LaSalle 2008 NRC - ILTandMe

#1. Which of the following properly identifies the IRMs assigned to Activity Control Unit 1 in the RMCS rod block logic?

A. IRMs A; B; E; and F

B. IRMs C; D; G; and H

C. IRMs A; C; E; and G

D. IRMs B; D; F; and H

#2. The 1A Diesel Generator has just experienced the complete loss of pressure in Train A of the Starting Air system. Which of the following describes the starting capability of the 1A Diesel Generator in the described condition? The 1A Diesel Generator is . ………

A. NOT capable of starting due to a loss of Control Air pressure.

B. NOT capable of starting due to a loss of ALL Starting Air pressure.

C. capable of starting on a manual start signal ONLY.

D. capable of starting on a manual OR automatic start signal.

#3. BEFORE starting SBLC from Control Room Panel 1H13-P603; the reactor operator observed the following conditions: – ON light for 1C41-F004A; SBLC INJ SQUIB VLV was EXTINQUISHED – ON light for 1C41-F004B; SBLC INJ SQUIB VLV was LIT – Annunciator 1H13-P603 A105 SBLC SQUIB VLV CONTINUITY LOSS was LIT. Which of the following would cause these indications?

A. Loss of power from Bus 111Y

B. Loss of power from Bus 112Y

C. Loss of power from Bus 135X-1

D. Loss of power from Bus 136X-2

#4. 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.

#5. Unit 1 is in a maintenance outage that started 30 days ago. – The unit ran at 100 % for 90 days prior to the outage. – Reactor coolant temperature is currently 146 F and level is +50 inches. – A complete loss of shutdown cooling occurs. If conditions do NOT change; and based on the information provided in the graph below; Unit 1 will enter Mode 3 within ____________ hours.

A. 3 to 4 LOA-RH-101 Unit 1 RHR Abnormal; Att. A.

B. 5 to 6

C. 7 to 8

D. 9 to 10

#6. Concerning damage to plant components; the most limiting temperature concern related to the loss of the Reactor Closed Cooling Water system is the

A. Control Rod Drive pump bearings.

B. Reactor Water Clean Up Heat Exchanger tubes.

C. Reactor Recirculation pump motor windings.

D. Drywell Instrument Nitrogen compressors.

#7. Unit 1 reactor has scrammed from rated conditions. 6 SRVS opened on the initial transient and SRVs are cycling to control reactor pressure. Which of the following properly describes the response of the Unit 1 LLS logic to this event?

A. ONLY Division I LLS logic will be initiated.

B. ONLY Division II LLS logic will be initiated.

C. BOTH Division I and Division II LLS logic will be initiated.

D. NEITHER Division I or Division II LLS logic will be initiated.

#8. Unit 2 was at rated conditions when a transient occurred. A Group 1 isolation has automatically initiated. LOA-MS-201; Recovery from a Group 1 Isolation; directs that the Group 1 isolation be reset. Why are the control switches VERIFIED in the CLOSED position prior to DEPRESSING the Inboard and Outboard Isolation Reset Pushbuttons? Failure to place the MSIV control switches in the CLOSED position will result in ………………

A. the MSIVs going OPEN when the Inboard and Outboard Isolation Reset Pushbuttons are DEPRESSED.

B. the Group 1 Isolation logic NOT resetting when the Inboard and Outboard Isolation Reset Pushbuttons are DEPRESSED.

C. the MSIVs indicating OPEN after the Inboard and Outboard Isolation Reset Pushbuttons

D. a reset of the Group 1 Isolation logic when the Inboard and Outboard Isolation Reset Pushbuttons are DEPRESSED, followed immediately by the INITIATION of a new Group 1 isolation signal.

#9. Unit 2 has scrammed due to a transient. – RCIC is taking suction from the Suppression Pool and injecting into the RPV. – Suppression Pool level is -8 inches – Suppression Chamber pressure is 5 psig – Suppression Pool temperature is 215 F Which of the following could cause fluctuations in RCIC discharge pressure and flow indications?

A. Suppression pool temperature rising to 230F.

B. Suppression Pool level dropping to – 15 inches

C. Suppression Chamber pressure rising to 10 psig

D. Suppression Chamber pressure lowering to 3 psig

#10. Unit 1 is operating at 100% power when the RWLCS Trouble Alarm is received. A review of the 1DS001 Panel Event List indicates “Reactor Lev B NR Err.” How will the RWLC system respond to this condition?

A. The RWLC system will automatically transfer to the alternate B Narrow Range level transmitter.

B. The B Narrow Range Level signal is disregarded. When the B Narrow Range Level transmitter is repaired; the signal will be automatically reconnected.

C. The B Narrow Range Level signal is rejected. The RWLC system will calculate average level to be lower than actual causing level to increase to the level 8 Setpoint.

D. The B Narrow Range level signal is disregarded. When the B Narrow Range Level transmitter is repaired; the signal must be manually reconnected at the RWLC Operator Station.

#11. With the 1A RHR system operating in the LPCI injection mode; a TRIP of the Common Diesel Generator Cooling Water Pump will directly result in which of the following?

A. The A RHR pump room ambient temperature will be higher than expected due to the loss of cooling water to the area coolers.

B. The A RHR Pump seal temperatures will be higher than expected due to the loss of cooling water to the seal coolers.

C. The A RHR Pump Motor bearing temperatures will be higher than expected due to the loss of cooling water to the motor cooler.

D. The A RHR Pump bearing temperatures will be higher than expected due to the loss of cooling water to the pump bearing coolers.

#12. Unit 2 is starting up from a refueling outage; with the mode switch in START-UP and the IRMs on Range 7; when annunciator 2H13-P603-A106 SRM INOPERATIVE OR HI alarms. Which of the following accurately describes the expected automatic action(s) associated with this alarm?

A. INITIATES a 1/2 scram ONLY.

B. BLOCKS control rod withdrawal ONLY.

C. BLOCKS Control rod withdrawal and INITIATES a 1/2 scram.

D. NO expected automatic actions; alarm ONLY.

#13. Unit 1 has scrammed from rated conditions. – Reactor level is 25 inches and being controlled with the MDRFP. – Reactor pressure is 850 psig – RCIC is operating in the pressure control mode with the RCIC Pmp Dsch Flow Controller in AUTO with flow set at 600 GPM. The 1E51-F022; RCIC Full Flow Test Upstream Valve was throttled in the CLOSED direction (but not full closed) in several large increments to adjust system parameters. Which of the following describes the impact this action will have on the RCIC system?

A. RCIC pump discharge pressure will go down.

B. RCIC pump discharge pressure will go up.

C. RCIC pump discharge flow will stabilize at a lower value.

D. RCIC pump discharge flow will stabilize at a higher value.

#14. Unit-1 was operating at 100% reactor power when a LOCA occurred resulting in the following: – The reactor scrammed – RPV pressure has dropped to 480 psig – RPV level is -140 inches and steady – HPCS and RCIC are injecting to the RPV Based on these conditions; the LPCS Injection Valve is (1) and the LPCS Min Flow Valve is (2).

A. (1) OPEN and (2) OPEN

B. (1) OPEN and (2) CLOSED

C. (1) CLOSED and (2) OPEN

D. (1) CLOSED and (2) CLOSED

#15. Unit 1 is operating in a normal full power line-up; the following two alarms were just received: – 1H13-P603-A511; RWLCS TROUBLE – 1DS001 SCS A/B PS 1 Fault Based on these alarms; the Turbine Driven Reactor Feedwater Pumps will ___(1)_; and an equipment operator must be directed to inspect the _(2)___ Uninterruptible Power Supply.

A. (1) continue to operate in 3-element automatic (2) Process Computer

B. (1) continue to operate in 3-element automatic (2) Technical Support Center

C. (1) be required to be transferred to the manual back-up stations (2) Process Computer

D. (1) be required to be transferred to the manual back-up stations (2) Technical Support Center

#16. The following conditions exist on Unit-2: – The desiccant in the Unit-2 Station Air Dryer 2SA02D was replaced and the dryer placed on line. – Annunciator 2PM10J-B105 U2 STA AIR DRYER TROUBLE is in alarm due to R-point R1419; U2 STA AIR DRYER HUMIDITY HI. Which of the following correctly identifies: (1) The impact this condition will have on the IA system; and (2) the actions to be taken based on the above conditions?

