ML21019A574

Initial License Exam Administered Written Exam Key

ML21019A574
Person / Time
Site:	Monticello
Issue date:	11/03/2020
From:	Chuck Zoia Operations Branch III
To:	Nuclear Management Co
Zoia C
Shared Package
ML19127A318	List: ML21019A572 ML21019A573 ML21019A574
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Download: ML21019A574 (108)

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2020 MONTICELLO ILT NRC EXAM - KEY

1. Complete the following statement describing the immediate RPV level response to a Trip of a Recirc Pump from rated conditions AND the correct reason?

RPV water level will A. rise due to reverse flow in the idle loop.

B. lower due to reverse flow in the idle loop.

C. rise due to increased voids in the core region.

D. lower due to collapsing voids in the core region.

CORRECT ANSWER: C JUSTIFICATION: Due to the decrease in core flow, an increase in core voids will occur. This will cause the indicated level to increase.

A is incorrect: Water level will rise and reverse flow will occur, but this is not the reason for the water level rise.

B is incorrect: Reverse flow will occur but will not cause water level to lower.

D is incorrect: Plausible option as this will be the water level response for a scram.

REFERENCE:

C.4-B.01.04.A Bases 10 CFR 55.41b(2)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2016 NRC Exam #5 295001 Partial or Complete Loss of TIER: 1 GROUP: 1 CATEGORY:

Forced Core Flow Circulation K/A: AK3.01 IMPORTANCE: RO 3.4 COG LEVEL: 1B K/A DESCRIPTION: Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE CIRCULATION: Reactor water level response.

DIFFICULTY 2 LESSON PL: MT-ILT-AOP-003L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

2. The reactor was operating in MODE 1 when the following occurred:

• Loss of 125V DC Bus B

• Subsequent Loss of ALL Offsite Power What indications will the BOP operator observe when monitoring the EDGs?

11 EDG 12 EDG A. start only start only B. start and load start only C. start only start and load D. start and load start and load CORRECT ANSWER: B JUSTIFICATION: EDGs would receive an auto start signal, both EDGs would auto start, but only the 11 EDG would have DC power available to flash the field and load.

A, C, and D are incorrect: Plausible, but incorrect variations on this event.

REFERENCE:

C.4-B.09.10.A 10 CFR 55.41b(8)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 Audit Exam 295003 Partial or Complete loss of TIER: 1 GROUP: 1 CATEGORY:

AC K/A: AA1.03 IMPORTANCE: RO 4.4 COG LEVEL: 2 RI K/A DESCRIPTION: Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF AC: Systems necessary to assure safe plant shutdown.

DIFFICULTY 3 LESSON PL: MT-ILT-AOP-019L OBJECTIVE: 8

2020 MONTICELLO ILT NRC EXAM - KEY

3. The plant is at rated conditions.

• Breaker B4482 (Y82 120V INST AC ALT SOURCE XFMR) is tagged OPEN.

A malfunction results in the 250 VDC Input voltage to Y-81 (DIV 2 120 VAC CLASS 1E INVERTER) lowering to 90 VDC.

Which is correct for the conditions above?

A. ODA-1 (Operator Display Assembly-APRM 1/3) will LOSE display.

B. AO-1085A/B (SJAE STEAM SUPPLIES) will fail closed.

C. BOTH Main Feedwater Regulating Valves will LOCKUP.

D. Panels Y-30 & Y-80 will both remain energized.

CORRECT ANSWER: C JUSTIFICATION: The examinee must recognize the low input voltage will result in an inverter shutdown and a loss of Y-30 and Y-80 because the alternate source isnt available. The C.4 for a loss of Y-80 directs performance of C.4 for Y-30 first. A loss of Y-30 results in a lock of both FW REG valves.

A is incorrect. ODAs 3 and 4 will lose display.

B is incorrect. A loss of Y-30 will cause the SJAE supply valves to fail open.

D is incorrect. With DC input voltage lowering to < 200 VDC an inverter shutdown will occur.

K/A - The examinee must interpret and determine that a battery voltage of 90 VDC (Partial Loss) will result in a loss of DC supply to the inverter. This in turn will result in a lockup of both MFRVs.

MT-ILT-AOP-020L Objective 4: Describe the applicable operational implications as they relate to a loss of a specific UPS.

REFERENCE:

C.4-B.09.13.G C.4-B.09.13.E 10 CFR 55.43b(5)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2010 NRC Exam #90 295004 Partial or Total Loss of DC TIER: 1 GROUP: 1 CATEGORY:

Power K/A: AA2.03 IMPORTANCE: RO 2.8 COG LEVEL: 2 RI K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF DC POWER: Battery voltage.

DIFFICULTY 4 LESSON PL: MT-ILT-AOP-020L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

4. The plant was at rated conditions when a Main Turbine trip resulted in a reactor scram and a trip of 152-308 (13/15 BUS TIE ACB). Given the following conditions:

• RPV pressure is 920 psig and rising slowly

• Bus 15 is being supplied by 1AR Transformer

• Main Turbine Hydraulic Oil pressure is 262 psig

• 7-A-3 (TURB AUX OIL PUMP P-61 LOCKOUT) is IN alarm What action is required to restore P-61 for continued use of the Main Turbine Bypass Valves?

A. Reset the motor lockout relay locally and P-61 will AUTOMATICALLY start.

B. Reset the motor lockout relay locally AND start P-61 from C-07.

C. Restore Bus 15 from Bus 13 AND start P-61 from C-07.

D. Start P-61 from C-07 is ALL that is required.

CORRECT ANSWER: B JUSTIFICATION: The Bypass Valves require control oil pressure to function. With the Main Turbine tripped, control oil pressure is supplied by the Aux Oil Pump. With the essential bus transfer of Bus 15 to 1AR, the Aux Oil pump will lockout and the lockout relay must be reset locally before it can be restarted from control room panel C-07.

A is incorrect: Plausible that P-61 would auto start with RPV pressure rising above the normal pressure control setting of

~910 psig. It would not auto start unless oil pressure lowered to 201 psig.

C is incorrect: Plausible that this lockout could only be reset with the normal power supply to Bus 15.

D is incorrect: Plausible as several pumps overload flags can be reset by momentarily taking the switch to off from the control room switch.

REFERENCE:

ARP 7-A-3 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 1 GROUP: 1 CATEGORY: 295005 Main Turbine Generator Trip K/A: 2.4.35 IMPORTANCE: RO 3.8 COG LEVEL: 2 RI K/A DESCRIPTION: Knowledge of the local auxiliary operator tasks during and emergency and the resultant operational effects.

DIFFICULTY 3 LESSON PL: MT-ILT-AOP-021L OBJECTIVE: 8

2020 MONTICELLO ILT NRC EXAM - KEY

5. The plant was at rated conditions when a reactor scram occurred.

Which of the following will require IMMEDIATE entry into C.5-2007 (FAILURE TO SCRAM)?

A. All control rods at position 04.

B. All control rods at position - - EXCEPT 22-31 at position 04.

C. All control rods at position - - EXCEPT 22-31 at position 48.

D. All control rods at position 04 EXCEPT 22-31 at position 48.

CORRECT ANSWER: D JUSTIFICATION: Position -- is the insert overtravel position where it is expected that all controls rods will reach immediately after a scram and then settle back into the 00 position after pressure bleeds down after a few minutes. Shut down reactivity margin is assured when all control rods are inserted to position 00 with the analytically highest worth control rod fully withdrawn. Additionally, entry into C.5-2007 is not required if all control rods are inserted to at least position 04.

A, B and C are incorrect: Plausible combinations for C.5-2007 entry; however, none of these conditions require entry into the failure to scram procedure.

REFERENCE:

C.5.1-1100 TS 3.1.1 10 CFR 55.41b(6)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 Audit Exam - Edits to stem TIER: 1 GROUP: 1 CATEGORY: 295006 SCRAM K/A: AK1.03 IMPORTANCE: RO 3.7 COG LEVEL: 1B K/A DESCRIPTION: Knowledge of the operational applications for the following concepts as they apply to SCRAM: Reactivity control.

DIFFICULTY 2 LESSON PL: MT-ILT-EOP-002L OBJECTIVE: 3

2020 MONTICELLO ILT NRC EXAM - KEY

6. The plant was at rated conditions when a Cable Spreading Room fire forced the crew to enter C.4-C (SHUTDOWN OUTSIDE CONTROL ROOM). All immediate actions have been taken for IMMEDIATE Control Room evacuation and all systems responded as designed.

When the MASTER ASDS TRANSFER SWITCH on the ASDS Panel is taken to the TRANSFER position, which lights in the picture above do you expect to be ON and why?

A. All lights would remain OFF until S32 is placed in the INSERT position.

B. ONLY the green light would be LIT because the RX Mode Switch would be in RUN.

C. The amber AND red lights would be LIT because RX Mode Switch would be in SHUTDOWN.

D. The green AND amber lights would be LIT because the scram air header would be depressurized.

CORRECT ANSWER: D JUSTIFICATION: The examinee must recognize that with the immediate actions taken the reactor would have been manually scrammed with the mode switch left in RUN. Scraming the reactor will de-energize RPS and depressurize the scram air header which will cause the amber light to come on. The green light comes on when the MASTER switch is placed in transfer indicating power available to the ARI solenoid.

A is incorrect: The green light is on when the MASTER switch is placed in transfer.

B is incorrect: Since a manual scram would have been inserted, RPS will de-energize and depressurize the scram air header which will cause the amber light to come on C is incorrect: The red light will not come on until S32 is placed in INSERT and the Mode switch would be in RUN.

REFERENCE:

B.05.17-02 pg. 7 10 CFR 55.41(6)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #6 TIER: 1 GROUP: 1 CATEGORY: 295016 Control Room Abandonment K/A: AK2.02 IMPORTANCE: RO 4.0 COG LEVEL: 3 SPK K/A DESCRIPTION: Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following: Local Control Room Stations.

DIFFICULTY 3 LESSON PL: M8107L-083 OBJECTIVE: 6

2020 MONTICELLO ILT NRC EXAM - KEY

7. Complete the following statement concerning system component temperatures on a loss of RBCCW from rated power?

The (1) system must be shutdown prior to the outlet temperature of the (2) exceeding 120° F to protect downstream piping from over temperature.

(1) (2)

A. CRDH CRD Pump Gear Box oil Cooler B. FPCC Fuel Pool Cooling Heat Exchanger C. Recirc Reactor Recirc Pump Seal Coolers D. RWCU Non-regenerative Heat Exchanger CORRECT ANSWER: B JUSTIFICATION: The FPCC heat exchanger outlet temp must be monitored and FPCC system removed from service before the heat exchanger outlet temp reaches 120 F. The FPCC Heat Exchanger outlet piping is not analyzed for temps above 120°F.

A, C and D are incorrect: Plausible RBCCW cooled components, however, these systems dont have temperature concerns for downstream piping.

REFERENCE:

C.4-B.02.05.A 10 CFR 55.41b(10)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2013 NRC Exam #60 TIER: 1 GROUP: 1 CATEGORY: 295018 Partial or Complete Loss of CCW K/A: AK3.03 IMPORTANCE: RO 3.1 COG LEVEL: 1 B K/A DESCRIPTION: Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF CCW: Securing individual components (prevent equipment damage)

DIFFICULTY 3 LESSON PL: MT-ILT-AOP-004L OBJECTIVE: 6

2020 MONTICELLO ILT NRC EXAM - KEY

8. The plant is at rated conditions when an Instrument Air leak occurs. Given the following:

• 15 Air Compressor (A/C) is in LEAD and running

• 16 Air Compressor (A/C) is in STANDBY

• 17 Air Compressor (A/C) is in LAG

• Instrument Air discharge header cross-tie valves are CLOSED

• Instrument and Service Air pressure is 99 psig What is the expected A/C response to an ES-8 Sequencer failure?

A. All A/Cs will remain running and/or IMMEDIATELY start.

B. 15 A/C will remain in LEAD; 17 A/C will IMMEDIATELY start.

C. 15 A/C will continue running; 16 A/C will start NEXT if pressure continues to lower.

D. 15 A/C will continue running; 17 A/C will start NEXT if pressure continues to lower.

CORRECT ANSWER: D JUSTIFICATION: The normal IA pressure band is97-105 psig. Prior to the ES-8 failure, 15 AC would have been running. Failure of the ES-8 Sequencer will result in automatic local (Electronikon) control. Under local control the ACs start under the predetermined lead, lag and standby setpoints as follows:

LEAD - 97 psig LAG - 93 psig STANDBY - 89 psig A is incorrect: Plausible system response to a sequencer failure.

B is incorrect: 15 A/C will be running and 17 A/C wont start until 93 psig in local control.

C is incorrect: 15 A/C will be running but 16 A/C wont start next.

REFERENCE:

B.08.04.01-01 B.08.04.01-05 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2018 Audit Exam TIER: 1 GROUP: 1 CATEGORY: 295019 Partial or Total Loss of IA K/A: AA1.01 IMPORTANCE: RO 3.5 COG LEVEL: 1I K/A DESCRIPTION: Ability to operate and/or monitor the following as they apply to PARTIAL OR TOTAL LOSS OF IA: Backup air supply.

DIFFICULTY 3 LESSON PL: M8107L-024 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

9. The plant is in Mode 4 when a Loss of Normal Shutdown Cooling occurs.

Given the following:

• Both Recirc pumps have tripped

• Shutdown Cooling has been restored

• RPV water level lowered to +25 inches

• Operators are intentionally raising RPV water level What is the reason for intentionally raising RPV water level in these conditions?

A. To restore RPV water level to the normal band of +30-40 inches.

B. To restore RPV water level back on-scale of the Vessel Flood Up indicator.

C. To raise RPV water level above the Main Steam lines for a Torus bleed and feed.

D. To restore RPV water level above the separator turnaround area for natural circulation.

CORRECT ANSWER: D JUSTIFICATION: With RPV water level <+55 and no Recirc pumps running, a loss of shutdown cooling has occurred.

When normal shutdown cooling is restored, RPV water level is raised to +55-80. This ensures that level is above the separator turnaround area (+46) to promote natural circulation.

A is incorrect: This is the normal level band when operating in mode 1.

B is incorrect: This indicator will be used but its scale is -50 to +365.

C is incorrect: A bleed and feed would only be performed if normal shutdown cooling couldnt be restored.

REFERENCE:

C.4-B.03.04.A 10 CFR 55.41b(10)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #9 TIER: 1 GROUP: 1 CATEGORY: 295021 Loss of Shutdown Cooling K/A: AA2.03 IMPORTANCE: RO 3.5 COG LEVEL: 1 P/B K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF SHUTDOWN COOLING: Reactor water level.

DIFFICULTY 2 LESSON PL: MT-ILT-AOP-007 OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

10. The plant is in Mode 5 when a fuel assembly is dropped on the remaining fuel in the core causing a large LOCA. Given the following timeline:

1000: The Fuel assembly is dropped 1030: RPV water level reaches -130 inches 1045: RPV water level reaches -150 inches 1100: RPV water level reaches -180 inches At which of the times above has a TS Safety Limit violation FIRST occurred, if at all?

A. 1030 B. 1045 C. 1100 D. The RPV Level Safety Limit does NOT apply in Mode 5.

CORRECT ANSWER: A JUSTIFICATION: Top of Active Fuel (TAF -126) is the safety limit for RPV water level. In the timeline above 1030 is the first time listed when this limit is being exceeded.

B is incorrect: Plausible for confusing the Minimum Steam Cooling RPV water level (-149) as the safety limit.

C is incorrect: Plausible for confusing Two Thirds Core Height (-174) as the safety limit.

D is incorrect: Plausible as the majority of safety limits only apply when the reactor is at power.

REFERENCE:

TS 2.1.1.4 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 1 GROUP: 1 CATEGORY: 295023 Refueling Accidents K/A: 2.2.22 IMPORTANCE: RO 4.0 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of limiting conditions for operations and safety limits.

DIFFICULTY 2 LESSON PL: MT-ILT-ITS-003L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

11. The plant was at rated conditions when an event occurred in the Drywell (DW) resulting in the following conditions:

• DW pressure is 12.2 psig and rising slowly

• DW temperature is 225°F and rising slowly

• Torus water level is +1 inch and rising slowly

• Torus water temperature is 95°F and rising slowly

• 4 RHR pumps are running and A RHR is in the Torus Spray mode At this point, the CRS directs that B RHR be placed in the Drywell Spray mode. Which of the following statements describes why this action is needed?

Drywell sprays A. ARE initiated above 12 psig DW pressure to restore and maintain pressure suppression capability.

B. CAN NOT be initiated below 12 psig DW pressure because RHR NPSH limits would be exceeded.

C. CAN NOT be initiated below 12 psig DW pressure because de-inertion of the primary containment could occur.

D. ARE initiated above 12 psig DW pressure to preclude chugging that could cause fatigue failure in the downcomers.

CORRECT ANSWER: D JUSTIFICATION: Drywell sprays are initiated if drywell pressure exceeds 12 psig to preclude a phenomenon known as chugging.

Chugging is the cyclic condensation of steam at the downcomer openings of the drywell vents. When a steam bubble collapses at the exit of the downcomers, the rush of water drawn in the downcomers to fill the void induces stress at the junction of the downcomers and the vent header. Repeated application of such stresses could cause fatigue failure of these joints.

A is incorrect: Pressure suppression capability would not be a concern until DW pressure exceeds 25 psig. Although one of the goals of spraying the DW is to prevent losing this capability, its not the reason for doing it at 12 psig and the restore in this distracter implies that it is currently being exceeded which it isnt.

B is incorrect: RHR NPSH limits are not being exceeded as torus water temperature would need to be in excess of 200°F for this to be true.

C is incorrect: The DW Spray limit is only a concern at much lower DW temperatures.

REFERENCE:

C.5.1-1200 C.5-1200 10 CFR 55.41(5)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2018 Audit Exam - Edits to stem TIER: 1 GROUP: 1 CATEGORY: 295024 High Drywell Pressure K/A: EK1.01 IMPORTANCE: RO 4.1 COG LEVEL: 2DR K/A Knowledge of the operational implications of the following concepts as they apply to HIGH DESCRIPTION: DRYWELL PRESSURE: Drywell integrity.

DIFFICULTY 3 LESSON PL: MT-ILT-EOP-003L OBJECTIVE: 7.b

2020 MONTICELLO ILT NRC EXAM - KEY

12. Given the following:

What instrument values will cause the GOOD DATA column to change to NO?

A. PT-6-58 lowers to 975 psig.

B. PT-6-58 rises to 1075 psig.

C. PT-6-53A lowers to 850 psig D. PT-6-53B rises to 1100 psig CORRECT ANSWER: B JUSTIFICATION: PT-6-58 feeds the Blue Pen recorder FPR-6-98 on C-05 and the PCS indication above. The range on FPR-6-98 is 950-1050 psig. A reading of 1075 psig on the PT will result in the instrument value above changing to magenta asterisks and the GOOD DATA column changing to NO.

A is incorrect: Plausible if examinee does not know the narrow range values.

C is incorrect: Wide range instruments are 0-1200 psig. Plausible for confusion between EPR pressure range of 900-1050.

D is incorrect: Wide range instruments are 0-1200 psig. Plausible if examinee relates the wide range pressure value with the reactor scram pressure setting of 1056 psig.

REFERENCE:

B.01.01-03 PCS Users Guide 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 1 GROUP: 1 CATEGORY: 295025 High Reactor Pressure K/A: EK2.10 IMPORTANCE: RO 2.9 COG LEVEL: 2 RI K/A DESCRIPTION: Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following:

SPDS.

DIFFICULTY 4 LESSON PL: M8107L-028 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

13. The plant was at rated conditions when a valid scram signal was received. The following conditions now exist:

• Most control rods did NOT insert

• Reactor power is 20% and oscillating 8% peak-to-peak

• The MSIVs closed and LL Set is controlling RPV pressure

• RPV water level is -40 inches and intentionally being lowered

• Torus water temperature is 125°F and rising

• SBLC is being injected For the conditions above, SBLC being injected to A. minimize thermal-hydraulic instabilities.

B. maintain the integrity of the fuel cladding.

C. maintain a backup high pressure injection source D. minimize the threat to primary containment integrity.

CORRECT ANSWER: D JUSTIFICATION: Before torus temperature reaches 110°F A scram failure with MSIV closure results in torus heatup due to steam discharged through the SRVs. If torus temperature cannot be maintained below the Heat Capacity Limit, C.5-1200 will require a blowdown and challenge primary containment.

A is incorrect: Plausible with the given conditions; however, power oscillations in excess of 25% peak-to-peak would be needed for indications of thermal-hydraulic instabilities.

B is incorrect: Plausible; however flux oscillations of 8% peak-to-peak at a lower reactor power of 20% are not expected to threaten fuel clad integrity.

C is incorrect: Injecting with SBLC is a high pressure injection source option in the level leg of RPV Control when RPV water level cannot be maintained +9 to +48. Plausible for current RPV water level of -40 inches.

REFERENCE:

C.5.1-2007 10 CFR 55.41b(6)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New 295026 Suppression Pool High TIER: 1 GROUP: 1 CATEGORY:

Water Temperature K/A: EK3.04 IMPORTANCE: RO 3.7 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: SBLC injection.

DIFFICULTY 3 LESSON PL: MT-ILT-EOP-007L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

14. The plant was at rated conditions when a reactor scram occurred due to a steam leak inside containment. The following plant conditions now exist:

• RPV Level is (-) 57 inches and slowly rising

• Reactor Pressure is 580 psig and slowly lowering

• Drywell Pressure is 13 psig

• Drywell Temperature is 265 °F

• Part C of C.5-3502 (CONTAINMENT SPRAY) has been initiated During the performance of Step 1, the Div 1 CONTAINMENT SPRAY 2/3 CORE HEIGHT BYPASS switch (10A-S18A) is unable to be placed in the MANUAL OVERRIDE position.

Which is correct concerning Div 1 Drywell (DW) Spray for the conditions above?

