LaSalle SRO Quiz - ILTandMe

#1. 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.

#2. Given the following conditions: Unit-1 was at 100% power. ‘A’ IN Compressor is cross-tied to ‘B’ Dryer. Group 1 and Group 10 isolations were caused by an instrument failure. The Unit 1 Supervisor directs the LOCAL Operators to (1) IAW (2) .

a. (1) CHECK; 1IN22M; Rupture Disk is NORMAL to verify the IN Dryer did not over pressurize the purge line (2) LOA-IN-101; Loss of Drywell Pneumatic Air Supply

b. (1) CHECK; 1IN22M; Rupture Disk is NORMAL to verify the IN Dryer did not over pressurize the purge line (2) LOP-IN-03; Drywell Pneumatic System Transfer to Station Instrument Air System

c. (1) ISOLATE 1IN09MA; South Side Bottle Bank Gas Manifold System in order to preserve bank pressure (2) LOP-IN-03; Drywell Pneumatic System Transfer to Station Instrument Air System

d. (1) ISOLATE 1IN09MA; South Side Bottle Bank Gas Manifold System in order to preserve bank pressure (2) LOA-IN-101; Loss of Drywell Pneumatic Air Supply

#3. Given the following conditions: – The plant has been operating at full power for an extended period of time. – All components/systems were operable and lined up for normal operation prior to the following event.A rupture of the main condenser inlet water box results in a trip of all running Circulating Waterpumps. Select the statement below that describes your procedure use.

a. RPV Control to control RPV Level and Pressure. Primary Containment Control to control Suppression Pool level and temperature.

b. RPV Control to control RPV Level. Secondary Containment Control to mitigate flooding caused by the condenser water box rupture.

c. RPV Control to control RPV pressure. Primary Containment Control to control Suppression Pool and Drywell temperatures.

d. Primary Containment Control to control Suppression Pool level and temperature. Secondary Containment Control to mitigate flooding caused by the condenser water box rupture.

#4. Unit 2 is in Hot Shutdown with the following conditions: Both of the running VR exhaust fans have tripped. Reactor building differential pressure is +0.01 inch H20. Which of the following is the overriding document for this situation?

a. LGA-002; Secondary Containment Control.

b. The associated annunciator response procedures.

c. Tech Spec 3.6.5.1; Secondary Containment Integrity.

d. LOA-VR-201; Unit 2 Recovery from a Group 4 Isolation or Spurious Trip of Reactor Building Ventilation.

#5. Unit 1 is operating at rated conditions with 1A VP in-service; when an inadvertent Group2 Isolation occurs.Drywell temperature was recorded as 95F at the time of the isolation; 1 minute ago.Which of the following identifies the procedure to be directed for use for bulk drywelltemperature determination while recovering from the isolation signal?

a. LGA-003; Primary Containment Control

b. LOP-CX-02; Safety Parameter Display System

c. LOA-PC-101; Primary Secondary Containment Trouble

d. LOP-CM-04; Primary Containment Temperature Determination

#6. The Heat Capacity Temperature Limit (HCTL) is

A. the maximum primary containment temperature at which SRVs can be opened and will remain open.

B. the highest suppression chamber temperature which can occur without steam in thesuppression chamber airspace

C the highest suppression pool temperature at which opening an SRV will not result in exceeding the code allowable stresses in the SRV tail pipe, tail pipe supports, quencher, or quencher supports

D. the highest suppression pool temperature at which emergency RPV depressurization will not raise Suppression chamber temperature above maximum temperature capability of the suppression chamber.

#7. A LOCA has occurred; with no injection sources available. RPV Level is below the top of active fuel. While reviewing electrical prints; it is determined that temporary wiring could be run to an ECCS pump in order to make it available for use. Which of the following is required; at a MINIMUM; to permit this evolution?