A. (1) Moisture in the IA system will result in the corrosion of IA piping. (2) DE-ENERGIZE Unit-2 Station Air Dryer Control Power at MCC 231A-1; Comp. E-1 to automatically place both drying towers in service. CONTACT System Engineering to PERFORM Dew Point Checks to DETERMINE additional actions.

B. (1) Moisture in the IA system will adversely affect the operation of supported components. (2) Track the length of time the Dryer humidity alarm is up solid. If the alarm is up solid longer than 24 hours; STARTUP a Standby Dryer if available; and SHUTDOWN the Unit-2 Station Air Dryer.

C. (1) Moisture in the IA system will plug the downstream filters; reducing system pressure. (2) As soon as plant conditions allow; STARTUP a Standby Dryer if available; and SHUTDOWN the Unit-2 Station Air Dryer.

D. (1) Moisture in the IA system will cause carryover of desiccant fines into the IA piping. (2) INCREASE Unit-2 Station Air Dryer purge flow from normal setting of 58 psig to 68 psig. CONTACT System Engineering to PERFORM Dew Point Checks to DETERMINE additional actions.

#17. Unit 1 has scrammed from rated conditions due to a loss of offsite power. The following conditions exist at time zero: – All emergency diesel generators started and energized their respective emergency bus. – The reactor is shutdown. – Drywell pressure is 2.0 psig; going up at 0.25 psig per minute – Reactor pressure is 460 psig; going down 8 psig per minute. – Reactor water level just fell to the Level 1 setpoint; going down at 2 inches per minute. – All low pressure ECCS pumps are running. – RCIC has tripped. – HPCS has tripped. Which one of the following describes the response of the Automatic Depressurization System (ADS) if plant conditions remain as stated and no operator action is taken?

A. ADS will NOT automatically initiate.

B. ADS will automatically initiate in 1 minute and 45 seconds.

C. ADS will automatically initiate in 9 minutes and 58 seconds.

D. ADS will automatically initiate in 11 minutes and 43 seconds.

#18. Unit 1 has scrammed from rated conditions and a normal plant line-up. Following the scram; RPV level dropped below Level 2; and then recovered. RPV level has exceeded the Level 8 setpoint and is going up slowly. Which of the following describes the current status of the HPCS system if no operator actions have been taken regarding HPCS operation? HPCS Pump Injection Valve Minimum Flow Valve

A. RUNNING OPEN CLOSED

B. RUNNING CLOSED OPEN

C. OFF CLOSED CLOSED

D. OFF CLOSED OPEN

#19. Unit 2 has scrammed from rated conditions. – There is a small leak in the DRYWELL. – DRYWELL pressure indication is unavailable – There is no indication of a bypass path in the containment. – SUPPRESSION CHAMBER pressure is 1.2 psig Based on the above information; DRYWELL pressure is approximately ___(1)_ AND Stand-by Gas Treatment _(2)___ have auto-started.

A. (1) 1.2 psig (2) should

B. (1) 6.2 psig (2) should

C. (1) 1.2 psig (2) should NOT

D. (1) 6.2 psig (2) should NOT

#20. Which of the following statements accurately describes the status of the Division 1 ARI system as depicted in the ARI display above? (Large; italicized letters indicate the tile or device is LIT; all other tiles or devices are NOT LIT.)

A. Manually initiated less than two minutes ago.

B. Manually initiated more than two minutes ago.

C. Automatically initiated less than two minutes ago.

D. Automatically initiated more than two minutes ago.

#21. Unit 1 and Unit 2 are both operating at rated conditions and Annunciators 1PM01J – A310 and A414 just alarmed. Based on the above indications; the operating crew will be required to enter ……………

A. LOP-DC-02; DC System Unit Tie Operations and LGP 3-1; Power Changes.

B. LOP-DC-02; DC System Unit Tie Operations and LGP 3-2; Reactor Scra

C. LOA-DC-101; Unit 1 DC Power System Failure and LGP 3-1; Power Changes.

D. LOA-DC-101; Unit 1 DC Power System Failure and LGP 3-2; Reactor Scram.

#22. Line L0101 has to be isolated for maintenance. This will require isolating Bus __ (A) _ in the Unit (B) ___ Ring Bus.

A. (A) Nine (9) (B) One (1)

B. (A) Four (4) (B) One (1)

C. (A) Two (2) (B) Two (2)

D. (A) Eleven (11) (B) Two (2)

#23. (WHITE lights indicate illuminated; GRAY lights indicate extinguished) With the APRM Meter Function Switch in the COUNT position; APRM channel C meter will indicate (1) _; and the associated INOP light (2) _ be illuminated.

A. (1) 65% (2) SHOULD

B. (1) 65% (2) SHOULD NOT

C. (1) 70% (2) SHOULD

D. (1) 70% (2) SHOULD NOT

#24. Unit 1 has scrammed from rated conditions due to a feedwater break in the drywell. – All control rods have fully inserted. – RPV pressure is 650 psig and going down slowly – RPV level is -120 inches and going down slowly – DW pressure is 20 psig and steady – HPCS is OOS – RCIC tripped on overspeed and won t reset. The bus feed breaker for 125V DC Bus 111Y tripped open during the transient and will not reclose. The Unit 1 Assist NSO has just opened all Main Turbine Bypass Valves in anticipation of an RPV Blowdown. If conditions for automatic initiation of ADS are met; which of the following describes: (1) The response of the ADS SRVs; AND (2) What action; if any; required to be taken with the Main Turbine Bypass Valves?

A. (1) ADS valves will open automatically (2) Main Turbine Bypass Valves must be CLOSED.

B. (1) ADS valves will NOT open automatically. (2) Main Turbine Bypass Valves must be CLOSED

C. (1) ADS valves will open automatically. (2) No action is required to be taken with the Main Turbine Bypass Valves

D. (1) ADS valves will NOT open automatically. (2) No action is required to be taken with the Main Turbine Bypass Valves

#25. Which of the following describes the component in the SBGT system designed to remove entrained water droplets in the air being passed through the system?

A. Electric Heater

B. Rough Prefilter

C. Demister

D. HEPA Pre-Filter

#26. Unit 1 is operating at rated conditions when a feedwater transient occurs. – The M/A Transfer Stations for BOTH Turbine Driven Reactor Feedwater Pumps (TDRFP) are placed in manual. – RPV level is just above 50 inches on the Narrow Range Level indicators (NR) and going up slowly. – The Reactor Operator is adjusting the M/A stations to control feedwater flow and reports that level will peak at approximately 51 inches on NR. In accordance with the guidance of LOA-FW-101; Reactor Feedwater Pump Control; the reactor operator is directed to. . . . .

A. REDUCE reactor power.

B. INSERT a manual scram.

C. MATCH steam flow and feed flow.

D. PLACE the TDRFP back-up controllers in service.

#27. Unit 2 has scrammed from rated conditions due to a spurious Group 1 isolation signal. The plant has responded as designed. Reactor pressure peaked at 1091 psig; dropped to a low of 850 psig and is currently at 1050 psig. Which of the following properly describes the response of the Unit 2 SRVs to this transient?

A. SRVs initially opened in Safety mode; closed at their LLS closure setpoints; and are currently controlling pressure in LLS mode.

B. SRVs initially opened in Safety mode; closed at 3% below their Safety mode lift setpoints; and are currently controlling pressure in LLS mode.

C. SRVs initially opened in Relief mode; closed at their LLS closure setpoints; and are currently controlling pressure in LLS mode.

D. SRVs initially opened in Relief mode; closed at 100# below their Relief mode lift setpoints; and are currently controlling pressure in LLS mode.

