LaSalle SRO Quiz - ILTandMe

#1. Unit 1 is at rated power with the following conditions: – ‘A’ Narrow Range Level instrument is selected. – Both TDRFPs are in 3-element control. Which of the following; without operator intervention; would trip the TDRFPs and require entry into LGP-3-2? De-pressurization over fifteen minutes of the…

a. high pressure leg to the ‘A’ MSL flow instrument.

b. high pressure leg to the ‘A’ TDRFP flow instrument.

c. low pressure leg to the ‘A’ FW Header flow instrument.

d. variable leg to the ‘A’ Narrow Range level instrument.

#2. Unit 2 is at rated power. – Two control rod accumulator trouble alarms are received for two fully-withdrawn Control Rods within one minute; the first for HCU 22-11 and the second for HCU 10-19. Investigation revealed that accumulator 22-11 has a pressure of 900 psig and accumulator 10-19 has high water level and a pressure of 1000 psig. Assuming no in-field operator actions are taken; the Unit Supervisor is required to ……. (Reference material provided for this question)

A. declare ONLY the associated control rod for accumulator 22-11 inoperable within 1 hour.

B. declare ONLY the associated control rod for accumulator 22-11 inoperable within 8 hours.

C. declare the associated control rod for accumulator 22-11 inoperable immediately AND declare the associated control rod for accumulator 10-19 inoperable within 1 hour.

D. declare the associated control rod for accumulator 22-11 inoperable within 1 hour AND declare the associated control rod for accumulator 10-19 inoperable within 8 hours.

#3. The Shift Manager is REQUIRED to notify the Duty Station Manager perOP-AA-106-101; Significant Event Reporting; for which one of the following events?

A. Entering a 12 hour shutdown time clock due to an inoperable RR Flow Control Valve.1

B. Entering a 4 hour time clock requiring restoration of ECCS due to a scheduled surveillance.

C. Personnel injury that was treated and released by the site nurse.

D. Load reduction of 20% per a pre-approved Electric Power Operations request.

#4. A major event has occurred on Unit-1.The following conditions exist several hours later: Drywell Pressure is 10 psig and steady. Suppression Chamber pressure is 5 psig and steady. The hydrogen recombiner is in operation for mixing. Division 1 and 2 Post-LOCA monitors indicate 7% hydrogen in the Drywell andrising slowly. Division 1 and 2 Post-LOCA monitors indicate 2% oxygen in the Drywell andrising slowly. Containment venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENThas just been started IAW LGA-011 HYDROGEN CONTROL.The following sequence of events take place next: The NSO reports oxygen levels in the containment are now at 4% and steady. Then 1N62-P600-B304 STATION VENT STACK RADIATION HIGH alarms.What will the Unit Supervisor direct next?

A. Continue venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT; okay toexceed ODCM limits and Secure Recombiner IAW LGA-HG-101 OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

B. Secure venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT due toexceeding ODCM limits and Continue to run Recombiner IAW LGA-HG-101OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

C. Continue venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT, okay to exceed ODCM limits and Continue to run Recombiner IAW LGA-HG-101 OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

D. Secure venting per LGA-VQ-02 EMERGENCY CONTAINMENT VENT due toexceeding ODCM limits and Secure Recombiner IAW LGA-HG-101OPERATION OF THE RECOMBINER AS A MIXING SYSTEM.

#5. Unit 2 is operating at 100% power on THROTTLE pressure control: One of three (3) throttle pressure transmitters has drifted low with a pressure output 20 psig lower than the others. A second pressure transmitter fails; and the drifted low throttle pressure transmitter is auto selected as the controlling pressure transmitter.For the given conditions; Turbine Control Valves will (1) ; and the Unit Supervisor will direct action in accordance with (2) .

A. (1) Close (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.3 Turbine Control Valve/Turbine Stop Valve Failed/Failing Full Closed

B. (1) Close (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.1 Loss of a Pressure Regulator

C. (1) Open (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.2 Turbine Control Valve Failed/Failing Full Open

D. (1) Open (2) LOA-EH-201; UNIT 2 EHC Abnormal; B.1 Loss of Pressure Regulator

#6. Unit 2 is in MODE 4. Average Reactor Coolant temperature is 110F. 2A RHR loop is in the Shutdown Cooling (SDC) Mode of operation. 2E12-F004A; RHR Pump Suppression Pool Suction Valve; was vented with Average Reactor Coolant temperature at 120F. Suppression Pool Temperature is 80F. 242Y is deenergized for planned maintenance. What is the affect; if any; of this evolution on the LPCI mode of operation for the 2A RHR system? The LPCI mode of 2A RHR system is&

A. OPERABLE; provided the system is maintained capable of being realigned when required.

B. NOT affected; since it is NOT required to be operable with the current plant conditions.

C. INOPERABLE; since the minimum flow valve is deenergized closed for SDC Operations.

D. INOPERABLE; since the Suppression Pool Suction Valve CANNOT be opened due to the potential of thermal binding.

#7. Unit 1 is at 100% power: The assist NSO is completing a TIP set per LOP-NR-06; Traversing Incore Probe Operation. TIP Drive Control Unit 1D is taken to Manual Reverse. The assist NSO reports the Unit 1D TIP indicates stuck at the indexer.Two minutes later; Unit 1 scrams. What action will the Unit Supervisor direct and why?

