LaSalle SRO Quiz - ILTandMe

#1. Both units are at 100% power.The alternate RPS power supply is out of service for corrective maintenance.- 0830 on June 1, the underfrequency protection for one of the EPMAs on the 1A RPS MG Set is declared INOPERABLE.- 0930 on June 1, the undervoltage protection for one of the EPMAs on the 1B RPS MG Set is declared INOPERABLE.- The RPS Alternate Power Supply cannot be restored to serviceIncluding any extensions allowed by Technical Specifications, when must the 1A RPS MG Set EPMA be restored to OPERABLE status to prevent removing the EPMA from service OR entering a Condition requiring a shutdown?

A. 1030 on June 1

B. 0830 on June 4

C. 0930 on June 4

D. 0830 on June 5

#2. 10CFR50.54(X) Conditions of licenses and HU-AA-104-101; Procedure Use and Adherence; state; in part: ……. reasonable action that departs from a license condition or a Technical Specification in an emergency when this action is immediately needed to protect the public health and safety is permitted. These actions shall be:

A. Approved by a licensed SRO prior to taking the action.

B. Reported to the NRC within 15 minutes of the action being taken.

C. Approved by the Operations Director prior to the action being taken.

D. Performed immediately and approved by a licensed SRO when possible.

#3. LGA-009; Radioactivity Release Control has been entered due to an unisolable Main SteamSystem leak in the Turbine Building coupled with damaged fuel. The reactor is shutdown withall control rods fully inserted. Which of the following actions will most effectively minimize theradiation exposure to both onsite and offsite personnel?

a. Start MSIV Leakage Control.

b. Blowdown of the RPV using the ADS valves.

c. Ensuring that the Turbine Building HVAC system is in operation.

d. Rapid depressurization of the RPV using the Main Turbine Bypass Valves.

#4. (1) What caused the above condition?(2) Prior to restarting the VR fans, what action will be directed first by the Unit Supervisor?

A. (1) Loss of A RPS Bus(2) Bypass Main Steam Tunnel delta T trips per LOA-VR-101, UNIT 1 RECOVERY FROM A GROUP 4 ISOLATION OR SPURIOUS TRIP OF REACTOR BUILDING VENTILATION

B. (1) Loss of 111Y(2) Bypass Main Steam Tunnel delta T trips per LOA-VR-101 UNIT 1 RECOVERY FROM A GROUP 4 ISOLATION OR SPURIOUS TRIP OF REACTOR BUILDING VENTILATION

C. (1) Loss of A RPS Bus(2) Secure Standby Gas Treatment per LOP-VG-02, SHUTDOWN OF THE STANDBY GAS TREATMENT SYSTEM

D. (1) Loss of 111Y(2) Secure Standby Gas Treatment per LOP-VG-02, SHUTDOWN OF THE STANDBY GAS TREATMENT SYSTEM

#5. Per Tech Spec Bases; which of the following is the LOWEST reactor pressure and the LOWEST CRD Accumulator pressure at which CRD pump availability is NOT needed to ensure control rod scram insertion times? Reactor Accumulator Pressure Pressure

a. 800 psig 800 psig

b. 800 psig 940 psig

c. 940 psig 800 psig

d. 940 psig 940 psig

#6. Unit 1 is in Cold Shutdown and Unit 2 is at rated conditions – Bus 142Y is OOS for cleaning and inspection. – Fault on the ring bus results in a loss of all off-site power – Unit 2 trips due to the transient – 2A D/G failed to start; the other D/Gs operated as expected – Unit 2 SBGT received an initiation signal Assuming no operator action has been taken yet; the status of the Unit 1 and Unit 2 SBGT systems is ____(1)_; requiring you to direct an NSO to (2)_

A. (1) Unit 1 SBGT running and Unit 2 SBGT NOT running (2) VERIFY proper operation of Unit 1 SBGT.

B. (1) Unit 1 SBGT NOT running and Unit 2 SBGT running (2) VERIFY proper operation of Unit 2 SBGT.

C. (1) Unit 1 SBGT running and Unit 2 SBGT running (2) VERIFY proper operation of Unit 2 SBGT and SHUTDOWN Unit 1 SBGT.

D. (1) Unit 1 SBGT NOT running and Unit 2 SBGT NOT running (2) START the 2A DG; energize bus 242Y; and VERIFY proper operation of Unit 2 SBGT.

#7. Unit 2 has scrammed from 100% reactor power: Unit 2 RPV water level is STABLE at -80 inches with RCIC and HPCS injection maximized. Annunciator 2H13-P601-D102; RCIC VACUUM TANK PRESSURE HIGH; is in alarm. The Barometric Condenser Vacuum Pump is not running. (1) What would be the effect of continued RCIC operation? (2) What action will the Unit Supervisor direct?

A. (1) RCIC turbine shaft seal damage. (2) Secure RCIC.

B. (1) RCIC turbine shaft seal damage. (2) Continue to operate RCIC.

C. (1) Airborne contamination in the RCIC room. (2) Secure RCIC.

D. (1) Airborne contamination in the RCIC room. (2) Continue to operate RCIC.

#8. Following an event on Unit-1; the control room operators gather the followinginformation:- RB RCIC Room Area Radiation Monitor is pegged high- RB North HCU Area Radiation Monitor is pegged high- SBGT Area Radiation Monitor is reading 100 mrem/hr- RCIC has received an isolation signal however the isolation valves have failed to close- Unit-1 continues to operate in MODE 1The above conditions require a (1) because two (2) valuesfor the same parameter have been exceeded.