A. Approval from One (1) Licensed SRO.

B. Approval from Two (2) Licensed SRO’s

C. A 50.59 Safety Evaluation has been completed.

D. Approval from the NRC.

#8. An earthquake has resulted in the following conditions on Unit 1: – The reactor automatically scrammed from rated conditions and all control rods fully inserted. – Suppression Pool water level has dropped to – 9 inches (minus nine inches) due to a leak in the LPCS pump suction piping; AND continuing to go down at 1 inch per minute. – 5 minutes later; the leak was stopped by closing the 1E21-F001; LPCS Pump Suction Valve. Which of the following sources for Suppression Pool Temperature are acceptable for use when determining Suppression Pool Water temperature for the given conditions? 1) SPDS 2) Computer points L122 and L123 3) Remote Shutdown Panel Indicator 1TI-CM037 4) AVG SP TEMP 1TR-CM037A and 1TR-CM038A (1PM13J Recorders) 5) SP TEMP SIG PROCESSORS 1UY-CM037 and 1UY-CM038 (1PM13J NuMacs)

A. 1; 2; and 3 ONLY.

B. 3; 4; and 5 ONLY

C. 2; 3; and 4 ONLY

D. 1; 2; 3; 4 and 5

#9. Unit 2 is at 100% RTP with the Division 1 Diesel Generator OOS: Loss of SAT occurs ACB 2415 FAILS to Fast Transfer Bus 242Y trips on overcurrent(1) What Attachment of LOA-AP-201, Unit 2 AC Power System Trouble will be directed by the Unit Supervisor?(2) What Reactor Water Level Instrument is available?

A. (1) Attachment K, Station Blackout Contingencies(2) B Narrow Range Instrument

B. (1) Attachment J, Restore Power to 242Y Using Unit Tie Breakers, 142Y Powered from SAT 142 and 142Y – 142X Bus Tie Breaker Closed(2) B Narrow Range Instrument

C. (1) Attachment K, Station Blackout Contingencies(2) A Narrow Range Instrument

D. (1) Attachment J, Restore Power to 242Y Using Unit Tie Breakers, 142Y Powered from SAT 142 and 142Y – 142X Bus Tie Breaker Closed(2) A Narrow Range Instrument

#10. Unit-2 was operating at 100% power: A rupture in the 2C RHR suction line has flooded the Reactor Building Raceway. Manual scram was inserted due to low Suppression Pool level. 14 Control Rods are at position 04. The MDRFP is maintaining level per the LGAs. All ECCS Pumps are in PTL. The Turbine Bypass Valves are maintaining reactor pressure at 920 psig. Suppression Pool Level has rapidly dropped to -20 feet. What is the correct operator action?

A. Initiate ADS per LGA-006; ATWS Blowdown

B. Depressurize using Other Blowdown Systems per LGA-004; RPV Blowdown

C. Depressurize using Other Blowdown Systems per LGA-006; ATWS Blowdown

D. Depressurize using Alternate Pressure Control Systems per LGA-010; Failure to Scram

#11. During a refueling outage the reactor core is being loaded.- All SRMs are fully inserted- All control rods are fully inserted- The signal to noise ratio for all SRMs is 15:1- There are at least 6 fuel assemblies adjacent to each SRM- There are more than 10 fuel assemblies loaded in each quadrant- Fuel assemblies are being loaded into the same quadrant where SRM A is located While lowering a Fuel Assembly into the same quadrant as SRM A is located; the NSO takes thefollowing SRM readings:SRM A = 2.5 SRM B= 2.0 SRM C = 4.0 SRM D = 3.0Based on the above SRM indications core alterations should be …|

A. allowed to continue because SRM D is operable and is located in an adjacent quadrant towhere core alterations are taking place.

B. suspended immediately because the capability to detect local reactivity changes in the core isdegraded with SRM B inoperable. |

C. allowed to continue because SRMs D and A are operable and are located in an adjacentquadrant and a quadrant where core alterations are taking place.

D. suspended immediately because the capability to detect local reactivity changes in the core is.degraded with SRM A inoperable. Provide Technical Specification 3.3.1.2; pages 3.3.1.2-1 through 3.3.1.2-6 to the examinee as a handout.

