Text

Proposed Written Examination
	ML23012A139
Person / Time
Site:	Monticello
Issue date:	09/28/2022
From:	; Nuclear Management Co, Xcel Energy
To:	; NRC/RGN-III/DORS/OB
	Iskierka-Boggs T
Shared Package
ML21188A292	List: L-MT-22-023, 75-Day Exam Package; ML23012A009; ML23012A012; ML23012A134; ML23012A136; ML23012A137; ML23012A139; ML23012A143;
References
	Download: ML23012A139 (1)
	v • d • e

2022 MONTICELLO ILT NRC EXAM - RO

1.

The plant was at rated conditions when #11 Recirc Pump tripped.

C.4-B.01.04.A (TRIP OF ONE RECIRC PUMP) is being performed

The OATC closes MO-2-53A (11 Recirc Pump Discharge)

Which is correct concerning the action taken above?

MO-2-53A A. should have been left open to prevent thermal clamping.

B. was closed to prevent reverse flow and backward pump rotation.

C. was closed to prevent APRM setpoints from being lower than desired.

D. should have been left open to ensure APRM setpoints are accurate for total core flow.

2022 MONTICELLO ILT NRC EXAM - RO

2.

The plant was at rated conditions when a Station Blackout (SBO) occurred. Complete the following statement:

Unnecessary DC loads are disconnected during performance of the SBO procedure to ensure battery capacity is available for ________ of RCIC operation.

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months C. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

2022 MONTICELLO ILT NRC EXAM - RO

3.

The plant is shutdown for a planned maintenance outage with "A" RHR in shutdown cooling.

The Control Room Operator has identified the following changes in plant conditions:

SRM Channels 23 and 24 indications are trending down

Service Water Effluent monitor indication is trending down

RBCCW radiation monitor indication is trending down Given the above conditions, which Abnormal Procedure should be entered AND why?

A. LOSS OF A 125 VDC BUS for a loss of D-11 (Div 1 125 VDC Distribution Panel)

B. LOSS OF A 125 VDC BUS for a loss of D-21 (Div 2 125 VDC Distribution Panel)

C. LOSS OF A 24 VDC BUS for a loss of D-15 (Div 1 24 VDC Distribution Panel)

D. LOSS OF A 24 VDC BUS for a loss of D-25 (Div 2 24 VDC Distribution Panel)

2022 MONTICELLO ILT NRC EXAM - RO

4.

The plant was at rated conditions when a main turbine generator trip and reactor scram occurred. Given the CURRENT conditions:

Reactor pressure is 810 psig and slowly rising

Main Turbine speed is 1780 rpm and slowly lowering

C.4-A (REACTOR SCRAM) Part B has NOT yet been performed Based on current plant conditions; what is the expected equipment status below?

MAIN TURBINE BYPASS VALVES MAIN TURBINE AUX OIL PUMP A.

OPEN ON B.

OPEN OFF C.

CLOSED ON D.

CLOSED OFF

2022 MONTICELLO ILT NRC EXAM - RO

5.

In response to a reactor scram, the OATC verifies that the Recirc pumps have runback to minimum speed or have tripped.

What is the reason this action is performed?

A. To prevent NPSH limits from being exceeded on the Recirc pump suctions.

B. To eliminate potential for neutron flux oscillations if an ATWS were to occur.

C. To eliminate potential for neutron flux oscillations while the reactor is shutting down.

D. To prevent the recirc pumps from running at shutoff head due to the drop in core d/p.

2022 MONTICELLO ILT NRC EXAM - RO

6.

A significant event has occurred that required the crew to establish plant control at ASDS Control Panel C-292.

Which of the following actions can be performed with B RHR from C-292?

A. Raise RPV water level in the LPCI Mode.

B. Lower Torus water temperature in the Torus Cooling Mode.

C. Lower RPV pressure/temperature in the Shutdown Cooling Mode.

D. Lower Drywell pressure/temperature in the Containment Spray Mode.

2022 MONTICELLO ILT NRC EXAM - RO

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

2022 MONTICELLO ILT NRC EXAM - RO

8.

The plant is at rated conditions when a Service Air leak occurs. Given the following:

C.4-B.08.04.01.A (LOSS OF INSTRUMENT AIR) has been entered

Instrument Air (IA) header pressure is 81 psig and lowering

The BOP places the handswitch for CV-1474 (SERV AIR ISOL CV) in CLOSE Which is a correct reason for the BOP placing the handswitch for CV-1474 in CLOSE?

A. CV-1474 should have automatically closed at 90 psig.

B. This is an IMMEDIATE ACTION of C.4-B.08.04.01.A.

C. CV-1474 does NOT have an AUTOMATIC close feature.

D. This prevents CV-1474 from re-opening if air pressure begins to rise.

2022 MONTICELLO ILT NRC EXAM - RO

9.

The plant was at rated conditions when a transient occurred resulting in a reactor scram.

Actions are being taken to place the plant in Cold Shutdown. Given the following:

A RHR is in Shutdown Cooling

RPV pressure is 70 psig and slowly lowering A LOCKOUT on Bus 15 then occurs and 30 minutes later decay heat has caused RPV pressure to rise to 80 psig.

With the conditions above, which of the following is currently available AND can be used to continue the plant cooldown?

A. RCIC.

B. HPCI.

C. B Shutdown Cooling.

D. Main Turbine Bypass Valves.

2022 MONTICELLO ILT NRC EXAM - RO

10.

The plant is in a Refuel Outage with fuel being loaded into the core.

Which of the following would be considered a refueling error?

A. The lug on the fuel bundle bail points AWAY from the control cell.

B. The base of the fuel bundle serial number is NEAREST the center of the control cell.

C. The channel fastener cap screw is pointed at the CENTER of the respective control cell.

D. An out of sequence in-core fuel bundle is latched with the grapple (NO UPWARD MOTION HAS OCCURRED).

2022 MONTICELLO ILT NRC EXAM - RO

11.

The plant was operating in Mode 2 with a startup in progress. A large leak develops in the Reactor Vessel Bottom Head and the following timeline of events occur:

TIME Reactor Level Reactor Pressure Drywell pressure 00:00:00 30 inches 900 psig 0.5 psig 00:05:00 9 inches 880 psig 0.7 psig 00:10:00 -15 inches 840 psig 1.3 psig 00:15:00 -30 inches 800 psig 1.9 psig 00:20:00 -40 inches 760 psig 2.1 psig 00:25:00 -47 inches 720 psig 2.3 psig Based on the above timeline, which of the following is correct?

A. ONLY a Partial Group 2 Isolation occurred at 00:05:00.

B. All Main Steam Isolation Valves are closed at 00:10:00.

C. Both Emergency Diesel Generators are running at 00:15:00.

D. Division 1 RHR was selected for LPCI Loop injection path at 00:25:00.

2022 MONTICELLO ILT NRC EXAM - RO

12.

The plant is at rated conditions when a Group 1 isolation results in a scram and numerous control rods FAIL to insert. C.5-2007 (FAILURE TO SCRAM) has been entered.

The OATC chooses to perform Part D (RESCRAM CONTROL RODS) of procedure C.5-3101 (ALTERNATE ROD INSERTION).

Which of the following is CORRECT for the performance of Part D?

A. Low-Low Set will be disabled during a portion of Part D.

B. RPV water level must be > -47 inches to perform Part D.

C. BOTH divisions of RPS power are required to perform Part D.

D. CRDH flow will add additional positive reactivity once the scram is reset.

2022 MONTICELLO ILT NRC EXAM - RO

13.

The plant was at rated conditions when a severe ATWS condition occurred. The following indications were noted at 0800:

Of the times below, when will the Torus Heat Capacity (Detail M) be exceeded FIRST?

(Assume Torus temperature rate of change, Torus water level and Reactor pressure remain constant. Detail M is on the following page).

A. 0829 B. 0836 C. 0840 D. 0845

2022 MONTICELLO ILT NRC EXAM - RO

14.

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.

2022 MONTICELLO ILT NRC EXAM - RO

15.

The plant was at rated conditions when a major event occurred including a Torus leak.

Torus water level is -1 foot and lowering

RCIC is injecting to the RPV at rated flow Which Torus level below would the RCIC exhaust FIRST be discharging into the Torus air space?

A. - 3.5 feet B. - 4.0 feet C. - 4.5 feet D. - 6.0 feet

2022 MONTICELLO ILT NRC EXAM - RO

16.

The plant was at normal rated conditions when a LONOP and LOCA occurred.

RBCCW has been restored

CRD-14 (CRD CHARGING WATER TO ACCUMS) is OPEN

C.5-3204 (RPV MAKEUP WITH CRD) is required for RPV level control Which is correct concerning RPV level if CRD pumps are restarted with the conditions above?

A. A pressure transient could cause a LOWER indicated RPV water level.

B. A pressure transient could cause a HIGHER indicated RPV water level.

C. RPV level would not be affected; CRD pumps will NOT start following a LONOP.

D. RPV level would not be affected; CRD-141 (RPV BACKFILL ISOL) auto CLOSES on a scram.

2022 MONTICELLO ILT NRC EXAM - RO

17.

The plant was at rated conditions when a scram and ATWS condition occurred. The following conditions are present:

Reactor power 20% and lowering

The Main Condenser is unavailable

RPV pressure is cycling on Lo-Lo Set

Torus water temperature is 95°F and rising

RPV water level is being maintained -150 to -100

Standby Liquid Control (SBLC) System 1 has been initiated The CRS now directs the OATC to report when SBLC tank level reaches 985 gallons.

Which of the following describes the reason for reporting this tank level?

A. This will allow a normal RPV depressurization to begin.

B. This will allow RPV water level to be restored to +9 to +48.

C. This will allow SBLC injection from System 1 to be secured.

D. This will allow the crew to exit C.5-2007 (FAILURE TO SCRAM).

2022 MONTICELLO ILT NRC EXAM - RO

18.

The plant is at rated conditions. Given the following:

4-A-12 (OFF GAS HI RADIATION) has been in alarm for 5 minutes A rapid power reduction was performed down to 80% reactor power Main Steam Line Radiation Monitors still indicate above normal radiation levels Which action must be taken for the above conditions and why?

A. Initiate the SBGT system to filter the off-site release.

B. Insert a Reactor scram to minimize the off-site release.

C. Bypass the Off-gas Storage system to isolate the off-site release.

D. Restart an Off-gas Recombiner train to lower off-gas radiation levels.

2022 MONTICELLO ILT NRC EXAM - RO

19.

The plant is at rated conditions when a small lube oil fire is reported in the Recirc MG Set Room.

Which is the most effective method of extinguishing this fire?

A. CO2 B. Halon C. Pressurized water D. Dry Chemical / Foam

2022 MONTICELLO ILT NRC EXAM - RO

20.

The plant was at rated conditions when grid disturbance resulted in a Main Generator transformer lockout. A fire has erupted in the main generator transformer and the Fire Brigade has been dispatched.

Where can the Main Generator Transformer deluge be initiated from?

A. A control switch on C-300 (Zonalert Control Room Panel).

B. A deluge valve in the Northwest corner of the12 EDG Room.

C. A deluge valve outside the South wall of the Recirc MG Set Room.

D. A deluge valve in the Southeast corner of the East Electrical Equipment Room.

2022 MONTICELLO ILT NRC EXAM - RO

21.

The plant was in Mode 1 when a High RPV Water Level Trip occurred:

1. Which logic initiates this trip?

2. What equipment is protected by this trip?

(1)

(2)

A.

ATWS SRV Bellows B.

ECCS SRV Bellows C.

ATWS Main Turbine blading D.

ECCS Main Turbine blading

2022 MONTICELLO ILT NRC EXAM - RO

22.

The plant was at rated conditions when a steam line rupture resulted in the following:

Drywell temperature is 340°F and rising

Attempts to spray the drywell have been unsuccessful

The CRS is directing an RPV Blowdown While performing your RPV Blowdown actions, the following indications were noted:

(ALL lights below are extinguished)

Which SINGLE condition below would be a valid reason for the indications shown above?

A. The SRV bellows has RUPTURED.

B. The SRV amber light is BURNT OUT.

C. The SRV is mechanically STUCK CLOSED.

D. The SRV solenoid valve is NOT ENERGIZED.

2022 MONTICELLO ILT NRC EXAM - RO

23.

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 alarm 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.

2022 MONTICELLO ILT NRC EXAM - RO

24.

The plant is at rated conditions when a steam leak occurs in the Steam Jet Air Ejector room.

If an automatic Secondary Containment isolation/SBGT initiation occurs, what will happen to the release rate from the RB Exhaust Plenum Room, and why?

