LaSalle SRO Quiz - ILTandMe

#1. You are the Unit 1 Supervisor and Unit-1 is shutting down following 100 days of continuous operation at rated conditions. The Reactor Operator is inserting control rods; with IRMs on Range 8; when power is lost to the 1A IRM/1C IRM RECORDER. Based on the above conditions; the 1A and 1C IRM alarms and trips are ___(1)_ and you will direct the Reactor Operator to _(2)___.

A. (1) Non-Functional (2) SCRAM the reactor

B. (1) Functional (2) CONTINUE inserting control rods

C. (1) Non-Functional (2) INSERT a half scram for the affected channel.

D. (1) Functional (2) STOP all control rod motion.

#2. Unit 1 is at 100% Power. LOS-RH-M1 RHR SYSTEM OPERABILITY TEST FOR MODE 1;2; and 3 for1A RHR is in progress with Engineering performing ultrasonic testing for fill andvent verification. Engineering has reported that the ultrasonic testing for the 1A RHR dischargepiping did NOT meet maximum acceptance criteria for the size of the void in thesystem piping; and normal venting methods did NOT remove the voids.What actions are required for Tech SpecsfTRM?

A. Enter 72 hour timeclock per TRM 3.7.i for system snubbers.

B. Enter 7 day timeclock per TS 3.5.1 for ECCS pump operability.

C. Enter 8 day timeclock per TS 3.3.5.1 for ECCS Instrumentation.

D. Enter 24 hour timeclock for TRM 3.3.e for ECCS Discharge Line keep filled alarminstrumentation.

#3. Which one of the following events requires notification of the NRC Operations Center via theEvent Notification System (ENS red phone)?

a. A valid actuation that caused inboard and outboard MSIVs to close.

b. An invalid actuation of HPCS while the pump and injection valve are OOS.

c. An invalid actuation of the RWCU inboard isolation valve that trips the RWCU pump.

d. A valid actuation of LPCS with injection into the vessel as part of a pre-planned test.

#4. Unit 2 is operating at 100% power on THROTTLE pressure control: One of three (3) throttle pressure transmitters has drifted low with a pressure output 20 psig lower than the others. A second pressure transmitter fails; and the drifted low throttle pressure transmitter is auto selected as the controlling pressure transmitter.For the given conditions; Turbine Control Valves will (1) ; and the Unit Supervisor will direct action in accordance with (2) .

A. (1) Close (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.3 Turbine Control Valve/Turbine Stop Valve Failed/Failing Full Closed

B. (1) Close (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.1 Loss of a Pressure Regulator

C. (1) Open (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.2 Turbine Control Valve Failed/Failing Full Open

D. (1) Open (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.1 Loss of Pressure Regulator

#5. LGA-009; Radioactivity Release Control has been entered due to an unisolable Main SteamSystem leak in the Turbine Building coupled with damaged fuel. The reactor is shutdown withall control rods fully inserted. Which of the following actions will most effectively minimize theradiation exposure to both onsite and offsite personnel?

a. Start MSIV Leakage Control.

b. Blowdown of the RPV using the ADS valves.

c. Ensuring that the Turbine Building HVAC system is in operation.

d. Rapid depressurization of the RPV using the Main Turbine Bypass Valves.

#6. 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.

#7. A high power ATWS is in progress on Unit 2: Hardcard actions for ATWS are completed LGA-MS-201, USING MAIN CONDENSER AS A HEAT SINK IN ATWS, is in progress with the hardcard actions complete. MSL radiation monitors indicate a Hi/Hi radiation condition Off Gas post treatment rad monitor indicates Hi radiation Main Steam Tunnel temperature is 200 F and rising MSL flow is risingWhat is the NEXT required action?

