LaSalle RO Quiz - ILTandMe

#1. LGA-RT-101; RPV Depressurization Using RWCU Blowdown is in progress and theMain Condenser is NOT available to accept RWCU flow.For the given conditions; LGA-RT-101 provides an ALARA warning for abnormally highairborne radiation levels in the . . .

a. Radwaste Control Room.

b. Division 3 Switchgear room.

c. vicinity of the Radwaste Tanks.

d. RWCU Heat Exchanger rooms.

#2. 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.

#3. 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.

#4. Given the following: A reactor startup is in progress NO control rods have been withdrawn Initial SRM count rates are: SRM A 30 SRM B 35 SRM C 50 SRM D 45Which of the following is the requirement IAW LGP-1-1 “Unit Startup” to STARTsingle notch withdrawal of control rods?

A. RWM is Inoperable

B. SRM C count rate of 200

C. Group 1 control rods all at position 48

D. The reactor is NOT critical after reaching the ECP estimated critical prediction

#5. The Unit 1 reactor core is being loaded with the following conditions in place: – All SRMs are fully inserted – All control rods are fully inserted – There are at least 6 fuel assemblies adjacent to each SRM – There are more than 10 fuel assemblies loaded in each quadrant. Determine if loading fuel at location 15-18 is allowed; and if the requirement for operable SRMs is met.

A. Allowed. The requirement to have an OPERABLE SRM in the quadrant of the reactor core where CORE ALTERATIONS are being performed is met. The requirement to have an OPERABLE SRM in an adjacent quadrant containing fuel is met.

B. Allowed. The requirement to have an OPERABLE SRM in the quadrant of the reactor core where CORE ALTERATIONS are being performed is met. An OPERABLE SRM in an adjacent quadrant containing fuel is NOT required.

C. NOT allowed. The requirement to have an OPERABLE SRM in the quadrant of the reactor core where CORE ALTERATIONS are being performed is NOT met. The requirement to have an OPERABLE SRM in an adjacent quadrant containing fuel is met.

D. NOT allowed. The requirement to have an OPERABLE SRM in the quadrant of the reactor core where CORE ALTERATIONS are being performed is NOT met. The requirement to have an OPERABLE SRM in an adjacent quadrant containing fuel is NOT met.

#6. Due to a security event Both Units are shutdown with the following conditions: Both Unit 1 and 2 SATs are NOT available. Both Unit 1 and 2 Division 1 and 2 DGs are NOT available.Which of the following is the Preferred action to be taken to mitigate an off-siterelease?

A. Line up B.5.b pump in Spent Fuel Pool Spray mode to directly cool fuelassemblies per LOA-SY-004 EXTREME DAMAGE MITIGATION STRATEGIES.

B. Line up FC pumps per LOA-FC-101 FUEL POOL COOLINGSYSTEM/REACTOR CAVITY LEVEL ABNORMAL to supply cooling to the spentfuel pool.

C. Line up B RH in Fuel Pool Cooling Assist per LOP-RH-15 RHR FUEL POOLCOOLING ASSIST AND ALTERNATE FUEL POOL COOLING MODES.

D. Line up B.5.b pump in Spent Fuel Pool Make Up mode to maintain fuelassemblies submerged per LOA-SY-004 EXTREME DAMAGE MITIGATIONSTRATEGIES.

#7. To provide an additional margin of safety; the APRM Flow Biased Simulated ThermalPower Upscale Trip and alarm setpoints are automatically adjusted in proportion to (1) flow rate signals. These signals are passed through a (2) valuegate to ensure conservatism is added to the flow biased trip circuits.

a. (1) Feedwater(2) low

b. (1) Feedwater(2) high

c. (1) Reactor Recirculation(2) low

d. (1) Reactor Recirculation(2) high

#8. During a casualty; an NSO opened an SRV to control RPV pressure. The SRV was closed andmanually opened again 15 seconds later.Which one of the following describes the potential adverse consequences of this action?

a. Suppression Pool wall damage due to cyclic dynamic loading.

b. SRV tailpipe damage due to excessive water level in the tailpipe.

c. ECCS pump damage due to the creation of a vortex in the suppression pool.

d. SRV seat damage due to partial opening of the valve with limited air pressure.

