LaSalle RO Quiz - ILTandMe

#1. Unit 1 is at 100% RTP: LIS-MS-305A, UNIT 1 MAIN STEAM LINE PIPE TUNNEL HIGH DIFFERENTIAL TEMPERATURE ISOLATION (DIV 1) FUNCTIONAL TEST is in progress. Alarms have been flagged.Subsequently: LOR-1H13-P601-F501, DIV 1 MSL PIPE TUNNEL DIFF TEMP HI Alarms. (The first annunciation of the shift). This alarm has no flag.What action(s) is/are required? Acknowledge the annunciator…

A. ONLY.

B. AND announce, “expected alarm”

C. AND announce, “DIV 1 MSL PIPE TUNNEL DIFF TEMP HI” ONLY.

D. AND announce, “DIV 1 MSL PIPE TUNNEL DIFF TEMP HI” AND reference the LOR.

#2. Unit-1 was operating at 25% RTP with the 1B21-F028A; Main Steam IsolationValve closed. Subsequently MSIV 1B21-F022C spuriously closed .Based on the above MSIV closures; RPS relays in …

A. both channels should have de-energized causing a full scram.

B. both channels should remain energized.

C. Channel Al should have de-energized causing a 1/2 scram.

D. Channel B1 should have de-energized causing a 1/2 scram.

#3. Unit 1 is at 100% power. Off-Gas Charcoal Adsorber Train Mode Switch in AUTO with the following lineup: 1N62-F043; Off Gas Charcoal Adsorber Bypass Valve is open. 1N62-F042; Off Gas Charcoal Adsorber Inlet Valve is closed. 1N62-F057 Off Gas System Discharge to Stack is open 1N62-F085A/B Holdup Line Drain Valve are open What is the expected response of the Off Gas System to a valid Hi-Hi Post Treatment radiation condition?

A. No Off Gas Valves will auto position until a Hi-Hi-HI Rad signal is reached.

B. 1N62-F043 will close and 1N62-F042 will open.

C. 1N62-F043 will close; 1N62-F042 will open and 1N62-F057 will close.

D. 1N62-F043 will close; 1N62-F042 will open; 1N62-F057 will close and 1N62-F085A/B will close.

#4. Unit 1 is operating at rated conditions with a TIP trace in progress. TIP A is at the top of the core position when a LOCA occurs. Drywell pressure quickly rises to 5 psig.At what point does the TIP Ball Valve close?The TIP Ball Valve closes . . .

a. immediately.

b. when the TIP stops withdrawing at the indexer position.

c. when the TIP stops withdrawing at the in-shield position.

d. when the TIP stops withdrawing at the core bottom limit position.

#5. According to LOS-DG-M2; “Diesel Generator Operability Test;” the EDG speed droop switchmust be positioned to “50” prior to paralleling with AC power sources. The speed droop switchis placed in this position to . . .

a. allow the EDG to share the load.

b. prevent exceeding limits on fuel rack position.

c. ensure that the EDG picks up all loads on the bus.

d. ensure the EDG will carry the design load assumed in the safety analysis.

#6. Given the following: – REACTOR BLDG CCW EXP TANK LEVEL HI/LO – RBCCW Expansion Tank Level is 52″ – RBCCW RAD HI/LO – RBCCW PRM reading 10;000 CPMWhich one of the following could cause the above symptoms?

a. RBCCW Heat Exchanger tube leak.

b. Drywell Penetration Cooling Coil leak.

c. Reactor Recirc Pump Motor Winding cooler leak.

d. Reactor Water Cleanup Non-Regenerative Heat Exchanger tube leak.

#7. Per HU-AA-101; Human Performance Tools and Verification Practices; which oneof the following correctly states the philosophy to be applied while performing IndependentVerification (IV) of safety related valves located in the Outboard MSIV Room while operatingin Mode 1? |

A. Request that the Shift Manager waive the IV due to the low frequency of personnel traffic inthe areas and complete the IV for the rest of the checklist. .

