11 feet

B. 400 psig +13 feet

C. 900 psig -11 inches

D. 900 psig +14 feet

#14. Which of the following describes an event the Limiting Condition for Operation for the Main Condenser Offgas system is based upon?

A. Rod Drop Accident

B. Holdup Line Rupture

C. Main Steam Line Rupture

D. Rod Withdrawal Accident

#15. Unit 1 is at full power with RPV pressure at 1025 psig. What is the MAXIMUM allowable time to complete the required action in accordance with Tech Specs; and what is the basis of that action? Reduce reactor steam dome pressure to < 1020 psig within…

A. 15 MINUTES; because the reactor coolant system pressure/temperature limit for brittle fracture is exceeded.

B. 15 MINUTES; because the initial steam dome pressure assumed in transient and accident analysis is exceeded.

C. 2 HOURS; because the reactor coolant system pressure/temperature limit for brittle fracture is exceeded.

D. 2 HOURS; because the initial steam dome pressure assumed in transient and accident analysis is exceeded.

#16. RHR ‘B’ is operating in the Suppression Pool Cooling mode following a Group 1 Isolation at1300 on November 22; 2006. Select the statement below that describes the impact on theRHR ‘B’ if the RHR B room temperature rises to 185F by 1500 on the same day.

a. RHR ‘B’ MUST be declared INOPERABLE immediately.

b. RHR ‘B’ MUST be declared INOPERABLE if room temperature is NOT restored to <150F by 1600 on November 22; 2006.

c. An Operability Determination MUST be completed before 1700 on November 22.

d. An Operability Determination MUST be completed before 1300 on December 22; 2006.

#17. Unit-2 was operating at full rated conditions when an event occurred requiring amanual scram:1) The NSO armed and depressed all manual scram pushbuttons2) All group scram lights remained lit and control rods did NOT move3) The NSO manually initiated both divisions of ARI4) All control rods fully inserted following ARI initiationBased on the above event; (1) and therefore; (2) arerequired to be notified per Nuclear Accident Reporting System (NARS)

A. (1) NONE of the EALs are applicable;(2) NO outside agencies

B. (1) EAL MA3 is the highest applicable EAL;(2) ONLY Illinois EMA and REAC

C. (1) EAL MS3 is the highest applicable EAL;(2) Illinois EMA and REAC; the local county Sheriff and EMA; and LaSalle County ESDA|

D. (1) EAL MS3 is the highest applicable EAL;(2) ONLY Illinois EMA and REAC

#18. Unit 2 is at 100% RTP: ‘A Reactor Recirc Flow Control Valve Locked-up for Maintenance Moments later On the DS001 Alarm Screen “TDRFP A/B Soft Trip” appears 2H13-P603-A409, Feedwater Control Reactor Water Level Low – Level 4 Annunciates 2C Motor Driven Reactor Feed Pump Starts Reactor Water Level is recovering(1) What condition caused the above alarm on the DS001?(2) What procedure will the Unit Supervisor direct as the highest PRIORITY?

A. (1) High Pressure Stop Valve and Low Pressure Stop Valve not full open and a Trip device in the tripped position(2) LOA-FW-201, Reactor Level/Feedwater Pump Control Trouble

B. (1) Greater than 60% mismatch between expected discharge flow and actual discharge flow for 3 seconds, provided there is no mismatch between total pump flow and total header flow.(2) LOA-FW-201, Reactor Level/Feedwater Pump Control Trouble

C. (1) High Pressure Stop Valve and Low Pressure Stop Valve not full open and a Trip device in the tripped position(2) LOA-RR-201, Unit 2 Reactor Recirculation System Trouble

D. (1) Greater than 60% mismatch between expected discharge flow and actual discharge flow for 3 seconds, provided there is no mismatch between total pump flow and total header flow.(2) LOA-RR-201, Unit 2 Reactor Recirculation System Trouble

#19. Unit-1 is performing a normal unit shutdown. The containment is being de-inertedwhen annunciator 1H13-P603-B501; Pri Cnmt Pressure Hi/Lo is received. Drywell pressureindication is verified to read negative 0.6 psig (-0.6 psig).The NEXT action required by Technical Specifications is to …

A. restore pressure to within the limits in 1 hour so that containment pressure remains withindesign values if Drywell Spray is initiated.

B. place the mode switch in SHUTDOWN immediately because containment design limits willbe exceeded if Suppression Chamber Spray is initiated. |

C. place the mode switch in SHUTDOWN immediately because containment design limits willbe exceeded if Drywell Spray is initiated.

D. restore pressure to within the limits in 1 hour so that containment pressure remains within |design values if Suppression Chamber Spray is initiated. |

#20. 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.

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