The release rate will A. lower because the Turbine Building supply fans will trip.

B. rise because the Plenum room exhaust fans take suction from the SJAE room.

C. rise because SJAE room exhaust will be redirected to the RB Exhaust Plenum room.

D. lower because the SBGT system will be processing the steam leak from the SJAE room.

2022 MONTICELLO ILT NRC EXAM - RO

25.

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:

Annunciators that are IN alarm:

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

259-A-6 (RBV EFFLUENT HIGH RADIATION)

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)

Based ONLY on the alarm conditions above; which is a correct action to take, and why?

A. Restart Secondary Containment ventilation because both SBGT trains failed to start.

B. Depress both SBGT TEST pushbuttons on C-24A/B because both SBGT trains failed to start.

C. Restart Secondary Containment ventilation to ensure a negative pressure exists in the Reactor Building.

D. Depress both SBGT TEST pushbuttons on C-24A/B to ensure a filtered release from the Reactor Building.

2022 MONTICELLO ILT NRC EXAM - RO

26.

Given the following conditions:

Main Steam Chase temperature is 220°F and rising

Room temperatures in other Reactor Building areas are normal

Numerous Turbine Building rad monitors show a rise in radiation levels Complete the following statements:

PCIS Group __(1)__ Isolation(s) has/have occurred.

Rupture of the Blowout Panels is causing steam to be released to the __(2)__.

(1) (2)

A. IV & V Turbine Operating Floor B. I Turbine Operating Floor C. IV & V Condenser Hotside D. I Condenser Hotside

2022 MONTICELLO ILT NRC EXAM - RO

27.

The plant was operating at rated conditions when a LOCA occurred in the Drywell (DW).

Given the following:

DW pressure is 11 psig and slowly lowering

RPV pressure is 440 psig and slowly lowering

RPV water level is -164 inches and slowly lowering

B RHR System status is shown on the following page Based on the given conditions, complete the following statement:

The Torus Spray/Cooling valves A. WILL automatically close when DW pressure is < 1.5 psig.

B. WILL automatically close when RPV pressure is < 420 psig.

C. WILL automatically close when RPV water level reaches 2/3 core height.

D. SHOULD have automatically closed when RPV pressure went < 460 psig.

2022 MONTICELLO ILT NRC EXAM - RO

28.

The plant is in Mode 5 performing a core reload:

The core reload is 50% complete

RPV water level is > 2111 above the top of the RPV flange

Division 1 Shutdown Cooling (SDC) is inoperable and unavailable

12 and 14 RHR pumps are in the SDC mode If 14 RHR pump trips, will Tech Specs continue to allow loading of fuel into the core, why?

A. NO, since Division 1 SDC is not available.

B. YES, since one RHR pump is still the SDC mode of operation.

C. YES, if an alternate method of DHR is verified available within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. NO, two RHR pumps must be in the SDC mode of operation at all times when moving fuel.

2022 MONTICELLO ILT NRC EXAM - RO

29.

The plant is in Mode 4 with the following conditions:

11 & 13 RHR Pumps are at rated flow in the Shutdown Cooling mode.

12 & 14 RHR Pumps are at rated flow in the Torus Cooling mode.

A small LOCA results in RPV water level lowering to a stable +5 inches.

Which approximates the TOTAL RHR System flow rate once conditions stabilize?

A. 0 gpm B. 6000 gpm C. 8000 gpm D. 16,000 gpm

2022 MONTICELLO ILT NRC EXAM - RO

30.

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

RPV water level lowered to -45" and is now +35" and stable

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, which one of the following is correct?

A. The ADS timer is initiated.

B. RCIC suction has auto transferred at a torus level of +2 inches.

C. Core spray pumps are running and injecting to the Reactor vessel.

D. HPCI is injecting at rated flow to the RPV with its suction aligned to the Torus.

2022 MONTICELLO ILT NRC EXAM - RO

31.

A plant transient has occurred that resulted in an automatic initiation and injection from the Division 1 Core Spray system. MO-1753 (DIV 1 CS INJECTION INB) is full open with an ECCS initiation signal still present.

Can MO-1753 be used to throttle Core Spray flow? Why or why not?

A. NO, this valve CANNOT be closed with an initiation signal still present.

B. NO, MO-1751 (DIV 1 CS INJECTION OTB) should be used for throttling flow with an initiation signal present.

C. YES, placing HS 14A-S16A (DIV 1 CS INJECTION BYPASS) keylock switch to "BYPASS" will bypass the MO-1753 open signal.

D. YES, placing HS 14A-S1A for MO-1753 (DIV 1 CS INJECTION INB) in the "CLOSE" position will bypass the MO-1753 open signal.

2022 MONTICELLO ILT NRC EXAM - RO

32.

An ATWS event has occurred and the OATC has initiated SBLC from C-05.

Complete the statements below.

Forced circulation is __(1)__ to ensure adequate dispersion of the boron solution into the core.

RWCU pumps __(2)__ receive an automatic trip signal.

A. (1) required (2) will B. (1) required (2) will NOT C. (1) NOT required (2) will D. (1) NOT required (2) will NOT

2022 MONTICELLO ILT NRC EXAM - RO

33.

The reactor was at rated conditions when the following occurred:

A manual scram has been inserted

All scram signals are clear EXCEPT the SDV HI HI level

The SDV HI HI level has been bypassed

The CRS directs the scram to be reset Which position(s) of the Mode Switch will allow the scram to be reset?

A. SHUTDOWN ONLY B. SHUTDOWN OR REFUEL ONLY C. SHUTDOWN OR REFUEL OR START AND HOT STBY ONLY D. SHUTDOWN OR REFUEL OR START AND HOT STBY OR RUN

2022 MONTICELLO ILT NRC EXAM - RO

34.

The Reactor Mode Switch is in STARTUP TO HOT STANDBY. IRM 17 is BYPASSED and ALL other IRM Range Switches are on Range 4. A failure of IRM 11 results in the following IRM readings:

IRM 11 IRM 12 IRM 13 IRM 14 IRM 15 IRM 16 IRM 17 IRM 18 125 70 69 76 72 67 0 68 Based on conditions above; which of the following is the status of RPS and/or RMCS?

A. A Full Scram has occurred.

B. An RMCS rod block ONLY has occurred.

C. An RMCS rod block and a RPS A half scram ONLY have occurred.

D. An RMCS rod block and a RPS B half scram ONLY have occurred.

2022 MONTICELLO ILT NRC EXAM - RO

35.

The plant is in a Refuel Outage with the following conditions:

Fuel is being moved into and out of the core

Maintenance is under the vessel staging for CRD Mechanism removal

Shorting links have been REMOVED

IRMs are on Range 1

All SRMs read ~10 cps

Mode Switch is in REFUEL Complete the statements below if the SRM count level were to rise to 5.5 x 105 cps.

1) Annunciator SRM HI/INOP will _____(1)_____.

2) Annunciator ROD WITHDRAW BLOCK will _____(2)_____.

3) A _____(3)_____ will occur.

(1) (2) (3)

A. NOT Alarm Alarm Half Scram ONLY B. Alarm NOT Alarm Full Scram C. Alarm Alarm Half Scram ONLY D. Alarm Alarm Full Scram

2022 MONTICELLO ILT NRC EXAM - RO

36.

A plant startup is in progress.

FT-2-110A (REC 11 FLOW XMTR - APRM 1) failed upscale causing the following alarms:

5-A-3 (ROD WITHDRAW BLOCK)

5-A-30 (APRM FLOW BIAS OFF NORMAL)

Complete the statements below?

__(1)__ is preventing control rods from being withdrawn.

Bypassing APRM 1 __(2)__ allow control rods to be withdrawn.

A. (1) RBM Flow Comparison >10%

(2) WILL B. (1) RBM Flow Comparison >10%

(2) WILL NOT C. (1) APRM Flow Upscale >110%

(2) WILL D. (1) APRM Flow Upscale >110%

(2) WILL NOT

2022 MONTICELLO ILT NRC EXAM - RO

37.

A plant transient has occurred resulting in a loss of No. 11 and No. 12 Reactor Feed Water pumps, Reactor scram, and a Group 1 Primary Containment Isolation.

RCIC was operating to restore RPV water level when RCIC flow lowered to 0 gpm and the following indications were observed:

RCIC turbine exhaust pressure is 20 psig

The Mechanical Overspeed light on C-04 is ON.

The Group 5 Isolation Reset light on C-04 is ON

MO-2078 (RCIC Turbine Steam Supply Valve) is OPEN

MO-2080 (RCIC Turbine Trip and Throttle Valve) is CLOSED Based on the above indications, what was the cause of the RCIC turbine trip?

A. Mechanical overspeed B. High Reactor water level C. High turbine exhaust pressure D. Group 5 containment isolation

2022 MONTICELLO ILT NRC EXAM - RO

38.

The plant is at rated conditions when RCIC automatically initiated on a valid initiation signal.

RCIC continues to operate at rated flow.

Which of the following will cause 4-A-14 (RCIC FLOW LOW) to alarm?

A. Torus water level of -5 inches B. Condensate Storage Tank level of 2 feet 5 inches C. CV-2104 (RCIC Pump Minimum Flow Valve) fails open D. RCIC pump suction pressure degrades to 17 inches Hg Vac

2022 MONTICELLO ILT NRC EXAM - RO

39.

The plant was at rated conditions when a steam line rupture occurred in the drywell and the following conditions are now present:

Drywell Sprays are unavailable

Drywell temperature is 290°F and rising

A complete loss of 125 VDC Bus A has occurred

Emergency Depressurization has been entered

As the BOP, the CRS directs you to open all three ADS valves Given the conditions above, which of the following SRVs must you use 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.

2022 MONTICELLO ILT NRC EXAM - RO

40.

The plant is at rated conditions with the HPCI turbine at rated speed for quarterly testing.

HPCI-82 (EXH LINE ISOLATION) experiences a stem failure resulting in a complete blockage of the HPCI exhaust line.

Using P&ID NH-36249 (HPCI-Steam Side); how would this blockage affect the HPCI system if the turbine FAILED TO TRIP on high exhaust pressure, and what action must be taken?

A. The HPCI system is NOT protected in this condition; HPCI must be manually tripped.

B. Rupture discs will burst relieving steam directly to the HPCI room; verify the Group 4 Isolation.

C. Rupture discs will burst relieving steam directly to the Torus catwalk area; verify the Group 4 Isolation.

D. Rupture discs will burst relieving steam via a 4 inch line directly to the Torus water space; HPCI must be manually tripped.

2022 MONTICELLO ILT NRC EXAM - RO

41.

The plant is at rated conditions when 3-A-17 (AUTO BLOWDOWN VLV BELLOWS LEAKING) alarms and the following indication is observed:

Which of the following describes the ability of SRV A to depressurize the RPV vessel?

SRV A A. will operate automatically in the ADS mode.

B. will operate automatically in the LL-SET mode.

C. will operate for its safety function but at a lower reactor pressure.

D. CANNOT be opened manually from C-03 to depressurize the RPV vessel.

2022 MONTICELLO ILT NRC EXAM - RO

42.

The plant was at rated conditions when a 12 Bus Lockout occurred. Immediate Actions have been taken for the trip of 12 Reactor Feed Pump (RFP). Given the following:

CV-3490 (12 RFP FW RECIRC TO CDSR) failed open

11 RFP suction pressure is 92 psig and stable

RPV water level is +27 inches and stable

Reactor power is 62% and stable What action should be taken to mitigate the conditions above?

A. Insert control rods IAW C.4-F (RAPID POWER REDUCTION).

B. Scram the reactor IAW C.4-K (IMMEDIATE REACTOR SHUTDOWN).

C. Raise the setpoint of LC-6-83 (FW MASTER CONTROLLER) back to normal.

D. Raise the setpoint of FC-1095 (11/12 COND PMP RECIRC FLOW) to 4500 gpm.

2022 MONTICELLO ILT NRC EXAM - RO

43.

Given the following conditions:

Drywell pressure is 1.0 psig

Reactor level is 35 inches

"A" SBGT is isolated for maintenance and "B" SBGT is in Standby What is the response of "B" SBGT following a loss of RPS Bus A (Y-50)?

A. Starts immediately.

B. Starts after a 10-second delay.

C. Remains in Standby since no initiation signal is present.

D. Remains in Standby since RPS Bus B (Y-40) is still available.

2022 MONTICELLO ILT NRC EXAM - RO

44.

The plant was at rated conditions when a Station Blackout (SBO) occurred.

Which 4160 VAC bus(es) can be procedurally reenergized for the conditions above?

