LaSalle RO Quiz - ILTandMe

#1. Unit 2 is at full power Suppression Pool (SP) Cooling is in operation Average pool temperature is increasing RCIC testing is in progress If SP temperature continues to rise; the unit is required to immediately stop RCIC testing if SP temperature exceeds (1) degrees F; or immediately place the reactor mode switch in SHUTDOWN if SP temperature exceeds (2) degrees F.

A. (1) 105 (2) 110

B. (1) 110 (2) 120

C. (1) 105 (2) 120

D. (1) 100 (2) 110

#2. Unit 1 is in a refueling outage. A single fuel bundle is being loaded into the core. The signal-to-noise ratio is 15 to 1. The MINIMUM count rate to verify the required SRMs operable is __ counts per second.

a. 0.7

b. 1.0

c. 2.0

d. 3.0

#3. Unit 1 was at 100% RTP when all CW pumps tripped and were unable to be restarted.Assuming no operator actions, after 60-minutes you would expect to observe tO automatically control reactor pressure.

A. Turbine Bypass Valves throttling at 920 psig

B. Turbine Bypass Valves throttling at 1006 psig

C. One SRV cycling between 896 and 1006 psig

D. One SRV cycling between 976 and 1076 psig

#4. Automatic fire suppression is delayed from activation in the DG rooms to…

a. allow the fire brigade time to extinguish the fire without having to secure the DG.

b. allow personnel in the DG room time to exit prior to activation.

c. ensure that a signal spike would not cause unneeded loss of the DG.

d. ensure that a signal spike would not cause unneeded activation.

#5. The ADS accumulators are at a higher pressure than the SRV accumulators because . . .

a. the ADS system requires 2 solenoids to open the valve.

b. the ADS valves must be able to open with an elevated drywell pressure.

c. elevated pressure ensures better seating of the SRV accumulator check valve.

d. ADS accumulator components require higher actuation pressure.

#6. Given the following plant conditions: – Reactor recirculation loop B pump tripped – Power and flow in the allowable region of Technical SpecificationsThermal Limits: 1. Average Planar Linear Heat Generation Rate 2. Minimum Critical Power Ratio 3. Linear Heat Generation Rate 4. Maximum Allowable Power RatioWhich of the above thermal limits must be adjusted?

a. 1; 2; and 4.

b. 1; 2; and 3.

c. 1 and 2 only

d. 3 and 4 only

#7. What is the significance of the 1/4-inch diameter black dot located on the label forControl Room recorder 1TR-CM037A AVG SP TEMP? The black dot signifies that the recorder . . .

a. is intended for use under accident conditions.

b. is a Technical Specification related instrument.

c. has redundant indication available at the Remote Shutdown Panel.

d. requires manual compensation based on environmental conditions.

#8. Unit 1 is in a Refueling Outage. HPCS is running for a post-maintenance test. LPCS is being drained for a pump inspection. A RHR is running in the SDC mode of operation. C RHR pump discharge valve repair is in progress. Annunciator 1PM13J-B304; RB SE-SW EQUIP DRN SUMP TROUBLE is LIT.o R1438 RB SE DRN SUMP TROUBLE is indicated on the SER display. Annunciator 1PM13J-402; RB SOUTH FLOOR DRN SUMP TROUBLE just LIT.o R1437 RB S FLR DRN SUMP TROUBLE is indicated on the SER display.Which of the following systems should be checked FIRST to determine the cause of thelisted alarms?

a. A RHR

b. C RHR

c. HPCS

d. LPCS

#9. A reactor startup following a 21 day refueling outage is in progress on Unit 2: The NSO determines the reactor is critical and stops rod withdrawal. Reactor power continues to rise with no rod motion. One hour later; reactor power turns and begins to lower.In accordance with LGP 1-1 Attachment L; Precautions to Be Used Before; During; and After Pulling Critical (1) Why did reactor power start lowering? (2) Which of the following would indicate the reactor has returned to subcritical?

A. (1) Moderator temperature lowered. (2) Multiple SRM or IRM readings continuously lowering without rod insertions ONLY.

B. (1) The reactor reached the point of adding heat. (2) Multiple SRM or IRM readings continuously lowering without rod insertions ONLY.

C. (1) Moderator temperature lowered. (2) Multiple SRM or IRM readings continuously lowering without rod insertions AND Multiple IRM downscale readings AND Multiple IRMs are below the levels established when initially at the Point of Adding Heat.

D. (1) The reactor reached the point of adding heat. (2) Multiple SRM or IRM readings continuously lowering without rod insertions AND Multiple IRMs have been down ranged through at least two ranges AND Multiple IRMs are below the levels established when initially at the Point of Adding Heat.

#10. Reactor startup is in progress. The reactor is NOT critical. SRM s read as follows: Channel: A B C D Counts Per Second: 2×103 3×103 2×103 5×103 Predict the effect of a loss of the SRM C High Voltage Power Supply; AND what would be the necessary operator action? EFFECT NECESSARY OPERATOR ACTION

A. Rod Block Suspend startup until repairs are competed.

B. Rod Block Bypass the affected channel and continue startup.

C. Half Scram Bypass the affected channel and continue startup.

D. Half Scram Suspend startup until repairs are competed.

#11. The mode switch is inSTARTUP. IRMs are all on range 5 or 6.During performance of a surveillance for the mode switch, SRMA is moved out ofOPERATE and placed in theSTANDBY position.Which of the following alarm response procedures must be entered?