#28. Unit 2 is operating at rated conditions with the following line-up of the Condensate/Condensate Booster (CD/CB) pumps: – A ; B ; and D Condensate/Condensate Booster (CD/CB) pumps are on line – C Condensate/Condensate Booster (CD/CB) pump is OOS and unavailable Which of the following describes the expected response of the Unit 2 CD/CB Pumps and Reactor Feedwater Pumps if an electrical fault results in the lockout and de-energization of Bus 252?

A. ONLY A CD/CB Pump trips and NO Reactor Feedwater Pump trips.

B. ONLY B CD/CB Pump trips and NO Reactor Feedwater Pump trips.

C. B and D CD/CB Pumps trip and ALL Reactor Feedwater Pumps trip.

D. A and B CD/CB Pumps trip and ALL Reactor Feedwater Pumps trip.

#29. Unit 1 has been manually scrammed from rated conditions due to a steam leak in the drywell. – RPV level is 25 inches and steady. – Drywell pressure is 21.5 psig – Drywell temperature is 232 F – Suppression Chamber pressure is 16 psig – Suppression Chamber temperature is 216 F – Suppression Pool Water Temperature is 115 F – 1A RHR/RHR WS is running in the Suppression Chamber Spray and Suppression Pool Cooling modes of operation. – 1B RHR is running in the Drywell Spray mode of operation. – Reactor pressure is at 600 psig and going down at 50 psig per minute Which of the following properly describes how containment parameters will be effected within the next three minutes? Assume no manual actions are taken related to the operation of the 1A and 1B RHR system components.

A. Drywell air temperature will rise due to the closure of 1E12-F016B; 1B RHR DW Spray Upstream Isol.

B. Drywell pressure will rise due to the closure 1E12-F017B; 1B RHR DW Spray Downstream Isol.

C. Suppression Chamber air temperature will rise due to the closure of valve 1E12-F027A; 1A RHR SP Spray Isol.

D. Suppression Pool water temperature will rise due to the opening of valve 1E12-F048A; 1A RHR Hx Bypass Vlv.

#30. A LOCA is in progress; with the following: – All drywell vacuum breakers have failed to open; when required. Which one of the following identifies the containment failure mechanism that can result from the vacuum breaker failures?

A. Excessive inward pressure on the Drywell wall.

B. Excessive upward pressure on the Drywell floor.

C. Excessive downward pressure on the Drywell floor.

D. Excessive inward pressure on the Suppression Pool wall.

#31. Which of the following recorders and/or indicators are supplied input from instruments designed to provide accurate RPV level in the event that rapid depressurization of the RPV occurs?

A. Upset Level recorder on the 1(2)H13-P603 panel

B. Narrow Range Level indicators and recorder on the 1(2)H13-P603 panel

C. Wide Range Level indicators and recorders on the 1(2)H13-P601 and 1(2)H13-P603 panels

D. Shutdown Range Level indicator on the 1(2)H13-P602 panel and Upset Range Level recorder on the 1(2)H13-P603 panel.

#32. A precaution in LOP-TG-02; Turbine Generator Startup warns that Operation of the main turbine generator while above a frequency of 60.5 Hz or below a frequency of 59.5 Hz will cause damage to which of the following?

A. Turbine Blades

B. Generator Stator

C. Generator Rotor Windings

D. Low Pressure Turbine Bearings

#33. Given the following plant conditions: – Unit-1 is starting up; with reactor power at 4%. – Control rods are being withdrawn per LOP-RM-01 – The NSO selects rod 18-31 – Rod 18-31 shows a red double question mark ( ?? ) on the RWM Display Screen Based on the above information; ………

A. Rod 18-31 is identified as a “Selection Error”. Rod 18-31 is outside of the latched step of the normal sequence and rod blocks are enforced to prevent ALL movement.

B. Rod 18-31 is identified as a “Selection Error”. Rod 18-31 is outside of the latched step of the normal sequence and rod blocks are enforced to prevent withdrawal ONLY.

C. Rod 18-31 position is “Unknown; (Bad)”. The rod will be treated as a withdrawal error and must be corrected before proceeding further into the normal sequence.

D. Rod 18-31 position is “Unknown; (Bad)”. The rod will be restricted to a maximum of one notch in the withdraw direction while proceeding further into the normal sequence.

#34. Unit 1 is currently at 90% reactor power with surveillance LOS-RD-SR7 “Channel Interference Monitoring” in progress. Alarm 1H13-P603; A406; RBM HI/INOP has just illuminated due to the 1A RBM generating a valid “Failure to Null” signal. This condition will result in a ___(1) _ requiring _(2) ___ before continuing with the surveillance.

A. (1) rod insert and withdrawal block (2) bypassing the 1A RBM at panel 1H13-P603

B. (1) rod withdrawal block ONLY (2) bypassing the 1A RBM at panel 1H13-P603

C. (1) rod insert and withdrawal block (2) placing the 1A RBM Mode Switch in “STANDBY” at panel 1H13-P608

D. (1) rod withdrawal bock ONLY (2) placing the 1A RBM Mode Switch in “STANDBY” at panel 1H13-P608

#35. A reactor startup is in progress; with the following: – Reactor power is currently on Range 3 of the Intermediate Range Monitoring system – Control rod 30-31 is the next control rod to be moved AND it is currently at notch position 12. Following the selection of control rod 30-31; the “ACTIVITY CONTROLS DISAGREE” light on the Rod Select Module illuminates; and remains LIT. Based on the above condition; which one of the following describes the ability to move the control rod? Using Reactor Manual Control System; control rod 30-31 can be………

A. inserted only.

B. withdrawn only.

C. inserted or withdrawn.

D. neither inserted nor withdrawn.

#36. 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.

#37. The RR Flow Control valves provide a means of controlling reactor power from (1) and varying Reactor Recirculation flow from (2) of rated.

A. (1) 0 – 100% (2) 0 – 100%

B. (1) 0 – 100% (2) 25 – 100%

C. (1) 60 – 100% (2) 0 – 100%

D. (1) 60 – 100% (2) 25 – 100%

#38. Unit 1 is operating at rated conditions when an earthquake occurs – A circumferential rupture of the 1A RR pump discharge pipe immediately upstream of the 1B33-F067A; 1A RR PMP DSCH VLV develops. – The breaker to the 1A 1B33-F067A; 1A RR PMP DSCH VLV trips OPEN; de-energizing the valve. With all other systems and components responding as designed to the accident; . . ..

A. the drywell internal pressure design limit will be exceeded.

B. no primary containment design limit will be exceeded.

C. the primary containment temperature design limit will be exceeded.

D. the downward loading of the drywell floor design limit will be exceeded.

#39. The calculation of Maximum Subcritical Banked Withdrawal Position extends the shutdown rod pattern; which meets the Tech Spec calculation for shutdown margin; to the _____(1)_ most reactive rod(s) fully withdrawn and all other control rods inserted to at least position _(2)_____.

A. (1) one (2) 00

B. (1) one (2) 02

C. (1) two (2) 00

D. (1) two (2) 02

#40. Unit 2 is at rated condtions when the #1 Turbine Control Valve drifts CLOSED. In response to the event; REACTOR power will initially (1); followed by (2)_

A. (1) RISE (2) ONLY #2 Turbine Control Valve going OPEN.

B. (1) RISE (2) the remaining Turbine Control Valves and/or Turbine Bypass Valves going OPEN

C. (1) LOWER (2) ONLY #2 Turbine Control Valve going OPEN.

D. (1) LOWER (2) the remaining Turbine Control Valves and/or Turbine Bypass Valves going OPEN.

#41. During the actions in the LGA-010; Failure to Scram ; Level leg; reactor water level is lowered to – 60 to – 100 inches in order to __(1)_ and after hot shutdown boron weight is added level is raised in order to (2)__.