(Assume only Step 1 has been performed so far)

A. DW Sprays can ONLY be initiated by locally opening the valves.

B. DW Sprays can ONLY be initiated with 10A-S18A in MANUAL OVERRIDE.

C. DW Sprays CAN be initiated from C-03; ALL required spray permissives are currently satisfied.

D. DW Sprays CAN be initiated from C-03 after the CONTAINMENT SPRAY/COOLING LPCI INITIATION BYPASS switch is placed in BYPASS during Step 2.

CORRECT ANSWER: D JUSTIFICATION: Containment Spray Isolation Valves (Drywell and Torus) MO-2010, MO-2020, MO-2022, MO-2011, MO-2021 and MO-2023 are all interlocked to be automatically closed when a LPCI automatic initiation signal is received.

These valves cannot be opened when a LPCI initiation signal is present except under the following conditions: a) reactor water level is greater than 2/3 core height [interlock can be bypassed], b) drywell pressure greater than 1 psig, and c) the associated Containment Spray/Cooling LPCI Initiation Bypass switch in BYPASS. The LPCI initiation signal is from PS-10-101A-D and the drywell permissive for core spray originates from PS-10-119A-D.

A is incorrect: These valves could be opened locally or in the control room with water above 2/3 core height.

B is incorrect: These valves could be opened in the control room with water above 2/3 core height.

C is incorrect: A valid actuation of LPCI has been received and must be bypassed.

REFERENCE:

C.5-3502 B.03.04-01/02 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2016 NRC Exam #59, minor edits - Previous 2 NRC Exams TIER: 1 GROUP: 1 CATEGORY: 295028 High Drywell Temperature K/A: EA1.01 IMPORTANCE: RO 3.8 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell spray DIFFICULTY 3 LESSON PL: M8107L-044 OBJECTIVE: 8

2020 MONTICELLO ILT NRC EXAM - KEY

15. The following plant conditions exist after a Loss of Coolant Accident:

• Emergency Depressurization is being performed.

• Average Drywell Air Temperature is 320°F and rising slowly.

• RPV Flooding is in progress due to loss of RPV water level indication.

• Torus Average Water temperature is 150°F and rising slowly.

• The three available RHR pumps are injecting into the RPV at 10,400 gpm.

• Torus level is -1 foot and lowering steadily due to RPV injection.

The following trends have just been reported to the CRS from panel and outplant operators:

• RPV pressure is beginning to rise

• RHR loop flows are lowering slowly.

• RHR pump amps are lowering slowly.

• RHR pump discharge pressure is rising slowly.

• Torus water level has stopped lowering and is now stable.

Which one of the following would account for these indications?

A. The Main Steam lines are showing indications of being full.

B. The ECCS suction strainers are becoming blocked.

C. The elevated Drywell air temperature is affecting the RHR system indications.

D. The low Torus water level and rising Torus temperature are affecting RHR pump NPSH.

CORRECT ANSWER: A JUSTIFICATION: Indications of a flooded vessel are RPV pressure rising. Additionally, IF injection sources are aligned with suction from the torus, THEN suppression pool water level will initially lower (caused by flooding the RPV and steam lines) and then stabilizes when the steam lines are full.

B is incorrect: This would cause lowering or erratic flow and amps but not rising discharge pressure.

C is incorrect: Drywell air temperature is very elevated and has caused the loss of RPV level indications but has no effect on the trends provided.

D is incorrect: This would cause lowering or erratic flow and amps but not rising discharge pressure.

REFERENCE:

C.5-3305 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - Edits to stem and choices 295030 Low Suppression Pool TIER: 1 GROUP: 1 CATEGORY:

Water level K/A: EA2.03 IMPORTANCE: RO 3.7 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Reactor pressure DIFFICULTY 3 LESSON PL: MT-ILT-EOP-006L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

16. The plant was at rated conditions when an event resulted in the current RPV Level and trend?

40 0 If RPV level continues to lower, what is the earliest approximate time that ALL RHR and Core Spray pumps will be running? (Assume a Blowdown is NOT required).

A. 1201 B. 1206 C. 1216 D. 1221 CORRECT ANSWER: C JUSTIFICATION: Once -47 is reached a 15 minute timer starts. If level remains below -47 for the 15 minutes a start sequence will begin for the RHR and Core Spray pumps at intervals of 5, 10, 15, 20 or 25 seconds depending on if the EDGs or 1AR are supplying power to the essential buses. Based on the process computer plot trend, -47 is reached at approximately 1200 so all 6 low pressure ECCS pumps should be running by 1216.

A is incorrect: This would be correct for an ECCS start signal on high drywell pressure but this wouldnt be expected for just a LONOP.

B is incorrect: Plausible for confusion with the 5 minute timer following a LPCI loop select signal.

D is incorrect: Plausible as the 15 minute timer used to be a 20 minute timer prior to a recent plant modification.

REFERENCE:

B.03.04-02 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 1 GROUP: 1 CATEGORY: 295031 Reactor Low Water Level K/A: 2.1.19 IMPORTANCE: RO 3.9 COG LEVEL: 3 PEO K/A DESCRIPTION: Ability to use plant computers to evaluate system or component status.

DIFFICULTY 3 LESSON PL: M8107L-023 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

17. The plant is at rated conditions when an event occurred resulting in an ATWS condition. The CRS has entered C.5-2007 (Failure to Scram) and directs the BOP operator to inhibit ADS.

What is the basis IAW C.5-2007 (FAILURE TO SCRAM) for performing this step?

Inhibiting ADS prevents A. a large RPV water level shrink resulting in the addition of positive reactivity.

B. a rapid loss of RPV inventory that would result in a loss of adequate core cooling.

C. the addition of a large amount of heat to the suppression pool which would challenge the Heat Capacity limit.

D. a power excursion due to the injection of cold, unborated water as RPV pressure lowers which could result in core damage.

D IS CORRECT: In C.5-2007, RPV water level may be intentionally lowered below the ADS setpoint to reduce reactor power. ADS actuation is prevented for several reasons including rapid, uncontrolled injection of relatively cold, unborated water could occur as RPV pressure decreases. If the reactor is not shutdown or if the shutdown margin is small, this could add sufficient positive reactivity to cause a power excursion large enough to damage the core.

A is incorrect: Positive reactivity would be added but not from shrink.

B is incorrect: This would not occur with all injections sources available.

C is incorrect: Although unnecessary heat would be added, this is not the reason for performing the step.

REFERENCE:

C.5.1-2007 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2009 NRC Exam #24 TIER: 1 GROUP: 1 CATEGORY: 295037 K/A: EK1.06 IMPORTANCE: RO 4.0 COG LEVEL: 1B K/A DESCRIPTION: Knowledge of the operational implications of the following concepts as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Cooldown effects on reactor power.

DIFFICULTY 2 LESSON PL: M8114L-005 OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

18. The plant was at rated conditions when an event occurred resulting in the following PCS indications for 75 minutes:

Using the PCS indications and EAL Matrix above; which of the following is correct?

STACK and RB VENT Entry Into SPDS Indications C.5-1400 (RADIOACTIVITY RELEASE CONTROL)

A. VALIDATED REQUIRED B. VALIDATED NOT REQUIRED C. NOT VALIDATED REQUIRED D. NOT VALIDATED NOT REQUIRED CORRECT ANSWER: A JUSTIFICATION: The PCS indications show validated data (Green Checks). The Stack-gas monitor reading is above the Alert level on the EAL Matrix which is an EOP-1400 entry condition.

B is incorrect: Vent indications are below Alert but EOP-1400 entry is required because the Stack is above the ALERT level.

C is incorrect: ALERT level is reached; however Data is validated (green checks). Plausible as some displays use YELLOW for invalidated data.

D is incorrect: Data is validated as annotated by the GREEN checks and EOP entry condition is required.

REFERENCE:

C.5.1-1400 PCS Users Guide 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2015 NRC Exam #18 TIER: 1 GROUP: 1 CATEGORY: 295038 High Off-Site Release Rate K/A: EK2.04 IMPORTANCE: RO 3.9 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following: Stack-gas monitoring system.

DIFFICULTY 2 LESSON PL: M8107l-076 OBJECTIVE: 6

2020 MONTICELLO ILT NRC EXAM - KEY

19. The plant was at rated conditions when a Cable Spreading Room fire required an immediate evacuation of the Control Room. C.4-C (SHUTDOWN OUTSIDE CONTROL ROOM)

Immediate Actions have been performed.

Complete the statement below concerning the performance of these Immediate Actions?

The plant is Scrammed and the Reactor Mode Switch is A. left in RUN to ensure the CONTAINMENT VENT RUN MODE INTLK remains in effect.

B. left in RUN to maintain the MSIVs open and allow for plant cooldown from the ASDS panel.

C. left in RUN to prevent an inadvertent depressurization of the vessel if a pressure regulator failure were to occur.

D. placed in SHUTDOWN to ensure the reactor has a positive shutdown signal while the Control Room is unoccupied.

CORRECT ANSWER: C JUSTIFICATION: If immediate evacuation is required the plant is scrammed and the Mode Switch is left in RUN to allow for a Group 1 Isolation if RPV pressure lowers to <840 psig. This may occur because there is a chance of a pressure regulator failure occurring within the assumed 10 minutes required to establish ASDS control.

A is incorrect: Although this interlock would remain in effect and is plausible, this is not the reason for performing this step.

B is incorrect: Plausible as the switch is left in RUN and leaving the MSIVs open for cooldown is a viable reason.

However, it is actually left in this position to ensure the MSIVs close.

D is incorrect: Plausible as the normal immediate action after pushing the scram push buttons is to place the Mode switch in shutdown.

REFERENCE:

C.4-C & Bases 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2018 NRC Exam #6 - Previous 2 NRC Exams TIER: 1 GROUP: 1 CATEGORY: 600000 Plant Fire on Site K/A: AK3.04 IMPORTANCE: RO 2.8 COG LEVEL: 1B K/A DESCRIPTION: Knowledge of the reasons for the following responses as they apply to Plant Fire on Site:

Actions contained in the abnormal procedures for plant fire on site.

DIFFICULTY 2 LESSON PL: MT-ILT-AOP-025L OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

20. The plant was at rated conditions when a Main Generator over voltage condition occurred resulting in a Generator Lockout and a Station Blackout (SBO).

Which actions from C.4-A (REACTOR SCRAM) can be successfully performed by the OATC?

1. Insert SRM and IRM detectors

2. Observe the negative reactor period for the scram conditions

3. Close both discharge valves for the tripped recirculation pumps A. 1 ONLY.

B. 2 ONLY.

C. 2 and 3 ONLY.

D. 1, 2 and 3.

CORRECT ANSWER: B JUSTIFICATION: SRM Period indication would be available because it is powered from SRM 24 VDC.

A is incorrect: Correct actions to take but SRMs and IRM cannot be inserted due to loss of power to L38 and Y-20 (detector drive relay power supply).

C is incorrect: Correct action to take; however, AC power would be lost to these valve actuators.

D is incorrect: Correct actions to take but SRMs and IRM cannot be inserted due to loss of power to L38 and Y-20 (detector drive relay power supply) and AC power would be lost to these valve actuators.

REFERENCE:

C.4-B.09.13.B C.4-A 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2010 NRC Exam #20 700000 Generator Voltage and Electric TIER: 1 GROUP: 1 CATEGORY:

Grid Disturbances K/A: AA1.04 IMPORTANCE: RO 4.1 COG LEVEL: 2DR K/A DESCRIPTION: Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Reactor Controls.

DIFFICULTY 3 LESSON PL: MT-ILT-AOP-024L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

21. The plant is at rated conditions when a malfunction occurs that results in degrading Main Condenser vacuum from excessive air in-leakage. Complete the following statement:

Excessive Main Condenser air in-leakage will cause Off-Gas process flowrate to rise and A. result in recombiner temperatures exceeding 850°F design limit.

B. exceed the capacity of the off-gas storage compressor and raise delay line pressure.

C. result in an AO-7557A/B 11/12 RECOMBINER TRAIN OUTLET high pressure isolation.

D. result in an AO-1085A/B, 11/12 COMBINED 2ND STAGE SUCT low pressure isolation.

CORRECT ANSWER: B JUSTIFICATION: If the steam jet air ejectors and Recombiners process off-gas at flowrates greater than design, off-gas storage compressor capacity will be exceeded and delay line pressure will increase. It may be necessary to bypass the storage system.

A is incorrect: An off-gas flow spike will not cause recombiner temperature to exceed the design limit of 850 F. Plausible as temperature will go up but the design limit will not be exceeded.

C is incorrect: A High pressure isolation will not occur from high Offgas flowrate. Plausible as this will occur but will not cause a high pressure isolation.

D is incorrect: A rise in flowrate will not cause a low pressure condition. Plausible for opposite effect causing a low pressure isolation.

REFERENCE:

B.-7.02.01-02 10 CFR 55.41b(13)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank 295002 Loss of Main Condenser TIER: 1 GROUP: 2 CATEGORY:

Vacuum K/A: AA2.04 IMPORTANCE: RO 2.8 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to Loss of Main Condenser Vacuum: Offgas system flow.

DIFFICULTY 3 LESSON PL: M8107L-091 OBJECTIVE: 8

2020 MONTICELLO ILT NRC EXAM - KEY

22. The plant is at rated conditions when multiple alarms are received including 5-B-24 (REACTOR WATER LEVEL HI/LOW). RPV water level is 41 and rising. C-05 RPV level control indications are on the following page.

What action must be taken for the given conditions?

A. Place ONLY the CV 6-12A MAN/AUTO STATION in MANUAL.

B. Place ONLY the CV 6-12B MAN/AUTO STATION in MANUAL.

C. Place BOTH CV 6-12A/B MAN/AUTO STATIONS in MANUAL.

D. Place the Digital Feedwater MASTER Level Controller in MANUAL.

CORRECT ANSWER: C JUSTIFICATION: RPV level being 41 is high outside the normal band (30-40). Indications are given for a locked A Feedwater Reg Valve that is drifting open causing RPV level to rise. This requires entry into the abnormal procedure for Loss of RPV Level control. This procedures immediate action directs the operator to take manual control of BOTH main Feedwater regulating valves to control RPV level. The picture shows the A Main Feedwater Reg. valve RESET light on, but this actually means that this Reg. valve is locked. This action is taken to remove DFCS and ensure the controller is in direct control of RPV water level.

A is incorrect: Plausible if examinee believes that the red light on means the valve lock is reset. This action will not allow control of RPV level since this regulating valve is locked.

B is incorrect: Plausible as this used to be the required procedural action, but now BOTH Main FW Reg valves are taken to manual.

D is incorrect: This is not a required action as this will have no effect on the locked reg. valve.

REFERENCE:

C.4-B.05.07.A C.6-005-B-40 10 CFR 55.41(7, 10)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2010 NRC #16 TIER: 1 GROUP: 2 CATEGORY: 295008 High Reactor Water Level K/A: 2.4.49 IMPORTANCE: RO 4.6 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

DIFFICULTY 2 LESSON PL: MT-ILT-AOP-011L OBJECTIVE: 1

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

23. The plant is stable in Mode 1 with a startup in progress at 12% reactor power.

Which of the following malfunctions will cause a REDUCTION in Jet Pump NPSH?

Loss of .

A. Air to a Main Feedwater Regulating Valve.

B. Power to a Main Feedwater Regulating Valve.

C. Air to the Low Flow Feedwater Regulating Valve.

D. Control signal to the Low Flow Feedwater Regulating Valve.

CORRECT ANSWER: D JUSTIFICATION: The examinee must determine that a reduction in Jet Pump NPSH will be caused by lowering RPV water level. Based on the indications, the Low Flow Feedwater Regulating Valve will only be in-service. A loss of signal the LFRV will cause it to fail closed resulting in lowering RPV water level and a reduction in Jet Pump NPSH.

A and B are incorrect: Both of these malfunctions will cause the MFRVs to lock and potentially drift. This may cause a reduction in Jet Pump NPSH; however, the MFRVs are not placed in service during a startup until approximately 17%

power or 100 MWe on the Main Turbine Generator which is not online yet.

C is incorrect: Loss of air to the LFRV will cause it to fail as-is, RPV water level and Jet Pump NPSH should remain steady.

REFERENCE:

B.05-07-01 10 CFR 55.41b(3)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #21 - Edits to stem TIER: 1 GROUP: 2 CATEGORY: 295009 Low Reactor Water Level K/A: AK1.03 IMPORTANCE: RO 2.7 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of the operational applications of the following concepts as they apply to LOW REACTOR WATER LEVEL: Jet pump NPSH.

DIFFICULTY 3 LESSON PL: M8107L-068 OBJECTIVE: 5

2020 MONTICELLO ILT NRC EXAM - KEY

24. The plant was at rated conditions with Drywell Atmospheric Cooling (DAC) in Mode 1.

If Drywell temperature in the CRD under-vessel area reaches 155°F, which of the following AUTOMATIC actions will occur?

A. DAC remains in Mode 1 (Normal Mode) with 3 fans in service.

B. DAC will align to Mode 5 (Scram Mode) with 4 fans in service.

C. DAC will align to Mode 6 (Post Scram Mode) with 3 fans in service.

D. DAC will align to Mode 7 (Shutdown Mode) with 4 fans in service.

CORRECT ANSWER: B JUSTIFICATION: The Drywell Atmosphere Cooling system is started manually and is normally in operation. The SCRAM mode of operation is initiated by four temperature switches, TS-1431, TS-1432, TS-1433, and TS-1434 located in the control rod drive area. These temperature switches are arranged in a one-out-of-two twice logic array. When the Temperature in the control rod drive area reaches 150°F, the standby fan will start and all dampers will open, except V-D-31 and V-D-33, which will close, thereby providing maximum cooling to the CRD area.

A is incorrect: Four fans will be running but DAC will shift to Mode 5 which will shift to a specific damper alignment.

C is incorrect: Post Scram Mode has the same damper alignment as the Scram mode, however 4 fans will be running.

D is incorrect: Four fans will be running but DAC will shift to Mode 5 which will shift to a specific damper alignment.

REFERENCE:

B.08.16-02 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #14 - Edits to stem and distractor TIER: 1 GROUP: 2 CATEGORY: 295012 High Drywell Temperature K/A: AK2.02 IMPORTANCE: RO 3.6 COG LEVEL: 1 I K/A DESCRIPTION: Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following: Drywell cooling.

DIFFICULTY 2 LESSON PL: M8107L-044 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

25. A plant startup is in progress and control rod 34-39 is selected to be NOTCHED OUT from Position 10 to Position 12. The RWM Withdraw Limit is Position 16.

After initiating a single ROD OUT NOTCH Sequence, the OATC observes the following:

• 4-Rod Display indicates Control Rod 34-39 has STOPPED at Position 14

• Control Rod Select Matrix Backlighting for Control Rod 34-39 is ON

• Full Core Display white select light for Control Rod 34-39 is OFF

• The 2 SEC SELECT BLOCK red light is ON Which one of the following CORRECTLY identifies the cause of these indications?

A. The RMCS timer has failed.

B. Rod select power has been lost.

C. The RWM is enforcing a Withdraw Block.

D. The RPIS Reed Switch at Position 11 momentarily closed.

CORRECT ANSWER: A JUSTIFICATION: An interlock is provided in RMCS to disable rod withdrawal and prevent inadvertent reactivity addition in the event the rod drive timer switch should fail while a rod withdrawal movement is in progress. If such a failure occurred, the interlock would cause the directional control solenoid valves of the selected rod to be disconnected from the drive control busses of the RMCS following a time delay of approximately two seconds. Proper operation of the interlock is demonstrated when the associated rod select light located in the full core display is OFF. ARP 5-A-19 (ROD SELECTOR BLOCK TIMER MALFUNCTION) confirmatory indications: Indicating light 2 SEC SELECT BLOCK red light is ON (Panel C-05)

B is incorrect: The backlighting would also be lost.

C is incorrect: The control rod position is still within the limits the RWM.

D is incorrect: This would not cause the white select light to go out.

REFERENCE:

B.05.05-01 ARP 5-A-19 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank TIER: 1 GROUP: 2 CATEGORY: 295014 Inadvertent Reactivity Addition K/A: AK3.02 IMPORTANCE: RO 3.7 COG LEVEL: 3 SPK K/A DESCRIPTION: Knowledge of the reasons for the following as they apply to INADVERTENT REACTIVITY ADDITION: Control rod blocks DIFFICULTY 3 LESSON PL: M8107L-032 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

26. The plant was operating at rated conditions when an event occurred resulting in the following:

• Drywell pressure is 1.6 psig

• Reactor water level is 7 inches

• Fuel Pool radiation monitors indicate 52 mrem/hr

• Reactor Building vent radiation monitors indicate 21 mrem/hr Which one of the following identifies an expected response to current plant conditions?

A. RCIC will automatically initiate.

B. SBGT will automatically initiate.

C. RWCU will automatically isolate.

D. LPCI Loop Select Logic will energize.

CORRECT ANSWER: B JUSTIFICATION: Fuel Pool activity levels have reached the Partial Group 2 isolation and SBGT initiation setpoint. The Fuel Pool monitors upscale initiation setpoint is 50 mrem/hr. (the Reactor Building vent plenum monitors have a high trip of 26 mrem/hr)

A is incorrect: Although a 9 Low level Group 2 isolation and reactor scram signal is present, RCIC does not automatically initiate until Low-Low Level (-47) is reached.

C is incorrect: RWCU doesnt automatically isolate until 1.84 psig in the Drywell or -47 RPV water level. Plausible, however, because RWCU previously did automatically isolate at 9.

D is incorrect: LPCI loop select logic will not energize until 1.84 psig in the drywell or -47 RPV water level.

REFERENCE:

B.04.02-01 B.05.11-02 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2013 NRC Exam #24 295033 High Secondary Containment Area TIER: 1 GROUP: 2 CATEGORY:

Radiation Levels K/A: EA1.01 IMPORTANCE: RO 3.9 COG LEVEL: 1I K/A DESCRIPTION: Ability to operate and/or monitor the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area radiation monitoring system.

