LaSalle RO Quiz - ILTandMe

#1. Unit 1 is shutdown. Average Reactor Coolant temperature is currently 229F; with a steady cooldown rate of 10F/Hr. Which of the following indicates the earliest that the unit will be in MODE 4?

A. 90 minutes

B. 120 minutes

C. 150 minutes

D. 180 minutes

#2. Which of the following indications provide for MAXIMUM heatup during shell warming? (1) Turbine Stop Valve position meter is indicating (2) .

A. (1) #1 (2) 10%

B. (1) #1 (2) 100%

C. (1) #2 (2) 10%

D. (1) #2 (2) 100%

#3. A differential temperature between the bottom of the RPV and the RPV flange thatis greater than 80F on LOA-RR-101; Attachment B; Monitoring of the Reactor WaterTemperature / Pressure During Loss of Both RR Pumps is indicative of…

A. inadequate natural circulation flow.

B. inadequate RT bottom head drain flow.

C. inadequate control rod cooling water flow.

D. excessive RT non-regenerative heat exchanger WR flow.

#4. In order to ensure adequate NPSH for the Recirculation Pumps; the ReactorRecirculation pumps . . .

a. downshift if Feedwater flow <20%.

b. downshift if RPV Water Level drops to Level 3.

c. downshift if <10.1F dT exists between the steam dome and RR pumpsuction.

d. utilize start/upshift logic that requires RR Flow Control Valves to be at aminimum position of 20%.

#5. Given: 1. Reactor building supply and exhaust dampers will close on both units because of the interlock with Group IV. 2. The CRD Pump Cubicle Fans will trip because of low reactor building ventilation air exhaust flow. 3. A Group I MSIV isolation on Hi Steam Tunnel Differential Temperature will occur because of high temperatures following the reactor building ventilation trip. 4. Primary Containment Nitrogen Inerting and Makeup Isolation Valves will close because of the interlock with Group IV.From the above list; the functions that are expected to result from the initiation of a Group IVPrimary Containment Isolation Signal is (are) . . .

a. 3 only

b. 2 and 4 only

c. 1 and 3 only

d. 1; 2 and 4 only

#6. The purpose of the Critical L Path interlock is to keep the . . .

a. Reactor Building Overhead crane main hook aligned with a pre-determined path when transporting the reactor head between the reactorand the reactor head pedestal.

b. Refueling Main Hoist grapple a minimum of 2 feet away from the walls ofthe fuel pools in order to prevent damage to suspended fuel bundlesduring loading into the spent fuel racks.

c. Refueling Bridge Main Hoist grapple aligned with the centerline of thecattle chute in order to prevent damage to suspended fuel bundlesduring transport between the reactor and the fuel pool.

d. Reactor Building Overhead Crane from traveling over the Spent Fuel Poolduring spent fuel cask movement; and to allow the cask to travel onlyover strengthened structural members that can support a cask dropaccident.

#7. Both Units are at 100% power. All Traveling Screens are in Automatic All Traveling Screen differential levels are at 2 in wg. Lake Level as read on the PPC in the MCR is 699.3 ftWhat effect; if any; would a COMPLETE LOSS OF INSTRUMENT AIR have on:1) The Screen Wash capability of the Traveling Screens?2) Lake Level Indication in t.he MCR?

A. (1) Screen Wash capability would be LOST(2) Will be unreliable

B. (1) Screen Wash capability would be LOST(2) NO EFFECT

C. (1) Screen Wash capability would be AUTOMATICALLY MAXIMIZED(2) Will be unreliable

D. (1) Screen Wash capability would be AUTOMATICALLY MAXIMIZED(2) NO EFFECTLAS LICENSED OPS Page: 105 of 154 05 November 2014

#8. Unit 1 is cooling down for a refueling outage with the following conditions present: Reactor Pressure is 100 psig 1A RHR in Shutdown Cooling EHC pressure set is at 150 psig MSIV’s are open Reactor scram has been reset All running RHR Service Water Pumps trip With no operator action; which of the following events will be expected to occur NEXT?

A. 1A RHR pump trip

B. Turbine BPV’s open

C. MSIV’s isolate

D. Reactor Scram

#9. Unit 1 has just scrammed due to a large LOCA. Drywell Temperature has risen to 350 0 F. What are the concerns; if any?

a. Core flow instrumentation is no longer reliable.

b. Drywell temperature instrumentation is no longer reliable.

c. The MSIVs may not function.

d. The SRVs may not function.