A. Bus 13 ONLY B. Bus 14 ONLY C. Buses 13 and 15 D. Buses 14 and 16

2022 MONTICELLO ILT NRC EXAM - RO

45.

The plant was at rated conditions when SPR-63 (SUDDEN PRESSURE RELAY) actuated in the Main Generator transformer.

Which of the following completes the statements below?

This condition DIRECTLY actuates the __(1)__.

The field breaker trips open __(2)__.

A. (1) turbine lockout relay (286/T)

(2) immediately B. (1) turbine lockout relay (286/T)

(2) once 8N7 and 8N8 are sensed open C. (1) generator lockout relay (286/G)

(2) immediately D. (1) generator lockout relay (286/G)

(2) once 8N7 and 8N8 are sensed open

2022 MONTICELLO ILT NRC EXAM - RO

46.

Given the following 480 Volt UPS Electrical Distribution Drawing:

If an inverter UNDERVOLTAGE fault results in 0 volts sensed at Point X above; which of the following describes how Y-94 will receive its power?

A. LC-107 will automatically supply power to Y-94.

B. LC-108 will automatically supply power to Y-94.

C. 250 VDC Battery 17 will automatically supply power to Y-94.

D. The Maintenance Bypass Breaker must be manually closed to power Y-94.

2022 MONTICELLO ILT NRC EXAM - RO

47.

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 and no operator action is taken.)

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 immediately after a Core Spray or RHR pump is 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.

2022 MONTICELLO ILT NRC EXAM - RO

48.

The plant is operating at rated conditions when a DC supply breaker trip results in the receipt of 20-B-09 (DIVISION II 125/250 DC TROUBLE).

Which system must be monitored in the control room to confirm the given power loss?

A. HPCI B. RCIC C. RWCU D. Turbine Lube Oil

2022 MONTICELLO ILT NRC EXAM - RO

49.

The plant is at rated conditions. Given the following:

1AR transformer is tagged out for maintenance.

52-908/CS (109-102 LOAD CENTER TIE ACB 52-908) handswitch in PTL.

If a BUS 13 LOCKOUT were to occur AND 11 EDG failed to start, which Load Centers will be energized ONE MINUTE after the lockout?

LC-101

LC-103

LC-107 A. LC-103 ONLY B. LC-101 AND LC-103 ONLY C. LC-101 AND LC-107 ONLY D. All three Load Centers would be energized

2022 MONTICELLO ILT NRC EXAM - RO

50.

A plant startup/heatup is in progress with the following conditions:

CV-2403 (RWCU DUMP FLOW) is 60% open to maintain RPV level

CV-6-13 (LOW FLOW REGULATING VALVE) is closed in Automatic control

A complete loss of Instrument Air occurs While implementing C.4-B.08.04.01.A (LOSS OF INSTUMENT AIR), which of the following valve indications would be expected?

CV-2403 CV-6-13 A.

open closed B.

60% open open C.

open open D.

closed closed

2022 MONTICELLO ILT NRC EXAM - RO

51.

A plant startup is in progress with the following conditions:

MO-2399 (RWCU RETURN ISOL) is 25% open

MO-3501 (RBCCW FROM RWCU HX) is 50% open

CV-2403 (RWCU EXCESS FLOW CTRL VLV) is controlling dump flow at 60 gpm With the conditions above which of the following actions must be taken if annunciator 4-B-26 (CLEANUP DEMIN TEMP HI) is received?

A. Throttle OPEN CV-2403.

B. Throttle OPEN MO-3501.

C. Throttle CLOSED MO-3501.

D. Throttle CLOSED MO-2399.

2022 MONTICELLO ILT NRC EXAM - RO

52.

The normal Service Water supply has been lost to the following coolers:

V-AC-6 (RCIC ROOM COOLER)

V-AC-7A/B (CRD ROOM COOLERS)

V-AC-8A/B (HPCI ROOM COOLERS)

If EFT-ESW Pumps were started, which cooler(s), if any, will still be monitored for outlet radiation?

[Service Water System P&IDs NH-36041 (M-110) and NH-36664 (M-112) are provided]

A. V-AC-8A/B ONLY B. V-AC-8A/B and V-AC-6 ONLY C. V-AC-7A/B and V-AC-6 and ONLY D. NO coolers will be monitored for outlet radiation.

2022 MONTICELLO ILT NRC EXAM - RO

53.

The plant was at rated conditions when an event occurred resulting in the following readings:

1. Control Room Air Intake Monitors - 2.5 mrem/hr

2. Refueling Floor Radiation Monitors - 60 mrem/hr

3. RB Exhaust Plenum Radiation Monitors - 21 mrem/hr Which of the given instrument radiation readings will cause CRV/EFT to initiate in the High Radiation Mode?

A. 1 ONLY B. 2 ONLY C. 1 & 2 ONLY D. 1, 2 AND 3

2022 MONTICELLO ILT NRC EXAM - RO

54.

Given the following:

Control rod 26-27 is at position 48

Control rod 30-19 is at position 48 and is presently being inserted to position 42 using normal rod insertion Complete the statement below?

Annunciator 5-A-27, ROD DRIFT, will alarm _______________.

A. if rod 26-27 moves off position 48 B. when rod 30-19 moves past position 47 C. if the TIMER TEST switch is taken to the RESET position D. when the ROD MOVEMENT CONTROL switch is released to the OFF position

2022 MONTICELLO ILT NRC EXAM - RO

55.

Which of the following will lose power on a loss of D11 (DIVISION 1 125 VDC)?

A. TIP Shear Valve B. SRMs 21 and 22 C. IRMs 15, 16, 17 and 18 D. HPCI System Control Power

2022 MONTICELLO ILT NRC EXAM - RO

56.

The plant was at rated conditions when a Torus break and LOCA occurred.

RPV pressure is 25 psig

Torus water level is - 6 feet

RHR pumps are unavailable

DW/Torus pressure is 8 psig and slowly rising

RHRSW-14 (EMERG INJ VIA A RHRSW) will NOT open

P&IDs M-112 and M-121 for RHRSW and ESW Systems is provided Which of the following methods can be used to spray the Torus?

A. RHRSW B. Fire Water C. Domestic Well Water D. Condensate Service Water

2022 MONTICELLO ILT NRC EXAM - RO

57.

The plant is in a refuel outage with the following conditions established:

Reactor Cavity Flooded

Fuel Pool to Cavity Gates Removed If the reactor cavity bellows were to develop an unisolable leak, which of the following represents how low water level would get in the fuel pool?

(Assume emergency makeup is NOT available.)

A. ONLY the upper tie plates of the fuel would become UNCOVERED.

B. ONLY 1/3 of the fuel would become UNCOVERED.

C. ONLY 2/3 of the fuel would become UNCOVERED.

D. A complete draining of the spent fuel pool would occur.

2022 MONTICELLO ILT NRC EXAM - RO

58.

Which plant conditions meet the definition of REFUELING MODE 5?

A. Reactor water temperature is 100°F Mode switch is in SHUTDOWN ALL RPV closure head bolts fully tensioned B. Reactor water temperature is 180°F Mode switch is in SHUTDOWN RPV head is removed C. Reactor water temperature is 200°F Mode switch is in REFUEL ALL RPV closure head bolts fully tensioned D. Reactor water temperature is 221°F Mode switch is in SHUTDOWN ALL RPV closure head bolts fully tensioned

2022 MONTICELLO ILT NRC EXAM - RO

59.

With the plant operating at full power, the indicated flow on the "D" Main Steam Line went fully upscale. Actual steam flow rose to 123% flow for two seconds. The flow indications on the "A", "B" and "C" Main Steam Lines lowered to less than their normal 100% flow during the two second transient.

Which statement describes expected plant protection response to this condition?

A. Group I isolation resulting in automatic reactor scram.

B. Trip of Main Steam Line High Flow Channel B ONLY.

C. No response until the high flow is sensed for > 5 seconds.

D. No response until high flow is sensed on a 3rd main steam line.

2022 MONTICELLO ILT NRC EXAM - RO

60.

The plant was operating at rated conditions in a normal electric plant lineup. An event occurs that results in the following:

Annunciator 20-A-08 (FIRE) is alarming

Annunciator 8-A-01 (NO. 1 GENERATOR LOCKOUT) is alarming

The Main Transformer Fire System status is shown below The BOP operator rotates the arming collar and depresses the pushbutton shown above.

Which of the following, if any, is a valid reason for performing these actions?

A. These actions MANUALLY INITIATE deluge spray on the Main Generator Transformer.

B. These actions MANUALLY TRIP open the 345 KV Main Generator output breakers 8N7 and 8N8.

C. These actions MANUALLY TRIP open the Main Generator Field breaker which results in a Generator LOCKOUT.

D. These actions are NOT required; the Main Transformer Deluge IS currently spraying water on the transformer.

2022 MONTICELLO ILT NRC EXAM - RO

61.

The plant is in Mode 1 with a shutdown in progress. Given the following:

Main Turbine Bypass Valves (BV) are closed

LP Turbine exhaust hood temperature is 120°F and stable

CV-1269 (COND HDR TO TURB EXH HOOD SPRAY) is in AUTO

Main Turbine Control Valves (CVs) are open approximately 12% of rated position If condensate flow is lost through CV-1269, which temperature, if any, will FIRST initiate annunciator 7-B-06/07 (LP TURB G-1A/B EXH HOOD HIGH TEMP)?

A. 175°F B. 200°F C. 225°F D. None, this alarm is inactive with CVs <15% open.

2022 MONTICELLO ILT NRC EXAM - RO

62.

Which of the following is correct concerning the Cable Spreading Room (CSR) fire dampers?

CSR fire dampers A. automatically close from Halon pressure.

B. must be closed manually from the ASDS Panel.

C. must be closed manually from PAB 2 outside the CSR.

D. automatically close when control is transferred to the ASDS Panel.

2022 MONTICELLO ILT NRC EXAM - RO

63.

The plant is at 50% power with the Circulating Water System in Partial Recirc.

Both CWPs are running

11 CTP is running

The CWP/CT Pump Auto Trip Interlock Bypass Switch is in AUTO.

A Circ Water rupture results in the receipt of 101-A-11 (HOTWELL AREA FLOODING) and water level on the Pit Floor is at 3 feet and stable.

What will be the status of the CWPs and 11 CTP following this event?

11 CWP 12 CWP 11 CTP A.

RUNNING RUNNING RUNNING B.

TRIPPED RUNNING TRIPPED C.

TRIPPED TRIPPED RUNNING D.

TRIPPED TRIPPED TRIPPED

2022 MONTICELLO ILT NRC EXAM - RO

64.

Which of the following requires the assigned individual(s) to be respirator qualified?

1. Being a Fire Brigade member

2. Being a Control Room Operator during a Toxic Gas event

3. Being an ASDS Panel Operator for Shutdown Outside the Control Room

4. Being a Control Room Operator during ALL Emergency Plan implementations A. 1 and 2 ONLY B. 1, 2 and 3 ONLY C. 1, 2 and 4 ONLY D. 1, 2, 3, and 4

2022 MONTICELLO ILT NRC EXAM - RO

65.

The plant was at rated conditions when the following valid annunciator was received:

Which SRVs will be affected by the alarm indication above?

A. A, B & G B. A, B & E C. C, H & F D. C, D & H

2022 MONTICELLO ILT NRC EXAM - RO

66.

A plant startup is in progress with RPV pressure at 800 psig and both Recirc loops in service.

Which of the following by itself would be a Safety Limit violation with the above conditions?

A. MCPR changed to 0.99 B. MCPR changed to 1.12 C. Reactor power rose to 27%

D. Rated core flow lowered to 8%

2022 MONTICELLO ILT NRC EXAM - RO

67.

The plant is at rated conditions with all electrical buses on their normal supply and the Subyard aligned as follows for maintenance:

10 Bank Transformer is ISOLATED

Breaker 1N2 (13.8 KV OCB) is OPEN

Breaker 1N6 (13.8 KV OCB) is OPEN If a 1R Transformer lockout occurs with the conditions above, which of the following TS/TRM Conditions, if any, must be entered?

A. NO TS/TRM action(s) is/are required to be entered.

B. Enter TS 3.8.1 for lack of qualified Offsite Circuits.

C. Enter TLCO 3.8.1 for lack of NSP transmission lines.

D. Enter TS 3.8.1 and TLCO 3.8.1.

2022 MONTICELLO ILT NRC EXAM - RO

68.

The plant is in Mode 2 when the following annunciators actuated:

3-B-8 (MAIN STEAM LINE HI RADIATION)

3-B-16 (MAIN STEAM LINE CH A HI RADIATION)

3-B-32 (MAIN STEAM LINE CH B HI RADIATION)

If the alarm conditions are now clear, what action(s) must be taken to restart the Mechanical Vacuum Pump (MVP)?

