LaSalle SRO Quiz - ILTandMe

#1. Unit two is at 50% power – A high-high level in the 23A heater has occurred – The NSO reports that feedwater temperature has decreased by ten degrees. – The Assist NSO reports: – the associated Extraction Steam Inlet have failed to close. – the associated Extraction Non-Return valves have failed to close. – The NSO scrams the reactor and trips the Main Turbine. The NSO’s actions were…

a. CORRECT to prevent possible backflow of water into the main turbine causing damage.

b. CORRECT to prevent possible fuel damage due to the decreasing feedwater temperature.

c. INCORRECT without first checking the minimum feedwater temperature for the current power.

d. INCORRECT without first attempting a manual isolation of the valves.

#2. Unit 2 is shutdown. While returning the ‘2A’ RHR pump to service; the control power fuse for the breaker CAN NOT be located. The preferred method for determining a replacement fuse is by using the …

a. Placards placed near the fuse.

b. Vendor manuals.

c. EWCS Data Panels.

d. Station fuse list.

#3. 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.

#4. With Unit 1 at 50% power; a malfunction in the feedwater level control system causes reactorwater level to decrease to +5 inches. After the transient subsides; the following conditionsexist: – reactor pressure 1050 psig decreasing – reactor water level 18 inches steady – main turbine tripped – power range indicators unavailable – IRMs fully insertedThe reactor operator reports that neutron level is steady and reading 100 on Range 10 of theIRMs. Reactor power is ___(1)_and LGA 010; “Failure to Scram” requires thatRecirculation pumps _(2)___.

a. (1) 40%; (2) be tripped

b. (1) 4%; (2) be tripped

c. (1) 40%; (2) remain operating

d. (1) 4%; (2) remain operating

#5. 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.

#6. A LOOP occurred on Unit 1 and Unit 2: The RCIC corner room fan trips on overcurrent. RCIC EQP ROOM temperature reads 185 F and is rising. RCIC is online and maintaining reactor water level in band.Unit 1 RCIC is….

A. operable but will be INOP if corner room temperature is not lowered below 150 F within 4 hours.

B. inoperable because RB ventilation and room cooling are both lost to the RCIC corner room.

C. operable until an analysis is performed that demonstrates inoperability of the equipment.

D. inoperable until room temperature lowers below 150F.

#7. An electrical ATWS has occurred from rated conditions on Unit 1:B RPS remains energized following the ATWS choreography ARI has FAILED to actuate LGA-NB-01 (Alternate Rod Insertion) Method 1 is in progress LGA-NB-01 Attachment 1B is complete (Scram Solenoid Fuses Removal) LGA-NB-01 Attachment 1E (SDV Vent and Drain Fuses Removal) has been ordered but has NOT yet been started(1) What is the current status of the Scram Discharge Volume Vent and Drain Valves?(2) What should be ordered NEXT if Attachment 1E is NOT successful in repositioning SDV Vent and Drain Valves?

A. (1) OPEN (2) Evacuate unnecessary personnel from the Reactor Building

B. (1) OPEN(2) Perform Method 6 (Single Rod Scram) of LGA-NB-01

C. (1) CLOSED(2) Evacuate unnecessary personnel from the Reactor Building

D. (1) CLOSED(2) Perform Method 6 (Single Rod Scram) of LGA-NB-01

#8. 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

#9. 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

#10. An ATWS event has occurred on Unit-1.- Drywell pressure is +0.5 psig- A PCIS Group 1 Isolation has occurred- One SRV was open and maintaining reactor pressure in LLSYou are maintaining RPV level per the level band prescribed by step 9 of LGA-010 when the;Unit NSO reports that at -100 inches on the Wide Range the SRV went closed. Reactor pressure |is approximately 900 psig and steady.As the Unit Supervisor; you should …

A. exit level band 9 and control level per level band 8 because power is still ABOVE 3%.

B. continue to control level in the currently prescribed level band because power is stillABOVE 3%.

C. exit level band 9 and control level per level band 7 because power has decreasedBELOW 3%;

D. continue to control level in the currently prescribed level band even though power hasdecreased BELOW 3%.

#11. An operator on rounds reports that his digital dosimetry is alarming on dose rate while touringthe RT pump room. The indicated dose rate is greater than that allowed by the RWP. TheSRO should direct the rounds operator to . . .

a. leave the radiologically controlled area and report to RP.

b. obtain new dosimetry at the WEC.

c. wait in the area for an RP to arrive.

d. initiate a Condition Report and continue with rounds.