A. De-energize the Ball Valve in NOT more than 72 hours to close the ball valve.

B. De-energize the Ball Valve in NOT more than 4 hours to close the ball valve.

C. Fire the Shear Valve in NOT more than 72 hours to isolate the penetration.

D. Fire the Shear Valve in NOT more than 4 hours to isolate the penetration.

#8. Given the following: Power is at 100% At 1200 on 2/16; it was determined that part of a T.S. required surveillance was NOT performed. The incomplete surveillance was performed on 2/13 The last complete satisfactory surveillance was completed at 1200 on 1/15. The surveillance is required to be performed at least once per 31 days At 1600 on 2/16; the surveillance is performed and is determined to be UNSAT. Which of the following is required first?

a. Be in Hot Shutdown by NO later than 0400 on 2/17.

b. Be in Cold Shutdown by NO later than 1600 on 2/17.

c. Be in Hot Shutdown by NO later than 0400 on 2/20.

d. Be in Cold Shutdown by NO later than 1600 on 2/20.

#9. Unit 2 is in an ATWS condition. – ADS was initiated per LGA-006 “ATWS Blowdown” – ONLY SRVs S; C; U; and D are OPEN; ALL other SRVs remain CLOSED – RPV pressure is 550 psig and going down quickly – Level is -272 inches on Fuel Zone – Reactor Building temperature is 201F – Drywell temperature is 280F – Wide Range level is -140 inches – Narrow Range level is 0 inches Based on the given conditions; you will direct the reactor operator to inject with Preferred ATWS systems when reactor pressure . . . . . . .

A. is BELOW 325 psig; per LGA-005; RPV Flooding .

B. REACHES 325 psig; per LGA-005; RPV Flooding .

C. is BELOW 325 psig; per LGA-010; Failure to Scram .

D. REACHES 325 psig; per LGA-010; Failure to Scram .

#10. In order to move fuel within the RPV; the fuel handling SRO must be &

A. within phone contact.

B. on the refuel bridge.

C. at the refuel floor managers desk.

D. within 10 minutes of the refuel floor.

#11. Unit 2 scrammed from rated conditions 4 hours ago due to a spurious Group 1 isolationsignal that will not clear. RPV level dropped to -25 and is now +35 and being controlled with theMDRFP. Drywell pressure is 1.2 psig 2A RHR was placed in the SDC mode of operation 30 minutes ago. The 2A RHR motor just tripped due to an Instantaneous Overcurrent condition.Which of the following procedures can be directed for use to mitigate the consequencesof the loss of SDC for the given conditions?1. LGA-MS-012. LGA-RH-201 3. LOA-RH-201 4.LOP-RT-09

a. 1 AND 2 ONLY.

b. 2 AND 3 ONLY.

c. 3 AND 4 ONLY.

d. 2; 3; AND 4 ONLY.

#12. During a reactor pressure transient; 4 Safety Relief Valves (SRVs) automaticallyopened when RPV pressure reached 1090 psig. All other SRVs have remained closed during the |transient. Which one of the following correctly states the status of the SRVs and the actions that should bedirected by the Unit Supervisor?

A. Four SRYs have opened before their relief setpoint; close the SRVs per LOA-SRV-101;Stuck Open Safety Relief Vales.

B. All thirteen SRVs have functioned as designed; control pressure below 1059 psig perLGA-001; RPV Control.

C. Two SRVs have failed to open at their relief setpoint; control pressure below 1059 psig perLGA-001; RPV Control.

D. One SRV has opened before its relief setpoint; close the SRV per LOA-SRV-101; StuckOpen Safety Relief Valve.

#13. While operating at RTP; with no surveillances or tests in progress; Unit 1 received a1A RHR/LPCS LN INTEGRITY MONITOR alarm. The Reactor Building Equipment Operatorreported that DPIS-1E12-N029A was reading normal at zero psid on the local panel.Which of the following actions are required for this condition?

a. Declare LPCS INOPERABLE. Restore to OPERABLE status within 7 days.

b. Declare RHR A INOPERABLE. Restore to OPERABLE status within 7 days.

c. Declare RHR A /LPCS dP instrumentation channel INOPERABLE. Restore to OPERABLE status within 72 hours.

d. Declare RHR A and LPCS INOPERABLE. Restore RHR A or LPCS to OPERABLE status within 72 hours.

#14. An ATWS has occurred. Reactor Power is 20% and oscillating. SBLC is injecting. Turbine Bypass Valves are maintaining RPV pressure. Reactor level is +18 inches. Which of the following is the required level band and why?