A. (1) void the core to minimize power generation and reduce heat rate to the suppression pool (2) promote mixing of the boron throughout the core

B. (1) trip Recirculation Pumps to minimize power generation and reduce heat rate to the suppression pool (2) allow MSIV s to be reopened to commence a normal Cooldown

C. (1) promote concentrating boron in the high power areas of the core (2) promote mixing of the boron throughout the core

D. (1) widen the pressure band for using SRV s and RCIC to maintain reactor pressure band (2) allow MSIV s to be reopened to commence a normal Cooldown

#42. There is a fire in the 0A Control Room HVAC Emergency Make-up Train charcoal bed. Which of the following properly describes all of the actions required to deluge the charcoal bed?

A. 1) OPEN the Manual Deluge Stop Valves; and then 2) ACTUATE the FP system from the main control room. If unable to actuate from the main control room; then ACTUATE at the Aux. Electric Equipment Room.

B. 1) Locally CLOSE the Manual Deluge Leakoff Line Stop Valve; and then 2) ACTUATE the FP system from the main control room. If unable to actuate from the main control room; then ACTUATE locally at the train.

C. 1) Locally CLOSE the Manual Deluge Leakoff Line Stop Valve; 2) OPEN the Manual Deluge Stop Valves; and then 3) ACTUATE the FP system from the main control room. If unable to actuate from the main control room; then ACTUATE at the Aux. Electric Equipment Room.

D. 1) Locally CLOSE the Manual Deluge Leakoff Line Stop Valve; 2) OPEN the Manual Deluge Stop Valves; and then 3) ACTUATE the FP system from the main control room. If unable to actuate from the main control room; then ACTUATE locally at the train.

#43. Unit 2 was operating at rated conditions when a loss of Suppression Pool integrity resulted in a rapid lowering of Suppression Pool level. The Unit 2 reactor was scrammed and LGA-001; RPV Control and LGA-003; Primary Containment Control were entered. Which of the following identifies the action to be taken; and why; if Suppression Pool level drops to -12.5 feet?

A. INITIATE ADS to minimize the effects of chugging on the Primary Containment.

B. PREVENT all heat input into the Suppression Pool to ensure Heat Capacity Limit is NOT exceeded.

C. INITIATE ADS due to inability to condense steam discharged from the RPV into the drywell during a LOCA.

D. INHIBIT ADS to prevent direct pressurization of the Primary Containment from the SRV T- quenchers.

#44. Unit 1 and Unit 2 are operating at rated conditions when a grid disturbance results in reduced voltage being supplied to the ESS busses; and LOA-AP-101; Unit 1 AC Power Abnormal is entered. If ESS bus voltage cannot be restored to normal; direction is provided to . . . .

A. MANUALLY OPEN the normal supply breakers to the affected bus if voltage is < 3120 volts for one minute to protect large motors supplied by the bus.

B. MANUALLY START and LOAD the associated emergency diesel generator onto the bus if voltage is < 3868 volts for 3 minutes to prevent further degradation of the bus.

C. PLACE the associated emergency diesel generator supply breaker in Pull – to – Lock if voltage is < 3120 volts for one minute to prevent the automatic start and loading of the diesel generator onto a degraded bu

D. MANUALLY OPEN the normal and diesel generator supply breakers to the bus if voltage is < 3868 volts for 3 minutes to prevent damage to the diesel generator when starting with no ECCS initiation signal present.

#45. Which of the following identifies the reason that the Unit-1 reactor will automatically scram as a result of the simultaneous loss of 111Y and 112Y?

A. De-energizes both backup scram valves.

B. De-energizes control power to both TDRFPs.

C. De-energizes both divisions of isolation logic.

D. De-energizes both divisions of ARI initiation logic.

#46. Unit 2 is at rated conditions with the 2B Drywell Instrument Nitrogen Compressor out of service for maintenance; when the 2A Drywell Instrument Nitrogen Compressor trips due to a mechanical failure. The Assist NSO opens the Unit 2 Instrument Air to Drywell Pneumatics Cross-tie valves 2IN059 and 2IN060 in response to the event. Which of the following describes the loads picked up by the Instrument Air system following the opening of the cross-tie valves with all other components in the Instrument Nitrogen system responding as designed? The Instrument Air system will pick up loads supplied by . .

A. the regulated Instrument Nitrogen supply line to the drywell ONLY.

B. the unregulated Instrument Nitrogen supply line to the drywell ONLY.

C. BOTH the regulated and unregulated Instrument Nitrogen supply lines to the drywell.

D. BOTH the regulated and unregulated supply lines to the drywell; EXCEPT TIP Purge.

#47. A failure to scram has occurred and the crew is taking actions per LGA-010; Failure to Scram . The following conditions exist: – RPV pressure being maintained 800-1000 psig with SRVs – Rods are being inserted manually; 6 rods still at position 48 – Hot Shutdown Boron has been injected into the RPV Based on the above; the reactor ………

A. is shutdown and cooldown may now commence.

B. is not shutdown since more than one rod is not fully inserted.

C. will not be shutdown until the Cold Shutdown Boron Weight has been injected.

D. is shutdown and will remain shutdown if pressure is maintained within current limits.

#48. Unit 2 was at rated conditions when the 2A RR Pump inadvertently downshifted to slow speed. At the time of the event; both Recirculation Loop Flow Controller M/A stations were in the Loop Auto Mode of operation. The 2B RR Pump remained running in high speed following the downshift of the 2A RR Pump. Assuming no operator actions; which mode of operation are the Recirculation Loop flow controller M/A stations expected to be in?

A. BOTH 2A and 2B Recirculation Loop Flow Controller M/A stations in Loop Auto mode of operation.

B. BOTH 2A and 2B Recirculation Loop Flow Controller M/A stations in Loop Manual mode of operation.

C. 2A Recirculation Loop Flow Controller M/A station in Loop Manual mode and the 2B Recirculation Loop Flow Controller M/A station in Loop Auto.

D. 2B Recirculation Loop Flow Controller M/A station in Loop Manual mode and the 2A Recirculation Loop Flow Controller M/A station in Loop Auto.

#49. Unit 2 has scrammed from rated conditions. – A small high pressure steam leak in the drywell has caused drywell temperature to rise to 320F and continues to go up. – Drywell pressure is 20 psig and going up slow. Following the initiation of drywell sprays; drywell pressure is expected to have a. ..

A. slow; steady drop due to convective cooling

B. slow; steady drop due to evaporative cooling.

C. rapid; large reduction due to convective cooling.

D. rapid; large reduction due to evaporative cooling.

#50. LOA-AP-101; Unit 1 AC Power System Abnormal directs which of the following indications for use when monitoring RPV level in the control room?

A. A; B; and C Narrow Range Indicators

B. A and B Narrow Range Indicators ONLY

C. A and C Narrow Range Indicators ONLY

D. B and C Narrow Range Indicators ONLY

#51. Given the following initial conditions: – Unit-1 is shutdown – Reactor Coolant temperature is 170 F – 1B RHR is in shutdown cooling mode with 5600 gpm flow – 1E12-F003B; B RHR Hx Outlet Vlv is FULL OPEN – 1E12-F048B; B RHR Hx Bypass Vlv is FULL CLOSED – Both RR Pumps are OOS for motor bearing inspections – RPV water level is being maintained at +40 to +45 inches on the Shutdown Range For the given conditions; why is it necessary to increase 1B RHR Pump flow to above 6000 gpm by throttling OPEN the 1E12-F053B; B RHR Shtdn Clg Return Isol.?

A. To prevent vibration of the jet pumps.

B. To prevent cavitation in the jet pumps.

C. To prevent excessive temperature stratification within the reactor vessel.

D. To raise reactor vessel water level above +50 inches on the Shutdown Range.

#52. 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)

#53. The Unit-1 Standby Gas Treatment (SBGT) system is out of service. The Unit-2 SBGT system is available. Which one of the following would be an issue if the Unit-2 SBGT system would become inoperable? The inability to …

A. monitor Refuel Floor radiation levels.

B. maintain negative pressure in the Primary Containment.

C. provide a controlled release path during a fuel handling accident.

D. provide pressure control between clean and contaminated areas within the reactor building.

#54. Which of the following identifies an instrument used to monitor for a high off-site release rate and how it is identified per Regulatory Guide 1.97 Post Accident Instrumentation?