A. Only the PCIS Group 1 Isolation logic must be reset.

B. Only the PCIS Group 2 Isolation logic must be reset.

C. Only the PCIS Group 3 Isolation logic must be reset.

D. Both the PCIS Groups 1 AND 3 Isolation logics must be reset.

2022 MONTICELLO ILT NRC EXAM - RO

69.

A Site Area Emergency has been declared at the plant. You are currently offsite and have been called in to report to the Operations Support Center (OSC).

Which building is the OSC located within?

A. Monticello Training Center B. Plant Engineering Building C. Plant Admin Building D. Warehouse 1

2022 MONTICELLO ILT NRC EXAM - RO

70.

In Mode 1; which of the following indicate that thermal hydraulic oscillations are occurring?

(Evaluate each conditions separately)

A. APRM recorders indicating a peak-to peak oscillation of 1.5%.

B. Core thermal power at 30% with Total Core flow at 30 Mlbm/hr.

C. A single LPRM UPSCALE alarm in the center region of the core.

D. RBM ODAs indicating a peak-to-peak LPRM oscillation of 12.0%.

2022 MONTICELLO ILT NRC EXAM - RO

71.

Prior to a refueling outage, all or nearly all control rods are fully withdrawn at 100% power.

After a refueling outage, a significant amount of control rods are inserted much farther into the core at 100% power.

What is the reason for the change in full power control rod position?

(EOC = End of Cycle, BOC = Beginning of Cycle)

A. Reactivity from power defect at BOC is much greater than at EOC.

B. The integral control rod worth at EOC is much greater than at BOC.

C. Reactivity from void coefficient at EOC is much greater than at BOC.

D. The excess reactivity in the core at BOC is much greater than at EOC.

2022 MONTICELLO ILT NRC EXAM - RO

72.

The plant was at 70% power for 11 days when power was raised to 100% in a 2-hour period.

Once at 100% power, what minor Recirc flow adjustments will be made to offset the change in Xenon-135 concentration over the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ?

A. Lower Recirc flow due to Xe-135 burnout.

B. Raise Recirc flow due to Xe-135 burnout.

C. Lower Recirc flow due to I-135 decay.

D. Raise Recirc flow due to I-135 decay.

2022 MONTICELLO ILT NRC EXAM - RO

73.

The plant was at rated conditions when a scram occurred. RPV pressure has been stable at 925 psig for one hour.

Which of the following is the MINIMUM pressure that the reactor may be reduced to at the end of a one hour cooldown without violating Technical Specifications?

A. 405 psig B. 385 psig C. 365 psig D. 345 psig

2022 MONTICELLO ILT NRC EXAM - RO

74.

The plant has been at rated power for several weeks. It has been determined that air binding is occurring in the main condenser waterboxes.

Which of the following would result from the air binding?

A. Offgas system flow will rise.

B. Main Generator output will rise.

C. Condenser vacuum will degrade.

D. Circ Water condenser outlet temperature will lower.

2022 MONTICELLO ILT NRC EXAM - RO

75.

A rapid rise in the differential temperature (DT) between the fuel clad and the coolant with a lowering in heat flux indicates _________.

A. bulk boiling is occurring B. nucleate boiling is occurring C. critical heat flux (CHF) is rising D. departure from nucleate boiling (DNB)

2022 MONTICELLO ILT NRC EXAM - SRO-I

1.

The plant was at rated conditions when #11 Recirc Pump tripped.

C.4-B.01.04.A (TRIP OF ONE RECIRC PUMP) is being performed

The OATC closes MO-2-53A (11 Recirc Pump Discharge)

Which is correct concerning the action taken above?

MO-2-53A A. should have been left open to prevent thermal clamping.

B. was closed to prevent reverse flow and backward pump rotation.

C. was closed to prevent APRM setpoints from being lower than desired.

D. should have been left open to ensure APRM setpoints are accurate for total core flow.

2022 MONTICELLO ILT NRC EXAM - SRO-I

2.

The plant was at rated conditions when a Station Blackout (SBO) occurred. Complete the following statement:

Unnecessary DC loads are disconnected during performance of the SBO procedure to ensure battery capacity is available for ________ of RCIC operation.

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months C. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

2022 MONTICELLO ILT NRC EXAM - SRO-I

3.

The plant is shutdown for a planned maintenance outage with "A" RHR in shutdown cooling.

The Control Room Operator has identified the following changes in plant conditions:

SRM Channels 23 and 24 indications are trending down

Service Water Effluent monitor indication is trending down

RBCCW radiation monitor indication is trending down Given the above conditions, which Abnormal Procedure should be entered AND why?

A. LOSS OF A 125 VDC BUS for a loss of D-11 (Div 1 125 VDC Distribution Panel)

B. LOSS OF A 125 VDC BUS for a loss of D-21 (Div 2 125 VDC Distribution Panel)

C. LOSS OF A 24 VDC BUS for a loss of D-15 (Div 1 24 VDC Distribution Panel)

D. LOSS OF A 24 VDC BUS for a loss of D-25 (Div 2 24 VDC Distribution Panel)

2022 MONTICELLO ILT NRC EXAM - SRO-I

4.

The plant was at rated conditions when a main turbine generator trip and reactor scram occurred. Given the CURRENT conditions:

Reactor pressure is 810 psig and slowly rising

Main Turbine speed is 1780 rpm and slowly lowering

C.4-A (REACTOR SCRAM) Part B has NOT yet been performed Based on current plant conditions; what is the expected equipment status below?

MAIN TURBINE BYPASS VALVES MAIN TURBINE AUX OIL PUMP A.

OPEN ON B.

OPEN OFF C.

CLOSED ON D.

CLOSED OFF

2022 MONTICELLO ILT NRC EXAM - SRO-I

5.

In response to a reactor scram, the OATC verifies that the Recirc pumps have runback to minimum speed or have tripped.

What is the reason this action is performed?

A. To prevent NPSH limits from being exceeded on the Recirc pump suctions.

B. To eliminate potential for neutron flux oscillations if an ATWS were to occur.

C. To eliminate potential for neutron flux oscillations while the reactor is shutting down.

D. To prevent the recirc pumps from running at shutoff head due to the drop in core d/p.

2022 MONTICELLO ILT NRC EXAM - SRO-I

6.

A significant event has occurred that required the crew to establish plant control at ASDS Control Panel C-292.

Which of the following actions can be performed with B RHR from C-292?

A. Raise RPV water level in the LPCI Mode.

B. Lower Torus water temperature in the Torus Cooling Mode.

C. Lower RPV pressure/temperature in the Shutdown Cooling Mode.

D. Lower Drywell pressure/temperature in the Containment Spray Mode.

2022 MONTICELLO ILT NRC EXAM - SRO-I

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

2022 MONTICELLO ILT NRC EXAM - SRO-I

8.

The plant is at rated conditions when a Service Air leak occurs. Given the following:

C.4-B.08.04.01.A (LOSS OF INSTRUMENT AIR) has been entered

Instrument Air (IA) header pressure is 81 psig and lowering

The BOP places the handswitch for CV-1474 (SERV AIR ISOL CV) in CLOSE Which is a correct reason for the BOP placing the handswitch for CV-1474 in CLOSE?

A. CV-1474 should have automatically closed at 90 psig.

B. This is an IMMEDIATE ACTION of C.4-B.08.04.01.A.

C. CV-1474 does NOT have an AUTOMATIC close feature.

D. This prevents CV-1474 from re-opening if air pressure begins to rise.

2022 MONTICELLO ILT NRC EXAM - SRO-I

9.

The plant was at rated conditions when a transient occurred resulting in a reactor scram.

Actions are being taken to place the plant in Cold Shutdown. Given the following:

A RHR is in Shutdown Cooling

RPV pressure is 70 psig and slowly lowering A LOCKOUT on Bus 15 then occurs and 30 minutes later decay heat has caused RPV pressure to rise to 80 psig.

With the conditions above, which of the following is currently available AND can be used to continue the plant cooldown?

A. RCIC.

B. HPCI.

C. B Shutdown Cooling.

D. Main Turbine Bypass Valves.

2022 MONTICELLO ILT NRC EXAM - SRO-I

10.

The plant is in a Refuel Outage with fuel being loaded into the core.

Which of the following would be considered a refueling error?

A. The lug on the fuel bundle bail points AWAY from the control cell.

B. The base of the fuel bundle serial number is NEAREST the center of the control cell.

C. The channel fastener cap screw is pointed at the CENTER of the respective control cell.

D. An out of sequence in-core fuel bundle is latched with the grapple (NO UPWARD MOTION HAS OCCURRED).

2022 MONTICELLO ILT NRC EXAM - SRO-I

11.

The plant was operating in Mode 2 with a startup in progress. A large leak develops in the Reactor Vessel Bottom Head and the following timeline of events occur:

TIME Reactor Level Reactor Pressure Drywell pressure 00:00:00 30 inches 900 psig 0.5 psig 00:05:00 9 inches 880 psig 0.7 psig 00:10:00 -15 inches 840 psig 1.3 psig 00:15:00 -30 inches 800 psig 1.9 psig 00:20:00 -40 inches 760 psig 2.1 psig 00:25:00 -47 inches 720 psig 2.3 psig Based on the above timeline, which of the following is correct?

A. ONLY a Partial Group 2 Isolation occurred at 00:05:00.

B. All Main Steam Isolation Valves are closed at 00:10:00.

C. Both Emergency Diesel Generators are running at 00:15:00.

D. Division 1 RHR was selected for LPCI Loop injection path at 00:25:00.

2022 MONTICELLO ILT NRC EXAM - SRO-I

12.

The plant is at rated conditions when a Group 1 isolation results in a scram and numerous control rods FAIL to insert. C.5-2007 (FAILURE TO SCRAM) has been entered.

The OATC chooses to perform Part D (RESCRAM CONTROL RODS) of procedure C.5-3101 (ALTERNATE ROD INSERTION).

Which of the following is CORRECT for the performance of Part D?

A. Low-Low Set will be disabled during a portion of Part D.

B. RPV water level must be > -47 inches to perform Part D.

C. BOTH divisions of RPS power are required to perform Part D.

D. CRDH flow will add additional positive reactivity once the scram is reset.

2022 MONTICELLO ILT NRC EXAM - SRO-I

13.

The plant was at rated conditions when a severe ATWS condition occurred. The following indications were noted at 0800:

Of the times below, when will the Torus Heat Capacity (Detail M) be exceeded FIRST?

(Assume Torus temperature rate of change, Torus water level and Reactor pressure remain constant. Detail M is on the following page).

A. 0829 B. 0836 C. 0840 D. 0845

2022 MONTICELLO ILT NRC EXAM - SRO-I

14.

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.

2022 MONTICELLO ILT NRC EXAM - SRO-I

15.

The plant was at rated conditions when a major event occurred including a Torus leak.

Torus water level is -1 foot and lowering

RCIC is injecting to the RPV at rated flow Which Torus level below would the RCIC exhaust FIRST be discharging into the Torus air space?

A. - 3.5 feet B. - 4.0 feet C. - 4.5 feet D. - 6.0 feet

2022 MONTICELLO ILT NRC EXAM - SRO-I

16.

The plant was at normal rated conditions when a LONOP and LOCA occurred.

RBCCW has been restored

CRD-14 (CRD CHARGING WATER TO ACCUMS) is OPEN

C.5-3204 (RPV MAKEUP WITH CRD) is required for RPV level control Which is correct concerning RPV level if CRD pumps are restarted with the conditions above?

A. A pressure transient could cause a LOWER indicated RPV water level.

B. A pressure transient could cause a HIGHER indicated RPV water level.

C. RPV level would not be affected; CRD pumps will NOT start following a LONOP.

D. RPV level would not be affected; CRD-141 (RPV BACKFILL ISOL) auto CLOSES on a scram.

2022 MONTICELLO ILT NRC EXAM - SRO-I

17.

The plant was at rated conditions when a scram and ATWS condition occurred. The following conditions are present:

Reactor power 20% and lowering

The Main Condenser is unavailable

RPV pressure is cycling on Lo-Lo Set

Torus water temperature is 95°F and rising

RPV water level is being maintained -150 to -100

Standby Liquid Control (SBLC) System 1 has been initiated The CRS now directs the OATC to report when SBLC tank level reaches 985 gallons.

Which of the following describes the reason for reporting this tank level?