DIFFICULTY 2 LESSON PL: M8107L-008 OBJECTIVE: 7.d

2020 MONTICELLO ILT NRC EXAM - KEY

27. A transient occurred 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago resulting in the following current conditions:

• Torus temperature is 165°F

• Drywell temperature is 275°F

• Drywell Oxygen concentration is 3.5%

• Drywell Hydrogen concentration is 4.2%

• Drywell pressure is 14.6 psig and lowering

• RPV water level is -164 inches and steady

• 11 Core Spray pump is the only injection source and is injecting at 3200 gpm Which of the following is correct for the above conditions?

A. Adequate core cooling is not being maintained.

B. The Drywell EQ Temperature Limit is being exceeded.

C. The Torus Design Temperature Limit is being exceeded.

D. The Drywell Hydrogen Lower Flammability Limit is being exceeded.

CORRECT ANSWER: D JUSTIFICATION: The accumulation of a significant amount of hydrogen is indicative of a loss of adequate core cooling.

Hydrogen concentration of 4% is the lower flammability limit which is double of what is expected during a DBA LOCA. In the above conditions the primary containment atmosphere has degraded enough to where a dangerous explosive mixture is present and if ignited could result in damage to the primary containment.

A is incorrect: With RPV level above 2/3 core height and one CS injecting at >3050 gpm, adequate core cooling is being maintained.

B is incorrect: The Drywell EQ temperature limit is 338°F which is not being exceeded.

C is incorrect: Torus design temperature is 281°F which is not being exceeded.

REFERENCE:

C.5.1-1200 10 CFR 55.41(9)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - Edits to stem and choices TIER: 1 GROUP: 2 CATEGORY: 500000 High CTMT Hydrogen Conc.

K/A: EA2.03 IMPORTANCE: RO 3.3 COG LEVEL: 3 SPR/SPK K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to High Primary Containment Hydrogen Concentrations: Combustible limits for drywell.

DIFFICULTY 3 LESSON PL: MT-ILT-EOP-003L OBJECTIVE: 3.b

2020 MONTICELLO ILT NRC EXAM - KEY

28. The plant was at rated conditions when a significant LOCA occurred. Given the following:

• ADS has automatically initiated

• An RPV depressurization is in progress.

• ALL RHR and Core Spray pumps are running Complete the following statement that describes the effect on the ADS System if ALL RHR and Core Spray pumps TRIP. (Assume RPV water level remains constant at -80 inches.)

Automatic Depressurization of the Reactor...

A. continues without Core Spray or RHR pumps running due to the seal-in logic.

B. will cease and re-initiate only if ALL Core Spray and RHR pumps are restarted.

C. will cease and re-initiate 107 seconds after a Core Spray or RHR pump is restarted.

D. will cease; both inhibit switches must be taken to INHIBIT and back to AUTO to re-establish depressurization.

CORRECT ANSWER: C JUSTIFICATION: If the RHR and CS pumps trip, relays K10A and K12A are de-energized, which open up the K10A and K12A contacts to de-energize the 107 second timer, closing the valves. If one ECCS pump is restarted, contacts K10A and K12A close to start the107 second timer again.

A is incorrect: If RPV water level went above -47 inches, it would continue because of the seal in. This is not the case if the pumps trip. Depressurization would stop.

B is incorrect: It will cease and re-initiate if one pump restarts. All pumps are not required to restart.

D is incorrect: Plausible because taking the switches to inhibit does reset the timer but it wouldnt be required to restart depressurization.

REFERENCE:

B.03.03-01 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #43 TIER: 2 GROUP: 1 CATEGORY: 203000 RHR/LPCI: Injection Mode K/A: K3.03 IMPORTANCE: RO 4.2 COG LEVEL: 1I K/A DESCRIPTION: Knowledge of the effect that a loss or malfunction of the RHR/LPCI: INJECTION MODE will have on the following: Automatic depressurization logic.

DIFFICULTY 3 LESSON PL: M8107L-025 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

29. The plant is at rated conditions with the 1AR Transformer ISOLATED for modifications. A loss of normal off-site power (LONOP) then occurs coincident with an ECCS initiation signal.

Complete the following statement for the above conditions.

Nominally, #11 and #12 RHR Pumps will auto start _________ after the LONOP.

A. 10 seconds B. 15 seconds C. 20 seconds D. 25 seconds CORRECT ANSWER: B JUSTIFICATION: If normal auxiliary electrical power is not available at the time of an ECCS automatic initiation, a 10 second delay is added to allow the two EDG to start, come up to speed and for their respective breakers to CLOSE. This will be followed by a 5 second delay before starting 11 & 12 RHR Pumps. A total of 15 seconds will lapse before 11 and 12 RHR pumps start.

If normal auxiliary electrical power is available at the time of an ECCS automatic initiation, the starting of the RHR and Core Spray pumps will be delayed to limit the maximum motor starting load. The time delays employed are as follows:

Time Essential Bus 15 Essential Bus 16 5 seconds 11 RHR Pump 12 RHR Pump 10 seconds 13 RHR Pump 14 RHR Pump 15 seconds 11 Core Spray Pump 12 Core Spray Pump A, C and D are incorrect: Plausible start times.

REFERENCE:

B.03.04-02 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2016 NRC Exam #50 TIER: 2 GROUP: 1 CATEGORY: 203000 RHR/LPCI Injection Mode K/A: K4.01 IMPORTANCE: RO 4.2 COG LEVEL: 1I K/A DESCRIPTION: Knowledge of RHR/LPCI INJECTION MODE design features and/or interlocks which provide for the following: Automatic system initiation and/or injection.

DIFFICULTY 2 LESSON PL: M8107L-023 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

30. The 11 RHR Pump is operating in a Normal Shutdown Cooling Mode. Given the following:

11 RHRSW Pump flow is 2000 gpm 11 RHR Pump flow is 3800 gpm RHR HX dP is 50 psid Which of the following actions would BOTH raise the cooldown rate AND be allowed by procedure?

Throttle A. OPEN RHR-4-1 (11 RHR HX INLET).

B. OPEN MO-2002 (11 RHR HX BYPASS).

C. OPEN RHR-5-1 (11 RHR HX DISCHARGE).

D. CLOSE CV-1728 (11 RHR HX RHRSW OUTLET).

CORRECT ANSWER: A JUSTIFICATION: If increased cooldown rate is desired, then perform one or more of the following actions as required to achieve the desired cooldown rate:

• Throttle open RHR-4-1

• Throttle closed MO-2002

• Increase RHRSW flow while maintaining RHR HX dP > 20 psid Operating the RHRSW controller in manual from the control room in the open direction will raise RHRSW flow which is allowed as long as dP remains > 20 psid. With the given conditions there is plenty of room to adjust.

B and D are incorrect: Adjusting these valves is allowed per procedure but the wrong direction is given and both adjustments will cause cooldown rate to lower.

C is incorrect: This adjustment would raise cooldown rate but the valve is normally full open and this adjustment isnt IAW the procedure.

REFERENCE:

B.03.04-05 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2018 NRC Exam #29 TIER: 2 GROUP: 1 CATEGORY: 205000 Shutdown Cooling K/A: K5.03 IMPORTANCE: RO 2.8 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Heat removal mechanisms DIFFICULTY 2 LESSON PL: M8107L-023 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

31. The plant was at rated conditions when a LOCA occurred. Given the following:

• RPV water level lowered to -43" and is now +25"

• RPV pressure is 650 PSIG and slowly lowering

• Drywell pressure 5 PSIG and rising slowly

• Torus level is +1 foot and rising slowly Assuming NO operator actions; is HPCI Injecting/NOT Injecting and from where is its suction source aligned to?

A. Injecting CSTs B. Injecting Torus C. NOT Injecting CSTs D. NOT Injecting Torus CORRECT ANSWER: B JUSTIFICATION: The specified conditions satisfy the operational requirements for HPCI operation (high DW pressure 1.84#) only and its suction would automatically realign to the Torus with Torus level greater than +2.

A is incorrect: The HPCI suction would align to the Torus once Torus level reached +2.

C is incorrect: Plausible to confuse HPCI with low pressure ECCS systems which wont line up to inject until 420#.

D is incorrect: Plausible to confuse HPCI with RCIC which only initiates on low RPV water level of -47.

REFERENCE:

B.03.03-01 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 206000 HPCI K/A: A1.04 IMPORTANCE: RO 3.7 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to predict and/or monitor changes in parameters associated with HPCI controls including:

Suppression pool level.

DIFFICULTY 2 LESSON PL: M8107L-002 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

32. The plant is at rated conditions with the Service Water (SW) system functional.

• A cooling water leak was discovered on V-AC-5 (DIV 1 ECCS ROOM COOL UNIT)

• The Division 1 RHR/Core Spray Pump Room temperature is 91°F

• The cooling water line to V-AC-5 was isolated

• V-AC-5 is NOT available Which of the following is correct concerning the operability of 11 Core Spray (CS) Pump?

A. 11 CS Pump is operable since motor cooling is not affected.

B. 11 CS Pump is operable provided room temperature is <104°F.

C. 11 CS Pump is NOT operable without the availability of V-AC-5.

D. 11 CS Pump is NOT operable because room temperature is >90°F.

CORRECT ANSWER: C JUSTIFICATION: The RHR/Core Spray Room Cooling Units, V-AC-4 and V-AC-5, provide area cooling to remove heat generated from the RHR/CS pump motors. The cooling units must be available and function properly to maintain RHR room temperature below acceptable limits to prevent overheating of components in the room. The RHR room coolers are required and assumed started within 10 minutes of an accident when all 3 pumps are running. RHR and CS Pumps must be declared inoperable if the respective room cooler is NOT available.

A is incorrect: A CS Pump can remain operable with a loss of motor cooling.

B is incorrect: This is an operability requirement that is currently not being exceeded; however, without V-AC-5 the pump is still inoperable.

D is incorrect: The 90°F operability requirement applies to river temperature, not room temperature.

REFERENCE:

B.03.01-05 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 209001 LPCS K/A: K6.05 IMPORTANCE: RO 2.8 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of the effect that loss or malfunction of the following will have on the Core Spray System: ECCS Room coolers DIFFICULTY 3 LESSON PL: M8107L-005 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

33. The plant is in Mode 3 with operations preparing to add chemicals to the SBLC Storage Tank

• SBLC tank boron concentrations and temperatures are still within limits.

• The RB Operator is standing by to sparge the SBLC tank to ensure adequate mixing.

What action, if any, is required, prior to opening AS-22 (SBLC SPARGER SUPPLY) and why?

A. NO action required; SBLC operability is NOT required in Mode 3.

B. NO action required; boron concentration and temperatures are within limits.

C. Declare one SBLC subsystem inoperable; air may be drawn into the in-service suction line.

D. Declare both SBLC subsystems inoperable; air may be drawn into the common suction line.

CORRECT ANSWER: D JUSTIFICATION: Per Condition Report 99000953, it is possible to draw air into the SBLC suction while sparging the SBLC storage tank. If enough air were to enter the SBLC pump suction, both pumps would be inoperable. Since it is difficult to quantify the amount of air entering the pump suction, and other methods of demonstrating acceptable pump performance are undesirable, the SBLC system will be declared inoperable whenever sparging the SBLC storage tanks."

Procedure Step 2. If SBLC is required to be operable, then evaluate TS 3.1.7 for SBLC inoperable Procedure Step 3. Fully open AS-22 A is incorrect: SBLC is required to be operable in Modes 1, 2 and 3.

B is incorrect: SBLC system will be declared inoperable whenever sparging the SBLC storage tanks regardless of concentration C is incorrect: Both are required to be declared inoperable when sparging.

REFERENCE:

B.03.05-05.G.2 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 211000 SBLC K/A: A2.06 IMPORTANCE: RO 3.1 COG LEVEL: 1 P/B K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the SBLC System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings.

DIFFICULTY 3 LESSON PL: M8107L-004 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

34. The plant was at normal rated conditions when a Recirc Pump tripped. Given the following:

• SINGLE LOOP operations have been established

• The EFWS Function is NOT enabled

• Rx Recirc Drive flow is 44%

What power approximates when 5-A-22 (APRM UPSC/INOP TRIP) will be received?

A. 60%

B. 70%

C. 80%

D. 92%

CORRECT ANSWER: C JUSTIFICATION: With one recirc pump running the single loop EFWS disabled equation must be used to determine the STP SLO APRM Upscale RPS Scram setpoint. This equation with EFWS disabled is .55(W) + 55.6. W is equal to percent total recirc flow which in this case is 44%. The RPS Scram setpoint would be 79.8%.

M8107L-072 LO7: Describe, from memory, RPS automatic initiation signals, operation, control, automatic functions, flowpaths, alarms, setpoints and/or interlocks.

A is Incorrect: This number represents the SLO STP rod block with EFWS enabled for the given flow. 2.49(w) - 49.6%

B is Incorrect: This number represents the SLO scram with EFWS enabled. 2.49(w) - 39.3 = 79.80%

D is Incorrect: This number represents the TLO scram without EFWS enabled. 0.61(w) +65.2 = 92.04%

REFERENCE:

ARP 5-A-22 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 212000 RPS K/A: A3.08 IMPORTANCE: RO 3.7 COG LEVEL: 3 PEO K/A DESCRIPTION: Ability to monitor automatic operations of the RPS system including: Recirc Pump Trip DIFFICULTY 3 LESSON PL: M8107L-072 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

35. A plant startup is in progress in Mode 2 with all IRMs on Range 9 or 10. An event occurs resulting in the following:

• IRM 11 has failed fully upscale

• The fault has NOT been cleared yet

• A Rod Block and Half Scram have occurred

• C-36 indications for IRM 11 are on the following page Which of the following action(s) will clear the Rod Block?

A. Bypass IRM 11 on C-05.

B. Reset the fault on C-36 ONLY.

C. Place the IRM 11 Mode Switch to STANDBY on C-36 ONLY.

D. Place the IRM 11 Mode Switch to STANDBY AND reset the fault on C-36.

CORRECT ANSWER: A JUSTIFICATION: With the fault not clear, IRM 11 must be bypassed to clear the rod block. Placing the mode switch in Standby will only clear the back panel lights.

B is incorrect: Plausible as this would clear the rod block if the fault was cleared.

C is incorrect: Plausible as this will remove the feed to RMCS, but the fault must be clear and reset.

D is incorrect: Plausible as this would clear the rod block if the fault was cleared

REFERENCE:

B.05.01.01 10 CFR 55.41 (7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 215003 IRM System K/A: A4.04 IMPORTANCE: RO 3.1 COG LEVEL: 3 PEO K/A DESCRIPTION: Ability to manually operate and/or monitor in the control room: IRM back panel switches, meters, and indicating lights.

DIFFICULTY 4 LESSON PL: M8107L-064 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

36. A plant startup is in progress with the Mode Switch in STARTUP. Given the following:

• All SRM indicators are on-scale with detectors partially withdrawn

• All IRMs are on Range 1 reading between 10-50 on the 125 scale.

An event occurs that results in the following C-05 indication:

Which one of the following will cause the above conditions?

A. An SRM reading lowers to 90 cps.

B. An SRM reading rises to 60,000 cps.

C. An SRM period shortens to 10 seconds.

D. An IRM reading lowers to 4 on the 125 scale.

CORRECT ANSWER: A JUSTIFICATION: This will cause annunciator 5-A-28 (SRM RETRACT NOT PERMITTED) and the white RETRACT PERMIT indicating light on C-05 to go off AND will cause a rod block if IRMs are < Range 3. The rod block will result in annunciator 5-A-3 (ROD WITHDRAWAL BLOCK) and the rod out permit light to go out as shown in the picture.

B is incorrect: The SRM upscale rod block is set at 9.07 x 104 or 90,700 cps (Nominal 1 x 105). 60,000 cps would be 6 x 104 and not above the HI (rod block).

C is incorrect: If the period is shorter than 12 seconds a period alarm is received but this doesn't cause a rod block.

D is incorrect: An IRM reading lowering to <5 will result in a rod block only if IRMs are on range 2 or higher.

REFERENCE:

B.05.01.01-02 ARP 5-A-3 ARP 5-A-28 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2013 NRC Exam #36 TIER: 2 GROUP: 1 CATEGORY: 215004 Source Range Monitor K/A: K4.01 IMPORTANCE: RO 3.7 COG LEVEL: 3 SPR K/A DESCRIPTION: Knowledge of SRM system design features and/or interlocks which provide for the following: Rod withdrawal blocks DIFFICULTY 3 LESSON PL: M8107L-054 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

37. The plant is in Mode 2 and operators are preparing to withdraw the first control rod for a reactor startup. All operable SRM detectors are fully inserted.

Given the sets of SRM readings (in counts per second), would the SRM system be considered OPERABLE or NOT OPERABLE for startup? Evaluate each set of SRM readings separately.

SRM 21 22 23 24 Set 1) Inoperable 3 4 2 Set 2) 4 2 3 2 Set 3) 4 2 3 3 A. Set 1) OPERABLE for startup Set 2) OPERABLE for startup Set 3) NOT OPERABLE for startup B. Set 1) NOT OPERABLE for startup Set 2) OPERABLE for startup Set 3) NOT OPERABLE for startup C. Set 1) OPERABLE for startup Set 2) NOT OPERABLE for startup Set 3) OPERABLE for startup D. Set 1) NOT OPERABLE for startup Set 2) NOT OPERABLE for startup Set 3) OPERABLE for startup CORRECT ANSWER: D JUSTIFICATION: In order to meet the general design requirement to provide the nuclear information needed for knowledgeable and efficient reactor startup and low flux level operation, the source range monitor must Provide a minimum signal-to-noise count ratio of 3:1 and a minimum count rate of 3 counts per second with all control rods inserted prior to initial power operation. During startup in MODE 2, three of the four SRM channels are required to be OPERABLE in order to provide a representation of the overall core response during those periods when reactivity changes are occurring.

A is incorrect: Set 1 & 2 only 2/4 SRMs (22 & 23) are operable. 3 of 4 required.

B is incorrect: Set 2 only 2/4 SRMs (21 & 23) are operable. Set 3 is operable for startup 3/4 (21, 23 & 24).

C is incorrect: Set 1 only 2/4 SRMs (22 & 23) are operable. 3 of 4 required.

REFERENCE:

B.05.01.01-05 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 215004 SRMs K/A: 2.4.21 IMPORTANCE: RO 4.0 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control etc.

DIFFICULTY 3 LESSON PL: M8107L-054 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

38. The plant is at rated conditions when a RPS MG Set malfunction results in the following:

Which of the following PRNM components, if any, will lose power with the above condition?

A. RBM A only.

B. APRMs 1 & 3 only.

C. 2 of 4 Voters - 1 & 3 only.

D. None, they are auctioneered with RPS Bus B.

CORRECT ANSWER: C JUSTIFICATION: Primary power (120 VAC) for the PRNM system is provided from bus A and bus B of the RPS Power Distribution System. The 2 of 4 Voters are powered from the associated RPS bus; RPS A powers 2 of 4 Voters 1 and 3, RPS B powers 2 of 4 Voters 2 and 4.

A and B are incorrect: APRM and RBM drawers are powered from both RPS A and RPS B through LVPS and auctioneering circuits.

D is incorrect: The 2 of 4 voters do not receive auctioneered power.

REFERENCE:

B.5.1.2-05 B.09.12-05 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2013 NRC Exam #37 TIER: 2 GROUP: 1 CATEGORY: 215005 APRM/LPRM K/A: K1.01 IMPORTANCE: RO 4.0 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of the physical connections and/or cause-effect relationships between APRM/LPRM systems and the following: RPS DIFFICULTY 3 LESSON PL: M8107L-066 OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

39. An event occurred that resulted in a complete loss of D31 (125/250 VDC Distribution Panel)

Which of the following systems will be affected for the given power loss?

A. HPCI B. RCIC C. #12 EDG D. Emergency Bearing Oil CORRECT ANSWER: B JUSTIFICATION: D31 supplies DC to one 125 VDC center tapped distribution panel (D33) and two 250 VDC distribution panels (D311 and D313). The examinee must determine that D31 is for division 1 and that it supplies panel D311. All of the major valves for RCIC receive main and/or control power from D311.

A is incorrect: HPCI receives power from Division II 250 VDC Panel D312.

C is incorrect: 12 EDG receives 125 VDC for control power but its from panel D211.

D is incorrect: DC powered pumps in these systems are powered from the 250 VDC NON-1E 17 Battery.

REFERENCE:

ARP 8-A-20 C.4-B.09.09A 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 217000 RCIC K/A: K2.01 IMPORTANCE: RO 2.8 COG LEVEL: 1F K/A DESCRIPTION: Knowledge of electrical power supplies to the following: Motor operated valves.

DIFFICULTY 2 LESSON PL: M8107L-003 OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

40. It has been determined that the following relays are defective and will NOT actuate:

• 14A-K7A (REACTOR LOW LOW LEVEL)

• 14A-K8A (REACTOR LOW LOW LEVEL)

Which of the following is correct concerning the faulted relays?

A. EDGs will fail to start on a valid Low Low Level signal.

B. HPCI will fail to inject on a valid Low Low Level signal.

C. RHR Pumps will fail to start on a valid Low Low Level signal.

D. ADS will fail to depressurize the RPV on a valid Low Low Level signal.

CORRECT ANSWER: D JUSTIFICATION: Using the print provided, it can be determined that these two relays are used for the Division 1 Core Spray and ADS auto initiation on low-low RPV water level. Failure of these relays to initiate ADS on Low Low Level will prevent the ADS system from depressurizing the reactor when required and thus prevent restoration of reactor water level with low pressure systems.

A, B and C are incorrect: These systems all use Core Spray instrumentation for auto start on high drywell pressure and/or low-low RPV water level. EDGs use these relays partially in division 1 and 2 start logic but the EDG will still start.

HPCI and RHR pump starts do not use these relays.