A. SBGT WRGM EFF ACT identified by a BLACK dot.

B. SBGT WRGM CHAN ACT identified by a LGA stick

C. STACK WRGM EFF ACT identified by an ORANGE label with BLACK lettering.

D. STACK WRGM CHAN ACT identified by a PURPLE label with WHITE lettering.

#55. Unit 2 has scrammed. – Drywell pressure is 5.6 psig and going up slowly. – Suppression Pool Temperature is 107 F and going up slowly. The Unit Supervisor has directed the U-2 Assist NSO to START all available pool cooling per LGA-RH-203; Unit 2 A/B RHR Operations In the LGAs/SAMGs”. Per direction provided in the Strategies for Successful Transient Mitigation; the NSO is . .

A. required to request Unit Supervisor permission to use the LGA-RH-203 Hard Card to start all available pool cooling.

B. authorized to start all available pool cooling using the LGA-RH-203 Hard Card without requesting Unit Supervisor permission.

C. authorized to start all available pool cooling in a transient condition WITHOUT referencing procedure LGA-RH-203 or the LGA-RH-203 Hard Card.

D. required to have procedure LGA-RH-203 OPEN and AVAILABLE for reference prior to using the LGA-RH-203 Hard Card to start all available pool cooling.

#56. Unit-1 has scrammed from rated power with the following conditions: – Drywell pressure is 2.1 psig and rising due to a small coolant leak – Drywell temperature is 175F and rising slowly – RPV level dropped to -25 inches and is now rising – All control rods are at position 00 EXCEPT control rod 26-35 which is at position 48 Which of the following lists the MINIMUM set of actions to be completed?

A. Enter LGA-001; Reactor Pressure Vessel Control and VERIFY RCIC initiated.

B. Enter LGA-002; Secondary Containment Control; and VERIFY Reactor Building Ventilation has isolated.

C. Enter LGA-003; Primary Containment Control and VERIFY ECCS systems have initiated.

D. Enter LGA-010; Failure to Scram and INITIATE ARI.

#57. Given a DBA LOCA and high suppression pool temperature; which of the following identifies the MAXIMUM amount of time available to start all available Suppression Pool Cooling and still meet the FSAR assumptions?

A. 10 minutes

B. 15 minutes

C. 20 minutes

D. 30 minutes

#58. The plant is operating at 22% power; with the Feedwater heaters on-line; when a failure causes a main turbine trip. Which of the following is correct for this condition?

A. Feedwater temperature remains constant.

B. The reactor scrams from the main turbine trip.

C. Reactor power goes up due to a decrease in feedwater temperature.

D. Reactor power goes down due to an increase in feedwater temperature.

#59. Which of the following interlocks was established to ensure adequate Net Pump Suction Head is maintained to the Reactor Recirculation Pumps?

A. Low Reactor Water Level; Level 2.

B. Low Reactor Water Level; Level 3.

C. Low Feedwater Flow; < 20% Rated Feedwater Flow.

D. Steam dome to Reactor Recirculation Suction dT < 10.1F.

#60. Unit 1 is in an ATWS condition. – RPV pressure is 935 psig – 8 Control Rods did NOT fully insert – All scram solenoid group lights are EXTINGUISED – 1H13-P613-A102; SCRAM PILOT VLV AIR HDR PRESS LO is LIT – All Scram Valve lights are LIT – CRD drive water pressure is 320 psid Which method and associated action(s) should be performed first to insert control rods in accordance with LGA-NB-01; Alternate Rod Insertion ?

A. Method 1; Fuse Removal

B. Method 2; Depressurizing Scram Air Header

C. Method 3; Single Rod Insert (bypass the RWM if required)

D. Method 5; Venting CRD Withdraw Line

#61. Main Steam Tunnel temperatures and pressures are rising due to steam leak in the tunnel. As Main Steam Line Tunnel pressure rises; the low pressure blowout panels will actuate relieving pressure to the (1) resulting in (2) release to the environment.

A. (1) Turbine Building; (2) a monitored

B. (1) Turbine Building; (2) an UNMONITORED

C. (1) Auxiliary Building Roof; (2) a monitored

D. (1) Auxiliary Building Roof; (2) an UNMONITORED

#62. The unit has scrammed and RCIC is being used to maintain RPV level. The RCIC controller is in MANUAL and the operator has just adjusted the controller to establish 450 gpm to the RPV. Assuming no operator action; how will RCIC operation be affected if RPV pressure rises from 750 to 950 psig?

A. RCIC pump flow and RCIC Turbine speed will both rise.

B. RCIC pump flow and RCIC Turbine speed will both remain the same.

C. RCIC pump flow will go up and RCIC Turbine speed will remain the same.

D. RCIC pump flow will go down and RCIC Turbine speed will remain the same.

#63. 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

#64. Given the following plant conditions: After a scram; 12 control rods are at notch position 48 – ARI was initiated 15 minutes ago – BOTH CRD pumps are tripped and will NOT restart – RPS sub-channels are de-energized and CANNOT be reset – A fire has destroyed both RPS power supply cabinets – RPV pressure is 920 psig 1) What action is directed to be taken for the given conditions to insert the 12 control rods currently at notch position 48? 2) What is the operational effect resulting from the action taken?

A. 1) PLACE the individual CRD SRI-TEST-NORM switches to TEST. 2) OPENS the individual CRD s scram valves.

B. 1) VENT and REMOVE the CRD HCU Air Supply Filter 2) DEPRESSURIZES the Scram Air Header to OPEN all scram valves.

C. 1) RESET ARI; and then INSERT individual control rods using RMCS. 2) CLOSES all scram valves; allowing RMCS to INSERT individual control rods.

D. 1) Manually VENT the individual CRD withdrawal lines. 2) VENTS the individual CRD s overpiston area.

#65. 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 these conditions?

A. Upon receipt of the High Suppression Pool Water Level alarm; 2E51-F010; RCIC PMP SUCT From CY Tank Valve will close; and then 2E51-F031; RCIC PMP SUCT From SP Valve will open.

B. Upon receipt of the High Suppression Pool Water Level alarm; 2E51-F031; RCIC PMP SUCT From SP Valve will open; and then 2E51-F010; RCIC PMP SUCT From CY Tank Valve will close.

C. RCIC suctions will remain in standby configuration until a low CY Tank Level condition occurs. The RCIC suctions will then transfer with 2E51-F031; RCIC PMP SUCT From SP Valve opening; followed by the 2E51-F010; RCIC PMP SUCT From CY Tank Valve closing.

D. RCIC suctions will remain in standby configuration until a low CY Tank Level condition occurs. The RCIC suctions will then transfer with 2E51-F010; RCIC PMP SUCT From CY Tank Valve closing followed by the 2E51-F031; RCIC PMP SUCT From SP Valve opening.

#66. Unit 1 was just scrammed in accordance with LGP 2-1; Normal Unit Shutdown; as part of a controlled shutdown for a refueling outage. The RPV Pressure bar on the SPDS display just turned blue. This indicates which one of the following?

A. Reactor Pressure Vessel pressure is below the low alarm point.

B. Reactor Pressure Vessel pressure is above the high alarm point.

C. Reactor Pressure Vessel pressure is NOT being monitored by a sufficient number of required operable instrument channels.

D. Reactor Pressure Vessel pressure was above the high or below the low alarm setpoint; and has now returned to normal.

#67. Unit 2 is in a refueling outage. – Fuel removal from the reactor core is in-progress. – You are the NSO in the Unit 2 control room; in communication with the required personnel; using the primary means of communication identified in B.3.9 “Refueling Operations”; B.3.9.b “Communications”. – For an unknown reason the primary means of communication FAILS. Which of the following describes; 1) the actions required to be taken and 2) the communication link that failed?