A. OPEN MSIVs to use the Main Condenser as a heat sink.

B. Verify MSIVs REMAIN OPEN to use the Main Condenser as a heat sink

C. CLOSE MSIVs so that the Containment is used as a heat sink.

D. Verify MSIVs REMAIN CLOSED so that the Containment is used as a heat sink.

#8. A restoration lineup of the Reactor Water Cleanup System is being performed following localleak rate testing of the containment penetrations. The restoration requires IndependentVerification (IV). One of the valves is difficult to access and is located in area where themeasured dose rate is approximately 80 mrem/hr.Which one of the following describes the requirements for independent verification under theseconditions?

a. Independent verification may be waived for ALARA concerns. Alternate verification techniques shall be considered.

b. Independent verification may be waived for ALARA concerns; only if there is an alternate method available to verify valve position.

c. Independent verification must be completed; but the operator must be accompanied by a Radiation Protection Technician.

d. Independent verification must be completed; but the Radiation Protection Manager must authorize the planned exposure.

#9. The Unit 1 is in Mode 1 and the Drywell must be purged as part of a shutdown for a maintenance outage. Which of the following actions MUST be verified complete prior to authorizing the NSO to commence purging the drywell? 1.) Verify Noble Gas Channels 1PL15J and 1PL75J are clear 2.) Verify one SBGT Train has been placed in service 3.) Obtain sample results for Principal Gamma Emitters and Tritium from within 30 hours 4.) Verify Containment is aligned for purge through the Containment vent and Purge System

A. 1 and 4 ONLY

B. 1 and 2 ONLY

C. 2 and 3 ONLY

D. 3 and 4 ONLY

#10. Which of the following events would require notification to State and Local authorities and an ENS notification?

A. Loss of Drywell cooling and Drywell temperature at 320F.

B. 125VDC bus 111Y at 104 volts for 30 minutes.

C. Unisolable steam leak in the RCIC room with radiation levels at 2 X 104 mr/hr.

D. Unisolable water leak from the spent fuel water level at 841 11″ .

#11. 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.

#12. 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.

#13. 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%

#14. Both Units are at 100 % power. EMD has just completed and restored fromLES-FP-06 PREACTION SPRINKLER/SPRAY SYSTEMS IONIZATION SMOKEDETECTOR TEST for the U-2 cable spreading room with the following results: 14 smoke detectors passed the surveillance requirements. Current hourly fire watch for the LES-FP-06 is still in place. Fire detection outside the cable spreading room is inoperable withcompensatory actions in place.When leaving the room; they discovered the Fire Door #279 to the Cablespreading room inoperable.Identify the required compensatory actions; if any; for this situation.

A. Continue the HOURLY Fire Watch.

B. Establish a CONTINUOUS Fire Watch.

C. NONE; the HOURLY Fire Watch may be secured after the LES-FP-06 has beensigned off.

D. Stage an extra fire hose in the area AND establish a CONTINUOUS Fire Watchafter the LES-FP-06 has been signed off.

#15. Unit 2 is at 100% Power with NO active time clocks; when the following occurred: 2H13-P601-C404 RHR 2A and LPCS LINE INTEGRITY MONITOR Alarm wasreceived. Local reading was confirmed to be reading 1 psid to the left of zero; indicating aproblem with LPCS injection line. IMO was dispatched and the calibration was confirmed in tolerance for the DPswitch per LOR actions.(1) Based on the above condition a LPCS Core Spray piping leak/break may haveoccurred. ______ _(2) What is the status of the LPCS system?

A. (1) inside the shroud(2) Requires an operability determination.

B. (1) inside the shroud(2) Declare the system inoperable and immediately start a plant shutdown.

C. (1) between the Reactor Pressure Vessel and the Core Shroud(2) Requires an operability determination.

D. (1) between the Reactor Pressure Vessel and the Core Shroud(2) Declare the system inoperable and immediately start a plant shutdown.

#16. Unit 2 is at 100% RTP with the Division 1 Diesel Generator OOS: Loss of SAT occurs ACB 2415 FAILS to Fast Transfer Bus 242Y trips on overcurrent(1) What Attachment of LOA-AP-201, Unit 2 AC Power System Trouble will be directed by the Unit Supervisor?(2) What Reactor Water Level Instrument is available?