REFERENCE:

NX-7833-21-1 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: NX-7833-21-1 QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 218000 ADS K/A: K3.01 IMPORTANCE: RO 4.4 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of the effect that a loss or malfunction of the ADS System will have on the following: Restoration of reactor water level after a break that does not depressurize the reactor when required.

DIFFICULTY 2 LESSON PL: M8107L-025 OBJECTIVE: 8

2020 MONTICELLO ILT NRC EXAM - KEY

41. What design feature is used to ensure that a single failure of the flow element sensing line will NOT prevent a Group 3 Isolation signal on high system flow?

A. A downscale trip on one of the four RWCU high flow transmitters will initiate a Group 3 Isolation signal.

B. A high Drywell pressure signal at 1.84 psig provides redundancy to the RWCU high system flow Group 3 Isolation signal.

C. A negative differential pressure signal will initiate a Group 3 Isolation signal at an indicated flow of minus 200 (-200) gpm.

D. A single instrument trip will initiate a high system flow Group 3 Isolation signal to ensure conservative automatic action is initiated.

CORRECT ANSWER: C JUSTIFICATION: A break in the RWCU high side instrument line could prevent the 4 flow transmitters from responding to a high flow condition; therefore, a separate flow transmitter provides a separate input to the Group 3 isolation logic. A negative differential pressure condition provides a Group 3 isolation at in indicated flow of -200 gpm.

A is incorrect: This only occurs for radiation detectors that provide input to the partial Group 2 isolation logic.

B is incorrect: High drywell pressure will initiate the Group 3 isolation, however, it is not for redundancy of the high flow signal.

C is incorrect: A single instrument high flow isolation is only in the Group 4 and 5 isolation logic for HPCI and RCIC.

REFERENCE:

B.05.06-02 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank TIER: 2 GROUP: 1 CATEGORY: 223002 PCIS K/A: K4.07 IMPORTANCE: RO 2.8 COG LEVEL: 1I K/A DESCRIPTION: Knowledge of PCIS design features and/or interlocks which provide for the following: Physical separation of system components (to prevent localized environmental factors, electrical faults, and physical events from impairing system response).

DIFFICULTY 3 LESSON PL: M8107L-030 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

42. The plant is operating in Mode 1 with the following conditions:

• SRV H tailpipe temperature is 140°F and rising

• SRV H Amber light remains OFF If these conditions continue, what action must be taken NEXT if SRV H tailpipe temperature exceeds 210°F?

A. Start a Normal Plant Shutdown.

B. Perform a Rapid Power Reduction.

C. Take action for a Stuck Open Relief Valve D. Mix water in the Torus using Core Spray or RHR.

CORRECT ANSWER: D JUSTIFICATION: The given indications are a leaking SRV that will add heat to the torus. IAW the abnormal procedure for leaking SRV, the Core Spray System is placed in the Torus Mixing Mode when tailpipe temperature exceeds 210°F.

This prevents high localized Torus water temperatures since significant heat addition could start beyond this temperature.

A is incorrect: A shutdown should be scheduled to be performed within 30 days to replace the SRV but is not required immediately.

B and C are incorrect: These would be correct procedures to enter if the valve was stuck open but since the amber light is off these procedures wont be entered. The amber light is illuminated once 30 psig is reached in the tailpipe which indicates the SRV is open.

REFERENCE:

C.4-B.03.03.B B.03.03-01 10 CFR: 55.43b(5)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank TIER: 2 GROUP: 1 CATEGORY: 239002 SRVs K/A: K5.04 IMPORTANCE: RO 3.3 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES: Tail pipe temperature monitoring.

DIFFICULTY: LESSON PL: MT-ILT-AOP-006L OBJECTIVE: 7,8

2020 MONTICELLO ILT NRC EXAM - KEY

43. An event occurred resulting in entry into C.5-2002 (Emergency Depressurization) due to high drywell temperature concurrent with a complete loss of 125 VDC Bus A.

As the BOP, the CRS directs you to open all three ADS valves Which SRVs must be used to perform the Emergency Depressurization from C-03?

A. SRVs A, C and D.

B. SRV D and two NON-ADS valves.

C. SRV A & C and one NON-ADS valve.

D. ONLY NON-ADS valves will be available.

CORRECT ANSWER: A JUSTIFICATION: With a loss of 125 VDC Bus A, all power is lost to the A ADS Logic and backup power is lost to the B ADS Logic. 125 VDC Bus B would still be available to actuate ADS with the B ADS Logic. The operator can use all three ADS valves (A, C, & D). The three ADS valves would be the preferred SRV to use for ED as they are EQ qualified up to 335°F.

B and C are incorrect: For Emergency depressurization, if an ADS valve doesnt work the operator is directed to use NON-ADS valves. Both of these are plausible for divisional misconceptions and if the examinee doesnt recall that ADS logic power is auctioneered with 125 VDC B.

D is incorrect: Plausible to think none of the valves would work because the use of the LL SET SRVs requires division A power to be opened from C-03.

REFERENCE:

B.03.03-05 B.03.03-06 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2010 NRC Exam TIER: 2 GROUP: 1 CATEGORY: 239002 SRVs K/A: K6.04 IMPORTANCE: RO 3.0 COG LEVEL: 2DR K/A DESCRIPTION: Knowledge of the effect that a loss or malfunction of the following will have on RELIEF/SAFETY VALVES: DC Power.

DIFFICULTY 3 LESSON PL: M8107L-025 OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

44. The plant is at rated conditions with RPV water level stable at +35 inches. The Digital Feedwater Level Control System (DFCS) is in AUTO with 3-element control.

If the C Main Steam Line Flow input to DFCS instantaneously fails FULLY DOWNSCALE; complete the following statement that describes the expected response of the DFCS System?

DFCS A. shifts to MANUAL control due to a loss of the Main Steam Flow Instrument.

B. RAISES the master controller output due to a Steam Flow to Feed Flow mismatch.

C. LOWERS the master controller output due to a Steam Flow to Feed Flow mismatch.

D. shifts to SINGLE-ELEMENT control due to a loss of the Main Steam Flow Instrument.

CORRECT ANSWER: D JUSTIFICATION: The level control system monitors the quality of these signals and will automatically switch to single element control (where these signals are not required) if a failure is detected. A failure is assumed to exist if a signal is out of range high or low, if there is disagreement between the two feedwater flow signals, or if there is a disagreement among the four steam flow signals.

A is incorrect: Plausible auto action for the level controller with an out-of-range input, but this will not occur under these conditions.

B and C are incorrect: Plausible misconceptions of proper system operation with a feed flow mismatch, but output will remain the same in single element with plant conditions stable.

REFERENCE:

B.05.07-02 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #46 TIER: 2 GROUP: 1 CATEGORY: 259002 Reactor Water Level Control K/A: K6.03 IMPORTANCE: RO 3.1 COG LEVEL: 1I K/A DESCRIPTION: Knowledge of the effect that a loss or malfunction of the following will have on the Reactor Water Level Control System: Main Steam flow input.

DIFFICULTY 3 LESSON PL: M8107L-046 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

45. Following a transient, Secondary Containment isolated and the SBGT system initiated.

The reading for DPI-4424, CONTROL ROOM C24 MANOMETER, is found to be negative 0.02 (-0.02) inches of water.

What could be a possible cause for this condition?

A. The Turbine Building supply fan (V-MZ-1) failed to trip.

B. The Refueling Pool exhaust damper (V-D-36) failed to close.

C. The in-service Reactor Building exhaust fan (V-EF-24A or B) failed to trip.

D. The Reactor Building supply fans (V-AC-10A & B) inlet isolation dampers failed to close.

CORRECT ANSWER: D JUSTIFICATION: If Rx Bldg dP degraded to greater than -0.25 H2O then verify the inlet isolation dampers are closed.

Failure of the inlet isolation dampers (V-D-57/58/59/60) for V-AC-10A/B to close would mean that a hole exists in SCTMT and that SBGT would not be able to draw a significant negative pressure in the Reactor Building.

A is incorrect: The Turbine supply fans are tripped automatically when SCTMT is isolated, but this is for a safety issue only. The status of this fan would not affect this manometer reading.

B is incorrect: This damper is not a SCTMT isolation damper. Its position would not affect secondary pressure during isolation.

C is incorrect: If the operating exhaust fan failed to trip this would only help make the Reactor building more negative.

REFERENCE:

C.4-B.04.01.B NH-36267 (M-155) NH-36807 (M-156) 10 CFR 55.41b()

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - Edits to stem and choices TIER: 2 GROUP: 1 CATEGORY: 261000 SBGT K/A: A1.04 IMPORTANCE: RO 3.0 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to predict and/or monitor changes in parameters associated with operating the SBGT system controls including: Secondary containment differential pressure.

DIFFICULTY 4 LESSON PL: MT-ILT-AOP-008L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

46. The plant is at rated conditions with #12 EDG running unloaded for routine testing.

In the picture provided, the synchroscope is rotating slowly in the counterclockwise direction and the BOP operator is preparing to parallel the #12 EDG with 16 Bus.

Which of the following actions should be taken and why?

A. Close the #12 EDG output breaker when the synchroscope reaches the 12 oclock position; proper conditions are met for paralleling AC sources.

B. Lower #12 EDG speed such that the synchroscope is rotating in the clockwise direction; this will ensure the EDG picks up load when the output breaker is closed.

C. Raise #12 EDG speed such that the synchroscope is rotating in the clockwise direction; this will ensure the EDG picks up load when the output breaker is closed.

D. Raise #12 EDG output voltage such that the synchroscope is rotating in the clockwise direction; this will prevent excessive reactive currents flowing into the EDG.

CORRECT ANSWER: C JUSTIFICATION: In the picture shown the incoming voltage is the EDG voltage and the running voltage is 16 Bus voltage and they are matched. 12 EDG speed should be raised such that the synchroscope is rotating slowly in the clockwise direction. This will ensure that the EDG picks up load when the output breaker is closed.

A is incorrect: 12 EDG speed must be raised so the synchroscope is rotating in the clockwise direction.

B is incorrect: 12 EDG speed must be raised not lowered.

D is incorrect: Raising voltage will not change the rotation of the synchroscope.

REFERENCE:

B.09.08-05 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2009 NRC Exam #51 TIER: 2 GROUP: 1 CATEGORY: 262001 AC Electrical Distribution K/A: K5.01 IMPORTANCE: RO 3.1 COG LEVEL: 3 SPK K/A DESCRIPTION: Knowledge of the operational implications of the following concepts as they apply to AC ELECTRICAL DISTRIBUTION: Paralleling two AC power sources.

DIFFICULTY 3 LESSON PL: M8107L-042 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

47. The plant was at rated conditions with #11 Core Spray in Torus Mixing mode when a 15 Bus Lockout occurred. Given the following:

• LC-103 and LC-104 are crosstied

• The 15 Bus Lockout condition has been corrected

• E.2-05 (RESTORE BUS 15 FROM BUS 13) is being performed

• #11 Core Spray (CS) System status is provided on the following page For the conditions above, what action must be taken, and why?

A. Close MO-1741 to ensure #11 CS Pump doesnt restart when 15 Bus is re-energized.

B. De-energize LC-103 from LC-104 to prevent damage to the Load Center crosstie breaker.

C. Place #11 CS Pump to PTL to prevent an inadvertent restart when 15 Bus is re-energized.

D. Place MO-1751 CS Injection Bypass back to AUTO to prevent MO-1751 from auto opening.

CORRECT ANSWER: C JUSTIFICATION: Breakers for pump motors fed from Bus 15 are opened and/or placed in PTL. This is to prevent inadvertent restart of loads upon restoration of power, to limit current loading of the source transformer upon re-energization of the dead bus, and to prevent auto restart of ECCS pumps with partially drained discharge lines.

A is incorrect: Unlike RHR pumps, CS pumps do not have a start interlock with their suction valves. E.2-05 doesnt require this valve to be repositioned.

B is incorrect: LC-103 may remain energized from LC-104 provided that the 15 Bus to LC-103 source breaker is open.

Procedure E2.05 requires that source breaker to be open.

D is incorrect: The 15 Bus lockout procedure has this switch placed in bypass to prevent its auto opening so it wouldnt be required by E.2-05.

REFERENCE:

E.2-05 10 CFR 55.41b(7,10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 262001 AC Electrical Distribution K/A: A2.07 IMPORTANCE: RO 3.0 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the AC Electrical Distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Energizing a dead bus.

DIFFICULTY 3 LESSON PL: M8107L-105 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

48. The plant is at rated conditions. While in the EFT Building you notice the following indications for Y71 (DIV 1 UPS INVERTER).

Based on the indications above; which of the following is correct?

A. A complete loss of Y10 & Y70 has occurred.

B. Y71 is supplying loads in its normal operating mode.

C. Y71 has transferred its loads to the alternate source.

D. Y71 reverse transferred its loads from the alternate source back to the inverter.

CORRECT ANSWER: C JUSTIFICATION: With the reverse transfer light on this is the indication that the inverter transferred to the alternate source (MCC-134) and is no longer using the inverter to supply loads Y10 and Y70.

A is incorrect: The CRITICAL AC OUT still has power available to Y10 and Y70 as indicated by the STATIC SWITCH OUTPUT light being lit.

B is incorrect: The normal supply is through the inverter which would be indicated by the forward transfer light being on.

D is incorrect: This would happen if a fault was received and then cleared; however, this has not occurred for reasons stated above. This is plausible because of the nomenclature of REVERSE TRANSFER.

REFERENCE:

B.09.13-05 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2013 NRC Exam #45 TIER: 2 GROUP: 1 CATEGORY: 262002 UPS K/A: A3.01 IMPORTANCE: RO 2.8 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to monitor automatic operations of the UPS including: Transfer from preferred to alternate source.

DIFFICULTY 3 LESSON PL: M8107L-061 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

49. The following PCS battery voltage indications are observed in the control room:

Which of the following is correct for the #11 and # 13 battery voltage indications above?

A. BOTH systems are center tapped and indicate normal.

B. NEITHER system is center tapped, both indicate low.

C. 125 VDC is NOT center tapped and indicates low.

D. 250 VDC is NOT center tapped and indicates low.

CORRECT ANSWER: C JUSTIFICATION: 125 VDC is not a center tapped system and would normally indicate between 120-140 VDC.

A is incorrect: Plausible for the examinee believes these voltage readings are normal center tapped voltages; however, 125 VDC is NOT center tapped.

B is incorrect: Plausible for the examinee believes these voltage readings are not center tapped voltages; however, 250 VDC is center tapped an nominally would indicate 125-143 VDC D is incorrect: Plausible for examinee to confuse which DC system is center tapped. A center tap on the 250 VDC batteries provides 125 VDC for control power.

REFERENCE:

ARP 8-C014 B.09.09-01 10 CFR 55.41b(8)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 263000 DC Electrical Distribution K/A: A4.02 IMPORTANCE: RO 3.2 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to manually operate and/or monitor in the control room: Battery voltage indicator.

DIFFICULTY 3 LESSON PL: M8107L-040 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

50. The reactor is shutdown for a scheduled refueling outage. The following conditions exist:

• RPV water level is 57 inches

• Reactor Coolant Temperature is 149°F

• The Reactor Mode switch is in SHUTDOWN

• ALL Reactor Vessel Head closure bolts are detensioned

• Division 2 RHR/RHRSW pumps are in Shutdown Cooling (SDC)

• Division 1 AC Busses are deenergized for a scheduled maintenance window Maintenance personnel assigned to work on EDG 11 have mistakenly pumped down the lube oil sump for EDG 12.

Which one of the following Technical Specification LCOs would be NOT MET?

A. LCO 3.4.8 (RHR Shutdown Cooling System - Cold Shutdown)

B. LCO 3.8.2 (AC Sources - Shutdown)

C. LCO 3.8.8 (Distribution Systems - Shutdown)

D. LCO 3.9.8 (RHR - Low Water Level)

CORRECT ANSWER: B JUSTIFICATION: The maintenance activity has resulted in EDG 12 being inoperable. The unavailability of EDG 12 along with the Division 1 maintenance window, the examinee must determine that no EDGs are operable and LCO 3.8.2 is not satisfied. Then the examinee must also recognize that the plant is in Mode 5.

A is incorrect: Plausible if examinee believes both Bus 15 and Bus 16 are required for shutdown cooling. Bus 16 remains energized from offsite power and the requirements for LCO 3.4.8 are met.

C is incorrect: Plausible if examinee believes both distribution systems are required in Mode 4. The required distribution system is unaffected and remains energized from offsite power.

D is incorrect: Plausible if examinee believes both Bus 15 and Bus 16 are required for RHR Low Water Level. Bus 16 remains energize from offsite power and the requirements for LCO 3.9.8 are met.

REFERENCE:

TS 3.8.2 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2016 NRC Exam #69 - Previous two NRC Exams TIER: 2 GROUP: 2 CATEGORY: 264000 EDGs K/A: 2.2.36 IMPORTANCE: RO 3.1 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to analyze the effect of maintenance activities such as degraded power sources, on the status of limiting conditions for operations.

DIFFICULTY 3 LESSON PL: M8107L-034 OBJECTIVE: 10

2020 MONTICELLO ILT NRC EXAM - KEY

51. What insures adequate pneumatic supply to operate the Low-Low Set (LL-SET) SRVs if a loss of their normal pneumatic supply occurs?

A. 2 of 3 LL-SET valves have a backup pneumatic supply from Alternate N2 B. 2 of 3 LL-SET valves have a backup pneumatic supply from Accumulators.

C. All 3 LL-SET valves have a backup pneumatic supply from Alternate N2.

D. All 3 LL-SET valves have a backup pneumatic supply from Accumulators.

CORRECT ANSWER: A JUSTIFICATION: With the SRVs located inside primary containment they are pneumatically supplied normally with Instrument Nitrogen. If a loss of Instrument N2 occurs, their back up air supply is as follows:

• Alternate N2 Train A supplies one Lo-Lo Set SRV (E).

• Alternate N2 Train B supplies one Lo-Lo Set SRV (H)

• One LLSET SRV (G) has 4 safety-related backup accumulators.

B and D are incorrect: Only one LLSET SRV is backed up from accumulators.

C is incorrect: Only 2 of the 3 are backed up form Alternate N2.

REFERENCE:

B.03.03-01 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 300000 Instrument Air K/A: K1.03 IMPORTANCE: RO 2.8 COG LEVEL: 1 F K/A DESCRIPTION: Knowledge of the physical connections and/or cause-effect relationships between Instrument Air and the following: Containment Air.

DIFFICULTY 3 LESSON PL: M8107L-025 OBJECTIVE: 5.d

2020 MONTICELLO ILT NRC EXAM - KEY

52. Given the following plant conditions

• Instrument Air system pressure is 102 psig with 15 A/C in Lead

• 6-B-20 (15 AIR DRYER S-121 TROUBLE) is in alarm

• S-121 (15 INST & SERVICE AIR DRYER) drying is in FIXED Mode and dew point is 10°F Complete the statements below?

S-121 will automatically cycle between chambers based on __(1)__.

The 15 air compressor/dryer train should __(2)__.

A. (1) the level of moisture in the chamber (2) be removed from lead (priority 1) operation B. (1) the level of moisture in the chamber (2) remain in lead (priority 1) operation until dew point is < 0°F C. (1) a fixed time interval (2) be removed from lead (priority 1) operation D. (1) a fixed time interval (2) remain in lead (priority 1) operation until dew point is < 0°F CORRECT ANSWER: C JUSTIFICATION: (1) Correct, The dryer will still switch back and forth between chambers on a fixed timer, and it will purge and recharge each time (2) Correct, if the dew point from one of the dryers is 0°F, the dryer should be removed from lead (priority 1) operation A is incorrect: AMLOC Mode [NORMAL] dryer will automatically cycle between chambers based on the level of moisture in the chamber as sensed on the AMLOC (2) Correct, if the dew point from one of the dryers is 0°F, the dryer should be removed from lead (priority 1) operation B is incorrect: AMLOC Mode [NORMAL] dryer will automatically cycle between chambers based on the level of moisture in the chamber as sensed on the AMLOC (2) Incorrect, if the dew point from one of the dryers is 0°F, the dryer should be removed from lead (priority 1) operation D is incorrect: The dryer will still switch back and forth between chambers on a fixed timer, and it will purge and recharge each time (2) Incorrect, if the dew point from one of the dryers is 0°F, the dryer should be removed from lead (priority 1) operation

REFERENCE:

B.08.04.01-01/05 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2016 NRC Exam #51 - Previous two NRC Exams TIER: 2 GROUP: 1 CATEGORY: 300000 Instrument Air K/A: A2.01 IMPORTANCE: RO 2.9 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the Instrument Air system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Air dryer and filter malfunctions.

DIFFICULTY 4 LESSON PL: M8107L-024 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

53. The plant was operating at rated conditions when a Loss of ALL Offsite Power occurred.

The following conditions exist:

• Bus 16 has a LOCKOUT condition present

• ALL other plant equipment responded as expected Based on the above conditions, what will be the status of the following ESW Pumps?

11 EDG-ESW 12 EDG-ESW 13 EFT-ESW 14 EFT-ESW A. OFF OFF RUNNNG RUNNING B. RUNNING OFF OFF OFF C. RUNNING OFF RUNNING OFF D. RUNNING RUNNING RUNNING OFF CORRECT ANSWER: C JUSTIFICATION: With the loss of ALL offsite power both EDGs will start. A start signal will be generated for 11 & 12 EDG-ESW pumps when their respective EDG load onto the busses. However since 16 bus is locked out the 12 EDG output breaker will not close and power will not be available to LC-104 or MCC-134A therefore 12 EDG-ESW pump will not start. Also with the loss of ALL offsite power an auto start signal will be generated for 13 & 14 EFT-ESW pumps. However since 16 bus is locked out power will not be available to LC-104 or MCC-144 therefore 14 EFT-ESW pump will not start.

MNGP only has 2 RBCCW pumps with simple power supplies. EDG-ESW is a critical and operationally important Component Cooling Water system. The EDG-ESW system is being substituted for K/A 400000.