A. 1) Within 1 hour restore direct communications with personnel located on the refueling platform. If not restored within 1 hour; suspend core alterations. 2) Dedicated GAI-tronics PA system

B. 1) Within 1 hour restore direct communications with personnel located on the refueling platform. If not restored within 1 hour; suspend core alterations. 2) Dial telephone system

C. 1) Core alterations must be suspended immediately. Direct communication with personnel located on the refueling platform must be established before core alterations can continue. 2) Dedicated GAI-tronics PA system

D. 1) Core alterations must be suspended immediately. Direct communication with personnel located on the refueling platform must be established before core alterations can continue. 2) Dial telephone system

#68. Unit 2 is at rated conditions. – A Division 3 work week is in-progress. – Electricians are scheduled to replace the HPCS Pump control switch at panel 2H13-P601. In accordance with OP-AA-103-101; Control Room Access Control; to gain access to the 2H13-P601 panel the electricians must gain permission from . . . . . ?

A. the WEC supervisor to enter the Control Room; and the Unit Supervisor to conduct business upon entering the Control Room; and the Reactor Operator to enter the zone of control.

B. ONLY the WEC supervisor to enter the Control Room; and the Unit Supervisor to conduct business upon entering the Control Room.

C. ONLY the WEC supervisor to enter the Control Room; and the Reactor Operator to enter the zone of control.

D. ONLY the Unit Supervisor to conduct business upon entering the Control Room; and the Reactor Operator to enter the zone of control.

#69. You are the Unit 2 NSO An Instrument Maintenance Technician is in the Control Room to perform a credited functional surveillance that will initiate a pressure switch that actuates an associated alarm. The associated alarm is a Nuisance alarm and has an Issue Report tag and ORANGE Dot affixed to the annunciator tile. The surveillance __(1)_ be performed (2)__.

A.: (1) CAN (2) with the alarm defeated

B. (1) CANNOT (2) with the alarm defeated

C. (1) CAN (2) with the annunciator bulbs removed

D. (1) CANNOT (2) with the annunciator bulbs removed

#70. You are an operator currently working in the reactor building on an assigned task. The RWP controlling your task includes the following information: – RWP Dose Approval: 300 mrem/day – ED Dose Alarm: 240 mrem – Dose Rate Alarm 800 mrem/hr The actual dose rate in your work area is 60 mrem/hr. You have accumulated 191 mrem and require more time in the area to complete the task. Which of the following describes your response to the given situation while maximizing your time working on the task and also meeting the expectations of RP-AA-1008; Unescorted Access to and Conduct in Radiologically Controlled Areas ; and why?

A.: Exit the area immediately because the expectation it to exit the area before your accumulated dose has exceeded 80% of the ED Dose Alarm setpoint.

B. Continue to work in the area for 48 minutes or less; because the expectation is to exit the area prior to receiving a cumulative dose alarm

C. Continue to work in the area until the ED Dose Alarm is received because the expectation is to exit the area when you receive a cumulative dose alarm.

D. Continue to work in the area for up to 74 minutes because the expectation is to exit the area prior to exceeding the RWP dose approval.

#71. Which of the following identifies the lowest off-site release rate that requires entry into LGA-009; Radioactivity Release Control ? Offsite release rate above ……….

A. 9.66 E+5 uCi /sec.

B. 1.9 E+07 uCi /sec.

C. 3.7 E+07 uCi /sec.

D. 3.7 E+08 uCi /sec.

#72. Unit 2 has scrammed from rated conditions due to a DBA LOCA. RPV level is -220″ (minus 220 inches) on the Fuel Zone Level Indicator and steady. RPV pressure is 50 psig and steady. LPCS is injecting at 6300 gpm. In accordance with LGA-001; “RPV Control”; which of the following is true regarding the status of core cooling? Adequate core cooling…

A. is established and will be maintained under the current conditions.

B. is NOT established; but will be; if RPV level is raised and then maintained at greater than or equal to -195 (minus 195 inches) on the Fuel Zone Level Indicator

C. is NOT established; but will be; if RPV pressure is reduced to less than or equal to 20 psig and RPV level is maintained greater than or equal to -210 (minus 210 inches) on the fuel zone indicator.

D. is NOT established; but will be; if RPV pressure does not change; HPCS injection is established at greater than or equal to 6350 gpm and RPV level is maintained greater than or equal to –10 (minus 210 inches) on the fuel zone indicator

#73. You are a licensed Reactor Operator on dayshift; working on outage clearance orders in the South Service Building. – You do NOT have assigned responsibilities in the Emergency Response Organization (ERO). – A transient occurs that results in the declaration of a SITE AREA EMERGENCY and activation of the Evacuation/Assembly Siren. To which of the following locations do you report?

A. Technical Support Center

B. Work Execution Center (WEC)

C. South Service Building Trackway

D. Operations Control Center (OCC)

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

A. RWCU Heat Exchanger rooms.

B. Radwaste Control Room.

C. vicinity of the Radwaste Tanks.

D. vicinity of the Reactor Building Equipment Drain Tank Room.

#75. Unit 1 is in Mode 5 with the mode switch in REFUEL. Fuel moves were in progress when the fuel grapple failed to respond to a CLOSE signal. All fuel bundles remain in the proper location and are NOT suspended from the fuel grapple. Fuel moves have been stopped and the control room immediately informed of the issue. Per LFP 100-1; Master Refuel Procedure ; whose permission; if any; is required to be granted prior to resuming fuel moves?

A. Operations Shift Manager.

B. Unit 1 Control Room Supervisor.

C. L-SRO/ SRO in charge of fuel moves.

D. No permission required to be obtained.

#76. You are the Unit 1 Unit Supervisor. With Unit 1 operating at rated conditions; a manual scram was inserted due to a sudden drop in condenser vacuum. The Unit 1 NSO transferred the Mode Switch to SHUTDOWN and then reported the following: – Four rods remain FULL OUT. – RPV Level is – 15 inches and rising slowly – Suppression Pool temperature is 106 F and going up slowly Based on the indication below; reactor power is determined to be _(1) and you must provide direction to hold RPV level in the band of (2)__; in accordance with the governing LGA.

A. (1) unknown (2) 11 inches and 59.5 inches

B. (1) less than or equal to 3%. (2) -150 inches on Wide Range and 59.5 inches

C. (1) greater than 3% and less than 14% (2) -150 inches on Wide Range and – 60 inches

D. (1) greater than 14% (2) -150 inches and -120 inches on Wide Range

#77. The Unit has scrammed and LGA-003 Primary Containment Control has been entered. – Suppression Pool temperature is 112 F – Drywell pressure is 15 psig – Drywell temperature is 335 F and steadily rising. – There are NO bypass paths in the containment. – Suppression Pool level is + 2 inches. – Chamber sprays are in operation. – RR pumps are tripped. – ECCS is not needed for core cooling. Which of the following identifies the Emergency Operating Procedure required action to be directed by the US regarding drywell spray operation and why?

A. Do NOT spray the drywell. Suppression Chamber pressure is too low.

B. Do NOT spray the drywell. Drywell Spray Initiation Limit has been exceeded.

C. Spray the drywell; all conditions are met. Continue drywell sprays; stopping only when drywell temperature is below 135 F to allow the restart of normal drywell cooling.

D. Spray the drywell; all conditions are met. Stop drywell sprays before drywell pressure becomes negative to prevent exceeding the containment negative pressure limit.

#78. 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

#79. Unit 1 is at 32% core thermal power following a refueling outage. The 1A TDRFP has just been placed on-line along with the MDRFP to feed the RPV. The following alarms (and R-point) have just been received: – 1PM01J-B304; DIV 2 125V DC 112X/Y BUS FEED BKR AUTO TRIP R0988; 125V DC Pnl 112X Mn Fd Bkr Trip – 1PM01J-B401; 4KV SWGR BUS 142X DC CONT PWR FAILURE – 1PM01J-A407; 6.9KV SWGR BUS 152 DC CONT PWR FAILURE As the Unit Supervisor; you will direct the crew to. . .