B. Request that the WEC SRO waive the IV due to the low frequency of personnel traffic in the |areas and complete the IV for the rest of the checklist.

C. Request that the Shift Manager waive the IV for these valves to reduce personnel exposureand complete the IV for the rest of the checklist.

D. Perform the IV after receiving High Radiation and ALARA briefs from the WEC SRO.

#8. Unit 1 is in Mode 4. Inboard and Outboard MSIVs are closed; with their control switches in the closedposition. The 1A RPS MG set tripped and cannot be restored. The Alternate RPS power supply is unavailable. The Shift Manager has directed that the MSIVs be re-opened.Based solely on available power to the MSIV solenoids; which of the following identifieswhich MSIVs; if any; that can be opened with ONLY the 1B RPS power supplyavailable?

a. None.

b. Inboard ONLY.

c. Outboard ONLY.

d. BOTH Inboard and Outboard.

#9. Which of the following identifies the reason(s) for placing the 1B Diesel Gen ControlSelector switch to LOCAL MANUAL when abandoning the control room?1. Defeat automatic initiation of the 1B Diesel Generator.2. Transfer control power from DC Bus 113 to AC Bus 143-1.3. Transfer manual control of the 1B Diesel Generator to the 1B DG Room.

a. 1; 2; AND 3.

b. 3 ONLY.

c. 1 AND 3 ONLY.

d. 2 AND 3 ONLY.

#10. Unit 1 is at rated conditions and in a normal electrical line-up. The Main Turbine/Generator trips. The fast transfer of the 4160 KV bus FAILS.Which of the following identifies 1)component(s) which would be de-energized and 2) theaction required to re-energize the affected bus?

a. 1) 1B CW pump2) Synchronize and close ACB 1425

b. 1) 1A and 1C CD pumps2) Synchronize and close ACB 1415

c. 1) 1B and 1D CD pumps2) Synchronize and close ACB 1425

d. 1) 1A and 1C CW pumps2) Synchronize and close ACB 1415

#11. Surveillance test; LIS-RI-112; “UNIT 1 REACTOR VESSEL HIGH WATER LEVEL 8 RCICTURBINE TRIP AND MAIN TURBINE/FEEDWATER PUMP TRIP CALIBRATION;” was inprogress. While restoring from testing transmitter; 1B21-N705A; “RCIC Div 1 Level 8 trip logic;”the NSO noticed annunciator “RCIC RX VESSEL WTR LVL HI” was still lit.If the “RX WATER LVL HI C TRIP – LEVEL 8 TRIP” status light is actuated under theseconditions; the other expected actions; if any; that will occur are . . .

a. no additional actions.

b. both divisions of RCIC logic trip (only).

c. Main Turbine trip and feedwater pumps trip (only).

d. both divisions of RCIC logic trip; Main Turbine trip; and Feedwater pumps trip.

#12. After a transient; the following parameters are noted: – Drywell pressure 12 psig rising – Drywell air temperature 240F rising – Suppression chamber pressure 7 psig rising – Suppression pool water temperature 105F risingAssuming no operator action has been taken; the event describes a . . .

a. failed open SRV.

b. breached containment following a water break LOCA.

c. normally functioning containment following a high pressure discharge into the drywell.

d. normally functioning containment following a bypass path discharge into the suppression chamber airspace.

#13. Unit 2 is at 100% power when the following occurred: A U-2 Main Generator lockoutIAW OP-LA-103-102-1003 “STRATEGIES FOR SUCCESSFUL TRANSIENTMITIGATION” which of the following annunciators received should the crewaddress first?