A. This will allow a normal RPV depressurization to begin.

B. This will allow RPV water level to be restored to +9 to +48.

C. This will allow SBLC injection from System 1 to be secured.

D. This will allow the crew to exit C.5-2007 (FAILURE TO SCRAM).

2022 MONTICELLO ILT NRC EXAM - SRO-I

18.

The plant is at rated conditions. Given the following:

4-A-12 (OFF GAS HI RADIATION) has been in alarm for 5 minutes A rapid power reduction was performed down to 80% reactor power Main Steam Line Radiation Monitors still indicate above normal radiation levels Which action must be taken for the above conditions and why?

A. Initiate the SBGT system to filter the off-site release.

B. Insert a Reactor scram to minimize the off-site release.

C. Bypass the Off-gas Storage system to isolate the off-site release.

D. Restart an Off-gas Recombiner train to lower off-gas radiation levels.

2022 MONTICELLO ILT NRC EXAM - SRO-I

19.

The plant is at rated conditions when a small lube oil fire is reported in the Recirc MG Set Room.

Which is the most effective method of extinguishing this fire?

A. CO2 B. Halon C. Pressurized water D. Dry Chemical / Foam

2022 MONTICELLO ILT NRC EXAM - SRO-I

20.

The plant was at rated conditions when grid disturbance resulted in a Main Generator transformer lockout. A fire has erupted in the main generator transformer and the Fire Brigade has been dispatched.

Where can the Main Generator Transformer deluge be initiated from?

A. A control switch on C-300 (Zonalert Control Room Panel).

B. A deluge valve in the Northwest corner of the12 EDG Room.

C. A deluge valve outside the South wall of the Recirc MG Set Room.

D. A deluge valve in the Southeast corner of the East Electrical Equipment Room.

2022 MONTICELLO ILT NRC EXAM - SRO-I

21.

The plant was in Mode 1 when a High RPV Water Level Trip occurred:

1. Which logic initiates this trip?

2. What equipment is protected by this trip?

(1)

(2)

A.

ATWS SRV Bellows B.

ECCS SRV Bellows C.

ATWS Main Turbine blading D.

ECCS Main Turbine blading

2022 MONTICELLO ILT NRC EXAM - SRO-I

22.

The plant was at rated conditions when a steam line rupture resulted in the following:

Drywell temperature is 340°F and rising

Attempts to spray the drywell have been unsuccessful

The CRS is directing an RPV Blowdown While performing your RPV Blowdown actions, the following indications were noted:

(ALL lights below are extinguished)

Which SINGLE condition below would be a valid reason for the indications shown above?

A. The SRV bellows has RUPTURED.

B. The SRV amber light is BURNT OUT.

C. The SRV is mechanically STUCK CLOSED.

D. The SRV solenoid valve is NOT ENERGIZED.

2022 MONTICELLO ILT NRC EXAM - SRO-I

23.

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 alarm 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.

2022 MONTICELLO ILT NRC EXAM - SRO-I

24.

The plant is at rated conditions when a steam leak occurs in the Steam Jet Air Ejector room.

If an automatic Secondary Containment isolation/SBGT initiation occurs, what will happen to the release rate from the RB Exhaust Plenum Room, and why?

The release rate will A. lower because the Turbine Building supply fans will trip.

B. rise because the Plenum room exhaust fans take suction from the SJAE room.

C. rise because SJAE room exhaust will be redirected to the RB Exhaust Plenum room.

D. lower because the SBGT system will be processing the steam leak from the SJAE room.

2022 MONTICELLO ILT NRC EXAM - SRO-I

25.

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:

Annunciators that are IN alarm:

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

259-A-6 (RBV EFFLUENT HIGH RADIATION)

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)

Based ONLY on the alarm conditions above; which is a correct action to take, and why?

A. Restart Secondary Containment ventilation because both SBGT trains failed to start.

B. Depress both SBGT TEST pushbuttons on C-24A/B because both SBGT trains failed to start.

C. Restart Secondary Containment ventilation to ensure a negative pressure exists in the Reactor Building.

D. Depress both SBGT TEST pushbuttons on C-24A/B to ensure a filtered release from the Reactor Building.

2022 MONTICELLO ILT NRC EXAM - SRO-I

26.

Given the following conditions:

Main Steam Chase temperature is 220°F and rising

Room temperatures in other Reactor Building areas are normal

Numerous Turbine Building rad monitors show a rise in radiation levels Complete the following statements:

PCIS Group __(1)__ Isolation(s) has/have occurred.

Rupture of the Blowout Panels is causing steam to be released to the __(2)__.

(1) (2)

A. IV & V Turbine Operating Floor B. I Turbine Operating Floor C. IV & V Condenser Hotside D. I Condenser Hotside

2022 MONTICELLO ILT NRC EXAM - SRO-I

27.

The plant was operating at rated conditions when a LOCA occurred in the Drywell (DW).

Given the following:

DW pressure is 11 psig and slowly lowering

RPV pressure is 440 psig and slowly lowering

RPV water level is -164 inches and slowly lowering

B RHR System status is shown on the following page Based on the given conditions, complete the following statement:

The Torus Spray/Cooling valves A. WILL automatically close when DW pressure is < 1.5 psig.

B. WILL automatically close when RPV pressure is < 420 psig.

C. WILL automatically close when RPV water level reaches 2/3 core height.

D. SHOULD have automatically closed when RPV pressure went < 460 psig.

2022 MONTICELLO ILT NRC EXAM - SRO-I

28.

The plant is in Mode 5 performing a core reload:

The core reload is 50% complete

RPV water level is > 2111 above the top of the RPV flange

Division 1 Shutdown Cooling (SDC) is inoperable and unavailable

12 and 14 RHR pumps are in the SDC mode If 14 RHR pump trips, will Tech Specs continue to allow loading of fuel into the core, why?

A. NO, since Division 1 SDC is not available.

B. YES, since one RHR pump is still the SDC mode of operation.

C. YES, if an alternate method of DHR is verified available within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. NO, two RHR pumps must be in the SDC mode of operation at all times when moving fuel.

2022 MONTICELLO ILT NRC EXAM - SRO-I

29.

The plant is in Mode 4 with the following conditions:

11 & 13 RHR Pumps are at rated flow in the Shutdown Cooling mode.

12 & 14 RHR Pumps are at rated flow in the Torus Cooling mode.

A small LOCA results in RPV water level lowering to a stable +5 inches.

Which approximates the TOTAL RHR System flow rate once conditions stabilize?

A. 0 gpm B. 6000 gpm C. 8000 gpm D. 16,000 gpm

2022 MONTICELLO ILT NRC EXAM - SRO-I

30.

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

RPV water level lowered to -45" and is now +35" and stable

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, which one of the following is correct?

A. The ADS timer is initiated.

B. RCIC suction has auto transferred at a torus level of +2 inches.

C. Core spray pumps are running and injecting to the Reactor vessel.

D. HPCI is injecting at rated flow to the RPV with its suction aligned to the Torus.

2022 MONTICELLO ILT NRC EXAM - SRO-I

31.

A plant transient has occurred that resulted in an automatic initiation and injection from the Division 1 Core Spray system. MO-1753 (DIV 1 CS INJECTION INB) is full open with an ECCS initiation signal still present.

Can MO-1753 be used to throttle Core Spray flow? Why or why not?

A. NO, this valve CANNOT be closed with an initiation signal still present.

B. NO, MO-1751 (DIV 1 CS INJECTION OTB) should be used for throttling flow with an initiation signal present.

C. YES, placing HS 14A-S16A (DIV 1 CS INJECTION BYPASS) keylock switch to "BYPASS" will bypass the MO-1753 open signal.

D. YES, placing HS 14A-S1A for MO-1753 (DIV 1 CS INJECTION INB) in the "CLOSE" position will bypass the MO-1753 open signal.

2022 MONTICELLO ILT NRC EXAM - SRO-I

32.

An ATWS event has occurred and the OATC has initiated SBLC from C-05.

Complete the statements below.

Forced circulation is __(1)__ to ensure adequate dispersion of the boron solution into the core.

RWCU pumps __(2)__ receive an automatic trip signal.

A. (1) required (2) will B. (1) required (2) will NOT C. (1) NOT required (2) will D. (1) NOT required (2) will NOT

2022 MONTICELLO ILT NRC EXAM - SRO-I

33.

The reactor was at rated conditions when the following occurred:

A manual scram has been inserted

All scram signals are clear EXCEPT the SDV HI HI level

The SDV HI HI level has been bypassed

The CRS directs the scram to be reset Which position(s) of the Mode Switch will allow the scram to be reset?

A. SHUTDOWN ONLY B. SHUTDOWN OR REFUEL ONLY C. SHUTDOWN OR REFUEL OR START AND HOT STBY ONLY D. SHUTDOWN OR REFUEL OR START AND HOT STBY OR RUN

2022 MONTICELLO ILT NRC EXAM - SRO-I

34.

The Reactor Mode Switch is in STARTUP TO HOT STANDBY. IRM 17 is BYPASSED and ALL other IRM Range Switches are on Range 4. A failure of IRM 11 results in the following IRM readings:

IRM 11 IRM 12 IRM 13 IRM 14 IRM 15 IRM 16 IRM 17 IRM 18 125 70 69 76 72 67 0 68 Based on conditions above; which of the following is the status of RPS and/or RMCS?

A. A Full Scram has occurred.

B. An RMCS rod block ONLY has occurred.

C. An RMCS rod block and a RPS A half scram ONLY have occurred.

D. An RMCS rod block and a RPS B half scram ONLY have occurred.

2022 MONTICELLO ILT NRC EXAM - SRO-I

35.

The plant is in a Refuel Outage with the following conditions:

Fuel is being moved into and out of the core

Maintenance is under the vessel staging for CRD Mechanism removal

Shorting links have been REMOVED

IRMs are on Range 1

All SRMs read ~10 cps

Mode Switch is in REFUEL Complete the statements below if the SRM count level were to rise to 5.5 x 105 cps.

1) Annunciator SRM HI/INOP will _____(1)_____.

2) Annunciator ROD WITHDRAW BLOCK will _____(2)_____.

3) A _____(3)_____ will occur.

(1) (2) (3)

A. NOT Alarm Alarm Half Scram ONLY B. Alarm NOT Alarm Full Scram C. Alarm Alarm Half Scram ONLY D. Alarm Alarm Full Scram

2022 MONTICELLO ILT NRC EXAM - SRO-I

36.

A plant startup is in progress.

FT-2-110A (REC 11 FLOW XMTR - APRM 1) failed upscale causing the following alarms:

5-A-3 (ROD WITHDRAW BLOCK)

5-A-30 (APRM FLOW BIAS OFF NORMAL)

Complete the statements below?

__(1)__ is preventing control rods from being withdrawn.

Bypassing APRM 1 __(2)__ allow control rods to be withdrawn.

A. (1) RBM Flow Comparison >10%

(2) WILL B. (1) RBM Flow Comparison >10%

(2) WILL NOT C. (1) APRM Flow Upscale >110%

(2) WILL D. (1) APRM Flow Upscale >110%

(2) WILL NOT

2022 MONTICELLO ILT NRC EXAM - SRO-I

37.

A plant transient has occurred resulting in a loss of No. 11 and No. 12 Reactor Feed Water pumps, Reactor scram, and a Group 1 Primary Containment Isolation.

RCIC was operating to restore RPV water level when RCIC flow lowered to 0 gpm and the following indications were observed:

RCIC turbine exhaust pressure is 20 psig

The Mechanical Overspeed light on C-04 is ON.

The Group 5 Isolation Reset light on C-04 is ON

MO-2078 (RCIC Turbine Steam Supply Valve) is OPEN

MO-2080 (RCIC Turbine Trip and Throttle Valve) is CLOSED Based on the above indications, what was the cause of the RCIC turbine trip?

A. Mechanical overspeed B. High Reactor water level C. High turbine exhaust pressure D. Group 5 containment isolation

2022 MONTICELLO ILT NRC EXAM - SRO-I

38.

The plant is at rated conditions when RCIC automatically initiated on a valid initiation signal.

RCIC continues to operate at rated flow.

Which of the following will cause 4-A-14 (RCIC FLOW LOW) to alarm?

A. Torus water level of -5 inches B. Condensate Storage Tank level of 2 feet 5 inches C. CV-2104 (RCIC Pump Minimum Flow Valve) fails open D. RCIC pump suction pressure degrades to 17 inches Hg Vac

2022 MONTICELLO ILT NRC EXAM - SRO-I

39.

The plant was at rated conditions when a steam line rupture occurred in the drywell and the following conditions are now present:

Drywell Sprays are unavailable

Drywell temperature is 290°F and rising

A complete loss of 125 VDC Bus A has occurred

Emergency Depressurization has been entered

As the BOP, the CRS directs you to open all three ADS valves Given the conditions above, which of the following SRVs must you use 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.