A. SCRAM the reactor.

B. CONTINUE power ascension

C. REDUCE power as necessary; and then locally trip the MDRFP breaker at Bus 152.

D. REDUCE power as necessary; and then locally trip the 1A TDRFP at the pump s front standard.

#80. A rupture in the ‘A’ Diesel Fire Pump discharge piping directly upstream of 0FP-001A; ‘A’ DFP Discharge Check Valve has been identified. Which; if any; of the TRM 3.7.j Fire Suppression Water Systems Conditions are entered and why? (Included find P.ID M-71 Sheet 1; and associated TRMs for reference)

A. Condition B applies because the rupture is common to both water supplies.

B. Condition A applies because the rupture is NOT common to both water supplies.

C. Neither condition applies because the rupture is NOT common to both water supplies.

D. Neither condition applies because the rupture can be isolated while maintaining both A DFP and B DFP operable.

#81. You are the Unit 2 Control Room Supervisor. Unit 2 is at rated conditions. The Unit 2 Reactor Operator reports that the following valves have just changed to CLOSED indication.: – 2C11-F380; Scram Discharge Volume Downstream Vent Isolation Valve – 2C11-F381; Scram Discharge Volume Downstream Drain Isolation Valve There are no other abnormal indications to report. Next; a mechanic calls to report that he inadvertently stepped on and broke a 1/2 instrument air line on 761 elevation in the Unit1 Reactor Building while walking down an outage work package. He crimped the line shut to stop the leak. Per Technical Specifications; the reported condition will require . . . . (References provided for this question)

A. isolating the Scram Discharge Volume Drain Line OR Vent Line within 8 hours.

B. isolating the Scram Discharge Volume Drain Line AND Vent Line within 8 hours.

C. isolating the Scram Discharge Volume Drain Line OR Vent Line within 7 days.

D. isolating the Scram Discharge Volume Drain Line AND Vent Line within 7 days.

#82. Unit 1 is operating at rated conditions. – The 1A TBCCW Pump and Heat Exchanger are in operation. – The 1B TBCCW Pump is out of service for maintenance. The following annunciators just alarmed on the 1PM10J Panel: – LOR-1PM10J-A301; TBCCW PMP AUTO TRIP – R1520 1A TBCCW Pump A-Trip. – LOR-1PM10J-A304; TBCCW PMP DSCH HDR PRESS LO – R1522 TBCCW Pump Dsch Hdr Press Lo Based on the given conditions; what action is required to be taken first?

A. Scram the Unit 1 reactor per LGP-3-2 the guidance provided in the LOA.

B. Commence a Unit 1 shutdown per LGP-3-1

C. Cross tie Unit 1 TBCCW to Unit 2 TBCCW

D. Supply supplemental cooling to Unit 1 loads per LOA-WT-101 Loss of Turbine Building Closed Cooling Water (TBCCW)”

#83. You are the Unit 1 Unit Supervisor. – Unit 1 is operating at rated conditions. – An operator calls you to report that the HPCS room sump is overflowing and there is water flowing into the HPCS pump room from under the CRD Pump Room door. – The leak is coming from an RBCCW line that was disconnected during maintenance on the 1A CRD pump and has been damaged. – The leak can not be quickly isolated. The operator then leaves to attempt to isolate the leak. A short time later the HPCS Water Leg pump trips. The information provided CONFIRMS that water level in the HPCS pump room has ____(1)_ and entry into LGA-002 is _(2)____

A. (1) NOT Exceeded Max Normal Level (2) NOT required.

B. (1) Exceeded Max Normal Level ONLY (2) required.

C. (1) Exceeded Max Normal Level ONLY (2) NOT required.

D. (1) Exceeded Max Normal AND Max Safe Level (2) required.

#84. You are the Unit 2 Control Room Supervisor. – Unit 2 has scrammed from rated conditions. – Drywell pressure is 2.2 psig and going up slowly. – VR has tripped and Unit 2 VR is required to be started in accordance with LGA-VR-01; Reactor Building Ventilation Startup . – No actions have been taken in the main control room related to VR following the trip of the fans. You will direct an extra reactor operator to perform the in-plant actions to INSTALL jumpers to defeat isolation signals for ___(1) and then _(2)______

A. (1) VR High Drywell Pressure and VR/FC Rad (2) IMMEDIATELY OPEN the VR isolation dampers.

B. (1) VR High Drywell Pressure and VR/FC Rad (2) STANDBY to OPEN the VR isolation dampers after control room actions are taken.

C. (1) VR High Drywell Pressure and Low-Low-Level (2) IMMEDIATELY OPEN the VR isolation dampers.

D. (1) VR High Drywell Pressure and Low-Low-Level (2) STANDBY to OPEN the VR isolation dampers after control room actions are taken.

#85. Unit 1 was operating at rated conditions when an automatic scram occurred due to low RPV water level. Following the scram; hydrogen was detected in the drywell and has risen to 7%. Oxygen concentration in the drywell is 4% As the Unit 1 Supervisor you entered LGA-011; Hydrogen Control and directed the following actions: – Operate the Unit 1 recombiner as a mixing system per LGA-HG-101. – Vent and purge the primary containment per LGA-VQ-02 and LGA-VQ-03. You just observed that oxygen concentration in the drywell suddenly increased to 5.5 %. Based on the above conditions; you will direct the crew to. . . . ..

A. (1) CONTINUE containment vent and purge; (2) STOP the hydrogen recombiner; (3) and DO NOT INITIATE a BLOWDOWN.

B. (1) CONTINUE containment vent and purge; (2) CONTINUE to OPERATE the hydrogen recombiner; (3) and INITIATE a BLOWDOWN.

C. (1) CONTINUE containment vent and purge; (2) STOP the hydrogen recombiner; (3) and INITIATE a BLOWDOWN.

D. (1) STOP containment vent and purge; (2) STOP the hydrogen recombiner; (3) and INITIATE a BLOWDOWN.

#86. The following conditions exist on Unit 1: – Unit 1 is operating at rated conditions – It is a Division III Work Week – LOS-HP-Q1; HPCS Inservice Test is in progress with the HPCS system running with the 1E22-F023; HPCS Test to SP Valve throttled to establish a flowrate of 6200 gpm. What will be the impact of a sustained loss of Bus 113 125V DC on the HPCS system and what action is required to be directed in response to the event; assuming HPCS is not required to maintain RPV level?

A. The ability to control all HPCS components from control room panel 1H13-P601 is lost. Direct the Reactor Operator to allow the HPCS system to remain running at 6200 gpm until Bus 113 125V DC is restored

B. The ability to trip the HPCS pump from the control room panel 1H13-P601 is lost. Direct a Reactor Operator to secure the HPCS pump by placing the control switch in Pull-to-Lock and then locally tripping the HPCS Pump Breaker at Bus 143 Cub 4.

C. All protective trips and interlocks for the HPCS system are lost. Direct the Reactor Operator to shutdown the HPCS system from control room panel 1H13-P601 by CLOSING the 1E22- F023; HPCS Test to SP Valve and placing the HPCS Pump control switch to STOP.

D. The HPCS Minimum Flow Valve will go full open. Direct the Reactor Operator to trip the HPCS pump from control room panel 1H13-P601 by placing the control switch to STOP; and then CLOSE the HPCS Minimum Flow Valve by placing the control switch in the CLOSED position.

#87. 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.

#88. Unit 1 has automatically scrammed due to a grid disturbance. – All control rods are fully inserted. – A steam leak developed in the drywell following the scram. – Drywell pressure is 17 psig and going up moderately – RPV pressure is 550 psig and going down slowly – RPV level is – 25 inches; going up slowly; supplied by the 1A and 1C Condensate/Condensate Booster Pumps – 1A RHR Pump is OOS for repairs The following annunciators (among others) are in alarm: – 1H13-P601 – B106; 1B RHR PMP AUTO TRIP – 1H13-P601 – B107; 1B/1C LPCI SYSTEM ACTUATED – 1H13-P601 – B304; CHAN B/D RHR DRYWELL PRESS HI (Red bordered alarm) – 1H13-P601 – B308; 1C RHR PMP DSCH PRESS LO – 1PM01J – A206; 6.9KV BUS 151/152 OVERCURRENT – 1PM01J – A214; 4KV BUS 141X/Y OVERCURRENT – 1PM13J – A202; SUP POOL WTR BULK TEMP HI – 1PM13J – A102; SUP POOL WTR BULK TEMP HI-HI Based on the listed alarms AND assuming you have only one equipment operator available for assignment; you will direct the equipment operator to inspect the . . .