#10. Select the statement below that completes the description of the basis behind the “RPV LevelInstrument Criteria” (Table K) found in the emergency operating procedures (LGAs).Elevated temperatures in the Drywell and/or Reactor Building causes the water density todecrease in the . . .

a. horizontal runs of the instrument variable legs; causing indicated level to read lower than actual level.

b. vertical runs of the instrument variable legs; causing indicated level to read lower than actual level.

c. horizontal runs of the instrument reference legs; causing indicated level to read higher than actual level.

d. vertical runs of the instrument reference legs; causing indicated level to read higher than actual level.

#11. Unit 1 is starting up from a refueling outage. – RPV Level is 36 on narrow range – MDRFP is on-line; in manual; with feedwater header flow at 3.8 MLB/HR. – Reactor power is 15% and steady – Pressure is being controlled with Turbine Bypass Valves. – Steam flow is as indicated. (Note: Lower portion of meters are displayed for clarity)Based on the information provided; which of the following annunciators will alarm first if no operator action is taken regarding the operation of the MDRFP?

A. 1H13-P603 A512; RWLCS FAILURE

B. 1H13-P603 A110; RX VESSEL PRESS HI

C. 1H13-P603 A309; FW CONTROL RX VESSEL LVL 7 HI

D. 1H13-P603 A409; FW CONTROL RX VESSEL LO LVL 4

#12. Unit 1 is in Run with the following conditions: Provide Tech Spec pages 1-19 to 1-22 SBLC tank volume 4800 gal SBLC tank concentration 13% SBLC tank temperature 70F Which of the following describes the status of the system?

a. A one hour LCO is in effect.

b. An eight hour LCO is in effect.

c. A seven day LCO is in effect.

d. Technical Specifications requirements are satisfied.

#13. A transient has occurred causing Unit 2 reactor fuel failure. – The crew closed the MSIVs and MSL drains due to elevated steam line radiation ten minutes ago. – Groups II; IV; VII; and X isolations initiated and were verified to be complete ten minutes ago. – The STA reports that the SBGT WRGM value has increased in the last ten minutes to 7E6 pCi/sec. The most likely source of the increasing release rate is leakage FROM the …

a. Reactor Coolant Pressure Boundary TO the Primary Containment.

b. Primary Containment TO the Secondary Containment.

c. Reactor Coolant Pressure Boundary TO Primary Containment Cooling System.

d. Secondary Containment TO the Auxiliary Building.

#14. 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.

#15. What is the Power Supply to 1C Condensate/Condensate Booster Pump?

A. Bus 141X

B. Bus 142X

C. Bus 151

D. Bus 152

#16. LGA-001 entry conditions have been met. Which one of the following conditions would require entering LGA-010?

A. one control rod is at position 04 and one at 02; all other control rods are at position 00.

B. two control rods are at position 04; all other control rods are at position 00

C. twenty-five control rods are at position 02; all other control rods are at position 00

D. one control rod is a position 48; all other contro! rods are at position 00

#17. You are the Unit-2 assist NSO. The plant has been operating at full power; under steady stateconditions; for several weeks. Over the last several days; during performance of the shiftlysurveillance; you have noticed an upward trend in drywell ambient air temperature.As the Unit-2 assist NSO you should . . .

a. discuss your findings with the Unit Supervisor and proceed as directed.

b. direct the responsible non-licensed operator to adjust the chiller load controllers to increase cooling to the drywell.

c. direct the Unit Reactor Operator to reduce reactor power to 95 percent to reduce heat addition to the drywell.

d. discuss your findings with the responsible system engineer and proceed with their recommendations.

#18. A leak in the RWCU system has occurred causing a high temperature isolation.This isolation occurred at a temperature of (1) measured in the (2)

A. (1) 120 F(2) RT Pump Room

B. (1) 146 F(2) RT Pump Room

C. (1) 120 F(2) RT HX Room

D. (1) 146 F(2) RT HX Room

#19. Unit 1 is operating at power when the PCIS Group 1 K7A relay fails open; de-energizing the K51 Relay which de-energizes solenoid 3 for the Inboard MSIV s and de-energizes solenoid 2 for the outboard MSIV s. Which of the following is the expected response of the MSIV s to this failure? INBOARD OUTBOARD Provide Electrical Prints 1E-1-4203AB-AF; AU

A. Remain Open Remain Open

B. Close Close

C. Close Remain Open

D. Open Close

#20. During a reactor startup; the NSO can more closely monitor the SRMs by…

a. changing the recorder speed.

b. changing the indicated range.

c. adjusting the discriminator voltage.

d. selecting the process computer screen.

Results