A. – 150 inches to – 60 inches; to decrease the Natural Circulation driving head and core flow.

B. – 150 inches to – 60 inches; to concentrate the boron; thus lowering the reactor power level.

C. – 150 inches to +59.5 inches; to allow reactor pressure to decrease; which will add negative reactivity due to reduced moderator density.

D. – 150 inches to +59.5 inches; to allow level control to be returned to automatic; thereby providing flexibility to perform other LGA actions.

#15. Unit 1 is at 100% power:LOR-1N62-P600-B208, OFF GAS POST-TREATMENT RADIATION TROUBLE is in alarm.At the 1H13-P604 the1A &1B Off Gas Post-Treatment Rad Monitors (1D18-K601A & 1D18-K601B) fail downscale.(1) What is the status of the 1N62-F057, Off Gas Vent Stack Discharge Valve?(2) What is/are the ODCM required action(s)?

A. (1) OPEN(2) Enter ODCM 12.2.2 RA D.1 and D.2 and D.3

B. (1) OPEN (2) Enter ODCM 12.2.2 RA C.1

C. (1) CLOSED(2) Enter ODCM 12.2.2 RA C.1

D. (1) CLOSED(2) Enter ODCM 12.2.2 RA C.1

#16. A DBA LOCA is occuring on Unit 1: HPCS is injecting at 6500 gpm 141Y tripped on overcurrent Drywell and Chamber Sprays are on ‘1B’ RHR ‘1C’ RHR pump tripped on overcurrent RPV Pressure is 20 psig DW pressure is 20 psig RPV Water level is -220″ on Fuel Zone and lowering 2″/min An RPV blowdown per LGA-004, RPV BLOWDOWN, has been initiated(1) Adequate core cooling is not met because(2) Per LGA-001, RPV CONTROL, the next action directed by the Unit Supervisor will be to

A. (1) spray flow is inadequate, and the top 1/3 of the fuel is not adequately cooled.(2) maximize injection using preferred and alternate injection sources

B. (1) RPV water level is too low, and the top of jet pump risers are uncovered.(2) maximize injection using preferred and alternate injection sources

C. (1) spray flow is inadequate, and the top 1/3 of the fuel is not adequately cooled.(2) exit all LGAs and Enter all SAMGs

D. (1) RPV water level is too low, and the top of jet pump risers are uncovered.(2) exit all LGAs and Enter all SAMGs

#17. 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.

#18. LGA-009 has been entered due to high offsite release. What affect; if any; does this have onpermissible radiation exposure limits?

a. There is no affect on allowable exposure limits.

b. Automatically authorized to increase allowable exposure limit by a factor of 2.

c. Automatically authorized to increase allowable exposure limit to federal limits.

d. Automatically authorized to increase allowable exposure limit to emergency limits.

#19. Unit 1 is operating at rated conditions when the Unit 1 Process Computer UPS Normaland Alternate AC power feed breakers trip. It has been determined it will be at least one hour before the Normal and/orAlternate Power Supplies will be restored.Which of the following identifies the procedure to be directed in response to this eventand the actions; if any; required to be taken?

a. LOP-CX-08; Uninterruptible Power Supply Startup; Operation; andShutdownNo immediate actions required.

b. LOP-CX-08; Uninterruptible Power Supply Startup; Operation; andShutdownLimit PPC operation to less than 30 minutes.

c. LOA-RM-101; Unit 1 RCMS Abnormal OperationVerify RCMS controllers have automatically rebooted.

d. LOA-RM-101; Unit 1 RCMS Abnormal OperationVerify RCMS automatically transferred to the Alternate Power Supply.

#20. A Unit startup is in progress with the following conditions: The reactor is critical; below the point of adding heat. The reactor is on an infinite period. Reactor power is on the Intermediate Range Monitors (IRMs) Range 2. The unit NSO withdraws several control rod notches per the sequence package and takes the following readings to determine reactor period: Initial power 20 on IRM Range 2. Final power 40 on IRM Range 2. Time to change from initial to final power was 30 seconds. Annunciator 1H13-P603-A306; SRM Short Period; alarms. Based on the above information and calculated reactor period; the SRM SHORT PERIOD annunciator (1) be alarming; and the Unit Supervisor shall direct the NSO to (2) .

A. (1) should NOT (2) insert control rods using RCMS

B. (1) should NOT (2) continue control rod withdrawal

C. (1) should (2) insert control rods using RCMS

D. (1) should (2) manually scram the reactor

Results

#3. The Shift Manager is REQUIRED to notify the Duty Station Manager perOP-AA-106-101; Significant Event Reporting; for which one of the following events?

#10. In order to move fuel within the RPV; the fuel handling SRO must be &

#14. An ATWS has occurred. Reactor Power is 20% and oscillating. SBLC is injecting. Turbine Bypass Valves are maintaining RPV pressure. Reactor level is +18 inches. Which of the following is the required level band and why?

#17. 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:

#18. LGA-009 has been entered due to high offsite release. What affect; if any; does this have onpermissible radiation exposure limits?