#12. You are the Unit 2 Control Room Supervisor. – Unit 2 has scrammed from rated conditions. – Drywell pressure is 2.2 psig and going up slowly. – VR has tripped and Unit 2 VR is required to be started in accordance with LGA-VR-01; Reactor Building Ventilation Startup . – No actions have been taken in the main control room related to VR following the trip of the fans. You will direct an extra reactor operator to perform the in-plant actions to INSTALL jumpers to defeat isolation signals for ___(1) and then _(2)______

A. (1) VR High Drywell Pressure and VR/FC Rad (2) IMMEDIATELY OPEN the VR isolation dampers.

B. (1) VR High Drywell Pressure and VR/FC Rad (2) STANDBY to OPEN the VR isolation dampers after control room actions are taken.

C. (1) VR High Drywell Pressure and Low-Low-Level (2) IMMEDIATELY OPEN the VR isolation dampers.

D. (1) VR High Drywell Pressure and Low-Low-Level (2) STANDBY to OPEN the VR isolation dampers after control room actions are taken.

#13. The following conditions exist: A small LOCA is in progress A RHR and LPCS are injecting RPV water level is -55 inches and lowering Drywell Pressure is at 4 psig and slowly lowering Drywell Temperature is at 152F and slowly lowering Drywell and Suppression Chamber Sprays are running on 1B RHR LOR-1H13-P601-B112; 1A RHR SERV WTR RAD HI; has just alarmed at 165 cpm and rising rapidly. What actions must be directed next?

a. SHUTDOWN the A RHR Service Water Loop ONLY per LOP-RH-05; Operation of RHR Service Water System.

b. SHUTDOWN the A RHR System per LOP-RH-13; Suppression Pool Cooling Operation; AND SHUTDOWN the A RHR Service Water Loop per LOP-RH-05; Operation of RHR Service Water System.

c. OPEN 1E12-F048A; A RHR HX Bypass Valve; and ISOLATE the A RHR Heat Exchanger per LOP-RH-03; Draining the RHR and RHR Service Water Systems; ONLY.

d. OPEN 1E12-F048A; A RHR HX Bypass Valve; and ISOLATE the A RHR Heat Exchanger per LOP-RH-03; Draining the RHR and RHR Service Water Systems; AND SHUTDOWN the A RHR Service Water Loop per LOP-RH-05; Operation of RHR Service Water System.

#14. 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.

#15. 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

#16. The Technical Requirements Manual (TRM) Basis for the Automatic Depressurization System (ADS) Manual Inhibit Switches is to prevent…

A. core damage from low pressure ECCS systems injecting at low pressures from an automatic ADS during an ATWS.

B. an automatic ADS from reducing reactor pressure below 150 psig, ensuring RCIC is available for injection during an ATWS.

C. the ADS logic from being initiated from an external hot short by limiting the voltage across the relay coil with the shorting contact.

D. ADS SRVs from opening during an Anticipated Transient Without Scram (ATWS), ensuring all energy is diverted to the Main Condenser.

#17. 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

#18. A condition related to unknown reactor vessel water level where Adequate Core Cooling existsis described by . . .

a. LGA-001 directed LGA-005 entry; 6 SRVs open; RPV pressure is 25 psig.

b. LGA-001 directed LGA-005 entry; 5 SRVs open; RHR Head Spray established.

c. LGA-010 directed LGA-005 entry; 6 SRVs are open; RPV pressure is 340 psig.

d. LGA-010 directed LGA-005 entry; 7 SRVs are open; RPV pressure is 200 psig.

#19. Which of the following identifies why the Turbine Bypass System is required to beoperable at >25% reactor power?To ensure that the (1) safety limit(s) is/are NOT violated during the (2) transient(s).

a. (1) MCPR (only)(2) turbine trip and feedwater controller failure maximum demand(only)

b. (1) MCPR (only)(2) turbine trip; feedwater controller failure maximum demand; andturbine generator load rejection

c. (1) MCPR and Reactor Pressure(2) turbine trip and feedwater controller failure maximum demand(only)

d. (1) MCPR and Reactor Pressure(2) turbine trip; feedwater controller failure maximum demand; andturbine generator load rejection

#20. Unit 1 is at 70% power performing a Control Rod Sequence Exchange Control rod 18-19 is being continually withdrawn from position 00 to position 12. The operator does not release either the withdraw or continuous withdraw pushbuttons.(1) The RWM: (2) The Unit supervisor will direct:

A. (1) Stops control rod withdrawal at position 12 (2) The RWM is to be declared inoperable ONLY.

B. (1) Stops control rod withdrawal at position 14 (2) The control rod is to be inserted to position 00.

C. (1) Stops control rod withdrawal at position 14 (2) The control rod is to be inserted to position 12.

D. (1) Stops control rod withdrawal at position 12 (2) The RWM is to be declared INOP and the control rod is to be inserted to position 00.

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