#12. While operating at full power with the RCIC turbine running at 600 gpm for asurveillance; an event occurred on Unit-1. ;The NSO observed the following indications as a direct result of the event:- RCIC turbine tripped on overspeed but no trip alarm was received- Division 1 Post LOCA monitor automatically started- All SRV OPEN and CLOSED position indicating lights are out- PCIS Group 4 outboard valves automatically closedAs the Unit Supervisor; your FIRST priority is to direct the NSO to enter …

A. LOA-PC-101; Primary/Secondary Containment Trouble due to a Group 2 isolation.

B. LOA-PC-101; Primary/Secondary Containment Trouble due to a Group 4 isolation.

C. LOA-DC-101; Unit 1 DC Power System Failure due to loss of 112Y.

D. LOA-DC-101; Unit DC Power System Failure due to loss of 111 Y.

#13. Unit 1 is at rated conditions with NO LCO action statements in effect. Electrical maintenance has requested permission to de-energize the LPCS minimum flow valve in the closed position while they perform a required breaker inspection. Which of the following describes the shortest time clock that would be entered if you allowed the maintenance to start?Provide Tech Specs 3.5.1 ;3.6.1.1; and 3.6.3.

a. 1 hour

b. 4 hours

c. 12 hours

d. 7 days

#14. You have been performing the duties of the Field Supervisor for the first 4-hours of the shift when a casualty occurs and it is necessary for you to relieve the Unit Supervisor on the affected Unit. Which one of the following are REQUIRED to be performed prior to assuming command and control of the affected Unit during the casualty situation? 1. Review appropriate abnormal conditions and initiating events. 2. Review the current status of the EOP flowcharts. 3. Receive permission from the Shift Manager. 4. Turnover to another qualified Field Supervisor.

a. 1; 2; and 3 ONLY

b. 1; 2 and 4 ONLY

c. 1 and 3 ONLY

d. 2 and 3 ONLY

#15. Unit 2 is at 100% RTP: ‘A Reactor Recirc Flow Control Valve Locked-up for Maintenance Moments later On the DS001 Alarm Screen “TDRFP A/B Soft Trip” appears 2H13-P603-A409, Feedwater Control Reactor Water Level Low – Level 4 Annunciates 2C Motor Driven Reactor Feed Pump Starts Reactor Water Level is recovering(1) What condition caused the above alarm on the DS001?(2) What procedure will the Unit Supervisor direct as the highest PRIORITY?

A. (1) High Pressure Stop Valve and Low Pressure Stop Valve not full open and a Trip device in the tripped position(2) LOA-FW-201, Reactor Level/Feedwater Pump Control Trouble

B. (1) Greater than 60% mismatch between expected discharge flow and actual discharge flow for 3 seconds, provided there is no mismatch between total pump flow and total header flow.(2) LOA-FW-201, Reactor Level/Feedwater Pump Control Trouble

C. (1) High Pressure Stop Valve and Low Pressure Stop Valve not full open and a Trip device in the tripped position(2) LOA-RR-201, Unit 2 Reactor Recirculation System Trouble

D. (1) Greater than 60% mismatch between expected discharge flow and actual discharge flow for 3 seconds, provided there is no mismatch between total pump flow and total header flow.(2) LOA-RR-201, Unit 2 Reactor Recirculation System Trouble

#16. Unit 1 is at 100% power:if fuse 1D18-J013-F502 were to blow;(1) What annunciator will come in first?(2) What is/are the ODCM required action(s)?

A. (1 )1 N62-P600-B207 OFF-GAS POST TREATMENT RADIATION HIGH(2) Enter ODCM 12.2.2.A RA D.1 and D.2 and D.3

B. (1) 1N62-P600-B208 “OFF GAS POST-TREATMENT RADIATION TROUBLE”(2) Enter ODCM 12.2.2.A RA C.1

C. (1) 1N62-P600-B208 “OFF GAS POST-TREATMENT RADIATION TROUBLE”(2) Enter ODCM 12.2.2.A RA D.1 and D.2 and D.3

D. (1) 1N62-P600-B207 OFF-GAS POST TREATMENT RADIATION HIGH(2) Enter ODCM 12.2.2.A RA C.1

#17. Unit One is at rated condition. Provide T.S. 3.8.2.3 The DIV 2 125V DC BATT CHARGER TROUBLE alarm has come in. The Battery Charger voltage indicates 120 volts. Which of the following describes the impact this situation has on the continued operation of the plant?

a. Action must be taken within 1 hour to be in at least STARTUP within the next 6 hours; at least HOT SHUTDOWN within the following 6 hours and at least COLD SHUTDOWN within the subsequent 24 hours.

b. Action must be taken within 2 hours to be in at least STARTUP within the next 6 hours; at least HOT SHUTDOWN within the following 6 hours and at least COLD SHUTDOWN within the subsequent 24 hours.

c. The battery charger must be restored to operable status within 1 hour or the unit must be in at least HOT SHUTDOWN within the next 12 hours and COLD SHUTDOWN within the following 12 hours.

d. The battery charger must be restored to operable status within 2 hours or the unit must be in at least HOT SHUTDOWN within the next 12 hours and COLD SHUTDOWN within the following 24 hours.