A. (1) manual scram (LGP-3-2) and blowdown (LGA-004 or LGA-006);(2) Max Safe

B. (1) unit shutdown (LGP-2-1);(2) Max Normal

C. (1) manual scram (LGP-3-2) and blowdown (LGA-004 or LGA-006);(2) Max Normal

D. (1) unit shutdown (LGP-2-1);(2) Max Safe

#9. Unit 2 is operating at rated power with the following conditions: – Primary Containment Vent Fan 2VP02CB is OOS. Primary Containment Vent Fan 2VP02CA trips. Which of the following describe the expected crew response to this event? Enter LGA-003…

a. immediately and start hydrogen and oxygen monitors.

b. immediately and start containment venting lAW LGA-VQ-02.

c. if Drywell temperature exceeds 135F on 2TR-CM037A or B. Then start hydrogen and oxygen monitors.

d. if Drywell temperature exceeds 135F on 2TR-CM037A or B. Then start containment venting lAW LGA-VQ-02.

#10. 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.

#11. A Unit 1 shutdown is in progress due to the following chemistry parameters which werereported approximately 6 hours ago. The plant was operating at 50% power prior tocommencing the shutdown. Reactor pH 8.8 Reactor Water conductivity 11 micromhos/cm Reactor Water chlorides 150 ppbSix hours later with the plant having just entered Mode 2; Chemistry reports the following: Reactor pH 6.5 Reactor Water conductivity 0.9 micromhos/cm Reactor Water chlorides 150 ppbWhich one of the following actions is required for these plant conditions?

a. Restore RCS Chemistry to within limits within 24 hours.

b. Restore RCS Chemistry to within limits within 48 hours.

c. Restore RCS Chemistry to within limits within 72 hours.

d. Be in Mode 3 in 12 hours and Mode 4 in 36 hours.

#12. 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

#13. 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.

#14. Authorization to receive radiological exposures in excess of 10CFR20 limits is the responsibility of the

a. Station Director

b. Recovery Manager

c. Com Ed Medical Director

d. Radiation Protection Director

#15. Unit 2 has scrammed and experienced a DBA LOCA. RPV pressure is 15 psig and going down slow.Based on the following indications; determine if adequate core cooling exists; and why

a. Does NOT exist. RPV water level is too low.

b. Does NOT exist. Core spray flow is too low for the indicated RPV waterlevel.

c. Does exist. RPV water level alone is high enough to ensure adequatecore cooling.

d. Does exist. Core spray flow and RPV water level are high enough to ensure adequate core cooling.

#16. Unit 1 has suffered a transient; which has resulted in RCIC tripping on low steam pressure. Drywell temperature is currently 310F and steady. Suppression Pool Level is +4.0 inches. 1A CRD Pump is running and the scram has not been reset. Vessel level dropped to – 135 inches and increasing 1 inch/min. on the wide range level instruments. Based on the above information; reactor vessel level instruments are (1) and (2) should be performed.

A. (1) NOT valid (2) LGA-001; RPV Control

B. (1) NOT valid (2) LGA-005; RPV Flooding

C. (1) valid (2) LGA-001; RPV Control

D. (1) valid (2) LGA-005; RPV Flooding

#17. The U-1 is at 8% Reactor Power with the mode switch in START-UP.An outboard containment isolation valve that is required to be operable in MODES1; 2; and 3; FAILED its stroke time testing. To comply with the associated LCO TS3.6.1.3 Primary Containment Isolation Valves; the inoperable valve has beenclosed and deactivated.After 6 hours maintenance has been completed and Post Maintenance Testing(PMT) requires the valve to be opened and timed closed.Which of the following actions is required to perform the PMT?

A. Enter LCO 3.0.3 complete the Post Maintenance Test; then exit LCO 3.0.3.

B. Prior to entering MODE 1; enter LCO 3.0.4; perform the Post Maintenance Testthen exit LCO 3.0.4.

C. Perform the electrical stroke timing ONLY if the valve is reclosed within 4 hours tocomply with Tech Specs 3.6.1.3 Primary Containment Isolation Valves.

D. Enter LCO 3.0.5; only for time required to prove Operability without furthermaintenance; then exit LCO 3.0.5.

#18. 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.

#19. Given the following: – At 12:00 the threshold value for an UNUSUAL EVENT was exceeded; with indication available in the main control room. – At 12:08 the threshold value for an ALERT was exceeded; with indication available in the main control room. – At 12:09 the Shift Emergency Director classified an UNUSUAL EVENT based on the associated main control room indication. – At 12:13; the Shift Emergency Director classified an ALERT EVENT based on the associated main control room indications. – At 12:18 the Shift Emergency Director notified the required agencies of the UNUSUAL EVENT. Based on the above conditions; which of the following identifies the latest time at which the State/Local notifications of the ALERT EVENT classification can be initiated and still meet notification requirements in accordance with EP-AA-111 Emergency Classification and Protective Action Recommendations and EP-AA-114 Notifications ?

A. 12:15

B. 12:23

C. 12:24

D. 12:28

#20. Unit 2 is operating at 100% power. HPCS inadvertently initiated and injected due to a contractor striking an instrument with a toolbox. HPCS secured per LOP-HP-04; Shutdown of High Pressure Core Spray System After An Automatic Initiation. This situation is&

A. NOT reportable.

B. Reportable per SAF 1.4.

C. Reportable per SAF 1.5.

D. Reportable per SAF 1.7.

Results