A is incorrect: Plausible if examinee doesnt realize that the EDGs would auto start and that power isnt available to 14 EFT-ESW pump.

B is incorrect: Plausible if examinee doesnt realize that an auto start signal will be generated for the EFT-ESW pumps.

D is incorrect: Plausible if examinee doesnt recall that 12 EDG must power up Bus 16 in order for 12 EDG-ESW Pump to start.

REFERENCE:

B.08.01.02-01 B.08.01.04-01 10 CFR 55.41(3)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2010 NRC Exam #53 TIER: 2 GROUP: 1 CATEGORY: 400000 Component Cooling Water K/A: K2.01 IMPORTANCE: RO 2.9 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of electrical power supplies to the following: CCW Pumps.

DIFFICULTY 3 LESSON PL: M8107L-016 OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

54. Reactor power is at 15% during a plant shutdown. The OATC selects control rod 34-39 at position 24 for insertion causing a RWM SELECT BLOCK.

Predict which of the following will occur if switch 3A-S3 (ROD OUT NOTCH OVERRIDE) is placed in the EMERG ROD IN position?

Control rod 34-39 A. will NOT insert.

B. inserts and a Rod Drift alarm is generated.

C. inserts followed by the normal rod settle function.

D. inserts and the normal rod settle function is bypassed.

A IS CORRECT: With the RWM Selection Error (SELECT BLOCK) present, the candidate must recognize that RWM INSERT and WITHDRAWL blocks will be enforced. RWM INSERT blocks will prevent inward rod motion using the ROD IN or the EMERG ROD IN.

K/A match: Selecting the wrong control rod will result in a RWM and RMCS Rod Block. This will result in the loss of ability to withdraw and in this case, also insert control rods because of the select block B is incorrect: The rod would not drive in due to the insert block but this alarm would be received.

C is incorrect: The rod would not drive in due to the insert block and the settle function is bypassed when using this switch.

D is incorrect: The rod would not drive in.

REFERENCE:

B.05.05-01 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2009 NRC Exam #54 TIER: 2 GROUP: 2 CATEGORY: 201002 RMCS K/A: K3.01 IMPORTANCE: RO 3.4 COG LEVEL: 2 RI K/A DESCRIPTION: Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL CONTROL SYSTEM will have on the following: Ability to move control rods.

DIFFICULTY 4 LESSON PL: M8107L-001 OBJECTIVE: 6

2020 MONTICELLO ILT NRC EXAM - KEY

55. The plant was at rated conditions when # 11 Reactor Feed Pump began to experience high motor bearing temperatures. C.4-F (RAPID POWER REDUCTION) was entered and reactor power was lowered to 90% with Recirc pumps.

If the feed pump trips on motor overload, complete the following statement.

The Recirc Pumps will A. runback to approximately 20% speed.

B. runback to approximately 30% speed.

C. runback to approximately 50% speed.

D. remain at the speed they were lowered to for C.4-F.

CORRECT ANSWER: C JUSTIFICATION: The examinee must recognize that current recirc flow is about 70%. With a loss of a feed pump when total steam flow is >65%, the recirc pumps will runback to approximately 50% speed.

A is incorrect: Lowering to 20% can only be done with local manual adjustment of the scoop tube.

B is incorrect: The runback to 30% will occur if total feed flow lowers to <20%. This will not occur on a single feed pump trip from 80% power.

D is incorrect: Lowering recirc pump speed to 80% power only reduces pump speed to about 60%; the runback will still occur to 50% speed.

REFERENCE:

B.05.08-01 C.4-B.06.05.A 10 CFR 55.41(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2009 NRC Exam #57 TIER: 2 GROUP: 2 CATEGORY: 202001 Recirculation K/A: K4.16 IMPORTANCE: RO 3.3 COG LEVEL: 2 RI K/A DESCRIPTION: Knowledge of the Recirculation System design features and/or interlocks which provide for the following: Recirc pump downshift/runback.

DIFFICULTY 3 LESSON PL: M8107L-047 OBJECTIVE: 8

2020 MONTICELLO ILT NRC EXAM - KEY

56. Which of the following describes the effects of a large resin breakthrough from the Reactor Water Cleanup System filter/demineralizer?

STRAINER D/P CONDUCTIVITY FILTER D/P A. RISE RISE LOWER B. RISE LOWER LOWER C. LOWER RISE LOWER D. LOWER LOWER RISE CORRECT ANSWER: A JUSTIFICATION: Strainer dP increase, Conductivity increases, Filter dP decreases. The resin breakthrough occurs when the precoated filter fails to hold the resin precoat. The conductivity increases when the resin reaches the Reactor and the resin breaks down, due to the heat, to form an acidic solution. Indications are:

a) High conductivity in the Reactor water; b) Low pH in the Reactor water; c) A slight decrease in power; d) dP of the questionable filter may drop.

B is incorrect: Plausible to believe that a lower pH will cause a lowering conductivity.

C is incorrect: Strainer D/P will rise due to the upstream release of resin precoat from the filter.

D is incorrect: Filter D/P will lower due to the loss of the resin precoat.

REFERENCE:

B.02.02-05.G.8 10 CFR 55.41b(5)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank TIER: 2 GROUP: 2 CATEGORY: 204000 RWCU K/A: K5.07 IMPORTANCE: RO 2.5 COG LEVEL: 2 DR K/A DESCRIPTION: Knowledge of the operation implication of the following concepts as they apply to the RWCU System: Conductivity measurement.

DIFFICULTY 3 LESSON PL: M8107L-030 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

57. The plant is at rated conditions. Traversing In-core Probe (TIP) scans are in progress when a PCIS malfunction results in an inadvertent Group 2 isolation.

Complete the following statement that describes the expected TIP System response to this condition.

The drive mechanism will automatically retract A. in fast speed to the IN-SHIELD position and then its respective BALL VALVE will close.

B. in slow speed to the IN-SHIELD position and then its respective SHEAR VALVE will fire.

C. in fast speed to the INDEXING MECHANISM and then its respective BALL VALVE will close.

D. in slow speed to the IN-SHIELD position and then its respective BALL VALVE must be manually closed.

CORRECT ANSWER: A JUSTIFICATION: When a Group 2 isolation signal is received, the drive mechanisms will automatically shift to fast speed, reverse and withdrawal the detectors to the in-shield position. When the detectors are in-shield, the ball valves will automatically close.

B is incorrect: The detectors retract in fast speed and the shear valve can only be manually fired. It is plausible to believe that the shear valve will automatically fire for a containment isolation signal.

C is incorrect: The indexing mechanism is located inside primary containment. It is plausible to believe the drive mechanism should remain in primary containment with an isolation signal; however, this wouldnt allow the ball valve to close.

D is incorrect: The detectors retract in fast speed and the ball valves close automatically.

REFERENCE:

B.05.03-02 10 CFR 55.41b(7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #58 TIER: 2 GROUP: 2 CATEGORY: 215001 Traversing In-Core Probe K/A: K6.04 IMPORTANCE: RO 3.1 COG LEVEL: 1I K/A DESCRIPTION: Knowledge of the effect that a loss or malfunction of the following will have on the TIP System:

Primary Containment isolation system.

DIFFICULTY 2 LESSON PL: M8107L-059 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

58. During surveillance testing, I&C determined Fuel Zone Level Instruments were mis-calibrated prior to the last startup.

Which of the following components and/or indications would be affected?

A. 2/3 core height Containment Spray permissive and indication on C-03 and C-292.

B. Reactor scram signal, Group 1, 2 and 3 PCIS, and indication on C-05.

C. ECCS initiation logic signals and HPCI and RCIC high level trips.

D. ATWS and the Reactor Feed Pump/Turbine trips.

CORRECT ANSWER: A JUSTIFICATION: Fuel Zone (Core flooding) level indicating switches LIS-2-3-73A & B are intended for use during emergency conditions; they transmit a signal allowing Containment Spray to be initiated when shroud water level is equal to or greater than 2/3 core height. Transmitters LT-2-3-112A & B located on racks C-121 and C-122 transmit signals to level indicators LI-2-3-91A & B, located on Panel C-03 for remote indication of shroud water level. In addition, LT-2-3-112B transmits a signal to an indicator LI-4108 and recorder LR-4102, located on Panel C-292 in the EFT for emergency indication and recording of Reactor fuel range (shroud) water level during a Control Room evacuation event.

B is incorrect: These are fed from separate LIS-2-3-657s that correlate to Safeguards level indication on the FW variable leg.

C is incorrect: These are fed from separate LS-2-3-672s that correlate to Safeguards level indication on the FW variable leg.

D is incorrect: These are fed from separate LT-2-3-680s that correlate to Safeguards level indication on the FW variable leg.

REFERENCE:

B.01.01-01 10 CFR 55.41b(7)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank 216000 Nuclear Boiler TIER: 2 GROUP: 2 CATEGORY:

Instrumentation K/A: A1.03 IMPORTANCE: RO 2.9 COG LEVEL: 1F K/A DESCRIPTION: Ability to predict and/or monitor changes in parameters associated with operating the Nuclear Boiler Instrumentation System including: Surveillance testing.

DIFFICULTY 3 LESSON PL: M8107L-056 OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

59. During normal 100% power operation, a Drywell-Suppression Chamber vacuum breaker valve failed to indicate fully closed. Test 0213 (DRYWELL TO SUPPRESSION CHAMBER VACUUM BREAKER LEAKAGE OPERATIONAL CHECK) was performed and the following results were recorded for STEP 16:

Time Differential Pressure Time Differential Pressure (HH:MM:SS) (psid) (HH:MM:SS) (psid) 09:30:00 0.300 09:31:10 0.125 09:30:10 0.275 09:31:20 0.100 09:30:20 0.250 09:31:30 0.075 09:30:30 0.225 09:31:40 0.050 09:30:40 0.200 09:31:50 0.035 09:30:50 0.175 09:32:00 0.025 09:31:00 0.150 09:32:10 0.016

1) Based on the acceptance criteria, is this data ACCEPTABLE or NOT ACCEPTABLE? AND

2) What immediate action is required?

A. 1) ACCEPTABLE

2) Continue plant operation and re-perform TEST 0213 Quarterly.

B. 1) ACCEPTABLE

2) Reset the annunciator circuit and ensure the vacuum breaker is NOT operated.

C. 1) NOT ACCEPTABLE

2) Notify shift supervision to make preparations for a normal plant shutdown.

D. 1) NOT ACCEPTABLE

2) Notify shift supervision that LCO 3.6.1.7.B Tech Spec conditions are NOT met.

CORRECT ANSWER: D JUSTIFICATION: If the best fit trend line from the data plotted in step 17 is trending below the curve in Figure 1 (Unacceptable Region) then notify shift supervision that LCO 3.6.1.7.B Tech Spec conditions are NOT met.

A, B and C are incorrect: Plausible options and actions to take based on incorrectly plotting the differential pressures on figure 1 and/or misinterpreting the procedure steps.

REFERENCE:

Test 0213 TS 3.6.1.7 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: Test 0213 QUESTION SOURCE: Significantly Modified from bank 223001 Primary Containment and TIER: 2 GROUP: 2 CATEGORY:

Auxiliaries K/A: A2.09 IMPORTANCE: RO 3.4 COG LEVEL: 3 SPR K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the PC System; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Vacuum breaker malfunction.

DIFFICULTY 3 LESSON PL: M8107L-008 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

60. The plant is in Mode 5 with #11 FPCC Pump and #11 FPCC Heat Exchanger in service when a 90 gpm leak on the T-48B (12 FPCC SKIMMER SURGE TANK) outlet pipe occurs.

Which of the following correctly completes the statement below for the given FPCC leak?

(Assume NO operator action has been taken.)

Fuel Pool water level will A. lower slightly and stabilize after T-48A (11 FPCC SKIMMER SURGE TANK) level reaches 2 feet 6 inches.

B. lower slightly and stabilize after T-48B (12 FPCC SKIMMER SURGE TANK) level reaches 4 feet.

C. remain unchanged because T-48B (12 FPCC SKIMMER SURGE TANK) would NOT be in service.

D. remain unchanged because the Condensate Service system will automatically provide surge tank makeup.

CORRECT ANSWER: A JUSTIFICATION: Since makeup to the system is manual, a leak will drain the surge tanks. Low-Low level (26) in the surge tanks will trip the running FPCC pump. With no water being pumped to the pool, level will lower until it reaches the top of the weirs and then stabilize. Water from the Fuel Pool overflows the weirs into the Skimmer Surge Tanks and is then pumped from the Skimmer Surge Tanks back to the pool.

B is incorrect: Water level wont change until the FPCC pumps trip at 2 6 C is incorrect: Although the Low-Low level pump trip switches are both in the 11 surge tank, the surge tanks are cross-connected by an 8 tie line; if one has a leak, level will lower in both surge tanks. Fuel pool level will lower and stabilize.

D is incorrect: The Condensate Service system must manually be placed in service to provide makeup. Fuel pool level will lower and stabilize.

REFERENCE:

B.02.01-01 USAR-14.07 10 CFR 55.41b(8)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #10 TIER: 2 GROUP: 2 CATEGORY: 233000 FPCC K/A: A3.02 IMPORTANCE: RO 2.6 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to monitor automatic operations of the FPCC System including: Pump(s) Trips DIFFICULTY 3 LESSON PL: M8107L-022 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

61. The plant is at 64% power during a planned power reduction for scheduled MSIV testing.

Which statement describes the reason for reducing power prior to closing an MSIV for testing?

To avoid a...

A. scram due to high flux.

B. scram due to low reactor water level.

C. Group 1 isolation due to low reactor pressure.

D. reactor feedpump trip due to high reactor water level.

CORRECT ANSWER: A JUSTIFICATION: Before closing a MSIV for testing using fast closure, the reactor power must be reduced to 66% or less of design power to avoid a scram from high flux, high reactor pressure or high flow on the remaining steam lines.

B, C and D are incorrect: Plausible plant responses for fast closure of an MSIV at power.

REFERENCE:

B.02.04-05 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank TIER: 2 GROUP: 2 CATEGORY: 239001 Main and Reheat Steam K/A: A4.10 IMPORTANCE: RO 3.8 COG LEVEL: 1P K/A DESCRIPTION: Ability to manually operate and/or monitor in the control room: Reactor power DIFFICULTY 2 LESSON PL: M8107L-007 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

62. The Reactor is at 400°F with all conditions stable.

• RPV Level indicates +25" on the feedwater level instruments

• B.01.01-06 Figure 30 (Feedwater Level Instruments) on the following page Complete the following statement:

Actual Reactor water level is....

A. 8-11 inches.

B. 14-17 inches.

C. 42-45 inches.

D. 52-55 inches.

CORRECT ANSWER: B JUSTIFICATION: With all conditions stable, indicated water level will be what the Reg valve is set at. Using the figure for the given temperature actual level would be 13-16 inches.

A is incorrect: Plausible for misreading the table by one temperature/pressure line too low.

C is incorrect: Plausible for reverse use of indicated and actual level on the table.

D is incorrect: Plausible for reverse use of indicated and actual level on the table and misreading the table by one line.

REFERENCE:

B.01.01-06 Figure 30 10 CFR 55.41b(2)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #60 - Minor edits to stem TIER: 2 GROUP: 2 CATEGORY: 259001 Feedwater K/A: 2.1.25 IMPORTANCE: RO 3.9 COG LEVEL: 3 SPR K/A DESCRIPTION: Ability to interpret reference materials, such as graphs, curves, tables, etc.

DIFFICULTY 3 LESSON PL: M8107L-056 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

63. Which of the following Fire Protection System components will be affected on a complete loss of power to Y-10?

A. Fire System Jockey Pump (P-106)

B. Main Transformer Deluge pushbutton on C-20 C. Zonalert Control Room Annunciator Panel (C-300)

D. 11 & 12 MG Deluge System Air Compressor (K-103)

CORRECT ANSWER: C JUSTIFICATION: Control Room Panel C-300 receives power from Y10 & Y30.

A is incorrect: Plausible as although this is a small plausible pump, it is powered from MCC-113.

B is incorrect: Plausible as the pushbutton receives power from 24 VDC D11.

D is incorrect: Plausible as this compressor receives power from 120 vac Panel L-42.

REFERENCE:

B.08.05-05 10 CFR 55.41b(8)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 2 CATEGORY: 286000 Fire Protection K/A: K2.03 IMPORTANCE: RO 2.5 COG LEVEL: 1F K/A DESCRIPTION: Knowledge of electrical power supplies to the following: Fire detection system.

DIFFICULTY 3 LESSON PL: M8107L-010 OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

64. SBGT A train was manually initiated with NO isolation of Secondary Containment.

Complete the following statement concerning this configuration.

The SBGT A train suction will compete with RB exhaust fans which may cause a...

A. low flow alarm on SBGT A train.

B. high temperature alarm on SBGT A train.

C. high room temperature in the SBGT Room.

D. low flow automatic initiation of SBGT B train.

CORRECT ANSWER: A JUSTIFICATION: Operating either SBGT Train in manual without isolating or adjusting RB ventilation (SCNMT) causes SBGT to compete with V-EF-24A, V-EF-24B and/or V-EF-28 for suction from the RB. This may also cause the SBGT heater to cycle on and off due to colder temps. Operating SBGT in manual without SCTMT isolation also caused SBGT discharge to compete with the exhaust from the Off-gas Storage building ventilation. Therefore, system flow is significantly lower than during a SCTMT isolation and may cause low flow annunciators to alarm.

B is incorrect: Plausible as a low temperature condition may occur.

C is incorrect: Plausible but this condition is not expected unless a loss of ventilation occurs in the room.

D is incorrect: Plausible as an auto initiation would only occur on a low flow condition from an auto start signal.

REFERENCE:

B.04.02-05.D.3 10 CFR 55.41b(8)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 2 GROUP: 2 CATEGORY: 288000 Plant Ventilation K/A: K1.02 IMPORTANCE: RO 3.4 COG LEVEL: 1F K/A DESCRIPTION: Knowledge of the physical connections and/or cause effect relationships between Plant Ventilation Systems and the following: Secondary Containment.

DIFFICULTY 2 LESSON PL: M8107L-027 OBJECTIVE: 5

2020 MONTICELLO ILT NRC EXAM - KEY

65. The plant is operating at rated conditions:

• Control Room Ventilation is in Normal Mode A

• Filter Train Fan V-ERF-11 Selector Switch is in AUTO LEAD If an instrument malfunction inadvertently shifts the CRV/EFT system to High Rad Mode, which of the following correctly predicts the resultant CRV/EFT system status?

Air Conditioner A Return Air Fan A 11 Filter Train Fan Control Room Pressure V-EAC-14A V-ERF-14A V-ERF-11 to Admin/Rx Bldg P A. Running Running Running Positive B. Running Running OFF Negative C. Running Running Running Negative D. OFF OFF Running Positive A IS CORRECT: If the system shifts to High Rad Mode. The fans in service prior to the manual trip would be V-EAC-14A and V-ERF-14A which would remain running and V-ERF-11 would auto start to complete the auto initiation of the high radiation mode of the EFT/CRV system. This mode would pressurize the control room.

B is incorrect: V-ERF-11 would auto start and the system is designed to maintain the control room pressurized. This would be a likely answer if the candidate does not know the system now starts on Group II signals.

C is incorrect: The system is designed to maintain the control room pressurized.

D is incorrect: The CRV/EFT system does not trip the CRV units in operation when the high radiation mode initiates.

REFERENCE:

B.08.13-01 page 3 and 4, B.08.13-06 Figure 5 10 CFR 55.41 (7)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2009 NRC Exam #65 - Edits to stem TIER: 2 GROUP: 2 CATEGORY: 290003 Control Room HVAC K/A: K3.04 IMPORTANCE: RO 2.8 COG LEVEL: 2 RI K/A DESCRIPTION: Knowledge of the effect that a loss or malfunctions on the CRV System will have on the following:

Control room pressure.

DIFFICULTY 3 LESSON PL: M8107L-049 OBJECTIVE: 7

2020 MONTICELLO ILT NRC EXAM - KEY

66. The plant is at rated conditions with no abnormal conditions present and no abnormal evolutions in progress.

IAW the Technical Requirements Manual (TRM), which of the following is the minimum number of active licenses required for Shift Crew Composition?

A. Two B. Three C. Four D. Five CORRECT ANSWER: C JUSTIFICATION: In Modes 1, 2 and 3; the TRM requires 2 SROs and 2 RO for minimum shift composition.

A is incorrect: This is the requirement in Modes 4 and 5. Also its the minimum number of licenses required in the control room at all times IAW the AWI.

B is incorrect: Management expectation is that 3 actives licenses are in the control room at all times.

D is incorrect: Five to Six is the normal crew composition but its not required by the TRM.

REFERENCE:

AWI-04.01.01 10 CFR: 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Significantly Modified - 2018 NRC Exam #66 TIER: 3 GROUP: 1 CATEGORY: Conduct of Operations K/A: 2.1.1 IMPORTANCE: RO 3.8 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of conduct of operations.

DIFFICULTY: 2 LESSON PL: M8107L-039 OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

67. A reactor startup is in progress with one reactor feed pump in service. Control rod withdrawals are planned to re-commence in approximately one hour.

For the conditions above; as the OATC, you are...

A. required to walkdown panels C-03 through C-08 approximately once per hour.

B. allowed to perform peer checks on panels C-03 through C-08 when directed by the CRS.

C. required to remain within the control room area which provides an unobstructed view of panels C-03 through C-08 at all times.

D. required to remain in the light carpeted area adjacent to panel C-05 and the immediately adjacent areas of panels C-04 and C-06.

CORRECT ANSWER: D JUSTIFICATION: During transition periods (i.e. plant startup prior to placing the second RFP in service, plant shutdown, testing with the potential to affect Reactor critical parameters, etc.) the OATC SHALL remain within the light carpeted area adjacent to Panel C-05 and the immediately adjacent areas of Panels C-04 and C-06. Another licensed duty Control Room Operator SHALL assume responsibility for monitoring the remaining portions of Panels C-03 through C-08.