A. (1) Attachment K, Station Blackout Contingencies(2) B Narrow Range Instrument

B. (1) Attachment J, Restore Power to 242Y Using Unit Tie Breakers, 142Y Powered from SAT 142 and 142Y – 142X Bus Tie Breaker Closed(2) B Narrow Range Instrument

C. (1) Attachment K, Station Blackout Contingencies(2) A Narrow Range Instrument

D. (1) Attachment J, Restore Power to 242Y Using Unit Tie Breakers, 142Y Powered from SAT 142 and 142Y – 142X Bus Tie Breaker Closed(2) A Narrow Range Instrument

#17. Rad Protection (RP) has surveyed a work site and determined that personnelworking in the area would be exposed to 300 mrem/hr gamma radiation. During an ALARAreview; four options were discussed.Which one of the following four options listed would be in alignment with ALARA principles?

A. Option 1 : TWO mechanics install 2 layers of lead shielding in a 300 mremhour field for 20 minutes, then ONE operator completes the task in a 60 mremhour field in 30 minutes, then the TWO mechanics return to remove the shielding in a 300 mremhour field for 20 minutes.

B. Option 2 : ONE mechanic installs 1 layers of lead shielding in a 300 mremhour field for 20 minutes, then ONE operator completes the task in a 80 mremhour field in 30 minutes, then the ONE mechanic returns to remove the shielding in a 300 mremhour field for 20 minutes.

C. Option 3: TWO mechanics install 2 layers of lead shielding in a 300 mremhour field for 20 minutes, then TWO operators completes the task in a 50 mremhour field in 30 minutes, then the TWO mechanics return to remove the shielding in a 300 mremhour field for 20 minutes.

D. Option 4: ONE mechanic installs 1 layer of lead shielding in a 300 mremhour field for 20 minutes, then TWO operators completes the task in a 100 mremhour field in 30 minutes, then the mechanic returns to remove the shielding in a 300 mremhour field for 20 minutes.

B

#18. Unit 1 has experienced a LOCA condition. Normal Injections systems are all running Reactor Vessel level is at – 100 inches and dropping at 1inch per minute. Reactor Vessel pressure is at 50 psig. Fire Protection has been directed as an Alternate Injection System. Concurrently; there is a fire in the 1A DG Day Tank Room and the Fire Protection system has actuated. All Fire Protection Pumps are running. Fire protection hoses have been connected to the 1A and 1B TDRFP suction lines. As the US; direction at this point should be to&

A. Secure the FP supply to both TDRFP s; the FP system should be used for firefighting only.

B. Secure the FP supply to one of the TDRFP s in order to provide sufficient fire fighting capability.

C. Allow the FP supply to the TDRFP s to continue; the capacity is within requirements to feed the vessel and provide Fire Protection supply.

D. Allow the FP supply to the TDRFP s to continue; vessel level should be maintained regardless of Fire Protection requirements.

#19. Unit 1 is operating at rated conditions. – The 1A TBCCW Pump and Heat Exchanger are in operation. – The 1B TBCCW Pump is out of service for maintenance. The following annunciators just alarmed on the 1PM10J Panel: – LOR-1PM10J-A301; TBCCW PMP AUTO TRIP – R1520 1A TBCCW Pump A-Trip. – LOR-1PM10J-A304; TBCCW PMP DSCH HDR PRESS LO – R1522 TBCCW Pump Dsch Hdr Press Lo Based on the given conditions; what action is required to be taken first?

A. Scram the Unit 1 reactor per LGP-3-2 the guidance provided in the LOA.

B. Commence a Unit 1 shutdown per LGP-3-1

C. Cross tie Unit 1 TBCCW to Unit 2 TBCCW

D. Supply supplemental cooling to Unit 1 loads per LOA-WT-101 Loss of Turbine Building Closed Cooling Water (TBCCW)”

#20. While operating in Mode 3. A new system engineer has requested that the Unit-1 HPCS pumpbe started with the full flow test valve throttled to 75% open to determine starting current.The evolution is NOT described in current procedures; nor the Safety Analysis Report.The Shift Manager may . . .

a. approve the evolution without restrictions.

b. NOT approve the test under any conditions.

c. ONLY approve the test if another SRO with an engineering degree agrees.

d. NOT approve the test until a written safety evaluation has been performed and approved.

Results