#18. You are the Shift Manager with both Unit 1 and Unit 2 operating at rated conditions when an accident occurs on the refuel floor; resulting in the following conditions: – An ALERT has been declared due to damage to irradiated fuel and the loss of water level in the fuel pool. – The TSC is being staffed; however command and control has NOT been transferred from the Main Control Room. – A worker has been injured during the accident and has been verified to be located on the refuel bridge and has a high probability of survival if promptly treated for the injuries. – You have been requested to authorize an exposure of 27 Rem TEDE for two workers who have volunteered to rescue the injured person. – Rad Protection management personnel have reviewed the situation and recommend rescuing the injured worker. – The emergency workers have been properly briefed in the field; have acknowledged that they have volunteered and understand the associated risks; and are waiting in the reactor building for authorization to rescue the injured person. Which of the following statements is correct regarding your authorization of the request in compliance with EP-AA-113; Personnel Protective Actions and based on the given conditions?

A. You can authorize the request because command and control has not been transferred to the TSC.

B. You can authorize the request ONLY after obtaining approval from the Plant Manager because command and control has not been transferred to the TSC and Plant Manager concurrence is required.

C. You can NOT authorize the request because approval can only be granted by the Station Emergency Director and may not be delegated.

D. You can NOT authorize the request because the emergency workers will exceed the maximum allowable Emergency Exposure limit of 25 Rem TEDE.

#19. Given the following conditions: Reactor pressure is 800 psig and stable A LOCA with an ATWS is in progress Reactor water level is 12″ and stable Drywell temperature is 345F and rising Drywell pressure is 4 psig and rising Suppression Pool temperature is 190F and stable Suppression Pool level is +1 foot RR pumps are tripped 1A and 1 B RHR pumps are running in Suppression Pool cooling Which of the following actions will be directed next to control containment temperature?

A. Start Drywell Sprays

B. Blowdown per LGA-006; ATWS BLOWDOWN

C. Open Turbine Bypass Valves; OK to exceed 100F per hour

D. Perform LGA-VP-01; PRIMARY CONTAINMENT TEMPERATURE REDUCTION

#20. Unit 1 was operating at full power when a loss of feed occurred. All RPV Level 3 and Level 2actuations and isolations functioned as designed except the Standby Gas Treatment systemfailed to start. RCIC subsequently isolated due to a high RCIC room temperature; however;RCIC room temperature is now trending downward. Operators have determined that NO otheractuation or isolations signals currently exist.Select the statement below that correctly describes action(s) required to be directed by the UnitSupervisor in accordance with LGA-002; Secondary Containment Control:

a. Restart the Reactor Building Ventilation system.

b. Close the MSIVs and start MSIV Leakage Control.

c. Start the Primary Containment Purge system (aligned for Secondary Containment pressure control).

d. Rapidly depressurize the RPV; using the Main Turbine Bypass Valves; in anticipation of RPV Emergency Depressurization.

Results

#2. Given the following conditions: Unit-1 was at 100% power. ‘A’ IN Compressor is cross-tied to ‘B’ Dryer. Group 1 and Group 10 isolations were caused by an instrument failure. The Unit 1 Supervisor directs the LOCAL Operators to (1) IAW (2) .

#4. Unit 2 is in Hot Shutdown with the following conditions: Both of the running VR exhaust fans have tripped. Reactor building differential pressure is +0.01 inch H20. Which of the following is the overriding document for this situation?

#6. The Heat Capacity Temperature Limit (HCTL) is

#16. Unit 1 is at 100% power:if fuse 1D18-J013-F502 were to blow;(1) What annunciator will come in first?(2) What is/are the ODCM required action(s)?

#17. Unit One is at rated condition. Provide T.S. 3.8.2.3 The DIV 2 125V DC BATT CHARGER TROUBLE alarm has come in. The Battery Charger voltage indicates 120 volts. Which of the following describes the impact this situation has on the continued operation of the plant?