#9. Which of the following describes the minimum and maximum level indications that can be monitored from the Remote Shutdown Panel? Minimum: _____(1) Maximum: _(2)____

A. (1) 0 (zero inches) (2) +60 inches (plus 60 inches)

B. (1) 0 (zero inches) (2) +180inches (plus 180 inches)

C. (1) -150 inches (minus 150 inches) (2) +60 inches (plus 60 inches)

D. (1) -311 inches (minus 311 inches) (2) -111 inches (minus 111 inches)

#10. Unit 1 was operating at 100% reactor thermal power with SRV 1B21-F013U; leaking steam pastits seat. The leakage caused the suppression pool to heatup. Under these circumstances;initiating suppression pool cooling would be necessary to prevent __________ during accidentconditions.

a. SRV tailpipe damage

b. RH; LPCS; and HPCS pumps thermal damage

c. incomplete condensing of steam discharged to the suppression pool

d. possible water hammer when starting RH; LPCS or HPCS pumps

#11. What are the Operational implications of the 0 DG room temperature reaching 109 F and the 0 DG is in operation. When the 0 DG is secured …

A. the ventilation fan will immediately automatically stop.

B. the ventilation fan will continue to run and manual shutdown is required.

C. the ventilation fan will continue to run until room temperature lowers to approximately 104F.

D. the ventilation fan will automatically stop when the DG is secured; but restart if room temperature reaches 110F

#12. Unit 1 has experienced a LOCA. LGA-004 has been performed based on the Pressure Suppression Pressure limit being exceeded. Containment Pressure is at 52 psig and increasing. LGA-VQ-02; Emergency Containment Vent has been directed. Actions during the performance of this procedure should include &

A. shutdown of the Control Room Ventilation System.

B. shutdown of the Control Room Emergency Makeup train.

C. evacuation of the Reactor Building; Auxiliary Building; and Turbine Building in Unit 1 ONLY.

D. evacuation of the Reactor Building; Auxiliary Building; and Turbine Building in Unit 1 AND Unit 2.

#13. Given the following initial plant information: Unit-1 is in a refueling outage. Unit-1 UAT is a qualified off-site source. Bus 13 is de-energized. Unit-2 is in Mode 2 with a start-up in progress.Given this initial lineup; which one of the following combinations of failures wouldresult in a loss of all Off-Site AC power to both units?

A. Unit 2 Ring Bus and TR-81

B. Unit-1 UAT and Unit-2 SAT

C. Unit-1 UAT and Lines L0101 and L0104

D. Unit-2 SAT and Lines L0102 and L0103

#14. Unit 2 RCIC is in a normal standby lineup. Leaking valves cause Suppression Pool Level to increase such that High Suppression Pool Water Level alarms are received on the 2H13-P601 panel. Which one of the following describes the response of the RCIC system to this condition?

A. RCIC Suction from the Suppression Pool; 2E51-F031; will open and then RCIC Suction from the CY Tank; 2E51-F010; will close.

B. RCIC Suction from the CY Tank; 2E51-F010; will close and then RCIC Suction from the Suppression Pool; 2E51-F031; will open.

C. RCIC suctions will remain in standby configuration until a low CY Tank level condition occurs at which time they will transfer with 2E51-F031; RCIC Suction from the Suppression Pool; opening and then 2E51-F010; Suction from the CY Tank; closing.

D. RCIC suctions will remain in standby configuration until a low CY Tank level condition occurs at which time they will transfer with 2E51-F010; Suction from the CY Tank; closing and then 2E51-F031; RCIC Suction from the Suppression Pool; opening.

#15. The Off-Gas system was in operation with flow bypassing the charcoal adsorber trains(Charcoal Adsorber Train mode switch was in AUTO). Power was subsequently lost to24/48 VDC Distribution Panel 1A. The Off-Gas system flow-path will . . .

a. isolate.

b. remain as is.

c. realign with flow through both the charcoal adsorber trains and the bypass line.

d. realign with flow through the charcoal adsorber trains with the bypass line isolated.

#16. A LOCA has occurred in the Drywell on Unit 1: Drywell pressure is 5 psig. Drywell temperature is 340°F. Suppression Pool level is + 10 feet. What is the operational impact; if any; of initiating Drywell Sprays?