A is incorrect. Plausible as these are OATC duties during normal plant operations.

B is incorrect: Plausible as the OATC must avoid prolonged distractions, however this task would be allowed.

C is incorrect: Plausible allowance for the OATC during steady-state operations.

REFERENCE:

OWI-01.06 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank TIER: 3 GROUP: 1 CATEGORY: Conduct of Operations K/A: 2.1.2 IMPORTANCE: RO 4.1 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of operator responsibilities during all modes of plant operation.

DIFFICULTY 2 LESSON PL: M8108-038 OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

68. You are an on-duty RO during the last day of the calendar quarter. Given the following:

• You have stood 6 twelve hour shifts as the BOP operator this quarter

• You are currently standing your 5th twelve hour shift as the OATC this quarter

• The CRS requests that you assist the RB operator with a RWCU F/D evolution If you assist in the evolution, which of the following is correct concerning maintaining your operator license active?

A. Your license will remain active based on the BOP shifts already stood.

B. Your license will remain active if the assistance is < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and you return as the OATC.

C. Your license will remain active if the assistance is < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and you return as the OATC.

D. Your license will NOT remain active if you assist with this evolution for any amount of time.

CORRECT ANSWER: B LESSON PLAN: M8108L-038 OBJECTIVE: 2 JUSTIFICATION: The licensed individual filling the OATC designated license position may be temporarily relieved of the Control Room panel monitoring requirements. This does NOT affect the individuals status regarding license maintenance credit so long as the individual remains on duty as a licensed operator and the duration of the relief is less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

A is incorrect: Shifts stood in the BOP operator position do not count for license maintenance credit. Only OATC and Lead RO count for this credit.

C is incorrect: Plausible time requirement for confusion between 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts.

D is incorrect: Plausible no relief requirement.

REFERENCES:

OWI-01.06 OWI-01.08 REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #66 TIER / GROUP: 3 CATEGORY: Conduct of Operations IR: RO 3.7 K/A NUMBER: 2.1.3 COG LEVEL: 1P DIFFICULTY: 3 10CFR 55.41b: 10 K/A DESCRIPTION: Knowledge of shift or short-term relief turnover practices.

2020 MONTICELLO ILT NRC EXAM - KEY

69. The plant is at rated conditions. An electrical malfunction results in the loss of the 1R and 1AR Transformers. The plant remains operating with the 2R Transformer supplying all loads.

With the conditions above; what is the MAXIMUM time allowed to perform SR 3.8.1.1 (Offsite Circuit Breaker Alignment Check)?

A. 15 minutes B. 20 minutes C. 30 minutes D. 60 minutes CORRECT ANSWER: D JUSTIFICATION: With the loss of the 1R and 1AR Transformers, only ONE offsite circuit (2R) remains available. This requires entry into TS 3.8.1 for not having 2 qualified offsite circuits. Required Action A.1 requires the performance of SR 3.8.1.1 for 2R within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

A is incorrect: Plausible for confusion with reactor pressure < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS.

B is incorrect: Plausible for confusion with CRDH pressure < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS.

C is incorrect: Plausible for confusion with RPV heatup and cooldown < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS.

REFERENCE:

TS 3.8.1 10 CFR: 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None, < 1Hour TS QUESTION SOURCE: Bank - 2018 Audit Exam TIER: 3 GROUP: 2 CATEGORY: Equipment Control K/A: 2.2.39 IMPORTANCE: RO 3.9 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of less than or equal to one hour Technical Specification action statements for a system.

DIFFICULTY: 3 LESSON PL: M8107L-036 OBJECTIVE: 10

2020 MONTICELLO ILT NRC EXAM - KEY

70. The plant was at rated conditions when an ATWS event occurred. Given the following:

• The SBLC System Selector switch was placed in the SYS 1 position

• The 11 SBLC pump immediately experienced a motor overload condition

• The red circled overloads on the following page opened as a result of the condition.

Given the conditions above, which of the following describes the response (FIRED OR UNFIRED) of the 11 SBLC Squib Valve and why?

A. FIRED; Squib valve operation is independent of these overloads.

B. FIRED; Squib valves DO NOT utilize the same power supply as the pumps.

C. UNFIRED; these overloads only affect the local operation of the SBLC pump.

D. UNFIRED: these overloads prevent the pump start AND the squib valve from firing.

CORRECT ANSWER: A JUSTIFICATION: The Squib valve utilizes a separate current path that doesnt pass through these overloads, therefore they will fire.

B is incorrect: The Squib valve will fire but its not because they have a separate power supply. They utilize the same power as the pump.

C is incorrect: Plausible as the motor overloads are located below the circuit labeled local starter.

D is incorrect: Plausible as both the pump and Squib valves utilize the same power supply.

REFERENCE:

NX-7879-5 10 CFR 55.41b(6)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam # 70 TIER: 3 GROUP: 2 CATEGORY: Equipment Control K/A: 2.2.15 IMPORTANCE: RO 3.9 COG LEVEL: 3 PEO K/A DESCRIPTION: Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.

DIFFICULTY LESSON PL: M8107L-104 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

71. The plant is in a refueling outage. A task needs to be performed in the Drywell and the RWP indicates a job dose estimate of 58 mrem.

Which of the following approaches to performing the job will maintain the total dose within the RWP job dose estimate?

A. One individual performing the job in a 90 mrem/hr field for 45 minutes.

B. Two individuals performing the job in a 90 mrem/hr field for 20 minutes.

C. One individual installing temporary shielding in a 90 mrem/hr field for 30 minutes and then performing the job in a 25 mrem/hr field for 60 minutes.

D. Two individuals installing temporary shielding in a 90 mrem/hr field for 10 minutes and then both individuals performing the job in a 25 mrem/hr field for 30 minutes.

CORRECT ANSWER: D JUSTIFICATION: : Total Dose = 2 x 15 mrem + 2 x 12.5 mrem = 55 mrem As part of Operations Shift briefs, the operators are required to evaluate upcoming work items and look for opportunities to reduce exposure.

A is incorrect: Total Dose = 90 mrem/hr x .75 = 67.5 mrem B is incorrect: Total Dose = 2 x 30 mrem = 60 mrem C is incorrect: Total Dose = 90 mrem/hr x .5 + 25 mrem = 70 mrem

REFERENCE:

4AWI-08.04.02 4AWI-08.04.08 10 CFR 55.41b(12)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2015 NRC Exam #73 TIER: 3 GROUP: 3 CATEGORY: Radiation Control K/A: 2.3.7 IMPORTANCE: RO 3.5 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to comply with radiation work permits during normal or abnormal conditions.

DIFFICULTY 3 LESSON PL: M8108L-039 OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

72. Complete the following statement that correctly identifies an activity that WOULD allow Independent Verification (IV) to be waived?

Removing a Danger Tag from A. B3301 (#11 SBLC Pump) while in hot shutdown.

B. B152-503 (#13 RHR Pump) while in hot shutdown.

C. FP-5 (FIRE SYS TEST VALVE) at rated plant conditions.

D. RC-3-1 (11 RWCU PUMP SUCT) at rated plant conditions.

CORRECT ANSWER: D JUSTIFICATION: Independent verification for Danger tags may be waived when significant radiation, safety or other hazards exist. This valve is not safety related and is located in the RWCU Pump Room. This room is a locked high radiation area and radiation levels would be high at rated condition.

A and B are incorrect: IVs SHALL be performed when removing of a Danger tags from safety related equipment required for operability. In hot shutdown both of these pieces of equipment would be required for operability C is incorrect: IVs SHALL be performed when removing a Danger tag from fire protection equipment.

REFERENCE:

4 AWI-04.04.02 Section 4.2.9 10 CFR 55.41(10)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank - 2010 NRC Exam #70 TIER: 3 GROUP: 3 CATEGORY: Radiation Control K/A: 2.3.13 IMPORTANCE: RO 3.4 COG LEVEL: 2 DR/RW K/A DESCRIPTION: Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

DIFFICULTY 2 LESSON PL: M8108L-039 OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

73. Which of the following annunciators identify an indication of a possible entry condition into an Emergency Operating Procedure (EOP)?

A. Red bordered B. Yellow bordered C. Blue backlit ONLY D. Red backlit ONLY CORRECT ANSWER B JUSTIFICATION: Annunciators that are in Alarm that have a yellow border are indicative of a possible EOP entry condition. During periods of multiple annunciators in Alarm, operators should prioritize annunciator responses to ensure that any EOP entry is made in a timely manner.

A is incorrect: This color border is associated with emergency conditions on the plant computer screens.

C is incorrect: This color is associated with RPV Hi/Lo Level annunciators.

D is incorrect: This color is associated with RPS actuations.

REFERENCE:

C.6 General 10 CFR 55.41b(10)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: Bank TIER: 3 GROUP: 4 CATEGORY: Emergency Procedures/Plan K/A: 2.4.31 IMPORTANCE: RO 4.2 COG LEVEL: 1F K/A DESCRIPTION: Knowledge of annunciator alarms, indications, or response procedures DIFFICULTY 2 LESSON PL: MT-ILT-EOP-001L OBJECTIVE: 1

2020 MONTICELLO ILT NRC EXAM - KEY

74. Following an E-Plan emergency declaration, the NRC is notified within one hour using which of the following?

A. By phone via the Joint Information Center (JIC) Hotline.

B. By phone via the Emergency Notification System (ENS).

C. Electronically via the Electronic Information Exchange (EIE).

D. Electronically via the Emergency Response Information System (ERIS).

CORRECT ANSWER: B JUSTIFICATION: The NRC is notified with one hour using the ENS communication line.

A is incorrect: This line is used to update the state on the emergency and the state emergency operations center.

C is incorrect: This system is for electronic submittals to the NRC but not for emergencies.

D is incorrect: This system provides access to the necessary forms used for emergency notification but this isnt the correct method of notification.

REFERENCE:

A2.501 10 CFR 55.41b(10)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 3 GROUP: 4 CATEGORY: Emergency Plan/Procedures K/A: 2.4.43 IMPORTANCE: RO 3.2 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of emergency communication systems and techniques.

DIFFICULTY 2 LESSON PL: MT-BEP-OPS-001L OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

75. The plant was at rated conditions when a Reactor scram was inserted due to a high radiation condition in the Reactor Building. Given the following valid annunciators:

Annunciator IN alarm:

• 3-B-55 (REACTOR BLDG EXH PLENUM HI RAD)

Annunciators that are NOT IN alarm:

• 3-A-49 (SBGT ANNUNCIATOR)

• 5-A-1/2 (REAC BLDG VENT & FP RAD CH A/B - HI/LO)

Which of the following explains the annunciators above?

A. Reactor Building Exhaust Plenum radiation of 22 mr/hr.

SBGT is in STANDBY as expected.

B. Reactor Building Exhaust Plenum radiation of 22 mr/hr.

SBGT failed to automatically start.

C. Reactor Building Exhaust Plenum radiation of 37 mr/hr.

SBGT is in STANDBY as expected.

D. Reactor Building Exhaust Plenum radiation of 37 mr/hr.

SBGT failed to automatically start.

CORRECT ANSWER: A JUSTIFICATION: 3-B-55 is received when Reactor Building Exhaust Plenum radiation reaches 20 mr/hr (Alarm ONLY).

SBGT would still be in standby as expected with 3-A-49 not in alarm.

B, C and D are incorrect: SBGT would auto start until 26 mr/hr. Reactor Building Exhaust plenum radiation of 26 mr/hr will bring in alarm 5-A-1/2. SBGT has not failed to start.

LP LO 8: Predict the impact/consequences on the SBGT/SCT Systems given the following: Reactor building ventilation exhaust high radiation.

REFERENCE:

ARP 3-B-55 ARP 3-A-49 ARP 5-A-1/2 10 CFR 55.41b(10)

REFERENCE PROVIDED DURING EXAM: None QUESTION SOURCE: New TIER: 3 GROUP: 4 CATEGORY: Emergency Plan/Procedures K/A: 2.4.45 IMPORTANCE: RO 4.1 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to prioritize and interpret the significance of each annunciator or alarm.

DIFFICULTY 4 LESSON PL: M8107L-008 OBJECTIVE: 8

2020 MONTICELLO ILT NRC EXAM - KEY

76. The plant was at rated conditions when the Main Turbine tripped and an ATWS event occurred. Ten minutes into the event the following conditions exist:

• Bus 15 is LOCKED OUT

• Reactor power is 20% and slowly lowering

• SBLC is injecting, tank level is 1350 gallons and lowering

• RPV water level is -80 inches lowering and difficult to control

• H SRV remains full open and G SRV is cycling open and closed As the CRS, what must be directed from C.5-2007 (Failure to Scram)?

A. Allow LO-LO SET to remain cycling.

B. Stabilize RPV pressure 800-1000 psig using SRVs.

C. Open additional SRVs to lower RPV pressure to 930 psig.

D. Stabilize RPV pressure below 1056 psig using main turbine bypass valves.

CORRECT ANSWER: C JUSTIFICATION: H SRV cycles between 972-1052 psig, G SRV cycles between 982-1062 psig. Because the Main Turbine tripped, the bypass valves do not have enough capacity for 20% reactor power. The power is being generated is keeping H SRV open therefore pressure is only cycling at the G SRV setpoint. Additionally, RPV water level difficult to control the CRS should prioritize lowering pressure to 930 psig due to rapid SRV cycling.

A is incorrect: Lo-Lo Set is functioning properly. However, rapid cycling is occurring due to the indication that level is difficult to control. Pressure is required to be reduced to 930psig, as yes has to be answered when addressing the question in the triangle of C.5-2007 pressure leg Rapid SRV Cycling?

B is incorrect: This is considered rapid SRV cycling and 800-1000 psig can only be directed after reactor pressure is lowered to less than 930psig.

D is incorrect: The bypass valves would not be available due to the Main Turbine trip, Bus 15 lockout and loss of the Turbine Aux Oil pump.

REFERENCE:

C.5.1-2007 and C.5-2007 10 CFR 55.43 (5)

REFERENCE PROVIDED DURING EXAM: EOP 2007 Flowchart QUESTION SOURCE: Bank - 2018 Audit Exam SRO ONLY JUSTIFICATION EOP Flowchart navigation and EOP action determination.

TIER: 1 GROUP: 1 CATEGORY: 295005 Main Turbine Generator Trip K/A: AA2.05 IMPORTANCE: SRO 3.9 COG LEVEL: 3SPK/SPR K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: Reactor Power.

DIFFICULTY 2 LESSON PL: M8114L-005 OBJECTIVE: 2,3

2020 MONTICELLO ILT NRC EXAM - KEY

77. The plant was at rated conditions when a severe fire started in the Cable Spreading Room.

Given the following:

• Immediate Control Room evacuation was successfully completed

• Main Turbine Bypass Valves have failed OPEN

• MSIVs failed to automatically close

• RPV pressure is lowering What should be directed to the ASDS Panel operator and what E-Plan declaration is appropriate?

A. Close the INBOARD MSIVs and declare an NUE.

B. Close the OUTBOARD MSIVs and declare an NUE.

C. Close the INBOARD MSIVs and declare an ALERT.

D. Close the OUTBOARD MSIVs and declare an ALERT.

CORRECT ANSWER: D JUSTIFICATION: IF the RPV rapidly depressurizes OR RPV water level cannot be maintained, THEN place the MSIV closure switch to CLOSE. ONLY the outboard MSIVs can be closed from the ASDS Panel.

A, B and C are incorrect: The Inboard MSIVs cannot be closed from the ASDS Panel. The requirements of an NUE are met because of the fire, however, an ALERT would be declared due to transfer of plant control to the ASDS Panel (HA6.1)

REFERENCE:

C.4-C B.05.17-02 EAL Matrix 10 CFR: 55.43b(1)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: EAL Matrix SRO ONLY JUSTIFICATION: Abnormal action determination and EAL declaration QUESTION SOURCE: Bank - 2018 Audit Exam TIER: 1 GROUP: 1 CATEGORY: 295016 Control Room Abandonment K/A: 2.1.20 IMPORTANCE: SRO 4.6 COG LEVEL: 3 SPK/SPR K/A DESCRIPTION: Ability to interpret and execute procedure steps.

DIFFICULTY: 3 LESSON PL: MT-ILT-AOP-025L OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

78. The plant is in a refueling outage with the following conditions present:

• The RPV head is removed

• RPV water level is at the reactor vessel flange

• Plant radiation levels are normal for plant conditions A leak occurs in the East Shutdown Cooling room thats confirmed by the Reactor Building Operator and plant conditions changed as follows:

• RPV water level lowers to -35 inches

• A1 (1027 RB NE LOW) radiation level rises to 18 mrem/hr

• A20 (CONTROL ROOM LOW RANGE) radiation level rises to 16 mrem/hr

• All other area radiation levels are below their alarm setpoints

• The leak is isolated and RPV level is restored to the flange 65 minutes later What E-plan classification should be declared?

A. NUE RU2.1 B. Alert RA2.2 C. Alert RA3.1 D. Site Area Emergency RS2.1 CORRECT ANSWER: C JUSTIFICATION: A control room low range radiation reading of >15 mrem/hr requires the declaration of an Alert IAW RA3.1.

A is incorrect: Plausible as RU2.1 and CU1.1 are met for lowering RPV water level and visible leakage with a rise in radiation levels.

B is incorrect: Plausible for the rising A1 radiation, but 20 mrem/hr hasnt been exceeded.

D is incorrect: Plausible for misinterpretation between fuel pool level and RPV level reduction.

REFERENCE:

EAL Matrix B.01.01-06 10 CFR: 55.43b(5)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: EAL Matrix SRO ONLY JUSTIFICATION: E-Plan classification determination QUESTION SOURCE: New TIER: 1 GROUP: 1 CATEGORY: 295023 Refueling Accidents K/A: AA2.01 IMPORTANCE: SRO 4.0 COG LEVEL: 3 SPR K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS:

Area radiation levels.

DIFFICULTY: 4 LESSON PL: MT-BEP-OPS-001L OBJECTIVE: 3

2020 MONTICELLO ILT NRC EXAM - KEY

79. The plant was at rated conditions when a severe transient and reactor scram occurred.

Given the following:

• DW Pressure is 10 psig

• DW Temperature is 250°F

• RPV pressure is 1000 psig

• Reactor Building Temperature is 205°F

• Fuel Zone level instruments read -49 inches

• Safeguards level instruments read -45 inches

• Vessel Flood level instrument reads -40 inches

• One control rod remains at position 48 Based on the above conditions, which of the following actions must be taken by the CRS?

A. Enter C.5-2006 (RPV FLOODING) at Point 23.

B. Enter C.5-2006 (RPV FLOODING) at Point 24.

C. Remain in C.5-1100 (RPV CONTROL) and control RPV water level using Fuel Zone instruments ONLY.

D. Remain in C.5-1100 (RPV CONTROL) and control RPV water level using Fuel Zone AND/OR Safeguards instruments.

CORRECT ANSWER: C JUSTIFICATION: In EOP-1100 a NOTE exists at the top of the level leg telling the CRS to check Figure 1 (Details A/B/C) for level instrumentation. Based on given temperatures, only the Fuel Zone instruments can be used. With RB temperature > 200F, Fuel Zone instruments are good to -274 inches provided the recirc pumps are tripped which they would be with DW pressure at 10 psig.

A is incorrect: Plausible if the examinee misreads Detail C and misinterprets one rod stuck out as meeting the conditions for an ATWS.

B is incorrect: Plausible if the examinee misreads Detail C and doesnt think any of the instruments are reading accurately and incorrectly thinks RPV water level is UNKNOWN.

D is incorrect: The Safeguards instruments are NOT usable; however this is a plausible choice if the candidate misreads Detail C and uses the < 200°F portion of the detail. Safeguard instruments would be good to -48 inches in this case.

REFERENCE:

C.5.1-1100 C.5-1100 10 CFR: 55.43b(5)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: EOP-1100 & 2006 Flowchart SRO ONLY JUSTIFICATION: EOP interpretation and direction of EOP actions.

QUESTION SOURCE: Bank - 2018 Audit Exam TIER: 1 GROUP: 1 CATEGORY: 295028 High DW Temperature K/A: 2.4.6 IMPORTANCE: SRO 4.7 COG LEVEL: 3 SPR K/A DESCRIPTION: Knowledge of EOP mitigation strategies.

DIFFICULTY: 3 LESSON PL: MT-ILT-EOP-002L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

80. Given the following sets of parameters:

Case1) Torus Water Temperature, stable at 170°F RPV Pressure, stable at 1000 psig Drywell Pressure, stable at 20 psig Torus Water Level, stable at -2 feet Case 2) Torus Water Temperature, stable at 160°F RPV Pressure, stable at 900 psig Drywell Pressure, stable at 20 psig Torus Water Level, stable at -1 feet Assuming actions to restore and maintain the above parameters have NOT been successful; determine if entry into C.5-2002 (EMERGENCY DEPRESSURIZATION) is required/not required for each of these cases?

A. Case 1) BLOWDOWN NOT required.

Case 2) BLOWDOWN NOT required.

B. Case 1) BLOWDOWN NOT required.

Case 2) BLOWDOWN required.

C. Case 1) BLOWDOWN required.

Case 2) BLOWDOWN NOT required.

D. Case 1) BLOWDOWN required.

Case 2) BLOWDOWN required.

CORRECT ANSWER: C JUSTIFICATION: EOP-1200 (PRIMARY CONTAINMENT CONTROL) directs a blowdown based on High/Low Torus water level, high Drywell temperature/pressure, Heat Capacity limit or Pressure Suppression Pressure. Based on the conditions above, only Case 1 would require a blowdown. The SRO examinee can determine this by plotting low torus water, high torus water temperature and reactor pressure on Detail M. In Case 1 Detail M is being exceeded and an Emergency Blowdown is required. Neither case is exceeding Detail O.