2022 MONTICELLO ILT NRC EXAM - SRO-I

40.

The plant is at rated conditions with the HPCI turbine at rated speed for quarterly testing.

HPCI-82 (EXH LINE ISOLATION) experiences a stem failure resulting in a complete blockage of the HPCI exhaust line.

Using P&ID NH-36249 (HPCI-Steam Side); how would this blockage affect the HPCI system if the turbine FAILED TO TRIP on high exhaust pressure, and what action must be taken?

A. The HPCI system is NOT protected in this condition; HPCI must be manually tripped.

B. Rupture discs will burst relieving steam directly to the HPCI room; verify the Group 4 Isolation.

C. Rupture discs will burst relieving steam directly to the Torus catwalk area; verify the Group 4 Isolation.

D. Rupture discs will burst relieving steam via a 4 inch line directly to the Torus water space; HPCI must be manually tripped.

2022 MONTICELLO ILT NRC EXAM - SRO-I

41.

The plant is at rated conditions when 3-A-17 (AUTO BLOWDOWN VLV BELLOWS LEAKING) alarms and the following indication is observed:

Which of the following describes the ability of SRV A to depressurize the RPV vessel?

SRV A A. will operate automatically in the ADS mode.

B. will operate automatically in the LL-SET mode.

C. will operate for its safety function but at a lower reactor pressure.

D. CANNOT be opened manually from C-03 to depressurize the RPV vessel.

2022 MONTICELLO ILT NRC EXAM - SRO-I

42.

The plant was at rated conditions when a 12 Bus Lockout occurred. Immediate Actions have been taken for the trip of 12 Reactor Feed Pump (RFP). Given the following:

CV-3490 (12 RFP FW RECIRC TO CDSR) failed open

11 RFP suction pressure is 92 psig and stable

RPV water level is +27 inches and stable

Reactor power is 62% and stable What action should be taken to mitigate the conditions above?

A. Insert control rods IAW C.4-F (RAPID POWER REDUCTION).

B. Scram the reactor IAW C.4-K (IMMEDIATE REACTOR SHUTDOWN).

C. Raise the setpoint of LC-6-83 (FW MASTER CONTROLLER) back to normal.

D. Raise the setpoint of FC-1095 (11/12 COND PMP RECIRC FLOW) to 4500 gpm.

2022 MONTICELLO ILT NRC EXAM - SRO-I

43.

Given the following conditions:

Drywell pressure is 1.0 psig

Reactor level is 35 inches

"A" SBGT is isolated for maintenance and "B" SBGT is in Standby What is the response of "B" SBGT following a loss of RPS Bus A (Y-50)?

A. Starts immediately.

B. Starts after a 10-second delay.

C. Remains in Standby since no initiation signal is present.

D. Remains in Standby since RPS Bus B (Y-40) is still available.

2022 MONTICELLO ILT NRC EXAM - SRO-I

44.

The plant was at rated conditions when a Station Blackout (SBO) occurred.

Which 4160 VAC bus(es) can be procedurally reenergized for the conditions above?

A. Bus 13 ONLY B. Bus 14 ONLY C. Buses 13 and 15 D. Buses 14 and 16

2022 MONTICELLO ILT NRC EXAM - SRO-I

45.

The plant was at rated conditions when SPR-63 (SUDDEN PRESSURE RELAY) actuated in the Main Generator transformer.

Which of the following completes the statements below?

This condition DIRECTLY actuates the __(1)__.

The field breaker trips open __(2)__.

A. (1) turbine lockout relay (286/T)

(2) immediately B. (1) turbine lockout relay (286/T)

(2) once 8N7 and 8N8 are sensed open C. (1) generator lockout relay (286/G)

(2) immediately D. (1) generator lockout relay (286/G)

(2) once 8N7 and 8N8 are sensed open

2022 MONTICELLO ILT NRC EXAM - SRO-I

46.

Given the following 480 Volt UPS Electrical Distribution Drawing:

If an inverter UNDERVOLTAGE fault results in 0 volts sensed at Point X above; which of the following describes how Y-94 will receive its power?

A. LC-107 will automatically supply power to Y-94.

B. LC-108 will automatically supply power to Y-94.

C. 250 VDC Battery 17 will automatically supply power to Y-94.

D. The Maintenance Bypass Breaker must be manually closed to power Y-94.

2022 MONTICELLO ILT NRC EXAM - SRO-I

47.

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 and no operator action is taken.)

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 immediately after a Core Spray or RHR pump is 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.

2022 MONTICELLO ILT NRC EXAM - SRO-I

48.

The plant is operating at rated conditions when a DC supply breaker trip results in the receipt of 20-B-09 (DIVISION II 125/250 DC TROUBLE).

Which system must be monitored in the control room to confirm the given power loss?

A. HPCI B. RCIC C. RWCU D. Turbine Lube Oil

2022 MONTICELLO ILT NRC EXAM - SRO-I

49.

The plant is at rated conditions. Given the following:

1AR transformer is tagged out for maintenance.

52-908/CS (109-102 LOAD CENTER TIE ACB 52-908) handswitch in PTL.

If a BUS 13 LOCKOUT were to occur AND 11 EDG failed to start, which Load Centers will be energized ONE MINUTE after the lockout?

LC-101

LC-103

LC-107 A. LC-103 ONLY B. LC-101 AND LC-103 ONLY C. LC-101 AND LC-107 ONLY D. All three Load Centers would be energized

2022 MONTICELLO ILT NRC EXAM - SRO-I

50.

A plant startup/heatup is in progress with the following conditions:

CV-2403 (RWCU DUMP FLOW) is 60% open to maintain RPV level

CV-6-13 (LOW FLOW REGULATING VALVE) is closed in Automatic control

A complete loss of Instrument Air occurs While implementing C.4-B.08.04.01.A (LOSS OF INSTUMENT AIR), which of the following valve indications would be expected?

CV-2403 CV-6-13 A.

open closed B.

60% open open C.

open open D.

closed closed

2022 MONTICELLO ILT NRC EXAM - SRO-I

51.

A plant startup is in progress with the following conditions:

MO-2399 (RWCU RETURN ISOL) is 25% open

MO-3501 (RBCCW FROM RWCU HX) is 50% open

CV-2403 (RWCU EXCESS FLOW CTRL VLV) is controlling dump flow at 60 gpm With the conditions above which of the following actions must be taken if annunciator 4-B-26 (CLEANUP DEMIN TEMP HI) is received?

A. Throttle OPEN CV-2403.

B. Throttle OPEN MO-3501.

C. Throttle CLOSED MO-3501.

D. Throttle CLOSED MO-2399.

2022 MONTICELLO ILT NRC EXAM - SRO-I

52.

The normal Service Water supply has been lost to the following coolers:

V-AC-6 (RCIC ROOM COOLER)

V-AC-7A/B (CRD ROOM COOLERS)

V-AC-8A/B (HPCI ROOM COOLERS)

If EFT-ESW Pumps were started, which cooler(s), if any, will still be monitored for outlet radiation?

[Service Water System P&IDs NH-36041 (M-110) and NH-36664 (M-112) are provided]

A. V-AC-8A/B ONLY B. V-AC-8A/B and V-AC-6 ONLY C. V-AC-7A/B and V-AC-6 and ONLY D. NO coolers will be monitored for outlet radiation.

2022 MONTICELLO ILT NRC EXAM - SRO-I

53.

The plant was at rated conditions when an event occurred resulting in the following readings:

1. Control Room Air Intake Monitors - 2.5 mrem/hr

2. Refueling Floor Radiation Monitors - 60 mrem/hr

3. RB Exhaust Plenum Radiation Monitors - 21 mrem/hr Which of the given instrument radiation readings will cause CRV/EFT to initiate in the High Radiation Mode?

A. 1 ONLY B. 2 ONLY C. 1 & 2 ONLY D. 1, 2 AND 3

2022 MONTICELLO ILT NRC EXAM - SRO-I

54.

Given the following:

Control rod 26-27 is at position 48

Control rod 30-19 is at position 48 and is presently being inserted to position 42 using normal rod insertion Complete the statement below?

Annunciator 5-A-27, ROD DRIFT, will alarm _______________.

A. if rod 26-27 moves off position 48 B. when rod 30-19 moves past position 47 C. if the TIMER TEST switch is taken to the RESET position D. when the ROD MOVEMENT CONTROL switch is released to the OFF position

2022 MONTICELLO ILT NRC EXAM - SRO-I

55.

Which of the following will lose power on a loss of D11 (DIVISION 1 125 VDC)?

A. TIP Shear Valve B. SRMs 21 and 22 C. IRMs 15, 16, 17 and 18 D. HPCI System Control Power

2022 MONTICELLO ILT NRC EXAM - SRO-I

56.

The plant was at rated conditions when a Torus break and LOCA occurred.

RPV pressure is 25 psig

Torus water level is - 6 feet

RHR pumps are unavailable

DW/Torus pressure is 8 psig and slowly rising

RHRSW-14 (EMERG INJ VIA A RHRSW) will NOT open

P&IDs M-112 and M-121 for RHRSW and ESW Systems is provided Which of the following methods can be used to spray the Torus?

A. RHRSW B. Fire Water C. Domestic Well Water D. Condensate Service Water

2022 MONTICELLO ILT NRC EXAM - SRO-I

57.

The plant is in a refuel outage with the following conditions established:

Reactor Cavity Flooded

Fuel Pool to Cavity Gates Removed If the reactor cavity bellows were to develop an unisolable leak, which of the following represents how low water level would get in the fuel pool?

(Assume emergency makeup is NOT available.)

A. ONLY the upper tie plates of the fuel would become UNCOVERED.

B. ONLY 1/3 of the fuel would become UNCOVERED.

C. ONLY 2/3 of the fuel would become UNCOVERED.

D. A complete draining of the spent fuel pool would occur.

2022 MONTICELLO ILT NRC EXAM - SRO-I

58.

Which plant conditions meet the definition of REFUELING MODE 5?

A. Reactor water temperature is 100°F Mode switch is in SHUTDOWN ALL RPV closure head bolts fully tensioned B. Reactor water temperature is 180°F Mode switch is in SHUTDOWN RPV head is removed C. Reactor water temperature is 200°F Mode switch is in REFUEL ALL RPV closure head bolts fully tensioned D. Reactor water temperature is 221°F Mode switch is in SHUTDOWN ALL RPV closure head bolts fully tensioned

2022 MONTICELLO ILT NRC EXAM - SRO-I

59.

With the plant operating at full power, the indicated flow on the "D" Main Steam Line went fully upscale. Actual steam flow rose to 123% flow for two seconds. The flow indications on the "A", "B" and "C" Main Steam Lines lowered to less than their normal 100% flow during the two second transient.

Which statement describes expected plant protection response to this condition?

A. Group I isolation resulting in automatic reactor scram.

B. Trip of Main Steam Line High Flow Channel B ONLY.

C. No response until the high flow is sensed for > 5 seconds.

D. No response until high flow is sensed on a 3rd main steam line.

2022 MONTICELLO ILT NRC EXAM - SRO-I

60.

The plant was operating at rated conditions in a normal electric plant lineup. An event occurs that results in the following:

Annunciator 20-A-08 (FIRE) is alarming

Annunciator 8-A-01 (NO. 1 GENERATOR LOCKOUT) is alarming

The Main Transformer Fire System status is shown below The BOP operator rotates the arming collar and depresses the pushbutton shown above.

Which of the following, if any, is a valid reason for performing these actions?

A. These actions MANUALLY INITIATE deluge spray on the Main Generator Transformer.

B. These actions MANUALLY TRIP open the 345 KV Main Generator output breakers 8N7 and 8N8.

C. These actions MANUALLY TRIP open the Main Generator Field breaker which results in a Generator LOCKOUT.

D. These actions are NOT required; the Main Transformer Deluge IS currently spraying water on the transformer.

2022 MONTICELLO ILT NRC EXAM - SRO-I

61.

The plant is in Mode 1 with a shutdown in progress. Given the following:

Main Turbine Bypass Valves (BV) are closed

LP Turbine exhaust hood temperature is 120°F and stable

CV-1269 (COND HDR TO TURB EXH HOOD SPRAY) is in AUTO

Main Turbine Control Valves (CVs) are open approximately 12% of rated position If condensate flow is lost through CV-1269, which temperature, if any, will FIRST initiate annunciator 7-B-06/07 (LP TURB G-1A/B EXH HOOD HIGH TEMP)?