A. 2H13-P603-B406 “CHANNEL A1 AND 81 CRD DISCHARGE VOLUME HIGHLEVEL”

B. 2H13-P603-B106 “Channel A1/B1 TURBINE CONTROL VALVE FASTCLOSURE”

C. 2H13-P603-B505 “Channel A1/B1 Rx Vessel Level 3 Low”

D. 1 PM02J 8308 ” Main Turbine Trip”

#14. Unit 1 is in a LOCA Drywell pressure is 10 psig and rising slowly Drywell and Suppression Chamber Hydrogen is 1% Drywell and Suppression Chamber Oxygen is 2% What action is required? The Hydrogen Recombiner must be& ..

A. STOPPED manually

B. STARTED manually

C. Verified to have AUTO-TRIPPED

D. Verified to have AUTO-STARTED

#15. Unit 1 was at 100% power when the following occurs: Drywell pressure is 2 psig. 2 minutes later; Off-site power is lost on Unit 1.When the diesel generator output breakers close ….. .

A. A and C RHR pumps start immediately; Low Pressure Core Spray and B RHRpumps start five seconds later.

B. Low Pressure Core Spray and B RHR pumps start immediately; A and C RHRpumps start five seconds later.

C. Low Pressure Core Spray and C RHR pumps start immediately; A and B RHRpumps start five seconds later.

D. A and B RHR pumps start immediately; Low Pressure Core Spray and C RHRpumps start five seconds later.

#16. Drywell Temperature 310F. Reactor Building Ventilation has isolated. Area Coolers are NOT able to maintain Reactor Building Temperatures. Reactor Building Temperature 180F. Reactor Vessel Pressure 90 psig. Cooldown Rate has NOT exceeded 100F/hour. Which of the following is a usable; on-scale level reading?

A. Shutdown Range level indication reading +80 inches.

B. Upset Range level indication +2 inches.

C. Narrow Range level indication reading +3 inches.

D. Fuel Zone level indication reading – 310 inches.

#17. The RR Flow Control valves provide a means of controlling reactor power from (1) and varying Reactor Recirculation flow from (2) of rated.

A. (1) 0 – 100% (2) 0 – 100%

B. (1) 0 – 100% (2) 25 – 100%

C. (1) 60 – 100% (2) 0 – 100%

D. (1) 60 – 100% (2) 25 – 100%

#18. Given the following conditions: – A reactor startup is in progress. – The reactor is critical at the POAH. – Reactor coolant temperature is 330F. – Reactor heat-up rate is approximately 30F/hr. – All required systems/components are operable.If the most reactive control rod were to drop under these conditions; fuel damage . . .

a. will NOT occur due to enforcement of the rod withdrawal sequence.

b. will occur but be limited by enforcement of the rod withdrawal sequence.

c. will occur with exposures at the site boundary approaching 10 CFR 100 limits.

d. will NOT occur because the control rod velocity limiter limits the free fall velocity.

#19. Unit 1 is at rated conditions with TIP traces in progress. TIP area is posted and verified clear. B’ TIP has just completed a trace and has been returned to the shield. ‘A’ TIP is at position 0001. The 1H13-P601-B211; RB TIP ROOM RAD HI/DOWNSCALE; has come in and is verified to be HI. Which of the following is the NEXT expected action(s) for the operator running the TIP trace?

a. close the ‘A’ TIP ball valve ONLY

b. continue with the next TIP trace

c. close the ‘A’ TIP ball valve and shutdown the TIP machine

d. withdraw the ‘A’ TIP to the in-shield position and then close the ‘A’ TIP ball valve

This question was deleted following exam review

#20. Unit 2 is at rated conditions when an electrician inadvertently disconnects the 2A TDRFP discharge valve open limit switch causing alarm 2H13-P603-A410; 2A/2B TDRFP NOT READY; to annunciate in the control room. Which of the following describes the response of the RR FCVs to this event?

a. ONLY the ‘A’ RR FCV will run back to minimum position.

b. ONLY the ‘B’ RR FCV will run back to minimum position.

c. Both ‘A’ and ‘B’ RR FCVs will run back to minimum position.

d. Both ‘A’ and ‘B’ RR FCVs will remain at their present position.

Results