A, B and D are incorrect: Torus water level, Drywell pressure, Heat Capacity limit Pressure Suppression Pressure are all within limits of Figure M and O for Case 2 and a blowdown is not required.

REFERENCE:

C.5.1-1200 C.5-1200 10 CFR: 55.43b(5)

REFERENCE PROVIDED DURING EXAM: EOP 1200 Flowchart SRO ONLY JUSTIFICATION: EOP Flowchart navigation and action determination.

QUESTION SOURCE: Bank - 2013 NRC Exam #80 - Edits to stem 295030 Low Suppression Pool Water TIER: 1 GROUP: 1 CATEGORY:

Level K/A: EA2.02 IMPORTANCE: SRO 3.9 COG LEVEL: 3 SPR K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Suppression Pool Temperature.

DIFFICULTY: 2 LESSON PL: MT-ILT-EOP-003L OBJECTIVE: 4.a

2020 MONTICELLO ILT NRC EXAM - KEY

81. The plant was at rated conditions when a Group 1 Isolation and subsequent reactor scram occurred. The following conditions now exist:

• RPV level is +20 inches and stable

• RPV pressure is 1030 psig and rising

• Reactor period is -80 seconds and steady

• Reactor power is now on IRM Range 5 and lowering

• Standby Liquid Control (boron) has NOT been injected

• Five (5) control rods are at position 08, all other rods have fully inserted Based on the conditions above, which of the following procedures must be selected/directed by the CRS and why?

A. C.4-A (REACTOR SCRAM) to insert the remaining control rods.

B. C.5-3101 (ALTERNATE ROD INSERTION) to insert the remaining control rods.

C. C.5-3205 (TERMINATE AND PREVENT) to eliminate injection from Condensate &

Feedwater, HPCI and LPCI.

D. C.5-3302 (ALTERNATE PRESSURE CONTROL) to stabilize RPV pressure below 1056 psig using the Main Turbine Bypass Valves.

CORRECT ANSWER: A JUSTIFICATION: Based on the given conditions the examinee must interpret control rod position to determine which EOP setpoint has been exceeded and must be entered. With more than one rod out beyond position 04 the setpoint for the Failure to Scram EOP has been met and must be entered. Once that is entered the examinee must use reactor power and period to determine that the reactor is NOT critical. If the reactor is not critical the Failure to Scram EOP (C.5-2007) directs the exit of the Power Leg EOP and entry into Scram AOP C.4-A. This procedure will direct the insertion of the remaining control rods.

B is incorrect: If the reactor was critical this would be performed.

C is incorrect: This action would be performed if reactor power remained >4%.

D is incorrect: This action would normally be directed from EOP-1100 or 2007. However, the examinee must recognize that the Group 1 automatic action would close the MSIVs and render the main turbine bypass valves useless.

REFERENCE:

C.5-1100 Flowchart C.5-2007 Flowchart C.4-A 10 CFR: 55.43b(5)

REFERENCE PROVIDED DURING EXAM: EOP-1100 & 2007 Flowcharts SRO ONLY JUSTIFICATION: Assessment of facility condition and selection of abnormal procedure QUESTION SOURCE: Bank - 2013 NRC Exam #81 295037 SCRAM condition present and reactor power TIER: 1 GROUP: 1 CATEGORY:

above APRM downscale or unknown K/A: 2.4.2 IMPORTANCE: SRO 4.6 COG LEVEL: 3SPR/SPK K/A DESCRIPTION: Knowledge of system setpoints, interlocks and automatic actions associated with EOP entry conditions.

DIFFICULTY: 3 LESSON PL: MT-ILT-EOP-007L OBJECTIVE: 5

2020 MONTICELLO ILT NRC EXAM - KEY

82. The plant was at rated conditions when the control room receives a report from the field of a fire in the Mechanical Vacuum Pump Room. Given the following:

00:00:00 Fire reported to control room 00:08:00 Fire Brigade began attacking the fire 00:16:00 Control Room notified the fire is extinguished Given the information above, complete the statement below by determining if an Emergency Plan classification is required? If so, who assumes the responsibilities of the Shift Emergency Communicator (SEC)? If NOT, why?

Emergency Plan classification A. is required. Shift Security Supervisor B. is required. Shift Radiation Protection Technician C. is NOT required. The fire was only fought for 8 minutes.

D. is NOT required. The Mechanical Vacuum Pump is not vital equipment.

CORRECT ANSWER: A JUSTIFICATION: The SRO examinee must determine that the MVP room is within the Turbine Building as defined by EAL Table H-2 (Turbine Building). The SRO examinee must then determine that E-Plan classification HU4.1 applies because the fire is burning longer than 15 minutes. In the case of a fire, the Shift Chemist and Shift RPT are required to report as part of the fire brigade resulting in the Security Shift Supervisor as the only available SEC.

B is incorrect: Although the Shift RPT is qualified SEC they must report as a fire brigade members.

C is incorrect: An E-Plan classification is required because the fire burned longer than 15 minutes.

D is incorrect: Plausible if examinee doesnt recognize the MVP room is within the Turbine Building.

REFERENCE:

EAL Matrix 4AWI-08.02.02 10 CFR: 55.43b(1)

REFERENCE PROVIDED DURING EXAM: EAL Matrix SRO ONLY JUSTIFICATION: E-Plan classification QUESTION SOURCE: Bank - 2013 NRC Exam #82 - Edits to stem TIER: 1 GROUP: 1 CATEGORY: 600000 Plant Fire On Site K/A: AA2.16 IMPORTANCE: SRO 3.5 COG LEVEL: 3 SPR/SPK K/A DESCRIPTION: Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Vital equipment and control systems to be maintained and operated during a fire.

DIFFICULTY: 2 LESSON PL: MT-BEP-OPS-001L OBJECTIVE: 3

2020 MONTICELLO ILT NRC EXAM - KEY

83. The plant was at rated conditions when an inadvertent Group I isolation resulted in an ATWS condition. The panel operators report the following conditions:

• Reactor power is 10% and slowly lowering due to SBLC injection

• Torus water temperature is 200°F and slowly rising

• ALL available torus cooling is in service

• Torus water level is +2 ft. and slowly rising

• Drywell pressure is 4.4 psig and steady Which action should be directed by the CRS to maintain maximum available torus cooling and stay within C.5-1200 Detail F (RHR NPSH Limit)?

A. Reduce flow in each RHR loop to 3000 gpm B. Reduce flow in each RHR loop to 3500 gpm C. Reduce flow in each RHR loop to 6000 gpm D. Reduce flow in each RHR loop to 7000 gpm CORRECT ANSWER: C JUSTIFICATION: Torus overpressure is calculated to be 7 psig. With Torus temperature at 200°F, the highest flowrate allowed IAW Figure F using the 7 psig curve would be 6000 gpm. If possible the RHR pumps should always be operated within the NPSH limits. RHR flow should be operated at the maximum flow rate possible to reduce torus temperature.

A is incorrect: Plausible for utilizing the one pump per loop curve.

B is incorrect: Plausible for miscalculation of overpressure.

D is incorrect: This is too much flow and will jeopardize adequate NPSH, but is plausible if the examinee misinterprets Figure F or miscalculates Overpressure protection.

REFERENCE:

C.5-1200 Figure F C.5.1-1200 10 CFR: 55.43b(5)

REFERENCE PROVIDED DURING EXAM: EOP-1200 Flowchart QUESTION SOURCE: Bank - 2018 Audit Exam - Edits to stem and choices SRO ONLY JUSTIFICATION: EOP Figure interpretation and action determination TIER: 1 GROUP: 2 CATEGORY: 295013 High Suppression Pool Temp K/A: 2.2.44 IMPORTANCE: SRO 4.4 COG LEVEL: 3SPR K/A DESCRIPTION: Ability to interpret control room indications to verify status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

DIFFICULTY: 3 LESSON PL: MT-ILT-EOP-002L OBJECTIVE: 5

2020 MONTICELLO ILT NRC EXAM - KEY

84. The plant was at rated conditions when a steam line rupture occurred in the Steam Chase.

Turbine Building ventilation has been restarted and Reactor Building Vent (RBV) Effluent monitor readings are as follows:

1700 - 5 x 104 uCi/sec 1715 - 8 x 104 uCi/sec 1730 - 1 x 105 uCi/sec 1745 - 4 x 105 uCi/sec 1800 - 5 x 105 uCi/sec Based ONLY on the conditions above:

(1) What is the source of the rising RBV Effluent monitor readings?

(2) Which E-Plan Emergency Classification is required?

A. (1) SBGT discharging to the RB Plenum (2) Alert B. (1) Turbine Floor fans discharging to the RB Plenum (2) NUE C. (1) SBGT discharging to the RB Plenum (2) NUE D. (1) Turbine Floor fans discharging to the RB Plenum (2) Alert CORRECT ANSWER: B JUSTIFICATION: The SRO examinee must recognize that the blowout panels have ruptured and with Turbine building ventilation restored the leakage from the steam chase is being directed to the RB Plenum. The SRO Examinee must further determine that the RBV NUE level of 3 x E4 has been exceeded for 60 minutes.

A is incorrect: SBGT does not draw from the Steam Chase or the Turbine building. Plausible if the examinee does not understand the SBGT flow path. Alert level of 6 x 105 has been exceeded but NOT for >15 minutes.

C is incorrect: SBGT does not draw from the Steam Chase or the Turbine building. Plausible if the examinee does not understand the SBGT flow path.

D is incorrect: SBGT does not pull from the Steam Chase and Reactor Building plenum radiation level exceeds the Alert level. Alert level of 6 x 105 has been exceeded but NOT for >15 minutes.

REFERENCE:

EAL Matrix 10 CFR: 55.43b(5)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: EAL Matrix SRO ONLY JUSTIFICATION: Assessment of conditions and procedure direction & EAL matrix interpretation QUESTION SOURCE: Significantly Modified - 2018 NRC Exam #82 TIER: 1 GROUP: 2 CATEGORY: 295017 Abnormal Offsite Release Rate K/A: AA2.04 IMPORTANCE: SRO 4.3 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to determine and/or interpret the following as they apply to ABNORMAL OFFSITE RELEASE RATE: Source of off-site release.

DIFFICULTY: 2 LESSON PL: M8107L-008 OBJECTIVE: 6.f

2020 MONTICELLO ILT NRC EXAM - KEY

85. The plant was at rated conditions with #12 CRD Pump isolated for maintenance. A Loss of Coolant Accident (LOCA) concurrent with a Loss of All Off-Site Power occurred resulting in the following conditions:

• #11 EDG failed to start

• Reactor water level is -182 inches and lowering.

• 5-B-17 (CHARGING WATER LOW PRESSURE) is in alarm.

• Containment High Range Radiation Monitors are coming on-scale.

Which of the following actions must be directed by the CRS and why?

A. Start a Condensate Pump.

This ensures there is no effect on previously analyzed Control Room Operator doses.

B. Restart #11 CRD Pump.

This pressurizes the CRD system preventing a post-LOCA bypass leakage pathway from the CRD seals.

C. Close CRD-10-1 and CRD-10-2 (11 and 12 CRD Post Filter Inlets).

This isolates a post-LOCA bypass leakage pathway from the CRD seals.

D. Close CRD-10-1 and CRD-10-2 (11 and 12 CRD Post Filter Inlets).

This isolates a post-LOCA bypass leakage pathway that would overfill the WCT.

CORRECT ANSWER: C JUSTIFICATION: The CRS may authorize C.4 actions to be performed concurrently, out of order, ore re-performed as plant conditions dictate. If CRD flow cannot be immediately re-established with an ECCS initiation signal and evidence of significant fuel damage is present, manual isolation valves are closed or a condensate pump is started. This action is taken per CRS direction in response to NRC Information Notice 90-078 which describes a potential post-LOCA bypass leakage pathway from the reactor coolant system past the CRD seals and valves in the HCU back to the CRD pump header and out to the CSTs. Redundant check valves in the CRD header limit leakage to a small amount. Closure of the manual valves or starting a condensate pump to pressurize the CRD suction header will eliminate this leakage pathway.

This ensures there is no effect on previously analyzed Control Room Operator doses.

A and B are incorrect: Plausible but in these conditions 11 CRD Pump and the condensate pumps would not be available D is incorrect: Plausible as the post filters drain to the WCT but overflowing the WCT is not a concern for this condition.

REFERENCE:

C.4-B.01.03.A Bases C.4 General 10 CFR: 55.43b(1, 5)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: Assessment of core damage during abnormal/emergency situations and directing appropriate procedural action based on system limitations.

QUESTION SOURCE: Bank TIER: 1 GROUP: 2 CATEGORY: 295022 Loss of CRD Pumps K/A: 2.1.32 IMPORTANCE: SRO 4.0 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to explain and apply system limits and precautions.

DIFFICULTY: 3 LESSON PL: MT-ILT-AOP-002L OBJECTIVE: 13

2020 MONTICELLO ILT NRC EXAM - KEY

86. The plant is at rated conditions in January when the following annunciators are received:

• 6-B-07 (COND STOR TK T-1A LOW LEVEL)

• 6-B-08 (COND STOR TK T-1B LOW LEVEL)

• 6-B-13 (COND STOR TANKS LOW SUCTION TEMP)

Condensate storage tank levels are confirmed to be 2 feet and lowering and suction temperature is confirmed to be 65°F and lowering.

Using conditions above and the RCIC panel indications on the following page; the CRS will direct what procedure, if any?

A. B.02.03-05.G.1 (Manual Switchover of RCIC Suction from the CSTs to the Torus)

B. B.02.03-05.G.2 (Manual Switchover of RCIC Suction from the Torus to the CSTs)

C. B.02.03-05.H.1 (Closing RCIC Torus Suction Valves With Low CST Level Signal Present)

D. None, the RCIC suction will auto transfer to the Torus when CST levels reach 1 foot 6 inches.

CORRECT ANSWER: A JUSTIFICATION: Using the indications on the following page, the examinee must recognize that RCIC failed to automatically transfer its suction source to the torus when CST levels went below 2 feet 6 inches. This amount of water is required in the CSTs for RCIC operability and since the automatic action didnt occur, the CRS should direct to action to be completed. Additionally, the receipt of 6-B-13 provided direction to transfer the suction to the Torus.

B is incorrect: Plausible for misinterpretation of the RCIC panel indications.

C is incorrect: A low CST level signal is present; however, this procedure is used to bypass the auto suction transfer.

D is incorrect: Plausible for not recollecting the transfer setpoint and confusion of CW low basin level trip setpoints.

REFERENCE:

B.02.03-05.G.1 TS 3.3.5.2 Bases 10 CFR: 55.43b(5)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: Assessment of facility conditions and selection of appropriate procedure.

QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 217000 RCIC K/A: A2.16 IMPORTANCE: SRO 3.4 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the RCIC system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low condensate storage tank level.

DIFFICULTY: 3 LESSON PL: M8107L-003 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

87. The plant was at rated conditions when the following events occurred:

0800:00 A LOCA & Loss of ALL Offsite Power occurs 0800:10 BOTH Essential AC Busses are re-energized 0800:15 3-A-41 (AC INTERLOCK) is received 0800:45 8-B-18 (NO. 15 4160V BUS LOCKOUT) is received 0801:00 RPV pressure control is established with LL-SET 0801:15 3-A-38 (REACTOR LOW LOW LEVEL) is received 0801:30 RPV water level is -60 and continuing to lower Based on the above timeline, which procedure must be directed, and why?

A. C.5-1100 (RPV CONTROL) Center Leg to Inhibit ADS.

B. C.4-B.09.02.A (STATION BLACKOUT) for the loss of Bus 15.

C. C.5-3205 (TERMINATE & PREVENT) to terminate RHR and Core Spray injection.

D. B.09.07-05.E.7 (XFER OF LPCI SWING BUS FROM ALT TO NORM) for the loss of Bus 15.

CORRECT ANSWER: A JUSTIFICATION:

In order for the ADS System to initiate, the following two signals are required.

• 100 psig discharge pressure from a low pressure ECCS pump (This causes the AC Interlock alarm) AND

• RPV level below -47 (This causes the Reactor Low-Low Level alarm).

At 0801:15 Alarm 3-A-25 (AUTO BLOWDOWN TIMER ACTIVATED) will be received which refers to C.5-1100 for guidance. With the ADS Timer activated, C-5-1100 directs the CRS to Inhibit ADS.

B is incorrect: After the loss of Bus 15, Bus 16 will still be available.

C is incorrect: Although this action may be performed IAW C.5-1100 it is not required at this time as reactor pressure is above the shutoff head (320 psig) of the low pressure ECCS pumps. LL-Set pressure control is 900-1056 psig.

D is incorrect: The LPCI swing bus would transfer to a Bus 16 supply on the loss of power and transferring it back to a Bus 15 supply would not be correct.

REFERENCE:

C.5-1100 B.03.03-01 10 CFR 55.41b(5)

REFERENCE PROVIDED DURING EXAM: EOP-1100 Flowchart QUESTION SOURCE: New SRO ONLY JUSTIFICATION: Assessment of conditions and emergency procedure direction.

TIER: 2 GROUP: 1 CATEGORY: 218000 ADS K/A: 2.4.50 IMPORTANCE: SRO 4.0 COG LEVEL: 3 PEO K/A DESCRIPTION: Ability to verify system alarm setpoints and operator controls identified in the alarm response manual.

DIFFICULTY 3 LESSON PL: MT-ILT-EOP-002L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

88. The plant is at rated conditions when several valid annunciators are received including the following:

• 3-A-49 (SBGT ANNUNCIATOR)

• 8-A-4 (Y-10/Y-70 INSTR AC LOSS OF VOLTAGE)

• 8-A-24 (DIV 1INVERTER Y71 TROUBLE)

Based on the given conditions, which one of the following procedures, if any, must be directed to mitigate the conditions above?

A. C.4-B.05.07.A (LOSS OF REACTOR WATER LEVEL CONTROL)

B. C.4-B.04.01.A (PRIMARY CONTAINMENT ISOLATION - GROUP 1)

C. C.4-B.04.01.B (PRIMARY CONTAINMENT ISOLATION - GROUP 2)

D. NONE would be directed without knowing what specific circuit was lost.

CORRECT ANSWER: C JUSTIFICATION: The examinee must recall that 8-A-4 will not be received unless a complete loss of Y-10 and/or Y-70 has occurred. Additionally, the examinee must recall that a loss of Y-70 will result in a partial loss of power to the Group 2 Isolation Logic. A Partial Group 2 isolation will occur and that this procedure must be entered.

A is incorrect: Y-10 and Y-30 auctioneer power to DFWLC; however, control will not be lost as Y-10 and Y-30 will maintain power.

B is incorrect: Y-70 does supply power to the inboard solenoids for the MSIVs; however, this power is backed up by 125 VDC and entry into this procedure would not be required.

D is incorrect: Plausible for not understanding the implications of annunciator 8-A-4.

REFERENCE:

C.4-B.09.13.F C.4-B.09.13.F Bases 10 CFR: 55.43b(5)

REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: Assessment of conditions and selection of abnormal procedure.

QUESTION SOURCE: Bank - 2013 NRC Exam #90 TIER: 2 GROUP: 1 CATEGORY: 223002 PCIS K/A: A2.03 IMPORTANCE: SRO 3.3 COG LEVEL: 1 B/F K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the PCIS system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System logic failures DIFFICULTY: 4 LESSON PL: MT-ILT-AOP-020L OBJECTIVE: 3

2020 MONTICELLO ILT NRC EXAM - KEY

89. Complete the following statement.

IAW Technical Specifications, SBGT is used to mitigate the consequences of A. Fuel Handling Accidents ONLY.

B. Rod Drop Accidents AND Fuel Handling Accidents.

C. Rod Drop Accidents AND Loss of Coolant Accidents.

D. Loss of Coolant Accidents AND Fuel Handling Accidents.

CORRECT ANSWER: D JUSTIFICATION: The design basis for the SBGT System is to mitigate the consequences of a loss of coolant accident and fuel handling accidents involving recently irradiated fuel.

A is incorrect: This is correct, but not the only accident.

B and C are incorrect: Rod Drop Accidents are mitigated through the use of control rod systems; rod pattern control and rod block instrumentation.

REFERENCE:

TS 3.6.4.3 Bases 10 CFR: 55.43b(2)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: Knowledge of Technical Specification Bases QUESTION SOURCE: Bank - Edits to stem and choices TIER: 2 GROUP: 1 CATEGORY: 261000 SBGT K/A: 2.2.25 IMPORTANCE: SRO 4.2 COG LEVEL: 1B K/A DESCRIPTION: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

DIFFICULTY: 2 LESSON PL: M8107L-008 OBJECTIVE: 10

2020 MONTICELLO ILT NRC EXAM - KEY

90. The plant was at rated conditions with 11 EDG operating in parallel with Off-Site power IAW 0187-01 (11 EDG/ESW QUARTERLY PUMP AND VALVE TESTS). A loss of ALL Off-Site power occurs resulting in the following:

• 11 EDG tripped on overspeed

• Bus 15 is de-energized with no faults

• Bus 16 experienced a LOCKOUT condition What procedure must be used to reset the 11 EDG overspeed trip and restore Bus 15?

A. C.4-B.09.06.C (LOSS OF BUS 15 OR BUS 16)

B. C.6-08-B-35 (NO 11 DIESEL ENG MAINTENANCE LOCKOUT)

C. 0187-01 (11 EDG/ESW QUARTERLY PUMP AND VALVE TESTS)

D. B.09.08-05.H.2 (LOCAL SHUTDOWN OF 11 DIESEL IN EMERGENCY CONDITION)

CORRECT ANSWER: C JUSTIFICATION: 0187-01 (11 EDG/ESW QUARTERLY PUMP AND VALVE TESTS) states that if offsite power is lost while the EDG is loaded and in parallel with off-site power and the EDG trips on overspeed, then reset the overspeed trip, place speed droop knob to zero, and depress and release both engine stop pushbuttons. These actions will restart the EDG and provide power to Bus 15.

A is incorrect: This AOP would be entered but does not provide steps to restore the EDG.