A. 175°F B. 200°F C. 225°F D. None, this alarm is inactive with CVs <15% open.

2022 MONTICELLO ILT NRC EXAM - SRO-I

62.

Which of the following is correct concerning the Cable Spreading Room (CSR) fire dampers?

CSR fire dampers A. automatically close from Halon pressure.

B. must be closed manually from the ASDS Panel.

C. must be closed manually from PAB 2 outside the CSR.

D. automatically close when control is transferred to the ASDS Panel.

2022 MONTICELLO ILT NRC EXAM - SRO-I

63.

The plant is at 50% power with the Circulating Water System in Partial Recirc.

Both CWPs are running

11 CTP is running

The CWP/CT Pump Auto Trip Interlock Bypass Switch is in AUTO.

A Circ Water rupture results in the receipt of 101-A-11 (HOTWELL AREA FLOODING) and water level on the Pit Floor is at 3 feet and stable.

What will be the status of the CWPs and 11 CTP following this event?

11 CWP 12 CWP 11 CTP A.

RUNNING RUNNING RUNNING B.

TRIPPED RUNNING TRIPPED C.

TRIPPED TRIPPED RUNNING D.

TRIPPED TRIPPED TRIPPED

2022 MONTICELLO ILT NRC EXAM - SRO-I

64.

Which of the following requires the assigned individual(s) to be respirator qualified?

1. Being a Fire Brigade member

2. Being a Control Room Operator during a Toxic Gas event

3. Being an ASDS Panel Operator for Shutdown Outside the Control Room

4. Being a Control Room Operator during ALL Emergency Plan implementations A. 1 and 2 ONLY B. 1, 2 and 3 ONLY C. 1, 2 and 4 ONLY D. 1, 2, 3, and 4

2022 MONTICELLO ILT NRC EXAM - SRO-I

65.

The plant was at rated conditions when the following valid annunciator was received:

Which SRVs will be affected by the alarm indication above?

A. A, B & G B. A, B & E C. C, H & F D. C, D & H

2022 MONTICELLO ILT NRC EXAM - SRO-I

66.

A plant startup is in progress with RPV pressure at 800 psig and both Recirc loops in service.

Which of the following by itself would be a Safety Limit violation with the above conditions?

A. MCPR changed to 0.99 B. MCPR changed to 1.12 C. Reactor power rose to 27%

D. Rated core flow lowered to 8%

2022 MONTICELLO ILT NRC EXAM - SRO-I

67.

The plant is at rated conditions with all electrical buses on their normal supply and the Subyard aligned as follows for maintenance:

10 Bank Transformer is ISOLATED

Breaker 1N2 (13.8 KV OCB) is OPEN

Breaker 1N6 (13.8 KV OCB) is OPEN If a 1R Transformer lockout occurs with the conditions above, which of the following TS/TRM Conditions, if any, must be entered?

A. NO TS/TRM action(s) is/are required to be entered.

B. Enter TS 3.8.1 for lack of qualified Offsite Circuits.

C. Enter TLCO 3.8.1 for lack of NSP transmission lines.

D. Enter TS 3.8.1 and TLCO 3.8.1.

2022 MONTICELLO ILT NRC EXAM - SRO-I

68.

The plant is in Mode 2 when the following annunciators actuated:

3-B-8 (MAIN STEAM LINE HI RADIATION)

3-B-16 (MAIN STEAM LINE CH A HI RADIATION)

3-B-32 (MAIN STEAM LINE CH B HI RADIATION)

If the alarm conditions are now clear, what action(s) must be taken to restart the Mechanical Vacuum Pump (MVP)?

A. Only the PCIS Group 1 Isolation logic must be reset.

B. Only the PCIS Group 2 Isolation logic must be reset.

C. Only the PCIS Group 3 Isolation logic must be reset.

D. Both the PCIS Groups 1 AND 3 Isolation logics must be reset.

2022 MONTICELLO ILT NRC EXAM - SRO-I

69.

A Site Area Emergency has been declared at the plant. You are currently offsite and have been called in to report to the Operations Support Center (OSC).

Which building is the OSC located within?

A. Monticello Training Center B. Plant Engineering Building C. Plant Admin Building D. Warehouse 1

2022 MONTICELLO ILT NRC EXAM - SRO-I

70.

In Mode 1; which of the following indicate that thermal hydraulic oscillations are occurring?

(Evaluate each conditions separately)

A. APRM recorders indicating a peak-to peak oscillation of 1.5%.

B. Core thermal power at 30% with Total Core flow at 30 Mlbm/hr.

C. A single LPRM UPSCALE alarm in the center region of the core.

D. RBM ODAs indicating a peak-to-peak LPRM oscillation of 12.0%.

2022 MONTICELLO ILT NRC EXAM - SRO-I

71.

Prior to a refueling outage, all or nearly all control rods are fully withdrawn at 100% power.

After a refueling outage, a significant amount of control rods are inserted much farther into the core at 100% power.

What is the reason for the change in full power control rod position?

(EOC = End of Cycle, BOC = Beginning of Cycle)

A. Reactivity from power defect at BOC is much greater than at EOC.

B. The integral control rod worth at EOC is much greater than at BOC.

C. Reactivity from void coefficient at EOC is much greater than at BOC.

D. The excess reactivity in the core at BOC is much greater than at EOC.

2022 MONTICELLO ILT NRC EXAM - SRO-I

72.

The plant was at 70% power for 11 days when power was raised to 100% in a 2-hour period.

Once at 100% power, what minor Recirc flow adjustments will be made to offset the change in Xenon-135 concentration over the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ?

A. Lower Recirc flow due to Xe-135 burnout.

B. Raise Recirc flow due to Xe-135 burnout.

C. Lower Recirc flow due to I-135 decay.

D. Raise Recirc flow due to I-135 decay.

2022 MONTICELLO ILT NRC EXAM - SRO-I

73.

The plant was at rated conditions when a scram occurred. RPV pressure has been stable at 925 psig for one hour.

Which of the following is the MINIMUM pressure that the reactor may be reduced to at the end of a one hour cooldown without violating Technical Specifications?

A. 405 psig B. 385 psig C. 365 psig D. 345 psig

2022 MONTICELLO ILT NRC EXAM - SRO-I

74.

The plant has been at rated power for several weeks. It has been determined that air binding is occurring in the main condenser waterboxes.

Which of the following would result from the air binding?

A. Offgas system flow will rise.

B. Main Generator output will rise.

C. Condenser vacuum will degrade.

D. Circ Water condenser outlet temperature will lower.

2022 MONTICELLO ILT NRC EXAM - SRO-I

75.

A rapid rise in the differential temperature (DT) between the fuel clad and the coolant with a lowering in heat flux indicates _________.

A. bulk boiling is occurring B. nucleate boiling is occurring C. critical heat flux (CHF) is rising D. departure from nucleate boiling (DNB)

2022 MONTICELLO ILT NRC EXAM - SRO-I

76.

The plant is in Mode 5 during a refueling outage with the following conditions:

All SRVs are gagged CLOSED

The Reactor is fueled with the Cavity flooded

Fuel Pool Gates are IN with a drain time of > 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Decay Heat load is within the RWCU capacity.

The Condensate & Feedwater System is unavailable

Division 2 AC and DC electrical buses are de-energized for emergent maintenance

11 RHR pump and 13 RHRSW pump are in Shutdown Cooling An electrical fault results in an 11 RHR Pump LOCKOUT.

What will be the resultant Decay Heat Removal risk color and what action should be taken regarding the Division 2 electrical bus maintenance? (Form 2270 pg. 2 is provided on the following page).

A. YELLOW; stop the maintenance until 11 RHR pump is restored.

B. YELLOW; continue the maintenance around the clock until completed.

C. ORANGE; stop the maintenance until 11 RHR pump is restored.

D. ORANGE; continue the maintenance around the clock until completed.

2022 MONTICELLO ILT NRC EXAM - SRO-I

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 performed by the CRS?

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.

2022 MONTICELLO ILT NRC EXAM - SRO-I

78.

The plant is at rated conditions when a Train A N2 leak results in the following:

PI-4895 (ALT N2 TRAIN A HEADER PRESSURE) reads 85 psig

AI-719 (ALT N2 TRAIN A PCV-4904 ISOL) is OPEN Which of the following is correct?

A. ONLY Declare one LLS valve inoperable Restore ALT N2 Train A pressure within 14 days.

B. ONLY Declare one ADS valve inoperable Restore ALT N2 Train A pressure within 14 days.

C. Declare one ADS valve AND one LLS valve inoperable Restore ALT N2 Train A pressure within 14 days.

D. Declare two ADS valves inoperable Place the plant in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2022 MONTICELLO ILT NRC EXAM - SRO-I

79.

The plant is in Mode 5 when a Refueling Accident occurred at 1230. Given the following:

At 0100 the Stack WRGMs read as follows:

Stack Effluent Monitor Channels A & B read 5.0E+5 µCi/Sec.

At 0105 the Stack WRGMs read as follows:

Stack Effluent Monitor Channel A & B read 6.8E+5 µCi/Sec.

Of the times below, when is the earliest that conditions will be met to declare an ALERT?

(Assume radiation levels continue to rise at the same rate)

A. 0100 B. 0105 C. 0110 D. 0115

2022 MONTICELLO ILT NRC EXAM - SRO-I

80.

Which of the following activities REQUIRE the use of the Bypass Control Process?

A. LIFTING an electrical lead for annunciator 5-B-45 (DRYWELL HI/LO PRESS).

B. Installing a TEMPORARY hose to drain the Service Water System to the floor drains.

C. Opening C-31 INSTALLED Knife Switch 16 with plant power fed from the 1R Transformer.

D. Installing new Condensate Demineralizers that have NOT yet been RELEASED to the plant.

2022 MONTICELLO ILT NRC EXAM - SRO-I

81.

The plant is at rated condition in a normal electrical lineup with the following conditions:

Reactor power indicates 2003 MWth

The EPR Control Position is set at 904 PSI

The MPR Handwheel Position indicates 914 PSI An equipment malfunction causes the MCC-142A supply breaker to TRIP OPEN.

For the above conditions:

1) Which of the following procedures must be directed?

2) Why?

A. 1) C.4-K (IMMEDIATE REACTOR SHUTDOWN)

2) To lower reactor power below the license limit.

B. 1) C.4-K (IMMEDIATE REACTOR SHUTDOWN)

2) For a Pressure Regulator setpoint failing downscale.

C. 1) C.4-B.05.09.B (PRESSURE REGULATOR FAILURE CAUSING INCREASED PRESSURE)

2) To lower reactor pressure in order to lower reactor power below the license limit.

D. 1) C.4-B.05.09.B (PRESSURE REGULATOR FAILURE CAUSING INCREASED PRESSURE)

2) For a Pressure Regulator setpoint failing downscale.

2022 MONTICELLO ILT NRC EXAM - SRO-I

82.

The plant is at rated conditions:

4-B-4 (SUPPRESSION WATER LEVEL HI/LOW) is received

Torus water level indicates -0.4 feet on SPDS Complete the statements below:

(1) IAW the Technical Specification Bases, are the DBA LOCA assumed initial conditions satisfied for Torus water level?

(2) If the Torus Downcomer lines become uncovered, which capability will be lost?

A. (1) satisfied (2) pressure suppression function B. (1) satisfied (2)

Torus cooling capability C. (1)

NOT satisfied (2) pressure suppression function D. (1)

NOT satisfied (2)

Torus cooling capability

2022 MONTICELLO ILT NRC EXAM - SRO-I

83.

A transient occurred resulting in the following conditions:

Drywell pressure is 58 psig and slowly rising

Torus water level is 13 ft. and slowly rising

Drywell radiation is 10 R/hr and slowly rising

Attempts to spray the drywell have been unsuccessful

Significant fuel damage is NOT anticipated You have decided to perform C.5-3505 (VENTING PRIMARY CONTAINMENT).

Which one of the following choices identifies:

(1) The recommended vent path?

(2) The desired strategy for venting Primary Containment?

A. (1) SBGT through the 18 inch torus vent (C.5-3505 PART C)

(2) Venting MUST be limited to ONLY the volume required to maintain pressure below the DW pressure limit B. (1) SBGT through the 18 inch torus vent (C.5-3505 PART C)

(2) Venting MAY be extended for a period of time to reduce the amount of radioactivity that may have to be released once fuel damage occurs C. (1) Hard Pipe Vent (C.5-3505 PART A)

(2) Venting MUST be limited to ONLY the volume required to maintain pressure below the DW pressure limit D. (1) Hard Pipe Vent (C.5-3505 PART A)

(2) Venting MAY be extended for a period of time to reduce the amount of radioactivity that may have to be released if fuel damage occurs

2022 MONTICELLO ILT NRC EXAM - SRO-I

84.