A. LOR-1H13-P603-A308, ROD OUT BLOCK &;LOR-1H13-P603-A106, SRM INOPERATIVE OR HI

B. LOR-1H13-P603-A308, ROD OUT BLOCK &; LOR-1H13-P603-A206, SRM DOWNSCALE

C. LOR-1H13-P603-B203, CHANNEL A1 REACTOR AUTO SCRAM &; LOR-1H13-P603-A206, SRM DOWNSCALE

D. LOR-1H13-P603-B203, CHANNEL A1 REACTOR AUTO SCRAM & LOR-1H13-P603-A106, SRM INOPERATIVE OR HI

#12. Assume that AC Electrical Power is lost to the Division 1; 125 vde BatteryChargers.Continuing to operate without restoring AC Electrical Power to the Division 1; 125 vdeBattery Chargers will result in …

A. inoperability of RCIC due to loss of power to the governor electronics and several RCICinstruments.

B. inoperability of the 1A Diesel Generator due to loss of field flash and control power.

C. failure of the turbine lube oil to automatically start Emergency Bearing Oil Pump whenrequired.

D. automatic closure and isolation of many inboard primary containment isolation valves.

#13. Which of the following identifies the level instruments that input into RWLC?1. Upset2. Wide Range3. Narrow Range

a. 1; 2; and 3

b. 3 ONLY

c. 1 and 3 ONLY

d. 2 and 3 ONLY

#14. Unit 1 is operating at 100% power with 250 VDC MCC 121Y de-energized; when the supply breaker to MCC 135X-3 trips. What is the status of the Plant Process Computer (PPC) Uninterruptible Power Supply (UPS) AND what must occur in order for it to be powered from its preferred; normal source?

A. De-energized; restore MCC 135X-3 OR 250 VDC MCC 121Y

B. De-energized; restore MCC 135X-3 AND 250 VDC MCC 121Y

C. On alternate power supply; restore MCC 135X-3 OR 250 VDC MCC 121Y

D. On alternate power supply; restore MCC 135X-3 AND 250 VDC MCC 121Y

#15. Unit 1 is shutdown with HPCS in standby. Suppression pool water level is being lowered from normal level to – 9 feet. Predict the impact of this change on the High Pressure Core Spray (HPCS) discharge Line Pressure. HPCS discharge line pressure will&

A. remain constant due to the water leg pump suction source.

B. remain constant due to the water leg pump check valve.

C. will decrease by 3-5 psig.

D. will decrease by 7-9 psig

#16. Unit 1 is operating at rated power. Which of the following components could be eligible to have independent verification waived? A Danger tag to be hung on the…

A. 1AP57E-F4; breaker for 1WS113 at MCC 131Y-1.

B. 1FC095A; Fuel Pool Filter Demineralizer Hold Pump Suction valve.

C. 0CO01C CO2 compressor pressure switch isolation valve; 0CO039.

D. 1CD035A; condensate polishing 1A inlet valve control switch at 1PL05J; TB 687.

#17. Select the answer below that reflects the recommended verbalization of component 1FC088Awhen giving an order to manipulate the component.

a. One F C Eighty Eight A

b. One F C Zero Eight Eight A

c. One F C Eighty Eight Alpha

d. One F C Zero Eight Eight Alpha

#18. Unit 1 is at 100% power. The function switch for the ” A” RBM is placed in ” STANDBY” . What; if any; rod blocks will be applied?

A. Insert Block only.

B. Withdraw Block only.

C. Insert and Withdraw Block.

D. No rod blocks.

#19. You have been directed by the Unit Supervisor to place the 1B DGMaintenance-Auto Transfer Switch in the MAINT position.Where is the switch located?

A. In the 1B DG Room on Local Contro! Panel (1E22-P301B).

B. In 143 Switchgear room in the auxiliary compartment above the 1B DG Output Breaker.

C. In the Main control room on panel 1H13-P601.

D. Inthe 1B DG Room next to the 1B DG Governor.

#20. The Unit 1 reactor is shutdown with head installed and the following conditions: – Coolant temperature is 170F – ‘B’ train residual heat removal is in shutdown cooling operation at 7000 gpm – both recirculation pumps out of service – reactor water level is being maintained at +50 inches on the Shutdown RangeIf an inadvertent PCIS Group 6 isolation occurs and the isolation signal can NOT be cleared; inorder to minimize thermal stratification of the bottom reactor vessel head AND enhance RPVmoderator temperature monitoring; the operators would . . .

a. minimize RWCU blowdown flow.

b. maximize CRD flow to the vessel.

c. maximize RBCCW flow to the RWCU heat exchanger.

d. raise reactor vessel level to at least 220 inches on the shutdown range.

Results