B is incorrect: This ARP would be received and entered for an overspeed trip but does not provide steps to restore the EDG.

D is incorrect: This procedure would be used to shutdown the tripped EDG, but since the plant is currently in a SBO a restart would be required. Also plausible as the engine stop pushbuttons need to be depressed to restart the EDG.

SRO Only: The CRS would brief the procedures continuous awareness step in the PJB and direct the actions if the event occurred. Not RO responsibility.

REFERENCE:

B.09.08-05 D.1 10 CFR: 55.43b(5)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: Assessment of facility conditions and selection of appropriate procedure.

QUESTION SOURCE: New TIER: 2 GROUP: 1 CATEGORY: 264000 EDGs K/A: A2.02 IMPORTANCE: SRO 3.1 COG LEVEL: 2 DR K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the EDGs; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Unloading prior to securing emergency generator.

DIFFICULTY: 3 LESSON PL: M8107L-042 OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY

91. The plant is at rated conditions. Test 0081 (Control Rod Drive Scram Insertion Test) is being performed. Given the following data:

Control Rod (CR) scram times to notch position 06:

• CR 30 5.8 seconds

• CR 30 5.9 seconds

• CR 34 5.7 seconds Which of the following is a correct action to be taken at this time?

(A map of Control Rod positions is provided on the following page)

A. Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B. Declare all three CRs operable but slow ONLY.

C. Fully insert CR 34-27 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and locally disarm it within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

D. Fully insert all three CRs within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and locally disarm them within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

CORRECT ANSWER: A JUSTIFICATION: For the 3 adjacent control rods above, all are SLOW. Part b of LCO 3.1.4 states that only 2 adjacent control rods can be slow. This requires entry into Condition A. When this LCO is not met, the rate of negative reactivity insertion during a scram may not be within the assumptions of the safety analyses. Therefore, the plant must be brought to a Mode in which the LCO does not apply. Therefore, the plant must be taken to Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B is incorrect: Declaring all 3 rods operable but slow is wrong per Note 2 of 3.1.4.1.

C and D are incorrect: No Control rods are required to be declared inop. These actions of TS 3.1.3 would not be taken for any of the control rods.

REFERENCE:

TS 3.1.4 & Bases TS 3.1.3 10 CFR: 55.43b(2)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: TS 3.1.3 & TS 3.1.4 SRO ONLY JUSTIFICATION: TS Condition and Required Action determination.

QUESTION SOURCE: Significantly Modified - 2018 NRC Exam #77 201003 Control Rod and Drive TIER: 2 GROUP: 2 CATEGORY:

Mechanism K/A: 2.1.7 IMPORTANCE: SRO 4.7 COG LEVEL: 3 SPK K/A DESCRIPTION: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

DIFFICULTY: 4 LESSON PL: M8107L-020 OBJECTIVE: 10

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

92. At 0600, the plant is at normal rated conditions. ALL RCS Operational LEAKAGE rates have been stable for 3 days. The previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LEAKAGE calculations are as follows:

• Average total LEAKAGE is 24.5 gpm

• Average unidentified LEAKAGE is 3.5 gpm At 0700, the Radwaste Drywell Equipment Sump level rate of change has risen by 1.7 gpm due to a failure in the 12 Recirc Pump upper seal.

Which of the following describes the required TS ACTION and COMPLETION TIME?

(Assume the increased LEAKAGE remains constant and no operator action is taken.)

A. The plant must be placed in Mode 3 by 1900 for Pressure Boundary LEAKAGE.

B. The unidentified LEAKAGE RATE must meet the LCO statement by 1100.

C. The unidentified LEAKAGE must meet the LCO statement by 1100.

D. The total LEAKAGE must meet the LCO statement by 1100.

CORRECT ANSWER: D JUSTIFICATION: Total leakage exceeds LCO 3.4.4.c (<25 gpm). This requires restoration in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

A is incorrect: Reactor Recirculation pump seal leakage is not pressure boundary leakage.

B is incorrect: The total leakage rate has risen in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> but is less than 2 gpm.

C is incorrect: Reactor Recirculation pump seal leakage is not unidentified leakage.

REFERENCE:

LCO 3.4.4 LCO 3.4.4 Bases 10 CFR: 55.43b(2)

REFERENCE PROVIDED DURING EXAM: TS 3.4.4 SRO ONLY JUSTIFICATION: Facility operating limitations in the technical specifications and their bases.

QUESTION SOURCE: Bank - 2015 NRC Exam #92 - Edits to stem TIER: 2 GROUP: 2 CATEGORY: 268000 Radwaste K/A: A2.01 IMPORTANCE: SRO 3.5 COG LEVEL: 3 SPK/SPR K/A DESCRIPTION: Ability to (a) predict the impacts of the following on the RADWASTE system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: System rupture.

DIFFICULTY: 3 LESSON PL: M-8107L-101 OBJECTIVE: 10

2020 MONTICELLO ILT NRC EXAM - KEY

93. The plant was at rated conditions when an event occurred resulting in the following:

Based on the given conditions, which one of the following parts of C.5-3203 can be directed by the CRS when using Alternate RPV Injection?

(Assume Preferred Injection systems are unavailable)

A. PART A - RHRSW A CROSS-TIE TO LPCI B. PART B - CONDENSATE SERVICE TO PRESSURIZATION STATION C. PART C - SERVICE WATER CROSS-TIE TO CONDENSATE/FEEDWATER D. PART D - FIRE WATER CROSS-TIE TO LPCI CORRECT ANSWER: D JUSTIFICATION: This part can be used as long as the Screen Wash, Electric or Diesel Fire pump is available. The Screen Wash FP is deenergized as it is powered from LC-101. The Electric FP is deenergized as it is powered from LC-104. The Diesel Fire Pump would be available.

A is incorrect: ONLY RHRSW A can be used to cross-tie with LPCI. Since all other busses are deenergized (15 Bus), the A pumps would not have power. This part cannot be used because 11 and/or 13 RHRSW pumps must be available.

B is incorrect: In order to use this part the condensate service pumps must have power. 11 CSP is powered from MCC-111 which doesnt have power because LC-101 is deenergized. 12 CSP is powered from MCC-141 which does come off of LC-104 but is non-essential so it also doesnt have power.

C is incorrect: In order for this part to be used a condensate pump must be running. With the SBO both condensate pumps would not have power.

REFERENCE:

C.5-3203 C.5-1100 10 CFR: 55.43b(5)

REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: Assessment of facility conditions and selection of appropriate procedure.

QUESTION SOURCE: Bank - 2018 Audit Exam TIER: 2 GROUP: 2 CATEGORY: 286000 Fire Protection K/A: 2.1.23 IMPORTANCE: SRO 4.4 COG LEVEL: 3 SPR/SPK K/A DESCRIPTION: Ability to perform specific system and integrated plant procedures during all modes of pant operation.

DIFFICULTY: 4 LESSON PL: MT-ILT-EOP-002L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY

94. The plant was at rated conditions when an ATWS event occurred.

IAW OWI-03.06 (STRATEGIES FOR SUCCESSFUL TRANSIENT MITIGATION); which is a correct procedural assignment for the CRS to direct? (Assume full crew compliment on duty)

A. Lead RO to perform C.5-3101 (ALTERNATE ROD INSERTION).

B. BOP to perform C.5-3301 (RPV LOW-LOW LEVEL MSIV ISOLATION).

C. Lead RO to perform C.5-3301 (RPV LOW-LOW LEVEL MSIV ISOLATION).

D. OATC to perform C.5-3205 (TERMINATE AND PREVENT) for CFW and HPCI.

CORRECT ANSWER: B JUSTIFICATION:

OWI-03.06 4.2. C.5-2007, Failure to Scram Execution 4.2.1. The CRS will make the following orders per C.5-2007

1. BOP to defeat RPV Low-Low Level MSIV Isolation per C.5-3301, if the Main Condenser is available.

2. Lead RO level order. For example, terminate and prevent CFW and HPCI per C.5-3205.

3. OATC to insert Control Rods per C.5-3101.

4. OATC to inject SBLC per the hard card (if applicable).

A is incorrect: The OATC would perform this procedure.

C is incorrect: The BOP would perform this procedure.

D is incorrect: The Lead RO would perform this procedure with a full crew compliment.

REFERENCE:

OWI-03.06 10 CFR: 55.43b(1)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: SRO responsibilities for procedure direction during emergency conditions.

QUESTION SOURCE: New TIER: 3 GROUP: 1 CATEGORY: Conduct of Operations K/A: 2.1.6 IMPORTANCE: SRO 4.8 COG LEVEL: 1P K/A DESCRIPTION: Ability to manage the control room crew during plant transients.

DIFFICULTY: 2 LESSON PL: M8108L-038 OBJECTIVE: 2

2020 MONTICELLO ILT NRC EXAM - KEY

95. The plant is in Mode 1 when annunciator 5-A-46 (SRV OPEN) is received along with the following stable indications:

SRV E TAILPIPE TEMPERATURE Which of the following is a correct action to be taken by the CRS for the above conditions?

A. Restore the SRV to OPERABLE status within the LCO completion time.

B. Restore the failed instrument(s) to OPERABLE status within the LCO completion time.

C. Direct C.4-B.03.03.A (STUCK OPEN RELIEF VALVE) for an open ADS valve.

D. Direct C.4-B.03.03.A (STUCK OPEN RELIEF VALVE) for an open LL-SET valve.

CORRECT ANSWER: B JUSTIFICATION: The SRO examinee must determine if the SRV OPEN alarm is consistent with conditions shown in the pictures. The amber light lit means pressure switch has activated (30#), which would indicate that an S/RV is open; however, the associated MSL flow and tailpipe temperature do not reflect that the S/RV is open. This is indicative of a pressure switch instrument failure which requires entry into LCO 3.3.6.3 Condition A since its a LLS valve.

A is incorrect: Plausible TS action for an inoperable LL-SET Valve.

C is incorrect: Plausible for believing the SRV is open and that its an ADS valve.

D is incorrect: Plausible for believing the SRV is open.

REFERENCE:

TS 3.3.6.3 TRM 3.3 C.4-B.03.03-A 10 CFR: 55.43b(2)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: TS Action determination QUESTION SOURCE: Bank - 2018 NRC Exam #95 - Previous 2 NRC Exams TIER: 3 GROUP: 1 CATEGORY: Conduct of Operations K/A: 2.1.45 IMPORTANCE: 4.3 COG LEVEL: 3 SPR/SPK K/A DESCRIPTION: Ability to identify and interpret diverse indications to validate the response of another indication.

DIFFICULTY: 3 LESSON PL: M8107L-025 OBJECTIVE: 10

2020 MONTICELLO ILT NRC EXAM - KEY

96. The plant is in Mode 5 with SHUTDOWN MARGIN testing in progress.

• The Reactor Mode Switch is in STARTUP

• The RWM is OPERABLE and programmed to conform to the SDM sequence

• At 0800 on June 20th, a withdrawn control rod is determined to be uncoupled Which of the following describes the required Tech Spec Required Action?

A. Insert the control rod by 1100 using RMCS and disarm the control rod by 1200.

B. Insert ALL withdrawn control rods by 1100 using RMCS and disarm only the affected control rod by 1500.

C. Stop the test and do NOT change any control rod positions until another licensed operator is stationed to verify control rod movement.

D. Immediately position the Reactor Mode Switch to SHUTDOWN or REFUEL.

CORRECT ANSWER: A JUSTIFICATION: IAW TS 3.10.8 Condition A - One or more control rods not coupled to its associated CRD and its required action is to fully insert the inoperable control rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarm in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

B is incorrect: Plausible action to take IAW TS 3.9.4 Condition A for confusion between full-in and uncoupled.

C is incorrect: Plausible action to take IAW the TS 3.10.8.b.1 LCO condition pertaining to LCO 3.3.2.1 for non-compliance with the BPWS.

D is incorrect: Plausible for confusion between TS 3.10.8 Condition A and B.

REFERENCE:

TS 3.10.8 10 CFR: 55.43b(2)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: TS 3.3.2.1, 3.9.2, 3.9.4, 3.10.3, 3.10.8 SRO ONLY JUSTIFICATION: Infrequent TS Action Determination.

QUESTION SOURCE: Bank - 2018 Audit Exam TIER: 3 GROUP: 2 CATEGORY: Equipment Control K/A: 2.2.7 IMPORTANCE: SRO 3.6 COG LEVEL: 3 SPR K/A DESCRIPTION: Knowledge of the process for conducting special or infrequent tests.

DIFFICULTY: 2 LESSON PL: MT-OPS-ITS-013L OBJECTIVE: 10

2020 MONTICELLO ILT NRC EXAM - KEY

97. The plant is in MODE 5 during a planned refueling outage. Given the following:

• 11 CRD pump is in service

• The Rx Cavity is FLOODED & Fuel Pool Gates are REMOVED

• Calculated Drain time is 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />

• ALL Division 1 systems are available

• Secondary Containment is NOT available

• No High risk evolutions OR WICAs are in progress

• 1R, 2R and 1AR Transformers are available

• A station power transfer is in progress

• Division 2 AC and DC Electrical Buses are de-energized for maintenance Using Form 2270, what are the following Shutdown Risk Assessment classifications?

A. Decay Heat Removal YELLOW Inventory Control GREEN Electrical Control YELLOW Secondary Containment GREEN B. Decay Heat Removal GREEN Inventory Control GREEN Electrical Control YELLOW Secondary Containment GREEN C. Decay Heat Removal GREEN Inventory Control GREEN Electrical Control ORANGE Secondary Containment RED D. Decay Heat Removal GREEN Inventory Control YELLOW Electrical Control RED Secondary Containment GREEN CORRECT ANSWER: B JUSTIFICATION: DHR and IC are GREEN due to Div 1 System availability, Electrical Control is YELLOW because of the station power transfer. Secondary Containment is GREEN because its not required.

A is incorrect: DHR is plausible YELLOW for miscalculation of available systems.

C is incorrect: Electrical control is plausible Red if its not realized the 1 EDG is still available. Secondary Containment is plausible RED if the examinee believes it required.

D is incorrect. IC is plausible YELLOW for miscalculation of available systems.

REFERENCE:

Form 2270 10 CFR: 55.43b(6)

REFERENCE PROVIDED DURING EXAM: Form 2270 SRO ONLY JUSTIFICATION: Shutdown Risk assessment activities QUESTION SOURCE: New TIER: 3 GROUP: 2 CATEGORY: Equipment Control K/A: 2.2.18 IMPORTANCE: SRO 3.9 COG LEVEL: 3 SPR K/A DESCRIPTION: Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

DIFFICULTY: 2 LESSON PL: M8108L-039 OBJECTIVE: 1

2020 MONTICELLO ILT NRC EXAM - KEY

98. The plant was at rated conditions when an event occurred. Twenty (20) minutes later the following conditions exist:

• A General Emergency has been declared

• The TSC and EOF have NOT yet been manned

• 5790-401-01 (EMERGENCY EXPOSURE AUTHORIZATION FORM) has been initiated for Joe Radworker and is ready for your review

• Joe is assigned to manipulate several valves for protection of valuable property

• Radiation Protection estimates that Joe will receive the following exposure:

o Whole Body: 7 REM o Lens of the Eye: 35 REM o Hands and Forearms: 75 REM

• A.2-401 Figure 7.1 (EMERGENCY WORKER EXPOSURE LIMITS) is provided on the following page.

As the Emergency Director; which one of the following is correct, and why?

A. Approve the 5790-401-01 as the estimated exposures are within limits.

B. Do NOT approve the 5790-401-01 as the estimated exposure to the Whole Body exceeds the limit.

C. Do NOT approve the 5790-401-01 as the estimated exposure to the Hands and Forearms exceeds the limit.

D. Do NOT approve the 5790-401-01 as the estimated exposure to the Lens of the Eye exceeds the limit.

CORRECT ANSWER: D JUSTIFICATION: The allowed Emergency Worker Exposure Limits for an emergency activity to protect valuable equipment is 10 REM. NOTE 3 on Figure 7.1 allows 3 times this number for lens of the eye and 10 times this number for the skin and/or extremities. Based on that the limits are as follows:

Lens of the eye: 30 REM Hands and forearms: 100 REM Whole Body: 10 REM A, B and C are incorrect: Plausible for incorrect application of Figure 7.1.

REFERENCE:

A.2-401 10 CFR: 55.43b(4)

REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: SRO Job Responsibilities as Initial ED.

QUESTION SOURCE: Bank - 2013 NRC Exam # 98 TIER: 3 GROUP: 2.3 CATEGORY: Radiation Control K/A: 2.3.4 IMPORTANCE: SRO 3.7 COG LEVEL: `3SPR K/A DESCRIPTION: Knowledge of radiation exposure limits under normal or emergency conditions.

DIFFICULTY: 2 LESSON PL: MT-BEP-OPS-001L OBJECTIVE: 9

2020 MONTICELLO ILT NRC EXAM - KEY 2020 MONTICELLO ILT NRC EXAM - KEY

99. The plant was at rated conditions when a Loss of ALL Offsite Power and LOCA occurred.

Given the following:

• 11 EDG failed to start

• 12 Service Water pump is running

• 12 EDG-ESW pump failed to start

• Drywell pressure is 2.2 psig and slowly rising

• Drywell temperature is 138°F and slowly rising

• RPV pressure is 820 psig and slowly lowering

• RPV water level is -10 inches and slowly rising using HPCI Based on the conditions above, which of the following procedures must be prioritized and directed FIRST by the CRS and why?

A. C.5-3502 (CONTAINMENT SPRAYS) to start Drywell Sprays B. C.5-3503 (DEFEAT DRYWELL COOLER TRIPS) to start Drywell cooling C. C.5-3205 (TERMINATE AND PREVENT) to prevent Core Spray and LPCI injection D. B.08.01.02-05.H.3 (XFER EDG CLG FROM EDG-ESW TO SW) to restore 12 EDG cooling CORRECT ANSWER: D JUSTIFICATION: With a LONOP and a loss of 12 ESW PUMP the 12 EDG will be running without cooling water. Not establishing cooling will result in a loss of safety function as the diesel would trip and de-energize bus 16 reducing the plant to the minimum available ECCS systems. A MOD during RFO23 changed the SW lineup to the EDGs requiring manual manipulation of valves to provide SW cooling to the EDGs when the associated ESW pump fails to start.

A is incorrect: Although this action may be performed IAW C.5-1200 it is not required until 12 psig in the Drywell.

Additionally, Figure N would not currently allow this action.

B is incorrect: This action may be performed once the RBCCW pumps are restarted following the load shed, however, if 12 EDG trips on high temperature RBCCW will become unavailable.

C is incorrect: Although this action may be performed IAW C.5-1100 it is not urgent at this time as reactor pressure is above the shutoff head (320 psig) of the low pressure ECCS pumps.

REFERENCE:

C.4-B.09.02.B B.08.01.02-05.H.3 10 CFR: 55.43b(5)

REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: Assessment of conditions and Abnormal procedure direction.

QUESTION SOURCE: Bank - 2015 NRC Exam - #90 TIER: 3 GROUP: 4 CATEGORY: Emergency Procedures/Plan K/A: 2.4.22 IMPORTANCE: SRO 4.4 COG LEVEL: 3 SPK K/A DESCRIPTION: Knowledge of the basis for prioritizing safety functions during abnormal/emergency operations.

DIFFICULTY: 2 LESSON PL: MT-ILT-AOP-023L OBJECTIVE: 4

2020 MONTICELLO ILT NRC EXAM - KEY 100. What is the INITIAL Protective Action Recommendation (PAR) for a General Emergency Classification made in the Control Room NOT due to a loss of the containment barrier?

A. Evacuate a 2 mile radius and 2-5 mile downwind. All others monitor and prepare.

B. Evacuate a 2 mile radius and 2-10 mile downwind. All others monitor and prepare.

C. Contact the State Planning Chief or State Duty Officer if State EOC is not activated.

D. No PAR is appropriate when projected plume dose rates do NOT exceed 1000 mrem (TEDE)

OR 5000 mrem (CDE) thyroid dose.

CORRECT ANSWER: A JUSTIFICATION: According to A.2-204, declaration of a General Emergency requires timely initial protective action recommendations (PARs) to off-site agencies. Under these circumstances, NO dose projections are required for formulating the initial off-site protection action recommendation UNLESS there is a Rapidly Progressing Severe Accident. A Rapidly Progressing Severe Accident is a General Emergency (GE) with rapid loss of containment integrity (emergency action levels indicate containment barrier loss) and loss of ability to cool the core. Thus, since this GE is NOT due to loss of containment barrier per the EAL, the applicant shall conclude a GE exists WITHOUT a Rapidly Progressing Severe Accident. Figure 7.3.A of A.2-204 is used. The applicant should conclude the initial PAR is to Evacuate a 2 mile radius and 2-5 miles downwind. All others monitor and prepare.

B is incorrect: 2-10 miles downwind is not the initial PAR distance if a Rapidly Progressing Severe Accident does NOT exist (there is not a loss of containment barrier).

C is incorrect: This action is taken AFTER the recommendation is made.

D is incorrect: Initial PARs for a General Emergency involving loss of physical control or core damage require immediate evacuation of the general public and are justified without dose projection; recommending off-site protective actions shall not be delayed.

LP LO 1: Describe SRO/Interim ED actions for a General Emergency.

REFERENCE:

A.2-204 10 CFR: 55.43b(4)

ADDITIONAL REFERENCE PROVIDED DURING EXAM: None SRO ONLY JUSTIFICATION: SRO E-Plan activities QUESTION SOURCE: Bank - 2016 NRC Exam - Previous 2 NRC Exams TIER: 3 GROUP: 4 CATEGORY: Emergency Procedures/Plan K/A: 2.4.44 IMPORTANCE: SRO 4.4 COG LEVEL: 1P K/A DESCRIPTION: Knowledge of emergency plan protective action recommendations.

DIFFICULTY: 3 LESSON PL: MT-BEP-OPS-001L OBJECTIVE: 1