A. Drywell parameters will return to allowable values upon initiation of Drywell Sprays with no additional operational impact.

B. High differential pressure between the Suppression Chamber and the Drywell may result in exceeding the Primary Containment Pressure Limit.

C. The evaporative cooling pressure drop may result in Primary Containment pressure dropping at a rate too fast to be compensated for by operator action.

D. The evaporative cooling pressure drop may result in high differential pressure between the Suppression Chamber and the Drywell; lowering the margin to the Pressure Suppression Pressure limit.

#17. Unit 1 was at full power operation with RCIC operating for a quarterly surveillance test. TheUnit 1 control room NSO received a report from equipment operators that the RCIC room wasfilled with steam. The NSO observed RCIC area temperatures and noted the following: – RCIC Equipment Area ambient temperature was 195F and increasing – RCIC Area Vent Differential temperature was 103F and increasing – Annunciator 1H13-P601-D411; “Div I RCIC Equip Area Diff/Area Temp Hi;” was alarming – Division II; RCIC Primary Containment Isolation System had NOT actuatedAssuming no operator actions were initiated; the RCIC Turbine Steam Supply ___(1)_automatically close(s) AND operator actions need be taken to _(2)___.

a. (1) inboard isolation valves; (2) shutdown RCIC in accordance with LOP-RI-03; “Reactor Core Isolation Cooling System Isolation and System Shutdown”

b. (1) outboard isolation valve; (2) shutdown RCIC in accordance with LOP-RI-03; “Reactor Core Isolation Cooling System Isolation and System Shutdown”

c. (1) inboard isolation valves; (2) recover RCIC in accordance with LOP-RI-04; “Turbine Trip Recovery and Turbine Reset of RCIC”

d. (1) outboard isolation valve; (2) recover RCIC in accordance with LOP-RI-04; “Turbine Trip Recovery and Turbine Reset of RCIC”

#18. Both Units are operating at 100% power: Station Air Compressors 2SA01C and 0SA01C are running in a normal lineup. Unit 2 Turbine Building Closed Cooling Water (TBCCW) flow is lost in the Turbine Building. How will the Station Air compressors respond if TBCCW flow is NOT restored in the Unit 2 Turbine Building?

A. 0SA01C Air Compressor ONLY will TRIP on high discharge AIR TEMPERATURE.

B. 2SA01C Air Compressor ONLY will TRIP on high discharge AIR TEMPERATURE.

C. 2SA01C AND 0SA01C Air Compressors are unaffected and will continue operating.

D. 2SA01C AND 0SA01C Air Compressors will TRIP on high discharge AIR TEMPERATURE.

#19. A LOCA has occurred on Unit 2 – Drywell pressure is 2.1 psig – Reactor water level is -25 inches and stable – The HPCS injection valve has been manually closed – The HPCS Pump has been overridden to STOP Which of the following describes the response of the HPCS system if Off-site power is lost and the ESF buses are re-energized by their respective Diesel Generators? The HPCS system will. ..

A. INJECT to the vessel by manual operation ONLY.

B. automatically INJECT to the vessel on a Level 2 signal.

C. immediately INJECT to the vessel on a High Drywell Pressure signal.

D. immediately ALIGN valves to inject to the vessel; but require a manual pump start.

#20. Unit 1 is in Mode 4: Reactor Coolant temperature is 150 F Alternate shutdown cooling is in operation with heat removal provided by the reactor water cleanup system 2 RT filter demineralizers are in service The B RWCU Non-Regenerative Heat Exchanger is in use to maintain vessel temperature, with the local D/P gauge 1PDI-WR028, reading of 10.0 psidTwo minutes later: The local RBCCW D/P gauge 1PDI-WR028, reads 2 psid The WR head tank level is steadyWhat is the significance in the change of this D/P reading and the consequence of this change?

A. Reduced WR flow to the Non-Regenerative heat exchanger and a high motor temperature trip of the reactor water cleanup pumps.

B. Reduced WR flow to the Non-Regenerative heat exchanger and potential isolation of the RT filters.

C. Increased WR flow to the Non-Regenerative heat exchanger and could violate temperature limits on the reactor vesse

D. Increased WR flow to the Non-Regenerative heat exchanger and potential heat exchange cavitation

Results