The plant was at rated conditions when a seismic event occurred.

The following conditions exist:

RPV water level is -60 and slowly rising

RPV pressure is 600 psig and slowly lowering

HPCI is injecting at rated flow

Both trains of Drywell Sprays are in operation.

Torus level is +3 feet and stable

CST level is +3 feet and stable Given the above conditions, which of the following Torus Level mitigating actions is required to be implemented IAW C.5-1200 (PRIMARY CONTAINMENT CONTROL)?

A. Drain Torus Water to Radwaste.

B. Stop RPV injection from the HPCI system.

C. Perform Emergency RPV Depressurization.

D. Stop Drywell Sprays and anticipate RPV Depressurization.

2022 MONTICELLO ILT NRC EXAM - SRO-I

85.

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

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.

2022 MONTICELLO ILT NRC EXAM - SRO-I

86.

The plant is in Mode 5 during a refuel outage with Secondary Containment established.

A LOCA from the RHR system occurs resulting in RPV water level lowering to -58 inches for 35 minutes; which of the following EAL classifications must be made?

A. ALERT IAW CA1.1 B. ALERT IAW CA1.2 C. Site Area Emergency IAW CS1.1 D. Site Area Emergency IAW CS1.2

2022 MONTICELLO ILT NRC EXAM - SRO-I

87.

The reactor was operating at 30% power. I&C technicians were performing calibration testing on the Group 1 isolation logic and inadvertently caused a Group 1 isolation. Reactor pressure peaked at 1052 psig.

Given FP-OP-REP-01 Attachment 2 (10CFR 50.72 REPORTABLE PLANT EVENTS); which is the most restrictive 10CFR 50.72 notification required, if any?

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. None required

2022 MONTICELLO ILT NRC EXAM - SRO-I

88.

The plant was at rated conditions when the following SRV A indications were observed:

C.4-B.03.03.A (STUCK OPEN RELIEF VALVE) is in progress

SRV A handswitch was placed in OPEN and RETURNED to the normal position

Reactor power was reduced and is currently stable at 80%

SRV A indication remains as indicated above Which C.4-B.03.03.A action must be directed next by the CRS?

A. Bypass the Div II Lo-Lo Set Logic on CR panel C-253D.

B. Remove the four fuses associated with SRV A on CSR panel C-32.

C. Place the SRV A handswitch in the CLOSE position on CR panel C-03.

D. Place the SRV A handswitch in the CLOSE position on ASDS panel C-292.

2022 MONTICELLO ILT NRC EXAM - SRO-I

89.

The plant is in Mode 1 when annunciator 5-A-46 (SRV OPEN) is received along with the following indications:

Which of the following is a required TRM/Tech Spec REQUIRED ACTION and COMPLETION TIME for the above conditions?

A. None; TRM/Tech Spec Actions are NOT required.

B. Restore SRV E to OPERABLE status within 14 days.

C. Restore the instrument channel to OPERABLE status within 30 days D. Restore the instrument channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

2022 MONTICELLO ILT NRC EXAM - SRO-I

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)

2022 MONTICELLO ILT NRC EXAM - SRO-I

91.

The plant was in Mode 1 when an RBCCW line break required the #11 Recirc Pump to be tripped. Actions have been taken to stabilize the plant and the following conditions exist:

Reactor power is 42%

A jet pump loop flow is 7 Mlb/hr

B jet pump loop flow is 32 Mlb/hr Which Technical Specification actions below, if any, are correct for the above conditions?

(C.2-06 Figure 1 Power/Flow Map is on following page)

A. Be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to satisfy 2/3 core height reflood analyses.

B. Match Recirc loop jet pump flows within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to satisfy LOCA analyses.

C. Ensure the limits of LCO 3.2.1, 3.2.2 and 3.3.1.1 are applied when applicable.

D. No TS action is required since the plant remains outside Stability Regions I and II.

2022 MONTICELLO ILT NRC EXAM - SRO-I

92.

The plant is in Mode 3. Given the following:

BOTH airlock doors for the DW personnel airlock have seal damage

At 1530 on July 4th, BOTH airlock doors are declared inoperable

Total containment leakage, including personnel airlock leakage, is 0.55 La Which of the following describes the Tech Spec ACTIONS that required to be taken?

A. Primary containment is declared inoperable The ACTIONS of TS 3.6.1.1 and TS 3.6.1.2 are entered B. Either one of the two doors is closed by 1630 on July 4th The door that is closed is LOCKED by 1530 on July 5th C. The inner door ONLY must be verified closed by 1630 on July 4th The inner door is restored to OPERABLE status by 1530 on July 5th D. Either one of the two doors closed by 1630 on July 4th Restore the airlock to OPERABLE status by 1530 on July 5th

2022 MONTICELLO ILT NRC EXAM - SRO-I

93.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LEAKAGE calculations are as follows:

Average total LEAKAGE is 24.5 gpm

Average unidentified LEAKAGE is 3.5 gpm At 0700, average total leakage rises to 26.2 gpm and the following is indicated:

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.

2022 MONTICELLO ILT NRC EXAM - SRO-I

94.

The plant is at rated conditions. At 0930 Johnny Craig informs you that he is leaving immediately due to a personal emergency.

Crew positions and Operations Department Organization/Qualification chart on the next page.

As the CRS, which of the following is correct?

A. Direct a call-out to fill a Fire Brigade position within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

B. Direct a call-out to fill a Safe Shutdown position within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. Direct a call-out to fill a Fire Brigade position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. Direct Johnny Craig to remain on watch until a NPE&RO can fill his position.

2022 MONTICELLO ILT NRC EXAM - SRO-I POSITION CREW MEMBER 1

Shift Manager Eagle 2

Control Room Supervisor VanCulin 3

STA/SRO Kosey 4

NLPE&RO Teige 5

NPE&RO Craig 6

NPE&RO Yunger 7

NAPEO Waaraniemi 8

NAPEO Gustafson 9

NAPEO West 10 RP Specialist Olson 11 Chemistry Technician Trump 12 Fire Brigade Leader Craig 13 Fire Brigade Member #1 Waaraniemi 14 Fire Brigade Member #2 Gustafson 15 Fire Brigade Member #3 Olson 16 Fire Brigade Member #4 Trump 17 Safe Shutdown Member #1 Eagle 18 Safe Shutdown Member #2 West 19 Safe Shutdown Member #3 Teige 20 Safe Shutdown Member #4 Craig Operations Shift Group SHIFT 1 SHIFT 2 SHIFT 3 SHIFT 4 SHIFT 5 SHIFT 6 Shift Manager Olson Antony1 Haugen Eagle Krull Stalpes Ctrl Room Supv Allen Lashinski Hayward VanCulin Plautz Vacant STA/SRO Conway1 Gutridge Grossman Kosey4 Kruckenberg Brunner NLPE&RO Casperson1 Johnson Robeck Teige Ergen Schwarzkopf NPE&RO Swedberg1 Marstein1, 4 Komarek Craig Barfknecht Heino Leyk1 Jendro1 Pagel Yunger4 Kruschke Jundt Holmstadt NAPEO Pudlick Kranz Dean Waaraniemi Ostby4 Kothenbeutel (RB&TB qualified)

Lawrence Smeby4 Winkelman Gustafson Laning Behler Middendorf Johansen Kovanen West Swales Karkhoff Rusin Kiekow Braun Ramaley Mork Volkmuth Crew Notes:

1. No Solo Operation

2. Duty Restriction

3. Not Qualified

4. Not Fire Brigade Qualified

2022 MONTICELLO ILT NRC EXAM - SRO-I

95.

The plant is in MODE 5 with a core offload in progress. Complete the following statement:

The basis of the Control Rod OPERABILITY - Refueling Technical Specification is to A. ensure ALL control rods remain fully inserted.

B. prevent AND mitigate prompt reactivity excursion events.

C. ensure ALL control rod scram accumulators are OPERABLE.

D. prevent movement of ANY control rod while in Refueling Mode.

2022 MONTICELLO ILT NRC EXAM - SRO-I

96.

The plant is in Mode 2 performing a reactor startup.

Given the following at 1000:

Control Rod withdrawal commenced

Average SRM count rate was 20 cps Given the following at 1300:

The highest achieved average SRM count rate was 160 cps

The reactor was then scrammed and all rods fully inserted If control rod withdrawal is scheduled to recommence at 1600; which of the following is correct in regards to initiating Form 2150 (PRESTART CHECKLIST) and why?

A. A NEW checklist must be initiated because the reactor would have been critical.

B. The ORIGINAL checklist is still valid because < 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months elapsed with control rods withdrawn C. The ORIGINAL checklist is still valid because < 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months have elapsed since control rods were fully inserted.

D. A NEW checklist must be initiated because > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months have elapsed since control rod withdrawal commenced.

2022 MONTICELLO ILT NRC EXAM - SRO-I

97.

The plant is at rated conditions with MO-2021 (RHR DIV 2 DRYWELL SPRAY OTBD) closed and its breaker open for maintenance activities. While conducting rounds, the Reactor Building Operator reports the following:

PI-10-115A (A RHR HX DISHCHARGE PRESSURE) indicates 27 psig

PI-10-115B (B RHR HX DISHCHARGE PRESSURE) indicates 49 psig Which of the following Tech Spec REQUIRED ACTIONS and COMPLETION TIMES are required for the above conditions?

A. Restore one LPCI subsystem to OPERABLE status within 7 days ONLY.

B. Restore a RHR drywell spray subsystem to OPERABLE within 7 days ONLY.

C. Restore a RHR drywell spray subsystem to OPERABLE within 7 days AND Restore low pressure ECCS injection/spray subsystem to OPERABLE within 7 days.

D. Restore a RHR drywell spray subsystem to OPERABLE within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND Restore low pressure ECCS injection/spray subsystem to OPERABLE within 7 days.

2022 MONTICELLO ILT NRC EXAM - SRO-I

98.

The plant was at rated conditions when a HPCI steam supply line break occurred. All attempts to isolate the leak have NOT been successful. Conditions are as follows:

RM A-14, HPCI Turbine Area, indicates 1R/hr

TR-4926, Point 26, 896 HPCI Turbine Area, indicates 215ºF and rising

TR-4926, Points 27 and 28, 896 HPCI Turbine Area, indicate 210ºF and rising

Annunciator 4-A-11 (REACTOR BUILDING HI RADIATION) is in alarm

Annunciator 3-B-56 (HIGH AREA TEMPERATURE STEAM LEAK) is in alarm Based on plant conditions, what action is the CRS required to direct?

A. Insert a manual Scram ONLY B. Commence a normal plant shutdown C. Insert a manual Scram AND initiate a Blowdown D. Insert a manual Scram AND if Point 27 or 28 exceed 212ºF then initiate a Blowdown.

2022 MONTICELLO ILT NRC EXAM - SRO-I

99.

An emergency has occurred with the following conditions:

Off-site Monitoring Teams are projected to receive a thyroid dose of 13 rem CDE

Personnel in security buildings are projected to receive a thyroid dose of 27 rem CDE

A.2-304 (POTASSIUM IODIDE USE) is provided As the Emergency Director, which one of the following describes the course of action regarding Potassium Iodide use?

Issue KI to...

A. Personnel in security buildings ONLY but NOT to pregnant and nursing women.

B. Personnel in security buildings ONLY but NOT to people with known iodine allergies.

C. Off-site Monitoring Teams AND personnel in security buildings but NOT to pregnant and nursing women.

D. Off-site Monitoring Teams AND personnel in security buildings but NOT to people with known iodine allergies.

2022 MONTICELLO ILT NRC EXAM - SRO-I 100.

The plant was at rated conditions when an LONOP and LOCA occurred. HPCI and RCIC have been unable to maintain RPV water level and the following conditions are now present:

15 Bus LOCKOUT has occurred

Drywell pressure is 8 psig and rising slowly

RPV pressure is 550 psig and lowering slowly

RPV water level is -110 inches and lowering slowly

12 and 14 RHR pumps are running in the Torus Spray/Cooling Mode

12 Core Spray pump is running with MO-1752 (#12 CS OUTBOARD ISOLATION)

OPEN and MO-1754 (#12 CS INBOARD ISOLATION) CLOSED As the CRS, which one of the following directions must be given at this time?

A. Initiate an Emergency Depressurization.

B. Start an additional low pressure ECCS pump.

C. Secure Torus Sprays and realign B RHR to LPCI Mode.

D. Place the 12 Core Spray system in its normal injection lineup.

ML23012A139

Text

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