A. 1C RHR pump.

B. 1B RHR pump and breaker.

C. 4KV BUS 141Y.

D. 6.9 KV BUS 151.

#89. 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 .

#90. You are the Unit 1 Supervisor and Unit-1 is shutting down following 100 days of continuous operation at rated conditions. The Reactor Operator is inserting control rods; with IRMs on Range 8; when power is lost to the 1A IRM/1C IRM RECORDER. Based on the above conditions; the 1A and 1C IRM alarms and trips are ___(1)_ and you will direct the Reactor Operator to _(2)___.

A. (1) Non-Functional (2) SCRAM the reactor

B. (1) Functional (2) CONTINUE inserting control rods

C. (1) Non-Functional (2) INSERT a half scram for the affected channel.

D. (1) Functional (2) STOP all control rod motion.

#91. – You are assigned to the position of Unit 1 Reactivity SRO. – Unit 1 is starting up from a refueling outage and reactor power is 19% with the turbine on-line. – “RWM Blocks to Full” is NOT ENABLED While withdrawing control rods; input corresponding to the Rod Worth Minimizer Low Power Alarm Point (LPAP) indicates power is above the LPAP; while Low Power Setpoint (LPSP) input indicates power is below the LPSP. As the result of this condition; the RWM will ______(1)_ and you must direct the crew to _(2)______ THEN continue with control rod withdrawals.

A. (1) automatically ENABLE control rod blocks (2) STOP control rod movement; NOTIFY a Qualified Nuclear Engineer and RESOLVE the problem;

B. (1) automatically DISABLE control rod blocks (2) ACKNOWLEDGE the alarm; NOTIFY a Qualified Nuclear Engineer; MANUALLY ENABLE control rod blocks;

C. (1) BLOCK all control rod movement (2) VERIFY power below the Low Power Set Point (LPSP); NOTIFY a Qualified Nuclear Engineer; BYPASS the RWM;

D. (1) LOCKUP; preventing all control rod movement (2) VERIFY power is below the Low Power Alarm Set Point (LPAP); NOTIFY a Qualified Nuclear Engineer; BYPASS the RWM;

#92. 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.

#93. You are the Unit 1 Control Room Supervisor. – Unit 1 is at rated conditions. – The Unit 1 Reactor Water Clean-up (RWCU) system isolated 2 hours ago on an invalid signal and the operations crew responded in accordance with LOA-RT-101; Loss of RWCU System. – The RWCU system pressure is 950 psig and rising as CRD purge is being used to raise RWCU system pressure to reactor pressure. – A Chemistry technician wants to sample RWCU and just called requesting permission to open the following Process Stops: 7) RWCU Header Sample Line 1A2 Panel Upstream Valve 8) 1A RWCU Demin Discharge Sample Line 1A3-1 panel Upstream Valve 9) 1B RWCU Demin Discharge Sample Line 1A3-2 Panel Upstream Valve 10) 1C RWCU Demin Discharge Sample Line 1A3-2 Panel Upstream Valve In accordance with LOA-RT-101; you are to ____(1)_ permission to open the Process Stop valves in order to (2)_____.

A. (1) give (2) restore the TRM required conductivity recorders to operation.

B. (1) give (2) allow sampling of the RWCU system to determine if Filter Demin damage or resin intrusion has occurred.

C. (1) deny (2) prevent overflowing the sample sinks with the RWCU system isolated.

D. (1) deny (2) prevent depressurizing the system and creating voids in the RWCU piping.

#94. Unit 1 and Unit 2 are both in Mode 5; Refuel The following Non Licensed Operators are assigned to the on coming shift: Chad Johnson Tom Smith Randy Jefferson Bill Washington Frank Jones Paul White Mike Black Mark Franklin Paul White called in sick and will not be coming in for his shift. Jeff Martin and Pat Hardy are available for call-out if needed. With the remaining crew compliment; staffing requirements in accordance with OP-LA-101-111-1001; On-Shift Staffing Requirements (1) met and a callout of (2) is required. (Reference material provided for this question)

A. (1) ARE (2) NO One

B. 1) ARE NOT (2) Jeff Martin or Pat Hardy

C. (1) ARE NOT (2) Jeff Martin ONLY

D. (1) ARE NOT (2) Pat Hardy ONLY

#95. Unit 1 is at 80% power. Unit 2 is in a refueling outage. – At 0600 on May 11; the 0 (Common) DG is declared inoperable for maintenance. – At 0650 on May 11; SR 3.8.1.1 is completed for the OPERABLE required offsite circuits. Including any extensions permitted by Technical Specifications; which one of the following describes the LATEST time to complete the next performance of SR 3.8.1.1? (Reference material provided)

A. 1450 on May 11

B. 1650 on May 11

C. 0650 on May 12

D. 1250 on May 12

#96. You are the Unit 1 Control Room Supervisor. The refuel floor supervisor called to report that a radiated fuel bundle has been dropped in the Unit 1 Fuel Pool; and bubbles are being released from the fuel bundle and rising to the surface of the fuel pool. The following annunciators are in alarm: – 1H13-P601-E306 FUEL POOL VENT RAD HI – 1H13-P601-F205 DIV 1 FUEL POOL RAD HI-HI – 1H13-P601-E205 DIV 2 FUEL POOL RAD HI-HI Unit 1 and Unit 2 remain at rated conditions. Release rates have remained normal. In response to this event you will enter . . . . .

A. LOA-FH-001 Irradiated Fuel Assembly Damage ONLY.

B. LOA-FH-001 Irradiated Fuel Assembly Damage AND LGA-002 Secondary Containment Control AND LGA-009; Radioactivity Release Control ONLY.

C. LOA-FH-001 Irradiated Fuel Assembly Damage AND LGA-002 Secondary Containment Control AND LGA-VG-101; Secondary Containment Vent Control ONLY.

D. LOA-FH-001 “Irradiated Fuel Assembly Damage” AND LGA-002 “Secondary Containment Control” AND LGA-VG-101; “Secondary Containment Vent Control” AND LGA-VR-01; “Reactor Building Ventilation Startup Following System Isolation”.

#97. Unit-1 has just scrammed due to a loss of the SAT – LGP-3-2; Reactor Scram; is being performed – LOA-AP-101; Unit-1; AC Power System Abnormal; is being performed Two minutes later suppression pool temperature is 106F and rising. Which of the following describes the required actions to be directed by the Unit-1 Control Room Supervisor?

A. Concurrently enter LGA-003; Primary Containment Control and start all available pool cooling.

B. Exit LOA-AP-101 and enter LGA-003; Primary Containment Control and start all available pool cooling.

C. Continue LOA-AP-101 and LGP-3-2 and monitor suppression pool temperature; do NOT enter LGA-003; Primary Containment Control.

D. Exit LGP-3-2 and enter LGA-003; Primary Containment Control and monitor suppression pool temperature; do NOT start all available pool cooling.

#98. Unit-1 is in Mode 1 at 100% power: – at 12:00 on June 1; the 1A RHR WS Pump is declared inoperable – at 20:00 on June 1; the 1B RHR WS Pump is declared inoperable – at 15:00 on June 2; the 1A RHR WS Pump is restored to OPERABLE Including any extensions permitted by Technical Specifications; which one of the following is the latest time and date allowed to restore the 1B RHR WS Pump to OPERABLE status without entering a shutdown timeclock? (Reference provided for this question)

A. 20:00 on June 1

B. 04:00 on June 2

C. 12:00 on June 8

D. 20:00 on June 8

#99. 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.

#100. 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

Results